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1. control 85 Code PWR WWER BWR PHWR RBMK 11 13 Moderator deuterium excursion 11 14 Voiding of the CPS cooling circuit RSSHR Reduction of secondary side heat removal 12 1 Turbine trip throttle Turbine trip Turbine trip Turbine trip Turbine trip valve closure EHC Turbine trip with Failure of one or two problems turbine bypass valve turbogenerators failure 12 2 Generator trip or Generator trip Generator trip Generator trip Generator trip generator caused faults 12 3 Feedwater flow instability operator error 12 4 Feedwater flow Inadvertent closure of instability feedwater pipeline miscellaneous isolation valve mechanical causes 12 5 Loss or reduction in feedwater flow one loop 12 6 Total loss of Loss of feedwater Loss of MFW supply Loss of feedwater flow feedwater flow all pump loops 12 7 Full or partial closure Inadvertent closure of Main steam isolation Failure to close the of MSIV one loop main steam isolating valve MSIV closure MSV valve Partial MSIV closure Inadvertent closure of Inadvertent closure of main steam isolation one MSIV valves 12 8 Closure of all MSIVs 12 9 Inadvertent closure of turbines stop or regulation valve 12 10 Inadvertent SGs level SG pressurization regulation valve operation lead to SG level decrease 12 11 Inadvertent closure of SG steam line isolation valve 12 12 Deaerator tank or
2. due to causes affecting unit availability cause codes other than I J K M O U Rule XEL Energy losses due to outages with type code Xxx and Cause Code other than I J K M O U If some short term outages are not reported there may be deviations from the above rule Therefore the tolerance limit for external energy losses is equal to 10 hours of operation at the reference unit power VI Energy losses due to Full Outages This test finds out whether the energy loss due to full outages the second character of the type code is F corresponds to the outage duration it assumes the unit is disconnected from the grid during that time Rule Outage energy loss Hours of outage duration x Reference unit power Similarly to the Test I results of this test may be affected by the shutting down and starting up periods which are mostly included in the full outage data Therefore 24 hours of operation at the reference power has been established as the tolerance limit VII Lifetime Electricity Generation This test compares a reported lifetime generation with the sum of a previous year value of lifetime generation and current year generation Rule Lifetime Electricity Generation LEG previous year s LEG Electricity Generation for the current year VIII Scrams Compares numbers of scrams reported in the Operating Experience OE data set with a number of outage records coded as scram Rule The number of
3. 0 EAF REG x 100 Energy Unavailability Factor EUF Energy unavailability factor can be calculated from the relationship EUF 100 EAF over a specific time period EUF is a composition of following factors EUF PUF UUF XUF Where PUF planned energy unavailability factor UUF unplanned energy unavailability factor due to causes in the plant XUF unplanned unavailability factor due to causes external to the plant 101 SCRAM RATE UNPLANNED AUTOMATIC SCRAMS PER 7000 HOURS CRITICAL UA7 UNPLANNED SCRAMS PER 7 000 HOURS CRITICAL US7 PURPOSE The purpose of the unplanned automatic total scrams per 7 000 hours critical indicator is to monitor performance in reducing the number of unplanned automatic manual reactor shutdowns The indicator provides an indication of success in improving plant safety by reducing the number of undesirable and unplanned thermal hydraulic and reactivity transients requiring reactor scrams It also provides an indication of how well a plant is operated and maintained Taking into account the number of hours that a plant was critical provides an indication of the effectiveness of scram reduction efforts while a unit is in an operating condition In addition normalizing individual unit scram data to a common standard 7000 hours critical provides a uniform basis for comparisons among individual units and with the industry values DEFINITION The indicator is defined as the number of unp
4. Speciticaton Data Operational Data Non lectrical Application Change Reactor Change Year Heat Consumption Highlights Month District Heating POH Process Heat PPH Total Heat Delivery POH PPH Totalinceded trom Osta status Gcal Gean tGcall non nuclear back up we heat source Gean Jan 32035 20601 0837 0 Publehed gt Feb 31451 22345 530000 Pte gt Mor ioe 10758 218846 Pubiched Agr 11607 11440 708s Published May 1433 1448 23816 Publehed dun 979 31 19700 Pibiehod gt Sul 470 5576 19048 Pilea Avg 6208 6260 124650 Pibiched Sop 0 00 Publehed Oct i 00 Pubiehed gt Wey 553 61 64710 Pubkhed Dec 15663 17754 397 0 P bided v Tots 128575 pan 2389780 Published atthe d a o SS es EE ff the back up heat source ra used for midipie umis please cianfy FIG 6 2 NEA data for district and process heat District Heating PDH Data entry for monthly energy in giga calories Gcal supplied for district heating The thermal energy provided during the reference month for district heating delivered in the form of heat steam or hot water measured as the difference between the plant feed outlet and return inlet headers see Figure 6 1 District heating is the heat provided to space heaters installed at houses buildings and facilities outside the power plant for warming the living environment In some cases supply of hot water for living is combined with this system If it is di
5. and next gt gt allow easy movement to the other IE records The IE record which is specified as based on the controlled shutdown UF2 record can be excluded from the IE records using the button Exclude This button is not active for records based on scrams When an outage record was reported in more fragments all linked fragments as shown and the combined outage is considered as one initiating event The IE data use the same data status controls as described in 2 4 69 Additional data items for IE records Initiating Event Code Selection of the initiating event code using the drop down list of the generic initiating events offered by PRIS WEDAS for the relevant reactor type WEDAS provides a drop down list of IE codes with IE description for the relevant reactor type The generic list codes are synchronised across the reactor types Annex 1 contains lists of generic IE codes for particular reactor types and models Clarifying notes a The data provider can select only one code from the list b For selected forced controlled shutdowns the code of Administrative shutdown is automatically assigned Explanation The explanation should provide the reason behind the assignment of a particular IE code In order to ensure enough information for the user to judiciously decide whether the event belongs to the IE for which the user wants to calculate the frequency the explanation and justifica
6. even if the plant was not actually required to start up during the period Unavailability data are used for calculating several statistics on a monthly and annual basis explicitly the following nuclear power plant performance indicators Energy Availability Factor EAF Planned Energy Unavailability Factor PUF Unplanned Energy Unavailability Factor UUF Unit Capability Factor UCF Unplanned Capability Loss Factor UCL Forced Loss Rate FLR 37 RUP normal revision operation nal Reference Unit Power LOOO Seen ace Oa SO Po Sco Favourable F ambient Revised 900 40 1 dada 2 B conditions Reference conditions coast down 4 i Unit Power 800 i operation i l Regulatory i i restriction 700 Unplanned Feedwater load pump failure following i 800 i Starting up Controlled PEL 500 EG i shutdown EG i EP 400 300 200 Major refurbishment i N Automatic reactor scram and with refuelling Outage extension nplanned outage due to reactor 100 i i protection problems see E 1 2 3 4 5 6 7 8 9 10 11 12 Month Section Description 0 1 Load following operation Power reduction due to a feed water pump failure protection actuation gt immediate controlled reactor power reduction FEL Reduced power operation due to unfavourable ambient conditions XEL Coast down operation XEL Unit shutdown for a planned refuelling and major refurbishment PEL Reactor
7. 46 e f For intermittent outages e g due to load following operation enter cumulative data for the reporting period Outage duration cannot make the outage end into the next year reporting period Energy Loss net Data entry for total energy expressed in electric megawatt hours MW e h that has not been delivered to the grid or other consumers due to the outage Energy loss for full outages is crosschecked with calculation based on outage duration in the consistency test VI see 5 4 1 Clarifying notes a b c d e The calculation of energy losses due to reduced power is always related to the Reference Unit Power see rules in 5 2 2 Energy losses are calculated separately for each outage If several outages are concurrent in a period of time energy loss for each outage is reported as if the unit was operated at the reference power at the beginning of the outage The field cannot be left blank For reactor scrams after disconnection of the unit from the grid zero 0 energy loss is reported For intermittent outages e g due to load following operation enter cumulative data for the reporting period Start Date Data entry for a date of the first day of the outage in the form of YYYY MM DD For instance 2013 12 28 for 28 December 2013 Clarifying notes a b c d If no start date can be specified e g for a continuous load following operation
8. 8 5 Pressure regulator fails to close 8 6 Pressure control failure LU LOCA LOCA inside confinement 9 1 Leakage from control Control rod ejection rods induced LOCA 9 2 Leakage in primary HTS leaks lt system charging capacity HTS leaks gt charging capacity HTS LRV spuriously fails open 9 3 Pressurizer leakage Break in piping upstream of the pressurizer relief valves or steam bleed valves PRV spuriously fails open 9 4 Stuck Open Safety Inadvertent opening of Relief Valve pressurizer safety valve 9 5 Large LOCA Large pipeline primary Large Loss of Coolant Large LOCA Guillotine break of side LOCA Accident DGH Guillotine break of downcomer Guillotine break of the MCP pressure header vagy 9 6 Medium LOCA Medium pipeline Medium Loss of primary side LOCA Coolant Accident 9 7 Small LOCA Small pipeline primary Small Loss of Coolant Pressure tube rupture Break in the inlet side LOCA Accident Pressure tube and pipeline of a fuel calandria tube rupture channel Feeder stagnation Break in the outlet break pipeline of a fuel Feeder break channel End fitting break with Break of a channel fuel ejection tube inside the reactor cavity Partial critical break of the DGH 9 8 Very Small LOCA Very small pipeline Very Small Loss of primary side LOCA Coolant Accident 9 9 Gas removal system pipeline rapture Inadvertent opening of gas removal system valve 9 10 LOCA due to failure of closure plug
9. 9 11 FM induced small LOCA no fuel ejection 84 Code PWR WWER BWR PHWR RBMK 9 12 FM induced small LOCA with fuel ejection 9 13 FM induced HTS leaks 9 14 Rupture of water communication line 9 15 Rupture of a pipeline in the blowdown and cooling system PRISL Primary to secondary leakage 10 1 Steam generator tube Steam generator tube Steam generator tube rupture PRISE rupture single or rupture single or primary to secondary multiple multiple leakage 10 2 Steam generator collector header leakage RA Reactivity accident 11 1 CVCS malfunction Inadvertent boron boron dilution dilution 11 2 Uncontrolled rod Uncontrolled control Rod withdrawal at Prolonged withdrawal withdrawal rods withdrawal power of a control rod from the core at both nominal and low power Prolonged withdrawal of a bank of control rods at both full and low power 11 3 Inadvertent control Inadvertent insertion Control rod drop rods insertion of control rod or rods including the absorber part of short rods falling out of the core 11 4 Detected fault in reactor protection system 11 5 Core instability 11 6 SLCS inadvertent injection 11 7 Loss of regulation 11 8 Dual failure of group controllers 11 9 Dual failure of data highways 11 10 Dual failure of channel A device controllers 11 11 Dual failure of channel C device controllers 11 12 Loss of reactivity
10. Data entry for a number of unplanned manual scrams that occurred during the reporting period while the reactor was critical 31 Manual means that initial signal that caused actuation of the reactor protection system logic was provided from manual scram switches or in certain cases described in the clarifying notes manual turbine trip switches or pushbuttons provided in the main control room Number of critical hours in the reporting period 32 Data entry for a number of hours during the reporting period when the reactor was critical Critical means that during the steady state condition of the reactor prior to the scram the effective multiplication factor Ker was essentially equal to one A decimal point not comma should be used in case of a decimal number Number of critical hours is reportable even if less than 1000 Nevertheless to be included in the industrial values the reactor unit must have at least 1000 critical hours per year Requiring this minimum number reduces the effect of reactor units that are shut down for long periods of time and whose limited data may not be statistically valid Clarifying notes a All unplanned reactor scrams must be reported even if they occurred after the unit was disconnected from the grid when the reactor remained at power and critical and even if they occurred due to reasons considered not being under management control b Scrams that are planned to occur as pa
11. fuel rationing Fuel management limitation including high flux tilt stretch out operation to i The cause coded T can apply to planned unplanned to support a next unit and external outages on site desalination and off site heat distribution j Causes related to equipment A repair D testing E back fitting F G nuclear regulatory requirements H human actions L environmental conditions N fire P fuel management S and other Z should whenever applicable be followed by the code of the plant system affected by or otherwise involved in the outage k The cause code J which was originally assigned to energy losses related to grid limitation and grid instability failure was split into two codes I and J The new code I applies to the energy that was not produced because of grid limited capacity to transmit available power of the reactor unit The code J applies to the energy that was not produced because of grid failure loss of grid or grid instability 1 The new cause code O was introduced for generation losses that result from market regulations when priority in dispatching is given some generating units renewables also known as must run units If this cause cannot be distinguish the related losses can be included in the cause code K load following Any power reduction that is caused by low market prices should not be included in this category because such regulation remains under the plant manag
12. pipeline leakage 12 13 Inadvertent opening of Low deaerator level deaerator safety valve 12 14 Inadvertent operation of deaerator level regulation valve lead to deaerator level decrease 86 Code PWR WWER BWR PHWR RBMK 12 15 Turbine bypass or control valves cause increase in pressure closed 12 16 Feedwater heater failure Loss of feedwater heater Feedwater control failure 12 17 Loss of feedwater high pressure pre heater RT Reactor trip 13 1 Spurious trips cause Not qualified reactor Spurious trip via Spurious trips cause unknown trip instrumentation RPS unknown fault 13 2 Automatic trip no Inadvertent automatic Scram due to plant Automatic trip no transient condition reactor trip occurrences transient condition 13 3 Manual trip no Manual erroneous Manual scram no out transient condition reactor trip of tolerance condition LC Loss of condenser 14 1 Condenser leakage Leakage of condenser tank or pipeline 14 2 Loss of condensate Loss of condensate Loss of condensate pumps one loop pump 14 3 Loss of condensate pumps all loops 14 4 Loss of condenser Loss of condenser Loss of normal Loss of condenser Loss of condenser vacuum vacuum condenser vacuum vacuum vacuum Loss of circulating water 14 5 Inadvertent close of condensate pipeline valve 14 6 Loss of condenser water control 1
13. seizure 82 Code PWR WWER BWR PHWR RBMK 7 4 Inadvertent closure of Spurious partial main circuit isolation closure of the MCP valves throttling valve in an operating reactor 75 Loss of all feedwater flow 7 6 Trip of one feedwater pump or condensate pump TET Feedwater low flow 7 8 Low feedwater flow during startup or shutdown 7 9 Loss of TICCW Turbine Island Closed Cooling Water 7 10 Channel flow reduced to gt 70 of normal flow 7 11 Channel flow reduced to lt 70 of normal flow severe flow blockage 7 12 Failure of the isolation disc of the DGH check valve 7 13 Shaft break of one of the MCPs 7 14 Break of a MCP check valve plate or of an MCP gate valve disc LPPC Loss of primary pressure control 8 1 Pressurizer spray Failure to injection failure into pressurizer spray from MCP Inadvertent pressurizer heaters activation 8 2 High pressurizer pressure HTS pressure control failure high 8 3 Low pressurizer pressure Inadvertent injection into pressurizer spray from normal makeup system Inadvertent injection into pressurizer spray from MCP Pressurizer heaters failure or inadvertent disconnection HTS pressure control failure low 8 4 Pressure regulator fails to open 83 Code PWR WWER BWR PHWR RBMK
14. 4 Kroko site iKeake Safety injection 2 o ha iGako Unit Default image sko NPP Dotwutt image Manage Images for this Reactor Krako Main Steam Kreko Reactor Coolant System bis sip t E fa Manage Images for this Site FIG 4 4 Examples of schematics An image can be uploaded and assigned either to one particular reactor unit or to a plant site When assigned to the site all reactor units of the site share the image The function Manage Images for this Reactor available on the left part of the schematics screen supports image uploading administration and editing on the reactor unit level while the function Manage Images for this Site does the same on the site level Manage All Images deals with all images available to a data provider The image management functions open a table of existing images either for a reactor or a site This table contains already uploaded images and related information and image functions view edit delete 22 Design Schematics Manage images Specification Data Basic information Design Characteristics Schomatics Milestones Operation Data Manage imagus for this Roarto Thumbnail image Tithe Kriko NPP Krsko Awchary Feotanter Kesko Main Feedwater 1 Kasko Main Feecweeor 2 Kroko Main Steam Krsko plant Kesko Reactor Cogtant Syster Kesko Satety Wyection 1 Krsko Satety
15. Reactor Information System PRIS by the IAEA staff In the 1990s data collection was arranged off line through electronic file exchange With advances in computer software it was decided to make arrangements for data capture directly on line into PRIS to facilitate data entry for an increasing number of reactors The IAEA Web Enabled Data Acquisition System WEDAS assists PRIS data providers with an easy to use tool for on line data entry resulting in improved data quality and considerable time saving in data input into PRIS This PRIS WEDAS user s manual provides guidelines and detailed information for each of the data items required and facilitates the use of the PRIS WEDAS application The purpose of this manual is to ensure PRIS performance indicator data are collected consistently and that the required quality of data collection is assured It replaces reporting instructions published in IAEA Technical Reports Series No 428 The IAEA officer responsible for this publication was J Mandula of the Division of Nuclear Power EDITORIAL NOTE This publication has been prepared from the original material as submitted by the contributors and has not been edited by the editorial staff of the IAEA The views expressed remain the responsibility of the contributors and do not necessarily reflect those of the IAEA or the governments of its Member States Neither the IAEA nor its Member States assume any responsibility for consequences which may
16. Reactor identification Conti Detaits Definkion of Milestones Conatraction Start Dato whon first mayor places of concrete usually tor the base mat of the reactor building is done From this date the roartor ia camsidered to be under constuchon First Criticatity Date whon the reactor is made critical for the first time Grid Connection Date when the plant ts frat commected to the alectical god for the supply of power After thie cate the piant is considered in Operation Commercial Operation Date when the plant is handed over by the comtiactors to the owner and declared officially m commercial oparmion Permanent Shutdown Oste when the plant 6 officialy decimed by the owner 10 be taker out of Commercial operation and shut down permanently This part of the specification data contains the main information required for reactor unit identification Those pieces of information are usually used for reactor categorisation in PRIS statistics and reports Unit name It is the name given to the nuclear power plant and is an important reference in PRIS Unit name is a combination of name and numbers including spaces and hyphens The structure of nomenclature used in the PRIS systems is as follows e NAME u StationID UnitID Note Parts in square brackets are optional Examples of names EMBALSE DOEL 1 GUNDREMMINGEN B QINSHAN 2 1 DUNGENESS B 1 11 Clarifying notes a StationID and Unit
17. XEL This assumes that the plant equipment was not expected to be capable of mitigating the external event If the plant equipment was designed to have prevented damage from the size of the event the losses would be unplanned losses FEL e When a unit supplied reduced electricity to the grid due to electricity steam supply to the neighbouring unit of the same plant the related energy losses are reportable as XEL An internal extraction of energy does not affect unit capability but the unit is not fully available for the grid f When a unit supplied reduced electricity to the grid due to steam supply to a non electrical application unit on site desalination and off site heat distribution the related energy losses are reportable as XEL 43 g Energy losses due to labour strikes are not considered to be under the plant management control and are reportable as externally caused losses XEL e If a labour strike occurs during plant operation any shutdown or load reduction generation losses during the strike are reportable as externally caused losses e If the strike occurs during an unplanned forced outage reportable unplanned losses resume after the strike is over e If the strike occurs during a planned and scheduled outage the original scheduled end date of the planned outage is considered to have been extended by the duration of the strike The revised scheduled end date is used to determine planned losses and outage extension
18. an already uploaded supports uploading a new image into PRIS To upload the button and the file explorer 23 Basic Information Design Characteristics Schematics Milestones Contact Detain Kr ko NPP File Nama 43 ip9 Tithe Kidke NPP Type Cross secton drawing Y dessa roomse Deseription Simplified schematics Ba a my J oF eaaa aa Copyright Krsko NPP ji es J pias e m Savo Replace imagu Image useage selection Curent usage FIG 4 6 Image uploading or editing screen When a new image is successfully uploaded into PRIS the following information should be specified Title The title of the image should be unique in PRIS It is recommended to use combination of reactor site name and additional specification The screen also contains the internal file name under which the image is stored in PRIS Type Selection from the pop up menu e Panoramic view e Schematic diagram e Cross section drawing e Operating flow diagram e Map e Technical photo Description Text filed for additional information about content of an image Copyright Reference to the source or author of the image The uploaded image can be assigned to other reactor units or sites under the control of the data provider For this purpose WEDAS provides a table Image usage selection of all reactor units and sites under the image specification Assignment is done by marking a ch
19. as the data provider In this case he has full access to the raw data of assigned reactor units and is responsible for reporting and updating the data Utilities operating several NPPs can nominate one data provider for an individual power plant or for more power plants The data provider has full access to the raw data of the assigned plant s The data providers and liaison officers are responsible for correctness completeness and timeliness of the reported data The data is reported on monthly quarterly or six monthly bases However the data must be reported at least once a year and before the following deadlines e End of January completion updating and verification of specification data basic information design characteristics decommissioning data and country annual data e Mid February production and outages data PRIS Data Report eee Reporting Period Reporting Date Minimal Reporting Frequency i an Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Previous Year Current Year Acceptable Reporting Frequency ff 5 y aan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Previous Year z n Current Year Recommended Reporting Frequency i gt 3an Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Previous Year J Current Year Ce Desirable Reporting Frequency san Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Previous Year tas Current Year FIG 2 2 PRIS data reporting frequency Th
20. losses once the strike is over Energy losses due to labour strikes during a planned outage are reportable as externally caused energy losses XEL in monthly records and related outage records are coded as externally caused outage extension XF3 5 3 OUTAGES For the purpose of PRIS coding the outage is the status of a reactor unit when its actual output power is lower than the reference unit power for a certain period The outage includes both power reduction and unit shutdown however it is recognised that in a common understanding outage means the shutdown only The outage records support analyses of energy losses according to their character causes frequency and analyses of system reliability The outage record consists of start date and duration related energy loss codes for type and cause of the outage and the system involved operating mode and outage description For details about PRIS outage coding see the references 1 and 2 New outage record is created by clicking the button Add on the outage record landing screen see Figure below WEDAS uses internal numbering of outages It is desirable to report all power reductions in outage records As a minimum all significant outages including outage extensions and reactor scrams should be reported The outage is considered significant if the loss in the energy production corresponds to at least ten hours of continuous operation at the reference unit power or if it has be
21. of a power up rate type Improved measurement lt 2 Measurement uncertainty recapture power up rates are less than 2 and are achieved by implementing enhanced techniques for calculating reactor power This involves the use of state of the art feed water flow measurement devices to more precisely measure feed water flow which is used to calculate reactor power More precise measurements reduce the degree of uncertainty in the power level which is used by analysts to predict the ability of the reactor to be safely shut down under postulated accident conditions Stretch power up rate 2 7 Stretch power up rates are typically up to 7 and are within the design capacity of the plant The actual value for percentage increase in power a plant can achieve and stay within the stretch power up rate category is plant specific and depends on the operating margins included in the design of a particular plant Stretch 28 power up rates usually involve changes to instrumentation set points but do not involve major plant modifications Extended power up rate gt 7 Extended power up rates are greater than stretch power up rates and have been approved for increases as high as 20 These up rates require significant modifications to major balance of plant equipment such as the high pressure turbines condensate pumps and motors main generators and or transformers e Main modification selection in case the RUP revision is related to technic
22. or automatic shutdown of the reactor by a rapid insertion of negative reactivity into the reactor core e g by control rods liquid injection shutdown system etc This is caused by actuation of the reactor protection system manual scram switches and in certain cases described in the clarifying notes manual turbine trip switches or pushbuttons provided in the main control room The scram signal may have resulted from exceeding a set point or may have been spurious Data are collected for unplanned scrams that were not an anticipated part of planned tests Scram related data are used on an annual basis for calculation of unplanned automatic and manual scram rates UA7 US7 The number of automatic and manual scrams is crosschecked with outage records coded as UF4 UF5 XF4 XF5 in the consistency test VIII see 5 4 1 Number of unplanned automatic scrams in the reporting period Data entry for a number of unplanned automatic scrams that occurred during the reporting period while the reactor was critical Automatic means that the initial signal that caused actuation of the reactor protection system logic was provided from one of the sensors monitoring plant parameters and conditions rather than the manual scram switches or in certain cases described in the clarifying notes manual turbine trip switches or pushbuttons provided in the main control room Number of unplanned manual scrams in the reporting period
23. shutdown should be categorized as planned or unplanned depending on whether the shutdown is planned or unplanned For example energy losses while entering and recovering from a planned outage will be considered as planned losses If an outage extension unplanned outage occurs at the end of a planned outage the energy loss during recovery from the outage will still be considered as a planned loss because the shutdown was originally caused by a planned outage see Figure 5 4 time period 5 6 as an example of this situation Energy losses for unrelated but concurrent causes that result in generation losses are determined and reportable as if the energy losses occurred separately However total losses in a month cannot exceed REG with priority given to unplanned energy losses during operation Special cases of concurrent losses are discussed in clarifying notes If energy losses during an event occur due to a combination of causes under management control and causes beyond the plant management control the related portions should be identified and included when computing reportable losses A unit in reserve shutdown should be considered as available if it can be restarted within the normal time required for unit start up However if work on plant equipment is undertaken that would prevent a restart the energy that potentially could have been produced while the plant was unavailable should be computed and reported as planned or unplanned energy loss
24. specify a new phase Clarifying notes a b c d e Decommissioning plan documentation containing information on the way of proceeding with the decommissioning of a facility On site within the site area Off site outside the site area Safe enclosure a condition of a nuclear facility during the decommissioning process in which only surveillance and maintenance takes place If a safe enclosure licence e g possession only licence was granted insert that date as the start year of either active or passive safe enclosure period Dismantling the disassembly and removal of any SSC during decommissioning Dismantling can be performed immediately after retirement or may be deferred In some information sources the term decommissioning steps is used rather than decommissioning phases 7 3 FUEL MANAGEMENT Specification Data Decommissioning Data Main Decommissioning Phases Fuel Management Contractors and milestones Print View Contact Details Management of fuel removal only for fuel removed during the Start year End year Comments decommissioning period 7 Transfer to reactor facility 2003 2003 Transfer away from a reactor facility 2008 2008 7 Storage in an on site facility 2008 Storage in an off site facility Shipment to a reprocessing plant Z Underwater storage period 2002 2011 7 Dry storage period 2011 2061 Encapsulation 66 Ada FIG 7 3 Fuel management screen Management
25. the information is not used Refuelling Start date Grid disconnection for refuelling Data entry for a date and time of grid disconnection for refuelling outage which is part of the reported operating cycle Operating Cycle and Refuelling End date Grid reconnection after refuelling Data entry for a date and time of grid reconnection after a refuelling outage which is part of the current operating cycle When the refuelling outage is not finished by the end of the reported year and is not known in a time of data reporting leave this data field empty It can be completed in the next year reporting 5 2 PRODUCTION DATA Monthly production data consists of two parts electricity production and unavailability data Reference Unit Power is an integral part of each monthly record which is controlled through the RUP revision on the Operating Experience data screen Production data are expected to be provided monthly during the year Reporting monthly records annually is also possible but in this case PRIS end users cannot benefit from performance monitoring in a current year 5 2 1 Electricity production and on line hours Electricity production and on line hours data are used for calculating several PRIS statistics especially Electricity Generation EG Operation Factor OF and Load Factor LF Operational Data Opersting Repecienoe Producdon Oureper Cunetetersy Chects Fettrmmcce mocatrs Coote Cass e Energy 04
26. the maximum electrical power that could be maintained continuously throughout a prolonged period of operation under reference ambient conditions The gross electrical power is measured at the output terminals of the turbine generator i e including the amount of electricity used in the plant auxiliaries and in the transformers This value should be updated whenever the reference unit power is changed during operation Original Design Net Electrical Power The original design net electrical power is the unit electrical output after deducting the self consumption power assumed by the original unit design no matter if it has ever been routinely achieved during operation This value does not reflect possible power changes during subsequent operation in a specific environment of a site Latest Reference Unit Power RUP No entry required This is read only information about the latest Reference Unit Power as updated through operational data see Chapter 5 1 1 The Reference Unit Power net electrical capacity expressed in MW e is the maximum electrical power that could be maintained continuously throughout a prolonged period of operation under reference ambient conditions The power value is measured at the unit outlet terminals i e after deducting the power taken by unit auxiliaries and the losses in the transformers that are considered integral parts of the unit The reference unit power is expected to r
27. to nuclear power units using a portion of their output energy in the form of heat steam for non electrical applications desalination district heating and process heat The electrical equivalent of energy supplied to off site non electrical application systems during the reporting period in the form of steam is expressed in gigawatts hours electric GW h It is a sum of energy used for heat application systems e PDH for heat Gcal provided for district heating e PPH for heat Gcal provided for process heat e PDI for heat Gcal provided for desalination by sea water distillation e PRO for electricity provided for desalination by reverse osmosis MW h The NEG electrical equivalent allows incorporation of this part of energy into statistics and indicators related to electricity production like Load Factor including heat LFH To convert the thermal energy in GCal into electrical energy in GW h the following factor may be applied 1 16E 3 x PDH PPH PDI x 0 3 GW h GCal where the factor 0 3 is used as a default value for an average thermal efficiency If desalination data contain Desalinated Water Volume DWV m but PDI is not provided the following conversion factor to electrical energy GW h may be applied 2 6E 5 x DWV GW h m The total NEG GW h may be expressed as NEG 1 16E 3 x PDH PPH PDI x 0 3 2 6E 5 x DWV if PDI 0 1E 3xPRO WEDAS estimates NEG using the above formula The calculated value is
28. 0 Ga to ie r datay MW Unglennes Forces nptanned Ert Uspiamssg Ceher re cA Tutsi FIG 5 2 Monthly production data table 34 Energy Generated net EG Data entry for monthly net electrical energy in MW e h supplied during the month to the grid as measured at the unit outlet terminals i e after deducting the electrical energy taken by unit auxiliaries and the losses in transformers that are considered integral parts of the unit Values over the maximum production capacity Reference Energy Generation minus losses are indicated in WEDAS by brown framing the data field and providing a message when the cursor is moved over the data field The value can be saved and system will indicate it as an overproduction Please check correctness of the entered value in such a case The energy generated is the energy supplied to the grid and not the balance of the energy considering energy import from the grid In some months the reactor unit can have a negative balance of energy WEDAS allows entering negative values but the correct value is the energy which was supplied to the grid without its reduction by energy imported from the grid EG values are crosschecked in the consistency test II for energy balance see 5 4 1 On line Hours t Data entry for total clock hours in the month during which the unit operated with at least one main generator connected to the grid The number cannot be greater than the refer
29. 06 12 07 12 99 13 00 13 01 13 02 13 03 13 04 13 05 13 06 13 07 13 08 13 09 13 10 13 11 13 12 13 13 13 99 14 00 14 01 14 02 14 03 14 04 14 05 14 06 14 07 14 08 14 99 15 00 15 01 15 02 15 03 15 04 15 05 15 99 16 00 16 01 16 02 Auxiliary shielding and heat insulation Moderator and auxiliaries PHWR Annulus gas system PHWR RBMK None of the above systems Reactor I amp C Systems Control and safety rods including drives and special power supply Neutron monitoring in core and ex core Reactor instrumentation except neutron Reactor control system Reactor protection system Process computer Reactor recirculation control BWR None of the above systems Reactor Auxiliary Systems Primary coolant treatment and clean up system Chemical and volume control system Residual heat removal system including heat exchangers Component cooling system Gaseous liquid and solid radwaste treatment systems Nuclear building ventilation and containment inerting system Nuclear equipment venting and drainage system including room floor drainage Borated or refuelling water storage system CO injection and storage system GCR Sodium heating system FBR Primary pump oil system including RCP or make up pump oil D20 leakage collection and dryer system PHWR Essential auxiliary systems GCR None of the above systems Safety Systems Emergency core cooling systems including accumulators and core spr
30. 4 7 Leakage of condenser heat exchanger LOST Loss of steam 15 1 Steam line breaks Steam line break inside confinement Steam line break outside confinement Main Steam Line Break MSLB Inside RB MSLB Inside TB Rupture of steam water communication line 15 2 Sudden opening of Inadvertent opening of Inadvertent opening Inadvertent opening steam relief valves atmospheric steam of TG bypass valve of bypass valve dump valves BRU A Inadvertent opening Inadvertent opening of main steam safety of safety relief valve relief valve stuck 15 3 Inadvertent opening of SG safety valves 15 4 Inadvertent opening of turbine control valves 87 Code PWR WWER BWR PHWR RBMK 15 5 Small steam LOCA Break of the main steam duct 15 6 Inadvertent opening of MSVs MSV jammed open 15 7 Loss of extraction steam supply SSF Support systems failure 16 1 Total Loss of Component Cooling Water 16 2 Loss of circulating water 16 3 Loss of service water Loss of service water Loss of service water Loss of service water Loss of service water system supply 16 4 Total Loss of Emergency Service Water 16 5 Partial Loss of CCW expansion joint Component Cooling or line breaks Water 16 6 Partial Loss of Emergency Service Water 16 7 Loss of component Loss of Component cooling Cooling 16 8 Loss of ventil
31. 4536 Email bkwell nde vsnl net in e Web site http www bookwellindia com ITALY Libreria Scientifica AEIOU Via Vincenzo Maria Coronelli 6 20146 Milan ITALY Telephone 39 02 48 95 45 52 Fax 39 02 48 95 45 48 Email info libreriaaeiou eu Web site http www libreriaaeiou eu JAPAN Maruzen Co Ltd 1 9 18 Kaigan Minato ku Tokyo 105 0022 JAPAN Telephone 81 3 6367 6047 Fax 81 3 6367 6160 Email journal maruzen co jp e Web site http maruzen co jp NETHERLANDS Martinus Nijhoff International Koraalrood 50 Postbus 1853 2700 CZ Zoetermeer NETHERLANDS Telephone 31 793 684 400 Fax 31 793 615 698 Email info nijhoff nl e Web site http www nijhoff nl Swets Information Services Ltd PO Box 26 2300 AA Leiden Dellaertweg 9b 2316 WZ Leiden NETHERLANDS Telephone 31 88 4679 387 Fax 31 88 4679 388 Email tbeysens nl swets com Web site http www swets com SLOVENIA Cankarjeva Zalozba dd Kopitarjeva 2 1515 Ljubljana SLOVENIA Telephone 386 1 432 31 44 Fax 386 1 230 14 35 Email import books cankarjeva z si e Web site http www mladinska com cankarjeva_zalozba SPAIN Diaz de Santos S A Librerias Bookshop Departamento de pedidos Calle Albasanz 2 esquina Hermanos Garcia Noblejas 21 28037 Madrid SPAIN Telephone 34 917 43 48 90 Fax 34 917 43 4023 Email compras diazdesantos es Web site http www diazdesantos es UNITED KINGDOM The Stationery Office Lt
32. COMPUTER MANUAL SERIES No 23 PRIS WEDAS User s Manual to the Web Enabled Data Acquisition System for PRIS S IAEA al Atomic Energy Agency PRIS WEDAS The following States are Members of the International Atomic Energy Agency AFGHANISTAN ALBANIA ALGERIA ANGOLA ARGENTINA ARMENIA AUSTRALIA AUSTRIA AZERBAIJAN BAHAMAS BAHRAIN BANGLADESH BELARUS BELGIUM BELIZE BENIN BOLIVIA PLURINATIONAL STATE OF BOSNIA AND HERZEGOVINA BOTSWANA BRAZIL BRUNEI DARUSSALAM BULGARIA BURKINA FASO BURUNDI CAMBODIA CAMEROON CANADA CENTRAL AFRICAN REPUBLIC CHAD CHILE CHINA COLOMBIA CONGO COSTA RICA COTE D IVOIRE CROATIA CUBA CYPRUS CZECH REPUBLIC DEMOCRATIC REPUBLIC OF THE CONGO DENMARK DJIBOUTI DOMINICA DOMINICAN REPUBLIC ECUADOR EGYPT EL SALVADOR ERITREA ESTONIA ETHIOPIA FIJI FINLAND FRANCE GABON GEORGIA GERMANY GHANA GREECE GUATEMALA GUYANA HAITI HOLY SEE HONDURAS HUNGARY ICELAND INDIA INDONESIA IRAN ISLAMIC REPUBLIC OF IRAQ IRELAND ISRAEL ITALY JAMAICA JAPAN JORDAN KAZAKHSTAN KENYA KOREA REPUBLIC OF KUWAIT KYRGYZSTAN LAO PEOPLE S DEMOCRATIC REPUBLIC LATVIA LEBANON LESOTHO LIBERIA LIBYA LIECHTENSTEIN LITHUANIA LUXEMBOURG MADAGASCAR MALAWI MALAYSIA MALI MALTA MARSHALL ISLANDS MAURITANIA MAURITIUS MEXICO MONACO MONGOLIA MONTENEGRO MOROCCO MOZAMBIQUE MYANMAR NAMIBIA NEPAL NETHERLANDS NEW ZEALAND NICARAGUA N
33. ID can be a numerical or alphabetic character b PRIS unit name is not necessarily derived from the site name In some cases multiple stations with different names are located on the same site Alternate name It is the alternate name used for the power reactor unit Use this data item only if applicable Sometimes reactor names have short and long official versions This data field allows introduction of such names Unit code Unit code consists of the country ISO code and the PRIS reference number The code is assigned to the reactor unit when the reactor record is created and cannot be changed The reference number can be a combination of numeral and alphabetical characters Clarifying notes a The reference number is assigned by the PRIS Liaison Officer or data provider responsible for the data of a referred reactor unit b The reference number should be unique within the country c Unit code can be used as a key data field in the PRIS database nevertheless PRIS contains an internal key Reactor ID for internal links Country Read only information name of the country where the station site is located Country is assigned to the reactor unit when the reactor record is created and cannot be changed Reactor type 12 Nuclear power reactors are classified into types based on principal concept of design moderator material coolant or nuclear reaction Reactor
34. IGER NIGERIA NORWAY OMAN PAKISTAN PALAU PANAMA PAPUA NEW GUINEA PARAGUAY PERU PHILIPPINES POLAND PORTUGAL QATAR REPUBLIC OF MOLDOVA ROMANIA RUSSIAN FEDERATION RWANDA SAN MARINO SAUDI ARABIA SENEGAL SERBIA SEYCHELLES SIERRA LEONE SINGAPORE SLOVAKIA SLOVENIA SOUTH AFRICA SPAIN SRI LANKA SUDAN SWAZILAND SWEDEN SWITZERLAND SYRIAN ARAB REPUBLIC TAJIKISTAN THAILAND THE FORMER YUGOSLAV REPUBLIC OF MACEDONIA TOGO TRINIDAD AND TOBAGO TUNISIA TURKEY UGANDA UKRAINE UNITED ARAB EMIRATES UNITED KINGDOM OF GREAT BRITAIN AND NORTHERN IRELAND UNITED REPUBLIC OF TANZANIA UNITED STATES OF AMERICA URUGUAY UZBEKISTAN VANUATU VENEZUELA BOLIVARIAN REPUBLIC OF VIET NAM YEMEN ZAMBIA ZIMBABWE The Agency s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters New York it entered into force on 29 July 1957 The Headquarters of the Agency are situated in Vienna Its principal objective is to accelerate and enlarge the contribution of atomic energy to peace health and prosperity throughout the world COMPUTER MANUAL SERIES No 23 PRIS WEDAS USER S MANUAL TO THE WEB ENABLED DATA ACQUISITION SYSTEM FOR PRIS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA 2015 COPYRIGHT NOTICE All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Conven
35. NTRY ANNUAL INFORMATION 0 ascacestciseelsbacsatastandevtaratvinusbateetnusdaounsattantenadmaguaaavats 8 4 SPECIFICATION DATA Socii desta saad O a E A nats doe beaetteab acacia ts 10 AA BASICINFORMATION guresisreninesa e E E 10 4 1 1 Reactor identification ss sessseesseeeessseeseseesseesesrssseesesrtsstessesstsseessessessresseeseese 11 4 1 2 Reactor unit c pacity anerian oE E E E EEE E E via auld Oy 16 4 2 DESIGN CHARACTERISTICS sevice cesssscesesateesdeaeiesedrduxcavensseerttaoneddscnn ee utasucasenveees 19 4 3 CONNECTED NON ELECTRICAL APPLICATIONS cccccccccseessesseeseeseeseeeseeseees 21 4 ASCHEMA PICS ar odoin ac a Aa kde c s tg E dy Sacae ge dates ages ea eae gta we 21 45 MILESTONE Sipen aA wea echov esata estat A cee Ae Ou lice ata 25 5 OPERATIONAL DATA em e ta tend Qa ase aes A Aa eae ca es aaa ee 27 5 1 OPERATING EXPERIENCE DA TAY scscwetes cas cay acacia ead eaataeeuetie 27 SA Reference Unit POW Clee asenne a cient i ea a teeta a aaa aaa 27 5 1 2 Energy production estee a R aera aati laa a 30 5 1 3 Highlights of operatii scien teas vaulan catgchsSctes tau Baaneoas iiaa ge eee Taia ee ae 31 Sc VA Scranir lat ed NUMMDL S ancsheesasess snsaeaalacednestcnun cs ehacsasuabacousealarsiacsabaneeetaeaesestanensites 31 5 1 5 Operating Cycle Information ss seseseosseseessrossesssesressesseeseesseestesresseeseeseesseesse 33 5 2 PRODUC HON DATA noenee aana a n E e a eae 34 5 2 1 Electricity production and on line hour
36. OCA through control rods intermediate cooling system outside confinement 5 3 Interfacing system LOCA through MCPs intermediate circuit outside confinement 5 4 Other Interfacing system LOCA outside confinement 5 5 Blowback from HTS into ECC and rupture of ECC piping LOSP Loss of power 6 1 Loss of all off site Loss of all off site Loss of off site power Loss of all off site Total loss of in house power power power power supply 6 2 Loss of power to Loss of power in Partial loss of off site Total loss of Class IV Loss of in house necessary plant switchyard power power power supply systems Partial loss of Class IV power 6 3 Loss of Vital AC Bus Loss of 0 4 kV 220 V Loss of 6 6 kV AC Total loss of Class II power Power power Loss of essential 6 kV Loss of 380 V AC Partial loss of Class II power Power power 6 4 Loss of Vital DC Bus Loss of DC power Loss of DC Power Total loss of Class I power Partial loss of Class I power 6 5 Loss of transformer Loss of auxiliary power loss of auxiliary transformer RPF Reduction of primary flow 7 1 Loss of RCS flow Loss of RCS flow due Recirculation control Partial loss of HTS Trip of one MCP one loop to unknown reason failure decreasing flow due to failure of flow one pump Trip of one recirculation pump 7 2 Total loss of RCS Trip of MCP Trip of all recirculation Total loss of HTS Trip of several MCPs flow pumps pumped flow 7 3 MCP seizure Recirculation pump MCP seizure
37. Outage system component code Outage type code Owner Planned energy loss Planned Energy Unavailability Factor Power Reactor Information System PRIS Liaison Officer PRIS tutorial Process heating energy Reactor model Reactor status Reactor supplier Reactor type Reference period Reference energy generation Reference unit power Refuelling outage Shutdown reasons Shutdown Cancellation date Site Thermal power Total production of electricity in a country Turbine supplier Unavailability data Unit Capability Factor Unit Capability Loss Factor Unit code Unit name Unplanned Automatic Scram Rate Unplanned energy loss U U Jnplanned Scram Rate Web Enabled Data Acquisition System 76 Jnplanned Energy Unavailability Factor Abbreviation OC OE OF PEL PUF PRIS PRIS LO PPH RUP UCF UCL UA7 UEL UUF US7 WEDAS Section 5 1 5 5 1 5 4 2 5 3 4 1 1 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 5 3 4 1 1 5 2 2 5 4 2 1 2 25 6 2 1 4 1 1 4 1 1 4 1 1 4 1 1 5 2 1 S22 4 1 2 5 1 5 tee 4 1 3 4 1 1 4 1 2 4 1 1 522 5 4 2 5 4 2 4 1 1 4 1 1 5 4 2 5 22 5 4 2 5 4 2 AGR BWR DWV EAF ECCS EG EL EPL EUF FBR FEL FLR Gcal GCR GW GW h HTGR HWGCR IAEA ID IE IRS ISO LF LFH LTS LWGR MW MW h NAS NCH NEA NEG NMS NPP NSSS OC OE OF PBMR PDH PDI PEL PHWR PI ABBREVIATIONS advanced gas cooled reactor boiling water reactor desalinated water vo
38. R aed Rene 75 ABBREMIA TIONS coosssusiussgvtcsnsaastionntartaeuctawseeiacs stents EE E EEE AS T1 ENERGY UNITS AND CONVERSION FACTORS o oo eee cece eeeeeecesecnaecsesaeeeeeeeeees 79 ANNEX I GENERIC INITIATING EVENT LIST IN PRIS oo eeeeseeceseeeeeeenneeneeeees 81 ANNEX II QUESTIONNAIRE FOR CONSTRUCTION DATA 0 eeeteeeee eee 93 ANNEX III SHORT DEFINITIONS OF PRIS KEY PERFORMANCE INDICATORS 97 1 INTRODUCTION TO THE PRIS DATA STRUCTURE The Power Reactor Information System PRIS is the IAEA database on the world s nuclear power plants It contains the specifications and performance data of power reactor units The PRIS database is available free of charge to IAEA Member States through its public website and on line applications PRIS contains information on all power reactors that are in operation under construction or permanently shut down covering the history of nuclear power since 1954 The data for monthly production and power losses have been recorded in PRIS since 1970 The PRIS database has an open modular structure The latest status of the structure is shown in Figure 1 1 The module of reactor specification data supports all other modules except the country data module containing specific data In the operational data module the electricity production data also includes information on energy provided by nuclear power plants to non electrical applications such as district heating process heat supply and desalination The da
39. RIS users in case you expenence protherns printing repons Som PRES Statistics please ask a uset wth agrerusirative peges to hog ou to your Windows machine in onder 1o download the toquired AcuraX control PRISTA reports can only te puted Bom wither Mamet Explorer Allermutyely export reperts to POF ang grset the cosufting fie Current statue Of te nucleos industry e 436 nucioat power eeactors m Operation 3 nuclear power reactors in Long Term Shutdown e T2 coclew power reactors Uoder Constrection For the Geert naws on Nucteas Power Plants wed AES Dare Comer PTOS The rfman amanet N PRIS Out not await 0 De pti wer ete Sor eter uae Of De a gerrsetcn anaryerg t Ht al oot Oe queced Fay AAK S MEA forum wert cere of Pe LALA od Se Cancened Member Styne PRIS Fewer Beotio bfermeBon Dsena Copei Pernetera Abie Esergy Ages Comtert Ly died PE FIG 2 1 PRIS WEDAS login For each country one PRIS liaison officer can be registered in WEDAS The function of the liaison officer is e To support official communication with IAEA regarding PRIS e To support and supervise the process of data reporting within the country e To participate at the biannual meeting to discuss development of PRIS The liaison officer has full access to his country s data and read only access to all raw data of power reactor units within the country This allows him to supervise data inputs in the country In some countries the PRIS liaison officer also serves
40. al modifications one or more areas where modifications have been implemented should be selected in the following categories Fuel modification or reactor core arrangement Primary systems steam generators drum separators main coolant pumps Balance of plant turbine main generator condenser heat exchangers feed water systems Instrumentation and control systems e Description it is required to provide more details why RUP has been changed e Attachment for additional details it is possible to upload a related publication More than one revision can be specified during the reporting year When month is specified all data fields with red asterisks should be duly filled in WEDAS does not allow saving when not specified WEDAS has an internal check of the new RUP value It cannot be greater than the latest gross electrical power specified in Basic Information of the specification data module Whenever the RUP is modified it is necessary to review and update values of the latest gross electrical power eventually the thermal power if necessary in Basic Information The RUP revision record can be removed by clicking on the Delete icon in the last column of the record This action will restore the previous RUP values in the monthly records Clarifying notes a If a maximum power capability has been determined by formal test the reference unit power is determined by correcting test results to reference ambie
41. alculated from the commercial date to eliminate the influence of trial operation Shutdown Cancellation Date Shutdown Cancellation date signifies the date when the plant is officially declared to be shut down by the owner and taken out of operation permanently For cancelled projects when a reactor is planned or under construction it is the date when the project is declared to be cancelled 4 2 DESIGN CHARACTERISTICS The NPP design characteristics represent a fundamental part of the PRIS database They provide important information on the main components of a NPP unit such as the reactor or turbine briefly describe safety and essential auxiliary systems and list technical specifications of significant plant equipment The objective of the unit design characteristics is to provide a consistent overview of design features and technical specifications of the reactor units stored in the PRIS database The characteristics serve as the most comprehensive information on the design of all operating under construction and shutdown units worldwide In combination with other PRIS data and outputs such as production data outage data and performance indicators design characteristics offer an important tool for various performance analyses The classification system enables the appropriate characteristics to be used as convenient selection or filtration criteria for choosing reactor units suitable for a particular analysis there
42. ally scheduled work or to complete corrective maintenance work on equipment required for start up all energy losses associated with the outage extension should be considered as unplanned outage extension loss EPL not forced However outage extensions to complete discretionary work 1 e preventive maintenance or modifications not originally scheduled for completion during the outage should be considered as planned if the work is scheduled at least four weeks before the extension began Other externally caused Energy Losses net XEL Data entry for energy expressed in electric megawatt hours MW e h that was not delivered during the month due to constraints reducing plant availability and being beyond the plant management control 42 Externally caused energy losses are crosschecked with outage records in the consistency test V see 5 4 1 Clarifying notes a Energy losses caused by the following conditions should be reported as XEL e Environmental conditions seasonal variations in cooling water temperature flood storm lightning lack of cooling water due to drought tidal valves high sea or water intake restrictions that could not be prevented by operator action e Fuel coast down power reduction at the end of fuel cycle resulting in release of a positive reactivity to compensate for high fuel burn up e Restrictions on supply and services due to external constraints lack of funds due to delayed pay
43. an be added via the function Add Milestone The milestone record is specified by the following data items Category Selection of the milestone category from the following list e Power up rating e Power de rating e Licence renewal e Major component system replacement SG I amp C TG e Major refurbishment for an extended period e Major external events earthquake flooding e Regulatory restrictions e Political decisions e Other 25 Clarifying comments to be provided in a separate data field if other is selected Date The date of the milestone in the format YY YY MM DD or just year YYYY Usually it is the date when an event or decision occurred or when a modification was implemented Description The text field for more detailed description of the milestone For every milestone WEDAS allows to add links to the internet sites or to attach documents with more detailed information The PRIS database is connected to the IAEA Incident Reporting System IRS which contains detailed reports about operational events at reactor units The milestone screen contains a list of reactor specific events reported into IRS The list consists of an incident date title and short abstract Please refer to IRS for additional information 26 5 OPERATIONAL DATA 5 1 OPERATING EXPERIENCE DATA The Operating Experience OE data screen contains information on the general
44. arise from the use of this publication This publication does not address questions of responsibility legal or otherwise for acts or omissions on the part of any person The use of particular designations of countries or territories does not imply any judgement by the publisher the IAEA as to the legal status of such countries or territories of their authorities and institutions or of the delimitation of their boundaries The mention of names of specific companies or products whether or not indicated as registered does not imply any intention to infringe proprietary rights nor should it be construed as an endorsement or recommendation on the part of the IAEA The IAEA has no responsibility for the persistence or accuracy of URLs for external or third party Internet web sites referred to in this publication and does not guarantee that any content on such web sites is or will remain accurate or appropriate CONTENTS 1 INTRODUCTION TO THE PRIS DATA STRUCTURE cceccccceesteceeeesseeeeeeeaes l 2 WEDAS A PPE ICANT QIN mecene nn R E EEE R R a lh eam oka Gat re 2 2 1 WEDAS USERS ACCESS RIGHTS RESPONSIBILITIES cc cccecceeseeseeeteeeeeees 2 2 2 DATA ENTRY SCREEN DS Ss ete te cant E fae oa cae Ral 4 2 TILLERS POR DATA ENTRY a iets cek E Y Values veces se Sancuscaeaueataes 5 24 DATA STATUS CONTRO Dusena E E sear aaa eas 5 2 5 ON LINE HELPS AND TUTORIA i sacccctocasiceseondun nes cuedoanesatyline aves den sbaverdcnegueneetiian cate 7 3 COU
45. ation Loss of ventilation Loss of Ventilation Loss of control room ventilation Loss of distribution room ventilation Loss of reactor building ventilation HVAC failure 16 9 Loss of instrument air Loss of control air Loss of Instrument Air Total loss of instrument air 16 10 Loss of intermediate cooling circuit LOSFW Loss of feedwater 17 1 Feedwater line breaks Feedwater line break Symmetric feedwater Break of the main in unisolable from SG part Feedwater pipeline break inside confinement Feedwater pipeline isolable break outside confinement Feedwater pipeline unisolable break outside confinement line break outside RB Asymmetric feedwater line break outside RB Asymmetric feedwater line break inside RB feedwater pipeline 88 Code PWR WWER BWR PHWR RBMK CONT Confinement Containment 18 1 Containment pressure problems LOOL Loss of Load 19 1 Electric load rejection Generator load surge 19 2 Electric load rejection with turbine bypass valve failure FM Fuelling machine events 20 1 Fuel bundle in channel crushed by FM 20 2 Failure of FM D20 supply or cooling FM off reactor 20 3 Failure of transfer port and transition piece cooling fuel stuck damaged 20 4 Fuel assembly jamming or breaking off during its installation in the spent fuel pool by the refuelling machine 20 5 Canister with spent fuel falling or be
46. ault setting is All except the data status The default status In Progress helps data providers in identification of pending data entry This setting can lead to empty table not shown in cases where all data has been already submitted To see reactor records in all data status it is necessary to select particular reactor or particular year The system does not allow setting all filters as All The columns of the landing table can be sorted using Sort by 2 4 DATA STATUS CONTROL Data provision through the WEDAS system has four steps e In Progress The data are fully under the data provider s control The data provider can enter or modify the data and check them via consistency tests and indicator calculations While data are in progress the system and PRIS administrator consider them as unfinished and unauthorised The data remain in WEDAS only and are not used in any of the PRIS outputs e Submitted This indicates that a data provider has finished data entry and data can be considered as completed and authorised Status is changed from In Progress to Submitted by the data provider Before submitting production data the data provider is expected to use all consistency tests and performance indicator calculation which WEDAS provides for data quality assurance While data are submitted the data provider can see the data but cannot modify them In order to correct any later identified discrepancies
47. automatic scrams in OE must be the same as the number of combined outages in the year with outage of type UF4 or XF4 The number of manual scrams in OE must be same as the number of combined outages in the year with outage type UF5 or XF5 5 4 2 Performance indicators WEDAS offers the option to perform calculation of all basic performance indicators using the entered data elements directly Data providers are encouraged to use this function as a next stage of data quality control before data submission The following performance indicators can be calculated in the WEDAS system EAF Energy Availability Factor EUF Energy Unavailability Factor PUF Planned Energy Unavailability Factor 57 UUF XUF UCF UCL FLR OF LF UAT US7 Unplanned Energy Unavailability Factor External Energy Unavailability Factor Unit Capability Factor Unit Capability Loss Factor Forced Loss Rate Operation Factor Load Factor Unplanned Automatic Scram Rate Unplanned Scram Rate For definitions of performance indicators see 1 or Annex 3 Indicator values can be calculated for the months for which the data have been entered If input data is available quarterly or annual indicator values can also be calculated To compare the current indicator values with long term performance indicator values for the last 12 months and 36 months are also provided The calculation table is complemented by performance statistics of
48. ay system High pressure safety injection and emergency poisoning system Auxiliary and emergency feed water system Containment spray system active Containment pressure suppression system passive Containment isolation system isolation valves doors locks and penetrations Containment structures Fire protection system None of the above systems Reactor Cooling Systems Reactor coolant pumps blowers and drives Reactor coolant piping including associated valves Reactor coolant safety and relief valves including relief tank Reactor coolant pressure control system Main steam piping and isolation valves BWR None of the above systems Steam generation systems Steam generator PWR boiler PHWR AGR steam drum vessel RBMK BWR Steam generator blow down system 16 03 16 99 17 00 17 01 17 02 17 03 17 04 17 05 17 06 17 07 17 99 Steam drum level control system RBMK BWR None of the above systems Safety I amp C Systems excluding reactor I amp C Engineered safeguard feature actuation system Fire detection system Containment isolation function Main steam feed water isolation function Main steam pressure emergency control system turbine bypass and steam dump valve control Failed fuel detection system DN monitoring system for PHWR RCS integrity monitoring system RBMK None of the above systems Fuel and Refuelling Systems 21 00 21 01 21 02 21 03 21 99 Fuel Handling and Storage Faciliti
49. by improving the relevance of such analyses The PRIS set of NPP design characteristics are defined and described in detail in the publication IAEA TECDOC 1544 Nuclear Power Reactor Design Characteristics The characteristics have been organised in four main groups Primary Systems Secondary Systems Spent Fuel Storage and Non Electrical Applications In these main groups systems subgroups have been arranged and named according to usual plant equipment configuration and terminology Figure 4 3 shows a part of data entry screen for primary systems 19 Specification Data Operatinnal asta hangan React Basic Information Design Charactocistics Schemntics Milestones Coutact Getaite Primary Systeme Parameters Flag Solect Reactor pressure voesol sacio wresel whispe Cytndrical Hamsphaneai End React wessel cernes omats Valea Reactor weasel matera Adoved Steel eee cluding mn Seniniens Sine Vennel claching rmatenal upectcatece 55 4 Rem A540 rd heg 123272 a Samet or 937 on m nes 200 Reactor Corm of SSSAMERy gaaastry Square gt Rod Fuel mateni uo Ratusting type OFF ane Mogen mocenal H20 o 56 male i Ayy Averaze Gocharge dumup Mar 44000 Artie Ste Gathatar i 104 Artie Cote bengt length m Tr barther oF saie tual Abaas bunda FIG 4 3 Design characteristics Currently the design characteristics in PRIS are a standard set of 139 parameters All parameters have on line help and defi
50. coming jammed in a hanging position during refuelling 20 6 Fuel assembly jamming or breaking off during its removal from the channel by the refuelling machine under reactor operational conditions 20 7 Fuel assembly falling or becoming jammed in a hanging position during its handling by the central hall crane IFBE Irradiated fuel bay events 21 1 Failure of fuel cooling in irradiated fuel bay IBF magazine 21 2 Loss of bay inventory into RB during irradiated fuel transfer 21 3 Loss of IFB heat sink 21 4 Loss of IFB inventory outside the RB 89 Code PWR WWER BWR PHWR RBMK 21 5 Loss of IFB ventilation system LMHS Loss of moderator heat sink 22 1 Partial loss of moderator heat sink 22 2 Total loss of moderator heat sink 22 3 All pipe failure of moderator system outside calandria 22 4 All pipe failure of moderator system inside calandria 22 5 Calandria drain line breaks outside the shield tank 22 6 Moderator system leaks into GP1 RCW 22 7 Calandria vessel failure SCE Single channel event 23 1 Calandria tube failure LESC Loss of end shield cooling 24 1 Total loss of end shield cooling 24 2 Loss of end shield cooling system inventory due to pipe breaks or leaks UHS Ultimate heat sink fai lure 25 1 Loss of main heat sink 25 2 Loss
51. construction and operation to permanent shutdown Reactor status should be selected from the drop down list A logic applied on the list offers only those categories that can follow the current status of a reactor Timely update of reactors status helps IAEA and nuclear industry keeping track of nuclear power development Any update of this data item requires communication with the PRIS administrator who should change the Basic Information data status to in progress to allow reactor status modification Definitions Planned reactor A reactor is considered as planned from the date of application for construction license to the date of construction start when the first major placing of concrete usually for the basement of the reactor building was carried out Suspended plan Planned project was suspended and a new date for construction start has not been specified Cancelled plan Planned project was definitely cancelled before construction start Under construction A reactor unit is under construction from the construction start date to the date of first grid connection Suspended construction Construction of a reactor was suspended and a new date for construction start has not been specified Cancelled construction Construction of a reactor was definitely cancelled before the construction was finished 13 14 Operational In operation A reactor is considered as operational or in operation from its fi
52. crams performed as a part of planned tests are not reported c The outage extension is a prolongation of the planned outage beyond its originally planned completion date Outage extension must be reported as unplanned in a separate outage record However when outage extension is announced at least four weeks in advance it is considered a part of the planned outages and is not reported separately as unplanned extension 45 eeereg pre Poom Oxeages eoem o ootia or m te FIG 5 7 Outage data screen Data elements in an outage record Outage duration Data entry for total time of the outage measured in hours from the beginning of the reporting period or the outage whichever comes last to the end of the reporting period or the outage whichever comes first Clarifying notes a If a part of the outage extends to the next reporting period the corresponding outage duration is coded for each reporting period separately All outage fragments of the same outage should be linked into one combined outage b If an outage record is not fragmented and includes both the power decrease and power rise periods before and after a full outage period the time should include also those parts c The outage duration cannot be zero 0 and the field cannot be left blank d For reactor scram after disconnection of the unit from the grid energy loss is zero at least a minimum duration 0 01 hour should be reported
53. ctor unit PRIS does not maintain except the Reference Unit Power history of specification data It is a responsibility of data providers to keep specification data updated Specification data should be updated immediately after a change in specification WEDAS registers the date of the latest update Even if no update is needed for specification data a regular verification is required mainly for basic information at least once per year and design characteristics at least once per five years The same data status categories as described in Chapter 2 4 are used for specification data but with a significant exception that some data items are editable even in the Published status It means that all updates are done directly in PRIS production tables and are reflected in all PRIS statistics and outputs starting the next day after the change The key data items for example reactor name reference number reactor type or reactor status are locked when published To update information in these data fields the PRIS administrator should change the data status to in progress to allow a data provider to modify content 4 1 BASIC INFORMATION Reactor basic information consists of reactor identification status under construction in operation etc suppliers historical milestones and capacity parameters These data are used for reactor classification Some data items are highlighted by red asterisks Those data items are obligato
54. culated for each period as shown below Lp 400 X REG OPERATION FACTOR OF PURPOSE The purpose of this indicator is to monitor the actual time utilization of the unit with the turbo generator set synchronized to the grid whatever the power produced over a certain period of time DEFINITION Operation factor is defined as the ratio of the number of hours the unit was on line to the total number of hours in the reference period expressed as a percentage It is a measure of the unit time availability on the grid and does not depend on the operating power level In some systems the indicator is called as a Time Utilization Factor DATA ELEMENTS The following data are required to calculate this indicator for each unit e t unit on line hours in the reference period e TT reference period in hours 98 CALCULATIONS The unit operation factor is calculated as shown below t OF T 100 UNIT CAPABILITY FACTOR UCF PURPOSE The purpose of this indicator is to monitor progress in attaining high unit and industry energy production reliability This indicator reflects effectiveness of plant programs and practices in maximizing available electrical generation and provides an overall indication of how well plants are operated and maintained DEFINITION Unit capability factor is defined as the ratio of the capable energy generation over a given time period to the reference energy generation over the same time
55. d TSO PO Box 29 Norwich Norfolk NR3 1PD UNITED KINGDOM Telephone 44 870 600 5552 Email orders books orders tso co uk enquiries book enquiries tso co uk e Web site http www tso co uk UNITED STATES OF AMERICA Bernan Associates 4501 Forbes Blvd Suite 200 Lanham MD 20706 4391 USA Telephone 1 800 865 3457 Fax 1 800 865 3450 Email orders bernan com Web site http www bernan com Renouf Publishing Co Ltd 812 Proctor Avenue Ogdensburg NY 13669 USA Telephone 1 888 551 7470 Fax 1 888 551 7471 Email orders renoufbooks com Web site http www renoufbooks com United Nations 300 East 42 Street IN 919J New York NY 1001 USA Telephone 1 212 963 8302 Fax 1 212 963 3489 Email publications un org Web site http www unp un org Orders for both priced and unpriced publications may be addressed directly to IAEA Publishing Section Marketing and Sales Unit International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna Austria Telephone 43 1 2600 22529 or 22488 Fax 43 1 2600 29302 Email sales publications iaea org Web site http Awww iaea org books LL6SE SL sae ES j r aps i s a re a4 6 amp 4 v J s d d d gas i E s 4 i ie 7 Pd J i 4 i i t 5 tne s en ante i Peta i Err ro oe tt Er ae n f s e e T M O O TANTANA aS PNZ is p z oaa i ve errtae si si
56. d in the outage For example if a minor equipment failure such as an oil leak dropping on a hot pipeline or a short circuit in a non vital switchgear cabinet results in an extensive 49 50 b c d fire that directly causes an outage the fire is considered the direct cause of the outage For a particular outage full or partial only one cause may be selected If two or more causes were involved in the outage select the most significant If outages occur successively they must be reported as separate outages due to different causes For example if unit power was first reduced due to an equipment failure but the unit subsequently tripped due to a human error when responding to the failure these incidents should be reported as two separate outages caused by equipment failure and human factor respectively Similarly partial and full outage following immediately one after the other and having the same direct cause must be reported separately The direct cause code consists of following codes Plant equipment failure Refuelling without a maintenance Inspection maintenance or repair combined with refuelling Inspection maintenance or repair without refuelling Testing of plant systems or components Major back fitting refurbishment or upgrading activities with refuelling Major back fitting refurbishment or upgrading activities without refuelling Nuclear regulatory requirements Grid limitation a new cause code in th
57. dditional information about a location of the nuclear power plant e Address of the plant e Name of city near the nuclear power plant e State province of the country e Country assigned when the reactor record is created e Geographical coordinates latitude and longitude of the site e Climatic zone selection from Subarctic Mild temperature Subtropical Tropical e Location selection from Inland near a lake Inland near a river Seacoast Reactor Site Address Cty Stato Country BELGIUM Lataude od min sac Longaude z gd min sec Retreat Mape Climatic Zone Locaton X Information Status Subenmed Save FIG 4 2 Site specification The site specification screen also contains a map which shows the location of the site after coordinates have been filled in The map helps as verification of correctness of coordinates Operator A short name of the current company that operates the nuclear power plant Operator specification contains additional information e Full name of the operator e Address of headquarters e Website URL of an official website of the company 15 Owner A short name of the owner of the nuclear power plant Owner specification contains additional information e Full name of the owner In case of consortium of more companies the names of all companies and their share e Address of headquarters of the company having majority share in ow
58. displayed in brown The calculated value may be corrected by data providers considering the actual thermal efficiency of the plant The corrected value is displayed in black Lifetime Cumulative Energy Generation net 30 Data entry for sum of net electricity generated supplied to the grid in GW h since the first connection of a reactor unit to the grid WEDAS checks the reported value against a sum of annual energy production in the current reporting year and lifetime electricity production reported for the previous year A decimal point not comma should be used in case of a decimal number Lifetime generation is verified in the consistency test VII see 5 4 1 5 1 3 Highlights of operation Text information highlighting the main achievements and main events affecting operation of a reactor unit Highlights during the year Brief description of general performance and operational modes of the plant over the reporting period e g operation at full power in base load mode load following for a period shut down for a period major achievements leading to increased availability Description of significant factors affecting energy generation over the reporting period e g limitations introduced by regulatory bodies limitations due to fuel management shortage of consumables personnel factors equipment performance environmental conditions 5 1 4 Scram related numbers Scram means the manual
59. e PRIS coding system Grid failure or grid instability AS he EOUH OBR demand losses due to reactive power demand from the grid Human factor related Governmental requirements or Court decisions dry weather cooling water temperature limits etc Fire DYO ZXR outside the plant spare part delivery problems etc a extend an operating cycle or coast down operation due to fuel burn up T Heat supply on site to support next unit or desalination and off site heat distribution U Security and access control and other preventive shutdown due to external threats Z Others e Planned outages may be due to causes coded B C D E F G f Unplanned outages may be due to causes coded A H L P g External outages may be due to causes coded I J K M N O R T and U Energy losses coded as I J K O M U are not reportable as externally caused unavailability XEL but are reportable in outage records h The cause coded S can apply to planned stretch out operation unplanned high flux tilt and external outages coast down operation Load following frequency control reserve shutdown due to reduced energy Environmental conditions flood storm lightning lack of cooling water due to Load dispatching prioritization a new cause code in the PRIS coding system External restrictions on supply and services labour strikes lack of funds due to delayed payments from customers disputes in fuel industries
60. e as a loss associated with an equipment failure Continuous de rated operation due to the presence of failed fuel is classified as unplanned until the unit is shut down for refuelling g If a unit begins an outage or load reduction before the scheduled start date the energy loss from the beginning of the outage or load reduction to the scheduled start date is an unplanned forced energy loss FEL h Special cases of concurrent losses when the reactor unit is shut down e A loss cannot be classified as planned and scheduled to correct causes of unplanned losses after the unplanned losses begin However when causes of unplanned losses continue after the scheduled start date of already planned and scheduled shutdown the unplanned losses are not reported during the planned shutdown period The reported losses are unplanned FEL EPL for the period before the planned outage and planned PEL for the period of the scheduled shutdown e If unplanned losses continue even after the scheduled end date of the planned shutdown the unplanned losses are either o Outage extension losses if repair of that cause is required for startup or work planned and scheduled during the planned period was not completed as planned and scheduled o Unplanned forced losses if the cause existed prior to the planned outage and was not repaired by its end and not needed for startup i If an outage extends beyond the scheduled start up date either to complete origin
61. e checks are designed to catch data entry errors If the correct value is outside the range please use the contact us feature There are circumstances where data is not available or not applicable for the required parameters A Flag selection feature is provided for these cases to override the data checks and allow other data to be saved The design parameter can be marked not applicable the parameter is not relevant for a reported reactor type or not available the parameter is relevant but not known and will be specified later To override the checks select the parameter s checkbox and then select the appropriate Flag option The save action also verifies any parameter marked as not applicable or not available is not allowed to have data entered The flag can be cleared when applicable value is available select parameter s checkbox and then select clear flag choice in the Flag selection list 4 3 CONNECTED NON ELECTRICAL APPLICATIONS As a separate part of design characteristics the reactor units with non electrical applications NEA have a screen with read only information about NEA units connected to the reactor units For details regarding NEA units see Chapter 6 The NEA units are specified by e NEA unit name e Type e Service start date 4 4 SCHEMATICS In addition to the design specification data the PRIS database can accommodate other descriptive data such as uni
62. e preferable means of data reporting is through WEDAS To improve data quality WEDAS has quality and consistency checks to verify the accuracy of the data provided Reporting data in Excel spread sheets or MS Access tables is also possible but causes extra effort for the PRIS administrator when it comes to data importing and testing All PRIS contact persons registered in WEDAS have full access to the PRIS Statistics application which allows them to generate statistical reports from PRIS 2 2 DATA ENTRY SCREENS After successful login the WEDAS landing page appears As default it is open with the choice Reactor Information see the green bar on the top of WEDAS screen The other data options are Country Information for country level data module and Add New Reactor for creating a new reactor record in PRIS Poorer Remote Uvigtrmuttioe Sy geen Reactor Information Das rom Seremos Cert Opererional ets Cec cee emiceeny hare v ort beerees et nere bene ae Vea Prima tna doe BLA Dais Ma aea ae e SER an at oaan e be aa ead a a l all ae pi Mo gaume oaee i S AD eito ooet oa nOn l aunat aa aei e o Oa DEL S eee FIG2 3 PRIS WEDAS Landing Page The landing screen for reactor information Figure 2 3 contains radio buttons for selection of reactor unit specific data modules e Specification Data e Operational Data e Decommissioning Data e Initiating Events e Construction Data Activation of data screens for particular react
63. eactor coolant pump reference energy generation reference unit power steam generator steam generating heavy water reactor structure system or component on line hours reference period hours turbine generator terawatt hour unplanned automatic scram rate unit capability factor unplanned capability loss factor unplanned energy loss uniform resource locator unplanned scram rate unplanned unavailability factor Russian model of PWR World Association of Nuclear Operators web enabled data acquisition system externally caused energy loss external unavailability factor ENERGY UNITS AND CONVERSION FACTORS cal Calorie kg ce kilogram coal equivalent kg oe kilogram oil equivalent m natural gas cubic meter natural gas m kg ce kg oe natural gas 79 ANNEX I GENERIC INITIATING EVENT LIST IN PRIS Code PWR WWER BWR PHWR RBMK AS Administrative shutdown 0 0 Administrative Administrative Administrative Administrative Administrative shutdown shutdown shutdown shutdown shutdown EPI Excess of primary inventory 1 1 Inadvertent safety Inadvertent safety Inadvertent startup of Spurious ECCS injection actuation injection actuation HPCI HPCS actuation 1 2 Inadvertent injection Inadvertent injection to to primary side from primary side from make up water make up water system system 1 3 Startup of inactive Startup of inactive Act
64. eckbox on the left of the reactor site names 24 The right part of the table Current usage contains a list of reactors sites to which the image has been already assigned including information who added the image into PRIS The function Replace Image provides a possibility to replace an existing image with a new one while keeping all specifications and assignments 4 5 MILESTONES The Milestones data screen provides the possibility to specify important operational events design modifications major refurbishments or decisions that had a significant impact on the reactor unit operating history svasmcation Ove nat wrtaurnn Basic korny esiga Checartermica Schemeticy Milestones Convert Catete Miiwtianes Ste Category Date Description tdo Update ete Desete Acc Meiuse 43d Anacreon Documente Ostermect Add Document Deerrytien ve wenn Incident Date lee Aberoct 1960 22 22 RAPD TEMPERATURE DECREASE OF REACTOR PRESSURE Da 03 potis wd tor phanine ihe pow s a s tty tom Th VESSEL OLE TO OPERATING ERROR BIN ee eed iu cot OF the ornare piy 10 tuite fony Qus C ewtegeis ote t aS 24 A FAST OROS M THE REMOVAL EFFICIENCY OF OFF GAS imag ee 5 EEE t af p Oa eared a Pe f r Pas epsit sermon higitan FETERS dal tet hee detect by bed bese oon a otc ey of the 1380 08 69 FALLRE OF THE ROCKER AM fi THE EUS VALVE sg Ne poen MERILE H ese Re 4 wer Ara Na I S In PTRS wae H bee FIG 4 7 Milestone data screen A new milestone c
65. ed to be planned assuming this decision is due to all of the following reasons or circumstances e The unit is considered as able to run at maximum power during the four week period prior to the initial planned outage start date e Any forced or unplanned outage occurring during this four week period or before the new start date shall not become the reason for putting forward the planned outage Unplanned Energy Losses net UEL 40 The energy expressed in electric megawatt hours MW e h which was not delivered during the month because of unplanned shutdowns unplanned load reductions or outage extensions due to causes under the plant management control The shutdowns or load reductions due to causes under plant management control are considered unplanned if they are not scheduled at least four weeks in advance Unplanned energy loss is reported in two categories e Forced energy loss during operation e Unplanned extension of planned outages Unplanned energy loss is a sum of the above data items and is shown as read only information It is crosschecked with outage records in the consistency test III see 5 4 1 Forced energy losses FEL Data entry for energy expressed in electric megawatt hours MW e h that was not delivered during the month because of unplanned shutdowns or unplanned load reductions that happened during operation due to causes under the plant management control Extensi
66. emain constant unless following design changes or a new permanent authorization the management decides to amend the original value 4 1 3 Reactor unit history Specification of key dates provides a brief overview of reactor unit history The selected dates are important milestones and represent the time boundary between the different status periods of a reactor during its lifetime Construction Licence Date The construction licence date is a date when application for construction licence has been submitted From this date the reactor should be considered as a planned reactor and reported into PRIS Construction Start Date The date when the first major placing of concrete usually for the base mat of the reactor building is carried out 17 From this date the reactor is considered to be under construction Clarifying notes a Current definition of construction start is the first concrete pouring for the main base mat of the reactor building Due to new technologies and the modular construction of a new NPP a significant part of the nuclear island budget more than 40 is spent before the first concrete is laid For this reason it is proposed to use Authorisation to Proceed ATP as the beginning of construction for plants using modular construction b For floating NPP the construction start date is the beginning of platform construction Suspended construction The check box for act
67. ement control Systems components involved in the outage Selection of a system from the table and component subsystem from the dropdown list primarily involved in affected by the outage Clarifying notes a For a single outage full or partial only one system may be selected If two or more systems were involved in the outage select either the system directly causing the outage or the one being most significantly affected b Outages records with cause codes A E must be completed with system component codes Outages records with other cause codes can be whenever applicable completed with system component codes c If no particular system could be specified from the general system group enter the general system code xx 00 d In case a particular system was involved in the outage but no suitable code was found in the list choose the appropriate general system group and enter the other code xx 99 e The choice None is applicable for outage records if no system was involved affected f The system code consists of following codes Nuclear Systems 11 00 Reactor and Accessories 11 01 Reactor vessel and main shielding including penetrations and nozzles 11 02 Reactor core including fuel assemblies 11 03 Reactor internals including steam separators dryers BWR graphite pressure tubes 51 52 11 04 11 05 11 06 11 99 12 00 12 01 12 02 12 03 12 04 12 05 12
68. emineralized water supply system including water treatment 53 34 05 34 06 34 07 34 08 34 09 34 10 34 99 35 00 35 01 35 02 35 03 35 04 35 05 35 99 Auxiliary steam supply system including boilers and pressure control equipment Non nuclear area ventilation including main control room Chilled water supply system Chemical additive injection and makeup systems Non nuclear equipment venting and drainage system Communication system None of the above systems All other I amp C Systems Plant process monitoring systems excluding process computer Leak monitoring systems Alarm annunciation system Plant radiation monitoring system Plant process control systems None of the above systems Electrical Systems 41 00 41 01 41 02 41 03 41 04 41 05 41 99 42 00 42 01 42 02 42 03 42 04 42 05 42 06 42 07 42 99 Main Generator Systems Generator and exciter including generator output breaker Sealing oil system Rotor cooling gas system Stator cooling water system Main generator control and protection system None of the above systems Electrical Power Supply Systems Main transformers Unit self consumption transformers station auxiliary house reserve etc Vital AC and DC plant power supply systems medium and low voltage Non vital AC plant power supply system medium and low voltage Emergency power generation system e g emergency diesel generator and auxiliaries Power supply system logics
69. en caused by an unplanned reactor scram even if the unit had been shut down for less than 10 hours 44 hyeri Eao Produrtion Outages funn ithendy Dacha Piel bantad atalara Cedir latata Csgo Porous Wart us on Type Cause Energy hns Operations Dos npin Nsa tias Chuitage Prous ety mode before t ALOLT O00 Ms uFi AIO mR End Dae 206 00 416 I0 Steat 45 PFO Boda dad End Date 2004 06 30 mht Ontages in Group 4 io xe it teres g h teare Reeve Combos Outages Save FIG 5 6 Screen of outage records WEDAS is ready for reporting outages in fragments as the duration of some outages is longer than the reporting period month or an outage course is a combination of various types and causes Fragments belonging to one outage should be combined into one logical ensemble allowing it to be analysed as one occurrence combined outage WEDAS supports outage fragment combination by a special function Preview Combine Outages Clarifying notes a If more outages occurred at a time they would be considered as separate outages and reported as if the unit was operating at the reference power b The reactor scram is defined as a reactor shutdown achieved by rapid insertion of negative reactivity into the reactor core which can be performed either manually or automatically All unplanned reactor scrams must be reported even if they occurred after the unit was disconnected from grid when the reactor remained at power Planned s
70. en caused the remaining control rods to insert into the core This scram is not reportable because the reactor was not critical e A reactor scram occurred while conducting a special test on the turbine The plant procedure used for this test indicated that a scram would occur while performing the test This scram is not reportable because the scram is part of a planned operation and is covered by plant procedures e While conducting a routine surveillance test of the reactor protection system at 100 power a reactor scram occurred when a spurious signal was received on one protection system channel while another channel was being tested This scram is reportable as an unplanned automatic scram e While at full power a main feed water pump tripped Operators attempted to restart the pump and to reduce reactor power but actions to maintain steam generator PWR or reactor BWR levels were unsuccessful Operators then initiated a manual reactor scram before the set point for an automatic scram was reached This scram is not reportable as an automatic scram because it did not result from an automatic actuation of the reactor protection system but is reportable as an unplanned manual scram e While at 75 power operators tripped the main turbine to prevent over speed caused by a malfunction in the turbine control system The turbine trip caused an automatic reactor scram This scram is reportable as an unplanned manual scram because the scram
71. ence Unit Power revision in a reporting year This function allows revising the RUP value in a reporting year The revised value of RUP is stored in a related monthly production record For this reason the function is active only when both operating experience data and at least one monthly production data record are in the status In Progress RUP revision can be applied only to those months for which status is In Progress in the production data screen If RUP is modified due to a power up rating project more detailed information of the project should be provided RUP revision requires the following information e Selection of a month from which the RUP value is applicable e Specification of new value for RUP Enter a new reference unit power net capacity in MW e that is foreseen to be permanent since the selected month Note that regulatory limitations for the net reference unit power of non permanent nature should not be reported here but as a partial outage due to regulatory limitation e Selection of type of revision Power up rate Power Up rate due to technical modification Power de rate Reduction of RUP due to technical limitation or regulation Results of new tests Result of new tests of plant efficiency Recalculation Recalculation to updated environmental condition or modified systems Correction Correction of an incorrect value provided by mistake e Power up rating requires selection
72. ence period hours In case of daylight saving it is necessary to modify the reference period hours first On line hours are crosschecked with outage records in the consistency test I see 5 4 1 Reference Period T Generally data entry for a total number of hours in the whole calendar month For units being commissioned during the month the clock hours from the first connection to the grid to the end of the month For units being in operation at the beginning of the month the clock hours from the beginning of the month to the end of the month or to the final disconnection from the grid whichever comes first WEDAS provides a possibility to adapt reference hours to daylight saving time It is possible to modify reference hours by 1 hour by overwriting predefined hours This modification should be confirmed by checking the box Update reference hours above the Save button Multiplication of reference period hours by RUP determines REG 35 5 2 2 Unavailability data For the purpose of the PRIS the unit unavailability is defined as a status of power plant unit when it is not able to operate at its reference power for technical or environmental reasons This condition which may be under or beyond plant management control reflects only lack of readiness of the unit for the grid It does not include situations when a power plant unit was operated at a reduced power while it would be able to operate at the
73. enter the first day of the reporting period If an outage continues from the previous reporting period enter the first day of the reporting period The field cannot be left blank For reporting outages in fragments the start date and time should be the same as the end of a previous outage fragment A maximum tolerance is 24 hours Start Time The time of outage beginning is specified by selection of hours and minutes Default selection is 00 00 Continuation of a previous outage fragment Manual setting of outage fragment links 47 Selection from the dropdown list assigns an outage record which is preceding part fragment of the same outage This assignment creates a logical link between those two parts only when the following rules are fulfilled e Time concurrence end of a preceding part is consistent with the beginning of this outage record e The first character of the Type Code P U X for Planned Unplanned and External is the same The only exception is unplanned extension of planned outage UF3 UP3 XF3 and XP3 These fragments can be combined with preceding planned P outage fragments e For the third character of the Type Code it is not allowed to combine codes 1 4 and 5 e The Cause Code of combined unplanned U or external X fragments should be the same except when planned outage is combined with unplanned extension The code E for planned outages P can be combined w
74. es On power refuelling machine Fuel transfer system Storage facilities including treatment plant and final loading and cask handling facilities None of the above systems Secondary plant systems 31 00 31 01 31 02 31 03 31 04 31 05 31 06 31 07 31 99 32 00 32 01 32 02 32 03 32 04 32 05 32 99 33 00 33 01 33 02 33 03 33 99 34 00 34 01 34 02 34 03 34 04 Turbine and auxiliaries Turbine Moisture separator and re heater Turbine control valves and stop valves Main condenser including vacuum system Turbine by pass valves Turbine auxiliaries lubricating oil gland steam steam extraction Turbine control and protection system None of the above systems Feed water and Main Steam System Main steam piping and valves Main steam safety and relief valves Feed water system including feed water tank piping pumps and heaters Condensate system including condensate pumps piping and heaters Condensate treatment system None of the above systems Circulating Water System Circulating water system pumps and piping ducts excluding heat sink system Cooling towers heat sink system Emergency ultimate heat sink system None of the above systems Miscellaneous Systems Compressed air essential and non essential high pressure and low pressure Gas storage supply and cleanup systems nitrogen hydrogen carbon dioxide etc Service water process water supply system including water treatment D
75. ference energy generation expressed in of megawatt hours electric CALCULATIONS The unplanned capability loss factor is determined for each period as shown below UCL eae 100 REG 100 OPERATING PERIOD FORCED LOSS RATE FLR PURPOSE The purpose of this indicator is to monitor industry progress in minimizing outage time and power reductions that result from unplanned equipment failures human factor or other conditions during the operating period excluding planned outages and their possible unplanned extensions This indicator reflects the effectiveness of plant programs and practices in maintaining systems available for safe electrical generation when the plant is expected to be at the grid dispatcher disposal DEFINITION Operating period forced loss rate is defined as the ratio of the unplanned energy losses during a given period of time considering only the operating period to the reference energy generation minus energy losses corresponding to planned outages and their possible unplanned extensions during the same period expressed as a percentage DATA ELEMENTS The following data is required to determine each unit s value for this indicator e REG Reference energy generation expressed in units of megawatt hours e PEL Planned energy losses expressed in units of megawatt hours e UEL Unplanned energy losses contains two terms UEL FEL EPL o FEL forced energy losses o EPL unplanned extension of a plan
76. fficult to provide individual data for PDH the total data for PDH PPH are acceptable If monthly data are difficult to provide the annual total data are acceptable Process Heating PPH 60 Data entry for monthly energy in giga calories Gcal supplied for process heating The thermal energy provided during the reference period for process heat delivered in the form of heat steam or hot water measured as the difference between the plant feed outlet and return inlet headers see Figure 6 1 Process heating is the heat provided as an energy source to chemical processes for producing commodities Typical products are paper cardboard concrete heavy water and saltern Utilization of waste heat in the form of warm water or steam for example for use in the fishery industry or in green houses is also possible but is usually excluded from reporting because it does not affect heat balance of the reactor unit Back up Source Data entry for monthly energy in giga calories Gcal supplied from non nuclear back up heat source The thermal energy provided by the non nuclear back up heat source if applicable to compensate insufficient availability of heat from the nuclear reactor This applies only when the back up heat source is under control of the nuclear power plant The non nuclear back up heat source may be installed at a nuclear power plant with multiple units in order to secure heat delivery capabilit
77. generated EG plus sum of energy losses EL should be less than REG increased by 10 of possible overproduction Formula used EG ZEL lt REG 0 1EG This criterion checks energy balance and limits overproduction to 10 of an actual EG By yellow framing the system points out a possible mistake but is ready to accept the value Red framing of the data field indicates not acceptable values WEDAS also provides additional information when a cursor is moved over the highlighted data field Planned Energy Losses net PEL Data entry for energy expressed in electric megawatt hours MW e h that was not delivered during the month because of planned shutdowns or planned load reductions due to causes under the plant management control Energy losses are considered to be planned if they are scheduled at least four weeks in advance The planned energy loss is determined by planned start date and duration of a planned outage Energy losses considered to be under plant management control are explained in the clarifying notes Planned energy losses are crosschecked with outage records in the consistency test IV see 5 4 1 39 Clarifying notes a Planned energy losses caused by the following conditions are considered to be under the control of plant management e refuelling or planned maintenance outages e planned outages or load reductions for testing repair or other plant equipment or personnel related causes b Energ
78. hnical Meeting Vienna Austria 6 9 October 2014 103 CS IAEA International Atomic Energy Agency No 23 ORDERING LOCALLY In the following countries IAEA priced publications may be purchased from the sources listed below or from major local booksellers Orders for unpriced publications should be made directly to the IAEA The contact details are given at the end of this list AUSTRALIA DA Information Services 648 Whitehorse Road Mitcham VIC 3132 AUSTRALIA Telephone 61 3 9210 7777 Fax 61 3 9210 7788 Email books dadirect com au Web site http www dadirect com au BELGIUM Jean de Lannoy Avenue du Roi 202 1190 Brussels BELGIUM Telephone 32 2 5384 308 Fax 32 2 5380 841 Email jean de lannoy euronet be e Web site http www jean de lannoy be CANADA Renouf Publishing Co Ltd 5369 Canotek Road Ottawa ON K1J 9J3 CANADA Telephone 1 613 745 2665 Fax 1 643 745 7660 Email order renoufbooks com Web site http www renoufbooks com Bernan Associates 4501 Forbes Blvd Suite 200 Lanham MD 20706 4391 USA Telephone 1 800 865 3457 Fax 1 800 865 3450 Email orders bernan com Web site http www bernan com CZECH REPUBLIC Suweco CZ spol S r o Klecakova 347 180 21 Prague 9 CZECH REPUBLIC Telephone 420 242 459 202 Fax 420 242 459 203 Email nakup suweco cz Web site http www suweco cz FINLAND Akateeminen Kirjakauppa PO Box 128 Keskuskatu 1 00101 Hels
79. i Packages Number of Contractors Delay Code 1234567890 Delay Code 1234567890 Delay Code 1234567890 Delay Code 1234567890 Delay Code 1234567890 Delay Code 1234567890 Delay Code 1234567890 REASON FOR DELAY Design changes Quality Deficiency Equipment deficiency Quality Deficiency Rework Project Management Contractual Problems Financial Human Resources Force Majeure Political Decision Other Name of the Main Contractor fill in the table bellow Name of the Major Contractors fill in the table bellow BASIC SCOPE of Contracts Contractor Name on Site Design Engineering Design Supervision Supply Construction Erection Commissioning Plant Operation Training b Contractor selection process O Government Decision O Bidding 94 4 MANUFACTURERS OF THE MAIN COMPONENTS COMPONENT Name of Manufacturer Country Reactor Pressure Vessel Calandria Steam generator Turbine Generator Main Output Transformers Fuel for First Core 5 EXPERIENCE FROM CONSTRUCTION AND COMMISSIONING WITH RESPECT TO REDUCTION OF PROJECT SCHEDULE AND IMPROVEMENT IN QUALITY A GOOD PRACTICES B NEW TECHNOLOGY e g qualification of special processes C ADVANCE METHODS e g modular concepts new automatic machines use of IT in project management DEFINITIONS Licence Holder every legal entity that is the Licence Holder for the Nuclear Power Plan
80. inancial problems Natural calamities Regulatory suspension Others specify Activities during suspension Project controls including consideration for project re start Retention of human resources Preservation and maintenance of equipment and facilities Updating for new technology and regulatory requirements Preservation of project data Project after restart New contract with original project design New contract and modified project design Continuation of original contract OOOOOOO0O 2eOOOOO g OOO f Investment Total cost equivalent of USD USD 2 PROJECT MILESTONES TERMINOLOGY DEFINITIONS MILESTONE Planned Achieved COMMENTS and reasons Date Date for delay if any A PRE PROJECT ACTIVITY Regulatory Licenses for construction Delay Code 1234567890 Contract Effective Date Delay Code 1234567890 Start ground breaking Delay Code 1234567890 B CONSTRUCTION 1 Concrete pouring Reactor Building Delay Code 1234567890 Placement of Reactor Pressure Vessel Delay Code 1234567890 inside Reactor Building Completion of Primary Boundary Test Delay Code 1234567890 Cold Hydro 93 Containment Pressure Test C COMMISSIONING 1 Hot Functional Test Fuel Loading 1 Criticality 1 Grid Synchronization 100 Power Operation Licenses for Commercial Operation CODE SOANDNBWN Ke 3 CONTRACTING STRATEGY a Type of contract O Turnkey O Split Packages Number of Contractors Name of Contractors O Mult
81. including load shed logic emergency bus transfer logic load sequencer logic breaker trip logic etc Plant switchyard equipment None of the above systems Operational mode Selection of one of the following operational modes describing the status of the unit immediately before the outage Power operation Start up shutdown operation Hot standby reactor subcritical Hot shutdown reactor subcritical Cold shutdown reactor subcritical Reactor pressure vessel open Description of the outage 54 The text in this field should describe briefly the nature of the outage and provide details It is desirable that the description provides information in addition to that provided in codes Clarifying notes a In the description it is possible to specify general causes in details the type of human factor operator mistake omission failure to monitor plant processes the type of equipment failure spurious actuation of a system component trip damage or malfunction the type of adverse environmental condition frost lightning high sea the type of load following operation frequency control reserve shutdown the cause of fire etc b For outage records with cause code Z Others the description should provide information about the direct cause c If applicable provide details of the actual type of operation activity in the particular mode e g power ascension after an outage steady power ope
82. inki FINLAND Telephone 358 9 121 41 Fax 358 9 121 4450 Email akatilaus akateeminen com Web site http Awww akateeminen com FRANCE Form Edit 5 rue Janssen PO Box 25 75921 Paris CEDEX FRANCE Telephone 33 1 42 01 49 49 Fax 33 1 42 01 90 90 Email fabien boucard formedit fr e Web site http www formedit fr Lavoisier SAS 14 rue de Provigny 94236 Cachan CEDEX FRANCE Telephone 33 1 47 40 67 00 Fax 33 1 47 40 67 02 Email livres lavoisier fr e Web site http www lavoisier fr L Appel du livre 99 rue de Charonne 75011 Paris FRANCE Telephone 33 1 43 07 50 80 Fax 33 1 43 07 50 80 Email livres appeldulivre fr e Web site http www appeldulivre fr GERMANY Goethe Buchhandlung Teubig GmbH Schweitzer Fachinformationen Willstatterstrasse 15 40549 Dusseldorf GERMANY Telephone 49 0 211 49 8740 Fax 49 0 211 49 87428 Email s dehaan schweitzer online de Web site http Awww goethebuch de HUNGARY Librotade Ltd Book Import PF 126 1656 Budapest HUNGARY Telephone 36 1 257 7777 Fax 36 1 257 7472 Email books librotade hu Web site http www librotade hu INDIA Allied Publishers 1 Floor Dubash House 15 J N Heredi Marg Ballard Estate Mumbai 400001 INDIA Telephone 91 22 2261 7926 27 Fax 91 22 2261 7928 Email alliedp vsnl com Web site http www alliedpublishers com Bookwell 3 79 Nirankari Delhi 110009 INDIA Telephone 91 11 2760 1283
83. inpectuan 2 Krsko Une Comec Secetts Description Type Copyright Datawit Sengiited tchemacs Crose necnon NEK Kreto NPP Mnl Ede Metach awry Apatiary F epctuator Operating flow NEK Vea Eda Oetacn System Gagrams Man Feedwater System Operating flow NEK View 1 Eda gt Detacht v2 Gagan Moin Feodwater Systere Operating tow NEK Veew Edi Otac 22 agar Mast amp Reheat Steuny Operating flow NER Mew Etaj Oach System Gagrars Pancenrme View NEK Vaw J Eda Oetach Rearto Cociam Systam Oparating flow NEK View I Edd Oetacn Gagrams ECCS Safety Injection Operating flow NEK View Panj Datat Syston 1 4 Gagan Resatsal Heat Removal Operating tow NEK Mews Ede Detach System 2 4 Gagaro Paoa View NEK e Em tach Amach New image Anach kosstng image Save Changes FIG 4 5 Image management screen The table allows selection of one default image for the reactor unit or site The reactor default image is used for the reactor report on the public PRIS website and for reactor dashboard reports The site default image is used for plant images on the PRIS website home page and for the reactor report if reactor default image was not selected The function Attach Existing Image image to the r eactor unit site The function Attach New Image image a file location should be selected through the The size of an image cannot exceed 700 kB Choose File provides the possibility to assign
84. ith cause codes B C D F G when E code is used for fragments related to testing of plant systems or components at the end of planned outages usually start up period after an outage e If system code is used all fragments should have the same system code If the system code is specified at least in one fragment and is not specified for other fragments then the combined outage has this fragment system code To link an outage record with other record reported in a previous year the function Get Previous Year Outages should be used Type code Selection of a two or three character code for the outage type from the dropdown list Clarifying notes a The type code consists of three partial codes characters First character P Planned outage due to causes under the plant management control U Unplanned outage due to causes under the plant management control X Outage due to causes beyond the plant management control external e Criteria for first character categorisation are in Chapter 5 2 2 For outages under the plant management control the key criterion is if the outage was scheduled at least four weeks in advance e External outages may be also considered planned or unplanned Although this aspect is not explicitly coded adding the third character see below to the external outage code will imply the unplanned external outage 48 e The unplanned extension of planned outages due to change
85. ivation of dates for the suspended construction period which is defined as a time period of plant Construction without any progress in the project schedule and without any construction activity at a site In case the construction was suspended for some period the following dates should be specified e Construction suspended date e Construction restart date Construction Suspended Date The start day of the suspended period Construction Restart Date The end day of the suspended period usually when the new contract for finishing the construction was signed First Criticality Date The date when the reactor was made critical for the first time It is an important milestone in plant commissioning Grid Connection Date The date when the plant is first connected to the electrical grid for the supply of power After this date the plant is considered to be in operation Commercial Operation Date The date when the plant is officially declared commercial by the owner 18 Clarifying notes a To declare commercial operation the owner should fulfil all obligations prevailing in the country e g nuclear operating license successful trial operation other required licences of the local regulatory authorities etc b The period from the first grid connection to the commercial date is called as trial operation c All PRIS performance indicators are c
86. lanned automatic manual scrams reactor protection system logic actuations that occur per 7 000 hours of critical operation DATA ELEMENTS The following data are required to determine each unit s value for this indicator e AS number of unplanned automatic scrams while critical e MS number of unplanned manual scrams while critical e CH number of hours of critical operation CALCULATIONS The unit and industry values for this indicator are determined for a period as shown below UA7 2 7000 CH US7 ee 7000 gt _ CH DATA QUALIFICATION REQUIREMENTS 102 The unit must have at least 1000 critical hours per year Requiring this minimum number of critical hours reduces the effects of plants that are shut down for long periods of time and whose limited data may not be statistically valid CONTRIBUTORS TO DRAFTING AND REVIEW Gelman S G Gospodarczyk M Johansson N G Juin A Karlsson M J Lahti T Mandula J Popp J Porto L R C Samdani G Semenova L VNIIAES Russian Federation Department of Energy United States of America Forsmark Nuclear Power Plant Sweden EDF DOAAT OSGE France SSM Sweden Fortun Finland International Atomic Energy Agency Nuccon GmbH Liechtenstein Eletronuclear Brazil Consultant Pakistan Energoatom Ukraine Consultants Meeting Vienna Austria 17 19 September 2013 Vienna Austria 13 15 May 2014 Vienna Austria 14 16 April 2015 Tec
87. lestones Specify main decommissioning events and milestones and year of their occurrence For an activity lasting for an extended period specify either its beginning or finishing To add another record click on the Add button and specify a new milestone 67 8 INITIATING EVENTS DATA An initiating event IE is an incident that requires an automatic or operator initiated action to bring the plant into a safe and steady state condition where in the absence of such action the core damage states of concern can result in severe core damage Initiating events are usually categorized in divisions of internal and external initiators reflecting the origin of the events Initiating event frequency is important for probabilistic safety analyses but due to the rare occurrence the statistics derived available via personal professional experience might be inadequate The IAEA has been providing assistance to Member States in PSA applications risk informed decision making and maintenance optimization The PRIS initiating events module which can be named as Scram related initiating events supports IE frequency analyses through the particular PRIS outage records e Unplanned scrams coded as UF4 UF5 XF4 XF5 e Selected forced controlled shutdowns coded as UF2 This PRIS module effectively identifies initiating events for calculating realistic IE frequencies from the worldwide shared data For the purpose of the IE
88. losure licence e g possession only licence was granted insert that date as the start year of either active or passive safe enclosure period Comments The text box for additional information about the decommissioning strategy or description of changes in the strategy Current status of decommissioning and foreseen objectives The text box for information about the future steps and objectives of decommissioning 7 2 DECOMMISSIONING PHASES Soecificatce Data Decommissioning Dats M n Oecommissioning Phases Fuel Management Contractors and miletiones Pret eae Centert Dema Scheduled decommissioning Phases Startyesr End year Comments 7 Ceawng up Te Fea Drcomma soerg Par NOS Pint P Peviscon zo Penctor core sefvelling See aso Fuel Management xa xoa Waste conditionng sete only for decommusoonng waste OPERE Waste smpment f alle only foe decommsstonng wasis J s e encors t preparator saan An aww eee 7 Parts tor areg 200 Active cate enclosure pencd sara 219 Feateve I s ercicace pesos Z Fas immig Fiai survey oH 7 Litesce tereni ated egal dof at Me OAS Of the Seco ascii process and ane EMOT for estncred unrestricted xk use 233 ae FIG 7 2 Decommissioning phases screen 65 Scheduled decommissioning Phases Selection of applicable phases and specification e Phase start year e Phase end years e Comments to a phase To add other specific phases click on the Add to
89. lti stage flash or multi effect distillation or in the form of heat measured as the difference between at the plant feed outlet and return inlet headers or between the heat extraction points and return points in the case of in plant facilities Electrical Energy Provided for Reverse Osmosis Process PRO Data entry for monthly electricity in mega watt hours MW e h supplied for reverse osmosis If applicable enter the electrical energy provided during the reference period to the desalination systems of reverse osmosis process By definition this electrical energy is a part of in site power Desalinated Water Volume DWV 62 Data entry for volume in cubic meters m of water produced by the desalination systems The monthly water production and its fraction delivered to off site consumers 7 DECOMMISSIONING DATA Decommissioning of a nuclear power plant is the process of facilities dismantling fuel transfer contaminants removal contaminated material disposal and other activities This is the process to reduce the risk of public radioactive exposure to radioactive materials remaining at the plant to a safe and reasonably low level Activities such as characterization decontamination dismantling and demolition of the installations are performed during particular periods Decommissioning data in WEDAS are organised in four screens 1 Main information 2 Decommissioning phases 3 Fuel ma
90. lume energy availability factor emergency core cooling system electricity generated energy loss extensions of planned energy loss energy unavailability factor fast breeder reactor forced energy loss forced loss rate gigacalorie gas cooled reactor gigawatt gigawatt hour high temperature gas cooled graphite moderated reactor heavy water moderated gas cooled reactor International Atomic Energy Agency identification initiating event incident reporting system International Organization for Standardization load factor load factor including heat long term shutdown light water cooled graphite moderated reactor megawatt megawatt hour number of automatic scrams number of critical hours non electrical application electrical equivalent of non electrical energy generated number of manual scrams nuclear power plant nuclear steam supply system operating cycle operating experience operation factor pebble bed modular reactor district heating energy distillation energy planned energy loss pressurized heavy water reactor performance indicator TT PPH PRIS PRIS LO PRISTA PRO PUF PWR RBMK RCP RUP SG SGHWR SSC TG TWh UA7 UCF UCL UEL URL US7 UUF VVER WANO WEDAS XEL XUF 78 process heating energy power reactor information system PRIS liaison officer PRIS Statistics distillation electricity planned unavailability factor pressurized water reactor Russian model of LWGR r
91. management l management control XEL control Capability Planned Unplanned losses PEL FIG 5 3 Data model for production and unavailability data The energy loss due to reduced power is always related to the Reference Unit Power The values of power losses to be used in computing energy losses due to a particular event are the losses that would have occurred if the unit were operating at the reference power level at the 36 time of the event Figure 5 4 shows principles for calculation The power losses relative to the reference unit power may be determined by one of the following techniques e Subtracting the actual power level during the event from the power level immediately prior to the event when the power was at or near the reference power level e Computing the power level reduction that would have occurred with the unit at the reference power level e Using historical data from similar events occurring at the reference power level For example if a unit experiences a 10 MW power loss due to an equipment problem while operating at 75 of the reference power and it is determined from calculations or from similar events that have occurred at the reference power that the same equipment problem would have resulted in a 20 MW power loss at the reference power level then 20 MW should be used when computing the energy loss Energy losses related to load reduction preceding a shutdown and load increases following the
92. ments from customers disputes in fuel industries fuel rationing spare part procurement difficulties etc e Heat supply to non electrical applications e Shutdowns load reductions and outage extensions caused by labour strikes b Energy losses due to the following causes should not be reported as XEL but should be reported in outage records as these losses are not related to plant unavailability e Grid instability grid failure or grid unavailability e Lack of demand load following frequency control reserve shutdown economic shutdown or losses due to reactive power demand from the grid e A unit that is in reserve shutdown should be considered as available if it can be restarted within the normal time required for unit start up e Security and access control and other preventive shutdown due to external threats e Governmental requirements or court decisions c The unit which is damaged by earthquake or other external events when being in a planned shutdown continues reporting planned generation losses until the scheduled end date for the original outage After that the losses should be reported as XEL in monthly records and as an externally caused outage extension XF3 in outage records until start up d If a unit was operating and scrammed as a result of an environmental event for instance earthquake or storm the scram should be reported and subsequent energy losses due to damage caused by the event are reportable as
93. module generic lists of initiating events have been developed for the following types and models of reactor units PWR VVER BWR PHWR CANDU and LWGR RBMK The IE module allows assignment of selected outage records to a particular initiating event code from the generic list and provides additional information needed for IE analyses Ir batirg E vente Screws and wist ted conpulle Aunti Initiating Event Onage record Cote Cm Explosion Patemewter Pirom Dasa Stee 7 un Tye Caw Description Sow Em FIG 8 1 Initiating Event screen The IE screens provide a list of all scrams and unplanned controlled immediate shutdowns that have been reported for the reactor unit in outage records since 2002 Currently the year 2002 when the PRIS outage coding system was modified limits selection of outage records nevertheless the recoding of historical records will allow this limitation to be removed WEDAS has three screens for the IE module 1 List of IE records This screen contains all unplanned scrams either assigned or not assigned yet to a particular initiating event and those unplanned controlled immediate shutdown records that were selected in the second screen as IE records 68 2 Controlled shutdowns This screen contains all forced controlled shutdown records from PRIS outages that were coded by the UF2 type code as IE candidates The screen allows selection of those forced shutdowns that are evaluated as an ini
94. n on line help window Using the left arrow of a browser the window is switched back to a data entry screen For the production data module which is the most complex module of PRIS special guidelines labelled PRIS Tutorial have been developed and integrated into WEDAS The Tutorial also contains practical exercises for outage coding Tutorial is available in the main menu of WEDAS Data entry chapters from Tutorial are also available directly from data entry screens through the use of the Quick Help button in the top right corner of a screen Power Reactor Information System tutori ou sre r UETA Pines PRIS Tutoria Index of Contents Introduction o Whatis PRIS e What is WEDAS e How and when to report PRIS Data e How PRIS Data proceed in WEDAS Energy production energy losses and availablity for energy production Whai is Availability How to report Availability of Data e Parformance Indicators o What does Outage mean Data Entry Country Annual information Regctor Basic Information Reactor Design Charactenstics Reactor Operational Data Annual Information Monthly Production and Unavailability Data Outage Records Outage Data How WEDAS checks Data Consistency indicator Calculation The information contained in PRIS but not available on the public web site is for internal use of the organization analysing it It shall not be quoted in any Dublic or international forum without permeson of
95. nagement 4 Contractors and milestones Experiences on decommissioning are collected by compiling information of the techniques used in decommissioning activities and disseminated to Member States The data can be completed or edited anytime and only the latest update is maintained in the database It is expected that data are updated when necessary 7 1 MAIN INFORMATION Sorten Daa Decommissioning Osta Msn Decommyesconmg Praeee Fusi Management Contrsctors and mitenones Pret ee Coesact Cate Sowney BULGARIA Neme of he mectrest KOZLODUY 9 carne Motis E 03492 Ect Act Mee Sears Shutdown ceston Select oher ently ohen more of the listed riteris ecatshes he whuitdermn reason Select mere Than Ghe retten it spgiicanle The sechnology or process beng weed bezeme ocsoele The process was co Enger profitebe Crsnges A boanadg requremerts After an operating nodent Oier WOMOO Pos esson pesse Mendon Mem deor Omer PONTOD IPARES DEISE MOTTON Tern DAON b P ic acceptance or soltcs mesons Aw moe component faire o setetcrenee Ti None of tte above Wiesse specty bein Agreemene betweee Bulgarien Government and Derepean Commission dated 79th Bovember a 1865 Scllewed by Decisioe of the Govermment ANAE dated 13th December 2002 for Trite 153 and CU accension seeaty fox Unite 364 gt Current decomma uong strategy Catered samaring COAG pene EIMAn ard places emanceg SOOoCe Peat mmo Iie cosut Y Comments Deserbe sirs charge
96. nces in methodologies in official statistics small differences can exist between the official nuclear productions compared to the sum of electricity production from individual reactor units as reported in PRIS Total Production The total domestic electricity production in GW h from all power plants coal gas oil hydro nuclear renewables operated in the country Exported production from these plants is also counted Imported energy is not counted Type Selection between NET and GROSS production data Preferable data is NET production which is the electricity supplied to the grid However some countries have a problem reporting a NET value for total production For this reason the system allows reporting GROSS values The selection relates to both nuclear and total production It is important to note that if total production is reported as GROSS production the nuclear production should also be GROSS regardless the NET monthly data Clarifying notes a Net generation is the amount of electricity generated by a power plant that is transmitted and supplied to the grid for consumer use It is measured at the unit outlet terminals i e after deducting the electrical energy taken by unit auxiliaries and the losses in transformers that are considered integral parts of the unit b Net generation is less than the total gross power generation as some power produced is consumed within the plant itself by powe
97. ned outage energy loss CALCULATIONS The operating period forced loss rate FLR is determined for each period as shown below 100 FEL FLR se l NE REG PEL EPL 1 ENERGY AVAILABILITY FACTOR EAF PURPOSE The purpose of this indicator is to monitor availability of a reactor unit to supply electricity to the grid on its reference power This indicator reflects effectiveness of plant programs and practices in maximizing available electrical generation and provides an overall indication of how well plants are operated and maintained DEFINITION The energy availability factor over a specified period is the ratio of the energy that the available capacity could have produced during this period to the energy that the reference unit power could have produced during the same period The energy that the available capacity could have produced is REG PEL UEL XEL DATA ELEMENTS The following data are required to determine each unit s value for this indicator e REG reference energy generation net expressed in units of megawatt hours e PEL planned energy loss expressed in units of megawatt hours e UEL Unplanned energy loss expressed in units of megawatt hours e XEL Externally caused beyond the plant management control energy loss expressed in units of megawatt hours CALCULATIONS The energy availability factor is determined for each period as shown below _ REG PEL UEL XEL
98. nership e Website URL of an official website of the company with majority share in ownership Reactor supplier A short name of the main supplier of the reactor including the nuclear steam supply system Note Reactor supplier is not always identical with the reactor pressure vessel manufacturer Reactor supplier specification contains additional information e Country of origin of the company e Full name of the company Turbine supplier A short name of the main supplier of the turbine generator TG Turbine supplier specification contains the following additional information e Country of origin of the company e Full name of the company 4 1 2 Reactor unit capacity The reactor capacity is an important part of reactor specification It is specified as thermal and electrical capacity The capacity values especially the Reference Unit Power influence calculation of many PRIS statistics and performance indicators Its timely update is necessary for PRIS output correctness Latest Thermal Power The reference thermal power of the plant expressed in thermal megawatts MW The reactor thermal power is the net heat transferred from the fuel to the coolant This value should reflect any change in fuel design or reactor core arrangement Latest Gross Electrical Power The reference gross electrical power of the plant expressed in electric megawatts MW e 16 It is
99. nitions under the parameter name Wherever possible multiple choices of the design characteristics based on existing or known design features have been included The choices provide hints for data providers on the data to be entered Instead of typing the data in a text window the data provider can simply select the most appropriate option from a pop up menu Because of the variety of possible designs the multiple choices are not meant as the only possible choices The list is open and it is expected that while completing the database other options may be found missing In such cases the data providers can make comments to the database administrator proposing or requiring new options and the administrator can amend the multiple choice menu When filling design parameters the save action verifies that the required design parameters have appropriate values Significant characteristics are mandatory in PRIS and are indicated by red asterisks When the values for mandatory parameters are not entered or the values are outside the normal range the save action will raise a red warning box The warning message will state Data could not be saved The parameter s with invalid or missing data will be highlighted in red 20 When the data value entered is outside the specified normal range the user may discover the valid range by hovering over the input field and reading the range description in a popup i e Valid Range 1 70 Thes
100. nnnunnnnnunnan nunnan Loss Factor Unplanned Energy Loss EPL Extension of Planned ood Acaseocconoesda Loss Total Unavailable PEL Capacity Planned Energy Loss XEL UCF External Energy Loss Unit Capability Factor beyond plant management control EAF Available but not Energy Availability Factor supplied LF Load Factor Available Capacity EG Energy Generation actual supply Parformance indicators Data elements Load following frequency control grid adjustments reserve shutdown grid failure security prevention political decision FIG A3 1 Relations among PRIS key performance indicators 97 LOAD FACTOR LF PURPOSE The purpose of this indicator is to provide the ratio of the actual electrical energy supplied to the grid compared to the reference energy generation over a certain period of time This indicator reflects the actual energy utilization of the unit for electricity production DEFINITION Load factor for a given period is the ratio of the electrical energy which the reactor unit has produced over that period divided by the energy it would have produced at its reference power capacity over that period DATA ELEMENTS The following data are required to calculate this indicator for each unit e EG actual electrical energy supplied net expressed in units of megawatt hours e REG reference energy generation net expressed in units of megawatt hours CALCULATIONS The unit load factor is cal
101. nt conditions If a formal test has not been performed the reference power should be based on design values adjusted for reference ambient conditions b The reference unit power value should include the electrical equivalent of the portion of energy delivered in the form of steam heat that might have been used for non electrical applications However this applies only to the units where the heat production may reduce the unit electrical power below its maximum value c The reference unit power is expected to remain constant unless design changes that affect the capacity are made to the unit or a new permanent authorization forces the plant management to amend the original value d Intentional plugging of steam generator tubes is considered a plant design modification RUP should be re evaluated and revised if necessary to account for 29 the reduced maximum capability of the unit due to the intentionally plugged steam generator tubes 5 1 2 Energy production Annual information about electricity supplied to the grid and to non electrical application systems during the reported year and lifetime generation by the end of the reported year Annual energy production Read only information of sum of monthly net energy production in GW h as reported in the production data table for a reported year Electrical equivalent net of non electrical energy generated NEG This data item is shown and is applicable only
102. of fuel removal only for fuel removed during the decommissioning period Selection of applicable fuel management phases and specification e Phase start year e Phase end years e Comments to a phase To add other specific fuel management phases not listed in the table click on the Add button and specify a new phase Clarifying notes a At reactor storage Spent fuel storage that is integral or associated with a reactor and part of the refuelling operation b Storage Period The period when spent fuel is kept under storage and may include future periods even after completion of NPP decommissioning c Encapsulation 1 Immobilization of dispersed solids by mixing with a matrix material in order to produce a waste form 2 Emplacement of a solid waste form e g spent fuel assemblies in a container 7 4 CONTRACTORS AND MILESTONES Soac cation Oma Decommissioning Daza Main Docommasioning Phases Fuel Management Contractors and milestones Print View Contact Greate Name s idontification of the main decommissioning contractors Ne Sais contrece an Beas signed yet Decommissioning milestones Your Leece Siena eve DAE Datel Nol metry iBee Lasting Me d garet Sorog Lect mrettnne Hess Be Bt tocuned o ee date stat ow ond FIG 7 4 Decommissioning contractor and milestone screen Main decommissioning contractor s Specify one or more decommissioning contractors Decommissioning mi
103. of ultimate heat sink GT General Transient 26 1 Problems with control rod drive mechanism and or rod drop 26 2 Pressure temperature power imbalance rod position error 26 3 Partial loss of Reactor Vessel Level Instrumentation 26 4 Complete loss of Reactor Vessel Level Instrumentation 26 5 Loss of suppression pool contents 90 Code PWR WWER BWR PHWR RBMK 26 6 Increase in drywell temperature 26 7 General transient General transient General transient General transient General transient EXTEA Earthquake 27 1 Earthquake Earthquake Earthquake Earthquake Earthquake EXTWH Strong wind ligh tning extremely weather 28 1 Strong wind weather lightning extremely Strong wind lightning extremely weather Strong wind lightning extremely weather Strong wind lightning extremely weather Strong wind lightning extremely weather 91 ANNEX II QUESTIONNAIRE FOR CONSTRUCTION DATA 1 GENERAL INFORMATION a Reactor unit Country Name of the project station Construction licence holder Progress of construction cae F O Smooth progress without significant delay O Delayed significantly more than 2 years O With a suspended period Suspension date Restart date Reasons for suspension Political Public resistance Energy market changes Economic environment conditions Investor f
104. off line and subcritical Refuelling with a major turbine refurbishment focused on power up rate PEL Unplanned extension of the outage due to a reactor flange leak EPL Reactor critical Unit connected to the grid planned start up tests PEL Revision of the Reference Unit Power RUP increase 9 Normal operation at the increased reference unit power 10 Automatic reactor scram due to a reactor protection system failure FEL 10 11 Unplanned outage to identify and solve the RPS problem FEL 11 Reactor critical 11 12 Unit connected to the grid start up from the unplanned outage FEL 12 13 Reduced power due to regulatory restriction RPS reliability verification FEL 13 14 Increased power operation due to favourable environmental conditions N Mm BR Ww O0OMANINDUNANA BWW l l oo on FIG 5 4 Example of power history and classification of energy loss 38 Operational Dem Opeevting Erpertence Production Gutepes Cameetolertsy Chacts Pachom kashe e wotnc ntate Motman p4 hanst bonih i Energa ove Gm to ime eeerenderety Mites Moh It EG NWet On ime eC Period Ppusn Urgieneed Poced Unpteened Est Uopiamemi Ofif FE eat Taal xE FIG 5 5 Unavailability data table WEDAS includes internal checks protecting against saving entered values that do not meet the following criteria e Sum of energy losses for a month should not be greater than reference energy generation REG e Electricity
105. ons of planned energy losses EPL Data entry for energy expressed in electric megawatt hours MW e h that was not delivered during the month due to unplanned extensions of planned shutdowns or load reductions beyond the original planned end date when originally scheduled work was not completed or new work was added to the outage less than 4 weeks before the scheduled end date if causes were under the plant management control Clarifying notes for both categories of unplanned losses a Unplanned energy losses resulting from the following conditions are considered to be under the control of plant management e unplanned maintenance outages FEL e unplanned outages or load reductions for testing repair or other plant equipment or personnel related causes FEL e unplanned outage extensions EPL e unplanned outages or load reductions that are caused by or prolonged by regulatory actions taken as a result of plant equipment or personnel performance This also relates to regulatory actions applied on a generic basis to all like plants FEL EPL b Unplanned energy losses due to the following causes should not be reported as FEL or EPL because these losses are not considered to be under the control of the plant management e grid instability or failure e lack of demand reserve shutdown economic shutdown or load following e environmental limitations for example low cooling pond level water intake restrictions earthq
106. or unit or year is achieved by clicking on any column of the selected reactor record or year in the landing table WEDAS supports selecting more than one reactor unit Checking the boxes in the first column of the table and clicking on Group selects all identified reactor units To select all reactors in the landing table use the checkbox in the heading of the first column The data entry screens contain functions for switching the reactor unit within the group to any year within the last ten years The landing screen for country information is described in Chapter 3 Data items for the new reactor screen are described in Chapter 4 WEDAS users can add a new reactor to the PRIS system The submitted reactor data however are not loaded into the PRIS system until the PRIS administrator approves them and switches the data status into Published Once approved and published the new reactor record cannot be deleted For modification of locked data items or for deleting the new reactor record must be switched back to the In process status 2 3 FILTERS FOR DATA ENTRY The WEDAS landing screens contain a table of reactor units which are assigned to the login user Reactor records in the table are controlled by filters e Reactor name e Year only for operational data e Reactor status only for specification data e Data status The landing screen is open with default setting for filters In case of operational data the def
107. owing 55 month the duration of each full outage is interpolated into one month and for each month a difference between the reference period and the total duration of full outages in the month is calculated Rule On line Hours Period Reference Hours X Full Outage Hours Each full outage includes also the period of shutting down and starting up when the unit is still or already connected to the grid If these marginal periods are reported in the PRIS as a part of the full outage i e they are not reported separately as partial outages it brings a certain inaccuracy in the number of on line hours Therefore the 24 hour per month tolerance was selected for this case II Energy generated and energy losses This energy balance test compares reported values of electricity generated with the possible production which is a value calculated from reference energy generation and energy losses reported in monthly records unavailability and energy losses interpolated to a month from outages which are not related to plant unavailability outage cause codes I J K M O U Rule Actual Production Possible production Possible production Reference Hours x Reference unit power Energy losses due to plant unavailability amp Energy losses due to outages with one of cause codes I J K M O U Operation at a power higher than the reference unit power results in overproduction which causes difference between ac
108. performance of the plant and significant factors affecting energy generation over the year The annual information should be updated when necessary for instance for revision of reference unit power but finalized after the end of a reported year OE data have five sections Prvvteae Cyein mmie i FIG 5 1 Operating experience data screen 5 1 1 Reference Unit Power The reference unit power RUP is the maximum electrical power that could be maintained continuously throughout a prolonged period of operation under reference ambient conditions The power value is measured at the unit outlet terminals i e after deducting the power taken by unit auxiliaries and the losses in the transformers that are considered integral parts of the unit The reference ambient conditions are environmental conditions representative of the annual mean or typical conditions for a unit It is expected that historical heat sink temperatures will be used to determine the reference ambient conditions The same reference ambient conditions will generally apply for the life of the unit Periodic review of these reference conditions is not required RUP determines the reference energy generation REG which is calculated by multiplying RUP by the period hours REG is expressed in units of megawatt hours electric 27 RUP at the end of previous year Read only value of RUP taken from a production record for December in the previous year Refer
109. period expressed as a percentage Capable energy generation is the energy that could have been produced under reference ambient conditions considering only limitations within control of plant management i e plant equipment and personnel performance and work control DATA ELEMENTS The following data are required to determine each unit s value for this indicator e REG Reference energy generation expressed in units of megawatt hours e PEL Planned energy loss expressed in units of megawatt hours e UEL Unplanned energy loss is expressed in units of megawatt hours CALCULATIONS The unit capability factor is determined for each period as shown below a REG PEL UEL Aow T REG k UNPLANNED CAPABILITY LOSS FACTOR UCL PURPOSE The purpose of this indicator is to monitor industry progress in minimizing outage time and power reductions that result from unplanned equipment failures or other conditions This indicator reflects the effectiveness of plant programs and practices in maintaining systems available for safe electrical generation 99 DEFINITION Unplanned capability loss factor is defined as the ratio of the unplanned energy losses during a given period of time to the reference energy generation expressed as a percentage DATA ELEMENTS The following data is required to determine each unit s value for this indicator e UEL Unplanned energy losses expressed in units of megawatt hours electric e REG Re
110. r auxiliary equipment such as pumps motors and pollution control devices c Gross electricity production is the total electricity produced by an electric power plant It is measured at the output terminals of the turbine generator i e including the amount of electricity used in the plant auxiliaries and in the transformers Nuclear Share A read only calculated value in percentage of nuclear share which is defined as the ratio of the nuclear electricity production to the total electricity production from all sources in a country Comments This text box is for additional information Data providers can use this data item for e Informing whether the data are final or preliminary e Reference to data source e Reasons why net nuclear production is not identical to a sum of electricity production of individual reactor units in monthly data records 4 SPECIFICATION DATA In PRIS each reactor unit is identified by a set of specification data The purpose of specification data is to provide comprehensive information about technical and design characteristics location history ownership and main events of reactor units Specification data in PRIS are divided into separate tabs e Basic information e Design characteristics e Connection to non electrical application units shown only for units with NEA e Schematics e Milestones Specification data should reflect the current situation at a rea
111. ration at rated or reduced power upon the grid dispatcher s request etc 5 4 QUALITY CONTROL OF PRODUCTION DATA WEDAS provides supporting function to improve and maintain data quality in the production data module Each operational data screen contains in the top right corner the following functions e Consistency checks e Performance indicators Data providers are encouraged to use these functions before submitting data to the system 5 4 1 Consistency Checks WEDAS offers sophisticated consistency tests including crosschecks of data elements from different data sections Annual Information Monthly Production Outages etc These tests consider outage causes and their effect on unit availability For individual consistency checks tolerance limits have been established e If there is inconsistency within the given tolerance limits the identified difference is shown in brown colour For published data these differences are accepted and data are considered consistent e If there is inconsistency exceeding these limits the difference is shown in red colour and inconsistency sign is not cleared for published data The consistency tests are divided into eight sections I On line Hours This test compares on line hours for each month when the unit was connected to the grid with the result of calculation from full outage records the second character of the type code is F As an outage can start in one month and finish in a foll
112. reference unit power for example due to low energy demand transmission grid failures or unfavourable political situation in the country It follows from the above definition that unit operation at reduced power does not always imply unit unavailability In other words a unit may be operated at a reduced power even though it is fully available In the Unit Unavailability Data table only those energy losses which have been caused by power plant unit unavailability as defined above should be entered Three types of energy losses caused by unit unavailability have been defined and are reportable in the unavailability data table of PRIS planned energy loss PEL unplanned energy loss FEL EPL both due to causes controllable by the plant management and externally caused energy loss XEL which is due to constraints beyond the plant management control Energy losses due to reasons like a grid failure load following operation or government court decisions when the unit was fully available capable of reaching the reference unit power are not reportable in the unavailability data table For completeness of information on energy loss due to those reasons however the energy losses with the unit fully available should be reported in the Outage Data module see the outage cause codes I J K M O and U in the Chapter 6 Reference Energy Generation REG a a Unavailable Energy Beyond plant Under plant
113. rovide specification and operational data of their nuclear power reactors to the IAEA The data provided is verified and approved by PRIS Administrators before its use in PRIS statistics and publications This manual provides a complete description of the PRIS data structure defines all data items and provides guidelines for reporting PRIS data through WEDAS 2 1 WEDAS USERS ACCESS RIGHTS RESPONSIBILITIES Each Member State with nuclear power plants submits authorized data into PRIS using WEDAS The data is normally submitted through the official PRIS contact persons WEDAS deals with raw data and is therefore available only to registered users requiring login see Figure 2 1 The IAEA issues WEDAS registration and provides login ID and password to the official nominees l A EA Power Reactor information System PRIS Sign in Welcome to PRIS Username The Power Reacto information System PRES 16 a comprehenmve data source on nucleal power reactors in the World t chodes reactor apecdcaten and pelfermance history data The menthty power producers and ponat lestes data have Parwo Od Fn heon recendad in PRES since 1970 Due ts dotaded clausiication of anergy lnsves and compraheraive outage coding Fd gysten 2 set Of intemaponeily accepted pertpemance indicatore ure calculated kom the PRIS pedormance data oai lt Orr a PRIS 2 6 Release Tran veer pasowan PRIS 2 0 inchides a new version of PRIS Stulisdcs avaiable jo si regstered P
114. rs Data status Decommissioning contractors Decommissioning milestones Decommissioning phases Decommissioning strategy Desalinated water volume Design net electrical power Distillation electricity Distillation energy District heating energy Electrical equivalent of non electrical energy generated Energy Availability Factor Energy generated Energy loss Energy Unavailability Factor Extensions of planned energy loss External Energy Unavailability Factor Externally caused energy loss First criticality date Forced energy loss Forced Loss Rate Grid connection date Gross electrical power Initiating Event Initiating Event Code Lifetime energy generation Load Factor Load factor including heat Manual scrams Non electrical applications Nuclear production of electricity in a country Nuclear share On line hours Abbreviation NAS NCH DWV PRO PDI PDH NEG EAF EG EL EUF EPL XUF XEL FEL FLR IE LF LFH NMS NEA Section 4 1 1 5 1 2 5 1 4 5 3 4 1 3 5 4 9 4 1 3 4 1 3 4 1 3 4 1 3 5 1 4 2 4 7 4 7 4 T2 7 1 6 2 2 4 1 2 6 2 2 6 2 2 6 2 1 5 1 2 5 4 2 5 2 1 5 2 2 5 4 2 5 2 2 5 4 2 5 2 2 4 1 3 5 2 2 5 4 2 4 1 3 4 1 2 5 1 2 5 4 2 5 1 2 5 1 4 5 2 1 75 Data item Operating cycle Operating Experience Operation Factor Operational mode Operator Outage Outage cause code Outage description Outage duration Outage energy loss Outage extension Outage start date
115. rst grid connection to permanent shutdown Thus when a reactor is temporarily not generating electricity because of outages for e g refuelling maintenance repair large refurbishment or political decision the reactor is still categorized as operational The only exception to this classification is when the reactor s status is declared as long term shutdown then it is excluded from the list of operational reactors even though it has not yet reached permanent shutdown Long term Shutdown Reactor is considered in long term shutdown status from the long term shutdown date to the restart date if it has been shut down for an extended period usually more than one year and any of the following conditions has occurred in the early period of shutdown e no firm restart date or recovery schedule has been established but there is the intention to re start the unit eventually or e restart is not being aggressively pursued there is no vigorous onsite activity to restart the unit This status may be for example due to technical economical strategic or political reasons This status does not apply to long term maintenance outages including unit refurbishment if the outage schedule is consistently followed or to long term outages due to regulatory restrictions licence suspension if restart licence recovery term and conditions have been established Such units are still considered operational in a long term outage The alterna
116. rt of a test e g a reactor protection system actuation test or scrams that are part of a normal operation or evolution and are covered by controlled procedures are not included c Reactor protection system actuation signals that occur while all control rods are inserted are not counted because no control rod movement occurred as a result of the signals d During start up shutdown or changing power condition the reactivity transients may cause the reactor to go subcritical or super critical for a short period of time However the plant is considered critical for purposes of this reporting if the reactor was critical prior to the reactivity transient and may be assumed to return to a critical condition after the transient is completed e g a plant is considered to remain critical after initial criticality is declared on a reactor start up and to be critical until taken permanently subcritical on a reactor shutdown e Each scram caused by intentional manual tripping of the turbine should be analysed to determine those which clearly involve a conscious decision by the operator to manually trip the turbine to protect important equipment or to minimize the effects of a transient Scrams that involve such decisions are considered manual scrams f Practical examples of reactor protection system actuations e While shutting down the reactor sufficient control rods had been inserted to make the reactor subcritical A spurious scram signal th
117. ry and should be completed Assignment of red asterisks depends on the status of a power reactor Data providers are required to update the data in the case of any modification Specification data should be reviewed and verified at least once per year To verify the data push the button Mark as verified 10 Sasic infonmnation Specification Data Basic Information Design Characteristics Schomatics Milestones Upa neme Mionate iare Unt Code Cawitry Reactor Type Reactor Model Status Ste Operator Oww Reactor Suppher Tuibin Supple Uypocity Latest Thorma Power Latest Gree Elactitat Poway Ongni Dewar Mel Electneat Pawwr Latest Reteonice Unt Povas net Ifistoty Constuchon Lense Dato Connnauon Dore Suspended consmacton Comcalty Gate Gk Cate Correretciat Date Long Tern Shutdows Date eaten Date Permanent Shutdown Vate Information Status PICKERING I CA 4 CANADA PHNR Pressunzed Hoavy ViaterAloderatod and Coolod Reactor CANDU 500A Operational PICKERING Diets OPG Edi Add New Search OPG Eat Add New Seach OWAECL Fat Acd Hawi Search NELP Edu Adu New Seach 1744 sive SAZ Nive 508 MWe 515 MWe 1955 02 24 yyyy n i 19050601 yyyy end 197140125 yyyy nemo IID yyyy amdi 197197 29 yyypmm da 1997 1231 yyyyam dd 2005 08 26 yyyy cendd yyy ened Pubbshed FIG 4 1 Reactor unit basic information 4 1 1
118. s 0 cceeecceesceesceeseceeeceeeecsaeceteceeeeeeaees 34 52 2 Unavyailability dataro anaE aAa TA RT EAE e RERA R AATA EESE 36 53 OUTAGES roert n E EE RE E E O ue E aa 44 5 4 QUALITY CONTROL OF PRODUCTION DATA saasssssessesssssssessesssesrosessesresrseesres 55 5 4 1 Co sistency CNGCK Sex suca consis in n tare RA a al a aurol ans 55 5 4 2 Performance AEC ALIS osano cnc oct ensi aeie aa cosines oa E AEEA yada vos 57 6 NON ELECTRICAL APPLICATION DATA ccccsssssssssessccsseestessceesessceseeseaseonesseesneaes 59 6 VHIGHEIGHT Seen a a a a A a a ae eee 59 6 2 MONTHLY DATA FOR HEAT CONSUMPTION 0 cccccccsecseeseeseeeseceeesseesenseeeeees 60 6 2 1 Energy supply for district heating and process heat cceseseeseeereeeeeeteeneeeaee 60 6 2 2 Energy supply for water desalination ac cass 3 sis acl nt ea tanalaauera alent 61 7 DECOMMISSIONING DAT x ccasccasentusiaahnceaecuneeececkunde epanabagceendetenaoh sana ceundaeuneusaeteeson ess 63 T1IMAIN INFORMATION cas cite Siar ates ni e e Souaaiteas sada SO te ahad tae Nae a ESENE 63 7 2 DECOMMISSIONING PHASES co cecasassiscoscssedaccue se bsaesi hvieavesteacoda masta oeeoeuccolees 65 T3 EVEL MANAGEMENT eeror carseat seve cees EO EE tae te ial viel i acaba aac 66 TACONTRACTORS AND MILESTONES Sondra a i eaa 67 9 CONSTRUCTION PERIOD DATA A ifane uiae a a e e A ARESA 71 REFERENCES cenana neni E A E NEE e a E A E na eachoweees 173 INDEX nea en a AEE E A AEAEE a eras a at AEEA AIE
119. s in outage start date should be coded as a separate outage Second character F Full outage P Partial outage e An outage is considered full if the actual unit output power has been reduced to zero percent unit disconnected from all off site power supply lines e An outage is considered partial if the actual unit output power is lower than its reference value but the reactor unit is still connected to the grid Third character 1 Controlled shutdown or load reduction that could be deferred but had to be performed earlier than four weeks after the cause occurred or before the next refuelling outage whatever comes first 2 Controlled shutdown or load reduction that had to be performed in the next 24 hours after the cause occurred 3 Extension of planned outage 4 Automatic reactor scram 5 Manual reactor scram e Third character is applicable to unplanned outages e The third character should be assigned also to outages due to causes beyond plant management control external which can be considered unplanned see the cause codes J M N R T and U below b The outage type may have one of the following codes PF or PP UF1 5 or UPI1 3 XF or XP XF1 5 or XP1 3 Direct Cause code Selection of a cause code for the outage from the dropdown list Clarifying notes a The code represents a direct cause of the outage The direct cause is defined as an immediate action or condition that has directly resulte
120. s manual The concept for international shared information on construction and commissioning of new nuclear power plants consists of the following information e decision making process e project organisation and management e original schedule and its adherence e reasons for delay e period of suspended construction e type of contract e milestones e contractors and subcontractors e experience from construction main issues significant events influencing factors The data may be obtained for on going projects and commissioned projects since 1990 71 1 2 3 4 REFERENCES INTERNATIONAL ATOMIC ENERGY AGENCY The Power Reactor Information System PRIS and its Extension to Non electrical Applications Decommissioning and Delayed Projects Information IAEA Technical Reports Series No 428 IAEA Vienna 2005 INTERNATIONAL ATOMIC ENERGY AGENCY International Outage Coding System for Nuclear Power Plants IAEA TECDOC 1393 IAEA Vienna 2004 INTERNATIONAL ATOMIC ENERGY AGENCY Nuclear Power Plant Design Characteristics IAEA TECDOC 1544 IAEA Vienna 2007 PRIS Public Website www iaea org pris 73 INDEX Data item Alternate unit name Annual energy production Automatic scrams Combined outage Commercial operation date Consistency checks Construction period data Construction license date Construction restart date Construction start date Construction suspended date Critical hou
121. s to the decommascneg strategy Cirrrerit atata of decommmissinning amd formeen objectives Licenses for cperation a9 fatilieies for aenegement of eadicaccive varse which shall be a decommissioned by Sf RAN proe om Ortcbeg S010 fos five years An updated Decommissioning Strategy for units 1 4 was adopted by FNF in 004 inclading FIG 7 1 Decommissioning main information 63 Country Read only information from the reactor unit specification Name of the reactor unit Read only information from the reactor unit specification License Holder A short name abbreviation of the license holder The license holder is a holder of a legal document granting authorization to perform specified activities related to the decommissioning of a nuclear power plant The license holder specification contains additional information Full name Address Website URL of an official website of the company Shutdown reason Selection of one or more reasons for reactor unit shutdown Options for selection The technology or process being used became obsolete The process was no longer profitable Changes in licensing requirements After an operating incident Other technological reasons please mention them below Other economic reasons please mention them below Public acceptance or political reasons After major component failure or deterioration None of the above Please specify below Some selec
122. t Construction or Operation shall be deemed the Responsible Person by law Suspended Period a defined time of the Nuclear Power Plant Construction with Zero Progress in the Project Milestones Suspension Date Start Day for the Suspended Period Restart Date One Day after the Suspended Period End Day Turnkey contract a main contractor is responsible for design construction and commissioning of the whole project and in charge of the project management plant approach The bulk of the capital cost as well as the risk of the project is placed with the main contractor Split package contract two major contract packages for nuclear and conventional islands are defined island approach Multi package contract In the multi package contract approach potentially with several hundred contracts the plant owner takes the major responsibility and risk associated with the project implementation component approach 95 ANNEX III SHORT DEFINITIONS OF PRIS KEY PERFORMANCE INDICATORS Based on this manual it was possible to simplify key performance indicators PI definitions removing data element definitions and data requirements from definitions specified in the reference publication TRS 428 1 The relation between performance indicators and related data elements is shown on Figure A3 1 Reference Unit Power eS ESET TESST gt 100 FEL UCL UEL Forced Energy Loss Unplanned Capability Pf usununnsunef Squrnuneunnn
123. t system schematics and flow diagrams local maps and photographs of the unit site These images can provide a comprehensive picture of unit design technology and system configuration and also give a clear idea of unit location appearance and nearby setting Appropriate unit schematics or drawings would enhance applicability of the design characteristics to the above purposes The following types of images at least should be included in the PRIS database e A simplified or functional cross section of the containment reactor building including the main components and the pressure suppression system e Operating flow diagrams of the primary system with all the main components reactor RCP loops steam generators pressurizer etc including the ECCS pumps tanks piping and connections of the ECCS to the primary circuit The diagrams should show at least the components included in the primary system design characteristics e Any additional diagrams and schematics for example those of the balance of plant systems or technical photos can be provided if available or found useful by the NPP personnel 21 Reactor Design Schematics Cross section drawing Kr ko NPP Eikas dpa w Operating flow diagrams Krako Ausciary F eecwater Panoramic View Krako plant Site Schematics Panoramic View Krsko NPP Kreka Main Feedwater 1 Kreko Main Feedwater 2 A 0 S e A 1 gt Sheram aa gt Rigs
124. ta module Initiating Event Data which utilises information from selected outage records has been introduced into PRIS to support probabilistic safety assessment models The decommissioning data module contains information about the decommissioning process of shutdown units The construction data module contains information about the organisation and experience of NPP construction Annual Country Data Module Total mici ar production Total producbon Nuclear share Jperatonal jnitlating Events 7 Wam Construction Decommissioning Data Module DetaModule gam Data Module Data Modula FIG 1 1 Modular structure of PRIS 2 WEDAS APPLICATION The IAEA PRIS database is supported by Member States through the officially nominated liaison officers and data providers The official contact persons are responsible for timely reporting and updating PRIS data In order to facilitate the data collection process and improve data quality the IAEA has developed the PRIS Web Enabled Data Acquisition System WEDAS as a tool for on line data reporting Its address is http prisweb iaea org alias http pris iaea org wedas The system is accessible via the Internet and serves as the interface between data providers and the PRIS system WEDAS simplifies data collection and allows data providers to check and correct data before submission to PRIS WEDAS is accessible to designated contact persons in Member States allowing them to p
125. the IAEA and the concemed Member State PRIS Power Reactor Information System Copyright International Atomic Energy Agency Contact Lis About PRES FIG 2 5 PRIS WEDAS Tutorial 3 COUNTRY ANNUAL INFORMATION PRIS provides and shares an overview of nuclear electricity production in individual countries and globally These data as well as their trends are generally used in nuclear energy analyses For a specified year the country information landing screen shows a table with data for each of last 10 years The default specification is the previous year j Wustem Posunss Teesi Prccusrteee we tataw Vaan 5 tert tijat FIG 3 1 Country data screen Data are provided annually and should be submitted by February of the next year If final data are not available by that time preliminary data can be used as a temporary entry which should be updated when the final data are available Year A new record for country data is created and activated by entering the new year and clicking on Go Existing country records can be selected by entering the required year into the year field or by clicking on the required year in the landing table Nuclear Production The total electrical energy production in GW h from all nuclear power plants operated in a country Exported production is also counted Country annual data are reported using the official country statistics Due to possible differe
126. the data provider can change the status back to in progress The status Submitted gives the PRIS administrator a green light for data verification and crosschecking Submitted data remain in WEDAS only and are not used in PRIS outputs e Approved When data pass all verification and consistency tests the PRIS administrator can change the data status to Approved Data in this status are locked and cannot be edited modified or deleted The data is not yet available for any PRIS statistics and outputs Published When data status is switched to Published data are replicated from WEDAS to production tables of the PRIS database and included in all PRIS statistics and outputs Published data are locked and cannot be edited modified or deleted like approved data If a correction is needed contact the PRIS administrator who can switch the data back to the In Progress status STATUS Status changed to In Progress Data revision Feedback from data Data published owners m j Is data correct Requestfor correction FIG 2 4 PRIS Data reporting process Published 2 5 ON LINE HELPS AND TUTORIAL To support data providers WEDAS has on line helps for all data items in all PRIS data modules On line helps are under the titles of data items Titles with on line help are called active titles When a cursor is moved above an active title the title is underlined and a mouse click opens a
127. tiating event The IE code Administrative shutdown is the only option for those records When IE code and additional information are specified the record is copied as an IE record into screen 1 3 All This screen provides an overview of all scrams and all controlled shutdowns reported for the reactor unit in the outage data module The assigned and completed IE record includes the following information e All information reported in the outage records Chapter 5 3 e Initiating event code from the IE generic list e Additional information It is necessary as the originally reported outage information and codes were not intended to support initiating event analysis To assign IE code and to provide additional information click on any of records listed in the table of landing screens This results in opening the IE data screen Figure 8 2 sting Events hutiating Event 2002 4 Imormation Stama Submm ed lt lt prev Next gt gt Save Exit Seram details click Nere to tee ail outages for 2002 Outage Previous Senet Duration Type Cause Energy loss Operational Description Outage thous nen mode before 2002 05 07 00 00 S34 US A4200 198972 Hot shutdown reactor subcobeat Automatic scram dee to man traesformer fatto FIG 8 2 Initiating Events data screen Together with data entry fields the IE data screen contains all data details read only of the selected outage record in the bottom part The buttons lt lt prev
128. tion as adopted in 1952 Berne and as revised in 1972 Paris The copyright has since been extended by the World Intellectual Property Organization Geneva to include electronic and virtual intellectual property Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form must be obtained and is usually subject to royalty agreements Proposals for non commercial reproductions and translations are welcomed and considered on a case by case basis Enquiries should be addressed to the IAEA Publishing Section at Marketing and Sales Unit Publishing Section International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna Austria fax 43 1 2600 29302 tel 43 1 2600 22417 email sales publications iaea org http www iaea org books For further information on this publication please contact Nuclear Power Engineering Section International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna Austria Email Official Mail iaea org PRIS WEDAS USER S MANUAL TO THE WEB ENABLED DATA ACQUISITION SYSTEM FOR PRIS IAEA VIENNA 2015 IAEA CMS 23 ISSN 1018 550X IAEA 2015 Printed by the IAEA in Austria November 2015 FOREWORD Historically the IAEA collected nuclear power plant data by sending out questionnaires to its Member States each year The response used to come mostly in the form of hard copies which were then manually entered into the Power
129. tion criteria have a text box for additional information The category other should be used only when none of the listed criteria matches the shutdown reason Current decommissioning strategy Selection of the currently applied strategy for decommissioning Options for selection 64 Immediate dismantling and removal of all radioactive materials Deferred dismantling placing all radiological areas into safe enclosure Deferred dismantling including partial dismantling and placing of the remaining radiological areas into safe enclosure In situ disposal involving encapsulation of radioactive material and subsequent restriction of access None of the above Please specify below Clarifying notes a Dismantling The disassembly and removal of any structure system or component during decommissioning Dismantling can be performed immediately after permanent retirement of a nuclear facility or may be deferred b Encapsulation 1 Immobilization of dispersed solids by mixing with a matrix material in order to produce a waste form 2 Emplacement of a solid waste form e g spent fuel assemblies in a container c In situ disposal also called entombment Decommissioning strategy where the nuclear facility is disposed wholly or partly at its existing location d Safe enclosure A condition of a nuclear facility during the decommissioning process in which only surveillance and maintenance takes place If a safe enc
130. tion for selection of an IE code from the drop down list should be provided Clarifying notes a In case of a break in the secondary part boiler feed water steam line or a break in the primary part the initial break flow should be approximated and given b To the extent possible a summary of the event progression leading to reactor scram should be given including any operator error or intervention c If an investigation was completed then the direct apparent or root cause as the case may be may be given The parameter on which the reactor scram occurred The parameter on which the reactor scram occurred e g low primary pressure When more than one trip parameters are enunciated one after the other the parameter should indicate the first trip parameter on which scram actually occurred Power level in of RUP 70 The reactor power level in percentage at the time the initiating event scram occurred 9 CONSTRUCTION PERIOD DATA This PRIS data module is under development The objective of the new PRIS module is to summarise information that can be used for an international survey and sharing which would benefit those planning to construct new power reactors especially the Member States considering construction of the first power reactor The final questionnaire for the construction commissioning period data module which was agreed by PRIS Technical Meeting in 2012 is in Annex 2 of thi
131. tive term for long term shutdown is suspended operation which is more consistent with other life cycle stages planning and construction of reactor units If an intention not to restart the shutdown unit has been officially announced by the owner the unit is considered permanently shut down Permanent Shutdown A reactor unit is permanently shut down when it is officially declared by the owner to be taken out of commercial operation and shut down permanently Clarifying notes a The first grid connection date is the date when the plant was connected for the first time to the electrical grid to supply electricity After this date the plant is considered in operation b Cancellations or suspensions of projects may occur when the plant is under construction or planned Therefore the specific condition of the plant when the project was cancelled should be classified as below e The status is suspended when there is no definite decision and the plant may restart construction or put in the planned list in the future e The status is cancelled when there is a definite decision and the plant will not restart construction or be in the planned list any longer Site Site name specification This is the name of a locality that can host more than one reactor unit A reactor unit name is usually derived from the site name but there are cases where site and reactor unit names are different Site specification contains a
132. tual and possible production In this test a tolerance limit for overproduction has not been established For missing energy a tolerance limit is equal to 10 hours of operation at the reference unit power HI Unplanned energy losses This test compares unplanned energy losses UEL FEL EPL reported monthly in the Unavailability Data part with the interpolated energy loss from outages coded as unplanned the first character in the outage type code is U Rule UEL Energy losses due to outages with type code Uxx If some short term outages not considered as significant are not reported there may be discrepancy in the above rule Therefore the tolerance limit for unplanned energy losses is equal to 10 hours of operation at the reference unit power IV Planned energy losses 56 This test compares planned energy losses PEL with the interpolated energy loss from outages coded as planned outages the first character in the outage type code is P Rule PEL Energy losses due to outages with type code Pxx If some short term outages are not reported there may be discrepancy in the above rule Therefore the tolerance limit for planned energy losses is equal to 10 hours of operation at the reference unit power V Other energy losses This test compares other energy losses XEL with the interpolated energy loss from outages coded as external outages the first character in the outage type code is X
133. type should be selected from the list with the IAEA classification for type of reactor as below BWR Boiling Light Water Cooled and Moderated Reactor FBR Fast Breeder Reactor GCR Gas Cooled Graphite Moderated Reactor HTGR High Temperature Gas Cooled Graphite Moderated Reactor HWGCR Heavy Water Moderated Gas Cooled Reactor HWLWR Heavy Water Moderated Boiling Light Water Cooled Reactor e LWGR Light Water Cooled Graphite Moderated Reactor e PHWR Pressurized Heavy Water Moderated and Cooled Reactor e PBMR Pebble Bed Modular Reactor e PWR Pressurized Light Water Moderated and Cooled Reactor e SGHWR Steam Generating Heavy Water Reactor Reactor model The reactor model identifies a specific reactor design series within a particular reactor type All models of the same reactor type usually have the same basic design characteristics moderator and coolant type and form Clarifying notes a Because of the wide variety of reactor models this data field is free text It is expected to use an official and short specification of the model b The role of the PRIS administrator is to unify spelling of the same reactor models in PRIS c Examples of reactor models Magnox AGR for GCR or VVER V 213 Konvoi EPR for PWR Reactor status Classification of reactor status is based on historical phases of power reactor life cycle from a planning phase through
134. uakes tsunami or deluges that could not be prevented by operator action e industrial action labour strikes see clarifying note below e fuel coast downs e seasonal restriction to achievable power due to variations of cooling water parameters temperature salinity c In general the generation losses that were not planned and scheduled 4 weeks in advance as is the case with typical equipment or personnel caused losses are unplanned and remain as such until the cause of the unplanned losses is not fixed The fact that management knows or is aware the losses will continue beyond the 4 weeks does not make the losses or cause of the losses planned 41 d In case of generation losses due to equipment degradation heat exchanges valve steam leaks etc the energy losses would be reported as unplanned forced until the degradation cause of the unplanned losses is repaired or the unit enters a planned outage scheduled before the cause of the unplanned loss e If the equipment problem cannot be fixed immediately and requires a temporary design change for example isolation of the failed component which reduces the power for months until the final repair is done the related power loss for the whole period of reduced power should be classified as unplanned until all corrective maintenance required for operation at full power operation is completed f Energy losses associated with failed fuel are considered the sam
135. uation of an idle coolant pump 1 coolant pump 1 MCP 1 4 Recirculation control failure increasing flow 1 5 High feedwater flow during startup or shutdown 1 6 Feedwater increasing Excessive feedwater flow at power flow 1 7 Abnormal startup of idle recirculation pump 1 8 Inadvertent startup of RCIC 1 9 Reduction of feedwater temperature ESSHR Excess of secondary side heat removal 2 1 Inadvertent SG level Inadvertent SG level regulation valve regulation valve operation lead to SG operation lead to SG level increase level increase 2 2 Increase in feedwater Increase in feedwater flow one loop flow one loop 2 3 Increase in feedwater Increase in feedwater flow all loops flow all loops 2 4 Inadvertent opening of steam dump valve to condenser BRU K 2 5 Symmetric SG blow down line break outside RB 2 6 Symmetric SG blow down line break inside RB 2 7 Asymmetric SG blow down line break inside RB 81 Code PWR WWER BWR PHWR RBMK FI Fires 3 1 Fire within plan Fire within plan Fire within plan Fire within plan Fire within plan FL Flood 4 1 Floods Floods Floods Floods Floods LO LOCA LOCA outside confinement 5 1 Interfacing system Interfacing system Loss of Coolant HTS leaks into RCW Break of a small LOCA LOCA Accident bypassing interfacing LOCA diameter pipeline containment outside the ALS 5 2 Interfacing system L
136. units with the same reactor type 58 6 NON ELECTRICAL APPLICATION DATA Some power plant units produce a portion of their output energy in the form of heat steam for non electrical applications like desalination district heating and industrial heat This energy should be reported provided the production of heat steam reduces the actual output electrical power below the reference unit power defined in Section 5 1 1 Nuclear Heat Source Non nuclear back up source 1 2 An Heat Source 1 2 n EtA Feed Header Retum Header Plant Boundary performance data taken Note At some nuclear power plants e g in Russia there may be two feed return headers one each for district heating and process industry FIG 6 1 Schematic diagram of energy supply to a NEA unit 6 1 HIGHLIGHTS Highlights The text field is intended to provide highlights of energy delivery to non electrical application systems during the reported year Any relevant information may be entered Limitations This text data field may provide explanation when the operation of non electrical application systems was limited by insufficient heat delivery from the nuclear heat source s during the reported year Provide information as what caused this and what countermeasures were taken etc 59 6 2 MONTHLY DATA FOR HEAT CONSUMPTION 6 2 1 Energy supply for district heating and process heat PEEN eo onsumption
137. was caused by operators manually tripping the turbine to prevent equipment damage 5 1 5 Operating Cycle Information These data items are applicable and shown only for PWR and BWR reactors with off line refuelling Operating cycle OC in PRIS is a period from the start up after refuelling to the start up after the next refuelling The first cycle is from first grid connection to the start up after the first refuelling outage Check the box if new operating fuel cycle started in the reporting year Operating cycle data are introduced by information about the previous operating cycle Operating cycle data are used for calculation of performance indicators for OC periods and for statistics on duration of operating cycles and refuelling outages Marking the check box next to the label Actual Operating Cycle opens the data field for the actual reporting year Cycle number The sequence number of an operating cycle that started in the reporting year The first cycle from the first grid connection has number 1 WEDAS automatically assigns the number based on the previous record The number can be manually corrected if necessary In this case numbers of previous records should also be rectified 33 Cycle Start date Read only information transferred from the previous cycle record Cycle Start date is identical with Operating Cycle End Date as specified for the previous cycle If previous cycle is not specified
138. wi we ee p b p G 51 n bai s d E f 7 i b 4 e 4 4 4 b i g it t i i F I a F o b i 4 i et a oo i i p 2 Ja Fa F n Fa t t s i INTERNATIONAL ATOMIC C ENERGY AGENCY l VIENNA ISSN 1018 550X _ j trpa m r _
139. y from the plant to compensate insufficient availability of heat from the nuclear reactor Clarifying text for back up heat source used If the back up heat source is used for multiple units please clarify why the operation of non electric application systems was limited by insufficient heat delivery from the nuclear heat source s Give descriptive explanations of what caused this what countermeasures were taken etc 6 2 2 Energy supply for water desalination Desa ination systems 20 Specification Data Operatbonal Data Non Electrical Application Change React Change Year Desalination Systems Highlights Month Thermal energy provided tor Electrical energy provided tor Water Production m Gata status Ofstitiation Gest Reverse Osmosis Process MVite gt h Jan DE 73436 Publshed v heb i914 24032 Pubie Mar 2282 S217t Published gt Apr 1398 7S2 Pulled v Way 96a 28355 Published v Jun 2065 31029 Fitisted ul 3104 4279 Pulsed v Aug 3045 2145 Pubbshed v so 2922 33512 Fubished oct 2338 36726 Fudished Now 27733 3766 Pbished v Dec 732 10824 Published v Total 26179 o 387835 Publinhed Update FIG 6 3 NEA data for desalination 61 Thermal Energy Provided for Distillation PDI Data entry for monthly energy data in giga calories Gcal supplied for water distillation Enter the thermal energy provided during the reference period to the desalination systems of distillation type mu
140. y losses due to tests may be considered as planned if they are identified at least four weeks in advance and are part of a regular programme even if the precise time of the test is not decided four weeks in advance c The scheduled start and end dates of planned outages and load reductions are those dates negotiated with and agreed to by the network and or grid dispatcher at least four weeks in advance These dates may differ from dates shown on the detailed schedule of activities used at the unit for directing the outage d In general any change in the planned outage start date is considered unplanned unless it is announced at least four weeks in advance The following rules should be applied for unplanned changes e Ifa unit begins an outage or load reduction before the scheduled start date unplanned change the energy loss from the beginning of the outage or load reduction to the scheduled start date is an unplanned forced energy loss e If the start date is postponed the outage is still considered planned only until the originally scheduled completion date e Energy losses due to required tests following refuelling are considered planned losses f In general changes in a planned outage or load reduction start date must be announced at least four weeks in advance to be considered as planned However if the grid dispatcher requests a change in the start date less than four weeks in advance the outage or load reduction is consider

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