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1. AC Alternating Current ADAMS Agency Wide Documents Access and Management System CFR Code of Federal Regulations CRE Control Room Envelope DRS Division of Reactor Safety ECR Engineering Change Request EDG Emergency Diesel Generator HPCI High Pressure Coolant Injection HPSW High Pressure Service Water IR Issue Report IST In Service Test LC Load Center LOCA Loss of Coolant Accident LOOP Loss of Offsite Power MCC Motor Control Center MCCB Molded Case Circuit Breaker MCREV Main Control Room Emergency Ventilation NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission PARS Publicly Available Records PMT Post Maintenance Test RHR Residual Heat Removal TS Technical Specifications UFSAR Updated Final Safety Analysis Report Attachment2. 07 00001 E424 480V LC Breakers Replace OD Trip Devices with Solid State Rev 0 ECR 07 00010 Install Permanent Stay Full Line for HPCI Rev 1 ECR 07 00148 Lack of Spares for SCRAM Discharge Volume Level Switches Rev 0 ECR 07 00158 Peach Bottom 3 Cycle 16 Cycle Management Fuel Load Rev 1 ECR 07 00284 Replace E1 EDG Speed Switch with Older Model Rev 0 ECR 07 00342 Physical Mod Recommended for MO 3 23 016 OP for Margin Rev 0 ECR 07 00439 Change IM MCCB to TM MCCB Rev 0 ECR 08 00011 Install Hot Tap to Support ESW System A Header Draining Rev 0 ECR 08 00017 Retire E3 EDG Aux Pumps and Associated Breaker Change to TM Rev 0 ECR 08 00033 2BP098 Failing to Pump Rev 1 ECR 08 00074 Develop Core Spray Pump TS and IST Acceptance Criteria Rev 1 ECR 08 00104 Implementation of New Tech Specs for CR Envelope at PB Rev 0 ECR 08 00289 ESW Pipe Hot Tap B Header Rev 0 ECR 08 00371 Temporary Power for Critical Loads Fed from MCC E324 O A Rev 1 ECR 09 00036 Peach Bottom 3 Soft Shutdown Sequence Rev 2 ECR 09 00339 2BP098 D W Equipment Drain Sump Pump No Flow Rev 0 ECR 09 00360 E17 EDG Tachometer Drive Coupling Shaft Pin Replacement Rev 0 Calculations and Analysis 11187 M 22 PBOC HELB Analysis Plant Model Rev 2 ME 0073 Core Spray Pump In Service Testing Acceptance Criteria Rev 3 ME 0299 RCIC Pump Discharge Head Loss Rev 0 ME 0537 NPSH for HPCI and RCIC Rev 1 NEDC 32163P
3. 50 59 The reviewed safety evaluations and screenings are listed in the attachment Findings No findings of significance were identified Enclosure 2 1 2 2 2 Permanent Plant Modifications 10 samples High Pressure Service Water HPSW Orifice Changes Inspection Scope The team reviewed a modification Engineering Change Request ECR 06 00023 to the HPSW system outlet piping from the Unit 3 D residual heat removal RHR heat exchanger The modification installed a multi hole orifice plate and removed the plugs from another orifice plate in the same line This change was necessary following the replacement of internal components of the Unit 3 D RHR heat exchanger outlet valve because the newer assembly had a greater resistance coefficient and resultant pressure drop The team conducted the review to verify that the design bases licensing bases and performance capability of the HPSW system had not been degraded by the modification The team discussed the modification and design basis with design and system engineers to assess the adequacy of the modification and to verify that the HPSW system had been fully restored to service Post modification test results were reviewed to ensure the HPSW pressure and flow rate met the acceptance criteria The 10 CFR 50 59 screening determination associated with this modification was also reviewed as described in section 1R17 1 of this report Additional documents reviewed are lis
4. Peach Bottom 2 3 SAFER GESTR Analysis Rev 0 NEDC 32230P Peach Bottom Power Rerate Project Engineering Report dated March 1994 PE 0166 Emergency Diesel Generator Loading for Cases Defined by UFSAR Rev 8V and 9 PE 0193 Coordination Study for 480VAC Load Centers and MCCs Rev 5M 5P and 6F PE 0194 Coordination Study for 4kV 1E Switchgear Rev 3H i PM 0123 Diesel Generator Fuel Oil Consumption for 6 Days and 7 Days Operation with LOCA Dependent Loads Rev 4 Attachment A 3 PM 0957 Calculate HPCI RCIC Room Temperature Profiles for 95 F River Temperature Small Break LOCA Rev 1 PM 1050 Heat Balance Thermal Power Uncertainty Analysis Rev 00C PM 1051 Heat Balance Thermal Power Uncertainty Analysis Maintenance and Fail Rev 2 PM 1079 Design Analysis for High Pressure Service Water Orifice Sizing dated 3 9 07 PM 1081 Calculation of Maximum CRE Breach Rev 0 Corrective Action Reports 00227081 00600094 00656655 00935800 00328572 00600132 00662397 01040244 00370589 00601583 00723246 01044407 00388447 00606820 00727345 01044358 00478007 00618400 00792467 00580590 00640506 00852379 Issue report written as a result of inspection effort Drawings 31775 Order 6280 M245 1 3 14 Inch Pressure Breakdown Restriction Orifices dated 4 24 75 6280 A 487 Sht 1 Barrier Plans Rev 11 6280 M 1 S Electrical Schematic Diagram Rod Worth Minimizer System Rev 11 6280 M 315 Sht 3 P amp ID Emergency Service
5. Water and High Pressure Service Water Systems Rev 53 6280 M 353 P amp I Diagram Reactor Recirculation Pump System Rev 56 6280 M 384 Control Room HVAC Rev 40 6280 M 815 Sht 3 Q A D Emergency Service Water and High Pressure Service Water Systems Rev 34 E 1617 Single Line Diagram E324 and E424 Emergency Load Centers Rev 64 E 1619 Single Line Meter and Relay Diagram Rev 32 E 1621 Single Line Diagram E324 T B E124 P A E124 O A and E34 O A Rev 65 Surveillance and Modifications Acceptance Tests M 055 005 480V ITE Solid State Breaker Trip Device Testing performed 7 15 08 M C 700 231 K Line Static Circuit Breaker Calibration performed 5 18 08 and 8 21 08 RE 41 Installation Verification of the 3D Monicore Thermal Operating Limits performed 11 20 09 RT O 032 300 3 HPSW Pump Valve and Flow Functional Test performed 10 21 05 and 1 28 10 RT O 052 251 2 E1 Diesel Generator Inspection PMT performed 8 5 07 and 06 28 09 RT O 052 253 2 E3 Diesel Generator Inspection PMT performed 5 13 09 RT R 59C 500 3 NSSS Computer Calculation of Core Thermal Power performed 10 19 09 ST I 002 250 3 Core Flow Verification performed 10 20 09 ST O 014 301 2 Core Spray Loop A Pump Valve Flow and Cooler Functional and In Service Test performed 10 27 09 and 1 25 10 Attachment A 4 ST O 014 301 3 Core Spray Loop A Pump Valve Flow and Cooler Functional and In Service Test performed 1 6 10 4 14 09 7 15 09
6. change documentation procedures the UFSAR the Technical Specifications TSs and plant drawings to assess the adequacy of the safety evaluations The team compared the safety evaluations and supporting documents to the guidance and methods provided in Nuclear Energy Institute NEI 96 07 Guidelines for 10 CFR 50 59 Evaluations as endorsed by NRC Regulatory Guide 1 187 Guidance for Implementation of 10 CFR 50 59 Changes Tests and Experiments to determine the adequacy of the safety evaluations The team also reviewed a sample of sixteen 10 CFR 50 59 screenings for which Exelon had concluded that no safety evaluation was required These reviews were performed to assess whether Exelon s threshold for performing safety evaluations was consistent with 10 CFR 50 59 The sample included design changes calculations and procedure changes The team reviewed the safety evaluations that Exelon had performed and approved during the time period covered by this inspection i e since the last modifications inspection The screenings and applicability determinations were selected based on the safety significance risk significance and complexity of the change to the facility In addition the team compared Exelon s administrative procedures used to control the screening preparation review and approval of safety evaluations to the guidance in NEI 96 07 to determine whether those procedures adequately implemented the requirements of 10 CFR
7. the design bases and licensing bases for the fuel had not been adversely affected by the modification The team reviewed the analysis to determine what codes were used in the core design and Enclosure 2 8 6 compared those codes to the codes approved by the NRC as listed in the UFSAR The team also reviewed any changes made by the fuel vendor to the approved codes to ensure that changes made to the approved methodologies resulted in conservative results Additionally the team reviewed the results from start up physics testing to verify that appropriate acceptance criteria had been applied and the testing results were within the acceptance criteria Documents reviewed are listed in the attachment Findings No findings of significance were identified Modification to Provide Continuous Prelube for E1 EDG Inspection Scope The team reviewed a modification ECR 05 00255 which provided continuous prelube of the E1 EDG lower crankshaft line Exelon implemented the modification to keep the system piping filters strainers and heat exchangers filled so that lube oil will be quickly provided to the bearings in the event of an emergency start The modification included replacing the existing lube oil heater with a higher kilowatt rated heater and adding a thermostatically controlled valve that allows oil to flow to the engine lower crankshaft line only after it has reached a sufficient temperature The team conducted the review to
8. 0220918 C0223502 R0846490 A1637932 C0221991 C0226624 R1087543 Vendor Manuals 385 A VC 26 Low Voltage Air Magnetic Power Circuit Breakers Rev 2 385 A VC 27 Power Shield Solid State Trip Device Rev 0 677 C VC 32 LEFM Check Plus 2000 FC Flow Measurement System User Manual dated December 2002 L 200 VC 4 Limitorque Valve Operator Engineering Reference Manual Rev 0 NE 72 2 Instructions for HFD Circuit Breakers Rev 0 S 102 VC 2 Rod Worth Minimizer Detailed Design Rev 2 Attachment A 5 Miscellaneous 6280 M1JJ 49 1 Core Spray Pump 2A 2B 2C 2D 3A 3B 3C 3D Pump Curve Rev 1 982861 03 Focused Area Self Assessment 2010 Mods and 50 59 Inspection dated 2 1 10 ASME OM Code 2001 ER 463 Bounding Uncertainty Analysis for Thermal Power Determination at PB Unit 3 Using the LEFM Check Plus System Rev 1 IAR TSTF 448 Control Room Envelope Habitability dated 4 12 07 NEDO 32965 A Reactor Stability Detect and Suppress Solutions Licensing Basis for Reload Applications dated August 1996 NEDO 33091 A Improved BPWS Control Rod Insertion Process dated July 2004 Purchase Order 90 031267 Rev 0 Restricting Orifice Data Sheet for RO 3789 A B C D dated 2 12 74 Restricting Orifice Data Sheet for RO 3800 A D RO 3801 A D dated 2 12 75 USAEC Safety Evaluation for Peach Bottom Atomic Power Station Units 2 and 3 dated 8 11 72 VTS 985 082881 01R Engine Prelube Keepwarm System Requirements dated 8 28 81 LIST OF ACRONYMS
9. B 2007 036 S Install Permanent Stay Full Line for HPCI Rev 0 PB 2007 043 S Torque Switch bypass for MO 3 23 016 Rev 0 PB 2008 002 S Installation of Emergency Service Water Hot Tap A Header Rev 0 PB 2008 004 S Revision to Calculations PE 0166 Diesel Loading and PM 0123 EDG Fuel Oil Consumption Rev 0 PB 2008 007 S Change MCCB from IM to TM Rev 0 PB 2008 008 S Replacement of Obsolete SCRAM Discharge Volume SDV High Level Switches LS 2 03 231C D Rev 0 PB 2008 013 S Revise Thermal Power Uncertainty Calculations Rev 0 Attachment A 2 PB 2008 022 S Installation of Emergency Service Water Hot Tap B Header Rev OPB 2008036 S PB Units 2 and 3 Tech Spec Bases Revision to B 3 3 2 1 Rev 0 PB 2008 037 S Temporary Power for Critical Loads from E324 O A Rev 0 PB 2009 036 S Reclassification of Stairwells 24 and 25 from bats Environment to Mild Environment Rev 0 Modification Packages ECR 96 04115 Evaluate Repair Replacement for MO 89B Valve Rev 2 ECR 00 01131 Solid State Trip Devices for Load Center Breakers Rev 0 ECR 04 00352 Modify Orifice Plates Downstream of MO 3 10 089D Rev 0 ECR 05 00255 Mod to Provide Continuous Prelube for E1 EDG Rev 0 ECR 06 00023 Low Flow Thru HPSW Side of 3D RHR HX During RT O 032 300 3 Rev 0 ECR 06 00099 E434 480V LC Breakers Replace OD Trip Devices with Solid State Rev 1 ECR 06 00461 Retire E 1 EDG Motor Driven Aux Pumps from Service Rev 2 ECR
10. EV system as well as the hole size that correlated to the current leakage out of the CRE Exelon implemented this modification in order to more easily determine the impact of maintenance work on CRE operability The team conducted the review to ensure that the design bases licensing bases and performance capabilities of the CRE and MCREV system had not been adversely affected by the modification l The team reviewed calculation PM 1081 Calculation of Maximum CRE Breach to determine that the maximum opening size had been correctly calculated and that assumptions used in the calculation were appropriate The team also reviewed completed copies of procedure GP 30 Control Room Envelope Boundary Integrity to verify that the opening size limits were being maintained The team interviewed the design engineer to discuss the design criteria associated with the change and walked down the CRE with the program engineer to ensure that conditions in the field aligned with the calculation assumptions Documents reviewed are listed in the attachment Findings No findings of significance were identified Unit 3 Cycle 16 Core Reload Analysis Inspection Scope The team reviewed the analysis performed by Exelon for the design of the Unit 3 cycle 16 core reload ECR 07 00158 The analysis was performed to ensure that various core parameters and thermal limits would not be exceeded throughout the life of the core The team conducted the review to ensure that
11. Pardee 2 Distribution w encl via E mail S Collins RA R1ORAMAIL Resource M Dapas DRA RIORAMAIL Resource D Lew DRP RIDRPMAIL Resource J Clifford DRP RIDRPAMAIL Resource D Roberts DRS R1DRSMail Resource P Wilson DRS R1DRSMail Resource P Krohn DRP A Rosebrook DRP E Torres DRP J Bream DRP F Bower DRP SRI A Ziedonis DRP RI S Schmitt DRP OA L Trocine RI OEDO D Bearde DRS RidsNrrPMPeachBottom Resource ROPreportsResource nrc gov L Doerflein DRS J Lilliendahl DRS Docket No License No Report No Licensee Facility Location Inspection Period Inspectors Approved By U S NUCLEAR REGULATORY COMMISSION REGION 50 277 and 50 278 DPR 44 and DPR 56 05000277 2010006 and 05000278 2010006 Exelon Generation Company LLC Exelon Peach Bottom Atomic Power Station Units 2 and 3 Delta Pennsylvania March 1 2010 through March 19 2010 J Lilliendahl Reactor Inspector Division of Reactor Safety DRS Team Leader K Mangan Senior Reactor Inspector DRS M Orr Reactor Inspector DRS S Rich Reactor Engineer NSPDP in training G Figueroa Reactor Systems Engineer Office of Nuclear Regulatory Research RES observer Lawrence T Doerflein Chief Engineering Branch 2 Division of Reactor Safety i Enclosure SUMMARY OF FINDINGS IR 05000277 2010006 and 05000278 2010006 3 1 2010 3 19 2010 Peach Bottom Atomic Power Station Units 2 and 3 En
12. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 475 ALLENDALE ROAD KING OF PRUSSIA PENNSYLVANIA 19406 1415 April 28 2010 Mr Charles G Pardee Senior Vice President Exelon Generation Company LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Rd Warrenville IL 60555 SUBJECT PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 NRC EVALUATION OF CHANGES TESTS AND EXPERIMENTS AND PERMANENT MODIFICATIONS TEAM INSPECTION REPORT 05000277 2010006 AND 05000278 2010006 Dear Mr Pardee On March 19 2010 the U S Nuclear Regulatory Commission NRC completed an inspection at the Peach Bottom Atomic Power Station The enclosed inspection report documents the inspection results which were discussed on March 19 2010 with Mr W Maguire and other members of your staff The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission s rules and regulations and with the conditions of your license In conducting the inspection the team reviewed selected procedures calculations and records observed activities and interviewed station personnel Based on the results of this inspection no findings of significance were identified In accordance with 10 CFR 2 390 of the NRC s Rules of Practice a copy of this letter its enclosure and your response if any will be available electronically for public inspection in the NRC Public Document Room or fro
13. am reviewed performance test data obtained after the installation of the tachometer drive coupling and the on site manufactured shaft and pins to verify proper performance of the E1 EDG speed switch The team performed a walkdown of E1 EDG to assess the system configuration The documents reviewed are listed in the attachment Findings No findings of significance were identified Core Spray Pump Technical Specification and In service Test Acceptance Criteria Inspection Scope The team reviewed the design change ECR 08 00074 that revised the acceptance criteria for the core spray pump surveillance tests Exelon revised calculation ME 0073 Core Spray Pump In Service Testing Acceptance Criteria as well as the TS surveillance Enclosure 2 4 bases documents Exelon implemented this design change to ensure pump testing results could be used for both in service testing IST requirements for differential pressure and TS surveillance requirements which used discharge pressure as an acceptance criterion The team evaluated the change to ensure that the design bases and licensing bases had not been adversely affected and performance capability of the core spray system would be properly evaluated against design and licensing requirements The team reviewed calculation ME 0073 to determine if the pressure acceptance criterion for each pump had been correctly calculated Additionally the team verified the appropriateness of calculat
14. and 10 22 09 ST O 014 306 2 Core Spray Loop B Pump Valve Flow and Cooler Functional and In Service Test performed 2 11 09 5 16 09 11 18 09 and 2 11 10 ST O 014 306 3 Core Spray Loop B Pump Valve Flow and Cooler Functional and In Service Test performed 11 14 09 and 2 17 10 ST 0 032 301 3 HPSW Pump Valve and Flow Functional and IST performed 12 29 05 ST O 054 754 2 E42 4kV Bus Undervoltage Relays and LOCA LOOP Functional Test performed 9 30 08 ST R 002 900 3 Reactivity Anomalies performed 10 19 09 ST R 002 910 3 Shutdown Margin Determination performed 10 11 09 Procedures AO 2A 16 2 Manual Adjustment of Recirculating Pump Seal Second Stage Pressure Rev 2 AO 33 6 0 ESW Pump Discharge Cross Tie Operations Rev 1 CC AA 103 Configuration Change Control for Permanent Physical Plant Changes Rev 20 CC AA 309 Control of Design Analyses Rev 9 GP 3 Normal Plant Shutdown Rev 117 GP 30 Control Room Envelope Boundary Integrity Rev 1 LS AA 104 Exelon 50 59 Review Process Rev 6 LS AA 104 1000 50 59 Resource Manual Rev 5 M 055 004 480V K Line Load Center Breaker Inspection Rev 6 MA PB 724 005 480V ABB ITE Load Center Breaker Maintenance Rev 1 ON 117 Loss of CRD Regulating Function Rev 15 SO 52A 8 A Diesel Generator Daily Shutdown Inspection Rev 49 ST O 62A 210 2 RWM Operability Check Rev 16 Work Orders A1508236 A1646537 C0223475 C0228635 A1558892 C0214743 C0223499 C0229510 A1625842 C
15. cket water system or air cooling system which could impact EDG design basis accident response The team also reviewed the post modification test plan and results to ensure appropriate acceptance criteria had been met and the tests demonstrated the adequacy of the new design Finally the team walked down the E3 EDG to verify that the retired equipment was fully isolated from the EDG The 10 CFR 50 59 screening determination associated with this modification was also reviewed as described in section 1R17 1 of this report Documents reviewed are listed in the attachment Findings No findings of significance were identified OTHER ACTIVITIES Identification and Resolution of Problems IP 71152 Inspection Scope The team reviewed a sample of Issue Reports IRs associated with 10 CFR 50 59 and plant modification issues to determine whether Exelon was appropriately identifying characterizing and correcting problems associated with these areas and whether the planned or completed corrective actions were appropriate In addition the team reviewed IRs written on issues identified during the inspection to verify adequate problem identification and incorporation of the problem into the corrective action system The IRs reviewed are listed in the attachment Findings No findings of significance were identified Meetings including Exit The team presented the inspection results to Mr W Maguire Site Vice President and other members of Exe
16. ensure that the design bases licensing bases and performance capability of the EDG had not been adversely affected by the modification The team assessed selected design inputs and attributes to ensure that they were consistent with the design and licensing bases The team interviewed the responsible design and system engineers to understand the implementation of the modification and subsequent system performance The team reviewed the electrical loading calculations and breaker coordination calculations to assess the adequacy of the design with respect to the additional heater load Additionally the team evaluated if the design introduced any new failure modes for the lube oil system which could impact EDG design basis accident response The team also reviewed the post modification test plan and results to ensure appropriate acceptance criteria had been met and the tests demonstrated the adequacy of the new design The 10 CFR 50 59 screening determination associated with this modification was also reviewed as described in section 1R17 1 at this report Documents reviewed are listed in the attachment Findings No findings of significance were identified Enclosure 29 2 10 7 Modification to Replace Electro Mechanical Trip Devices with Solid State Trip Devices Inspection Scope The team reviewed a modification ECR 07 00001 which replaced the electro mechanical trip devices in safety related 480V breakers with solid state trip dev
17. gineering Specialist Plant Modifications Inspection This report covers a two week on site inspection period of the evaluations of changes tests or experiments and permanent plant modifications The inspection was conducted by three region based engineering inspectors one inspector in training and one observer No findings of significance were identified The NRC s program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG 1649 Reactor Oversight Process Revision 4 dated December 2006 A NRC Identified and Self Revealing Findings No findings of significance were identified B Licensee Identified Violations None ii Enclosure 1R17 REPORT DETAILS REACTOR SAFETY Cornerstones Initiating Events Mitigating Systems and Barrier Integrity Evaluations of Changes Tests or Experiments and Permanent Plant Modifications IP 71111 17 Evaluations of Changes Tests or Experiments 22 samples Inspection Scope The team reviewed six safety evaluations to determine whether the changes to the facility or procedures as described in the Updated Final Safety Analysis Report UFSAR had been reviewed and documented in accordance with 10 CFR 50 59 requirements In addition the team evaluated whether Exelon had been required to obtain NRC approval prior to implementing the change The team interviewed plant staff and reviewed supporting information including calculations analyses design
18. ices Exelon implemented the modification because the electro mechanical devices were obsolete The modification included replacing the trip devices setting the new trip device setpoints and updating the breaker coordination calculation The breaker coordination calculation was updated to verify that the new device trip characteristics would provide adequate coordination The team conducted the review to ensure that the design bases licensing bases and performance capability of the safety related 480V system had not been adversely affected by the modification The team assessed selected design inputs and attributes to ensure that they were consistent with the design and licensing bases The team interviewed the responsible design engineer to understand the implementation of the modification and subsequent system performance The team reviewed the original and revised versions of PE 0193 Coordination Study for 480VAC Load Centers and Motor Control Centers MCCs to assess the adequacy of the design with respect to the new trip device characteristics and the new trip settings The team also reviewed the post modification test plan and results to ensure that the actual trip settings were in accordance with the design trip settings The associated equivalency change evaluation was also reviewed Documents reviewed are listed in the attachment Findings No findings of significance were identified Modification to Retire E3 EDG Auxiliary Pump
19. ification was adequate The team walked down the E1 EDG to assess the system configuration The documents reviewed are listed in the attachment Findings No findings of significance were identified E1 EDG Tachometer Drive Coupling Shaft Pin Replacement Inspection Scope The team reviewed a modification ECR 09 00360 associated with the replacement of the E1 EDG tachometer drive coupling shaft and pins These components support the EDG s automatic start design function Exelon implemented this modification following the determination that the tachometer drive coupling shaft and pins had been damaged during engine reassembly The replacement drive assembly did not include the required shaft and pins which transfer camshaft rotation through the tachometer drive to the speed switch This modification consisted of the fabrication of a new shaft and pins identical to the existing components The team evaluated the change to confirm that the design bases licensing bases and performance capability of the EDG had not been inadvertently degraded by the modification The team reviewed the plan to fabricate the replacement parts to evaluate the suitability of the replacement material The team interviewed design engineers with regards to the technical evaluation of material used material specifications risk assessment fabrication and acceptable machining tolerances single point vulnerability review and acceptance testing The te
20. ion assumptions The team also reviewed the core spray pump surveillance procedures to confirm that the design change had been incorporated into the procedures and the test configuration ensured design requirements were satisfied The team assessed past surveillance test data to ensure that any negative trends would be captured by the new criteria Finally the team interviewed design and IST engineers to discuss the design criteria associated with the change Documents reviewed are listed in the attachment Findings No findings of significance were identified Modification of MO 3 23 016 Torque Switch Inspection Scope The team reviewed a modification ECR 07 00342 that changed the closing logic for the high pressure coolant injection HPCI turbine steam line isolation valve MO 3 23 016 The valve also has the safety function to close for primary containment isolation The modification replaced the 2 rotor switch with a 4 rotor switch and bypassed the torque switch stop signal until the valve closed indication was also actuated Exelon implemented this modification in order to allow the use of the full capability of the valve motor to close the valve rather than be limited by the torque switch setting The team conducted the review to ensure that the design bases licensing bases and performance capabilities of the primary containment isolation system and HPCI system had not been adversely affected by the modification The team assessed se
21. lected design inputs and attributes to ensure that they were consistent with the design and licensing bases The team verified that the safety related component qualification for the new switch was adequate Additionally the team confirmed that the new design did not introduce any new failure modes for the valve which could impact the HPCI system design basis accident response The team also reviewed the post modification test plan and results to ensure appropriate acceptance criteria had been met which demonstrated the adequacy of the new design Finally the team interviewed the motor operated valve engineer to discuss the implementation of the modification The 10 CFR 50 59 screening determination associated with this Enclosure 2 6 id 5 modification was also reviewed as described in section 1R17 1 of this report Documents reviewed are listed in the attachment Findings No findings of significance were identified implementation of New Technical Specifications for Control Room Envelope Inspection Scope The team reviewed a modification ECR 08 00104 to the control room envelope CRE habitability program that changed the way operability of the CRE was evaluated With the change Exelon established a maximum breech size in the envelope as the requirement to ensure its operability Exelon performed a calculation to determine the size of the maximum opening based on the capabilities of the main control room emergency ventilation MCR
22. lon s staff at an exit meeting on March 19 2010 The team returned the proprietary information reviewed during the inspection to the licensee and verified that this report does not contain proprietary information Enclosure A 1 ATTACHMENT SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT Exelon Personnel W Maguire Site Vice President R Smith Licensing J Chizever Manager Mechanical Design Engineering K Cutler Design Engineer LIST OF ITEMS OPENED CLOSED AND DISCUSSED None LIST OF DOCUMENTS REVIEWED 10 CFR 50 59 Evaluations PB 2007 001 E Improved Control Rod Shutdown Sequence Soft Shutdown Rev 0 PB 2007 002 E GP 3 Revision to Defeat the Mode Switch to Shutdown Scram Rev 0 PB 2007 003 E Continuous Venting of Recirculation Seals Rev 0 PB 2008 001 E Unit 2 Drywell Equipment Drain Sump Temporary Logic Reconfiguration Rev 0 PB 2009 001 E Install Higher Value Sensitivity Resistor on Control Circuit LS 2 20 360 Rev 0 PB 2009 002 E Application of TRACGO4P for OPRM Setpoint Determination Rev 0 10 CFR 50 59 Screened Out Evaluations PB 2005 065 S PBAPS EDG Keep Warm Modifications Rev 5 PB 2006 055 S Abandonment of EDG Motor Driven Aux Lube Oil Jacket Coolant and Air Coolant Pumps Rev 0 PB 2007 007 S ESW Pump Discharge Cross Tie Operation Rev 0 PB 2007 008 S Low Flow Thru HPSW Side of 3D RHR HX During RT O 032 300 3 Rev 0 PB 2007 028 S Revise RCIC TDH Requirements in UFSAR and DBD Rev 0 P
23. m the Publicly Available Records PARS component of the NRC s document system ADAMS ADAMS is accessible from the NRC Web site at http Avww nrc gov reading rm adams html the Public Electronic Reading Room Sincerely Lawrence T Doerflein Chief f Engineering Branch 2 Division of Reactor Safety Docket Nos 50 277 50 278 License Nos DPR 44 DPR 56 Enclosure Inspection Report No 05000277 2010006 and 05000278 2010006 w Attachment Supplemental Information cc w encl Distribution via ListServ April 28 2010 Mr Charles G Pardee Senior Vice President Exelon Generation Company LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Rd Warrenville IL 60555 SUBJECT PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 NRC EVALUATION OF CHANGES TESTS AND EXPERIMENTS AND PERMANENT MODIFICATIONS TEAM INSPECTION REPORT 05000277 2010006 AND 05000278 2010006 Dear Mr Pardee On March 19 2010 the U S Nuclear Regulatory Commission NRC completed an inspection at the Peach Bottom Atomic Power Station The enclosed inspection report documents the inspection results which were discussed on March 19 2010 with Mr W Maguire and other members of your staff The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission s rules and regulations and with the conditions of your license In conducting the inspection the team reviewed selected procedu
24. res calculations and records observed activities and interviewed station personnel Based on the results of this inspection no findings of significance were identified In accordance with 10 CFR 2 390 of the NRC s Rules of Practice a copy of this letter its enclosure and your response if any will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records PARS component of the NRC s document system ADAMS ADAMS is accessible from the NRC Web site at http www nre gov reading rm adams html the Public Electronic Reading Room Sincerely RA Lawrence T Doerflein Chief Engineering Branch 2 Division of Reactor Safety Docket Nos 50 277 50 278 License Nos DPR 44 DPR 56 Enclosure Inspection Report No 05000277 2010006 and 05000278 2010006 w Attachment Supplemental Information cc w encl Distribution via ListServ ADAMS ACCESSION NO ML101180465 SUNSI Review Complete _ LTD Reviewer s Initials DOCUMENT NAME G DRS Engineering Branch 3 Lilliendahl PB Mods Report 2010006 rev1 doc After declaring this document An Official Agency Record it will be released to the Public To receive a copy of this document Indicate in the box C Copy without attachment enclosure E Copy with attachment enclosure N No cop OFFICE RI DRS _ RVDRP __ RvDRS Eea aa A al NAME JLilliendahi PKrohn LDoerflein eee ee eee OFFICIAL RECORD COPY C
25. s and Associated Breaker Change Inspection Scope The team reviewed a modification ECR 08 00017 that retired the E3 EDG jacket coolant air coolant and lube oil motor driven backup auxiliary pumps Exelon implemented the modification because the aforementioned pumps required excessive maintenance introduced leak paths increased the failure modes and did not appreciably increase the reliability of the EDGs Exelon had previously completed this modification for the other EDGs The modification included isolating and removing the pumps blind flanges etc removing the pump power and controls and replacing the EDG MCC instantaneous magnetic molded case circuit breakers MCCBs with thermal magnetic MCCBs The team conducted the review to ensure that the design bases licensing bases and performance capability of the EDG had not been adversely affected by the modification _ Enclosure 40A2 40A6 The team assessed selected design inputs and attributes to ensure that they were consistent with the design and licensing bases The team interviewed the responsible design and system engineers to understand the implementation of the modification and subsequent system performance The team reviewed the breaker coordination calculations to assess the adequacy of the design with respect to the change in circuit breaker design Additionally the team confirmed that the design did not introduce any new failure modes for the lube oil system ja
26. ted in the attachment Findings No findings of significance were identified E1 Emergency Diesel Generator EDG Speed Switch Replacement Inspection Scope The team reviewed a modification ECR 07 00284 which replaced the E1 EDG engine speed switch Exelon implemented this modification following erratic behavior of the speed switch during routine surveillance testing Exelon had previously upgraded the speed switch to a newer model and did not have any available new spares The modification re installed the original model speed switch The original model speed switch had a successful history of use since plant construction and was determined to meet the criteria of an equivalent change The team conducted the review to ensure that the design bases licensing bases and performance capability of the EDG had not been adversely affected by the modification The team reviewed the high and low speed switch setpoints to verify there were no adverse impacts to operating margins and that the speed switch functioned in accordance with the design basis The team reviewed post maintenance test data to confirm that the replacement speed switch met the acceptance criteria and the EDG Enclosure 2 3 2 4 3 was operable Additionally the team reviewed the associated work order packages and conducted interviews with design and system engineers regarding the design installation and testing of the switches to verify that the mod
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