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Category:Letter type:L
MONTHYEARL-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-158, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models L-24-157, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-114, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation L-24-115, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 272023-11-29029 November 2023 Submittal of the Updated Final Safety Analysis Report, Revision 27 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports 2024-09-17
[Table view] Category:Report
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-154, Pressure and Temperature Limits Report Revision2022-07-0606 July 2022 Pressure and Temperature Limits Report Revision L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-02-10010 February 2022 Steam Generator Inspection Report- Fall 2021 Refueling Outage IR 05000334/20210052021-09-0101 September 2021 Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005) ML21131A0242021-05-17017 May 2021 Review of Reactor Pressure Vessel Capsule Y Analysis Report ML21055A0582021-03-10010 March 2021 Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021 Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks ML21026A3372021-01-26026 January 2021 Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML21127A1652020-07-17017 July 2020 ODCM: Index, Matrix and History of ODCM Changes L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020 ODCM: Liquid Effluents ML21127A1482020-07-17017 July 2020 ODCM: Controls for RETS and REMP Programs L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020 CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency ML19280A0382019-10-22022 October 2019 Ti 2515-191 Summary of Findings ML21127A1562019-07-17017 July 2019 ODCM: Gaseous Effluents ML19051A1092019-02-20020 February 2019 LTR-SDA-18-054-NP, Revision 0 - Technical Justification to Support the Extended Volumetric Examination Interval for Beaver Valley Unit 2 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019 Emergency Response Data System Data Point Library Update L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado. ML21127A1592018-01-22022 January 2018 ODCM: Radiological Environmental Monitoring Program L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017 Pressure and Temperature Limits Reports, Revisions 8 and 9 L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017 Mitigating Strategies Assessment (MSA) for Flooding ML17213A0162017-05-11011 May 2017 Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1 ML17213A0172017-05-11011 May 2017 Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16312A3112016-11-0707 November 2016 Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review... L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016 Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016 Report of Facility Changes, Tests and Experiments L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016 Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016 Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016 Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. ML16277A1142015-10-28028 October 2015 ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels. ML15274A3072015-10-0505 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015 Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML15132A4962015-05-22022 May 2015 Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620) ML16277A1222015-04-20020 April 2015 ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points. ML15119A1042015-03-31031 March 2015 SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4 L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015 SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4 ML21127A1582015-02-11011 February 2015 ODCM: Bases for ODCM Controls ML16277A1152015-01-30030 January 2015 ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints. ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014 Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 ML21127A1442014-10-0707 October 2014 ODCM: Information Related to 40 CFR 190 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14224A5772014-07-31031 July 2014 SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report. ML14224A5762014-07-31031 July 2014 SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions. ML14224A5752014-06-25025 June 2014 R17 Steam Generator F* (F Star) Report ML14009A0892014-02-10010 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident 2023-08-07
[Table view] Category:Miscellaneous
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20210052021-09-0101 September 2021 Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005) ML21131A0242021-05-17017 May 2021 Review of Reactor Pressure Vessel Capsule Y Analysis Report ML21055A0582021-03-10010 March 2021 Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021 Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019 Emergency Response Data System Data Point Library Update L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado. ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16312A3112016-11-0707 November 2016 Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review... L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016 Report of Facility Changes, Tests and Experiments L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016 Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016 Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016 Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. ML15274A3072015-10-0505 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015 Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML15132A4962015-05-22022 May 2015 Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620) ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014 Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14009A0892014-02-10010 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident ML13284A0242013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix B, Seismic Walkdown Checklists (Swcs), Part 3 of 5 ML13284A0272013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix B, Seismic Walkdown Checklists (Swcs), Continued, Part 4 of 5 ML13284A0262013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix a, Resumes and Qualifications, Part 2 of 5 ML13284A0252013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Part 1 of 5 ML13284A0232013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix a, Resumes and Qualifications, Part 2 of 5 ML13284A0192013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix B Seismic Walkdown Checklists (Swcs), Part 3 of 5 ML13284A0222013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Part 1 of 5 ML13284A0202013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix B Seismic Walkdown Checklists (Swcs) Continued. Part 4 of 5 ML13284A0212013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix C Area Walk-by Checklists (Awcs), Part 5 of 5 L-13-036, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules2013-05-28028 May 2013 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules L-13-095, Discharge Monitoring Report (NPDES) Permit No. PA00256152013-02-22022 February 2013 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-12-437, Containment Liner Random and Non-Random Examinations Report2012-12-18018 December 2012 Containment Liner Random and Non-Random Examinations Report L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13008A0422012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklits (Swcs), Battery 2N. Pages 1 - 82 ML13008A0412012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report. Cover Through A-40 ML13135A2382012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 513 Through Sheet 301 of 513 ML13008A0432012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Purge Valve Isolation. Pages 83 - 161 ML13008A0442012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Bus F1, Low Voltage Switchgear. Pages 162 - 240 ML13008A0452012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), SGI Level Switch SP9B6. Pages 241 - 318 ML13008A0462012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Relief Valves SW 3963. Pages 319 - End ML13135A2412012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C - Area Walk-by Checklists (Awcs) and Appendix D - Component List for Anchorage Configuration Check ML13135A2402012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 302 of 513 Through Sheet 513 of 513 ML13135A2362012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report ML13135A2372012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13008A0402012-10-23023 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C Area Walk-by Checklists (Awcs), Prim. Aux. Bldg 735'6. Pages 135 - 191 ML13008A0392012-10-23023 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C Area Walk-by Checklists (Awcs), Emer. Swgr. Room Train A. Pages 66 - 134 2023-08-07
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FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergyNuclear OperatingCompany Shippingport,PA 15077 Eric A. Larson 724-682-5234 Site .Vice President Fax: 724-643-8069 May 28, 2013 L-1 3-036 10 CFR 50, Appendix H ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules As required. by 10 CFR 50, Appendix H, FirstEnergy Nuclear Operating Company (FENOC) hereby submits a request for Nuclear Regulatory Commission (NRC) approval of a revision to the Beaver Valley Power Station, Unit Nos. 1 and 2 reactor vessel (RV) surveillance capsule withdrawal schedules. The proposed changes to the surveillance capsule withdrawal schedules are consistent with the recommendations specified in American Society for Testing and Materials Standard Practice E185-82, "Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessel."
The FENOC evaluation of the proposed changes is provided in Enclosure A. The RV surveillance capsule withdrawal schedules would be revised to be consistent with the recommendations included in Section 8 of WCAP-15571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," Supplement 1, Revision 2, dated September 2011 and Section 8 of WCAP-16527-NP, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program,"
Supplement 1, Revision 1, dated September 2011. WCAP-1 5571 and WCAP-16527-NP are provided in Enclosures B and C, respectively.
To allow for normal NRC processing, FENOC requests approval of the proposed schedule changes by May 31, 2014.
Beaver Valley Power Station, Unit Nos. 1 and 2 L-1 3-036 Page 2 There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A.
Lentz, Manager - Fleet Licensing, at (330) 315-6810.
Sincerely, Eric A. Larson
Enclosures:
A FENOC Evaluation of the Proposed Changes B WCAP-1 5571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," Supplement 1, Revision 2, dated September 2011 C WCAP-16527-NP, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program,"
Supplement 1, Revision 1, dated September 2011 cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
2' Enclosure A L-1 3-036 FENOC Evaluation of the Proposed Changes (9 Pages Follow)
FENOC Evaluation of the Proposed Changes
Subject:
Request Approval for Changes to the Beaver Valley Power Station, Unit Nos. 1 and 2 Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedules Table of Contents 1.0
SUMMARY
DESCRIPTION ........................................................................... 2 2.0 R E Q UIR E ME N T S ........................................................................................... 2
3.0 PROPOSED CHANGE
S ................................................................................ 3
4.0 TECHNICAL EVALUATION
............................................................................ 7 5 .0 C O NC LUS IO N ............................................................................................. .. 8 6 .0 R E F E R E NC E S .............................................................................................. . . 9
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 2 of 9 1.0
SUMMARY
DESCRIPTION FirstEnergy Nuclear Operating Company (FENOC) is requesting approval of proposed changes to the Beaver Valley Power Station, Unit Nos. 1 (BVPS-1) and 2 (BVPS-2) reactor pressure vessel (RPV) material irradiation surveillance capsule withdrawal schedules. The proposed changes are submitted pursuant to 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements,"Section III.B.3, which requires that: 1) withdrawal schedules be submitted with a technical justification as specified in 10 CFR 50.4, "Written Communications," and 2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation.
NRC approval of the proposed schedule would satisfy a BVPS-1 and a BVPS-2 license condition regarding the capsule withdrawal schedule that states:
For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E185-82 [Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels] to the extent practicable for the configuration of the specimens in the capsule.
Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
Additionally, the nuclear industry has developed a Coordinated Pressurized Water Reactor (PWR) Reactor Vessel Surveillance Program (CRVSP), which is documented in "Material Reliability Program: Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326)." The purpose of the CRVSP is to increase the fluence levels of future surveillance capsules at withdrawal while maintaining compliance with 10 CFR 50 Appendix H and consistent with the guidance of NUREG-1 801, Revision 2, "Generic Aging Lessons Learned (GALL)
Report." The CRVSP will help generate high fluence PWR surveillance data in support of extended life operations.
The proposed changes to the RPV surveillance capsule withdrawal schedules are consistent with the recommendations specified in ASTM E185-82, as referenced by the requirements of 10 CFR 50, Appendix H.
2.0 REQUIREMENTS 10 CFR 50, Appendix H, requires nuclear power plant licensees to implement RPV surveillance programs to "monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region.. .which result from the exposure of these materials to neutron irradiation and the thermal environment." 10 CFR 50, Appendix H, Section III.B.1 states that the design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 3 of 9 ASTM E185 that is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to which the RPV was purchased. The rule permits the use of later editions of ASTM El 85, but including only those editions through 1982 (that is, ASTM E185-82).
10 CFR 50, Appendix H, Section III.B.3, requires prior NRC approval of RPV surveillance capsule withdrawal schedule changes. Further, NRC Administrative Letter 97-04, "NRC Staff Approval for Changes to 10 CFR 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules," dated September 30, 1997, specifies that changes to RPV surveillance capsule withdrawal schedules that do not conform to ASTM E185 require approval by the license amendment process, whereas changes that conform to the ASTM standard require only staff verification of such conformance. The proposed changes to the BVPS-1 and BVPS-2 surveillance capsule withdrawal schedules conform to ASTM E185-82, and therefore, a license amendment is not required for these proposed changes.
3.0 PROPOSED CHANGE
S The purpose of the proposed changes is to revise the BVPS-1 and BVPS-2 RPV surveillance capsule withdrawal schedules due to updated neutron fluence projections. Additionally, the proposed BVPS-2 RPV surveillance capsule withdrawal schedule implements the MRP-326 recommendation regarding Capsule A. The current surveillance capsule withdrawal schedules and the proposed revised schedules are provided below.
The current BVPS-1 Updated Final Safety Analysis Report (UFSAR) Table 4.5-3, "Reactor Vessel Material Irradiation Surveillance Schedule," is as follows:
Capsule Vessel Lead Withdrawal Fluence Location Factor (a) EFPY [effective full (n/cm 2 , E > 1.0 MeV)(a)
(deg) power years] (b)
V 165 1.60 1.16 (removed) 3.23 x 1018 (c)
U 65 1.05 3.59 (removed 6.46x 10TM (c)
W 245 1.09 5.89 (removed) 9.86 x 1018 (c)
Y 295 1.22 14.3 (removed) 2.15 x 1019 (c)
X 285 1.76 25.9 5.87 x 10T (f)
T 55 (d) Standby Z 305 (e) Standby S 45 0.63 (g) Standby (a) Updated in Capsule Y dosimetry analysis.
(b) Effective full power years from plant startup. Changes to this column will require prior NRC approval, (except to indicate that capsules have been removed), as specified in Section III.B.3, Appendix H of 10 CFR 50.
(c) Actual fluence, calculated from plant evaluation.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 4 of 9 (d) Capsule T was moved to the Capsule U location at the end of Cycle 10 (10.8 EFPY). The lead factor was approximately 0.77 through the first 10 cycles.
The average lead factor for Cycle 11 and higher is 0.95.
(e) Capsule Z was moved to the Capsule V location at the end of Cycle 10 (10.8 EFPY). The lead factor was approximately 0.77 through the first 10 cycles.
The average lead factor for Cycle 11 and higher is 1.11.
(f) Reactor Vessel Clad/Base Metal interface at 45 EFPY.
(g) Capsule S was moved to the Capsule Y location at the end of Cycle 19.
NOTE: This information was obtained from Section 4.5 [WCAP-15571, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," November 2000],
except for Capsule X removal time and fluence which were subsequently updated to reflect power uprate to 2900 MWt [megawatts thermal]. Note that the 1R1 9 movement of Capsule S was a result of the need to move this capsule to a location with a higher lead factor.
The following recommended BVPS-1 surveillance capsule withdrawal schedule, is consistent with WCAP-15571, Supplement 1, Revision 2, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program," and meets the requirements of ASTM El 85-82.
Capsule Current (Original) Lead Withdrawal Fluence, fa)
Capsule Location Factor(a) EFPY(b) [n/cm 2 , E > 1.0 MeV]
V 1650 1.61 1.16 2.99 x 10" U 650 1.06 3.59 6.04 x 1018 W 2450 1.11 5.89 9.30 x 101' Y 2950 1.2 14.29 2.05 x 1019 X(c) 2850 1.72 26.5(c) 5.01 x 1019(c)
T(d 65° (550) 0.99 Standby(d)
S(e) 2950 (450) 0.64 Standby(e)
Z__ _ 1650 (305 0) 1.24 36.6(') ---
Notes:
a) Updated in WCAP-15571, Supplement 1, Revision 2 b) Effective full power years (EFPY) from plant startup.
c) Capsule X is planned to be withdrawn at the end of Cycle 22, which corresponds to 26.5 EFPY. This capsule will meet the requirements of ASTM El 85-82 for the fifth capsule to be withdrawn for the 40-year end-of-life (EOL).
d) Capsule T was moved to the Capsule U location at the end of Cycle 10. In order to achieve higher fluence data for this capsule, Capsule T should be relocated to the current Capsule Z location when Capsule Z is withdrawn from the vessel [see footnote (f)].
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 5 of 9 e) Capsule S was moved to the Capsule Y location at the end of Cycle 19. In order to achieve higher fluence data for this capsule, Capsule S should be relocated to the Capsule X location when Capsule X is withdrawn from the vessel at 26.5 EFPY.
f) Capsule Z was moved to the original Capsule V location at the end of Cycle 10.
Based on the current information, Capsule Z should be withdrawn after 36.6 EFPY, which corresponds to the peak vessel fluence at 60-year EOL (50 EFPY),
5.58 x 1019 n/cm 2 (E > 1.0 MeV).
NOTE: For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
The current BVPS-2 UFSAR Table 5.3-6, "Reactor Vessel Material Irradiation Surveillance Schedule," is as follows:
Capsule Current Location Lead Withdrawal Fluence (degree) Factor(a) EFPY(b) (n/cm 2 , E > 1.0 MeV)
U 343 3.17 1.24 6.08 x 105 (c)
V 107 3.64 5.98 2.63 x 1019(c)
W 110 3.29 9.77 3.625 x 1019(c) 5.837 x 1T' 9 (d)
X 287 3.71 14 Y 290 3.29 Standby Z 340 3.29 Standby Notes:
(a) Updated in Capsule W dosimetry analysis.
(b) Effective Full Power Years (EFPY) from plant startup. Changes to this column will require prior NRC approval as specified in Section III.B.3, Appendix H, of 10 CFR 50.
(c) Fluence calculated by plant-specific evaluation.
(d) Approximately equal to the projected peak vessel fluence at 48 EFPY, not less than once or greater than twice the maximum EOL (32 EFPY) inner vessel wall fluence.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 6 of 9 The following recommended BVPS-2 surveillance capsule withdrawal schedule is consistent with WCAP-16527-NP, Supplement 1, Revision 1, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," and meets the requirements of ASTM E185-82.
Capsule Current (Original) Lead Withdrawal Fluence, f(a)
Capsule Location Factor(a) EFPY(b) [n/cm 2 , E > 1.0 MeV]
U 3430 3.17 1.25 6.15 x 1018 V 1070 3.64 5.99 2.64 x 1019 W 1100 3.25 9.84 3.61 x 1019 X 2870 3.69 14.00 5.63 x 10'9 y(C) 2900 3.17 (c)
Z(c) 3400 3.17 (c) ---
A_(d) 1070 3.58 32(d) ---
Notes:
a) Updated in WCAP-16527-NP, Supplement 1, Revision 1.
b) Effective full power years (EFPY) from plant startup.
c) It is recommended that one of these capsules be pulled at a time when the capsule fluence exceeds one times the projected peak 80-year EOL fluence, but before the capsule fluence reaches two times the projected 60-year EOL fluence. Therefore, based on the current information, Capsule Y or Z should be withdrawn between 20.5 EFPY and 32.4 EFPY. In order to be consistent with NUREG-1929, "Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2," this capsule should be pulled at the refueling outage closest to 2 26.1 EFPY, which corresponds with a peak vessel fluence level of 8.5 x 1019 n/cm (E > 1.0 MeV). The second capsule will remain in the vessel to provide fluence monitoring or future testing. The withdrawal of this capsule will be revisited at a later time.
d) Supplemental Capsule A contains BVPS-1 initially unirradiated material specimens, as well as previously irradiated material specimens from BVPS-1, St. Lucie, and Fort Calhoun. Supplemental Capsule A was inserted in the vacant Capsule V location at the end of Cycle 8. In order to be consistent with the "Materials Reliability Program:
Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326)" recommendation, Capsule A is to be removed and tested when it reaches a fluence value equivalent to the peak 80-year vessel fluence for BVPS-1. This is expected to occur at approximately 32 EFPY.
NOTE: For the renewed operating license term, all capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 7 of 9
4.0 TECHNICAL EVALUATION
BVPS-1 This request proposes to revise the BVPS-1 RPV surveillance capsule withdrawal schedule to account for updated neutron fluence projections based on the results of the latest surveillance Capsule Y evaluation, sister plant surveillance data (St. Lucie Unit 1 and Fort Calhoun), and the implementation of the extended power uprate program.
Calculations were performed for end-of-license extension (EOLE) at 50 EFPY.
The surveillance capsules are used to monitor changes in the toughness properties of ferritic materials in the RPV beltline. The surveillance capsules are located closer to the core than the reactor vessel beltline materials, so that fracture toughness testing can be used to determine the nil-ductility transition temperature of the vessels at a later time in life. The current BVPS-1 Pressure - Temperature (P-T) limit curves were developed in accordance with 10 CFR 50, Appendix G, "Fracture Toughness Requirements," through 30 EFPY. These limits are based on the limiting beltline material adjusted reference temperature (ART) values, that is, lower shell plate B6903-1. The proposed change in the capsule withdrawal schedule does not adversely affect the validity of the existing P-T limit curves for the 30 EFPY term.
The proposed change to the surveillance capsule schedule is based on the requirements of the 1982 Edition of ASTM E185 as provided in 10 CFR 50, Appendix H. Since the reference temperature nil-ductility transition shift (ARTNDT) projected at EOLE is greater than 2000 F (222.10 F), ASTM E185-82, Table 1, "Minimum Recommended Number of Surveillance Capsules and Their Withdrawal Schedule (Schedule in Terms of Effective Full-Power Years of the Reactor Vessel),"
requires the withdrawal of a minimum of five capsules. Four of the eight BVPS-1 reactor vessel surveillance capsules have been withdrawn and tested. At the end of Cycle 22, a fifth surveillance capsule (Capsule X) is planned to be withdrawn from the reactor vessel. In accordance with ASTM El 85-82, Table 1, note E, the fifth capsule is to be removed at, "Not less than once or greater than twice the peak EOL vessel fluence..." Withdrawal of Capsule X would meet the requirements of ASTM El 85-82 for the fifth capsule to be withdrawn for the 40-year EOL. Additionally, Capsule Z should be withdrawn after 36.6 EFPY, which corresponds to the peak vessel fluence at 60-year EOL (50 EFPY), 5.58 x 1019 n/cm 2 (E > 1.0 MeV).
Capsule T and Capsule S could be utilized for 80-year EOL data.
In summary, the proposed revision to the BVPS-1 RPV surveillance capsule withdrawal schedule is based on the analysis of the latest surveillance capsule removed (Capsule Y) and complies with the requirements provide in ASTM E185-82.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 8 of 9 BVPS-2 This request proposes to revise the BVPS-2 RPV surveillance capsule withdrawal schedule to account for updated neutron fluence projections based on the results of the latest surveillance Capsule X evaluation and the implementation of the extended power uprate program. Calculations were performed for EOLE at 54 EFPY.
The surveillance capsules are used to monitor changes in the toughness properties of ferritic materials in the RPV beltline. The surveillance capsules are located closer to the core than the reactor vessel beltline materials, so that fracture toughness testing can be used to determine the nil-ductility transition temperature of the vessels at a later time in life. The BVPS-2 P-T limit curves were developed in accordance with 10 CFR 50, Appendix G, for 22 EFPY, 30 EFPY, 40 EFPY, and 54 EFPY. BVPS-2 is operating to the 22 EFPY P-T limit curves. These limits are based on the limiting beltline material ART values, that is, intermediate shell plate B9004-1. The proposed change in the capsule withdrawal schedule does not adversely affect the validity of the existing P-T limit curves for the 22 EFPY term.
The proposed change to the surveillance capsule schedule is based on the requirements of the 1982 Edition of ASTM E185 as provided in 10 CFR 50, Appendix H. Since the ARTNDT is less than 100' F (72.40 F), ASTM E185-82, Table 1 requires the withdrawal of a minimum of three capsules. Four of the six BVPS-2 reactor vessel surveillance capsules have been withdrawn and tested. Per ASTM El 85-82, Table 1, note E, the third capsule is to be removed at, "Not less than once or greater than twice the peak EOL vessel fluence..." Withdrawal of Capsule X meets the requirements of ASTM E185-82, as Capsule X was the fourth capsule to be withdrawn for the 40-year EOL.
To satisfy requirements for a 60-year as well as a potential 80-year capsule, either capsule Y or Z should be withdrawn between 20.5 EFPY and 32.4 EFPY. In order to be consistent with NUREG-1 929, this capsule should be pulled at the refueling outage closest to 26.1 EFPY, which corresponds with a peak vessel fluence level of 8.5 x 1019 n/cm 2 (E > 1.0 MeV). The remaining capsule is considered a standby capsule and would remain in the vessel for fluence monitoring or future testing.
5.0 CONCLUSION
The proposed BVPS-1 and BVPS-2 RPV surveillance capsule withdrawal schedules will continue to meet the RPV surveillance capsule withdrawal schedule criteria in ASTM E185-82 as required by 10 CFR 50.
FENOC Evaluation of the Proposed Changes Beaver Valley Power Station, Unit Nos. 1 and 2 Page 9 of 9
6.0 REFERENCES
- 1. WCAP-1 5571, Supplement 1, Revision 2, "Analysis of Capsule Y from Beaver Valley Unit 1 Reactor Vessel Radiation Surveillance Program,"
September 2011.
- 2. WCAP-16527-NP, Supplement 1, Revision 1, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," September 2011.
- 3. Electric Power Research Institute, "Materials Reliability Program:
Coordinated PWR Reactor Vessel Surveillance Program (CRVSP) Guidelines (MRP-326)," 2011.