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Category:Letter type:L
MONTHYEARL-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 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-24-014, 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-24-164, 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-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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-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-23-229, 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 L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time 2024-08-27
[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:Technical
MONTHYEARL-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 ML21026A3372021-01-26026 January 2021 Steam Generator Inspection Report Revision - Spring 2020 Refueling Outage L-21-135, ODCM: Liquid Effluents2020-07-17017 July 2020 ODCM: Liquid Effluents ML21127A1652020-07-17017 July 2020 ODCM: Index, Matrix and History of ODCM Changes 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 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 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 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 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 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 ML16277A1142015-10-28028 October 2015 ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels. 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. ML21127A1442014-10-0707 October 2014 ODCM: Information Related to 40 CFR 190 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 ML13364A1662014-01-29029 January 2014 Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14029A0212014-01-28028 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Beaver Valley Power Station, Units 1 and 2, TAC Nos.: MF0841 and MF0842 (Revision 2) ML14030A1352014-01-27027 January 2014 WCAP-17790-NP, Revision 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals. ML14030A1342014-01-27027 January 2014 WCAP-17789-NP, Rev. 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals. L-13-387, Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Page 284 Through Page T-422013-11-30030 November 2013 Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Page 284 Through Page T-42 ML14002A0902013-11-30030 November 2013 Firstenergy Nuclear Operating Company Beaver Valley Power Station Units 1 and 2, NFPA 805 Transition Report. Cover Through Page 283 ML13126A0422013-04-15015 April 2013 RTL A9.630F, 2012 Annual Environmental Operating Report, (Non-Radiological) ML13126A0392013-04-12012 April 2013 RTL A9.690E, 2012 Radioactive Effluent Release Report and 2012 Annual Radiological Environmental Operating Report, Enclosure 1, Cover Through Enclosure 2, Attachment 3 ML13028A4712013-01-14014 January 2013 SG-SGMP-13-2, Rev. 1, Beaver Valley Unit 2, End-of-Cycle 16 Voltage-Based Repair Criteria 90-Day Report. L-12-458, Unit 2 - 2R16 Steam Generator F* (F Star) Report2012-12-0404 December 2012 Unit #2 - 2R16 Steam Generator F* (F Star) Report ML13008A0482012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-by Checklists, Sheet 79 of 123 Through End ML13008A0472012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-by Checklists, Page C-1 Through Sheet 78 of 123 ML16277A1162012-04-26026 April 2012 ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors. ML16277A1232012-04-26026 April 2012 ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors. ML13151A0602011-09-30030 September 2011 Enclosure 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 ML13151A0592011-09-30030 September 2011 Enclosure B, WCAP-15571, Analysis of Capsule Y from Beaver Valley, Unit 1 Reactor Vessel Radiation Surveillance Program, Supplement 1, Revision 2, Dated September 2011 ML16277A1242011-08-10010 August 2011 ERS-SFL-88-027, Rev. 3, Process Safety Limits, Alarm Setpoints and EAL Indicator Value for 2CHS-RQ101A/B. ML16277A1172011-08-0909 August 2011 ERS-JTL-99-005, Rev. 3, Unit 1 Letdown Radiation Monitor (RM-1CH-101) Alarm Setpoint Calculation and Emergency Action Level (EAL) ERS-JTL-99-005 21 Value Determination. ML16277A1272011-08-0707 August 2011 ERS-SMM-11-002, Containment Radiation Monitor Readings Following Clad Damage (FC2 Loss, FC7 Loss, RC2 Loss and CT2 Potential Loss). ML16277A1182011-08-0707 August 2011 ERS-SMM-11-002, Containment Radiation Monitor Readings Following Clad Damage (FC2 Loss, FC7 Loss, RC2 Loss and CT2 Potential Loss). L-11-024, Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack2011-02-18018 February 2011 Chapters 5 and 7 of Holtec Licensing Report, in Support of License Amendment Request for Unit 2 Spent Fuel Pool Rerack ML1029404582010-10-18018 October 2010 Holtec Report No: HI-2084175, Licensing Report for Beaver Valley, Unit 2, Rerack. ML0912102632009-04-0909 April 2009 HI-2084175, Revision 3, Holtec Licensing Report for Beaver Valley, Unit 2 Rerack, Enclosure C ML0900203862008-12-30030 December 2008 WCAP-16144-NP, Revision 1, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Beaver Valley Unit 2 ML0829002092008-08-31031 August 2008 WCAP-16158-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Beaver Valley Unit 2 2022-07-06
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Text
Y-ENOC 1""
Beaver Valley Power Station PO. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L. Wlliam Pearce 724-682-5234 Vice President Fax: 724-643-8069 May 19, 2005 4 L-05-093 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station (BVPS), Unit No. 2 BV-2 Docket No. 50-412, License No. NFP-73 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R11
References:
- 1. NRC Bulletin 2004-01: "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," dated May 28, 2004.
- 2. FirstEnergy Nuclear Operating Company (FENOC) 60-Day Response to NRC Bulletin 2004-01 for BVPS (Letter L-04-081 dated July 27, 2004).
- 3. FENOC Supplemental Response to NRC Bulletin 2004-01 for BVPS (Letter L-04-128 dated September 29, 2004).
During the recent BVPS Unit 2 2R1 1 Refueling Outage, a visual inspection of Alloy 82/182/600 material locations in the pressurizer penetrations and steam space piping, within the scope of NRC Bulletin 2004-01 (Reference 1), was performed. This inspection was conducted per the FENOC response for BVPS (References 2 and 3) to the Bulletin. In accordance with the Bulletin, a 60-day report, detailing the inspection results, is being provided. The BVPS Unit 2 Evaluation Report for 2R1 1 Pressurizer Penetration Inspections is enclosed with this letter.
There are no new regulatory commitments contained in this letter. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-4284.
Sincerely, L. William Pearce Enclosure
Beaver Valley Power Station, Unit No. 2 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R1 1 L-05-093 Page 2 c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator
FirstEnergy Nuclear Operating Company (FENOC)
Evaluation Report for 2R1 I Beaver Valley Unit 2 Pressurizer Penetration Inspections (Ref: NRC Bulletin 2004-01)
April 2005
Enclosure to Letter L-05-093 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R1 1 Introduction NRC Bulletin 2004-01 was issued on May 28, 2004, advising PWR licensees that current methods of inspecting Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections may need to be supplemented with additional measures to detect and adequately characterize flaws due to primary water stress corrosion cracking (PWSCC). The Bulletin also requested that licensees provide information related to the materials of fabrication of these locations, as well as the scope, method, and frequency of past and future inspections of these locations to ensure that degradation of Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections will be identified, adequately characterized, and repaired. FENOC responded to Bulletin 2004-01 for BVPS via letter L-04-081, dated July 27, 2004.
The BVPS Unit 2 commitment to Bulletin 2004-01 for the 2R1 1 refueling outage is as follows:
A 100% bare metal visual inspection of the five (5) Alloy 82/182 nozzle-to-safe-end welds associated with the pressurizer spray (1), relief (1), and safety (3) nozzles. (
Reference:
L-04-081, dated July 27, 2004).
These nozzles represent the only BVPS Unit 2 Alloy 600/82/182 locations in the pressurizer penetrations and steam space piping connections within the scope of Bulletin 2004-01.
In addition, FENOC provided a supplemental response to Bulletin 2004-01 for BVPS via letter L-04-128, dated September 29, 2004, which stated:
...if circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of the Bulletin, FENOC will enter the issue into the BVPS Corrective Action Program, develop plans to perform an adequate extent-of-condition evaluation, and will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.
The BVPS 2R1 1 bare metal visual inspections of these Alloy 82/182 weld locations were planned prior to this Bulletin commitment in response to the "Needed" recommendation identified in Materials Reliability Program (MRP) 2004-05, dated April 2, 2004, and as part of the BVPS Alloy 600/690 Management Program.
Pressurizer Nozzle Configuration The five BVPS Unit 2 Alloy 82/182 pressurizer nozzle-to-safe-end welds are configured as shown in the Figure below. The safety (3) and relief (1) nozzle are 6" nozzles. The spray (1) nozzle is a 4" nozzle. All nozzle-to-safe-end welds are full penetration butt welds.
Page 1 of 2
Enclosure to Letter L-05-093 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R1 1
\ ;zV11, =Visually Inspected Surface (360')
PZR CS Nozzle Alloy Alloy 316 SS SS 316 SS (wI 309L SS Clad) 82/182 821182 Safe-End Weld Pipe Butter Weld Figure: BVPS Unit 2 PZR Nozzle Configuration Inspections Performed In order to facilitate the visual inspections of the five pressurizer nozzles, insulation was removed around each nozzle. Bare metal visual inspections were performed 3600 around each nozzle, covering 100% of the outside diameter surface from the carbon steel nozzle base material out to the stainless steel pipe, including the Alloy 82/182 buttering and weld. The inspections were documented on still images and visual inspection logs. All examinations were performed by FENOC VT-2 qualified personnel, and approved by the FENOC Level IlIl visual examiner.
Inspection Results The bare metal visual inspections conducted on the five Alloy 82/182 pressurizer steam space nozzles during 2R11 identified no indications of RCS leakage or nozzle weld cracking.
Inspection results were documented via still images and visual inspection reports.
Conclusion The five (5) Alloy 82/182 nozzle-to-safe-end welds associated with the pressurizer spray (1),
relief (1), and safety (3) nozzles are the only BVPS Unit 2 components within the scope of NRC Bulletin 2004-01. Bare metal visual inspections were completed during 2R1 I in accordance with BVPS commitments identified in FENOC Bulletin response L-04-081. The visual inspections identified no indications of leakage from any of the five pressurizer nozzles. As such, the action addressed in BVPS supplemental Bulletin response L-04-128 did not apply during 2R11. Future inspections will be performed in accordance with the frequencies and methods previously identified in BVPS commitments to Bulletin 2004-01.
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Text
Y-ENOC 1""
Beaver Valley Power Station PO. Box 4 FirstEnergy Nuclear Operating Company Shippingport, PA 15077-0004 L. Wlliam Pearce 724-682-5234 Vice President Fax: 724-643-8069 May 19, 2005 4 L-05-093 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station (BVPS), Unit No. 2 BV-2 Docket No. 50-412, License No. NFP-73 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R11
References:
- 1. NRC Bulletin 2004-01: "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors," dated May 28, 2004.
- 2. FirstEnergy Nuclear Operating Company (FENOC) 60-Day Response to NRC Bulletin 2004-01 for BVPS (Letter L-04-081 dated July 27, 2004).
- 3. FENOC Supplemental Response to NRC Bulletin 2004-01 for BVPS (Letter L-04-128 dated September 29, 2004).
During the recent BVPS Unit 2 2R1 1 Refueling Outage, a visual inspection of Alloy 82/182/600 material locations in the pressurizer penetrations and steam space piping, within the scope of NRC Bulletin 2004-01 (Reference 1), was performed. This inspection was conducted per the FENOC response for BVPS (References 2 and 3) to the Bulletin. In accordance with the Bulletin, a 60-day report, detailing the inspection results, is being provided. The BVPS Unit 2 Evaluation Report for 2R1 1 Pressurizer Penetration Inspections is enclosed with this letter.
There are no new regulatory commitments contained in this letter. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-4284.
Sincerely, L. William Pearce Enclosure
Beaver Valley Power Station, Unit No. 2 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R1 1 L-05-093 Page 2 c: Mr. T. G. Colburn, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator
FirstEnergy Nuclear Operating Company (FENOC)
Evaluation Report for 2R1 I Beaver Valley Unit 2 Pressurizer Penetration Inspections (Ref: NRC Bulletin 2004-01)
April 2005
Enclosure to Letter L-05-093 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R1 1 Introduction NRC Bulletin 2004-01 was issued on May 28, 2004, advising PWR licensees that current methods of inspecting Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections may need to be supplemented with additional measures to detect and adequately characterize flaws due to primary water stress corrosion cracking (PWSCC). The Bulletin also requested that licensees provide information related to the materials of fabrication of these locations, as well as the scope, method, and frequency of past and future inspections of these locations to ensure that degradation of Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections will be identified, adequately characterized, and repaired. FENOC responded to Bulletin 2004-01 for BVPS via letter L-04-081, dated July 27, 2004.
The BVPS Unit 2 commitment to Bulletin 2004-01 for the 2R1 1 refueling outage is as follows:
A 100% bare metal visual inspection of the five (5) Alloy 82/182 nozzle-to-safe-end welds associated with the pressurizer spray (1), relief (1), and safety (3) nozzles. (
Reference:
L-04-081, dated July 27, 2004).
These nozzles represent the only BVPS Unit 2 Alloy 600/82/182 locations in the pressurizer penetrations and steam space piping connections within the scope of Bulletin 2004-01.
In addition, FENOC provided a supplemental response to Bulletin 2004-01 for BVPS via letter L-04-128, dated September 29, 2004, which stated:
...if circumferential cracking is observed in either the pressure boundary or non-pressure boundary portions of any locations covered under the scope of the Bulletin, FENOC will enter the issue into the BVPS Corrective Action Program, develop plans to perform an adequate extent-of-condition evaluation, and will discuss those plans with cognizant NRC technical staff prior to restarting the affected unit.
The BVPS 2R1 1 bare metal visual inspections of these Alloy 82/182 weld locations were planned prior to this Bulletin commitment in response to the "Needed" recommendation identified in Materials Reliability Program (MRP) 2004-05, dated April 2, 2004, and as part of the BVPS Alloy 600/690 Management Program.
Pressurizer Nozzle Configuration The five BVPS Unit 2 Alloy 82/182 pressurizer nozzle-to-safe-end welds are configured as shown in the Figure below. The safety (3) and relief (1) nozzle are 6" nozzles. The spray (1) nozzle is a 4" nozzle. All nozzle-to-safe-end welds are full penetration butt welds.
Page 1 of 2
Enclosure to Letter L-05-093 NRC Bulletin 2004-01 Inspection 60-Day Report for 2R1 1
\ ;zV11, =Visually Inspected Surface (360')
PZR CS Nozzle Alloy Alloy 316 SS SS 316 SS (wI 309L SS Clad) 82/182 821182 Safe-End Weld Pipe Butter Weld Figure: BVPS Unit 2 PZR Nozzle Configuration Inspections Performed In order to facilitate the visual inspections of the five pressurizer nozzles, insulation was removed around each nozzle. Bare metal visual inspections were performed 3600 around each nozzle, covering 100% of the outside diameter surface from the carbon steel nozzle base material out to the stainless steel pipe, including the Alloy 82/182 buttering and weld. The inspections were documented on still images and visual inspection logs. All examinations were performed by FENOC VT-2 qualified personnel, and approved by the FENOC Level IlIl visual examiner.
Inspection Results The bare metal visual inspections conducted on the five Alloy 82/182 pressurizer steam space nozzles during 2R11 identified no indications of RCS leakage or nozzle weld cracking.
Inspection results were documented via still images and visual inspection reports.
Conclusion The five (5) Alloy 82/182 nozzle-to-safe-end welds associated with the pressurizer spray (1),
relief (1), and safety (3) nozzles are the only BVPS Unit 2 components within the scope of NRC Bulletin 2004-01. Bare metal visual inspections were completed during 2R1 I in accordance with BVPS commitments identified in FENOC Bulletin response L-04-081. The visual inspections identified no indications of leakage from any of the five pressurizer nozzles. As such, the action addressed in BVPS supplemental Bulletin response L-04-128 did not apply during 2R11. Future inspections will be performed in accordance with the frequencies and methods previously identified in BVPS commitments to Bulletin 2004-01.
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