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Category:Letter
MONTHYEARIR 05000334/20244032024-11-13013 November 2024 Cybersecurity Problem Identification and Resolution Inspection Report 05000334/2024403 and 05000412/2024403 (Cover Letter Only) IR 05000334/20240032024-11-13013 November 2024 Integrated Inspection Report 05000334/2024003 & 05000412/2024003 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 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 ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) 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 IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 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 05000334/LER-2024-004, 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 ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, 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 IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) 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 05000334/LER-2024-002, 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 05000334/LER-2024-001, 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 ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports 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 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 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 IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 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 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report 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 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions 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 2024-09-26
[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
[Table view] |
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FENOC ........ FirstEnergy Nuclear Operating Company Paul A. Harden Site Vice President June 9, 2011 L-11-148 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No.2 Docket No. 50-412, License No. NPF-73 Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Steam Generator Tube Inspection Report -Technical Specification 5.6.6.2.4 In accordance with Technical Specification 5.6.6.2.4, FirstEnergy Nuclear Operating Company hereby submits a report containing tube inspection results for Beaver Valley Power Station, Unit No.2, steam generators.
The enclosed report provides information required by the technical specification that was obtained during inspections conducted during the spring 2011 refueling outage. There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Fleet Licensing, at (330) 761-6071.
Paul A. Harden
Enclosure:
Unit #2 -2R15 Steam Generator F* (F Star) Report cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative FIRST ENERGY NUCLEAR OPERATING COMPANY Technical Services Engineering Department Nuclear Engineering ProgramsSection Issue Date: May 13, 2011
Subject:
Unit #2" 2R15 Steam Generator F* (F Star) Report Prepared by:
__ SG Program Owner, Date: 0 s I , 3/ II Reviewed by: Jeff <<3 --' Date:
Approved by: Doug Reeves o<J..--t.-
==-Date: S-/I?:> / 1/ Manager, Technical Services UNIT #2 -2R15 STEAM GENERATOR F* (F STAR) REPORT Pursuant to Specification 5.6.6.2.4 of the Technical Specifications, the following information is to be transmitted to the NRC within 90 days after entering MODE 4 following an outage in which the F* (F Star) methodology was implemented.
For 2R 15, MODE 4 occurred on April 7th, 2011. Therefore, this information must be submitted to the NRC on or before July 6, 2011. Per Specification 5.6.6.2.4, the following information is to be submitted and is discussed within this document: (a) The total number of indications, the location of each indication, the orientation of each indication, the severity of each indication and whether the indications initiated from the inside or outside surface, (b) The cumulative number of indications detected in the tubesheet region as a function of elevation within the tubesheet, (c) The projected end-of-cycle accident induced leakage from tubesheet indications.
During the 2R 15 outage, the Plus Point probe was utilized to inspect the top of tubesheet region. The 2R 15 inspection scope was 100% of the inservice hot leg tubes in all three steam generators (SG's) plus a 20% random sample of the inservice cold leg tubes in SG "A". The inspection distance in either leg was from 6.0 inches above the top of tubesheet to 3.0 inches below the top of tubesheet and bounds the required F* examination distance (Le. the expanded portion of the tube below the bottom of roll expansion transition) of 2.22 inches below the bottom of the expansion transition.
A small number of tubes (10 total in the hot leg of all 3 SG's and 4 in SG "A" cold leg) have roll expansion transitions at lower than nominal elevations.
These particular tubes were inspected to a depth of 5.0 inches below the top of tubesheet to ensure that the F* distance was adequately examined.
As seen from the information contained within, the morphology for the vast majority of the indications reported from the hot leg tubesheet region is believed to be attributed to circumferentially oriented outside diameter stress corrosion cracking (ODSCC). This is based on signal recognition and location of the reported indications.
All ODSCC indications observed were plugged upon detection.
All top of tubesheet circumferential indications were stabilized prior to installing the hot leg plug. None of the indications that were removed from service during 2R15 represented a (Cycle 15) leakage potential at postulated main steam line break (MSLB) conditions.
The information provided on the following pages summarizes the degradation observed during the 2R15 tubesheet region examinations.
The data has been analyzed utilizing the 300 kHz channel from the Plus Point probe. This provides the most accurate sizing technique and is used for assessing the severity of the indications.
Page 2 of7 SG "A" Hot Leg Tubesheet:
Twenty tubes were plugged for indications reported during the hot leg tubesheet region examination.
Of these tubes; nineteen tubes were reported with either single or multiple circumferential OOSCC indications located at or slightly below the top of tubesheet and one tube was reported with single axial OOSCC indication located above the top of tubesheet.
SG "A" Cold Leg Tubesheet:
No indications were reported during the 20% random sample inspection of the cold leg tubesheet region. 2RCS-SG21A 2R15 Tubesheet Indications Indication Location Orientation**
SG Row Column Elevation* A 6 50 TSH -0.12" A 8 38 TSH -0.03" A 8 57 TSH -0.09" A 9 23 TSH -0.08" A 11 38 TSH -0.14" A 12 37 TSH -0.15" A 12 41 TSH -0.09" A 12 42 TSH +0.00" A 13 44 TSH -0.07" A 19 55 TSH -0.20" A 20 21 TSH -0.13" A 25 33 TSH -0.08" A 27 72 TSH -0.05" A 33 33 TSH -0.06" A 38 49 TSH +0.49" A 40 43 TSH -0.05" A 41 49 TSH -0.10" A 42 42 TSH -0.07" A 42 45 TSH -0.01" A 43 47 TSH -0.01"
- TSH -Top of Tubesheet (Hot Leg) ** MCI -Multiple Circumferential Indications SAl -Single Axial Indication SCI -Single Circumferential Indication
- Reported Using the 300 kHz Plus Point Coil Volts SCI 0.12 SCI 0.18 SCI 0.16 SCI 0.21 SCI 0.13 SCI 0.20 SCI 0.13 SCI 0.17 SCI 0.19 MCI 0.13 SCI 0.14 SCI 0.24 SCI 0.20 MCI 0.17 SAl 0.12 MCI 0.27 SCI 0.16 SCI 0.17 SCI 0.07 SCI 0.08 Page 3 of7 Severity***
Axial Length 0.17" Initiation Arc Surfacel Projected Length Degradation Leakage 65 u OOSCC 0 110 u OOSCC 0 123 0 OOSCC 0 132 0 OOSCC 0 33 u OOSCC 0 59 u OOSCC 0 82 u OOSCC 0 69 u OOSCC 0 69 0 OOSCC 0 190 u OOSCC 0 98 u OOSCC 0 91 u OOSCC 0 155 0 OOSCC 0 130 u OOSCC 0 OOSCC 0 229 u OOSCC 0 50 u OOSCC 0 106 u OOSCC 0 107 0 OOSCC 0 34 u OOSCC 0 SG "8" Hot Leg Tubesheet:
Twenty four tubes were plugged for indications reported during the hot leg tubesheet region examination.
Of these tubes; twenty one tubes were reported with either single or multiple circumferential ODSeC indications located at or slightly below the top of tubesheet and three tubes were reported with single axial ODSee indications located above the top of tubesheet.
2RCS-SG21B 2R15 Tubesheet Indications Indication Location Orientation**
SG Row Column Elevation*
B 7 41 TSH+O.OO" B 8 32 TSH -0.01" B 8 54 TSH -0.04" B 9 54 TSH -0.12" B 11 19 TSH +0.00" B 11 46 TSH -0.08" B 11 47 TSH +0.00" B 12 57 TSH -0.12" B 15 53 TSH -0.06" B 16 32 TSH -0.12" B 17 9 TSH -0.08" B 17 24 TSH -0.08" B 17 38 TSH -0.10" B 18 49 TSH -0.10" B 20 33 TSH -0.09" B 21 24 TSH +0.04" B 21 25 TSH +0.01" B 21 44 TSH -0.11" B 22 14 TSH -0.09" B 25 26 TSH +0.14" B 32 51 TSH -0.09" B 32 56 TSH +0.00" B 37 51 TSH -0.11" B 38 56 TSH -0.09"
- TSH -Top of Tubesheet (Hot Leg) ** MCI -Multiple Circumferential Indications SAl -Single Axial Indication SCI -Single Circumferential Indication
- Reported Using the 300 kHz Plus Point Coil Volts SCI 0.19 SCI 0.10 MCI 0.29 SCI 0.18 SCI 0.12 SCI 0.19 MCI 0.21 SCI 0.20 SCI 0.19 SCI 0.14 SCI 0.16 SCI 0.11 SCI 0.24 SCI 0.28 SCI 0.15 SAl 0.31 SAl 0.15 SCI 0.13 SCI 0.10 SAl 0.10 MCI 0.10 SCI 0.12 SCI 0.08 SCI 0.13 Page 4 of7 Severity***
Axial Length 0.28" 0.16" 0.23" Initiation Arc Surfacel Projected Length Degradation Leakage 87 u OOSCC 0 47 u OOSCC 0 219 u OOSCC 0 75 u OOSCC 0 27 0 OOSCC 0 61 u OOSCC 0 161 u OOSCC 0 68 u OOSCC 0 44 u OOSCC 0 124 0 OOSCC 0 80u OOSCC 0 34 u OOSCC 0 75 u OOSCC 0 134 u OOSCC 0 27 u OOSCC 0 OOSCC 0 OOSCC 0 41 u OOSCC 0 59 u OOSCC 0 OOSCC 0 267 u OOSCC 0 58 u OOSCC 0 27 u OOSCC 0 70 u OOSCC 0 SG "C" Hot Leg Tubesheet:
Seven tubes were plugged for indications reported during the hot leg tubesheet region examination.
Of theses tubes; six tubes were reported with either single or multiple circumferential OOSCC indications located at or slightly below the top of tubesheet and one tube was reported with a single axial OOSCC indication located above the top of tubesheet.
2RCS-SG21C 2R15 Tubesheet Indications Indication Location Orientation**
SG Row Column Elevation1o C 3 46 TSH -0.17" C 8 57 TSH -0.06" C 8 58 TSH +0.12" C 9 92 TSH -0.16" C 11 53 TSH -0.03" C 20 57 TSH -0.07" C 35 61 TSH -0.09"
- TSH -Top of Tubesheet (Hot Leg) 1o1o MCI -Multiple Circumferential Indications SAI-Single Axial Indication SCI -Single Circumferential Indication
- 1o Reported Using the 300 kHz Plus Point Coil Volts SCI 0.09 SCI 0.20 SAl 0.20 SCI 0.08 SCI 0.18 SCI 0.06 MCI 0.19 Page 5 of7 Severity101o1o Axial Length 0.16" Initiation Arc Surfacel Projected Length Degradation Leakage 47 u OOSCC 0 155 u OOSCC 0 OOSCC 0 30 u OOSCC 0 36° OOSCC 0 33 u OOSCC 0 67 u OOSCC 0 Non Tubesheet Region Degradation:
The following information lists the tubes that were removed from service for degradation in other areas of the steam generators.
This information is being submitted for completeness of the tube plugging performed 2R15 and is not required to be reported by Technical Specification 5.6.6.2.4.
2RCS-SG21A Indication Location Severity *** Initiation Orientation**
Axial Arc Surfacel Projected SG Row Column Elevation*
Volts Length Length Degradation Leakage A 7 37 4H -0.10" SAl 0.16 0.26" OOSCC 0 A 8 25 2H -0.26" SAl 0.13 0.31" OOSCC 0 A 16 8 3H -0.04" SAl 0.11 0.23" OOSCC 0 A 16 9 2H +0.14" SAl 0.12 0.41" OOSCC 0 A 16 24 6H -0.05" SAl 0.16 0.31" OOSCC 0 2RCS-SG21B Indication Location Severity *** Initiation Orientation**
Axial Arc Surfacel Projected SG Row Column Elevation*
Volts Length Length Degradation Leakage B 1 33 3H +0.18" SAl 0.10 0.45" OOSCC 0 B 6 31 3H +0.09" SAl 0.10 0.45" OOSCC 0 B 6 35 3H -0.02" SAl 0.16 0.33" OOSCC 0 B 6 42 2H +0.16" MAl 0.16 0.40" OOSCC 0 B 8 35 6H +0.05" SAl 0.11 0.16" OOSCC 0 B 10 32 3H +0.01" SAl 0.10 0.32" OOSCC 0 B 11 55 2H +0.00" SAl 0.09 0.17" OOSCC 0 B 11 59 2H +0.10" SAl 0.09 0.37" OOSCC 0 B 11 60 3H +0.06" SAl 0.08 0.34" OOSCC 0 B 13 72 3H +0.04" SAl 0.08 0.28" OOSCC 0 B 14 55 2H +0.10" SAl 0.18 0.52" OOSCC 0 B 15 66 3H -0.04" SAl 0.07 0.16" OOSCC 0 B 16 12 4H +0.00" SAl 0.16 0.28" OOSCC 0 B 16 14 3H +0.01" SAl 0.34 0.28" OOSCC 0 B 17 34 6H +0.17" SAl 0.10 0.29" OOSCC 0 B 18 31 2H +0.06" SAl 0.12 0.16" OOSCC 0 B 18 67 3H +0.08" SAl 0.11 0.23" OOSCC 0 B 20 34 2H -0.14" SAl 0.13 0.61" OOSCC 0 B 29 57 2H +0.00" SAl 0.07 0.23" OOSCC 0 B 31 17 2H -0.18" SAl 1.15 0.20" PWSCC 0 Page 6 of7 2RCS-SG21C Indication Location Severity *** Initiation Orientation**
Axial Arc Surfacel Projected SG Row Column Elevation*
Volts Length Length Degradation Leakage C 3 55 8C +0.04" SAl 0.21 0.21" OOSCC 0 C 15 29 4H +0.00" SAl 0.31 0.21" OOSCC 0 C 15 29 6H +0.00" SAl 0.13 0.26" OOSCC 0 C 29 12 VARIOUS PVN See Below 0 C 30 74 4H -0.03" SAl 0.17 0.42" OOSCC 0 C 31 59 6H +41.53" SCI 0.37 26 u OOSCC 0 C 31 63 3H +0.12" SAl 0.11 0.17" OOSCC 0 C 31 63 4H +0.07" SAl 0.07 0.16" OOSCC 0
- 2H, 3H, 4H, 6H -2 nd , 3 m , 4th, 6 th Hot Leg Tube Support Plate (Flow distribution baffle is referred to as 1 H/1 C) 8C -8 th Cold Leg Tube Support Plate ** MAl -Multiple Axial Indications PVN -Permeability Variation SAI-Single Axial Indication SCI -Single Circumferential Indication
- Reported Using the 300 kHz Plus Point Coil R29 C12 -This tube exhibited permeability variations ranging from 0.16 volts to 11.58 volts between the 7 th hot leg tube support plate and the 4th cold leg tube support plate. The bobbin probe (200 kHz) was used to verify that no axial OOSCC was present at the tube support plate intersections.
The bobbin probe (100 kHz) was used to verify that no axial OOSCC was present in the free span regions. A magnetically biased Plus Point probe was used to verify that no circumferential OOSCC was present at free span dings which may have represented a structural or leakage potential.
A full length in-situ pressure test was subsequently performed on the tube. No leakage or burst was observed at any of the test pressures.
Post in-situ bobbin probe testing showed no detectable degradation at the tube support plate intersections or in the free span regions. The tube was stabilized on the hot leg side prior to removing it from service via plugging.
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