Letter Sequence Response to RAI |
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MONTHYEARML16301A1322016-10-27027 October 2016 NRR E-mail Capture - Beaver Valley Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Request for Licensing Action to Revise the Emergency Plan (CAC Nos. MF8448 & MF8449) Project stage: Acceptance Review ML17093A7622017-04-10010 April 2017 Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request Project stage: RAI L-17-104, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan2017-05-20020 May 2017 Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan Project stage: Response to RAI ML17222A2192017-08-10010 August 2017 E-mail Comments from Pennsylvania State Environmental Protection Regarding Emergency Plan Emergency Action Level Scheme to Adopt the NEI-99-01 Eals, Revision 6, for Beaver Valley Power Station, Units 1 and 2 Project stage: Other L-17-275, Supplement to Request for Licensing Action to Revise the Emergency Plan2017-09-0707 September 2017 Supplement to Request for Licensing Action to Revise the Emergency Plan Project stage: Supplement ML17256A2502017-09-13013 September 2017 NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6, Project stage: RAI L-17-296, Response to Request for Additional Information Re Request to Revise the Emergency Plan2017-09-20020 September 2017 Response to Request for Additional Information Re Request to Revise the Emergency Plan Project stage: Response to RAI ML17270A1902017-09-27027 September 2017 E-mail Regarding Beaver Valley Power Station, Units 1 and 2 - Issuance of Amendments Emergency Action Level Scheme Change Based on NEI 99-01, Revision 6 Project stage: Other ML17216A5702017-10-12012 October 2017 Issuance of Amendments Emergency Action Level Scheme Changed Based on NEI 99-01, Revision 6 (CAC Nos. MF8448 and MF8449; EPID L-2016-LLA-0011) Project stage: Approval ML17317A0052017-11-0303 November 2017 NRR E-mail Capture - (External_Sender) Beaver Valley Emergency Action Level License Amendment Safety Evaluation Project stage: Other ML17345A8782017-11-13013 November 2017 NRR E-mail Capture - (External_Sender) FW: Beaver Valley Emergency Action Level License Amendment Safety Evaluation Project stage: Other ML18016A1032018-01-19019 January 2018 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 300 and 189 (CAC Nos. MF8448 and MF8449; EPID L-2016-LLA-0011 and EPID L-2017-LRO-0069) Project stage: Approval 2017-05-20
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Category:Emergency Preparedness-Emergency Plan
MONTHYEARL-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-18-213, Emergency Preparedness Plan2018-09-24024 September 2018 Emergency Preparedness Plan L-18-086, Submittal of Emergency Preparedness Plan2018-03-15015 March 2018 Submittal of Emergency Preparedness Plan L-17-296, Response to Request for Additional Information Re Request to Revise the Emergency Plan2017-09-20020 September 2017 Response to Request for Additional Information Re Request to Revise the Emergency Plan L-17-104, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan2017-05-20020 May 2017 Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan ML16277A1132016-09-28028 September 2016 Beaver Valley Power Station, Unit Nos. 1 and 2, Request for Licensing Action to Revise the Emergency Plan L-16-259, Emergency Preparedness Plan2016-08-16016 August 2016 Emergency Preparedness Plan L-14-280, License Amendment Request to Modify Emergency Preparedness Plan Regarding the Emergency Planning Zone Boundary2014-09-0404 September 2014 License Amendment Request to Modify Emergency Preparedness Plan Regarding the Emergency Planning Zone Boundary L-12-326, Response to a Request for Additional Information on a Proposed Emergency Preparedness Plan Revision2012-09-28028 September 2012 Response to a Request for Additional Information on a Proposed Emergency Preparedness Plan Revision ML0823804372008-08-18018 August 2008 Emergency Preparedness Plan, Consisting of Rev. 26 to Section 4, Emergency Conditions. L-08-023, Revised Emergency Preparedness Plan - Appendix a, Letters of Agreement, Revision 152008-01-11011 January 2008 Revised Emergency Preparedness Plan - Appendix a, Letters of Agreement, Revision 15 L-07-124, Submittal of Revisions to Emergency Response Data System2007-09-12012 September 2007 Submittal of Revisions to Emergency Response Data System L-04-122, A5.735A, Rev 27, Emergency Preparedness Plan.2004-09-23023 September 2004 A5.735A, Rev 27, Emergency Preparedness Plan. ML0407104742004-03-0202 March 2004 Emergency Preparedness Plan 2022-09-07
[Table view] Category:Letter type:L
MONTHYEARL-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-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023 Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H 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 L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022 Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022 Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022 Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022 Request for Fire Protection Program Changes L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022 License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022 Spent Fuel Storage Cask Registration 2023-09-14
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-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-23-139, 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-23-129, 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-23-086, 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-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage ML22094A1152022-04-0404 April 2022 Response to a Request for Additional Information Regarding a Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation (EPID No. L-202 L-22-079, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-16016 March 2022 Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations ML21147A1462021-05-27027 May 2021 Response to Request for Additional Information Regarding Generic Letter 2004-02 ML21132A2422021-05-12012 May 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-21-106, Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits2021-04-22022 April 2021 Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits ML21055A8862021-02-24024 February 2021 Response to Request for Additional Information Regarding Steam Generator Inspection 180-Day Report ML21048A0822021-02-16016 February 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-21-030, Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-20202021-01-27027 January 2021 Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-2020 L-20-277, Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request2021-01-22022 January 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-20-293, Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.162020-11-30030 November 2020 Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16 L-20-162, Supplemental Response to NRC Generic Letter 2004-022020-11-30030 November 2020 Supplemental Response to NRC Generic Letter 2004-02 L-20-276, Response to Request for Additional Information Regarding Steam Generator Inspection Report2020-10-30030 October 2020 Response to Request for Additional Information Regarding Steam Generator Inspection Report L-20-161, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .2020-06-0909 June 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter . L-20-155, Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040)2020-05-0606 May 2020 Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040) L-20-097, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,.2020-04-14014 April 2020 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,. L-20-125, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SRR-1, Rev. 0, Snubber Testing2020-04-0303 April 2020 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SRR-1, Rev. 0, Snubber Testing L-19-182, Response to RAI Regarding an Application for Order Consenting to Transfer of License2019-08-0202 August 2019 Response to RAI Regarding an Application for Order Consenting to Transfer of License L-18-209, Response to Request for Additional Information Regarding Steam Generator Technical Specification License Amendment Request2018-10-28028 October 2018 Response to Request for Additional Information Regarding Steam Generator Technical Specification License Amendment Request L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-25025 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 ML18099A1232018-04-0606 April 2018 Response to Request for Additional Information Regarding Request to Modify Rtpts Values L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement L-17-375, Response to Request for Additional Information Regarding Request 1-TYP-4-BA-01 to Extend the Inservice Inspection Interval for Certain Reactor Vessel Welds2018-01-0505 January 2018 Response to Request for Additional Information Regarding Request 1-TYP-4-BA-01 to Extend the Inservice Inspection Interval for Certain Reactor Vessel Welds L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)2017-12-23023 December 2017 Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088) L-17-296, Response to Request for Additional Information Re Request to Revise the Emergency Plan2017-09-20020 September 2017 Response to Request for Additional Information Re Request to Revise the Emergency Plan L-17-197, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052017-06-23023 June 2017 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-17-104, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan2017-05-20020 May 2017 Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan 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-17-053, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Numbers PR6 and PR72017-02-22022 February 2017 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Numbers PR6 and PR7 L-17-024, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052017-01-30030 January 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-16-299, Response to Generic Letter 2016-01. Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-10-31031 October 2016 Response to Generic Letter 2016-01. Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-16-212, Response to Request for Additional Information Regarding 2015 Steam Generator Inspection Reports2016-07-14014 July 2016 Response to Request for Additional Information Regarding 2015 Steam Generator Inspection Reports L-16-162, Response to Requests for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, and Request to Change Implementation Schedule2016-05-12012 May 2016 Response to Requests for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, and Request to Change Implementation Schedule L-16-085, Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications.2016-03-22022 March 2016 Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications. ML16063A2882016-03-0202 March 2016 Response to NRC Request for Additional Information, Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident L-16-058, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052016-02-24024 February 2016 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-15-371, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-12-21021 December 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-15-303, Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program2015-11-0606 November 2015 Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program L-15-325, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-11-0606 November 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 L-15-261, Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program2015-08-26026 August 2015 Response to Request for Additional Information Regarding Submittal of Reactor Vessel Internals Aging Management Program L-15-202, Response to Request for Additional Information on Expedited Seismic Evaluation Process (ESEP) Reports and Seismic Hazard and Screening Reports Submitted, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term..2015-06-29029 June 2015 Response to Request for Additional Information on Expedited Seismic Evaluation Process (ESEP) Reports and Seismic Hazard and Screening Reports Submitted, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term.. L-15-188, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-06-26026 June 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 2023-06-13
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FENOC," Beaver Valley Power Slafion P.O. Box 4 F irstEnergy Nuclear Operating Company Shippingport, PA 15077 Richard D. Bologna 724-682-5234 Sife Vice President Fax: 724-643-8069 September 20, 2017 L-17-296 10 CFR 50, Appendix E ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50412, License No. NPF-73 Response to Request for Add itional lnformation Reqardino a Reouest to Revise the Emeroencv Plan (CAC Nos. MF84$8 AND MFB449)
By correspondence dated September 28, 2016 (Accession No. ML162774194), as supplemented by correspondence dated May 10, 2017 (Accession No. ML171444484) and September 7,2017 (Accession No. ML172508169) FirstEnergy Nuclear Operating Company (FENOC) submitted a request to revise the current Beaver Valley Power Station Unit Nos. 1 and 2 (BVPS) Emergency Plan emergency action level scheme to one based on Nuclear Energy Institute (NEl) 99-01, "Development of EmergencyAction Levels for Non-Passive Reactors," Revision 6.
By correspondence dated September 13,2017 the Nuclear Regulatory Commission (NRC) requested additional information to complete its review. FENOC's response is attached. As a result, the EmergencyAction Level (EAL) Bases Document has been revised, and the revised pages are enclosed.
The information contained in this supplement does not impact the conclusions of the significant hazards consideration determination or environmental considerations of the original request provided in Enclosure A of FENOC letter dated September 28, 2016 (Accession No. ML1 6277 A1g4l.
Beaver Valley Power Station, Unit Nos. 1 and 2 L-17-296 Page 2 There are no regulatory commitments contained in this submittal. lf there are any questions or additional information is required, please contact Mr, Thomas A Lentz, Manager - Fleet Licensing, at (330) 315-6810.
I declare undpr penalty of perjury that the foregoing is true and correct. Executed on Septemb*, J O, 2o1i.
Sincerely, Richard D. Bologna
Attachment:
Response to September 13, 2017 Request for Additional lnformation Enclosu re:
Emergency Action Level Technical Bases Document - HG1 Only cc NRC Region I Administrator NRC Resident lnspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
ATTACHMENT L-17-296 Response to September 13, 2017 Request for Additional Information Page 1 of 1 By application dated September 28, 2016 (Accession No. ML16277A194), as supplemented by letters dated May 20, 2017 (Accession No. ML17144A484) and September 7, 2017 (Accession No. ML17250B169), First Energy Nuclear Operating Company (the licensee) requested approval of changes to revise the emergency action level (EAL) scheme for the Beaver Valley Power Station, Unit Nos. 1 and 2, to one based on the Nuclear Energy Institute (NEI) document NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, dated November 21, 2012 (Accession No. ML12326A805). By correspondence dated September 13, 2017, NRC staff requested additional information to complete its review.
The requested information is presented below in bold type, followed by the FENOC response.
EAL HG1.1 Basis: RAI-BVPS-33
- 1. The clarification to the threshold value of Damage to spent fuel has occurred or is IMMINENT (as determined by lowering of spent fuel pool (SFP) level reading less than or equal to 0.5 feet or cannot be monitored for two hours or longer) is not part of the EAL. This could cause inconsistencies in the application of the EAL. Please include it as part of the EAL or as a note, included in the wallboard.
Response
EAL HG1.1 (Unit 1) was revised to include the following note, Note 18: IMMINENT damage to the spent fuel can be determined by spent fuel pool level (Ll-1FC-200A/B) reading 0.5ft. (Level 3).
EAL HG1.1 (Unit 2) was revised to include the following note, Note 19: IMMINENT damage to the spent fuel can be determined by spent fuel pool level (2FNC-Ll101 A/B) reading 0.5ft. (Level 3).
- 2. Please provide a justification for including an inability to monitor the SFP for two hours. As proposed, a loss of SFP level indication without indications of a loss of SFP integrity does not justify a General Emergency classification.
Response
The statement or cannot be monitored for two hours or longer has been deleted from the EAL HG1.1 (Unit 1 and Unit 2) basis section.
Enclosure L-17-296 Emergency Action Level Technical Bases Document - HG1 Only (4 pages follow)
Section 4 Emergency Preparedness Plan EMERGENCY ACTION LEVEL Bases ATTACHMENT 1:
Unit 1 EAL Technical Bases Category: H - Hazards and Other Conditions Affecting Plant Safety HG1.1 Subcategory: 1 - Security Initiating Condition: HOSTILE ACTION resulting in loss of physical control of the facility.
EAL:
HG1.1 General Emergency A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the Security Shift Supervisor AND EITHER of the following has occurred:
- 1. ANY of the following safety functions cannot be controlled or maintained.
Reactivity Control (ability to shut down the reactor and keep it shut down)
Core Cooling RCS heat removal OR
- 2. Damage to spent fuel has occurred or is IMMINENT (Note 18)
Note 18: IMMINENT damage to the spent fuel can be determined by spent fuel pool level (Ll-1FC-200A/B) reading 0.5ft. (Level 3).
Mode Applicability:
All Basis:
This IC addresses an event in which a HOSTILE FORCE has taken physical control of the facility to the extent that the plant staff can no longer operate equipment necessary to maintain key safety functions. It also addresses a HOSTILE ACTION leading to a loss of physical control that results in actual or IMMINENT damage to spent fuel due to 1) damage to a spent fuel pool cooling system (e.g. pumps, heat exchangers, controls, etc.) or, 2) loss of spent fuel pool integrity such that sufficient water level cannot be maintained as determined by spent fuel pool level (LI-1FC-200A/B) reading 0.5 ft. (Level 3).
Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.
4 - 111
Section 4 Emergency Preparedness Plan EMERGENCY ACTION LEVEL Bases ATTACHMENT 1:
Unit 1 EAL Technical Bases No Changes - Information Only HG1.1 Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].
Emergency plans and implementing procedures are public documents; therefore, EALs should not incorporate Security-sensitive information. This includes information that may be advantageous to a potential adversary, such as the particulars concerning a specific threat or threat location. Security-sensitive information should be contained in non-public documents such as the BVPS Physical Security/Contingency Plan (ref 1).
Basis Reference(s):
- 1. BVPS Physical Security Plan/Contingency Plan (Safeguards)
- 2. NEI 99-01 Rev. 6 HG1
- 3. NEI 99-01 Rev. 6 AS2
- 4. ECP No. 13-0561-000, Reference Documents for ECP-13-0561 - Installation of Spent Fuel Pool Level Instrumentation for Beyond Design Basis External Events 4 - 112
Section 4 Emergency Preparedness Plan EMERGENCY ACTION LEVEL Bases ATTACHMENT 3:
Unit 2 EAL Technical Bases Category: H - Hazards HG1.1 Subcategory: 1 - Security Initiating Condition: HOSTILE ACTION resulting in loss of physical control of the facility.
EAL:
HG1.1 General Emergency A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the Security Shift Supervisor .
AND EITHER of the following has occured:
- 1. ANY of the following safety functions cannot be controlled or maintained.
Reactivity control (ability to shut down the reactor and keep it shut down)
Core cooling RCS heat removal OR
- 2. Damage to the spent fuel has occurred or is IMMINENT (Note 19)
Note 19: IMMINENT damage to the spent fuel can be determined by spent fuel pool level (2FNC-Ll101 A/B) reading 0.5ft. (Level 3).
Mode Applicability:
All Basis:
This IC addresses an event in which a HOSTILE FORCE has taken physical control of the facility to the extent that the plant staff can no longer operate equipment necessary to maintain key safety functions. It also addresses a HOSTILE ACTION leading to a loss of physical control that results in actual or IMMINENT damage to spent fuel due to 1) damage to a spent fuel pool cooling system (e.g., pumps, heat exchangers, controls. etc.) or, 2) loss of spent fuel pool integrity such that sufficient water level can not be maintained as determined by spent fuel pool level (2FNC-Ll101A/B) reading 0.5 ft. (Level 3).
Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.
4 - 331
Section 4 Emergency Preparedness Plan EMERGENCY ACTION LEVEL Bases ATTACHMENT 3:
Unit 2 EAL Technical Bases No Changes - Information Only HG1.1 Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].
Emergency plans and implementing procedures are public documents; therefore, EALs should not incorporate Security-sensitive information. This includes information that may be advantageous to a potential adversary, such as the particulars concerning a specific threat or threat location. Security-sensitive information should be contained in non-public documents such as the BVPS Physical Security/Contingency Plan (ref. 1).
Basis Reference(s):
- 1. BVPS Physical Security Plan/Contingency Plan (Safeguards)
- 2. NEI 99-01 Rev. 6 HG1
- 3. NEI 99-01 Rev. 6 AS2
- 4. ECP No. 13-0561-000, Reference Documents for ECP-13-0561 - Installation of Spent Fuel Pool Level Instrumentation for Beyond Design Basis External Events 4 - 332