Letter Sequence Response to RAI |
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Results
Other: ML18130A760, ML18130A820, ML18130A849, ML18130A885, NRC-2018-0187, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment, NRC-2018-0192, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment, NRC-2018-0193, First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2
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MONTHYEARL-17-112, Exemption Request for Physical Barrier Requirement2017-07-19019 July 2017 Exemption Request for Physical Barrier Requirement Project stage: Request ML17262A7232017-09-20020 September 2017 FENOC Fleet - Results of Acceptance Review of the Exemption Request Exemption from the Definition of Physical Barrier in 10 CFR 73.2 for Physical Security Plans Project stage: Acceptance Review 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 Project stage: Response to RAI 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 Project stage: Request ML18130A8852018-08-29029 August 2018 FENOC Fleet - Beaver Valley; Davis-Besse; Perry - Environment Assessment and Finding of No Significant Impact Related to Exemption Request for a Physical Barrier Requirement (CAC Nos. MG0010, MG0011, MG0012, and MG0013; EPID L-2018-LLE-0019 Project stage: Other ML18130A8892018-08-29029 August 2018, 4 September 2018 Environmental Assessment and Finding of No Significant Impact Related to Exemption Request for a Physical Barrier Requirement Project stage: Request ML18130A7602018-09-0404 September 2018 First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2 Project stage: Other ML18130A8492018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment Project stage: Other ML18130A8202018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment Project stage: Other NRC-2018-0192, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment2018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation, LLC; Environmental Assessment Project stage: Other NRC-2018-0187, Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment2018-09-0404 September 2018 Firstenergy Nuclear Operating Company (Fenoc); Firstenergy Nuclear Generation Company, LLC - Environmental Assessment Project stage: Other NRC-2018-0193, First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 22018-09-0404 September 2018 First Energy Operating Company (FENOC) Firstenergy Nuclear Generation, LLC, Beaver Valley Power Station, Units 1 and 2 Project stage: Other 2018-03-16
[Table View] |
Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier RequirementML18078A033 |
Person / Time |
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Site: |
Beaver Valley, Davis Besse, Perry |
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Issue date: |
03/16/2018 |
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From: |
Moul D FirstEnergy Nuclear Operating Co |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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CAC 000976, CAC MG0010, CAC MG0012, CAC MG0013, EPID L-2017-LLE-0019, L-18-061 |
Download: ML18078A033 (8) |
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Category:Letter type:L
MONTHYEARL-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 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-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023 Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20 L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023 Submittal of the Updated Safety Analysis Report, Revision 23 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-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan 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-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023 Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD 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-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative 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-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023 Plan, Nineteenth Inservice Inspection Summary Report L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models 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-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations 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-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations 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-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection 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-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 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-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023 Annual Radiological Effluent Release Report L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Radiological Environmental Operating Report 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-23-049, Core Operating Limits Report for Operating Cycle 202023-03-30030 March 2023 Core Operating Limits Report for Operating Cycle 20 L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report 2024-01-24
[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-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report 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 ML22292A0232022-10-18018 October 2022 Framatome Inc., Document ANP-2718-007Q1NP, Revision 0, Response to Request for Additional Information on Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station - First Energy Nuclear Operating Company L-22-229, Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit2022-10-13013 October 2022 Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit 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-22-171, Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-0632022-07-14014 July 2022 Response to Request for Additional Information Regarding Proposed Inservice Inspection Alternative IR-063 L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building L-22-110, Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement2022-04-28028 April 2022 Response to Request for Additional Information Re 10CFR50.55a Request Number VR-12, Revision 0, Request for Relief from Containment Isolation Valve ASME OM Code Requirement 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-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022 Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3 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 ML22081A1472022-03-11011 March 2022 R22 (March 2022) - Steam Generator Tube Inspection Discussion Points 11 March 2022 ML22049A0662022-02-10010 February 2022 Response to NRC Questions from 2/1/2022 Regulatory Conference on Failed Field Flash Selector Switch L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022 Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 ML21147A1462021-05-27027 May 2021 Response to Request for Additional Information Regarding Generic Letter 2004-02 L-21-123, Response to Request for Additional Information Regarding a License Amendment Request That Revises2021-05-18018 May 2021 Response to Request for Additional Information Regarding a License Amendment Request That Revises ML21132A2422021-05-12012 May 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request ML21130A2192021-05-10010 May 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083) 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 ML21088A3442021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 L-21-101, Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-022021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 ML21055A8862021-02-24024 February 2021 Response to Request for Additional Information Regarding Steam Generator Inspection 180-Day Report L-21-080, Response to Requests for Additional Information Re 10 CFR 50.55a Request Numbers VR-3. VR-4. VR-5, VR-61 and VR-7 (EPID Numbers L-2021-LLR-0007, L-2021-LLR-0008, L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011)2021-02-22022 February 2021 Response to Requests for Additional Information Re 10 CFR 50.55a Request Numbers VR-3. VR-4. VR-5, VR-61 and VR-7 (EPID Numbers L-2021-LLR-0007, L-2021-LLR-0008, L-2021-LLR-0009, L-2021-LLR-0010, and L-2021-LLR-0011) L-21-077, Response to Request for Additional Information Re 10 CFR 50.55a Request Number SR-2 Revision 0 Snubber Testing Extension2021-02-19019 February 2021 Response to Request for Additional Information Re 10 CFR 50.55a Request Number SR-2 Revision 0 Snubber Testing Extension ML21048A0822021-02-16016 February 2021 Response to Request for Additional Information Regarding Steam Generator Tube Sleeve License Amendment Request L-21-060, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SR-2, Revision 0, Snubber Testing Extension2021-02-0808 February 2021 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number SR-2, Revision 0, Snubber Testing Extension 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-20-313, Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force2020-12-0707 December 2020 Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force 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-20-311, Response to Request for Additional Information Regarding Request for Exemption - Part 73 Force-on-Force2020-11-25025 November 2020 Response to Request for Additional Information Regarding Request for Exemption - Part 73 Force-on-Force L-20-291, Supplemental Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602020-11-19019 November 2020 Supplemental Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 ML20308A4362020-11-0202 November 2020 Response to Request for Additional Information for Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR-056, Revision 3 ML20308A4372020-11-0202 November 2020 Response to Request for Additional Information (Redacted) 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-20-251, Response to a Request for Additional Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602020-09-29029 September 2020 Response to a Request for Additional Information Regarding a License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 L-20-197, Response to Request for Additional Information Regarding Request to Extend License Expiration Date by Recapturing Low-Power Testing Time2020-07-30030 July 2020 Response to Request for Additional Information Regarding Request to Extend License Expiration Date by Recapturing Low-Power Testing Time ML20197A2122020-07-15015 July 2020 Response to Request for Additional Information for Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR-056, Revision 3 L-20-183, Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force2020-06-23023 June 2020 Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force 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-20-154, Response to Request for Additional Information for Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR-054, Revision 22020-06-0202 June 2020 Response to Request for Additional Information for Proposed Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR-054, Revision 2 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,. 2023-06-13
[Table view] |
Text
ArstEnergx 341 White Pond Drive Solutions
' Akron, Ohio 44320 Donald A. Moul 330-315-6800 President & CNO FirstEnergy Solutions Generation Companies March 16, 2018 L-18-061 10 CFR 73.5 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement
[EPID-L-2017-LLE-0019 (CAC Nos. 000976/05000334/L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011, 000976/05000334/L-2017-LLE-0019 MG0012, and 000976/05000334/L-2017-LLE-0019 MG0013)]
By letter dated July 19, 2017 (Accession Number ML17200D139), FirstEnergy Nuclear Operating Company (FENOC) requested a permanent exemption from a requirement of 10 CFR 73.2, "Definitions" for Beaver Valley Power Station Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant.
By e-mail dated February 9, 2018, the Nuclear Regulatory Commission (NRC) requested additional information to complete its review of the FENOC request. The FENOC response to the NRC request for information is attached to this letter.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at 330-315-6810.
Sincerely, Donald A. Moul
Beaver Valley Power Station, Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station Perry Nuclear Power Plant L-18-061 Page 2
Attachment:
Response to Request for Additional Information cc:
NRC Region I Administrator NRC Region Ill Administrator NRC Resident Inspector - Beaver Valley NRC Resident Inspector - Davis-Besse NRC Resident Inspector- Perry NRC Project Manager - FENOC Fleet Director BRP/DEP Site BRP/DEP Representative Utility Radiological Safety Board Branch Chief, OEMA, State of Ohio
Attachment L-18-061 Response to Request for Additional Information Page 1 of 6 The NRC staffs request for additional information is provided in bold text, followed by the FENOC response.
RAl#1:
As required by§§ 73.55(e) and 73.55(e)(3)(i)(B), describe the site-specific conditions and locations, in relation to site layout, that were identified and analyzed to determine the specific use, type, function, and placement of the affected physical barriers (fences) and the need for the vertical bracket configuration at each location. Specifically, clarify the locations of fence sections described in the submittal (i.e., the vertical configuration of barbed wire on the top of limited protected area sections (on gates, near gates, near interfaces with buildings, and on corners at BVPS, and similar configurations at DBNPS and PNPP, to include near the IDS at DBNPS)), and clarify the technical basis/need for the vertical bracket configuration at each location to which it is applied.
Response
Site layouts with the locations and descriptions of the protected area physical barrier fencing sections topped with vertically-oriented brackets containing barbed wire or similar material are provided in Figures 1, 2, and 3 for BVPS, DBNPS, and PNPP, respectively. The response to RAI #2 provides the technical basis or need for the vertical bracket configuration at each location.
RAl#2:
As required by§ 73.55(e)(1), describe the technical basis for the vertical bracket design, construction, installation, and maintenance relative to the capability to control access into facility areas for which access must be controlled or denied, and how the vertical bracket configuration satisfies the physical protection program design requirements of§ 73.55(b).
Specifically, describe how the vertical bracket configuration ensures that the requirements of§§ 73.55(e)(3) and 73.55(e)(8) are effectively met relative to: (1) protection against the design basis threat; (2) performance of the intended function (limit access, channeling to access portals, deterrence, delay, and/or support to access controls); (3) the level of deterrence, delay, and/or support to access controls relied upon by the physical protection program; and (4) the function that the fence performs in support of the protective strategy (to include any impact to adversary or responder timelines that are dependent upon the
Attachment L-18-061 Page 2 of 6 delay assigned to the fence and/or confirm that delay time provided by the vertical bracket configuration has been accounted for in the licensee's protective strategy for both adversary and responder timelines).
§ 73.55(e)(3) states that physical barriers must:
(1) Be designed and constructed to
- a. Protect against the design basis threat of radiological sabotage;
- b. Account for site-specific conditions; and
- c. Perform their required function in support of the licensee physical protection program.
(2) Provide deterrence, delay, or support access control.
(3) Support effective implementation of the licensee's protective strategy.
§ 73.55(e)(8)(i) states in part that the "protected area perimeter must be protected by physical barriers that are designed and constructed to:
(A) Limit access into the protected area to only those personnel, vehicles, and materials required to perform official duties; (B) Channel personnel, vehicles, and materiavls to designated access control portals";
Response
As clarified on a February 7, 2018 phone call regarding the level of detail the NRC staff was expecting for the response to this question, the NRC staff stated RAI #2 is questioning why the angular fence topping design is not acceptable at all locations.
As stated in the exemption request and shown in the response to RAI #1, the vertical bracket configuration is limited to locations on gates, near gates, near interfaces with buildings, and on corners. DBNPS also has vertical brackets in two locations adjacent to the IDS where physical separation clearance is required. Other than the DBNPS locations near the IDS, the vertical bracket configuration at the other locations described in the exemption request is preferred to maintain sufficient tension in the barbed wire strands. The angular brackets use slits in the steel to accommodate the barbed wire.
The majority of the barbed wire is not hard-fastened to the bracket, but fits snugly in the slits when the wire is tensioned. Greater barbed wire tension can therefore be applied when using vertical brackets as opposed to angular brackets on the end of fence runs (which includes on top of gates, adjacent to gates, and adjacent to buildings). Angular corner arms do not provide a good tension point in the barbed wire.
Attachment L-18-061 Page 3 of 6 RAl#3:
Provide any analyses performed to establish or confirm the technical basis for the affected configuration and/or information supporting the capability of the
'affected configuration to satisfy applicable Commission requirements and ensure the effectiveness of the protective strategy, to include any impact to adversary or responder timelines that are dependent upon the delay assigned to the fence and/or confirm that delay time provided by the vertical bracket configuration has been accounted for in the licensee's protective strategy for both adversary and responder timelines. As required by § 73.55(e)(2), the licensee shall retain, in accordance with § 73. 70, all analyses and descriptions of the physical barriers and barrier systems used to satisfy the requirements of this section, and shall protect these records in accordance with the requirements of§ 73.21.
Response
The protective strategy for adversary and responder timelines has been developed in accordance with a FENOC business practice applicable to BVPS, DBNPS, and PNPP, and satisfies applicable Commission requirements. The vertical bracket configuration has no impact to adversary or responder timelines in the protective strategies for the FENOC fleet. This is due to site-specific evaluations that determined the limiting perimeter barrier fence scenarios are most similar to the configuration illustrated on page eight of RIS 2003-06, or the use of mechanical breaching utilizing the same configuration. Whether or not the fence toppings are vertical or angled makes no difference to the protective strategy limiting timelines.
Attachment L-18-061 Page 4 of6
- Gates With Vertical Posts
- Vertical Posts V-N3150.0 E8550.0
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Figure 1. BVPS Location of Protected Area Physical Barrier Fencing Sections Topped With Vertically-oriented Brackets.
Attachment L-18-061 Page 5 of 6
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- Gates With Vertical Posts eee Vertical Fencing NearIDS Figure 2. DBNPS Location of Protected Area Physical Barrier Fencing Sections Topped With Vertically-oriented Brackets
Attachment L-18-061 Page 6 of 6 e
Gates With Vertical Posts Vertical Posts 0 I 0
Figure 3. PNPP location of Protected Area Physical Barrier Fencing Sections Topped With Vertically-oriented Brackets.