Letter Sequence Response to RAI |
---|
EPID:L-2022-LLA-0071, Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time (Approved, Closed) |
|
|
|
---|
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
[Table view] |
Text
Energy Harbor Nuclear Corp.
Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 John J. Grabnar 724-682-5234 Site Vice President, Beaver Valley Nuclear December 7, 2022 10 CFR 50.90 L-22-246 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 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO (EPID No. L-2022-LLA-0071)
By letter dated May 16, 2022 (Accession No. ML22137A049), Energy Harbor Nuclear Corp. requested Nuclear Regulatory Commission (NRC) approval for a license amendment request (LAR). The LAR revises Beaver Valley Power Station, Unit 1 and 2 Technical Specifications (TS) to add a Limiting Condition for Operation (LCO) titled Decay Time restricting movement involving fuel or over fuel that has occupied part of a critical reactor core within the previous 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. The current TS restrictions on fuel movement involving fuel that has occupied part of a critical reactor core within the previous 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> appear in the applicability statements and conditions of several TS LCOs. The proposed LAR would consolidate those restrictions in the new LCO.
By email dated November 8, 2022, the NRC staff requested additional information regarding the Beaver Valley LAR. The Energy Harbor Nuclear Corp. response to the November 8, 2022, NRC request is attached.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Manager, Fleet Licensing, at (330) 696-7208.
Beaver Valley Power Station, Unit Nos. 1 and 2 L-22-246 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on December 7, 2022.
Sincerely, John J Digitally signed by John J Grabnar Grabnar Date: 2022.12.07 12:13:17
-05'00' John J. Grabnar
Attachment:
Response to Request for Additional Information cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative
Attachment L-22-246 Response to Request for Additional Information Page 1 of 4 By letter dated May 16, 2022, Energy Harbor Nuclear Corp. submitted a license amendment request (LAR) for Nuclear Regulatory Commission (NRC) review and approval. By email dated November 8, 2022, NRC staff requested additional information to complete its review. The request for additional information is presented below in bold type and is followed by the Energy Harbor Nuclear Corp. response.
Regulatory Basis Criterion 3 of Title 10 of the Code of Federal Regulations, part 50.36(c)(2)(ii)(C) states a technical specification limiting condition for operation of a nuclear reactor must be established for a structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The prohibition of fuel movements involving recently irradiated fuel (fuel that has occupied part of a critical reactor core within the previous 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />), as required by the fuel handling analysis, appears in the applicability statements of TS [Technical Specification] 3.3.7, Control Room Emergency Ventilation System (CREVS)
Actuation Instrumentation, and TS 3.3.11, Control Room Emergency Air Cooling System (CREACS).
Attachment L-22-246 Page 2 of 4
Response
The NOTE for LCO 3.7.11 is not applicable for Unit 2. Neither the CREACS heat removal function nor the CREACS atmosphere purge capability is required following a fuel handling accident (FHA) at Unit 2. While the CREACS heat removal function is also not required following a FHA at Unit 1, the atmosphere purge capability is required for Unit 1 to support fuel movement involving irradiated fuel to limit dose.
Attachment L-22-246 Page 3 of 4
Response
Section 15.7.4 of the Unit 2 UFSAR describes the radiological consequence of a FHA, including accident-specific control room model assumptions, with no mention of a control room purge. In UFSAR Chapter 15, radiological consequences of each of the design basis accidents (DBA) were analyzed. Resulting doses to main control room personnel due to DBAs are presented in Table 15.0-13, Control Room Doses (TEDE)
From Design Basis Accidents. Note 5 of the table indicates the control room is purged for a main steam line break and a steam generator tube rupture. Note 5 is not applied to the FHA.
On September 23, 2020 (Accession No. ML20213A731), the NRC staff issued Amendments 305 and 195 for Unit 1 and Unit 2, respectively. By letter dated October 21, 2020 (Accession No. ML20285A266), the NRC staff issued a correction to the safety evaluation (SE) for these amendments. Section 3.1.7 of the SE provides a discussion of a FHA. Data and assumptions for a FHA are presented in Table 11 in Section 5 of the SE. In Table 11, a control room purge is credited for Unit 1 only. No control room purge is credited for Unit 2.
A control room purge is required for a Unit 1 FHA because the prevailing weather patterns at the BVPS site carry radionuclide releases from Unit 1 towards the common control room, while such releases from a Unit 2 FHA are carried away from the common control room.
These documents demonstrate that Unit 2 FHA analysis has not taken credit for CREACS control room atmosphere purge.
SCPB RAI-02:
The APPLICABILITY of current TS 3.3.7, Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation, specifies several ESFAS
[Engineered Safety Feature Actuation System] signals for the CREVS actuation.
Containment Isolation - Phase B (CIB) is one of those signals to actuate CREVS.
Function 3 in Table 3.3.7-1 for CIB is removed in the proposed TS 3.3.7.
Section 3.0 of Attachment 1 (page 16 of 41) to the LAR relating to TS 3.3.7 CREVS provides the following justifications for the removal of this actuation signal from the current TS APPLICABILITY requirements.
Containment Isolation - Phase B Table 3.3.7-1 Item 3, Containment Isolation - Phase B (CIB), is proposed for deletion. Currently, Table 3.3.7-1 lists CIB as part of the
Attachment L-22-246 Page 4 of 4 CREVS Actuation Instrumentation but does not list any requirements for the instrumentation. Instead, the Table 3.3.7-1 entry appears to be for information only and simply states: Refer to LCO 3.3.2, ESFAS Instrumentation, Function 3.b, for all initiation functions and requirements. References to LCO 3.3.2 for the CIB appear in the TS Bases. As such, there is no need to repeat this information in the TS LCO.
In Modes 1 through 4, the LOCA accident analysis assumes an automatic Control Room Ventilation System isolation on a CIB signal and subsequent manual initiation of a CREVS fan for filtered makeup and pressurization of the control room. As stated in Table 3.3.7-1, the Operability requirements for CIB, in Modes 1 through 4, are specified in LCO 3.3.2, Engineered Safety Feature Actuation System (ESFAS).
The staff reviewed LCO 3.3.2 Function 3.b and found no mention of CREVS Actuation Instrumentation. It is not clear how operability is addressed to ensure automatic Control Room Ventilation System isolation on CIB signal. The licensee is requested to provide additional justifications for deleting Function 3 for CIB from TS 3.3.7. Specifically, the licensee is requested to explain how LCO 3.3.2 Function 3.b addresses CREVS Actuation Instrumentation.
Response
ESFAS instrumentation is segmented into three distinct but interconnected modules, one of which is the Solid State Protection System (SSPS). The SSPS equipment is used for the decision logic processing of inputs from field contacts, control board switches, and the signal processing equipment bistables. If a required logic matrix combination is completed, the system will send actuation signals via master and slave relays to those components whose aggregate function best serves to alleviate the condition and restore the unit to a safe condition.
CREVS is one of the systems receiving a signal from SSPS slave relays, which places it under Function 3.b(2), Automatic Actuation Logic and Actuation Relays, in Table 3.3.2-1. Surveillance Requirement (SR) 3.3.2.2, SR 3.3.2.3, and SR 3.3.2.6 address operability for this function in Modes 1, 2, 3, and 4. Site operating surveillance tests remain in place to satisfy these SRs. Therefore, operability requirements for CIB in Modes 1 through 4 remain unchanged.
The proposed removal of Table 3.3.7.1 Item 3 does not modify or remove any requirements associated with CIB actuation.