Letter Sequence RAI |
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MONTHYEARL-15-150, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-05-27027 May 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI 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 Project stage: Response to RAI ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI 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 Project stage: Response to RAI 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 Project stage: Supplement ML16099A0112016-03-0303 March 2016 NRR E-mail Capture - Draft 3rd Round PRA RAIs - Beaver Valley Units 1 & 2 - NFPA-805 LAR (CAC Nos. MF3301 & MF3302) Project stage: Draft RAI ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML16089A0622016-03-30030 March 2016 Meeting to Discuss BVPS Draft PRA RAI - Slides Project stage: Request ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML16105A0082016-04-25025 April 2016 March 30, 2016, Summary of Meeting with Firstenergy Nuclear Operating Company on Its Draft Probabilistic Risk Assessment RAI Related to Its License Amendment Request to Adopt NFPA Standard 805 Project stage: Draft RAI 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 Project stage: Response to RAI ML16158A0022016-06-0101 June 2016 NRR E-mail Capture - Beaver Valley, Units 1 & 2 - Update on NFPA 805 (CAC Nos. MF3301 & MF3302) Project stage: Other ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI 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 Project stage: Response to RAI 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 Project stage: Supplement ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request Project stage: RAI ML17313A6422017-11-0909 November 2017 Transmittal of Draft Safety Evaluation for Proposed Amendments Transition to NFPA 805 (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) Project stage: Draft Approval ML17335A0962017-11-27027 November 2017 NRR E-mail Capture - Beaver Valley: NFPA 805 LAR: License Condition: Fire Protection Program Changes That Have More than Minimal Risk Impact (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) Project stage: Other ML18058A9422017-12-11011 December 2017 NFPA 805 Amendment Application Transition License Condition Project stage: Other ML17291A0812018-01-22022 January 2018 Issuance of Amendments Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) Project stage: Approval ML18058B0722018-02-23023 February 2018 BVPS NFPA 805 License Amendment Change Requested, and Other SE Comments Project stage: Other ML18059A7982018-02-26026 February 2018 BVPS NFPA 805 License Amendment Change Requested, and Other SE Comments Project stage: Other ML18058A9852018-02-27027 February 2018 BVPS-1 License Condition Page Project stage: Other ML18058A9532018-02-27027 February 2018 Comments on BVPS SE Project stage: Other ML18065A4032018-04-0505 April 2018 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 301 and 190 Project stage: Approval ML18099A2322018-04-18018 April 2018 Correction of an Error in the Renewed Facility Operating License No. DPR-66 Associated with License Amendment No. 301 CAC No. MF3301; EPID L-2013-LLF-0001) Project stage: Other 2016-06-01
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Category:Letter
MONTHYEARML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) IR 05000334/20240102024-08-20020 August 2024 Comprehensive Engineering Team Inspection - Inspection Report 05000334/2024010 and 05000412/2024010 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-158, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 L-24-157, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations L-24-114, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation L-24-115, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection 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-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0707 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 2024-09-17
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports ML24044A1772024-02-14014 February 2024 RAI for 180 Days Steam Generator Report ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22278A0972022-10-0606 October 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 ML22013A7512022-01-13013 January 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010 ML21292A0482021-10-19019 October 2021 Ti 2515/194 Inspection Documentation Request ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21124A1322021-05-0404 May 2021 Notification of Conduct of a Fire Protection Team Inspection ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20290B0082020-10-0808 October 2020 Draft Request for Additional Information - Steam Generator Letter ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20072N0402020-03-12012 March 2020 Request for Additional Information - Control Envelope Habitability LAR ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19143A0732019-05-29029 May 2019 FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments ML18242A3642018-08-29029 August 2018 Request for Additional Information (Final) -Steam Generator Technical Specification LAR ML18102B0852018-04-12012 April 2018 NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver ML18043A0102018-02-0909 February 2018 NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans ML18024B3642018-01-24024 January 2018 NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review ML18019A0722018-01-18018 January 2018 NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule ML17353A1582017-12-19019 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17352B2612017-12-18018 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information 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, ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request ML17093A7622017-04-10010 April 2017 Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request ML17031A0362017-02-0303 February 2017 Request for Additional Information Regarding Relief Request Numbers PR6 and PR7 ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16147A2842016-06-14014 June 2016 Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15279A1252015-10-0505 October 2015 Licensed Operator Positive for Fitness-for-Duty-Test ML15181A2142015-07-14014 July 2015 Request for Additional Information Regarding License Amendment Request to Revise Steam Generator Technical Specifications to Reflect TSTF-510 and to Revise Alloy 800 Sleeve Technical Specifications (TAC Nos. MF6054 & MF6055) ML15125A4162015-05-11011 May 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302) ML15016A4392015-01-20020 January 2015 Draft Request for Additional Information ML15007A5582015-01-15015 January 2015 Request for Additional Information Steam Generator Inspection Reports 2024-07-17
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Mr. Marty L. Richey Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 2, 2016 FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (CAC NOS. MF3301 AND MF3302)
Dear Mr. Richey:
By letter dated December 23, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML 14002A086), as supplemented by letters dated February 14, 2014; April 27, 2015; May 27, 2015; June 26, 2015; November 6, 2015; December 21, 2015; February 24, 2016; and May 12, 2016 (ADAMS Accession Nos. ML 14051A499, ML 15118A484, ML 15147A372, ML 15177A110, ML 15313A306, ML 15356A136, ML 16055A160, and ML 16133A340, respectively), FirstEnergy Nuclear Operating Company (FENOC) submitted a license amendment request to change the Beaver Valley Power Station, Units Nos. 1 and 2, fire protection program to one based on the National Fire Protection Association Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition. The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete the review, as listed in the enclosed request for additional information (RAI). A draft RAI was sent to your staff by e-mail dated November 2, 2016, to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. A clarification call with FENOC was held on November 22, 2016. During the call, it was agreed that FENOC would provide a response within 60 days from the date of this letter.
M. Richey If you have any questions, or if circumstances result in the need to revise the agreed upon response date, please contact me at (301) 415-2871 or by e-mail at Michael.Marshall@nrc.gov. Docket Nos. 50-334 and 50-412
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT NFPA 805 FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated December 23, 2013 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML 14002A086), as supplemented by letters dated February 14, 2014; April 27, 2015; May 27, 2015; June 26, 2015; November 6, 2015; December 21, 2015; February 24, 2016; and May 12, 2016 (ADAMS Accession Nos. ML14051A499, ML15118A484, ML15147A372, ML15177A110, ML15313A306, ML 15356A136, ML 16055A160, and ML 16133A340, respectively), FirstEnergy Nuclear Operating Company submitted a license amendment request to change the Beaver Valley Power Station, Units Nos. 1 and 2, fire protection program to one based on the National Fire Protection Association Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition, as incorporated in Title 10 of the Code of Federal Regulations Section 50.48(c). The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to complete its review of the license amendment request. Probabilistic Risk Assessment (PRA) Request for Additional Information 27, "Very Early Warning Fire Detection System (VEWFDS) Credit" Section 2.4.3.3 of NFPA 805 states that the probabilistic safety analysis (also referred to as PRA) approach, methods, and data shall be acceptable to the authority having jurisdiction, which is the NRC. Section 2.4.4.1 of NFPA 805 further states that the change in public health risk arising from transition from the current fire protection program to an NFPA 805-based program, and all future plant changes to the program, shall be acceptable to the NRC. Regulatory Guide (RG) 1.17 4, Revision 2, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" (ADAMS Accession No. ML 100910006), provides quantitative guidelines on core damage frequency (CDF), large early release frequency (LERF), and identifies acceptable changes to these frequencies that result from proposed changes to the plant's licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staff's review of the information in the license amendment request identified additional information that is needed to fully characterize the risk estimates. New guidance on the credit taken for VEWFDS is available in NUREG-2180, "Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities, (DELORES-VEWFIRE)," of which the final (pre-publication) version is available at ADAMS Accession Nos. ML 16286AOOO and ML 16286A002. The methodology in NUREG-2180 is acceptable to the NRC because it is currently the best Enclosure available guidance. By letter dated July 1, 2016 (ADAMS Accession No. ML 16167A444), the guidance provided in Frequently Asked Question 08-0046, "Closure of National Fire Protection Association 805 Frequently Asked Question 08-0046, 'Incipient Fire Detection Systems'," dated November 23, 2009 (ADAMS Accession No. ML093220426), has been retired, and alternative approaches for staff evaluation are necessary. Explain how credit (e.g., approach, methods, data, and assumptions) taken in the fire PRA (FPRA) for the proposed VEWFDS is consistent with the guidance in NUREG-2180 or bounds the risk results (i.e., CDF, LERF, change in CDF, and change in LERF) that would be obtained, had the guidance in NUREG-2180 been applied. If credit taken for VEWFDS in the FPRA is not consistent with or bounded by NUREG-2180, provide: a. The risk results (i.e., CDF, LERF, change in CDF, and change in LERF): (1) without credit for VEWFDS that would be obtained had the guidance in NUREG-2180 been applied or (2) that would be obtained had an alternative method been used, along with a description and justification for the alternative method. Development and use of an alternative proposal may extend the time required to complete the review. The new risk results can be generated from a sensitivity study type evaluation insofar as formal incorporation of the new method into the PRA model of record is not required. b. Explain how the total risk and increase in risk are consistent with the guidelines in RG 1.174.
ML 16333A016 OFFICE NRR/DORULPL 1-2/PM NRR/DORULPL 1-2/PM NAME MMarshall JPoole DATE 12/01/2016 12/02/2016 Sincerely, IRA/ Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LFields, NRR RidsNrrDraApla Resource RidsNrrLALRonewicz Resource RidsNrrPMBeaverValley Resource JHyslop, NRR NRR/DORULPL 1-2/LA NRR/DORULPL 1-2/BC(A) LRonewicz SKoenick 11/28/2016 12/02/2016 NRR/DORL/LPL 1-2/PM MMarshall 12/02/2016