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MONTHYEARML0622603432006-08-21021 August 2006 Westinghouse Electric Company, Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Unit Nos. 1 and 2 (Tac MD2377 and MD2378) Project stage: Withholding Request Acceptance ML0712300372007-05-17017 May 2007 RAI, Request for Additional Information Regarding the Spent Fuel Pool Critically Analysis License Amendment Request (TAC Nos. MD2377 and MD2378) Project stage: RAI L-07-084, Response to a Request for Additional Information (RAI Dated May 21, 2007) in Support of License Amendment Request Nos. 333 and 2042007-07-20020 July 2007 Response to a Request for Additional Information (RAI Dated May 21, 2007) in Support of License Amendment Request Nos. 333 and 204 Project stage: Response to RAI L-07-103, Supplemental Information for License Amendment Request Nos. 333 & 204 (Rev. 2 of WCAP-16518)2007-07-26026 July 2007 Supplemental Information for License Amendment Request Nos. 333 & 204 (Rev. 2 of WCAP-16518) Project stage: Supplement ML0721103192007-07-31031 July 2007 WCAP-16518-NP, Rev. 2, Beaver Valley, Unit 2, Spent Fuel Pool Criticality Analysis Project stage: Other ML0806507282008-03-0606 March 2008 Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis License Amendment Request Project stage: RAI L-08-100, Responses to Request for Additional Information in Support of License Amendment Request No. 204, Revision 12008-03-11011 March 2008 Responses to Request for Additional Information in Support of License Amendment Request No. 204, Revision 1 Project stage: Response to RAI ML0807304762008-03-27027 March 2008 Issuance of Amendment Incorporation of the Results of a New Spent Fuel Pool Criticality Analysis Project stage: Approval 2007-07-26
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Category:Letter
MONTHYEARIR 05000334/20244032024-11-13013 November 2024 Cybersecurity Problem Identification and Resolution Inspection Report 05000334/2024403 and 05000412/2024403 (Cover Letter Only) IR 05000334/20240032024-11-13013 November 2024 Integrated Inspection Report 05000334/2024003 & 05000412/2024003 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 2024-09-26
[Table view] Category: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 IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 ML24044A1772024-02-14014 February 2024 RAI for 180 Days Steam Generator Report ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to 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 IR 05000334/20220102022-01-13013 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 2024-07-17
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Text
March 6, 2008 Mr. Peter P. Sena III Site Vice President 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 NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE SPENT FUEL POOL CRITICALITY ANALYSIS LICENSE AMENDMENT REQUEST (TAC NO.
MD2378)
Dear Mr. Sena:
By letter dated June 14, 2006, as supplemented by letters dated July 20, July 26, and December 21, 2007, FirstEnergy Nuclear Operating Company (FENOC, licensee) requested an amendment to the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2) Technical Specifications (TSs). The proposed changes to the TSs would incorporate the results of topical report, Westinghouse Commercial Atomic Power (WCAP)-16518, Beaver Valley Unit 2 Spent Fuel Pool Criticality Analysis, Revision 1, May 2006. The new criticality analysis will permit utilization of vacant storage locations dictated by the existing TS storage configurations in the BVPS-2 spent fuel storage pool. By letter dated December 21, 2007, the licensee withdrew their license amendment request (LAR) for BVPS-1. On January 10, 2007, an audit was held between the Nuclear Regulatory Commission (NRC), representatives of Westinghouse Electric Company (vendor), and representatives of FENOC to discuss and evaluate documents that addressed the NRC staffs position/concerns, as they pertained to the review of the LAR.
The NRC staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The licensee indicated that a response to the RAI will be provided by March 14, 2008.
P. Sena Please contact me at (301) 415-1016, if you have any questions regarding this matter.
Sincerely,
/RA/
Nadiyah S. Morgan, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
RAI cc w/encl: See next page
P. Sena Please contact me at (301) 415-1016, if you have any questions regarding this matter.
Sincerely,
/RA/
Nadiyah S. Morgan, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLI-1 R/F RidsNrrDorlLplI-1 KWood NMorgan SLittle RidsNrrDssSrxb DWerkheiser, RI RidsNrrDorlDpr RidsOGCMailCenter RidsRgn1MailCenter RidsAcrsAcnw&mMailCenter ADAMS ACCESSION NO. ML080650728 OFFICE LPLI-1/PM LPLI-1/LA SRXB/BC LPLI-1/BC NAME NMorgan SLittle GCranston MKowal DATE 3/6/08 3/6/08 3/6/08 3/6/08 OFFICIAL RECORD COPY
Beaver Valley Power Station, Unit Nos. 1 and 2 cc:
Joseph J. Hagan Ohio EPA-DERR President and Chief Nuclear Officer ATTN: Zack A. Clayton FirstEnergy Nuclear Operating Company P.O. Box 1049 Mail Stop A-GO-19 Columbus, OH 43266-0149 76 South Main Street Akron, OH 44308 Peter P. Sena III Site Vice President James H. Lash FirstEnergy Nuclear Operating Company Senior Vice President of Operations Beaver Valley Power Station and Chief Operating Officer Mail Stop A-BV-SEB1 FirstEnergy Nuclear Operating Company P.O. Box 4, Route 168 Mail Stop A-GO-14 Shippingport, PA 15077 76 South Main Street Akron, OH 44308 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Danny L. Pace Mail Stop A-GO-2 Senior Vice President, Fleet Engineering 76 South Main Street FirstEnergy Nuclear Operating Company Akron, Ohio 44308 Mail Stop A-GO-14 76 South Main Street Manager, Site Regulatory Compliance Akron, OH 44308 FirstEnergy Nuclear Operating Company Beaver Valley Power Station Jeannie M. Rinckel Mail Stop A-BV-A Vice President, Fleet Oversight P.O. Box 4, Route 168 FirstEnergy Nuclear Operating Company Shippingport, PA 15077 Mail Stop A-GO-14 76 South Main Street Commissioner James R. Lewis Akron, OH 44308 West Virginia Division of Labor 749-B, Building No. 6 David W. Jenkins, Attorney Capitol Complex FirstEnergy Corporation Charleston, WV 25305 Mail Stop A-GO-15 76 South Main Street Director, Utilities Department Akron, OH 44308 Public Utilities Commission 180 East Broad Street Manager, Fleet Licensing Columbus, OH 43266-0573 FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 Director, Pennsylvania Emergency 76 South Main Street Management Agency Akron, OH 44308 2605 Interstate Dr.
Harrisburg, PA 17110-9364
Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:
Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077 Ms. Carol OClaire Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin-Granville Road Columbus, OH 43235-2206 Mr. Dan Hill Chief, Radiological Health Program West Virginia Department of Health and Human Resources Capitol & Washington Streets 1 Davis Square Suite 200 Charleston, WV 25305-0360
REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING THE SPENT FUEL POOL (SFP) CRITICALITY ANALYSIS LICENSE AMENDMENT REQUEST FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 2 By letter dated June 14, 2006, as supplemented by letters dated July 20, July 26, and December 21, 2007, FirstEnergy Nuclear Operating Company (FENOC, licensee) requested an amendment to the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2) Technical Specifications (TSs). The proposed changes to the TSs would incorporate the results of topical report, (WCAP)-16518, which will permit utilization of vacant storage locations dictated by the existing TS storage configurations in the BVPS-2 spent fuel storage pool. By letter dated December 21, 2007, the licensee withdrew their license amendment request (LAR) for BVPS-1.
Based on previous RAI questions (References 1 and 2) and information obtained from the audit, the Nuclear Regulatory Commission (NRC) staff request further information on the following items:
- 1. On January 25, January 28, February 1, February 4, February 11, and February 12, 2008, the NRC staff conducted an audit of Westinghouse calculations associated with the BVPS-2 spent fuel pool criticality analysis. Those calculations were documented as calculations notes, CN-CRIT-224 and CN-CRIT-244. Please provide Section 7 of CN-CRIT-244 to support the NRC staffs safety evaluation (SE) for the BVPS-2 SFP criticality LAR. Also, identify any portions that are replaced due to response to questions listed below.
- 2. After considering the information in CN-CRIT-244 and NUREG/CR-6801 (Reference 5),
it appears the axial burnup profile used in WCAP-16518 under predicts keff for any case run at 15 gigawatt day per metric ton uranium (GWD/MTU) or 25 GWD/MTU. Provide a site-specific analysis that demonstrates that BVPS-2 retains reactivity margin with the burnup profile used in the WCAP-16518 analysis.
- 3. WCAP-16518 calculates the burnup uncertainty in a method different than that specified in the NRC staff guidance, Reference 3. The NRC staff has reviewed the justification for the new method and determined it is inadequate to justify the method. Calculate the burnup uncertainty in accordance with the NRC staff guidance in Reference 3.
- 4. WCAP-16518 calculates a typical temperature bias for each storage configuration. The staff has reviewed the justification for method calculating the temperature bias and determined it is inadequate for the staff to reach a reasonable assurance conclusion that the limiting temperature bias has been determined for each storage configuration.
Provide a site-specific analysis that demonstrates that the limiting temperature bias has been determined for each storage configuration.
Enclosure
- 5. During the depletion phase of the analysis, core operating parameters should be selected to maximize 241Pu production and increase the reactivity of the spent fuel.
WCAP-16518 did not use core operating parameters which would maximize 241Pu production. NUREG/CR-6665, Reference 4, provides some indication of the impact of the core operating parameters. The information in CN-CRIT-244 indicated that the axial burnup profile used in WCAP-16518 provides sufficient margin to accommodate this issue above, but not below 30 GWD/MTU. Provide a site-specific analysis that demonstrates that BVPS-2 retains reactivity margin with the burnup profile used in the WCAP-16518 analysis.
References
- 1. FirstEnergy Nuclear Operating Company letter L-07-084, Peter P. Sena III, Site Vice President, Beaver Valley Power Station, to USNRC document control desk re: A Beaver Valley Power Station, Unit Nos. 1 and 2, BV-1 Docket No. 50-334, License No. DPR-66, BV-2 Docket No. 50-412, License No. NPF-73, Responses to a Request for Additional Information (RAI dated May 21, 2007) in Support of License Amendment Request Nos.
333 and 204 (TAC Nos. MD2377 and MD2378),@ July 20, 2007. (ADAMS ML072050213)
- 2. FirstEnergy Nuclear Operating Company letter L-07-103, Edward H. Hubley, Acting Director, Maintenance, Beaver Valley Power Station, to USNRC document control desk, re: A Beaver Valley Power Station, Unit Nos. 1 and 2, BV-1 Docket No. 50-334, License No. DPR-66, BV-2 Docket No. 50-412, License No. NPF-73, Supplemental Information for License Amendments Request Nos. 333 and 204 (Revision 2 of WCAP-16518) (TAC Nos. MD2377 and MD2378)@ July 26, 2007. (ADAMS ML073320036)
- 3. NRC Memorandum from L. Kopp to T. Collins, Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants, August 19, 1998. (ADAMS ML003728001)
- 4. NUREG/CR-6665, AReview and Prioritization of Technical Issues Related to Burnup Credit for LWR Fuel,@ (ADAMS ML003688150)
- 5. NUREG/CR-6801, ARecommendations for Addressing Axial Burnup in PWR Burnup Credit Analysis,@ (ADAMS ML03110292)