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MONTHYEARML0515302672005-06-0303 June 2005 6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI L-05-123, Response to Request for Additional Information on Generic Letter 2004-022005-07-22022 July 2005 Response to Request for Additional Information on Generic Letter 2004-02 Project stage: Response to RAI ML0603803422006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors TAC Nos. MC4665 and MC4666 Project stage: RAI ML0613802732006-05-18018 May 2006 Request for Scheduler Extension from Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC46666) Project stage: Other L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions2008-02-14014 February 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors2008-02-29029 February 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors Project stage: Supplement ML0812301162008-02-29029 February 2008 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,... Project stage: Other L-08-257, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions2008-08-28028 August 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions Project stage: Request ML0827402412008-09-30030 September 2008 Extension Request Approval Letter Generic Letter 2004--02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-10-29029 October 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps2009-03-11011 March 2009 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps Project stage: Other ML0909001932009-03-31031 March 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Project stage: Other ML0910501002009-04-21021 April 2009 Correction Letter Extension Request Approval to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other L-09-131, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions2009-04-30030 April 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions Project stage: Request ML0912400302009-05-0505 May 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-06-30030 June 2009 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Supplement ML1002903182010-02-18018 February 2010 RAI, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: RAI ML1008407562010-03-31031 March 2010 Notice of Teleconference Meeting with Firstenergy Nuclear Operating Company Regarding Mutual Understanding of NRR Staff'S Request for Additional Information and to Discuss Generic Letter 2004-02 Project stage: RAI ML1013206652010-05-18018 May 2010 Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI L-13-176, Generic Safety Issue 191 Resolution Plan2013-05-16016 May 2013 Generic Safety Issue 191 Resolution Plan Project stage: Other 2009-03-11
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Category:Letter
MONTHYEARML24025A0922024-01-25025 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 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 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 IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 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 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - 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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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 SUB~IECT: BEAVER VALLEY POWER STATION, UNIT NO.2 - EXTENSION REQUEST APPROVAL LETTER RE: GENERIC LETrER 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS," (TAC NO. MC4666)
Dear Mr. Sena:
Generic Letter (GL) 2004-02 identified potential susceptibility of pressurized-water reactor recirculation sump screens to debris blockage during design-basis accidents requiring recirculation operation of emergency core cooling systems (ECCS) or containment spray systems (CSS), and on the potential for additional adverse effects due to debris blockage of flowpaths necessary for ECCS and CSS recirculation and containment drainage. The GL requested that all corrective activities be completed no later than December 31, 2007.
By letter dated December 20, 2007, you requested an extension for certain activities associated with your response to GL 2004-02. The Nuclear Regulatory Commission (NRC) staff evaluated the information provided in your letter and concluded that for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2), it was acceptable to extend the due date for completion of corrective actions until February 29, 2008.
By letter dated February 14, 2008, you requested an extension for certain sump blockage corrective actions associated with your response to GL 2004-02. The NRC staff evaluated the information provided in your letter and concluded that for BVPS-1, it was acceptable to extend the due date for completion of corrective actions until September 30, 2008, and for BVPS-2, it was acceptable to extend the due date for completion of corrective actions until March 31, 2009, or 60 days after NRC approval of a combined buffer change and containment overpressure credit license amendment request, whichever was sooner.
P.Sena -2 By letter dated August 28,2008, as supplemented by letter dated October 29,2008, you requested an extension for certain sump blockage corrective actions associated with your response to GL 2004-02. The NRC staff evaluated the information provided in your letters and concluded that for BVPS-1, it is acceptable to extend the due date for completion of GL 2004-02 corrective actions until startup, following the spring 2009 refueling outage, which commences in April 2009. The NRC staff evaluated the information provided in your letters and determined that for BVPS-2, it is acceptable to extend the due date for completion of corrective actions until startup following the fall 2009 refueling outage (2R 14).
Please contact me at 301-415-1016, if you have any questions on this matter.
Sincerely, Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
As stated cc w/encl: Distribution via Listserv
EXTENSION REQUEST APPROVAL RELATED TO GENERIC LETTER 2004-02 CORRECTIVE ACTIONS FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION, UNIT NO.2 DOCKET NO. 50-412 By letter dated August 28, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082480045), as supplemented by letter dated October 29,2008 (ADAMS Accession No. ML083080094), FirstEnergy Nuclear Operating Company (licensee),
requested an extension to the corrective action due date of September 30, 2008, stated in Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, "Potentiallrnpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors," (GL 2004-02), for the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS 1 and 2). The stated intent of this extension was to allow additional time for completion of testing to be performed in order to identify the type and quantity of insulation required to be modified at BVPS- 2, and to finalize documentation for the supplemental response (including test reports and accompanying analyses) to GL 2004-02. The licensee requested an extension until startup following the fall 2009 refueling outage (RFO), which commences in October 2009, for BVPS-2.
The NRC staff has based its review of extension requests for the due date for completion of GL 2004-02 corrective actions on criteria stated in SECY-06-0078. Specifically, an extension may be granted if:
- the licensee has a plant-specific technical/experimental plan with milestones and schedule to address outstanding technical issues with enough margin to account for uncertainties, and
- the licensee identifies mitigative measures to be put in place prior to December 31,2007, and adequately describes how these mitigative measures will minimize the risk of degraded emergency core cooling system (ECCS) and containment spray system (CSS) functions during the extension period, and
- for proposed extensions beyond several months, a licensee's request will more likely be accepted if the proposed mitigative measures include temporary physical improvements to the ECCS sump or materials inside containment to better ensure a high level of ECCS sump performance.
Enclosure
-2 With regard to the first extension criterion, the licensee has provided a plant-specific technical/experimental plan, with milestones and schedules, to complete the GL 2004-02 corrective actions, as described in their letters dated August 28 and October 29, 2008.
The licensee retested for debris and chemical effects in the fall of 2008, using the predicted precipitant loading in accordance with WCAP-16793 and a protocol that introduced debris in accordance with the March 28, 2008 NRC Reviewers Guide. The planned testing was performed such that post-accident containment pressure was credited in defining an acceptable debris loading. Other planned activities included updating evaluations, analysis, and documentation to reflect the new test results once testing is completed.
A follow-up supplemental response to GL 2004-02 including the results of BVPS-2 debris and chemical effects testing, results of downstream effects analyses (both in-vessel and ex-vessel),
and details of corrective actions will be submitted to the NRC by April 30, 2009. This regulatory commitment is established in lieu of the BVPS-2 regulatory commitment identified in the licensee's letter dated February 14, 2008 (ADAMS Accession No. ML080510246).
With regard to the second extension criterion, the NRC staff considers that, based on the information provided in the licensee's letter dated August 28, 2008, the modifications, mitigation measures, and compensatory measures in effect at BVPS-2, minimize the risk of degraded ECCS and CSS functions during the extension period and the NRC staff has not identified any issues with the BVPS-2 corrective action plan.
With regard to the third extension criterion, the significant modifications discussed in the licensee's August 28, 2008, letter; in particular, the installation of large replacement strainers at BVPS-1 and 2, satisfies this extension criterion. Additionally, the licensee's letter dated August 28,2008, provides plant risk evaluations for BVPS-1 and 2. The NRC staff has not reviewed the analysis in detail, but agrees with the licensee's conclusion that the impact on risk for the requested extension period for actions to address chemical effects beyond the December 31, 2007, implementation date specified in GL 2004-02 is low based on the mitigative measures identified in this document.
The NRC staff has not identified any issues with the BVPS-2 corrective action plan and expects the licensee to follow the outlined planned for BVPS-2 as described in their August 28, 2008, letter. The BVPS-2 retesting should identify the type and quantity of insulation required to be modified. Additional required corrective actions resulting from the BVPS-2 retesting, including insulation modifications will be implemented prior to startup following the fall 2009 refueling outage (2R14).
The NRC believes that the licensee has a reasonable plan for BVPS-2 that should result in the installation of final GL 2004-02 corrective actions that provide acceptable strainer function with adequate margin for uncertainties. Furthermore, the NRC staff has concluded that the licensee has put mitigation measures in place at BVPS-2 to adequately reduce risk for the approved extension period discussed below.
Based on the licensee having satisfactorily addressed the NRC GL 2004-02 due date extension criteria as discussed above, the NRC staff finds it is acceptable to extend the completion date for corrective actions resulting from the BVPS-2 retesting, including insulation modifications,
-3 until startup following the fall 2009 RFO. In addition, a follow-up supplemental response to GL 2004-02 including the results of BVPS-2 debris and chemical effects testing (that includes credit for post-accident containment pressure), results of downstream effects analyses (both in-vessel and ex-vessel), the effects on NPSH margins, and details of corrective actions, will be submitted to the NRC by April 30, 2009.
ML090900193 *See memo dated March 30, 2009
- Concurre dbiv ema:'1 OFFICE LPLI-1/PM LPLI-1/LA DSS/SSIB/BC (A) DORULPLI-1/BC NAME NMorgan SLittle** DHarrison* MKowal DATE 3/31/09 3/31/2009 3/30/2009 3/31/09