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MONTHYEARML0603704632006-02-0909 February 2006 RAI, Response to GL-2004-02, Potential Impact to Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors. Project stage: RAI ML0721205432007-08-0909 August 2007 Draft Open Items from Staff Audit of Corrective Actions to Address GL 2004-02 Project stage: Draft Other ML0729706052007-10-24024 October 2007 Exigent License Amendment Request Re Alternative Containment Analysis Methodology Supporting Information - Gothic Model Input Files Project stage: Other ML0727404002007-11-15015 November 2007 Corrective Actions for Generic Letter 2004-02 Project stage: Acceptance Review ML0731905532007-11-15015 November 2007 North Anna, Units 1 and 2, and Surry, Units 1& 2, Request for Extension of Completion Dates for Corrective Actions Regarding NRC Generic Letter 2004-02 Project stage: Request ML0731001672007-11-15015 November 2007 Report on Results of Staff Audit of Corrective Actions to Address Generic Letter 2004-02 Project stage: Other ML0734505942007-12-13013 December 2007 Approval of Extension of Completion Dates for Corrective Actions of Generic Letter 2004-02 Project stage: Other ML0806505622008-02-29029 February 2008 Supplemental Response to NRC GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806503142008-02-29029 February 2008 Kewaunee, NRC Generic Letter 2004-02 Supplemental Response, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0806505632008-02-29029 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0814207932008-05-21021 May 2008 North Anna, Units 1 and 2, and Surry, Units 1 & 2, NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Request.. Project stage: Request ML0814306122008-05-22022 May 2008 Units 1 & 2 - NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors Request for Interim. Project stage: Request ML0814905722008-05-29029 May 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0818302472008-07-0101 July 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML0821301802008-08-0404 August 2008 Audit Report of Corrective Actions for Generic Letter 2004-02 Project stage: Other ML0825404952008-09-0505 September 2008 North Anna and Surry Power Station, Units 1 and 2, NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Accidents at Pressurized-water Reactors Request for Extension of Completion Dates for Corrective Actions Project stage: Request ML0827300222008-09-29029 September 2008 Request for Extension of Completion Dates for Generic Letter 2004-02 Corrective Actions Project stage: Other ML1012506232010-05-24024 May 2010 Summary of Meeting with Dominion Nuclear Connecticut, Inc. (DNC) to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI 2008-05-21
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Category:Memoranda
MONTHYEARML23151A5472023-06-0101 June 2023 Public Meeting Summary - 2022 Annual Assessment Meeting Regarding North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station ML22130A1702022-05-20020 May 2022 Summary of April 21, 2022, Public Meeting to Discuss Potential Emergency Preparedness License Amendment Request ML22130A0332022-05-0909 May 2022 Public Meeting Summary 2021 Annual Assessment Meeting Regarding North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station, Docket Nos. 50-280 and 50-281, Meeting Number 20220349 ML22034A3932022-02-16016 February 2022 Calendar Year 2021 Security Baseline Completion Memo ML21293A0992021-12-10010 December 2021 Meeting Summary for Draft Supplemental Environmental Impact Statement Public Meeting ML21221A3012021-10-18018 October 2021 June 24, 2021, Meeting Summary: Discussion of Dominion'S Response to Select Staff Requests for Additional Information on Subsequent License Renewal Application (EPID No. L-2020-SLR-0000) - Memo ML21239A0642021-09-0202 September 2021 August 27, 2021, Summary: Discussion Between NRC and Dominion Regarding the NAPS Subsequent License Renewal - an Inconsistency in Documentation Regarding RCP Code Case N-481 (EPID No. L-2020-SLR-0000) - Memo ML21236A0512021-08-27027 August 2021 August 16, 2021, Meeting Summary: Discussion of Aging Management of Cyclic Fatigue in the Subsequent License Renewal Application (EPID No. L-2020-SLR-0000) - Memo ML21221A0262021-08-26026 August 2021 Meeting Summary Regarding Discussion of Dominion'S Response to Select Staff Requests for Additional Information on Subsequent License Renewal Application ML21221A1362021-08-10010 August 2021 Meeting Summary: Discussion of Dominion'S Response to Select Staff Requests for Additional Information on Subsequent License Renewal Application ML21145A2122021-06-0909 June 2021 Meeting Summary: Discussion of Dominion'S Response to Select Staff Requests for Additional Information on Subsequent License Renewal Application (EPID No. L-2020-SLR-0000) - Memoranda ML21131A1612021-05-11011 May 2021 Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Virgil C. Summer Nuclear Station, Docket No. 50-395; North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station, Docket Nos. 50-280 and 50-281, Meeting ML21027A0232021-01-28028 January 2021 Summary of January 26, 2021 Closed Meeting with Dominion Energy Regarding Performance of Force on Force Exercises in a Pandemic Environment ML20350B4562020-12-17017 December 2020 Summary of the Historic and Cultural Resources Environmental Audit Meeting Related to the Review of the Subsequent License Renewal Application for the North Anna Power Station, Units 1 and 2 ML20136A1752020-05-15015 May 2020 Sur 2019 Aam Meeting Summary ML19190A2862019-07-16016 July 2019 Summary of July 7, 2019, Public Meeting with Dominion to Discuss Open Phase Condition RAI Responses ML19165A1122019-06-14014 June 2019 Memoranda to File Environmental Assessment and Finding of No Significant Impact for the Virginia Electric and Power Company, Dominion Energy Kewaunee, Inc., and Dominion Nuclear Connecticut, Inc.'S Decommissioning Funding Plans Submitted ML19128A3432019-05-0808 May 2019 Public Meeting Summary - 2018 Annual Assessment Public Meeting Regarding North Anna Power Station, Docket Nos. 50-338 and 50-339 ML18151A4682018-05-29029 May 2018 Public Meeting Summary - 2017 Annual Assessment Public Meeting Regarding North Anna Power Station, Docket Nos. 50-338 and 50-339 ML17209A7652017-08-0303 August 2017 Fire Protection Input for Millstone Power Station Unit 2 Exemption from Title 10 of the Code of Federal Regulations Part 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability, for Use of Operator Manual Actions ML17137A0932017-05-17017 May 2017 Request for Additional Information, Alternative to Reactor Vessel Threads in Flange Examination Requirements ML17123A2092017-05-0303 May 2017 Summary of Meeting to Discuss Annual Assessment of the North Anna Power Station, Units 1 and 2 with the Public for the Period of January 1, 2016 Through December 31, 2016 ML16215A0752016-08-24024 August 2016 North Anna Power Station - Audit Report for Proposed License Amendment to Revise the Technical Specifications to Address the Issue Identified in Westinghouse Documents NSAL-09-5. Rev. 1 and NSAL-15-I ML16209A4132016-07-27027 July 2016 Safety Evaluation For North Anna Power Station, Units 1 And 2, Proposed License Amendment To Revise The Technical Specifications To Address The Issue Identified In Westinghouse Documents NSAL-09-5. Rev. 1 and NSAL-15-I (TAC No. MF7186 and MF7187) ML16139A5892016-05-23023 May 2016 North Anna Trip Report, April 11, 2016 ML16124A7582016-05-0303 May 2016 April 14, 2016, Summer of Public Meeting - North Anna, Units 1 and 2 ML16098A5302016-04-14014 April 2016 Audit Plan - Application for Amendment North Anna Power Station, Units 1 and 2. the Proposed License Amendment Revises the Issues Identified in Westinghouse Documents NSAL-09-5, Rev 1 and NSAL-15-1 ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML15253A4032016-03-11011 March 2016 Recommendation for Dispositioning Proposed Generic Issue on the Effects of Downstream Dam Failures on Nuclear Power Plants ML15281A2672015-10-28028 October 2015 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief ML15232A8112015-08-24024 August 2015 Evaluation of Information Related to Commitments 6 and 8 from Confirmatory Action Letter No. NRR-2011-002 ML15238B5922015-08-17017 August 2015 Review of Commitment Action Completion Confirmation Action Letter Regarding Earthquake in 2011 ML15230A2162015-08-13013 August 2015 Review of Commitment Actions in Confirmatory Action Letter Regarding Earthquake in 2011 ML15128A5462015-05-0808 May 2015 Summary of Public Meeting with North Anna, Units 1 and 2 to Discuss the Annual Assessment with the Public ML14101A1202014-04-11011 April 2014 Public Meeting Summary - North Anna Power Station, Docket Nos. 50-338, 50-339 ML1208704282012-03-26026 March 2012 Memo C Bladey, Adm, Notice of EA and Fonsi - VEPCO, North Anna Power Station (72-1030, 50-338, 50-339, 72-56) ML13127A3682012-03-13013 March 2012 Memo from M. Case to P. Hiland, Subject: Review of Draft Nureg/Cr - Xxxx Entitled, Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Vali ML13219A0462012-03-13013 March 2012 Memo from M. Case to P. Hiland, Subject: Review of Draft NUREG/CR-XXXX Entitled, Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Valida ML11277A0292011-10-0404 October 2011 Summary Audit Report of North Anna Post-Seismic Fuel Inspections ML11271A1782011-10-0303 October 2011 Review of Topical Report, Revision 11 for Kewaunee Power Station and ISFSI, Millstone Power Station, Units 1, 2, & 3 and ISFSI, North Anna Power Station, Units 1 & 2 and ISFSI, Surry Power Station, Units 1 & 2 and ISFSI (Tac ME6649, ME6650, ML12054A1452011-09-19019 September 2011 Email from G. Thomas, NRR to D. Hoang, NRR Et Al. FW: North Anna Seismic Report - Summary Report of August 23/2011 Earthquake Response and Restart Readiness Determination Plan North Anna Power Station Units 1 and 2 and ISFSI ML12053A4082011-09-15015 September 2011 Email from M. Khanna, NRR to K. Karwoski, NRR Et Al. on North Anna Seismic Issue Restart Action Plan Draft Final.Docx ML11249A1562011-09-0707 September 2011 Notice of Forthcoming Meeting with Virginia Electric and Power Company (Vepco), on the August 23, 2011 Earthquake Near the North Anna Power Station, Unit Nos. 1 and 2 ML12005A0302011-08-30030 August 2011 Letter from V. Mccree, Region II to M. Franke, Region II; Augmented Inspection Charter to Evaluate Total Loss of Offsite Power, Dual Unit Reactor Trips and Plant Equipment Issues Following a Seismic Event at North Anna ML11171A7022011-06-29029 June 2011 Final Response to TIA 2011-003, Nine Mile Point Nuclear Station Unit 1 Licensing Basis for Degraded Grid Relay Time Delays ML1027800722010-10-0404 October 2010 Special Inspection Charter ML1023100152010-08-18018 August 2010 Notice of Meeting with Virginia Electric & Power to Discuss Proposed Addition of Analytical Methodology to Core Operating Limits Report ML1017304812010-06-22022 June 2010 Forthcoming Meeting with Virginia Electric and Power Company (Vepco), Regarding North Anna Power Station, Unit Nos. 1 and 2 to Discuss Fuel Transition Licensing Approach, Schedule of Submittals, Alignment of Resources and Key Deliverables ML0915605552009-06-0808 June 2009 Notice of Meeting with Virginia Electric and Power Co. (Dominion) to Discuss a Proposed License Amendment Regarding the Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System 2023-06-01
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August 9, 2007 MEMORANDUM TO: Evangelos C. Marinos, Chief, Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Michael L. Scott, Chief /RA by Ralph Architzel for/
Safety Issue Resolution Branch Division of Safety Systems Office of Nuclear Reactor Regulation
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, DRAFT OPEN ITEMS FROM STAFF AUDIT OF CORRECTIVE ACTIONS TO ADDRESS GENERIC LETTER 2004-02 (TAC NO. MC4696 AND MC4697)
Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, requested that all pressurized-water reactor licensees (1) evaluate the adequacy of the emergency sump recirculation function with respect to potentially adverse effects associated with post-accident debris, and (2) implement any plant modifications determined to be necessary. Virginia Electric and Power Company (the licensee) has conducted an evaluation of recirculation sump performance for the North Anna Power Station, and is conducting significant modifications, including installation of new recirculation sump strainers at both units.
The staff conducted a detailed audit of the new sump design and associated analyses, evaluations, testing and modifications for North Anna Power Station during the week of July 16, 2007. This audit was an in-process snapshot of the licensees GL 2004-02 corrective actions, which are to be completed by December 31, 2007. This is one of several audits to be conducted over an approximate two-year period to establish a sample basis to assist in verifying the adequacy of pressurized-water reactor licensee corrective actions, as dicussed in GL 2004-02.
This memorandum transmits the draft open items from the audit. These draft open items are subject to change as the audit report is developed, finalized and issued. Please note that the audit report will contain no conclusion as to the overall adequacy of the licensees GL 2004-02 corrective actions. That conclusion will be reached when the final GL 2004-02 response (which the staff expects to receive by December 31, 2007) is reviewed. That response is expected to respond to the audit report open items, as well as generic requests for additional CONTACT: Ralph Architzel, DSS/SSIB Joe Golla, DPR/PGCB (301) 415-2804 (301) 415-1002
information issued to the licensee in 2006, and will describe the finalized GL 2004-02 corrective actions for North Anna Power Station.
Docket Nos: 50-338 and 50-339
Enclosure:
As stated
information issued to the licensee in 2006, and will describe the finalized GL 2004-02 corrective actions for North Anna Power Station.
Docket Nos: 50-338 and 50-339
Enclosure:
As stated CONTACT: Ralph Architzel, SSIB/DSS (301)415-2804 Joe Golla, PGCB/DPR (301)415-1002 DISTRIBUTION: PUBLIC SSIB R/F JGolla RJervey North Anna Power Station Audit Team ADAMS Accession Number: ML072120543 NRR-106 OFFICE DSS/SSIB DCI/CSGB:BC DSS/SSIB:BC NAME RArchitzel AHiser MScott /RA by RArchitzel for/
DATE 08/01/07 08/02/07 08/09/07 OFFICIAL RECORD COPY
DRAFT OPEN ITEMS FOR JULY 2007 AUDIT OF NORTH ANNA POWER STATION CORRECTIVE ACTIONS FOR GENERIC LETTER 2004-02 (TAC NOS. MC4696 AND MC4697)
Open Item: Net Positive Suction Head Available Calculation The calculated net positive suction head available margins for the low head safety injection, inside recirculation spray and outside recirculation spray pumps were non-conservative. The margins for these pumps were overestimated by approximately 0.6 feet of head as a result of an error in the calculation of the static head of liquid.
Open Item: Justification for Time-Dependent Head Loss Assumptions The licensee assumed that at the beginning of low head safety injection operation in the recirculation mode there would be no debris accumulation on the low head safety injection strainer, and that the strainer head loss due to debris would reach the peak thin bed head loss after a period of time. The licensee needs to provide the basis for these assumptions.
Open Item: Temperature Scaling of Head Loss Test Data The licensee scaled test head losses to plant sump conditions based only on temperature-driven viscosity variations. Test phenomena driven by differential pressure (e.g., opening of paths through the bed) should be considered as well.
Open Item: Justification for 5D ZOI for qualified coatings in containment The licensee is using a five pipe diameter zone of influence for qualified coatings in containment, based on a Westinghouse test report currently under NRC review. This item will remain open pending completion of that review.
Open Item: Evaluate Chemical Effects The licensee's chemical effects analysis was incomplete at the time of the audit. Also, the licensee has not evaluated the contribution of coatings to chemical effects by: (1) leaching constituents that could form precipitates or affect other debris; and (2) changing form due to the pool environment. Since the licensees integrated chemical effects testing plans have not been completed, the staff could not review the application of the debris bed head loss acceptance criteria to verify that the long-term and short-term acceptance criteria are bounding with respect to intermediate conditions.
Open Item: Downstream Effects Evaluations Preliminary The licensees evaluations of the downstream effects of debris on systems and components are preliminary, based in part on the generic methodology of WCAP-16406-P which is under review by the NRC staff. Conclusions and findings of the staff review need to be applied to the North Anna Power Station evaluation of post-LOCA downstream effects.
ENCLOSURE
Open Item: Use of Manufacturers Pump Performance Curves The pump performance inputs considered in the preliminary downstream components evaluation were obtained from manufacturers pump performance curves. The evaluation should consider the use of degraded pump curves or in-service testing curves as these curves better represent actual system operating conditions.
Open Item: Emergency Core Cooling System (ECCS) Minimum and Maximum Operating Points The preliminary downstream component evaluation did not consider the use of minimum and maximum system operating points; instead, best-efficiency performance values were used. The ECCS operating point values were not referenced back to system bases calculations.
Open Item: Fixed Throttle Valve Setting The downstream component evaluation did not reference operating procedures or testing history in order to demonstrate high confidence that throttle valves will remain in their fixed position during ECCS operation. Throttle valve fixed position is the basis for assuming the systems hydraulic resistance to be fixed.
Open Item: ECCS Instrument Locations The evaluation documented that the ECCS instrument locations are adequate because of an assumption of good engineering practice. This assumption needs to be verified, such as by means of isometrical drawings or an ECCS survey.
Open Item: Overall Downstream ECCS Evaluation The licensee had yet to perform an overall system evaluation that integrates the results of the downstream components evaluation.
The evaluation should address compliance with 10 CFR 50.46, Long Term Core Cooling.
Open Item: Quantification and Assessment of Downstream Effects That Cause Seal Leakage The licensee did not quantify seal leakage associated with downstream effects into the Auxiliary Building, nor evaluate the effects on equipment qualification, sumps and drains operation, or on room habitability.
Open Item: Debris Bypass Testing The licensee had not made a final determination on how the bypass testing data is going to be implemented in the downstream effects evaluation for ECCS and internal vessel components.
Open Item: Downstream Effects-Core Blockage Although downstream evaluations were in progress during the audit, the licensee has not made any final conclusions as to whether the cores at North Anna Power Station could be blocked by debris following a LOCA, and this area is incomplete.
Open Item: Assessment of Qualified Coatings The licensee needs to justify that visual assessment techniques can accurately identify degraded qualified coatings in containment, perform physical testing that can be correlated to DBA performance, or assume all of the coatings fail. This will remain an open item pending submission and NRC approval of the Electric Power Research Institute/Nuclear Utility Coatings Council test report.