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| Accession No. ML042360586) dated September 13, 2004, requesting that licensees address the issues raised by Generic Safety Issue (GSI) - 191, "Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance." | | Accession No. ML042360586) dated September 13, 2004, requesting that licensees address the issues raised by Generic Safety Issue (GSI) - 191, "Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance." |
| The stated purpose of GL 2004-02 was focused on demonstrating compliance with Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50 Section 50.46, "Acceptance Criteria For Emergency Core Cooling Systems For Light Water Reactors." Specifically the GL requested addressees to perform an evaluation of the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation and, if necessary take additional action to ensure system function, in light of the potential susceptibility of pressurized-water reactor (PWR) sump screens to blockage during a design basis accident requiring recirculation operation of the ECCS or 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 stated purpose of GL 2004-02 was focused on demonstrating compliance with Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50 Section 50.46, "Acceptance Criteria For Emergency Core Cooling Systems For Light Water Reactors." Specifically the GL requested addressees to perform an evaluation of the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation and, if necessary take additional action to ensure system function, in light of the potential susceptibility of pressurized-water reactor (PWR) sump screens to blockage during a design basis accident requiring recirculation operation of the ECCS or CSS, and on the potential for additional adverse effects due to debris blockage of flowpaths necessary for ECCS and CSS recirculation and containment drainage. |
| By letters dated March 1, 2005 (ADAMS Accession No. ML050670465), and September 1, 2005 (ADAMS Accession No. ML052500399), Duke Energy Carolinas, LLC (the licensee) provided responses to GL-2004-02 for the McGuire Nuclear Station, Units 1 and 2. In order for the NRC staff to complete its review, by letter dated February 9, 2006 (ADAMS Accession No. | | By letters dated March 1, 2005 (ADAMS Accession No. ML050670465), and September 1, 2005 (ADAMS Accession No. ML052500399), Duke Energy Carolinas, LLC (the licensee) provided responses to GL-2004-02 for the McGuire Nuclear Station, Units 1 and 2. In order for the NRC staff to complete its review, by letter dated February 9, 2006 (ADAMS Accession No. ML060370427) the NRC issued a request for additional information (RAI). |
| ML060370427) the NRC issued a request for additional information (RAI). | |
| By letters dated February 28, 2008 (ADAMS Accession No. ML080730131) and April 30, 2008, (ADAMS Accession No. ML081280488) the licensee provided responses to the RAis. The NRC staff reviewed the responses and concluded that additional information was still required. By letter dated November 18, 2008 (ADAMS Accession No. ML083080350) the NRC issued a second set of RAis. | | By letters dated February 28, 2008 (ADAMS Accession No. ML080730131) and April 30, 2008, (ADAMS Accession No. ML081280488) the licensee provided responses to the RAis. The NRC staff reviewed the responses and concluded that additional information was still required. By letter dated November 18, 2008 (ADAMS Accession No. ML083080350) the NRC issued a second set of RAis. |
| By letters dated September 30, 2010 (ADAMS Accession No. ML102870100), July 2, 2012 (ADAMS Accession No. ML12200A021), and July 31, 2013 (ADAMS Accession No. | | By letters dated September 30, 2010 (ADAMS Accession No. ML102870100), July 2, 2012 (ADAMS Accession No. ML12200A021), and July 31, 2013 (ADAMS Accession No. ML13231A113), the licensee provided responses to the second set of RAis. |
| ML13231A113), the licensee provided responses to the second set of RAis. | |
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| S. Capps The NRC staff performed a thorough review of all Duke Energy Carolinas, LLC responses and RAI supplements to GL 2004-02. The NRC staff conclusions have been documented (ADAMS Accession No. ML14085A065). Based on the NRC staff conclusions, the NRC staff finds that Duke Energy Carolinas, LLC has provided adequate information as requested by GL 2004-02. | | S. Capps The NRC staff performed a thorough review of all Duke Energy Carolinas, LLC responses and RAI supplements to GL 2004-02. The NRC staff conclusions have been documented (ADAMS Accession No. ML14085A065). Based on the NRC staff conclusions, the NRC staff finds that Duke Energy Carolinas, LLC has provided adequate information as requested by GL 2004-02. |
Latest revision as of 22:16, 5 February 2020
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MONTHYEARML0603704272006-02-0909 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 MC4692 & MC4693) Project stage: RAI ML0608904212006-03-0101 March 2006 Final Safety Evaluation Report Related to the License Renewal of Brunswick Steam Electric, Units 1 and 2 (TAC Nos. MC4639 and MC4640) Project stage: Approval ML0807301312008-02-28028 February 2008 Response to Request for Additional Information on GL-04-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0812804882008-04-30030 April 2008 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request ML0830803502008-11-18018 November 2008 Request for Additional Information (RAI) Regarding Supplemental Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Project stage: RAI ML0921605972009-07-28028 July 2009 Update on Status of 11/18/08 Request for Additional Information & Additional Testing Pursuant to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Request ML0921101202009-07-28028 July 2009 Catawba Nuclear Station Units 1 & 2 -Update on the Status of the November 21, 2008 Request for Additional Information (RAI) and Additional Testing Pursuant to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Reci Project stage: Request ML0922908922009-08-18018 August 2009 Notice of Conference Call with Duke Energy Carolinas, LLC (Duke), Regarding Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2) and McGuire Nuclear Station Units 1 and 2 Project stage: Other ML0927304602009-10-0707 October 2009 09/01/2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02. Meeting Handouts Project stage: Request ML0926700202009-10-0707 October 2009 Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02 Project stage: Other ML1012604632010-05-0707 May 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC (Duke) to Discuss Duke'S Responses to Generic Letter 2004-02 at Catawba 1 and 2 and McGuire 1 and 2 Project stage: Other ML1028701002010-09-30030 September 2010 Catawba Units 1 & 2, Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water.... Project stage: Request ML1029306502010-10-20020 October 2010 Notice of Forthcoming Conference Call with Duke Energy Carolinas, LLC Regarding McGuire Nuclear Station, Units 1 and 2 and Catawba Nuclear Station, Units 1 and 2, Project stage: Other ML1030810242010-11-10010 November 2010 Summary of November 1, 2010, Meeting with Duke to Discuss Responses to Generic Letter (GL) 2004-02 (Tac Nos. MC4673, MC4674, MC4692, and MC4693) Project stage: Meeting ML13141A4032013-05-0808 May 2013 Closure Options for Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter Project stage: Other ML13231A1132013-07-31031 July 2013 Closure Option 1 Response to In-Vessel Downstream Effects Request for Additional Information for Generic Safety Issue (GSI) 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution.. Project stage: Request ML14085A0652014-04-24024 April 2014 NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz Project stage: Request ML14090A4442014-04-24024 April 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4692 and MC4693) Project stage: Other 2009-08-18
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Category:Letter
MONTHYEARIR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 24, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, CLOSEOUT OF GENERIC LETTER, 2004-02, "POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED-WATER REACTORS" (TAC NOS. MC4692 AND MC4693)
Dear Mr. Capps:
The U.S. Nuclear Regulatory (NRC) issued Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors" (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML042360586) dated September 13, 2004, requesting that licensees address the issues raised by Generic Safety Issue (GSI) - 191, "Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance."
The stated purpose of GL 2004-02 was focused on demonstrating compliance with Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50 Section 50.46, "Acceptance Criteria For Emergency Core Cooling Systems For Light Water Reactors." Specifically the GL requested addressees to perform an evaluation of the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation and, if necessary take additional action to ensure system function, in light of the potential susceptibility of pressurized-water reactor (PWR) sump screens to blockage during a design basis accident requiring recirculation operation of the ECCS or CSS, and on the potential for additional adverse effects due to debris blockage of flowpaths necessary for ECCS and CSS recirculation and containment drainage.
By letters dated March 1, 2005 (ADAMS Accession No. ML050670465), and September 1, 2005 (ADAMS Accession No. ML052500399), Duke Energy Carolinas, LLC (the licensee) provided responses to GL-2004-02 for the McGuire Nuclear Station, Units 1 and 2. In order for the NRC staff to complete its review, by letter dated February 9, 2006 (ADAMS Accession No. ML060370427) the NRC issued a request for additional information (RAI).
By letters dated February 28, 2008 (ADAMS Accession No. ML080730131) and April 30, 2008, (ADAMS Accession No. ML081280488) the licensee provided responses to the RAis. The NRC staff reviewed the responses and concluded that additional information was still required. By letter dated November 18, 2008 (ADAMS Accession No. ML083080350) the NRC issued a second set of RAis.
By letters dated September 30, 2010 (ADAMS Accession No. ML102870100), July 2, 2012 (ADAMS Accession No. ML12200A021), and July 31, 2013 (ADAMS Accession No. ML13231A113), the licensee provided responses to the second set of RAis.
S. Capps The NRC staff performed a thorough review of all Duke Energy Carolinas, LLC responses and RAI supplements to GL 2004-02. The NRC staff conclusions have been documented (ADAMS Accession No. ML14085A065). Based on the NRC staff conclusions, the NRC staff finds that Duke Energy Carolinas, LLC has provided adequate information as requested by GL 2004-02.
The NRC staff finds the information provided demonstrates that debris will not inhibit the ECCS or CSS performance of its intended function in accordance with 10 CFR 50.46 to assure adequate long term core cooling following a design basis accident. Therefore, the NRC staff finds the licensee's responses to GL-2004-04 are adequate and considers GL-2004-02 closed for the McGuire Nuclear Station, Units 1 and 2. No further information or action is requested of the licensee.
If you have any questions, please call me at 301-415-2481.
Si(J;Jtf., \
G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 cc: Distribution via Listserv
ML14090A444 OFFICE NRR/LPL2-1 /PM NRR/LPL2-1/LA NRR/PGCB/ABC NRR/SSIB/ABC NRR/LPL2-1/BC NRR/LPL2-1/PM VCusumano NAME EM iller SFigueroa SStuchell RPascarelli EM iller (JStang for)
DATE 4/1/14 4/3/14 4/3/14 4/7/14 4/24/14 4/24/14