Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement
Results
Other: ML060890398, ML060950574, ML073511698, ML081200606, ML081790538, ML090980515, ML092080216, ML092440479, ML100190011, NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706), NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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MONTHYEARML0515202022005-06-0202 June 2005 6/2/05, Turkey Point, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0515201832005-06-0202 June 2005 Request for Additional Information, Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. Project stage: RAI ML0515202272005-06-0303 June 2005 6/3/05, Seabrook, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603703962006-02-0808 February 2006 RAI, 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 ML0603704382006-02-0808 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 Project stage: RAI ML0603801332006-02-0909 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 Project stage: RAI ML0603704912006-02-0909 February 2006 RAI - 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 ML0608903982006-04-11011 April 2006 Requested Extension of Completion Schedule for NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other ML0609505742006-04-13013 April 2006 Approval of GSI-191/GL 2004-02 Extension Request Project stage: Other NRC 2007-0085, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2007-11-16016 November 2007 Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2007-155, Request for Extension of Completion Date of the Generic Letter 2004-02 Actions2007-12-0707 December 2007 Request for Extension of Completion Date of the Generic Letter 2004-02 Actions Project stage: Request ML0735116982007-12-20020 December 2007 GSI-191/GL 2004-02 Extension Request Approval (Tac No. MC4705/4706) Project stage: Other L-2008-030, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-27027 February 2008 Supplemental 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 L-2008-033, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-02-28028 February 2008 Supplemental 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 L-2008-073, NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations2008-04-14014 April 2008 NRC Generic Letter 2004-02 Request for an Extension to the Completion Date for Ex-Vessel Downstream Effects Evaluations Project stage: Request ML0812006062008-04-29029 April 2008 Approval of Extension Request for GL 2004-02 Project stage: Other NRC 2008-0038, Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-06-0909 June 2008 Supplemental Response to Generic Letter 2004-02, Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request L-2008-137, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008 Supplemental 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 L-2008-138, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2008-06-30030 June 2008 Supplemental 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 ML0817905382008-07-0101 July 2008 Generic Safety Issue 191/Generic Letter 2004-02, Additional Extension Request Approval Project stage: Other ML0826106902008-09-17017 September 2008 Request for Additional Information Related to GL 2004-02 Project stage: RAI ML0826107052008-09-17017 September 2008 Request for Additional Information (RAI) Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors Project stage: RAI ML0834400782008-12-19019 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI ML0833806712008-12-22022 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information (TAC Mc 4725) Project stage: RAI ML0833001732009-01-0707 January 2009 GSI-191/GL 2004-02 Request for Additional Information Project stage: RAI ML0836589782009-01-16016 January 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI ML0835800232009-01-22022 January 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information Project stage: RAI L-2009-063, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2009-03-19019 March 2009 Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Response to RAI L-2009-062, Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-03-19019 March 2009 Response to NRC Request for Additional Information Regarding the Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Response to RAI NRC 2009-0033, Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-04-0707 April 2009 Response to Request for Additional Information GSI-191/GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0909805152009-04-0808 April 2009 SONGS - GSI-191 Chemical Effects Project stage: Other L-2009-084, Response to Nrc'S Request for Additional Information2009-04-22022 April 2009 Response to Nrc'S Request for Additional Information Project stage: Request NRC 2009-0053, Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706)2009-06-12012 June 2009 Request for Extension of Unit 1 and 2 Completion Dates for Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC MC4705/4706) Project stage: Request NRC 2009-0059, Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-06-29029 June 2009 Response to Request for Additional Information GSI-I91/GL 2004-02 Potential Lmpact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0920802162009-07-27027 July 2009 Notice of Forthcoming Conference Call with Florida Power and Light Concerning Turkey Point Generic Letter 2004-02 Response Project stage: Other L-2009-180, Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/20082009-07-30030 July 2009 Responses to Nrc'S Request for Additional Information on Generic Letter 2004-02 Supplemental Responses, Dated 02/27/2008 and 06/30/2008 Project stage: Supplement NRC 2009-0077, Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2009-07-31031 July 2009 Response to Request for Additional Information GSI-191/GL 2004-02 (TACs MC4705/4706) Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Response to RAI ML0924404792009-09-11011 September 2009 Summary of Conference Call with Florida Power & Light, to Discuss Generic Letter 2004-02, Potential Impact of Debris Blackage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor, Responses Project stage: Other NRC 2009-0113, Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706)2009-10-27027 October 2009 Generic Letter 2004-02, Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4705/4706) Project stage: Other ML1001900112010-01-19019 January 2010 Notice of Conference Call with Florida Power & Light Concerning Turkey Point Generic Letter 2004-02 Response Project stage: Other ML1003512132010-02-18018 February 2010 Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1009700022010-04-0909 April 2010 Request for Additional Information, Regarding GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI NRC 2010-0046, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors2010-06-11011 June 2010 Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation Durian Design Basis Accidents at Pressurized-Water Reactors Project stage: Supplement ML1019405202010-07-14014 July 2010 Notice of Conference Call with Florida Power and Light Company to Discuss Draft Responses to NRC Requests for Additional Information for Generic Letter 2004-02 Project stage: Draft RAI ML1007407182010-07-28028 July 2010 February 3, 2010, Turkey Point, Unit 3 & 4, Summary of Meeting with Florida Power & Light, on Generic Letter 2004-02 Project stage: Meeting L-2010-205, Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2010-09-17017 September 2010 Responses to Nrc'S Request for Additional Information Dated Feb. 18, 2010 Re Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009903062010-09-22022 September 2010 Request for Additional Information Regarding GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML1025902742010-12-17017 December 2010 Summary of Teleconference Meeting with Florida Power & Light Company, on Generic Letter 2004-02 Project stage: Meeting NRC 2011-0010, Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2011-02-0404 February 2011 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML1103502052011-02-0404 February 2011 Forthcoming Public Teleconference with NextEra Energy Seabrook, LLC, to Discuss Planned Testing for Seabrook Specific Erosion Project stage: Request 2009-01-07
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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
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Text
July 1, 2008 Mr. James McCarthy Site Vice President FPL Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - GENERIC SAFETY ISSUE 191/GENERIC LETTER 2004-02 ADDITIONAL EXTENSION REQUEST APPROVAL (TAC NOS. MC4705 AND MC4706)
Dear Mr. McCarthy:
By letter dated November 16, 2007, Florida Power and Light Energy Point Beach, LLC (FPLE-PB) requested an extension of the December 31, 2007, due date to the corrective action, stated in Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors (GL 2004-02) for Point Beach Nuclear Plant (PBNP), Units 1 and 2. By letter dated December 20, 2007, the NRC granted an extension until June 30, 2008.
By letter dated June 9, 2008, as supplemented by letter dated June 23, 2008, FPLE-PB requested to move the previously granted due date of June 30, 2008, until September 30, 2008.
The stated intent of this extension was to allow FPLE-PB additional time to complete chemical effects head loss testing, analysis of potential chemical precipitants, and evaluation of both in-vessel and ex-vessel downstream effects. FPLE-PB requested an extension to September 30, 2008, for completion of these activities and the submittal of the final results to the NRC.
The NRC has determined that for PBNP Units 1 and 2, it is acceptable to extend the due date for completion of strainer chemical effects testing and in-vessel and ex-vessel downstream effects evaluations as described in the enclosed NRC staff evaluation of the extension request, until September 30, 2008. If you have any questions, please contact me at (301) 415-1424.
Sincerely,
/RA/ JPoole for Jack Cushing, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
As stated cc w/encl: See next page
ML081790538 *Per memo dated June 27, 2008 OFFICE LPL3-1/PM LPL3-1/LA DSS/SSIB/BC LPL3-1/BC JCushing/JPoole THarris MScott* LJames NAME for DATE 6/ 30 /08 6/27/08 6/27/08 7/ 01 /08 Point Beach Nuclear Plant, Units 1 and 2 cc:
Mr. Antonio Fernandez Licensing Manager Senior Attorney FPL Energy Point Beach, LLC FPL Energy , LLC 6610 Nuclear Road P. O. Box 14000 Two Rivers, WI 54241 Juno Beach, FL 33408-0420 Mr. Ken Duveneck Mr. Mano Nazar Town Chairman Senior Vice President and Town of Two Creeks Nuclear Chief Operating Officer 13017 State Highway 42 FPL Energy, LLC Mishicot, WI 54228 P. O. Box 14000 Juno Beach, FL 33408-0420 Resident Inspector's Office U.S. Nuclear Regulatory Commission Mr. R. S. Kundalkar 6612 Nuclear Road Vice President Two Rivers, WI 54241 Nuclear Technical Services FPL Energy, LLC Chairman P. O. Box 14000 Public Service Commission of Wisconsin Juno Beach, FL 33408-0420 P.O. Box 7854 Madison, WI 53707-7854 J. Kitsembel Electric Division Mr. J. A. Stall Public Service Commission of Wisconsin Senior Vice President and P. O. Box 7854 Chief Nuclear Officer Madison, WI 53707-7854 FPL Group P. O. Box 14000 Mr. M. S. Ross Juno Beach, FL 33408-0420 Managing Attorney FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420
EVALUATION OF EXTENSION REQUEST TO COMPLETE CORRECTIVE ACTIONS GENERIC SAFETY ISSUE -191 ASSESSMENT OF DEBRIS ACCUMULATION ON PWR SUMP PUMP PERFORMANCE (GSI-191)/GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS (GL-2004-02)
POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301 By letter dated June 9, 2008, (Agencywide Documents Access and Management System (Adams) Accession No. ML081620337), as supplemented by letter dated June 23, 2008 (ML081760129), Florida Power and Light Energy Point Beach, LLC (FPLE-PB), the licensee, requested an extension to the Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors, corrective action due date for Point Beach Nuclear Plant (PBNP) Units 1 and 2. The stated intent of this extension was to allow FPLE-PB additional time to complete chemical effects head loss testing, analysis of potential chemical precipitants, and evaluation of both in-vessel and ex-vessel downstream effects. FPLE-PB requested an extension to September 30, 2008, for completion of these activities and the submittal of the final results to the NRC.
In its letter dated November 16, 2007 (ML073230345), FPLE-PB requested an extension to allow FPLE-PB additional time to complete chemical effects testing, reevaluate ex-vessel downstream effects to address Westinghouse WCAP-16406-P, Evaluation of Downstream Sump Debris Effects in Support of GSI 191, Revision 1, and complete an evaluation of in-vessel downstream effects. FPLE-PB requested an extension to June 30, 2008. The NRC approved an extension for completion of PBNP Units 1 and 2 sump clogging corrective actions from the GL 2004-02 due date of December 31, 2007, until June 30, 2008 (NRC letter dated December 20, 2007, ML073511698).
FPLE-PB stated in its June 9, 2008, letter, that it has not been able to conduct the confirmatory head loss testing of the replacement emergency core cooling system (ECCS) sump screens as a result of limited test facility availability. The request for an additional extension is due to demonstration by industry testing that actual zone-of-influence (ZOI) values, specifically the ZOI for NUKON insulation, are substantially smaller than the default values in NEI 04-07. Therefore, FPLE-PB is revising, for PBNP Units 1 and 2, the debris generation analyses to reflect these later test results and reduce the total quantity of fibrous debris from NUKON. As a result of these supporting analytical changes, the scheduled large flume testing for FPLE-PB at Alden Laboratories has been delayed to the week of July 7, 2008.
FPLE-PB also stated in its June 9, 2008, letter, that the testing contractors have indicated that the preparation, review and approval of the final test reports and supporting calculations will require 6 weeks following completion of testing. FPLE-PB stated that it intends to develop the final submittal to the NRC in parallel, and to provide that submittal by September 30, 2008.
The June 9, 2008, letter, revises the following FPLE-PB regulatory commitment stated in Point Beachs supplemental response to GL 2004-02 dated February 29, 2008 (ML080630613), as follows:
The final submittal of the testing and analyses demonstrating acceptable long-term ECCS performance in the areas of downstream and chemical effects will be made by September 30, 2008.
The NRC has based its reviews for granting extensions to the due date for completion of GL 2004-02 corrective actions on the criteria stated in SECY-06-0078 Status of Resolution of GSI-191, Assessment of [Effect of] Debris Accumulation on PWR Sump Performance.
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 ECCS and containment spray system functions during the extension period.
The SECY also states that for proposed extensions beyond several months, a licensees 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.
With regard to the first extension criterion, FPLE-PB has previously provided, as described in the previous extension request letter cited above, a plant-specific technical/experimental plan, with milestones and schedules, to complete the GL 2004-02 corrective actions. FPLE-PBs letter dated June 9, 2008, stated that the scheduled large flume testing for Point Beach at Alden Laboratories has been delayed to the week of July 7, 2008, and that final test reports and supporting calculations will require 6 weeks following completion of testing. FPLE-PB intends to develop the final submittal to the NRC in parallel, and to provide that submittal by September 30, 2008.
FPLE-PBs letter also stated that the replacement screens have been installed, the affected procedures have been revised to reflect the operating requirements of the screens, and there are no remaining modifications or changes planned.
In its letter dated June 23, 2008, FPLE-PB stated that the recent industry experience had prompted FPLE-PB to develop contingency plans in the event that the plant-specific large flume testing scheduled in July 2008, produces unacceptable results. FPLE-PB stated in this letter that contingencies considered included:
- Further steam jet testing to reduce the asbestos, CalSil, and generic fiberglass insulation destruction pressures from the conservative default values endorsed in NEI 04-07.
- Alternative test protocols that attempt to more closely and realistically simulate the settling of debris on the floor of containment prior to the start of containment sump recirculation.
- Reduction of fibrous insulation debris sources.
- Enhancing the existing metallic insulation jacketing with additional banding to reduce the debris that could be generated.
- Installation of additional debris interceptors.
FPLE-PB stated in its June 23, 2008, letter, that based on the demonstrated efficacy of debris interceptors tested for other facilities, the installation of additional debris interceptors is anticipated to be the most appropriate modification to obtain near-term closure of GL 2004-02 at PBNP Units 1 and 2. FPLE-PB also stated in its letter that the July 2008, test window scheduled for PBNP Units 1 and 2 at Alden Laboratories includes sufficient time to complete two full tests, in addition to the baseline clean strainer test.
Therefore, FPLE-PB anticipates the following contingency testing:
- 1. A design-basis debris load test, with the debris introduction sequenced to demonstrate both thin bed performance and full design loading performance.
- 2. In the event of an unsatisfactory result during the first test, the second test run will include a debris interceptor located upstream of the test strainer. This test should be sufficient to demonstrate the effectiveness of a debris interceptor with the PBNP Units 1 and 2 specific debris loading and flow velocities.
FPLE-PB stated that, if needed, the design and installation of debris interceptors would proceed expeditiously for PBNP Units 1 and 2. Specifically, FPLE-PB stated in its June 23, 2008, letter, that it anticipates that the PBNP Unit 1 installation could be expedited to occur during the fall 2008 refueling outage, and that the PBNP Unit 2 installation could occur during the fall 2009 refueling outage.
With regard to the second extension criterion, the licensee stated in its letter dated June 9, 2008, that the bases for a reasonable assurance of operability with the installed replacement strainers is unchanged from that detailed in its letter dated November 16, 2007, and that further bases are provided in FPLE-PBs supplemental response to GL 2004-02, dated February 29, 2008. In addition, the licensee stated that mitigative measures that were described in the November 16, 2007, letter, remain in effect.
The NRC staff evaluation of the previous extension request concluded that FPLE-PB had put mitigation measures in place to adequately reduce risk for the previous requested extension period (June 30, 2008), as stated in the NRC extension approval letter cited above. The installation of larger surface area sump strainers on both units is the most significant of these
mitigative measures. Redundant 1500 ft2 strainers replaced the 21 ft2 sump screens. In addition, the licensee stated in its letter dated November 16, 2007, that preliminary testing of the strainers indicates that there is significant margin to accommodate potential chemical precipitate effects.
The NRC staff believes that FPLE-PB has a reasonable plan for PBNP Units 1 and 2 that should result in the completion of final GL 2004-02 corrective actions that provide acceptable strainer function with adequate margin for uncertainties. The additional time requested in the June 9, 2008, letter, is considered to be of low safety concern given the mitigation measures and plant improvements already in place. 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 GL 2004-02 corrective actions associated with strainer performance testing, final analysis and related licensing activities, as described in this enclosure, for PBNP Units 1 and 2, from June 30, 2008, to September 30, 2008. The NRC expects PBNP Units 1 and 2 to place a high priority on completing remaining actions and updating the plants licensing bases as soon as possible.
Additionally, the NRC has reviewed FPLE-PBs contingency plan as described in this extension approval. The NRC finds the contingency actions described in this plan to be acceptable, and, if needed, expects FPLE-PB to expeditiously perform the contingency actions as described above.
This extension approval does not represent approval of an additional extension period for corrective actions after September 30, 2008. If further corrective actions are determined by FPLE-PB to be necessary for PBNP Units 1 and 2, FPLE-PB would need to submit an additional extension for NRC approval.