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 type:NRC
MONTHYEARNRC 2023-0013, Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-07-0707 July 2023 Response to Regulatory Information Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations NRC 2023-0006, Post-Exam Submittal Cover Letter2023-03-0101 March 2023 Post-Exam Submittal Cover Letter NRC 2023-0005, Report of Changes to Emergency Plan2023-02-21021 February 2023 Report of Changes to Emergency Plan NRC 2022-0032, Sixth 10-Year Interval Inservice Testing (1ST) Program Plan2022-09-30030 September 2022 Sixth 10-Year Interval Inservice Testing (1ST) Program Plan NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022 License Amendment Request 295, Beacon Power Distribution Monitoring System NRC 2022-0019, Report of Changes to Emergency Plan2022-07-13013 July 2022 Report of Changes to Emergency Plan NRC 2022-0022, Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2,2022-07-11011 July 2022 Response to Request for Supplemental Information (Rsi) Regarding License Amendment Request (LAR) 297, Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, NRC 2022-0015, Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report2022-04-27027 April 2022 Fall 2021 Unit 2 (U2R38) Steam Generator Tube Inspection Report NRC 2022-0014, 2021 Annual Monitoring Report2022-04-14014 April 2022 2021 Annual Monitoring Report NRC 2021-0012, Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41)2022-04-0707 April 2022 Core Operating Limits Report (COLR) Unit 1 Cycle 41 (U 1 C41) NRC 2022-0003, License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process2022-03-25025 March 2022 License Amendment Request 296, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Systems Using the Consolidated Line Item Improvement Process NRC 2022-0006, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2022-02-22022 February 2022 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections NRC 2022-0004, Report of Changes to Emergency Plan2022-02-0909 February 2022 Report of Changes to Emergency Plan NRC 2022-0005, Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2022-02-0101 February 2022 Refueling Outage U2R38 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2022-0001, Report of Changes to Emergency Plan2022-01-11011 January 2022 Report of Changes to Emergency Plan NRC 2021-0046, Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40)2021-10-28028 October 2021 Core Operating Limits Report (COLR) Unit 2 Cycle 39 (U2C39) and Changes to Unit 1 COLR Unit 1 Cycle 40 (U1C40) NRC 2021-0031, Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-0562021-07-15015 July 2021 Registration of Holtec Hi STORM Casks HI-STORM-37-054, HI-STORM-37-055, and HI-STORM-37-056 NRC 2021-0027, Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-0532021-06-30030 June 2021 Registration of Holtec Historm Casks HISTORM-37-051, HISTORM-37-052, and HISTORM-37-053 NRC 2021-0028, Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism2021-06-23023 June 2021 Generic Letter 2004-02 Containment Sump Debris Transport Calculation Non-Conservatism NRC 2021-0021, 2020 Annual Monitoring Report2021-04-29029 April 2021 2020 Annual Monitoring Report NRC 2021-0019, Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to Regulatory Information Summary 2021-01 Preparation and Scheduling of Operator Licensing Examinations NRC-2021-0010, CFR 50.59 Evaluation and Commitment Change Summary Report2021-04-0202 April 2021 CFR 50.59 Evaluation and Commitment Change Summary Report NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021 Technical Specification Bases and Technical Requirement Manual Change Summary NRC 2021-0006, Report of Changes to Emergency Plan2021-03-18018 March 2021 Report of Changes to Emergency Plan NRC 2021-0005, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-022021-02-11011 February 2021 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 2004-02 NRC 2021-0002, Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2021-01-21021 January 2021 Refueling Outage U1 R39 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report2021-01-21021 January 2021 Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report NRC 2021-0001, Report of Changes to Emergency Plan2021-01-13013 January 2021 Report of Changes to Emergency Plan NRC 2020-0044, Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise2020-12-0808 December 2020 Response to Request for Additional Information Request for Exemption from 10 CFR 73, Appendix B, Section VI Regarding Annual Force-On-Force Exercise NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020 Application for Subsequent Renewed Facility Operating Licenses NRC 2020-0039, Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40)2020-11-0202 November 2020 Core Operating Limits Report (COLR) Unit 1 Cycle 40 (U1 C40) NRC 2020-0031, NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-0812020-10-0505 October 2020 NextEra Energy Point Beach, LLC Response to Apparent Violation in NRC Inspection Report 05000266/2020012, 05000301/2020012: EA-20-081 NRC 2020-0029, Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-09-15015 September 2020 Supplement to License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0024, Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements2020-08-17017 August 2020 Response to Request for Additional Information Request for Exemption from Certain Operator Requalification Requirements NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020 License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss NRC 2020-0023, NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations2020-08-12012 August 2020 NextEra Energy Point Beach, LLC - Revised Response to Regulatory Information Summary 2020-01, Preparation and Scheduling of Operator Licensing Examinations NRC 2020-0021, Response to NRC Inspection Report and Preliminary White Finding2020-08-12012 August 2020 Response to NRC Inspection Report and Preliminary White Finding NRC 2020-0018, Report of Changes to Emergency Plan2020-07-15015 July 2020 Report of Changes to Emergency Plan NRC-2020-0016, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-12012 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic NRC 2020-0012, Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations2020-05-20020 May 2020 Refueling Outage U2R37 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations NRC 2020-0008, Report of Changes to Emergency Plan2020-04-0606 April 2020 Report of Changes to Emergency Plan NRC 2020-0007, Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38)2020-03-27027 March 2020 Core Operating Limits Report (COLR) Unit 2 Cycle 28 (U2C38) NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020 License Amendment Request 289: Tornado Missile Protection Licensing Basis NRC 2020-0001, Pressure Temperature Limits Report (PTLR)2020-01-0909 January 2020 Pressure Temperature Limits Report (PTLR) NRC 2019-0044, Report of Changes to Emergency Plan2019-11-0101 November 2019 Report of Changes to Emergency Plan NRC 2019-0036, Submittal of 2018 Update to Final Safety Analysis Report2019-10-18018 October 2019 Submittal of 2018 Update to Final Safety Analysis Report NRC 2019-0037, Technical Specification Bases Change Summary2019-10-18018 October 2019 Technical Specification Bases Change Summary NRC 2019-0034, Technical Requirements Manual Change Summary2019-10-18018 October 2019 Technical Requirements Manual Change Summary NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report2019-10-18018 October 2019 CFR 50.59 Evaluation and Commitment Change Summary Report NRC 2019-0042, NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information2019-10-17017 October 2019 NextEra Energy Point Beach, LLC, Relief Request 1-RR-13 and 2-RR-13, Response to Request for Additional Information 2023-07-07
[Table view] |
Text
February 4,201 1 NRC 2011-0010 GL 2004-02 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units Iand 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergencv Recirculation Durinq Design Basis Accidents at Pressurized-Water Reactors
{TAC No. MC4705lMC4706)
References:
See Below Via Reference (I), the Commission granted a request submitted and subsequently supplemented by NextEra Energy Point Beach, LLC (NextEra) (References 2 and 3) for an extension to achieve compliance with the provisions of Generic Letter (GL) 2004-02 for Point Beach Nuclear Plant (PBNP), Unit 1.
The Regulatory Commitment made by NextEra in Reference (3), and reiterated in Reference (I), states the following:
Within 60 days following establishment of sufficient Commission direction to resolve the remaining GSI-I 91 issues, PBNP will submit to the NRC a plan with milestones to achieve final resolution.
The extension was approved until 90 days following Commission direction to the NRC staff to address the NRC Staff Requirements Memorandum dated May 17, 2010. The Commission provided the stated direction to the NRC staff via Reference (4).
With respect to PBNP Unit 2, the extension was approved by the NRC in a letter dated June 30, 2009 (Reference 5). Unit 2, therefore, was not addressed in References (1) and (3).
The Regulatory Commitment made in Reference (6) states that NextEra will complete modifications to resolve GSI-191 for Unit 2 by June 30, 2011.
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 I
Document Control Desk Page 2 Subsequent to the above correspondence, Reference (4) was issued by the Commission to the NRC staff on December 23,2010. This document acknowledges that stakeholders and the Staff have agreed upon tests and analyses that remain to be completed regarding in-vessel effects, which could be the controlling factor in resolving GSI-191. It further acknowledges the prudence of deferring further plant modification actions, such removal of fibrous insulation, until tests and analyses are complete.
A path forward is uncertain, pending completion of testing and analyses, and completion of NRC staff evaluations of Options Iand 2, which are expected to occur over the next 18-month period and will culminate with a report to the Commission. Accordingly, it would be premature for NextEra to provide a detailed milestone schedule and activities for resolution and closure of GL 2004-02 at this time, pending further direction from the NRC staff.
The deterministic justification for continued operation provided to the Commission by NextEra for the previously requested extensions for resolution and closure of GL 2004-02 remain unchanged. In Reference (4), the Commission further validates NRC staff and licensee conclusions to date by stating, "...the vastly enlarged advanced strainers installed, compensatory measures already taken, and the low probability of challenging pipe breaks, adequate defense-in-depth is currently being maintained."
NextEra has established and implemented mitigating measures and physical improvements such as a new strainer design installed on both Units Iand 2 which significantly increases the available flow area from approximately 21 ft2 to 1,900 ft2. The amount of fibrous insulation inside containment on both Units has been significantly reduced. In addition to the physical modifications that have taken place at PBNP, inspections of the protective coatings in containment are performed on a refueling outage frequency, in accordance with the PBNP protective coatings program. Procedural controls have been established to limit potential debris sources in containment and emergency procedures have been revised to direct operators to monitor sump performance.
Therefore, the above Regulatory Commitments for Units 1 and 2 are revised as follows:
e NextEra shall develop a plan to achieve final resolution of GSI-191 for PBNP, Units 1 and 2, consistent with future industry guidance and the Reference (4) Staff Requirements Memo, by June 30, 2012.
If you have questions or require additional information, please contact Mr. James Costedio at 9201755-7427.
In accordance with the provisions of 10 CFR 50.91, a copy of this submittal has been provided to the designated Wisconsin Official.
Document Control Desk Page 3 Very truly yours, NextEra Energy Point Beach, LLC site-vice-president cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
References:
( 1 NRC letter to NextEra Energy Point Beach, LLC, dated June 30, 2010, Point Beach Nuclear Plant, Unit I- Generic Letter 2004-02 Extension Request Approval (TAC No. MC4705) (MLI 01800052)
(2) NextEra Energy Point Beach, LLC letter to NRC, dated February 19, 2010, Request for Extension of Completion Date for Generic Letter 2004-02, Potential lmpact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC No.
MC4705lMC4706) (MLI 00500632)
(3) NextEra Energy Point Beach, LLC letter to NRC, dated June 11, 2010, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02, Potential lmpact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC No. MC4705lMC4706) (MLI 01650080)
(4) U.S. Nuclear Regulatory Commission, "Staff Requirements -
SECY-10-0113 - Closure Options for Generic Safety Issue - 191, Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance," Commission Staff Requirements Memo SECY-10-0113, December 23,201 0 (MLI 03570354)
(5) NRC letter to NextEra Energy Point Beach, LLC, dated June 30, 2009, Point Beach Nuclear Plant, Units Iand 2 - GSI-191IGL 2004-02 Additional Extension Request Approval (TAC Nos. MC4705 and MC4706)
(ML091800430)
(6) NextEra Energy Point Beach, LLC letter to NRC, dated June 12, 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 Nos. MC4705lMC4706) (ML091660326)
Text
February 4,201 1 NRC 2011-0010 GL 2004-02 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units Iand 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Plan for Completion of Actions for Generic Letter 2004-02 Potential Impact for Debris Blockage in Emergencv Recirculation Durinq Design Basis Accidents at Pressurized-Water Reactors
{TAC No. MC4705lMC4706)
References:
See Below Via Reference (I), the Commission granted a request submitted and subsequently supplemented by NextEra Energy Point Beach, LLC (NextEra) (References 2 and 3) for an extension to achieve compliance with the provisions of Generic Letter (GL) 2004-02 for Point Beach Nuclear Plant (PBNP), Unit 1.
The Regulatory Commitment made by NextEra in Reference (3), and reiterated in Reference (I), states the following:
Within 60 days following establishment of sufficient Commission direction to resolve the remaining GSI-I 91 issues, PBNP will submit to the NRC a plan with milestones to achieve final resolution.
The extension was approved until 90 days following Commission direction to the NRC staff to address the NRC Staff Requirements Memorandum dated May 17, 2010. The Commission provided the stated direction to the NRC staff via Reference (4).
With respect to PBNP Unit 2, the extension was approved by the NRC in a letter dated June 30, 2009 (Reference 5). Unit 2, therefore, was not addressed in References (1) and (3).
The Regulatory Commitment made in Reference (6) states that NextEra will complete modifications to resolve GSI-191 for Unit 2 by June 30, 2011.
NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 I
Document Control Desk Page 2 Subsequent to the above correspondence, Reference (4) was issued by the Commission to the NRC staff on December 23,2010. This document acknowledges that stakeholders and the Staff have agreed upon tests and analyses that remain to be completed regarding in-vessel effects, which could be the controlling factor in resolving GSI-191. It further acknowledges the prudence of deferring further plant modification actions, such removal of fibrous insulation, until tests and analyses are complete.
A path forward is uncertain, pending completion of testing and analyses, and completion of NRC staff evaluations of Options Iand 2, which are expected to occur over the next 18-month period and will culminate with a report to the Commission. Accordingly, it would be premature for NextEra to provide a detailed milestone schedule and activities for resolution and closure of GL 2004-02 at this time, pending further direction from the NRC staff.
The deterministic justification for continued operation provided to the Commission by NextEra for the previously requested extensions for resolution and closure of GL 2004-02 remain unchanged. In Reference (4), the Commission further validates NRC staff and licensee conclusions to date by stating, "...the vastly enlarged advanced strainers installed, compensatory measures already taken, and the low probability of challenging pipe breaks, adequate defense-in-depth is currently being maintained."
NextEra has established and implemented mitigating measures and physical improvements such as a new strainer design installed on both Units Iand 2 which significantly increases the available flow area from approximately 21 ft2 to 1,900 ft2. The amount of fibrous insulation inside containment on both Units has been significantly reduced. In addition to the physical modifications that have taken place at PBNP, inspections of the protective coatings in containment are performed on a refueling outage frequency, in accordance with the PBNP protective coatings program. Procedural controls have been established to limit potential debris sources in containment and emergency procedures have been revised to direct operators to monitor sump performance.
Therefore, the above Regulatory Commitments for Units 1 and 2 are revised as follows:
e NextEra shall develop a plan to achieve final resolution of GSI-191 for PBNP, Units 1 and 2, consistent with future industry guidance and the Reference (4) Staff Requirements Memo, by June 30, 2012.
If you have questions or require additional information, please contact Mr. James Costedio at 9201755-7427.
In accordance with the provisions of 10 CFR 50.91, a copy of this submittal has been provided to the designated Wisconsin Official.
Document Control Desk Page 3 Very truly yours, NextEra Energy Point Beach, LLC site-vice-president cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
References:
( 1 NRC letter to NextEra Energy Point Beach, LLC, dated June 30, 2010, Point Beach Nuclear Plant, Unit I- Generic Letter 2004-02 Extension Request Approval (TAC No. MC4705) (MLI 01800052)
(2) NextEra Energy Point Beach, LLC letter to NRC, dated February 19, 2010, Request for Extension of Completion Date for Generic Letter 2004-02, Potential lmpact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC No.
MC4705lMC4706) (MLI 00500632)
(3) NextEra Energy Point Beach, LLC letter to NRC, dated June 11, 2010, Supplemental Response for Extension Request for Completion of Actions for Generic Letter 2004-02, Potential lmpact for Debris Blockage in Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC No. MC4705lMC4706) (MLI 01650080)
(4) U.S. Nuclear Regulatory Commission, "Staff Requirements -
SECY-10-0113 - Closure Options for Generic Safety Issue - 191, Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance," Commission Staff Requirements Memo SECY-10-0113, December 23,201 0 (MLI 03570354)
(5) NRC letter to NextEra Energy Point Beach, LLC, dated June 30, 2009, Point Beach Nuclear Plant, Units Iand 2 - GSI-191IGL 2004-02 Additional Extension Request Approval (TAC Nos. MC4705 and MC4706)
(ML091800430)
(6) NextEra Energy Point Beach, LLC letter to NRC, dated June 12, 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 Nos. MC4705lMC4706) (ML091660326)