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MONTHYEARW3F1-2011-0037, Day Response to NRC Bulletin 2011-01, Mitigating Strategies2011-06-10010 June 2011 Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request W3F1-2011-0038, 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies2011-07-11011 July 2011 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request ML1131106742011-11-23023 November 2011 Request for Additional Information Regarding 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: RAI W3F1-2012-0001, Response to Request for Additional Information for the 60-day Response to NRC Bulletin 2011-01, Mitigating Strategies2012-01-0505 January 2012 Response to Request for Additional Information for the 60-day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Response to RAI ML12172A2682012-06-26026 June 2012 Closeout of NRC Bulletin 2011-01, Mitigating Strategies Project stage: Other 2011-07-11
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Category:Letter type:W
MONTHYEARW3F1-2024-0038, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0039, Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-09-24024 September 2024 Response to Request for Additional Information - Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0041, Reply to a Notice of Violation, EA-24-0522024-09-19019 September 2024 Reply to a Notice of Violation, EA-24-052 W3F1-2024-0040, Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days2024-09-0303 September 2024 Special Report SR 2024-001-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0019, (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 252024-07-22022 July 2024 (Waterford 3) - Steam Generator Tube Inspection Report for the 25th Rf Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0032, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-07-17017 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation W3F1-2024-0025, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test W3F1-2024-0024, Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days2024-06-17017 June 2024 Special Report SR 2023-004-02 Radiation Monitor Inoperable Greater than 7 Days W3F1-2024-0013, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program2024-05-0808 May 2024 Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program W3F1-2024-0018, Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 252024-05-0101 May 2024 Submittal of Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 25 / Refuel 25 W3F1-2024-0014, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20242024-04-29029 April 2024 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2024 W3F1-2024-0015, Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure2024-04-24024 April 2024 Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure W3F1-2024-0016, Annual Radiological Environmental Operating Report (AREOR) - 20232024-04-24024 April 2024 Annual Radiological Environmental Operating Report (AREOR) - 2023 W3F1-2024-0017, Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.22062024-04-23023 April 2024 Annual Report of Individual Monitoring of Radiation Exposure for 2023 Per 10 CFR 20.2206 W3F1-2024-0020, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20232024-04-11011 April 2024 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2023 W3F1-2024-0008, Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-01 for Examinations of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds W3F1-2024-0009, Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-03-18018 March 2024 Proposed Alternative WF3-RR-24-02 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles W3F1-2024-0012, Response to NRC Integrated Inspection Report 05000382/20230042024-03-11011 March 2024 Response to NRC Integrated Inspection Report 05000382/2023004 W3F1-2024-0006, Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days2024-02-28028 February 2024 Special Report SR-2023-004-01, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0056, Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owners Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 2024-09-03
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Entergy Nuclear South Entergy Operations, Inc.
17265 River Road
Ente-rgy Killona, LA 70057.3093 Fax 504 739 6678 jkowa1e@enter. corn Joseph A. Kowalewski Vice Pesdent. Opaflo W3F1 2011 0037 Vv atutrd June 10, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD. 20852
Subject:
30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies Entergy Operations Inc.,
Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License Number NPF-38
Reference:
NRC Bulletin 2011-01: Mitigating Strategies, dated May 11,2011
Dear Sir or Madam:
On May 11, 2011, the NRC issued the referenced Bulletin 2011-01 and requested a written response within 30 days. Attached is Entergys 30-day written response for Waterford 3.
In response to the events on September 11, 2001, and NRC requirements, Entergy developed preplanned strategies and implemented guidance to maintain or restore core cooling, containment, and spent fuel cooling capabilities under the circumstances associated with the loss of large areas of the plant due to fire or explosions. Following the events on March 11, 2011, at the Fukushima Daiichi Nuclear Power Station, Entergy took actions to ensure availability of these capabilities. The attached response reflects these actions.
There are no new commitments contained in this submittal.
If you need any additional information, please contact Mr. William Steelman, Licensing Manager, at 504-739-6685.
I declare under penalty of perjury that the contents of this response are true and correct to the best of my knowledge and belief. Executed on this 10th day of June 2011.
Sincerely, Joph A. Kowalewski Site Vice President
Attachment:
30-Day Response to NRC Bulletin 2011-01 cc: Regional Administrator Resident Inspector Project Manager
Letter W3F1-2011-0037 Attachment 1 30-Day Response to NRC Bulletin 2011-01 to W3F1-2011-0037 Page 1 of 2 QUESTION 1 Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
RESPONSE
The strategies required by section B.5.b of the Interim Compensatory Measures Order EA 026 and implemented pursuant to a license condition were submitted to the NRC by References 1, 2, 3, 4, 5, 6, and 8 and reviewed and approved by the NRC in Reference 7.
Entergy has assessed the status of equipment necessary to execute the mitigating strategies as identified in the referenced letters. Based upon the assessment, the equipment is available and capable of performing its intended function.
QUESTION 2 Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?
RESPONSE
Entergy has assessed the capability to execute the mitigating strategies as identified in the referenced letters. Based upon the assessment, the guidance and strategies are capable of being executed considering the current configuration of facility, staffing, and skill levels of the staff.
REFERENCES
- 1. Letter, A.J. Harris to USNRC, Response to NRC Guidance Regarding Mitigation Strategies, W3F1-2005-0038, dated May 31, 2005
- 2. Letter, J.E. Venable to USNRC, Response to NRC Guidance Regarding Mitigation Strategies, W3F1-2005-0065, dated September 7, 2005
- 3. Letter, R.J. Murillo to USNRC, Response to NRC Request for Additional Information Regarding the February 2002 Order Section B.5.b, W3F1-2005-0071, dated October 20, 2005
- 4. Letter, J.E. Venable to USNRC, Response to Report of Inspection of Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Temporary Instruction 2515/164; NRC Inspection Report 05000333/2005011, W3F1-2006-0010, dated February 24, 2006
- 5. Letter, J.A. Ridgel to USNRC, Response Providing Information Regarding Implementation Details for the Phase 2 and 3 Mitigating Strategies, W3F1-2006-0064, dated January 11, 2007 to W3F1-2011-0037 Page 2 of 2
- 6. Letter, K.S. Cook to USNRC, Supplemental Response Regarding Implementation Details for Phase 2 and 3 Mitigation Strategies, W3F1-2007-0016, dated April 26, 2007
- 7. Letter, USNRC to K.T. Walsh, Conforming License Amendment to Incorporate the Mitigation Strategies Required By Section B.5.b of Commission Order EA-02-026 (TAC NO. MD4569) dated July 26, 2007
- 8. Letter, R.J. Murillo to USNRC, Commitment Change Notification to B.5.b Response Letter W3F1-2006-0064, W3F1-2007-0041, dated November 15, 2007
Text
Entergy Nuclear South Entergy Operations, Inc.
17265 River Road
Ente-rgy Killona, LA 70057.3093 Fax 504 739 6678 jkowa1e@enter. corn Joseph A. Kowalewski Vice Pesdent. Opaflo W3F1 2011 0037 Vv atutrd June 10, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD. 20852
Subject:
30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies Entergy Operations Inc.,
Waterford Steam Electric Station, Unit 3 (Waterford 3)
Docket No. 50-382 License Number NPF-38
Reference:
NRC Bulletin 2011-01: Mitigating Strategies, dated May 11,2011
Dear Sir or Madam:
On May 11, 2011, the NRC issued the referenced Bulletin 2011-01 and requested a written response within 30 days. Attached is Entergys 30-day written response for Waterford 3.
In response to the events on September 11, 2001, and NRC requirements, Entergy developed preplanned strategies and implemented guidance to maintain or restore core cooling, containment, and spent fuel cooling capabilities under the circumstances associated with the loss of large areas of the plant due to fire or explosions. Following the events on March 11, 2011, at the Fukushima Daiichi Nuclear Power Station, Entergy took actions to ensure availability of these capabilities. The attached response reflects these actions.
There are no new commitments contained in this submittal.
If you need any additional information, please contact Mr. William Steelman, Licensing Manager, at 504-739-6685.
I declare under penalty of perjury that the contents of this response are true and correct to the best of my knowledge and belief. Executed on this 10th day of June 2011.
Sincerely, Joph A. Kowalewski Site Vice President
Attachment:
30-Day Response to NRC Bulletin 2011-01 cc: Regional Administrator Resident Inspector Project Manager
Letter W3F1-2011-0037 Attachment 1 30-Day Response to NRC Bulletin 2011-01 to W3F1-2011-0037 Page 1 of 2 QUESTION 1 Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
RESPONSE
The strategies required by section B.5.b of the Interim Compensatory Measures Order EA 026 and implemented pursuant to a license condition were submitted to the NRC by References 1, 2, 3, 4, 5, 6, and 8 and reviewed and approved by the NRC in Reference 7.
Entergy has assessed the status of equipment necessary to execute the mitigating strategies as identified in the referenced letters. Based upon the assessment, the equipment is available and capable of performing its intended function.
QUESTION 2 Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?
RESPONSE
Entergy has assessed the capability to execute the mitigating strategies as identified in the referenced letters. Based upon the assessment, the guidance and strategies are capable of being executed considering the current configuration of facility, staffing, and skill levels of the staff.
REFERENCES
- 1. Letter, A.J. Harris to USNRC, Response to NRC Guidance Regarding Mitigation Strategies, W3F1-2005-0038, dated May 31, 2005
- 2. Letter, J.E. Venable to USNRC, Response to NRC Guidance Regarding Mitigation Strategies, W3F1-2005-0065, dated September 7, 2005
- 3. Letter, R.J. Murillo to USNRC, Response to NRC Request for Additional Information Regarding the February 2002 Order Section B.5.b, W3F1-2005-0071, dated October 20, 2005
- 4. Letter, J.E. Venable to USNRC, Response to Report of Inspection of Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Temporary Instruction 2515/164; NRC Inspection Report 05000333/2005011, W3F1-2006-0010, dated February 24, 2006
- 5. Letter, J.A. Ridgel to USNRC, Response Providing Information Regarding Implementation Details for the Phase 2 and 3 Mitigating Strategies, W3F1-2006-0064, dated January 11, 2007 to W3F1-2011-0037 Page 2 of 2
- 6. Letter, K.S. Cook to USNRC, Supplemental Response Regarding Implementation Details for Phase 2 and 3 Mitigation Strategies, W3F1-2007-0016, dated April 26, 2007
- 7. Letter, USNRC to K.T. Walsh, Conforming License Amendment to Incorporate the Mitigation Strategies Required By Section B.5.b of Commission Order EA-02-026 (TAC NO. MD4569) dated July 26, 2007
- 8. Letter, R.J. Murillo to USNRC, Commitment Change Notification to B.5.b Response Letter W3F1-2006-0064, W3F1-2007-0041, dated November 15, 2007