Letter Sequence Request |
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EPID:L-2020-LLA-0164, Presentation Cpc/Ceac Replacement License Amendment Request - September 22, 2020 (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML20255A218, ML20255A239, ML20255A242, ML20255A253, ML20255A257, ML20258A071, ML20258A087, ML20258A088, ML20258A091, ML20258A092, ML21084A255, ML21091A147, ML21160A057, ML21160A085
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MONTHYEARML20255A2182018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20255A2392018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20255A2422018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 6, Engineered Safety Features (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20255A2572018-07-25025 July 2018 10 to Final Safety Analysis Report, Reference Drawings (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20255A2532018-07-25025 July 2018 10 to Final Safety Analysis Report, Chapter 12, Radiation Protection (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20258A0922019-09-11011 September 2019 11 to Final Safety Analysis Report, Reference Drawings (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20258A0912019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 12 - Radiation Protection (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20258A0882019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 06 - Engineered Safety Features (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20258A0872019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 05 - Reactor Coolant System and Connected Systems (EPID L-2020-LLA-0164) - Redacted Project stage: Other ML20258A0712019-09-11011 September 2019 11 to Final Safety Analysis Report, Chapter 01 - Introduction and General Description of Plant - Redacted Project stage: Other W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request ML20239B0552020-08-26026 August 2020 NRR E-mail Capture - NRC LIC-109 Acceptance Review Results for Waterford U3 Digital Upgrade LAR Project stage: Acceptance Review ML20288A7292020-09-22022 September 2020 Presentation Cpc/Ceac Replacement License Amendment Request - September 22, 2020 Project stage: Request ML20289A2672020-09-22022 September 2020, 22 October 2020 Summary of September 22, 2020, Category 1 Public Meeting Di&C License Amendment Request Project stage: Request ML20265A2872020-10-0101 October 2020 Request for Withholding Information from Public Disclosure Submittals for a Digital Upgrade Project stage: Withholding Request Acceptance ML20268B3242020-10-0101 October 2020 Regulatory Audit in Support of Review of Digital Upgrade License Amendment Request Project stage: Approval PMNS20201184, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-0707 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 Project stage: Meeting ML20288A7422020-10-22022 October 2020 Summary of September 22, 2020, Meeting License Amendment Request to Install Digital Upgrade (EPID L-2020-LLA-0164) (Non-proprietary Version) Project stage: Meeting PMNS20201234, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 Project stage: Meeting PMNS20201233, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 Project stage: Meeting PMNS20201232, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 Project stage: Meeting PMNS20201195, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32020-10-28028 October 2020 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 Project stage: Meeting ML20315A2672020-12-17017 December 2020 Summary of October 21,2020, Redacted Category 1 Public Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06,Rev.2, Licensing Processes(NON-PROPRIETARY) Project stage: Meeting ML20325A3212020-12-17017 December 2020 Summary of November 4, 2020, Nonproprietary - Category 1 Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes (Redacted) Project stage: Meeting ML20325A2412020-12-17017 December 2020 Summary of November 18, 2020, REDACTED- Category 1 Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes Project stage: Meeting W3F1-2021-0002, Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-22022 January 2021 Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request PMNS20201419, Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 32021-02-0505 February 2021 Partially Closed Meeting with Entergy Operations, Inc. to Discuss a License Amendment Request for a Digital Upgrade at Waterford Steam Electric Station, Unit 3 Project stage: Meeting ML21032A0132021-02-19019 February 2021 01/06 and 01/21/2021 Summary of - Category 1 Meetings with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C ISG No. 06, Rev. 2 for Waterford Steam Electric Station Project stage: Meeting ML21039A2682021-02-22022 February 2021 Summary of Category 1 Meetings with Entergy Operations, Inc. LAR to Install Digital Upgrade in Accordance with Digital I&C ISG No. 06, Rev. 2 for Waterford Steam Electric Station, Unit 3 Project stage: Meeting W3F1-2021-0025, Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-03-0505 March 2021 Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request W3F1-2021-0026, Open Item Response, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-03-19019 March 2021 Open Item Response, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request ML21084A2552021-03-22022 March 2021 NRR E-mail Capture - Supplement to Audit Plan Dated October 1, 2020 (Waterford 3, L-2020-LLA-0164) Project stage: Other ML21091A1472021-04-0101 April 2021 Annual Report for Entergy Quality Assurance Program Manual and Indian Point Energy Center Quality Assurance Program Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to Project stage: Other ML21071A2862021-04-0101 April 2021 Summary of Cat. 1 Public Meeting with Entergy Operations,Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital Instrumentation and Control Interim Staff Guidance No.06,Rev.2,Licensing Processes NON-PROPRIETARY Project stage: Meeting ML21075A0322021-04-0202 April 2021 Summary of Redacted - Category 1 Public Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C ISG No. 06, Revision 2, Licensing Processes Project stage: Meeting ML21095A1932021-04-0707 April 2021 Request for Withholding Information from Public Disclosure, Project stage: Withholding Request Acceptance ML21085A8652021-04-0808 April 2021 Summary of March 17, 2021, Category 1 Public Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes (EPID L-2020-LLA-0164) Non Project stage: Meeting ML21090A0022021-04-12012 April 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21112A2542021-04-29029 April 2021 Request for Additional Information Digital Upgrade to the Core Protection and Control Element Assembly Calculator System (EPID L 2020 Lla 0164) - Redacted Version Project stage: RAI ML21112A2492021-05-0707 May 2021 Summary of April 14, 2021, Redacted - Partially Closed Observation Meeting with Entergy Operations Inc., LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Revision 2 (EPID L-2020-LLA-0164) (Non-Pro Project stage: Meeting W3F1-2021-0032, Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-05-21021 May 2021 Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request W3F1-2021-0041, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System2021-06-0202 June 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System Project stage: Request ML21160A0852021-06-0404 June 2021 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Louisiana Regarding a Waterford Steam Electric Station, Unit 3 Amendment - Digital Upgrade I&C Project stage: Other W3F1-2021-0047, Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-06-21021 June 2021 Open Item Response - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System Project stage: Request W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator Project stage: Request W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 Project stage: Request ML21203A3532021-08-0909 August 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21160A0572021-08-16016 August 2021 Summary of Regulatory Audit in Support of Digital Upgrade License Amendment Request (EPID L-2020-LLA-0164)Non-Proprietary Project stage: Other ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System Project stage: Approval 2021-03-22
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Category:Letter type:W
MONTHYEARW3F1-2024-0049, Notification of Readiness for Supplemental Inspection2024-10-21021 October 2024 Notification of Readiness for Supplemental Inspection W3F1-2024-0042, License Amendment Request to Extend Allowable Outage Times for One or More Control Room Air Conditioning Units Inoperable2024-10-16016 October 2024 License Amendment Request to Extend Allowable Outage Times for One or More Control Room Air Conditioning Units Inoperable W3F1-2024-0038, 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 2024-09-03
[Table view] Category:Report
MONTHYEARW3F1-2024-0024, 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 W3F1-2024-0018, 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 W3F1-2023-0056, 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 ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2019-0043, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20182019-07-0101 July 2019 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2018 W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results2019-03-14014 March 2019 Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results ML18275A2342018-12-27027 December 2018 NRC Record of Decision for the License Renewal Application for Waterford, Unit 3 W3F1-2018-0029, Submittal of Annual Report on Westinghouse Electric Co., LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20172018-06-0707 June 2018 Submittal of Annual Report on Westinghouse Electric Co., LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2017 ML17163A1852017-06-30030 June 2017 Biological Evaluation of Impacts to Federally Listed Species for Waterford License Renewal W3F1-2017-0042, Focused Evaluation of External Flooding2017-05-17017 May 2017 Focused Evaluation of External Flooding ML17023A2822017-02-27027 February 2017 Flood Hazard Mitigating Strategies Assessment ML16308A4472016-10-19019 October 2016 Final ASP Program Analysis Precursor for Waterford Steam Electric Station, Unit 3 Re. Both Emergency Diesel Generators Declared Inoperable (LER 382-2015-007) ML15268A0202015-09-23023 September 2015 Attachment 3, Fuel Thermal Conductivity Degradation Evaluation (Non-Proprietary) W3F1-2015-0042, Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-147 Through the End2015-07-21021 July 2015 Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-147 Through the End ML15204A3242015-07-21021 July 2015 Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-62 Through 3-146 ML15204A3232015-07-21021 July 2015 Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 1 Through 3-61 ML14129A3502014-04-29029 April 2014 Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 25, 2014 ML13220A4022013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A9692013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Waterford Steam Electric Generating Station, Unit 3, TAC No.: MF0977 W3F1-2013-0054, CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B2013-09-0909 September 2013 CFR 71.95 Report on Issues Involving Radwaste Cask 8-120B W3F1-2013-0027, Closure Option for Generic Safety Issue - 1912013-05-16016 May 2013 Closure Option for Generic Safety Issue - 191 W3F1-2013-0024, Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 10142013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 1014 ML13120A4642013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment C, Rev. 0, Safety Injection Sump Outlet Header B Isolation, Enclosure to W3F1-2013-0024, Pages 312 - 591 of 1014 ML13120A4622013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment G, Rev. 0, Peer Review Checklist for SWEL, Enclosure to W3F1-2013-0024, Pages 820 - 1014 of 1014 ML13120A4612013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Revision 1, Wateford, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Enclosure to W3F1-2013-0024, Pages 1 - 311 of 1014 CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments W3F1-2012-0100, WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 22012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 2 ML12333A2772012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 1 2024-06-17
[Table view] Category:Technical
MONTHYEARW3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment W3F1-2021-0004, License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual2021-04-0505 April 2021 License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to the Technical Requirements Manual ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) W3F1-2021-0015, Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2021-01-29029 January 2021 Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2020-0038, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System2020-07-23023 July 2020 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System W3F1-2019-0022, Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results2019-03-14014 March 2019 Resubmittal of Reactor Vessel Material Surveillance Program Capsule Test Results ML17163A1852017-06-30030 June 2017 Biological Evaluation of Impacts to Federally Listed Species for Waterford License Renewal ML15268A0202015-09-23023 September 2015 Attachment 3, Fuel Thermal Conductivity Degradation Evaluation (Non-Proprietary) ML13220A4022013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A9692013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Waterford Steam Electric Generating Station, Unit 3, TAC No.: MF0977 W3F1-2013-0024, Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 10142013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment D, Rev. 0, Area Walk-by Checklists (Awcs), Enclosure to W3F1-2013-0024, Pages 592 - 817 of 1014 ML13120A4642013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment C, Rev. 0, Safety Injection Sump Outlet Header B Isolation, Enclosure to W3F1-2013-0024, Pages 312 - 591 of 1014 ML13120A4622013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Attachment G, Rev. 0, Peer Review Checklist for SWEL, Enclosure to W3F1-2013-0024, Pages 820 - 1014 of 1014 ML13120A4612013-03-25025 March 2013 Engineering Report WF3-CS-12-00003, Revision 1, Wateford, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Enclosure to W3F1-2013-0024, Pages 1 - 311 of 1014 ML12333A2722012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 3 W3F1-2012-0100, WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 22012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 2 ML12333A2772012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 1 ML12333A2752012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 5 ML12333A2742012-11-16016 November 2012 WF3-CS-12-00003, Rev. 0, Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 4 ML12181A4152012-06-28028 June 2012 Attachment 1 to W3F1-2012-0049, Analysis of Proposed Operating License Change, Section 4.0 Through 6.0 W3F1-2012-0040, Technical Specification Bases Update to the NRC for the Period November 1, 2011 Through April 30, 20122012-05-30030 May 2012 Technical Specification Bases Update to the NRC for the Period November 1, 2011 Through April 30, 2012 ML1005506072010-02-28028 February 2010 WCAP-17187-NP, Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for Waterford Steam Electric Station, Unit 3 Using Leak-Before-Break Methodology, Enclosure 2 to W3F1-2010-0003 ML0918312592009-06-24024 June 2009 Attachment 6 to W3F1-2009-0022, HI-2094376, Rev. 0, Licensing Report for Waterford, Unit 3 Spent Fuel Pool Criticality Analysis ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 W3F1-2008-0039, Steam Generator Conditions Observed at Waterford 32008-05-20020 May 2008 Steam Generator Conditions Observed at Waterford 3 W3F1-2008-0018, Attachment 2, Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, (Non-Proprietary Version)2008-02-29029 February 2008 Attachment 2, Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, (Non-Proprietary Version) W3F1-2007-0045, Supplement to the ECCS Performance Analysis Submittal in Support of Next Generation Fuel - 1999 EM Optional Steam Cooling Model Justification2007-10-0404 October 2007 Supplement to the ECCS Performance Analysis Submittal in Support of Next Generation Fuel - 1999 EM Optional Steam Cooling Model Justification CNRO-2006-00039, Results of the Waterford 3 Pressurizer Flaw Evaluation2006-08-31031 August 2006 Results of the Waterford 3 Pressurizer Flaw Evaluation ML0523803522005-08-25025 August 2005 Steam Generator Tube Inspection Results for the 2003 Outage W3F1-2005-0045, 60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage2005-07-19019 July 2005 60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage ML0513702182005-05-17017 May 2005 Pgs. 1-61 Waterford 3 EAL Basis Document (W3-EP-001-001 Rev. Xx) ML0513702362005-05-16016 May 2005 Pgs. 62-123 Waterford 3 EAL Basis Document (W3-EP-001-001 Rev. Xx) W3F1-2005-0025, Holtec Licensing Report Errors2005-04-15015 April 2005 Holtec Licensing Report Errors W3F1-2004-0101, to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 32004-10-19019 October 2004 to Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 3 W3F1-2004-0075, Reissue of Report BAW-2177, Analysis of Capsule W-97 Entergy Operations, Inc. Waterford Generating Station Unit 3 - Reactor Vessel Material Surveillance Program2004-09-13013 September 2004 Reissue of Report BAW-2177, Analysis of Capsule W-97 Entergy Operations, Inc. Waterford Generating Station Unit 3 - Reactor Vessel Material Surveillance Program W3F1-2004-0044, Small Break Loss-of-Coolant Accident Emergency Core Cooling System Performance Analysis2004-05-26026 May 2004 Small Break Loss-of-Coolant Accident Emergency Core Cooling System Performance Analysis ML0414101032004-04-0202 April 2004 Faxed on 04/02/94 to T.Alexion - Entergy - Waterford, Initial Engineering Evaluation for SBLOCA with DC Bus Single Failure CNRO-2003-00049, Letter Transmitting Mark-Up of Engineering Report M-EP-2003-004, Rev. 0 Fracture Mechanics Analysis for the Assessment Potential for Primary Water Stress Corrosion Crack (PWSCC) Growth, Un-Inspected Regions..., Pages 43 Through 572003-09-26026 September 2003 Letter Transmitting Mark-Up of Engineering Report M-EP-2003-004, Rev. 0 Fracture Mechanics Analysis for the Assessment Potential for Primary Water Stress Corrosion Crack (PWSCC) Growth, Un-Inspected Regions..., Pages 43 Through 57 CNRO-2003-00038, Rev. 0 to M-EP-2003-004, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element Drive Mechanism At..., Appendix D, Attachment 5 Thro2003-09-15015 September 2003 Rev. 0 to M-EP-2003-004, Fracture Mechanics Analysis for the Assessment of the Potential for Primary Water Stress Corrosion Crack Growth Un-Inspected Regions of the Control Element Drive Mechanism At..., Appendix D, Attachment 5 Through Enc CNRO-2003-00030, Arkansas, Unit 2 and Waterford, Unit 3, Letter CNRO-2003-00027 to NRC, Relaxation Requests to NRC Order EA-03-009, Dated July 1, 20032003-07-24024 July 2003 Arkansas, Unit 2 and Waterford, Unit 3, Letter CNRO-2003-00027 to NRC, Relaxation Requests to NRC Order EA-03-009, Dated July 1, 2003 CNRO-2003-00020, Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-0092003-06-11011 June 2003 Arkansas, Unit 2 and Waterford, Unit 3, Relaxation Requests to NRC Order EA-03-009 W3F1-2002-0099, Ses, Report of Facility Changes, Tests & Experiments for Period from June 1, 2001 Through May 31. 20022002-11-27027 November 2002 Ses, Report of Facility Changes, Tests & Experiments for Period from June 1, 2001 Through May 31. 2002 ML19066A0671986-11-30030 November 1986 Overview Description of the Core Operating Limit Supervisory System (COLSS)(CEN-312-NP, Revision 01-NP 8701270057) ML19066A0851986-04-30030 April 1986 CPC and Methodology Changes for the CPC Improvement Program (CEN-310-NP-A 8605270198) ML15350A2151985-09-0505 September 1985 Overview Description of Core Operating Limit Supervisory System (Colss)(Rev 00-NP to CEN-312-NP) 2021-09-30
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Text
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.90 W3F1-2021-0015 January 29, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Revised Vendor Oversight Plan Summary - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (CEAC) System Waterford Steam Electric Station, Unit 3 NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38
Reference:
Entergy Operations, Inc. letter to U.S. Nuclear Regulatory Commission (NRC),
"License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) system and Control Element Assembly Calculator (CEAC) system," dated July 23, 2020, (ADAMS Accession No. ML20205L587)
In Reference 1, Entergy Operations, Inc. (Entergy) submitted, to the U.S. Nuclear Regulatory Commission (NRC), a proposed amendment to Appendix A, "Technical Specifications" (TS) of Renewed Facility Operating License No. NPF-38 for Waterford Steam Electric Station, Unit 3 (Waterford). The proposed change would revise the Waterford TS in order to implement a planned digital instrumentation and control (DI&C) modification at Waterford. The DI&C modification will replace the existing digital minicomputers of the Core Protection Calculator (CPC) system and Control Element Assembly Calculator (CEAC) system with the more reliable, digital system based on the Westinghouse Electric Company (Westinghouse) Common Qualified (Common Q) Platform.
As specified in NRC DI&C Interim Staff Guidance (ISG)-06, "Licensing Process," Revision 2, Section C.2.2.1, the referenced license amendment request (LAR) included a description of the Entergy Vendor Oversight Plan (VOP) for the CPC/CEAC replacement project. This was provided as Attachment 14, "CPC Replacement Project Vendor Oversight Plan (VOP)
Summary" (VOP Summary).
W3F1-2021-0015 Page 2 of 2 Subsequent to submittal of the referenced LAR, Entergy has revised the VOP, and has incorporated applicable changes into a revised VOP Summary. The Enclosure to this letter provides the revised VOP Summary. This document replaces the original VOP Summary (i.e., 4 of the referenced LAR) in its entirety. Changes to the original VOP Summary are identified with underlined text and revision bars in the right margin.
The No Significant Hazards Consideration determination provided in the Referenced LAR submittal is not altered by the information provided in this letter.
There are no new regulatory commitments included in this letter.
In accordance with 10 CFR 50.91(b)(1), "Notice for public comment; State consultation," a copy of this letter, without the proprietary attachments, is being provided to the designated State Official.
Should you have any questions or require additional information, please contact Paul Wood, Regulatory Assurance Manager, Waterford, at (504) 464-3786 or pwood1@entergy.com.
I declare under penalty of perjury, that the foregoing is true and correct. Executed on January 29, 2021.
Respectfully,
!"# %&'()* $
Ron Gaston RWG/jls
Enclosure:
CPC Replacement Project Vendor Oversight Plan (VOP) Summary, Revision 1 cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford Steam Electric Station, Unit 3 Louisiana Department of Environmental Quality NRC Project Manager Waterford Steam Electric Station, Unit 3
Enclosure W3F1-2021-0015 CPC Replacement Project Vendor Oversight Plan (VOP) Summary, Revision 1
W3F1-2021-00015 Enclosure Page 1 of 15 CPC Replacement Project Vendor Oversight Plan (VOP) Summary, Revision 1
- 1. Background DI&C-ISG-06 Section C.2.2 provides Licensee Prerequisites for use of the Alternate Review Process (ARP) (Reference 7). In Section C.2.2.1, DI&C-ISG-06 describes that to use the ARP, the license amendment request (LAR) should provide a description of the licensee's Vendor Oversight Plan (VOP). Section C.2.2.1 says that the LAR should include:
A description of the licensees Vendor Oversight Plan. The plan, when executed, can be used to ensure that the vendor: (1) executes the project consistent with the LAR, and (2) uses an adequate software QA program. The Vendor Oversight Plan, when executed, helps ensure that the vendor will meet both the process and the technical regulatory requirements. Vendor oversight is a series of licensee interactions with the vendor and progresses throughout the entire system development life cycle. The plan should address the intended interactions among the vendors design, test, verification and validation (V&V), and QA organizations.
The VOP is an important element of the ARP. Since the LAR approval is requested earlier in the project lifecycle than for the other DI&C-ISG-06 review processes (i.e. Tier 1, 2 or 3), the Staff needs to understand how the licensee intends to ensure that the vendor produces high quality software and system.
Entergy Operations, Inc. (Entergy) developed a VOP for the Waterford Steam Electric Station, Unit 3 (Waterford) Core Protection Calculator (CPC) System (CPCS) modification to ensure that Westinghouse executes the project consistent with:
Entergy procurement documents (Reference 1)
Westinghouse Software Program Manual (SPM) and Westinghouse platform-related documentation, which have been NRC-approved as described in LTR Section 6.1 (LAR Attachment 4)
Project description consistent with the LAR This revision to the VOP Summary summarizes the contents of Entergy document VOP-WF3-2019-00236, Core Protection Calculator System Vendor Oversight Plan, Revision 3, and replaces, in its entirety, the original VOP Summary which was submitted to the NRC as 4 to Entergy's July 23, 2020 LAR (ADAMS Accession No. ML20205L587). This document has been issued for use. The project team is currently conducting vendor oversight activities of Westinghouse. The following is the VOP Table of Contents.
W3F1-2021-00015 Enclosure Page 2 of 15 Waterford Core Protection Calculator System Replacement Project Vendor Oversight Plan Table of Contents Table of Contents
- 1. Project Scope and Description............... ............ .................... .................... ........ ............ ................... 5 Vendor Oversight Plan (VOP) Scope ................ ...... .......... .... ............................... ............................ 6
- 3. Abbreviations ........... ..................................................................................................................... 10
- 4. Reference .......................................................... .......................................................... ................. 12
- 5. Project Organization and Roles (Stakeholde ) ................ ...................... .. .. ..................................... 13
- 6. De\elopment and Assessment of Potential Project and Technical Risk Factors ......... ... ....... .......... .. 16
- 7. Determine Performance Measures and Acceptance Criteria .......... .... ...... ........ ..... ............... .. ... ....... 18 Critical Characteristics .......... .......... .... ...... ...... .... .......... ........ .......... ..... ... .. ..... ..... .... ...... ......... .......... .. 18 Ph sical Critical Characteristics ........................ .... .............. .. .................... ..................................... 18 Perfonnance Critical Characteristics ........................................ .................. .................... ................ 20 Em ironmental Critical Characteristics .......... .................... .................... .................... .................... . 2 1 cyber Critical Characteristics ... ..... ..... ..... ..... .......... ..... ..... .......... ..... ..... .......... ......... .......... .......... .. 22 Design A11ifacts .. ............ ...... .................... ........ .......... ..... ... .. .......... ..... ... .. .. ... ..... ........ ....... ............. ... 22 Progranunatic Elements .................................................................................. ................... ................ 24 Quality Assurance ....... ............ .................... .. ..... .............................. ........... ............. ...................... 25 Configuration Management. ............. .......... ... .... ............. ... ................................... ...... .......... ......... . 25 Software Verification and Validation (V& V) ....... ... ..... ... .. ....... ... ..... ..... ....... ... ....... ... ....... ... ....... .. .. 27 Sofu1Vare Safety ...... .......... ........ .......... ..... ..... .......... ..... ..... .......... ..... ..... .......... ......... ........... ......... .. 29 Secure De\ elopment Environment ........ ... ..... .......... ..... ..... .......... .... .... .. .. ... ..... .... .... ....... ..... ...... ... .. 29 Cyb er Security ............................................................................................................... ................ 30 Software Lifec.ycle Processes ............................. ..................... .................... ... ................................ 30 Hardware Requiren1ents .............. .................. .................... ............ ........ .... ...... ..... ......... ..... ....... .... . 31 Plant Specific. Action Items (PSAis)...... ... ..... .......... ..... ..... .......... .......... .......... ......... ........... ......... .. 32
- 8. Implement Appropriate Oversight Methods ........................ .................... .................... .................... 32
- 9. Perform Correcti e Actions ................................. .................. .................... .................... ................ 33
- 10. Docutnentation ........................................................................................ .................... .............. 34 Attachment 1 CPCS Replacement Project Organization Chart .............................................................. 35 Entergy CPCS Project Organization Chart ............ .................... .......... .. ...... .. .... ...... ..... ......... ..... ...... ...... 36 Westinghouse CPCS Project Organization Chart ... ..... ..... ..... ..... .......... ..... ..... .......... ..... ................... ...... . 37 Attachment 2 CPCS Replacement Project Division of Responsibility ..................................................... 38
W3F1-2021-00015 Enclosure Page 3 of 15
- 2. Vendor Oversight Plan (VOP) Scope This scope of the VOP is for the Westinghouse scope of the CPCS Replacement Project. The Westinghouse scope includes the hardware, software, design documentation, and licensing documentation. The VOP does not cover vendor oversight of the Architect Engineer (A/E) performing the modification process activities. The A/E does not provide any oversight of Westinghouse activities or digital products. The A/E does not perform the DI&C-ISG-06 (Reference 7) activities associated with the "vendor". For Waterford, the A/E is typically referred to as the Engineer of Choice (EOC) in the project documents. Waterford vendor oversight of the A/E is performed by Entergy engineering procedures and owners acceptance review separate from this VOP (Reference 19).
Stakeholders identified in VOP Section 5 will participate in vendor oversight activities to the extent that vendor activities can affect their needs. The level of vendor oversight follows a procedure-driven graded approach, based on project and technical risk factors, which are described in VOP Section 6. All levels of the graded approach will include specifically defined performance measures and acceptance criteria which are described in VOP Section 7. The performance measurements described in the VOP include critical characteristics, design artifacts, and programmatic elements. The various levels of graded oversight are described in VOP Section 8. The site Corrective Action Process (CAP) will be used to document and ensure resolution of issues/problems. This is described in VOP Section 9. Finally, oversight results will be documented as described in VOP Section 10.
Vendor oversight activities include:
Conducting audits Conducting Quality Surveillances of vendor activities under Waterford Quality Assurance (QA) program including activities for the CPCS Replacement Project Critical Procurement Plan (CPP). Note: QA surveillances are governed by existing Entergy procedures (Reference 4).
Providing input to and review/confirmation of specific vendor activities and related information items Reviewing vendor design artifacts (e.g., specifications, drawings, analyses)
Observing or witnessing specific vendor activities Participating directly in specific vendor activities Coordinating multi-disciplined interactions between various stakeholders Communicating status, schedule, and results of oversight activities through daily or weekly Waterford/Westinghouse Project Management team teleconferences, Waterford/Westinghouse Engineering team teleconferences, Waterford/Westinghouse Licensing team teleconferences Capturing issues in Waterford/Westinghouse corrective action programs Elevating emerging risks and issues (if necessary) to decision makers with higher authority Updating the VOP (if necessary) based on emerging results
W3F1-2021-00015 Enclosure Page 4 of 15 The VOP is an umbrella document covering the range of activities in which Entergy is engaged to perform effective vendor oversight.
The Quality Assurance Program Manual (QAPM) (Reference 30) provides a consolidated overview of the quality program controls which govern the operation and maintenance of Entergys quality related items and activities. The QAPM implements 10 CFR 50 Appendix B, and the QAPM is implemented through the use of approved procedures (e.g., policies, directives, procedures, instructions, or other documents) which provide written guidance for the control of quality related activities and provide for the development of documentation to provide objective evidence of compliance.
For the CPCS procurement process outlined in CPP-WF3-2019-002 (Reference 6), the main implementing procedures for the QAPM are as follows:
EN-MP-100, Critical Procurements (Reference 13),
EN-QV-108, QA Surveillance Process [QAPM C.2] (Reference 4),
EN-LI-102, Corrective Action Program [QAPM A.1, A.6, A.7, B.13, B.15] (Reference 21),
EN-DC-149, Acceptance of Vendor Documents [QAPM B14.a, b - Document Control]
(Reference 18) and EN-DC-115, Engineering Change Process [QAPM A.7, B.2, B.8, B.11, B.15] (Reference 19).
The VOP works in coordination with existing Entergy Quality Assurance processes and procedures. The coordination with existing QA processes, procedures and staff ensures that all vendor documents, software and equipment meet all quality and design requirements.
The remainder of this section details the references that were used to create the VOP and how the existing Entergy procedures ensure the VOP and QA processes are interrelated.
The following key documents provide input to vendor oversight activities:
Critical Procurement Plan (CPP) (Reference 6)
Procurement specification and other Westinghouse contract documentation, Project-specific specifications, NRC DI&C-ISG-06 Rev. 2 Licensing Process, WCAP-16096 Common Qualified Platform Software Program Manual (Reference 9),
EPRI Digital Engineering Guide (DEG) (Reference 3) and EPRI Handbook for Evaluating Critical Digital Equipment and Systems (Reference 8).
There are several Entergy procedures which are being utilized to conduct vendor oversight activities under the VOP. Those procedures are described below:
EN-MP-100 (Reference 13) provides guidance for the establishment of oversight activities to ensure critical materials and related services are planned and executed such that all applicable requirements are met. Monitoring, verification and acceptance phase activities are defined in the CPP during the Planning Phase. Verification can be either through the normal Receipt Inspection process or other activities outlined in the CPP. The CPP may require activities during manufacturing, testing, receipt inspection, pre-installation or post-installation testing.
W3F1-2021-00015 Enclosure Page 5 of 15 The CPP provides a summary of the requirements and necessary actions including on-site services (when required), to ensure that the Critical Procurement will meet Entergys expectations. The CPP provides details for the project scope, the focus areas or scope of the project design and implementation, and the project risks for the procurement process. The scope of supply in Contract 10575450-01 (Reference 1), and the scope details in SPEC 00005-W (Reference 5), provide details for the CPC modification and equipment.
The CPP credits the management of the procurement risks based on the Westinghouse software verification and validation process, factory acceptance testing, performance of site acceptance testing, and rigorous software testing. QA surveillances will be performed to ensure the approved Westinghouse processes were followed. Actions in the CPP are controlled and documented as Waterford work tracking items.
EN-DC-149 (Reference 18) provides guidance for the review and approval of Westinghouse documents and drawings. EN-DC-149 establishes the process to be used to control the receipt, distribution, review, and revision of technical vendor documents originating from outside Entergy. The overall process governing the preparation, revision, review, approval, acceptance and use of vendor produced calculations is addressed in EN-DC-126 (Reference 25). The overall Engineering Report process is addressed by EN-DC-147 (Reference 26). For such documents, the vendor acceptance should be documented as per the guidance in the above referenced procedures.
The technical review per EN-DC-149 will be performed to the level of detail described in Table 5.1 for Risk Ranked Review of Vendor Supplied Documents. The risk ranking is developed with the Pre-Job Brief in accordance with Sections 5.2 and 5.3 of EN-HU-104 (Reference 27). .6 of EN-HU-104 provides the methodology for determining the overall risk level of the activity.
EN-HU-104 (Reference 27) provides direction for the risk assessment of technical work, senior management notifications of results, pre-job briefs, independent third-party reviews (ITPR), and post-job briefs to capture lessons learned. The CPC Replacement project risk rank is 1 or high-high. This risk ranking requires a Challenge Board, which includes station and fleet personnel with expertise in the area. An Independent Third-Party Review by A/E, consultant, or Off-site Specialists (ITPR) is being performed since this project is risk rank 1. EN-OM-132 (Reference
- 28) is being used to perform a risk assessment.
EN-OM-132 provides a consistent method within Entergy to evaluate and manage risks and can be applied to a broad range of issues. This process describes the method to perform risk assessments and is designed to be used when prompted or required by specific processes, such as EN-HU-104.
EN-FAP-PM-004 (Reference 29) drives consistency and certainty in project delivery capabilities and outcomes through a process for project development, planning and execution. The Project Manager establishes and updates the risk assessment, which is the Quantitative Risk Assessment (QRA). This process provides a comprehensive framework for project development, planning, and execution.
EN-PM-100 (Reference 12) establishes requirements and guidance to ensure a standard and predictable approach to project management throughout the life cycle of the project. This procedure provides requirements and guidance for risk and issue identification and management. The Project Manager is responsible for ensuring all risks and issues are identified, evaluated and managed properly.
W3F1-2021-00015 Enclosure Page 6 of 15
- 3. Project Organization and Roles (Stakeholders)
The following stakeholder roles and responsibilities are described in the VOP.
Entergy Project Team Project Manager Assistant Project Manager Quality Assurance (QA) Representative Lead Responsible Engineer Digital or I&C Engineers Cyber Security Engineer System Engineer Lead Licensing Engineer Human Factors Engineer Maintenance Representative Operations Representative Simulator Representative Various Test Coordinator/Engineers Westinghouse Project Team Project Manager Quality Manager Design Engineers Cyber Security Engineer Simulator Project Representative Test Engineers and Software V&V Engineers CPCS Product Manager CPCS Technical Advisor CPCS Technical Lead CPCS Licensing lead
- 4. Development and Assessment of Potential Project and Technical Risk Factors EN-HU-104 (Reference 27) provides direction for the risk assessment of technical work, senior management notifications of results, pre-job briefs, independent third-party reviews (ITPR), and post-job briefs to capture lessons learned. Based on EN-HU-104, the CPC Replacement project risk rank is a 1 or high-high. An Independent Third-Party Review (ITPR) is being performed for critical documents.
All modes of plant operation were considered when assessing consequence risk factors.
The consequence risk factors assessment includes an evaluation of the following criteria:
Reactivity Management Reactor Scram or Lost/limited Generation Radiological release or exposure Potential for creating a serious personnel safety issue Operability issue affecting multiple trains of safety related system Regulatory non-compliance Unplanned Tech Spec entry into a shutdown LCO less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Unplanned Safety System Actuation/Loss
W3F1-2021-00015 Enclosure Page 7 of 15 Regulatory open item created or not addressed Operator Workaround or challenge created or not addressed Unplanned Component Unavailability Tech Spec violation Reportable environmental consequence Repeat functional failure of Maintenance Rule systems, structures or components with potential to create new (a)(1) system Reactor coolant or steam generator chemistry transient outside of acceptable band As a result of the high-high risk ranking (EN-HU-104, Risk Rank 1), EPRI DEG Table 5-1 was considered to evaluate additional project and technical risk factors. The following project and technical risk factors were assessed in accordance with EPRI DEG (Reference 3), Table 5-1:
Schedule Technical Staff Conceptual Design Hazards Procurement Human Factors Engineering Data Communications Cyber Security Plant Integration Design Testing Configuration Management Training Per EPRI DEG Section 5.2.3, moderate risk factors indicate a need for supplemental oversight methods. Based on the risk categorization, vendor oversight activities have been prioritized.
- 5. Determine Performance Measures and Acceptance Criteria Performance measures and their acceptance criteria are included in the VOP. The scope of vendor oversight is expected to evolve during the project. Project-specific performance measures that warrant vendor oversight are updated as this list changes.
The performance measures are divided into three categories with acceptance criteria provided for each:
Critical Characteristics, Design Artifacts, and Programmatic Elements.
- 1. Critical Characteristics The Critical Characteristics are those important design, material, and performance characteristics of a system that, once verified, will provide reasonable assurance that the system will perform its intended critical functions. Note that the critical characteristics are drawn, in part, from the projects Critical Procurement Plan (Reference 6) and EPRI Topical Report 1011710 (Reference 8).
W3F1-2021-00015 Enclosure Page 8 of 15 The critical characteristics are divided into the following categories:
Physical, Performance, Environmental, and Cyber.
Design inputs and/or Critical Characteristics, Cyber Security (Reference 23), Software Quality Assurance (Reference 24) or other design requirements specific to the procurement of the CPCS are evaluated in the CPP. This includes critical characteristics to be verified during construction of the CPCS modification. Critical characteristics will be verified during factory testing and V&V activities, which will bound the design requirements.
Oversight of critical characteristics utilizes the following vendor oversight activities:
Conducting vendor audits and quality surveillances Reviewing Westinghouse design output documents Participating in Factory Acceptance Testing Conducting Site Acceptance Testing Observing or witnessing specific vendor activities Capturing issues in Waterford/Westinghouse corrective action programs
- 2. Design Artifacts The Design Artifacts are the set of design output documents described in the Westinghouse procurement documentation. These documents are generated in accordance with the Westinghouse SPM, which is NRC-approved. Examples of design artifacts include: System Requirements Specification (SyRS), Software Requirements Specification (SRS), Availability Analysis, Licensing Technical Report (LTR).
Waterford engineering procedures and processes provide the review framework for these design documents. Entergy procedure EN-DC-149, Acceptance of Vendor Documents, provides the process to be used to control the receipt, distribution, review, and revision of technical vendor documents. This process:
Ensures review by appropriate departments and disciplines, Ensures that affected documents, programs, and data bases are updated, Ensures that the vendor is in compliance with the design specification and purchase order, Ensures the document is consistent with plant licensing and design basis, and Ensures technical review is performed based on the risk ranking of the project documents.
W3F1-2021-00015 Enclosure Page 9 of 15 In addition, Waterford is utilizing the independent third-party review (ITPR) review process for critical design artifacts (e.g., SyRS, SRS, LTR, etc.). This independent review, by industry subject matter experts, allows:
Entergy to provide additional, independent oversight of the Westinghouse products Entergy to receive independent feedback on the quality of their vendor oversight of Westinghouse design artifacts Oversight of the design artifacts utilizes the following vendor oversight activities:
Conducting vendor audits Reviewing Westinghouse design output documents (e.g., specifications, drawings, analyses)
Providing input to and review/confirmation of specific vendor activities and related information items Coordinating multi-disciplined interactions between various stakeholders Capturing issues in Waterford/Westinghouse corrective action programs
- 3. Programmatic Elements The Programmatic Elements include the vendors programs and processes relevant to the project. The elements of the system lifecycle are described in the Westinghouse SPM (Reference 9). The SPM describes the requirements for the software design and development process including the software/hardware interface. The SPM also describes the requirements for the use of software in Common Q systems.
The following SPM plans are developed:
Software Safety Plan, which identifies the processes that, will reasonably assure that safety-critical software does not have hazards that could jeopardize the health and safety of the public.
Software Quality Assurance Plan (SQAP), which describes the process and practice of developing and using software. The SQAP addresses standards, conventions, reviews, exception reporting and other software quality issues.
Software Verification and Validation Plan (SVVP), which describes the method of assuring correctness of the software.
Software Configuration Management Plan (SCMP), which describes the method of maintaining the software in an identifiable state at all times.
Software Test Plan, which describes the method for testing software.
Some of these SPM plans will have project-specific instances (i.e., SVVP, SCMP, and Software Test Plan). These project-specific plans will be evaluated to ensure they are developed in accordance with the SPM.
W3F1-2021-00015 Enclosure Page 10 of 15 The SPM describes the software lifecycle phases as:
Concept Requirements Analysis Design Implementation or Coding Test Installation and Checkout Operation and Maintenance Retirement Reviews will be performed of verification and validation (V&V) for each applicable lifecycle phase for each plan through Test. The Installation and Checkout, Operations and Maintenance, and Retirement phases are Entergy responsibility and not included in scope of VOP. However, per SPM PSAI #4, Entergy will review the Westinghouse Technical Manual, provided in accordance with Reference 1, to verify it satisfies the requirements for the Software Operations Plan per the Common Q SPM.
Oversight of the programmatic elements utilizes the following vendor oversight activities:
Conducting vendor audits Reviewing Westinghouse design output documents Providing input to and review/confirmation of specific vendor activities and related information items Observing or witnessing specific vendor activities Participating directly in specific vendor activities Coordinating multi-disciplined interactions between various stakeholders Capturing issues in Waterford/Westinghouse corrective action programs The VOP provides acceptance criteria related to the following important system development topics. Example Acceptance criteria are provided in sub-bullets below:
Quality Assurance o Ensure that Westinghouse complies with the requirements of Appendix B to 10 CFR Part 50 and 10 CFR Part 21 to control the quality of safety-related materials, equipment, and services, o Ensure the Software Quality Assurance (SQA) program in accordance with the SPM is effective in controlling the software development process to assure quality, and meets the commitments described in the LAR for SQA.
Configuration Management o Ensure that the Westinghouse Configuration Management Release Reports identifies, names, and describes the documented physical and functional characteristics of the code, specifications, design, and data elements to be controlled for the project. Verify that Westinghouse follows the configuration management process in the NRC-approved Common Q SPM.
W3F1-2021-00015 Enclosure Page 11 of 15 Software Verification and Validation (V&V) o Verify that Westinghouse follows the V&V requirements in the NRC-approved Common Q SPM. The description of the software V&V processes will address the following:
V&V organization responsibilities, V&V processes, activities, and tasks, V&V reporting, V&V administrative controls for anomaly resolution and reporting, task iteration policy, and deviation policy, and V&V test documentation.
Software Safety o Verify that documentation exists to show that the safety analysis activities have been successfully accomplished for each life cycle activity group. In particular, the documentation will show that:
System safety requirements have been adequately addressed for each activity group, No new hazards have been introduced; that the software or logic requirements, design elements, and code elements that can affect safety have been identified, and All other software or logic requirements, design, and code elements will not adversely affect safety.
Secure Development Environment o Verify that the Westinghouse has a development environment that complies with the requirements the NRC-approved Common Q SPM, Section 12. SDE documentation exists for key attributes including:
Having a method for identifying the origin of critical components and ensuring that all critical asset components are compliant with the suppliers security requirements and free of counterfeits.
Cyber Security o Verify that all known cyber security vulnerabilities of the operating system, vendors software, firmware, or hardware is remediated or a description of why the vulnerability is not a concern for the system as installed is supplied.
Software Lifecycle Processes o Verify that Westinghouse plans and performs application software lifecycle activities in a traceable and orderly manner in accordance with the SPM. The VOP evaluates the following lifecycle areas:
Software Requirements - Ensure that project requirements are examined, understandable, and unambiguous. Reference is made to applicable drawings, specifications, codes, standards, regulations, procedures or instructions. Verify that security requirements are specified commensurate with the risk from unauthorized access or use. The requirements traceability shows where in the software or application logic design, the required action is being performed as well as providing traceability back to the system requirements that generated these software requirements.
W3F1-2021-00015 Enclosure Page 12 of 15 Software Design - Verify that the architecture is sufficiently detailed to allow for understanding the operation, flow of data, and the deterministic nature of the software or logic. Verify the technical adequacy of the design and ensure internal completeness, consistency, clarity, and correctness of the software design.
In addition, the software or logic design specification will be reviewed to determine that it is understandable and traceable to the software requirements. While the software design will consider the operating environment, measures to mitigate the consequences of problems will also be an integral part of the design.
Hardware Requirements o Verify the hardware is designed and manufactured to meet the physical and functional requirements described in the procurement specification, SyRS(s),
and design documents and drawings.
Plant Specific Action Items (PSAIs) o Ensure that PSAIs identified in the Topical Reports and further discussed in the Licensing Technical Report (LTR), are addressed as described in the LAR.
Entergy engineering procedures and processes provide the review framework for these design documents. Entergy procedure EN-DC-149, Acceptance of Vendor Documents, provides the process to be used to control the receipt, distribution, review, and revision of technical vendor documents (Reference 18). This process:
Ensures review by appropriate departments and disciplines Ensures that affected documents, programs, and data bases are updated Ensures that the vendor is in compliance with the design specification and purchase order Ensures the document is consistent with plant licensing and design basis Ensures technical review is performed based on the risk ranking of the project documents
- 6. Implement Appropriate Oversight Methods As discussed in Section 4 above, vendor oversight is based on risk factors. Therefore, the amount and specific focus of the oversight activities vary as the project evolves.
Oversight of Westinghouse occurs based on the various Risk Factors (VOP Section 5) and Performance Measures (VOP Section 6). Waterford may adjust the risk factors as the project progresses.
LOW RISK factors indicate continued use of routine oversight methods, such as:
Periodic Audits Periodic Surveillances Routine Design Reviews Routine Project Meetings
W3F1-2021-00015 Enclosure Page 13 of 15 MODERATE RISK factors indicate a need for supplemental oversight methods, such as:
Increased surveillance frequency Interim design reviews Challenge boards Increased frequency of project meetings HIGH RISK factors indicate a need for extraordinary oversight methods, such as:
Placement of oversight staff inside the vendors organization Management intervention Stop work order and implement recovery plan
- 7. Perform Corrective Actions Condition reports for entry into the corrective action program document vendor performance or quality that is in question. The following conditions, as a minimum, trigger a condition report:
Westinghouse noncompliance with the Westinghouses own quality program, software processes, or hardware processes Nuclear safety may be adversely impacted if the digital item is installed and operated Unit generation may be adversely impacted if the digital item is installed and operated Digital item quality simply cannot be assured Digital item quality cannot be assured without a significant project delay Digital item quality is not assured, and identical or similar digital items are already installed in the facility, in other applications, and are considered operable or available Westinghouse has been awarded other Entergy POs or contracts to deliver other digital items, and performance measures indicate that the quality of the other items may not be assured If the Waterford project team identifies performance issues, oversight would be enhanced to include:
Periodic meetings to discuss and resolve issues Additional technical reviews or surveillances Management Intervention Stop work and implement recovery plan
W3F1-2021-00015 Enclosure Page 14 of 15
- 8. Documentation Per the EPRI DEG, for high consequence and high technology configurability, vendor oversight must be documented. Through DI&C-ISG-06 and public interactions, the NRC has expressed an interest in vendor oversight. Documentation would help provide assurance to the NRC, during an inspection, that Waterford has been conducting oversight of Westinghouse through the system development lifecycle.
Vendor oversight can be documented through multiple methods:
Formal audit plans/reports Comments/feedback on design artifacts through the owner acceptance engineering process Teleconference notes Emails Written correspondence between Waterford and Westinghouse Note that documentation format may vary but the content will provide the vendor oversight level of detail and corrective actions (if any).
- 9. Attachments The VOP includes attachments for:
CPCS Replacement Project Division of Responsibility CPCS Replacement Project Organization Chart o Entergy CPCS Project Organization Chart o Westinghouse CPCS Project Organization Chart
- 10. References
- 1. Entergy procurement documents including Contract 10575450-01
- 2. American Society of Mechanical Engineers (ASME), NQA-1:2015, Quality Assurance Requirements for Nuclear Facility Applications
- 3. EPRI Technical Report 3002011816, Digital Engineering Guide (DEG)
- 4. EN-QV-108, QA Surveillance Process
- 5. SPEC-18-00005-W, Rev 0
- 6. CPCS Replacement Project Critical Procurement Project (CPP), CPP-WF3-2019-002 (WTWF3-2019-00236)
- 7. NRC DI&C-ISG-06, Licensing Process, Revision 2
- 8. EPRI Topical Report 1011710, Handbook for Evaluating Critical Digital Equipment and Systems
- 9. WCAP-16096, Westinghouse Software Program Manual (SPM) for Common Q' Systems
- 10. WCAP-16097, Westinghouse Common Qualified Platform Topical Report
- 11. CWTR3-19-21 R2, Attachment 1, Compliance Matrix
- 12. NMM procedure EN-PM-100, Conduct of Project Management
W3F1-2021-00015 Enclosure Page 15 of 15
- 13. NMM procedure EN-MP-100, Critical Procurements
- 14. IEEE Std. 1028, Standard for Software Requirements and Audits
- 15. IEEE Std. 344-1975, Seismic Qualification of Equipment for Nuclear Power Generating Stations
- 16. RG 1.152, Criteria for Use of Computers in Safety Systems of Nuclear Power Plants, Revision 3
- 17. CWTR3-19-23, Westinghouse Cyber Security Compliance Matrix
- 18. NMM procedure EN-DC-149, Acceptance of Vendor Documents
- 19. NMM procedure EN-DC-115, Engineering Change Process
- 20. NMM procedure EN-DC-163, Human Factors Evaluation
- 21. EN-LI-102, Corrective Action Program
- 22. EN-DC-117, Post Modification Testing and Special Instructions
- 23. EN-IT-103, Nuclear Cyber Security Program
- 24. EN-IT-104, Software Quality Assurance Program
- 25. EN-DC-126, Engineering Calculation Process
- 26. EN-DC-147, Engineering Reports
- 27. EN-HU-104, Technical Task Risk & Rigor
- 28. EN-OM-132, Nuclear Risk Management Process
- 29. EN-FAP-PM-004, Project Implementation - Segment 3 & 4
- 30. Entergy Quality Assurance Program Manual, Rev 39, Effective July 16, 2020