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MONTHYEARW3F1-2020-0047, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors2020-12-18018 December 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Reactors Project stage: Request ML21039A6412021-01-28028 January 2021 NRR E-mail Capture - NRC LIC-109 Acceptance Review Results for Waterford 3 50.69 LAR Project stage: Acceptance Review W3F1-2021-0003, Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B2021-02-0808 February 2021 Application for Technical Specification Change to Adopt Risk-Informed Extended Completion Times - RITSTF Initiative 4B Project stage: Request ML21099A0022021-04-14014 April 2021 Regulatory Audit in Support of Review of Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors EPID L-2020-LLA-0279 Project stage: Approval ML21134A2122021-05-21021 May 2021 Audit Meeting Agenda and Audit Questions for LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System, and Components for Nuclear Power Reactors Project stage: Meeting ML21167A1442021-06-24024 June 2021 Summary of Regulatory Audit in Support of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, System and Components for Nuclear Power Reactors, LAR Project stage: Approval ML21218A0402021-07-26026 July 2021 NRR E-mail Capture - Final RAIs to Entergy Operations, Waterford Steam Electric Station, Unit 3 LAR to Adopt 10 CFR 50.69 Project stage: RAI 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 Project stage: Request ML21349B3642021-12-15015 December 2021 Supplement - Application to Implement an Alternate Defense-in-Depth Categorization Process, an Alternate Pressure Boundary Categorization Process, and an Alternate Seismic Categorization Process in Accordance Project stage: Supplement ML22209A1062022-01-20020 January 2022 NRR E-mail Capture - (External_Sender) Options Moving Forward Regarding Waterford TSTF-505 and 50.69 Project stage: Other W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors Project stage: Supplement 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. Project stage: Response to RAI ML22215A2062022-08-0303 August 2022 NRR E-mail Capture - Waterford 3 - LAR to Adopt Title 10 of the Code of Federal Regulations, Section 50.69: Loe and Completion Date Update Project stage: Approval 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 Project stage: Response to RAI ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Approval 2021-06-24
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Category:Audit Plan
MONTHYEARML21099A0022021-04-14014 April 2021 Regulatory Audit in Support of Review of Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors EPID L-2020-LLA-0279 ML20268B3242020-10-0101 October 2020 Regulatory Audit in Support of Review of Digital Upgrade License Amendment Request ML16259A1892016-12-0505 December 2016 Nuclear Regulatory Commission Plan for the Audit of Mitigation Strategies Assessment Submittals Related to Order EA-12-049, Order to Modify Licenses With Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML16172A0082016-07-0808 July 2016 Environmental Site Audit Plan Regarding Waterford Steam Electric Station, Unit 3 ML16168A3592016-06-28028 June 2016 Plan for the Aging Management Program Regulatory Audits Regarding the Waterford Steam Electric Station, Unit 3 License Renewal Application Review ML16152A5952016-06-0606 June 2016 License Renewal Scoping and Screening Methodology Audit Documentation List 6/13/16 - 6/16/16 ML16152A0092016-06-0606 June 2016 License Renewal Scoping and Screening Methodology Audit Plan 6/13/16 6/16/16 ML15231A3542015-08-25025 August 2015 Nuclear Regulatory Commission Plan for Audit on Entergy Operations Inc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 Flooding for Waterford Steam Electric Station ML15141A4682015-05-27027 May 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14350A2122014-12-22022 December 2014 Regulatory Audit Plan; January 12-14, 2015 Audit in Support of the Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2021-04-14
[Table view] Category:Letter
MONTHYEARIR 05000382/20244022024-10-10010 October 2024 Security Baseline Inspection Report 05000382/2024402 Public IR 05000382/20244032024-10-0909 October 2024 Security Baseline Inspection Report 05000382/2024403 IR 05000382/20240112024-10-0101 October 2024 State Fire Protection Team Inspection Report 05000382/2024011 IR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24268A1132024-09-24024 September 2024 Acknowledgment of Response to NRC Inspection Report 05000382/2024013, and Notice of Violation ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure 05000382/LER-2024-001, 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 ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement2024-02-14014 February 2024 Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-30030 December 2023 Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000382/20230032023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 2024-09-06
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April 14, 2021 Site Vice President Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REGULATORY AUDIT IN SUPPORT OF REVIEW OF APPLICATION TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEM, AND COMPONENTS FOR NUCLEAR POWER REACTORS (EPID L-2020-LLA-0279)
Dear Sir or Madam:
By letter W3F1-2020-0047 dated December 18, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20353A433), Entergy Operations, Inc. (the licensee) submitted a license amendment request (LAR) for the Waterford Steam Electric Station, Unit 3 (Waterford 3). The proposed amendment would adopt Title 10 of the Code of Federal Regulations Section 50.69 (10 CFR 50.69), Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, into the Waterford 3 licensing basis.
The U.S. Nuclear Regulatory Commission (NRC) staff has identified the need for a regulatory audit to examine the licensees non-docketed information with the intent to gain understanding, to verify information, or to identify information that will require docketing to support the basis of the licensing or regulatory decision.
The NRC staff will conduct the audit virtually at NRC Headquarters in Rockville, Maryland, via a licensee-established electronic portal available to NRC staff from approximately April 14, 2021, through June 11, 2021, with formal audit meetings from June 1 to through June 3, 2021.
The audit plan, which was discussed with your staff on April 8, 2021, is enclosed with this letter.
If you have any questions, please contact me at (301) 415-1383 or by e-mail at Perry.Buckberg@nrc.gov.
Sincerely,
/RA/
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Audit Plan cc: Listserv
REGULATORY AUDIT PLAN BY THE OFFICE OF NUCLEAR REACTOR REGULATION TO SUPPORT THE REVIEW OF LICENSE AMENDMENT REQUEST TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREAMENT OF STRUCTURES, SYSTEMS AND COMPONENENTS FOR NUCLEAR POWER REACTORS ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 BACKGROUND
By letter W3F1-2020-0047 dated December 18, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20353A433), Entergy Operations, Inc.
(Entergy, the licensee) submitted a license amendment request (LAR) for the Waterford Steam Electric Station, Unit 3 (Waterford 3).
The proposed amendment would adopt Title 10 of the Code of Federal Regulations Section 50.69 (10 CFR 50.69), Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, into the Waterford 3 licensing basis.
2.0 REGULATORY AUDIT BASES A regulatory audit is a planned licensing or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. The audit is conducted with the intent to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision. Performing a regulatory audit is expected to assist the U.S. Nuclear Regulatory Commission (NRC) staff in efficiently conducting its review of the LAR and to gain insights to the licensees processes and procedures. Information that the NRC staff relies upon to make the safety determination must be submitted on the docket.
The basis of this audit is Entergys LAR for Waterford Steam Electric Station, and NUREG-0800, Standard Review Pan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition, Section 19.2, Review of Risk Information Used to Support Permanent Plant-Specific Changes to the Licensing Basis: General Guidance, dated June 2007 (ADAMS Accession No. ML071700658).
This audit will be conducted in accordance with the Office of Nuclear Reactor Regulation (NRR)
Office Instruction LIC-111, Revision 1, Regulatory Audits, dated October 2019 (ADAMS Accession No. ML19226A274). An audit was determined to be the most efficient approach toward a timely resolution of issues associated with this LAR review, since the NRC staff will have an opportunity to minimize the potential for multiple rounds of requests for additional Enclosure
information and ensure no unnecessary burden will be imposed by requiring the licensee to address issues that are no longer necessary to make a safety determination.
3.0 PURPOSE AND SCOPE The purpose of the audit is to gain a more detailed understanding of the licensees process to implement risk-informed categorization and treatment of structures, systems and components (SSCs) as proposed in the LAR. The NRC staff will audit internal events and fire probabilistic risk assessment (PRA) and the risk-informed approach implementing 10 CFR 50.69.
The areas of focus for the regulatory audit are the information contained in the licensees submittal, the enclosed audit information needs, and all associated and relevant supporting documentation (e.g., methodology, process information, calculations, etc.) identified below.
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The following documentation should be available to the audit team:
- 1. Applicable peer review reports and closure reports for internal events, internal flooding, fire and seismic PRAs.
- 2. Available 10 CFR 50.69 SSCs categorization program procedures (i.e., categorization review and adjustment process, decision criteria for Independent Decision-Making Panel, etc.).
- 3. Uncertainty notebooks for internal events, internal flooding, and fire PRAs related to PRA model assumptions and sources of uncertainty.
- 4. Documentation of review of PRA model assumptions and sources of uncertainty and identification of key assumptions and sources of uncertainty for the application identified in the LAR.
- 5. PRA notebooks for the modeling of Diverse and Flexible Mitigation Capability (FLEX) equipment and FLEX human error probabilities, if credited in the PRA.
- 6. Documentation related to the disposition of open facts and observations.
5.0 AUDIT TEAM The audit will be conducted by NRC staff from NRR, Division of Operating Reactor Licensing (DORL), Plant Licensing Branch 4 (LPL4); Division of Risk assessment (DRA), Probabilistic Risk Assessment Licensing Branches A and C (APLA and APLC); and an NRC contractor from Pacific Northwest National Laboratory (PNNL). Key licensee personnel involved in the development of the LAR should be made available for interactions on a mutually agreeable schedule to respond to any questions from the NRC staff.
NRC Staff Team Perry Buckberg, NRR/DORL/LPL4 Mihaela Biro, NRR/DRA/APLA Alexander Schwab, NRR/DRA/APLA
Sunwoo Park, NRR/DRA/APLC Steve Alferink, NRR/DRA/APLC De Wu, NRR/DRA/APLC Mark Wilk, PNNL 6.0 LOGISTICS The NRC staff requests the licensee to have the information discussed in Section 4.0 readily available and accessible for the NRC staffs review via an internet-based portal. The audit will occur via the internet-based portal at NRC Headquarters Office in Rockville, Maryland, from approximately April 14, 2021, through June 11, 2021, with formal audit meetings from June 1, 2021, through June 3, 2021. The NRC staff requests the licensee to have its staff generally available by telephone at mutually agreeable times during regular business hours (e.g.,
Monday - Thursday, 9:00 a.m. to 4:00 p.m., Eastern Time) while the internet-based portal is open from April 12, through June 11, 2021, if the NRC staff has any questions during the audit related to any information on the portal. The NRC staff requests the licensee to have its staff available by telephone and agreed virtual media during regular business hours during the actual audit week from June 1, through June 3, 2021. The NRCs licensing project manager will inform the licensee via routine communications when the NRC staff no longer needs access to the portal.
7.0 SPECIAL REQUESTS The NRC staff would like access to the documents listed above in Section 4.0 through the online portal that allows the NRC staff and contractors to access documents via the internet.
The following conditions associated with the online portal must be maintained throughout the duration that the NRC staff and contractors have access to the online portal:
The online portal will be password-protected, and separate passwords will be assigned to the NRC staff and contractors who are participating in the audit.
The online portal will be sufficiently secure to prevent the NRC staff and contractors from printing, saving, downloading, or collecting any information on the online portal.
Conditions of use of the online portal will be displayed on the login screen and will require acknowledgement by each user.
Username and password information should be provided directly to the NRC staff and contractors. The NRC project manager will provide Entergy the names and contact information of the NRC staff and contractors who will be participating in the audit. All other communications should be coordinated through the NRC project manager.
6.0 DELIVERABLES An audit summary, which may be public, will be prepared within 90 days of the completion of the audit. If the NRC staff identifies information during the audit that is needed to support its regulatory decision, the staff will issue requests for additional informant to the licensee after the audit.
ML21099A002 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DRA/APLA/BC NAME PBuckberg PBlechman RPascarelli DATE 4/13/2021 4/13/2021 4/13/2021 OFFICE NRR/DRA/APLC NRR/DORL/LPL4/PM NRR/DORL/LPL4/BC NAME SRosenberg PBuckberg JDixon-Herrity DATE 4/13/2021 4/13/2021 4/14/2020