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EPID:L-2018-LLA-0008, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors (Approved, Closed) EPID:L-2018-LLA-0034, TSTF-425 (Approved, Closed) |
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MONTHYEARBSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors Project stage: Request HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. Project stage: Request ML18045A8492018-02-14014 February 2018 NRR E-mail Capture - Brunswick 50.69 - Risk Informed SSC Acceptance Review Project stage: Acceptance Review ML18130A0212018-05-0909 May 2018 NRR E-mail Capture - Brunswick - Adoption of 10 CFR 50.69 - Hwpra and Xfpra Audit Plan and Setup of Online Reference Portal Project stage: Other ML18180A4182018-07-0202 July 2018 Audit Plan for Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components Forr Nuclear Power Reactors (EPID L-2018-LLA-0008; L-2018-LLA-0034) Project stage: Other ML18220A7902018-08-0707 August 2018 NRR E-mail Capture - Brunswick - Adoption of 10 CFR 50.69 - Supplement to the Hwpra and Xfpra Audit Plan for BSEP Onsite Audit Project stage: Other ML18263A3042018-09-20020 September 2018 NRR E-mail Capture - Brunswick Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: Draft RAI RA-18-0144, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report2018-09-27027 September 2018 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Report Project stage: Request ML18282A1492018-10-0909 October 2018 NRR E-mail Capture - Brunswick RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: RAI ML18264A0282018-10-0909 October 2018 RAI Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization Aad Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: RAI RA-18-0175, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-10-18018 October 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. Project stage: Response to RAI RA-18-0178, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for ...2018-11-0202 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for ... Project stage: Response to RAI ML18282A2242018-11-14014 November 2018 Regulatory Audit Summary Regarding License Amendment Requests to Adopt 10 CFR 50.69 Project stage: Other ML18360A0352018-12-21021 December 2018 NRR E-mail Capture - Brunswick Draft 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: Draft RAI ML18361A6712019-01-0808 January 2019 Summary of Meeting with Duke Energy Progress, LLC to Discuss License Amendment Request for Shearon Harris Unit 1, Regarding 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Project stage: Meeting ML19015A0302019-01-14014 January 2019 NRR E-mail Capture - Brunswick 2nd Round RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: RAI RA-19-0010, Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-02-13013 February 2019 Response to NRC RAI Re Application to Adapt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Request ML19056A2212019-02-25025 February 2019 NRR E-mail Capture - Brunswick Draft 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: Draft RAI ML19067A2712019-03-0707 March 2019 NRR E-mail Capture - Brunswick 3rd Round RAI - LAR to Allow Implementation of the Provisions 10 CFR 50.69 Project stage: RAI ML19060A0912019-03-18018 March 2019 Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: RAI RA-19-0152, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors.2019-04-0808 April 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,Systems, and Components (Sscs) for Nuclear Power Reactors. Project stage: Response to RAI RA-19-0153, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear ..2019-04-23023 April 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear .. Project stage: Response to RAI ML19149A2102019-07-0101 July 2019 Regulatory Audit Summary, License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants Project stage: Other ML19149A4712019-09-17017 September 2019 Issuance of Amendment Nos. 292 and 320, Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors Project stage: Approval ML19192A0122019-09-17017 September 2019 Issuance of Amendment No. 174 Adopt Title 10 of the Code of Federal Regulations 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components Project stage: Approval 2018-09-20
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Category:Audit Plan
MONTHYEARML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner ML21348A7192021-12-21021 December 2021 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML21260A0742021-09-22022 September 2021 Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times ML21099A2742021-04-26026 April 2021 Regulatory Audit for Review of LAR to Revise 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML18180A4182018-07-0202 July 2018 Audit Plan for Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components Forr Nuclear Power Reactors (EPID L-2018-LLA-0008; L-2018-LLA-0034) ML17220A3282017-08-10010 August 2017 Nuclear Regulatory Commission Audits of Licensee Responses to Phase 2 of Order EA-13-109 to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions 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 ML15231A0222015-09-0808 September 2015 Nuclear Regulatory Commission Plan for the Audit of Duke Energy Progress, Inc. Interim Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 - Seismic for Brunswick Steam Electric Plant, ML15148A7622015-06-11011 June 2015 Nuclear Regulatory Commission Plan for the Audit of Duke Energy Progress, Inc.'S Flooding Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Brunswick Steam Electric Plants, Units 1 a ML14356A0032015-02-10010 February 2015 Audit of Licensee Responses to the Expedited Seismic Evaluation Process to Support Implementation of Near-Term Task Force Recommendation 2.1, Seismic ML14322A1882014-11-26026 November 2014 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies an Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 ML14308A0312014-11-0606 November 2014 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 ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 ML13127A0382013-05-14014 May 2013 Plan for the Regulatory Audit Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident 2023-05-12
[Table view] Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 IR 05000324/20243012023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) 2024-01-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 July 2, 2018 Mr. Steven Capps Senior Vice President Nuclear Corporate Duke Energy Corporation 526 South Church Street, EC-07H Charlotte, NC 28202
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 AND SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -AUDIT PLAN RE: APPLICATION TO ADOPT 10 CFR 50.69, "RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS, AND COMPONENTS FOR NUCLEAR POWER REACTORS" (EPID L-2018-LLA-0008 AND L-2018-LLA-0034)
Dear Mr. Capps:
By letters dated January 10 and February 1, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 1801 OA344 and ML18033B768, respectively), Duke Energy Progress, LLC (Duke Energy) submitted license amendment requests for Brunswick Steam Electric Plant, Units 1 and 2, and Shearon Harris Nuclear Power Plant, Unit 1. The proposed amendments would modify the licensing basis to allow for the implementation of the provisions of Section 50.69, "Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants," of Title 10 of the Code of Federal Regulations ( 10 CFR).
The U.S. Nuclear Regulatory Commission (NRC) staff will conduct a regulatory audit to support its review of the proposed license amendments. The audit will be conducted at Duke Energy's corporate office in Charlotte, North Carolina, on July 17-19, 2018. The NRC staff's audit plan is enclosed. The audit plan may be supplemented with audit questions at a later time.
S. Capps If you have any questions, please contact me at 301-415-2760 or Martha.Barillas@nrc.gov.
Sincerely, Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325, 50-324, and 50-400
Enclosure:
Regulatory Audit Plan cc: Mr. William R. Gideon Vice President Brunswick Steam Electric Plant Duke Energy Progress, LLC 8470 River Road, SE (M/C BNP001)
Southport, NC 28461 Ms. Tanya Hamilton Site Vice President Shearon Harris Nuclear Power Plant, Unit 1 5413 Shearon Harris Road, M/C HNP01 New Hill, NC 27562-0165 Listserv
REGULATORY AUDIT PLAN BY THE OFFICE OF NUCLEAR REACTOR REGULATION TO SUPPORT THE REVIEW OF LICENSE AMENDMENT REQUESTS FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 AND SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 TO ADOPT 10 CFR 50.69, "RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS DOCKET NOS. 50-325, 50-324, AND 50-400
1.0 BACKGROUND
By letters dated January 10 and February 1, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML18010A344 and ML180338768, respectively), Duke Energy Progress, LLC (Duke Energy) submitted license amendment requests (LARs) for Brunswick Steam Electric Plant, Units 1 and 2 (BSEP), and Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendments would modify the licensing basis to allow for the implementation of the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.69, "Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants," and provide the ability to use probabilistic risk assessment (PRA) models, the internal events PRA (IEPRA), internal flooding PRA (IFPRA), and internal fire PRA (FPRA) for the proposed 10 CFR 50.69 categorization process.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed Duke Energy's submittals and determined that a regulatory audit of the BSEP and HNP IEPRA, IFPRA, and FPRA models and overall 10 CFR 50.69 categorization process would assist in the timely completion of the subject LAR review process. An audit is determined to be the most efficient approach to ensure a timely resolution of issues associated with this LAR review. This audit should minimize the potential for multiple rounds of requests for additional information (RAls) 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.
2.0 REGULATORY AUDIT BASIS A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. A regulatory audit is conducted with the intent to gain understanding, to verify information, and/or to identify information that will require docketing to support the basis of a licensing or regulatory decision.
Performing a regulatory audit of the licensee's information is expected to assist the staff in efficiently conducting its review or gain insights on the licensee's processes or procedures.
Information that the NRC staff relies upon to make the safety determination must be submitted on the docket. However, the NRC staff may review supporting information retained as records under 10 CFR 50. 71 and 10 CFR 54.37, which although not required to be submitted as part of the licensing action, would help the staff better understand the licensee's submitted information.
Enclosure
3.0 REGULATORY AUDIT SCOPE OR METHOD The audit will be performed consistent with the NRC's Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-111, "Regulatory Audits," dated December 16, 2008 (ADAMS Accession No. ML082900195). The purpose of this audit is to gain a more detailed understanding of Duke Energy's 10 CFR 50.69 categorization process by verifying conformance of categorization process with NRG-endorsed guidance and Duke Energy's implementation of the endorsed categorization process.
To accomplish these objectives, the NRC audit team will be:
- validating PRA quality is adequate for use in the BSEP and HNP applications;
- identifying new information that is needed in order for staff to reach a licensing or regulatory decision; and
- discussing audit questions with Duke Energy.
Upon completion of the audit, the NRC audit team will determine its need for any RAls to ensure any information needed to make its regulatory determination is available on BSEP's and HNP's dockets. Audit questions will likely be sent prior to the audit.
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The NRC audit team will require access to personnel knowledgeable in all aspects of Duke Energy's 10 CFR 50.69 applications for BSEP and HNP. At a minimum, a hard copy and electronic copy of the following documentation should be available to the audit team on the first day of the audit. In addition, presentations and specific discussion topics provided below may be requested.
Documents:
- Internal events and fire PRA documentation should be available on a computer with licensee support
- Internal events and fire PRA peer review reports and findings and observations (F&O) closure reports
- Documentation of changes to the PRA models with justification of upgrades/updates
- Documentation of preliminary categorization results, if available
Presentations:
- 50.69 process presentation
- Walk-through categorization results Discussions:
- Discussions of audit questions related to:
- a. F&Os
- b. PRA updates/upgrades, focused-scope peer reviews and F&O closure 5.0 TEAM ASSIGNMENTS The audit will be conducted by NRC staff from NRR's Division of Risk Assessment, PRA Licensing, and NRC contractors from the Pacific Northwest National Laboratories (PNNL) in support of the technical audit team members. Staff knowledgeable in 10 CFR 50.69 and risk-informed licensing reviews will comprise the audit team. Observers at the audit may include NRR technical reviewers and project managers (PMs).
The NRC Audit Team Leader will be Leslie Fields (PM) with Michael Levine as the NRC BSEP Technical Lead, and Brandon Hartle as the NRC HNP Technical Lead. The audit team leader will conduct daily briefings on the status of the review and coordinate audit activities while on site. The tables below show (1) the audit milestones and schedule, and (2) the planned audit team composition and their assigned areas for review during the audit.
Regulatory Audit Plan Review Areas and Assignments BSEP/HNP Lead Support 1 Categorization Process Team NRC QA/Contractor 2 PRA Technical Adequacy M. Levine/B. Hartle S. Dinsmore/ PNNL 2.a Peer Reviews M. Levine/B. Hartle S. Dinsmore/ PNNL 2.b Facts and Observations M. Levine/B. Hartle S. Dinsmore/ PNNL 2.c PRA updates/upgrades M. Levine/B. Hartle S. Dinsmore/ PNNL 3 External Hazards M. Reisi-Fard/S Vasavada S. Dinsmore/ PNNL 4 Integrated Decision-making Panel M. Levine/B. Hartle S. Dinsmore/ PNNL 5 Documentation, Configuration Control, Quality L. Fields Team Audit Team Roster NRC Staff Title Leslie Fields NRC Team Leader Michael Levine NRC Brunswick Technical Lead Brandon Hartle NRC Harris Technical Lead Stephen Dinsmore NRCQA Mark Wilk PNNL Garill Coles PNNL
6.0 LOGISTICS The regulatory audit will begin the morning of July 17, 2018, and will last approximately 3 days, concluding on the afternoon of July 191h. The NRC staff will schedule a conference call prior to the audit to discuss the details of the generic audit plan. The dates in the milestone chart below are subject to change based on mutual agreement between the licensee and the NRC. An entrance meeting for this audit will be held on the first day at 9:00 a.m. and an exit meeting will be held the final day at 4:00 p.m. (earlier/later) based on a mutually agreed-upon time. The NRC audit team leader will provide daily progress briefings to licensee personnel on the first and second day of the audit.
The audit will take place at a location agreed upon by the licensee and NRC audit team leader where (1) the necessary reference material and (2) appropriate Duke Energy staff should be available to support the review. Visitor access will be requested for the entire audit team for the duration of the audit. We recommend that security paperwork and processing be handled prior to the first day of the audit, if possible.
Audit Milestones and Schedule Activity Time Frame Comments Logistics/Clarification Teleconference from NRC Headquarters to discuss July 12, 2018 Call logistics and any Duke Energy questions.
NRC staff will present a brief team introduction and Onsite Audit Kick-Off discuss the scope of the audit. The licensee should July 17, 2018 Meeting introduce team members and give logistics for the week.
Meet with licensee to provide a summary of any End of Day Summary July 17-18, 2018 significant findings and requests for additional Briefings assistance.
Provide Rooms for Facilitate discussions between site and staff Focused Topic July 17-18, 2018 technical areas. Provide 1-2 breakout areas, if Discussions possible, for smaller discussions.
Onsite Audit Exit NRC staff will hold a brief exit meeting, with July 19, 2018 Meeting licensee staff to conclude audit activities.
Audit Summary (see 90 days after exit To document the audit.
Section 8.0 below) 7.0 SPECIAL REQUESTS The regulatory audit team will require the following to support the regulatory audit:
- Two computers with internet access and printing capability in the NRC room, access to the site portal, and wired or wireless guest internet access for all team members.
- 1 main conference room with 1 additional private area for conference calling capability should be made available. The main NRC conference room should be set up for 6 to 8 NRC staff and contractors.
- Access to licensee personnel knowledgeable in the categorization process, plant design, operation and the plant PRA. In addition, Duke Energy staff who participated in preparing the LAR submittal should be available for discussion.
8.0 DELIVERABLES A regulatory audit summary will be issued within 90 days of the completion of the audit. If information evaluated during the audit is needed to support a regulatory decision, the NRC staff will identify it in an RAI. The NRC staff will provide the RAI in separate docketed correspondence.
ML18180A418 *via email OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DRA/APLA/BC*
NAME MBarillas BClayton (JBurkhardt for) SRosenberg DATE 07/02/18 06/29/18 06/22/18 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME BVenkataraman MBarillas DATE 07/02/18 07/02/18