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MONTHYEARML20304A4562020-10-30030 October 2020 Enclosures to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Project stage: Request ML20304A4542020-10-30030 October 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. Project stage: Request ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 Project stage: Other ML21039A2222021-02-18018 February 2021 Audit Plan and Setup of Online Reference Portal for 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: Other ML21110A1232021-04-27027 April 2021 Audit Questions for 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: Other ML21139A0222021-06-0909 June 2021 Audit Summary for 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: Other ML21210A0272021-07-29029 July 2021 Evaluation of the Proposed Change Project stage: Request ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 Project stage: RAI ML21286A6802021-10-13013 October 2021 Response to 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: Request ML21356B5052021-12-22022 December 2021 Plan, Unit 1, Final Supplement to 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: Request ML21344A0052021-12-29029 December 2021 Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants Project stage: Approval 2021-12-29
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Category:Audit Plan
MONTHYEARML24247A3042024-09-11011 September 2024 Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections ML23065A3212023-03-28028 March 2023 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23068A3772023-03-20020 March 2023 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request and Exemption for Fuel Transition to Framatome Gaia Fuel (EPID L-2022-LLA-0150 and EPID L-2022-LLE-0030) - Nonproprietary ML22061A0042022-03-0707 March 2022 Audit Questions for License Amendment Request to Revise Technical Specifications to Adopt TSTF-505 and TSTF-439, Revision 2 ML22048A0022022-02-18018 February 2022 Regulatory Audit Plan and Setup of Online Reference Portal for License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2 and TSTF-439, Revision 2 ML21197A0632021-07-23023 July 2021 Audit Plan and Setup of Online Reference Portal for License Amendment Request Risk-Informed Approach for Closure of Generic Safety Issue-191 ML21110A1232021-04-27027 April 2021 Audit Questions for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21039A2222021-02-18018 February 2021 Audit Plan and Setup of Online Reference Portal for License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18156A4042018-06-19019 June 2018 Regulatory Audit Plan for September 18-19, 2018, in Support of License Amendment Request to Incorporate New Technical Specification 3.7.20 ML17177A4462017-07-0606 July 2017 Audit Plan for Licensee Responses Concerning Seismic Hazard Reevaluations Related to Request for Information -(50.54(F) Letter) Regarding Recommendation 2.1 of the Near-Term Task Force 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 ML15309A3262015-11-0909 November 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051 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 ML14083A6202014-03-26026 March 2014 Nuclear Regulatory Commission Audits of Licensee Responses to Reliable Spent Fuel Pool Instrumentation Order EA-12-051 2024-09-11
[Table view] Category:Letter
MONTHYEARIR 05000483/20240032024-10-23023 October 2024 Integrated Inspection Report 05000483/2024003 IR 05000483/20240132024-10-21021 October 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2024013 IR 05000483/20244012024-10-0909 October 2024 Material Control and Accounting Program Inspection Report 05000483/2024401 Public ULNRC-06901, Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter)2024-10-0101 October 2024 Concurrent Inoperability of Control Room Air Conditioning System Train and Opposite Train Emergency Diesel Generator Results in Condition Prohibited by Technical Specifications Limiting (Letter) ML24247A3042024-09-11011 September 2024 Regulatory Audit Questions for License Renewal Commitments 34 and 35 (EPID L-2024-LRO-0009) - Non-Proprietary IR 05000483/20244032024-08-28028 August 2024 Security Baseline Inspection 05000483-2024-403 IR 05000483/20240052024-08-14014 August 2024 Updated Inspection Plan for Callaway Plant (Report 05000483/2024005) IR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20240022024-07-18018 July 2024 And Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ML24144A0492024-06-11011 June 2024 Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML24158A5222024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008) ML24178A1132024-06-0606 June 2024 Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site ML24143A1632024-05-23023 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001 ML24137A2342024-05-16016 May 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ML24122A1132024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ML24108A1082024-04-17017 April 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009 IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 ML24088A3212024-04-0101 April 2024 Notification of Commercial Grade Dedication Inspection (05000483/2024013) and Request for Information ML24086A5132024-03-26026 March 2024 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06863, Submittal of Annual Exposure Report for 20232024-03-20020 March 2024 Submittal of Annual Exposure Report for 2023 ML24079A1622024-03-19019 March 2024 Re Nuclear Property Insurance Reporting ML24066A1932024-03-0707 March 2024 2024 Callaway Plant Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ULNRC-06852, Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 262024-03-0505 March 2024 Owners Activity Reports (OAR-1 Forms) for Cycle/Refuel 26 IR 05000483/20230062024-02-28028 February 2024 Annual Assessment Letter for Callaway Plant Report 05000483/2023006 ML24052A3662024-02-26026 February 2024 Regulatory Audit Plan in Support of Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20230022024-02-21021 February 2024 Amended Integrated Inspection Report 05000483/2023002 ULNRC-06858, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-02-21021 February 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ML24036A1712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0079 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) IR 05000483/20230042024-01-19019 January 2024 – Integrated Inspection Report 05000483/2023004 2024-09-11
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February 18, 2021 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Ameren Missouri Callaway Energy Center 8315 County Road 459 Steedman, MO 65077
SUBJECT:
CALLAWAY PLANT, UNIT NO. 1 - AUDIT PLAN AND SETUP OF ONLINE REFERENCE PORTAL FOR LICENSE AMENDMENT REQUEST TO ADOPT 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS (EPID L-2020-LLA-0235)
Dear Mr. Diya:
By application dated October 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20304A454), Union Electric Company, dba Ameren Missouri (the licensee), submitted a license amendment request for Callaway Plant, Unit No. 1 (Callaway). The proposed amendment would modify the Callaway licensing basis by the addition of a license condition (i.e., License Condition 2.(C).(19)), 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 reactors.
To improve the efficiency of the U.S. Nuclear Regulatory Commission (NRC) reviews, the licensees representatives and the NRC staff have discussed the use of an audit using an online reference portal that would allow the NRC staff and contractors limited read-only access to the basis documents and other reference materials cited in the applications. The NRC staff plans to initially conduct a desk audit to review the documentation provided on the portal. The online reference portal would allow the NRC staff to audit basis documents to determine whether the information included in the documents is necessary to reach a safety conclusion on the application. Documents identified as necessary for analysis of the application will be identified by the NRC staff. The licensee will be formally requested to submit those documents on the NRC docket. Use of the online reference portal is acceptable, as long as the following conditions are met:
The online reference portal will be password-protected and passwords will be assigned to those directly involved in the review on a need-to-know basis; The online reference portal will be sufficiently secure to prevent staff from printing, saving, or downloading any documents; and
F. Diya Conditions of use of the online reference portal will be displayed on the login screen and will require concurrence by each user.
The NRC staff would like to request that the portal be populated with the documents listed in the enclosure to this letter. This is the initial list identified by the NRC staff. If the licensee intends to submit a license amendment request for Technical Specifications Task Force (TSTF)
Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF
[Risk-Informed TSTF] Initiative 4b, the NRC staff prefers that additional supporting documents be included in the portal. The NRC staff may request additional documents during the review, which will be transmitted to you via email. This will help with the preparation for a virtual audit.
Please provide NRC staff access to the portal and send me the information needed to access the portal, such as username and password, as soon as possible. The conditions associated with the online reference portal must be maintained throughout the duration of the review process. Please provide written confirmation that Ameren Missouri agrees to the terms and conditions set forth in this letter.
If you have any questions, please contact me at (301) 415-8371 or by e-mail at Mahesh.Chawla@nrc.gov.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
Audit Plan cc: Listserv
ML21039A222 via e-mail OFFICE NRR/DORL/LPL4/PM* NRR/DORL/LPL4/LA* NRR/DEX/EXHB* NRR/DRA/APLA/BC*
NAME MChawla PBlechman BHayes RPascarelli DATE 2/11/2021 2/11/2021 2/17/2021 2/12/2021 OFFICE NRR/DEX/EMIB* NRR/DRA/APLC/BC* NRR/DORL/LPL4/BC* NRR/DORL/LPL4/PM*
NAME ABuford SRosenberg JDixon-Herrity MChawla DATE 2/17/2021 2/16/2021 2/18/2021 2/18/2021 REMOTE AUDIT PLAN REGARDING RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT NO. 1 DOCKET NO. 50-483
1.0 BACKGROUND
By letter dated October 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20304A454), Union Electric Company, dba Ameren Missouri (the licensee) requested that the U.S. Nuclear Regulatory Commission (NRC) modify the licensing basis for Callaway Plant, Unit No. 1 (Callaway). The proposed license amendment would modify the Callaway 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 reactors. The proposed changes are based on Nuclear Energy Institute (NEI) 00-04, 10 CFR 50.69 SSC [Structure, System, and Component] Categorization Guideline, Revision 0, dated July 2005 (ADAMS Accession No. ML052910035), which is endorsed by the NRC in Regulatory Guide 1.201, Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to their Safety Significance, Revision 1, dated May 2006 (ADAMS Accession No. ML061090627).
2.0 REGULATORY AUDIT BASES A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. The audit is conducted with docketing to support the basis of a licensing or regulatory decision. Performing a regulatory audit is expected to assist the NRC staff in efficiently conducting its review of the license amendment request (LAR) and to gain insights of 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 remote audit is the licensees LAR for Callaway, and NUREG-0800, Standard Review Plan 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).
The remote audit will be performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, Regulatory Audits, Revision 1, dated October 31, 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 1
information (RAIs) 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 remote audit is to gain a more detailed understanding of the licensees process to implement risk-informed categorization and treatment of SSCs as proposed in the LAR. The NRC staff will review internal events (excluding internal flooding) probabilistic risk assessment (PRA), internal flooding PRA, high winds PRA, seismic PRA, and fire 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 documentations (e.g., methodology, process information, calculations, etc.). The relevant supporting documents are identified below.
4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE REGULATORY REMOTE AUDIT The following documentation should be available to the audit team:
Callaway Energy Center Report PRA-OEH-ANALYSIS, Other External Hazards:
Screening Assessment Notebook, Update 8 Pressurized-Water Reactor Owners Group (PWROG)-19012-P, Peer Review of the Callaway Internal Events and Internal Flood Probabilistic Risk Assessment, dated April 2019 PWROG-19022-P, Peer Review of the Callaway External Hazard Screening Assessment and High Winds Probabilistic Risk Assessment, dated April 2019 PWROG-19034-P, Independent Assessment of Facts & Observations Closure and Focused Scope Peer Review of the Callaway Probabilistic Risk Assessments, dated November 2019 PWROG-18044-P, Peer Review of the Callaway Seismic Probabilistic Risk Assessment, dated June 2018 PWROG-19011-P, Independent Assessment of Facts & Observations Closure and Focused Scope Peer Review of the Callaway Seismic Probabilistic Risk Assessment, dated March 2019 LTR-RAM-II-10-019, Fire PRA Peer Review Against the Fire PRA Standard Supporting Requirements from Section 4 of the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessments for Nuclear Power Plant Applications for The Callaway Nuclear Plant Fire Probabilistic Risk Assessment, dated October 2009 AMN#PES00021-REPT-001, Callaway Energy Center Fire Probabilistic Risk Assessment Peer Review F&Os [Facts and Observations] Closure, dated June 2019
AMN#PES00031-REPT-001, Callaway Energy Center Probabilistic Risk Assessment Focused Scope Peer Review, dated July 2020 AMN#PES00031-REPT-002, Callaway Energy Center Probabilistic Risk Assessment Peer Review F&Os Closure, dated July 2020 PWROG-19020-NP Revision 1, Newly Developed Method Peer Review Pilot-General Screening Criteria for Loss of Room Cooling in PRA Modeling, dated April 2020 PWROG-18027-NP Revision 0, Loss of Room Cooling in PRA Modeling, dated April 2020.
PRA-IE-UNCERT, Probabilistic Risk Assessment (PRA), Uncertainty Analysis Notebook, Revision 000 PRA-IE-UNCERT Appendix 6, Disposition of Key Uncertainties: Risk-Informed Engineering Programs (10CFR50.69), Revision 000.
PRA notebooks associated with the seismic and high winds PRA models, including model assumptions, hazards, fragilities, plant responses, quantifications, uncertainty analysis, and etc.
Any draft or final risk-informed completion time program procedures (i.e., risk management action procedure, PRA functionality determination procedure, recording limiting condition for operation procedures, etc.).
5.0 AUDIT TEAM The members of the audit team are anticipated to be:
Mahesh Chawla, Project Manager, NRC (Mahesh.Chawla@nrc.gov)
Joshua Havertape, APLA,1 NRC (Joshua.Havertape@nrc.gov)
Jeff Circle, APLA, NRC (Jeff.Circle@nrc.gov)
De Wesley Wu, APLC,2 NRC (De.Wu@nrc.gov)
Keith Tetter, APLC, NRC (Keith.Tetter@nrc.gov)
Kaihwa (Robert) Hsu, EMIB,3 NRC (Kaihwa.Hsu@nrc.gov)
Kevin Quinlan, EXHB,4 NRC (Kevin.Quinlan@nrc.gov)
David Heeszel, EXHB, NRC (David.Heeszel@nrc.gov)
Garill Coles, Contractor, PNNL5 (garill.coles@pnnl.gov) 1 Probabilistic Risk Assessment Licensing Branch A 2
Probabilistic Risk Assessment Licensing Branch C 3
Mechanical Engineering and inservice testing Branch 4
External Hazards Branch 5
Pacific Northwest National Laboratory
6.0 LOGISTICS Once the electronic portal is set up and the documentation is made available to the NRC staff, a virtual audit will be scheduled and conducted remotely. The virtual audit will be conducted via Microsoft Teams, or a compatible platform to be agreed upon. Prior to the audit, the NRC staff and contractors will review the portal information and develop audit questions. An entrance briefing will be held at the beginning of the audit, and an exit briefing will be held at the end of the audit. The NRC project manager will coordinate with the licensee the audit date and any identified changes to the schedule and logistics.
7.0 SPECIAL REQUESTS The NRC staff would like access to the documents listed above in Section IV through an online portal that allows the NRC staff and contractors to access documents remotely by February 22, 2021. The NRC staff and contractors access to the online portal should be terminated by September 30, 2021.
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 acknowledgment by each user.
User name and password information should be provided directly to the NRC staff and contractors. The NRC project manager will provide Ameren Missouri the names and contact information of the NRC staff and contractors who will be participating in the audit. All other communications should be coordinated with the NRC project manager.
8.0 DELIVERABLES An audit summary, which may be public, will be prepared within 90 days of the completion of the site audit. If the NRC staff identifies information during the remote audit that is needed to support its regulatory decision, the staff will issue RAIs to the licensee after the completion of the site audit.