ML25027A426
| ML25027A426 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/10/2025 |
| From: | Scott Wall NRC/NRR/DORL/LPL3 |
| To: | Lies Q Indiana Michigan Power Co |
| Wall S | |
| References | |
| EPID L-2024-LLA-0025 | |
| Download: ML25027A426 (1) | |
Text
February 10, 2025 Q. Shane Lies Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT:
DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 - 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 (EPID L-2024-LLA-0025)
Dear Q. Shane Lies:
By \
letter dated March 6, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24073A234), Indiana Michigan Power Company (I&M, the licensee) submitted a license amendment request (LAR) for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). The proposed LAR would adopt 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 support its review, by \
letter dated May 2, 2024 (ML24116A000), the U.S. Nuclear Regulatory Commission (NRC) staff notified the licensee that they would conduct a regulatory audit from May 13, 2024, to September 20, 2024, through an online portal (also known as electronic portal, ePortal, electronic reading room) established by the licensee. Due to scheduling conflicts associated with a special inspection related to emergency diesel generator failures (ML24345A203), and the necessity to have clarification discussions, the regulatory audit was extended to January 3, 2025. The regulatory audit summary is enclosed with this letter.
Q. Shane Lies If you have any questions, please contact me at (301) 415-2855, or by e-mail at Scott.Wall@nrc.gov.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Regulatory Audit Summary cc: Listserv
Enclosure REGULATORY AUDIT
SUMMARY
REGARDING LICENSE AMENDMENT REQUEST TO SUPPORT THE REVIEW OF THE LICENSE AMENDMENT REQUEST TO ADOPT THE REQUIREMENTS OF 10 CFR 50.69 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316
1.0 BACKGROUND
By \
letter dated March 6, 2024 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML24073A234), Indiana Michigan Power Company (I&M, the licensee) submitted a license amendment request (LAR) for Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 (CNP). The proposed LAR would adopt Title 10 of the Code of Federal Regulations (10 CFR), section 50.69, Risk-informed categorization and treatment of structures, systems and components [SCCs] for nuclear power reactors.
The U. S. Nuclear Regulatory Commission (NRC) staff performed a preliminary review of the LAR and determined that a regulatory audit would assist in the timely completion of the review.
An audit plan was provided to the licensee on May 2, 2024 (ML24116A000), which provided the list of requested documents and other details pertaining to the audit. The purpose of the audit was to gain an understanding of the information needed to support the NRC staffs licensing decision regarding the LAR and to develop requests for additional information (RAIs), if necessary. The information submitted in support of the LAR is under final review, and any additional information needed to support the LAR review will be formally requested by the NRC staff using the RAI process in accordance with Office of Nuclear Reactor Regulation (NRR)
Office Instruction LIC-101, Revision 6, License Amendment Review Procedures (ML19248C539).
The regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. The 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 licensees information is expected to assist the NRC staff in efficiently conducting its review or gain insights on the licensees 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 Title 10 of the Code of Federal Regulations (10 CFR) section 50.71, Maintenance of records, making of reports, and/or 10 CFR 54.37, Additional records and recordkeeping requirements, which, although not required to be submitted as part of the licensing action, would help the NRC staff better understand the licensees submitted information.
2.0 SCOPE By \
letter dated May 2, 2024 (ML24116A000), the NRC staff issued an audit plan. The original audit duration was from May 13, 2024, to September 20, 2024. Due to scheduling conflicts associated with a special inspection related to emergency diesel generator failures (ML24345A203), and the necessity to have clarification discussions, the regulatory audit was extended to January 3, 2025. To support discussions, the NRC staff provided 10 audit questions with items for I&M to clarify. I&M posted answers to these questions to the online portal. The NRC staff held clarification discussions with the I&M staff via Microsoft Teams on November 14, 2024, and November 18, 2024. All audit questions were discussed. Technical discussions were focused on the probabilistic risk assessment (PRA).
3.0 AUDIT TEAM The NRC audit team included the following:
Scott Wall, Plant Licensing Branch III (LPL3)
Adrienne Brown, PRA Licensing Branch A (APLA)
David Gennardo, APLA Michael Swim, PRA Licensing Branch C (APLC)
Sunwoo Park, APLC Rob Atienza, Containment and Plant Systems Branch (SCPB)
Brian Lee, SCPB Fred Forsaty, Nuclear Systems Performance Branch (SNSB)
Ming Li, Instrumentation and Controls Branch B (EICB)
Edmund Kleeh, Electrical Engineering Branch (EEEB)
Gurjendra Bedi, Mechanical Engineering and Inservice Testing Branch (EMIB)
Cory Parker, Vessels and Internals Branch (NVIB)
Stephen Cumblidge, Piping and Head Penetrations Branch (NPHP) 4.0 DOCUMENT AND FILES REVIEWED Item #
File Name Document Title 1
1BTI1V001-RPT-01.pdf D.C. Cook Focused Scope Peer Review -
Pre-Initiator HRA (Rev. 0) 2 1V042-RPT-01 DC Cook FO Closure Final.pdf D.C. Cook PRA Finding Level Fact and Observation Independent Assessment (Rev. 0) 3 AEPDCC~00036-REPT-001.pdf Cook Nuclear Plant Evaluation of Detailed Hydrogen Analyses (01V015-RPT-01) Against the LERF Supporting Requirements of the ASME PRA Standard (2013) (Rev. 0) 4 AEPDCC-00051-REPT-001.pdf Cook Nuclear Plant Seismic PRA Hydrogen Findings Closure Report (Revision 0)
Item #
File Name Document Title 5
AEPDCC-00058-REPT-001.pdf Donald C. Cook Nuclear Plant Units 1 and 2 SPRA Fact and Observation Independent Assessment and Focused-Scope Peer Review (Revision 0) 6 D0403140002-1515.pdf D.C. Cook Focused Scope Peer Review for Fire PRA (Revision 0) 7 LTR-RAM-II-10-041-final_report.pdf Fire PRA Peer Review Against the Fire PRA Standard Supporting Requirements from Section 4 of the ASME/ANS Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessments for Nuclear Power Plant Applications for the D C Cook Fire Probabilistic Risk Assessment (July 2010) 8 P3801-0001-01 CNP FSPR R0.pdf Focused Scope Peer Review of the D.C. Cook Nuclear Plant (CNP) Fire PRA Model Against the ASME PRA Standards Requirements (P3801-0001-01, Revision 0) 9 P3823-0001-01 CNP FSPR R0.pdf Focused Scope Peer Review of the D.C. Cook Nuclear Plant (CNP) Fire PRA Model Against the ASME PRA Standards Requirements (Revision 1 of P3801-0001-01) 10 P3823-0001-02 CNP FO R0.pdf F&O Closure Review of the D.C. Cook Nuclear Plant (CNP) Fire PRA Model Against the ASME PRA Standards Requirements (P3823-0001-02, Revision 0) 11 Peer-Review-Legend.pdf Peer-Review-Legend 12 PRA-NB-FSPR-FLEX.pdf DC Cook Focused-Scope Peer Review on the Incorporation of FLEX (Revision 0) 13 PWROG-15076-P.pdf Peer Review of the D.C. Cook Nuclear Plant Internal Events Probabilistic Risk Assessment (Revision 0) 14 PWROG-17027-P_FINAL.pdf Focused Scope Peer Review of the DC Cook Internal Fire Probabilistic Risk Assessment (Revision 0) 15 PWROG-18062-P (4).pdf Peer Review of the D.C. Cook Nuclear Plant, Units 1
& 2, Seismic Probabilistic Risk Assessment (Revision 0) 16 PRA-NB-SPRA-QU (1).pdf Seismic PRA Quantification Notebook (Revision 1) 17 PRA-NB-FIRE-UNC.pdf Fire PRA Uncertainty and Sensitivity Analysis (Revision 1) 18 PRA-NB-UNC.pdf Internal Events Uncertainty Notebook (Revision 3) 19 PRA-NB-HRA Rev 11.pdf Human Reliability Analysis Notebook 20 PRA-NB-SY-FLEX.pdf FLEX System Notebook (Revision 1) 21 PRA-NB-SY-AC.pdf AC Electrical Power System Notebook (Revision 8) 22 15C4313-RPT-003.pdf Summary of Building Response Analysis for Cook Nuclear Plant (CNP) Unit 1 & Unit 2 SPRA (Revision 4) 23 PRA-NB-SY-LTC.pdf Long Term Cooling System Notebook (Revision 5) 24 PRA-NB-SY-PORV.pdf Pressurizer Power-Operated Relief Valve System Notebook (Revision 7)
Item #
File Name Document Title 25 PRA-NB-SY-MS.pdf Main Steam System Notebook (Revision 7) 26 PRA-NB-SY-RHR.pdf Residual Heat Removal System Notebook (Revision 7) 27 R1900-0041-0001.pdf Plant Boundary Definition and Partitioning (Revision
- 12) 28 PRA-NB-SY-CRID.pdf 120V AC Electrical Power System Notebook (Revision 6) 29 PRA-NB-SY-CTS.pdf Containment Spray System Notebook (Revision 7) 30 PRA-NB-SY-DC.pdf DC Electrical Power System Notebook (Revision 7) 31 PRA-NB-SY-DIS.pdf Distributed Ignition System Notebook (Revision 7) 32 PRA-NB-SY-CCW.pdf Component Cooling Water System Notebook (Revision 8) 33 PRA-NB-SY-ESFAS.pdf Reactor Protection and Engineered Safeguards Actuation System Notebook (Revision 6) 34 PRA-NB-SY-ACCUM.pdf Accumulator System Notebook (Revision 6) 35 PRA-NB-FPIE-DATA.pdf Internal Events Data Collection and Analysis Notebook (Revision 2) 36 PRA-NB-LER.pdf Large Early Release Frequency Notebook (Revision 2) 37 PRA-NB-SY-AFW.pdf Auxiliary Feedwater System Notebook (Revision 9) 38 F&O-Impacted-Docs-Legend.pdf F&O-Impacted-Docs-Legend 39 PRA-NB-FIRE-IGN.pdf Fire PRA Fire Ignition Frequency Calculation (Revision 4) 40 PRA-NB-FIRE-CF.pdf DC Cook Fire PRA Circuit Failure Likelihood Analysis (Revision 1) 41 DC COOK-PR-09.pdf Evaluation of Secondary Hazards Associated with Vibratory Ground Motion at DC Cook Nuclear Plant for SPRA (Revision 1) 42 15C4313-CAL-010.pdf Response Analysis of Auxiliary Building (Revision 3) 43 DC COOK-PR-07.pdf Seismic Hazard Analysis for DC Cook Nuclear Plant:
Executive Summary (Revision 6) 44 PRA-NB-FIRE-FQ.pdf FIRE PRA Model Quantification Notebook (Revision 4) 45 1-OHP-4021-057-002.pdf Placing In/Removing from Service Circulating Water Deicing System (Revision 030) 46 Airport-Data-Ref-610.pdf Airport Master Record (5/15/2024) 47 12-OHP-4022-001-010.pdf Severe Weather (Revision 024) 48 EC-MOD-ECC-0000046977.pdf Flood Control Wiring Protection for Unit 1 A Train (Revision 0) 49 EC-MOD-ECC-0000046979.pdf Flood Control Wiring Protection for Unit 2 A Train (Revision 0) 50 AEP-NRC-2015-14.pdf Donald C. Cook Nuclear Plant Unit 1 and 2, Response to March 12, 2012, Request for Information, Enclosure 2, Recommendation 2.1:
Flooding, Required Response 2, Hazard Reevaluation Report (March 6, 2015)
Item #
File Name Document Title 51 EC-MOD-ECC-0000046978.pdf Flood Control Wiring Protection for Unit 1 B Train (Revision 0) 52 EC-MOD-ECC-0000046980.pdf Flood Control Wiring Protection for Unit 2 B Train (Revision 0) 53 DC Cook IPEEE Summary.pdf Donald C. Cook Nuclear Plant Unit 1 and 2, Individual Plant Examination of External Events Summary Report (April 1992) 54 AEP-NRC-2015-116.pdf Donald C. Cook Nuclear Plant Unit 1 and 2, Update to Interim Action Plant re. Flood Hazard Reevaluation (December 14, 2015) 55 NUREG-CR-4461.pdf NUREG/CR-4461, Rev. 2, Tornado Climatology of the Contiguous United States 56 INL-EXT-18-45359.pdf Analysis of Loss-of-Offsite-Power Events 1987-2017 57 OP-12-5119.pdf Donald C. Cook Nuclear Plant, Flow Diagram Circulating Water, Priming System & Screen Wash Units No 1 & 2, DWG. No. OP-12-5119-88 (5/25/17) 58 PMP-5091-FLD-001.pdf Flood Protection Program Implementation (Revision 011) 59 NEI-00-04.pdf NEI 00-04, Revision 0, 10 CFR 50.69 SSC Categorization Guideline 60 NEI-5069-Template.pdf 50.69 License Amendment Request Submittal Template 61 PMP-5055-SWM-001.pdf Severe Weather Guidelines (Revision 014) 62 PMP-5055-001-001.pdf Winterization/Summerization (Revision 042) 63 MD-12-MSC-003-N.pdf Evaluation of Offsite Sources of Toxic Gas and Explosives (Revision 4) 64 ITSA-U1.pdf Donald C. Cook Nuclear Plant, Unit 1 Technical Specifications List of Effective Pages (12/6/22) 65 ITSA-U2.pdf Donald C. Cook Nuclear Plant, Unit 2 Technical Specifications List of Effective Pages (12/6/22) 66 PRA-TORMIS-QNT-001.pdf Risk Quantification to Support TORMIS Analysis for Cook Tornado Assessment (Revision 0) 67 PRA-EXT-HAZ-SCRN Rev0.pdf External Hazards Assessment for D.C. Cook Nuclear Plant (Revision 0) 68 PRA-NB-QU.pdf Internal Events Quantification Notebook (Revision 7) 69 RG-170.pdf Regulatory Guide 1.70, Revision 3, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants LWR Edition 70 UFSAR Text, Tables, and UCRs.pdf D.C. Cook Nuclear Plant, Updated Final Safety Analysis Report, Revision 31.0, List of Effective Pages (eUFSAR Version 31.9, updated 2/20/2024) 71 SD-990930-004.pdf Probability of Tornado Missile Strike on Targets at D.C. Cook Nuclear Plant (Revision 16) 72 12-EHP-9010-PRA-001.pdf Probabilistic Risk Assessment (Revision 11) 73 PMP-5069-RIE-001 Rev 0.pdf 10 CFR 50.69 Active Component Risk Significance Insights (Revision 000)
Item #
File Name Document Title 74 PMP-5069-RIE-002 Rev 0.pdf 10 CFR 50.69 Passive Component Categorization (Revision 000) 75 PMP-5069-RIE-003 Rev 0.pdf 10 CFR 50.69 Risk Informed Categorization for Structures, Systems, and Components (Revision 000) 76 PMP-5069-RIE-005 Rev 0.pdf 10 CFR 50.69 Integrated Decision-Making Panel Duties and Responsibilities (Revision 000) 77 PRA-NB-HRA-PRE.pdf Pre-Initiator Human Reliability Analysis Notebook (Revision 3) 78 12-OHP-4022-057-001.pdf Screen House Forebay Degraded Condition (Revision 011) 5.0 RESULTS OF THE AUDIT As a result of the audit, the NRC staff gained a better understanding of the licensees analyses and calculations supporting the implementation of the provisions of 10 CFR 50.69. Several RAIs were issued to the licensee on December 30, 2024 (ML24366A003). The licensee provided a response to the RAIs on February 6, 2025 (ML25037A168).
ML25027A426 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DRA/APLA/BC NRR/DRA/APLC/BC NAME SWall SRohrer RPascarelli ANeuhausen DATE 01/29/2025 01/29/2025 01/31/2025 01/29/2025 OFFICE NRR/DEX/EICB/BC NRR/DEX/EEEB/BC NRR/DEX/EMIB/BC NRR/DSS/SNSB/BC NAME FSacko WMorton (SRay for)
SBailey PSahd (DMurdock for)
DATE 02/03/2025 02/10/2025 02/03/2025 01/30/2025 OFFICE NRR/DSS/SCPB/BC NRR/DNRL/NPHP/BC NRR/DNRL/NVIB/BC NRR/DORL/LPL3/BC(A)
NAME MValentin MMitchell ABuford IBerrios DATE 01/29/2025 01/29/2025 02/03/2025 02/10/2025 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 02/10/2025