ML25107A169
| ML25107A169 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/29/2025 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | Ferneau K Indiana Michigan Power Co |
| Wall S | |
| References | |
| EPID L-2024-LLA-0025 | |
| Download: ML25107A169 (5) | |
Text
April 29, 2025 Kelly J. Ferneau Executive 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 NO. 1 - CORRECTION TO PAGES ISSUED FOR AMENDMENT NO. 365 REGARDING ADOPTION OF 10 CFR 50.69, RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS (EPID L-2024-LLA-0025)
Dear Kelly Ferneau:
By letter dated April 9, 2025, the Nuclear Regulatory Commission (NRC) issued Amendment No. 365 to Renewed Facility Operating License No. DPR-58, for the Donald C. Cook Nuclear Plant (CNP), Unit No. 1. The amendment revised the CNP Renewed Facility Operating License (RFOL) No. DPR-58 to add a new license condition to allow for implementation of Title 10 of the Code of Federal Regulations Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
The NRC inadvertently issued a page of RFOL No. DPR-58 that had an error on page 10 for CNP Unit No. 1. Specifically:
on page 10, the last license condition should be license condition L; not J.
The error was introduced during the issuance of License Amendment No. 365 for CNP Unit No. 1.
The NRC staff has determined that these were inadvertent typographical errors and are entirely editorial in nature. The correction does not change any of the conclusions in the safety evaluation associated with Amendment No. 365 for CNP Unit No. 1, and does not affect the associated notice to the public.
The corrected pages are enclosed and should be replaced as follows:
Remove Insert Unit 1 RFOL page 10 Unit 1 RFOL page 10
K. Ferneau If you have any questions concerning this action, please contact me at (301) 415-2855 or by e-mail to 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 No. 50-315
Enclosure:
Corrected Pages to Amendment No. 365 to DPR-58 cc: Listserv
ENCLOSURE DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-315 CORRECTED PAGE TO LICENSE AMENDMENT NO. 365 RENEWED FACILITY OPERATING LICENSE NO. DPR-58 PAGE 10 Renewed License No. DPR-58 Amendment No: 319, 322, 323, 334, 365 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Donald C. Cook Nuclear Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 1, submitted by letter dated May 10, 2006.
The Indiana and Michigan Power Company shall fully implement and maintain in effect all provisions of the Commission-approved Donald C. Cook Nuclear Plant Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Donald C. Cook Nuclear Plant CSP was approved by License Amendment No. 315 as supplemented by changes approved by License Amendment Nos. 319, 325, and 333.
E.
Deleted by Amendment No. 80 F.
Deleted by Amendment No. 80 G.
In all places of this renewed operating license, the reference to the Indiana and Michigan Electric Company is amended to read Indiana Michigan Power Company.
H.
Deleted by Amendment No. 287 I.
Deleted by Amendment No. 287 J.
The licensee is authorized to use digital signal processing instrumentation in the reactor protection system.
K.
Updated Final. Safety Analysis Report The Indiana Michigan Power Company Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to the period of extended operation. The Indiana Michigan Power Company shall complete these activities no later than October 25, 2014, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following issuance of this renewed operating license. Until that update is complete, Indiana Michigan Power Company may make changes to the programs and activities described in the supplement without prior Commission approval, provided that Indiana Michigan Power Company evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
L.
All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan
ML25107A169 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC(A)
NAME SWall SRohrer IBerrios DATE 04/16/2025 04/17/2025 04/28/2025 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 04/29/2025