ML24169A214

Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System

ML24169A214
Person / Time
Site:	Cook
Issue date:	07/25/2024
From:	Scott Wall Plant Licensing Branch III
To:	Lies Q Indiana Michigan Power Co
Wall S
References
EPID L-2024-LLA-0026
Download: ML24169A214 (1)

Text

July 25, 2024 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 NO. 1 - ISSUANCE OF AMENDMENT NO. 362 REGARDING CHANGE TO TECHNICAL SPECIFICATION 3.4.12, LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEM (EPID L-2024-LLA-0026)

Dear Q. Shane Lies:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 362 to Renewed Facility Operating License No. DPR-58, for the Donald C. Cook Nuclear Plant, Unit No. 1. The amendment consists of changes to the license and technical specifications (TSs) in response to your application dated March 6, 2024.

The amendment revises the TSs by adding the Completion Time requirement Immediately to TS 3.4.12, Low Temperature Overpressure Protection (LTOP) System, Actions Table to Condition F, Required Action F.2.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.

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

Enclosures:

1. Amendment No. 362 to DPR-58

2. Safety Evaluation

3. Notice and Environmental Finding cc: Listserv

INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 362 License No. DPR-58

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company dated March 6, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 362, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: July 25, 2024 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2024.07.25 09:23:33 -04'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 362 DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE DOCKET NO. 50-315 Renewed Facility Operating License No. DPR-58 Replace the following page of the Renewed Facility Operating License No. DPR-58 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

REMOVE INSERT Technical Specifications Replace the following page of the Renewed Facility Operating License, Appendix A, Technical Specifications, with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

REMOVE INSERT 3.4.12-3 3.4.12-3 Renewed License No. DPR-58 Amendment No: 361, 362 and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; and (5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not to exceed 3304 megawatts thermal in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 362, are hereby incorporated in this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.

(4)

Fire Protection Program Indiana Michigan Power Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensees amendment request dated July 1, 2011, as supplemented by letters dated September 2, 2011, April 27, 2012, June 29, 2012, August 9, 2012, October 15, 2012, November 9, 2012, January 14, 2013, February 1, 2013,

LTOP System 3.4.12 Cook Nuclear Plant Unit 1 3.4.12-3 Amendment No. 287, 334, 356, 362 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One required RCS relief valve inoperable in MODE 5 or 6 while complying with LCO A.2.c or A.2.d.

E.1 Restore required RCS relief valve to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> F. Required RCP not running.

F.1 Do not start a RCP.

AND F.2 Enter Condition G.

Immediately Immediately G. Two or more required RCS relief valves inoperable.

OR Required Action and associated Completion Time of Condition A, C, D, E, or F not met.

OR LTOP System inoperable for any reason other than Condition A, B, C, D, E, or F.

G.1 Depressurize RCS and establish RCS vent of 2.0 square inches or block open a single PORV.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 362 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 58 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-315 Application Safety Evaluation Date March 6, 2024, ADAMS Accession No. ML24073A067 July 25, 2024 Principal Contributors to Safety Evaluation Scott Wall

1.0 INTRODUCTION

Indiana Michigan Power Company (I&M, the licensee) requested a change to the technical specifications (TSs) for Donald C. Cook Nuclear Plant, Unit No. 1 (CNP-1), by license amendment request (application). The proposed change would revise the TSs by adding the Completion Time requirement Immediately to TS 3.4.12, Low Temperature Overpressure Protection (LTOP) System, Actions Table to Condition F, Required Action F.2. Currently in CNP-1 TS 3.4.12, Condition F Completion Time for Required Actions includes only one completion time.

2.0 REGULATORY EVALUATION

AND GUIDANCE 2.1 Description of Change The following text will be added to CNP-1 TS 3.4.12 (addition in bold):

CONDITION REQUIRED ACTION COMPLETION TIME F. Required RCP not running.

F.1 Do not start a RCP.

AND F.2 Enter Condition G.

Immediately Immediately 2.2 Applicable Regulatory Requirements The U.S. Nuclear Regulatory Commission (NRC) regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR), section 50.36.

Paragraph 50.36(a)(1) requires, in part, that an application for an operating license include proposed TSs. The regulations in 10 CFR 50.36 require that the TSs include items in the following five categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.

Under 10 CFR 50.90, whenever a holder of a license wishes to amend the license, including technical specifications in the license, an application for amendment must be filed, fully describing the changes desired. Under 10 CFR 50.92(a), determinations on whether to grant an applied for license amendment are to be guided by the considerations that govern the issuance of initial licenses to the extent applicable and appropriate.

3.0 TECHNICAL EVALUATION

3.1 Evaluation of Technical Specification Change This amendment will add Immediately as the Completion Time for Required Action F.2 of CNP-1 TS 3.4.12 in accordance with License Amendment No. 356, issued by letter dated January 12, 2021 (ML20329A001). License Amendment No. 356 provided the licensee authorization to add a new TS 3.4.12 Condition F to provide actions if the required reactor coolant pump (RCP) is not running. The prescribed actions are to not start a RCP and to enter Condition G immediately. However, the licensee inadvertently failed to include Immediately in the mark-up page in their April 7, 2020, application (ML20108F011), and the NRC staff did not issue a revised page which clearly showed Immediately as the Completion Time for Required Action F.2 of CNP-1 TS 3.4.12 in License Amendment No. 356.

3.2 NRC Staff Conclusion

The NRC staff finds that the proposed TS change is editorial and is in the nature of a clarification. As such, the NRC staff concludes that the regulatory requirements of 10 CFR 50.36 continue to be met, and therefore, the proposed change is acceptable.

4.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO RELATED TO AMENDMENT NO. 362 TO RENEWED FACILITY OPERATING LICENSE NO. DPR 58 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT NO. 1 DOCKET NOS. 50-315 Application Safety Evaluation Date March 6, 2024, ADAMS Accession No. ML24073A067 July 25, 2024

1.0 INTRODUCTION

Indiana Michigan Power Company (I&M, the licensee) requested a change to the technical specifications (TSs) for Donald C. Cook Nuclear Plant, Unit No. 1 (CNP-1), by license amendment request (application). The proposed change would revise the TSs by adding the Completion Time requirement Immediately to TS 3.4.12, Low Temperature Overpressure Protection (LTOP) System, Actions Table to Condition F, Required Action F.2. Currently in CNP-1 TS 3.4.12, Condition F Completion Time for Required Actions includes only one action statement.

2.0 STATE CONSULTATION

In accordance with the Commissions regulations, the State of Michigan official was notified of the proposed issuance of the amendment on June 17, 2024. The State official had no comments.

3.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in Title 10 of the Code of Federal Regulations (10 CFR) Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration as published in the Federal Register on April 16, 2024 (89 FR 26946), and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

ML24169A214 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NAME SWall SRohrer SMehta (RElliot for)

DATE 06/17/2024 06/20/2024 06/20/2024 OFFICE NRR/DSS/SCPB/BC OGC - NLO NRR/DORL/LPL3/BC NAME MValentin PLom JWhited DATE 06/25/2024 07/12/2024 07/24/2024 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 07/25/2024