Letter Sequence Meeting |
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EPID:L-2023-LLA-0011, Request for Approval of Change Regarding Neutron Flux Instrumentation (Approved, Closed) |
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Text
February 2, 2024 LICENSEE:
Indiana Michigan Power Company, LLC FACILITY:
Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2
SUBJECT:
SUMMARY
OF JANUARY 24, 2024, MEETING WITH INDIANA MICHIGAN POWER COMPANY REGARDING NEUTRON FLUX INSTRUMENTATION FOR DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 (EPID L-2023-LLA-0011)
On January 24, 2024, an observation meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Indiana Michigan Power Company (I&M, the licensee) via webinar. The purpose of the meeting was to discuss the January 26, 2023, license amendment request (LAR) for the Donald C. Cook Nuclear Plant (CNP), Unit Nos. 1 and 2, related to removing Neutron Flux Instrumentation from Technical Specification (TS) 3.3.3., Post Accident Monitoring (PAM) Instrumentation (Agencywide Documents Access and Management System (ADAMS) at Accession No. ML23026A284). The meeting notice and agenda dated December 27, 2023, are available in ADAMS at Accession No. ML23361A085. The licensee did not have specific handouts for the meeting. To support discussion, the NRC staff used NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [light-water reactor] Edition, Branch Technical Position [BTP] 7-10, Guidance on Application of Regulatory Guide 1.97, Revision 6, dated August 2016 (ML16019A169). A list of attendees is enclosed.
The licensee indicated that they will be providing a response to the November 17, 2023, NRC staffs request for additional information (ML23321A122). The licensee also indicated that they intend to adjust the original LAR. Rather than removing the Neutron Flux Instrumentation from TS 3.3.3, the licensee intends to add a note pertaining to non-environmentally qualified instruments being acceptable. The licensee highlighted that BTP 7-10, table 2, For PWRs
[pressurized-water reactors]: Acceptable Deviations and Clarifications to Revisions 2 and 3 of Regulatory Guide 1.97, states, in part, the following:
Variable Deviation Acceptance Guidelines/Clarification Neutron flux Environmental qualification A non-environmentally qualified instrument is acceptable if qualified core exit thermocouples and reactor coolant system (RCS) hot and cold leg temperature indications are provided in conjunction with directions in emergency procedures for operator action to ensure that boric acid injection is occurring The NRC staff provided feedback on the following topics:
Technical Bases: The NRC staff acknowledged the language within BTP 7-10 and stressed the importance of the licensee providing the technical bases to support applying this deviation. Specifically, the NRC staff noted that while the language pertaining to PWR neutron flux environmental qualification within the PWR Table in the BTP 7-10 has existed since the first public issuance of the BTP in June 1997, it is not clear whether the technical basis assumptions underlying this guidance is still valid. In particular, the guidance pertaining to the use of hot leg and cold leg temperature indications for detection of a return to criticality following a reactor shutdown does not appear to be appropriate for accident events where RCS flow is terminated.
Review Timeline: The NRC staff reminded the licensee that should the supplemental letter provided additional information that expands the scope of the application as originally noticed, a new notice of consideration of approval of the application would need to be published in the Federal Register and a new project timeline and hours estimation would need to be discussed.
I&M currently plans to provide the supplement by late February 2024.
No members of the public had questions or comments during the meeting. No regulatory decisions were made at this meeting. Please direct any inquiries to me at 301-415-2855, or 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. 50-315 and 50-316
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES JANAURY 24, 2024, PUBLIC MEETING WITH I&M DONALD C. COOK NUCLEAR PLANT, UNIT NOS. 1 AND 2 LICENSE AMENDMENT REQUEST RELATED TO NEUTRON FLUX INSTRUMENTATION Name Organization Scott Wall Nuclear Regulatory Commission (NRC)
Jeff Whited NRC Shivani Mehta NRC Lauren Nist NRC David Rahn NRC Hang Vu NRC Fanta Sacko NRC Ahsan Sallman NRC Steve Wyman NRC Santosh Bhatt NRC Michelle Honcharik NRC Michael K. Scarpello Indiana Michigan Power Company (I&M)
Helen L Levendosky I&M Bradford M Culwell I&M Daniel J Vincent I&M Rodney G Pickard I&M Keith A Steinmetz I&M Eddie Hoskin I&M Jason Wright I&M Jeff Hodge I&M Bud Hinckley I&M Dan Billings I&M David Goff I&M Mary Miller Dominion Energy
ML24031A587 NRC-001 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME SWall SRohrer JWhited SWall DATE 01/31/2024 02/01/2024 02/01/2024 02/02/2024
