Letter Sequence Meeting |
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EPID:L-2024-LRM-0055, Meeting with Indiana Michigan Power Company (I&M) Regarding Capsule Withdrawal Schedule (Open) |
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Text
April 16, 2024 LICENSEE:
Indiana Michigan Power Company, LLC FACILITY:
Donald C. Cook Nuclear Plant, Unit No. 2
SUBJECT:
SUMMARY
OF APRIL 10, 2024, MEETING WITH INDIANA MICHIGAN POWER COMPANY REGARDING THE SURVEILLANCE CAPSULE PROGRAM FOR DONALD C. COOK NUCLEAR PLANT, UNIT NO. 2 (EPID L-2024-LRM-0055)
On April 10, 2024, an observation public 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 resolution path should I&M not be able to reinsert three capsules used as part of the reactor vessel surveillance program for the Donald C. Cook Nuclear Plant (CNP), Unit No 2. The meeting notice and agenda dated April 5, 2024, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML24096B755. No handouts were used. A list of attendees is enclosed.
The licensee indicated that three standby capsules were pulled during the current refueling outage (RFO) for CNP, Unit 2, in preparation to relocate them to higher lead factor locations within the reactor vessel for further irradiation. However, the instrument tool used for reinsertion of the capsules into the new locations was not working properly. The licensee stated that they are working with Westinghouse to correct the issue with the instrument tool and plan to reattempt insertion of the capsules later in the current RFO. Should the next attempt during the current RFO to reinsert the capsules be unsuccessful, the licensee indicated that it plans to store the capsules in the spent fuel pool (SFP) until the next RFO.
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, III.B.3. states:
A proposed withdrawal schedule must be submitted with a technical justification as specified in 10 CFR 50.4. The proposed schedule must be approved prior to implementation.
The current reactor vessel material surveillance capsule withdrawal schedule for CNP is contained in Section 4.5.1.1.1, Radiation Surveillance Program, of the CNP Updated Final Safety Analysis Report (UFSAR) (ML22340A183). The licensee indicated that the withdrawal schedule in its FSAR has sufficient flexibility should there be a need to store the standby capsules in the SFP for one operational cycle that a revision of the reactor vessel material surveillance capsule withdrawal schedule would not be necessary.
10 CFR 50, Appendix H, III.B.1. states in part:
The design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of the ASTM E 185 that is current on the issue date of the [American Society of Mechanical Engineers] ASME Code to which the reactor vessel was purchased; for reactor vessels purchased after 1982, the design of the surveillance program and the withdrawal schedule must meet the requirements of [American Society for Testing and Materials] ASTM E 185-82.
For reactor vessels purchased in or before 1982, later editions of ASTM E 185 may be used, but including only those editions through 1982. For each capsule withdrawal, the test procedures and reporting requirements must meet the requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule.
The licensee indicated that should there be a need to store the spare capsules in the SFP for one operational cycle, the CNP Radiation Surveillance Program would still meet the requirements of the ASTM E 185. Therefore, the licensee stated that there would be no need for an exemption at this time.
During the public comment portion of the meeting, in response to questions received from a member of the public, the NRC staff provided feedback on the following topics:
Location of current capsule withdrawal schedule: The NRC staff indicated that the current reactor vessel material surveillance capsule withdrawal schedule for CNP is contained in Section 4.5.1.1.1 of the CNP UFSAR (ML22340A183).
Assessment of Radiation Embrittlement: The NRC staff indicated that it uses Regulatory Guide (RG) 1.99, Radiation Embrittlement of Reactor Vessel Materials, Revision 2 (ML02740284), as guidance when calculating the effects of irradiation embrittlement of the reactor pressure vessel, and assessment of surveillance data obtained from implementing the reactor vessel material surveillance program required by Appendix H to 10 CFR Part 50.
Reporting of Analysis of Capsules: It was requested that the NRC staff provide the accession numbers of the documents reporting the results of previously tested capsules for CNP, Unit 2. The staff did not have the information available at the time of the meeting. The accession numbers are provided below:
Capsule T - SwRI Project 02-5928, Reactor Vessel Material Surveillance Program for Donald C. Cook Unit No.2 Analysis of Capsule T, dated September 16, 1981 (ML22048A003)
Capsule Y - SwRI Project 06-7244-002, Reactor Vessel Material Surveillance Program for Donald C. Cook Unit No.2 Analysis of Capsule Y, dated February 1984 (ML20126K207)
Capsule X - SwRI Project 06-8888, Reactor Vessel Material Surveillance Program for Donald C. Cook Unit No.2: Analysis of Capsule X, dated May 1987 (ML17334B113)
Capsule U - WCAP-13515, Revision 1, Analysis of Capsule U from Indiana Michigan Power Company D. C. Cook, Unit 2 Reactor Vessel Radiation Surveillance Program, dated May 2002 (ML022100438)
One member of the public participated in the meeting. No regulatory decisions were made at this meeting. No feedback forms were received.
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 No. 50-316
Enclosure:
List of Attendees cc: Listserv
Enclosure LIST OF ATTENDEES APRIL 10, 2024, PUBLIC MEETING WITH AMERICAN ELECTRIC POWER (AEP) / I&M DONALD C. COOK NUCLEAR PLANT, UNIT NO 2 SURVEILLANCE CAPSULE PROGRAM Name Organization Scott Wall Nuclear Regulatory Commission (NRC)
Jeff Whited NRC Angie Buford NRC On Yee NRC Carolyn Fairbanks NRC Michael K. Scarpello American Electric Power (AEP) / I&M Lindsay Paulus AEP / I&M Dale E. Turnetti AEP / I&M Richard Wynegar AEP / I&M Amanda Britton AEP / I&M Derek Simpson Westinghouse Michael Keegan Dont Waste Michigan
ML24103A187 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME SWall SRohrer JWhited SWall DATE 04/12/2024 04/15/2024 04/15/2024 04/16/2024
