ML22129A006

Summary of April 20, 2022, Meeting with Duke Energy Progress, LLC, to Discuss Proposed License Amendment Request to Revise Reactor Coolant System Pressure Isolation Valve Operational Leakage Surveillance Requirement Frequency (L-2022-LRM 00

ML22129A006
Person / Time
Site:	Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire
Issue date:	05/10/2022
From:	Andrew Hon Plant Licensing Branch II
To:	Donahue J Duke Energy Corp
Hon A
References
EPID L-2022-LRM 0031
Download: ML22129A006 (4)

Text

May 10, 2022

LICENSEES: Duke Energy Progress, LLC and Duke Energy Carolinas, LLC

Catawba Nuclear Station, Units 1 and 2; H. B. Robinson Steam Electric Plant, Unit 2; McGuire Nuclear Station, Units 1 and 2; Oconee Nuclear Station, Units 1, 2, and 3; and Shearon Harris Nuclear Power Plant, Unit 1

SUMMARY

OF APRIL 20, 2022, MEETING WITH DUKE ENERGY PR OGRESS, LLC, TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST TO REVISE REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVE OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENT FREQUENCY (L-2022-LRM-0031)

On April 20, 2022, an observation public meeting was held virtu ally between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Duke E nergy Progress, LLC (the licensee) via teleconference. The purpose of the meeting was to discuss a proposed license amendment request (LAR) to revise the plant-specific technical specifications related to the reactor coolant system pressure isolation valve operational lea kage surveillance requirement frequency for several of the licensees nuclear power plants. The meeting notice and agenda, dated April 8, 2022, are available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML22109A231. A list of atten dees is enclosed.

The licensee presented informational slides at the meeting (ML2 2109A212) regarding the description of the planned change, applicable regulatory requir ements and guidance, the licensees evaluation approach, precedent, and schedule. The fo llowing are items for the licensee to consider for ensuring the submittal is complete:

Confirm the applicability of American Society of Mechanical Engineers (ASME)

Operation and Maintenance (OM) Code Case OMN-23, Alternative R ules for Testing Pressure Isolation Valves, as referenced in the licensees pre sentation, to the specific OM Code of Record being implemented at each nuclear power plant within the scope of the planned LAR, based on the ASME OM Code Case Applicability I ndex located on the ASME OM Committee website.

Consider the proposed Technical Specification changes based on the implementation of the program under Section 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors, in Title 10, Energy, of the Code of Federal Regulations (10 CFR 50.69) at the applicable nuclear power plants within the scope of the planned LAR.

Describe how the Surveillance Frequency Control Program frequency is adequately replaced by requirements in the inservice testing program. This is related to the issue regarding 10 CFR 50.69 above.

Describe how the proposed changes in the technical specifications for Surveillance Frequency Control Program and Inservice Testing Program are rel ated to NEI 04-10, Risk-Informed Method of Control of Surveillance Frequency, Re vision 1, and implemented TSTF-425, Relocate Surveillance Frequencies to Licensee Control -

RITSTF Initiative 5b.

Regarding the applicability of the OMN-23 Code Case, the licens ee clarified that the proposed request is not necessarily impacted by the applicability of thi s Code Case to the current Inservice Testing Program Plan interval for each site. For instance, applicability of the OMN-23 is for the 2020 Edition of the ASME Code. Harris would have to either request relief or wait for the next interval program plan to be issued, in which case only then could OMN-23 be used by the site. In the meantime, the site would still be obligated to the current 2-year frequency specified by the current Code interval for each respective site. In discussing OMN-23 during the presentation, the licensee used it as an example of the direction in which the industry is moving regarding this particular testing, and the current limitations written into the technical specifications that limit the ability to extend the frequency in accordance with other NRC-approved code cases. Application of OMN-23 would be outside the scope of this LAR.

With respect to the schedule for the LAR, the licensee anticipated submittal of the LAR on May 19, 2022, with a requested approval within 1 year of acceptance under normal review priority.

No comments or public meeting feedback were received. No regulatory decisions were made at this meeting.

Please direct any inquiries to me at 301-415-8480, or Andrew.Hon@nrc.gov.

Andrew Hon, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos.: 50-413, 50-414, 50-261, 50-369, 50-370, 50-269, 50-270, 50-287, 50-400

Enclosure:

List of Attendees

cc w/ enclosure: Listserv

LIST OF ATTENDEES

APRIL 20, 2022, MEETING WITH DUKE ENERGY PROGRESS, LLC, TO DISC USS PROPOSED LICENSE AMENDMENT REQUEST TO REVISE REACTOR COOLANT SY STEM PRESSURE ISOLATION VALVE OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENT FREQUENCY (L-2022-LRM-0031)

U.S. Nuclear Regulatory Commission

Andy Hon Thomas Scarbrough Gurigendra Bedi Stephen Smith Victor Cusumano Ian Tseng

Duke Energy

Lee Grzeck Dennis Earp David Dobson

Member of the Public

Jeff Mittman

Enclosure

ML22129A006 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME AHon RButler DWrona AHon DATE 05/09/2022 05/09/2022 05/10/2022 05/10/2022