ML24207A040

Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance

ML24207A040
Person / Time
Site:	Surry
Issue date:	08/21/2024
From:	John Klos NRC/NRR/DORL/LPL2-1
To:	Stoddard D Virginia Electric & Power Co (VEPCO)
References
EPID L-2024-LRM-0083
Download: ML24207A040 (1)

Text

August 21, 2024

Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUMMARY

OF JULY 17, 2024, PUBL IC MEETING WITH VIRGINIA ELECTRIC AND POWER COMPANY REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS 3.7, INSTRUMENTATION SYSTEMS, AND 3.14, CIRCULATING AND SERVIC E WATER SYSTEMS, FOR SURRY POWER STATION, UNITS 1 AND 2, TO SUPPORT REPAIRS USING CARBON FIBER REINFORCED POLYMER (EPID L-2024-LRM-0083)

Dear Daniel Stoddard:

On July 17, 2024, an observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Virginia Electric and Power Company (the licensee) via a webinar. The purpose of the meeting was for the licensee to discuss its plans to submit license amendments to support permanent repair of service water (SW) system. The repairs will involve installation of a temporary SW supply jumper and intake canal level probe to allow for system dewatering and installation of a Carbon Fiber Reinforced Polymer (CFRP) repair system in SW supply lines to component cooling heat exchangers for the Surry Power Station, Units 1 and 2 (Surry).

The meeting notice and agenda, dated June 27, 2024, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML24179A289.

The licensees slide presentation associated wi th the meeting is available at ML24183A208.

The NRC staff asked questions concerning:

The basis for the licensee proposes temporary, one time, proposed 35-day Allowed Outage Time (AOT) configuration.

Documentation and consideration of lessons learned for extreme weather conditions, such as at Duane Arnold Derecho of 2020, and their application in the development of contingency plan.

Any information docketed previously, including ADAMS Accession numbers, that support the LAR.

D. Stoddard

Any probabilistic risk assessment (PRA) numer ical values and/or risk insights (e.g.,

incremental conditional core damage probab ility (ICCDP) and incremental conditional large early release probability (ICLERP) values that may support the request which is expected to be mostly based on deterministic analysis.

The possible need for an audit of the temporary SW jumper and supporting engineering calculations.

That if the contingency action plan was activated via a restoration of the SW piping --

and a s partially completed CFRP repair system remained --procedures and actions to retain adequate SW integrity would be required.

The NRC staff suggested that the licensee:

Describe, in detail, the specific plant conditions (e.g., leakage rates, configurations, and/or environmental conditions that would initiate actions in the contingency plan.

Describe any conditions, including during contingency plans, that additional relief (e.g.

2017 (ML17303A068)) may be warranted.

Describe CRFP treatment and foreign material exclusion controls for the installation and verifications prior to a 42 SW flow path reestablishment.

Identify setpoint/plant conditions at which the temporary jumper, meant to provide cooling for the Surry, Unit 2 operating loads, and Unit 1 shutdown loads, remains sufficient. Describe actions for exceeding these setpoints and any plant conditions would prompt the reestablishment of the 42 SW piping.

Identify any other plant methods/configurations, rather than the use of 42 SW piping, during the contingency plan were considered.

Describe how a partially completed CFRP repair and monitoring will ensure structural integrity during the implementation.

Consider a license condition for this LAR in a similar manner to its application as it was applied previously in Surry LAR precedents (ML012700170, ML13231A170) where a SW jumper was utilized.

No regulatory decisions were made as a result of the teleconference. Members of the public were not in attendance. Public Meeting Feedback forms were not received.

D. Stoddard

If you have any questions, please contact me at (301) 415-5136, or via email at John.Klos@nrc.gov.

Sincerely,

/RA/

John Klos, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-280 and 50-281

Enclosure:

List of Attendees

cc: Listserv

LIST OF ATTENDEES

JULY 17, 2024, PRE-SUBMITTAL TELECONFERENCE

WITH VIRGINIA ELECTRIC AND POWER COMPANY

REGARDING PROPOSED LICENSE AMENDMENT TO

TECHNICAL SPECIFICATION 3.7, AND 3.14 FOR EXTENDED ALLOWED OUTAGE TIME

FOR SERVICE WATER PIPING MAINTENANCE

FOR SURRY POWER STATION, UNITS 1 AND 2, DOCKET NOS. 50-280 AND 50-281

U.S. Nuclear Regulatory Commission John Klos Jack Minzer Bryant Michael Markley David Nold Garry Armstrong Jay Robinson Joshua Wilson Ming Li Seung Min Ali Rezai Yi Lun Chu

Virginia Electric and Power Company G. Miller J. Kole J. Vasquez C. Zalesiak A. Nojaven C. Wilson J. Pak N. Hernandez J. Hough A. Harrow L. Gordon J. Jones

Members of the Public None

Enclosure

ML24207A040 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DSS/SCPB/BC DNRL/NPHP/BC NAME JMinzerBryant KGoldstein MValentin MMitchell DATE 07/24/2024 07/25/2024 08/02/2024 7/29/2024 OFFICE DRA/APLB/(A)BC DORL/LPL2-1/BC DORL/LPL2-1/PM NAME EDavidson MMarkley JKlos DATE 08/01/2024 08/21/2024 08/21/2024