ML20113F089

Summary of April 15, 2020, Pre-Submittal Meeting with PSEG Nuclear LLC to Discuss Proposed License Amendment on Leak Before Break Analyses

ML20113F089
Person / Time
Site:	Salem
Issue date:	04/27/2020
From:	James Kim NRC/NRR/DORL/LPL1
To:	Public Service Enterprise Group
Kim, James
References
EPID L-2020-LRM-0026
Download: ML20113F089 (4)

Text

April 27, 2020 LICENSEE: PSEG Nuclear LLC FACILITY: Salem Nuclear Generating Station, Unit Nos. 1 and 2

SUMMARY

OF APRIL 15, 2020, PRE-SUBMITTAL PUBLIC MEETING WITH PSEG NUCLEAR LLC TO DISCUSS PROPOSED LICENSE AMENDMENTS ON LEAK BEFORE BREAK ANALYSES (EPID L-2020-LRM-0026)

On April 15, 2020, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of PSEG Nuclear LLC (PSEG or the licensee) by teleconference. The purpose of the meeting was to discuss PSEGs proposed license amendment request on leak before break analyses for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The meeting notice and agenda, dated March 31, 2020, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML20091H672. A list of attendees is enclosed.

PSEGs presentations slides are available at ADAMS Accession No. ML20104C035. The licensee discussed the leak before break for specific piping attached to reactor coolant system (RCS) primary loops. The licensee specified that the RCS auxiliary lines the license amendment request would consider include the 6-inch safety injection lines, the 10-inch accumulator lines, the 14-inch residual heat removal line, and the 14-inch pressurizer surge line.

Also, a PSEG representative discussed the evaluation methods for leak before break using NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Section 3.6.3 criteria.

During the meeting, the following comments were made by the NRC staff:

Since the pipe material properties change over time, confirm whether the materials used for the in-scope piping are subject to thermal aging.

Confirm whether the pipe force and moment values used in the leak before break analyses are consistent with the measurement uncertainty recapture values (most recent) instead of the original piping system design values.

Verify 0.5 gallons per minute (gpm) leak detection based on the 6-inch safety injection leakage crack flow rate is the most limiting case. Include a comparison to the leakage crack flow rate from the original leak before break analyses for the reactor coolant loop piping.

The licensee does not anticipate changing the current technical specification limit of 1.0 gpm unidentified leakage, even though the 0.5 gpm leak detection is the most limiting case.

PSEG indicated it will address these comments in the license amendment request, which it plans to submit by the end of April 2020.

There were no comments from the members of the public; no public meeting feedback forms were received. No regulatory decisions were made at the meeting.

Please direct any inquiries to me at (301) 415-4125 or James.Kim@nrc.gov.

/RA/

James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosure:

List of Attendees cc: Listserv

LIST OF ATTENDEES APRIL 15, 2020, PRE-SUBMITTAL PUBLIC MEETING WITH PSEG NUCLEAR LLC TO DISCUSS SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 LEAK-BEFORE-BREAK ANALYSES LICENSE AMENDMENTS ATTENDEES ORGANIZATION John Tsao U.S. Nuclear Regulatory Commission (NRC)

Mark Yoo NRC Seung Min NRC Robert Beaton NRC David Nold NRC Chang Li NRC James Kim NRC Brian Thomas PSEG Nuclear LLC (PSEG)

Paul Duke PSEG Sam Markos PSEG Andrew Preston PSEG William McTigue PSEG Robert Page PSEG Tim Giles PSEG Paul Lindsay PSEG Sean Halfhill Westinghouse Eric Johnson Westinghouse Dean Utley Westinghouse Nathan Lang Westinghouse Jerry Humphreys New Jersey Department of Environmental Protection (NJDEP)

Elliot Rosenfeld NJDEP Jacob Fakory NJDEP Mehran Mohammadian Sargent and Lundy Craig Harrington EPRI-MRP Enclosure

ML20113F089 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME JKim LRonewicz JDanna JKim DATE 04/24/2020 04/24/2020 04/27/2020 04/27/2020