ML18207A733

Summary of Pre-Licensing Meeting with PG&E Co. to Discuss the Proposed LAR to Implement WCAP-16996-A, Revision 1, Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes at Diablo Canyon

ML18207A733
Person / Time
Site:	Diablo Canyon
Issue date:	08/10/2018
From:	Balwant Singal Plant Licensing Branch IV
To:	Pacific Gas & Electric Co
Singal B NRR/DORL/LPL4 301-415-3016
References
EPID L-2018-LRM-0041
Download: ML18207A733 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 10, 2018 LICENSEE: Pacific Gas and Electric Company FACILITY: Diablo Canyon Nuclear Power Plant, Units 1 and 2

SUMMARY

OF JULY 20, 2018, PRE-SUBMITTAL MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY TO DISCUSS THE PROPOSED LICENSE AMENDMENT REQUEST TO IMPLEMENT WCAP-16996-A, REVISION 1, "REALISTIC LOCA EVALUATION METHODOLOGY APPLIED TO THE FULL SPECTRUM OF BREAK SIZES (FULL SPECTRUM LOCA METHODOLOGY),"

AT DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 (EPID L-2018-LRM-0041)

On July 20, 2018, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Pacific Gas and Electric Company (PG&E, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss a proposed license amendment request by PG&E to adopt a new loss-of-coolant accident (LOCA) analysis methodology for Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Diablo Canyon). The meeting notice and agenda, dated June 29, 2018, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML18180A124. The licensee's presentation for this meeting is available in ADAMS at Accession No. ML18204A055.

During the meeting, the licensee stated that the Diablo Canyon application wjll be the first to request adoption of the new LOCA methodology following the NRC approval of the*

Westinghouse Topical Report WCAP-16996-A, Revision 1, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Sizes (FULL SPECTRUM LOCA Methodology)" (ADAMS Accession No. ML17277A132). The licensee stated that the adoption of the Full Spectrum LOCA (FS LOCA) Methodology is to satisfy a regulatory commitment to address fuel thermal conductivity degradation.

The licensee stated that the only technical specification (TS) change expected was to the methodology references associated with TS 5.6.5, "Core Operating Limits Report (COLR)." The licensee specified that there are no fuel or TS fuel limits that would change as a result of this amendment. The licensee discussed the current LOCA design basis analysis methodologies, and stated that the application would include an update to the PAD5 fuel performance code (versus the currently-used PAD4).

The NRC staff and the licensee discussed the limitations and conditions associated with the use of the FS LOCA methodology, including how Diablo Canyon's Westinghouse 4-loop nuclear steam supply system (NSSS) design would be addressed since several of the NRC staff's limitations and conditions specify additional steps that must be taken for the first application of FS LOCA to a plant other than a Westinghouse 3-loop NSSS.

The NRC staff requested that PG&E compare the FS LOCA-calculated peak clad temperatures, maximum local oxidation, and core wide oxidation with the results from the current analysis of record. Any significant differences should be explained in enough detail for the NRC staff to understand the basis for the differences beyond the methodology change.

The licensee stated that to meet the regulatory commitment, the application needs to be submitted by the end of the year. The NRC staff asked how the NRC rulemaking for Title 10 of the Code of Federal Regulations Section 50.46c would impact the application. The licensee stated that it would not have any impact. The NRC staff also stated that the review could be considered complex, since it is the first application of the FS LOCA methodology, and thus might not meet the normal 1-year review schedule. The licensee stated that this would not impact the Diablo Canyon operations.

There were no public comments nor meeting feedback received.

Please direct any inquiries to me at (301) 415-3016, or by e-mail at Balwant.Singal@nrc.gov.

Sincerely,

r:> QQ__~ ~  :)~v ia?want K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323

Enclosure:

List of Attendees cc: Listserv

LIST OF ATTENDEES JULY 20, 2018, MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY REGARDING THE PROPOSED LICENSE AMENDMENT REQUEST TO IMPLEMENT WCAP-16996-A, REVISION 1 DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-323 NAME ORGANIZATION Reed Anzalone NRC 1 (NRR)2 Robert Beaton NRC (NRR)

Mathew Panicker NRC (NRR)

Lisa Regner NRC (NRR)

Ken Schrader PG&E3 Dave Efron PG&E Jim Andrachek WEC4 Christopher Trelani WEC Jeffrey Kobelak WEC Brian Mount Dominion Energy 1 U.S. Nuclear Regulatory Commission 2 Office of Nuclear Reactor Regulation 3 Pacific Gas and Electric Company 4 Westinghouse Electric Company (representing PG&E)

Enclosure

Meeting Notice: ML18180A124 Meetmg

' Summary: ML18207A733 *b1ye-ma1*1 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DSS/SRXB/BC*

NAME BSingal PBlechman JWhitman DATE 07/30/18 07/30/18 08/03/18 OFFICE NRR/DSS/SNPB/BC* NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RLukes RPascarelli (LRegner for) BSingal DATE 08/06/18 08/09/18 08/10/18