ML18313A254

Summary of Public Meeting with Wolf Creek Nuclear Operating Corporation Regarding License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses for Wolf Creek Generating Station

ML18313A254
Person / Time
Site:	Wolf Creek
Issue date:	11/16/2018
From:	Balwant Singal Plant Licensing Branch IV
To:	Heflin A Wolf Creek
Singal B, NRR/DORL/LPL4-1
References
EPID L-2017-LLA-0211
Download: ML18313A254 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 16, 2018 LICENSEE:

Wolf Creek Nuclear Operating Corporation FACILITY:

Wolf Creek Generating Station

SUMMARY

OF OCTOBER 30, 2018, PUBLIC MEETING WITH WOLF CREEK NUCLEAR OPERATING CORPORATION REGARDING LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSES FOR WOLF CREEK GENERATING STATION (EPID L-2017-LLA-0211)

On October 30, 2018, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee) and its contractors at NRC headquarters. The purpose of the meeting was to discuss the NRC staff's request for additional information (RAI) dated October 4, 2018 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML18270A094), related to the license amendment request (LAR) for transition to Westinghouse core design and safety analyses for Wolf Creek Generating Station (WCGS).

The meeting notice and agenda are located in ADAMS at Accession No. ML18296A584. A portion of the meeting was closed to members of the public because proprietary information was discussed. A copy of the licensee's publicly available presentation slides is available at ADAMS Accession No. ML18299A049. A list of meeting attendees is enclosed.

The licensee explained that the existing current WCGS safety analyses methodologies and analyses of record are roughly 20 years old, and that the transition to the Westinghouse core design and safety analyses methodologies is being performed to utilize current methodologies and provide more consistent alignment with the Westinghouse fleet of plants. The licensee stated that this transition will bring WCGS up to the latest industry best practices and will help in closing all the open issues for this LAR.

As a part of the presentation, the licensee provided the description of the LAR, timeline for the submittal and NRC staff review activities, and thermal conductivity degradation (TCD) methodology changes, including technical interfaces with the Westinghouse Performance Analysis and Design Model (PAD5), the principal tool for evaluating fuel rod performance. The licensee stated the following:

Explicitly accounting for TCD in the Westinghouse methodology can only be accomplished by the PAD5 methodology.

Use of PAD5 in the re-analysis for the Rod Ejection and Steamline break events may necessitate relaxation of the current Technical Specification (TS) Safety Limit (SL) 2.1.1.2 value. As a result, all other not-loss-of-coolant accident (non-LOCA) analyses that support the basis of TS SL 2.1.1.2 may need to be re-analyzed.

Performance of limited TS SL 2.1.1.2 analyses with PADS is not a viable option.

The licensee stated that the performance of all the non-LOCA analyses will not support the review schedule for the LAR. Hence, the licensee proposed the following approaches to address the NRC staffs concerns and support the NRC staffs review schedule:

Provide a descriptive evaluation and quantitative examples to address TCD and demonstrate that the acceptance criteria for the rod ejection and steam line break events are met when accounting for TCD. The proposed approach is likely to support the NRC staff's review schedule and the WCGS fall 2019 refueling outage schedule.

All analyses that support the fuel melt TS limit will be revised to explicitly account for TCD and the results of the Rod Ejection and Steam line break events would be documented. However, full non-LOCA PADS implementation would be introduced into the licensing basis via Title 10 of the Code of Federal Regulations ( 1 O CFR),

Section 50.59, "Changes, tests, and experiments."

The NRC staff stressed the need for a timely and accurate response to the NRC staff's request for completing the review in a timely fashion. The licensee indicated the RAI response schedule will be provided to the NRC staff within a week in a later conference call.

The NRC staff also informed the licensee that internal staff discussions are needed to review the approaches proposed by the licensee and that additional NRC staff feedback could be provided during the next status call.

No Public Meeting Feedback forms were received.

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

Docket No. 50-482

Enclosure:

List of Attendees cc: Listserv

~

.\\ ~v:ty Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

LIST OF ATTENDEES OCTOBER 30, 2018, PUBLIC MEETING WITH WOLF CREEK NUCLEAR OPERATING CORPORATION LICENSE AMENDMENT REQUEST FOR TRANSITION TO WESTINGHOUSE CORE DESIGN AND SAFETY ANALYSES FOR WOLF CREEK GENERATING STATION NAME TITLE ORGANIZATION Robert Pascarelli Branch Chief U.S. Nuclear Regulatory Commission {NRC)

Jennifer Whitman Branch Chief NRC Fred Forsaty Reactor Engineer NRC Reed Anzalone Reactor Engineer NRC Terrence Brimfield Reactor Engineer NRC Thomas Wengert Senior Project Manager NRC Balwant Singal*

Senior Project Manager NRC Mark Blumberg*

Senior Reactor Engineer NRC Benjamin Parks*

Senior Reactor Engineer NRC Steve Smith Vice President Engineering Wolf Creek Nuclear Operating Corporation {WCNOC)

Jason Knust Licensing Engineer WCNOC Brian Beebe Director, Core Engineering Westinghouse Electric Company {Westinghouse)**

Dustin Wirth Westinghouse **

Kevin Roland Westinghouse**

Bill Higby*

Westinghouse**

Dave Rumschlag*

Westinghouse **

Karen Piute*

Westinghouse**

Kent Bonadio*

Westinghouse **

Ian Miller*

Westinghouse**

Zach Strater*

Westinghouse**

Jim Smith*

Licensing Manager Westinghouse **

Korey Hosack*

Westinghouse **

Steve Meyer Regulatory Affairs Functional Area STARS Manager

• Participated via phone

• • Westinghouse staff attended meeting in support of WCNOC Enclosure

Meeting Notice ML18296A584 S

ML18313A254 ummarv OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA RidsRgn4MailCenter Resource FForsaty, NRR BParks, NRR MBlumberg, NRR TBrimfield, NRR RAnzalone, NRR TWengert, NRR JJohnston, NRR CCook, EDO RIV NRR/DORL/LPL4 NRR/DSS/SRXB/BC lWengert NAME BSingal PBlechman (JBur1<hardt for)

(W /comments)

JWhitman DATE 11/08/18 11/13/18 11/08/18 11/13/18 OFFICE NRR/DSS/SNPB/BC NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME Rlukes RPascarelli BSingal DATE 11/14/18 11/16/18 11/16/18