ML15089A164

Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis

ML15089A164
Person / Time
Site:	Davis Besse, Oconee, Arkansas Nuclear, Three Mile Island
Issue date:	04/27/2015
From:	Rowley J G Licensing Processes Branch (DPR)
To:	Mendiola A J Licensing Processes Branch (DPR)
Rowley J G
Shared Package
ML15089A159	List: ML15089A164
References
Download: ML15089A164 (4)

Text

April 27, 2015

MEMORANDUM TO: Anthony J. Mendiola, Chief Licensing Processes Branch

Division of Policy and Rulemaking Office of Nuclear Reactor Regulation FROM: Jonathan G. Rowley, Project Manager /RA/ Licensing Processes Branch

Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

SUMMARY

OF FEBRUARY 25, 2015, PARTIALLY CLOSED MEETING WITH INDUSTRY STAKEHOLDERS REGARDING THE BABCOCK AND WILCOX LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL ANALYSIS

On February 25, 2015, a partially closed meeting was held between the U.S. Nuclear

Regulatory Commission (NRC) staff, representatives of Babcock and Wilcox (B&W) plants, and AREVA Inc. (AREVA). The purpose of the meeti ng was to discuss NRC staff actions to verify safe plant operation and the industry (utilities and AREVA) plans to revise the B&W plant large break loss-of-coolant accident (LBLOCA) evaluation model to correct an error in accounting for fuel thermal conductivity degradation and to reanalyze the B&W plant-specific LBLOCA analyses to demonstrate continued compliance with Title 10 of the Code of Federal Regulations (10 CFR) 50.46 requirements.

Jeremy Dean (NRC) made opening remarks for the NRC and Tom Byrne (Duke Energy) made opening remarks for the utilities that operate B&W plants. Benjamin Parks (NRC) led the NRC presentation during the open portion of the meeting, which provided the background on the issue. Benjamin also led the NRC presentation dur ing the closed portion of the meeting. Jerry Holm and Jacoben Tone (AREVA) made a presentation of the AREVA plans to revise the B&W plant LBLOCA evaluation model and to perform a reanalysis of the LBLOCA for each of the B&W plants.

The expectations expressed by the NRC, and the AREVA plans to (1) revise the B&W plant LBLOCA evaluation model and (2) perform a reanalysis of the LBLOCA for each of the B&W plants, were in general agreement.

A list of attendees is enclosed. The AREVA presentation can be found in the NRC Agencywide Documents Access and Management System (A DAMS) at Accession No. ML15057A036. The NRC presentation can be found in ADAMS at Accession No. ML15057A032.

CONTACT: Jonathan Rowley, NRR/DPR (301) 415-4053

Action Items The following action items were identified.

1. AREVA will submit for NRC review and approval a supplement to Topical Report (TR) BAW-10192PA, Revision 0, to revise the current approach to modeling fuel thermal conductivity degradation in the B&W plant LBLOCA evaluation model. A revision to BAW-10179P will be made to reference this BAW-10192PA, Revision 0, supplement. This supports the NRC position that the revision of the evaluation model requires review

and approval by the NRC. The submittal of the proposed TR supplements will provide for an efficient and consistent NRC staff review of the evaluation model revision. The NRC indicated that they will want to review the justification for not redoing sensitivity studies with the revised evaluation model.

2. The utilities plan to have AREVA reanalyze the LBLOCA for each plant after the NRC issues a safety evaluation for the TR suppl ement. Each utility will notify the NRC when the reanalysis is complete. The reanalysis will be evaluated by each utility under 10 CFR 50.59 to determine if a license amendment request is required.

3. The NRC indicated that they are preparing a regulatory information summary (RIS) to provide guidance for 10 CFR 50.46 evaluation model change reporting requirements.

The RIS is anticipated to be issued in late 2015.

4. The NRC stated that they had restarted the review of TR BAW-10192P, Revision 2, which had been suspended in 2010. AREVA indicated that BAW-10192P, Revision 2, was a Pressurizer Water Reactor Owners Group (PWROG) TR. The NRC would need to discuss with the PWROG whether it is desired that the review be restarted. The NRC requested a letter stating whether BAW-10192P, Revision 2, should be withdrawn, reviewed or classified as inactive.

Docket Nos. 50-269, 50-270, 50-287, 50-289, 50-313 and 50-346

Enclosure:

List of Attendees

ML15089A164 (Summary); ML15089A159 (Package): ML15042A558 (Notice): ML15057A036, ML15057A032 (Presentations) NRC-001 OFFICE PLPB/PM PLPB/LA PLPB/BC PLPB/PM NAME LAlvarado DHarrison AMendiola JRowley DATE 04/27/2015 04/07/2015 04/27/2015 04/27/2015 ENCLOSURE List of Attendees Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss-of-Coolant Accident Evaluation Model Analysis February 25, 2015 Name Organization Gayle Elliot AREVA Inc. (AREVA) John Klingenfus AREVA Russell Cox AREVA Jerald Holm AREVA Chris Allison AREVA Bret Boman AREVA Jacoben Tone AREVA Adam Bingham* Duke Energy Tracy A Saville* Duke Energy Scott Thomas Duke Energy Thomas R. Byrne* Duke Energy Mark Handrick Duke Energy Robert St Clair* Duke Energy Stephenie L. Pyle* Entergy Nuclear Operations (Entergy) Chip Garbe* Entergy Andy Tate* Entergy Bret Hawes* Entergy Bob Clark* Entergy Greg Broadbent Entergy Robert Jaffa Exelon Generation Company (Exelon) Frank Mascitelli Exelon Gregory Heasley Exelon Phil Lashley FirstEnergy Nuclear Operating Company (FENOC) Daniel B Kelley FENOC Jonathan Rowley U.S. Nuclear Regulatory Commission (NRC) Andrea George* NRC Eva Brown NRC Benjamin Parks NRC Jeremy Dean NRC Reed Anzalone NRC Chris Jackson NRC Robert Gladney NRC Jennifer Whitman NRC John G. Lamb NRC Jeffrey White NRC Shanlai Lu NRC Fred Forsaty NRC Lydiana Alvarado NRC

• participated via telephone conferencing