ML18341A098

Memo E-mail to File - Summary of November 8, 2018, Meeting with Dominion to Discuss Proposed LAR - 10 CFR 50.69 Risk-Informed Approach

ML18341A098
Person / Time
Site:	Millstone
Issue date:	12/07/2018
From:	Guzman R V Plant Licensing Branch 1
To:	James Danna Plant Licensing Branch 1
Guzman R V
References
EPID L-2018-LRM-0077
Download: ML18341A098 (3)

Text

From: Guzman, Richard To: Danna, James

Subject:

Memo E-mail to File - Summary of November 8, 2018, Meeting with Dominion to Discuss Proposed LAR - 10 CFR 50.69 Risk-Informed Approach Date: Friday, December 7, 2018 10:25:33 AM Jim, For your information, shown below is a summary of the November 8, 2018, Category 1 public meeting with Dominion Energy Nuclear Connecticut, Inc. to discuss the licensee's planned license amendment request submittal regarding its proposed implementation of 10 CFR 50.69, "Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors,"

for Millstone Power Station, Unit No. 2 (MPS2). This e-mail will be added to ADAMS as an official agency record and Listserv'd.

Please contact me if you have any questions regarding this meeting. ~~~~~~~~~Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone:

(301) 415-1030 Richard.Guzman@nrc.gov CATEGORY 1 PUBLIC MEETING MILLSTONE POWER STATION, UNIT NO. 2 PRE-APPLICATION MEETING MEETING

SUMMARY

10 CFR 50.69 RISK-INFORMED LICENSE AMENDMENT REQUEST NOVEMBER 8, 2018 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Dominion Energy Nuclear Connecticut, Inc. (DENC, the licensee) held a public meeting on November 8, 2018, to discuss the licensee's planned license amendment request (LAR)submittal regarding its proposed implementation of 10 CFR 50.69, "Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors,"

for Millstone Power Station, Unit No. 2 (MPS2). The provisions of 50.69 allow adjustment of the scope of structures, systems, and components (SSCs) subject to special treatment requirements (e.g., quality assurance, testing, inspection, condition monitoring, assessment, and evaluation) based on a method of categorizing SSCs according to their safety significance.

The licensee's meeting slides are available in Agencywide Documents Access and Management System at Accession No. ML18310A181. The licensee presented a summary of the following:

Description of the current MPS2 Probabilistic Risk Assessment (PRA) Models and Technical Adequacy Overview of the proposed deviations from Nuclear Energy Institute (NEI) 00-04, Revision 0, "10 CFR 50.69 SSC Categorization Guideline" Fire Risk Passive Categorization Seismic Safe Shutdown Equipment List (SSEL) per NEI 00-04 Projected schedule for submission The licensee provided an overview of their PRA model technical adequacy for internal events and stated that all supporting requirements have been reviewed by a peer review team against ASME/ANS RA-Sa-2009 standard.

A focus scope review was performed in March 2018 and in August 2018. The licensee indicated it will provide a sufficient description of the history of all focus scope reviews performed to date in its LAR. The licensee proposes to use the Appendix R Safe Shutdown Equipment List (SSEL) in lieu of the Individual Plant Examination of External Events (IPEEE) Fire Induced Vulnerability Evaluation; all items on the SSEL will be risk significant and will follow a conservative approach.

The licensee stated that it will include a review of multiple spurious operations and any deviations or exemptions from the fire protection program. The licensee also noted that Sequoyah followed a similar approach for its 50.69 LAR and will consider all applicable request for additional information items from that precedent review in their application.

In terms of the NEI 00-04 deviations related to passive categorization, the licensee will follow both the NEI 00-04 template and the precedents previously approved by the NRC using the risk-informed repair/replacement methodology (i.e., approved by the NRC for the Vogtle 50.69 application)

The licensee's seismic SSEL which was submitted as part of the IPEEE, will be applied to address seismic inputs for categorization per the NEI-00-04.

The licensee stated that the SSEL has been reviewed and confirmed that no changes to the list are required in support of the planned LAR. Periodic updates of the list are planned after each refueling outage. The licensee also clarified that MPS2 is a Tier II plant and will consider a future update for seismic SSEL based on the recent EPRI technical report; however, this analysis would be completed as a separate LAR (i.e., not linked to the planned 50.69 LAR). The licensee stated their planned LAR application is on track and projected for submission by December 2018. The licensee plans to request NRC approval of the amendment by the December 2019. No decisions were made regarding the acceptability of the licensee's proposed submittal.

There were no members of the public in attendance by teleconference.

To date, no public meeting feedback forms have been submitted through the NRC public meeting feedback system. LIST OF ATTENDEES NOVEMBER 8, 2018, MEETING WITH DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC), TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST REGARDING 10 CFR 50.69 RISK-INFORMED APPROACH DOCKET NO. 50-336 ATTENDEE ORGANIZATION Mihaela Biro U.S. Nuclear Regulatory Commission (NRC)Stephen Dinsmore NRC Richard Guzman NRC Michael Levine NRC Justin Fuller*NRC Chris Highley*NRC Lou McKown*NRC Neil Sheehan*NRC Gary Miller DENC Bill Webster DENC Allen Moldenhauer DENC Shayan Sinha DENC Bruce Huhmann*Ameren Missouri, Callaway Energy Center Andrew Burgess*Ameren Missouri, Callaway Energy Center Rob Burg*Engineering Planning and Management, Inc.Ali Azarm*Innovative Engineering

& Safety Solutions, LLC Jeff Semancik*Connecticut Department of Energy and Environmental Protection

• Participated via conference line