ML17068A045

Summary of 2/28/17 Public Teleconference with Southern Nuclear Operating Company to Discuss Vogtle Electric Generating Plant, Units 1 and 2, Risk-Informed Technical Specification License Amendment Request

ML17068A045
Person / Time
Site:	Vogtle
Issue date:	04/06/2017
From:	Geoffrey Miller Special Projects and Process Branch
To:	Markley M Plant Licensing Branch II
Miller G, NRR/DORL/LSPB, 415-2481
References
CAC ME9555, CAC ME9556
Download: ML17068A045 (5)

Text

MEMORANDUM TO:

FROM:

SUBJECT:

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 6, 2017 Michael T. Markley, Chief Plant Licensing Branch 11-1 Div_ision of Operating Reactor Lic~nsing

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Office of Nuclear Reactor Regulation

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G. Edward Miller, Project Manager

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Special Projects and Process Branch/ c--~~c. ;- It.. __

Division of Operating Reactor Licensi~

Office of Nuclear Reactor Regulation

SUMMARY

OF FEBRUARY 28, 2017, PUBLIC MEETING REGARDING LICENSE AMENDMENT REQUEST TO IMPLEMENT RISK-INFORMED TECHNICAL SPECIFICATION COMPLETION TIMES AT VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (CAC NOS. ME9555 AND ME9556)

On February 28, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff held a public meeting1 with staff from Southern Nuclear Operating Company, Inc. (SNC or the licensee). The purpose of the meeting was to discuss SN C's license amendment request to implement risk-informed Technical Specification Completion Times (RICT) for the Vogtle Electric Generating Plant, Units 1 and 2. Specifically, the discussion was focused on draft request for additional information (RAI) questions 6, 10, and 11 that were provided to SNC on February 24, 2017. 2 The discussion was a continuation from a February 7, 2017, public meeting3 on this topic.

The NRC staff provided a summary of RAI 6, which focuses on accounting for the risk of common-cause failure (CCF) during emergent equipment failures. The NRC staff indicated that the preferred method, consistent with Regulatory Guide 1.177, "An Approach for Plant-Specific Risk-Informed Decisionmaking for lnservice Inspection of Piping," to address this issue would be to adjust the numerical RICT calculation to account for CCF until such a possibility had been eliminated. The NRC staff stated that, in lieu of numerically accounting for the increased possibility of CCF, risk management actions (RMAs) not credited in the probabilistic risk assessment could potentially be used if they were implemented prior to exceeding the front stop and were sufficient to ensure that any safety function(s) would not be lost if the remaining train failed to function upon demand. SNC noted that another way to ameliorate the increased risk from potential CCF would be to reduce the likelihood of initiating events that would place demand on the alternate train. The NRC staff indicated that such an approach would require further consideration, but that it would be difficult to compare the effect of the RMAs to the effect of CCF without calculating numerical impacts.

1 The original meeting notice is available via the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML17052A180.

2 The draft RAI is available under ADAMS Accession No. ML17058A127.

3 The meeting summary for the February 7, 2017, meeting is available under ADAMS Accession No. ML17041A366.

Although better understanding was reached, at the conclusion of the meeting, both parties agreed that additional interactions would be necessary with regard to RAI 6. SNC acknowledged that they understood what information was being requested for RAls 10 and 11.

Another public meeting would be planned at a later date and noticed via the normal process.

No regulatory decisions were made at the meeting. Following the discussion, an opportunity was afforded to any other participants who wished to ask questions or make comments. No questions or comments were received.

Docket Nos. 50-424 and 50-425

Enclosure:

List of Attendees cc: Listserv

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