ML13281A833

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Request for Additional Information to Support Review of Millstone Power Station Unit 3 Application for Technical Specification Change Regarding Risk Informed Justification for the Relocation of Specific Surveillance Frequency Requirements t
ML13281A833
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/09/2013
From: James Kim
Plant Licensing Branch 1
To: Heacock D
Dominion Nuclear Connecticut
Kim J
References
TAC ME9733
Download: ML13281A833 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 9. 2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION UNIT 3 REQUEST FOR ADDITIONAL INFORMATION TO SUPPORT REVIEW OF APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING RISK INFORMED JUSTIFICATION FOR THE RELOCATION OF SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM (TAC NO. ME9733)

Dear Mr. Heacock:

By letter dated October 4, 2012. Dominion Nuclear Connecticut, Inc. (the licensee) submitted an amendment to revise Technical Specification to adopt Technical Specification Task Force (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5b."

The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has detennined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided by November 1. 2013.

If you have any questions regarding this matter, please contact me at 301-415-4125.

Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION RELATED TO AN AMENDMENT TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TREVELLER TSTF-425, REVISION 3, TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE CONTROLLED PROGRAM MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 Question 1 The response to RAI 5 (April 17, 2013) indicates that Millstone Power Station Unit 3 (MPS3) plans to follow NEI 04-10 guidance from Step 10b. However, it further proposes a specific alternative bounding analysis methodology for fire initiating events which is not described in Nuclear Energy Institute (NEI) 04-10, Step 10b, and indicates that other hazard bounding analysis will use a bounding analysis not explicitly described in NEI 04-10, Step 10b. This step provides examples of alterative bounding approaches if the structure, system, or component is not explicitly in the probabilistic risk assessment (PRA). However, as the methodology is described in the response for fire-initiating events, the staff cannot find a bounding methodology due to an apparent lack of Fire PRA attributes. Given that MPS3 does not have a Fire PRA, according to the response to the RAI, an acceptable bounding analysis method should be consistent with alternative evaluation guidance described in NEI 04-10, Step 10b. As noted in NEI 04-10, this step also applies to other hazards analyses. More generally, if an alternative bounding analysis approach is proposed other than the examples noted in this step, sufficient justification should be provided to ensure it is a bounding analysis. Therefore, please describe the bounding method to be used for internal fire or other external events, how it is consistent with NEI 04-10, Step 10b, and how the bounding analysis considers the current plant configuration and operation.

Question 2 The LAR notes that a self-assessment of the MPS3 internal events PRA was performed in 2007 using an ASME/ANS Standard. Please indicate which version of the ASME/ANS Standard was used.

Enclosure

' .. ML13281A833 *via memo dated October 3, 2013

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