ML13218A310

Request for Additional Information Regarding Amendment for a Revised Calculated Peak Containment Internal Pressure

ML13218A310
Person / Time
Site:	Millstone
Issue date:	08/08/2013
From:	James Kim Plant Licensing Branch 1
To:	Heacock D Plant Licensing Branch 1
References
TAC MF1731
Download: ML13218A310 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 8, 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 REGARDING AMENDMENT FOR A REVISED CALCULATED PEAK CONTAINMENT INTERNAL PRESSURE (TAC NO. MF1731)

Dear Mr,

Heacock:

By letter dated April 25, 2013, Dominion Nuclear Connecticut, Inc. (the licensee), submitted a License Amendment Request to revise the calculated peak containment internal pressure (Pa) for the Design Basis Loss-Of-Coolant Accident described in Technical Specification Section 6.8.4F, "Containment Leakage Rate Testing Program."

The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has determined 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 within 45 days of the date of this letter.

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

Sincerely, cr~ ~

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 LICENSE AMENDMENT REQUEST FOR A REVISED CALCULATED PEAK CONTAINMENT INTERNAL PRESSURE DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423

1. Please verify that no change is needed in Technical Specification 3.6.1.4, "Containment Pressure," in order to maintain the calculated peak containment internal pressure (Pa) below the design limit. Please indicate the containment operating pressure used as the initial condition for the Design-Basis Accident Loss-Of-Coolant-Accident analysis performed.

2. Please verify that this issue is not related to the recent EPITOME computer modeling errors discovered by Westinghouse.

3. Please state if the Appendix J Type Band C test procedures do not require revision upon approval of this proposed LAR. The American National Standards Institute (ANSI) 56.8-1994, Section 3.3.2 requires that Type Band C testing be performed at a pressure not less than Pa (except for airlock door seals, which may have a lower pressure specified) and not more than 1.1 times Pa when a higher differential pressure results in increased sealing. Please discuss the site procedures for Type Band C testing, and provide a discussion on the requirement that the testing be performed within a range of pressures that, with the revised Pa, will continue to be within the range of pressures required by ANSI 56.8-1994.

4. Please describe the steps that will be taken following approval of this amendment with regard to Appendix J Type A testing procedures.

Enclosure

August 8, 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 SUB~'ECT: MILLSTONE POWER STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT FOR A REVISED CALCULATED PEAK CONTAINMENT INTERNAL PRESSURE (TAC NO. MF1731)

Dear Mr. Heacock:

By letter dated April 25, 2013, Dominion Nuclear Connecticut, Inc. (the licensee), submitted a License Amendment Request (LAR) to revise the calculated peak containment internal pressure (Pa) for the Design Basis Loss-Of-Coolant Accident (DBLOCA) described in TS Section 6.8.4F, "Containment Leakage Rate Testing Program."

The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has determined 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 within 45 days of the date of this letter.

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

Sincerely, Ira!

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 Distribution:

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• RBeali A DATE 8/7113 7126/13 8/8/13 Official Record Copy