ML13305B005
| ML13305B005 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/06/2013 |
| From: | James Kim Plant Licensing Branch 1 |
| To: | Heacock D Dominion Nuclear Connecticut |
| Kim J | |
| References | |
| TAC MF1731 | |
| Download: ML13305B005 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
lnnsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 November 6, 2013
SUBJECT:
MILLSTONE POWER STATION UNIT 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION FOR CALCULATED PEAK CONTAINMENT INTERNAL PRESSURE (TAC NO. MF1731)
Dear Mr. Heacock:
By letter dated April 25, 2013, Dominion Nuclear Connecticut, Inc. (the licensee) submitted an amendment to revise the calculated peak containment internal pressure for the design basis loss-of-coolant accident described in Technical Specification 6.8.4.f., "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.
Docket No. 50-423
Enclosure:
As stated cc w/encl: Distribution via Listserv Sincerely, r~
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION FOR CALCULATED PEAK CONTAINMENT INTERNAL PRESSURE MILLSTONE POWER STATION UNIT 3 DOCKET NO. 50-423 EEEB-1 In the LAR, the licensee states the following:
Change in Pa does not affect environmentally qualified equipment.
The containment temperatures, using the corrected large break LOCA mass and energy (M&E) releases, remain within the bounding containment temperature profile used to qualify equipment.
- a. Provide a discussion of the Environmental Qualification (EQ) re-analysis performed to show that the equipment remained qualified. In addition, provide a comparison of the EQ overlays with containment temperature and pressure profiles.
- b. Explain how margins are being maintained for qualified equipment in accordance with 10 CFR 50.49.
EEEB-2 Provide a discussion on any impact of the proposed change on areas of the plant outside of containment (e.g., changes to EQ parameters such as temperature and pressure).
Enclosure
- ML133058005 OFFICE LPL 1-1/PM LPL 1-1/LA NAME JKim KGoldstein DATE 11/06/13 11/04/13 Sincerely, Ira/
James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsAcrsAcnw MaiiCTR Resource RidsNrrDoriLpi1-1 Resource RidsNrrPMMillstone Resource AFoli, NRR RidsNrrDoriDpr Resource RidsNrrDeEeeb RidsRgn1 Mail Center
- via memo dated October 22 2013 DE/EEEB/BC LPL 1-1/BC (A)
JZimmerman*
RBeall 10/3/13 11/06/13