ML062340526
| ML062340526 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/10/2006 |
| From: | Gordon Peterson Duke Energy Carolinas, Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML062340526 (3) | |
Text
GARY R. PETERSON Vice President AwEnergye McGuire Nuclear Station Duke Energy Corporation MG01 VP / 12700 Hagers Ferry Rd.
Huntersville, NC 28078 704 875 5333 704 875 4809 fax grpeters@duke-energy.com August 10, 2006 U.
S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555-0001
Subject:
Duke Energy Company LLC d/b/a Duke Energy Carolinas, LLC (DUKE)
McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369 and 50-370 Relief Request MC-SRP-NS-01
Reference:
NRC letter to Mr. Gary R. Peterson, dated September 6, 2005 By letter dated September 6, 2005, the NRC issued a Safety Evaluation Report in response to DUKE's Relief Request for the Third 10-Year Pump and Valve Inservice Testing Program.
The NRC letter states in part:
"The proposed alternative, as stated in Relief Request MC-SRP-NS-01 to the Code reference value requirements of ISTB 4.3e(1) for the containment spray pumps, is denied on the basis that it does not provide an acceptable level of quality and safety, and compliance with code requirements would not result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
However, the alternative method identified in Relief Request MC-SRP-NS-01 provides sufficient assurance of operational readiness of the pumps to authorize the alternative for an interim period until the end of refueling cycle No.
17 (Spring 2007) for McGuire, Unit 1 and the end of refueling cycle No.
17 (Fall 2006) for McGuire, Unit 2 to allow time for the licensee to reevaluate its proposed alternative testing and/or to perform the required design changes pursuant to 10 CFR 50.55a(f) (6) (I)."
www. duke-energy. corn
U.S. Nuclear Regulatory Commission August 10, 2006 Page 2 Please note that there is a typographical error in the referenced letter.
The spring outage of 2007 for Unit 1 should be documented as end of refueling cycle No.
18 instead of No. 17.
In accordance with the ASME Code requirements McGuire has approved an engineering change request providing design changes for implementing a full flow test loop for the containment spray pumps for both Units.
These projects are MD-100346 for Unit 1 and MD-200347 for Unit 2.
McGuire is to complete implementation of MD-100346 by the end of the Spring outage in 2007 and MD-200347 by the end of the Fall outage in 2006.
Questions on this matter should be directed to Norman T.
Simms, McGuire Regulatory Compliance, at (704) 875-4685.
Sincerely, G.R. Peterson
U.S. Nuclear Regulatory Commission August 10, 2006 Page 3 cc w/attachment:
Mr.
W.D. Travers Regional Administrator, Region II U.
S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. J.F. Stang Jr., Project Manager (addressee only)
Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J.B. Brady Senior NRC Resident Inspector McGuire Nuclear Station