ML063420150
| ML063420150 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/27/2006 |
| From: | Brandi Hamilton Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML063420150 (4) | |
Text
BRUCE H HAMILTON B&Duke R
.,LD Vice President PahEnergy Oconee Nuclear Station Duke Energy Corporation ONO] VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax November 27, 2006 bhhamilton@duke-energy.com U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
SUBJECT:
Duke Power Company Oconee Nuclear Station Units 1, 2, and 3 Docket Nos. 50-269, 50-270, 50-287 Inservice Testing (IST) Program Fourth 10 Year Program Interval Use of Subsequent Code Edition By letter dated June 10, 2002, Oconee Nuclear Station (Oconee) submitted its Fourth 10 Year Interval IST Program to the NRC.
At this time, Oconee desires to revise that program to use Mandatory Appendix I, Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants, of the ASME OMb 2000 Code for testing of Pressure Relief Devices.
Pursuant to 10 CFR 50.55a(f)(4)(iv), Oconee hereby requests NRC approval of the use of Appendix I of the ASME OMb 2000 Code for the remainder of the fourth ten-year interval of the IST program. In accordance with Regulatory Issue Summary 2004-12, this request to use a later edition and addenda is not a relief request; it is simply a request to use a later Code. The details of the 10 CFR 50.55a request are enclosed.
Due to the impact of this change on outage planning for our Unit 2 EOC 22 outage in Spring 2007, approval is requested prior to April 1, 2007.
If you have any questions or require additional information, please contact Randy Todd at (864) 885-3418.
Sincerely, Bruce H. Hamilton
Enclosure:
10 CFR 50.55a Request Number ONS-PRD www. duke-energy. corn
U. S. Nuclear Regulatory Commission November 27, 2006 Page 2 xc w/att:
Mr. William D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SWW, Suite 23T85 Atlanta, GA 30303 L. N. Olshan, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 xc(w/o attch):
D. W. Rich Senior NRC Resident Inspector Oconee Nuclear Station Mr. Henry Porter Division of Radioactive Waste Management Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.
Columbia, SC 29201 I
U. S. Nuclear Regulatory Commission November 27, 2006 Page 3 bxc w/att:
R. L. Gill, Jr.
B. W. Carney, Jr.
R. P. Todd L. C. Keith G. L. Brouette (ANII)
G. B. Saxon J. R. Kiser S. D. Capps IST File NRIA File/ELL EC050 Document Control
10 CFR 50.55a Request Number ONS-PRD Request In Accordance with 10 CFR 50.55a(f)(4)(iv)
-- Use of subsequent ASME Code Edition and Addenda --
- 1. ASME Code Component(s) Affected All pressure relief devices in the scope of the OM Code, Section IST.
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 1995 Edition, 1996 OMa Addenda.
- 3. Proposed Subsequent Code Edition and Addenda The 1998 edition through 2000 OMb addenda of Mandatory Appendix I, Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants as referenced by ASME OM Code. The proposed Code Edition and Addenda of Mandatory Appendix I section of the Code will be applied in its entirety for all pressure relief devices in the scope of the Code. Other portions of IST program will continue to apply the 1995 Edition, 1996 OMa Addenda of the OM Code.
The 1998 Edition through 2000 OMb Addenda of the ASME OM Code was incorporated by reference into 10 CFR 50.55a(b) on September 26, 2002 (67 FR 60520), and became effective on October 28, 2002, with no modifications or limitations placed on ASME OM Code or Mandatory Appendix I requirements involving pressure relief valve testing.
- 4. Related Requirements There are no modifications or limitations listed in 10 CFR 50.55a(b) that apply to Mandatory Appendix I components in this subsequent Code Edition and Addenda. There are no applicable related requirements in the 2000 OMb Code other than Appendix I.
- 5. Duration of Proposed Request Due to the impact of this change on outage planning for our Unit 2 EOC 22 outage in Spring 2007, approval is requested prior to April 1, 2007. The duration of the request is for the remainder of the fourth ten-year program interval, which began June 1, 2002.
6. Precedents
This request is similar to a request submitted by Detroit Edison for Fermi-2 (Letter dated April 15, 2005, ML051230174) and approved by the NRC (Letter dated July 25, 2005, ML051710089).