ML051010391
| ML051010391 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/11/2005 |
| From: | Grecheck E Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 04-237B | |
| Download: ML051010391 (2) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY
29-RC-301-2501 R-l-01 DM (loop A hot leg) 27-1 /2-RC-303-2501 R-A p r i l 11, 2005 Wall ID Thickness Base Metal Weld Metal SA508 Class 2 /
austenitic 29 2.70 ASTM A-376 TP 31 6 stainless steel SA508 Class 2 /
auste ni tic United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 1-1 7DM (loop A cold leg) 29-RC-304-2501 R-l-Serial No.
04-2378 NL&OS/GDM RO Docket No.
50-281 License No.
DPR-37 27-1/2 2.56 ASTM A351 CF8M stainless steel SA508 Class 2 /
auste ni tic VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 ASME SECTION XI INSERVICE INSPECTION PROGRAM REACTOR PRESSURE VESSEL WELD EXAMINATION RELIEF REQUEST CORRECTION TO REVISED RELIEF REQUEST SR-036 01 DM (loop B hot leg) 27-1 /2-RC-306-2501 R-Reactor pressure vessel (RPV) nozzle to shell, shell to flange and nozzle to piping weld examinations are required to be performed during the Third Inservice Inspection (ISI)
Interval for Surry Power Station Units 1 and 2 in accordance with Surrys ASME Section XI Inservice Inspection Program. In a letter dated May 13, 2004 (Serial No.04-237),
Dominion submitted relief requests to permit the use of updated examination methodologies when performing the RPV weld examinations. Two of the relief requests included in that submittal, SR-031 and SR-036 for Surry Units 1 and 2, respectively, were revised in response to an NRC request for additional information and provided to the NRC in a subsequent letter dated August 10, 2004 (Serial No. 04-237A). The NRC approved the submitted relief requests in the safety evaluation report included in their letter dated February 1, 2005.
29 2.70 ASTM A-376 TP 31 6 stainless steel SA508 Class 2/
austenitic Upon review of the NRCs safety evaluation report, Dominion engineering personnel noted that Surry Unit 2 Relief Request SR-036, Revision 1, erroneously included Surry Unit 1 weld number designations rather than the Unit 2 weld numbers. The correct weld number designations for Surry Unit 2 Relief Request SR-036, Revision 1, are provided below.
1-1 7DM (loop B cold leg) 29-RC-307-2501 R-l-27-1/2 2.56 SA351 CF8M stainless steel SA508 Class 2 I auste ni ti c 01 DM (loop C hot leg) 27-1 /2-RC-309-2501 R-29 2.70 ASTM A-376 TP 31 6 stainless steel SA508 Class 2/
austenitic 1-1 7DM (loop C cold leg) I 27-1/2 I 2.56 I SA351 CF8M 1 stainless steel 1
Serial No. 04-237B Docket Nos. 50-281 Page 2 of 2 Correction of the Surry Unit 2 weld number designations is an administrative change only and does not affect the basis for the requested relief nor the basis for NRC approval of Relief Request SR-036, Revision 1.
If you have any questions or require additional information, please contact Mr. Gary D.
Miller at (804) 273-2771.
Very truly yours, E. S. Grecheck Vice President - Nuclear Support Services Commitments made in this letter: None cc:
U. S. Nuclear Regulatory Commission Region I I Sam Nunn Atlanta Federal Center Suite 23T85 61 Forsyth St., S.W.
Atlanta, Georgia 30303-8931 Mr. Stephen R. Monarque NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North 1 1555 Rockville Pike Mail Stop 8-H12 Rockville, Maryland 20852 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station Mr. R. A. Smith Authorized Nuclear Inspector Surry Power Station