ML18153A933

From kanterella
Jump to navigation Jump to search
Submits Actual Weld Exam Coverage Results Re ISI Program for Surry Power Station Unit 1
ML18153A933
Person / Time
Site: Surry 
Issue date: 04/25/1994
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-243, NUDOCS 9405020320
Download: ML18153A933 (2)


Text

e e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 25, 1994 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM PRESSURIZER WELD EXAMINATIONS Serial No.94-243 NES/ISI/EWT/ETS/vlh Docket No.

50-280 License No.

DPR-32 Our October 8, 1993 letter (Serial No.93-451 A) submitted Relief Request SR-005 for the Surry Unit 1 lnservice Inspection Program. This relief request identified a support structure obstruction which prevented complete examination of the shell-to-top head weld (weld 1-07) and the intersecting longitudinal weld (weld 1-15) on the pressurizer.

The relief request included expected examination coverage without removing the support interferences. In our letter we stated that if the examination coverage attained is significantly less than that proposed, we would submit the actual weld examination coverage results.

The actual weld examination coverage is as follows:

For weld 1-07 (shell-to-top head weld), for reflectors parallel to the weld seam the expected coverage was 66.7% and the actual coverage was 37.2%. For reflectors transverse to the weld seam the expected coverage was 79% and the actual coverage was 87%.

For weld 1-15 (intersecting longitudinal weld), the expected coverage was 44.5%.

However, no examination could be performed at the Code required examination area of O" to 12". The support interferences extend to a greater degree than expected. The pressurizer safety valve support covers the weld from O" to 24". On May 18, 1986 an examination was performed on this weld from 24" to 36" with no reportable indications.

Should you have any questions or require additional information, please contact us.

Very truly yours, C)P.OW~8~

fr W. L. Stewart Senior Vice President - Nuclear

~: S G C [, 11 - _________ _

9405020320 --940425 ~.

QPDR A DOCK 05000280

' 'I PDR I

cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station