ML18153B284

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Requests Withdrawal of ISI Program Relief Request SR-005, Submitted on 870416 & Suppl on 890215,w/respect to Pressurizer Weld Exams
ML18153B284
Person / Time
Site: Surry  
Issue date: 08/11/1993
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
93-451, NUDOCS 9308160212
Download: ML18153B284 (12)
v • d • e


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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August n~ 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INSERVICE INSPECTION PROGRAM PRESSURIZER WELD EXAMINATIONS Serial No.

NL&P/ETS Docket Nos.

License Nos.93-451 R1 50-280 50-281 DPR-32 DPR-37 Surry Power Station Units 1 and 2 submitted lnservice

  • Inspection Program relief requests SR-005 (Attachment 1) for each unit on April 16, 1987, which were supplemented on February 15, 1989. These requests identified a support structure obstruction, which prevented complete examination ofthe shell-to-top head weld and intersecting longitudinal weld on the pressurizers (1-RC-E-2 and 2-RC-E-2).

Specifically, relief was requested from the full volumetric examinations requirements of Section XI, 1980 Edition, Winter 1980 Addenda, Category 8-8. As an alternative, we proposed to examine the welds to the extent practical, and delay removing the support structure to perform a complete examination of the identified welds until later in the second ten year interval. These requests were evaluated and approved by the staff in a SER dated March 14, 1991.

We have reassessed the need to remove the support structure from the pressurizer to perform a complete examination and conclude that this approach is not required to maintain an adequate margin of safety. Furthermore, our evaluation estimated that the removal activities and inspection of the obstructed portion of the welds will require an expenditure of 18.4 man-rem per unit to accomplish.

Based on the above, it is our opinion that a complete examination requiring support structure removal is not commensurate with the gain in assurance of component integrity. As such, we are requesting withdrawal of relief request SR-005 for both Surry Unit 1 and Unit 2.

Therefore, we intend to perform the remaining third period Category 8-8 examinations on the pressurizer without removing the support interferences during the 1994 refueling outages for both units. The Code required examination will be completed to the extent practical. The specific examination coverage attained for these welds will be submitted in a new partial examination relief request following each refueling outage, pursuant to 1 O CFR 50.55a(g)(5)(iv) which permits this approach to impractical examinations.

______ 1J~.O_Oil2 9308160212-9308"i"-1--rn,,

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e This letter has been reviewed by the Surry Station Nuclear Safety and Operating Committee.

In order to support the Unit 1 refueling outage, we request your concurrence in withdrawing relief request SR-005 for both units by November 1, 1993.

If you have any questions concerning these requests please contact us.

Very trul~ yours,

\\~~,__-

"':~~

W. L. Stewart J

Attachment 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

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Surry Power Station Units 1 and 2 Pressurizer Weld Examinations

RBLIBP RBQUBST HO. SR-005 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The shell to top head circumferential weld on the Surry 1 Pressurizer is not accessible for 100% volumetric examination.

Additionally, the one foot intersecting longitudinal weld is also partially inaccessible.

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, requires a full volumetric examination for both the circumferential and longitudinal welds (Category B-B).

Relief is requested from this requirement due to the physiqal inaccessibility of the welds.

II. BASIS FOR RELIEF The shell to top head circumferential weld and intersecting longitudinal weld are inaccessible for either a full volumetric or surface examination due to interference from the insulation support ring.

The insulation support ring covers an area 4 inches wide just below the weld.

Only the four inches of weld 15 that intersect with weld 7 are inaccessible due to the support ring.

The remaining 8 inches of the required 12 inches may be examined in accordance with ASME Section XI.

III.

ALTERNATE PROVISIONS A volumetric examination will be performed to the extent practicable on welds 7 and 15.

Approximately 100% of the inner 1/3 of weld-7 can be examined in one direction and approximately 60% of the inner 1/3 in the opposite direction.

100% of Weld 15 will be examined from 4 11 through 12 11

  • The insulation support ring will be removed before the end of the inspection interval at which time 100% of both welds will be examined.

IV.

STATUS AS OF SER DATED MARCH 14, 1991 Granted.

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e RBLZBP REQUEST HO. SR-005 I.

IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The shell to top head circumferential weld on the Surry 2 Pressurizer is not accessible for 100% volumetric examination.

Additionally, the one foot i.ntersecting longitudinal weld is also partially inaccessible.

section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, requires a full volumetric examination for both the circumferential and longitudinal welds (Category B-B).

Relief is requested from this requirement due to the physical inaccessibility of the welds.

II.

BASIS FOR RELIEF The shell to top head circumferential weld and intersecting longitudinal weld are inaccessible for either a full volumetric or surface examination due to interference from the insulation support ring.

The insulation support ring partially covers weld 7.

Only the four inches of weld 2 that intersect with weld 7 are inaccessibl~ due to the support ring.

The remaining 8 inches of the required 12 inches may be examined in accordance with ASME Section XI.

III.

ALTERNATE PROVISIONS A volumetric examination will be performed to the extent practicable on welds 7 and 2.

Approximately 100% of the inner 1/3 of weld 7 can be examined in one direction and approximately 60% of the inner 1/3 in the opposite direction.

100% of weld 2 will be examined from 4 11 through 12 11

  • The insulation support ring will be removed before the end of the inspection interval at which time 100% of both welds will be examined.

IV.

STATUS AS OF SER DATED MARCH 14, 1991 Granted.

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