ML18153D286
| ML18153D286 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/29/1993 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-158, NUDOCS 9304050160 | |
| Download: ML18153D286 (7) | |
Text
ACCELERATED DOCUMENT DIST!i,UTION SYSTEM 1
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REGULAT~ INFORMATION DISTRIBUTIO STEM (RIDS)
ACCESSION NBR:9304050160 DOC.DATE: 93/03/29 NOTARIZED: NO DOCKET#
FACIL:S0-28i Surry Power Station, Unit 2, Virginia Electric &1 Powe 05000281 AUTH.NAME AUTHOR AFFILIATION STEWART,W.L.
Virginia Power (Virginia Electric & Power Co.)
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
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SUBJECT:
Requests relief from hydrostatic test requirements identifed in ASME Section 11,1980 Edition,Winter 1980 Addenda for ASME Class 3 valve.Request based on overpressurization concerns.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ~ ENCL _j_
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TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code NOTES:lcy NMSS/SCDB/PM.
COPIES RECIPIENT RECIPIENT ID CODE/NAME PD2-2 LA BUCKLEY,B LTTR ENCL ID CODE/NAME INTERNAL: ACRS NUDOCS-ABSTRACT OGC/HDS2 RES MILLMAN,G EXTERNAL: EG&G BROWN,B NRC PDR NOTES:
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 29, 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SUFIRY POWER STATION UNIT 2 Serial No.
NL&P/ETS Docket No.
License No.
INSIERVICE INSPECTION PROGRAM RELIEF REQUEST ASME SECTION XI HYDROSTATIC PRESSURE TEST 93-158 RO 50-281 DPR-37 Surry Unit 2 is currently conducting refueling operations.
Due to back leakage identified during plant operation, the discharge check valve (2-FW-142) for the steam driven auxiliary feedwater pump is being replaced during this outage.
Since an intermediate isolation valve does not exist and the discharge piping is welded directly to the pump, the high pressure hydrostatic test boundary for the upstream weld must include the steam driven auxiliary feedwater pump and the associated low pressure suction piping.
Therefore, pursuant to 1 O CFR 50.55a paragraph g(5), relief is requested from the hydrostatic test requirements identified in ASME Section XI, 1980 Edition, Winter 1980 Addenda for this ASME Class 3 valve. The basis of the relief request and the proposed alternative examinations are provided in the attachment to this letter.
It is our position that the proposed alternative examinations will provide sufficient information to assess the structural integrity of the weld as intented by the Code. We request your review and approval of this relief request by April 23, 1993, to support Unit 2 startup.
This relief request has been reviewed by the Station Nuclear Safety and Operating Committee.
It has been determined that the relief request does not involve an unreviewed safety question.
If you have any questions or require additional information, please contact us.
Very truly yours, I li~-~Q. L.~L\\**-**--
wl L > ~-iw'*..
W. L. Stewart Senior Vice President - Nuclear Attachment
- --9304050-160. 9.30329.-~-~j.
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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
Attachment Surry Power Station ASME Section XI Relief Request
Relief Request I.
Identification of Component Valve No, Line No.
Class 2-FW-142 6"-WAPD-103-601 3
(attached drawing)
II.
Impractical Code Requirement IWA-5214 of ASME Section XI, 1980 Edition, Winter 1980 Addendum, requires following a welded replacement, that a hydrostatic test (IWD-5223) be performed on the affected area.
Ill.
Basis For Relief Valve, 2-FW-142, is the 6 inch discharge check valve for the steam driven auxiliary feedwater pump, 2-FW-P-2. This valve prevents reverse flow, while operating one of the two other parallel auxiliary feedwater pumps. Valve, 2-FW-142, has experienced some internal leakage past the check valve disc. As a result of this internal leakage, replacement of the valve is being completed for this outage.
As is evident by the attached drawing, the upstream side of the valve, 2-FW-142, cannot be isolated during the required hydrostatic test from the auxiliary feedwater pump (2-FW-P-2), since no intermediate isolation exists, and the pump discharge piping is welded directly to the pump connection. Additionally, some of the suction piping will be included in the hydrostatic test boundary. The pump suction connection is a flange connection. However, using this flange for isolation purposes is considered difficult and undesirable due to the piping arrangement, and susceptibility to cold spring misalignment problems.
The IWD-5223 test pressure based on the design requirements of 2-FW-142 is 1576 psig. The inlet piping design pressure to pump, 2-FW-P-2, is only 150 psig. Conducting the required IWD-5223 test would result in overpressurization of the low pressure components.
IWA-5224(d) of ASME Section XI allows the use of the pressure "rating for the suction piping out to the first discharge shut-off valve in the case of centrifugal pumps during hydrostatic tests. Use of this paragraph in this application would require that only a 165 psig hydrostatic test be performed on this replacement.
Code committee personnel have indicated that a normal hydrostatic test (1576 psig) should be required for this replacement, and that the use of IWA-5224(d)
in this situation is not appropriate. As such, a relief request is needed due to the overpressurization concerns.
IV.
Alternate Requirements It is proposed that a volumetric and surface examination be performed on the new upstream weld of 2-FW-142 in lieu of a hydrostatic test. In addition, a system functional test (IWD-5222) and the corresponding visual (VT-2) examination of the replacement will be conducted during the normal Technical Specification operability test of pump 2-FW-P-2. The Code requirements will be met on the downstream weld of valve, 2-FW-142. These alternative requirements are the same as those proposed for the replacement of 1-FW-142, the discharge check valve for 1-FW-P-2 on Surry Unit 1, requested in our letter Serial No.90-761, dated December 10, 1990, and approved by your letter dated January 23, 1991.
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