ML18153B023
| ML18153B023 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/25/1994 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-391, NUDOCS 9408020085 | |
| Download: ML18153B023 (7) | |
Text
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PRIORITY 1 a.ccELERATED RIDS PROCESSING)
- REGULATO., INFORMATION DISTRIBUTION WSTEM (RIDS)
ACCESSION }JBR: 9 4080 2 008 5 DOC, DATE: 9 4/07 /2 5 NOTARI ZED: NO FACI~\\50-281 Surry Power Station, Unit 2, Virginia Electric & Powe AUTH.NAME AUTHOR AFFILIATION O'HANLON,J.P.
Virginia Power (Virginia Electric & Power Co.)
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards request for relief from requirements of ASME Section XI,1989 Edition re hydrostatic pressure testing of Valve 2-FW-172.
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 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 NO. 2 INSERVICE INSPECTION PROGRAM RELIEF REQUEST FROM ASME SECTION XI HYDROSTATIC PRESSURE TEST Serial No.94-391 NO/ETS Docket No.
50-281 License No.
DPR-37 During routine testing of Auxiliary Feedwater System check valves, internal leakage was identified through 2-FW-172. Valve and system operability were evaluated with the identified leakage and it was determined that the Auxiliary Feedwater System remains operable. Although the Auxiliary Feedwater System remains operable, it is our intention to replace 2-FW-172 during the next refueling outage that is currently scheduled to start in January 1995.
In accordance with the Code, a post replacement hydrostatic test is required.
However, the test boundary would include the low pressure suction side of the auxiliary feedwater pump causing an overpressure concern. Therefore, pursuant to 1 O CFR 50.55a(g)5, relief is requested from certain Code requirements identified in ASME Section XI, 1989 Edition for thisSection XI Class 3 valve replacement.
Provided for your approval in the following attachment is the basis for our request.
Resolution of this request is necessary prior to the Surry Unit 2 start-up.
If you have any questions concerning this request, please contact us.
Very truly yours,
~cw<;)(}#~~
7a;es P. O'Hanlon Senior Vice President - Nuclear Attachment
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9408020085 940725 PDR ADOCK 05000281
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cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station
e Attachment Surry Power Station ASME Section XI Relief Request
L___
e RELIEF REQUEST I.
Identification of Component Va!Ye #
Woe#
2-FW-172 4"-WAPD-107-601 (see attached drawing)
II.
Impractical Code Requirement Class 3
IWA-5214 of ASME Section XI, 1989 Edition, requires following a welded replacement, that a hydrostatic test (IWD-5223) be performed on the affected area.
Ill.
Basis For Relief Valve, 2-FW-172, is the 4 inch discharge check valve for the motor driven auxiliary feedwater pump, 2-FW-P-38. This valve prevents reverse flow, while operating one of the two other parallel arranged auxiliary feedwater pumps.
Valve, 2-FW-172, has experienced some internal leakage past the check valve disc. As a result of this internal leakage, the replacement of the valve has been scheduled for the next refueling outage.
As is evident by the attached drawing, the upstream side of the valve, 2-FW-172, cannot be isolated from the auxiliary feedwater pump (2-FW-P-38) during the required hydrostatic test, since no intermediate isolation exists, and the pump* discharge piping is welded directly to the pump discharge 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 due to the piping arrangement and undesirable due to susceptibility to cold spring misalignment problems.
Furthermore, the IWD-5223 test pressure based on the design requirements of 2-FW-172 is 1576 psig. The inlet piping design pressure to pump, 2-FW-P-38, is only 150 psig. Conducting the required IWD-5223 test would result in overpressurization of these 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-172 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-38. The Code requirements will be met on the downstream weld of valve, 2-FW-172.
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 NRC letter, dated January 23,.1991, and for the.replacement of 2-FW-142, the discharge check valve for 2-FW-P-2 on Surry Unit 2, requested in our letter serial No.93-158, dated March 29, 1993, and approved by NRC letter, dated April 13, 1993.
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