ML18153C470
| ML18153C470 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/10/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-761, NUDOCS 9012140015 | |
| Download: ML18153C470 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 10, 1990 Uriited States Nuclear Regulatory Commission AttEfrition: Document Control Desk Washfngton, D. C. 20555 Serial No.90-761 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 NO/ETS Docket Nos.
50-280 License Nos. DPR-32 INSERVICE INSPECTION PROGRAM RELIEF REQUEST ASME SECTION XI HYDROSTATIC PRESSURE TEST Pursuant to 1 O CFR 50.55a paragraph g(5), relief is requested from certain requirements identified in ASME Section XI, 1980 Edition, Winter 1980 Addenda for one ASME Class 3 valve. The following basis is provided.
Surry Unit 1 is currently completing its 1990 refueling outage.
Due to extensive modifications and the Auxiliary Feedwater System Technical Specification cross-tie operability requirements, the Auxiliary Feedwater System modifications and testing could not be completed until late in the outage.
During hydrostatic testing of the recently completed modifications on the Auxiliary Feedwater System, excessive internal back leakage was identified on check valve, 1-FW-142. To eliminate this back leakage the decision was made to replace the 6 inch discharge check valve for steam driven auxiliary feedwater pump (1-FW-P-2).
IWA-5214 of ASME Section XI requires, following replacement welding, that a hydrostatic test (IWD-5223) be performed with a corresponding VT-2 examination on the affected area. As no intermediate isolation exists and because the discharge piping is welded directly to the pump, the required test on the upstream weld would include 1-FW-P-2 (steam driven auxiliary feedwater pump) and the associated suction piping within the hydrostatic test boundary. This would result in over pressurization of these components to meet the test requirements (IWD-5223 test pressure: 1576 psig, suction piping design pressure: 30 psig).
Alternatively, it is proposed that a volumetric examination and a surface examination be performed on the new upstream weld in lieu of the hydrostatic test. In addition, a system functional test (IWD-5222) and its corresponding VT-2 examination will be conducted in conjunction with the normal Technical Specification required operability test for 1-FW-P-2.
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c 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 code paragraph in the application would eliminate the need for this relief request as test pressure would only be 33 psig for the replaced welds. Code committee personnel have indicated that this is a code oversight and that future code editions will change the requirements for high pressure multi-stage centrifugal pumps. As such, it is our position that a relief request is necessary. The proposed alternatives are consistent with similar relief requests which have been granted (e.g., Serial No.89-636, dated August 2, 1989, and approved on October 2, 1989, for Surry Unit 2).
It is our position that the proposed alternatives provide the necessary inspection intended by the code. We request your review and approval of this relief request by December 15, 1990 to support Unit 1 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, J)~
W. L. Stewart Senior Vice President - Nuclear cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station