ML20049J044
| ML20049J044 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/24/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20049J045 | List: |
| References | |
| NUDOCS 8203110420 | |
| Download: ML20049J044 (3) | |
Text
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AMR 0 Vice President - t;uclear Operations G 8 g g.Iy bo -
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Post Office Box 26666 TBarnhart-8 aD Richmond, Virginia 23261 ACRS-10 g
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Dear fir. Leasburg:
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SUBJECT:
RELIEF FROM HYDROSTATIC TESTING REQUIRENENlS Iti ACCORDANCE WITH 10 CFR 50.55a,(t;)l5))FOR THE NORTH ANNA POWER STATION, UNITS i:0. 1 & 2 (NA-l&2)
We have reviewed your letter dated January 20,1982 (Serial No. 024);
which innaccordance with 10 CFR 50.55a, pagagraph g(5); requested relief from the requirements of ASME,Section XI, for performing hydrostatic tests at NA-1&2. The bases for your request and our conclusions regarding relief are stated below.
During plant operations at NA-1, a steam leak developed on a two-inch socket and globe valve (Mark Number 1-80-13) which is the first manual isolation of the Steam Generator Blowdown System on "B" steam generator.
The steam leak will eequire the replacement of the corponents involved and this work is scheduled to be conducted during the forthcoming NA-1 refueling cutage.
Steam generator B, as well as all NA-1 steam generators, has already been subjected to three hydrostatic tests. Only five such testecycles are designed into the steam generators for NA-l&2. Valve 1-B0-13 is a Class 3 valve and requires a liquid penetrant examination of the completed weld and a hydrostatic test at the corpletion of valve repatrd. The locations of the welded joints (two total) are unisolable from steam generator 8 and thus a complete secondary hydrostatic test would be required.
In order to reduce the number of hydrostatic tests performed on steam generator "B", you have proposed a liquid penetration examination of each wild layer, including the root pass, and a subsequent leakage test at operating pressure during Mode 3 (Hot Standby) operations.
During plant operations at NA-2, a steam leak developed ai a three inch butt weld check valve (Nark number 2-FW-134) which is part of the Auxiliary Feedwater System (AFS) and whose function is a containment isolation check valve in the line leating to "C" steam acnerator. The steam leak will require the replaccoent of components involved and this replacement is scheduled during the forthcoming NA-2 outage.
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Steam generator "C" has already been hydrostatically tested twice. Valve 2-FW-134 is a Class 2 valve and requires radiographic and hydrostatic prs:;sure test after repair welding. The location of the welded joints is unisolable from steam generator "C" and also would require a comlete secondary hydrostatic test. Therefore, you have proposed an examination of valve 2-Fil-134 which includes a radiographic and ultrasonic test supplemented by a leakage test at operating pressure during f! ode 3 operations.
Based on the above, we conclude that in the case of ftA-1 the augmented liquid penetrant examination supplemented by the leakage test will provide adequate assurance of the integrity of the Stean Generator Blowdown System welds and these methods are acceptable.
For flA-2, we conclude the use of the two methods of examination supplemented by the leakage test will provide adequate assurance of the integrity of the AFS welds and these methods are acceptable.
Therefore, relief is hereby granted from the requirements of ASME,Section XI for hydrostatic tests at both NA-l&2 as srecified in your letter dated January 20, 1932.
We have determined that the inspection from which relief is sought is inpractical and pursuant to 10 CFR 50.55a(g)(6)(1) that the granting of this relief is authorized by law and will not endanger life or property, cr the cor.non defense and security, and is otherwise in the public interest.
In naking this determination we have given due consideration to the burden that could result if these requirements were imposed on your facility. We have determined that the granting of this relief does not involve a signifi-cant increase in the probability or consequences of an accident nor a significant decrease in a safety margin and thus does not involve a significant hazards consideration. Furthermore, we have determined that the granting of this relief from ASME Code requirements does not authorize a change in effluent types or total amounts nor an increase in poder level and will not result in any significant envirmeental impact. We have concluded that the granting of this relief is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 51.5(d)(4) that neither an environmentJ impact statement nor a negative declaration and environmental impact appnisal needs to be prepared in connection with this action.
Sincerely, Original signed by Robart A. Clark Robert A. Clark, Chief Operating Reactors Branch ill3 Division of Licensing
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Richard M. Foster, Esquire Mr. James Torson 501 Leroy Musick, Williamson, Schwartz, Leavenworth & Cope, P.C.
Socorro, New Mexico.87891 P. O. Box 4579 Boulder, Colorado 80306 Mrs. Margaret Dietr.ich Route 2, Box 568 Michael W. Maupin, Esquire Gordonsville, Virginia 22042 Hunton, Williams, Gay and Gibson j
P. O. Box 1535 fir. James C. Dunstance Richmond, Virginia 23212 State Corporation Commission i
Commonwealth of Virginia Alderman Library Blandon Building
,4 11anuscripts Department Richmond, Virginia 23209 University of Virginia e
Charlottesville, Virginia 22901 Mrs. June Allen North Anna Environmental Coalition Mr. Edwar.d Kube 87201.ockmoor Circle Board of Supervisors Wichita, Kansas 67207 Louisa County Courthouse P. O. Box 27 U.S. Environmental Protection Agency Louisa, Virginia 23093 Region III Office ATTN:
Regional Radiation Representative Ellyn R. Weiss, Esquire Curtis Building Sheldon, Harman, Roisman and Weiss 6th and Walnut Streets 1725 I Street, N.W. Suite 506 Philadelphia, Pennsylvania 19106 Washington, D. C.
20006 Mr. Paul W. Purdon Mr. W. R. Cartwright, Station Manager Environmental Studies Institute P. O. Box 402 Drexel University Mineral, Virginia 23117 32nd and Chestnut Streets-Philadelphia, Pennsylvania 19104 Mr. Anthnny Ganbardella Office of the Attorney General Atomic Safety and Licensing 11 South 12th. Street - Room 308 Appeal Board Panel Richmond, Virginia 23219 U.S. Nuclear Reg.ulatory Commission Washington, D. C.
20555 i
Resident Inspector / North Anna Regional Admini'trator s
c/o U.S.N.R.C.
Nuclear Regulatory Commission, Region II Route 2, Box 78A Office of Inspection an.d Enforcement Mineral, Virginia 23117 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. J. H. Ferguson Executive Vice President - Power Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 e
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