ML20035G055
| ML20035G055 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/16/1993 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Hairston W GEORGIA POWER CO. |
| Shared Package | |
| ML20035G056 | List: |
| References | |
| TAC-M86197, NUDOCS 9304260084 | |
| Download: ML20035G055 (5) | |
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April 16, 1993 j
Docket Nos. 50-424 and 50-425 l
Mr. W. G. Hairston, III j
Senior Vice President -
Nuclear Operations i
Georgia Power Company
'P. O. Box 1295
. Birmingham, Alabama 35201 7
Dear Mr. Hairston:
/
SUBJECT:
REQUEST FOR TEMPORARY RELIEF FROM Ar,ME SECTION XI TO SOLDER PINHOLE IN CONTAINMENT COOLER TUBE, V0GTLE ELECTRIC' GENERATING PLANT, UNIT 1 (TAC M86197)
By letter dated April 16, 1993, Georgia Power Company (GPC) reported the discovery of a leak-from a f nhole in one of the small -(5/8-inch diameter) i copper-nickle tubes of containment cooler.1-1501-A7-001-000 for Vogtle Unit 1.
The discovery during the current refueling outage for Unit. I was by visual-observation of the leak as the associated pinhole.was too small.to be observed, even when liquid. penetrant. tested.. You found that repairing the '
leak'in accordance with the ASME Code requirements is not practical and'would impose a significant burden because the high heat associated uith brazing could adversely affect other brazed joints-in close proximity to the pinhole.
Therefore, you propose to seal the pinhole using-a' lead / tin solder-and reinforce the tube with a sleeve to further ensure' it's _ integrity. You also-propose to monitor for potential leakage in accordance with plant procedures and Technical Specifications.
The containment cooler was manufactured to theLrequirements~of'the 19727 edition of the American Society of Mechanical Engineers -(ASME) Boiler 'and -
Pressure' Vessel Code,Section III, with addenda through.. Winter.1977'and is a
- Class.' component..You note that the proposed corrective action;does not meeti the repair and replacement requirements 1of Article'IWA-4000 of' ASME Code,Section XI.,However, you have concluded-that these code-requirements are n'ot-practical and that soldering,: sleeving,- and monitoring as proposed, is
- currently the only practical: option available..-Therefore, you requested our -
approval in-accordance with 10 CFR 50.55a(g)(6)(1). You also committed to:
perform a Code repair!or. other long term resolution during the next' l
maintenance / refueling od. age.
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Mr.'W. G. Hairston,
The enclosed Safety Evaluation provides the results of the NRC staff's review of your request for temporary relief. The relief is granted until completion nf your stated connitment to perform a Code repair or other long term resolution during the next maintenance / refueling outage (currently scheduled l
for fall 1994).
Should you find that relief needs to be continued beyond the next maintenance / refueling outage, you must provide a relief request with adequate information to support the relief requested.
Based on our evaluation of your relief request, we have determined that imposing the applicable provisions of Section XI of the ASME Code would be impractical.
The requested relief is granted, as stated above, and is authorized by law and will not endanger the common defense and security and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, the temporary relief request is granted pursuant to 10 CFR 50.55a(g)(6)(i).
Sincerely, 1
David B. Matthews, Director Project Directorate 11-3 l
Division of Reactor Projects - I/II
'l Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION See next page
- SEE PREVIOUS CONCURRENCE LA:PDI[ ) PM:PDII-3 OGC*
D:PDII-3 EMCB*
LBerry/l DHoodjD5y DMatthewf$F RHerman 04/Kf/93 04/f3/93 04/16/93 04/g/93[3 4/16/93 l
OFFICIAL RECORD COPY Document Name: FanCool.RR L
Mr. W. G. Hairston April 16, 1993 The enclosed Safety Evaluation provides the results of the NRC staff's review of your request for temporary relief. The relief is granted until completion of your stated commitment to perform a Code repair or other long term resolution during the next maintenance / refueling outage (currently scheduled for fall 1994).
Should you find that relief needs to be continued beyond the next maintenance / refueling outage, you must provide a relief request with adequate information to support the relief requested.
Based on our evaluation of your relief request, we have determined that imposing the applicable provisions of Section XI of the ASME Code would be impractical. The requested relief is granted, as stated above, and is authorized by law and will not endanger the common defense and security and is other.,ise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, the temporary relief request is granted pursuant to 10 CFR 50.55a(g)(6){i).
Sincerely, KJa=, Al fW~ %
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
)
See next page
--_______-.__________z
...... j
Mr. W. G. Hairston April 16, 1993 The enclosed Safety Evaluation provides the results of the NRC staff's review of your request for temporary relief. The relief is granted until completion of your stated commitment to perform a Code repair or other long term resolution during the next maintenance / refueling outage (currently scheduled for fall 1994). Should you find that relief needs to be continued beyond the next maintenance / refueling outage, you must provide a relief request with adequate information to support the relief requested.
Based on our evaluation of your relief request, we have determined that imposing the applicable provisions of Section XI of the ASME Code would be impractical. The requested relief is granted, as stated above, and is authorized by law and will not endanger the common defense and security and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, the temporary relief request is granted pursuant to 1
Sincerely, h5 Y f
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
Jee next page 1
Mr. W. G. Hairston, III Georgia Power Company Vogtle Electric Generating Plant cc:
Mr. J. A. Bailey Harold Reheis, Director Manager - Licensing Department of Natural Resources Georgia Power Company 205 Butler Street, SE. Suite 1252 P. O. Box 1295 Atlanta, Georgia 30334 Birmingham, Alabama 35201 Attorney General Mr. W. B. Shipman Law Department General Manager, Vogtle Electric 132 Judicial Building
~
Generating Plant Atlanta, Georgia 30334 P. O. Box 1600 Waynesboro, Georgia 30830 Mr. Alan R. Herdt Project Branch #3 Regional Administrator, Region II U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 101 Marietta Street, NW., Suite 2900 Atlanta, Georgia 30323 Atlanta, Georgia 30323 Mr. Dan H. Smith, Vice President Office of Planning and Budget Power Supply Operations Room 615B Oglethorpe Power Corporation 270 Washington Street, SW.
2100 East Exchange Place Atlanta, Georgia 30334 Tucker, Georgia 30085-1349 Mr. C. K. McCoy Charles A. Patrizia, Esquire Vice President - Nuclear Paul, Hastings, Janofsky & Walker Vogtle Project 12th Floor Georgia Power Company 1050 Connecticut Avenut NW.
P. O. Box 1295 Washington, DC 20036 Birmingham, Alabama 35201 Art Domby, Esquire Mr. R. P. Mcdonald Troutman, Sanders Executive Vice President -
600 Peachtree Street Nuclear Operations NationsBank Plaza Georgia Power Company Suite 5200 P. O. Box 1295 Atlanta, Georgia 30308-2710 Birmingham, Alabama 35201 Resident Inspector-
-Office of the County Commissioner U. S. Nuclear Regulatory Commission Burke County Comission P. O. Box 572-Waynesboro, Georgia 30830 Waynesboro, Georgia 30830 i
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t RELIEF REQUEST'- V0GTLE UNIT 1 DATED:
APR 16'1993 '
DISTRIBUTION
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Docket File NRC/ Local PDRs i.
PDIl-3 Reading Vogtle Reading i
S. Varga 14El G. Lainas 14H1 D. Matthews 14H25 i
L. Berry 14H25 D. Hood 14H25 OGC 15B18 E. Jordan NMBB3302 ACRS (10)
P-315 R. Herman 7D4 J. Strosnider 704 J. Davis 7D4 i
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