ML20237B550
| ML20237B550 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/11/1987 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML19302D177 | List: |
| References | |
| NUDOCS 8712160342 | |
| Download: ML20237B550 (2) | |
Text
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December 11, 1987 Docket No. 50-338 ENCLOSURE 1 CONTAINS PROPRIETARY INFORMATION TO BE WITHHELD FROM Mr. W. L. Stewart PUBLIC DISCLOSURE PURSUANT TO Vice President - Nuclear Operations 10 CFR 2.790 Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261
Dear Mr. Stewart:
SUBJECT:
PROPRIETARY SAFETY EVALUATION (SE) FOR OPERATION AT l
100% POWER FOR NORTH ANNA POWER STATION, UNIT NO. 1 (NA-1) l REGARDING STEAM GENERATOR TUBE RUPTURE (SGTR) ON JULY 15, 1987 We have completed our review of your letters dated September 15 and September 25, 1987 regarding the NA-1 SGTR (July 15, 1987).
Included in our review was the Westinghouse Electric Corporation Report, " North Anna Unit 1 Steam Generator Tube Rupture and Remedial Actions Technical Evaluation," dated September 1987.
As stated in the enclosed proprietary SE, we find that you have (1) adequately l
demonstrated the primary failure mechanism leading to the July 15, 1987 SGTR I
event was fatigue caused by flow-induced vibration, (2) adequately identified the major causal factors leading to this event, and (3) implemented acceptable diagnostic and corrective measures to prevent a similar fatigue failure in the future.
In addition, we have reviewed the results of operation at 50%
power with respect to SG integrity and find it to be acceptable.
Our findings, as stated above, were stated in our November 5, 1987
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Confirmatory Action Letter allowing NA-1 to operate at 100% percent of licensed power.
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i A non proprietary version of the SE is being provided to the service list and l
the Public Document Rooms.
Sincerely, 4
1 Original signed by B712160342 871211 PDR ADOCK 05000338 Leon B. Engle, Proj.ect Manager 5
PDR Project Directorate II-2 l
Division of Reactor Projects-I/II I
Office of Nuclear Reactor Regulation
Enclosures:
1.
Proprietary Safety Evaluation ENCLOSURE 1 CONTAINS PROPRIETARY 2.
Non-Proprietary Safety Evaluation INFORMATION TO BE WITHHELD FROM PUBLIC DISCLOSURE PURSUANT TO l
cc w/Non-Proprietary Safety Evaluation:
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$ PpR NRC & Local PDRs L. Engle 1042/ beb hg~ M E. Murphy H. Berkow T. Murley D. Miller R. Starostecki OGC-Bethesda L. Shao J. Partlow A. Thadani E. Jordan F. Miraglia ACRS (10)
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S. Varga G. Lainas N. Grace, R-II L. Reyes, R-II F. Cantrell, R-II J. Caldwell, Resident Inspector 4
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