ML20056F354
| ML20056F354 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/12/1993 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | Sieber J DUQUESNE LIGHT CO. |
| Shared Package | |
| ML20056F355 | List: |
| References | |
| TAC-M86503, NUDOCS 9308270023 | |
| Download: ML20056F354 (4) | |
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j' wasmnaron, o c. 2osss am August 12, 1993 Docket No. 50-412 3
Mr. J. 9 Sieber, Senior Vice President and utief Nuclear Officer Nuclear Power Division Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania 15077-0004
Dear Mr. Sieber:
SUBJECT:
BEAVER VALLEY UNIT 2 - RELIEF FROM CERTAIN ASME CODE REQUIREMENTS FOR TEMPORARY REPAIRS TO SERVICE WATER SYSTEM (TAC NO. M86503)
The purpose of this letter is to grant relief from ASME Code repair requirements for two 30-inch diameter expansion joints located in the service j
water system (SWS) of Unit 2.
A Code repair can not be performed without i
shutting the plant down because the repair would take longer than the time permitted by plant Technical Specifications for a SWS train to be out of service.
Your written request for relief, dated June 7,1993, has been reviewed by NRC staff, and the enclosed Safety Evaluation discusses our assessment and granting of relief.
i Section XI of the ASME Boiler and Pressure Vessel Code (hereafter called the Code) specifies Code-acceptable repair methods for flaws that exceed Code acceptance limits in piping that is in service. A code repair is required to restore the structural integrity of flawed ASME Code piping, independent of the operational mode of the plant when the flaw is detected.
Those repairs not in compliance with Section XI of the ASME Code are non-Code repairs.
However, the required code repair may be impractical for a flaw detected during plant operation unless the facility is shut down.
Pursuant to 10 CFR 50.55a(g)(6)(i), the Commission will evaluate determinations of impracticality, and may grant relief and may impose alternative requirements.
Relief was granted based upon the low leak rates involved, our discussion of the likelihood and consequences of further degradation, and the compensatory actions to which you agreed in telephone conversations on May 25 and 26, and June 2 and 3, 1993.
The compensatory actions included, for each leak:
installation of a restraining device to prevent separation of the joint if a 360 degrees failure should occur, a fiberglass / epoxy seal wrap around the leak, twice-a-day monitoring / recording / trending of the leak rates, agreement to call the NRC W either leak rate increased to one gallon per minute, visual monitoring of two similar but non-leaking expansion joints once per week, and agreement to perform a code repair of the two leaking expansion joints during the next scheduled 30-day outage but no later than the next refueling outage (scheduled to begin in September 1993.)
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Mr. J. D. Sieber August 12, 1993 We have reviewed the information Duquesne Light Company has provided in support of the relief requested in the June 7,1993, letter.
Based on this review, the staff concludes that performing Code repairs during power operation is impractical and that the proposed temporary repairs will provide reasonable assurance of the structural integrity of the two SWS leaking expansion joints. The staff has determined that granting relief, pursuant to 10 CFR 50.55a(g)(6)(i) is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Accordingly, the above identified relief request is hereby authorized, subject to the conditions detailed in the enclosed Safety Evaluation.
By this letter, we are closing TAC No. M86503.
Sincerely, Original signed by:
Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION:
' Docket File CMcCracken NRC & Local PDRs GHornseth PDI-3 Reading WLefave TEMurley/FMiraglia 0GC JPartlow EJordan ERossi GHill (2 copies)
JLieberman ACRS (10)
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DOCUMENT NAME: B:\\86503.REL
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1 Mr. J. D. Sieber August 12, 1993 We have reviewed the information Duquesne Light Company has provided in support of the relief requested in the June 7,1993, letter.
Based on this review, the staff concludes that performing Code repairs during power operation is impractical and that the proposed temporary repairs will provide l
reasonable assurance of the structural integrity of the two SWS leaking expansion joints. The staff has determined that granting relief, pursuant to 10 CFR 50.55a(g)(6)(1) is authorized by law and will not endanger life or property, or the common defense and security and is otherwise in the public j
interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Accordingly, the above identified relief request is hereby authorized, subject to the conditions detailed in the enclosed Safety Evaluation.
By this letter, we are closing TAC No. M86503.
Sincerely, a
Walter R. Butler, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page l
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l Mr. J. D. Sieber Beaver Valley Power Station Duquesne Light Company Unit 2 l
cc:
Jay E. Silberg, Esquire Bureau of Radiation-Protection Shaw, Pittman,,Potts & Trowbridge Pennsylvania Department of l
2300 N Street, NW.
Environmental Resources Washington, DC 20037 ATTN:
R. Barkanic Post Office Box 2063 Nelson Tonet, Manager Harrisburg, Pennsylvania 17120 Nuclear Safety l
Duquesne Light Company Mayor of the Borrough of l
Post Office Box 4 Shippingport i
Shippingport, Pennsylvania 15077 Post Office Box 3 Shippingport, Pennsylvania 15077 Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator, Region I Building 3, Room 319 U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road Charleston, West Virginia 25305 King of frussia, Pennsylvania 19406 John D. Borrows Resident Inspector Director, Utilities Department.
U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 181 180 East Broad Street Shippingport, Pennsylvania 15077 Columbus, Ohio 43266-0573 Director, Pennsylvania Emergency Management Agency Post Office Box 3321 Harrisburg, Pennsylvania 17105-3321 Ohio EPA-DERR ATTN:
Zack A. Clayton Post Office Box 1049 l
Columbus, Ohio 43266-0149 i
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