ML20101F262
| ML20101F262 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/19/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20101F266 | List: |
| References | |
| C311-92-2072, NUDOCS 9206240353 | |
| Download: ML20101F262 (3) | |
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GPU Nuclear Corporation
- g gp Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number.
717-948-8005 June 19, 1992 C311-92-2072 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station Unit 1, (TMI-1)
Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Request No. 217 Reactor Coolant Pump Snubber Operability In accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request (TSCR) No. 217.
Also enclosed is the Certificate of Service for this request certifying service to the cnief executives.of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.
The purpose of this TSCR is to request a temporary change to exclude Reactor Coolant Pump Snubber RC-U-003 from the operability requirements of Technical Specification Section 3.16.
Approval of this will provide a contingency action to be invoked in the event that the present periodic maintenance efforts fail to maintain the snubber in an operable condition during the current operating cycle. This change is to be in effect until inspection and repair of Snubber RC-U-003 hydraulic fluid leakage can be completed during the earliest outage of opportunity or refueling outage 10R, whichever occurs first.
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GPU Nuclear Corpora 5cn is a sLescan of Ger w puboc UW.es Co poranon
June 19, 1992
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C311-92-2072 Page 2 Pursuant to 10 CFR 50.91(a)(1), enclosed is an analysis applying the standards in 10 CFR 50.92 to make a determination of no significant hazards considerations. As stated above, pursuant to 10 CFR 50.91(a), we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to William P. Dornsife, the designated representative of the Commonwealth of Pennsylvania.
Sincerely,
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T. G. Broug ton Vice President and Director, TMI-l l
DJD/amk
Enclosures:
(1)
Technical Specification Change Request No. 217 (2)
Certificate of Service for Technical Specification Change Request No. 217 cc: Administrator, Region I TMI-1 Senior Resident Inspector THI-l Senior Project Manager 1
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET N0. 50-289 GPU NUCLEARLCORPORATI0t:
LICENSE N0. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. 217 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphh County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of - Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr.' Jay H. Kopp, Chairman-Mr. Russell L. Sheaffer, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown. PA 17057 Harrisburg,-PA 17120 Mr. William P. Dornsife, Acting Director PA. Dept. of Environmental Resources Bureau of Radiation Protection l
P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION BY:
b' Vice Presiden and Director, TMI-l June 19, 1992 DATE: _
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