ML20033A979
| ML20033A979 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/17/1981 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20033A980 | List: |
| References | |
| 3F-1181-27, NUDOCS 8111300244 | |
| Download: ML20033A979 (4) | |
Text
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P...o..w...e..r November 17,1981 File: 3-0-3-e
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l Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission i
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Washington, D.C. 20555
Subject:
Crystal River Unit 3
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Docket No. 50-302
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Operating License No. DPR-72 Technical Specification Change Request No. 87
Dear Sir:
Encicsed are three (3) originals and forty (40) copies af Technical Specification Change Request No. 87, requesting an amendment to Appendix A of Operating License No.
This change deletes four hydraulic shock suppressors (snubbers) from Table 3.7-3 of the Crystal River Unit 3 Technical Specifications. These snubbers are not required to perform any safety related function.
Florida Power Corporation has determined that the requested action involves a Cisss ill amendment per CFR170.22. Accordingly, the license ice of four thousand ($4,000) dollars is enclosed.
Also enclosed is a signed copy of the Certificate of Service for Technical Specification Change Request No. 87 to the Chief Executive of Citrus County, Florida.
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Very truly yours, I
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[760,,,o Manager Nuclear Support Services Enclosures 8111300244 81111h PDR ALOCK 05000302 P
PDR General Office 3201 Tnirty-fourin street swin. P O. Box 14042. St Petersburg. Fionda 33733 e 813-866-5151
STATE OF FLORIDA COUNTY OF CITRUS i
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P.Y. Baynard states that she is the Manager, Nuclear Support Services, of Florida Power Corporation; that she is authorized on the part of said company to sign and file with the Nuclear Regulatory Co= mission the information attached hereto; and that
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all such statements made and catters set forth therin are true and correct to the best of her knowledge, information, and.
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- Subscribed and sworn to before me, a Notary Public in and for the State and. County above named, this /7 day of DS2r., 1981.
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Nots y Public, State of Florida at Large, j N NauC SWE & ROUDA At m MY COMMISSION DPikES OCT 16 1985 My Co= mission Expires:
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UNITED STATES OF AMERICA' NUCLEAR REGULATORY CO3NISSXON
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IN THE MATTER OF
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DOCKET'NO. 50-302-FI.ORIDA POWER CORPORATION
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w CERTIFICATE OF SERVICE P.Y. Baynard deposes and says '
the following has been served on the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follcws:
- Chairman, Board of County Co=issioners of Citrus County Citrus' County Courthouse Inverness, FL 32650.
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One (1) original copy of Technical Sp'ecificati6n Change Requ'st No. 87 requesting amendment to Appendix / of Operating License No. DPR-72.
FLORIDA POWER CORPORATION bhad P.Y. Yaybdrd, F4 niger uclear Support Servicas SWORN TO AND SUBSCRIBED BEFORE ME THIS O DAY OF M g, 1981.
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Notary Public State of Florida at Lerge-My Ccrission Expires:
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Technjcal Specification Change Request No. 87 Replace page 3/4 of 7-30 of Appendix A with revised page 3/4 7-30 of Appendix A.
Proposed Change Delete the following snubbers from Table 3.7-3:
MUH-86 MUH-87 MUH-88 MUH-89 Reason for Proposed Change During the cycle three refueling outage, all snubbers, except the four listed above, were removed from the reactor building and rebuilt. The four snubbers listed above are located in the letdown cooler room where there is a significant radiation field. In the interest of maintaining personnel radiation exposure as low as reasonably achievable, Florida Power Corporation elected to leave these snubbers in place. Since these snubbers were not e
functionally tested or rebuilt, their operability cannot be assured. Stress analyse:; on the piping to which snubbers are attached has shown that failure af the snubbers w.J not affect system operability.
Safety Evaluation Plant safety will not be compromised by the proposed change. Analyses performed by Florida Power Corporation's Architect-Engineer have shown that these snubbers are not-necessary to maintain functional integrity of the letdown cooler line during the DBE nr thermal cycling of the plant. The analyses were performed assuming the two cases of fully locked-up and totally ineffective snubbers. These are the worst case failure modes.
Neither failure analysis rcealed stresses which would cause a loss of functional integrity of the system.