ML19256B610
| ML19256B610 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/03/1979 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19256B614 | List: |
| References | |
| NUDOCS 7908130598 | |
| Download: ML19256B610 (1) | |
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DEisenhut Occket No. 50-302 Memo File MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation
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FROM:
Darrell G. Eisenhut, Acting Director Division of Operating Reactors
SUBJECT:
HEMPTION FOR CRYSTAL RIVER, UNIT NO. 3 REGARDING SMALL BREAK LOCA ISSUE By memoranduct' dated May 25, 1979, we informed you of the likely need to issue an exmption to allow CR-3 to restart on schedule.
We have approved Flcrida P6wer Corporation's (FPC) proposed modification for final resolution of the B&W ssall break analysis problem. Our letter of May 29, 1979, documents.our paview. By letter dated June 5, 1979 FPC supple-mentqd its exempti,co request by discussing the economic penalties associated with utring. installation prior to restart (See page 3 of the enclosed exemp b -In addition. FPC limited its proposed exec:ption to the period thre ust 6,1979.
Since the exemption will be effective for no more than seven weeks of operation.
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. minimizing potential canent fuel costs of up to 15 million dollars, and having made..the appro findings with respect to safetsy, we propose that
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Darrell G. Eisenhut, Acting Director Division of Operating Reactors
Enclosure:
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7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Florida Power Corporation, et al Docket No. 50-302
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Crystal River Unit No. 3, Nuclear
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Generating Plant
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EXEMPTION I.
Florida Power Corporation (licensee):and eleven other co-owners cre the holders of Facility Operating License No. DPR-72 which authorizes the operation of the nuclear power reactor known as Crystal River Unit No. 3 Nuclear Generating Plant (facility), at steady sta'.e reactor power levels not in excess of 2452 megawatts thermal (rated power). The facility consists of a Babcock & Wilcox (B&W) designed pressurized water reactor (PWR) located at the licensee's site in Citrus County, Florida.
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262 II.
In April 1978 it was detennined that the limiting small break loss of coolant accident (LOCA) for B&W 177 fuel assembly lowered loop plants was a break on the discharge side of a reactor coolant pump. For this break, assuming loss I
of off site power and the worst single failure, about 50% of the flow from one high pressure injection pump would be available to cool the core.
Calculations indicated that peak clad temperature might exceed the 2200 F 1imit.
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CR-3 was shutdown wnen this problem &
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June 14,1978 the licensee submitted of the CR-3 at rated power prior to -
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