ML19309H313
| ML19309H313 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/18/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19309H314 | List: |
| References | |
| NUDOCS 8005130036 | |
| Download: ML19309H313 (5) | |
Text
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15 FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF XISSIMMEE CITY OF LEESBURG CITY OF HEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET N0. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applic cion for amendment by Florida Power Corporation, et al (thelicensees)datedMarch 17, 1978, complies with tne standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth-in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and t
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 30, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
==
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors l
Attachment:
Changes to the Technical 1
Specifications Date of Issuance:
April 18, 1980 6
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ATTACHf1ENT TO LICEf!SE hMENDMENT NO. 30
~
FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302 Replace the following page of Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
3/4 4-16 4
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l REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE O
LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE B0UNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
1 GPM total primary-to-secondary leakage through steam gen-erators, and d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and e.
10 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2150 + 20 psig.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
a.
With any PRESSURE B0UNDARY LEAKAGE, be in at least H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a.
Monitoring the containment atmosphere iodine radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, CRYSTAL RIVER. UNIT 3 3/4 4-15
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