ML20141M895
| ML20141M895 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/23/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Florida Power Corp, City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, Utilities Commission, City of New Smyrna Beach, FL, City of Ocala, FL, City of Orlando, FL, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative, City of Tallahassee, FL |
| Shared Package | |
| ML20141M896 | List: |
| References | |
| DPR-72-A-085 NUDOCS 8603030024 | |
| Download: ML20141M895 (4) | |
Text
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UNITED STATES g
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WASHINGTON D. C. 20555
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' FLORIDA POWER CORPORATION
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' CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRPA BEACH AND UTILITIES C0 MISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLAND~0 UTILITIES COMMISSION AND CITY OF ORLANDO SEB)!NG UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-307 CRYSTAL RIVEp UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-72 1.
The Nuclear Regulatory Ccmmission (the Comission) has found that:
A.
The application for amendment by Florica Power Corporation, et al.
(the licensees) dated November 17, 1981, complies with the standards e
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 Comission; C.
There is reasonable assurar:ce (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, ard (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 enmon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licensk amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGUL TORY COMMISSION Joh
. Stn1z, Director PJW Project Directorate #6 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 23, 1986 e
r-ATTACHMENT TO LICENSE AMENDMENT NO. 85 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET h0. 50-302 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE I
LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, 1 GPM total primary-to-secondary leakage through steam generators, c.
d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, 12 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of e.
3L 2150 t 20 psig, and f.
Leakage as specified in Table 3.4-2 for those Reactor Coolant System Pressure Isolation Valves identified in Table 3.4-2.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
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With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within a.
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 B0UNDARY LEAKAGE, reduce the leaktge 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 e
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, With any Reactor Coolant System Pressure Isolation Valve leakage c.
greater than the above limit, reactor operation may continue provided that at lecst two valves in each high pressure line having a non-functional valve are in, and remain in, the mode corresponding to the isolated condition.
(Motor operated valves shall be placed in the closed position and power supplies deenergized.)
l d.
The provisions of Section 3.0.4 are not applicable for entry into MODES 3 and 4 for the purpose of testing the isolation check valves.
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