ML20069M583
| ML20069M583 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/17/1982 |
| 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 | |
| ML20069M586 | List: |
| References | |
| TAC 49036, DPR-72-A-059 NUDOCS 8212010164 | |
| Download: ML20069M583 (4) | |
Text
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o UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555
'g
,o FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.59 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated October 26, 1982, complies with the 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; i
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B.
The facility will operate in conformity with the application, the l
provisions of the Act, and the rules and regulations of the Comission; 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 Commission'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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all appifcable requirements have been l
satisfied.
em 8212010164 821117 PDR ADOCK 05000302 p
2-2.
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. 59, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment became effective October 26, 1982.
FOR THE NUCLEAR REGULATORY COMMISSION
. o n F. Stolz, Chief /
Operating Reactors B p ch #4 t
vision of Licensing
Attachment:
Changes to the Technical Specifications i
(
Date of Issuance: November 17, 1982 l
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ATTACHMENT TO LICENSE AMENDhENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace page 3/4,6-15'of the 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.
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CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, either:
a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affe-ted penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated aulomatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
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 SHUTDOW'N within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
e.
The provisions of Specification 3.0.4 are not applicable for Main Stean Isoletion Valves MSV 411, 412, 413 and 414.
f.
The provisions of Specification 3.0.4 are not applicable for the remainder of Cycle IV for Intennediate Pressure Relief Line Isolation Valve, WDV-60.
SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after mainten-ance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.
1 CRYSTAL RIVER - UNIT 3 3/4 6-15 Amendment Nu. #, 59 l
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continuad) 4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
Verifying that on a containment isolation test signal, each a.
automatic isolation valve actuates to its isolation position.
b.
Verifying that on a containment radiation-high test signal, each purge and exhaust automatic valve actuates to its '
isolation position.
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' YSTAL F:.E:
UNIT 3 3/4 6-16
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