ML20235K905
| ML20235K905 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/16/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235K908 | List: |
| References | |
| NUDOCS 8902270296 | |
| Download: ML20235K905 (4) | |
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UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
h WASHINGTON, D. C. 20555
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30RIDAPOWERCORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE 1
CITY OF KISSIMMtE CITY OF LEE 5 BURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SHYRNA BEACH CITY OF OCALA ORLANDO UTILITIES CUifiT55TUTAlto CITY OF ORLANDO SEBRING UTILITIES COPMI5510M SEMINOLE ELECTRIC COOPERATIVE, INC,
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CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER U, NIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 i
License No. DPR-72 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated April 15, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)..
and the Comission'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 assurance (1) 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 con 6 cted 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 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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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:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.110, are hereby incorporated in the license.
Florida Power Corporation shall operdte the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
% LL rbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 16, 1989
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ATTACHMENT TO LICENSE AMENDMENT NO.110 FACILITY OPERATING LICENSE NO. DpR-72 DOCKET NO. 50-302 I
i Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised p6ge is identified by amendment number and contains vertical liner. indicating the ared of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Insert 3/45-5 3/4 5-5 i
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DIERGENCY CORE COOLING SYSYERS SURVEILIARCE REQUIREMENTS (continued) l ;
2.., < Verifying the correct position of each mechanical position stop for l
each of the stop check valves listed in Specification 4.5.2.c.
3.
Verifying that the flow controllers for the throttle valves listed in Specification 4.5.2.d. operate properly.
4.
A visual inspection of the containment emergency sump which verifies that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence i
of structural distress or corrosion.
l 5.
Verifying a total leak rate less than or equal to 6 gallons per hour for the LPI system at:
a)
Normal operating pressure or a hydrostatic test pressure of greater than or equal to 150 psig for those parts of the system p
downstream of the pump suction isolation valve, and i
b)
Greater than or equal to 55 psig for the piping from the contain-ment emer']ency sump isolation valve to the pump suction isolation valve.
f.
At least once per 18 months during Mode 3, 4, 5, or 6, by 1.
Verifying that each autcmatic valve in the flow path actuates to its correct position on a high pressure or low pressure safety injection test Lignal, as appropriate.
2.
Verifying that each HpI and LpI pump starts automatically upon receipt of a high pressure or low pressure safety injection test signal, as appropriate.
l g.
Following completion of HpI or LpI system modifications that could have altered system flow characteristics 1,
by performance of a flow balance test during shutdown to confirm the following injection flow rates into the Reactor Coolant System:
HPI System - Sinole Pumo2 LpI System - Sinale Pugg Single pump flow rate greater than or 1.
Injection Leg A -
equal to 500 gpm at 600 psig.
2800 to 3100 gpm.
While injecting through 4 injection Legs, 2.
Injection Leg B -
the flow rate for all combinations of 3 2800 to 3100 gpm.
Injection Legs greater than or equal to 350 gpm at 600 psig.
j 1 Flow balance tests performed prior to complete installation of modifi cations are valid if performed with the system change that could alter flow characteristics in effect.
2 The HPI Flow Balance Test shall be performed in MODE 3.
Crystal River - Unit 3 3/4 5-5 Amendment No. 72,77, 79,93, 110
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