ML19248D681
| ML19248D681 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/23/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19248D683 | List: |
| References | |
| NUDOCS 7908170170 | |
| Download: ML19248D681 (5) | |
Text
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- o UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASittNGTON, D. C. 20556 g?
J' FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEES 8URG 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 tat.LAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 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 July 13, 1979, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules ard regulations set forth in 10 CFR Chapter I; B.
The facility will acerata in conformity with the application, the provisions of the Act, and the rules and regulations of the Commissicn; 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 issuar.ce of this amendment will not be inimical to the commen 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 ? art 51 of the Ccmmissicn's regulations and all acclicable requirement:
have been satisfiec.
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7908170(76
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Accordingly, the license is amended by changes to the Technic al 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. 22, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY CONiISSION obert W. Reid. Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: July 23, 1979
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ATTACHMENT TO LICENSE AMENDMENT NO.
22 FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO.~50-302 Replace the following pages of Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
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DEEGENCY CCRE COOLING SYSTD45 SURVEILLANCE REOUTREu!NTS (Continued) 2.-
Verifying the correct position of each r.echanical position stop for each of the stop check valves listed in Specification 4.5.2.c.
3.
Verifying that the flow switches sr the throttle valves listed in Specification 4.5.2.c operate properly.
4.
A visual inspection of the contairenent emergency sump which verifies that the sutsystec suction inlets are not restricted by debris and that the se p cceponents (trash racks, screens, etc.) show no evidence of structural i
distress or corrosion.
S.
Verifying a total leak rate 1 6 gallons per hour for the LPI system at:
a)
Nomal operating pressure or a hydrostatic test pressure of > 150 psig for those parts of the system downstrea= oT the pu=p suction isolation valve, and b)
> 55 psig for the piping frce the contairment
--emergency step isolation valve to the ptcp suction isciation valve, f.
At least once per 18 maths, during shutdewn, by 1.
Verifying that each autceatic valve in the flow path actuates to its correct position on a high pressure er low pressure safety injection test signal, as apprcpriate.
2.
Verifying that each HPI and LPI pu=c test starts auto-matica11y upon receipt of a high pressure or low pressure safety injection test signal, as appropriate, Following completion of HPI or LPI s altered system flow characteristics,jv tem modifications that could have g.
J by performance of a flow balance test during shutdown to confirm the following injection flow rates into the Reactor Coolant System:
HPI System - Singla Pumo LPI System - Sinale Pumo Single pump flow rate > 500 gpm 1.
Injection Leg A - 2800 to at 600 psig 3100 gpm While injecting through 4 Injection Legs, 2.
Injection Leg B - 2S00 to the flow rate for all combinations 3100 gpm of 3 Injection Legs > 350 gpm at 600 psig CRYSTAL RIVER - UNIT 3 3/4 5-5
.'j Flow balance tests performed prior to complate installation of modi #ications are valid if performed with the system charge that could alter flow charac-l teristics in efftct.
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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T;y < 280*F
, LIMITING CONDITION FOR OPLRATION j
3.5.3 As a minimum, one ECCS subsystem con: prised of the following ha11 be OPERABLE:
a.
One OPERABLE high pressure injection (HPI) pump, b.
One OPERABLE low pressure injection (LPI) pump, c.
One OPERABLE decay heat cooler, and
- d.. An OPERABLE flow path capable of taking suction from thq t
t borated water storage tank (SWST) and transferring suction to the containment emergency sump.
' APPLICABILITY: MODE 4.
ACTION:
a.
With no ECCS subsystem 0PERABLE because of the inoperability of eithr the HPI pump or the flow path frcm the borated water sto age tank, restore at least one ECCS subsystem to CPERABLE str.us within one hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
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b.
With no ECCS subsystem OPERABLE because of the inoperability of either the decay heat cooler or LPI pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T less than 280*F by use of alternate heat removal methods. avg c.
In the event the ECCS is actuated and injects water into the reactor coolant system, a Special Report shall be prepared and sut:mitted to the Ccenission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accu =ulated actuation cycles to date.
SURVEILLANCE REOUIREMENTS
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4.5.3 The ECCS subsystems shall be de:renstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.
3l CRYSTAL RIVER - UNIT 3 3/454 A
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