ML20215L573
| ML20215L573 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/21/1986 |
| 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 | |
| ML20215L576 | List: |
| References | |
| DPR-72-A-093 NUDOCS 8610290121 | |
| Download: ML20215L573 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 p
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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 SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY 0PERATING LICENSE Amendment No. 93 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 August 14, 1986, as supplemented October 6, 1986, 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; 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 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 Commission'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 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. 93, 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 REGU TORY COMMISSION j.
ohIF.Stolz, Director PW Project Directorat #6 ivision of PWR Licen ng-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 21, 1986
ATTACHMENT TO LICENSE AMENDMENT N0.93 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET N0. 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 vertical lines _ indicating the area of change.
Remove Insert 3/4 5-5 3/4 5-5 4
i i
1 l
D ERGENCT CORE COOLING SYSTDtS SURVEILLANCE REQUIRDENTS (Continued) 2.
Verifying the correct position of each mechanical position stop fo'r' 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
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by debris,.and that the sump components (trash r'acks, screens, etc.) show no evidence of structural distress or corrosion.
5.
Verifying a total leak rate less than or equal to 6 gallons per hour for the LPI system at:
hdrostatic test, pressure a) Normal operating pressure or a
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of greater than or equal to 150 psig for those parts'of the system downstream of the pump suction isolation valve, and b) Greater than or equal to 55 psig for the piping from the containment emergency sump isolation valve to the pump suction isolation valve.
f.
At 1. east once per 18 months, in MODE 6, by 7
1.
Verifying that each automatic valve in' the flow path actuates to its correct position on a high pressure or low pressure j
safety injection test signal, as appropriate.3 2.
Verifying that each HPI and LpI pump starts automatically upon receipt of a~ high pressure or low pressure safety injection l
test signal, as appropriate.3 Following completion of HpI or LPI system modifications that could g.
have altered system flow characteristics, by performance of a flow 1
balance test during shutdown to confirm the following injection flow rates into the Reactor Coolant System:
HPI System - Sincle Pump 2 LPI System - Sincle Pumo Single pump flow rate greater than 1.
Injection Leg A - 2800 or equal to 500 gpm at 600 psig.
to 3100 gpm.
While injecting through 4 Injection 2.
Injection Leg B - 2800 Legs, the flow rate for all to 3100 gps.
combinations of 3 Injection Legs greater than or equal to 350 gpm at 600 psig.
1 Flow balance tests performed prior to complete installation of modifications are valid if performed with the syste= change that l
could alter flow characteristics in effect.
l The HPI Flow Bala,nce Test shall be performed in MODE 3.
2 I
l For Cycle VI, the surveillance frequency shall be at least once per 3
fuel cycle in MODE'6.
CRYSTAL RIVER - UNIT 3 3/4 5-5 Amendment No. 22, 77. 79,93
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