ML20133E394
| ML20133E394 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/23/1985 |
| 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 | |
| ML20133E398 | List: |
| References | |
| DPR-72-A-079 NUDOCS 8508070678 | |
| Download: ML20133E394 (8) | |
Text
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Q UNITED STATES
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g NUCLEAR REGULATORY COMMISSION t
j WASHINGTON, D. C. 20555
>,e...+4 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 OPERATING LICENSE Amendment No.79 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 May 1, 1985, as supplemented June 14, 1985, June 19, 1985, and July 8, 1985, 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; 8.
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 l
in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common l
j defense and security or to the health and safety of the public; and f
l 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.
8508070678 850723 PDR ADOCK 05000302 P
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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 Toilows:
Technical Specifications The Technical Specifications contained in Apper. dices A and B, as revised through Amendment No. 79, 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, except that the change to Technical Specification 4.5.2.f shall be effective prior to entry into Mode 3 during the startup for Cycle 6.
F THE NUCLEAR REGUL ORYCOMMiSSION J n c Stolz, Chief f;
O er ing Reactors Braneff #4 Div sion of Licensing
Attachment:
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Changes to the Technical Specifications Date of Issuance: July 23, 1985 l
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ATTACHMENT TO LICENSE AMENDMENT N0;79 FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
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9 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 2.
Verifying the correct position of each mechanical position stop for each of the stop check valves listed in Specification 4.5.2.c.
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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 4
that the subsystem suction inlets are not restricted by the sump components (trash ritds, screens, etc.) show, debris and that i
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:
a)
Normal operating pressure or a hydrostatic test pressure 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,
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At least once per 18 months in MODE 6, by l
1.
Verifying that each automatic valve in the flow peth actuates to its correct position on a high pressure or low pressure safety injection test signal, as appropriate.
2.
Verifying that each MPI and LPI pump starts automatically upon receipt of a high pressure or low pressure safety injection test signal, as appropriate.
Following completion of HPI or LPI system modifications that could have g.
altered system flow characteristics!, by performance of a flow balance test during shutdown to confirm the following injection flow rates into the Reactor Coolant System:
HPl System - Single Pumo2 LPI System - Single Pumo l
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Tingle. pump flow rate greater than
- 1. Injection Leg A - 2800 to 3100 or equal to 500 gpm at 600 psig.
gpm.
While injecting through 4 Injection Legs,
- 2. Injection Leg B - 2800 to 3100 the flow rate for all combinations of 3 gpm.
Injection Legs greater than or equal to 350 gpm at 600 psig.
I Flow balance tests performee prior to complete installation of modifications are 3
valid if performed with the system change that could alter flow characteristics in effect.
khe HPI Flow Balance Test shall be performed inM '3.
l CRYSTAL RIVER - UNIT 3 3/45-5 Amendment No. 72, 7/, 79
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS Demonstrated OPERABLE by determining that each battery supplying c.
DC control power to the 230kv switchyard breakers is OPERABLE;
-1.
At least once per 7 days by verifying that:
a)
The electrolyte level of each pilot cell is between the minimum and maximum level indication marks, b)
The pilot cell specific gravity, corrected to 77'F, 4
and full electrolyte level is 3,1.20.
c)
The pilot cell voltage is 3,2.15 volts, and d)
The overall battery voltage is 3,120 volts.
2.
At least once per 92 days by verifying that:
a)
The voltage of each connected cell is 3,2.15 volts under float charge and has not decreased more than 0.10 volts from the value observed during the base-line tests, and b)
The specific gravity, corrected to 77'F, and full electrolyte level of each connected cell is > 1.20 and has not decreased more than 0.01 from the value observed during the previous tests, and c)
The electrolyte level of each connected cell is between the minimum and maximum level indication marks.
3.
At least once per 18 months by verifying that:
a)
The cells,. cell plates, and battery racks show no visual indication of physical damage or adnormal deterioratit9.
b)
The cell-to-ce-and terminal connections are clean, tight and coated with anti-corrosion materials, c)
The batte y charger will supply at least 95 amperes at 125 volts for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
CRYSTAL RIVER - UNIT 3 3/4 8-3 g
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 4.
At least once per 11 months, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for i hour vhen the battery is subjected to a battery service test.
3.
At least once per 60 months, by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.
This performance discharge test shall oe performed suosequent to the satisfactory completion of the required bsttery service test.
4.8.1.1.2 Each diesel generator sha!! be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1.
Verifying the fuel level in the day fuel tank, 2.
Verifying the fuel level in the fuel storage tank, 3.
Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank, 4.
Verifying the diesel starts from ambient condition and accelerates to at least 900rrpm in less than or equal to 10 seconds, 5.
Verifying the generator'is synchronized, loaded to greater than or equal to 1500 kw, and operates for greater than or equal to 60 minutes, and 6.
Verifying'the diesel generator is aligned to provide standby power to the associated emergency busses.
b.
At least once each 92 days by verifying that a sample of diesel fuel from the fuel storage tank is within the acceptable limits specified in Table 1 of ASTM D973 68 when checked for viscosity, water and sediment.
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C.
At least once per 18, months by 1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommenda*1cas for this class of standby service,.
CRYSTAL RIVER - UNIT 3 3/4 S 4 Amendments Nos. g, g4', 79