ML20024E148
| ML20024E148 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/19/1983 |
| 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 | |
| ML20024E149 | List: |
| References | |
| DPR-72-A-065 NUDOCS 8308090292 | |
| Download: ML20024E148 (6) | |
Text
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION o
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FLORIDA POWER CORPORATION CITY OF ALACHUA
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CITY OF BUSHNELL CITY OF GAsNESVILLE
' CITY OF KISSIMEE CITY OF LEESBUR T CITY OF NEW SMYRNA BEACH AND UTILITIES COMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES M D CITY OF ORLANDO l
SEBRING UTILITIES COP 9tISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR 'ENERATING PLANT G
- AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65
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License No. DPR-72 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated June 24, 1983, 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 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 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.
8309090292 830719 DR ADOCK 05000
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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:
( 2). Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, 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 COMMISSION LL Jo F. Stolz, Chief 0 rating Reactors Branch #4 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 19,1983 6
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W ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of-the. Appendix " A" Technical Speci fications 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.
Pages 3/4 7-47 B 3/4 7-6 e
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t PLANT SYSTEMS 3/4 7.12 FIRE BARRIER PENETRATIONS LIMITING CONDITION FOR OPERATION 3.7.12 All fire barrier penetrations (including cable penetration barriers, firedoors and fire dampers)in fire zone boundaries protecting safety related areas shall be functional.
l APPLICABILITY:
At all times.
1 ACTION:
With one or more of the above required fire barrier penetrations non-a.
functional, within one hour either, establish a continuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish an hourly fire watch patrol.
q b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.12 Each of the above required fire barrier penetrations shall be verified to be functional:
At least once per 18 months by a visual inspection.
a.
b.
Prior to returning a fire barrier penetration to functional status following repairs or maintenanc,e by performance of a visual' inspection of the affected fire barrier penetration (s).
CRYSTAL RIVER UNIT 3 3/4 7-47 Amendment No. U, 65
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E.
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?LANT SY STEMS BASES 3/4.7.8 AUXILIARY BUILDING VENTILATION EXHAUST SYSTEM i
The OPERASILITY of the Auxiliary Building ventilation exhaust system ensures that suitable ambient conditions for personnel and equipment are maintained for all operating periods and that the effects of post accident contitions in the Auxiliary Building are mitigated.
Supply and exhaust duct systems are arranged,co direct air from areas of low to higher activity eventually directing it to the main exhaust filter system and from there through the fans to the exhaust vent.
The main exhaust filters include roughing, HEPA, and charcoal cells.
3/4.7.9 HYDRAULIC SNU3BERS The hydraulic snubbers are required OPERABLE to ensure that the struc-'
tural integrity of the reactor coolant system and all other safety-related systems is =aintained during and following a seismic or other event initiating dyna =ic loads.
The only snubbers excluded from this inspection program are
' those installed on nonsafety-related systems, and then only if their failure or failure of the system en which they are installed would have no adverse effect on any safety-related system.
The inspection frequency applic'able to snubbers containing seals fabricated f rom materials wbids have been demonstrated compatible with their operating envir-onment is based upon maintaining a constant level of snubber protection.
There-fore, the required inspection interval varies inversely with the observed snubber failures.
The nu=ber of inoperable snubbers found during an inspection of these snubbers deter =ines the time interval for the next required inspection of these snubbers.
Inspections performed -before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less than 25%) may not be used to lengthen the required inspection intervs1.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
Tc provide further assurance of snubber relisbility, i representative sample of the installed snubbers will be functionally tested during plant shutdowns st.18 month intervals. These tests will include strokinc of the snubbers to verify proper piston movement, lock-up and bleed.
Observed failures of these sample snubbers will require functional testing of additienal units.
To minimi:e personnel exposures, snubbers.instslied in hi;h radiation :enes or in especially dif f'icult to remove locstions may be exemptee frc= these functional testing requirements provided.the OPERA 3ILITY of these snubbers was demonstrated during functional testing se either the ecmpletf ?n ef their fabrication or at a subsequent date.
C?.YSTAL RI'.*E?. - CN1T 3 3 3/4 7-5 Amendment No. 52
s PLANT SYSTEMS BASES 3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located.
The fire suppression system consists of the water system, deluge and sprinklers, hose stations and Halon. The collective capability of the fire suppression systems is adequate to rninimize potential damage to safety related equipment and is a major element in the f acility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be' restored to service.
In the event that the fire suppression water system becomes inoperable, i.mmediate corrective measures must be taken.since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3/4.7.12 PENETRATION FIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent ponions of the facility.
This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspection.
Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered functional when the visually' observed condition is the same as the as-designed condition.
For those fire barrier penetra-tions that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.
During periods of time when a barrier 1s not functional, either 1) a continuous fire watch is required to be maintained in the vicinity of,the affected_. barrier, or 2) the fire detectors on at least one side of the,
affected barrier must be verified OPERABLE and an hourl'y fire watch patrol established, until the barrier is restored to functional status.
CRYSTAL RIVER-UNIT 3 B 3-4 7-6 Amendment flo. 73, 65