ML20247G040
| ML20247G040 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/12/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247G044 | List: |
| References | |
| NUDOCS 8909180348 | |
| Download: ML20247G040 (5) | |
Text
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UNITED STATES y'
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WASHINGTON, D. C. 20555
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINE5VILLE CITY OF KISSIMMEE CITY OF LEE 5 BURG CITY OF NEW SMYRNA BEACH AND UTILITIES COPEISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COPNISSION AND. CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET N0. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.120 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 June 12, 1989, 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 (i) that the activ1 ties authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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.
8909180348 890912 ADOC.K0500g2 PDR F
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2-2.
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.120,' are hereby incor) orated in the license.
Florida Power Corporation shall operate tbe facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
e bert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 12, 1989
ATTACHMENT-TO LICENSE AMENDMENT NO.120 !
FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 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.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Insert 3/4 6-2 3/4 6-2
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3/4.6 C"Nf1DMENP EYrfBE 3/4,6.1 MtD9JtY CINDLT!OGNT CENDLDefNT Df!E3t1TY tmrrne cremm ren omxrrm 3.6.1.1 Primary CDfIAINMENT 2NIERITY ahall be maintained.
APPLTC12rLITf: MXES 1, 2, 3 and 4.
ACIEE:
Without primary CDf!AINMENT 2 NIB 3tlTY, restore C2fDLINMENT 2NIBRITY ivithin cna hour or be in at least Icr SIANDBY vithin the next 6 hcurs and in CDID SHL7ITXNN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ETNTTTaNT INTinu2 EM 4.6.1.1 Primary CI3f!EDHDir INIBRITY ahall be dammstratmi:
At least anos par 31 days by verifying that:
a.
1.
All penetrations
- not capable of being clamed by 0r5U52 ccrrtaiment autmatic isolatim valves and required to be classi during accident curx11tions are clamed by valves, blind flanges, or danctivatad autmatic valves marmrod in their positions, exempt thces valves that may be opened under administrative controls per Specification 3.6.3.1, and 2.
All equipmerit hatens are cleasd and sealed.
b.
By verifying that and containannt air lack is crDUEZ par spcificatica 3.6.1.3.
- Despt valves, blind flanges, and danctivated autcuatic valves 212 are located inside the contalment and are lockad, saaled, or otharvias amamd in the cloemd position. ' mane penetraticms shall be verified ciceed during one CDID SHtJITON except that verification of these penetra*3:ms being cicmad nand not be parfccand acre ottan than anos par 92 days.
C3tMWIAI, RIVER - 13CT 3 3/4 6-1 Amanhent No. M
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f galMDRBffSM5BMi aarmlammer Iannma n-rr tvumrerrar Mm c====rrrar 3.6.1.2 Centalment leakage rates shall be limited to:
An overall inter; rated rate of 5 Ig, 0.25 Wwst by weight of the a.
containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 2 P, 53.3 psig.
a b.
A combined leakage rate of 5 0.60 Ig for all p-r-Lutions and valves subject to Type B arx1 C tests, when prasaurized to 2 P
- a APPLICMEIITY: MXES 1, 2, 3 armi 4.
With either (a) the measured overall integrated containment leakage rata l
avr== ding 0.75 Ig or (b) with the =ewi ocubined leakage Inte for all i
p r-dations and valves subject to Type B and C tests h_4_rg 0.60 Ig, restors the leakage rate (s) to within the limit (s) prior to increasing the Reactor Cbolant System temperature above 200*F.
stavrrr=, nurwmmamens 4.6.1.2 The ocattainment leakage rates shall be demonstrated at the following l
test schedule and shall be determined in conformance with the criteria specified in Apperziix J of 10 CER 50:
Stree Type A tests (Overall Intagrated Cbntalment Imakage Rate)
]
a.
shall be carducted at 40 10 acnth intervals durity shutdown at j
2 P, 53.3 psig, during ea,ch 10-year service pericxi.
The third j
a test of each set shall be acrductert durirg the shutdown for the d
10-year plant inservice inspection.
CRYSTAL RIVER UNIT 3 3/4 6-2 Amendment No. 775.120 i
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