ML20128M603
| ML20128M603 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/03/1985 |
| 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 | |
| ML20128M608 | List: |
| References | |
| DPR-72-A-075 NUDOCS 8507260028 | |
| Download: ML20128M603 (5) | |
Text
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UNITED STATES
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEE 5 BURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES t"DRRII5 TON KRD CITY OF ORLANDO SEBRING UTILITIES COPHISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 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.
(thelicensees)datedAugust 30, 1984, as supplemented June 17, 1985, 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 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 itsuance 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.
8507260028 850703 ADOCK050003]2 DR
e e 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 an, ended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 75, 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 NVCLEAR REGULATORY COMMISSION Jo i F. Stolz, Chief
[
ating Reactors Branch #4 ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 3,1985 7
]
i
i ATTACHMENT TO LICENSE AMENDMENT NO. 75 FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302 i
Replace the following page of the Appendix "A" Technical Specifications with the enclosed 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.
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MitJIMtIM Ci It EAl)Ot II MEAStillEMEt3 T Cil Atit1El.S l
!!!S ittil M Eft t LOCA Ilotl 11Af1GE OPEltABLE l.
Itcarfor Trip Ikeaker Clll) switrligear sonin cpen-close I per erip breaker and Imlica tion 124 foot elevation i per secondary trip breaker 2.
Itcartor Coolant Ite note slmtilown panel 520.6200F i per loop lemperature - II:
3.
l!eactor Coolant Pressure Itesamte shiitilown panel 0-2500 psig I
l 4.
Pressneizer Level Itenmie shuvilown panel 0 320" II 0 I
2 Y
3.
Steaan Generator Pressure llenmte stintdown panel 0-1200 psig I per steam generator l
g 6.
Steam Gene ator Level 4160 ES-It swierbgear 0-230*18 0 I per steam generator 2
ronin 108 foot elevation I
7.
I)eray IIcat itemoval Itenete shutdown panel 0-3000F I per cooler t emperature 8.
Motor Ilsiven Emergency Inter mediate Ikiihling 0-2000 psig i per pump E
Feedwates P essine 95 foot elevation f
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rinclear Scivices rioseil Auxilia y thiil. ling 0 300 psig I
6 CycleCooling Pmnps 95 foot elevation I)ischange Pressaue u
- 10. Iheclear Sc vices Close
r-p CIIANNEL CHANNEL q
INSTRtlMENT CilECK CAllBRATION rn M
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Reactor Trip Breaker Imlication M
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2.
Reactor Coolant Temperature-Th M
R 3.
Reactor Coolant Pressure M
R l
4 EYessurizer Level M
R#
3.
Steam Generator Level M
R w'e l
y 6.,
5 team Generator Presswe M
Rf 7.
Decay llent Memovat M
R Temperature 3.
Motor Driven Emergency M
R Feedwater Pressure 9.
Nuclear Services Closed M
R g
Cycle Cooling Pumps 3
Discharge Pressure
&g 10.
Nuclear Services closed M
R Cycle Cooling Cooler Outlet Temperature
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- The specified IE month calitwation frequency may be waived for Cycle V yw provided the sarveillance is performed <kwing Reitel V.
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