ML20067A156
| ML20067A156 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/23/1982 |
| 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 | |
| ML20067A158 | List: |
| References | |
| TAC 47117, DPR-72-A-060 NUDOCS 8212010330 | |
| Download: ML20067A156 (5) | |
Text
-
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- pace:g[0, UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
a WASHINGTON, D. C. 20066
%,...../
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.60 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by Florida Power Corporation, et al (_the licensees) dated October 28, 1981, 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; t
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 nealth 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 commoh 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.
8212010330 821123 PDR ADOCK 05000302 P
PUR
m u.
. 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. 60, 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 oh
. Stolz, Chief pe ating Reactors ranch #4
- ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 23, 1982
?
ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE NO. DPR-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.
3/4 3-37 3/4 3-38 4
e f
9
INSTRUMENTATIO!i POST-ACCIDENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Taoie 3,3-10 shall be OPERABLE with readouts on all channels in the control room.
Recorders on instruments 1 through 10 shall be OPERABi.E.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With tne ntraber of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inopera-ble channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
The provisions of Specification 3.0.4 are not applicanie.
SURVEILLANCE REQUIREMENTS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Tabl e 4.3-7.
i CRYSTAL RIVER - UNIT 3 3/4 3-3)
Amendment No. 60
I Alll E 3.3-10 POST-ACCIDENT HONITORING INS 1RUtiLNI AT10N Q3 HINIMUH g
HEASUREHtNT CllANNELS r-
=
INSIRUMENT RANGE OPERABLE 2
1.
Powr Range Nuclear flux 0 - 125%
2.
Reactor Building Pressure 0 - 70 psia 2
[
3.
Source Range Nuclear flux 10-1 to 106 cps 2
1 4.
Reactor Coolant Outlet Temperature 5200f - 6200f 2 per loop l
5.
Reactor Coolant Total flow 0 - 160 X 106 lb./hr.
1 0 - 2500 psig 2
6.
RC Loop Pressure 0 - 600 psig 1
1/00 - 2500 psig 2
0 - 320 inches 2
7.
Pressurizer Level M
8.
Steam Generator Outlet Pressure 0 - 1200 psig 2/ steam generator 4'
M 9.
Steam Generator Operating Range Level 0 - 100%
2/ steam generator 0 - 50 feet 2
- 10. Horated Water Storage Thnk I.evel 0 - 1.5 X 106 l b/hr.
2
- 11. Startup feeduater flow R
- 12. Reactor Coolant System Subcooling Margin Honitor
-6580f to 16680f 1
a F
- 13. PORV Rosition I:ulicator (Primary Detector)
N/A 1
k
- 14. PORV Position ludicator (Backup Detector)
N/A 0
- 15. PORV Hlock Valve Position Indicator N/A 0
in O
- 16. Safety Visive Position Indicator (Primary Detector)
N/A l/ Valve
- 11. Safety Valve Position indicator (Backup Detector)
N/A 0
e
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