ML20039B977
| ML20039B977 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/10/1981 |
| 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 | |
| ML20039B978 | List: |
| References | |
| DPR-72-A-047, TAC 47407 NUDOCS 8112280156 | |
| Download: ML20039B977 (4) | |
Text
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNEi.L 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. 47 License No. OPR-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 December 8,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as acended (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 ininical 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.
8112280156 811210 PDR ADOCK 05000302 P
PDR.
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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. 47, 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 b-John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 10, 1981 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 47 FACILITY OPERATING LICENSE NO. OPR-72 DOCKET NO. 50-302 Replace the following page of Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
3/4 1-34
REACTIVITY CONTROL SYSTEMS ROD PROGRAM LIMITING CONDITION FOR OPERATION 3.1.3.7 Each control rod (safety, regulating and APSR) shall be pro-grammed to operate in the core position and rod group specified in Figure 3.1-7.
APPLICABILITY: MODES 1* and 2*.
ACTION:
With any control rod not programmed to operate as specified above, be in HOT STANDBY within I hour.
SURVEILLANCE REQUIREMENTS 4.1.3.7 a.
Each control rod shall be demonstrated to be programmed to operate in the specified core position and red group by:
1.
Selection and actuation from the control room and verifi-cation of movement of the proper rod as indicated by both the absolute and relative position indicators:
a)
For all control rods, after the control rod drive patchs are locked subsequent to test, reprogramming or maintenance within the panels, b)
For specifically affected individual rods, following maintenance, test, reconnection or modification of power or instrumentation cables from the control rod drive control system to the control rod drive.
2.
Verifying that each cable that has been disconnected has been properly matched and reconnected to the specified control rod drive.
b.
At least once each 7 days, verify that the control rod drive patch panels are locked.
'See Special Test Exceptions 3.10.1 and 3.10.2.
CRYSTAL RIVER - UNIT 3 3/4 l-33 Amendment No.19 -
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Figure 3.1 7 Control Rod Locations and Group Designations for Crystal River 3. Cycle 4 l
1 2
3 4
5 6
7 8
9 to 11 12 13 to 15 I
l A
8 4
7 4
C 2
5 5
2 8
3 8
6 D
6, -
E 2
3 1
1 3
2 F
4 8
7 6
7 8
4 G
3 1
3 3
1 3
M W-7 3
6 4
6 3
7
-Y K
5 1
3 3
1 5
L 4
8 7
6 7
8 4
M 2
3 1
1 3
2 N
6 8
3 8
6 0
2 5
5 2
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X Croup Number No. of Croup rods Funetton 1
8 Safety 2
8 Safety 3
12 Safety 4
9 Safety 5
8 Control 6
8 Control 7
8 Control 8
J APSRs Total 69 CRYSTAL RIVER - UNIT 3 3/4 1-34
.tandment No.17, 47
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