ML20100M999
| ML20100M999 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/04/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20100N001 | List: |
| References | |
| DPR-62-A-106, DPR-71-A-079 NUDOCS 8412120533 | |
| Download: ML20100M999 (8) | |
Text
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'o UNITED STATES 8"
E,,o NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D, C. 20555
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CAROLINA POWER 8 LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedJune6,1984,complieswiththestandardsand 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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendnent can be conducted without endangering the health 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 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 Commission's regulations and all applicable requirements have been satisfied.
?.
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-71 is hereby amended to read as follows:
9412120533 941204
' PDR ADOCK 05000324 P
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee 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 Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 4,1984 4
J e
ATTACHMENT TO LICENSE' AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:
Remove Insert 1-10 1-10
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f i
e S
S
y TABLE 1.2-OPERATIONAL CONDITIONS AVERACE OPERATIONAL MODE SWITCH REACTOR COOLANT CONDITIONS POSITIONS TkMPERATURE 1.
1.
POWER OPERATION Run Any temperature j
2.
STARTUP Startup/ Hot Standby Any temperature 3.
HOT SHUTDOWN Shutdown *'***
> 212*F 4.
COLD SHUTDOWN Shuedown#'##'***
1 212'F 5.
REFUELINC*
Shutdown or Refuel ***#
f,212*F 1
1
(
f The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
- The reactor mode switch may be placed in the Refuel position while a single control rod drive is being. removed from the reactor pressure vessel i
per Specification 3.9.10.1.
- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
4 i
- See Special Test Exceptions 3.10.1 and 3.10.3.
- The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE.
i
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BRUNSWICK - UNIT 1 1-10 Amendment No. 79 i
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (thelicensee)datedJune6,1984,complieswiththestandardsand requirementsoftheAtomicEnergyActof1954,asamended(theAct)
P and the Comission's rules and regulations set forth in 10 CFR Chapter It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endancering 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 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 i
have been satisfied.
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-67 is hereby amended to read as follows:
I
2-2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106, are.hereby incorporated in the license.
The licensee 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 Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications a
Date of Issuance: December 4,1984
+
5
i:
t ATTACHMENT TO LICENSE AMENDMENT NO.106 i
FACILITY OPERATING LICENSE N0. OPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as follows:
Remove Insert 1-11 1-11
- F 4
f e'
t i
---m
- ,.*.i**.
TABLE 1.2 OPERATIONAL CONDITIONS AVERACE OPERATIONAL H0DE SWITCH REACTOR COOLANT CONDITIONS POSITIONS TEMPERATURE 1.
POWER OPERATION Run Any temperature 2.
STARTUP Startup/ Hot Standby Any temperature 3.'
HOT SHUTDOWN Shutdown #'***
> 212* F 4.
COLD SHUTDOWN Shutdown #'##'***
1 212'F
~
5.
REFUELING
- Shutdown or Refuel ***#
1212'F r
Se e
- The reactor modo switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.
- The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.9.10.1.
- Tuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
- See Special Test Exceptions 3.10.1 and 3.10.3.
The reactor mode switch may be placed in the Refuel position while a single control rod is being recoupled provided that the one-rod-out interlock is OPERABLE.
BRtmSWICX - UNIT 2 1-11 Amendment No. 106
-