ML20133G403
| ML20133G403 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/30/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20133G405 | List: |
| References | |
| DPR-62-A-113, DPR-71-A-088 NUDOCS 8508080669 | |
| Download: ML20133G403 (8) | |
Text
___
p#"%
UNITED STATES O
/ ^c NUCLEAR REGULATORY COMMISSION 3
g e
wasmucron. o. c. 20sss e
%,,,,,+
CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Ame..dment No. 88 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated September 7,1982, as supplemented April 13, 1984, May 7, and July 2, 1985, complies with the standards and 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 amendrrent 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 l
of the Comission's regulations and all applicable requirements 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-71 is hereby amended.to read as follows:
8508080669 8507 0 PDR ADOCK O 324 P
PDR d
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88. 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 C09tISSION I
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 30, 1985
ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 6-1 3/4 6-1 i
)
I
{
9 0
'I
(BSEP-1-19) 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTECRITY shall be maintained.
APPLICABILITY: CONDITIONS 1, 2, and 3.
ACTION:
Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:
At least oneg per 31 days by verifying that all primary containment a.
penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.3-1 or Specification 3.6.3.
b.
By verifying each primary contains.ent air lock OPERABLE per Specification 3.6.1.3.
By verifying the suppression pool OPERABLE per Specification 3.6.2.1.
c.
-* Except valves, blind flanges, and deactivated automatic valves which are located inside the containment, the MSIV Pit, the RWCU Penetration Triangle Room, or the TIP Room, and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once per 92 days. Those valves located above the drywell head requiring head shield block removal for verification will be verified prior to each replacement of the shield blocks.
1 BRUNSWICK - UNIT 1 3/4 6-1 Amendment No. 88 l
1
og UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION O
- p WASHINGTON, D. C. 20555 l
%,....+/
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.113 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated September 7,1982, as supplemented April 13, 1984, May 7, and July 2,1985, 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 (1) 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 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.
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,62 is hereby amended to read as follows:
.m
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.113, 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 NUCL AR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 30,1985 1
l
d ATTACHMENT TO LICENSE AMENDMENT NO. 113 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the Appendix A Technical Specifications as follows:
Remove Insert 3/4 6-1 3/4 6-1
~.
-e
. + -, -...
,e
+-,
e p.
(BSEP-2-19) 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTECRITY LIMITINC CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: CONDITIONS 1, 2, and 3.
ACTION:
Without PRIMARY CONTAINMENT INTECRITY, restore PRIMARY CONTAINMENT INTEGRITY within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least 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 /> and in COLD SH'JTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTECRITY shall be demonstrated:
a.
At least oneg per 31 days by verifying that all primary containment penetrations not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table 3.6.3-1 or Specification 3.6.3.
b.
By verifying each primary containment air lock OPERABLE per l
Specification 3.6.1.3.
I By verifying the suppression pool OPERABLE per Specification 3.6.2.1.
c.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment, the MSIV Pit, the RWCU Penetration Triangle Room, or the TIP Room, and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been de-inerted since the last verification or more often than once per 92 days. Those valves located above the drywell head requiring head shield block removal for verification will be verified prior to each replacement of the shield blocks.
BRUNSWICK - UNIT 2 3/4 6-1 Amendment No.ll3
.-