ML20078G707
| ML20078G707 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/26/1995 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078G711 | List: |
| References | |
| NUDOCS 9502030226 | |
| Download: ML20078G707 (8) | |
Text
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- g UNITED STATES i
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S NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20665 4001 h
l CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 j
BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 173 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated November 16, 1994, complies with the j
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-i B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; l
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 inimical to the comon defense and security or to the health and safety of the public; j
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-71 is hereby amended to read as follows:
9502030226 950126 PDR ADDCK 05000324 p
4
.g.,.
, (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as rev' >ed through Amendment No.173, are hereby -incorporated in the license. Carolina Power & Light Company shall operate the
' facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and 1
shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-nYt v--
i William H. Bateman, Director Project Directorate 11-1 i
Division of Reactor Projects - I/II j
Office of Nuclear Reactor Regulation
Attachment:
- Changes to the Technical Specifications Date of Issuance: January 26, 1995 t
f I
l I
i
ATTACHMENT TO LICENSE AMENDMENT NO. 173 s
FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paq21 3/4 6-3 3/4 6-3 3/4 6-3A 3/4 6-3B t
\\
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) c.
The leakage rate to less than or equal to 11.5 scf per hour for any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212 F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated in accordance with the schedule and criteria specified in 10 CFR 50. Appendix J.
as modified by approved exemptions. The provisions of Technical Specification 4.0.2 are not applicable to the test intervals specified in 10 CFR 50.
Appendix J.
a.
Deleted.
b.
Deleted.
c.
Deleted.
d.
Type B and C tests shall be conducted with gas at P, 49 psig. at intervals no greater than 24 months except for tests involving:
1.
Air locks.
2.
Main steam line isolation valves, e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
I g.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
h.
The provisions of Specification 4.0.2 are not applicable to 24 month surveillance intervals.
l (Pages 3/4 6-3A and 3/4 6-3B have been deleted.)
BRUNSWICK - UNIT 1 3/4 6-3 Amendment No. 88,173
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o UNITED STATES U
NUCLEAR REGULATORY COMMISSION k.....,/
WASHINGTON, D.C. 20555-0001
[AROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 MiENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated November 16, 1994, 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 Commission; 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 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.
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:
l j
1
! (2)
Technical Specifications r
The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No. 204, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
this license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION w-4 William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Raactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 26, 1995 l
4 i
ATTACHMENT TO LICENSE AMENDMENT NO. 204 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paoes insert Paaes 3/4 6-3 3/4 6-3 3/4 6-3A
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) c.
The leakage rate to less than or equal to 11.5 scf per hour for any one main steam line isolation valve, prior to increasing reactor coolant system temperature above 212*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated in accordance with the schedule and criteria specified in 10 CFR 50. Appendix J.
as modified by approved exemptions.
The provisions of Technical Specification 4.0.2 are not applicable to the test intervals specified in 10 CFR 50.
Appendix J.
a.
Deleted.
b.
Deleted.
c.
Deleted.
d.
Type B and C tests shall be conducted with gas at P, 49 psig, at intervals no greater than 24 months except for tests involving:
1.
Air locks.
2.
Main steam line isolation valves.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested at least once per 18 months.
g.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
h.
The provisions of Specification 4.0.2 are not applicable to 24 month surveillance intervals.
I i
(Page 3/4 6-3A has been deleted.)
1 BRUNSWICK - UNIT 2 3/4 6-3 Amendment No.py.J##,I66, 198,204