ML20059F942
| ML20059F942 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/11/1994 |
| From: | Bajwa S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F945 | List: |
| References | |
| NUDOCS 9401180034 | |
| Download: ML20059F942 (9) | |
Text
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.fe-k UNITED STATES I
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.167 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated October 19, 1993, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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-71 is hereby amended to read as follows:
9401100034 940111 DR ADDCK 0500 4
1 r.
. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 167, 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 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II t
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 11, 1994 9
4
s ATTACHMENT TO'I.ICENSE AMENDMENT NO.167 FACILITY OPERATING LICENSE NO. DPR-7.1 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 Paaes 3/4 6-3 3/4 6-3 8
1
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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 at.the following schedule and shall be determined in conformance with the criteria specified in Appendix J of 10CFR50:
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 10 month intervals during shutdown at Tfiethirdtestof.25psig,duringeach10-yearserviceperiod.
P, 49 psig, or P each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
b.
If any periodic Type A test fails to meet either 0.75 L, or 0.75 L. the test schedule for subsequent Type A tests shall be t
reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L or 0.75 L. a Type A test shall be t
performedateachplantshuldownforrefuelingorevery18 months, whichever occurs first, until two consecutive Type A tests meet 0.75 L'.or 0.75 L. at which time the above test schedule may be t
resumed l
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L, or 0.25 L.
t 2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
i 3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage at P,. 49 psig or P, 25 psig.
1 A one time exemption from the accelerated testing requirements of Specification 4.6.1.2.b has been granted. The next Unit 1 Type A test will be performed during the Reload 9 outage after which two consecutive Ty)e A test failures are required to resume the accelerated test scledule.
BRUNSWICK UNIT 1 3/4 6 3 Amendment No.65,II6.I26,167'
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.7 UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20565-0001 g
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CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UN'IT 2 AMENDMENT TO FACILITY OPERATING LICENSE
.i 9
Amendment No. 198 i
License No. DPR.i 1.
The Nuclear Regulatory Comission (the Commission) has found that:
-A.
The application for amendment filed by Carolina Power & Light
[
Company (the licensee), dated October 19, 1993, complies with the l
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 f
conducted in compliance with the Comission's regulations; D.
The issuance of this. amendment will not be inimical' to the comon j
defense and security or-to the health and safety of the public; and j
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; i
and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby a
amended to read as follows:
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s o (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.198, 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 30 days of issuance.
FOR THE' NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 11, 1994
e 4
e ATTACHMENT TO LICENSE AMENDMENT NO.198 FACILITY OPERATING LICENSE NO. DPR-62 D_0CKET 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 Paaes Insert Paaes 3/4 6-3 3/4 6-3 i
l I
s CdNTAINMENTSYSTEMS 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 at the following schedule and shall be determined in conformance with the criteria specified in Appendix J of 10CFR50:
a.
Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 i 10 month intervals during shutdown at P
49 psig, or P 25 psig, during each 10 year service period.
Th,ethirdtestof,eachsetshallbeconductedduringtheshutdown for the 10-year plant inservice inspection.
b.
If any periodic Type A test fails to meet either 0.75 L, or 0.75 L. the test schedule for subsequent Type A tests shall be t
reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L, or 0.75 L, a Type A test shall be 1
performed at each plant shutdown for refueling or every 18 months, whichever occurs first, until two consecutive Type A tests meet 0.75 L, or 0.75 L. at which time the above test schedule may be t
resume.
g c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25 L, or 0.25 L.
l t
2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to i
be equivalent to at least 25 percent of the total measured l
leakage at P, 49 psig or P. 25 psig.
t A one time exemption from the accelerated testing requirements of Specification 4.6.1.2.b has been granted. The next Unit 2 Type A test will be performed during the Reload 12 outage after which two consecutive Type A test failures are required to resume the accelerated test schedule.
BRUNSWICK - UNIT 2 3/4 6-3 Amendment No. 9I.I44.I66,198