ML20041E947
| ML20041E947 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/05/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20041E948 | List: |
| References | |
| DPR-62-A-069, DPR-71-A-046 NUDOCS 8203160003 | |
| Download: ML20041E947 (7) | |
Text
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S UNITED STATES j
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NUCLEAR REGULATORY COMMISSION y*
h WASHINGTON, D. C. 20555
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s CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. DPR-71 1.
The fiuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company dated February 3,1982,.as supplemented by letter dated February 25, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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
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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 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 Spec-ifications 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are hereby incorporated
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in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8203160003 820305 PDR ADOCK 05000324 P
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This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
n Domenic B. Vassal o, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 5,1982 e
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ATTACHMENT TO LICENSE AMENDMENT N0.46
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FACILITY OPERATING LICENSE N0. DPR-71 DOCKET NO. 50-325 Remove the following pages and replace with identically numbered pages.
3/4 8-3 3/4 8-4 l
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 2.
Verifying the fuel level in the day fuel tank, 3.
Verifying the fuel transfer pump can be v srted and transfers fuel from the day tank to the engine mounted tank, 4.
Verifying the diesel starts from ambient condition and accelerates to at least 514 rpm in ;[ 10 seconds, s
5.
Verifying the generator is synchronized, loaded to 2,1750 kw, l
and operates for > 15 minutes, and 6.
Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.
b.
At least once per 31 days by verifying the fuel level in the plant fuel storage tank.
At least once per 92 days by verifying that a sample of diesel fuel c.
from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM-D97.5-74 l
when checked for viscosity, water and sediment, l
d.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's l
recommendations for this class of standby service,
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2.
Verifying the generator capability to reject a load equal to one
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core spray pump without tripping, i
f 3
Simulating a. loss of offsite power in conjunction with an l
l emergency core cooling system test signal, and:
a)
Verifying de-energization of the emergency buses and load shedding from the emergency buses.
l b)*
Verifying the diesel starts from ambient condition on the l
auto-start signal, energizes the emergency buses with permanently connected loads, energizes the auto-connected loads through the load sequence relays and operates for 2,5 l
minutes while its generator is loaded with the emergency loads.
- For the verification of this iten scheduled for completion. by April 29, 1982, j
a onetime-only exemption is allowed to extend this inspection until before the completion of the Unit 2 spring 1982 refueling outage, scheduled to commence by April 30, 1982.
3/4 8-3 "
Amendment No. Ja',. 46 i
l BRUNSWICK - UNIT 1 I
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.l ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 4.
Verifying that on the emergency core cooling system test signal, all diesel generator trips except engine overspeed, generator differential, low lube oil pressure, reverse power, loss of field and phase overcurrent with voltage restraint, are automatically bypassed.
5.
Verifying the diesel generator operates for 160 minutes while loaded to 1 3500 kw.
6.
Verifying that the auto-connected loads to each diesel generator l
do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 3850 kw.
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Verifying that the automatic load sequence relays are OPERABLE l
with each load sequence time within 10% of the required value.
l
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- For the verification of this item scheduled for completion April 29, 1982, a onetime-only exemption is allowed to extend this inspection until before the completion of the Unit 2 spring 1982 refueling scheduled to commence by April 30, 1982.
l BRUNSWICK - UNIT 1 3/4 8-4 Amendment No'. pf,' 46
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UNITED STATES IS, NUCLEAR REGULATORY COMMISSION
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.~ ASHINGTON, D. c. 20555 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applicatica for amendment by Carolina Power & Light Company dated February 3,1982, as supplemented by letter dated February 25, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity 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' authorfied 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 adding paragraph 2.C.(2)(a).._..
to Facility 0perating License No. DPR-62 to read'as foll. owe-
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(a)
The end of the current surveillance period for the surveQ1 require,ments listed below may be extended beyond the time limit specified by Technical Specification 4.0.2a.
After May 1, 1982, the plant shall not be operated in Conditions 1, 2, or 3 until the surveillance requirements listed below have been co=pleted.
Upon accomplishment of,the surveillances, the provisions of Technical Specification 4.0.2a shall apply.
2 Specification 4.3.1.1; Table 4.3.1-1, items 9 & 10 4.3.1.2 4.3.1.3; Table 3.3.1-2, item 10 4.3.2.1; Table 4.3.2-1,. items 1.d.& 1.f ~ ~ ~
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4.3.2.3; Table 3.3.2-3, itein 5.a.1'
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4.3.3.2; Table 4.3.3-1, items 4.c & 4.f 4.5.2.a 4.8.1.1.2.d.2
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4.8.1.1.2.d.3 4.8.1.1.2.d.6 L
4.8.1.1.2.d.7 3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-$7' m
Domenic B. Vassall, Chief Operating Reactors Branch #2 Division of Licensing Date of Issuance: March 5,1982 a
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