ML20043H156
| ML20043H156 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/18/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043H157 | List: |
| References | |
| NUDOCS 9006220088 | |
| Download: ML20043H156 (5) | |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMIS$10N c
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WASHINGTON, D. C. 20666 l
CAROLINA POWER & LIGHT COMPANY et al.
DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
142 License No. DPR-71 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applicatica for amendment filed by Carolina Power & Light Company (the licensee), dated February 28, 1990, as amended April 4, 1990, complies with the standards and requirements of the Atomic Energy l
Act of 1954 as amended (the Act), and the Comission's rules and L
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 Commission; l
C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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 stfety 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; andparagraph2.C.(2)ofFacilityOperatingLicenseNo.DPR-71is hereby amended to read as follows:
9 9006220088 9006161 PDR ADOCK 05000325 P
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l June 18, 1990
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.142, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
Thit license amendment is effective as of the date of Unit I shutdown for the Reload 7/ Cycle 8 refueling outage with implementation to follow within 60 days of the' unit shutdown.
FOR THE NUCLEAR REGULATORY COMMISSION I
Orignal signed by:
Elinor G. Adensam Director Project Directorate 11-1 Division of Reactor Projects. 1/II Office of Nuclear Reactor Regulation A,
Attachment:
" Change = to the Technical'
. Specifications
'ED$teofIssuance,:. June 18, 1990 3
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l ATTACHMENT TO LICENSE AMENDMENT NO.14p FACILITY OPERATING LICENSE NO. DPR-71 l
DOCKET N0. 50-325 l-1.
l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
L Remove Pages Insert Pages U
2-1 2-1 5-1 5-1 l
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2.0 SAFETY LIMITS AWD LIMITINC SAFETY SYSTEM SETTINCS 2.1 SAFETY LIMITS THERMAL POWER (Low Pressure or Low Flow)
THEtitAL POWER shall not exceed 25% of RATED THERMAL POWER with the 2.1.1 reactor vessel steam done pressure less than 800 psia or core flow less than 101 of rated flow.
APPLICAAILITY:
00WDITIONS 1 and 2.
ACTIOWs With THERMAL POWER exceeding 25% of RATED THLAMAL POWER and the reactor vessel steam done pressure less than 800 pela or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
THERMAL POWER (Hiah Pressure and High Flow) 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 1.07 with the reactor vessel steam dome pressure greater than 800 psia and core l
' flow greater than 10% of rated flow.
APPLICABILITY:
CONDITIONS 1 and 2.
ACTIOWs With MCPR less than 1.07 and the reactor vessel steam done pressure greater l
than 800 psia and core flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
4 REACTOR C001. ANT SYSTDI PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam done, shall not escoed 1325 pois.
APPLICABILITY:
CONDITIONS 1, 2, 3, and 4.
ACTION With the reactor coolant systen pressure, as measured in the reactor vessel steam done, above 1325 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure < 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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i RRUNSWICK - UNIT 1 2-1 Amendment Wo. /y$4142 1
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5.0 DESICW FEATURES 5.1 SITE EKCLUSION AREA 5.1.1 The esclusion area shall be as shown in Figure 5.1.1-1.
LOW POPULATION 20WE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1, based on the information given in Section 2.2 of the FSAR.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1.
For the purpose of effluent release calculations, the boundary for atmospheric releases is the SITE BOUNDARY and the boundary for liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.
5.2 CONTAIWMENT l.
CONFICURATION l
5.2.1 The PRIMARY CONTAINNENT is a steel-lined, reinf orced concrete structure 3
composed of a series of vertical right cylinders and truncated cones which i
f orm a d rywell. This drywell is attached to a suppression chamber through a series of vents. The suppression chamber is a concrete, steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum f ree i
air volume of (288,000) cubic feet.
DESICW TEMPERATURE AND PRESSURE l
5.2.2 The primary containment is designed and shall be maintained f ort i
Maximum internal pressure 62 pois.
a.
b.
Maximum internal temperatures drywell 300'F i
i-suppression chamber 200'F c.
Maaimum external pressure 2 pois.
5.3 REACfGE Cott L
FUEL ASSEMBLIES 1
5.3.1 The reactor core shall contain 560 fuel assemblies limited to the following fuel types 8P8 8R, CE838EB, and CE838W8-3.
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i EtUWSWICE - UNIT 1 5-1 Amendment Wo. AA) 142
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