ML20079D717
| ML20079D717 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/18/1991 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079D718 | List: |
| References | |
| NUDOCS 9107240253 | |
| Download: ML20079D717 (5) | |
Text
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4 g# ts UNITED STATES k* i N7)
NUCLEAR REGULATORY COMMISSION kqg#
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^gh CAROLINA POWEP & LIGHT COMPANY, et al.
DOCKET NO. 50-324 BRUNSWICK STEAN ELECTRIC, PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Conmission) has found that:
A.
The application for amendment by Carolina powei & Light Company (the licensee), dated April 23, 1991, as supplemented July 9,1991, complies with the standards and requirements nf the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in c.onformity 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 authorizeo 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 Connission'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 thir amendment is in accordance with 10 CFR Part 51 of the Connission'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 )aragraph 2.C.(2) of Facility Operating License No. DPR-62 is here>y amended to read as follows:
9107240253 010718 PDR ADOCK 050003?4 F
6 i
2 (2) Technical Specifications The Technical Specifications contained in Appendices A snd B, as revised through Amendment No.184, are hereby incorporated in the license.
Carolina Power & Light Conpany 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 Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date Jf Issuance: July 18,1991
e e
ATTACHMENT 10 LICENSE AMENDMENT NO.184 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 inarginal lines.
Rernove Pages pgr_tPagess 2-1 2-1 5-1 5-1 O
l l
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4 2.0 SAFETY LIMITS AND LIMITlWC SAFETY SYSTEM SETTINCS 2.1 S AFETY LIMITS THFRMAL POWER (Low Pressure or Low Flow) 2.1.1 T!!ERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 800 psia or core !!ow less than 10% of rated flow.
APPLICABILITY:
CONDITIONS I and 2.
ACTION With TilERMAL POWER exceeding 2$1 of RATED THERMAL POWEH and the reactor vessel steam dome pressurc less than 800 psia or core llow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
THERMAL POWER (High Pressure and High flow) 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 1.07 l
with the reactor vessel steam dome pressure greater than 800 pela and core flow greater than 10% of rat.. flow.
APPLICABILITY:
CONDITIONS I and 2.
ACTION With MCPR less than 1.07 and the reactor vessel steam dome pressure greater l
than 800 psia and core flow greater than 10% of rated flow, be in at least HOT SHUTDOWN within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
REACTOR COOLANT SYSTEM PRESSURE 2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.
APPL.ICABILITY: CONDITIONS 1, 2, 3, and 4.
.<, TION With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 peig, be in at least HOT SHUTDOWN with reactor coolant system pressure < 1325 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
BRUNSWICK'- UNIT 2 2-1 Amendment No. /). /$,
1 84
d 5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA
$.l.1 The exclusion area shall be as shown in figure $.1.1-1.
1.0W p0PUI.ATION ZONE
$.1.2 Thy low population zone shall be as 6hown in figure 5.1.2-1.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in figure $.1.3-1.
For the purpose of effluent release calculations, the boundary f or atmospheric releases is the SITE BOUNDARY and the boundary f or liquid releases is the SITE BOUNDARY prior to dilution in the Atlantic Ocean.
5.2 CONTAINHENT CONFICURATION 5.2.1 The PRIMARY CONTAINHENT is a steel-lined, t
'orced concrete strecture composed of a series of vertical right cylinders a-runcated cones which form a drywell. This drywell is attached to a supt tion chamber through a series of vents. The suppression chamber is a coner s,
steel lined pressure vessel in the shape of a torus. The primary conta;.. <nt has a minimum f ree air volume of 288,000 cubic feet.
DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed ane shall be maintained tort a.
Maximum internal pressure 62 p.ig.
b.
Maximum internal temperatures drywell 300* F suppression chamber 200*f c.
Maximum externet pressure 2 psig.
5.3 REACTOR CORE FUEL ASSEMBl.lES 5.3.1 The reactor core shall contain 560 f uel sssemblies limited to the tollowing fuel types Bp8a8R, CE8x8EB, and CE8x8HB-3.
l BRUNSWICK - UNIT 2 5-1 Ame nd me nt No. II), /M.
184
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