ML19325F252
| ML19325F252 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/08/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19325F253 | List: |
| References | |
| NUDOCS 8911170234 | |
| Download: ML19325F252 (5) | |
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1 UNITED STATES
.E NUCLEAR REGULATORY COMMISSION e
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CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT 10 FACILITY OPERATING LICENSE Amendment No. 168
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License No. DPR-t>2 1.
The huclear Regulatory Comission (the Commission) has found that:
A.
The application for amendnent by Carolina Power & Light Company (the licensee), dated June 9,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Conadssion's rules and regulations set forth in 10 CFR
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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 anendment can be conducted without endangering the health h
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; L
D.
The issuance of this anendmer,t will not be inimical to the con. mon defense and security or to the health and safety of the public; and k
l E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements j
have been satisfiec.
2.
Accordingly, the license is anended by changes to the Technical Specifications, 6s indicatec in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License ho. DPR-62 is l
hereby amended to read as follows:
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'(2) Technical Specifications i-(/
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The Technical Specifications contained in Appendices A and' B, "a's revised through Anandment No.168, are hereby incorporated in the i -
license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
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This license anendant is effective as of the date of its issuance and !
4 shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G. Adensam Director Project Directorate 11 1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation cc
Attachment:
Changes to the Technical Specifications Date of Issuance: November 8, 1989 r
I Document Name:
Brunswick 2 Amend 73391 e
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DATE':10/j)3/89
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OFFICIAL RECORD COPY ly 1,
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ATTACHMENT TO LICENSE AMENDMENT NO.168 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324
.t Replace the following pages of the Appendu A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove Pages insert Pages 2-1 2-1 5-1 5-1 f
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~2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 ' SAFETY' LIMITS THERMAL' POWER (Low Pres 6ure or Low Flow) 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the reactor vessel steam dome pressure less than 800 psia or' core flow less than 10% of' rated flow.
APPLICABILITY:
CONDITIONS 1 and 2.
ACTION With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel steam dome pressure less than 800 psia 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 (High Pressure and High Flow) 2.1.2 The MINIMUM CRITICAL DOWER RATIO (MCPR) shall not be less than 1.06 with the reactor vessel steam dome pressure greater than 900 psia and core flow greater than 10% of rated flow.
APPLICABILITY OPERATIONAL CONDITIONS 1 And 2 ACTION:
P With MCPR less than 1.06 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.
APPLICABILITY: CONDITIONS 1, 2, 3, and 4.
ACTION:
With the reactor coolant system pressure, as measured in the reactor vessel steam dome, above 1325 psis, 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. 168 I
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5.0 DESIGN FEATURES o,
1.1 SITE EXCLUSION
- AREA
,-5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.
LOW POPULATION ZONE 5.1.2 The' low! population zone shall be as shown in Figure 5.1.2-1.
4 SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1.
For the purpose
'of effluent releas's 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 CONTAINNENT t
CONFICifRATION
'5.2.l' The PRIMARY CONTAINMENT is a steel-lined, reinforced concrete structure composed of a series of vertical right cylinders and truncated cones which form a drywell. 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's torus. The primary containment has a minimum free air volume of 288,000 cubic feet.
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' DESIGN TEMPERATURE AND PRESSURE l
lS 5.2.2 The primary containment is designed and shall be maintained fort 1"
Maximum internal presst.re 62 psig.
a.
b.
Maximum internal temperatures dryvell 300*F Suppression chamber 200*F c.
Maximum external pressure 2 psig.
1 5.3 REACTOR CQRE FUEL ASSEMBLIES 1"
5.3.1 The reactor cere shall contain 560 fuel assemblies limited to the l-following fuel types BP8x8R, CE8x8EB, and CE8x8NB.
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BRUNSWICK - UNIT 2 5-1 Amendment No. 168 l