ML20092B629
| ML20092B629 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-071) |
| Issue date: | 06/05/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20092B632 | List: |
| References | |
| DPR-71-A-071 NUDOCS 8406200312 | |
| Download: ML20092B629 (5) | |
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UNITED STATES
[ 'i fj NUCLEAR REGULATORY COMMISSION
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WA$HING TON. D. C. 2055')
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t CAROL!flA POWEP A LIGHT C0t'rANY DOCKET N0. F0 325, 8%f!SWICK STEAf! ELECTRIC MJtJT. llNIT 1 l
AffENDMENT TO FACILITY OPERATING LICErlSE l
/rrondrent No. 71 License No. OPR-71 I
1.
The flucicar Regulatury Commission (the Conmission) has 'ound that:
A.
The application for amendment by Carolina Pcwer & Light Cenpany (the licensee) dated Janeary 31, 1984, as supplemented February 29, 1984, cerrplies with the standarcs and requiretrants of the Atomic l
Energy Act of 1954, as arr.cnded (the Act) and the Cermission's rules and rer;ulations set forth in 10 CFR Chapter 1; B.
The facility will operate in confernity with the applicatiun, the provisions cf the Act, ar.d the rules ard regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized t'y 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 Ccrimission's regulations; D.
The issuance of this atendir.ent will net be inimical to the cortrron defense and security or to tbc health and safety of the public; and E.
The issuance of this arendment is in accordance with 10 CFR Part 51 of the Commission's regulations and cll applicable requiretrcnts l
have been satisfied.
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Accordingly, the license is amended by changes to the Trebrical Specifications as indicated in the attachttent to this license air.oneircnt, and paragrarh 2.C.(2) of facility Operating License No. OTR-71 is hereby arrended to read as follows:
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-2 (2) Technical Specifications The Technical Specifications contained in Appendices A and C, es revised through Arendment No. 71, are hereby incorporated in the license. The licensee 3 hall operate the facility in accordance with the. Technical Specifications.
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This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSI0tt I
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Domenic B. Vassallo, Chief i
Operating Reactors Branch #2 f
Division of. Licensing l
Attachment:
r Changes to the Technical Specifications 1
Date of issuance: June 5, 1984 I
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ATTACHMENT TO LICEtlSE Al'FNDPEtlT NO, 71 FACILITY OPERATING 1 ICEfiSE NO. OPR-71 CCCKET NO, 50-325 Revise the Apper. dix A Technical Specifications by renoving paces 5-1 and 5-4 and inserting revised pages 5-1 and 5-4..
The chani;ed areas are indicated by vertical lines.
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5.0_ DESTCN FEATURES 5.1 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, based on the information given in Section 2.2 of the FSAR.
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5.2 CONTAINMENT CONFIGURATION l
5.2.1 The PRIMARY CONTAIRMENT 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 a corus.
The primary containment has a sinimum free air volume of (288,000) cubic feet.
DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained fort Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperature s drywell 300 F.
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suppression chamber 200 F.
c.
Max 16um external pressure 2 psig.
i 5.3 REACTOR CORE
_ FUEL _ ASSEMBLIES 3.3.1 The reactor core shall contain $60 fuel assemblies, with each 8 x 8 fuel assembly containing 63 fuel rods and each 8 x 8R fuel assembly containing 62 fuel rods.
All fuel rods shall be cladded with Zircaloy 2.
Each fuel rod shall have a nominal active fuel length of 146 inches for 8 x 8 fuel and ISO inches for 8 x 8R fuel.
l BRUNSWICK - UNIT 1 3-1 Amendment No. 71
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES (Continued)
The initial loading shall have a maximum average enrichment of 2.35 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a saxinum average enrichment of 2.99 weight percent U-235.
CONTROL ROD ASSEMRLIES 5.3.2 The reactor core shall contain 137 control rod assemblies, each consisting of a cruciform array of stainless steel tubes containing 143 inches or boron carbide, 3 C, powder surrounded by a cruciform-shaped stainless steel 4
sheath.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE'AND TEMPERATURE 5.4.1 The nuclear boiler and reactor recirculation system is designed and shall be maintained:
a.
In accordance with the code requirements'specified in Section 4.2 of
-the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
b.
For a pressure of 1250 psig, and c.
For a temperature of 575 F.
VOLUME 5.4.2 The total water and steam volume of the reactor vessel'and.
recirculation system is approximately 18,670 cubic feet.
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5.5 METEOROLOGICAL TOWER LCCATION 5.5.1 The =eteorological tower shall~be.'ocated as shown in Figure 5.1.1-1.
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BR?f7JICK' = UNIT l ' '
, (5 ' Amendment No. '71