ML20087D639

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Revised Tech Spec Section 5.3.1,Pages 5-1 & 5-4 Changing 3.00 Weight Percent to 2.99 Weight Percent to Reflect Enrichment Level Used in Reload Analysis
ML20087D639
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 02/29/1984
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20087D591 List:
References
BSEP-1-02, BSEP-1-2, NUDOCS 8403130465
Download: ML20087D639 (2)


Text

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u (BSEP-1-02) 5.0 DESIGN 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.

5.2 CONTAINMENT CONFIGURATION 5.2.1 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 a torus. The primary containment has a minimum free air volume of (288,000) cubic feet.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for:

a. Maximum internal pressure 62 psig.
b. Maximum internal temperature: drywell 300 F.

suppression chamber 2000 F.

c.. Maximum external pressure.2 psig. .

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 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 150 inches for 8 x 8R fuel.

hP o O 000 BRUNcWICK - UNIr 1 5-1 Amendment No. i

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(BSEP-1-02) o 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 maximum average enrichment of 2.99 weight percent U-235.

CONTROL ROD ASSEMBLIES 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, B 4C, powder surrounded by a cruciform-shaped stainless steel sheath.

5.4 REACTOR COOL'sNT 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

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5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 18,670 cubic feet.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1.

BRUNSWICK - UNIT 1 5-4 Amendment No.