ML20087D639
| ML20087D639 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| 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.
0 suppression chamber 200 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.
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BRUNcWICK - UNIr 1 5-1 Amendment No.
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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 C, powder surrounded by a cruciform-shaped stainless steel 4
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:
In accordance with the code requirements specified in Section 4.2 of a.
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.
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.