ML20093A560
| ML20093A560 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/26/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093A561 | List: |
| References | |
| NUDOCS 8407100635 | |
| Download: ML20093A560 (2) | |
Text
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(BSEF-1-02/35)
O 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.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as a shown in Figure 5.1.3-1.
For the purpose of effluent release 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 CONTAIK4ENT 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:
Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperature:
drywell 3000F.
-suppression chamber 2000F.
Maximum external pressure 2 psig.
c.
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 f uel.
100635 840626 ADOCK05000g P
BRUNSWICK - UNIT 1 5-1 Amendment No.
-o (BSEP-2-36)
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION AND INSTRUMENT NUMBER RESPONSE TIME (Seconds)#
I b.
Reactor Core Isolation Cooling System Isolation
- l. RCIC Steam Line Flow - High
< 13(a)###
(E51-PDT-N017; i
E51-PDT-N018)
(E51-PDTS-N017-2; E51-PDTS-N018-2)
- 2. RCIC Steam Line High Flow Time Delay Relay
, NA t
(E51-TDR-K32; E51-TDR-K12)
- 3. RCIC Steam Supply Pressure - Low NA i
(E51-PS-N019A,B,C,D)
- 4. RCIC Steam Line Tunnel Temp - High NA (E51-TS-3319; E51-TS-3320; i
E51-TS-3321; E51-TS-3322; 1
E51-TS-3323; E51-TS-3355; E51-TS-3487)
- 5. Bus Power Monitor NA (E51-K42 and E51-K43)
- 6. RCIC Turbine Exhaust Diaphram Pressure - High' NA (E51-PS-N012A,B,C,D)
- 7. RCIC Steam Line Ambient Temperature - Nigh ~
NA (E51-TS-N603A,B)
- 8. RCIC Steam Line Areaa Temp - High NA (E51-dTS-N604A,B )
- 9. Emergency Area Cooler Temperature - High NA (E51-TS-N602A,B)
- 10. RCIC Fquipment Room A Temp - High NA (E51-dTS-N601 A,B )
l S.
SHUTDOWN COOLING SYSTEM ISOLATION a.
Reactor Vessel Water Level - Low, Level 1 NA i
(B21-LT-N017A-1,B-1,C-1,D-1)
(B21-LTM-N017A-1,B-1,C-1,D-1) b.
Reactor Steam Dome Pressure - High NA (B32-PS-N018A,B)
BRUNSWICK - UNIT 2 3/4 3-24A Amendment No.
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