ML20033E433
| ML20033E433 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/28/1990 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20033E430 | List: |
| References | |
| NUDOCS 9003120752 | |
| Download: ML20033E433 (2) | |
Text
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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL POWER (Low Pressure 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.
i APPLICABILITY CONDITIONS 1 and 2.
ACTION With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel l
steam dome pressure less than 800 psia or core flow less than 10% of rated flow, be in at leart 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).
1.07 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 4,94 l
with the reactor vessel steam dome pressure greater than 800 psia and core flow greater than 10% of rated flow.
APPLICABILITY: CONDITIONS 1 and 2.
ACTION:
I.D7 With MCPR less than 4,94 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 pois, 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 1 2-1 Amendment No. 444-l 9003120752 900228 PDR ADOCK 05000325 P
PDC 3
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.
j 5.2 CONTAINMENT CONFICURATION 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 attoched 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 fort Maximum internal pressure 62 psig.
a.
b.
Maximum internal temperature:
drywell 300 F.
0 0
suppression chamber 200 F.
Maximum external pressure 2 psig.
c.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies limited to the following fuel types:
0 02, 70 00,, BP8xBR, and CE8a(PNS-3.
- GE8xtf8, BRUNSWICK - UNIT 1 5-1 Amendment No. 44HF
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