ML20073C753
| ML20073C753 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/23/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20073C752 | List: |
| References | |
| NUDOCS 9104250378 | |
| Download: ML20073C753 (3) | |
Text
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ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PIANT, UNIT 2 NRC DOCKETS 50 325 6 50-324 OPERATING LICENSES DPR 71 6 DPR 62 REQUEST FOR LICENSE AMENDMENT FUEL CYCLE 10 RE14AD LICFESING TECHNICAL SPECIFICATION PACES UNIT 2 9104250378 910423 PDR ADOCK 05000324 P
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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINCS 2.1 SAFETY LIMITS l
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THERMAL POWER (Low Pres sure or Low Flow)
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l 2.1.1 THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the j
I reactor vessel steam dome pressure less than 800 psia or core flow less than i
10% of rated flow.
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APPLICABILITY:
CONDITIONS 1 and 2.
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ACTION:
1 With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel i
steam dome pressure less than 800 psia or core flow less than 10% of rated flow, be in at least HOT SHUTDOWN within 2 bot.rs.
THERMAL POWER (High Pressure and High Flow)
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2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than j,4e'-
with the reactor vessel steam dome pressure greater than 800 psia and core l
l flow greater than 10% of rated flow.
j APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2
( l,(}'7 ACTION:
With MCPR less than J 444dand 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 l
2.1.3 The reactor coolant system pressure, as measured in the reactor vessel steam dome, shall not exceed 1325 psig.
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APPLICABILITY:
CONDITIONS 1, 2, 3, and 4.
ACTION:
With the reactor coolar:t system pressure, as measured in the reactor vessel 1
steam dome, above 1325 psig, 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 />.
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BRUNbWICK - UNIT 2 2-1 Amendment No.,L5s4 -
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.e 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 CONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.
SITE BOUNDARY 5.1.3 The SITE BOUNDARY shall be as shown in Figure 5.1.3-1.
For the purpose of effluent ralease 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 CONTAINMENT 1
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 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 contai ment 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 300'F Suppression chamber 200*F c.
Maximum external pressure 2 psig.
5.3 REACTOR CORE i
FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies limited to the following fuel types BP8x8R, CE8x8EB,.and CE8x8NB/ and Ggg,,g MB 3, l
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BRUNSWICK - UNIT 2 5-1 Amendment No. JJWF l
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