ML20082B753

Proposed Tech Spec 2.1.2 Re MCPR Safety Limits & 5.3.1 Re Use of GE 8x8NB-3 Fuel Type for Cycle 10 Operation

ML20082B753
Person / Time
Site:	Brunswick
Issue date:	07/09/1991
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20082B740	List: ML20082B737 ML20082B753
References
TAC-80361, NUDOCS 9107160356
Download: ML20082B753 (3)

Text

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l ENCLOSURE ORUNSWICK STEAM ELECTRIC PLANT, UNIT 2 l NRC DOCKET NO. 50 324 OPERATING LICENSE NO. DPR 02 REQUEST FOR LICENSE AMENDMENT FUEL CYCLE 10 RELOAD LICENSING j (NRC TAC NO. 80301)

TYPED TECHfitCAL SPECIFICATION PAGES l

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9107160356 910709 PDR ADOCK 05000324

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4 2.0 SAFETY LlHITS AND LlHITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERHAL POWER (Low Pressure or Low Flow) 2.1.1 THERHAL POWER shall not exceed 2$% of RATED THERMAL p0WER with the reactor vessel steam dome pressure less than 800 psia or core flow less than 10% of rated flow.

A,P F PLIC AB I LITY: CONDITIONS I and 2.

ACTION With TilERHAL POWER exceeding 25% o ".ATED TilERHAL POWER and the reactor vessel steam dome pressure less than COO psia or core flow less than 10% of rated flow, be in at l ea s t 110T S P";00WN wi t hin 2 heu r s .

TilERHAL POWER (liigh Pressure and High Flow) 2.1.2 The HINIMUH CRITICAL POWER RATIO (MCPR) shall not be less than 1.07 l

with the reactor vessel steam dome presrure greater than 800 psia and core flow greater than 10% of rated flow.

APPLICABILITY: CONDITIONS I and 2.

ACTION:

With HCPR less than 1.07 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 h,urs.

REACTOR COOLANT SYSTCH 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 psig, be in at least il0T 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 2 2-1 Amendment No.

5.0 DESICN FEATURES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion arec shall be as shown in Figure 5.1.1-1.

LOW p0PULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.

SITE 110VNDARY 5.1.3 The SITE BOUNDARY shall be as showa 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 CONTAINHENT 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 vent s. The suppression chamber is a concrete, steel-lined pressure vessel in the shape of a torus. The primary containment has a minimum f ree air volume of 288.000 cubic feet.

DES.!CN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained f ort

a. Maximum internal pressure 62 psig.

b. Maximum internal temperatures drywell 300'F 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 limited to the tollowing fuel typest= BP8x8R. CEBx8EB, and CE8x8HB-3.

l BRUNSWICK - UNIT 2 5-1 Amendment No.

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