ML20043G473

Proposed Tech Specs Supporting Fuel Cycle 8 Reload Licensing

ML20043G473
Person / Time
Site:	Brunswick
Issue date:	06/13/1990
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20043G472	List: ML20043G471 ML20043G473
References
TAC-76402, NUDOCS 9006200343
Download: ML20043G473 (3)

Text

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[**- . ( ~ . ENCIASURE 1 f, BRUNSWICK STEAM ELECTRIC PIANT, UNIT = 1 -

                                                                         ~NRC DOCKET No. 50 325 OPERATING LICENSE NO. DPR 71--

FUEL CYCLE 8 REIDAD LICENSING (NRC TAC NO. 76402) ,

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A TECHNICAL SPECIFICATION PAGES 4 l

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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINCS o 2.1 SAFETY LIMITS q THERMAL POWER (Low Pressure or Low Finw) 2.1.l' THERMAL POWER shall not exceed 25% of RATED THERMAL POWER with the I reactor vessel steam dome pressure less than 800 psia or core flow less than ) 10% of rated flow. APPLICABILITYt CONDITIONS 1 and 2. ACTION l With THERMAL POWER exceeding 25% of RATED THERMAL POWER and the reactor vessel steam dome pressure less than 800 pois or core flow less than 10% of rated flow, be ia at least HOT SHUTDOWN within 2 hours. THERMAL POWER (High Pressure and High Flow) 2.1.2 The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 1.07 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: With' MCPR 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 hours. 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 psig, be in at least HOT SHUTDOWN with reactor coolant system pressure < 1325 psig within 2 hours. i 5

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BRUNSWICK - UNIT 1 2-1 Amendment No. 124

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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 SOUNDARY shall be as 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 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 f ree [- air volume of (288,000) cubic feet. i l DESIGN TEMPERATURE AND PRESSURE l 5.2.2 The primary containment is designed and shall be maintained fort

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 l -. FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 560 fuel assemblies limited to the 1 following fuel typest BP8x8R, CE8x8EB, and GE8x8NB-3. l , 1 l BRUNSWICK - UNIT 1 5-1 Amendment No. 113

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