ML071430302

Technical Specifications, Allow Additional Startup and Operating Flexibility and an Expanded Operating Domain

ML071430302
Person / Time
Site:	FitzPatrick
Issue date:	05/17/2007
From:	Boska J NRC/NRR/ADRO/DORL/LPLI-1
To:	Kansler M Entergy Nuclear Operations
Boska J P, NRR, 301-415-2901
References
TAC MC9681
Download: ML071430302 (4)

Text

-3-(5) ENO pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 287, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24, 1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989), 135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, April 30, 1986, September 15, 1986 and September 10, 1992 subject to the following provision:

ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire..Amendment No. 287 TABLE OF CONTENTS 1.0 USE AND APPLICATION

1.1 Definitions

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1.1-1 1.2 Logical Connectors

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1.2-1 1.3 Completion Times ................................

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1.3-1 1.4 Frequency

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1.4-1 2.0 SAFETY LIMITS (SLs)2.1 SLs .....................................................................................................

2.0-1 2.2 SL Violations

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2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

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3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

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3.0-3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) ..............................................................

3.1.1-1 3.1.2 Reactivity Anomalies

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3.1.2-1 3.1.3 Control Rod OPERABILITY

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3.1.3-1 3.1.4 Control Rod Scram Times ..................................................................

3.1.4-1 3.1.5 Control Rod Scram Accumulators

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3.1.5-1 3.1.6 Rod Pattern Control ............................................................................

3.1.6-1 3.1.7 Standby Liquid Control (SLC) System ................................................

3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ........ 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ...... 3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) ......................................

3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) .........................................

3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation

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3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation

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3.3.1.2-1 3.3.2.1 Control Rod Block Instrumentation

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3.3.2.1-1 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation

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3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation

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3.3.3.1-1 3.3.3.2 Remote Shutdown System .................................................................

3.3.3.2-1 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation

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3.3.4.1-1 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation

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3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation

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3.3.5.2-1 3.3.6.1 Primary Containment Isolation Instrumentation

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3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation

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3.3.6.2-1 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)System Instrumentation

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.3.3.7.1-1 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation

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3.3.7.2-1 3.3.7.3 Emergency Service Water (ESW) System Instrumentation

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3.3.7.3-1 (continued)

JAFNPP I Amendment 287 Definitions 1.1 1.1 Definitions (continued)

LINEAR HEAT GENERATION RATF II WRH3 LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR)The LHGR shall be the heat generation rate per unit length. o!fuei rod. !t the Integral of the heat flux over the heat transfer area associated with the unit length.A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not Including, the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.The MCPR shall be the smallest critical power that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

I MODE OPERABLE-OPERABILITY (continued)

JAFNPP 1.1-4 Amendment 287 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

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NOTES------------------------------

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.2. When a channel is placed in an Inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.1.2

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Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER ; 25% RTP.Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power is : 2% RTP while operating at > 25% RTP.SR 3.3.1.1.3

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Not required to be performed when entering MODE 2 from MODE I until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.4 Perform a functional test of each RPS automatic 7 days scram contactor.(continued)

I JAFNPP 3.3.1-1-3 Amendment 287