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| PROPOSED TECHNICAL SPECIFICATION CHANGE E
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| 9404040065 940329 1 PDR ADOCK 0500
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| _ . . _ .. P . ___ - _ . . - . , . . _ _ . _ _ _ _ _ . . . . . . _
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| 'EfACTIVITY CONTROL SYSTEMS . 1 LIMITINGCONDITIONFOROPERATION(Continuedi 1
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| ACTION: (Continue'd) i
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| : 2. If the inoperable control rod (s) is inserted, within 1 hour disarm the ' associated directional control valves ** either:
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| a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.
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| Otherwise, be in at least HOT SHUTDOWN within the next 12 hours.
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| : c. With more than 8 control rods inoperable, be in at least H0T SHUTDOWN within 12 hours.
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| : d. With one scram discharge volume vent valve and/or one scram discharge volume drain valve inoperable and open, restore the inoperable valve (s) to OPERABLE status within 24 hours or be in at least HOT SHUTDOWN within
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| * the next 12 hours.
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| : e. With any scram discharge volume vent valve (s) and/or any scram discharge volume drain valve (s) otherwise inoperable, restore the inoperable valve (s) to OPERABLE status within 8 hours or be in at least H0T SHUTDOWN within the next 12 hours.
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| SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:
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| : a. At least once per 31 days verifying each valve to be open,* and
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| : b. Evaluating scram discharge volume system response prior to plant startup-after each scram to verify that no abnormalities exist.
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| 4.1.3.1.2 When above the preset power level of the RWM, all withdrawn control l rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at ;
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| least one notch: '
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| : a. At least once per 7 days, and
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| : b. Within 24 hours when any control rod is immovable as a result of l excessive friction or mechanical interference.
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| *The'se valves may be closed intermittently for testing under administrative controls.
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| **May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
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| FERMI - UNIT 2 3/4 1-4 Amendment No. E7, EJ 1
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| 1 TABLE 3.3.2-3 ISOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSL. TIME (Sesonds) ;
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| : 1. PRIMARY CONTAINMENT ISOLATION ,
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| : a. Reactor Vessel Low Water Level
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| : 1) Level 3 NA l ,
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| : 2) Level 2 NA l
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| : 3) Level 1 s 1.0* l
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| : b. Drywell Pressure - High NA l
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| : c. Main Steam Line l
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| : 1) Radiation - High NA j. .
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| : 2) Pressure - Low NA l-
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| : 3) Flow - High NA l
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| : d. Main Steam Line Tunnel Temperature - High NA
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| : e. Condenser Pressure - High NA
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| : f. Turbine Bldg. Area Temperature - High NA
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| : g. Deleted
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| : h. Manual Initiation NA
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| : 2. REACTOR WATER CLEANUP SYSTEM ISOLATION
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| : a. A Flow - High NA
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| : b. Heat Exchanger / Pump /High Energy Piping Area Temperature - High NA -
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| : c. Heat Exchanger / Pump / Phase Separator Area Ventilation Temperature AT - High NA
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| : d. SLCS Initiation NA
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| : e. Reactor Vessel Low Water Level - Level 2 flA l
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| : f. Deleted
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| : g. Manual Initiation NA
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| : 3. .81 ACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
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| : a. RCIC Steam Line Flow - High NA l
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| : b. RCIC Steam Supply Pressure - Low NA l
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| : c. RCIC Turbine Exhaust Diaphragm Pressure - High NA
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| : d. RCIC Equipment Room Temperature - High NA
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| : e. Manual Initiation NA FERMI - UNIT 2 3/4 3-18 Amendment No. EJ, fJ ,
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| TABLE 3.3.2-3 (Continuedl ISOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)
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| : 4. HIGH PRESSURE COOLANT INJECTION SYSTEM ISOLATION
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| : a. HPCI Steam Flow - High NA l
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| : b. HPCI Steam Supply Pressure - Low NA l
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| : c. HPCI Turbine Exhaust Diaphragm Pressure - High NA
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| : d. HPCI Equipment Room Temperature - High NA
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| : e. Manual Initiation NA
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| : 5. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION
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| : a. Reactor Vessel Low Water Level - Level 3 NA
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| : b. Reactor Vessel (Shutdown Cooling Cut-in Permissive Interlock) Pressure - High NA
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| : c. Manual Initiation NA -
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| : 6. SECONDARY CONTAINMENT ISOLATION
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| : a. Reactor Vessel Low Water Level - Level 2 NA l !
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| : b. Drywell Pressure - High NA l
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| : c. Fuel Pool Ventilation Exhaust Radiation - High NA j
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| : d. Manual Initiation NA I
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| * Isolation system instrumentation response time for MSIVs only. No diesel generator delays assumed for MSIVs.
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| 1 FERMI - UNIT 2 3/4 3-19 Amendment No. /J,
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| 3/4.8 ELECTRICAL ~ POWER SYSTEMS 3/4.8.1 A.C. SOURCES' l A.C. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
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| : a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and
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| : b. Two separate and independent onsite A.C. electrical power sources, Division I and Division II, each consisting of two emergency diesel generators, each diesel generator with:
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| : 1. A separate day fuel tank containing a minimum of 210 gallons of fuel,
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| : 2. A separate fuel storage system containing a minimum of 35,280 gallons of fuel, and
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| : 3. A separate fuel transfer pump.
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| APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
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| ACTION:
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| : a. With one or both offsite ci uits of the above required A.C.
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| electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours; demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1. within one hour and at least once per 8 hours thereafter and, I
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| : b. With one or both diesel generators in one of the above required l onsite A.C. electrical power divisions inoperable, demonstrate the l l OPERABILITY of the remaining A.C. sources by performing i i Surveillance Requirement 4.8.1.1 I within one hour and at least I l
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| once per 8 hours thereafter, and if the diesel. generator (s) became I inoperable due to any cause other than an inoperable support i system, an independently testable component, or preplanned I preventive maintenance or testing, by performing Surveillance l l Requirement 4.8.1.1.2.a.4 for one diesel generator at a time I
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| )
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| within 24 hours, unless the absence of any potential common mode I failure for the remaining diesel generators is determined. l )
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| Restore the inoperable division to OPERABLE status within 72 hours l 1 or be in at least HOT SHUTDOWN within the next 12 hours and in 1 COLD SHUTDOWN within the following 24 hours. l l
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| FERMI - UNIT 2 3/4 8-1 Amendment No. l l
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| o ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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| : 7. Verifying that. all automatic- diesel generator trips, except overspeed, generator differential. low lube oil pressure, crankcase overpressure, and failure to start are automatically bypassed for an emergency start signal.
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| : 8. Verifying the diesel generator operates for at least 24 hours.
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| During the first 22 hours of this test, the diesel generator shall be loaded to greater than or equal to an indicated 2500-2600 kW and during the remaining 2 hours of this test, the diesel generator shall be loaded to an indicated 2800-2900 kW. The generator voltage and frequency shall be 4160 i 420 volts and 60 t 1.2 Hz within 10 seconds after the start signal;.the steady-state generator voltage and frequency shall be maintained within these limits during this test. Within 5 minutes after completing this 24-hour test, perform Surveillance Requirement 4.8.1.1.2.a.4).* I
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| : 9. Verifying that the auto-connected loads to each diesel generator do not exceed the 2000-hour rating of 3100 kW.
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| : 10. Verifying the diesel generator's capability to:
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| a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power, b) Transfer its loads to the offsite power source, and c) Be restored to its standby status.
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| : 11. Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within i 10% of its design interval.
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| : 12. Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:
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| a) 4160-volt ESF bus lockout.
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| b) Differential trip. <
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| c) Shutdown relay trip.
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| *If Surveillance Requirement 4.8.1.1.2.a.4) is not satisfactorily completed, l it is not necessary to repeat the preceding 24-hour test. Instead, the diesel generator may be operated at an indicated 2500-2600 kW for 2 hours or l until operating temperature has stabilized.
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| FERMI - UNIT 3/4 8-6 Amendment No.}}
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