Text

Amend 99 to License NPF-43,revising Surveillance Requirements for SDV Vent,Drain Valves & Instrumentation & Modifying Required Actions & Surveillance Requirements for EDGs
	ML20073S825
Person / Time
Site:	Fermi
Issue date:	06/28/1994
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20073S827	List: ML20073S825; ML20073S829;
References
	NUDOCS 9407060272
	Download: ML20073S825 (14)
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UNITED STATES t- (Y NUCLEAR REGULATORY COMMISSION i

1 W ASHINGTON. D C 20 % %O001 QLT!LOIT LDISON COMPANY QQ(KET No. 50-341 FERM1-2 AM1NDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-43 l.

The Nuclear Regulatory Commission (the Commission) has found that:

A The application for amendment by the Detroit Edison Company (the licensee) dated March 29, 1994, as corrected April 26, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, e ac+n.ied (the Act), and the Commisslon's rules ana regulat ions set forth in 10 LFk thapter I; i:

The 'ac ility will operate in conf ormity with the application, the pro isions of the Act, and the rules and regulations of the (ommission; T he,+

is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with tho Commission's regulations; D

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

[

lhe issu'oce of this amendment is in accordarce with 10 CFR Part 51 of the Lomm)..sion's regulations and all applicaLie requirements have been satisfied.

)

s 9407060272 940628 PDR ADOCK 05000341 P

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.0,(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

Technical-Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

DECO shall operate the f acility in accordance with the Tecnnical Specifications and the Environmental Protection Plan, 3.

This license amendment is effective as of the date of its issuance with full implementation within 45 days.

F0;. THE NUCLEAR REGULATORY COMMISSION h hl%

Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 28. 199; m

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ATTA(WMNT 10 LICENSE AMENDMENT _NO. 99 fAClllTY OPERATING LICENSE NO. NPF-43 QQCKET NO. 50-;41 Replace the following pages of the Appendix *A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Efft191[

lNSERT 3/4 1-3 3/4 1-3*

3/4 1-4 3/4 1-4 3/4 3-18 3/4 3-18 3/4 3-19 3/4 3-19 3/4 3-20 3/4 3-20*

3/4 8-]

3/4 8-1 3/4 8-2

_3/4 8-2*

3/4 8-3 3/4 8-3 3/4 8-4 3/4 8-4*

3/4 8-5 3/4 8-5*

3/4 8-6 3/4 8-6

. t 4

0verleaf page provided to maintain document completeness.

No changes

- contained on these pages.

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 CONTROL RODS

[0NTROL ROD OPERABILITY 11M1 TIE CONDIT10GMP RAT 10N 3.1.3.1 1.11 cont oi rods shall be OPERABLE.

1 APPLICABILITY:

OPERATIONAL CONDITIONS I and 2.

d ACTION:

E a.

With one control rod inoperable due to being immovable, as a result of excessive friction or mechanical interference, or known to be untrippable:

1.

Within I hour:

a)

Verify that the inoperable control rod, if withdrawn, is separated from all other inoperable control rods by et least two control cells in all directions.

c)

Disarm the associated directional control valves ** either:

1)

Electrically, or

2) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , 2.

Restner the inoperable control rod to OPERABLE status within 4F her-or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

With one or more control rods trippable but inoperable for causes other than addressed in ACTION a, above:

1.

If the inoperable control rod (s) is withdrawn, within I hour:

a)

Verify that the inoperable withdrawn control rod (s) is separated from all other inoperable withdrawn control rods by at least two control cells in all directions, anc b)

Demonstrate the insertion capability of the inoperable with-P drawn control rod (s) by inserting the control rod (s) at 1 ?ast one notch by drive water pressure within the normal operating i

range *.

Otherwise, insert the inoperable withdrawn control rod (s) and discrm the associated directional control valves ** either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water 7

it isolation valves.

I?)

Lf TThe inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.

- May be rearmed intermittently, under administrative contro), to permit testing associated with restoring the control red to OPERABLE status.

FERMI - UNIT 2 3/4 1-3

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REACTIVITY CONTROL SYSTEMS L1MITING CONDITION FOR OPERATION IContinued) l l

ACTION:

(Continued) 2.

If the inoperable control rod (s) is inserted, within I hour disarm the associated directional control valves ** either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUT.'.'0WN within the next 12 houes.

c.

With more then 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , With any scram discharge volume vent valvt(s) and/or any scram discharge e.

volume drain valve (s) otherwise inoperible, restore the inoperable valve (s) to OviRABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SUR'. Tit! ANCF REOUTREMENTS 4.1.3.1.1 The scram discharge vol u.me drain and vert valves shall be de cnstratrd OPERABLE by:

At least once per 31 days verifying each valve to be open,* and a.

b.

Evaluating scram discharge volume system re,ponse prior to plant startup I

after each scram to verify that no abnorralities exist.

l 4.1.3.1.2 When above the preset power level of the RWM, all withdrawn control rods not required to have their directional control valves disarmed elettrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:

a.

At least once per 7 days, and b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is immovable as a result of i

excessive friction or mechanical interference.

lt.ese valves may be closed intermittently for testing under administrative controls.

- May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

FERMI - UNIT 2 3/8 1-4 Amendment No. J/, Ef 99

TABLE 3.3.2-3 ISOLATION ACTUATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)

I 1.

PRIMARY CONTAINMENT ISOLATION s

a.

Reactor Yessel Low Water Level 1)

Level 3 NA g

2)

Level ?

NA g

3)

Level 1 s 1.0*

l b.

Drywell Pressure - High NA g

c.

Main Steam Line

~

{

1)

Radiation - High N/.

l 2)

Pressure - Low NA

[

3)

Flow - High NA l

d.

Main Steam Line Tunnel Temperature - High NA e.

Condenser Pressure - High NA f.

Turbine Bldg. Area Temperature High NA g.

Deleted h.

Manual Initiation NA 2.

RIAClQR WATER CLEANUP SYSTEM ISOLATION a.

A Flow High NA b.

Heat..tv nget/ Pump /High Energy Piping Area Tempeieture - High NA c.

Heat Exchanger / Pump / Phase Separator Area Ventilation-Temperature AT - High NA d.

SLCS Initiation NA e.

Reactor Vessel low Water level - Level 2 NA

{

f.

Deleted g.

Manual. Initiation NA 3.

REACTOR CORE ISOLATION COOLING SYSTEM _lSOLATION a.

RCIC Steam Line Flow - High NA l

b.

RCIC Steam Supply Pressure - Low NA l

c.

RCIC Turbine Exhust Diaphragm Pressure - High NA d.

RCIC Equipment Room Temperature - High NA e.

Manual Initiation NA 4-FERMI - UNIT 2 3/4 3-18 Amend.nent No. JJ $7,99 i

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TABLE 3.3.2-3 (Continued) 11QLAT10N ACTUATION SYSTEM INSTRUMENTATION REGPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds) l 4.

HIGH PRESSURE COOLANT INJECTION SYSTEH ISOLATION a.

HPCI Steam Flow - High NA l

b.

HPCI Steam Supply Pressure - Low NA l-HPCI Turbine Exhaust Diaphragm Pressure - High NA c.

d.

HPCI Equipment Room Temperature - High NA Minual Initiation NA S.

PHR SYSTEM SHUTDOWN COOLING MODE 150LATIGN a.

Reactor Vessel Low Water Level Level 3 NA b.

Reactor Vessel (Shutdown Cooling Cut in Permissive Interlock) Pressure - High NA c.

Manual Initiation NA E.

Slip'dDARY CONTAINMENT [ SOLATION a.

Reactor Vessel Low Water Level - Level 2 NA l

b.

Dryweil Pressure - High NA l

f el Pool Ventilation Exhaust Radiation - High NA l

c.

u d.

Manual Initiation NA I

l 1

I I

lsolation system instrumentation response time for MSIVs only. No fiesel generator delays assumed for MSIVs.

l I

j l

I FERMI rJ31T 2 3/4 3-39 Amendment No. $1, 99 s

l l

a

i TABtf 4.3 1.l_I_

m IS0l ATION ACTUATION ;NSTRUM[NTATION StlRVElll ANCE REQUIREMENTS CHANNIL OPERAT10NAL c

(.eiT "*lE l FUNCil0NAL CHANNEL CONDITIONS FOR WHICH

[

TRIP FUNCTION

_CilECA TEST CAllBRATION SURVElllANCE REQUIRED ER] MARY CONTAINMENT ISOLATION a.

Reactor Vessel low Water level-8 1) level 3 5

Q R

1, 2, 3 8

R 1, 2, 3 2) level 2 5

0' 3) level 1 5

Q R

1, 2, 3 b.

Dr/well Pressure - liigh 5

0 R

1, 2, 3 8

c.

Main Steam Line l

Y 1)

Radiation - High 5

Q R

1, 2, 3 I

E 2)

Pressure - Low 5

Q R

1 I

3)

Flow - High S

Q R

1, 2, 3 d.

Mala Steam 1.Ine Tunnel iemperature - liigh S

Q R

1, 2, 3 I

e.

Co idenser Pressure - High S

Q R

1, 2**, 3**

I A

f.

Tarbine Bldg. Area g

Temperature - High S

Q R

1, 2, 3 I

g a$l g.

Deleted h.

Manual Initiation NA R

NA 1, 2, 3 h.

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}/4.8 ELECTRICAL POUER SYSTEMS ll/4. L1 A.C. SOURCES 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:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system, and 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:

1.

A separate day fuel tank containing a minimum of 210 gallons of fuel, 2.

A separate fuel storage system containing a minimum of 35,280 gallons of fuel, and 3.

A separate fuel transfer pump.

6PPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With one or both offsite circuits of the above required A.C.

electrical power sources inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; demonstrate the OPERABILITY of the remaining A.C. srurces by performing Surveillance Requirement 4.8.1.1.1. within one hour ard at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter and, l

b.

With one or both diesel generators in one of the above required onsite A.C. electrical power divisions irgerable, demonstrate the OPERABILITY of the remaining A.C. scurces by perforiaing Surveillance Requirement 4.8.1.1.1 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months therer?ter, and if the diesel generator (s) became l

inoperable due to any case other than an inoperable support I

syttem, an independently testable component, or preplanned I

preventive mainterance or testing, by performing Surveillance l

Requirement 4.8.1.3.2.a.4 for one diesel generator at a time l

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , un:ess the absence of any potential common mode i

failure for the remaining diesel u nerat' ors is determined.

I Restore the inoperable division to OPERAGLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hnurs and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , rERMI - UNIT 2 3/4 8-1 Amendment No. 99 l

l

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) c.

With one or )oth diesel generators in one of the above required onsite A.C. electrical power divisions inoperable, 19 addition to ACTION b, above, verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months that all required systems, subsystems, trains, components and devices that depend on the remaining onsite A.C. electrical power division as a source of emergency power are also OPERABLE; otherwise, be in at least HOT SHUTDOWN wi'hin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d With both of the above required onsite A.C. electrical power divisions inoperable, 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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at lear.t one of the above required inoperable divisions to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the followf9g 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Pestore both of the above required divisions to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3

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FERMI - UNIT 2 3/4 8-2

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T1((TRICAk PNER SYSTEMS

[

SURVEfttANCE RE0VIREMENTS E

4.8.1.1.1 Each of the above required indepem ent circuits between the offsite transmission network and the onsite Class lE-distribution system shall be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.

4.8.1.1.2 Each of the above required diesel generators shall be demonstrated-3 OPERABLE:

a.

In accordance with the frequency specified in Table 4.8.1.1.2-1 on a STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day fuel tank.

2.

Verifying the fuel level in the fuel storage tank.

3.

Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank.

4 Verifying the iesel starts from ambient condition and accelerates to a* ieast 900 rpm in less than or equal to 10 seconds.* The generator voltage and frequency shall be 416b t 420 volts and 60 t 1.2 Hz within 10 seconds after the r, tart signal.

The diesel generator shall be started for this ted bv using one of the following signals:

a)

Manual, b)

Simulated loss-of-offsite power by itself.

c)

Simulated los s-of-offsite power in conjunction with an ESF actuation test signal.

d)

An ESF actustion test signal by itself.

5.

Verifying the diesel generator is synchronized, loaded to greater than or equal tr.n indicated 2500-2600 kW in accordance with the manufacturer's recommendations, and I

operates with this load for at least 60 minutes.

l 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

7.

Verifying the pressure in all diesel generator air start receivers to be greater than or equal to 215 psig.

J

All diesel generator starts for the purpose of this Surveillance Requirement may be preceded by an engine prelube period. The diesel generator start (10 sec) from ambient conditions shall-be perform-d at least i

once per-184 days in these surveillance tests.

All other engine starts for the purpose of this surveillance testing may be oreceded by sther warmup procedures recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.

FERMI - UNIT 2 3/4 8-3 Amenoment No. 99

l ELECToICAL POWER SYSTEMS SURVEILLANCE REQUIREMFNTS (Continued)

I b.

By removing accumulated water:

1.

From the day tank at lest once per 31 days and after each occasion when the diesel is operated for greater than I hour, and 2.

Fron the storage tank at least once per 31 days.

c.

By sampling new fuel oil in accordance with ASTM D4057-88 prior to addition to the storage tanks and:

1.

By s erifying in accordance with the tests specified in ASTM 097!.-91 prior to addition to the storage tanks that the sample has:

a)

An Apl Gravity of within 0.3 degrees at 60'F or a specified gravity of within 0.0016 at 60/60*F, when compared to the supplier's certificate or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or equal to 0.89 or an Apl gravity at 60*F of greater than or equal to 27 degrees but less than or equal to 39 degrees, b)

A kinematic viscos" at 40*C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by comparison with the supplier's certification.

c)

A flash point equal to or greater than 125'F, and d)

A clear and bright appearance with proper color when tested in accordance with ASTM D4176-B6.

2.

6y vsrifying with 31 days of obtaining 'che sample that the otbar properties specified in Table 1 of ASTM D575-91 are met when tested in accordance with ASTM 0975-91.

d.

At least once every 31 days by obtaining a sample of fuel oil from the storage tanks in accordance with ASTM D2275-88, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM D2276-88, Nethod A.

At least once per 18 months by:

e.

1 1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

FERMI - UNIT 2 3/4 8-4 Amendment No. 90,95 0CT 2 91933

~.

ELECTRICAL POWER SYSTEMS SL'RVEILLANCE REQUIREMENTS (Continued) 2.

Verifying the diesel generator capability to reject 6 load of greater than or equal to 1666 kW while maintaining engine speed less than the nominal speed plus 75% of the difference between nc.3inal speed and the overspeed trip setpoint or 115% of nominal speed, whichever is lower.

3.

Vr ifying the diesel generator capability to reject a load of.

2850 kW without tripping.

The generator voltage shall not exceed 4784 volts during and following the. load rejection.

4.

Simulating a loss-of-offsite power F3 itself, and:

a)

Verifying deenergization of the emergency busses and load shedding from the emergency busses.

b)

Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds, energizes the autocon-nected loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads.

After energization, the steady-state voltage and frequency of the emergency be::::

shall be maintained at 4160 420 volts and 60 1.2 Hz during this test.

E.

Verifying that on an ECCS actuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on st'andby for greater than or equal to 5 minutes; The generator voltage and frequency shcil be 4160 1 420 volts and 60 1 1.2 Hz within 10 seconds after the auto-start signal; the steady-state. generator voltage and frequency shall be maintained within these limits during this test.

6.

Simulating a loss-of-offsite' power in conjunction with an ECCS actuation test signal, and:

a)

Verifying deenergization of the emergancy busses and load shedding from the emergency busses.

b)

Verifying the diesel generator starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 10 seconds energizes the auto-connected shutdown inads'through the load sequencer and operates for greater than or equr.i to B minutes while its generator is loaded with the emergency loads.

After energization,-the steady-state voltage and frequency of the emergency busses-sha',1 be maintained at 4160 1 420 volts and 60 1 1.2 Hz during this test.

FERMI - UNIT 2 3/4 8-5

1 f.1ECTRICAL POM R SYSTEMS I

EUDVEf tM3CE RE0010EMENTS (Continued) 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.

8.

Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

During the first 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of this test, the diesel generator shall be loaded to an indicated 2800 2900 kW. The generator voltage and frequency shall be 4160 t 420 volts and 60 a 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 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test, perform Surveillance Requirement 4.8.1.1.2.a.4)

l 9.

'nrifying that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating of 3100 kW.

10.

Verifying the diesel generator's capability to:

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.

11.

Verifying that the automatic load sequence timer is OPEPABLE with the interval between each load block within 10', of its design interval.

12.

Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) 4160-volt ESF bus lockout.

b)

Differential trip.

c)

Shutdown relay trip.

~

1f 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 cient nenerator may be operated at an indicated 2500-2600 kW for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or l

until operating temperature has stabilized.

FERMI - UNIT 3/4 8-6 Amendment No.99 l

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ML20073S825

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