Text

Proposed TS 3/4.3.1,Action a Re Min Number of Operable Channels Per Trip Sys & 3/4.3.2,Action B Re Isolation Actuation Instrumentation Channel Trip Setpoint
	ML20118A648
Person / Time
Site:	LaSalle
Issue date:	09/16/1992
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20118A647	List: ML20118A646; ML20118A648;
References
	NUDOCS 9209240292
	Download: ML20118A648 (25)
	v • d • e

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3/4.3 INSTRUMENTATION

/4.3.1 REACTOR PROTECTTON SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILI1Y: As shown in Table 3.3.1-1.

ACTION:

.a. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channels and/or trip system in the tripped con within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . (TfGoitsions of'SpecRMiQonA074 e shc3o{dition*.applicab % S l

b. With the(tle~in[Nber of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within I hour and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.l g. j g p 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.*** W

4. 3. }. 3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its t limit at ieast once per 18 months. Each test shall include at least one channel l per trip system such that all channels are tested at least once every N times l 18 months where N is the total nuater of redundant channels in a specific reactor trip system.

A With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the (noperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the AC[ ION required by Table 3.3.1-1 for that Trip Function shall we taken.

na If more channels are inoperable in one trip system than in the other, select

' this would thattripsystemtoplaceinthetrippedccndition,exceptwhen/

cause the Trip Function to_ occur,- -

S l # ***The specified 18-month interval may be waived for Cycle vided i pro the / _ ,-

surveillar.ca is performed during Refuel 1, which is to commence no later,h than October 27, 1985. ._ '

,N _ __

LA SALLE - UNIT 1 3/4 3-1 Amendment No. 30 9209240292 920916 i PDR ADOCK 05000373 i p PDR

._, ~

j . .-

4 INSTRUMENTATION i 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING _ CONDITION FOR OPERATION

13.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 i

shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM l RESPONSE TIME as shown in Table 3.3.2-3. '

APPLICABILITY: As shown in Table 3.3.2-1, 2

, ACTION:

! a. With an isolation actuation instrumentation channel trip setpoint 4

less conservative than the value shown in the Allowable Values ;

i column of Table 3.3.2-2, declare the channel inoperable until the l 3 channel is restored to OPERABLE status with its trip setpoint adjusted '

consistent with the Trip Setpoint value.

1 4

-b. With the numbei of OPERABLE channels less than required by the Mini-4 mum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channe](s)_and/or trip system in the tripped con-dition* within one hour. ifhe provisions of~SpecifiFaTIFn 3~0.4~aFe74 i

(riot ~aisiiiliableT" _ j -

c. With the number of OPERABLE channels less than required by the l Minimum OPERABLE Channels per Trip System requirement for both trip i systems, place at least one trip system ** in the tripped condition ***

j within one hour and take the ACTION required by Table 3.3.2-1. '

I i ^An inoperable channel need not be placed in the tripped condition where this 1

would cauca the Trip Function to occur. In these cases, the inoperable channel l j

shall bt restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by l

by Table 3.3.2-1 for that Trip Function shall be taken.

- If more channels are inoperable in one trip system than in the other, select

that trip system to place in the tripped condition except when this would

cause the Trip Function to occur.

r

- - An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to-OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or the ACTION required by

Table 3.3.2-1 for that Trip Function shall be taken.

4 al LA SALLE - UNIT 1- 3/4 3-9 Amendment No. 26

d TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM _ ACTUATION INSTRUMENTATION i

ACTION ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

e

a. With one channel inoperable, place the inoperable channel in the tripped condition within one hou/*)or declara the associated system inoperable. I

b. With more than one channel inoperable declare the associated-

system inoperable.

- ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip Function, place the inoperable channel in the tripped condition within one hcar; restore the inoperable channel to OPERABLE status within 7 days or declare- '

the associated system inoperable.

ACTION 32 - 'With the number of 0FERABLE channels less than required by the Miniaum OPERABLE Channels per Trip Function requiremant, declare the associated ADS trip system or FCCS inoperable.

ACTION 33 -

With the number of OPERABLE channels less than the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

ACTION 34 -

With the. number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE' status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the associated ADS trip system or ECCS inoperable. '

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement i

, a. For one trip system, place that trip system in the tripped condition within one houn*)or declare the HPCS system -

inoperable. .

b. For both trip systems, declare the HPCS system inoperable.

ACTION 36 - With the number of OPERABLE channels less than required _by the Minimum OPERABLE Channels per Trip Function- requirement, place at .least one inoperable channellin the tripped condition within one hocr* or declare the HPCS system. inoperable.--

ACTION 37 -

WiththenumberofOPERABLEinstru[ntslessthantheMini.num Operable Instruments, place the.ihoperable instrument (s) in the tripped condition within I hourW or declare the associated ,

emergency diesel generator' inoperable and take_the ACTION requir-:d by Specification 3.8.1.1 or 't.8.1.2_as-appropriate.

( ~*The n~

provisions of Specification 3.0.4 are not applica5 M i -

LA SALLE - UNIT 1 3/4 3-27 Amendment No. 41 -

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h W.3i e s \ S J h m A U s* \

, INSTRUMEN1ATION f W rr M b '

i RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION I k' S j' $f '

If 4WM Ge t t lf d"]"

LIMITING CONDITION FOR OPERATION 3

3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.

APPLICABILIH: As shown in Table 3.3.7.12-1

! ~ ACTION:

f a. With a radicar.tive gareous effluent monitoring instrumentatior, channel alarm / trip setpoint less conwrvative than required, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.

I

b. With less than the minimum number of radioactive gaseous of fluent J

monitoring instrumentation channels OPERABLE, take the ACYION shown in Table 3.3.7.11-1.

c. The provisions of Soecifications 3.0.3 and 3.0.4 are not applicable.

V SURVEILLANCE REQUIREMENTS

)

4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL. CALIBRATION operations at the frequencies shown in Table 4.3.7.11-1.

v

'A SALLE - UNIT 1 3/4 3-8C

I INSTRUMENTATION 1 .

LOOSE-PART DETECT!0s SYSTEM LIMITING CONDITION FOR OPERATION A

3.3.7.12 The loose part detection system shall be OPERABLE.

1 [ APPLICABILITY: OPERAT*9NAL CONDITIONS 1 and 2. '

5 ACTION:

a. With one or more loose part detection system channels inoperable for i more than 30 days, prepare and submit a Special Report to the

Commission pursuant to Specification 6.6.c within the next 10 days

, outlining the cause of the nalfunction and the plans for restoring

the channel (s) to OPERABLE status.

b. The provisions of Specificatio 3.0.3($nd 3.5[{)are not applicable.

N i

e SURVEILLANCE REQUIREMENTS 3

1 4.3.7.12 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of: '

a. CHANNEL CHrCK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least onco per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.- '

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1 d

1 I

1 LA SALLE - UNIT 1 3/4 3-91 i

. _ - - _ . . . 4 .__ . - _ .

_ _ . _ _ ~ . _ . _ _ _ . .

.L Yb\uk

&f THIS PAGE INTENTI ALLY LEFT BLANK ,

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5 LA SAli.E - UNIT 1 3/4 4-lb Amendment No. <0

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i -

1 !

RE' ACTOR COOLANT SYSTEM f.

3/4.4.4 CHEMISTRY v I f) LIMITING CONDITION FOR OPERATION i

I j 3. 4.A Ine chemistry of the reactor coolant system shall be maintained within the. limits specified in Table 3.4.4-1.

3 APPLICABILITY: At all times.

I

ACTION

i

a. In OPERATIONAL CONDITION 1:

~ 1. With the conductivity, chloride concentration or pH exceeding the 4 limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one !

4- continuous. time interval and, for conductivity and chloride concentra-l tion, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, out with the conductivity 1 less than 10 pmho/cm at 25 C and with the chloride concentration

}ess than 0.5_ ppm..this need not be reported 3o_the Commiss.ionJand (the provisinns of Specification 3.0.4 are not applicable.

~ ~ [, >

~ -

2. With the conductivity, chloride concentration cr pH exceeding the i limit spe:ified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one l continuous time inteival or, for conductivity and chloride concentra-tion, for more than-336 hours per year, be in at least STARTilP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . J l 3. With the conductivity exceeding 10 pmho/cm at 25 C or chloride i concentration exceeding 0.5 ppm, 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 as rapidly as the cooldown rate limit permits. ,

! b. In OPERATIONAL CONDITION 2 and 3 with the conductivity, chloride concentra-

! tion or pH exceeding the limit specified in Table 3.4.4-1 for more than l 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in at least HOT SHUTDOWN within the ne"t 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDONN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

j

! c. At all other times:

i 1. With the conductivity or pH exceeding the limit specified in Table l 3.4.4-1, restore-the conductivity and pH to within the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

[

p y 2. With the chlcrjda_cgqcntr6tivo eweeding the limit- specified in

Table 3.4.4-lCexceeded3for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , perform an engineering -

~

. evaluation to defe~riiifne the effects of the out-of-limit condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the-reactor coolant system remains

acceptable for continued operation prior to proceeding to OPERATIONAL ,

4 CONDITION 3.

l 3. -The provisions of Specification 3.0.3 are not applicable.

LA SALLE - UNIT 1 3/4.4-10

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CONTAINMENV SYSTEMS d(/nE d Tk a /<']'

^

PRIMARY CONTAINMENT AIR LOCKS >

,IMITING CONDITION FOR OPF2ATION 3.6.1.3 Each primary cnntainment air lock shall be OPERABLE with:

a. Both doors -'osed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

. b. An overall air lock leakage rate of less than or equal to 0.05 L, at P,, 39.6 psig.

APPLICABILITY: OPEP.ATIONAL CONDITIONS 1, 2*, and 3.

l ACTION:

a. With one primary co6tainment air lock door inoperable:

1. Maintain et least the OPERABLE air lock door closed and either q restore the inoperable air lock door to OPERABLE status ,1 thin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3. 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4. The provisions of Specification 3.0.4 are not applicable,

b. With the primary containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; a restore the inoperable air lock 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 NOT 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 .

6 I

See Special Test Exception 3.10.1.

LA SALLE - UNIT 1 3/4 6-5 Amendment No. 18

CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPEPATION i 3.6.3 The prin.ary containment isolation valv t

and the reactor instrumentation I

. line excess flow check vehes shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTI0N: _

l a. With one or more of the primary containment isolation valves shown in

, Table 3.6.3-1 inoperable:

1.

!!aintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either; a) Restore the inoperable valve (s) to OPERABLE status, or b) Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,* or c) Isolate each affected penetration by use of at least one

- closed manual _ valve or blind flange.*

s) l d) i The provisions of Specification 3.0.4 are not applicable I provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the affected penetration is

! isolated in accordance with Action a.1.b) or a.1.c) above, }

and provided that the associated system is declared inoper-able, if applicable, and the appropriate action statements w for that syste.3 are performed. -

y

2. q, I Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months b and in COLD SHUTDOWN witt.in the-following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

i With one or more of the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 inoperable:-

I

1. O p

! fA&peCat:io,n.,maycontinue'andtheprovisionsofSpecificationh3 ndl._0.4/are not applicable provided that within 4 hcurs either:-

a) The inoperable valve is returned to OPERABLE status, or b) The instrument line is isolated and the associated instrument is declared inoperable.

2. Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN m within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

$ i

^1 solation valves closed to satifygkheserequirementsmaybereopenedonan intermittent basis under a thTstrative control, t.A SALLE - UNIT 1 3/4 6-22 Amendment No. 25

l e i PLANT SYSTEMS CO2 SYSTEMS L]MITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure 00:' $ E 7 0 "' h "

OPERABLE.*

U Un~ft2da3 M i

a. Division I diesal generator 0 room,

b. Division 2 diesel generator IA room.

c. Division 3 diesel generator 1B room.

' d. Unit 2 Division 2 diesel generator 2A room. ;hrd b

/ whs<r.g APPLICABILITY: Whenever equipment protected by the low pre.u ure CO systems 2 Ts required to be OPEPABLE. ,

ACTION:

a. With one or more of the above required Ir.w pressure CO2 systems inoperable, within I hour establish a t ntinuous fire watch with backup fire suppression equipment for ti sse areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status

} within 14 days or, prepare and submit a Special Report to the Com-

mission pursuant to Specification 6.6.C within the next 30 days l i outlining the action taken, the cause of the inoperability and the j plans and schedule for restoring the system to OPERABLE status.

, . . - a-I b. The provisions of Specification 3.0.3(and 3.0.f are not applicable.

(~ SURVEILLANCE REQUIREMENTS .

i 4.7.5.3 Each of the above required low pressure CO 2 systems shall be d

demonstrated OPERABLE:

~

i a. At least once per 7 days by verifying CO2 storage tank level to be

{i greatcr than 50% full and pressure to be greater than 290 psig, and

b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in the , correct positior..

c. At least once per 18 months by verifying:

1. The system valves and associated motor oper3ted ventilation i

dampers actuate, manually and-automatically, upon receipt of a simulated actuation signal, snd

2. Flow from each nozzle during a " Puff lest."

, *The normal or emergency power source may be inoperable in OPERATIONAL CONDIT]ON 4 or 5 or wkn defueled.

3 i

] LA SALLE - UNIT 1 3/4 7-17 Amendment No. 23 1

, , ,, . , - .--..-, ,. + -

, - - . * - ,,,,,n ,-

~

ELECTRICAL POWER SYSTEMS HOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION L b . 3. 5 - l 3.8.3.3 ThethermaloverloadprotectionofeachvalveshowninTabled.'8M.2;1 shall be bypassed continuously or under accident conditions, as applidbTe J y'D '

an OPERABLE bypass device integral with the motor starter.

APPLICABILITY: Whenever the motor operated valve is required to be OPERABLE.

ACTION:

4 (b.)

' With the thermal overload protection for one or more of the above required valves not bypassed continuously or under accident conditions, as applicable,

(_ by an OPERABLE integral bypass device, take administrative action to continuously bypass the thermal overload within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).

~

('b. TheprovisionsofSpeciffcation3.0.4arenotapplicdg.W l SURVEILLANCE REQUIREMENTS , 4.8.3.3.1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device by the performance of a CHANNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which are normally in force during plant operation and bypassed under accident

' conditions and by verifying that the thermal overload protection is bypassed for those thermal overloads which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing:

a. At least once per 18 month., and

b. Following maintenance on the motor starter.

4.8.3.3.2 The therrt 1 overload protection for the above required valves which are cor.;inuously bypassed shall be verified to be bypassed following testing during which the thermal overload protection was temporarily placed in force.

s e

LA SALLE - UNIT 1 3/4 8-26 Amendment No.18

_ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ _ _ _ . _ . . _ _. _ _ . _ _ ~ . . _ _ . - . . -

4 ELECTRICAL POWER SYSTEMS 6'h W

TABLE 3.8.3.N HOTOR_ OPERATED VALVES THERMAL OVERLOAD j 1 PROTECTION i 1

i ,

BYPASS DEVICE SYSTEM (S)

VALVE NUMBER (Continuous)(Accident Conditions) AFFECTE_D i a. IVG001 Accident Conditions SBGTS j IVG003 Accident Conditions 2VG001 Accident Conditions

] 2VG003 Accident Conditions

! b. IVP113A Accident Conaitions Primary containment i j IVP113B

~ Accident Conditions chilled water coolers IVP114A Accident Conditions IVP1148 Accident Conditions IVP053A Accident Conditions IVP0538 Accident Ccnditions

, IVP063A Accident Conditions

] IVP0638 Accident Conditions i c. IVQO38 Accid,:nt Conditions Primary containtrent j IVQ032 Accident Conditions vent and purge system '

IVQO35 Accident Conditions '

IVQ047 Accident Conditions 1 1VQ048 Accident Conditions .

IVQ050 Accident Conditions

IVQ051 Accident Conditions IVQ068 Accident Conditions IVQO37 Accident Conditions ,

! d. 1WR179 Accident Conditions RBCCW system 1hR180 Accident Conditions 1WR040 Accident Conditions IWR029 Accident Conditions

e. 1821 - F067A Accident Conditions Main steam system 1821 - F067B Accident Conditions 1821 - F067C Accident Conditions -

4' 1821 - F0670 Accident Conditions 1821 - F019 Accident Conditions j 1821 - F016 Accident Conditions 4

4 i

LASALLE-UNIT 1 3/4 8-27 Aundment No. 37 3

. . - . _ - . . - - - . - . - ~- - . . - - - - . . . - - - . _ - - _ - - - - _ - - _

~~

4 TABLE 3. 3. 3. 3$ (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION AN0/0R BYPASS DEVICES BYPASS DEVICE SYSTEM (S) i VALVE NUMBER (Continuous)(Accident Conditions) AFFECTED j e. 1821 - F020 Continuous Main steam system

) 1821 - F008 Continuous 1821 - F070 Continuous j 1821 - F069 Continuous 1821 - F071 Continuous a 1821 - F072 Continuous 1821 - F073 Continuous

f. 1821 - F065A Cor.tinuous Main feedwater system J

1021 - F06SB Continuous i g. 1E21 - F001 Continuous LFCS system i 1E21 - F005 Accident Conditions 1E21 - F011 Accident Conditions IE21 - F012 Accident Conditions

h. IC41 - F001A Accident Conditions SBLCS IC41 - F001B Accident Conditions

, i. 1G33 - F001 Accident Conditions RWCU l 1G33 - F004 Accident Conditions

! j. 1E12 - F052

Accident Conditions RHR system 1E12 - F064

g Accident Conditions i' 1E12 - F087A5 Accident Conditions 1E12 - F004A- Continuous 1E10 - F047A..t~ Continuous IE12 - F048A*) Accident Conditions I

. 1E12 - F003A Continuous

. 1E12 - F026A'*)* Accident Conditions '

l 1E12 - F068A Continuous. .

1E12 - F073A Continuous 1E12 - F074An Continuous- ;

i' 1E12 - F0114*h Accident Conditions 1E12 - F0246"

Accident Conditions.

1E12 - F016

Accident Conditions l 1E12 - F017

Accident Conditions

! 1E12 - F027 *>j - Accident Conditions 4

1E12 - F004B Continuous Continuous

. 1E12-F0478,N IE12 - F048B* Accident Conditions I 1E12 - F003B Continuous-i 1E12 - F0688 Continuous 1E12 - F073B Continuous 1E12 - F074Bm - -Continuous 1E12 - F026S** Accident Conditions

1E12-F011Bh Accident Conditions l x

The specified 18 month interval may be waiv e d for Cycle 1 provided the/

surveillance is performed durinaJefueL1. -- - '

LASALLE-UNIT 1 3/4 8-28 Amendment No. 24 r- e- .,---+r n- r- , , - , , , .e-,rw- vm, .-w.t. per,w ,,. --e y yofg v.-r- m-'-' s w -w a w -,em== w y

u.. . . .. m s 7 s ro s

. W TABLE 3.8.3.di(Continued)

MOTOR OPERA 1ED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICE 5 BYPASS DEVICE SYSTEM (5)

VALVE NUMBE.. (Continuous)(Accident Conditions) AFFECTED

j. 1E12-F0241*[JC Accident Conditions RHR system ;

1E12 - F006B Continuous 1E12 - F015B't Accident Conditions 1E12 - F01/S* LL Accident Conditions IE12-F0423*/ Accident Conditio is 1E12 - F0643*' Accident Conditions 1E12 - F093 Continuous 1E12 - F021d '~ Accident Conditions i ,

. 1E12 - F004C. Cor.tinuous 1E12 - F052BfL Accident Conditions i 1E12 - F087BPi Accident Conditions IF12 .099B*/ Accident Conditions

' 1 :2 - F099AC Accident Conditions 1E12 - F008 Accident Conditions 1E12 - F009 .. Accident Conditions 1E12 - F040A*\ Accident Conditions 1 1E12 - F040B* p- Accident Conditions 1E12 - F049A*l Accident Conditions 1E12 - F0498*! Accident Conditions 1E12 - F053A Accident Conditions c 1E12 - F0538 Accioent Conditions '

1E12 - F006A Continuous 1E12 - F023 , Accident Conditions Accident Conditions 1E12-F027B**k2' 1E12 - F042A* Accident Conditions 1E12 - F042C*/ Accident Conditions 1E12 - F06409 Accident Conditions 1E12 - F094 Continuous

k. 1E51 ~J86 Accident Conditions RCIC system 1E51 - F022 Accident Conditions 1E51 - F068 Continuous 1E51 - F069 Continuous 1E51 - F080 Accident conditions 1E51 - F046 Accident Conditions 1E51 - F059 Accident Coaditions 1E51 - F063 Accident Conditions 1E51 - F019 Accident Conditions 1E51 - F031 Continuous 1E51 - F045 Accident Conditions 1E51 - F008 Accident Conditions 1E51 - F010 Accident Conditions 1E51 - F013 Accident Conditions 1E51 - F064 Accident Conditions 1E51 - F076 Accident Conditions

_ _ ca._

[*The specified 18 month interval may be waived Jr Cycle 1 provided tho' '

\Qrveillance is performed durir.g Refuel 1. _ . ~ . _ -

LASALLE-UNIT 1 3/4 8-29 Amendment No. 24 4

l

e APPLICABILITY SURVfil. LANCE REQUIREMLNTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirements.

4.0.2 Each surveillance Requirement shall be performed within the specified ,

surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

g ~ . . -

4.0.3 Failure to perform a Surveillance Requirement within the specified time Nrd A interval shall constitute a' failure to meet the OPERABILITY requirements for a .

. h,3 q Limiting Condition for Operation. Exceptions to these requirements are stated 4 in the individual Specifications. Surveillancerequirementsdonothavetobe)

,Ij performed on inoperable equipment, j wmt

, .=- -- . ..

3

/ 4.0.4 Entry into an OPERATIONAL CONDITION or other specified conditf6 ,n shall N

not be made unless the Surveillance Requirement (s) associated with the Limiting ..e Condition for Operation nave been performed within the stated surveillence s interval or as otherwise specified. _ _ _ _

,__ _ j 4.0.5' Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 compnents shall be applicable as follows: ,

a. inservice inspection of ASME Code Class 1, 2, and 3 components and -

inservice testing of ASME Code Class 1, 2, and--3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g),.except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i).

b. Surveillance intervals specified in Section XI of the ASML-Boiler and Pressure Vessel Code and applicable Addenda for the inservice

inspection and testing activities required by.the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for-inservice inspection and testing inspection and testing activities activities Weekly At-least once per-7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 . days Semiannually or every_6 months. At least once per 184Ldays Every 9 months At least once per 276 days Yearly or_ annually At least once per 366 days g~ - ,

k'Not applicable to 18 month surveillances required for Unit 2- Cycle 2 operation)rk a

C LA'SALLE UNIT 2 3/4 0-2 AMENDMENT NO. 50.

3/4.3 INSTRUMENTAi!0N 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION

,LlHITING CONDITION FOR OPERATION 3.3.1 As a minimum, tbt reactor protection system instrumentation channels shown in Table .1.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

4 APPLICABillTY: As shown in Table 3.3.1-1.

ACTION:

4

a. With the number of OPERABLE channels less than required by the Mini- .

mum OPERABLE Channels per Trip System requirement for one trip system, I place the inoperable channels and/or trip system in the tripped con-

~

dition*>ithin 1 hoer. /The WoVisions of SpW ficaiioir.0.4 aie~rioNl '

~

(jpplicablev Zi-

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b. With the(thiS~ number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, pl.ce at least one trip system ** in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the f equencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be perforned at least once per 18 months.

4. 3.1. 3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip '

functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per'18 months. Each test shall include at lesst one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.

With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

- If more channels are inoperable in one trip system than in the other, select that trip system to place in the tripped condition, except when this would cause the Trip Function to occur.

LA SALLE - UNIT 2 3/4 3-1 Amendment No.17

k TABLE _3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTAT10N ACTION AC110N 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip function requirement:

a. With one channel inoperable, plac9 the irloperable channel in the tripped condition within one hou(*k lor declare the associated system inoperable,

b. With more than one channel inoperable, declare the associated system inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip function, place the inoperable channel in the tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip function requirement, declare the associated ADS trip system or ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

AC110N 34 - With the number of OPERABLE channels less than required by the Mirimum OPERABLE Channels per Trip function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the associated ADS trip system or ECCS inoperable.

ACTION 35 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement ,

a. For one trip system, place that trip system in the tripped or declare the HPCS system condition within one hourgL inoperable.

b. For both trip systems, declare the HPCS system inoperable.

AC110N 36 - Deleted p ACTION 37 -

With the number of OPERABLE instrym/nts e less thar. the Minimum OPERABLE IN51RUMENTS, place the, inoperable instrument (s) in the tripped condition within 1 hous*)or declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

i

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( *The provisions of Specification 3.0.4 are not applicablej, rA Amendment No. 27, 65

.LA SALLE - UNIT 2 3/4 3-27 l

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPER'.s10N 3.3.7.10 The redioactive liquid efflutnt monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.] are not exceeded. The alarm trip setpoints of these channels shall be determined in accordance with the Offsite Dose Calculation Manual (00CM).

APPLICABILITY: At all times.

AC.40N:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable,

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, in lieu of a Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified,

c. The provisions of Specificatior(s T 3.0.3[E03, and 6.6$B1."bare not applicable. '- '

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- v(

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the-CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CAllBRATION operations at the frequencies.shown in Table 4.3.7.10-1.

i LA SALLE - UNIT 2 3/4 3-81 l

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'Tkt er g in y I $ deriS l e u nemt.g delebd arb.u c.

]T;, 3 p

-INSTRUMENTATION

/ I. S c.Y rv'es *rn upcl.wyrd.

RA010AC11VE GASE0US EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous effluent monitoring instrumentat'on channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip =etpoints set to ensure that the limits of Specification 2.11.2.1 are not exceeded. The alarm / trip setpoints of f.hese channels shall be determined in accordance with the ODCM.

APPLICABILITY: As shown in Table 3.3.7.11-1 ACTIg:

a. With a radioactive gaseous effluent monitoring instrumentation c channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive gaseous ef fluents monitored by the af fected channel or +'clare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

g SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.11-1.

)

^

LA SALLE - UNIT 2 3/4 3-86

I INSTRUMENTATION LOOSE-PART DETECTION SYSTEM L

LIMITING CONDITION FOR OPERATION 3.3.7.12 The loose part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With one or more 100se part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.c within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

,-m

b. The provisions of Specificatio 3. 0. 3( and 3. 0 are not applicable.

SURVEILLla~: REQUIREMENTS 4.3.7.12 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of:

a. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least once-per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

LA SALLE - UNIT 2 3/4_3-91

3 o

REACTOR COOLANT SYSTLH

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ti h< /'

THis PAGE INTENT 10NALL ,LEFT BLANK I

-LA ShlLE - UNIT 2 -3/4 4-2a Amendment No.40

r REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CANDITION FOR OPERATION 3.4.4 :ne chemistry of the reactor coolant system shall be maintained within t h limits specified in Table 3.4.4-1.

APPLICABILITY: At all times.

E

".,jp IL ,( ,

%IION:

4pp '- a. In OPERATIONAL CONDITION 1:

w .,

1. With the conductivity, chloride concentration or pH e.<ceeding the M'g limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one V u 'I continuous time interval and, for cnnducti.ity and chloride concen-tration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, but with the conductivity

', ' ' f}Y; O iess than 10 pmho/cm at 2b*C and with the chloride concentration

'(' #

less than_0.5 ppmr this need not be reported to the Conminion,

~

'ind the provisions of SpesificaWh 3TO'.~4'are not~spp1Tcatil(4

2. With the conductivity, chloride concentration or pH exceedir the limit specified in Table 3.4.4-1 for more than 72 hof i during ore continuous time interval or, for conductivit- 'd chloride enncentration, for more than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months p': 1a at least STARTUP w?.: " the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3. With the con 6.ivity d:eeding 10 pmho/cm at 25 C o, .loride concentration exceed ., .,.5 ppm, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ant in COLD SHLTOOWN as rapidly as the cooldown rate limit permits, n

M b. Ia OPERATIONAL CONDITIONS 2 and 3 with the conductivity, chloride concentration or pH exceeding the limit specified in Tcble 3.4.4-1 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, 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 ,

n- within the f:'llowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

vg '

, c. At all other times:

1. With the conductivity or pH ( ceeding the limit specified in l Table 3.4.4-1, restore the conductivity and pH to within th' limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

2. With the chloride,concentr5 tion exceeding the limit specified in Table 3.4.4-1Qxceededi for more than a hours, perform an

~

engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity c: the reactor s coolant system. Determine that the structural integrity of the reactor coolant system remains acceptrble for continued opera-tion prior to proceeding to OPERATIONAL CONDITION 3.

3. The provisions of Specificatior. 3.0.3 are not applicable.

LA SALLE - UNIT 2 3/4 4-11

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7L a:p./ & ;ny u,a a J 7 <! M d a b ar 4.

CONTAINMENT SYSTEMS Thi s e< ski (I M*

PRIMARY CONTAINMENT AIR LOCKS unkd yd ^

LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERABLE with:

4 .

, a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock-leakage rate of less than or equal to 0.05 L, at P,, 39.6 r,ig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

a. With one primary containment air lock door inoperat.le:

1. Maintain at least the OPERABLE air leck door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of'the next required overall air lock leakage test provided that the.0PERABLE air lock door is verified to be locked closed at least-once per 31 days.

3. Otherwise, b2 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 hours.

4. The provisions.of Specification 3.0.4 are not applicable.

b. With the primary containment air lock inoperable except as a result-of an inoperable air lock door, maintain at laast one air lock door closed; restore the inoperable air lock to DFERABLE status.within 24.

hours or be in at least. HOT SHUTDOWN within the 3xt 12 he'.rs and in COLD SHUTDOWN within the following 24. hours.

7

See Speci 1 Test Exception ?.10.1.

h.

LA SALLE - UNIT 2 3/4 6-5 l

______2_______________-_ _ .- i _ - _ - _ _ - - - - - - - - - - - - - - - - --

o CONTAINMENT SYSTEMS 3/4.G.3 PRIMARY _ CONTAINMENT ISOLATION VALVES LIMITINC CONDITION FOR OPERATION 3.6.3 The primary containment isolation valves and the reactor instrumentation line excess flow check valves shown in Table 3.G.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.

, APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With one or more of the primary containment isolation valves shown in Table 3.6.c 1 inoperable:

1.

Maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either; a) Restore the inoperable valve (s) to OPERABLE status, or b) Isolate each affected penettstion by use of at least ene deactivated automatic valve secured in the isolated position,* or c) Isolate each affected penetration by use of at least onc

_ closed manual valve or blind flange.*

~

2e d) Theprovisionsof5fecification5.~0.4arenotapplicable _ Y_

provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the affected penetration is \

isolated in accordance with Action a.1.b) or a.1.c) above, and provided that the associated system is declared inoper- {

( able, if applicable, and the appropriate action statements /

for that system are performed. '

/

2. Otherwise, be in at least HOT SHI M nN within 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 .

b.

With one or more of the reactor instrumentation line excess flow chech valves shown in Table 3.6.3-1 inoperable:

1. Operation may continue and the provisions of Specification [3.0.3 Marid~3.0.4)are not applicable provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months '

e'ithEF: ' E a) The inoperable valve is returned to OPERABLE status, or b) The instrument line is isolated and the associated instrument is declared inoperable.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 aurs and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(w p,

Isolation valves ciosed to satihy these requirements may be reopened on an intermittent basis under adniinistrative control.

LA SALLE - UNIT 2 3/4 6-25 Amendment No. 14

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a

+

cLECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION s

LIMITING CONDITION FOR OPERATION ,

3.6 3.4--(

3.8.3.3 The thermal overload protection of each valve shown in Table (j58.4.2-}]'-'-

shall be bypassed continuously or under accident conditions, as applicable, by an OPERABLE bypass device integral with the motor starter.

APPLICA8ILITY: Whenever the motor operated valve is required to be OPERABLE.

ACTION:

y (5$ With the thermal cverload protection for one or more of the above-required valves not bypassed continuously or under accident conditions, f- as apolicable, by an OPERABLE integral bypass device, take administra-tive action to continuously bypass the thormal overload within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affacted valve (s) inopercale and apply the appropriate ACTION statement (sf for the affected system (s). '*

, ~ . - - -. - --

~~

Q The provisions of Specification 3.0.4 are not applicable g k SURVEILLANCE REQUIREMENTS g 4.8.3.3.1 The thermal overload protection for the above required valves _shall be verified to be bypassed continuously or under accident conditions, as applicable,-

by an OPERABLE integral bypass device by the performance of a ' CHANNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which' are normally in force during plant operation and bypassed under accident conditions and by verifying that the thermal overload protection is bypassed for those thermal 3 overloads which are continuously bypassed and temporarily placed in force only when the valve motors-are undergoing peciodic-or maintenance testing:

a. At least once per 18-nonths, and

b. Following maintenance on the motor starter.

7 4.8.3.3.2 The thermal overioad protection for the above required valves which are continuously hypassed shall be verified to be bypassed following-testing-during which the thermal overload protection was temporarily placed in force.

LA SALLE - UNIT 2 3/4 8-26

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ML20118A648

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