ML20098A986

Proposed Tech Specs Re Reactor Water Cleanup Pump Room High Ambient & High Differential Temp Isolation

ML20098A986
Person / Time
Site:	LaSalle
Issue date:	09/19/1984
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20098A985	List: ML20098A979 ML20098A986
References
NUDOCS 8409250347
Download: ML20098A986 (30)

Text

.s INSTRUMENTATION .

3 '

l 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION

~

3.3.2 The isolation actuation instrumen,tation channels shown in Table 3.3.2-1 shall be OPERA 8LE with their trip setpoints set consistent with the vatues shown in the Trip 5etpoint column of Table 3.3.2-2 and with ISQLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICA81LITY: As shown in Table 3.3.2-1. -

M:

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values -

column of Table 3.3.2-2, declare' the channel inoperable until the channel is restored to OPERA 8LE status with its trip setpoint adjusted consistent with the Trip 5etpoint value. -

b. With the number of OPERA 8LE channels less than required by the Minimum CPERA8LE Channels per Trip System requirement for one trip

. system, place that trip system in the tripped condition

• within one hour. The provisions of Specification 3.0.4 are not applicable.

-~ ,

With the number of OPERA 8LE channels less than required by the c.

Minimum QPERABLE #

Channels per Trip System requirement.for both trip systems, place at 1 east one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.

"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 channet shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required 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.

8409250347 840919 PDR ADOCK 05000373 PDR p

Mo c.ky (7) .

m,, c =.O. <*~= 4.

oh LA SALLE - UNIT 1 3/4 3-9 -

INSTRUMENTATICN .

- . m '

t' SURVEILLANCE REQUIREMENTS

.f 4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated CPERA8LE 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 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulate'd automatic operation of all channels shall be performed at least once per 18 months.

4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least 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 isolation trip system.

8 e A

6 0

[. -

~ cw.

a D 1}.

t 4 W h

. -LA SALLE - UNIT.1 .

3/4 3-10 .

e

TABLE 3.3.2-1 -

5 u, ISOLATION ACTUATION INSTRUNENTATION 5 VALVE GROUPS MINIMUM OPERA 8LE APPLICA8LE e OPERATED BY CHANNELS PER OPERATIONAL c TRIP FUNCTION SIGNAL (a) TRIP SYSTEN (b) CONDITION ACTION A. AUTONATIC INITIATION

1. PRINARY CONTAlfetENT ISOLATION

a. Reactor Vessel Water Level (1) Low, Level 3 7 2 1, 2, 3 20 (2) Low Low, Level 2 1,2,3 2 1,2,3 20

b. Drywell Pressure - High 2, 7 2 1,2,3 20

c. Main Steam Line

1) Radiation - High 1 2 1,2,3 21 9w 3 2 1,2,3 22 01w 2) 3)

Pressure - Low Flow .tigh 1

1 2

2/11ne I 1

1,2,3 23 .

21 h d. Main Steam Line Tunnel

(* Temperature - High 1 2 1,2,3 21

e. Mair. Steam Line Tunne'l l A Temperature - High 1 2 I II) ,2 II) ,3fI) 21 I h f. Condenser Vacuum - Low 1 2 1, 2* , 3* 21 i 2. SECONDARY CONTAlletENT ISOLATION

a. Reactor Building Vent Exhaust I

$ Plenum Radiation - High 4(* (*) 2 1, 2, 3 and ** 24 g

b. Drywell Pressure - High 4(c)(e) 2 1,2,3 24

{

a

c. Reactor Vessel Water Level - Low Low, Level 2 4 ICII*) 2 1, 2, 3, and 24

d. Fuel Pool Vent Exhaust '* ..

5 Radiation - High 4("}(*} * '

r: t

TABLE 3.3.2-1 (Continued) j

.- G '

m- ISOLATION ACTUATION INSTRUNENTATION '

o .N '-

E . VALVE GROUPS MINIMUN OPERABLE APPLICA8LE .l l

e- OPERATED BY CHANNELS PER OPERATIONAL CONDITION ACTION g TRIP f ullCTION SIGNAL (a) TRIP SYSTEM (b) .

[ 3. Ht; ACTOR WATER CLEANUP SYSTEM ISOLATION

.. A Flow - liigh 5 1 1,2,3 -

22

b. lleat Exchanger Area  ?

Temperature - liigh 5 1 1,2,3 22

c. Ileat. Exchanger Area Ventilation AT - High 5 1 1,2,3 22.

d. P~7 ".r:: tweeLie 00ig. 5 i .1, 2, 3 . r_ P7 'r : '!: tH:tL: t.!  ? , 2, 3 O w -H iv;. -- -5 1 kd SLCS Initiation S III NA 1, 2, 3 22 -

w A , Reactor Vessel Water Level - Low Low, Level 2 5 2 1,2,3 22

4. 141 ACTOR CORE IS0tATION COOLING SYST[N IS0L'ATION 5.' RCIC Steam Line flow - High 8 , g 1 1, 2, 3 22 1,. RCIC Steam Supply Pressure - low ,

8, 9 gg) 2 1,2,3 22 c.

RCIC Turbine Exhaust Diaphragm Pressure - High 8 2 ' 1, 2, 3 22 ii. RCIC Equipment Room .

Temperature - liigh 8 1 1,2,3 22

e. RCIC Steam Line Tunnel Temperature - High 8 1 1,2,3 22 I. RCIC Steam Line Tunnel a Tenperature - liigh 8 1 1,2,3 22 9 Drywell Pressure - liigh 9 f9) 2 1,2,3 22 1 e

. .. - . : . . . , . - - . .. .L .:. 9 . , -.. . . . . : . : 5 . . . . -. ..? ~ - -, .. :.... . X

) . .

TABLE 3.3.2-1 (Continued)

E .

. ISOLATION ACTUATION INSTRtBENTATION D MINIMUM OPERA 8LE APPLICABLE

VALVE GROUPS

, OPERATED BY CHANNELS PER OPERATIONAL TRIP Flit 4CTION SIGNAL (a) TRIP SYSTEM (b) CONDITION ACTION , ,

e i 3

-i 5. RitR SYSTEM STEAM CONDENSING MDOE ISOLATION 1 e .

i .s . RHR Equipment Area .

} A Temperature - High 8 1 1,2,3 22 4

b. RHR Area Temperature -

1 High 8 1 1, 2, 3 22 6

l c. AllR Heat Exchanger Steam Supply flow - High 8 1 1, 2, 3 22 ..

l

6. RilR SYSTEM SiluTDOWN COOLING MDOE ISOLATION i

7 U, 1:* .. Reactor Vessel Water i

• Level - Low,. Level 3 6 2 1, 2, 3

.' w

,25 A

w

1. . Reactor Vessel .

. (RilR Cut-in Permissive) j Pressure - High 6 1. 1, 2, 3 25 l c. RilR Pump Suction Flow - High 6 1 1,2,3 25 i

+

d. RelR Area Temperature -

j liigh 6 1 1,2,3 25

e. RilR Equipment Area AT - High 6 1 1,2,3 25 >

j p e

1

B. MANilAl INITIATION .

4

1. Is. hoard Valves 1,2,5,6,7 1/ group 1, 2, 3 26

} 2. Outboard Valves 1,2,5,6,7 1/ group 1, 2, 3 26

3. Intsoard Valves 4 (c) (e) 1/ group 1, 2, 3 and **,8 26

• • ""'**'d Ives 4( } ( } 1/ group 1, 2, 3 and **,8 26  ;

0 26 j{ 5. Is. hoard Valves 3,8,9 1/ valve 1, 2, 3 j LF 6. husboard Valves 3,8,9 1/ valve 1, 2, 3 26 1

! . - 7. Outboard Valve 8 II'I 1/ group 1, 2, 3 26 i

1

1 1 -

TA8LE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION e ACTION 20 -

Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN with the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21. - Se in at least STARTUP with the associated isolation valves 1

closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least H0T SHUTDOWN within.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 22 -

Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and l declare the affected system inoperable.

ACTION 23 - 8e in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

~ ACTION 24 '- Establish SECONDARY CONTAINNENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. l ACTION 25 -

Lock the affected system isolation valves closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.  :

2- ACTION 26 - Provided that the manual initiation function is OPERA 8LE for

'; each other group valve, inboard or outboard, as applicable, in *

!i- ,

, each line, restore the manual initi4 tion function to OPERA 8LE 4

status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, restore the manual initiation function to 0PERA8LE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise:

a. 8e in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or

b. Close the affected system isolation valves within the next hour and declare the affected system in operabla.

. NOTES

!F

• Nay be bypassed with reactor steam pressure < 1043 psig and all turbine_

j stop valves closed.

• • When handling irradiated fuel in the secondary containment and during CORE

ALTERATIONS and operations with a potential for draining the reactor vessel.

l. # During CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

(a) See Specification 3.6.3, Table 3.6.3-1 for valves in each valve group.

[ (b) A channel'may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for

required surveillance without placing the trip system in the tripped -

]' condition provided at least one other OPERA 8LE channel in the same trip i- system is monitoring that parameter.

(c) Also actuates the standby gas treatment system.

!- (d) A channel is 0PERA8LE if 2 of 4 instruments in that channel are OPERA 8LE.

4, (e) Also actuates secondary containment ventilation isolation dampers per

• Table 3.6.5.2-1.

(f) Closes only RWCU system inlet outboard valve.

(g) Requires RCIC steam supply pressure-low coincident with drywell pressure-high.

, (h) Manual initiation isolates 1E51-F008 only an'd only with a coincident i, reactor vessel water level-low, level 3, signal. ,

i (i) Both channels of each trip system may be placed in an inoperable status for up -

to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for required reactor building ventilation filter change and damper cycling without placing the trip system in the tripped condition provided that i the ambient temperature channels in the same trip systems are operable.

LA SALLE - UNIT 1 3/4 3-14 Amendment No. 18 M

c%q. , @ rd40t.wc4lLaWh

. ~ .

3 TABLE 3.3.2-2 -

5 ISOLATION ACTUATION INSTRUNENTATION SETPOINTS E

r- ALLO MBLE E TRIP FUNCTION TRIP SETPOINT VALUE

$, e

' A. AUTOMATIC INITIATION i5 1. PRINARY CONTAIISENT ISOLATION

-e j w . a. Reactor Vessel Water Level i 1) Low, Level 3 > 12.5 inches * > 11.0 inches" '

i

2) Low Low, Level 2 5 -50 inches

• I -57 inches

• q b. Drywell Pressure - High 31.69psig , ,

51.89psig

c. Main Steam Line

1) Radiation - High 5 3.0 x full power background 1 3.6 x full background'

2) Pressure - Low > 854 psig > 834 psig

. 3) Flow - High 1 111 psid 1 116 psid

d. Main Steam Line Tunnel '

Temperature - High -< 140*F

< 146*F

~ l i

l 4

e. Hain Steam Line Tunnel

< 42*F l

, A Temperature - High < 36*F Y f. Condenser Vacuum - Low I 7 inches Hg vacuum F 5.5 inches Hg vacuus i

5 '

2. SEC006ARY CONTAlletENT ISOLATION ,.

a. Reactor Building Vent Exhaust

' Plenum Radiation - High < 10 nr/hr < 15 ar/hr l l b. Drywell Pressure - High 31.69psig $1.89psig

! c. Reactor Vessel Water Level - Low Low, Level 2 > -50 inches *

> -57 inches *

d. Fuel Pool Vent Extaust

! Radiation - High 5 10 ar/hr 1 15 ar/hr l 1

i 3. REACTOR WATER CLEANUP SYSTEN ISOLATION i 5 a. AFlow - High 1 70 gpa 1 87.5 gpa j

{

b. Heat Exchanger Area Temperature

- High < 181*F

< 187'F g

5 c. Heat Exchanger Area Ventilation AT - High < 85*F < 91*F l z

! . d. " 7 ". :: ! ;:c;"_r;  ;.;e, 7 . .. . s act r i w  :.

6 I ; ^^.' I is^i

' " .,AS. .SLCS

- ; , c.;Initiation t";;.".G e" ; . i.T HA HA ,,

1 A Reactor Vessel Water Level - > -50 inches * > -57 inches

• Low Low, Level 2 4

i_____ _ ___ __

• /%.

p e ,

L u .

~~

4 f:s . TABLE 3.3.2-2.(Continued)

.-E- ,r' .

in ISOLATION ACTUATION INSTRUNENTATION SETPOINTS 3" r-

• m ALLOWA8tE '

^

e TRIP FUNCTION TRIP SETPOINT' VALUE -

c -

t 3' 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION 4 * ~

" a. RCIC Steam Line Flow - High $ 295% of rated flow, 185" H 2O -

$'290% o'f rated floet. 178" H 2O

( b. RCIC Steam Supply Pressure - Low 1 57 psig 1 53 psig RCIC Turbine Exhaust Diaphragm -

E- c.

-p Pressure High 5 10.0 psig $ 20.0 psig

d. 'RCIC Equipment Room Temperature - High 1 200*F $ 206*F g i e. RCIC Steam Line Tunnel j Temperature - High 1 200*F $ 206*F l

f. RCIC Steam Line Tunnel- ,

~

A Temperature - High' $ 123*F l w $ 117*F

} g. Drywell Pressure - High 1 1.69 psig $ 1.89 psig

[

t w -

! A 5. RHP SYSTEM STEAM CONGENSING MODE ISOLATION, ,

i k RHR.' Equipment Area

! a.

y A Temperature - High 1 50*F $ 56*F l

b. RHR Area Cooler Temperature -

b( '

High 1 200*F $ 206*F l

c. RHR Heat Exchanger Steam g Supply Flow - High 1 123" H 2O $ 128" H 2O

!O F

u

e--- 3

.- g

! 5

m

! l i

.. a . .-

TABLE 3.3.2-2 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SETPO.tNTS

'~ -

ALLOWASLE TRIP SETPOINT VALUE i TRIP FUNCTION l

e i5 6. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

-i .

" a. Reactor Vessel Water Level -

Low, Level.3 1 12.5 inches

• 1 11.0 inches

• Reactor Vessel p b (RHR Cut-in Permissive) 1 145 psig**

Pressure - High 5 135 psig** g

.p[ .c. RHR Pump Suction Flow - High 1 180" H 2O

$ 186" H 2O l

w d. RHR Area Cooler Temperature -

l l

) High 1 200*F $ 206*F

~

g e. RHR Equipment Area AT - High 1 50*F $ 56*F l .

w j Not Applicable Not Applicable  ;

7 8. NANUAL INITIATION  ;

O) i 1. Inboard Valves

2. Outboard Valves i I Inboard Valves 3.

4. Outboard Valves *

5. Inboard Valves 3 6. Outboard Valves P ~7. Outboard Valve 1

'f R

• See Bases Figure B 3/4 3-1.

g .I

. ** Corrected for cold water head with reactor vessel flooded. I j c -- E,  ;

e .

. o 4

9 e

• J

. ___ , .. _. . , , , . . . . , . . , . _ ~ . _ . . . . . . . ,

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

A. AUTOMATIC INITIATION

1. PRIMARY CONTAINMENT ISOLATION

a. . Reactor Vessel Water Level

1) Low Level 3 NA

2) Low Low, Level 2 11.g/g13(,),

b. Drywell Pressure - High. i 13

c. Main Steam Line

1) Radiation - High(b)

2) Pressure - Low 1 1.0*/113 1 1.0*/5 13((a)**

,) ,

3) Flow - High 1 0.S*/5 13g ,) ,

d. Main Steam Line Tunnel Temperature - High NA

e. Condenser Vacuum - Low NA

f. Main Steam Line Tunnel A Temperature - High NA

2. SECONDARY CONTAI'NMENT ISOLATION

a. Reactor Buildinggnt Exhaust Plenum )

Radiation - High < 13

b. Drywell Pressure - High 513

c. Reactor Vessel Water Level - Low, Level (g) < 13'

d. Fuel Pool Vent Exhaust Radiation - High 513(*)

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High 1 13(*)

b. Heat Exchanger Area Temperature - High NA

c. Heat Exchanger Area Ventilation AT-High NA

,,Rd. SLCS Initiation. - - . . . . . . . . . _ . . NA A Reactor Vessel Water Level - Low Low, Level 2 1 13(")

4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

a. RCIC Steam Line Flow - High < 13(*)  !

b. RCIC Steam Supply Pressure - Low 513(")

c. RCIC Turbine Exhaust Diaphragm Pressure - High NA

d. RCIC Equipment Room Temperature - High NA

e. RCIC Steam Line Tunnel Temperature - High NA

f. RCIC Steam Line Tunnel A Temperature - High NA

g. Drywell Pressure - High NA

5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION

a. RHR Equipment Ares a Tecperature - High NA

b. RHR Area Cooler Temperature - High NA

c. RHR Heat' Exchanger Steam Supply Flow High NA LA SALLE - UNIT 1 3/4 3-18 Amendment No. 18

~ r RBLE3.3.2-3(Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#

6. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

a. Reactor Vessel Water Level - Low, Level 3 < 13(a)

b. Reactor Vessel (RHR Cut-In Permissive) Pressure - High N.A. I

c. RHR Pump Suction Flow - High N.A. l

d. RHR Area Cooler Temperature High N.A. l

e. RHR Equipment Area AT High N.A. g B. MANUAL INITIATION N.A.  ;

1. Inboard Valves

2. Outboard Valves -

3.* Inboard Valves

4. Outboard Valves

5. Inboard Valves

6. Outboard Valves

7. Outboard Valve (a) The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME. Isolation systec instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.

(b) Radiation detectors are exempt from response time testing. Response time shall be measured from detector output or the input of the first electronic component in the channel.

Isolation system instrumentation response time for MSIVs only. No diesel generator delays assumed.

• • Isolation system instrumentation response time for associated valves except MSIVs.

1. Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

N Without 4S+1 second time delay.

1. 1. Without < 5 second time delay. g N.A. Not Applicable.

g LA SALLE . UNIT 1 3/4 3-19 Amendment No.18 NcM. For- e at b w c.s t oA

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

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

~ .- -

e .

n ..

C TABLE 4.3.2.1-1 k h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCC REQUIREMENTS I E CllANNEL OPERATI':NAL CONDITIONS (DR WHICH

• CllANNEL FUNCTIONAL CHANNEL 7 g TRIP __ FilHCTION CilECK TEST CALIBRATION SURVEILLANCE REQUIRED

~

[ U.

~

A AulollAllt INITIATION

1. PRIMARY CONTAINHENT ISOLATION q

= Reactor Vessel Water Level -

a.

E 1) Low, Level 3 S M R 1, 2, 3

2) Low Low, Level 2 S M R 1, 2, 3 ,

l. . Drywell Pressure - lii 0h NA M Q 1, 2, 3 f _

c. Main Steam Line

1) Radiation - liigh 5 M R 1, 2, 3

> 2) Pressure - Low NA M Q 1 .

% 3) Flow - liigh S M R 1, 2, 3

d. Main Steam Line Tunnel Temperature - liigh NA M R 1, 2, 3 1, 2*, 3*

L g e. Condenser Vacuum - Low NA M Q

• t. Main Steam Line Tunnel , .

y A Temperature - liigh NA M R 1, 2, 3

$ 2. -SECONDARY CONTAINHENT ISOLATION r

a. Reactor Building Vent Exhaust Plenum Radiation - liigh S' H R . 1, 2, 3 and **

Drywell Pressure - liigh 1, 2, 3

b. NA M Q

c. Reactor Vessel Water y K Level - Low Low, Level 2 . S M R 1, 2, 3, and

- d. Foel Pool Vent Exhaust

[ Radiation - liigh S M , R 1, 2, 3 and **

3. Hl' ACTOR WATER CIEANilP SYSTEM ISOLATION

~

d. A Flow - High S H R 1, 2, 3 Lt h. Heat Exchanger Area F Temperature - High NA M Q 1, 2, 3

c. Heat Exchanger Area Ventilation AT - liigh NA M Q 1, 2, 3 a, ^

. _; T u,29._ . ,  :: .y. ""

.. ..- Q i , 2, S

!- .. " .;. 'W:: "1;i i ? ;i L., o

! ,-. 7. t o , o ...u>

n 4 3> 2 2 -

,,,, Pad St CS Ini tiation NA -

R NA . 1, 2, 3

, geg, Reactor Vessel Water Level - tow Low, Level 2 5 M~ R 1, 2, 3 g

a j

. . , : . . ._ o ; . - .. .

^

(~

'y

[ ., *:

Y '

TABLE 4.3.2.1-1 (Continued) ,

5 u, ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS r" ;

CHANNEL OPERATIONAL-

[. CilANNEL FUNCTIONAL CilANNEL CON 01TIONS FOR WHICN #

CllECK TEST CALIBRATION SURVEILLANCE REQUIRED c- TRIP _ l'InlCTION

4. HEACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

]

RCIC Steam Line Flow - High M 1, 2, 3 l

a. NA Q

h. RCIC Steam Supply Pressure - ',_ ,

l NA M Q 1, 2, 3 Lo.s -

l l c. RCIC Turbine Exhaust Diaphragm '

Pressure - liigh NA M Q 1, 2, 3 l

d. RCIC Equipment Room s, l

Temperature lligh NA M- Q 1, 2, 3 l

- e. RCIC Steam Line Tunnel  ;

Temperature - liigh NA M Q 1,2,3 i R f. RCIC Steam Line Tunnel ,

ll

• A Temperature - High NA M Q 1,,2, 3 1, 2, 3 -

. Y g. Drywell Pressure - High NA M Q m

V

5. HilR SYSTEM STEAM CONDENSING MODE ISOLATION' ,

3

d. RilR l'quipment Area A .

Temperature - High NA M Q 1, 2, 3

$ b. RilR Area Cooler Temperature - ' .

M 1, 2, 3 l liigh NA Q. '

c. RilR lleat Exc' hanger Steam .

M 1, 2. 3 Supply Flow - liigh NA i Q 9

f- -

~

I 4

. - _ - _ _ _ ~

. . . , _ . . . .._......._...__c._....u.. . . _ .Y - .

9 ,e

/ q .,.

TABLE 4.3.2.1-1 (Continued) ,

'5

y. ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIRENENTS D CHANNEL OPERATIONAL E,

, CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR MIICH TRIP FUNCTION CHECK TEST- CALIBRATION SURVEILLANCE REQUIRE 0 e

6 -

• 6. RilR SYSTEN SHUTOOWN COOLING N00E ISOLATION

(

~

2 a. Reactor Vessel Water Level -

Low, Level 3 S M R 1, 2, 3 6

b. Reac. tor Vessel  !

p (RllR Cut-in Permissive).

M 1,2,3 P Pressure - liigh NA Q 1, 2, 3 " S-h c. RilR Pump Suction Flow - High NA M Q .

J d. RilR Area Teraperature - High NA M. Q. 1, 2, 3

e. RilR Equipment Area AT - H10h NA M Q. 1, 2, 3 l

1:' B. MANUAL INITIATION

+

Y 1. Inboard Valves NA R NA 1,' 2, 3 *

2. Outboard Valves .

1, 2, 3 0

J) M 3. Inhoard Valves .

1, 2, 3 and **,#

4. 1, 2, 3 and **,#

) 5.

Outboard Valves Inboard Valves 1, 2, 3 .

6. Dot. board Valves 1,.2, 3 1

7. Outboard Valve 1, 2, 3 g

P .

e

). *When reactor steam pressure > 1043 psig and/or any turbine stop v,alve is open.

'f **When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

1. Dm ing CORE ALTERATIONS and operations with a potential for draining the reactor vessel, s 0 ~

t1

~

l e

J

INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1

-shall be OPERA 8LE with their tri'p setpoints set consistent with the values shown in the Trip'Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM

. RESPONSE TIME as shown in Table 3.3.2-3.

APPLICA8ILITY: .As shown in Table 3.3.2-1.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare.the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value. . ,

l

b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system; place that trip system in the tripped condition

• within one hour. The provisions of Specification 3.0.4 are not applicable.

. c. With the number of OPERABLE channels less than required by the Minimum OPERA 8LE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.

"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 L

! channel shall be restored to OPERABLE' status witnin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required 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.

l .

i I .

l r% Cby . 1- L c e $ . m ce_ o ,

LA SALLE - UNIT 2 3/4 3-9

.~------------------_-------,-,-.-.,---.n..~.,,,.,-..---.,----,.,,-n,,-,.-,.,-,,,---,_-,-,,,,--wm,.,,,--an,,,---,--w.--.,_, . , -

INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.2.1- Each isolation actuation 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 4.3.2.1-1.

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

4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function shown-in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least 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 isolation trip system.

f s

e-LA SALLE - UNIT 2 3/4 3-10

TABLE 3.3.2-1 G j y ISOLATION ACTUATION INSTRUNENTATION F

m VALVE GROUPS MINIMUM OPERA 8tE APPLICA8LE

' OPERATED BY CHANNELS PER OPERATIONAL TRIP SYSTEM (b) CONDITION ACTION g TRIP FUNCTION SIGNAL (a) 4 A. AUTOMATIC INITIATION l m

1. PRIMARY CONTAINNENT ISOLATION

)

I a. Reactor Vessel Water Level (1) Low, Level 3 7 2 1, 2, 3- 20 i 1,2,3 1,2,3 20 l

'(2) Low Low, Level 2 2 2 1,2,3 20

b. Drywell Pressure - High 2, 7

c. Main Steam Line 1)' Radiation - High 1 2 1,2,3 21 i 3 2 1,2,3 22 2 1 23

2) Pressure - Low 1 21

3) Flow - High 1 2/line(d) 1, 2, 3 j

) l y d. Main Steam Line Tunnel 21 I Temperature - High 2 1,2,3 p 1

e. Main Steam Line Tunnel 1(1), 2(1), 3(1) 21 A Temperature - High 1 2 j

f. Condenser Vacuum - Low 1 2 1, 28, 3* 21 2 I Tv

2. SECONDARY CONTAINNENT ISGLATION

a. Reactor '8allding Vent Exhaust y Plenum Radiation - High 4(c)(e) 2- 1, 2, 3 and ** 24 ,, i

b. Drywell Pressure - High 4(c)(e) 2 1,2,3 24 2 1 n

c. Reactor Vessel Water .

1, 2, 3, and , 24 Da Level - Low Low, Level 2 4(c)(e) 2 c, ,

d. Fuel Pool Vent Exhaust 1, 2, 3, and ** 24 g Radiation - High 4(c)(e) . 2 X

m_. h _ _ _ _ _ . _ _ _ _ _ _ _ _ _

TABLE 3.3.2-1 (Continued)

G ISOLATION ACTUATION INSTRUMENTATION.

$ APPLICABLE VALVE GROUPS MINIMUM OPERA 8LE h1 OPERATED BY CHANNELS PER- OPERATIONAL SIGNAL (a) , TRIP SYSTEM (b) CONDITION ACTION c TRIP FUNCTION 5

H 3. REACTOR WATER CLEANUP SYSTEM ISOLATION N 1,2,3 22

a. A Flow - High' S 1 Heat Exchanger Area

b. 22 )

1, 2, 3 Temperature - High 5 1 l

c. Heat Exchanger Area Venttiation AT - High 5 1. 1, 2, 3 22 l

, p 1 _ .. l 2 ..-- ... ,-- -__ _ nu .n. e ,

^

e. . ,. 46. -W..-iias.iv - !

22 -

"#. 5 1 Ir2r3 m

A III NA 1, 2, 3 - 22 A fd SLCS Initiation S Y jeg. Reactor Vessel Wter 22 Level - Low Low, Level 2 2 1, 2, 3 U 5

4. REACTOR CORE ISOLATION 'C00 TING SYSTEM ISOLATION RCIC Steam Line flow - High 8 1 1,2,3 -22 a.

b. RCIC' Steam Supply Pressure - Low 8, 9gg) 2 1,2,3 22

c. RCIC Turbine Exhaust 1,2,3 22  !

Olaphrage Pressure - liigh 8 2 i

{

d. RCIC Equipment Room 22 j Temperature - High 8 1 1,2,3 s.

e. RCIC Steam Line Turnel 1,2,3 22 l Temperature - High 8 1

f. RCIC Steam Line Tunnel 1,2,3 22 A Temperature - liigh 8 1

~

g. Drywell Pressure - High 9 I9) 2 1,2,3 22

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

k t

TABLE 3.3.2-1 (Continued) . ,

^ ISOLATION ACTUATION INSTRUMENTATION "2

4 E VALVE GROUPS MINIMUM OPERA 8LE APPLICA8tE

• OPERATED BY' CHANNELS PER OPERATIONAL CONDITION ' ACTION

-[- TRIP FUNCTION- SIGNAL (a) TRIP SYSTEM (b)

I U 5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION

'" RHR Equipment Area I a.

A Temperature - High 8 1- 1, 2, 3 - 22 i

i b. RHR Area Temperature -

High 8 1 1,2,3, 22 l

I c. RHR Heat Exchanger Steam

Supply Flow - High 8 1 1,2,3 22 i

i j 6. RHR SYSTEM SHUTDOWN COOLING MGDE ISOLATION

w. a. Reactor Vessel Water .

D Level - Low, Level 3 6 . 2 1,2,3 25 1

i T b. Reactor Vessel

U (RHR Cut-in Permissive) 1,2,3 25

Pressure - High 6 1 i

RHR Puer: Suction Flow - High 6 1,2,3 25 i c. 1

! d. RHR Area Temperature - >

6 1, 2, 3 25

! High 1 l e. 'RHR Equipment Area AT - High 6 1 1,2,3 25 gc, T4

8. MANUAL INITIATION s T4 1,2,5,6,7 1/ group 1, 2, 3 26

! 1. Inboard Valves 1, 2, 5, 6, 7 1/ group 1,2,3 26 f -2. Outboard Valves Inboard Valves 4 (c) (e) 1/ group 1, 2, 3 and **,# 26 b")

j 3.

4. Outboard Valves 4 f CI I*I 1/ group 1, 2, 3 and **,# 26 h 3,8,9 1/ valve 1, 2, 3 26 l S. Inboard Valves 3,8,9 1/ valve 1, 2, 3 26

! 6. Outboard Valves l 7. Outboard Valve S IA)

~

1/ group 1, 2, 3 26 $(

d

h il

• 11

}"

I ge h= L:J G M n  ;

- g

?

_ TABLE 3.3.2-1 (Continued) -

o i

ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS E

= ACTION 20 -

Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN

. with the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21 -

Be in at least STARTUP with the associated isolation valves 3 closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. i i

ACTION 22 -

Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.  :

P ACTION 23 -

Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. -

ACTION 24 - Establish SECONDARY CONTAINMENT INTEGRITY with r.ne standby gas treatment systam operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 25 - Lock the affected system isolation valves closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> .

and declare the affected system inoperable. '

ACTION 26 - Provided that the manual initiation function is OPERABLE for each other group valve, inboard or outboard, as applicable, in 5 each line restore the manual initiation function to OPERABLE i e status wi$'lin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, restore the manual initiation function to OPERABLE ctatus withi 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise:

' a. Be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or

b. Close the affected rystem isolation valves within the next "

- hour and declare the affected system in operable.

w j TABLE NOTATIONS g

• May be bypassed with reactor steam pressure < 1043 psig and all turt,ine  ;

y step valvas closed. -

"* When handling irradiated fuel in the secondary containment and during CORE 4 L ALTERATICNS and operations with a potential for draining the reactor vessel. j g

1. During CORE ALTERATIONS and operations with a potential for draining the i

'__ reactor vessel. 2 (a) See Specification 3.6.3, Table 3.6.3-1 for valves in each valve group. I J 3

~!

(b) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the trippeo j r condition provided at least one other OPERABLE channel in the same trip 4 -

E system is monitoring that parameter. '

• (c) Also actuates the standby gas treatment system. .

(d) A channel is OPERABLE if 2 of 4 instrumants in that channel are OPERABLE. 1 E

• (e) Also actuates secondary containment ventilation isolation dampers per i

=- Table 3.6.5.2-1. 3

- (f) Closes only RWCU system inlet outboard valve. -

1. - (g) Requires RCIC steam supply pressure-low coincident with drywell -

pressure-high. y '

(h) Manual initiation isolates 2E51-F008 only and only with a coincident -

[ reactor vessel water level-low, level 3, signal.

(i) Both channels of each trip system may be placed in an inoperable status for (

- up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for required reactor building ventilation filter change and i

= damper cycling without placing the trip system in the tripped condition }

- provided that the ambient temperature channels in the same trip systems -

are OPERABLE.

- =

LA SALLE - UNIT 2 3/4 3-14

^

TA 3.3.2-2 .

i 5 ISOLATION AC10AT10N INSTRUMENTATION SETPOINTS l h ALLOWABLE E TRIP FUNCTION TRIP SETPolNT VALUE 1 ' A. AU10MATIC INITIATION k

-4

1. PRIMARY CONTAINMENT ISOLATION -

l u a. Reactor Vessel Water Level

1) Low, Level 3 1 12.5 inches

• 1 11.0 inches

• j 2) Low Low,. Level 2 1 -50. inches

• 1 -57 inches *

b. Drywell Pressure - liigh 1 1.69 psig i 1.89 psig i

c. Main Steam Line

1) Radiation - High 5 3.0 x full power background 5 3.6 x full background

2) Pressure - Low 1 854 psig 1 834 psig

3) Flow - High $ 111 psid $ 116 psid t d. Main Steam Line Tunnel Temperature - High 5 140*F $ 146*F w e. Main Steam Line Tunnel .

} A Temperature - High 5 36*F $ 42*F l j m f. Condenser Vacuum - Low > 7 inches Hg vacuum > 5.5 inches Hg vacuum I5 1

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Vent Exhaust l Plenum Radiation - High. 5 10 mr/h 5 15 mr/h

, b. Drywell Pressure - High 5 1.69 psig i 1.89 psig

c. Reactor Vessel Vater

! Level - Low Low, level 2 1 -50 inches * -

1 -57 inches

• j d. Fuel Pool Vent Exhaust j g Radiation - High $ 10 mr/h 5 15 mr/h a r.

{g 3. REACTOR WATER CLEANUP SYSTEM ISOLATION

@ a. AFlow - High 5 70 gpm 5 87.5 gpm i b. Heat Exchanger Area Temperature

5 - High ~< 181*F ~< 187*F -

j *" c. Heat Exchanger Area Ventilation AT - High j < 85* < 91*F d.

a n "r:: L;, r r "

• p. 7 !!E*r _

, MMar

. "r; ". "s..;.;; ' L,. "! "!;;h 7 1,or _ _ _ _ _  ? Igor .

1. d SLCS Initiation H.A. N.A.

p c. Reactor Vessel Water Level -

. Low Low, level 2 1 -50 inches

• 1 -57 inches *

- - _ - - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ . - ------__.)

)-

?

TABLE 3.3.2-2 (Continued) 5 ISOLATION ACTUATION INSTRUNENTATION SETPolNTS

? ALLOWABLE j;;

TRIP FUNCTION TRIPSETPb!NT VALUE k-e 4. REACTOR CORE ISOLATION COOLING SYSTEN ISOLATION N a. RCIC Steam Line Flow - High 1 290% of rated flow, 178" H 2O 1 295% of rated flow, 185" H 2O

. b. RCIC Steam Supply Pressure - Low 1 57 psig 1 53 psig -

c. RCIC Turbine Exhaust Diaphrags i Pressure - High 510.0 psig . 1 20.0 psig

d. RCIC Equipner.t Room Temperature - High 1 200*F 5 206*F

e. RCIC Steam Line Tunrel

Temperature - High 1 203*F 1 206*F .

i f. RCIC Steam Line Tunnel w A Temperature - Hloh 5 117*F 1 123*F

) g. Drywell Pressure - High 1 1.69 psig i 1.89 psig

[ 5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION I a. RHR Equipment Area A Temperature - High 5 50*F 1 56*F j b. RHR Area Cooler Temperature -

High $ 200*F 1 206*F ,

o

! c. RHR Heat Exchanger Steam ^

Supply Flow - High 1 125" H 2O , i 128" H 2O

N i

II, c.

b i

R

. t, i

(

l

~

TABLE 3.3.2-2 (Continued) 5 m ISOLATION ACTUATION INSTRUMENTATION SETPOINTS r"-

ALLOW 48LE-m TRIP FUNCTION TRIP SETPOINT VALUE i .b 6. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

-4

" a. Reactor Vessel Water Level -

! Low, Level 3 > 12.5 inches * > 11.0 inches

• 1

b. Reactor Vessel l (RHR Cut-in Permissive)

! Pressure - High 5 135 psig** $ 145 psig**

c. RHR Pump Suction Flow - High i 180" 1120 $ 186" N20 w d. RHR Area Cooler Temperature -

) High 1 200*F $ 206*F

e. RHR Equipment Area AT -High 1 50*F $ 56*F i

! 8. ' MANUAL INITIATION N.A. N.A. ,

4

1. Inboard Valves i 2. Outboard Valves .

i 3. Inboard Valves 2

! 4. Outboard Valves A l l ' 5. Inboard Valves ,

i i 6. Outboard Valves j -

7. Outboard Valve .

2 "T1 l

I n,

T*

ni e

• See Bases figure 8 3/4 3-1.

• • Corrected for cold water head with reactor vessel flooded. N N

{ N.A. - Not Applicable.

1 0

E k

i J

4 1

i

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

A. AUTOMATIC INITIATION

1. PRIMARY CONTAlletENT ISOLATION

a. Reactor Vessel Water Level

1) Low, Level 3 N.A.

b.

2) Low Low, Level 2 Drywell Pressure - High

<1.g<13(,),

513

c. Main Steam Line Radiation - High(b) a **

1) 5,1.0*/< 13(g,)),,

2) Pressure - Low < 1.0*/< 13

3) Flow - High I 0.5*/2 13(*),, ~

d. Main Steam Line Tunnel. Temperature - High N.A.

e. Condenser Vacuum - Low N.A.

f. Main Steam Line Tunnel a Temperature - High N.A.

2.- SECONDARY CONTAINMENT ISOLATION

a. -Reactor.BuildinggntExhaustPlenum Radiation - High < 13(,)

b. .Drywell Pressure - High

c. 7 13((*a)

ReactorVesselWaterLevel-Low, Level (g)" I51313(*))

d. Fuel Pool Vent Exhaust Radiation - High

3. REACTOR WATER CLEANUP SYSTEM ISOLATION

a. A Flow - High < 13(a)N

b. Heat Exchanger Area Temperature - High N.A.

c. Heat Exchanger Area Ventilation AT-High N.A.

d. 7 4 " . . . T. ,.. . . .. . . . . . . . ." . f .

. - "" " . . . . . . . s .l . . . .. . T lL,. ~

u_t_

ffd- SLCS Initiation N.A.

, pfe. R. actor vessai water tevei - tow tow, tevei 2 3.13(,)

4. REACTOR COAE ISOLATION COOLING SYSTEM ISOLATION

a. RCIC Steam Line Flow - High < 13(*) #

b. RCIC Steam' Supply Pressure - Low 513(*)

c. RCIC Turbine Exhaust Diaphragm Pressure - High N.A.

d. RCIC Equipment Room Temperature - High N.A.

e. RCIC Steam Line Tunnel Temperature - High N.A.

f. RCIC Steam Line Tunnel a Temperature - High N.A.

g. Drywell Pressure - High N.A.

5. RHR SYSTEM STEAM CONDENSING MODE ISOLATION

a. RHR Equipment Area a Temperature - High N.A.

b. RHR Area Cooler Temperature - High N.A.

c. RHR Heat Exchanger Steam Supply Flow High N.A.

LA SALLE - UNIT 2 3/4 3-18

n . . . . - -

pg gy scEAice CAJA?

TA8tE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPON5E TIME TRIP FUNCTION RESPONSE TIME (Seconds)#

6. RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION

a. Reactor Vessel Water Level - Low, Level 3 < 13C ")

b. Reactor Vessel (RHR Cut-In Permissive) Pressure - High N.A.

c. RHR Pump Suction Flow - High N.A.

d. RHR Area Cooler Temperature High N.A.

e. RHR Equipment Area AT High N.A.

8. MANUAL INITIATION N.A.

1. Inboard Valves

2. Outboard Valves

3. Inboard Valves ,

4. Outboard Valves )

5. Inboard Valves

6. Outboard Valves

7. Outboard Valve TABLE NOTATIONS (a) The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME. Isolation system instrumentation response time specified includes the delay for diesel generator starting assumed in the accident analysis.

'(b) Radiation detectors are exempt from response time testing. Response time shall be measured from detector output or the input of the first electronic component in the channel.

• Isolation system instrumentation response ti:ne for MSIVs only. No diesel generator delays assumed. i

• • ' Isolation system instrumentation response time for associated valves except MSIVs. .

1. Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

M Without 45_+1 second time delay.

1. 1. Without 5,5 second time delay.

N. A. Not Applicable.

LA SALLE - UNIT 2 3/4 3-19

TABLE 4.3.2.1-1 g ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL ~ OPERATIONAL l' vi N CHANNEL FUNCTIONAL CHANNEL _ CONDITIONS FOR WHICH CALIBRATION ~ SURVEILLANCE REQUIRED i E TRIP FUNCTION CilECK TEST f ' A.

_ AUTOMATIC INITIATION

1. PRIMARY CONTAINMENT 1501ATION m a. Reactor Vessel Water Level Low, Level 3 5 M R 1, 2, 3

1) .

1, 2, 3

2) Low Low, Level 2 S M R 1, 2, 3

, b. Drywell Pressure - High NA M Q

c. Main Steam Line Radiation - High S M R 1, 2, 3

! 1) 1

2) Pressure - Low NA M Q Flow - High S M R 1, 2, 3 i 3)

d. Main Steam Line Tunnel Temperature - High NA M R 1, 2, 3 w e. Condenser Vacuum - Low NA M Q 1, 2*, 3*

D f. Main Staam Line Tunnel 1, 2, 3 w A Temperature - High NA M R

, $ 2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Vent Exhaust 1

Plenum Radiatica - liigh S M R 1, 2, 3 and **

l 1,2,3 l b. Drywell Pressure - tilgh NA M Q

c. Reactor Vessel Water y Level - Lcw Low, level 2 5 M R 1, 2, 3, and i

! d. Fuel Pool Vent Exhaust ,

1, 2, 3 and **

Radiation - liigh S M R ,

3. REACTOR WATER CLEANUP SYSTEM ISOLATION 1, 2, 3

!, a. A Flow - High 5 M R

! b. Heat Exchanger Area '

1, 2, 3 i Temperature - liigh NA M Q j c. Heat Exchanger Area 1,

c . Ve:QilationAT _

.gh _

__ _ . M Q g .. . .

A. ; t'; ..t ' ! ; t h - - 1--

j  :. ." " ^

! lJ - ; . .t . . . . . J. "?. .

' ' ' ~ ~ ~ ~ ~ _

1 J. ]

< M SLCS ihTtTatfon NA R NA 1, 2, 3 '

l .y g Reactor Vessel Water 1, 2, 3 Level - Low Low, Level 2 S M R i .. - _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - -

F o e e E r a " 6 " ' " l 0 *~ C' 9

- TABLE 4.3.2.'l-1 (Continued):

i 5 ISOLATION ACTUATION INSTRimENTATION SURVEILLANCE REQUIREMENTS-5 E CHANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH 4

7 TRIP FUNCTION CHANNEL CtlECK TEST CALI8 RAT 10N SURVEILLANCE REQUIRED .

c I 5

-4 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION m .

a. RCIC Steam Line flow - High NA M Q 1, 2, 3

b. RCIC Ster.m Supply Pressure -

Low NA M Q 1, 2, 3

c. RCic Turbine Exhaust Diaphragm j Pressure - High NA M Q 1, 2, 3 l

d. RCIC Equipment Room Temperature - High NA M Q 1, 2, 3 i ,

1- e. RCIC Steam Line Tunnel Temperature - High NA M Q 1, 2, 3 w f. RCIC Steam Line Tunnel D A Temperature - High NA M Q 1, 2, 3

g. Drywell Pressure - High NA M 1, 2, 3 j y Q j 5. RHR SYSTEN STEAM CONDENSING N00E ISOLATION i

8

a. RHR Equipment Arca A

, Temperature - High NA M Q 1,2,3 I b. RHR Area Cooler Temperature -

. High NA M Q 1, 2, 3

) c. RHR Heat Exchange:- Steam Supply Flow - High NA M Q 1, 2, 3 i

i .

k 4

l -

s 8

4 i

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

n '..

g 1-

,u TABLE 4.3.2.1-1 (Continued). l ISOLATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIRENENTS

$ OPERATIONAL i-E CHANNEL

• CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH #

' CHECK TEST CALIBRATION $_URVEILLANCE REQUIEED TRIP FUNCTION C . , .

6. RHR SYSTEN SHUTDOWN COOLING MODE ISOLATION w

a. Reactor Vessel Water Level - 1, 2, 3 Low, Level 3 S M R

b. Reactor Vessel (RHR Cut-in Permissive) 1, 2, 3 Pressure - High NA .

M_ Q M 1, 2, 3

c. RHR Pump Suction Flow - High NA Q 1, 2, 3

d. RHR Area Temperature - High NA M Q N 1, 2, 3

e. RHR Equipment Area AT - High NA Q w B. MANUAL INITIATION i R NA 1,2,3 w 1. Inboard Valves NA 1, 2, 3 A

2. Outboard Valves 1, 2, 3 and **,#

3. Inboard Valves 1, 2, 3 and **,#

4. Outboard Valves 1, 2, 3

5. Inboard Valves 1, 2, 3

6. Outboard Valves 1, 2, 3

7. Outboard Valve "When reactor steam pressure > 1043 psi 0 and/or any turbine stop valve is open.

• • When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining tha reactor vessel. h Te i

1. 0uring CORE ALTERATIONS and operations with a potential for draining the reac*or vessel, ni 2: i n

n b

Q

,h.

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