ML20079M009

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Proposed Tech Spec Table 3.3.3-1, ECCS Actuation Instrumentation, Table 3.3.3-2, ECCS Actuation Instrumentation Setpoints & Table 4.3.3.1-1, ECCS Actuation Instrumentation Surveillance Requirements
ML20079M009
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 10/16/1991
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20079M003 List:
References
NUDOCS 9111070229
Download: ML20079M009 (37)
v • d • e


Text

  • :

AUACliMLNL B i

  • PRomSED CHANG [S 10 APPIND!X A, IECHN! CAL SPEC 1IICA110NS Of FACILITY OPLRAllNG LICENSLS NPf-ll AND NPI-18 REVISED.PAGES UNIL ONE J NPr-11.) UNIIJHQ JNPE-18) 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-30 3/4 3-30 3/4 3-30a 3/4 3-30a 3/4 3-32 3/4 3-34 3/4 3-33 3/4 5-5 3/4 3-34 3/4 5-6 3/4 5-5 3/4 5-7 3/4 5-6 3/4 5-8 3/4 5-7 3/4 5-9 3/4 5-8 3/4 6-36 3/4 5-9 3/4 6-37 3/4 6-33 3/4 6-37a (New Page) 3/4 6-34 3/4 8-30 8 3/4 6-34a (New Page) B 3/4 5-1 B 3/4 8-30 D 3/4 5-2 B 3/4 5-1 B 3/4 6-3a B 3/4 5-2 B 3/4 6-3a 3

911107022? 911016 PDR ADOCK 05000 373 P PDn

F _ .

U .

4 t

TABLE 3.3.3-1 (Continued)

  • 5 .

EMERGENCY' CORE COOLING SYSTEM ACTUATION IN6TRUMENTATION

.k MINIMUM OPERABLE APPLICABLE i

. CHANNELS PER TRIP OPERATIONAL  ;

l @ TRIP FUNCTION FUNCTION (a)  !

CONDITIONS ACTION l ~ . C. DIVISION 3' TRIP SYSTEM i

!. 1. HPCS' SYSTEM I i

i

a. Reactor Vessel Water Level - Low, Low, Level 2. 4 1, 2, 3, 4 *, 5* 35 4
b. Drywell Pressure - High 4 1, 2, 3 35 l

j De.lefe.{

c. Reactor vessel Water level-High. Level 8 r Condensate Storage Iank Level-tow gg 1. 2. 3.

I*

4*. 5* 32

e. t Suppression Pool Water level-High 2(d) * *
  • 4*. 5*

2 1. 2. 3. 36 J  ;

f. Pump Discharge Pressure-High (Bypass) 1 1, 2, 3, 4 * , 5" 31 i y g. HPCS System Flow Rate-Low (Permissive) 1 1, 2, 3, 4*, 5* 31
  • h. . Manual Initiation 1/ division 1, 2, 3, 4 * , 5* 34

, Y y D. LO55 0F POWER MINIMUM APPLICABLE I

TOTAL NO. INSTRUMENTS OPERABLE , OPERATIONAL i

0F INSTRtMENTS TO TRIP INSTRLMENTS',) CONDITIONS ACTION

! I. 4.16 kv Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5** 37

(Loss of Voltage)

D gra o a e) i' t

(a) A channel instrument 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 /> during periods of required '

surveillance without placing the trip system / channel / instrument in the tripped condition provided at least ore i

other OPERABLE channel / instrument in the same trip system is monitoring that parameter.  ;

(b) Also actuates the associated division diesel generator. i g c _ Provides signal to close HPCS pump discharge valve only on 2-out-of-2 togic. -

t g tid) Provides signal to HPCS pump suction valves only.)

, g

  • Applicable when the system is required i.o be OPERABL; per Specification 3.5.2 or 3.5.3. ,

g Required when ESF equipment is required to be OPERABLE. t z

Not required to be OPERABLE when reactor steam done pressure is < 122 psig.

. . . . _ _ - . . , __. .,- _ . - _ _ . _ - . _ _ _.. .a

o

, T,ABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

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

a. With one channel inoperable, place the inoperable channel in the tripped condition within one hour
b. With more than one channel inoperable, declare the associa'.ed system inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip Function, place the inoperablat 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 systerr or ECCS inoperable.

ACTION 33 -

With the numoer 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 inoporable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 e

,f v condition within one hour

ACTION 36 - [WiththenumberofOPERABLEchannelslessthanrequiredbythe" Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within konehour*ordeclaretheHPCSsysteminoperable.

ACTION 37 - With the number of OPERABLE instruments less than the Minimum Operable Instruments, place the inoperable instrument (s) in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

9 he provisions of Specification 3.0.4 are not applicable.

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

, TABLE 3.3.3-2 (Continued) p EMERGENC( CORE COOLING SYSTEM ACTUATION INSTRUMEf4TATION SETPOINTS -

1 r-It ALLOWABLE e TRIP FUNCTION TRIP SETPOINT VALUE C

C. DIVISION 3 TRIP SYSTEM

{

I

1. HPCS SYSTEM
a. Reactor Vessel Water level - Low Low, level 2 ->- 50 inches * >- 57 inches * ,
b. Drywell Pressure - High 1 1.69 psig i 1.~89 psig gg ,f

/'

c. Reactor Vessel Water Level - High, Level 8 _i 55.5 inches
  • 1 56 inches
  • OC d. Landensate 5:orage tank Level - Low > /15'/" Z /15'J'
e. Suppression Pool Water Level - High < 2 inches ** < 3 inches **
f. Pump Discharge Pressure - High 2"120psig '["110psig l
g. HPCS Systes Flow Rate - Low 3 1000 gpm 3 990 gpa
h. Manual Intiation NA NA Y D LOSS OF POWER
1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)f
a. 4.16 kV si<

845eS -

1) Divisions 1 and 2 2625 i 131 volts with 2625 1 262 volts with 1 10 seconds time delay i 11 seconds time delay 2496 1 125 volts with 2496 1 250 volts with

~

> 4 seconds time delay 1 3 seconds time delay 3I 3 2) Division 3 2870 t 143 volts with 2870 1 287 volts with g i 10 seconds time delay 1 11 seconds time delay 3

  • See Bases Figure B 3/4 3-1.

u, #These are inverse time delay voltage relays or instantaneous voltage relays with a time delay. The

  • Lower voltage conditions will result in voltages shown are the maximum that will not result in a trip.

decreased trip times.

[** Level is referenced to a plant elevation of 699 feet 11 inches (See Figure B 3/4.6.2-1). }- dE- #

Li O

TABLE 3.3.3-2 (Contin'ued) ,--

r-

~

EMEPCENCY CORE COOLING SYSTEM ACTUATION INSTRUNEl6TATION SETPOINTS  :

m

- AlloweLE I m TRIP FUNCTION TRIP SETPOINT VALUE i
i.  !@ 2. 4.16 kV Emergency Bus Undervoltage i y (Degraded Voltage)  !'

~ '%'

4.16 kV(B Y I a. 8t4 cs

N '

! 1) Divisions 1, 2 and 3 3814.1 76 volts with 3814 i 76 volts with

! 10 1 1 seconds time 10 1 1 seconds time delay with LOCA signal delay with LOCA signal e or or j 5 1 0.5 minutes time 5 1 0.5 minutes time delay without LOCA delay without LOCA i j signal signal i w l

w  !

,L 4, o

4 i.

I t

l I

i 4

a {

!' M j:  ?. '

i 7 j t L

1 j

! i o __ ___._. . _ . _ . . - _ . ._ - .- _ _ . . _ . _ _ . ~ ._. ___ - - . . . .

  • i

~ '

-TABLE 4.3.3.1-1

. f EMERGFNCY CORE C6OLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS C

;- i i
  • CHAi4NEL OPERATIONAL [

4 CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR idHICM j

!' E TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED L *;

[

I' w A. DIVISION I TRIP SYSTE*  !

t

1. RHR-A (LPCI M000 AND LPCS SYSTEM -

I

a. Reactor Vessel Water Level --  !

l Low Low Low, Level 1 NA M R '1, 2, 3, 4*, 5* i 4 b. Drywell Pressure - High . NA M Q 1, 2, 3  ;

j c. LPCS Pump Discharge Flow-Low NA M Q 1, 2, 3, 4*, 5*  !

1 d. LPCS and LPCI A Injection Valve

! Injection Line Pressure Low +

Interlock NA M R 1, 2, 3, 4*, 5*  !'

R

e. LPCS and LPCI A Injection Valve 4

Reactor Pressure Low Interlock NA M R 1, 2, 3, 4*, 5*

l T f. 'LPCI Pump A Start Time Delay Kelay NA M q 1, 2, 3, 4*, 5*

i< M g. LPCI Pump A Flow-Lcw NA M Q 1, 2, 3, 4 * , 5* ,

t h. Manual Initiation NA ** NA 1, 2, 3, 4*, 5* i I

2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"#'

{

Reactor Vessel W ter level -

{ a.

Low Low Low, Level 1 NA M R 1, 2, 3

$ b. Drywell Pressure-High NA M Q 1, 2, 3 ,

! c. Initiation Timer NA M Q 1, 2, 3 l

[, d. Reactor Vessel Water Level -  !

l .-Low, level 3 NA M R 1, 2, 3

e. LPCS Pump Discharge i g Pressure-High NA M Q 1, 2, 3 '
e f. LPCI Pump A Discharge i

! h Pressure-P.igh , MA M Q 1, 2, 3 m g. Manual Initiation MA R MA 1, 2, 3  !

f+ h. Drywell Pressure Bypass Timer NA M -

Q 1, 2, 3 f i z 1. Msnual Inhibit NA R MA 1, 2, 3

~

7 e

4 L

i  :

l

.m - . , , . , . , -

m-,. - - -. . . - . . _ . ~ . , . ~ .

, y - - -

, - u

~,

TABLE 4.3.3.1-1-(Continued) -

h EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE PEQUIREMENTS l CHANNEL- OPERATIONAL I CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH I E TRIP FUNCTION. CHECK ' TEST CALIBRATION SURVEILLANCE REQUIRED a

j - 8. DIVISION'2 TRIP SYSTEM

1. RHR 8 AND C (LPCI MODE) j a. Reactor Vessel Water Level -

d Low Low Low, Level 1 MA M R 1, 2, 3, 4*, 5*

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

[I c. LPCI 8 and C Injeu fon Valve Injection Line Pressure Low

, Interlock NA M R 1, 2, 3, 4", 5*

! d. LPCI Pump 8 Start Time Delay Relay NA M Q 1, 2, 3, 4*, 5*

1 Y

e.  !?CI Pump Discharge Flow-Low MA M Q 1, 2, 3, 4 * , 5*
f. Manual Initiation MA NA 1, 2, 3, 4", 5*

Y g. LPCI B and C Injection Valve

0 Reactor Pressure Low

{ Interlock NA M R 1, 2, 3, 4*, 5*

2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B"#

l a. Reactor Vessel Water Level -

l' Low Low Low, Level 1 NA M R 1, 2, 3

b. Drywc11 Prepure-High NA M Q 1, 2, 3
c. Initiation Timer NA M Q 1, 2, 3 l
d. Reactor Vessel Water Level -

Low, Level 3 MA M R 1, 7, 3

e. LPC5 Pump 8 and C Discharge g Pressure-High NA M Q 1, 2, 3

= f. Manual Initiation .

NA R NA 1, 2, 3

$ h. Drywell Pressure Bypass Timer NA M Q 1, 2, 3 l

<= i. Manual Inh.~it NA R NA 1, 2, 3 j r+

2" 1 P

0 t

i I

TABLE 4.3.3.1-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURvFILLANCE REQUIREMENTS p

n CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH E TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED C

- C DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM
a. Reactor Vessel Water Level -

' ow Low, level 2

_ NA M R 1, 2, 3, 4 * , 5*

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

__ c. Reactor Vessel Water Level-High gg d.

level 8

[ Condensate Storage Tank Level -

NA M R 1, 2, 3, 4 *, 5*

Low )

NA M Q 1, 2, 3, 4 * , 5*

y e. Suppression Pool Viter a level - High NA M 0 1. 2. 3. 4*. 5* j '

y f. Pump Discharge Pressure-High NA M Q 1, 2, 3, 4 * , 5

  • g g. HPCS System flow Rate-tow NA M Q 1, 2, 3, 4 * , 5*
h. Manual Ir.itiation NA R NA 1, 2, 3, 4*, 5*

D. LOSS OF POWER

1. 4.16 kV Emergency Bus Under-voltage (Loss of Voltage) NA NA R 1, 2, 3, 4 * *, 5**
2. 4.16 kV Emergency Bus Under- NA NA R 1, 2, 3, 4**, 5**

voltage (Degraded Voltage) l t

  1. Not required to be OPERABLE when reactor steam dome pressure is irss than or equal to 122 psig.
  • When the system is required to be OPERABLE after being marva11y realigned, as applicable, per

> Specification 3.5.2. -

7,; _ ** Required when ESF equipment is reouired to be_0PERABLE.

g ***The specified 18-month interval may be waived for Cycle 1 prcvided the surveillance is performed during ]

g Refuel 1, which is to cor:mence no later than October 27, 1985.

~

J A

IADLL3&3_1 (c9Aidnuedl PRIMRLC0EAIMLNL150L6110lLVALVES JADLLliOIA110NS Hove footnotes "*" and (a) through (1) from Page 3/4 6-34 to this location.

m. If valves IE51-r362 and IE51-r363 are locked closed and acceptably leak rate tested, then valves IE51-r059 and IE51-r022 are not considered to be primary containment isolation valves and are not required to be leak rate tested.
n. Either the IE51-r362 or the 1E51-r363 valve may be open when the RCIC system is_in the standby mode of operation, and both valves may be open during operation of the RCIC system in the full flow test mode, providing that:
1) valve IE51-r022 is acceptably leat rate tested, and
2) valve IE51-r059 is deactivated, locked closed and acceptably leak rate tested, and P the spectacle flange, installed immediately downstream of the

, IE51-r059 valve, is closed and acceptably leak rate tested.

LASALLE - UNIT 1 3/4 6-34a ProposeJ Amendment 1174/9 s

iv - - - - , - , - - , , - , , - - - - - ~ <+.-,4- -,-r -- .-,,.-_,--:- - ~ , -

e j ENERGENCY CORE COOLING SYSTEMS

+

SURVE!LLANCE REQUIREMENTS (Continued)

(a) LPCS system to be $ 500 psig and > $5 psig, respectively.  :

(b) LPCI subsystems to be $ 400 psig and 1 55 psig, respectively.

2) Low pressure setpoint of the HPCS system to be 1 63 f psig, i b) Header delta P instrutnentation and verifying the setpoint of the:
1) LPCS system and LPCI subsystems to be t 1 psid.

31 2) HPCS system to be between 5 1 2.0 psid greater than l

gjelCP 1

the normal indicated AP.

-3. Verifying that-the suction for the HPCS system is automatically 1 L transferred from the condensate stora e tank to the suppression >

chamber on a condensat't storage tank ow water level signal and j on a suppression chamber high water level signal. J

4. Visually inspecting the ECCS corner room watertight door eals ,

and-room penetration seals and verifyin2 no abnormal degradation, damage, or obstructions.

d.. For the ADS by: l 1.- 'At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST ,

of the accumulator backup compressed gas system low pitssure alarm system.  :

2.- -At least once per 18 months:

a) Performing a system functional test which includes simulated autumatic actuation of the system throughout its emergency operating sequence, but excluding actuC valve actuation. '

b) Manually opening each ADS valve and observi,ng the expected change in the indicated valve position. >

c)- Performing a CHANNEL CALIBRATION of the accumulator backup ,

compressed gas system low pressure alarm system and verifying i an alarm setpoint of 500 + 40. - O psig on decreasing pressure, i-l L LA SALLE - UNIT l' 3/4 5-5 i

Amenoment No 18 ,

l r

- ,, .r-,-_-,-.. _ _ . , . _ , . _m.__-,~..._..._,,.. . . , . . . . . , . _ , _ . , ~ , . . . . _ - . _ . _ , _ , . _ . . . . ~ . - . - , . - , - . _ , _ _

, ,ER R p CY COR[ 000llNG SYST[M5 3/4.5.2 ECCS - SHUTDOWN LIMITING COND1110N FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE:

a. The low pressure core spray (LPCS) system with a flow path capable of taking suction f rom the suppression chamber and transferring the water through the spray sparger to the reactor vessel,
b. Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppression chamber upon being manually realigned and transferring the water to the reactor vessel,
c. Low pressure coolant injection (LPCI) subsystem "B" of the RHR system with a flow path capable of taking suction from the suppression chamber upon being manually realigned and trt Jferring the water to the reactor v e s t.e l ,
d. Low pressure coolant injection (LPCI) subsystem "C"'of the RHR system with a flow path capable of taking suction from the suppression chamber upon being inanually reali ned and transferring the water to the reactor vessel. N r
e. The high pressure core spray' (HP'CS) s ~ capable of taking suction fromfone gf the fol'yctemlowino with a flow pat and trans- P waterTources ferring the water through the spray sparger to the reactor vessel II. from the suppression chamber, or (
2. When the suppression pool level is less than the limit or is drained, from the condensate storage tank containira at least 135,000 available gallons of water, equivalent to a level of 14.5 feet. l APPLICABILITY: OPERATIONAL CONDITION 4 or 5*.

ACTION:

a. With one of the above required subsystems / systems inoperabl,, restore at least two subsystems / systems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor vessel,
b. With both of the above required subsystems / systems inoperaDie, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel. Restore at least one subsystem /

system to OPER/BLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish SECONDARY CONIAINHENT INTEGRITY within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, i 'The ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the spent fuel pool gates are removed, and water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.

LA SALLE - UNfT 1 3/4 5-6 l

EHERG[NCY CORE COOLING SYSTEMS f

e SURV[IllANCE REQUIRIMENTS 4.b.2.1 At least the above required ECCS $ hall be demonstrated OPERABLE per 3 Surveillance Requirement 4.5.1, except that the header delta P instrumentation is not required to be OPERABLE.

4.5.2.2 The HPCS system shall be determined OPERABLE at least once per - f-12 hourt, by verifying the condensate storage tank required volume when the ondensate $torage tank is required to be 0PERABLE per Specification 3.5.2.e. _

t I

1 P

i J

LA SALLE - UN11 1 3/4 5-7 i l

l

EMERGENCY CORE COOLING SYSTIMS 3/4.5.3 $UPPr.[$$10N CHAMBER #

LIMITING CONDITION FOR OPERATION 3.5.3 The suppression chamber shall be OPERABLE:

a. In OPERATIONAL CONDITION 1, 2, or 3 with a contained water volume of at least 128,800 ft 8, equivalent to a level of +4 1/2 inch 35.**

l

b. In OPERAi!0NAL CONDITION 4 or $* With a contained water volume of t least 70,000 ftat equivalent to a level of -12 feet 7 inche g, aexcept

' thatlhe suppressfon cFaTober leveT~may be less than the limiror may be drained in OPERATIONAL CONDITION 4 or $* provided that:

1. No operations are performed that have a potential for draining the reactor vessel,
2. The reactor mode switch is locked in the Shutdown or Refuel position,
3. The condensate storage tank contains at least 135,000 available gallons of water, equivalent to a level of 14.5 feet, and
4. The HPCS system is OPERABLE per Specification 3.5.2 with an OPERABLE flow path capable of taking suction from the condensate storage tank and transferring the water through the spray L sparger to the, reactor vessel. j APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and $'.

ACTION:

a. In OPERAi!ONAL CONDITION 1, 2, or 3 with the suppression chamber water level less than the above limit, resto*e the water level to within the limit within I hour or 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 SHUf00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. In OPERATIONAL CONDITION 4 or $* with the suppreunion chamber water level less than the above limittor drained and Ehe above required condTtTons not satisifM suspend CMlTTUI TTONS and all operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the Shutdown position. Establish SICONDARY CONTAINM[NT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
  1. 5ee Specification 3.6.2.1 for pressure suppression requirements.
  • The suppression chamber is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded or being flooded from the suppression pool, the spent fue1 pool gates are removed when the cavity is flooded, and the water level is maintained within the lirits of Specifications 3.9.8 and 3.9.9.

" Level is referenced to a plant elevation of 699 feet 11 inches (See Figure B 3/4,6.2-1).

LA SALLI - UNIT 1 3/4 b-B Amendment No 69

,c EMERGENCY CORE C001ING SYSTEMS

/ tlMITitlG C0!:DIT10?! FOR UPERAllCN (Continued)

'/ ',

. ACT10f t: (Continued)

c. With one suppression chamber water level instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 7 days or verif y the suppression chamber water level to be greater than or equal to -4 1/2 inches ** or -12 feet 7 inches **, as applicable, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication.
d. With both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 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 /> and verify the suppression chamber water level to be greater than or equal to 41/2 inches *' or -12 f eet 7 inches **, as applicable, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication.

SURVElLLANCE RE0JllREMENTS 4.L.3.1 The suppression chamber shall be determined OPERABLE by verifying:

a. The wate" level to be greater than or equal to, as applicable:

1, -4 1/2 inches ** at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. -12 feet 7 inches ** at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,
b. Iwo suppression chamber water level instrumentation channels CPERABLE by performance of a:
1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
2. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
3. CHANNEL CALIBRATION at least once per 18 months, with the low water level alarm setpoint at greater than o, equal to

-3 inches.** l

4. 5. 3. 2 With the suppression chamber level less than the above limit lar drained in OPERATIONAL CONDITI0pb* , at least once per 12 hourg 4--

Q a. Verify the required conditions cf Specification 3.5.3.b. to be satisfied, orf i

b. g y'erify footnote conditions
  • to be satisfied.
  • The suppression chamber is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded or being flooded from the suppres-sion pool, the spent fuel pool gates are removed when the cavity is flooded, and the water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.

4 ** Level is referenced to a plant elevation of 699 feet 11 inches (See figure B 3/4.6.2-1)

~'

LA SALLE - UNIT 1 3/4 5-9 Amendrent Nc.

r-, , - , , , - . - - - . - -

s TARtE 3.6.3-1 (Continued) .

PRIMARY CONTAINMENT 1501ATION VAtVES T

r-VALVE FUNCTION AND NUMBER E Other Isolation Valves (Continued)

-4

- 4. Low Pressure Core Spray System .

1E21-F005 IE21-F001 Ii)

Il) 1E21-F012 IE21-F011 I3I Ill 1E21-F018 IE21-F031 II) 1E21-F006 I)

5. High Pressure Core Spray System s

" Ii) 1E22-F012 1E22-F014 I5) 1E22-F005 II Reactor Core Is',lation Cooling System 6.

1' E51- F059 M IE51-F013

  • 1E 51- F022. (m)

IESI-F069 IE51-F028 1E51- F3G2 fal 1E51-F068 p 1E51-F040(j) 1ESL- F363 M n 1E51-F031 Il)

E 1E51-F019 1E51-F055 II 3 I}

E 1E51-F066 g

g.

To .

s TABLE 3.6.3-1 (Continued) r-

" PRIMARY CONTAINMENT ISOLATION VALVES E

YALVE FUNCTION AND NUMBER

{

= Other Isciation Valves (Continued)

E 7. Post LOCA Hydrogen Control 1HG001A, B 1HG002A, B 1HG005A, B 1HG006A, B

8. Standby liquid Control System p Shdeg -10 IC41-F004A, B IC41-F007 rW w Pa3e f4 6- M L
9. Reactor Recirculation Seal Injectio, **

I w 1833-F013A,G()5) )

1 1833-F017A B T 10. Drywell Pneumatic System

$ 11N018 But > 3 seconds.

4 (a) See Specification 3.3.2, Table 3.3.2-1, for isolai. ion signal (s) that operates each valve group.

(b) Not included in total som of Type B and C tests.

(c) May be opened on an intermittent basis under administrative control.

(d) Not closed by SLCS actuation.

(e) Not closed by Trip Functions Sa, t, .c c. Specification 3.3.2, Table 3.3.2-1.

(f) Not closed by Trip Functions 4a, c, d, e or f of Specification 3.3.2. Table 3.3.2-1.

(g) Not subject to Type C leakage test.

(h) Opens on an iso!ation signal. Valves will be open during Type A test. No Type C test required.

(i) Also closed by drywell pressure-high signal.

E (j) llydraulic leak test at 43.6 psig.

E (kj Not subject to Type C leakage test - leakage rate tested per Specification 4.4.3.2.2.

S (1) These penetrations are provided with removable spools outboard of the outboard isolation valve.

3 During operation, these lines will be blind flanged using a double 0-ring and a type B 1eak test. In addition, the packing of these isolation valves will be soap-bubble tested to ensure 5 insinnificant or nn leakann at the containment _Leit_preiiure each refuelina ou(age. ,*

lhe specified 18-month interval may be%Iveii f or Cycle 1 provided the surveillance is perf ormec m

~ {*** durina Refuel 1,_phich is to_ commence nol ater_than October 27, 1985.

t

  • J ,

TABLE 3.8.3.3-1 (Continued) -'

M0'3d OPERATED VALVES THERMAL OVERLOAD

^

PROTECil0N BYPASS DEVICE SYSTEM (S)

VALVE NUMBER (Continuous)(Accident Condi,tions) AFFECTED

1. 1E32 - F001A Accident Conditions M51V-LCS 1E32 - F002A 'ccident Conditions IE32 - F003A Accident Conditions 1E32 - F001E Accident Conditions 1E32 - F002E Accident .:nditions 1E32 r003E Accident L nditions IE32 r'001J Accident Conditions IE32 - F002J Accident Conditions 1E32 - F003J Accident Conditions IE32 - F001N Accident Conditions 1E32 - F002N Accident Conditions 1E32 - F003N Accident Conditions 1E32 - F006 Accident Conditions 1E32 - F007 Accident Conditions 1E32 - F008 Accident Conditions 1E32 - F009 Accident Conditions
m. (1E22 - F001 Accident Conditions i - HPCS system 1E22 - F004 Accident Conditions 1 1E22 - f010 Accident Conditions ' - '(Ls/'

LlE22 - F0)) Accident Conditions 1E22 - F012 Accident Conditions 1E22 - F015 1 Accident Conditions IE22 - F023 Accident Conditions i

Co nk'. Ado MS LA SA'. E - UNIT 1 3 '4 6-30

9 3/4.5 EMERGENCY _ CORE C00(!NG SYSTEH BASES 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN ECCS Division 1 consists of the low pressure core sprey system, low pressure coolant injection subsystem "A" of the RHR system, and the automatic depressurization system (ADS) as actuated by ADS trip system "A". ECCS Division 2 consists of low pressure coolant injection subsystems "B"anr1 "C" of the RHR system and the automatic depressurization system as actuated by ADS trip system "B".

The low pressure core spray (LPCS) system is provided to assure that the core is adequately cooled following a loss-of-coolant accident and provides adequate core cooling capacity for all break sizes up to and including the double-ended reactor recirculation line break, and for transients or smaller l breaks following depressurization by the A05.

The LPCS is a primary source of emergency core cooling after the reactor vessel is depressurized and a source for flooding of the core in case of accidental draining.

The surveillance requirements provide adequate assurance that the LPCS system will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functicnal test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

The low pressure coolant injection (LPCI) mode of the RHR system is pro-vided to assure that the core is adequately cooled following a loss-of-coolant accident. Three subsystems, each with one pump, provide adequate core flooding for all break sizes up to and including the double ended reactor recirculation line break, and for transients or small breaks following depressurization by l the ADS.

The surveillance requirements provide adequate assurance that the LPCI system will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

ECCS Divistor 3 consists of the high pressure core spray system. The high pressure cc.. spray (HPCS) system is provided to assure that the reactor core is acequately cooled to limit fuel clad temperature in the event of a small break in the reactor coolant system and loss of coolant which does not result in rapid depressurization of the reactor vessel. The HPCS system-permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. The HPCS syste.n operates over a range of 1160 psid, dif ferential pressure between reactor vessel and HPCS suction source, to O psid.

The capacity of the HPCS system is selected to provide the required core cooling. The HPCS pump is designed to deliver greater than or equal to 516/1550/6200~ gpm at dif ferentia1 pressures of 1160/1130/200 psid. / Initially,

[ water f Fom the condensate _ storage tanFW usFd instead of liQeYting water from _

LA SALLE - UNIT 1 B 3/4 5-1 Amendment No. 29

y) der \s, Wtf { tem 50 hf 5Sim (n0I

' tnd in}ecied i& 00 ft%c%r,

~% d EMERGENCY CORE COOLING SYSTEMS i BASE 5

,E_CCS C ,0PI. RATING and SHUTDOWN (Continued) le wppression pool into the reactor, but no credit is taken in the ha:ards I analyses for the condensate storage tank water.l With the HPCS system inoperable, adequate core cooling is assured by the OPERAblLITY of the redundant and diversified automatic depressurization system and both the LPCS and LPCI systems. In addition, the reactor core iso'ation cooling (RCIC) system, a system for which no credit is taken in the hazards analysis, will automatically prov % makeup at reactor operating pressures on a reactor low water level conditio The HPCS out-of-service period of 14 days is based on the demonstrated OPERAblLITY of redundan* and diversified low pressure core cooling systems.

The surveillance requirements provide adequate assurance that the HPCS system will be OPERABLE when required. Although all active components are test-able and full flow can be demonstrated by recirculation through a test loop during reattor operation, . omplete functional test with reactor vessel injec*

tion requires reactor shutdom lhe pump cHscharge piping is maintained full to prevent water hammer damage and to provide cooling at the earliest moment.

Upon failure of the HPCS sr .m to function properly, if required, the autcratic depressurization syst , ADS) automaticall" causes selected safety-relief valves to open, depressurizing the reactor so that flow from the low pressure core cooling systems can enter the core in time to limit fuel cladding temperature to less than 2200 F. ADS is conservatively required to be OPERABLE whenever reactor vessel pressure exceeds 122 psig even thougt 0w pressure core 1 cooling systems provide adequate core cooling up to 350 psig.

ADS automatically controls seven selected safety-relief valves. Six valves are required to be OPERABLE since the LOCA analysis assumes 6 ADS valves in addition to a single failure. It is therefore a ropriate it permit one of the required valves to be out-of-service for up to 14 days without materially reducing system reliability.

3M 5. 3 SUPPRESSION CHAMEER The suppression chamber is also required to be OPERABLE as part of the ECC; to ensure that a sufficient supply of water is available to the HPC5, LPC5 and LPCI systems in 'he event of a LOCA. This limit on suppression cna% er minimum water volume ensures that sufficient water is available to permit recirculation cooling flow to the core (See figure B 3/4.6.2-1). The OPERABILITY of the suppression chamber in OPERATIONAL CONDITIONS 1, 2 or 3 is required by Specification 3.6.2.1.

Repair work might require making the suppression chamber inoperable.

This specification will permit thr;e repairs to be made and at the same tir*e give assurance that the irradiated f uel has an adequate cooling water supply when the suppression chamber must be made inoperable ( including craining} in OPERATIONAL CONCITION 4 or 5.

In OPERATIONAL CONDITION 4 and 5 the suppression chamoer minimum recuired W

w a '. e c volume is reduceo because the reactor coolant is maintained at or Delew 20;;;

Since pressure suppression is nct required below 210*f, the mininum wate" volume is based on NPSH, recirculation volume, vortet orevention plus a 2'-4" tafety rnargin for conservatism LA SALLE - UNIT 1 B 3 M 5-2 Amenatent No. 59

  • f .

Suppression Control

  • Plant Room / Local Chamber Level Elevation Indication 86' 10" -

700' 2" +3" High Level LCO (Volume 131,900 fts) 26' 9" -

700' 1" +2"HighLevelAlarmHPCU (EctTon Vilve ransferJ 26' 7" -

699' 11" -

0" Instrument Zero 86' 4" -

699' 8" -3" Low Level Alarm 26' 2 1/2" 699' 6 1/2" -4 1/2" Low Level LCO Opera-tional Condition 1, 2, or 3 (Volume 128,800 ft8 )

14' 687' 4" -12' 7" Low Level LCO Opera-tional Condition 4 or 5 (Volume 70,000 ft3 )

SUPPRESSION POOL LEVEL SETP0lHTS BASES FIGURE B 3/4.6.2-1 LA SALLE - UHli 1 B 3/4 6-3a Amendment No. 59 L

g TABLE 3.3.3-1 (Continued)

% EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 2

MINIMUM OPERABLE APPLICABLE c CHANNELS PER TRIP OPERATIONAL

$ TRIP FUNCTION FUNCTION I ") CONDITIONS ACTION C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM
s. Reactor vessel Water Level - Low, Low, level 2 4 1, 2, 3, 4*, 5* 35 p) b. Drywell Pressure - High
  • 4 1, 2, 3 35 gyy c. Reactor Vessel Water Level-High, level 8 g ,

4g 1, 2, 3, 4*, 5*

j Condensate Storage Tank Level-Low 2(d) 1, 2, 3, 4 *, 5*

32_

36

e. L5uppression Pool Water Level-High 2 1, 2, 3, 4 * , 5* 36 w f. Pump Discharge Pressure-High (Bypass) '

1 1,2,3,4*,5" ll e g. HPCS System Flow Rate-Low (Permissive) I 1, 2, 3, 4*, 5* 31 w

h. Moaual Initiation 1/ division 1, 2, 3, 4* , 5* 34 m

D. LOSS OF POWER MINIMUM TOTAL NO. INSTRU- OPERABLE APP *.ICABLE OF INSTRU- MENTS TO INSTRU- OPERATIONAL MENTS TRIP MENTS(a) CONDITIONS ACTION

1. 4.16 kV Emargency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5** 37 (Loss of Voltage)
2. 4.16 kV Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4* *, 5** 37 (Degraded Voltage) l TABLE NOTATION 2-4 (a) A channel / instrument 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 /> during periods of required 5 surveillance without placing the trip system / channel / instrument in the tripped condition provided at least S one other OPERABLE c5 anne 1/ instrument in the same trip system is monitoring that parameter.

S (b) Also actuates the associated division diesel generator.

r

?

(c) Provides sicnal to close HPCS pump discharge valve only on 2-out-of-2 logic.

1(d)

Provides signal to HPC5 pump suction valves only.J w

Applicable when the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.

Required when ESF equipmant is required tn be OPERABLE.

  1. Not required to be OPERABLE when reactor steam doma pressure is < 122 psig.

't

  • TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 - With the number of OPERABLE channels less than required by the Mir.imum OPERABLE Channels per Trip Function requirement:

a. With one channel inoperable, place the inoperable channel in the tripped condition within one hour
b. With more than one channel inoperable, declare the associated system inoperable.

ACTION 31 - With the nun.ber of OPERABLE channels less than required by the MirJmum OPERABLE channels per Trip Function, place the inoperable chasinel in the tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare the issociater system inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the asnociated A05 trip system or ECCS inoperable.

ACTION 33 - With the numbe of OPERABLE chan'nels less than the Minimum OPERABLE Channti.s 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 OPERAELE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the al.sociated ADS trip system or ECCS inoperable. l 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 condition within one hour
  • or declare the HPCS system

{)elded inoperable.

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

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 channel in the tripped condition within t one hour

ACTION 37 - With the number of OPERABLE instruments less than the Minimum OPERABLE INSTRUMENTS, place the inoperable instrument (s) in the tripped condition within I hour

"The provisions of Specification 3.0.4 are not applicable.

LA SALLE - UNIT 2 3/4 3-27 Amendment No.27

= .-

i l

_T_ABLE 3.3.3-2 (Continued)

EMERGENCY CORE COOLING SYSlEM ACTUATION INSTRUMENTATION SETPOINTS ALLOWABLE TRIP SETPOINT VALUE h TRIP FUNCTION E C. DIVISION 'l TRIP 5YSTEM r

$ 1. HPCS SYSTEM Reactor Vessel Water Level - Low Low, level ? >- 50 inches

  • 2- 57 inches
  • h a.

i; . Drywell Pressure - High 5 1.69 psig i 1.89 psig y

c. Reactor Vessel Water Level - High. Level 8 < 55.5 inches *

~

< 56 inches *~

j

' '" d. ' Condensate Storage Tank Level - Low M 15'7" T 715'3" Delded e. Suppression Pool Water Level - Hiah 'E 2 inches ** < 3 inches ** j f.

t Pump Discharge Pressure - High ~' T 20 psig 7 110 psig

g. HPCS System Flow Rai.e - Low g 1000 gpm > 900 gpm
h. Manual Intiation N.A. P.A.

l \

D. LOSS OF POWER

) w 1. 4.16 kV Emergency Bus Undervoltage l } (Loss of Voltage)#

l y a. 4.16 kV(Easis 8usc3

$ 1) Divisions 1 and 2 2625 131 volts with 2625 t 262 volts with 5 10 second time delay < 11 second time delay I 2496 125 volts with 2496 250 volts with 2 4 second time delay 2 3 second time delay

2) Division 3 2870 143 volts with 2870 1 287 volts with i 10 second time delay 1 11 second time delay 37 TABLE NOTATIONS
5. *See Bases Figure B 3/4 3-1.

S #These are inverse time delay voltage relays or instantaneous voltage relays with a time delay. The voltages shown

! 5 are the e.aximum that will not result in o trip. Lower voltage conditions will result in decreased trip times.

- N.A. Not Applicable I

? I** Level is referenced ta a plant elevation of 699 feet 11 inches (See Figure B 3/4.5.2-1). W l a

(

~

TABLE 3.3.3-2 (Continued) l-55 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS m"

ALLOWABLE TRIF SETPOINT VALUE f [ TRIP FUNCTION 2

D. LOSS OF POWER (Continued)

'o 2. 4.1, kV Emergency Bus Undervoltage (Degraded Voltage). / ,_ ,

a. 4.16 kV g s (6 Ges
1) Divisions 1, 2 and 3 3814 -3 volts with 3814 76 volts with l 10 1 1 secon's time 10 1 seconds time delay t

l delay with LUCA signal with LOCA signal or or l 5 1 0.5 minutes time delay l 5 0.5 minute

  • time delay without et T without LOCA signal u,

signal N,

z .

Y l 8

~

1 1

l l

y, l a

! S l E 1 =

0 e

1

. -[

.c g TABLE 4.3.3.1-1 (Continued)

[ EMERGENCY CORE COOLING SYSTEM ACTUATION-INSTRUMENTATION SURVEILLANCF REQUIREMENTS

'2

, CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH u

TRIP FUNCTION. CHICK TEST CAllBRATION SURVEILLANCE REQUIRED 4 N C. ' DIVISION 3-TRIP SYSTEM -

- 1. HPCS SYSTEM ~

a. Reactor Vessel Water.Le' vel - i Low Low, Level 2 NA M R 1, 2, 3, 4*, 5  ;
b. Drywell: Pressure-High. NA M' Q 1, 2, 3 g{ated c. Reactor Vessel Water Level-High Level 8 NA M R 1, 2, 3, 4 * , 5* i
d. ' Condensate Storage Tank Level '

w Low NA M 1, 2, 3, 4*, 5*

Q .

a e. Suppression Pool Water - '

w level - Hioh NA M Q 1, 2, 3, 4*, 5* ;

w f. Pump Discharge Pressure-High NA M Q 1, 2, 3, 4", 5"

g. HPCS System Flow Rate-tow NA M Q 1, 2,'3, 4*, 5* ,
h. Manual' Initiation NA R NA 1, 2, 3, 4*, 5* i i

4 D. LOSS OF POWER

1. 4.16 kV Emergency Bus Under- NA NA R 1, 2, 3, 4**, 5**

voltage.(Loss of Voltage) ,

2. 4.16 kV Emergency Bus Under- NA NA R 1, 2, 3, 4**, 5**- -i voltage (Degraded. Voltage) y ,

TABLE NOTATIONS h #Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 122 psig.

k *When the system is required to be 0PERABLE af ter being manually realigned, as applicable, per ,

, Specification 3.5.2.

P **Roquired when ESF' equipment is required to be OPERABLE.

i y .--way m W yyi er ti @ "ur _ _-J L-----

  • 4 ,

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Performing a CHANNEL CALIBRATION of the:

a) Discharge line " keep filled" pressure alarm instrumentation and verifying the:

1) High pressure setroint and the low pressure setpoint of the:

(a) LPCS system to be 1 500 psig and 1 55 psig, respectively.

(b) LPCI subsystems to be 5 400 psig and 3 55 psig, respectively.

'2) Low pressure setpoint of the HPCS system to be 1 63 psig.

b) Header delta P instrumentation and verifying the setpoint of the:

1) LPCS system and LPCI subsystems to be 1 psid.
2) HPCS system to be 5 2.0 psid greater than the normal indicated aP.

b h 3. Verifying that the suction for the HPCS system is automatically transferred f rom the condensate storage tank to the suppression chamber on a condensate storage tank low water level signal and ton a suppression chamber high water level signal.

4 Visually inspecting the ECCS corner room watertight door seals and room penetration seals anc verifying no abnormal degradatio..,

damage, or obstructions.

d. For the ADS by:
1. At least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the accumulator backup compressed gas system lo- 3ressure alarm system.
2. At least once per 18 months:

a) Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence, but excludirg actual valve actuation, b) Manually opening each ADS valve and observing the expected chang 2 in the indicated valve position.

c) Performing a CHANNEL CALIBRATION of the accumulator backup compressed gas system low pressure alarm system and verifying an alarm setpoint of 500 + 40, - O psig on decreasing pressure.

LA SALLE - UNIT 2 3/4 5-5

t o <

EMERGENCY CORE COOLING SYSTEMS, 3/4.5.2 ECCS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE:

a. The low pressure core spray (LPCS) system with a flow path capable of taking suction from the suppression chamber and transferring the water through the spray sparger to the reactor vessel.
b. Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from * % suppression chamber upon being manually realigned and transt ring the water to the reactor vessel.
c. Low pressure coolant injection (LPCI) subsystem "B" of the RHR system with a flow path capable of taking suction from the suppression chamber upon being manually realigned and transferring the water to the reactor vessel.
d. Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of taking suction from the suppression chamber upon being manually real_igned and tr nsferring the water to the reactor vessel, ge _ c.g55 ;en o.(
e. The high pressure core spray (HPCS) system with a flow pat capable of taking suction f rom {one of the f ollowing water sourcesf and trans- V ferring the water through the spray sparger to tne reactor vessel .
1. From the suppression chamber, or 1
2. When the suppression pool level is less than the limit or is I arained, from the condensate storage tank containing at least 135,000 available gallons of water, equivalent to a level of

, 14.5 feet.j APPLICABILITY: OPERATIONAL CONDITION 4 or 5*,

ACTION:

a. With one of the above required subsystems / systems inoperable, restore at least two subsystems / systems to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations that have a potential for draining the reactor-vessel.
b. With both of the ::bove required subsystems / systems inoperable, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel. Restore at least one subsystem /

system to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish SECONDARY CONTAIPMENT INTEGRITY within the r w t B hours.

  • Tne ECCS is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded, the spent fuel pool gates are removed, and water level is maintained within the limits of Specifications 3.9.8 and 3.9.9.

LA SALLE - UNIT 2 3/4 5-6

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2.1 At least the above required ECCS shall be demonstrated OPERABLE per Surveillance Requirement 4.5.1, except that the header delta P instrumentation is not required to be OPERABLE.

4.5.2.2 The HPCS system shall be determined OPERABLE at least once per (_, ' '

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the condensate storage tank required volume when the condensate storage tank is required to be OPERABLE per Specification 3.5.2.e.

E LA SALLE - UNIT 2 3/4 5-7

LIMITING CONDITION FOR OPERATION 3.5.3 Tne suppression chamber shall be OPERABLE:

a. In OPERATIONAL CONDITION 1, 2, or 3 with a contained water volume of at least 128,800 f ta, equivalent to a level of -41/2 inches.**

b.

In OPERATIONAL CONDITION 4 or 5* with a contained water volume of at least70,000fta,equivalenttoalevelof-12 feet 7incheQ*gexcept' that the suppression chamber level may be less than the limic or may be drained in OPERATIONAL CONDITION 4 or 5* provided that:

1.

No operations are performed tr.at have a potential for draining N

the reactor vessel, 2.

The reactor mode switch is locked in the Shutdown or Refuel position,

3. The condensate storage tank contains at least 135,000 available gallons of water, equivalent to a level of 14.5 feet, and 4 The HPCS system is OPERABLE per Specification 3.5.2 with an OPERABLE flow path capable of taking suction frcm the condensate storage tank and transferring the water through the spray sparger to the reactor vessel.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5*.

ACTION:

a. In OPERATIONAL CONDITION 1, 2, or 3 with the suppression chamber water level less than the above limit, restore the water level to within the limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 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 />.
b. J In OPERATIONAL CONDITION 4 or 5* with the suppression chamber water level less than the above limit [cr drained and the above recuired

% conditions._not satisfied /, suspeno CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the Shutcown position. Establish SECONDARY CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

  1. 5ee Specification 3.6.2.1 for pressure suppression requirements.

"The suppression chamber is not required tc be OPERABLE provided that the reactor vessel head is removed, toe cavity is flooded or being flooded frem the suppression pool, the spent fuel pool gates are removed when the cavity is flooded, anc the water level is maintainec within the limits of Specifications 3.9.8 and 3.9.9.

"" Level is referenced to a plant elevation of 699 feet 11 inches (see Figure B 3/4.6.2-1).

LA SALLE - UNIT 2 0 5-S Amenament No. 39

. .- s.

-(

a, g EMERGENCY CORE COOLING SYSTEMS l LIMITING: CONDITION FOR OPERATION (Continued) i ACTION: (Continued)

c. With one suppression chamber water level instrumentation channel >

inoperable, restore the inoperable channel to OPERABLE _ status within 7- days or verify the suppression chamber water level. to be greater

-the.n or equal to -4 1/2 inches ** or '12 feet 7 inches **, as applicable,

  • at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication,
d. :tiith both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel to OPERABl.E status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or b,e 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 SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and verify the suppression chamber water level to be greater than or equal to -41/2 inches ** or -12 feet 7 inches **, as applicable, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by local indication. 1 SURVEILLANCE RE0VIREMENTS 4.5.3.1 The, suppression chamber shall be determined OPERABLE by verifying:
a. The water level to be-greater than or equal to, as applicable: ,
1. -4 1/2 inches ** at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2 .- -12 feet 7 inches ** at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. Two suppression chamber water level instrumentation channels OPERABLE by performance of.a:
1. CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
2. CHANNEL FUNCTIONAL 1 TEST at least once per 31 days, and

-3. CHANNEL CALIBRATION at least once per 18 months, with the low water level-alarm setpoint'at greater than or equal to -

-3. inches.**

4.5.3.2 With the suppression chamber level less than the above limit lor drained in OPERATIONAL CONDITION 5*, at least once per 12-.hoursQ q ,

a. 'VerifytherequiredconditionsofSpecification3.5.3.b.to'be) '

i satisfied, or: f bil /erifyfootnoteconditions*tobesatisfied.

V ..- w

  • T e suppression chamber is not required to be OPERABLE provided that the reactor vessel head is= removed,-the cavity is^ flooded or being flooded from the suppres-sion pool, the spent ~ fuel pool gates are-_ removed when the cavity is flooded, and the water level is maintained within the limits of Specifications 3.9.8-and 3.9.9.
    • Level-is referenced to a plant elevation of 699 feet 11 inches (See Figure B 3/4.6.2-1). '

LA SALLE --UNIT' 2 3/4 5-9 Amendment'N . 39 r a- #,, -- - e- w

TABIE 3.6.3-1 (Continued) r-n PRIMARY CONTAINMENI ISOEATION VALVES V

E

, VALVE F UNCil0N Ah ) NtlMBER OtSer Isolation Valves (Continued)

4. Eow Pressure Core Spray System 2E21-F005 2E21-F001 II) 2E21-f012 Ib5 2E21-f011 Id}

2E21-F018 Il) 2E21-f031 Id) 2E 21-F 006 I) w 5. High Pressure Core Spray System s

" 2L22-F004 T 2E22-F015 Ii)

M 2E22-F023 I3) l 2E22-1012h5  ;

2E22-fP14*II 2E22-1005 I)

6. Reactor Core Isolation Cooling System i 2E51-f 013 l 2E51-F 069 l 2E51-F028

[

2E51-F068 2E51-F040 E,' N(i) f 2Es1-FOS 9(m) 2E51-F065 k) P_ E 51- FO ZZ (.m) 2E51-rc66 IkI 2_ ES1- F 361 (n) 4 2E51- F363 (n) 1 W

~

TABLE 3.6.3-1 (Continued)-

PRIMARY CONTAINMENT ISOLATION VALVES k VALVE'IUNCTION AND NUMBER-Other Isolation Vahes -(Continued)

7. Post LOCt. Hydrogen Control Z 2HG001A,:B- r

~ 2HG002A, B=

2HG005A,'B '

2HG006A, B-  :

fYiove, fooho'h% ko  !

8. Standby L.iquid Control System 2C41-F004A, 8 2C41-F007 .

y

9. Reactor Recirculation Seal Injection 1 w 2B33-F013A, D Ill 2 2033-F017A, B I3) l T

w

10. .Drywell Pneumatic Valves  !

21N018  !

TABLE NOTATIONS j

'But >'3 seconds.

g t

,i (a) See Specification 3.3.2, Table 3.3.2-1, for isolation signal (s) that operates each valve group.

(b). Not included in total sum of Type B and C tests.

(c) May be. opened on an intermittent basis under administrative control. 1 (d) Not closed by SLCS actuation. i (e) Not closed by Trip functions Sa, b, or c. Specification 3.3.2 Table 3.3.2-1.  !

(f) Not closed by Trip functions 4a, c, d, e, or f of Specification 3.3 2 T;ble 3.3.2-1. '

(g) Not subject to Type C leakage test. [

(h) Opens on an isolation signal. Valves will be open during Type A test. No Type C test required. l (i). Also closed by dryweli pressure-high signal. J y (j) Hydraulic leak test at 43.6 psig. ,  !

g (k) Not subject to lype C ' leakage test - leakane rate tested per Specification 4.4.3.2.2. l f} (1) Ihese penetrations are provided with removable spools outboard of the outboard isolation valve.  ;

% Daring operation, these lines will be blind flanged using a doubic 0-ring and a type B leak ,

'* - test. In addition, the packing of these isolation salves will be soap-bubble tested to ensure  ;

& insignificant or no leakage at the cor.tainment test pressure ecch refueling outage. -

U j s , +

y TABLE 3.6<3-1 (continuedl

, ,c- .,

121EMLCONTAINMENT ISQLAIl0N VALVES TABLE NOTATIONS Hove footnotes "*" and (a) through (1) from Page 3/4 6-37 to this location,

m. If valves 2E51-F362 and 2E51-F363 are locked closed and acceptably leak rate tested, then valves 2E51-F059 and 2E51-F022 are not considered to be primary containment isolation valves and are not required to be leak rate tested.
n. Either the 2E51-F362 or the 2E51-F363 valve may be open when the RCIC system is in the standby mode of operation, and both valves may be open during operation of the RCIC system in the full flow test mode, providing that:
1) valve 2E51-F0?' is acceptably leak rate tested, and
2) valve 2E51-F059 is deactivated, locked closed and acceptably leak rate tested, and
3) the spectacle flange, installed immediately downstream o' the 2E51-F059 valve, is closed and acceptably leak rate tested, i

l l

l

[

L LASALLE - UNIT 2 3/4 6-37a Proposed Amendment l 1174/10

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

. . - , p, . . ,

TABLE 3.8.3.3-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVCRLOAD PR01ECIlON

-BYPASS DEVICE -5YSTEM(5) .

VALVE NUMBER- (Continuous)(Accident Conditions) AFFECTED .,

2E32 - F003N Accident Conditions-

-2E32 - F006 ~ Accident Conditions 2E32 - F007 Accident Conditions

'2E32 - F008 Accident Conditions

=2E32 - F009- Accident Conditions +

m. QL.22-F001 Accident Condit' ons HPCS system 2E22 - F004 Accident Condit'ons p. /

702 - F610 Accident conditions' /

,2E22 - FQ11 Attiggat_CgD#tions! i

.2E22 =F012- Accident Cond'ltions 2E22 .-F015- 1' dent Co_nditions

=2E22 - F023 -

-Accident Conoitions 2+~

  • CetiMouts

~

L l

LASALLE - UNIT ~2 3/4 E-30 Amendment No. 25

/

3/4.5 EMERGENCY CORE COOLING SYSTEM BASES 3/4.5.1 and 3/4.5.2 ECCS - OPERATING and SHUTDOWN ECCS Division 1 consists of the low pressure core spray system, low pres-sure coolant injection subsystem "A" of the RHR system, and the automatic de-pressurization system (ADS) as actuated by ADS trip system "A". ECCS Division 2 consists of low pressure coolant injection subsystems "B"and "C" of the RHR sys-tem and the automatic depressurization system as actuated by ADS trip system B".

Tho low pressure core spray (LPCS) system is p.evided to assure that the core is adequately cooled following a loss-of-coolant accident and provides adequate core cooling capacity for all break sizes up to and including the double ended reactor recirculation line break, and for transients or smaller breaks following depressurization by the ADS. l The LPCS is a primary source of emergency core cooling after the reactor vessel is depressurized and a source for flooding of the core in case of accidental draining.

The surveillance requirements provide adequate assurance that the LPCS sys-tem will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

The low pressure coolant injection (LPCI) mode of the RHR system is pro-vided to assurt that the co're' is adequately cooled following a loss-of-coolant accident. Three subsystems, each with one pump, provide adequate core flooding for all break sizes up to and including the double-ended reactor recirculation line break, and for transients or small breaks following depressurization by the l ADS.

The surveillance requirements provide adequate assurance that the LPCI system will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test requires reactor

_ shutdown. The pump discharge piping is maintained full to prevent water l hammer damage to piping and to start cooling at the earliest moment.

ECCS Division 3 consists of the high pressure core spray system The high pressure core spray (HPCS) system is provHed to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the reactor coolant system and loss of coolant which does not result in rapid depressurization of the reactor vessel. The HPCS system permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized. The HPCS system operates over a range of 1160 psid, differential pressure between reactor vessel and HPCS suction source, to O psid.

I The capacity of the HPCS system is selected to prcvide the required core cooling. The HPCS pump 4 designed to deliver greater than or equal _ to

~ 516/1550/6200 opm_at differ _ential pressures of 1160/1130/20u psid. / Initially,

{ water from the condensate storaga tank is used insteso of injecting watar from LA SALLE - UNIT 2 B 3/4 5-1 Amendment No. 27

r Wder h, hken froM M 5 g w wa ee m L*MERGENCY CORE COOLING SYSTEMS 55 M fo65 c.

BASES ,

ECCS-OPERATING and SHUTDOWN (Continued)

~

the suppression pool into the reactor, but no credit is taken in the hazards 1 analyses for the ccndensate storage tank water. I s

With the HPCS system ino'>erable, adequate core cooling is assured by the OPERABILITY of the redundant and diversified automatic depressurization system and both the LPCS and LPCI systems. In addition, the reactor core isolation cooling (RCIC) system, a system for which no credit is taken in the hazards analysis,-will automatically provide makeup at reactor operating pressures on a r2 actor low water level condition. The HPCS out of w "vice period of 14 days is based on the demonstrated OPERABILITY of rer..,ndant ar.d diversified low pressure core cooling systems.

The surveillance requirements provide adequate assurance that the HPCS system will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation through a test loop during reactor operation, a complete functional test with reactor vessel injection requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage and to provide cooling at the earliest moment.

Upon failure nf the HPCS system to function properly, if required, the automatic depressurization system (ADS) automatically causes selected safety-relief valves to open, depressurizing the reactor so that flow from the low pressure core cooling systems can enter the core in time to limit fuel cladding temperature to less than 2200'F. ADS is conservatively required to be OPERABLE whenever reactor vessel pressure exceeds 122 psig even though low pressure core -

cooling systems provide adequate core cooling up to 350 psig.

l ADS automatically controls seven selected safety relief valves.

Six valves are required to be OPERABLE since the LOCA analysis assumes 6 ADS valves in addition to a single failure. It is therefore appropriate to permit one of the required valves to be out of-service for up to 14 days without materially reducing system reliability.

t 3/4.5.3 SUPPRESSION CHAMBER l The suppression chamber is also required to be OPERABLE as part of the ECCS l to ensure that a sufficient supply of water is available to the HPCS, LPCS and i LPCI systems in.the event of a LOCA. This limit on suppression chamber minimum l water volume ensures that sufficient water is available to permit recirculation cooling flow to the core (See Figure B 3/4.6.2-1). The OPERABILITY of the suppression chamber in OPERATIONAL CONDITIONS 1, 2 or 3 is required by Specification 3.6.2.1.

Repair work might wuire making the suppression chamber inoperable.

-This-specification will r ymit those repairs to be made and at the same time-i give assurance that t'

,rradiated fuel-has an adequate cooling water supply when the suppression chamber must be made inoperable /; including draining, in OPERATIONAL CONDITION 4 or 5.

In OPERATIONAL CONDITION 4 and 5 the suppression chamber minimum required water volume is reduced because the reactor coolant is maintained at or below 200 F. Since pressure suppression is not required below 212 F, the minimum water volume is bated on NPSH, recirculation volume, vortex prevention plus a 2'-4" safety margin for conservatism.

LA SALLE - UNIT 2 B 3/4 5-2 Amendment No. 41

- - - - - - . . - - - .-,--4 - . , - , , - , . -

(

e. . Control

'*5u)pression Plant Room / Local

- Chamber Level Elevation Indication 26' 10" -

700' 2" +3" High Level LCO (Volume 131,900 ft 3) 26' 9" 700' 1" +2" High Level AlarmjHPCS 1 ISuctionValveTransfer/

26' 7" 699' 11" 0" Instrument Zero 26' 4" 699' 8" -3" Low Level Alarm 26' 2 1/2" 699' 6 1/2" -4 1/2" Low Level LCO Opera-r Vo 28,8b0ft) 3 1

V 14' --

687' 4" -12' 7" Low Level LCO Opera-tional Condition 4 or 5 (Volume 70,000 ft3)

_. SUPPRESSION POOL LEVEL SETPOINTS BASES FIGURE B 3/4.6.2-1 LA SALLE UNIT 2 B 3/4 6-3a faendment No. 39

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