ML20136G346

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Proposed Tech Spec Changes to Include Low & Degraded Grid Voltage Mods That Will Be Installed on Divs I,Ii & III Trip Sys During First Refueling Outage.W/Significant Hazards Consideration
ML20136G346
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 11/13/1985
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20136G333 List:
References
0881K, 881K, NUDOCS 8511220323
Download: ML20136G346 (15)
v • d • e


Text

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ATTACFNENT B PROPOSED CHANGE TO-APPENDIX A TECHNICAL SPECIFICATION TO OPERATING' LICENSES NPF-ll and NPF-18 Revised-pages:

NPF NPF-18 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 3/4 3-27(a) 3/4 3-27(a) 3/4 3-30 3/4 3-30 3/4 3-34 3/4 3 p5J**ndi! Biaysga P

0881K

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TABLE 3.3.3-1 (Continued) g ,

v EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

,i MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL FUNCTION (a) CONDITIONS ACTION E TRIP FUNCTION L C. DIVISION 3 TRIP SYSTEM R ctor Ve sel Water Level - Low, Low, Level 2 4 1, 2, 3, 4*,'5* 35 1, 2, 3 35

b. Drywell Pressure - High 4(c) 1, 2, 3, e , 5* 32
c. Reactor Vessel Water Level-High, Level 8 2(d) 1, 2, 3, 4*, 5* 36
d. Condensate Storage Tank Level-Low 2(d)
c. Suppression Pool Water Level-High 2 1, 2, 3, 4* , 5* 36 Pump Discharge Pressure-High (Bypass) 1 1, 2, 3, 4*, 5* 31 f.

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

4*, 5* 34

h. Manual Initiation 1/ division 1, 2, 3, MINIMUM APPLICABLE 4*

D. LOSS OF POWER TOTAL NO. C;;n :::CL, OPERABLE OPERATIONAL OF CitANNEt6 TO TRIP J "":':ELS N CONDITIONS ACTION 4.16 kv Emergency Bus Undervoltage N bus N bus N bus 1, 2, 3, 4**, 5** 37 1.

(Loss of Voltaae)

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(a) A channe1 %ay be placed 7n an inoperable st 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 syste n the tripped condition provided at least one fg_ _y other OPERABLE channeltin the same trip system is monitoring that parameter.

_" ~P(b) Also actuates the associated division diesel generator.

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

(d) Provides signal to HPCS pump suction valves only.

  • Applicable when the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
    • Required when ESF equipment is required to be OPERABLE.
  1. Not required to be OPERABLE when reactor steam dome pressure is < 122 psig.

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TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION i

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 associated system inoperable.

ACTION 31 -

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

ACTION 32 -

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

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

ACTION 34 -

With the number of OPERABLE channels less than required by the

' Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <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. l29 With the number of OPERABLE channels less than required by the ACTION 35 -

Minimum OPERABLE Channels per Trip Function requirement

a. For one trip system, place that trip system in the tripped condition within one hour
b. For both trip systems, declare the HPCS system inoperable.

With the number of OPERABLE channels less than required by the ACTION 36 - Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour

the n er of OP BLE cha s less an the To al umber eclar the assoc tec emer ency fese gene at ACTION 37 - Wi q hann s, nop r le an ta the CTI reqtire by Spec *ff ation ...

r 3. 1.2, as propria e 7

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  • The provisions of Specification 3.0.4 are not applicable,

%NNJ Amendment No. 29 3/4 3-27 LA SALLE - UNIT 1

~.

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE CDOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 38 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per trip function requirements:

With one channel inoperable, remove the inoperable channel I*

a.

within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare the associated ECCS systems inoperable.

b. With both channels inoperable, restore at least one channel to OPERABLE status within one hour or declare the associated ECCS systems inoperable.

MN aa.e_ cCCt h eL

. s LA SALLE - UNIT 1 3/4 3-27(a) Amendment 10

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(w=-MW 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 />

ACTION 39 With the number of OPERABLE instruments one less than the Minimum Operable instrument, place the inoperable instrument in the tripped condition within one hour *. With both the inst:uments inoperable, verify that the remaining divisions'-degraded voltage instruments are operable and restore at least one ,

instrument to operable status within 7 days, or declare the associated emergency diesel generator inoperable and take.the action. required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

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e ie TABLE 3.3.3-2 (Continued) 5 y, EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS E

E ALLOWABLE

, TRIP FUNCTION TRIP SETPOINT VALUE C

}

C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM
a. Reactor Vessel Water Level - Low Low, Level 2 1- 50 inches
  • 1- 57 inches *
b. Drywell Pressure - High 5 1.69 psig 1 1.89 psig
c. Reactor Vessel Water Level - High, Level 8 5 55.5 inches
  • 1 56 inches *
d. Condensate Storage Tank Level - Low > 715'7" > 715'3"
e. Suppression Pool Water Level - High 3700'1" 3700'2"
f. Pump Discharge Pressure - High 1 120 psig 1 110 psig
g. HPCS System Flow Rate - Low 1 1000 gpm 1 900 gpa w h. Manual Intiation NA NA 1

w D. LOSS OF POWER O

o 1. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage)#

a. 4.16 Kv Basis
1) Divisions 1 and 2 2625 i 131 volts with 2625 1 262 volts with 5 10 second time delay 5 11 second time delay 2496 i 125 volts with 2496 1 250 volts with 1 4 second time delay 1 3 second time delay
2) Division 3 2870 1 143 volts with 2870 1 287 volts with QM i 10 second time delay 1 11 second time delay pp Y

~

  • See Bases Figure B 3/4 3-1.
  1. These are inverse time delay voltage relays or instantaneous voltage relays with a time delay. The voltages shown are the maximum that will not result in a trip. Lower voltage conditions will result in decreased trip times.

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.. e TABLE 4.3.3.1-1 (Continued) 9

, EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

?

r-7 CHANNEL FUNCTIONAL OPERATIONAL CHANNEL CllANNEL CONDITIONS FOR WHICil E TRIP FUNCTION CilECK TEST CALIBRATION SURVEILLANCE REQUIRED

-i e C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM
a. Reactor Vessel Water Level -

Low 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 Level 8 NA M R 1, 2, 3, 4*, 5*
d. Condensate Storage Tank Level -

, Low ,

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

} e. Suppression Pool Water

, Level - High NA M Q 1, 2, 3, 4*, 5*

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

  • g. HPCS System Flow Rate-Low NA M Q 1, 2, 3, 4*, 5*
h. Manual Initiation NA R NA 1, 2,  ?, 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**

s F

  1. Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 122 psig.
  • When the system is required to be OPERABLE after being manually realigned, as applicable, per Specification 3.5.2. -

g ** Required when ESF equipment is required to be OPERABLE.

g ***The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during g Refuel 1. M e

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TABLE 3.3.3-1 (Continued)

E m EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION K MINIMUM OPERABLE APPLICABLE i

E CHANNELS PER TRIP OPERATIONAL E TRIP FUNCTION FUNCTION (a) CONDITIONS ACTION Q

m C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM
a. Reactor Vessel Water Level - Low, Low, Level 2 4 1, 2, 3, 4*, 5* 35
b. Drywell Pressure - High I' 2, 3 35 Reactor Vessel Water Level-High, Level 8 4(c) 1, 2, 3, 4* , 5* 32
c. 2(d)
d. Condensate Storage Tank Level-Low 1, 2, 3, 4*, 5* 36 Suppression Pool Water Level-High 2(d) 2 1, 2, 3, 4*, 5* 36 e.
f. Pump Discharge Pressure-High (Bypass) 1 1,2,3,4*,5* 31
g. HPCS System Flow Rate-Low (Permissive) 1 1, 2, 3, 4 * , 5* 31 R 1/ division 5* 34
h. Manual Initiation ] 1, 2, 3, 4*,

{

HINIMUM APPLICABLE h D. LOSS OF POWER TOTAL NO. Ci.n J;ELS OPERATIONAL O F CllA!::E L., TO TRIP OPERABLE mllA  :::ELS . (N CONDITIONS ACTION

1. 4.16 kV Emergency Bus Undervoltage h/ bus h/ bus b/ bus 1, 2, 3, 4**, 5** 37 (Loss of Voltage)
2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage) (0! vision 3) g h/ bus 7/ bus // bus 1, 2, 3, 4**, 5**

[N

- (YO 2.dh TABLE NOTATION -

  • .B ew A]MD-(a) A channel ay be placed in an inoperable status for up to z nours auring peri m of required I surveillance without placing the trip syste in the tripped condition provided at least one

/ other OPERABLE channe kin the same trip system is monitoring that parameter.

(b) Also actuates the associated division diesel generator.

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

(d) Provides signal to HPCS pump suction valves only.

  • Applicable when the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
    • Required when ESF equipment is required to be OPERABLE.
  1. Not required to be OPERABLE when reactor steam dome pressure is < 122 psig.

TABLE 3.3.3-1 (Continued)

-EMERGENCY CORE COOLING SYSTEM ACTUATIO1 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 associated system inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip Function, place the inoperable channel in the tripped condition within one hour; restore the

. inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

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

t ACTION 33 - With the number of OPERABLE channels less than the Minimum

' OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

ACTION 34 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Functiori 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 associated ADS valve 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 i condition within one hour
b. For both trip systems, declare the HPCS system inoperable.

ACTION 36 - With the number of OPERABLE channels less than required by the

-Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within j one hour

. ACTION 37 - IWith number o ABLE chan s ss than t al Number

, of anr 1s, d are t asso ted em rgency esel 9 nerator i perab e a take the ACT require by ecificatio 3.8 .1

. r 3.8.1. as appropri .

! "The provisions of Specification 3.0.4 are not applicable.

SAP />4 wt-l LA SALLE - UNIT 2 3/4 3-27 1 g 37

I TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 38 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per trip function requirements:

a. With one channel inoperable, remove the inoperable channel within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare the associated ECCS systems inoperable.
b. With both channels inoperable, rectore at least one channel to OPERABLE status withfo one hour or declare the associated ECCS system inoperable.

w a ta & A b

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LA SALLE - UNIT 2 3/4 3-27(a)

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' 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 />

ACTION 39 With the number of OPERABLE instruments one less than the Minimum Operable instrument, place the inoperable instrument in the tripped condition within one hour *. With both the instruments inoperable, verify that the remaining divisions' degraded voltage instruments are operable and restore at least one instrument to operable status within 7 days, or declare the associated emergency diesel generator inoperable and take the action required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

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TABLE 3.3.3-2 (Continued) ,

9 EMERGENCY CORE. COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS m.

2 ALLOWABLE h TRIP FUNCTION TRIP SETPOINT VALUE g C. DIVISION 3 TRIP SYSTEM U 1. HPCS SYSTEM

a. Reactor Vessel Water Level - Low Low, Level 2 >- 50 inches * >- 57 incras*
b. Drywell Pressure - High 31.69psig 51.89psig
c. Reactor Vessel Water Level - High, Level 8 < 55.5 inches * < 56 inches *
d. Condensate Storage Tank Level - Low' I 715'7" i 715'3"
e. Suppression Pool Water Level - High 3700'1" 5700'2"
f. Pump Discharge Pressure - High 3 120 psig > 110 psig
g. HPCS System Flow Rate - Low > 1000 gpa 1 900 gpa
h. Manual Intiation N.A. N.A.

D. LOSS OF POWER m 1. 4.16 kV Emergency Bus Undervoltage g (Loss of Voltage)#

y a. 4.16 kV Basis U 1) Divisions 1 and 2 2625 i 131 volts with 2625 1 262 volts with

< 10 second time delay 5 11 second time delay 2496 i 125 volts with 2496 i 250 volts with

> 4 second time delay > 3 second time delay

2) Division 3 2870 1 143 volts with 2870 1 287 volts with 1 10 second time delay < 11 second time delay
2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
a. 4.16 kV Basis
1) -IL i s iun4 3814 1 76 volts with 3814 1 76 volts with

- bh 2MS 10 1 1 second time, delay 10 i 1,second time, del ALeeA smxil Lee-A

  • See Bases Figure B 3/4 3-1.

TABLE NOTATIONS f.2 0 5 h uD[p%

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  1. These are inverse time delay voltage relays or instantaneous voltage relays with a time delay. The voltages shown are the maximum that will not result in a trip. Lower voltage conditions will result in decreased trip times.

N.A. Not Applicable

- - - - - - - - - w

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, g TABLE 4.3.3.1-1 (Continued)

!C EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

j

?

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

, -Q m C. DIVISION 3 TRIP SYSTEM l

1. HPCS SYSTEM

) a. Reactor Vessel Water Level -

- Low Low, Level 2 NA M R 1, 2, 3, 4*, 5* l 4 b. Drywell Pressure-High NA M Q 1, 2, 3 Reactor vessel Water Level-High c.

j Level 8 NA M R 1,2,3,4*,5* l

d. Condensate Storage Tank Level -

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

{ R

e. Suppression Pool Water .

1 Level - High NA M Q 1, 2, 3, 4*, 5*

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

W g. HPCS System Flow Rate-Low NA M Q 1, 2, 3, 4*, 5*

h. Manual Initiation NA R NA 1, 2, 3, 4* , 5*

I D. LOSS OF POWER i

I 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) ,

j ina 2 2__- n TABLE NOTATIONS

  • , #Not required to be OPERABLE when reactor steam done pressure is less than or equal to 122 psig.

j [ *When the system is required to be OPERABLE after being manually realigned, as applicable. per P Specification 3.5.2.

g ** Required when ESF equipment is required to be OPERABLE.

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t ATTACHMENT C Significant Hazards-Consideration Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria.for oefining a.

significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

1. -Involve a significant increase in the probability or consequences of an accident previously evaluated because this modification reduces the possibility of common mode failure of electrical equipment due to operation outside the qualified voltage range of the equipment.
2. Create the possibility of a new or different kind of accident from

'any accident previously evaluated because loss of offsite power is an analyzed accident and this modification does-not effect that event.

3. Involve a significant reduction in the margin of safety because this change provides additional limitations and therefore fits the example of a change not likely to involve a significant hazards consideration as indicated in 48FR14870 item (ii).

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore,

-based on the guidance provided in the Federal Register and the criteria established in 10CFR50.92(c), the proposed change ooes not constitute a significant hazards consideration.

l

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