ML20212H294

Proposed Tech Specs,Including Mods That Will Be Installed on Div I During First Refueling Outage

ML20212H294
Person / Time
Site:	LaSalle
Issue date:	02/26/1987
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20212H288	List: ML20212H283 ML20212H294
References
NUDOCS 8703060067
Download: ML20212H294 (5)

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1 ATTAC19ENT B TECHNICAL SPECIFICATION CHANGE REOURST i

1 LASALLE COUNTY STATION UNIT 2  !

PROPOSED CHANGES TO APPENDIX A i

I REVISED PAGES:

NPF-18 3/4 3-26 3/4 3-30a 3/4 3-34 I

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0703060067 870226 4 PDR ADOCK 0500 P

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, e .t TABLE 4.3.3.1-1 (Continued)

C g EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS F

m CHANNEL OPERATIONAL

' CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH CHECK TEST CALIBRATION SURVEILLANCE RE00! RED E TRIP FUNCTION

[ C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM

a. Reactor Vessel Water Level - '- 1, 2, 3, 4* , 5*

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

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*

m

) e. Suppression Pool Water 1, 2, 3, 4 * , 5*

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

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

• g. HPCS System Flow Rate-Low NA 1, 2, 3, 48, 5*

h. Manual Initiation NA R D. LOSS OF POWER 4.16 kV Emergency Bus Under- NA NA R 1, 2, 3, 4**, 5**

1.

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

2. '

voltaae (Dearaded Voltage)

Qliivisions2and3 TABLE NOTATIONS N #Not required to be OPERABLE when reactor steam done pressure is less than or equal to 122 psig.

3 k *When the system is required to be OPERABLE af ter being manually realigned, as applicable, per a Specification 3.5.2. ,.

W ** Required when ESF equipment is required to be OPERA 8LE.

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!?v g TABLE 3.3.3-l'(Continued) y EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION r-b MINIMUM OPERA 8LE . APPLICABLE

' CHANNELS PER TRIP OPERATIONAL FUNCTION I ") CONDITIONS ACTION b

-e TRIP FUNCTION

'* DIVISION 3 TRIP SYSTEM C.

1. HPCS SYSTEM 3

a. Reactor Vessel Water Level - Low, Low, Level 2 4 1, 2, 3, 4*, 5* 35-4 1, 2, 3 35

b. Drywell Pressure - High g Reactor Vessel Water Level-High, Level 8 1, 2, 3, 4* , 5* 32 c.

Condensate Storage Tank Level-Low 2(e) 2 d) 1, 2, 3, 4* , 5* 36

d. g) 1, 2, 3, 4* , 5* 36

e. Suppression Pool Water Level-High .2

f. Pump Discharge Pressure-High (8ypass) 1 1,2,3,4*,5* 31 w 1, 2, 3, 4* , 5* 31

g. HPCS System Flow Rate-Low (Permissive) 1 2 1/ division 1,2,3,4*,58 34 m h. Manual Initiation LOSS OF POWER MINIMUM D.

TOTAL NO. INSTRU- OPERA 8LE APPLICA8LE OF INSTRU- MENTS 10 INSTRU- OPERATIONAL MENTS TRIP MENTS(a) CONDITIONS ACTION 4.16 kV Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4** , 5** 37

1. ~

(Loss of Voltage) b r ded Vo g) i 2 and 3) ,

TABLE NOTATION (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 a surveillance without placing the trip system / channel / instrument in the tripped condition provided at least S one other OPERA 8LE channel / instrument in the same trip system is monitoring.that parameter.

E (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.  ? -

E

• Applicable when the system is required to be OPERA 8LE per Specification 3.5.2 or 3.5.3.-

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• • Required when ESF equipment is required to be OPERA 8LE.

'" # Not required to be OPERABLE when reactor steam done pressure is 5 122 psig.

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,a **g TA8tE 3.3.3-2 (Continued).

g E EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRt#ENTATION SETP0lNTS F

" ALLOWABLE

• TRIP SETPOINT VALUE TRIP FUNCTION b D. LOSS OF POWER (Continued) ,

N 2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

a. 4.16 kV Sasis 3814 1 76 volts with 3814 1 76 volts with

1) Divisions 2 r' 1 10 1 1 seconds time 10 1 1 seconds time delay I , a cin ct 3 with LOCA signal delay with LOCA signal ,

or or 5 1 0.5 minutes time 5 1 0.5 minutes time delay~

delay without LOCA without LOCA signal signal g

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t ATTAQ9ENT C TECHNICAL SPECIFICATION CHANGE REOUBST LASALLE COUNTY STATION UNITS 1 AND 2 SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specifica-tion Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10CFH50.92, operation of LaSalle county Station Units 1 and 2 in accordance with the proposed amendment will nots (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 e 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, i

based on the guidance provided in the Federal Register and the criteria established in 10CFH50.92(e), the proposed change does not constitute a l significant hazards consideration.

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