ML20066G065

Proposed Tech Specs Re Main Steam Line Tunnel Isolation Actuation Instrumentation

ML20066G065
Person / Time
Site:	LaSalle
Issue date:	01/18/1991
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20066G063	List: ML20066G060 ML20066G065
References
NUDOCS 9101240353
Download: ML20066G065 (8)

Text

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.. , a ATIACHMENIR P ROPOSED_CBANGESIOlHEIECHNlGALSEERIElQ ATlON S . >

EQBREEB6TJNCtllGENSES_ NEE-11. AND NPF-18 -

REVISED PAGES UNIT 1 (NPF 11)

UNIT 2 (NPF-18) 3/4311 3/4 3-11 3/4 314 (a) _ 3/4 3:14 (a):-

B 3/4 3 2 B 3/4 3 2:

9101240353 910118 i PDR ADOCK 05000373 P PDR ,

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TABLE 3.3.2-1 ISOLATION ACTUATION INSTRIMEN'TATION s;~

VALVE GROUPS MIP"IPhiM OPERABLE  : APPLICABLE OPERt. tid BY CHANNELS PER OPERATIONAL

. TRIP FUNCTION SIGNAL (a) TRIP SYSTEM (b) CONDITION ACTION $

5~ A. f.UTOMATIC INITIATION

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1. PRIMARY CONTAINMENI ISOLATION

a. Reactor Vessel Water Level (1) . Low, Level 3 7 2 1, 2, 3 '20 (2) Low tow,' Level 2 2, 3 2 1, 2, 3 20 (3) Low Low Low, Level 1 [-

1, 10 2 1, 2, 3 20 i

b. DryweII Pressure - High ~2. 7. 10 2 1, 2. 3 20

c. Main Steam Line

1) Radiation - High J 2 1, 2, 3 ' 21 R

3 2 1, 2, 3- 22'

-2) Pressure - Low 1 2 1 23 y 3) Flow - High -1 2/line(d) - 1, 2, 3 ' 21 w

~ d. ' Main Steam Line Tunnel.

• Temperature - High' .172f36' 1 2. 21 ))'

e. Main Steam Line Tunnel aTemperature - High ,d ) ,2'.3'I.

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1 2 I 21 *

f. Condenser Vacuum Low .I 2 1, 2* , 3* 21 0)

2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Vent Exhaust Plenum Radiation - High 4 IC)I') 2 ,

1, 2.'3 and ** 24

b. Drywell Pressure - High '4(c)(e) 2. 1, 2, 3 24 g . c. Ree: tor Vessel Water g)(,)

level - Low Low, Level 2 4 2 1,.2, 3, and , 24 g 'd, Fuel Pool Vent Exhaust

• Radiation - High ;4(C)f*) 2' 3,, 2. 3, and ** 24 .

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i TABLE 3.3.2-1 (Continued)

NOTES (Continued)

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

pressure high, (h) Manual initiation isolates 1E51-F008 only and only with a r,oincident ,

i g(1)BothchannelsoreachtripsystemmayDeplaceuinaninoperablestatusforuh eactor vessel water level-low. level 2 signal, 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 i cycling without placing the trip system in the tripped. condition provided that 1 the a:bient temperature channels in the same trip systems are operable.

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Rept.act 1 WITH INSERT 1

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LA SALLE UNIT-1 3/4 314 (a) Amendment No.26

i INSTRUMENfATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used i to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints and response times for isolation of the reactor systems. When necessary, :

one channel may be inoperable for brief intervals to conduct required surveillance.

Some of the trip settings may have tolerances explicitly stated where both the high (

geg and low values are critical and may have a substantial effect on safety. The set- (1 B points of other instrumentation, where only the high or low end of the setting itave a direct bearing on safety, are established at a level away from the normal operating range to prevent inadvertent actuation of the systems involved.

Except for the MSIVs, the safety analysis does not address ir.dividual sensor I response times or the response times of the logic systems to which the sensors are connected. For D.C. operated valves, a 3 second delay is assumed before the valve starts to move. For A.C. operated valves, it is assumed that the i A.C. power supply is lost and is restored by startup of the emergency diesel generators.

In this event, a time of 13 seconds is asi,umed before the valve starts to move. In addition to the pipe break, the failure of the D.C. operated valve startep.is assumed; thus the r,ignal delay is concurrent with the 13 second diesel The safety analysis considers an allowable inventory loss in each case which in turn determines the valve speed in conjunction with the 13 second delay, it follows that checking the valve speeds and the 13 second time for emergency '

power establishment will. establish the response time for the isolation function .

However, to enhance overall system reliability and to monitor instrument channel response time trends, the isolation actuation instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.

3/4.3.3 EMERGENCY CORE _ COOLING JYSTEM ACTUATION INSTRUMENTATION The emergency core cooling system actuation instrumentation is provided to initiate the abilityactions of the to mitigatetothe operator consequences of accidents that are beyond control. This specification provides the OPERABILITY requirements, trip setpoints and response times that will ensure offectiveness of the systems to provide the design protection. Although the instruments are listed by system, in some cases the same instrument may be used to send the actuation signal to more than one system at the same time.

G LA SALLE - UNIT 1 B 3/4 3-2

TABLE 3.3.2-1 g ISOLATION ACTUATION INSTRUMENTATION C,

m VALVE GROUPS MINIMUM OPERABLE APPtICABtE OPERATED BY CHANNELS PER OPERATIONAL g TRIP FUNCTION SIGNAL (a) TRIP SYSTEM (b) CONDITION ACTION

[ A. AUTOMATIC INITIA1 ION

1. PRIMARY CONTAINMENT ISCLATION

a. Reactor Vessel Water Level (1) tow, Level 3 7 2 1,2,3 20 (2) Low Low, tevel 2 2, 3 2 1, 2, 3 20 (3) Low Low Low, Level 1 1, 10 2 1, 2, 3 20

b. Drywell Pressure - High 2, 7, 10 2 1, 2, 3 20

c. Main Steam Line y 1) Radiation - High 1 2 1,2,3 21 6

3 2 1,2,3 22 w

2) Pressure - Low

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3) flow - High 1

1 2

2/1ine Id) 1 1, 2, 3 23 21 Main Steam Line Tunnel d.

Temperature - High 1 2 l! 2[3 [. 21

• )' i

e. Main Steam Line Tunnel a Temperature - High 1 2 g (i)f r3(i) 21 1(i) ,2

f. Condenser Vacuum - Low 1 2 1, 2* , 3* 21 ~

2.

( )

SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Vent Exhaust Plenum Radiation - High 4(c)(e) 2 1, 2, 3 and ** 24 g b. Drywell Pressure - High 4(c)(e) 2 1, 2, 3 24

$ c. Reactor Vessel Water Level - tow tow, ievel 2 4(c)(e) 2 1, 2, 3, and 24 S 4. fuel Pool Vent Exhaust

r Radiation - High 4(c)(e)  ? 1, 2, 3, and ** 24

" ^

w

(i) Both channels of each triD 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 the ambient temperature channels in the 5. e trip systems are OPERABLE,

_ i Rept4cs wira INSERT A 8

I LA SALLE - UNIT 2 3/4 3-14(a) Amendment No, }4

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INSTRUMENTATION BASES I l

3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the OPERABILITY trip l setpoints and response times for isolation of the reactor systems. When necessary, one channel may be inoperable for brief intervals to conduct required surveillance.

lN6 EAT y Some of the trip settings may have tolerances explicitly stated where both the high B and low values are critical and may have a substantial effect on safety. The set-points of other instrumentation, where only the high or low end of the setting have a direct bearing on Fafety, are established at a level away from the normal operating range to prevent inadvertent actuation of the systems involved.

Except for the MSIVs, the safety analysis does not address individual sensor response times or the response times of the logic systems to which the sensors are connected. For D.C. operated valves, a 3 second delay is assumed before the valva starts to move. For A.C. operated valves, it is assumed that the A.C. power supply is lost and is restored by startup of the emergency diesel generators. In this event, a time of 13 seconds is assumed before the valve starts to move. In addition to the pipe break, the failure of the D.C. operated valve is assumed; thus the signal delay is concurrent with the 13 second diesel startup. The safety analysis considers an allowable inventory loss in each case which in turn determines the valve speed in conjunction with the 13 second delay.

It follows that checking the valve speeds and the 13 second time for emergency power establishment will establish the response time for the isolation functions.

However, to enhance overall system reliability and to monitor instrument channel response time trends, the isolation actuation instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME, 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The amergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents that are beyond the ability of the operator to control. This specification provides the OPERABILITY requirements, trip setpoints and response times that will ensure effectiveness of the systems to provide the design protection. Although the instruments are listed by system, in some cases the same instrument may be used to send the actuation signal to more than one system at the same time.

LA SALLE - UNIT 2 8 3/4 3-2

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

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' O-J l INSERT A

l. Both channels of each tria system may be placed in an inoperable status for i j up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for requirec reactor building ventilation system corrective -

maintenance, filter changes, damper cycling and surveillance tests, other j than Surveillance Requirement 4.6.5.1.c, without placing the trip. system in the tripped condition..

l J. Both channels of each tilp system may be placed in an inoperable status for u a to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for performance of Surveillance Requirement 4.6.5.1.c without p acing the trip system in the tripped condition.

l lNSERT B Both channels of each tria system for the main steam tunnel ambient temperature i and ventilation system dHerential temperature 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 system maintenance and -

testin and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for the required secondary containment Leak Rate test without plac the trip system in the tripped condition. This will allow for maintaining the reliabl ity of the ventilation system and secondary containment. -

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l ZNLD654/15 l

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