ML17289A841

Proposed TS Table 3.3.3-1 Re ECCS Actuation Instrumentation & Table 3.3.3-2 Re ECCS Actuation Instrumentation Setpoints

ML17289A841
Person / Time
Site:	Columbia
Issue date:	09/02/1992
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17289A840	List: ML17289A839 ML17289A841
References
NUDOCS 9209140202
Download: ML17289A841 (12)

Text

The following pages will be affected by this Technical Specification amendment.

INSERT REMOVE 3/4 3-28 3/4 3-28 3/4 3-29 3/4 3-29 3/4 3-29a 3/4 3-32 3/4 3-32 B 3/4 3-2a 9209140202 920902 PDR ADOCK 05000397 P PDR

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATIOH INSTRUMENTATION MINIMUM OPERABLE APPLICABLE CHANNELS PER OPERATIONAL TRIP FUNCTION TRIP SYSTEM a CONDITIONS ACTION C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM a% Reactor Vessel Water Level - Low, Low, Level 2 2(b) 1 2 3 4'A 5* 30

b. Drywell Pressure - High 2(b) 30 C. Reactor Vessel Water Level-High, Level 8 2(c) 1) 2, 3, 4* 5* 32

d. Condensate Storage Tanks Level-Low 2(d) 1) 2) 3 4))) 5))) 36

e. Suppression Pool Water Level-High 2(d) 4A 5A

f. HPCS System Flow Rate-Low (Minimum Flow) 1 4))l 5A

g. Manual Initiation 1/di visi on 1 2 3 4* 5*

MINIM APPL ABLE i TOTAL HO. CHANNELS CHAN LS OPERAT HAL D. LOSS OF POWER OF CHANNELS TO TRIP OPER BL w) CONDI ONS 0

1. 4.16 kV Emergency Bus Under-iA voltage (Loss of Voltage) 2/bus 1/bus 2/bus 1, 2, 3, 4**, 5"* 37

2. 4.16 kV Emergency Bus Under-voltage (Degraded Voltage Division 3/bus 2/bus J~us 3 4** 5*4 38~3) 4 1 and 2)

3. 4.16 kV Emergenc Bus Undervolta g e (Degraded Voltage Division 3) 2/bus 2/bus TABLE NOTATIONS

~bus 1, 2, 3, 4"*, 5*" ~, egz.

(a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> during periods of required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also activates 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.

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.

Hot required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.

I

%NTH01.LED. GQPP TABLE 3.3.3-1 (Can inued)

"~ERGEHCY CORE COOL HG SYSTBl ACTUATIOH EHSTRUMEHTAT:OH ACTTOH STATBIEHTS ACT.OH 30 the numoer of QPERASLE channels less 'han required by -he Minimum GPERASL Channels per Trip System requiroment:

a. For one tr p system, place the inaperable channel(s) and/or that rip system in the tripped candi cn within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />" or declare the assaciatad system inoperable.

b. For both trip systems, declare the associated sys-am inoaerable.

ACTIGH 31 " With the number of OPERABLE channels less than required by:ne Minimum OPERABLE Channels per Trip Sys am requir ment, olace the inoperable channel in the tripoed condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the inoperable channel to OPERABLE s atus '<<1 lin 7 days or declare the asscciated system inoperable.

ACT.OH 32 With the number of OPERABLE channels less than requir d by :he Minimum OPERABL" Channels per Trip System requirement, declare the associated system incoerable.

AC 70V ~3 " With the number of OPERABLE channels less han required "y he Minimum QPERASLE Channels per Trip System requir ment, plac the inoperable channel in :he ripped condi:ion within

'our.

ACT~CH 34- With the number af GPERASL= channels less than roquired by he Minimum OPERABLF Chanrel s per Trip System requirement r estare the inoperaole channel to OPERABLE status <<ithin B hours or declare .he asscciated ECCS inoperable.

ACTTGH 35 With the number of OPERABLE channels less than required by tne Minimum GPERASLE Channels per Trip System requirement, restore the inoperable channe1 to OPERABLE s atus within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or decl'are the asscciatad DOS division inoperable.

ACT7GH 36 With the number of OPERABLE channels less than required by the Minimum OPERASLE Channels per Trip Sys am requirement, olace the inoperable channel in the tripped condition <<i-hin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />" or declare .he HPCS sys em inoperable.

ACTTCN 37 " With the numoer af OPERABLE channels less than ne Total Number of Channels, declare the 'associated emergency diesel generator inooerable and take he ACT:OH required by Spec;f'cat an 3.S. 1.'r 3.8. 1.2, as aoorapriata. HOW

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ACTION 38 With the number of OPERABLE channels one less than the 'TOTAL NO. OF CHANNELS', remove the inoperable channel from the trip system within 1 hour*.

ACTION 39 With the number of OPERABLE channels two less than the 'TOTAL NO. OF CHANNELS', within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> remove one of the inoperable channels from the trip system and place the remaining channel in the tripped condition*.

ACTION 40 With the number of OPERABLE channels less than the 'MINIMUM CHANNELS OPERABLE', restore at least one channel t'o an OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 />.

ACTION 41 With the number of OPERABLE channels one less than the 'Total NO. OF CHANNELS', within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> place the inoperable channel in the tripped condition*.

ACTION 42 With the number of OPERABLE channels less than the 'MINIMUM CHANNELS OPERABLE', restore at least one channel to an OPERABLE status within 24 hours or declare the HPCS system inoperable.

The provisions of Specification 3.0.4 are not applicable.

TABI.F. 3.3.3-2 (Continued)

EHEROENCY CORE COOLINO SYSTEH ACTUATION INSTRI)HENTATION SETPOlt)TS ALLOWABLE C)

TRIP FUt{CTION TRIP Sl:TPOI tlT VALI)E n

I C. DIVISION 3 TRIP SYSTEH foal

1. IIPCS SYSTEH

a. Reactor Vessel Water Level - Low Low, l.evel 2 > "50 incl>es" > -57 inches

b. Drywell Pressure " Iligh < 1.65 psig < 1.85 psig 0R

c. Reactor Vessel Water Level - lligh, Level 8 < 54.5 inclies" < 56.0 inches

d. Condensate Storage Tank Level - l.ow > 448 ft 3 in. > 448 ft 0 in. elevatinn elevation

e. Suppression Pool Water Level - lligh < 466 ft 8 in. < 466 ft 10 sn. elevat>on elevation G i' f. IIPCS System Flow Rate Low (Hinimum Flow) > 1250 gpm > 1200 gpm I ial

g. Hanual Intiation R.A. R.A. I D. lOSS OF POWER U

l. 4-.16 kV Emergency Bus Undervoltage a.

4. 16 kV Basis - 2870 i 86 volts 2870 2 172 volts A Loss of Voltage NP 120 V Bas Is - 82 a 2. 5 vol ts 82 a 5 volts a.

b. -

Divisions 1 Division 3 and 2 4.16 120 V kV Basis - 3016 Basis - 87 i i 90 volts 2.5 volts 3016 87 t f 180 volts 5 volts

2. 4. 16 kV Emergency Bus Undervoltage k 8 i

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~ CONTROLLED COPYO INSTRUMENTATION BASES 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 setpoints and response times for isolation of the reactor systems. Mhen neces-sary, 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 and low values are critical and may have a substantial effect on safety. The setpoints of other instrumentation, where only the high or low end of the setting have 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 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 valve 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 O.C.-operated valve is assumed; thus the signal delay (sensor response) 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 conjunc-tion 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 isola" tion actuation instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION The emergency 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.

Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.

z AlsE'/2%

WASHINGTON NUCLEAR - UNIT 2

Insert to Bases paragraph 3/4.3.3 - New Page B 3/4 3-2a EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION Three degraded undervoltage relays are provided on the division 1 and 2 safety related buses to assure adequate voltage on these buses to support the ECCS loads. Actuation of two relays will result in tripping of the offsite source circuit breakers 7-1 or 8-3 as applicable. Three channels are provided to allow testing of a channel during operation at power. Two relay contacts within each trip system train are provided to minimize spurious trips of the offsite source to that division.

Two degraded undervoltage relays are provided on the division 3 safety related bus to assure adequate voltage on the bus to support HPCS loads. Actuation of both relays will result in tripping of circuit breaker 4-1.