ML17285A160

Proposed Tech Spec Tables 3.3.3-1,3.3.3-2 & 4.3.3.1-1 Re ECCS Actuation Instrumentation,Clarifying Testing Requirements & Capabilities of Divs 1,2 & 3 Loss of Power Trip Functions,Per Approved Design

ML17285A160
Person / Time
Site:	Columbia
Issue date:	12/21/1988
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17285A158	List: ML17285A156 ML17285A160
References
TAC-71445, NUDOCS 8901090108
Download: ML17285A160 (5)

Text

TABLE 3. 3. 3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATIOH INSTRUh1ENTATIOH M

IIINIMUM OPERABLE APPLICABLE Cb jwt7%

om CtIANNELS PER OPERATIONAL TRIP FUNCTION TNIP SYST~SN a zo CONDITIONS ACTION Cl C. DIVISION 3 TRIP SYSTEM w'4 Uo 1. HPCS SYSTEM Os no xm I

Reactor Vessel Water Level - Low, Low, Level

a. 2 2(b) 1, 2, 3, 4", 5~ 30 om M b. Drywell Pressure - High 2(b) 1, 2, 3 30 vlm C. Reactor Vessel Water Level-lligh, Level 8 2(c) 1, 2, 3, 4*, 5* 32 ow d. .Condensate Storage Tanks Level-Low oh) 2(d)

('uoso e. Suppression Pool Water Level-tligh 2(d)

,ne f. HPCS System Flow Rate-Low (Minimum F'low) 1 1, 2, 3, 4*, 5*

g. Manual Initiation 1/division l1IHIMUM APPLICABLE TOTAL HO. CHANNELS CIIANHELS OPERATIONAL OF CHANNELS TO TRIP OPERABLE CONDITIONS ACTION

0. LOSS OF POWER

l. 4. 16 kV Emergency Bus Under-voltage (Loss of Voltage) 2/bus 1/bus -2/bus 1, 2, 3, 4"", 5"* 37

2. 4.16 kV Emergency Bus Under-,><os>~< ~)

voltage (Degeaded Voltag+SS'/bus 2/bus 2/bus 1, 2, 3, 4*", 5+~ 38 svtegr~c)

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Ls tlWtsolga ~lb~s'- 2/Ideas lk z 3. 85

(~l g Ih Pgv'atm g TABLE NOTATIONS channel 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) A Ila surveillance without placing the trip system in the tripped condition provided at least one CL B other OPERABLE channel in the same trip system is monitoring that parameter.

D t+ (b) Also activates the associated division diesel generator.

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

(d) Provides signal to IIPCS 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.

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TABLE 3.3.3-2 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATIOH INSTRUMEHTATIOH SETPOINTS M

ALLOWABLE C) TRIP FUNCTION TRIP SETPOIHT VALUE C. DIVISION 3 TRIP SYSTEM I

foal

1. HPCS SYSTEM

a. Reactor Vessel Water Level Low Low, Level 2 '> -50 inches* > -57 inches

b. Drywell Pressure - High < 1.65 psig < 1.85 psig

c. Reactor Vessel Water Level - fligh, Level 8 < 54. 5 inches* < 56.0 inches

d. Condensate Storage Tank Level - Low >448 ft3 in > 448 ft 0 in. elevation elevation

e. Suppression Pool Water Level - High < 466 ft 8 in. < 466 ft 10 in. elevation elevation

f. HPCS System Flow Rate - Low (Minimum Flow) > 1250 gpm > 1200 gpm

g. Manual Intiation N.A. N.A.

D. LOSS OF POWER P

1. 4. 16 kV Emergency Bus Undervoltage a0 4. 16 kV Basis-- 2870 t 86 volts 2870 2 172 volts I Loss of Voltage H 120 V Basis - 82 t 2.5 volts 82 k 5 volts IVl CS

a. Divisions 1 and 2 ao 4.16 kV Basis - 3016 k 90 volts 3016 2 180 volts

b. Division 3 b. 120 V Basis - 87 2 2.5 volts 87 t 5 volts

2. 4.16 kV Emergency Bus Undervoltage a. 4. 16 kV Basis - 3632 2 108 volts 3632. k 216 volts Degraded Voltage (Divisions 1, 2, b. 120 V Basis - 104.0 t 3.0 volts 103.8 k 6.0 volts and 3 C. 8 2 ~K sec time delay 8 k.0.8 sec time delay o.4-TABLE NOTATIONS O

• See Bases figure B 3/4 3-1.

HThese 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.

TABLE 4.3.3. 1-1 (Continued)

EA EHERGENCY CORE COOLING SYSTEH ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREHENTS Cl CIIANNEL OPERATIONAL C) CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION . CHECK TEST CALIBRATION SURVEILLANCE RE UI RED C

m C. DIVISION 3 TRIP SYSTEH

l. HPCS SYSTEM M a. Reactor Vessel Mater Level-Low Low, Level 2 S 1, 2, 3, 4", 5"

b. Drywell Pressure-High N.A. 1 2.3

c. Reactor Vessel Mater Level-High, Level 8- 1, 2, 3, 4*, 5*

d. Condensate Storage Tank Level-Low N.A. 1, 2, 3, 4", 5"

e. Suppression Pool Water Level - High N.A. 1, 2, 3, 4", 5"

f. HPCS System Flow Rate-Low (Hinimum Flow) N.A. R 1, 2, 3, 4*, 5*

g. Hanual Initiation N.A. 'R N.A.

D. LOSS OF POWER

l. 4.16 kV Emergency Bus Undervoltage 4*%'**

(Loss of Voltage) N.A. N.A. R 3

2. 4. l6 kV Emergency Bus Undervoltage (gegeaded Voltaggg 'D',;ere~ 9.e lP) H.A .

H" R

' 4'Agc 5A "f.lb k'V Edacrgr~cg >< IlIucIertiolgZ~ ~ Qr A- ~ I 2.~ 3+

TABLE NOTATIONS 8Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.

O "When the system is required to be OPERABLE per Specification 3.5.2.

""Required when ESF equipment is required to be OPERABLE.

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