ML17291A756

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Proposed Tech Specs,Adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1
ML17291A756
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 04/25/1995
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17291A754 List:
References
NUDOCS 9505030443
Download: ML17291A756 (9)
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Text

Attachment 3 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES INDICATED 9505030443 950425 PDR ADOCK 05000397 j P PDR"

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TABLE 3. 3. 2-1 (Continued)

ISOLATION ACTUATION INSTRUHENTATION VALVE GROUPS HINIHUH APPLICABLE OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION ~PR I II CONDITION ACTION

3. REACTOR MATER CLEANUP SYSTEH ISOLATION
a. A ow - g 1 1, 2, 3 22
b. Heat Exchanger Area Temperature - High 7 1 1, 2, 3 22
c. Heat Exchanger Area Ventilation h Temp.-

High 7 1 1, 2, 3 22

d. Pump Area Temperature - High
1) Pump Room A 7 1 1, 2, 3 22
2) Pump Room 8 7 1 22
e. Pump Area Vent) lation h Temp. - High
1) Pump Room A 7 1 1, 2, 3 22
2) Pump Room B 7 1 1, 2, 3 22
f. SLCS Initiation 7(f) N.A. 1, 2, 3 22
g. Reactor Vessel Hater Level - Low Low, Level 2 7 2 1,2,3 22
h. RMCU/RCIC Line Routing Area Temperature - High 7 1 1, 2, 3 22 RWCU Line Routing Area Temperature - High Room 509 7 1 1, 2, 3 22 Room 511 7 1 22 Room 408 7 1 1, 2, 3 22 Room $ 09 7 1 1, 2, 3 22 Hanual initiation 7 1/group 1, 2, 3 24
k. Blase Joutn Flout " Mich 7 l /) 2i3 2'7

TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 20 Be in at least HOT SHUTDOWN within,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 next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21 Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 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 next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'.

ACTION 22 Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

ACTION 23 Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 24 Restore the manual initiation function 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 close the affected system isolation valves within the next hour and declare the affected system inoperable 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 25 Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 26 Lock close or close, as applicable, the affected system isolation AC71od27- i valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

Q(osa. Vde PNEUM-V-92 wi6in 4our or ps~Ar~ ACTlNf 22.

TABLE NOTATIONS "May be bypassed with reactor steam pressure < 1037 psig and all turbine stop valves closed.

""When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

PDuring CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

(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 /> for required surveillance without placing the trip system in the tripped con" dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b)Also actuates the standby gas treatment system.

(c)DELETED (d)A channel is OPERABLE if 2 of 4'etectors in that channel are OPERABLE.

containment ventilation isolation dampers per (e)Also actuates secondary Table 3.6.5.2-1.

(f)Closes only RWCU system outboard isolation valve RWCU-V-4.

(g)Only valves RHR-V-123A and RHR"V-123B in Valve Group 5 are required for primary isolation.

(h)Manual initiation isolates RCIC-V-8 only and only with a coincident reactor vessel level-low, level 3.

(i)Not required for RHR-V-8 when control is transferred to the alternate remote shutdown panel during operational conditions 1, 2 8 3 and the isolation interlocks are bypassed. When RHR-V-8 control is transferred to the remote shutdown panel under operational modes 1, 2, and 3 the associated key lock switch will be locked with the valve in the -closed position. Except RHR"V-8 can be returned to, and operated from, the control room, with the interlocks and automatic isolation capability reestablished in operational conditions 2 and 3 when reactor pressure is less than 135 psig.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-15 Amendment No. SH, N, ii2

o) 4

't

TABLE 3.3.2-2 (Continued)

ISOLATIOtt ACTUATION IHSTRUHENTATION SETPOINTS ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE

3. REACTOR WATER CLEANUP SYSTEH ISOLATIOtl
a. A Flow - lligh < 58.5 gpm < 65.5 gpm
b. lleat Exchanger Area Temperature - Iligh < 150'F < 160 F Heat Exchanger Area Ventilation h Temp. - Iligh < 60'F <70F Pump Area Temperature - Iligh Pump Room A <160F <180F Pump Room B 160oF < 180 F Pump Area Ventilation A Temp.

lligh Pump Room A <70F < 100F Pump Room 8 <70F < 100 F SLCS Initiation tl.A. tl.A.

Reactor Vessel Mater Level-Low Low, Level 2 > -50 inches* > -57 inches

h. RWCU/RCIC Line Routing Area Temperature - lligh < 160 F < 180'F RWCU Line Rout.ing Area Temperature - lligh Room 409 < 160F < 175'F Room 511 < 160oF < 180 F Room 408 < 160 F < 180 F Room 409 160oF < 175'F
j. Hanual Initiation H.A.

4 264.5gp~

N. A.

K. Bfou)doe)u Clot@-Aiph 4 2'. 7 gp~

4. REACTOR CORE ISOLATION COOLING SYSTEH ISOLATIOH
a. RCIC Steam Line Flow - High < 290K of rated flow < 300K of rated flow
b. RIIR/RCIC Steam Line Flow - Iligh < 101.5 inches ll20 < 107.5 inches II20 C. RCIC Steam Supply Pressure Low > 62 psig > 58 psig
d. RCIC Turbine Exhaust Diaphragm Pressure - Iligh < 10.0 psig < 20.0 psig RCIC Equipment Room Temperature - Iligh 60oF < 180 F

TABLE 4.3.2.1-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR NICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE UIRED

3. REACTOR MATER CLEANUP SYSTEN ISOLATION
a. 4 Flow'- High S Q 1, 2, 3
b. Heat Exchanger Area .

Temperature - High N.A. SA 20

c. Heat Exchanger Area Ventilation h Temperature-High N.A SA 2 3
d. Pump Area Temperature - High Pump Room A N.A SA 1~ 2j Pump Room 8 N.A. SA 1, 2,
e. Pump Area Ventilation h Temp. " High Pump Room A N.A. SA R 1,2,3 Pump Room 8 . N.A. SA R
f. SLCS Initiation N.A. R. N.A.
g. Reactor Vessel Water Level-- Low Low, Level 2 N.A. 2 3
h. fNCU/RCIC Line Routing Area Temperature - High N.A. SA R 1, 2, 3

.i INCU Line Routing Area Temperature - High N.A. SA R 1, 2, 3 j.. Manual Initiation N.A. R N.A.

K.. 'H[C ~doWRL HO~ High 13ZT 3

4. REACTOR CORE ISOLATIOA COOLING SYSTEM ISOLATION aO RCIC'Steam Line Flow - High S 1, 2, 3
b. RCIC/RHR Steam Line Flow - High S Co RCIC Steam Supply Pressure-Low- N.A. 1, 2, 3
d. RCIC Turbine Exhaust Diaphragm Pressule - High N.A. =-

1, 2,

e. RCIC Equipment Room Temperature - High N.A. 1, 2, 3 RCIC Equipment Room h Temperature - High N.A. SA

4

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