ML17285B025

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Proposed Tech Specs Re Accident Monitoring Instrumentation & Safety Relief Valves
ML17285B025
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 02/14/1990
From:
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17285B024 List:
References
NUDOCS 9002230438
Download: ML17285B025 (5)


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TABLE 3.3.7.5-1 ACCIDENT HONITORING INSTRUMENTATION RE(UIRED NUHBER OF CHANNELS 2/sector 2/valve" INSTRUMENT 1.

Reactor Vessel Pressure 2.

Reactor Vessel Water Level 3.

Suppression Chamber Water Level 4.

Suppression Chamber Water Temperature 5.

Suppression Chamber Air Temperature 6.

Drywell Pressure 7.

Drywell Air Temperature 8.

Drywell Oxygen Concentration 9.

Drywel l Hydr ogen Concentration 10.

Safety/Relief Valve Position Indicators 11.

Suppression Chamber Pressure 12.

Condensate Storage Tank Level 13.

Hain Steam Line Isolation Valve Leakage Control System Pressure MINIMUM CHANNELS OPERABLE 1/sector 1/valve APPLICABLE OPERATIONAL CONDITIONS 1,

2 1,

2 1,

2 1I 2 1,

2 1,

2 1,

2 1,

2 1

2 1

2 1

2 1

2 1

2 ACTION 80 80 80 80 80 80 80 80 80 80 80 80 80 0R 0

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  • NOTE - The acoustic monito6for HS-RV-Mmay be inoperable until the fbmCh Refueling Outage scheduled for No Later Than May 15, ~, or until the first forced outage of sufficient duration to effect repair/replacement prior to that date without applying the shutdown requirement of Action 80.a I'50

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INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION TABLE 4.3.7.5-1 ACCIDENT MONITORING INSTRUHENTATION SURVEILLANCE RE UIREHENTS APPLICABLE OPERATIONAL CONDITIONS n

I m

CD m

1.

Reactor Vessel Pressure 2.

Reactor Vessel Water Level 3.

4.

6.

a.

9.

Suppression Chamber Water Level Suppression Chamber Water Temperature Suppression Chamber Air Temperature Primary Containment Pressure Drywell Air Temperature Drywell Oxygen Concentration Drywell Hydrogen Concentration 10.

Safety/Relief Valve Position Indicators ll.

Suppression Chamber Pressure 12.

Condensate Storage Tank Level 13..

Hain Steam Line Isolation Valve Leakage Control System Pressure 14.

Neutron Flux:

APRH IRH SRH 15.

RCIC Flow 16.

HPCS Flow 17.

LPCS Flow H

H H

H H

H H

H H

H H

H H

H M

H R

R R

R R

R R

R' R

R R

R 1

2 1,

2 1,

2 1

2 1,

2 1,

2 1

2 1,

2 1,

2 1,

2 1

2

l. 2 1, 2-1, 2

1, 2

1 2

1, 2

1, 2

1 2

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."Surveillance of the OPERABLE Tailpipe Temperature instrument.channel5for SRY HS-RV-+ will be

~performed daily until the acoustic monitor for that valve is once again declared OPERABLE.

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CONTROLLED COPY REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY/RELIEF YALYES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of at least 12 of the following reactor coolant system safety/relief valves shall be OPERABLE with the specified code safety valve function liftsettings:"

2 safety/relief valves I 1150 psig +3%/-3X 4

safety/relief valves I 1175 psig +lX/-3X 4

safety/relief valves I 1185 psig +EX/-3X 4

safety/relief valves I 1195 psig +3%/-3X 4

safety/relief valves I 1205 psig +1K/-3X APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

Mith the safety valve tunction of one or more of the above required safety/relief valves inoperable, 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 />.

b.

Mith one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 90'F, close the stuck open safety/relief v'alve('s); if unable to close the open valve(s) within 2 minutes or if suppression pool average water tempera-ture is 110 F or greater, place the reactor mode switch in the Shut-down position.

c.

Mith one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days 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 />.+ + +

SURYEILLANCE RE UIREMENTS 4.4.2 The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE by performance of a:

a.

CHANNEL CHECK at least once per 31 days, and a

b.

CHANNEL CALIBRATION at least once per 18 months.""

"The lift setting pressure shall correspond to ambient conditions nf the valves at nominal operating temperatures and pressures.

""The provisions of Specification 4.0.4 are not applicable provided the survei.llance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

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