ML18092B381

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Proposed Tech Specs,Revising Action Statements for Reactor Trip Breakers & Automatic Trip Logic During Modes 3,4 & 5 & Limiting Conditions for Operation During Modes 1 & 2
ML18092B381
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/18/1986
From:
Public Service Enterprise Group
To:
Shared Package
ML18092B380 List:
References
NUDOCS 8612240265
Download: ML18092B381 (6)


Text

REVISED PAGES -

UNIT NO. 1

Cf.I

~

t<J

~

I c::

TABLE 3~3-1 {CONTINUED}

z H

~

t-'

~EACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MOOCS ACTION

18.

Turbine Trip

a.

Low Autostop Oil Pressure 3

2 2

1

~-

b.

Turbine Stop Valve Closure 4

4 4

1

19.

Safety Injection Input from SSPS 2

1 2

1,2 1.

l..U -

~

l..U

20.

Reactor Cool ant Pump Breaker I

Position Trip

~

a.

Above P-8 1/breaker 1

1/breaker 1

10

b.

Above P-7 1/breaker 2

1/breaker 1

11 per oper-ating loop

21.

Reactor Trip Breakers 2

1 2

1,2 1#~4 3*,4*,5*

13

22.

Automatic Trip Logic 2

1 2

1,2 1

3*,4*,5*

13

TABLE 3.3-1 (CONTINUED)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in Hor STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel associated with an operating lodp may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testirg per Specification 4.3.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL ~R to below P-8 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Ope~ation below P-8 may-continue pursuant to ACTION 11.

ACTION 11 - With less than the Miriirm..rrn Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in Hor STANIEY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

ACTION 13 - With the number of OPERABIE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to

  • OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next nour.

ACTION 14 - With one of the.diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least Hor STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the tiine required for perfo:rmirg maintenance to restore the breaker to OPERABLE status.

DESIGNATION P-6 P-7 SALEM - UNIT 1 REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT With 2 of 2 Intermediate Rarge Neutron Flux Channels < 6 x lo-11 amps.

With 2 of 4 Power Range Neutron Flux Channels > 11% of RATED THERMAL PCmER or 1 of 2 Turbine impulse chamber pressure channels

> a pressure equivalent to 11% of RATED THE'AL IOWER.

3/4 3-7 FUNCTION P~6 prevents or defeats the manual block of source rarge reactor trip.

P-7 prevents or defeats the autanatic block of reactor trip on:

  • Low flow in more than one primary coolant loop, reactor coolant pump under-voltage and under-frequency,. turbine trip, pressurizer low pressure, and pressurizer high level.

REVISED PAGES -

UNIT NO. 2

tll t"""'

t:tJ I

c::: z TABLE 3

  • 3 -1 ( C 0 NT IN UE D)

H 1-'3 N

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMLM TOTAL NO.

CHANNELS CHANNELS APPLICABLE F UNCT IONA L UN IT OF CHANNELS TO TRIP OPERAB.LE MODES ACTION

18.

Turbine Trip

a.

Low Autos top Oil Pressure 3

2*

2 1

~-*

b.

Turbine Stop Valve Closure 4

4 4

1

19.

Safety Injection Input f roin SSPS 2

1 2

1,2 1

w

20.

Reactor Coolant Pump Breaker

-P-Position Trip w

I

-P-Above*P-8 1/breaker 1

1/breaker 1

10

a.
b.

Above.P-7 1/breaker 2

1/breaker 1

11 per oper-ating loop

21.

Reactor Trip Breakers 2

1 2

1,2 1#'94 3*,4*,5*

13

22.

Automatic Trip Logic 2

1 2

1,2 1

3*,4*,5*

13

r*-

I TABLE 3.3-1 (CONTINUED)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOI' STI\\NDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testirYJ per Specification 4.3.1.1.

ACTION 10 - With one channel inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Operation below P-8 may continue pursuant to ACTION 11.

ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may

. continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 12 - With the number of channels OPERABLE one less than reqt.iired by the Minimum Channels OPERABIE requirerrent, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in Hor STANOOY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.

ACTION 13 - With the number of OPERABLE channels one less than the.Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.

ACTION 14 - With one of the diverse trip features (Undervoltage or shunt trip attachme.nt) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and be in at least Hor STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for perfonnirYJ maintenance to restore the breaker to OPERABLE status.

DESIGNATION P-6 P-7 SALEM - UNIT 2 REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT With 2 of 2 Intennediate Range Neutron Flux Channels < 6 x lo-11 amps.

With 2 of 4 Power Range Neutron Flux Channels > 11% of RATED THERMAL POWER or 1 of 2 Turbine

  • impulse chamber pressure channels

> a pressure equivalent to 11% of RATED THERMAL :EemER.

3/4 3-7 FUNCTION P-6 prevents or def eats the manual block of source range reactor trip.

P-7 prevents or defeats the autanatic block of reactor trip on:

I.ow flow in more than one prirna:ry coolant loop, reactor coolant pump under-voltage and under-frequency, turbine trip, pressurizer low pressure, arrl pressurizer high level.