ML20065R721

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Proposed Tech Specs Reactor Trip Sys Instrumentation Surveillance Requirements
ML20065R721
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/06/1994
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20065R720 List:
References
NUDOCS 9405130144
Download: ML20065R721 (10)
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Docket No. 50-423 l B14823 Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Trip System Instrumentation Surveillance Requirement Marked-Up Pages of Technical Specifications May 1994 9405130144 940506 l PDR ADOCK 05000423 i P PDR

-=1-2/22/4 ..

.c TABLE 3.3-1 (Continued) ,-

jf, ou y REACTOR TRIP SYSTEM INSTRUMENTATION so~.

MINIMUM c TOTAL NO. CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE H0 DES - ACTION h FUNCTIONAL UNIT

17. Reactor Trip System Interlocks (Continued)
c. Power Range Neutron Flux, P-8 4 2 3 1 8
d. Power Range Neutron 4 2 3 I 8 Flux, P-9
e. Power Range Neutron Flux, P-10 4 2 3 1,2 8 -
18. Reactor Trip Breakers 2 1 2 1, 2 10, 13 2 1 2 3*, 4*, 5* 11 ,
19. Automatic Trip and Interlock 2 1 2 1, 2 13A 2 2 3*, 4*, 5* 11 Logic 1 8 8 1, 2 1 b
20. Three Loop Operation 2 .

Bypass Circuitry (1 switch per (From differ-

[ loop in each ent loop g switches in g train) a bypass) 0 2 39, 4, 5 5 f 21. Shutdown Margin Monitor 2

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TABLE 3.3-1 (Continued)

TABLE NOTATIONS

  • When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.
    • Above the P-7 (At Power) Setpoint.
    1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
      1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) 5etpoint. >

0 The Shutdown Margin monitor may be blocked during reactor startup in /

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accordance with approved procedure.

(1) The applicable MODES and ACTION statements for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

(MLah 3 mm ruuh.y 4Q byp<4u b.<, dens Nk,n%-vcuked way Mp m W d*M ACTION STATEMENTS %v by p.

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ACTION 1 - 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 be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 - With the number of bPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and
c. Either, THERMAL POWER is restricted to less than or equal to 757. of RATED THERMAL POWER for four loop operation or 507. of RATED THERMAL POWER for three loop operation and the Power Range Neutron Flux Trip Setpoint is raduced to less than or equal to 85Y. of RATED THERMAL POWER for four loop operation or 607. of RATED THERMAL POWER for three loop operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

MILLSTONE - UNIT 3 3/4 3-5 Amendment No. E7 60.

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-- .' a .

TABLE 4.3-1 (Continued) 33 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTE OF

$ TRIP e ANALOG tCTUATING MODES FOR R CHANNEL DEVICE WHICH CHANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCI g FUNCTIONAL UNIT CHECK CALIBRATION TEST JEST LOGIC TEST IS RE0UIRED

[ 18. Reactor Trip Breaker N.A. N.A. N.A. M(7. 11) N.A. 1, 2, 3* ,

4*, 5*

19. Automatic Trip and N.A. N.A. N.A. N.A. M(7) 1, 2, 3*,

Interlock Logic .

4*, 5*

20. Three Loop Operation N.A. N.A. N . /. . R(20) N.A. 1, 2 Bypass Circuitry )

w 21. Reactor Trip Bypass N.A. N.A. N.A. M( 5) N.A. 1, 2, 3* ,

1 5*

Breake f :1(16) 4*,

22. Shutdown Margin Monitor N.A. N.A Q(19) 1.A. N.A. 3,4,5 N

a 2

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April 9, 1987

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INSTRUMENTATION BASES REACTOR TRIP SYSTEM INSTRUMENTATION and ENGINEERED SAFETY FEATURES ACTUA SYSTEM INST M ENTATION (Continued)

The Engineered Safety Features Acutation System senses selected plant parameters anc determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents, events, and transients. Once the required logic ccmcination is completed, the system sends actuation signals to those Engineered Safety Features, components whose aggregate function oest serves the receirements of the condition. As an example, the following actions may be ir.itiated by the Engineered Safety Features Actuation System to mitigate tne consequences of a steam line break or loss-of-coolant accident: (1) Safety Injection pumps start and automatic valves position, (2) Reactor trip, (3) feed-water isolation, (4) startup of the emergency diesel generators. (5) quench spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start, (10) sarvice water pumps start and automatic valves position, and (11) Control noom i,solates.

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MILLSTONE - UNIT 3 8 3/4 3-2a 'Amenament No. 3

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l Docket No. 50-423

.B14823 Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Trip System Instrumentation Surveillance Requirement Retyped Pages of Technical Specifications May 1994

og TABLE 3.3-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATI0ff M MINIMUM

, TOTAL NO. CHANNELS CHANNELS APPLICABLE c FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTIm 5

17. Reactor Trip System Interlocks (Continued)

]

c. Power Range Neutron Flux, P-8 4 2 3 1 8
d. Power Ranga Neutron 4 2 3 1 8 Flux, P-9
e. Power Range Neutron Flux, P-10 4 2 3 1,2 8 R.

to 18. Reactor Trip Breakers (2) 2 1 2 1, 2 10, 13 A 2 1 2 3* , 4*, 5* 11

19. Automatic Trip and Interlock 2 1 2 1, 2 12?

Logic 2 1 2 3*, 4*, 5* 11

20. Three Loop Operation 8 2 1, 2 1

_g Bypass Circuitry (1 switch per (From differ-g loop in each ent loop g train) switches ira g bypass) e g 21. Shutdown Margin Monitor 2 0 2 30, 4, 5 5 4

4

TABLE 3.3-1 (Continuedl TABLE NOTATIONS

  • When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.
    • Above the P-7 (At Power) Setpoint.
    1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
      1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

O The Shutdown Margin monitor may be blocked during reactor startup in accordance with approved procedure.

(1) The applicable MODES and ACTION statements for these channels noted in -

Table 3.3-3 are more restrictive a..J, therefore, applicable.

(2) Including any reactor trip bypass breakers that are racked in and closed for bypassing a reactor trip breaker.

ACTION STATEMENTS ACTION 1 - 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 be in H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed

. *vided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, i
b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and
c. Either, THERMAL POWER is restricted to less than or equal 1 to 75% of RATED THERMAL POWER for four loop operation or i 50% of RATED THERMAL F0WER for three loop operation and .

the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85 % of RATED THERMAL POWER for four loop operation ar 60% of RATED THERMAL POWER for three loop operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

MILLSTONE - UNIT 3 3/4 3-5 Amendment No. # , JP 0219

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TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5 TRIP i ANALOG ACTUATING MODES FOR

c. CHANNEL DEVICE WHICH z CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE Q FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
18. Reactor Trip Breaker N.A. N.A. N.A. M(7, 11) N.A.

g,2,3*,

19. Automatic Trip and N.A. N.A. N.A. N.A. M(7) 1 2 Interlock Logic 44 , $*3*,
20. Three Loop Operation N.A. N.A. N.A. R(20) N.A. 1, 2 Bypass Circuitry
21. Reactor Trip Bypass N.A. N.A. N.A. M(7 N.A. 1, 2 Breaker R(IE)15) 4*,$*3*,

m 22. Shutdown Margin Monitor N.A. N.A Q(19) N.A. N.A. 3,4,5 i

Y M

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INSTRUMENTATION BASES REAC. TOR TRIP SYSTEM jnSTRUMENTATION and ENGINEERED SAFETY FEATURES ACTUATION l SYSTEM INSTRUMENTATIDH (Continued) l l

The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermincd limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents, events, and transients. Once the required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety features Actuation System to mitigate the consequences of a steam line break or loss-of-coolant accident: (1) Safety injection pumps start and automatic valves position, (2) Reactor trip, (3) feed-water isolation, (4) startup of the emergency diesel generators, (5) quench spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start, (10) service water pumps start and automatic valves position, and (11) Control Room isolates.

REACTOR TRIP BREAKERS This trip function applies to the reactor trip breakers (RTBs) exclusive of individual trip mechanisms. The LCO requires two operable trains of trip '

breakers. A trip breaker train consists of all trip breakers associated with a single RT3 logic train that are racked in, closed, and capable of supplying power to the control rod drive (CRD) system. Thus, the train may consist of the main breaker, bypass breaker, or main breaker and bypass breaker, depending upon the system configuration. Two OPERABLE trains ensure no single random failure can disable the RTS trip capability.

These trip functions must be OPERABLE in MODE 1 or 2 when the reactor is critical. In H0DE 3, 4, or 5, these RTS trip functions must be OPERABLE when the RTBs or associated bypass breakers are closed, and the CR0 system is capable of rod withdrawal.

i MILLSTONE - UNIT 3 B 3/4 3-2a Amendment No. 7, i 0221

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