Text

Technical Specification Pages Amendment 37 to Licenses DPR-58 & DPR-74
	ML031480135
Person / Time
Site:	Cook
Issue date:	05/23/2003
From:	; NRC/NRR/DLPM
To:	;
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	Download: ML031480135 (22)
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1.0 DEFINITIONS I

TABLE 1.2 FREOUENCY NOTATION FREOUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

At least once per 62 days At least once per 184 days.

At least once per 549 days.

Prior to each reactor startup.

Completed prior to each release.

Not Applicable.

COOK NUCLEAR PLANT-UNIT 1 NOTATION S

D w

M Q

2 Months SA R

S/U p

N.A.

AMENDMENT X7-,277 I

Page 1-9

0o TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION CZ

16.

Undervoltage-Reactor Coolant 4-1/bus 2

3 1

6#

Pumps

17.

Underfrequency-Reactor 4-1/bus 2

3 1

6#

Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil 3

2 2

1 7

Pressure B.

Turbine Stop Valve 4

4 4

1 7#

Closure

19.

Safety Injection Input from 2

1 2

1, 2 1

ESF

20.

Reactor Coolant Pump Breaker Position Trip Above P-7 I/breaker 2

1/breaker per 1

11 operating loop

21.

ReactorTrip Breakers 2

1 2

1,2 13,15 3 *,4,5' 14 z

22.

Automatic Trip Logic 2

1 2

1, 2 1

3 3

,4-,5*

14

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 (Continued)

ACTION 8 -

(Deleted.)

ACTION 9 -

ACTION 10-ACTION 11-ACTION 12-ACTION 13-ACTION 14-ACTION 15-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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 1. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

With the number of OPERABLE Reactor Trip Breaker channels one less than required by the Minimum Channels OPERABLE requirement for reasons other than an inoperable diverse trip feature, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1.1, provided the other channel is OPERABLE.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION P-6 CONDITION AND SETPOINT With 2 of 2 Intermediate Range Neutron Flux Channels less than 6x10-" amps.

FUNCTION P-6 prevents or defeats the manual block of source range reactor trip.

COOK NUCLEAR PLANT-UNIT 1 (Deleted.)

(Deleted.)

I AMENDMENT, 42,44,277 Page 3/4 3-8

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

1.

Manual Reactor Trip CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST MODE IN WHICH SURVEILLANCE REQUIRED A. Shunt Trip Function B. Undervoltage Trip Function

2.

Power Range, Neutron Flux S

3.

Power Range, Neutron Flux, High Positive Rate

4.

Power Range, Neutron Flux, High Negative Rate

5.

Intermediate Range, Neutron Flux N.A.

NA.

S D(2,8), M(3,8),

and Q(6,8)

R(6)

R(6,8)

Q and SfU(l)

Q Q

S/U(17)

6.

Source Range, Neutron Flux

7.

Overtemperature delta T

8.

Overpower delta T S

R(6,14)

S S

9.

Pressurizer Pressure - Low S

10. Pressurizer Pressure-High S

11. Pressurizer Water Level -

High

12. Loss of Flow-Single Loop S

R(9)

R R

R S

R(8)

M(14) and S/U(1) 2(7), 3(7), 4 and 5 SA SA SA SA SA SA 1,2 1,2 1,2 1,2 1,2 1

AMENDMENT 99,420,421,444,277 N.A.

N.A:

N.A.

S/IU(l)(10)

SIU(I)(10) 1,2,3-,4-,5-1, 2,3, 4', 5' 1, 2 and 1,2 1,2 1, 2, and I

COOK NUCLEAR PLANT-UNIT 1 Page 34 3-12

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

13. Loss of Flow-Two Loops

14. Steam Generator Water Level -- Low-Low

15. Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level

16. Undervoltage-Reactor Coolant Pumps

17. Underfrequency-Reactor Coolant Pumps

18. Turbine Trip A. Low Fluid Oil Pressure B. Turbine Stop Valve Closure

19. Safety Injection Input from ESF

20. Reactor Coolant Pump Breaker Position Trip

21. Reactor Trip Breaker CHANNEL CHANNEL CHECK CALIBRATION S

R(8)

S R

S, R

N.A.

R R

N.A.

CHANNEL FUNCTIONAL TEST N.A.

SA SA M

M S/U(I)

S/U(I)

Q (4)(15)

R MODE IN WHICH SURVEILLANCE REOUIRED I

1,2 1,2 I

I 1,2 1,2 1,2 N.A.

A. Shunt Trip Function B. Undervoltage Trip Function

22. Automatic Trip Logic

23. Reactor Trip Bypass Breaker N.A.

N.A.

N.A N.A.

N.A.

2 Months (5)(1 1) and S/U(l)(ll) 2 Months (5)(1 1) and S/U(l)(1 1)

Q(15) 2 Months (5)(12) and S/U(1)(13) 1, 2, 3, 4* 5*

1, 2, 3* 4* 5*

1, 2, 3, 4* 5*

1, 2, 3*, 4*, 5*

COOK NUCLEAR PLANT-UNIT I I

I I

Page 34 3-13 AMENDMENT 99,42, 441, 277

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREIENTS 314.3 INSTRUMENTATION TABLE 4.3-1 (Continued!

NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.

Compare incore to excore axial imbalance above 15% of RATED THERMAL POWER. Recalibrate if absolute difference greater than or equal to 3 percent.

Manual ESF functional input check every 18 months.

Each train tested at least every other 62 days.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.

The provisions of Specification 4.0.4 are not applicable.

The provisions of Specification 4.0.4 are not applicable for f, (delta I) and f (delta I) penalties, or for measurement of delta T. (See also Table 2.2-1).

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s).

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

Local manual shunt trip prior to placing breaker in service.

Automatic Undervoltage Trip.

The provisions of Specification 4.0.4 are not applicable when leaving MODE 1. In such an event, the calibration and/or functional test shall be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after leaving MODE 1.

Each train tested at least every other 92 days.

Not Used.

If not performed in previous 184 days.

COOK NUCLEAR PLANT-UNIT 1 (1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

(10)

(1 1)

(12)

(13)

(14)

(15)

(16)

(17)

AMENDMENT-9,4-2,4-, 277 I

Page 34 3-14

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

1. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS TRIP ACTUATING CHANNEL DEVICE CHANNEL CHANNEL FUNCTIONAL OPERATIONAL CHECK CALIBRATION TEST TEST MODES IN WHICH SURVEILLANCE REOUIRED

a.

Manual Initiation

b. Automatic Actuation Logic

c.

Containment Pressure-High

d. Pressurizer Pressure-Low

e.

Differential Pressure Between Steam Lines-- High

f.

Steam Line Pressure--Low

2. CONTAINMENT SPRAY

a. Manual Initiation

b. Automatic Actuation Logic

c. Containment Pressure-- High-High N.A.

S SS N.A.

R R

R S

N.A.

S Q (2)

SA (3)

SA SA R

SA N.A.

R Q (2)

SA (3)

See Functional Unit 9 N.A.

N.A.

See Functional Unit 9 N.A.

N.A.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-31 AMENDMENT 00,420,124 444, 4-53,214,277 1,2,3,4 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3,4 1,2,3

/

i_

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

3. CONTAINMENT ISOLATION CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST TRIP ACTUATING DEVICE OPERATIONAL TEST MODES IN VHICH SURVEILLANCE REOUIRED

a. Phase "A" Isolation

1) Manual

2) From Safety Injection Automatic Actuation Logic

b. Phase "B" Isolation

1) Manual

2) Automatic Actuation Logic

3) Containment Pressure--

High-High

c. Purge and Exhaust Isolation

1) Manual

2) Containment Radioactivity--High N.A.

N.A.

S S

N.A.

Q (2)

N.A.

Q (2)

R SA (3)

R Q

See Functional Unit 9 -

N.A.

See Functional Unit 9 N.A.

N.A.

See Functional Unit 9 N.A.

AMENDMENT 400,444, 43,483,277 1,2,3,4 1,2,3,4 1,2,3 1,2,3,4 I

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-32

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

4. STEAM LINE ISOLATION

a. Manual

b. Automatic Actuation Logic

c. Containment Pressure-High-High

d.

Steam Flow in Two Steam Lines-High Coincident with T1vg-Low-Low

e. Steam Line Pressure-Low

5. TURBINE TRIP AND FEEDWATER ISOLATION a

Steam Generator Water Level--High-High

6.

MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water Level--Low-Low

b. 4 kv Bus Loss of Voltage

c.

Safety Injection

d. Loss of Main Feed Pumps CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST TRIP ACTUATING DEVICE OPERATIONAL TEST MODES IN WHICH SURVEILLANCE REOUIRED See Functional Unit 9 N.A.

N.A.

S R

S S

R R

S R

S S

N.A.

R R

N.A.

Q (2)

SA (3)

SA SA SA SA M

Q (2)

R N.A.

N.A.

1,2,3, 1, 2 3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-33 AMENDMENT 400, 420, 424,444, 4,

244, 277

_ _ ~ ~~ ~

I I

I

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS

a. Steam Generator Water Level--Low-Low

b. Reactor Coolant Pump Bus Undervoltage

8.

LOSS OF POWER

a. 4kvBusLoss of Voltage

b. 4 kv Bus Degraded Voltage CHANNEL CHANNEL CHANNEL FUNCTIONAL CHECK CALIBRATION TEST S

N.A.

S S

R R

SA M

M M

TRIP ACTUATING DEVICE OPERATIONAL TEST N.A.

N.A.

MODES IN WHICH SURVEILLANCE REOUTRED 1,2,3 1,2,3 1,2,3,4 1,2,3,4 AMENDMENT 00, 0, 444, 4-3, 277 I

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-33a

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST REOUIRED

9. Manual

a. Safety Injection (ECCS)

N.A.

R 1,2,3,4 Feedwater Isolation Reactor Trip (SI)

Containment Isolation-Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b. Containment Spray N.A.

N.A.

R 1,2,3,4 Containment Isolation-Phase "B" Containment Purge and Exhaust Isoladon

c. Containment Isolation-N.A.

N.A.

R 1,2,3,4 Phase "A" Containment Purge and Exhaust Isolation

d. SteamLinelsolation N.A.

N.A.

Q R

1,2,3

e.

Containment Air N.A.

N.A.

R 1,2,3,4 Recirculation Fan

10. CONTAINMENT AIR RECIRCULATION FAN

a.

Manual

-See Functional Unit 9--------

b. Automatic Actuation Logic N.A.

N.A.

Q (2)

N.A.

1, 2, 3

c. Containment Pressure - High S

R SA (3)

N.A.

1, 2, 3 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-33b AMENDMENT 39, ;04, 34, 277

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

TABLE NOTATION (1)

Deleted (2)

Each train or logic channel shall be tested at least every other 92 days.

(3)

The CHANNEL FUNCTIONAL TEST shall include exercising the transnitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

COOK NUCLEAR PLANT-UNIT 1 AMENDMENT 39, N4, 277 Page 3/4 3-34

1.0 DEFINITIONS TABLE 1.2 FREOUENCY NOTATION FREOUENCY At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months At least once per 7 days At least once per 31 days At least once per 92 days At least once per 62 days At least once per 184 days At least once per 549 days Prior to each reactor start-up Completed prior to each release Not Applicable COOK NUCLEAR PLANT-UNIT 2 NOTATION S

D w

M Q

2 Months SA R

SIU p

N.A.

I I

Page 1-10 AMENDMENT 5, 260

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

16.

Undervoltage-Reactor Coolant Pumps

17.

Underfrequency-Reactor Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil Pressure B.

Turbine Stop Valve Closure

19.

Safety Injection Input from ESF

20.

Reactor Coolant Pump Breaker Position Trip Above P-7

21.

Reactor Trip Breakers

22.

Automatic Trip Logic TOTAL NO. OF CHANNELS 4-1/bus 4-1/bus 3

4 2

I/breaker 2

2 CHANNELS TO TRIP 2

2 2

4 1

2 1

1 MINIMUM CHANNELS APPLICABLE OPERABLE MODES 3

1 3

2 3

2 I /breaker per operating loop 2

2 I

I 1

1,2 3

1,2 3*, 4*, 5*

AMENDMENT 86, 1,

424, 4-n, 260 l

ACTION 6#

I 11 13, 15 14 I

14 I

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3X4

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 3.3-1 (Continued)

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION

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

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

With the number of OPERABLE Reactor Trip Breaker channels one less than required by the Minimum Channels OPERABLE requirement for reasons other than an inoperable diverse trip feature, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1.1, provided the other channel is OPERABLE.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION P-6 CONDITION AND SETPOINT With 2 of 2 Intermediate Range Neutron Flux Channels < 6 X 10-1 amps.

FUNCTION P-6 prevents or defeats the manual block of source range reactor trip.

COOK NUCLEAR PLANT-UNIT 2 ACTION 11 ACTION 12 ACTION 13 ACTION 14 ACTION 15 AMENDMENT -&, 42,7,260 Page 34 3-7

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNIT

1.

Manual Reactor Trip A.

Shunt Trip Function B.

Undervoltage Trip Function

2.

Power Range, Neutron Flux

3.

Power Range, Neutron Flux, High Positive Rate

4.

Power Range, Neutron Flux, High Negative Rate

5.

Intermediate Range, Neutron Flux

6.

Source Range, Neutron Flux

7.

Overtemperature AT

8.

Overpower AT

9.

Pressurizer Pressure -- Low

10.

Pressurizer Pressure -- High

11.

Pressurizer Water Level -- High

12.

Loss of Flow-Single Loop CHANNEL CHANNEL CHECK CALIBRATION N.A.

N.A.

S N.A.

N.A.

S S

N.A.

D(2,8), M(3,8),

and Q(6,8)

R(6)

R(6,8)

R(6,14)

R(9)

R R

R R(8)

CHANNEL FUNCTIONAL TEST S/U(1)(10)

S/U(1)(10)

Q and S/U(1)

Q Q

S/U(17)

M(14) and SIU(l)

SA SA SA SA SA SA MODES IN WHICH SURVEILLANCE REOUIRED 1, 2,3', 4, 5*

1, 2,3*,4*,5*

1, 2 and*

1,2 1,2 1,2, and 2(7), 3(7), 4 and 5 1,2 1,2 1,2 1,2 1,2 1

0 0z zp z

I-tTi z

0-

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVETLLANCE REQUIREMENTS FUNCTIONAL UNIT

13. Loss of Flow-Two Loops

14. Steam Generator Water Level -- Low-Low

15. Steam/Feedwater Flow Mismatch and Low Steam Generator Water Level

16. Undervoltage-Reactor Coolant Pumps

17. Underfrequency-Reactor Coolant Pumps

18. Turbine Trip A.

Low Fluid Oil Pressure B.

Turbine Stop Valve Closure

19. Safety Injection Input from EFS

20. Reactor Coolant Pump Breaker Position Trip

21. Reactor Trip Breaker A.

Shunt Trip Function B.

Undervoltage Trip Function

22. Automatic Trip Logic

23. Reactor Trip Bypass Breaker CHANNEL CHECK S

S S

N.A.

N.A N.A.

CHANNEL CALIBRATION R(8)

R R

N.A.

CHANNEL FUNCTIONAL TEST N.A.

SA SA M

M S/U(I)

S/U(I)

Q (4)(15)

R 2 Months (5)(1 1) and S/U(I)(I 1) 2 Months (5)(1 1) and SIU()(I 1)

Q (15) 2 Months (5)(12) and S/U(1)(13)

MODES IN WHICH SURVEILLANCE REQUIRED 1

1,2 1,2 1,2 1,2 1,2 N.A.

1, 2,3,4*, 5*

1, 2,34, 4, 5*

1, 2,3*, 4*, 5*

1, 2,3*, 4*, 5' 00 z

P3 z

Nl.

0\\0 I

I I

I

3/4 LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-1 (Continued)

NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.

Compare incore to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference greater than or equal to 3 percent.

Manual ESF functional input check every 18 months.

Each train tested at least every other 62 days.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

Below P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint.

The provisions of Specification 4.0.4 are not applicable.

The provisions of Specification 4.0.4 are not applicable for f1 (delta I) and f2 (delta I) penalties, or for measurement of delta T. (See also Table 2.2-1).

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s).

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

Local manual shunt trip prior to placing breaker in service.

Automatic Undervoltage Trip.

The provisions of Specification 4.0.4 are not applicable when leaving MODE 1. In such an event, the calibration and/or functional test shall be performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after leaving MODE 1.

Each train tested at least every other 92 days.

Not Used.

If not performed in previous 184 days.

COOK NUCLEAR PLANT-UNIT 2 (1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

(10)

(1 1)

(12)

(13)

(14)

(15)

(16)

(17)

I Page 3/4 3-13 AMENDMENT 86,4 0,

-8, 260

3/4 LLMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVELLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST REOUIRED I.

SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a.

Manual Initiation See Functional Unit 9

b.

Automatic Actuation NA.

N.A.

Q (2)

N.A.

1,2,3,4 Logic

c.

Containment Pressure --

S R

SA (3)

N.A.

1,2,3 High

d.

Pressurizer Pressure -

S R

SA N.A.

1,2,3 Low

e.

Differential Pressure S

R SA N.A.

1,2,3 Between Stean Lines -

High

f.

Steam ine Pressure-S R

SA N.A.

1,2,3 Low

2.

CONTAINMENT SPRAY

a.

Manual Initiation See Functional Unit 9

b.

Automatic Actuation N.A.

N.A.

Q (2)

NA.

1, 2,3,4 Logic

c.

Containment Pressure --

S R

SA (3)

N.A.

1,2,3 High-High

3.

CONTAINMENT ISOLATION

a.

Phase "A' Isolation I)

Manual See Functional Unit 9----

2)

From Safety N.A.

NA.

Q (2)

N.A.

1,2, 3,4 Injection Automatic Actuation Logic

b.

Phase "B" Isolation

1)

Manual ee Functional Unit 9

2)

Automatic Actuation N.A.

N.A.

Q (2)

N.A.

1,2,3,4 Logic

3)

Containment S

R SA (3)

N.A.

1,2,3 Pressure-High-High COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-30 AMENDMENT -34, 434, -3, 48, 4, 260

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 314.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT

c.

Purge and Exhaust Isolation CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST TRIP ACTUATING DEVICE OPERATIONAL TEST MODES IN WHICH SURVEILLANCE REOUIRED I)

Manual

2)

Containment Radioactivity - High

4.

STEAM LINE ISOLATION See Functional Unit 9 S

R Q

a.

Manual

b.

Automatic Actuation Logic

c.

Containment Pressure -

High-High

d.

Steam Flow in Two Steam lines - High Coincident with T,vg - Low-Low

e.

Steam ine Pressure -

Low N.A.

S N.A.

Q (2)

R S

SA (3)

SA SA R

-See Functional Unit 9 N.A.

N.A.

5.

TURBINETRIPAND FEEDWATER ISOLATION

a.

Steam Genertor Water Level - High-High S

R SA N.A.

6.

MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

a.

Steam Genertor Water Level - Low-Low

b.

4 kV Bus Loss of Voltage

c.

Safety Injection

d.

Loss of Main Feed Pumps S

S N.A.

N.A.

R R

N.A.

SA M

Q (2)

R N.A.

N.A.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-31 AMENDMENT 82,97,434,434, 41,4,468,4, 260 N.A.

1,2,3,4 1,_2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2 I

I I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL UNrr CHANNEL CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST TRIP ACTUATING DEVICE OPERATIONAL TEST MODES IN WHICH SURVEILLANCE REOUIRED

7.

TURBINE DRIVEN AUXILIARY FEEDWATER PUMP

a.

Steam Generator Water Level -- Low-Low

b.

Reactor Coolant Pump Bus Undervoltage

8.

LOSS OF POWER

a.

4kv Bus Loss of Voltage

b.

4 kv Bus Degraded Voltage

9.

MANUAL

a.

Safety Injection (ECCS)

Feedwater Isolation Reactor Trip (SI)

Containment Isolation -

Phase "A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Water System

b.

Containment Spray Containment Isolation -

Phase "B" Containment Purge and Exhaust Isolation

c.

Containment Isolation -

Phase "A" Containment Purge and Exhaust Isolation

d.

Steam Line Isolation

e.

Containment Air Recirculation Fan

10. CONTAINMENTAIR RECIRCULATION FAN

a.

Manual

b.

Automatic Actuation Logic

c.

Containment Pressure.-

High N.A.

S N.A.

R

-See Functional U Q (2)

SA (3)

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-32 AMENDMENT 82,97, 434, 137, 459, 489, 247,260 S

R N.A.

S S

N.A.

R R

R N.A.

N.A.

SA M

M M

N.A.

NA.

N.A Q

N.A.

R R

R 1,2,3 1,2,3 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3,4 1,2,3 1,2,3,4 N.A.

N.A.

1,2,3 1,2,3 Jnt 9j-I

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

TABLE NOTATION (1)

Deleted (2)

Each train or logic channel shall be tested at least every other 92 days.

(3)

The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-33 AMENDMENT82, 44,48, 260

ML031480135

Text

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