ML031480135

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Technical Specification Pages Amendment 37 to Licenses DPR-58 & DPR-74
ML031480135
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 05/23/2003
From:
NRC/NRR/DLPM
To:
References
Download: ML031480135 (22)
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Text

1.0 DEFINITIONS I TABLE 1.2 FREOUENCY NOTATION NOTATION FREOUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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

w At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

2 Months At least once per 62 days I SA At least once per 184 days.

R At least once per 549 days.

S/U Prior to each reactor startup.

p Completed prior to each release.

N.A. Not Applicable.

COOK NUCLEAR PLANT-UNIT 1 Page 1-9 AMENDMENT X7-,277

0 o 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 *,4-,5*

3 14

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

ACTION 8 - (Deleted.)

ACTION 9 - (Deleted.)

ACTION 10- (Deleted.)

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 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 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 /> and/or open the reactor trip breakers.

ACTION 13- 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 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.

ACTION 14- 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 15- 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. One 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 per Specification 4.3.1.1.1, provided the other channel is OPERABLE.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range Neutron P-6 prevents or defeats the manual Flux Channels less than 6x10-" amps. block of source range reactor trip.

COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-8 AMENDMENT , 42,44,277

314 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.3 INSTRUMENTATION TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED

1. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. S/IU(l)(10) 1,2,3-,4-,5-B. Undervoltage Trip N.A: N.A. SIU(I)(10) 1, 2,3, 4', 5' Function
2. Power Range, Neutron Flux S D(2,8), M(3,8), Q and SfU(l) 1, 2 and and Q(6,8)
3. Power Range, Neutron N.A. R(6) Q 1,2 Flux, High Positive Rate
4. Power Range, Neutron NA. R(6) Q 1,2 Flux, High Negative Rate
5. Intermediate Range, S R(6,8) S/U(17) 1, 2, and Neutron Flux I
6. Source Range, Neutron S R(6,14) M(14) and S/U(1) 2(7), 3(7), 4 and 5 Flux
7. Overtemperature delta T S R(9) SA 1,2
8. Overpower delta T S R(9) SA 1,2
9. Pressurizer Pressure - Low S R SA 1,2
10. Pressurizer Pressure-High S R SA 1,2
11. Pressurizer Water Level - S R SA 1,2 High
12. Loss of Flow-Single Loop S R(8) SA 1 COOK NUCLEAR PLANT-UNIT 1 Page 34 3-12 AMENDMENT 99,420,421,444,277

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

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODE IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED

13. Loss of Flow-Two Loops S R(8) N.A. I I
14. Steam Generator Water S R SA 1,2 Level -- Low-Low
15. Steam/Feedwater Flow S, R SA 1,2 I Mismatch and Low Steam Generator Water Level
16. Undervoltage-Reactor N.A. R M I Coolant Pumps
17. Underfrequency-Reactor N.A. R M I Coolant Pumps
18. Turbine Trip A. Low Fluid Oil Pressure N.A. N.A. S/U(I) 1,2 B. Turbine Stop Valve N.A. N.A. S/U(I) 1,2 Closure
19. Safety Injection Input from N.A. N.A. Q (4)(15) 1,2 I ESF
20. Reactor Coolant Pump N.A. N.A. R N.A.

Breaker Position Trip

21. Reactor Trip Breaker A. Shunt Trip Function N.A. N.A. 2 Months (5)(1 1) 1, 2, 3, 4* 5*

and S/U(l)(ll)

B. Undervoltage Trip N.A. N.A. 2 Months (5)(1 1) 1, 2, 3* 4* 5*

Function and S/U(l)(1 1)

22. Automatic Trip Logic N.A N.A. Q(15) 1, 2, 3, 4* 5*
23. Reactor Trip Bypass N.A. N.A. 2 Months (5)(12) 1, 2, 3*, 4*, 5*

Breaker and S/U(1)(13)

COOK NUCLEAR PLANT-UNIT 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

(1) - If not performed in previous 7 days.

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

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

(4) - Manual ESF functional input check every 18 months.

(5) - Each train tested at least every other 62 days.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

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

(8) - The provisions of Specification 4.0.4 are not applicable.

(9) - 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).

(10) - 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).

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

(12) - Local manual shunt trip prior to placing breaker in service.

(13) - Automatic Undervoltage Trip.

(14) - 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after leaving MODE 1.

(15) - Each train tested at least every other 92 days.

(16) - Not Used.

(17) - If not performed in previous 184 days.

COOK NUCLEAR PLANT-UNIT 1 Page 34 3-14 AMENDMENT-9,4-2,4-, 277 I

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

1. SAFETY INJECTION, TURBINE TRIP, FEEDWATER ISOLATION, AND MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
a. Manual Initiation __ -- - ------ See Functional Unit 9 __ _ ___ ___ /
b. Automatic Actuation Logic N.A. N.A. Q (2) N.A. 1,2,3,4
c. Containment Pressure- High S R SA (3) N.A. 1,2,3
d. Pressurizer Pressure-Low R SA N.A. 1,2,3 SS
e. Differential Pressure Between R SA N.A. 1,2,3 Steam Lines-- High
f. Steam Line Pressure--Low S R SA N.A. 1,2,3
2. CONTAINMENT SPRAY
a. Manual Initiation - ---- -_ - - -- - i_ See Functional Unit 9 _ __ -- _ _---
b. Automatic Actuation Logic N.A. N.A. Q (2) N.A. 1,2,3,4
c. Containment Pressure-- High- S R SA (3) N.A. 1,2,3 High COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-31 AMENDMENT 00,420,124 444, 4-53,214,277

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 VHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST REOUIRED

3. CONTAINMENT ISOLATION
a. Phase "A" Isolation
1) Manual See Functional Unit 9 -
2) From Safety Injection N.A. N.A. Q (2) N.A. 1,2,3,4 Automatic Actuation I

Logic

b. Phase "B" Isolation
1) Manual See Functional Unit 9
2) Automatic Actuation N.A. N.A. Q (2) N.A. 1,2,3,4 Logic
3) Containment Pressure-- S R SA (3) N.A. 1,2,3 High-High
c. Purge and Exhaust Isolation
1) Manual See Functional Unit 9
2) Containment S R Q N.A. 1,2,3,4 Radioactivity--High COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-32 AMENDMENT 400,444, 43,483,277

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

4. STEAM LINE ISOLATION
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 High
d. Steam Flow in Two Steam S R SA N.A. 1,2,3 Lines-High Coincident with T1 vg-Low-Low
e. Steam Line Pressure-Low S R SA N.A. 1,2,3 I
5. TURBINE TRIP AND FEEDWATER ISOLATION a Steam Generator Water S R SA N.A. 1,2,3 Level--High-High I
6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator Water Level--Low-Low S R SA N.A. 1,2,3 I
b. 4 kv Bus Loss of Voltage S R M N.A. 1,2,3
c. Safety Injection N.A. N.A. Q (2) N.A. 1,2,3
d. Loss of Main Feed Pumps N.A. N.A. R N.A. 1,2 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-33 AMENDMENT 400, 420, 424,444, 4, 244, 277

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 TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST REOUTRED

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Generator Water S R SA N.A. 1,2,3 I Level--Low-Low
b. Reactor Coolant Pump Bus N.A. R M N.A. 1,2,3 Undervoltage
8. LOSS OF POWER
a. 4kvBusLoss of Voltage S R M N.A. 1,2,3,4
b. 4 kv Bus Degraded Voltage S R M N.A. 1,2,3,4 COOK NUCLEAR PLANT-UNIT 1 Page 3/4 3-33a AMENDMENT 00, 0, 444, 4-3, 277

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. N.A. 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. N.A. R 1,2,3,4 Containment Isolation-Phase "B" Containment Purge and Exhaust Isoladon
c. Containment Isolation- N.A. 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. 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 Page 3/4 3-34 AMENDMENT 39, N4, 277

1.0 DEFINITIONS TABLE 1.2 FREOUENCY NOTATION NOTATION FREOUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> w At least once per 7 days M At least once per 31 days Q At least once per 92 days 2 Months At least once per 62 days I SA At least once per 184 days R At least once per 549 days SIU Prior to each reactor start-up p Completed prior to each release N.A. Not Applicable COOK NUCLEAR PLANT-UNIT 2 Page 1-10 AMENDMENT 5, 260 I

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

REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO. OF CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT CHANNELS TO TRIP OPERABLE MODES ACTION

16. Undervoltage-Reactor Coolant 4-1/bus 2 3 1 6#

Pumps

17. Underfrequency-Reactor 4-1/bus 2 3 I Coolant Pumps
18. Turbine Trip A. Low Fluid Oil Pressure 3 2 2 I B. Turbine Stop Valve 4 4 3 1 Closure
19. Safety Injection Input from 2 1 2 1,2 I ESF
20. Reactor Coolant Pump Breaker Position Trip Above P-7 I/breaker 2 I/breaker per 3 11 operating loop
21. Reactor Trip Breakers 2 1 2 1,2 13, 15 3*, 4*, 5* 14
22. Automatic Trip Logic 2 1 2 1,2 I 3*, 4*, 5* 14 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3X4 AMENDMENT 86, 424, 1, 4-n, 260 l

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

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 hours1.157407e-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 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 /> and/or open the reactor trip breakers.

ACTION 13 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 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.

ACTION 14 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 15 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. One 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 per Specification 4.3.1.1.1, provided the other channel is OPERABLE.

REACTOR TRIP SYSTEM INTERLOCKS DESIGNATION CONDITION AND SETPOINT FUNCTION P-6 With 2 of 2 Intermediate Range P-6 prevents or defeats the Neutron Flux Channels < 6 X 10-1 amps. manual block of source range reactor trip.

COOK NUCLEAR PLANT-UNIT 2 Page 34 3-7 AMENDMENT -&, 42,7,260

0 TABLE 4.3-1 0

z REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE zp CHECK CALIBRATION TEST REOUIRED FUNCTIONAL UNIT z 1. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. S/U(1)(10) 1, 2,3', 4, 5*

B. Undervoltage Trip Function N.A. N.A. S/U(1)(10) 1, 2,3*,4*,5*

2. Power Range, Neutron Flux S D(2,8), M(3,8), Q and S/U(1) 1, 2 and*

and Q(6,8)

I-

3. Power Range, Neutron Flux, High Positive Rate N.A. R(6) Q 1,2 tTi
4. Power Range, Neutron Flux, High Negative Rate N.A. R(6) Q 1,2
5. Intermediate Range, Neutron Flux S R(6,8) S/U(17) 1,2, and z 6. Source Range, Neutron Flux S R(6,14) M(14) and SIU(l) 2(7), 3(7), 4 and 5
7. Overtemperature AT S R(9) SA 1,2 0-
8. Overpower AT S R(9) SA 1,2
9. Pressurizer Pressure -- Low S R SA 1,2
10. Pressurizer Pressure -- High S R SA 1,2
11. Pressurizer Water Level -- High S R SA 1,2
12. Loss of Flow-Single Loop S R(8) SA 1

0 TABLE 4.3-1 (Continued) 0 REACTOR TRIP SYSTEM INSTRUMENTATION SURVETLLANCE REQUIREMENTS CHANNEL MODES IN WHICH z CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED P3

13. Loss of Flow-Two Loops S R(8) N.A. 1
14. Steam Generator Water Level -- Low-Low S R SA 1,2
15. Steam/Feedwater Flow Mismatch and Low Steam S R SA 1,2 Generator Water Level
16. Undervoltage-Reactor Coolant Pumps N.A. R M
17. Underfrequency-Reactor Coolant Pumps N.A. R M
18. Turbine Trip A. Low Fluid Oil Pressure N.A. N.A. S/U(I) 1,2 B. Turbine Stop Valve Closure N.A. N.A. S/U(I) 1,2
19. Safety Injection Input from EFS N.A. N.A. Q (4)(15) 1,2 I
20. Reactor Coolant Pump Breaker Position Trip N.A. N.A. R N.A.
21. Reactor Trip Breaker A. Shunt Trip Function N.A. N.A. 2 Months (5)(1 1) and 1, 2,3 ,4*, 5* I S/U(I)(I 1) 2 Months (5)(1 1) and 1, 2,34, 4, 5* I B. Undervoltage Trip Function N.A. N.A.

SIU()(I 1) z 22. Automatic Trip Logic N.A N.A. Q (15) 1, 2,3*, 4*, 5*

Nl. 23. Reactor Trip Bypass Breaker N.A. N.A. 2 Months (5)(12) and 1, 2,3*, 4*, 5' I 0\ S/U(1)(13) 0

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

NOTATION

(1) - If not performed in previous 7 days.

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

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

(4) - Manual ESF functional input check every 18 months.

(5) - Each train tested at least every other 62 days.

I (6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

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

(8) - The provisions of Specification 4.0.4 are not applicable.

(9) - 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).

(10) - 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).

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

(12) - Local manual shunt trip prior to placing breaker in service.

(13) - Automatic Undervoltage Trip.

(14) - 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after leaving MODE 1.

(15) - Each train tested at least every other 92 days.

(16) - Not Used.

(17) - If not performed in previous 184 days.

COOK NUCLEAR PLANT-UNIT 2 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 TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST REOUIRED

c. Purge and Exhaust Isolation I) Manual See Functional Unit 9
2) Containment S R Q N.A. 1,2,3,4 Radioactivity - High
4. STEAM LINE ISOLATION
a. Manual ________________

-See Functional Unit 9

b. Automatic Actuation N.A. N.A. Q (2) N.A. 1,_2,3 Logic
c. Containment Pressure - S R SA (3) N.A. 1,2,3 High-High
d. Steam Flow in Two Steam S R SA N.A. 1,2,3 lines - High Coincident with T,vg - Low-Low
e. Steam ine Pressure - S R SA N.A. 1,2,3 I Low
5. TURBINETRIPAND FEEDWATER ISOLATION
a. Steam Genertor Water S R SA N.A. 1,2,3 I Level - High-High
6. MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS
a. Steam Genertor Water S R SA N.A. 1,2,3 I Level - Low-Low
b. 4 kV Bus Loss of Voltage S R M N.A. 1,2,3
c. Safety Injection N.A. N.A. Q (2) N.A. 1,2,3
d. Loss of Main Feed Pumps N.A. N.A. R N.A. 1,2 COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-31 AMENDMENT 82,97,434,434, 41,4,468,4, 260

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 UNrr CHECK CALIBRATION TEST TEST REOUIRED

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMP
a. Steam Generator Water S R SA N.A. 1,2,3 I Level -- Low-Low
b. Reactor Coolant Pump Bus N.A. R M N.A. 1,2,3 Undervoltage
8. LOSS OF POWER
a. 4kv Bus Loss of Voltage S R M N.A. 1,2,3,4
b. 4 kv Bus Degraded S R M N.A. 1,2,3,4 Voltage
9. MANUAL
a. Safety Injection (ECCS) N.A. N.A. 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. NA. R 1,2,3,4 Containment Isolation -

Phase "B" Containment Purge and Exhaust Isolation

c. Containment Isolation - N.A. N.A. N.A R 1,2,3,4 Phase "A" Containment Purge and Exhaust Isolation
d. Steam Line Isolation N.A. N.A. Q R 1,2,3
e. Containment Air N.A. N.A. N.A. R 1,2,3,4 Recirculation Fan
10. CONTAINMENTAIR RECIRCULATION FAN
a. Manual -See Functional UJnt 9j-
b. Automatic Actuation N.A. N.A. Q (2) N.A. 1,2,3 Logic
c. Containment Pressure.- S R SA (3) N.A. 1,2,3 High COOK NUCLEAR PLANT-UNIT 2 Page 3/4 3-32 AMENDMENT 82,97, 434, 137, 459, 489, 247,260

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

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