ML17331B095

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Proposed Tech Specs Re Extension of Surveillance Interval for Cycle 9
ML17331B095
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 12/03/1993
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331B094 List:
References
NUDOCS 9312100058
Download: ML17331B095 (12)
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Text

TABLE 4.3-1 '

~ Y Pr 0 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS Z CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST RE<EUIRED 4 .

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1. Manual Reactor Trip A. Shunt Trip Function N.A. N.A. S/U(1)(10) 3*, 4*, 5*

B. Undervoltage Trip- N.A. N.A. S/U(1)(lo) 3*, 4*, 5*

Function r I

~

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

and Q(6,8)

"0 UN, CQ,'Qi 3. Power Range, Neutron Flux, N.A. R(6) M 1, 2 High Positive Rate

%O tlO > 4.

ClO Power Range, Neutron Flux,: N;A. R(6) 1, 2 ACJI <

-Xml'QI High Negative Rate QlQ I Owl

5. Intermediate Range;-:-: S R(6,8)- S/U(1) 1, 2 and*

OtQ t Neutron Flux llOO,'ud, Rw 6. Source Range, Neutron Flux R(6,14) M(14) and S/U(1) 2(7), 3(7),

4 and 5

7. Over temperature AT R(9)T 1 2
8. Overpower AT S R(9)% 1 2
9. Pressurizer Pressure--Low 1, 2 Pressurizer Pressure--High 1, 2 r

RT,'(8)

11. Pressurizer Water Level--High,: 1, 2 0
12. Loss of Flow - Single Loop

~ ~

i TABLE 4. 3-2 Continued ENGINEERED SAFETY FEATURED ACTUATION SYSTEM ZNSTRUMENTATZON SURVEILLANCE RE UZR19KNTS TRIP hCTUATING MODES IN CEQSEL DEVZCE WHICH CHANNEL AfAHNEL FUHCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATIOH TEST TEST 7 ~ TURBINE DRIVEN hUXILZARY FEEDWATER PUMP ao Steam Generator Water H.h. 1, 2, 3 Level--Los-los

b. Reactor Coolant Pump H.h. H.h. 1, 2, 3 Bus Undervoltage S. LOSS OF POWER
a. 4 kv Bus N.h.. 1, 2, 3, 4 .

Loss of Voltage

b. 4 kv Bus H.h. 1, 2, 3, 4 Degraded Voltage
9. Manual
a. Safety Injection (ECCS) N.h. N.h. N.h. 1, 2, 3, 4 Feedwater Isolation Reactor Trip (SZ)

Containment Isolation-Phase. h" Containment Purge and Exhaust Isolation Auxiliary Feedvater Pumps Essential Service Water System

.b. Containment Spray N.h. H.h. H.h; 1 2 3. 4' Containment Zsolation-Phase "B" Containment Purge and Exhaust Isolation Containment hir Recirculation Fan

c. Containment Zsolation- N.h. N.h. N.h.

Phase "h" Containment Purge and Exhaust Isolation

d. Steam Line Isolation H.h. H.h. 'H(1/6 I C. Pmy<Sl~ af ~~<<c.J 5PCcgi<~kta~ .$ .0ig acr PPPll C&4.

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COOK NUCLEAR PLANT - UHIT 2 3/4 3-32 HO ms'7 fg

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e TABLE 4.3-10 POST-ACCIDENT MONIT RING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CIIANHEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure M R
2. Reactor Coolant Outlet Temperature - THO (Wide Range) M Rt
3. Reactor Coolant Inlet Temperature - TCOLD (Wide Range) M R+
4. Reactor Coolant Pressure - Wide Range M R
5. Pressurizer Water Level M Rt'
6. Steam Line Pressure M
7. Steam Generator Water Level - Harrow Range M R
8. RWST Water Level M R
9. Boric Acid Tank Solution Level M R
10. Auxiliary Feedwater Flow Rate M R
11. Reactor Coolant System Subcooling Margin Monitor M R
12. PORV Position Indicator - Limit Switches M R
13. PORV Block Valve Position Indicator - Limit Switches M R
14. Safety Valve Position Indicator - Acoustic Monitor M R
15. Incore Thermocouples (Core Exit Thermocouples)(4) M R(l) 4
16. Reactor Coolant Inventory 'Tracking System M(2) R(3)t (Reactor Vessel Level Indication)
17. Containment Sump Level* M R
18. Containment Water Level* M R (1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

(2) With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaini.ng Reactor Vessel Indication train OPERABLE.

(3) Completion of channel calibration for sensors to be performed below P-12 in MODE 3.

(4) The core exit thermocouples will not be installed until the 1988 refueling outage; therefore, surveillances will not be required until that time. See license amendment dated April 10, 1987 The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational. The schedule for modification or replacement of the transmitters i.s described in the Bases.

prov) 5)~..+ %~ch))ic~( qpccj4')'c +)~ q018$ R~ ~/pl~ ~(c COOK NUCLEAR PLANT - UNIT 2 3/4-3.-47 AHEHDHENT NO." Pg, gg~) f

REACTOR COOLANT SYSTEM 3 4.4.6 REACTOR COOLANT SYSTEM LPMCAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The 'following Reactor Coolant System leakage detection systems shall be OPERABLE:

a. One of the containment atmosphere particulate radioactivity monitoring channels (ERS-2301 or ERS-2401),
b. The containment sump level and flow monitoring system, and c ~ Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the reguired gaseous and/or particulate radioactivity monitoring channels are '!.:3 inoperable; otherwise, be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a. Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,
b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months, g I

c ~ Containmeni humidity monitor (if being used) - performance of CHANNEL

'CALIBRATION at least once per 18 months.

pceulsl'avs op Wec4n,caI Qclficcch'ou 4o g ~ ~PP '""

(i COOK NUCLEAR PLANT - UNIT 2 3/4 4-14 AMENDMENT NO.75

Attachment 4 to AEP:NRC:1181C Proposed Technical Specifications for Donald C. Cook Nuclear Plant Unit 2

TABLE 4 3-1 oO REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST N.A. N.A. S/U(1) (10) ], 2, 3*, 4*, 5 N.A. N.A. S/U(1)(10) ], 2, 3*, 4%, 5*

I Q and*

2. Power Range, Neutron Flux D(2,8),M(3,8) M and S/U(l) 1, 2 and Q(6,8)
3. Power Range, Neutron Flux, N.A. R(6) 1, 2

'igh Positive Rate Power Range, Neutron Flux, N.A. R(6) 1, 2 High Negative Rat'e

5. Intermediate Range, R(6,8) S/U(1) 1, 2 and
  • Neutron Flux
6. Source Range, Neutron Flux R(6, 14) M(14) and S/U(l) 2(7), 3(7), .

4 and 5

7. Overtemperature AT R(9) f 1 2
8. Overpower AT R(9)f 1, 2
9. Pressurizer Pressure--Low Rf 1, 2 Q
10. Pressurizer Pressure--High Rf l. 2
11. Pressurizer Water Level--High Rf 1 2
12. Loss of Flow - Single Loop R(8) f The provisions of Technical Specification 4.0.8 are applicable.

V, g J Cl El TABLE 4.3-2 Continued ENGINEERED SAFETY FEATURED ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP ACTUATING MODES IN CHANNEL DEVICE WHICH CHANNEL CHANNEL FUNCTIONAL OPERATIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST mg

7. TURBINE DRIVEN AUXILIARY FEEDWATER PUMP
a. Steam Generator Water N.A. 1, 2, 3 Level--Low-low
b. Reactor Coolant Pump N.A. N.A. 1 2 3 Bus Undervoltage 8, LOSS OF POWER
a. 4 kv Bus Rf N.A. 1,2,3 I Loss of Voltage
b. 4 kv Bus Rf N.A. 1,2,3,4 I Degraded Voltage
9. MANUAL
a. Safety Injection (ECCS) N.A. N.A. N.A. Rf 1 2 3 4 I 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. Rf 1, 2, 3, 4 Containment Isolation-Phase "B" Containment Purge and Exhaust Isolation Containment Air Recirculation Fan
c. Containment Isolation- N.A. N.A. N.A. Rf 1, 2, 3, 4 Phase "A" Containment Purge and Exhaust Isolation
d. Steam Line Isolation N.A. N.A. M(lf ) Rf 1 2 3 f The provisions of Technical Specification 4.0.8 are applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-32 AMENDMENT NO. 88, &7, 434, ka7.

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TABLE 4 3-10 A

O POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS O

CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure M R
2. Reactor Coolant Outlet Temperature - Ts~ (Wide Range) M Rt
3. Reactor Coolant Inlet Temperature - Tco~ (Wide Range) M R$
4. Reactor Coolant Pressure - Wide Range M R
5. Pressurizer Water Level M Rf
6. Steam Line Pressure M R
7. Steam Generator Water Level - Narrow Range M R
8. RWST Water Level M R
9. Boric Acid Tank Solution Level M R
10. Auxiliary Feedwater Flow Rate M R
11. Reactor Coolant System Subcooling Margin Monitor M Rf
12. PORV Position Indicator - Limit Switches- M R
13. PORV Block Valve Position Indicator - Limit Switches M R
14. Safety Valve Position Indicator - Acoustic Monitor M R
15. Incore Thermocouples (Core Exit Thermocouples)(4) M R(1) f
16. Reactor Coolant Inventory Tracking System M(2) R(3) f (Reactor Vessel Level Indication)
17. Containment Sump Level* M R
18. Containment Water Level* M R (1) Partial range channel calibration for sensor to be performed below P-12 in MODE 3.

(2) With one train of Reactor Vessel Level Indication inoperable, Subcooling Margin Indication and Core Exit Thermocouples may be used to perform a CHANNEL CHECK to verify the remaining O

Reactor Vessel Indication train OPERABLE.

(3) Completion of channel calibration for sensors to be performed below P-12 in MODE 3.

(4) The core exit thermocouples will not be installed until the 1988 refueling outage; therefore,,surveillances will not be required until that time. See license amendment dated April 10, 1987.

  • The requirements for these instruments will become effective after the level transmitters are modified or replaced and become operational. The schedule for modification or replacement of the transmitters is described in the Bases.

The provisions of Technical Specification 4.0.8 are applicable.

~. ~ 4

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REACTOR COOLANT SYSTEM 3 4 4 6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6 ' The following Reactor Coolant System leakage detection systems shall be OPERABLE'.

One of the containment atmosphere particulate radioactivity monitoring channels (ERS-2301 or ERS-2401),

b. The containment sump level and flow monitoring system, and
c. Either the containment humidity monitor or one of the containment atmosphere gaseous radioactivity monitoring channels (ERS-2305 or ERS-2405).

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

With only two of the above required leakage detection systems OPERABLE, operation may continue for up to .30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous and/or particulate radioactivity monitoring channels are inoperable; otherwise, be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE UIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

a ~ Containment atmosphere particulate and gaseous (if being used) monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3,

b. Containment sump level and flow monitoring system-performance of CHANNEL CALIBRATION at least once per 18 months,f
c. Containment humidity monitor (if being used) - performance of CHANNEL CALIBRATION at least once per 18 months.

f The provisions of Technical Specification 4.0.8 are applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 4-14 AMENDMENT NO.

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