ML17325A214
| ML17325A214 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/16/1987 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17325A213 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8707230759 | |
| Download: ML17325A214 (7) | |
Text
Attachment 5 to AEP:NRC:0856T Revised Pages for the Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Technical Specifications 8707230759'707i6 PDR ADOCK 050003' P
PDR,,'
TABLE 3.3-11 POST-ACCIDENT MONITORING INSTRUMENTATION 0
INSTRUMENT O
1.
Containment Pressure 2.
Reactor Coolant Outlet Temperature
- T (Wide Range)
HOT a
3.
Reactor Coolant Inlet Temperature
- T (Wide Range)
H 4.
Reactor Coolant Pressure
- Wide Range 5.
Pressurizer Water Level 6.
Steam Line Pressure 7.
Steam Generator Water Level - Narrow Range 8.
Refueling Water Storage Tank Water Level 9.
Boric Acid Tank Solution Level 4) 10.
Auxiliary Feedwater Flow Rate 11.
Reactor Coolant System Subcooling Margin Monitor I
Pn 12.
PORV Position Indicator
- Limit Switches~~~
13.
PORV Block Valve Position Indicator
- Limit Switches 14.
Safety Valve Position Indicator
- Acoustic Monitor 15.
Incore Thermocouples (Core Exit Thermocouples) 16.
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) 17.
Containment Sump Level 18.
Containment Water Level MINIMUM CHANNELS OPERABLE 2/Steam Generator 1/Steam Generator 1/Steam Generator~
1/Valve 1/Valve 1/Valve 2/Core Quadrant One Train (3 channels/Train)
]****
2**%*
g' Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow rate channel instrument PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.
~* Acoustic monitoring of PORV position (1 channel per three valves
- headered discharge) can be used as a
substitute for the PORV Indicator
- Limit Switches instruments.
- 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.
TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS A
INSTRUMENT O
1.
Containment Pressure HOT 2.
Reactor Coolant Outlet Temperature
- T (Wide Range)
H 3.
Reactor Coolant Inlet Temperature
- T (Wide Range)
COLD 4.
Reactor Coolant Pressure
- Wide Range 5.
Pressurizer Water Level 6.
Steam Line Pressure Steam Generator Water Level
- Narrow Range 8.
RWST Water Level CHANNEL CHECK CHANNEL CALIBRATION R
R+
9.
10ll 12 Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position"Indicator
- Limit Switches 13.
PORV Block Valve Position Indicator
- Limit Switches 14.
Safety Valve Position Indicator - Acoustic Monitor 15.
Incore Thermocouples (Core Exit Thermocouples) 16.
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)
Containment Sump Level**
Containment Water Level*~
M(2)
R(1)
R(3)
(3)
Partial range channel calibration for sensor to be performed below P-12 in MODE 3.
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 Reactor Vessel Indication train OPERABLE.
Completion of channel calibration f'r sensors to be performed below P-12 in MODE 3.
The provisions of Specification 4.0.6 are applicable.
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.
IHSTlllMENTATIOH 3/4.3.3. 7 FIRE DETECTION INSTRUMENThTION OpERASZLZTY of cbe fire detection instrumentation ensures chat adequate varning capability is available for che prompc detection of fires.
This cape bilicy is re quired Ln o rd e r co detect and locate fires in their early scages.
Prompt detection of fires vill reduce cba potential for dasLage to safecy relaced equipmenc and is an inregral elemenc in cbe overall facflity fire protection program.
In tba event that, a portion of tbe fire detection instrumentation is inoperable, the establishment of frequent fire patrols in cba affected areas is required co provide detection capability uncil the. inoperable instrumentation is restored co OPEMZLZTT.
Use of containment temperacure monicoring is alloved once per tuur if concainmenc fire detection is inope ra ble.
3/4.3.3.8 POST-ACCIDENT INSTRUMENThTION The OP BhSZLZTZ of cbn poet-accident instrumentation ensures that sufficient informacion is available on selected plane parameters to'monitor aad assess these variables during and folloving an accident.
The containment water level and containment sump level transmitters will be modified or replaced and OPERABLE by the end of the refueling outage scheduled to begin in February 1989.
D C COOK UHXT 1 S 3/4 3-4 hmgndment No+
TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION 7.
Steam Generator Water Level - Narrow Range 8.
Refueling Water Storage Tank Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator - Limit Switches>**
PORV Block Valve Position Indicator - Limit Switches 14.
Safety Valve Position Indicator
- Acoustic Monitor 15.
Incore Thermocouples (Core Exit Thermocouples) 16.
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication) 17.
Containment Sump Level 18.
Containment Water Level INSTRUMENT Ao 1.
Containment Pressure 0
2.
Reactor Coolant Outlet Temperature
- THOT (Wide Range) a 3.
Reactor Coolant Inlet Temperature
- TCOLD (Wide Range) 4.
Reactor Coolant Pressur'e
- Wide Range 5.
Pressurizer Water Level 6.
Steam Line Pressure MINIMUM CHANNELS OPERABLE 2/Steam Generator 1/Steam Generator 1/Steam Generator*
1/Valve 1/Valve 1/Valve 2/Core Quadrant One Train (3 channels/Train)
]*~*
2****
g Steam Generator Water Level Channels can be used as a substitute for the corresponding auxiliary feedwater flow g'ate channel instrument g **
PRODAC 250 subcooling margin readout can be used as a substitute for the subcooling monitor instrument.
- Acoustic monitoring of PORV position (1 channel per three valves
- headered discharge) can be used as a
substitute for the PORV Indicator - Limit Switches instruments.
- ~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.
TABLE 4.3-10
'POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS
~
INSTRUMENT A
O g
1.
Containment Pressure 2
Reactor Coolant Outlet Temperature
- THOT (Wide Range) g 3.
Reactor Coolant Inlet Temperature TC LD (Wide Range)
H 4.
Reactor Coolant Pressure
- Wide Range 5.
Pressurizer Water Level Steam Line Pressure CHANNEL CHECK M
CHANNEL CALIBRATION R
7.
8.
9.
10.
11.
12.
13.
14.
15.
16.
17.
Steam Generator Water Level - Narrow Range RWST Water Level Boric Acid Tank Solution Level Auxiliary Feedwater Flow Rate Reactor Coolant System Subcooling Margin Monitor PORV Position Indicator - Limit Switches PORV Block Valve Position Indicator
- Limit Switches Safety Valve Position Indicator - Acoustic Monitor Incore Thermocouples (Core Exit Thermocouples)
Reactor Coolant Inventory Tracking System (Reactor Vessel Level Indication)
Containment Sump Level*
M M
M(2)
R R
R(1)
R(3) 18.
Q (])
0 (3)
Containment Water Level*
M R
Partial range channel calibration for sensor to be performed below P-12 in MODE 3.
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 Reactor Vessel Indication train OPERABLE.
Completion of channel calibration for sensors to be performed below P-12 in MODE 3.
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.
r, C g--
ON OR vG INSMt-The OPERABILITY of the radiation monitoring channels ensures that 1) the radiati.on levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action i.s initi.ated when the radiation level trip setpoint is exceeded.
V L
INCOR~ DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represen" "he spatial neutron flux distribution of the-reactor core.
The OPERGILI:Y of this system is demonstrated by irradi.ating each detector used and no..alizing its respective output.
3 hf7C NS+ifwl-.>'
T~g<
The OPERABILITY of the se sm'c instmentation ensures that sufficient capability is availa'ole to pro...pt'y determine the magnitude of a seismic even" and evaluate the response of those features important to safety.
This capabi.lity is required to permit comparison of the measured response to that used in tne design basis
=or =he facility.
4
.4 f<
. LM~Nl'A ON The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine o" accidental release of radioactive materials to the at osphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
3
. 5 R
~
DOWN NS URETE ON Qe OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability i.s available to permit shutdown and maintenance of HOT
- STANDBY of the facility from locations outside of the control room.
This capability i.s required in the event control room habitabi.lity is lost and is consistent with General Desi.gn Criteria 19 of 10 CPR 50.
6
-A CID MSTR
.E T TTO B 3/4 3-2 The OPERABILITY of the post-accident instrumentation ensures that suffi.cient information is availaole on selected plant parameters to monitor and assess these variables during and following an accident.
The containment water level and containment sump level transmitters will be modified or replaced and OPERABLE by the end of the outage currently scheduled to begin in May 1988.
D. C.
COOK - UNIT 2
~
AMEND~+
NO.