Text

Proposed Tech Specs for Compliance w/NUREG-0737 Requirements
	ML17334A533
Person / Time
Site:	Cook
Issue date:	07/19/1984
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17334A532	List: ML17334A531; ML17334A533;
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	NUDOCS 8407240188
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ATTACHMENT NO. 2 TO AEP:NRC:0856A DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS 84o'71 9 eoR ADOCg gg'Ppp~~g t,

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ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a0 The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

C ~ The change is documented, reviewed by the PNSRC and approved by the Plant Manager within 14 days of implementation.

6.8.4 Plant procedures for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant and containment atmosphere samples and radioactive iodines and particulate samples in plant gaseous effluents under accident conditions. The program will include the following:

a ~ Training of personnel,

b. Procedures for sampling and analysis, c~ Provisions for maintenance of sampling and analysis equipment.

D. C. COOK UNIT 1 6-14 Amendment No.

6. 9 REPORTING RE UIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be sub-mitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

D. C. COOK UNIT 1 6-14a Amendment No.

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

ce The change is documented, reviewed by the PNSRC and approved by the Plant Manager within 14 days of implementation.

6.8.4 Plant procedures for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant and containment atmosphere samples and radioactive iodines and particulate samples in plant gaseous effluents under accident conditions. The program will- include the following:

a~ Training of personnel,

b. Procedures for sampling and analysis, c~ Provision for maintenance of sampling and analysis equipment.

D. C. COOK UNIT 2 6-14 Amendment No.

6.9 REPORTING RE UIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9. 1. 2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured value of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. 'Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, and (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e.,

initial criticality, completion of startup test program, and resumption or commencement of commercial D. C. COOK UNIT 2 6-14a Amendment No.

TABLE 3.3-6A POST-ACCIDENT RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES RANGE ACTION

l. AREA MONITORS HIGH RANGE 7

Containment Area 11 21 3 1 to 10 rad/hr PHOTON

2. Noble Gas Effluent Monitors a) UNIT VENT i Mid Range* -2 to 3 (VRS-1507) 1, 2, 3 2.5x10 10 p Ci/cc ii (VRS-1509)

High Range 1I 2I 3 10 to 10 5

pCi/cc b) Atmospheric Steam Dump Valves 5

Discharge 1/Loop 1, 2, 3 3 to 10 pCi/cc (1) c) Gland Seal Exhaust Mid Range -2 3 (SRA-1807) 1/ 2i 3 2. Sxl0 to 10 pCi/cc d) Condenser Exhaust (1)

System Mid Range -2 3 (SRA-1907) 1, 2, 3 2.5x10 to 10 pCi/cc

Automatic Switchover to High Range only Configuration (Alarm/Trip Setpoint is lxl0 ~Ci/cc)

- Per Requirements of Specification 3.3.3.8 (1) These instruments are under special test operation mode for moisture concern, but are functionally OPERABLE.

TABLE 3.3-6A POST-ACCIDENT RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES RANGE ACTION

l. AREA MONITORS HIGH RANGE 7

Containment Area 1I 2I 3 1 to 10 rad/hr PHOTON

2. Noble Gas Effluent Monitors a) UNIT VENT

i. Mid Range>> -2 3 (VRS-2507) 1I 2I 3 2.5x10 to 10 pCi/cc ii. High Range 5 (VRS-2509) ~

1/ 2/ 3 10 to 10 >Ci/cc b) Atmospheric Steam Dump Valves 5

Discharge 1/Loop 1, 2, 3 3 to 10 >Ci/cc c) Gland Seal (1)

Exhaust Mid Range -2 3 (SRA-2807) 1I 2I 3 2.5x10 to 10 >Ci/cc d) Condenser Exhaust (1)

System Mid Range -2 3 (SRA-2907) 1I 2I 3 2.5x10 to 10 ~Ci/cc

Automatic Switchover to High Range only Configuration (Alarm/Trip Setpoint is lx10 ~Ci/cc)

- Per Requirements of Specification 3.3.3.6 (1) These instruments are under special test operation mode for moisture concern, but are functionally OPERABLE.

7 TABLE 4.3-3A POST-ACCIDENT RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS O

00 CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS I INSTRUMENT CHECK CALIBRATION t3 1. AREA MONITORS High Range Containment Area N/A 1I 2I 3

2. Noble Gas Effluent Monitors a) Unit Vent

i. Mid'ange (VRS-1507) 1I 2I 3 ii. High Range (VRS-1509) N/A 1, 2, 3 b) Atmospheric Steam Dump Valve Discharge M R N/A 1, 2, 3 c) Gland Seal Exhaust (1)

Mid Range (SRA-1807) N/A 1I 2I 3 (1) d) Condenser Exhaust System Mid Range (SRA-1907) N/A 1, 2, 3 0

Acceptable criteria for calibration are provided in Table II.F.1-3 of NUREG-0737.

(1) These insgrpnents concern, u .are functxona sp8gjg pgst operation mode for moisture are undey ly-

O TABLE 4.3-3A A

O Q

POST-ACCIDENT RADIATION MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS I

CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS INSTRUMENT CHECK CALIBRATION

1. AREA MONITORS High Range Containment Area N/A 1, 2, 3

2. Nob'le Gas Effluent'onitors a) Unit Vent

.i. Mid Range (VRS-2507) 1/ 2I 3 ii. High Range (VRS-2509) N/A 1I 2I 3 b) Atmospheric Steam Dump Valve Discharge N/A 1I 2I 3 c) Gland Seal Exhaust (1)

,Mid Range (SRA-2807) N/A 1I 2I 3 (1) d) Condenser Exhaust System Mid Range (SRA-2907) N/A 1, 2, 3 0

Acceptable criteria for calibration are provided in Table II.F.1-,3 of NUREG-0737.

(1) These instruments are under special test operation mode for moisture concern, nut are functionally SBPutBFR..

a TABLE 3.3 POST-ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE

1. Containment Pressure

2. Reactor Coolant Outlet Temperature T (Wide Range)

3. Reactor Coolant Inlet Temperature T (Wide Range)

4. Reactor Coolant Pressure Wide Range

5. Pressurizer Water Level

6. Steam Line Pressure 2/Steam Generator

7. Steam Generator Water Level Narrow Range 1/Steam Generator

8. Refueling Water Storage Tank Water Level

, 9. Boric Acid Tank Solution Level

10. Auxiliary Feedwater Flow Rate 1/Steam Generator*

ll. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator Limit Switches*** 1/Valve

13. PORV Block Valve Position Indicator Limit Switches 1/Valve

14. Safety Valve Position Indicator - Acoustic. Monitor 1/Valve

15. Containment Water Level (Narrow Range)

16. Containment Water Level (Wide Range)

17. Radiation Monitoring Channels Per Table 3.3-6A 0

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 position Indicator Limit Switches instruments.

A A

TABLE 3.3-10 oO POST-ACCIDENT MONITORING INSTRUMENTATION I

INSTRUMENT MINIMUM CHANNELS OPERABLE H

1. Containment Pressure

2. Reactor Coolant Outlet Temperature T (Wide Range)

3. Reactor Coolant Inlet Temperature T (Wide Range) 2

4. Reactor Coolant Pressure Wide Range

5. Pressurizer Water Level

6. Steam Line Pressure 2/Steam Generator

7. Steam Generator Water Level Narrow Range 1/Steam Generator

8. Refueling Water Storage Tank Water Level

9. Boric Acid Tank Solution Level

10. Auxiliary Feedwater Flow Rate 1/Steam Generator*

11. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator Limit Switches*** 1/Valve

13. PORV Block Valve Position Indicator Limit Switches 1/Valve

14. Safety Valve Position Indicator Acoustic Monitor 1/Valve

15. Containment Water Level (Narrow Range)

16. Containment Water Level (Wide Range)

17. Radiation Monitoring Channels Per Table 3.3-6A 0

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 Position Indicator - Limit Switches instruments.

TABLE 4.3-7 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure

2. Reactor Coolant Outlet Temperature T (Wide Range) 3 Reactor Coolant Inlet Temperature TCOLD (Wide Range)

4. Reactor Coolant Pressure Wide Range

5. Pressurizer Water Level

6. Steam Line Pressure

7. Steam Generator Water Level Narrow Range

8. RWST Water Level

9. Boric Acid Tank Solution Level

10. Auxiliary Feedwater Flow Rate

/

11. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator Limit Switches

13. PORV Block Valve Position Indicator Limit Switches

14. Safety Valve Position Indicator Acoustic Monitor R

15. Containment Water Level (Narrow Range) N/A

16. Containment Water Level (Wide Range) N/A

17. Radiation Monitoring Channels (Per Table 4.3-3A)

"TABLE 4.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure

2. Reactor Coolant Outlet Temperature T (Wide Range)

3. Reactor Coolant Inlet Temperature T (Wide Range)

4. Reactor Coolant Pressure Wide Range

5. Pressurizer Water Level

6. Steam Line Pressure

7. .Steam Generator Water Level Narrow Range

8. RWST Water Level

9. Boric Acid Tank Solution Level

10. Auxiliary Feedwater Flow Rate R

11. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator Limit Switches

13. PORV Block Valve- Position Indicator Limit Switches

14. Safety Valve Position Indicator Acoustic Monitor

15. Containment Water Level (Narrow Range) N/A

16. Containment Water Level (Wide Range) N/A

17. Radiation Monitoring Channels (Per Table 4.3-3A)

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2 ACTION:

a0 With one hydrogen analysis device inoperable, restore the inoperable analysis device to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With both hydrogen analysis devices inoperable, restore at least one analysis device to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS 4.6.4.1 Each hydrogen analysis device shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using a four percent and fifteen percent nominal hydrogen gas, balance nitrogen.

D. C. COOK UNIT 1 3/4 6-23 Amendment No.

CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: Modes 1 and 2.

ACTION:

a. With one hydrogen analysis device inoperable, restore the inoperable analysis device to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With both hydrogen analysis devices inoperable, restore at least one analysis device to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS 4.6.4.1 Each hydrogen analysis device shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using a four percent and fifteen percent nominal hydrogen gas, balance nitrogen.

D. C. COOK UNIT 2 3/4 6-33 Amendment No.

INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMITING CONDIT1ON FOR OPERATION 3.3.3.11 The chlorine detection system, with its alarm setpoint adjusted to actuate at a chlorine concentra'tion of less than or equal to 5 ppm,

,shall be OPERABLE.

APPLICABILIY: All MODES.

ACTION:

a0 With the chlorine detection system inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

b. The provisions of Specifications 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.11 The chlorine detection system shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

D. C. COOK UNIT 1 3/4 3-69 Amendment No.

INSTRUMENTATION CHLORINE DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.11 The chlorine detection system, with its alarm setpoint adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE.

APPLICABILITY: ALL MODES.

ACTION:

a0 With the chlorine detection system inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.11 The chlorine detection system shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

D. C. COOK UNIT 2 3/4 3-64a Amendment No.

I INSTRUMENTATION BASES 3/4 '.3.9 RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor arid control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instru-mentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3/4.3.3.11 CHLORINE DETECTION SYSTEM The OPERABILITY of the detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February, 1975.

D. C. COOK UNIT 1 B 3/4 3-5 Amendment No.

3/4.3 INSTRUMENTATION BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service.

3/4.3.3.9 RADIOACTIVE LI UID EFFLUENT INSTRUMENTATZON The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for

, the Donald C. Cook Nuclear Plant.

3/4.3.3.11 CHLORINE DETECTION SYSTEM The OPERABILITY of the detection system ensures that sufficient capability is available to promptly detect and initiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, "Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February, 1975.

D. C. COOK UNIT 2 B 3/4 3-3 Amendment No.

3/4 3.4 TURBINE OVERSPEED PROTECTION h

This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.

D. C. COOK. UNIT 2 B 3/4 3-4 Amendment No.

PLANT SYSTEMS 3/4.7.5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system shall be OPERABLE with:

a. Two independent heating and cooling systems,

b. Two independent pressurization fans, and

c. One charcoal absorber and HEPA filter train.

APPLICABILITY: ALL MODES.

ACTION:

MODES 1, 2, 3, and 4:

With one heating and cooling system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one pressurization fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With the filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT,STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . P MODES 5 and 6:

d. With one pressurization fan inoperable, do one of the following: (1) restore the inoperable fan to OPERABLE status within 7 days, or (2) initiate and maintain operation of the remaining OPERABLE pressurization fan and the filter train in a recirculation mode, or (3) suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

e. With any of the following (1) both heating and cooling systems; (2) both pressurization fans;,(3) the filter train> inoperable, suspend all operations involving CORE ALTERATIONS or positive 'reactivity changes.

SURVEILLANCE RE UIREMENTS 4.7.5.1 The control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by 0

verifying that the control room air temperature is < 120 F.

D. C. COOK - UNIT 2 3/4 7-14 Amendment No.

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

b. At least once per 31 days on a STAGGERED TEST BASIS by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the system operates for at least 15 minutes.

co At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release xn any ventilation zone com-municating with the system by:

1. Verifying that the charcoal adsorbers remove > 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of

, 6000 cfm + 10%.

2. Verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI

.N510-1975 while operating the ventilation system at a flow rate of 6000 cfm + 10%.

3. Verifying within 31 days after removal that a laboratory analysis of a carbon sample from either at least one test canister or at least two carbon samples removed from one of the charcoal adsorbers demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130 C, 95% R.H.).

The carbon samples not obtained from test canisters shall be prepared by either:

a) Emptying one entire bed from a removed adsorber tray mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

4. Verifying a.system flow rate of 6000 cfm + 10% during system operation when tested in accordance with ANSI N510-1975.

d. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by either:

D. C. COOK UNIT 2 3/4 7-15 Amendment. No.

PLANT SYSTEMS 3/4. 7. 5 CONTROL ROOM EMERGENCY VENTILATION SYSTEM LZMITING CONDITION FOR OPERATION 3.7.5.1 The control room emergency ventilation system shall be OPERABLE with:

ao Two independent heating and cooling systems,

b. Two independent pressurization fans, and c~ One charcoal absorber and HEPA filter train.

APPLICABILITY: ALL MODES.

ACTION:

MODES 1, 2, 3, and 4:

a. With one heating and. cooling system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one pressurization fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With the filter train inoperable, restore the filter train to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours.

MODES 5 and 6:

d. With one pressurization fan inoperable, do one of the following: (1) restore the inoperable fan to OPERABLE status within 7 days, or (2) initiate and maintain operation of the remaining OPERABLE pressurization fan and the filter train in a recirculation mode, or (3) suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

e. .With, any of the following (1) both heating and cooling systems; (2) both pressurization fans; (3) the filter train; inoperable',. suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE UIREMENTS ~

4.7.5.1 The control room emergency ventilation system shall be demonstrated OPERABLE:

a. At least once pea'2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0 by verifying that the control room air temperature is < 120 F.

D. C. COOK UNIT 1 3/4 7-19 Amendment No.

ML17334A533

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