ML17326B525

Proposed Tech Specs,Reducing Fire Watch Burden at Plant

ML17326B525
Person / Time
Site:	Cook
Issue date:	02/06/1989
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326B524	List: ML17326B523 ML17326B525
References
NUDOCS 8902130023
Download: ML17326B525 (104)

Text

ATTACHMEiVT 2 TO AEP:NRC;0692BO PROPOSED REVISED TECHNICAL SPECIFICATION PAGES 8702i30023 390206 PDR ADOCK 050003i5 P

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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION SYSTEMS DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.7 Fire detection systems for each fire detection zone shown in Table 3.3-10A through 3.3-10D shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection system(s) is required to be OPERABLE.

ACTION:

When the number of inoperable fire detector(s) is greater than the maximum number of inoperable detectors per zone required by Table 3.3-10A through 3.3-10D:

a. For Table 3.3-10A, within 1 hour: 1) verify that the wet pipe or dry pilot preaction fire suppression system for the affected area is OPERABLE per Specification 4.7.9.2, or (2) establish a fire awatch patrol to inspect the affected area once per hour.

b. For Table 3.3-10B, within 1 hour: 1) verify that the other cross zoned detection circuit is OPERABLE, or 2) establish a fire watch patrol to insp'ect the affected area once per hour.

For Table 3.3-10C, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the affected area or fi,ltration unit once per hour.

d. For Table 3.3-10D, within 1 hour: 1) establish a fire watch patrol to inspect the containment once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2) monitor the containment air temperatures at least once per hour at the locations listed in Specification 4.6.1.5, or 3) view the areas visible to closed circuit television at least once per hour.

The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-51 AMENDMENT NO.

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INSTRUMENTATION SURVEILLANCE RE UIREMENTS 4.3.3.7 The fire detection system for each fire detection zone shown in Tables 3.3-10A through 3.3-10D shall be demonstrated OPERABLE as follows.

4.3.3.7.1 Each of the detectors in the above required fire detection systems which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

4.3.3.7.2 The supervised detector alarm circuits for the above required fire detection systems shall be demonstrated OPERABLE at least once per 6 months. The supervised detector alarm circuits include the detector circuits, fire and trouble alarm circuits from the remote fire protection control panel to the Control Room emergency fire control panel, and audible fire and,trouble alarm circuits.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-52 AMENDMENT NO.

TABLE 3.3-10A FIRE DETECTION SYSTEMS SINGLE ZONE FIRE DETECTION SYSTEMS IN AREAS CONTAINING WATER SUPPRESSION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical

l. Auxiliary Building

a. Elevation 587 ft.* 27

b. Elevation 609 ft.* 20

c. Elevation 633 ft.* 21

2. Turbine Building

a. Aux. Feed Water Pump Vestibule*

b. Diesel Generator Ramp/

Corridor

• System protects area common to both Units 1 and 2.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-53 AMENDMENT NO.

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TABLE 3.3-10B FIRE DETECTION SYSTEMS CROSS-ZONED DETECTION SYSTEMS 1 S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical

1. Auxiliary Building

a. 4KV Switchgear (AB)

b. Engineered Safety System Switchgear and Transformer Room

c. CRD, Transformer and Switchgear, Inverter and AB Battery Rooms

2. Cable Tunnels

a. Quadrant 1 Cable Tunnel

b. Quadrant 2 Cable Tunnel C. Quadrant 3N Cable Tunnel

d. Quadrant 3M Cable Tunnel

e. Quadrant 3S Cable Tunnel

f. Quadrant 4 Cable Tunnel

3. Cable Spreading Rooms

a. Switchgear Cable Vault (Circuit No. 23)

(Circuit No 24)

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b. Control Room Cable Vault (Circuit No. 17) 16 (Circuit No. 18) 16 Diesel Generator Rooms

a. Diesel Generator Room 1AB

b. Diesel Generator Room 1CD (1) Both detection circuits are required for actuation of the fire suppression system.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-53a AMENDMENT NO.

TABLE 3.3-10C FIRE DETECTION SYSTEMS MISCELLANEOUS SINGLE ZONE DETECTION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical

1. Auxiliary Building

a. Elevation 573 ft.*

b. East Main Steam Valve 14 Enclosure

c. Main Steam Line Area El. 612 ft. (Around Containment)

d. NESW Valve Area El. 612 ft.

e. Elevation 650 ft.* 17

2. -

Auxiliary Cable Vault (2)

3. Control Room (Includes Detectors 23 Above Suspended Ceiling)

4. Charcoal Filter Ventilation Units (3)

a. 1-HV-AES-1 None Charcoal Filters

b. 1-HV-AES-2 None Charcoal Filters

c. 1-HV-ACRF None Charcoal Filters d, 1-HV-CIPX None Charcoal Filters

• System protects area common to both Units 1 and 2.

(2) Detection circuit is required for actuation of the fire suppression system.

(3) The Water Spray System for the charcoal filters are manually actuated.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-53b AMENDMENT NO.

TABLE 3.3-10C (Con't)

FIRE DETECTION SYSTEMS MISCELLANEOUS SINGLE ZONE DETECTION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical

4. Charcoal Filter Ventilation Units Con't

d. 1-HV-CPR Charcoal Filters None

e. 12-HV-AFX+ Charcoal Filter None

5. Screenhouse

a. ESW Basement Area Elevation 575 ft.*

b. ESW Pump and MCC Rooms Elevation 591 ft.

6. Pressurizer Heater Transformer Room, Elevation 591 ft.

7. RP Access Control and Chem. 12 Labs, Elevation 609 ft.

8. Diesel Fuel Oil Transfer Pump None Room

9. New Fuel Storage Room*

>System protects area common to both Units 1 and 2.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-53c AMENDMENT NO.

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TABLE 3.3-10D FIRE DETECTION SYSTEMS DETECTION SYSTEMS INSIDE CONTAINMENT 4 S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical Ionization

1. Inside Containment

a. Quadrant 1 - Cable Trays (5)

b. Quadrant 2 - Cable Trays (5)

c. Quadrant 3 - Cable Trays (5) 10

d. Quadrant 4 - Cable Trays (5)

e. Reactor Coolant Pump No. 1 None

f. Reactor Coolant Pump No. 2 None

g. Reactor Coolant Pump No. 3 None

h. Reactor Coolant Pump No. 4 None (4) The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate tests.

(5) Thermistors located in cable trays are assigned to a quadrant based on the location of the thermistor circuit start point.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-53d AMENDMENT NO ~

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'NSTRUMENTATION BASES 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION SYSTEMS DETECTORS OPERABILITY of the fire detection systems/detectors ensures that adequate detection 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 the fires will reduce the potential for damage to safety related systems or components in the areas of the specified systems and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection system is inoperable, Actions a through e maintain the facility's fire protection program and allows for continued operation of the facility until the inoperable system(s)/detector(s) are restored to OPERABILITY. However, is not our intent to rely upon the compensatory action for an extended it period of time and action will be taken to restore the minimum number of detectors to OPERABLE status within a reasonable period.

In some cases, the local wet type fire suppression system, or preaction sprinkler system actuation/supervisory air (pneumatic detection system) is used as an alternative to the fire detection system in lieu of a fire watch. In these cases, the wet type suppression or the preaction actuation/supervisory air will serve as the early warning detection of a fire and alert the appropriate Control Room of a problem in the area.

For those areas with cross-zone fire detection, the remaining operable fire detection string will serve as adequate fire detection in lieu of a fire watch until the inoperable fire detection string can be returned to service.

3/4.3.3.8 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available 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 refueling outage to begin in February 1989.

Amendment 112 (Effective before startup following refueling outage currently scheduled in 2/89.)

COOK NUCLEAR PLANT - UNIT 1 B 3/4 3-4 AMENDMENT NO.

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PLANT SYSTEMS 3 4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.1 The fire suppression ~ater system shall be OPERABLE with:

a. Two* high demand 2000'PM pumps, one of which shall be a diesel driven pump, with their discharge aligned to the fire suppression header.

An OPERABLE open flow path capable of taking suction from Lake Michigan and transferring the water through distribution piping (with OPERABLE sectionalizing valves) up to the yard hydrant curb control valves and up to the hose station valve(s) or water suppression system controlling valve(s) required to be OPERABLE per Specifications 3.7.9.5 and 3.7.9.2, respectively.

APPLICABILITY: At all times.

ACTION:

With only one pump OPERABLE, restore an inoperable pump (diesel, if required), and equipment to OPERABLE status within 7 days or establish a backup fire suppression water system within the next 7 days.

b. With the fire suppression water system otherwise inoperable:

1. Restore the fire suppression water distribution system 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

2. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. The provisions of Specifications applicable.

3 '.3 and 3.0.4 are not

• Shared system with D AC. Cook - Unit 2 COOK NUCLEAR PLANT - UNIT 1 3/4 7-41 AMENDMENT NO.

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS 4.7.9.1.1 The fire suppression water system shall be demonstrated OPERABLE:

At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it for at least 15 minutes on recirculation flow.

At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c ~ At least once per 6 months by performance of a system flush of above ground internal distribution headers and fire hydrants.

At least once per 12 months by cycling each testable valve in the flow path through at. least one complete cycle of full travel.

At least once per 18 months by performing a system functional test which includes:

1. .Verifying that each automatic valve in the'low path actuates to its correct position,

2. Verifying that each pump develops a flow of at least 2000.,

gpm at a system head of at least 300 feet of water,

3. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and

4. Verifying that each high pressure pump starts in its sequence to maintain the fire suppression water 'replanned system pressure greater than or equal to 100 psig.

At least once per 3 years by performing a series of flow tests so that every fire main segment (excluding individual system supplies) has been verified to be clear of obstructions by a full flow test.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-42 AMENDMENT NO.

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.9.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:

1. The fuel storage tank contains at least 160 gallons of fuel, and

2. The diesel starts from ambient conditions and operates for at least 30 minutes.

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM D4057-81 is within the acceptable limits specified in Table 1 of ASTM-D975-81 when checked for viscosity, water, and sediment.

At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

4.7.9.1.3 The fire pump diesel starting battery bank and charger shall be demonstrated OPERABLE:

a ~ At least once per 7 days by verifying that:

1. The electrolyte level of each battery is above the plates, and The output battery voltage of each bank is greater than 24 volts.

b. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of each battery.

C. At least once per 18 months by verifying that:

1. The batteries, cell plates and battery packs show no visual indication of physical damage or abnormal deterioration, and

2. The battery-to-battery and terminal connections are clean, tight, free of corrosion, and coated with anti-corrosion material.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-43 AMENDMENT NO.

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'PLANT SYSTEMS SPRAY AND OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The spray and/or sprinkler systems located in the areas shown in Tables 3.7-5A and 3.7-58 shall be OPERABLE: I APPLICABILITY: Whenever equipment in the spray/sprinkler protected area is required to be OPERABLE.

ACTION:

a. With one or more of the water spray systems as listed in Table 3.7-5A inoperable, within 1 hour: 1) verify that the detection system for the affected filtration unit is OPERABLE per Specification 4.3.3.7, or 2) establish a continuous fire watch patrol.*

b. With one or more of the sprinkler systems as listed in Table

3. 7-5B inoperable, within 1 hour: 1) verify that at least one of the detection systems, where provided, (electric per Specification 4.3.3.7 or pneumatic per Table 3.7-5B) for the affected area is OPERABLE, or 2) establish a continuous fire watch patrol.*

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

• For high radiation areas, periodic monitoring (and hourly logging) of the closed circuit television coverage is an acceptable substitute'or the fire watch patrol. For high radiation areas where closed circuit television coverage does not exist, an hourly fire watch patrol will be instituted.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-44 AMENDMENT NO,

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7.9.2 Each of the above required water spray and/or sprinkler systems shall be demonstrated to be OPERABLE:

a. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel as provided by Technical Specification 4.7.9.1.1.d.

b. At least once per 18 months:*

1. By performing a system functional test which includes simulated automatic actuation of the system, and:

a) Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b) Cycling each valve in the flow path 'that is not testable during plant operation through at least one complete cycle of full travel.

2. By visual inspection of deluge and preaction system piping (this is not required for systems supervised by air) to verify their integrity.

By visual inspection of each open head deluge nozzle to verify that there is no blockage.

C. At least once per 3 years by performing an air flow test through the piping of each open head deluge system and verifying each open head deluge nozzle is unobstructed.

• The provisions of Specification 4.0.6 are applicable.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-45 AMENDMENT NO.

TABLE 3.7-5 A OPEN HEAD DELUGE WATER SPRAY SYSTEMS LOCATION ACTUATION 1-HV-AES-1 Charcoal Filters Manual - Electric - Heat 1-HV-AES-2 Charcoal Filters Manual - Electric - Heat 1-HV-ACRF-1 Charcoal Filters Manual - Electric - Heat 1-HV-CPR-1 Charcoal Filters Manual - Electric - Heat 12-HV-AFX Charcoal Filters* Manual - Electric - Heat 1-HV-CIPX Charcoal Filters Manual - Electric - Heat

• Shared system with Unit 2.-

COOK NUCLEAR PLANT - UNIT 1 3/4 7-46 AMENDMENT NO.

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TABLE 3.7-5 B CLOSED HEAD SPRINKLER SYSTEMS LOCATION TYPE SYSTEM ACTUATION Auxiliary building Preaction Sprinkler Dry Pilot**

El. 587 ft.*/***(Normally accessible areas, charging and Safety Injection Pump Rooms, stairways to El. 573 and 609)"

Auxiliary building Preaction Sprinkler Dry Pilot**

El. 609 ft.*/***(Normally accessible areas, CCW Pump area, stairways to El. 633 and 620 above Chem. Lab)

Auxiliary building Preaction Sprinkler Dry Pilot**

El. 633 ft.*/***(Normally accessible areas, excluding HVAC Vestibule Areas and stairways to El. 650)

Auxiliary Feedwater Pump Wet Pipe Automatic Corridor*/***

Turbine Building El. 591 Wet Pipe Automatic Generator End (Extended to Diesel Generator Corridor***)

Auxiliary Building Cask Preaction Sprinkler Dry Pilot**

Handling Area (El. 609)+/***

Auxiliary Building Drumming Preaction Sprinkler Dry Pilot**

Room (El. 587)*/***

Reactor Coolant Pumps (4)*** Preaction Sprinkler Manual Contractors Access Control Wet Pipe Automatic Building (El. 612)

• System protects area common to both Units 1 and 2.

• • Dry Pilot Actuation is considered to be a heat actuated pneumatic type detection system.

~*~Located in areas which also have an automatic detection system.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-47 AMENDMENT NO.

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PLANT SYSTEMS LOW PRESSURE CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.3 The low pressure C02 systems located in the areas shown in Table 3.7-6 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the low pressure C02 protected areas is required to be OPERABLE.

ACTION:

With one or more of the required low pressure CO systems isolated from automatic operation for personnel protection, verify that at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.7 in order to permit entry for routine tours, maintenance, construction, or surveillance testing.

b. With one or more of the required CO systems shown in Table 3.7-6 inoperable, within 1 hour: 1) verify at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.7, and establish a fire watch patrol to inspect the affected fire area once per hour, or 2) Establish a continuous fire watch to patrol the affected area.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.3 Each of the above required low pressure C02 systems shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the C02 storage tank level to be greater than or equal to 50% and pressure to be greater than or equal to 285 psig, and

b. At least once per 31 days by verifying that each manual valve in the flow path is in the correct position.

c. At least once per 18 months by verifying:

The systems valves, associated ventilation dampers and fans, and self-closing fire doors operate automatically upon receipt of a simulated actuation signal, and System actuation methods (automatic from detection system, manual pushbutton station, manual pneumatic release) are tested to verify proper actuation of the system.

3. Flow from each nozzle during performance of an airflow or CO "Puff Test".

COOK NUCLEAR PLANZ - UNIT 1 3/4 7-48 AMENDMENT NO.

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TABLE 3.7-6 LOW PRESSURE CARBON DIOXIDE SYSTEMS 17 TON CAPACITY LOCATION ACTUATION METHOD Diesel Generator 1AB Room Cross-zoned Heat Diesel Generator 1CD Room Cross-zoned Heat Diesel Generator Fuel Oil Pump Room Heat 4KV Switchgear Rooms Manual Control Rod Drive, Transf. Switchgear Rooms Manual Engineered Safety Switchgear Room Manual Switchgear Room Cable Vault Cross-zoned

. Ionization and Infrared Auxiliary Cable Vault Ionization Control Room Cable Vault (Backup)* Manual Penetration Cable Tunnel Quadrant 1 Manual Penetration Cable Tunnel Quadrant 2 Manual Penetration Cable Tunnel Quadrant 3N Manual Penetration Cable Tunnel Quadrant 3M Manual Penetration Cable Tunnel Quadrant 3S Manual Penetration Cable Tunnel Quadrant 4 Manual

• Control Room Cable Vault CO System is only required to be operable when the Cable Vault Halon System 2 is inoperable.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-49 AMENDMENT NO.

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PLANT SYSTEMS HALON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.4 The Halon system located in the Control Room Cable Vault shall be [

OPERABLE.

APPLICABILITY: Whenever equipment in the Halon protected area is required to be OPERABLE.

ACTION:

With the Halon System isolated from automatic operation for personnel protection, verify that at least one zone of fire detection for the affected area is OPERABLE in order to permit entry into the cable vault.

b. With the above required Halon system inoperable, within 1 hour:

1) verify that at least one zone of the fire detection system and the backup CO fire suppression system for the affected area are OPERABLE per 3pecifications 4.3.3.7 and 4.7.9.3 respectively, or

2) establish a continuous fire watch patrol.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.4 The above required Halon system shall be demonstrated OPERABLE:

At least once per 6 months by verifying each Halon storage tank to be greater than or equal to 95% of full charge weight or appropriate liquid level, and to be greater than or equal to 90%

of full charge pressure corrected for ambient temperature.

b. At least once per 18 months by:

1. Verifying the system (including associated ventilation dampers and fans, and doors) is tested for proper operation by a simulated actuation signal.

2. System actuation methods (automatic from detection system, manual pushbutton station, and manual cylinder actuator) are to be tested to verify proper actuation of the system.

3. Performance of an air flow test or C02 puff test through headers and nozzles to assure that there is no blockage.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-50 AMENDMENT NO.

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PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.9.5 The fire hose stations shown in Table 3.7-7 shall be OPERABLE:

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

With one or more of the fire hose stations shown in Table 3.7-7 inoperable: 1) For those areas where the inoperable fire hose station is the primary means of fire suppression (areas where no fixed systems are provided or areas where the fixed systems are inoperable), within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, route an additional equivalent capacity fire hose to the affected area(s), from an OPERABLE hose.

station(s) per Specification 4.7.9.5, or 2) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify that the fixed fire suppression system(s) that also protects the affected area(s) serviced by the fire hose station(s) is OPERABLE.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.5 Each of the fire hose stations shown in Table 3.7-7 shall be demonstrated OPERABLE:

a. At least once per 31 days by a visual inspection of the fire hose stations to assure all required equipment is at the station.

b. At least once per 18 months by:

1. Removing the hose for visual inspection and re-racking, and

2. Replacement of all degraded gaskets in couplings.

C. At least once per 3 years by:

Partially opening each hose station valve to verify OPERABILITY and no flow blockage.

2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psi greater than the maximum pressure available at that hose station, whichever is greater.

COOK NUCLEAR PLANT - UNlT 1 3/4 7-51 AMENDMENT NO.

TABLE 3.7-7 FIRE HOSE STATIONS Auxiliary Building** Minimum 12*

Access to Diesel Generator Rooms Hose Station No. 32 Access to Switchgear Rooms Hose Station No. 58 or No. 211 Access to Control Room Hose Station No. 82 or No. 81 Access to Pressurizer Heater Transformer Hose Station No. 31 Room Access to ESW Pump Rooms, MCC Room, and Hose Station No. 23 ESW Basement Area Access to Auxiliary Feed Pump Rooms Hose Station No. 35

• Shared with Unit 2

• • Within the Controlled Area COOK NUCLEAR PLANT - UNIT 1 3/4 7-52 AMENDMENT NO.

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PLANT SYSTEMS 3 4.7.10 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.10 Fire rated assemblies shall be OPERABLE as follows:

a. All fire rated assemblies (walls, floor/ceilings, and cable tray and conduit enclosures), separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area shall be OPERABLE.

b. All penetration sealing devices (fire door assemblies, fire dampers, and penetration seals for cable, around conduit, cable tray, piping and ventilation ductwork) in the above fire rated assemblies shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

With any of the above fire rated assemblies and/or sealing devices inoperable, within 1 hour: 1) verify that the fire detectors and/or fire suppression system on at least one side of the inoperable assembly are OPERABLE, or 2) establish a continuous fire watch patrol on one side of the penetration, or

3) secure the inoperable sealing device* in the closed position, and establish an hourly fire watch, or (4) for fire dampers and normally locked fire doors, secure the inoperable sealing device in the closed position.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.10.1 At least once'per 18 months the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by:

a. Performing a visual inspection of all accessible surfaces, of each fire rated assembly, for open penetrations.

b. Performing a visual inspection of each fire damper and its associated hardware.

c. Performing a Functional Test, requiring closure testing on 10% of the fire dampers.**

• Except fire doors on Turbine Driven Auxiliary Feedwater Pump and Hallway enclosures which must remain open due to HELB considerations.

• • This testing is in addition to the testing required by Specifications 4.7.9.3.c.l and 4.7.9.4.b.l.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-53 AMENDMENT NO.

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Con't

d. Performing a visual inspection of at least 10 percent of each type of penetration seal (cable, around conduit, cable tray, piping, and ventilation duct work penetration seals; and cable tray and conduit enclosures required for Appendix R compliance).

If apparent changes in appearance or abnormal degradations are found that could indicate a plant wide trend, a visual inspection of an additional 10 percent of each type of penetration seal shall be made. This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or abnormal degradation is found.

4.7.10.2 Each of the required fire doors shall be verified OPERABLE by:

a. Inspecting the hold-open, release, and closing mechanism and latches at least once per 6 months.

b. Verifying the position of each closed fire door at least once per 24 hours.

c. Verifying that doors with hold-open and release mechanisms are )

free of obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. Verifying the position of each locked closed fire door at least once per 7 days.

4.7.10.3 Following repairs or maintenance on an above required fire rated assembly or sealing device, the fire rated assembly or sealing device shall be verified to be operable before exiting the applicable action statement.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-54 AMENDMENT NO.

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BASES 3 4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression systems consists of the water system, spray and/or sprinklers, C02, Halon, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire protection program.

In the event that one or more C02 Suppression System requiring automatic actuation must be isolated for personal protection to permit entry for routine tours, maintenance, construction, or surveillance testing in the protected area, the fire detection system(s) required to be operable by Specification 3.3.3.7 shall be verified to be operable. Isolation of an automatic C02 suppression system temporarily puts this system in a manual actuation mode.

Reliance on the fire detection system, in conjunction with the ability to manually discharge the C02 suppression system will provide adequate fire protection for periods when personnel are required to work in these areas.

In the event that portions of the fire protection systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than equipment is the primary means of fire suppression.

if the inoperable Backup fire protection equipment will normally take the form of permanently mounted fire extinguishers and/or fire hose stations in or near the area, or fire hoses routed to the affected area. However, it is not our intent to rely on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire suppression system to OPERABLE status within a reasonable period.

The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met. An allowance is made for ensuring a sufficient volume of Halon and C02 in the storage tanks by verifying either the weight, level, or pressure of the tanks.

In the event the fire suppression water becomes inoperable, corrective measures must be taken since this system provides the major fire suppression capability of the plant. The corrective measures, including verification of fire detection operability, or roving fire watches, or alternate/backup suppression equipment, or systems, shall provide adequate fire suppression capability for the continued protection of the nuclear plant.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-7 AMENDMENT NO.

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~34.7. 9 Con't The purpose of the charcoal filter fire suppression Technical Specification is to account for detection and suppression of fires in the charcoal filters. Manual operation of these systems is allowed because two-point heat detection with control room and local annunciation of trouble conditions is provided for the charcoal filters. The OPERABILITY of the fire suppression system protecting the charcoal filters is only required when there is charcoal in the filt'ers and the filters are required to be.

operable. Actuation of spray water onto the charcoal filters requires both the manual opening of the system isolation valve and reaching the high temperature alarm setpoint for the automatic opening of the system deluge valve.

Because of the inaccessibility of the lower containment to personnel during operation due to ALARA radiation exposure concerns, the use of one or more CCTVs in the lower containment to monitor for fire and smoke is an acceptable substitute to an hourly fire watch, system becomes inoperable.

if the fire suppression All hourly fire watch patrols are performed at intervals of sixty minutes with a margin of fifteen minutes.

A continuous fire watch requires that a trained individual be in the specified area at all times and that each fire zone within the specified area be patrolled at least once every fifteen minutes with a margin of five minutes.

A control valve is defined as a valve that when closed does not leave an alternate open flow path to a system. A sectionalizing valve is defined as a valve that when closed does not prevent an alternate open flow path to a system and hence does not make the fire suppression water system inoperable. Under certain situations, the closure of a sectionalizing valve followed by the closure of a second valve will not leave an open flow path to one of the specified systems. In this instance, Action Statement b of Specification 3.7.9.1 is applicable.

Manual actuation of C02 fire suppression systems provides adequate fire protection for the protected areas based on operable fire detection in the area, low combustible loadings, and prompt fire brigade response to alarms.

Many of the action statements take credit for operable fire detection in lieu of a fire watch when a fire protection system is inoperable. Operable fire detection provides sufficient early warning capability of a fire to the appropriate Control Room.

3 4.7.10 FIRE RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize the possibility of a single fire involving more than one fire area prior to COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-8 AMENDMENT NO.

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BASES

~34.7.10 Con' dete'ction and extinguishment. The fire barriers and fire barrier penetrations sealing are devices periodically inspected to verify their OPERABILITY. The functional testing of the fire dampers is provided to ensure that the dampers remain functional. The ventilation seals area seals around ventilation duct work penetrating fire barriers. It is not our intent to rely on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire rated assembly to OPERABLE status within a reasonable period.

For the purpose of determining OPERABILITY, an OPERABLE fire rated assembly and/or sealing device is one that is capable of performing its intended safety function.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-9 AMENDMENT NO.

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ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.'9.2 Special reports shall be submitted to the Regional Administrator within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference Specifications:

a. Inservice Inspection Program Review, Specification 4.4.10

b. ECCS Actuation, Specifications 3.5.2 and 3.5.3

c. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3

d. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4

e. Seismic Event Analysis, Specification 4.3.3.3.2

f. Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3

g. Deleted

h. Deleted COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO.

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INSTRUMENTATION FIRE DETECTION INSTRUMENTATION SYSTEMS DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.8 Fire detection systems for each fire detection zone shown in Table 3.3-11A through 3.3-11D shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection system(s) is required to be OPERABLE.

ACTION When the number of inoperable fire detector(s) is greater than the maximum number of inoperable detectors per zone required by Table 3.3-11A through 3.3-11D:

a. For Table 3.3-11A, within 1 hour: 1) verify that the wet pipe or dry pilot preaction fire suppression system for the affected area is OPERABLE per Specification 4.7.9.2, or (2) establish a fire watch patrol to inspect the affected area once per hour.

b. For Table 3.3-11B, within 1 hour: 1) verify that the other cross zoned detection circuit is operable, or 2) establish a fire watch patrol to inspect the affected area once per hour.

C. For Table 3.3-11C, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the affected area or filtration unit once per hour.

d. For Table 3. 3-11D, within 1 hour: 1) establish a fire watch patrol to inspect the containment once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2) monitor the containment air temperatures at least once per hour at the locations listed in Specification 4.6.1.5, or 3) view the areas visible to closed circuit television at least once per hour.

e. The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-50 AMENDMENT NO.

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INSTRUMENTATION SURVEILLANCE RE UIREMENTS 4.3.3.8 The fire detection system for each fire detection zone shown in Tables 3.3-11A through 3.3-11D shall be demonstrated OPERABLE as follows.

4.3.3.8.1 Each of the detectors in the above required fire detection systems which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

4.3.3.8.2 The supervised detector alarm circuits for the above required fire detection systems shall be demonstrated OPERABLE at least once per 6 months. The supervised detector alarm circuits include the detector circuits,.fire and trouble alarm circuits from the remote fire protection control panel to the Control Room emergency fire control panel, and audible fire and trouble alarm circuits.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-51 AMENDMENT NO.

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TABLE 3.3-11A FIRE DETECTION SYSTEHS SINGLE ZONE FIRE DETECTION SYSTEMS IN AREAS CONTAINING WATER SUPPRESSION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical

1. Auxiliary Building

a. Elevation 587 ft.* 27

b. Elevation 609 ft.* 20

c. Elevation 633 ft.* 21

2. Turbine Building a ~ Aux. Feed Water Pump Vestibule*

b. Diesel Generator Ramp/

Corridor

• System protects area common to both Units 1 and 2.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-52 AMENDMENT NO.

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TABLE 3.3-11B FIRE DETECTION SYSTEMS CROSS-ZONED DETECTION SYSTEMS 1 S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical Ionization

1. Auxiliary Building

a. 4KV Switchgear (AB)

b. Engineered Safety System Switchgear and Transformer Room CRD, Transformer and Switchgear, Inverter and AB Battery Rooms

2. Cable Tunnels

a. Quadrant 1 Cable Tunnel

b. Quadrant 2 Cable Tunnel C. Quadrant 3N Cable Tunnel

d. Quadrant 3M Cable Tunnel

e. Quadrant 3S Cable Tunnel Quadrant 4 Cable Tunnel

3. Cable Spreading Rooms

a. Switchgear Cable Vault (Circuit No. 27)

(Circuit No. 28)

b. Control Room Cable Vault (Circuit No. 12) 19 (Circuit No. 13) 19 Diesel Generator Rooms

a. Diesel Generator Room 2AB

b. Diesel Generator Room 2CD (1) Both detection circuits are required for actuation of the fire suppression system.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-52a AMENDMENT NO.

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TABLE 3.3-11C FIRE DETECTION SYSTEMS MISCELLANEOUS SINGLE ZONE DETECTION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical

l. Auxiliary Building

a. Elevation 573 ft.*

b. East Main Steam Valve Enclosure

c. Main Steam Line Area 6 El. 612 ft. (Around Containment)

d. NESW Valve Area 1 El. 612 ft.

e. Elevation 650 ft.* 17

2. Auxiliary Cable Vault (2)

3. Control Room (Includes Detectors 21 Above Suspended Ceiling)

4. Charcoal Filter Ventilation Uni.ts (3),

a. 2-HV-AES-1 None Charcoal Filters

b. 2-HV-AES-2 None Charcoal Filters

c. 2-HV-ACRF None Charcoal Filters

d. 2-HV-CIPX None Charcoal Filters

• System protects area common to both Units 1 and 2.

(2) Detection circuit is required for actuation of the fire suppression system.

(3) The Water Spray System for the charcoal filters are manually actuated.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-52b AMENDMENT NO.

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TABLE 3.3-11C FIRE DETECTION SYSTEMS MISCELLANEOUS SINGLE ZONE DETECTION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical Ionization

=4. Charcoal Filter Ventilation Units Con't

d. 2-HV-CPR Charcoal Filters None

e. 12-HV-AFX+ Charcoal Filters None

5. Screenhouse

a. ESW Basement Area Elevation 575 ft.*

b. ESW Pump and MCC Rooms Elevation 591 ft.

6. Pressurizer Heater Transformer Room, Elevation 591 ft.

7. Diesel Fuel Oil Transfer Pump Room None rl

8. New Fuel Storage Room+

• System protects area common to both Units 1 and 2.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-52c AMENDMENT NO.

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TABLE 3.3-11C FIRE DETECTION SYSTEMS MISCELLANEOUS SINGLE ZONE DETECTION SYSTEMS S stem Location Maximum Ino erable Detectors Zone Smoke Heat Optical Ionization

1. Inside Containment

a. Quadrant 1 - Cable Trays (5)

b. Quadrant 2 - Cable Trays (5)

c. Quadrant 3 - Cable Trays (5) 15

d. Quadrant 4 - Cable Trays (5)

e. Reactor Coolant Pump No. 1 None

f. Reactor Coolant Pump No. 2 None

g. Reactor Coolant Pump No. 3 None

h. Reactor Coolant Pump No. 4 None (4) The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate tests.

(5) Thermistors located in cable trays are assigned to a quadrant based on the location of the .thermistor circuit start point.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-52d AMENDMENT NO.

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3 4.3 INSTRUMENTATION BASES 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION SYSTEMS DETECTORS OPERABILITY of the fire detection systems/detectors ensures that adequate detection 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 the fires will reduce the potential for damage to safety related systems or components in the areas of the specified systems and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection system is inoperable, Actions a through e maintain the facility's fire protection program and allows for continued operation of the facility until the inoperable system(s)/detector(s) are restored to OPERABILITY.

However, it is not our intent to rely upon the compensatory action for an extended period of time and action will be taken to restore the minimum number of detectors to OPERABLE status within a reasonable period.

In some cases, the local wet type fire suppression system, or preaction sprinkler system actuation/supervisory air (pneumatic detection system) is used as an alternative to the fire detection system in lieu of a fire watch. In these cases, the wet type suppression or, the preaction actuation/supervisory air will serve as the early warning detection of a fire and alert the appropriate Control Room of a problem in the area.

For those areas with cross zone fire detection, the remaining operable fire detection string will serve as adequate fire detection in lieu of a fire watch until the inoperable fire detection string can be returned to service.

3/4.3.3.9 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 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. 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.

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

i'~ 4 ik'P 3 4.3 INSTRUMENTATION BASES 3/4.3.3.10 RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive effluent gaseous 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 OCDM 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.

3/4.3.4 TURBINE OVERSPEED PROTECTION 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.

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

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PLANT SYSTEMS 3 4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.1 The fire suppression water system shall be OPERABLE with:

a. Two* high demand 2000 GPM pumps, one of which shall be a diesel driven pump, with their discharge aligned to the fire suppression header.

b. An OPERABLE open flow path capable of taking suction from Lake Michigan and transferring the water through distribution piping (with OPERABLE sectionalizing valves) up to the yard hydrant curb control valves and up to the hose station valve(s) or water suppression system controlling valve(s) required to be OPERABLE per Specifications 3.7.9.5 and 3.7.9.2, respectively.

APPLICABILITY: At all times.

ACTION:

With only one pump operable, restore an inoperable pump (diesel, if required), and equipment to OPERABLE status within 7 days or establish a backup fire suppression water system within the next 7 days.

b. With the fire suppression water system otherwise inoperable:

1. Restore the fire suppression water distribution system 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

2. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c ~ The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

• Shared system with D. C. Cook - Unit 1 COOK NUCLEAR PLANT - UNIT 2 3/4 7-36 AMENDMENT NO.

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS 4.7.9.1.1 The fire suppression water system shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it for at least 15 minutes on recirculation flow.

b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

c. At least once per 6 months by performance of a system flush of above ground internal distribution headers and fire hydrants.

d. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

e. At least once per 18 months by performing a system functional test which includes:

1. Verifying that each automatic valve in the flow path actuates to its correct position,

2. Verifying that each pump develops a flow of at least 2000 gpm at a system head of at least 300 feet of water,

3. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and

4. Verifying that each high pressure pump starts in its prepl'armed sequence to maintain the fire suppression water system pressure greater than 100 psig.

f. At least once per 3 years by performing a series of flow tests so that every fire main segment (excluding individual system supplies) has been verified to be clear of obstructions by a full flow test.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-37 AMENDMENT NO ~

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I PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.7 '.1.2 The fire pump diesel engine shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying:

1. The fuel storage tank contains at least 160 gallons of fuel, and

2. The diesel starts from ambient conditions and operates for at least 30 minutes.

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank obtained in accordance with ASTM-D4057-81 is within the acceptable limits specified in Table 1 of ASTM-D975-81 when checked for viscosity, water, and sediment.

At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.

4.7.9.1.3 The fire pump'iesel starting battery bank and charger shall be demonstrated OPERABLE:

a." At least once per 7 days by verifying that:

1. The electrolyte level of each battery is above the plates, and

2. The output battery voltage of each bank is greater than 24 l volts.

b. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of each battery.

C. At least once per 18 months by verifying that:

1. The batteries, cell plates and battery packs show no visual indication of physical damage or abnormal deterioration, and

2. The battery-to-battery and terminal connections are clean, tight, free of corrosion, and coated with anti-corrosion material.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-38 AMENDMENT NO.

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PLANT SYSTEMS SPRAY AND OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The spray and/or sprinkler systems located in the areas shown in Tables 3.7-5A and 3.7-5B shall be OPERABLE:

APPLICABILITY: Whenever equipment in the spray/sprinkler protected area is required to be OPERABLE.

ACTION:

a ~ With one or more of the water spray systems as listed in Table 3.7-5A inoperable, within 1 hour: 1) verify that the detection system for the affected filtration unit is OPERABLE per Specification 4.3.3.8, or 2) establish'a continuous fire watch patrol.*

With one or more of the sprinkler systems as listed in Table 3.7-5B inoperable, within 1 hour: 1) verify that at least one of the detection systems, where provided (electric per Specification 4.3.3.7 or pneumatic per Table 3.7-5B) for the affected area is OPERABLE, or 2) establish a continuous fire watch patrol.*

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

• For high radiation areas, periodic monitoring (and hourly logging) of the closed circuit television coverage is an acceptable substitute for the fire watch patrol. For high radiation areas where closed circuit television coverage does not exist, an hourly fire watch patrol will be instituted.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-39 AMENDMENT NO.

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4;7 '.2 Each of the above required water spray and/or sprinkler systems shall be demonstrated to be OPERABLE:

a ~ At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel as provided by Technical Specification 4.7.9.1.1.d.

b. At least once per 18 months:*

1. By performing a system functional test which includes simulated automatic actuation of the system, and:

a) Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

2. By visual inspection of deluge and preaction system piping (this is not required for systems supervised by air) to verify their integrity.

3. By visual inspection of each open head deluge nozzle to verify that there is no blockage.

At least once per 3 years by performing an air flow test through the piping of each open head deluge system and verifying each open head deluge nozzle is unobstructed.

• The provisions of Specification 4.0.6 are applicable.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-40 AMENDMENT NO.

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TABLE 3.7-5 A OPEN HEAD DELUGE WATER SPRAY SYSTEMS LOCATION ACTUATION 2-HV-AES-1 Charcoal Filters Manual - Electric - Heat 2-HV-AES-2 Charcoal Filters Manual - Electric - Heat 2-HV-ACRF-1 Charcoal Filters Manual - Electric - Heat 2-HV-CPR-1 Charcoal Filters Manual - Electric - Heat 2-HV-CIPX Charcoal Filters Manual - Electric - Heat 12-HV-AFX Charcoal Filters* Manual - Electric - Heat

• Shared system with Unit 1.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-41 AMENDMENT NO.

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TABLE 3.7-5 B CLOSED HEAD SPRINKLER SYSTEMS LOCATION TYPE SYSTEM ACTUATION Auxiliary building Preaction Sprinkler Dry Pilot**

El. 587 ft.*/***(Normally accessible areas, charging and Safety Injection Pump Rooms, stairways to El.

573 and 609)

Auxiliary building Preaction Sprinkler Dry Pilot**

El. 609 ft.*/***(Normally accessible areas, CCW Pump area, stairways to El. 633)

Auxiliary building Preaction Sprinkler Dry Pilot**

El. 633 ft.*/***(Normally accessible areas, excluding HVAC Vestibule Areas and stairways to El. 650)

Auxiliary Turbine Driven Feedwater Pump and Wet Pipe Automatic Pump Corridor*/***

Turbine Building 591 ft. Wet Pipe Automatic El. Generator End (Extended to Diesel Generator Corridor***)

Auxiliary Building Cask Preaction Sprinkler Dry Pilot**

Handling Area (El. 609)

• /***

Auxiliary Building Drumming Preaction Sprinkler Dry Pilot**

Area (El. 587)*/***

Reactor Coolant Pumps (4)~* Preaction Sprinkler Manual

• System protects area common to both Units 1 and 2.

~*Dry Pilot Actuation is considered to be a heat actuated pneumatic type detection system.

• • • Located in areas which also have an automatic detection system.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-4la AMENDMENT NO.

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PLANT SYSTEMS LOW PRESSURE CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.3 The low pressure C02 systems located in the areas shown in Table 3.7-6 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the low pressure C02 protected areas is required to be OPERABLE.

ACTION:

With one or more of the required low pressure C02 systems isolated from automatic operation for personnel protection, verify that at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.8 in order to permit entry for routine tours, maintenance, construction, or surveillance testing.

b. With one or more of the required C02 systems shown in Table 3.7-6 inoperable, within 1 hour: 1) verify at least one zone of fire detection for the affected area is OPERABLE per Specification 4.3.3.8, and establish a fire watch patrol to inspect the affected fire area once per hour, or 2) Establish a continuous fire watch to patrol the affected area.

c. The provisions of Specifications 3.0.3 and 3.0 ' are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.3 Each of the above required low pressure C02 systems shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the C02 storage tank level to be greater than or equal to 50% and pressure to be greater than or equal to 285 psig, and

b. At least once per 31 days by verifying that each manual valve in the flow path is in the correct position.

c. At least once per 18 months by verifying:

1. The systems valves, associated ventilation dampers and fans, and .self-closing fire doors operate automatically upon receipt of a simulated actuation signal, and

2. System actuation methods (automatic from detection system, manual pushbutton station, manual pneumatic release) are tested to verify proper actuation of the system.

3. Flow from each nozzle during performance of an air flow or CO 2

"Puff Test".

COOK NUCLEAR PLANT - UNIT 2 3/4 7-42 AMENDMENT NO.

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TABLE 3.7-6 LOW PRESSURE CARBON DIOXIDE SYSTEMS 17 TON CAPACITY LOCATION ACTUATION METHOD Diesel Generator 2AB Room Cross-Zoned Heat Diesel Generator 2CD Room Cross-Zoned Heat Diesel Generator Fuel Oil Pump Room Heat 4KV Switchgear Rooms Manual Control Rod Drive, Transf. Switchgear Rooms Manual Engineered 'Safety Switchgear Room Manual Switchgear Room Cable Vault Cross-Zoned Ionization and Infrared Auxiliary Cable Vault 'Ionization Control Room Cable Vault (Backup)* Manual Penetration Cable Tunnel Quadrant 1 Manual Penetration Cable Tunnel Quadrant 2 Manual Penetration Cable Tunnel Quadrant 3N Manual Penetration Cable Tunnel Quadrant 3M Manual Penetration Cable Tunnel Quadrant 3S Manual Penetration Cable Tunnel Quadrant 4 Manual

• Control Room Cable Vault CO System is only required to be operable when the Cable Vault Halon System 2 is inoperable.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-43 AMENDMENT NO.

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PLANT SYSTEMS HALON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.4 The Halon system located in the Control Room Cable Vault shall be OPERABLE.

APPLICABILITY: Whenever equipment in the Halon protected area is required to be OPERABLE.

ACTION'ith the Halon System isolated from automatic operation for personnel protection, verify that at least one zone of fire detection for the affected area is OPERABLE in order to permit entry into the cable vault.

b. With the above required Halon system inoperable, within 1 hour:

1) verify that at least one zone of the fire detection system and the backup CO fire suppression system for the affected area are OPERABLE per )pecifications 4.3.3.8 and 4.7.9.3 respectively, or 2) establish a continuous fire watch patrol.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.4 The above required Halon system shall be demonstrated OPERABLE:

'a ~ At least once per 6 months by verifying each Halon storage tank to be greater than or equal to 95% of full charge weight or appropriate liquid level, and to be greater than or equal to 90%

of full charge pressure corrected for ambient temperature.

b. At least once per 18 months by:

1. Verifying the system (including associated ventilation dampers and fans, and doors) is tested for proper operation by a simulated actuation signal.

2. Syst'm actuation methods (automatic from detection system, manual pushbutton station, and manual cylinder actuator) are to be tested to verify proper actuation of the system.

3. Performance of an air flow test or C02 puff test through headers and nozzles to assure that there is no blockage.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-44 AMENDMENT NO.

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PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.9.5 The fire hose stations shown in Table 3.7-7 shall be OPERABLE:

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7-7 inoperable: 1) For those areas where the inoperable fire hose station is the primary means of fire suppression (areas where no fixed systems are provided or areas where the fixed systems are inoperable), within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, route an additional equivalent capacity fire hose to the affected area(s) from an OPERABLE hose station(s) per Specification 4.7.9.5, or 2) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, verify that the fixed fire suppression system(s) that also protects the affected area(s) serviced by the fire hose station(s) is OPERABLE.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.9.5 Each of the fire hose stations shown in Table 3.7-7 shall be demonstrated OPERABLE:

a ~ At least once per 31 days by a visual inspection of the fire hose stations to assure all required equipment is at the station.

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b. At least once per 18 months by:

1. Removing the hose for visual inspection and re-racking, and

2. Replacement of all degraded gaskets in couplings.

At least once per 3 years by:

Partially opening each hose station valve to verify OPERABILITY and no flow blockage.

2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psi greater than the maximum pressure available at that hose station, whichever is greater.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-45 AMENDMENT NO.

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TABLE 3.7-7 FIRE HOSE STATIONS Auxiliary Building** Minimum 12*

Access to Diesel Generator Rooms Hose Station No. 7 Access to Switchgear Rooms Hose Station No. 45 or No. 212 Access to Control Room Hose Station No. 65 or No. 81 Access to Pressurizer Heater Transformer Hose Station No. 12 Room Access to ESW Pump Rooms, MCC Room, and Hose Station No. 20 ESW Basement Area Access to Auxiliary Feed Pump Rooms Hose Station No. 9

• Shared with Unit 1

• • Within the Controlled Area COOK NUCLEAR PLANT - UNIT 2 3/4 7-46 AMENDMENT NO.

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I i I PLANT SYSTEMS 3 4.7.10 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.10 Fire rated assemblies shall be OPERABLE as follows:

a. All fire rated assemblies (walls, floor/ceilings, and cable tray and conduit enclosures), separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area shall be OPERABLE.

b. All penetration sealing devices (fire door assemblies, fire dampers, and penetration seals for cable, around conduit, cable tray, piping and ventilation ductwork) in the above fire rated assemblies shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

With any of the above fire rated assemblies and/or sealing devices inoperable, within 1 hour: 1) verify that the fire detectors and/or fire suppression system on at least one side of the inoperable assembly are OPERABLE, or 2) establish a continuous fire watch patrol on one side of the penetration, or

3) secure the inoperable sealing device* in the closed position, and establish an hourly fire watch, or (4) for fire dampers and normally locked fire doors, secure the inoperable sealing device in the closed position.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.10.1 At least once per 18 months the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE by:

a. Performing a visual inspection of all accessible surfaces, of each fire rated assembly, for open penetrations.

b. Performing a visual inspection of each fire damper and its associated hardware.

c. Performing a Functional Test, requiring closure testing of 10%

of the fire dampers.**

• Except fire doors on Turbine Driven Auxiliary Feedwater Pump and Hallway enclosures which must remain open due to HELB considerations.

• • This testing is in addition to the testing required by Specifications 4.7.9.3.c.l and 4.7.9.4.b.l.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-47 AMENDMENT NO.

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PLANT SYSTEMS SURVEILLANCE RE UIREMENTS Con'

d. Performing a visual inspection of at least 10 percent of each type of penetration seal (cable, around conduit, cable tray, piping, and'ventilation duct work penetration seals; and cable tray and conduit enclosures required for Appendix R compliance).

If apparent changes in appearance or abnormal degradations are found that could indicate a plant wide trend, a visual inspection of an additional 10 percent of each type of penetration seal shall be made. This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or abnormal degradation is found.

4.7.10.2 Each of the required fire doors shall be verified OPERABLE by:

a. Inspecting the hold-open, release, and closing mechanism and latches at least once per 6 months.

b. Verifying the position of each closed fire door at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. Verifying that doors with hold-open and release mechanisms are free of obstructions at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. Verifying the position of each locked closed fire door at least f once per 7 days.

4.7.10.3 Following repairs or maintenance on an above required fire rated assembly or sealing device, the fire rated assembly or sealing device shall be verified to be operable before exiting the applicable action statement.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-48 AMENDMENT NO.

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PLANT SYSTEMS BASES The service life of a snubber is evaluated via manufacturer's input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc...). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

The number of snubbers to be functionally tested during each surveillance is based on calculations performed to allow extension of the surveillance interval from 18 months to 24 months, and therefore, the number of snubbers functionally tested deviates from the number required by the Westinghouse Standard Technical Specifications (NUREG-0452, Revision 4).

3 4.7.8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

3 4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression systems consists of the water system, spray and/or sprinklers, C02, Halon, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In the event that one or more C02 Suppression System requiring automatic actuation must be isolated for personal protection to permit entry for routine tours, maintenance, construction, or surveillance testing in the protected area, the fire detection system(s) required to be operable by Specification 3.3.3.7 shall be verified to be operable. Isolation of an automatic C02 suppression system temporarily puts this system in a manual actuation mode. Reliance on the fire detection system, in conjunction with the ability to manually discharge the C02 suppression system will provide adequate fire protection for periods when personnel are required to work in these areas.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-6 AMENDMENT NO.

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~34 7 .9.Con' In the event. that portions of the fire protection systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service. When the inoperable fire fighting equipment is intended for use as a backup means of fire suppression, a longer period of time is allowed to provide an alternate means of fire fighting than equipment is the primary means if the inoperable of fire suppression. Backup fire protection equipment will normally take the form of permanently mounted fire extinguishers and/or fire hose stations in or near the area, or fire hoses routed to the affected area. However, it is not our intent to rely on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire suppression system to OPERABLE status within a reasonable period.

The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met. An allowance is made for ensuring a sufficient volume of Halon and C02 in the storage tanks by verifying either the weight, level, or pressure of the tanks.

In the event the fire suppression water becomes inoperable, corrective measures must be taken since this system provides the major fire suppression capability of the plant. The corrective measures, including verification of fire detection operability, or roving fire watches, or alternate/backup suppression equipment, or systems, shall provide adequate fire suppression capability for the continued protection of the nuclear plant.

The purpose of the charcoal filter fire suppression Technical Specification is to account for detection and suppression of fires in the charcoal filters. Manual operation of these systems is allowed because two-point heat detection with control room and local annunciation of trouble conditions is provided for the charcoal filters. The OPERABILITY of the fire suppression system protecting the charcoal filters is only required when there is charcoal in the filters and the filters are required to be operable. Actuation of spray water onto the charcoal filters requires both the manual opening of the system isolation valve and reaching the high temperature alarm setpoint for the automatic opening of the system deluge valve.

Because of the inaccessibility of the lower containment to personnel during operation due to ALARA radiation exposure concerns, the use of one or more CCTVs in the lower containment to monitor for fire and smoke is an acceptable substitute to an hourly fire watch, system becomes inoperable.

if the fire suppression COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-7 AMENDMENT NO.

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~34.7.9 Con'e All hourly fire watch patrols are performed at intervals of sixty minutes with a margin of fifteen minutes.

A continuous fire watch requires that a trained individual be in the specified area at all times and that each fire zone within the specified area be patrolled at least once every fifteen minutes with a margin of five minutes.

A control valve is defined as a valve that when closed does not leave an alternate open flow path to a system. A sectionalizing valve is defined as a valve that when closed does not prevent an alternate open flow path to a system and hence does not make the fire suppression water system inoperable. Under certain situations, the closure of a sectionalizing valve followed by the closure of a second valve will not leave an open flow path to one of the specified systems. In this instance, Action Statement b of Specification 3.7.9.1 is applicable.

Manual actuation of C02 fire suppression systems provides adequate fire, protection for the protected areas based on operable fire detection in the area, low combustible loadings, and prompt fire brigade response to alarms.

Many of the action statements take credit for operable fire detection in lieu of a fire watch when a fire protection system is inoperable.

Operable fire detection provides sufficient early warning capability of a fire to the appropriate Control Room.

3 4.7.10 FIRE RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensure that fire damage will be limited. These design features minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment. The fire barriers and fire barrier penetrations for sealing devices are periodically inspected to verify their OPERABILITY. The functional testing of the fire dampers is provided to ensure that the dampers remain functional. The ventilation seals area seals around ventilation duct work penetrating fire barriers. It is not our intent to rely on backup systems or other compensatory measures for an extended period of time and action will be taken to restore the inoperable portions of the fire rated assembly to OPERABLE status within a reasonable period.

For the purpose of determining OPERABILITY, an OPERABLE fire rated assembly and/or sealing device is one that is capable of performing its intended safety function.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-8 AMENDMENT NO.'

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ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference Specifications:

,'a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b. inoperable Seismic Monitoring Instrumentation, Unit No. 1, Specification 3.3.3.3.

c.- Inoperable Meteorological Monitoring Instrumentation, Unit No. 1, Specification 3.3.3.4.

d. Deleted

e. Deleted

f. Seismic Event Analysis, Specification 4.3.3.3.2.

g. Sealed Source Leakage in excess of limits, Specification 4.7.9.1.3.

COOK NUCLEAR PLANT - UNIT 2 6-19 AMENDMENT NO.

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