ML17328A576

Amends 130 & 115 to Licenses DPR-58 & DPR-74,respectively, Modifying Fire Protection Tech Specs to Delete Requirement of Establishing Fire Watch If Fire Detection or Suppression Sys Is Out of Svc

ML17328A576
Person / Time
Site:	Cook
Issue date:	02/08/1990
From:	Thoma J Office of Nuclear Reactor Regulation
To:
Shared Package
ML17328A577	List: ML17328A576 ML17328A578
References
NUDOCS 9002230301
Download: ML17328A576 (69)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

1 AIIEHDIIENT TO FACILITY OPERATING LICENSE Amendment IIo. 130-License Ho.

DPR-58 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Hichigan Power Company (the, licensee) dated February 6, 1989. and supplemented on November 10,

1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and tI e Commission's rules and regulations set forth in 10'FR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance IIith the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-58 is hereby amended to read as follows:

Techni~cal S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

130, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

,FOR THE NUCLEAR REGULATORY COtiNISSION

Attachment:

Changes to the Technical'pecifications Date of Issuance:

February 8, 1990 J

hn O. Thoma, Acting Director Project Directorate III-l Division of Reactor Projects - III, IV,, V Im Special Projects Office of Nuclear Reactor Regulation

I C I

ATTACHMENT TO LICENSE AMENDMENT fl0.

130 FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

REMOVE 3/4 3-51 3/4 3-52 3/4 3-53 3/4 7-41 3/4, 7-42 3/4 7-43 3/4 7-44 3/4 7-45 3/4 7-46 3/4 7-47 3/4 7-48 3/4 7-49 3/4 7-50 3/4 7-51 3/4 7-52 B 3/4 3-4, B 3/4 7-7 B 3/4 7-8 6-19 INSERT 3/4 3-51 3/4 3-52 3/4 3-53 3/4 3-53a 3/4 7-41 3/4 7-42 3/4 7-43 3/4-7-44 3/4 7-45 3/4 7-46 3/4 7-47 3/4 7-48 3/4 7-49 3/4 7-50 3/4 7-51 3/4 7-52 3/4 7-53 3/4 7-54 B 3/4 3-4 B 3/4-7-7 B 3/4 7-8 B 3/4 7-9 6-19

• No corresponding page rusher in present TS.

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-10 shall be OPERABLE.

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

ACTION:

'I When the number of OPERABLE fire detectors is less than the minimum number of required OPERABLE detectors given below:

a.

When any, but not more than one-half the total or no two adjacent*

in any fire detection

zone, Function A detector(s) located outside of containment shown in Table 3.3-10 are inoperable:

1) restore the inoperable detector(s) to OPERABLE status within 14

days,

2) after the 14 day time limit expires, within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish an hourly fire watch patrol to inspect the zone(s) with the inoperable detector(s).

b.

For inoperable detectors located outside containment, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish an hourly fire watch patrol to -inspect the zone(s) when:

1) more than one-half of the Function A fire detectors in any fire detection zone shown in Table 3.3.10 are inoperable, or 2) any Function B fire detectors shown in Table 3.3.10 are inoperable, or

3) any two or more adjacent fire detectors*

shown in Table 3.3.10 are inoperable.

c

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'd, For "detector(s) located inside containment:

1) establish a fire watch patrol to inspect the containment zone at least once per 8

hours, or 2) monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

-+Adjacent fire detectors is defined as any detectors physically adjacent in the fire detection zone.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-51 AMENDMENT NO. 79~130

INSTRUMENTATION SURVEILLANCE RE UIREMENTS 4.3.3.7 The fire detection system for each fire detection zone shown in Table 3.3-10 shall be demonstrated OPERABLE as follovs.

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 system 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. 79yg3Q

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TABLE 3.3-10 Unit 1 and Common Area Fire Detection S stems Detector S stem Location Total Number of Detectors Auxiliary Building a) Elevation 587 b) Elevation 587 c) Elevation 609 d) Elevation 633 e) Elevation 650 f) New Fuel STGE Area g)

RP Access Control 6

Chem Labs Heat

'lame Smoke (x/y)*

(x/y)*

(x/y)*

23/OC 55/OC 41/OC 41/OC 34/OC 4/OC 25/0 Ul East Main Steam Valve Enclosure Ul Main Steam Line Area El, 612 (Around Containment)

Ul NESV Valve Area El.

612 Ul 4KV Switchgear (AB)

Ul 4KV Switchgear (CD)

Ul Engr. Safety System Switchgear

&- XFMR. Rm.

Ul CRD, XFMR. & Switchgear Rm.

Inverter

& Bttry. Rms.

0/3 0/3 0/5 0/5 28/0~

13/0~

2/0 0/2 0/2 0/9 0/8 Ul Pressurizer Heater XFMR. Rm.

Ul Diesel Fuel Oil Transfer Pump Rm.

Ul Diesel Generator Rm.

1AB Ul Diesel Generator Rm.

1CD Ul Diesel Generator Ramp Corr.

U162 AFWP Vestibule 0/1 0/2 0/2 12/0 4/0 2/OC Ul Control Room Ul Switchgear Cable Vault Ul Control Room Cable Vault Ul Aux. Cable Vault 45/0 0/10~

0/13 0/65~

0/6 Ul&2 ESW Basement Area Ul ESV Pump

& MCC Rms.

4/OC 9/0 C System protects area common to both Units 1 and 2

• (x/y) x is number of Function A (early warning fire detection and notification only) instruments.

y is number of Function B (actuation of fire suppression systems and early warning and notification) instruments.

circuit contains both smoke and flame detectors two circuits of five detectors each two circuits of 32 and 33 detectors each COOK NUCLEAR PLANT - UNIT 1 3/4 3-53 AMENDMENT NO. 79,130

TABLE 3.3-10 (Continued)

Unit 1 and Common Area Fire Detection S stems Detection S stem Location Total Number of Detectors Heat (x/y)*

Flame (x/y)*

Smoke

{x/y)*

Ul Cable Tunnels a)

Quad 1 Cable Tunnel b) Quad 2 Cable Tunnel c) Quad 3N d) Quad 3S e)

Quad 3M f) Quad 4 0/3 0/4 0/3 0/3 0/3 0/5 0/4 0/7 0/4 0/3 0/4 0/6 Ul Charcoal Filter Ventilation Units a) 1-HV-AES-1 b) 1-HV-AES-2 c) 1-HV-ACRF d) 1-HV-CIPX e) 1-HV-CPR f) 12-HV-AFX 0/1~

0/1~

0/]+k9rkk 0/]~

0/1~

0/1%%%%+C Ul Containment~~

a)

RCP 1

b)

RCP 2

c)

RCP 3

d)

RCP 4

e)

Quad 1

f) Quad 2

g)

Quad 3

h)

Quad 4

1/0 1/0 1/0 1/0 21/P~~

6/p~~

23/P~~

12/P~~~

C System protects area common to both Units 1 and 2

• {x/y) x is number of Function A (early warning fire detection and notification only) instruments.

y is number of Function B (actuation of fire suppression systems and early varning and notification) instruments.

Originally installed to automatically deluge charcoal filters.

However, manual actions are nov necessary.

The fire detection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate tests.

~~ Thermistors located in cable trays are assigned to a quadrant based on the location of the thermistor circuit startpoint.

COOK NUCLEAR PLANT - UNIT 1 3/4 3-53a AMENDMENT NO. 130

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:

a.

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.

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

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 />.

• Four High Demand Fire Pumps (two per Unit) are shared between Units 1

and 2.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-41 AMENDMENT NO. 79,130

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.

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 distribixtion 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 simulated automatic actuation of the system throughout its operating

sequence, and:

2.

Verifying that each automatic valve in the flow path actuates to its correct position, Verifying that each pump develops a flow of at least 2000 gpm at a system head of at least 300 feet of water by observing three points (minimum, rated, and peak) on the pump's performance curve.

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 preplanned sequence to maintain the fire suppression water 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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4 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:

I 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 t'e 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.

c ~

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 2.

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.

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 cle'an, tight, free of corrosion, and coated with anti-corrosion material.

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

79,130

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 4.3.3.7, 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 and establish an hourly fire watch patrol; or 2) establish a continuous fire watch patrol.*

co 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 a continuous fire watch.

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 ~

79 y 1 30

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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.l.d.

b.

At least once per 18 months:*

'1.

By performing a syst: em 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 1 3/4 7-45 AMENDMENT NO. 100,130

TABLE 3.7-5 A

OPEN HEAD DELUGE WATER SPRAY SYSTEMS LOCATION 1-HV-AES-1 Charcoal Filters 1-HV-AES-2 Charcoal Filters 1-HV-ACRF-1 Charcoal Filters 1-HV-CPR-1 Charcoal Filters 12-HV-AFX Charcoal Filters*

ACTUATION Manual - Electric - Heat Manual - Electric - Heat Manual

- Electric - Heat Manual - Electric - Heat 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. 97,13Q

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TABLE 3.7-5 B

CLOSED HEAD SPRINKLER SYSTEMS LOCATION TYPE SYSTEM ACTUATION Auxiliary building El.

587 ft.+/~* (Normally accessible

areas, charging and Safety Injection Pump

Rooms, stairways to El, 573 and 609)

Preaction Sprinkler Dry Pilot**

Auxiliary building El.

609 ft.*/***(Normally accessible

areas, CCW Pump

area, stairways to El.

633 and 620 above Chem.

Lab)

Preaction Sprinkler Dry Pilot**

Auxiliary building El.

633 ft.+/***(Normally accessible

areas, excluding HVAC Vestibule Areas and stairways to El. 650)

Preaction Sprinkler

Dry Pilot**

Auxiliary Feedwater Pump Corridor*/***

Wet Pipe Automatic Turbine Building El.

591 Generator End (Extended to Diesel Generator Corridor***)

Wet Pipe Automatic Auxiliary Building Cask Handling Area (El. 609)*/***

Preaction Sprinkler Dry Pilot**

Auxiliary Building Drumming Room (El. 587)+/***

Preaction Sprinkler Dry Pilot**

Contractors Access Control Building (El. 612)

Wet Pipe Reactor Coolant Pumps (4)***

Preaction Sprinkler Manual Automatic

• 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. 68,13()

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P1ANT SYSTEMS LOW PRESSURE.CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7..9.3 The low pr'essure 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:

,1.

The systems valves, associated ventilation dampers and fans, and self-closing fire doors operate automatically upon'eceipt 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. 79,130

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

Switchgear Rooms Engineered Safety Switchgear Room Cross-zoned Heat Cross-zoned Heat Heat Manual Manual Manual Switchgear Room Cable Vault Cross-zoned Ionization and Infrared Auxiliary Cable Vault Control Room Cable Vault (Backup)*

Penetration Cable Tunnel Quadrant 1

Penetration Cable Tunnel Quadrant 2

Penetration Cable Tunnel Quadrant 3N Penetration'able Tunnel Quadrant 3M Penetration Cable Tunnel Quadrant 3S Penetration Cable Tunnel Quadrant 4

Ionization

.Manual Manual Manual Manual Manual Manual Manual I

~Control Room Cable Vault" CO

.System is only required to be operable when the Cable Vau'lt Halon System is inoperable.

2."

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

795130

4

PLANT SYSTEMS

'ALON 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 j

to be OPERABLE.

ACTION:

a.

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:

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.

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.

79N130

PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7 '.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:

2.

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

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 1 3/4 7-51 AMENDMENT NO 79 130

TABLE 3.7-7 FIRE HOSE STATIONS Auxiliary Building+*

Access to Diesel Generator Rooms Access to Switchgear Rooms Access to Control Room Access to Pressurizer Heater Transformer Room Minimum 12*

Hose Station No.

32 Hose Station No.

58 or No. 211 Hose Station'No.

82 or No.

81 Hose Station No.

31 Access to ESW Pump Rooms, MCC Room, and ESW Basement Area Hose Station No.

23 Access to Auxiliary Feed Pump Rooms Hose Station No.

35

• Shared with Unit'

• • Withinthe 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:

All fire rated assemblies (walls, floor/ceilings, and cable tray and conduit enclosures),

separating safe shutdown 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 duct work) in the above fire rated assemblies shall be OPERABLE.

APPLICABILITY; At all times.

ACTION:

a.

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 and establish an hourly fire watch patrol, 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 patrol, 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.

~is testing is in addition to the testing required by Specifications 4.7.9.3.c.l and 4.7.9,4.b.l.

~Option (4) should be used for fire dampers only after the appropriate HVAC and radiological reviews have been performed.

COOK NUCLEAR PLANT - UNIT 1 3/4 7-53 AMENDMENT NO. 130

PIANT SYSTEHS SURVEILLANCE RE UIREHENTS 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 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 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 AHENDMENT NO. 130

INSTRUMENTATION 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 systems is inoperable, the

'ction statements provided 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.

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. 79,112,130

BASES 3 4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability i.s 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, CO

, 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 ma5or element in the facility fire protection program.

In the event that one or more C02 Suppression System requiring automatic actuation must be i.solated 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

'utomatic CO suppression system temporarily puts this system in a manual actuation mole.

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 suppression systems are inoperable, alternate backup firnfighting 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 if the inoperable equipment is the primary means 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 suppressi.on systems are met.

An allowance i.s made for ensuring a sufficient volume of Halon and CO in the storage tanks by verifying either the weight, level, or pressure of the tanks.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-7 AMENDMENT No. 6~, l30

BASES

~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.'he 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 ~ater 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, if the fire suppressi.on system becomes inoperable.

All hourly fire w'atch 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. 130 July.15, j,986 Eases Clarification

BASES

~34.7.10 Con't detection and extinguishment.

The fire barriers and fire barrier penetration sealing devices are peiiodically 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 vork 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 vill be taken to restore the inoperable portions of the fire rated assembly to OPERABLE status vithin a reasonable period.

For the purposes of deter'mining 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. 130

(s ADMINISTRATIVECONTROLS 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 Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3 g.

Deleted h.

Deleted COOK NUCLEAR PLANT - UNIT 1 6-19 AMENDMENT.NO. 87, 130

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+***+

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.

COOK NUCLEAR PLANT UNIT NO.

2 AMENDMEHT TO FACILITY OPERATING LICENSE Amendment Ho.

115 License Ho. DPR-74 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Indiana Michigan Power Company (the licensee) dated February 6, 1989 and supplemented on November 10, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of= Facility Operating License No.

DPR-74 is hereby amended to read as follows:

Technic~al S ecificatinns The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.

116, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COHtiISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 8, 1990 John 0.

Thoma, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation

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I ATTACHMENT TO LICENSE AMENDMENT NO. 115 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.

The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

REMOVE 3/4 3-50 3/4 3-51 3/4 3-52 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 3/4 '7-41 3/4 7-42 3/4 7-43 3/4 7-44 3/4 7-45 3/4 7-45a 3/4 7-46 3/4 7-47 B 3/4 3-3 B 3/4 7-6 B 3/4 7-7 B 3/4 7-8 6-19 INSERT 3/4 3-50 3/4 3-51 3/4 3-52 3/4 3-52a 3/4 7-36

-3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 3/4 7-41 3/4 7-41a 3/4 7-42 3/4 7-43 3/4 7-44 3/4 7-45 3/4 7-46 3/4 7-47 3/4 7-48 B 3/4 3-3 B 3/4 3-4 B 3/4 7-6 B 3/4 7-7 B 3/4 7-8 6-19

• No corresponding page number in present TS.

• "Page Deletion.

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

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

AGZZOH:

When the number of OPERABLE fire detectors is less than the minimum number of required OPERABLE detectors given below:

a.

When any, but not more than one-half the total or no two adjacent*

in any fire detection zone, Function A detector(s) located outside of containment shown in Table 3.3-11 are inoperable:

1) restore the inoperable detector(s) to OPERABLE status within 14 days,

2) after the 14 day time limit expires, within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish an hourly fire vatch patrol to inspect the zone(s) with the inoperable detector(s).

b.

For inoperable detectors located outside containment, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish an hourly fire watch patrol to inspect the zone(s) when:

1) more than one-half of the Function A fire detectors in any fire detection zone shown in Table 3.3.11 are inoperable, or 2) any Function B fire detectors shown in Table 3.3.11 are inoperable, or

3) any two or more adjacent fire detectors*

shovn in Table 3.3.11 are inoperable.

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For detector(s) located inside containment:

1) establish a fire watch patrol to inspect the containment zone at least once per 8

hours, or 2) monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

+Adjacent fire detectors is defined as any detectors physically adjacent in the fire detection zone.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-50 AMENDMENT NO. 61,115

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INSTRUMENTATION SURVEILLANCE RE UIREMENTS 4.3.3.8 The fire detection system for each fire detection zone shown in Table 3.3-11 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 ND 61,115

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TABLE 3.3-11 Unit 2 and Common Area Fire Detection S stems Detection S stem Location Total Number of Detectors Auxiliary-Building a) Elevation 587 b) Elevation 609 c) Elevation 633 d) Elevation 573 e) Elevation 650 f) New Fuel STGE Area Heat Flame (x/y)*

Smoke (x/y)*

55/OC 41/OC 41/OC 23/OC 34/OC 4/OC U2 East Main Steam Valve Enclosure U2 Main Steam Line Area El'12 (Around Containment)

U2 NESW Valve Area El.

612 28/0~

]3/0~

2/0 U2 4KV Switchgear (AB)

U2 4KV Swttchgear (CD)

U2 Engr. Safety System Switchgear

& XFMR. Rm.

U2

CRD, XFMR & Switchgear Rm.

Inverter 6

AB Bttry. Rms, U2 Pressurizer Heater XFMR. Rm.

U2 Diesel Fuel Oil XFMR. Rm.

U2 Diesel Generator Rm.

2AB'2 Diesel Generator Rm.

2CD U2 Diesel Generator Ramp Corr.

Ul&2 AFWP Vestibule 0/1 0/2 0/2 0/3 0/3 0/5 0/5 0/2 0/2 0/14 0/17 12/0 4/0 2/OC U2 Control Room U2 Switchgear Cable Vault:

U2 Control Rm. Cable Vault U2 Aux. Cable Vault 42/0 0/]0~*

0/13 0/76~

0/6 Ul&2 ESW Basement Area U2 ESW Pump

& MCC Rms.

4/OC 9/0 C System protects=area common to both Units 1 and 2

• (x/y) x is number of Function A (early warning fire detection and notification only) instruments.

y is number of Function B (actuation of fire suppression systems and early warning and notification) instruments.

circuit contains both smoke and flame detectors

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two circuits of five detectors each two circuits of 38 detectors each COOK NUCLEAR PLANT - UNIT 2 3/4 3-52 AMENDMENT N0.61, 115

TABLE 3.3-11 (Continued)

Unit 2 and Common Area Fire Detection S stems Detection S stem Location Total Number of Detectors Heat Flame (xgr>*

(xgV)"

Smoke

( (x/y)*

U2 Cable Tunnels a)

Quad 1 Cable Tunnel b) Quad 2 Cable Tunnel c) Quad 3N d) Quad 3S e)

Quad 3M f) Quad 4

0/3 0/4 0/3 0/3 0/3 0/5 0/4 0/7 0/3 0/4 0/4 0/6 U2 Charcoal Filter Ventilation Units a) 2-HV-AES-l=.

b) 2-HV-AES-2 c) 2-HV-ACRF d) 2-HV-CIPX e) 2-HV-CPR f)12-HV-AFX 0/1~

0/1~Ark 0/]~her 0/]~

0/] %%%Ink'/1~C U2 Containment~~

a)

RCP 1

b)

RCP 2

c)

RCP 3

d)

RCP 4

e)

Quad 1

f) Quad 2

g)

Quad 3

h) Quad 4

1/0 1/0 1/0 1/0 16/0~~

9/PVrln&Hrk%'9/P

~lnHrA'4/0~Ark%'

System protects area common to both Units 1 and 2

• (x/y) x is number of Function A (early warning fire detection and notification only) instruments.

y is number of Function B (actuation of fire suppression systems and early warning and notification) instruments.

Originally installed to automati.cally deluge charcoal filters.

However, manual actions are now necessary.

The fire'etection instruments located within the Containment are not required to.be OPERABLE during the performance of Type A Containment Leakage Rate tests.

~~ Thermistors lo'cated in cable trays are assigned to a quadrant based on the location of the thermistor circuit startpoint.

COOK NUCLEAR PLANT - UNIT 2 3/4 3-52a

'AMENDMENT NO. 3.j.5

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'ith 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.

The provisions of Specifications 3.0.3 and 3'.4 are not applicable.

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

~ater system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Four High Demand Fire Pumps (two per unit) are shared between Units 1 and 2.

COOK NUCLEAR PLANT - UNIT 2

'3/4 7-36 AMENDMENT NO. 61,115

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 s'tarting 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 simulated automatic actuation of the system throughout its operating

sequence, and:

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 by observing three points (minimum, rate'd and peak) on the pump's performance curve.

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 preplanned sequence to maintain the fire suppression water system pressure greater than 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 2 3/4 7-37 AMENDMENT N0.61,115

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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:

'I 1.

The fuel storage tank contains at least 160 gallons of fuel, and 2.

The diesel starts from ambient conditions and operates for 1

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:

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 I

volts.

b.

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

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.

'OOK NUCLEAR PLANT - UNIT 2 3/4 7-38 AMENDMENT NO. 61,115

PLANT SYSTEMS SPRAY AND OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The spray and/or sprinkler systems located in th'e 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:

&e 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.

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 4.3.3.8 or pneumatic per Table 3.7-5B), for the affected area is OPERABLE and establish an hourly fire watch patrol, or 2) establish a continuous fire watch patrol.*

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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 a continuous fire watch.

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. 61i115

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l 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:

\\

At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel's 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 AMENDHENT NO 78,115

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

Manual - Electric - Heat Manual - Electric - Heat Manual - Electric - Heat Manual - Electric - Heat Manual - Electric - Heat Manual

- Electric - Heat

<<Shared system with Unit 1.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-41 AMENDMENT NO. 84,115

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TABLE 3.7-5 B

LOCATION CLOSED HEAD SPRINKLER SYSTEMS TYPE SYSTEM ACTUATION Auxiliary building El. 587 ft.+/***(Normally accessible

areas, charging and Safety Injection Pump

Rooms, stairways to El.

573 and 609)

Preaction Sprinkler Dry Pilot**

Auxiliary building El.

609 ft.*/***(Normally

~

accessible

areas, CCW Pump area, stairways to El. 633)

Preaction Sprinkler Dry Pilot**

Auxiliary building El.

633 ft.*/~*(Normally accessible

areas, excluding HVAC Vestibule Areas and stairways to El. 650)

Preaction Sprinkler Dry Pilot**

Auxiliary Turbine Driven Feedwater Pump and Pump Corridor*/***

Wet Pipe Automatic Turbine Building 591 ft.

El. Generator End (Extended to Diesel Generator Corridor***)

Wet Pipe Automatic Auxiliary Building Cask Handling Area (El. 609)

• /***

Preaction Sprinkler Dry Pilot**

Auxiliary Building Drumming Area (El. 587)*/***

Preaction Sprinkler Dry Pilot+*

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 7-41a AMENDMENT NO. 115

PLANT SYSTEMS LOW PRESSURE CO SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.3'he 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:

a.

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 3.0.4 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:

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.

AMENDMENT NO. 50N115 3/4 7-42 3.

Flow from each nozzle during performance of an air flow or CO "Puff Test".

2 COOK NUCLEAR PLANT - UNIT 2

TABLE 3.7-6 LOW PRESSURE CARBON DIOXIDE SYSTEMS 17 TON CAPACITY LOCATION Diesel Generator 2AB Room Diesel Generator 2CD Room Diesel Generator Fuel Oil Pump Room 4KV Switchgear Rooms Control Rod Drive, Transf.

Switchgear Rooms Engineered Safety Switchgear Room Switchgear Room Cable Vault ACTUATION METHOD Cross-Zoned Heat Cross-Zoned Heat Heat Manual Manual Manual Cross-Zoned Ionization and Infrared Penetration Cable Tunnel Penetration Cable Tunnel Quadrant 3S Quadrant 4

Auxiliary Cable Vault Control Room Cable Vault (Backup)*

Penetration Cable Tunnel Quadrant 1

Penetration Cable Tunnel Quadrant 2

Penetration Cable Tunnel Quadrant 3N Penetration Cable Tunnel Quadrant 3M Ionization Manual Manual Manual Manual Manual Manual Manual

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

2 COOK NUCLEAR PLANT - UNIT 2 3/4 7-43 AMENDMENT N0.615115

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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 l

to be OPERABLE.

ACTION:

a.

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 kpecifications 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 syst: em shall be demonstrated OPERABLE:

b.

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.

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 t'est or C02 puff test through headers'nd nozzles to assure that there is no blockage.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-44 AMENDMENT NO. Q.,].].5

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~ I 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.

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:

1.

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. 61,116

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TABLE 3.7>>7 FIRE HOSE STATIONS Auxiliary Building+*

'Access to Diesel Generator Rooms Access to Switchgear Rooms A'ccess to Control Room Access to Pressurizer Heater Transformer Room Minimum 12*

'ose Station No.

7 Hose Station No. 45 or No.

212 Hose Station No.,65 or No.

81 Hose Station No.

12 Access to ESW Pump Rooms, MCC'Room, and ESW Basement Area Hose Station No.

20 Access to Auxiliary Feed Pump Rooms Hose Station No.. 9

• Shared with Unit 1

• • Withinthe Controlled Area COOK NUCLEAR PLANT - UNIT 2 3/4 7-46 AMENDMENT NO. 61,115

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 safe shutdown fire areas or separating portions of redundant systems important to safe shutdown within a fire'rea 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 duct work) in the above fire rated assemblies shall be OPERABLE.

APPLICABILITY: At all times.

ACTION'.

Pith any of the above fire rated assemblies and/or sealing devices inoperable, within 1 hour: ') verify that the fire detectors and/or fire suppression system on at least one side of. the inoperable assembly are OPERABLE and establish an hourly fire watch patrol, 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 patrol, 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 I

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.

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

~Option (4) should be used for fire dampers only after the appropriate HVAC and radiological reviews have been performed.

COOK NUCLEAR PLANT - UNIT 2 3/4 7-47 AMENDMENT N0.61,115

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 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. 115

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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, the action statements provided 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.

3/4.3.3.9 RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor

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'ethods 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. 61,115

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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. 115

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'heir 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 t'e 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 97,102,111,115

BASES 3/4.7.9 Con't In the event that portions of the fire protection systems are inoperable, alternate backup fire fighting equipment is 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 if the inoperable equipment is the primary means 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 areas.

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 CO in the storage tanks by verifying either the weight, level, or pressure 3f the tanks.

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken'ince this system provides the major fire suppression capability of the plant.

The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to 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 va'lve 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, if the fire suppression system becomes inoperable.

COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-7 AHENDHENT NO. 115 July 15, 1986 Bases Clarification

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~34.7.9 Con't All hourly fire watch patrols are performed at intervals of sixty minutes with a margin of 15 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 15 minutes with a margin of 5 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 CO 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 penetration 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 are 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'ire rated assembly to OPERABLE status within a reasonable period.

For the purposes 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. 115 July 15, 1986 Bases Clarifica-tion

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ADMINISTRATIVECONTROLS 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 N0..7351075115