ML17331A252
| ML17331A252 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/31/1993 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17331A253 | List: |
| References | |
| NUDOCS 9304130075 | |
| Download: ML17331A252 (31) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. i7~
License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 12,
- 1992, as supplemented January 27,
- 1993, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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.
'P304130075 930331
- PDR, ADOCK,05000315 P '
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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:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 171
, 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 issuance and is to be implemented within 30 days of issuance of this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
bhrch 31, 1993 Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO 1
TO FACILITY OPERATING LICENSE NO. DPR-58 OCKET 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 vertical lines indicating the area of change.
REMOV 3/4 7-41 3/4 7-42 3/4 7-43 3/4 7-45 B 3/4 7-7 B 3/4 7-8 B 3/4 7-9 INSERT 3/4 7-41 3/4 7-42 3/4 7-43 3/4 7-45 B 3/4 7-7 B 3/4 7-8 B 3/4 7-9
E 3 4.7.9 FIRE SUPPRESSIO SYS EMS IRE SUPPRESSION WA ER S
ST ITING CONDITION FOR 0 ERA N
3.7,9.1 The fire suppre'ssion water system shall be considered to be OPERABLE
<<ith:
a.
b.
Three fire suppression system pumps, 'ach with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header,.
Two fire <<ater tanks, 'ach <<ith a minimum usable volume of 565,000 gallons (34.0 feet level indication).
co An OPERABLE flow path capable of taking suction 'from either one of the fire water tanks and transferring the water through distribution piping (with OPERABLE sectionalixing valves) up to the yard hydrant curb control valves, to the hose station valve(s) and water suppression system controlling valve(s).
The hose station valve(s) and the water suppression system controlling valve(s) that are required to be in the flow path are given in Specifications 3.7.9.5 and 3.7.9.2, respectively.
~CTION:
a.
With one pump inoperable, restore the inoperable pump to OPERABLE status within 7 days or provide an alternate backup pump.
b.
With one fire water tank inoperable, restore the inoperable tank to OPERABLE status within 30 days or establish a backup water system supply.
Co 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 />.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable,
- These pumps and tanks are shared between Units 1 and 2, COOK NUCLEAR PLANT - UNIT 1 3/4 7-41 AMENDMENT NO.
171
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SURVEILLANC UIREMENTS 4.7.9.1.1 The fire suppression water system shall be demonstrated OPERABLE:
& ~
b.
At least once per 7 days by verifying the water supply contained in the fire water tanks.
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.
C ~
At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked,
- sealed, or otherwise secured in position, is in its correct position.
d.
At least once per 6 months by performance of a system 'flush of above ground internal distribution headers and fire hydrants.
e.
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 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 2500 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 pump starts in its preplanned sequence to maintain the fire suppression water system pressure greater than or equal to 100 psig.
- g. 't 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 obstruction by a full flow test.
COOK NUCLEAR PLANT - UNIT 1 3/4 7-42 AMENDMENT NO. W, 440 171
LANT SYS EMS URVEILLANCE RE U REMENTS Co t ued 4.7.9.1.2 The fire pump diesel engines shall be demonstrated OPERABLE:
a.
ht least once per 31 days by verifying:
1.
The fuel storage tanks contain at least 160 gallons of fuel, and 2.
The diesels start from ambient conditions and operate for at least 30 minutes.
b.
ht least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tanks 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>>
ht least once per 18 months by sub)ecting the diesels to an inspection in accordance with procedures prepared in con]unction with the manufacturer's recommendations for this class of standby service.
4.7,9.1.3 The fire pump diesel starting battery banks and chargers 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.
c ~
At least once per 18 months by verifying that:
1.
The'atteries, 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, W, 430 171
SYS RE I 4.7.9.2 Each of the above required water spray and/or sprinkler systems shall be demonstrated to be OPERABLE:
a ~
ht least once per 12 months by cycling each testable va1ve in the flow path thx'ough at least one complete cycle of full travel as provided by Technical Specification 4.7.9.1.1.e.
I 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 theix correct positions on a test signal, and+
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b)
Cycling each valve in the fl.ow path that is not testable during plant opexation 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 yeaxs by performing an air flow test through the piping of each open head deluge system and verifying each open head deluge nozzle is unobstructed.
~e fire protection water flow surveillance testing may be suspended unti1 the completion of the fire px'otection water storage tank and fire pump installations (May 31, 1993).
The surveillance testing suspended as a result of this amendment will be initiated at its normal frequency within four months of the new fire protection water storage tanks and fire pumps being declared OPERABLE, with the exception of unit outage required testing which would be completed before the end of the next scheduled unit outage.
COOK NUCLEAR Pum - UNIT 1 3/4 7-45 AMENDMENT NO, 400, 488, ~,~
171
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BASES 3 4.7.9 IRE SU PRESS 0
S S
EMS 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 consist 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 minimise 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 systems 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 suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment i:s 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 i.s 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.
In the event that the fire water tanks become inoperable, Lake Michigan may serve as their backup.
Two manual, diesel-engine driven, vertical-turbine fire pumps rated at 2000 gpm, which take suction off of Lake Michigan and provide water to the fire suppression
- header, are administratively controlled.
One of these pumps may serve as a backup to one of the fire suppression pumps that take suction off of the tanks.
However, it i,s 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.
While performing the surveillances speci. fied in 4.7.9.1 the fire suppression water system is still capable of performing its intended function.
Consequently, it is not necessary to enter the ACTION STATEMENT specified in 3.7.9.1 while the SURVEILLANCES specified in 4.7.9.1.1 are being performed, unless the tested equipment fails the SURVEILLANCE.
In addition, an allowance is made for ensuring a sufficient volume of Halon and CO, in the Halon and COi storage tanks by verifying either the weight, level, or pressure of the tanks.
COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-7 AMENDMENT N0.6p 171
+/GASES 4.4.7.9 Co tinued The fire suppression water system has three fire pumps common to both units which discharge into underground ring headers.
There is one motor-driven horizontal centrifugal fire pump rated at 2500 gpm that takes suction from the fire water storage tanks; and. two diesel-engine-driven horizontal centrifugal fire pumps rated at 2500 gpm that take suction from the fire water storage tanks.
Having a combination of diesel-driven and electric motor-driven pumps in the system design is consistent with NRC Branch Technical Position APSCB 9.5-1.
The flow paths capable of taking suction from Lake Michigan're normally isolated to preclude zebra mussel infestation of the system.
The purpose of the charcoal filter fire suppression T/S 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.
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, if the fire suppression system becomes inoperable.
All hourly fire ~etch 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.
COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-8 AMENDMENT NO. 430, 434
- 171,
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ASKS 4.7.9 Co tinued h control valve is defined as a valve that when closed does not leave an alternate open flow path to a system.
h 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 villnot leave an open flow path to one of the specified systems.
In this instance, Action Statement c of Specification 3.7.9.1 i,s applicable.
Manual actuation of CO fire suppression systems provides adequate fire piotection 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.
During Surveillance Testing of a Low Pressure CO System with the system inoperable, the requirement for a continuous fire watch may be suspended during portions of the test which result or may result in a discharge into the CO protected area.
Simi.larly, if a CO actuation occurs which results in the need to have the Low Pressure C02 System made inoperable, the requirement for a continuous fire watch may be suspended.
In either case, the area affected shall be restored to habitability as soon as practicable, after which the continuous fire watch is to be re-established if the system is still inoperable.
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 i.s 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. 480, 434
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated February 12,
- 1992, as supplemented January 27,
- 1993, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 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:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
154
, 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 issuance and is to be implemented within 30 days after issuance of this amendment.
FOR THE NUCLEAR REGULATORY COMMISSION p&+~
Ledyard B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 31, 1993
ATTACHMENT TO LICENSE AMEND E
NO.
154 FACILITY OPERATING LICENSE NO DPR-74 OCKET 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 vertical lines indicating the area of change.
~REMOV 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-40 B 3/4 7-6 B 3/4 7-7 B 3/4 7-8 INSERT 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-40 B 3/4 7-6
~
B 3/4 7-7 B 3/4 7-8 B 3/4 7-9
SYSTEMS 3 4.7.9 FIRE SUPPRESS 0
S S
IRE SUPP SS ON WATER S S
ITING CONDITION FOR 0
. 3.7.9.1 with:
ao The fire suppression water system shall be considered to be OPERABLE
(
Three fire suppression system pumps, 'ach with a capacity of 2500 gpm, with their discharge aligned to the fire suppression
- header, b.
'Two fire water tanks,'ach with a minimum usable volume of 565,000 gallons.
(34.0 feet level indication)
Co An OPERABLE flow path capable of taking suction from either one of the fire water tanks and transferring the water through distribution piping (with OPERABLE sectionalixing valves) up to the yard hydrant curb control valves, to the hose station valve(s) and water suppression system controlling valve(s).
The hose station valve(s) and the water suppression system controlling valve(s) that are required to be in the flow path are given in Specifications 3.7.9.5 and 3.7.9.2, respectively.
~CTION:
a.
With one pump inoperable, restore the inoperable pump to OPERABLE status within 7 days or provide an alternate backup pump.
b.
With one fire water tank inoperable, restore the inoperable tank to OPERABLE status within 30 days or establish a backup water system supply c
~
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'ackup 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 />.
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
+ These pumps and tanks are shared between Units 1 and 2.
COOK NUCLEAR PLANT - UNIT 2 3/4 7-36 AMENDMENT NO. M, 444
- 154,
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LANT SYSTEMS URVEILLANCE RE U
4.7.9.1.1 The fire suppression water system shall be demonstrated OPERABLE:
a.
b.
At least once per 7 days by verifying the water supply contained in the fire water tanks.
'L 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.
Co At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked,
- sealed, or otherwise secured in position, is in its correct position.
d.
At least once per 6 months by p'erformance of a system flush of above ground internal distribution headers and fire hydrants.
e.
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 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 2500 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 pump starts in its preplanned sequence to maintain the fire suppression water system pressure greater than or equal to 100 psig.
g ~
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 obstruction by a full flow test.
COOK NUCLEAR PLANT. - UNIT 2 3/4 7-37 AMENDMENT NO. 64, 414
- 154,
LANT SYSTEMS SURVE LLANC RE UIREME S
Co tinued, 4;7.9.1.2 The fire pump diesel engines shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying:
2 ~
The fuel storage tanks contain at least 160 gallons of fuel, and The diesels start from ambient conditions and operate for at least 30 minutes.
b.
At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tanks 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.
co At least once per 18 months by subjecting the diesels to an inspection in accordance with procedures prepared in conjunction with the manufacturer's recommendations for this class of standby service.
4.7.9.1.3 The fire pump diesel starting battery banks and chargers 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.
Ce 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, M, 444 f54
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4.7.9.2 Each of the above required water spray and/or sprinkler systems shall be demonstrated to be OPERABLE:
ao b.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cyc1e of full travel as provided by Technical Specification 4.7,9.l.l.e.
At least once per 18 months:
1.
By performing a
system functional test which includee 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, anN b) Cycling each valve In the flow path that is not testable during plant opsratI,on 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 supervI,sed by air) to verify their integrity.
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3.
Sy 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.
elhe fire protection ester flou suroeillence testing nsy he suspen6en until the completion of the fire protection water storage tank and fire pump installations
{May 31, 1993).
The surveillance testing suspended as a result of this amendment will be initiated at its normal frequency within four months of the new fire protection water storage 'tanks and fire pumps being declared OPERABLE, with tho anooption of unit outage required testing whtrh wnuld hp completed before the end of the next scheduled unit outage.
COOK NUCLEAR PLANT - UNIT 2 3/4 7-40 AMENDMENT 50. M, 44$,~,~
- 154,
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~SES 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 monigor 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 etati.stical 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 system consists of the water system,'pray and/or sprinklers, CO
, halon and fire hose stations.
The collective capability of the fire suppression systems is adequate to minimixe potential damage to safety-related equipment and is a major element in the facility fire protection program.
In the event that one or more CO suppression systems 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. 6k, XX'54,
~ )
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LANT SYS S
USES 3 4.7.9 Continued In the event that portions of the fire suppression 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 if the inoperable equipment is the primary means of fire suppression.
Backup fire protection equipment wi11 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.
In the event that the fire water tanks become inoperable',
Lake Michigan may serve as their backup.
Two manual, diesel-engine driven, vertical-turbine fire pumps rated at 2000 gpm, which take suction off of Lake Michigan and provide water to the fire suppression
- header, are administratively controlled.
One of these pumps may serve as a backup to one of the fire suppression pumps that take suction off of the tanks.
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. 'hile performing the surveillances specified in 4.7.9.1.1 the fire suppression water system is still capable of performing its intended function.
Consequently, it is not necessary to enter the ACTION STATEMENT specified in 3.7.9.1 while the SURVEILLANCES specified in 4,7.9.1.1 are being performed, unless the tested equipment fails the SURVEILIANCE.
In addition, an allowance is made for ensuring a sufficient volume of Halon and C02 in the Halon and C02 storage tanks by verifying either the weight, level, or pressure of the tanks, The fire suppression water system has three fire pumps common to both units which discharge into underground ring headers.
There is one motor-driven horizontal centrifugal fire pump rated at 2500 gpm that takes suction from the fire water storage tanks; and two diesel-engine-driven horizontal centrifugal fire pumps rated at 2500 gpm that take suction from the fire water storage tanks.
Having a combination of diesel-driven and electric-motor-driven pumps in the system design is consistent with NRC Branch Technical Position APSCB 9.5-1.
The flow paths capable of taking suction from Lake Michigan are normally isolated to preclude zebra mussel infestation of the system.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-7 AMENDMENT NO. 64> 445, 444 I
- 154,
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~ASES 4.
.9 Continued The purpose of the charcoal filter fire suppression T/S 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 f'ire suppression system protecting the charcoal filters is only required when there is charcoal in the filters.
Actuation of spray water onto the charcoal filters requires both the manual opening of the system isolhtion 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 a continuous fire watch, if the fire suppression system becomes inoperable.
All hourly fire watch patrols are performed at intervals of sixty minutes with a margin of fifteen minutes.
h continuous fire watch requires that a trained individual be in the specified area at all times and that each fire xone 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.
h sectionalixing 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 c 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.
COOK NUCLEAR PLANT - UNIT 2 'B 3/4 7-8 AMENDMENT NO. 44, XX',
- 154,
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7 ASKS 3 4.7.
Co t ued Many of the Action Statements take credit for OPERABLE fire detection in lieu of a fire vetch vhen a fire protection system is inoperable.
OPERABLE fire detection provides sufficient early earning capability of a fire to the appropriate Control Room.
During Surveillance Testing of a Low Pressure C02 System vith the system inoperable, the requirement for a continuous fire'match may be suspended during portions of the test vhich result or may result in a discharge into the C02 protected area.
. Similarly, if a C02 actuation occurs vhich results in the need to have the Lov Pressure C02 System made inoperable, the requirement for
'a continuous fire match may be suspended.
In either case, the area affected shall be restored to habitability as soon as practicable, after vhich the continuous fire vetch is to be re-established if the system is still inoperable.
3 4.7.10 FIRE RATED ASSEMBLIES The OPERABILITY of the fire barriers and barrier penetrations ensures that fire damage vi11 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 cwork 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 purpose of determining OPERABILITY, an OPERABLE fire rated assembly/sealing device is one that is capable of performing its intended safety function.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-9 AMENDMENT NO, 6k, 444, July 15, 1986 Bases Clarification 154,