ML20059H524

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Proposed Tech Specs Re Reduction of Control Room Temp Limit
ML20059H524
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 09/10/1990
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML20059H523 List:
References
NUDOCS 9009180036
Download: ML20059H524 (7)


Text

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  • ATTACHMENT 2 TO AEP:NRC:0398U ']' '

(1 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES h,

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

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OPERABLE with:

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a. Two independent heating and cooling systems,
b. Two independent pressurization fans, and 7 i
c. One charcoal adsorber and HEPA filter train, i-

, APPLICABILITY: MODES 1, 2, 3, and 4  ;

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ACTION:

a. With one heating and cooling system inoperable, restore the ,

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

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

SURVEILIANCE REQUIREMENTS 4.7.5.1 The control room emergency ventilation system shall be demon.

L strated OPERABLE:  ;.

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 95 F.

l Il COOK NUCLEAR PLANT UNIT 1 3/4 7 19 AMENDMENT NO.

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PIANT SYSTEMS [

BASES 3/4.7.5 CONTROL ROOM EMEROENCY VENTIIATION SYSTEM I The OPERABILITY of the control room emer5ency ventilation system ensures  ;

that the control room will remain habitable for operations personnel during and i following all_ credible accident conditions. The OPERABILITY of this system in  !

conjunction with control room design provisions is based on limiting the  !

radiation exposure to personnel occupying the control room to 5, rem or less  !

whole body, or its equivalent. This limitation is consistent with the requirements of Ceneral Design Criteria 19 of Appendix "A", 10 CFR 50.

The control room ventilation system normally maintains the control room at  ;

temperatures at which control room equipment is qualified for the life of the plant. Continued operation at the Technical Specification limit is permitted ,

since the portion of time the temperature is likely to be elevated is small in ,i comparison to the qualified life of the equipment at the limit, t 3/4.7.6 ESF VENTILATION SYSTEM The OPERABILITY of the ESF ventilation system ensures that adequate cooling is provided for ECCS equipment and that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to  ;

reaching the environment. The operation of this system and the resultant effect '

on offsite dossge calculations were assumed in the accident analyses. ,

The 1980 version of ANSI N510 is u nd as a testing guide. This standard, '

however, is intended to be rigorously applied only to systems which, unlike the

, ESF ventilation system, are designed to ANSI N509 standards. For the specific  ;

l case of the air aerosol mixing uniformity test required by ANSI N510 as a

!- prerequisite to in place leak testing of charcoal and HEPA filters, the l air aerosol uniform mixing test acceptance criteria were not rigorously met, t l- For this reason, a statistical correction factor will be applied to applicable l l surveillance test results where required.

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l 3/4.7.7 SEALED SOURCE CONTAMINATION The litritations on sealed source removable contamination ensure that the I total body ar individual organ irradiation does not exceed allowable limits in ,

the event of ingestion or inhalation of the probable leakage from the source i' material. The limitations on removable contamination for sources requiring leak-testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. Quantities of interest to this specification which are exempt from the leakage testing are consistent with the criteria of 10 CFR Parts 30,11-20 COOK NUCLEAR PIANT UNIT 1 B 2/4 7 5 AMENDMENT NO.  ;

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s PLANT SYSTEMS EASES 3/4.7.7 SEALED SOURCE CONTAMINATION and 70.19. Leakage from s>urces excluded from the requirements of this specification is not likely to represent more than one maximum permissible body burden for total body irrad.tation if the source material is inhaled or ingested.

3/4.7.8 HYDRAULIC SNUBBERS All snubbers are required OPERABLE to ensure that the structural ine.egrity '

of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. I Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which 1 they are installed, would have no adverse effect on any safety.related system. '

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

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  • j PIANT SYSTEMS' ,

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

a. Two independent heating and cooling systems,
b. Two independent pressurization fans, and
c. One charcoal adsorber and HEPA filter train.

APPLICABILITY: MODES 1, 2, 3, and 4. )j ACTION:

a. With One heating and cooling system inopcrable, restore the l, inoperable system to OPERABLE status wit.hin 7 days or be in ,.

at least HOT STANDBY within the next 6 nours and in COLD t' SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ;

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b. With one pressurization fan inoperable, restore the inoperable fan to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within -

the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,

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

ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.  ;

SURVEILIANCE REQUIREMENTS 4.7.5.1 The control room emergency ventilation system shall be demon- l strated OPERABLE: I

a. Atleastonceper12hoursbyverifyingthagthecontrolroom air temperature is less than or equal to 95 F. l,,
b. At least once per 31 days on a STAGGERED TEST BASIS by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the system operates for at least 15 minutes.

COOK NUCLEAR PLANT UNIT 2 3/4 7-14

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PLANT SYSTEMS  !

BASES .

3/4.7.2 STEAM CENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures l that the pressure induced stresses in the steam generators do not exceed

the agximum allowable fracture toughness stress limits. The limitations .;

of 70 F and 200 psig are based on average steam generator impact values h

taken at + 10 F-and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING WATER SYSTEM i The_0PERABILITY of the component coo 1Ang water system ensures that sufficient cooling capacity is available for continued operation of ,

safety related equipment during normal and accident conditions. The ,

redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions user in the accident analyses, j, 3/4,7.4 ESSENTIAL SERVICE WATER SYSTEM ,

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The OPERABILITY of the essential service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within  ;

! acceptable limits.

3/4.7.3 AND 3/4.7.4 '

1 The OPERABILITY of the Unit 2 flowpaths which support Unit 1 shutdown-l functions ensures the availability of cooling functions on Unit 1 and addresses the requirements of 10 CFR 50 Appendix R. The required flowpath consists of a L pump and associated water supplies and delivery systems. Fire watches posted in the affected opposite unit areas (i.e., Unit 1 areas requiring use of the Unit 2 component coolir.g water system or essential service water system in the event of a fire) may serve as the equivalent shutdown capability specified in the action l

statements of Specifications 3.7.3.1 and 3.7.4.1. In the affected areas, either establish continuous fire watches or verify the OPERABILITY of fire detectors per Specification 4.3.3.7 and establish hourly fire watch patrols. The required oppoeite unit equipment along with the surveillance requirements necessary to ensure that this equipment is capable of fulfilling its intended Appendix R alternate safe shutdown function have been established and are included in a plant procedure. An additional plant procedure details how the above noted fire watches will be implemented.

L L I COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-4

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PLANT SYSTEMS f

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3/4.7.5 CONTROL R001 EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room EMERGENCY ventilation system j ensures.that the control room will remain habitable for operations personnel. 4 during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less i whole body, or its equivalent. This limitation is consistent with the  ;

requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.

i The control room ventilation system normally maintains the' control room at ,

temperatures at which control room equipment is qualified for the life of the '!

plant. Continued operation at the Technical Specification limit is permitted.

since the portion of time the temperature is likely to be elevated is small in. ,

comparison to the qualified life of the equipment at the limit.

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1 COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-4a k

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