ML17331A979: Difference between revisions

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{{#Wiki_filter:ReplacePage3/45-5ofAEP:NRC:1181,Attachment2(proposedT/Ss)withthefollowingpage:9310010214930928PDRADOCK05000316PDR,,
{{#Wiki_filter:Replace Page  3/4 5-5 of AEP:NRC:1181, Attachment 2 (proposed T/Ss) with the following page:
0'I~4live'c EMERGENCYCORECOOLINGSYSTEMSSURVEILLANCEREUIREMENTSContinuedd0Atleastonceper18monthsby:VerifyingautomaticisolationandinterlockactionoftheRHRsystemfromtheReactorCoolantSystemwhentheReactorCoolantSystempressureisabove600psig.2.Avisualinspectionofthecontainmentsumpandverifyingthatthesubsystemsuctioninletsarenotrestrictedbydebrisandthatthesumpcomponents(trashracks,screens,etc.)shownoevidenceofstructuraldistressorcorrosion.te.Atleastonceper18months,duringshutdown,by:t1.VerifyingthateachautomaticvalveintheflowpathactuatestoitscorrectpositiononaSafetyInjectiontestsignal.2.Verifyingthateachofthefollowingpumpsstartauto-maticallyuponreceiptofasafetyinjectiontestsignal:a)Centrifugalchargingpumpb)Safetyinjectionpumpc)ResidualheatremovalpumpByverifyingthateachofthefollowingpumpsdevelopstheindicateddischargepressureonrecirculationflowwhentestedpursuanttoSpecification4.0.5:1.Centrifugalchargingpump2.SafetyInjectionpumpGreaterthanorequalto2405psigGreaterthanorequalto1409psig3.ResidualheatremovalpumpGreaterthanorequalto190psiggoByverifyingthecorrectpositionofeachmechanicalstopforthefollowingEmergencyCoreCoolingSystemthrottlevalves:1.Within4hoursfollowingcompletionofeachvalvestrokingoperationormaintenanceonthevalvewhentheECCSsub-systemsarerequiredtobeOPERABLE.tTheprovisionsofTechnicalSpecification4.0.8areapplicable.COOKNUCLEARPLANT-UNIT23/45-5AMENDMENTNO.&7i99,43k,434 ReplacePage3/45-5ofAEP:NRC:1181,Attachment3(markedupT/Ss)withthefollowingpage:
9310010214 930928 PDR    ADOCK 05000316 PDR,,
EMERGENCYCORECOOLINGSYSTEMSSURVEILLANCEREUIREMENTSContinuedd.Atleastonceper18monthsby:1.VerifyingautomaticisolationandinterlockactionoftheRHRsystemfromtheReactorCoolantSystemwhentheReacto'rCoolantSy'tempressureisabove600psig.2.Avisualinspectionofthecontainmentsumpandverifyingthat\thesubsystemsuctioninletsare.notrestrictedbydebrisandthatthesumpcomponents(trashracks,screens,etc.)shownoevidenceofstructuraldistressorcorrosion.fe.Atleast.onceper18months,duringshutdown,by:$1.VerifyingthateachautomaticvalveintheflowpathactuatestoitscorrectpositiononaSafetyInjectiontestsignal.2.Verifyingthateachofthefollowingpumpsstartauto-maticallyuponreceiptofasafetyinjectiontestsignal:a)Centrifugalchargingpump.b)Safetyinjectionpumpc)ResidualheatremovalpumpByverifyingthateachofthefollowingpumpsdevelopstheindicateddischargepressureonrecirculationflowwhentestedpursuanttoSpecification4.0.5:1.CentrifugalchargingpumpGreaterthanorequalto2405psig2.SafetyInjectionpumpGreaterthanorequalto1409psig3.ResidualheatremovalpumpGreaterthanorequalto190psiggByverifyingthecorrectpositionofeachmechanicalstopforthefollowingEmergencyCoreCoolingSystemthrottlevalves:1.Within4hoursfollowingcompletion'feachvalvestrokingoperationormaintenanceonthevalvewhentheECCSsub-systemsarerequiredtobeOPERABLE.l~prowslo~of)cdnrlic~5~COOKNUCLEARPLANT-UNIT23/45-5AMENDMENTNO.97~fgT,~}}
 
0
          'I ~
4 live' c
 
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS      Continued d0  At least once per    18 months  by:
Verifying automatic isolation        and interlock action of the  RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.
: 2. A  visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.t
: e. At least once per    18 months,   during shutdown, by:t
: 1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.
: 2. Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:
a)     Centrifugal charging    pump b)     Safety injection    pump c)     Residual heat removal    pump By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:
: 1. Centrifugal charging      pump      Greater than or equal to 2405 psig
: 2. Safety Injection    pump            Greater than or equal to 1409 psig
: 3. Residual heat removal      pump      Greater than or equal to 190 psig go  By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
: 1. Within 4 hours following completion of each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.
t The  provisions of Technical Specification 4.0.8 are applicable.
COOK NUCLEAR PLANT    UNIT 2            3/4 5-5          AMENDMENT NO. &7 i 99, 43k, 434
 
Replace Page 3/4 5-5 of AEP:NRC:1181, Attachment 3 (marked up T/Ss) with the following page:
 
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS        Continued
: d. At least once per      18 months  by:
: 1. Verifying automatic isolation        and  interlock action of the  RHR system from the Reactor Coolant System when the Reacto'r Coolant Sy'tem pressure    is  above 600  psig.
: 2. A  visual inspection of the containment \ sump and verifying that the subsystem suction inlets are.not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.f
: e. At least. once per    18 months, during shutdown, by: $
: 1. Verifying that    each automatic valve in the flow path actuates to    its correct position    on a Safety Injection test signal.
: 2. Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:
a)     Centrifugal charging    pump  .
b)     Safety injection  pump c)     Residual heat removal    pump By  verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:
: 1. Centrifugal charging      pump      Greater than or equal to 2405 psig
: 2. Safety Injection    pump            Greater than or equal to 1409 psig
: 3. Residual heat removal      pump      Greater than or equal to 190 psig g    By  verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
: 1. Within 4 hours following completion'f each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.
    ~ prowslo~ of )cdnrlic~
l 5~
COOK NUCLEAR PLANT      - UNIT 2              3/4 5-5                AMENDMENT NO.97~
fgT,~}}

Latest revision as of 14:15, 22 October 2019

Proposed Tech Specs Replacement Page 3/4 5-5 of AEP:NRC:1181 Attachments 1 & 3 Re Surveillance Interval Extension Withdrawal for Unit 2 Cycle 9
ML17331A979
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 09/28/1993
From:
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331A978 List:
References
NUDOCS 9310010214
Download: ML17331A979 (5)
v • d • e


Text

Replace Page 3/4 5-5 of AEP:NRC:1181, Attachment 2 (proposed T/Ss) with the following page:

9310010214 930928 PDR ADOCK 05000316 PDR,,

0

'I ~

4 live' c

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d0 At least once per 18 months by:

Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.

2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.t
e. At least once per 18 months, during shutdown, by:t
1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.
2. Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:

a) Centrifugal charging pump b) Safety injection pump c) Residual heat removal pump By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1. Centrifugal charging pump Greater than or equal to 2405 psig
2. Safety Injection pump Greater than or equal to 1409 psig
3. Residual heat removal pump Greater than or equal to 190 psig go By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.

t The provisions of Technical Specification 4.0.8 are applicable.

COOK NUCLEAR PLANT UNIT 2 3/4 5-5 AMENDMENT NO. &7 i 99, 43k, 434

Replace Page 3/4 5-5 of AEP:NRC:1181, Attachment 3 (marked up T/Ss) with the following page:

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued

d. At least once per 18 months by:
1. Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reacto'r Coolant Sy'tem pressure is above 600 psig.
2. A visual inspection of the containment \ sump and verifying that the subsystem suction inlets are.not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.f
e. At least. once per 18 months, during shutdown, by: $
1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal.
2. Verifying that each of the following pumps start auto-matically upon receipt of a safety injection test signal:

a) Centrifugal charging pump .

b) Safety injection pump c) Residual heat removal pump By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1. Centrifugal charging pump Greater than or equal to 2405 psig
2. Safety Injection pump Greater than or equal to 1409 psig
3. Residual heat removal pump Greater than or equal to 190 psig g By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion'f each valve stroking operation or maintenance on the valve when the ECCS sub-systems are required to be OPERABLE.

~ prowslo~ of )cdnrlic~

l 5~

COOK NUCLEAR PLANT - UNIT 2 3/4 5-5 AMENDMENT NO.97~

fgT,~

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