ML17331A979: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:ReplacePage3/45-5ofAEP:NRC:1181, Attachment 2(proposed T/Ss)withthefollowing page:9310010214 930928PDRADOCK05000316PDR,,
{{#Wiki_filter: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~4live'c EMERGENCY CORECOOLINGSYSTEMSSURVEILLANCE REUIREMENTS Continued d0Atleastonceper18monthsby:Verifying automatic isolation andinterlock actionoftheRHRsystemfromtheReactorCoolantSystemwhentheReactorCoolantSystempressureisabove600psig.2.Avisualinspection ofthecontainment sumpandverifying thatthesubsystem suctioninletsarenotrestricted bydebrisandthatthesumpcomponents (trashracks,screens,etc.)shownoevidenceofstructural distressorcorrosion.t e.Atleastonceper18months,duringshutdown, by:t1.Verifying thateachautomatic valveintheflowpathactuatestoitscorrectpositiononaSafetyInjection testsignal.2.Verifying thateachofthefollowing pumpsstartauto-matically uponreceiptofasafetyinjection testsignal:a)Centrifugal chargingpumpb)Safetyinjection pumpc)ResidualheatremovalpumpByverifying thateachofthefollowing pumpsdevelopstheindicated discharge pressureonrecirculation flowwhentestedpursuanttoSpecification 4.0.5:1.Centrifugal chargingpump2.SafetyInjection pumpGreaterthanorequalto2405psigGreaterthanorequalto1409psig3.ResidualheatremovalpumpGreaterthanorequalto190psiggoByverifying thecorrectpositionofeachmechanical stopforthefollowing Emergency CoreCoolingSystemthrottlevalves:1.Within4hoursfollowing completion ofeachvalvestrokingoperation ormaintenance onthevalvewhentheECCSsub-systemsarerequiredtobeOPERABLE.
0'I~4 live'c EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d 0 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 2.Safety Injection pump Greater than or equal to 2405 psig 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.
tTheprovisions ofTechnical Specification 4.0.8areapplicable.
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:
COOKNUCLEARPLANT-UNIT23/45-5AMENDMENT NO.&7i99,43k,434 ReplacePage3/45-5ofAEP:NRC:1181, Attachment 3(markedupT/Ss)withthefollowing 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.l~prowslo~of)cdnrlic~5~COOK NUCLEAR PLANT-UNIT 2 3/4 5-5 AMENDMENT NO.97~fgT,~}}
EMERGENCY CORECOOLINGSYSTEMSSURVEILLANCE REUIREMENTS Continued d.Atleastonceper18monthsby:1.Verifying automatic isolation andinterlock actionoftheRHRsystemfromtheReactorCoolantSystemwhentheReacto'rCoolantSy'tempressureisabove600psig.2.Avisualinspection ofthecontainment sumpandverifying that\thesubsystem suctioninletsare.notrestricted bydebrisandthatthesumpcomponents (trashracks,screens,etc.)shownoevidenceofstructural distressorcorrosion.f e.Atleast.onceper18months,duringshutdown, by:$1.Verifying thateachautomatic valveintheflowpathactuatestoitscorrectpositiononaSafetyInjection testsignal.2.Verifying thateachofthefollowing pumpsstartauto-matically uponreceiptofasafetyinjection testsignal:a)Centrifugal chargingpump.b)Safetyinjection pumpc)ResidualheatremovalpumpByverifying thateachofthefollowing pumpsdevelopstheindicated discharge pressureonrecirculation flowwhentestedpursuanttoSpecification 4.0.5:1.Centrifugal chargingpumpGreaterthanorequalto2405psig2.SafetyInjection pumpGreaterthanorequalto1409psig3.ResidualheatremovalpumpGreaterthanorequalto190psiggByverifying thecorrectpositionofeachmechanical stopforthefollowing Emergency CoreCoolingSystemthrottlevalves:1.Within4hoursfollowing completion'f eachvalvestrokingoperation ormaintenance onthevalvewhentheECCSsub-systemsarerequiredtobeOPERABLE.
l~prowslo~of)cdnrlic~
5~COOKNUCLEARPLANT-UNIT23/45-5AMENDMENT NO.97~fgT,~}}

Revision as of 08:25, 6 July 2018

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 d 0 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 2.Safety Injection pump Greater than or equal to 2405 psig 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.l~prowslo~of)cdnrlic~5~COOK NUCLEAR PLANT-UNIT 2 3/4 5-5 AMENDMENT NO.97~fgT,~

Retrieved from "https://kanterella.com/w/index.php?title=ML17331A979&oldid=814447"