Similar Documents at Cook |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17335A5581999-10-12012 October 1999
Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5611999-10-11011 October 1999
Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal
ML17335A5431999-10-0101 October 1999
Proposed Tech Specs Re Containment Recirculation Sump Water Inventory
ML17326A1591999-09-23023 September 1999
Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project
ML17326A1461999-09-17017 September 1999
Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality
ML17326A1181999-09-10010 September 1999
Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0941999-08-17017 August 1999
Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
ML17325B6061999-05-21021 May 1999
Proposed Tech Specs Revising Limitations on Positive Reactivity Additions
ML17325B5551999-04-19019 April 1999
Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17335A3681998-12-0303 December 1998
Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys
ML17335A3581998-12-0303 December 1998
Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A3621998-12-0303 December 1998
Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
ML17333A4221996-04-0808 April 1996
Revised Proposed Ts,Moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1
ML17333A3571996-03-12012 March 1996
Proposed Tech Specs,Removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3,4 & 5
ML17333A3301996-02-29029 February 1996
Proposed Tech Specs Re Boric Acid Storage Sys Boron Concentration
ML17333A3231996-02-26026 February 1996
Proposed TS 5.6.2 Re Increase in Max Nominal Fuel Assembly Enrichment Limit,Taking Credit for Use of Integral Fuel Burnable Absorber Matl
ML17333A3221996-02-22022 February 1996
Proposed Tech Specs,Proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor
ML17333A3171996-02-22022 February 1996
Proposed Tech Specs,Modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test
ML17333A3121996-02-16016 February 1996
Proposed Tech Specs Section 3.6.1.6,removing Words Structure & Steel Liner to Be Consistent W/Unit 2 Containment Sys Wording
ML17333A2671996-01-12012 January 1996
Proposed Tech Specs,Modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves
ML17333A2411995-12-19019 December 1995
Proposed Tech Specs 3/4.6.1.2,3/4.6.1.3,3/4.6/1/6 & 3/4.6.1.7,replacing Option a Scheduling Requirements for Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) W/Requirement Per 10CFR50 App J Option B
ML17332B0131995-11-10010 November 1995
Proposed Tech Specs Modifying Surveillance Testing of EDG During Refueling & Normal Operations
ML17332A9991995-10-20020 October 1995
Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV
ML17332A9151995-08-0808 August 1995
Proposed Tech Specs Re Deletion of Component Cyclic or Transient Limit Table
ML17332A8751995-08-0404 August 1995
Proposed Tech Specs for Repair of Hybrid Expansion Joint Sleeved SG Tubes
ML17332A8291995-06-30030 June 1995
Proposed Tech Specs Re Fuel Reconstitution,Per GL 90-02
ML17332A8111995-06-20020 June 1995
Proposed Tech Specs Removing Fire Protection Systems from Licenses
1999-09-23
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999
Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5611999-10-11011 October 1999
Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal
ML17335A5431999-10-0101 October 1999
Proposed Tech Specs Re Containment Recirculation Sump Water Inventory
ML17326A1591999-09-23023 September 1999
Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project
ML17326A1461999-09-17017 September 1999
Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality
ML17326A1181999-09-10010 September 1999
Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0941999-08-17017 August 1999
Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
ML17326A1471999-05-28028 May 1999
Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2.
ML17325B6061999-05-21021 May 1999
Proposed Tech Specs Revising Limitations on Positive Reactivity Additions
ML17325B5891999-05-0707 May 1999
Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
ML17325B5551999-04-19019 April 1999
Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A3581998-12-0303 December 1998
Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A3681998-12-0303 December 1998
Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys
ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
ML17335A3621998-12-0303 December 1998
Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view] |
Text
ATTACHMENT2TOAEP:NRC'1070PROPOSEDREVISEDTECHNICALSPECIFICATIONCHANGES~+>p3foppj,eygp-g~=-.@DOCKpgpppe>>PQQI REACTORCOOLANTSYSTEMOPERATIONALLFAKAGELIMITINGCONDITIONFOROPERATION3.4.6,2ReactorCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE,b.1GPMUNIDENTIFIEDLEAKAGE,c.1GPMtotalprimary-to-secondaryleakagethroughallsteamgeneratorsand500gallonsperdaythroughanyonesteamgenerator,d.10GPMIDENTIFIEDLEAKAGEfromtheReactorCoolantSystem,2e.Seallineresistancegreaterthanorequalto2.27E-lft/gpmand,f.1GPMleakagefromanyreactorcoolantsystempressureisolationvalvespecifiedinTable3.4-0.APPLICABILITY:MODES1,2,3and4~ACTION:a.WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.b.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excludingPRESSUREBOUNDARY,LEAKAGE,reducetheleakageratetowithinlimitswithin4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.c.Withanyreactorcoolantsystempressureisolationvalve(s)leakagegreaterthantheabovelimit,exceptwhen:1.Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage+byanamountthatreducestheWosatisfyALARArequirements,measuredleakagemaybemeasuredindirectly(asfromtheperformanceofpressureindicators)ifaccomplishedinaccordancewithapprovedproceduresandsupportedbycomputationsshowingthatthemethodiscapableofdemonstratingvalvecompliancewiththeleakagecriteria.~Speci.fication3.4.6.2.eisapplicablewithaveragepressurizerpressurewithin20psiofthenominalfullpressurevalue.'COOKNUCLEARPLANT-UNIT13/44-16AMENDMENTNO.
0REACTORCOOLANTSYSTEMLIMITINGCONDITIONFOROPERATIONContinued'arginbetweenthemostrecentmeasuredleakageandthemaximumlimitof5.0gpmby50tormore,declaretheleakingvalveinoperableandisolatethehighpressureportionoftheaffectedsystemfromthelowpressureportionbytheuseofa.combinationofatleasttwoclosedvalves,oneofwhichmaybetheOPERABLEcheckvalveandtheotheraclosedde-energizedmotoroperatedvalve.Verifytheisolatedconditionoftheclosedde-energizedmotoroperatedvalveatleastonceper24hours,orbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.SURVEILLANCEREUIREMENTS4.4.6.2.1ReactorCoolantSystemleakagesshallbedemonstratedtobewithineachoftheabovelimitsby:a.Monitoringthecontainmentatmosphereparticulateradioactivitymonitoratleastonceper12hours.b.Monitoringthecontainmentsumpinventoryanddischargeatleastonceper12hours.c.Determiningtheseallineresistanceatleastonceper31dayswhentheaveragepressurizerpressureiswithin20psiofitsnominalfullpressurevalue.Theseallineresistancemeasuredduring2thesurveillancemustbegreaterthanorequalto2.27E-1ft/gpm,Theseallineresistance,RSL,isdeterminedfromthefollowingexpression:RSL2.31(PCHPSQ2where:PCHP-chargingpumpheaderpressurepsigPSI2112psig(1owpressureoperation)2262psig(highpressureoperation)2.31conversionfactor(12in/ft)/(62.3lb/ft)23Q'hetotalsealinjectionflow,gpmTheprovisionsofSpecification4,0.4arenotapplicableforentryintoMODES3and4.d.PerformanceofaReactorCoolantSystemwaterinventorybalanceatleastonceper72hoursduringsteadystateoperation,andCOOKNUCLEARPLANT-UNIT13/44-17AMENDMENTNO.
REACTORCOOLANTSYSTEMSURVEILLANCEREUIREMENTSContinuede.Monitoringthereactorheadflangeleakoffsystematleastonceper24hours.4.4.6.2.2EachreactorcoolantsystempressureisolationvalvespecifiedinTable3.4-0shallbedemonstratedOPERABLEbyverifyingleakagetobewithinitslimitpriortoenteringMODE3:a.Aftereachrefuelingoutage;b.WhenevertheplanthasbeeninCOLDSHUTDOWNfor72hoursormoreandifleakagetestinghasnotbeenperformedintheprevious9months;c.Priortoreturningthevalvetoservicefollowingmaintenance,repairorreplacementworkonthevalve.COOKNUCLEARPLANT-UNIT13/44-17aAMENDMENTNO.
REACTORCOOLANTSYSTEMBASES34.4.6REACTORCOOLANTSYSTEMLEAKAGE34.4.6.1LEAKAGEDETECTIONSYSTEMSTheRCSleakagedetectionsystemsrequiredbythisspecificationareprovidedtomonitoranddetectleakagefromtheReactorCoolantPressureBoundary.ThesedetectionsystemsareconsistentwiththerecommendationsofRegulatoryGuide1.45,"ReactorCoolantPressureBoundaryLeakageDetectionSystems,"May1973.34.4.6.2OPERATIONALLEAKAGEIndustryexperiencehasshownthatwhilealimitedamountofleakageisexpectedfromtheRCS,theunidentifiedportionofthisleakagecanbereducedtoathresholdvalueoflessthan1gpm.Thisthresholdvalueissufficientlylowtoensureearlydetectionofadditionalleakage.The10GPMIDENTIFIEDLEAKAGElimitationsprovidesallowanceforalimitedamountofleakagefromknownsourceswhosepresencewillnotinterferewiththedetectionofUNIDENTIFIEDLEAKAGEbytheleakagedetectionsystems.ThelimitationonseallineresistanceensuresthattheseallineresistanceisgreaterthanorequaltotheresistanceassumedintheminimumsafeguardsLOCAanalysis.Thisanalysisassumesthatalloftheflowthatisdivertedfromtheboroninjectionlinetothesealinjectionlineisunavailableforcorecooling.COOKNUCLEARPLANT-UNIT1B3/44-3AMENDMENTNO,
REACTORCOOLANTSYSTEMOPERATIONALLEAKAGELIMITINGCONDITIONFOROPERATION3.4.6.2ReactoiCoolantSystemleakageshallbelimitedto:a.NoPRESSUREBOUNDARYLEAKAGE,b.1GPMUNIDENTIFIEDLEAKAGE,c.1GPMtotalprimary-to-secondaryleakagethroughallsteamgeneratorsand500gallonsper,daythroughanyonesteamgenerator,d.10GPMIDENTIFIEDLEAKAGEfromtheReactorCoolantSystem,2e.Seallineresistancegreaterthanorequalto2.27E-1ft/gpm,and1GPMleakagefromanyreactorcoolantsystempressureisolationvalvespecifiedinTable3.4-0,APPLICABILITY:MODES1,2,3and4>'~ACTION:a.WithanyPRESSUREBOUNDARYLEAKAGE,beinatleastHOTSTANDBYwithin6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.b.WithanyReactorCoolantSystemleakagegreaterthananyoneoftheabovelimits,excludingPRESSUREBOUNDARYLEAKAGE,reducetheleakageratetowithinlimitswithin4hoursorbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing-30hours.c.Withanyreactorcoolantsystempressureisolationvalve(s)leakagegreaterthantheabovelimit,exceptwhen:1.Theleakageislessthanorequalto5.0gpm,and2.Themostrecentmeasuredleakagedoesnotexceedthepreviousmeasuredleakage~byanamountthatreducesthe+TosatisfyALARArequirements,measuredleakagemaybemeasuredindirectly(asfromtheperformanceofpressureindicators)ifaccomplishedinaccordancewithapprovedproceduresandsupportedbycomputationsshowingthatthemethodiscapableofdemonstratingvalvecompliancewiththeleakagecriteria.~Specification3.4.6.2.eisapplicablewithaveragepressurizerpressurewithin20psiofthenominalfullpressurevalue.COOKNUCLEARPLANT-UNIT'23/44-15AMENDMENTNO.
REACTORCOOLANTSYSTEMLIMITINGCONDITIONFOROPERATIONContinuedmarginbetweenthemostrecentmeasuredleakageandthemaximumlimitof5.0gpmby50%ormore,declaretheleakingvalveinoperableandisolatethehighpressureportionoftheaffectedsystemfromthelowpressureportionbytheuseofatleasttwoclosedvalves,oneofwhichmaybetheOPERABLEcheckvalveandtheotheraclosedde-energizedmotoroperatedvalveVerifytheisolatedconditionoftheclosedde-energizedmotoroperatedvalveatleastonceper24hours,orbeinatleastHOTSTANDBYwithinthenext6hoursandinCOLDSHUTDOWNwithinthefollowing30hours.SURVEILLANCEREUIREMENTS4.4.6.2.1ReactorCoolantSystemleakagesshallbedemonstratedtobewithineachoftheabovelimitsby:a,Monitoringthecontainmentatmosphereparticulateradioactivitymonitoratleastonceper12hours.b.Monitoringthe'containmentsumpinventoryanddischargeatleastonceper12hours.c.Determiningtheseallineresistanceatleastonceper31dayswhentheaveragepressurizerpressureiswithin20psiofitsnominalfullpressurevalue.Theseallineresistancemeasuredduringthesurveillancemustbegreaterthanorequalto2.27E-1ft/gpm.Theseallineresistance,R,isdeterminedfromthefollowing"expression:RSL2.31(PCHPSIwhere:PCHPchargingpumpheaderpressure,psigPSI2262psig(highpressureoperation)2.31conversionfactor(12in/ft)/(62.3lb/ft)23Qthetotalsealin]ectionflow,gpmTheprovisionsofSpecification4.0,4arenotapplicableforentryintoMODES3and4,d.PerformanceofaReactorCoolantSystemwaterinventorybalanceatleastonceper72hoursduringsteadystateoperation,andCOOKNUCLEARPLANT-UNIT23/44-16AMENDMENTNO.
REACTORCOOLANTSYSTEMSURUEILLANCEREUIREMENTSContinuede.Monitoringthereactorheadflangeleakoffsystematleastonceper24hours.4.4.6,2'EachreactorcoolantsystempressureisolationplionvalvesecifiedinTae.-sabl34-0shallbedemonstratedOPERABLEpursuanttoSpecification4.0.5,except.thatinlieuofanyleakagetestingrequiredbyp4.0.5,eachvalveshallbedemonstratedOPERABLEbyverifyingleakagetobewithinitslimitpriortoenteringMODE3:.a.Aftereachrefuelingoutage;b.WhenevertheplanthasbeeninCOLDSHUTDOWNfor72hoursormoreandifleakagetestinghasnotbeenperformedinthepreviousmonths;c.Priortoreturningthevalvetoservicefollowingmaintenance,repairorreplacementworkonthevalve,COOKNUCLEARPLANT-UNIT23/44-16aAMENDMENTNO.
REACTORCOOLANTSYSTEMBASESThelimitationonseallineresistanceensuresthattheseallineresistanceisgreaterthanorequaltotheresistanceassumedintheminimumsafeguardsLOCAanalysis.Thisanalysisassumesthatalloftheflowthatisdivertedfromtheboroninjectionlinetothesealinjectionlineisunavailableforcorecooling.Thetotalsteamgeneratortubeleakagelimitof1GPMforallsteamgeneratorsnotisolatedfromtheRCSensuresthatthedosagecontributionfromthetubeleakagewillbelimitedtoasmallfractionofPart100limitsintheeventofeitherasteamgeneratortuberuptureorsteamlinebreak.The1GPMlimitisconsistent'withtheassumptionsusedintheanalysisoftheseaccidents.The500gpdleakagelimitpersteamgeneratorensuresthatsteamgeneratortubeintegrityismaintainedintheeventofamainsteamlineruptureorunderLOCAconditions.PRESSUREBOUNDARYLEAKAGEofanymagnitudeisunacceptablesinceitmaybeindicativeofanimpendinggrossfailureofthepressureboundary.ShouldPRESSUREBOUNDARYLEAKAGEoccurthroughacomponentwhichcanbeisolatedfromthebalanceoftheReactorCoolantSystem,plantoperationmaycontinueprovidedtheleakingcomponentispromptlyisolatedfromtheReactorCoolantSystemsinceisolationremovesthesourceofpotentialfailure.TheSurveillanceRequirementsforRCSPressureIsolationValvesprovideaddedassuranceofvalveintegritytherebyreducingtheprobabilityofgrossvalvefailureandconsequentintersystemLOCA.LeakagefromtheRCSPressureIsolationValvesisIDENTIFIEDLEAKAGEandwillbeconsideredasaportionoftheallowedlimit.34.4.7CHEMISTRYThelimitationsonReactorCoolantSystemchemistryensurethatcorrosionoftheReactorCoolantSystemisminimizedandreducesthepotentialforReactorCoolantSystemleakageorfailureduetostresscorrosion.MaintainingthechemistrywithintheSteadyStateLimitsprovidesadequatecorrosionprotectiontoensurethestructuralintegrityoftheReactorCoolantSystemoverthelifeoftheplant.Theassociatedeffectsofexceedingtheoxygen,chloride,andfluoridelimitsaretimeandtemperaturedependent.CorrosionstudiesshowthatoperationmaybecontinuedwithcontaminantconcentrationlevelsinexcessoftheSteadyStateLimits,uptotheTransientLimits,fo'rthespecifiedlimitedtimeintervalswithouthavingasignificanteffectonthestructuralintegrityoftheReactorCoolantSystem.ThetimeintervalpermittingcontinuedoperationwithintherestrictionsoftheTransientLimitsprovidestimefortakingcorrectiveactionstorestorethecontaminantconcentrationstowithintheSteadyStateLimits.COOKNUCLEARPLANT-UNIT2B3/44-4AMENDMENTNO.
