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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999
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Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section
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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
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Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B5901999-05-0707 May 1999
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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
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Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
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Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
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ML17335A2651998-10-0808 October 1998
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ML17335A2341998-09-14014 September 1998
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Rev 3 to Cook Nuclear Plant Restart Plan.
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Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
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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
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Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
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Rev 2 of Cook Nuclear Plant Restart Plan.
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Rev 1 to Cook Nuclear Plant Restart Plan.
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Rev 0 to Cook Nuclear Plant Restart Plan.
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Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
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Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
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Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
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Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
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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
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ML17334B5951996-07-11011 July 1996
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ISI & Testing.
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Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17325B5901999-05-0707 May 1999
Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys.
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Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program.
ML17325B4671999-03-0303 March 1999
Rev 5 to Cook Nuclear Plant Restart Plan.
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
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Rev 3 to Cook Nuclear Plant Restart Plan.
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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.
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.
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4701996-02-0808 February 1996
In-Service Pump Test Plan, Units 1 & 2
ML17334B5661995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class,1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 1, Final Plan
ML17334B5671995-11-30030 November 1995
Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class 1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 2, Final Plan
ML17332A2521994-08-0303 August 1994
Rev 3 to Plant Manager Procedure (PMP) 12 PMP 3150 PCP.100, Radwaste Pcp.
ML17332A2491994-08-0303 August 1994
Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm.
ML20063K0631994-02-11011 February 1994
Change Sheet 1 to Rev 5 to Plant Manager Procedure (PMP) 12 PMP 6010 RPP.304, Use of HEPA Vacuum Cleaners. W/ Updated Index,Page 14
ML17331B0441993-11-0909 November 1993
Rev 15 to Emergency Response Manual. W/931109 Ltr
ML17334B4851993-08-0909 August 1993
Rev 14 to Emergency Response Manual. W/930809 Ltr
ML17334B4821993-04-0202 April 1993
Rev 3 of Pump Inservice Test Program.
ML17329A5431992-06-11011 June 1992
Change Sheet 7 to Rev 6 to Procedure PMP 2080 EPP.107, Notification of Plant Personnel.
ML20077S7281991-03-14014 March 1991
Rev 3 to PMP 6010.OSD.001, Odcm
ML17325B3791990-03-0101 March 1990
Change Sheet 1 to Rev 3 to Procedure PMP 2080 EPP.106, Initial Offsite Notification.
ML17334B3551990-02-0505 February 1990
Rev 2 to DC Cook Nuclear Plant Units 1 & 2 Inservice Testing Pump Program.
ML17334B3561990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML17334B3571990-02-0505 February 1990
Rev 3 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
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Procedure MS-3.2.1.9-1B, Maint & Surveillance Ite Medium Voltage Switchgear Equipment
ML17325B0511988-12-0909 December 1988
Interim Acceptance Criteria for Safety-Related Piping Sys.
ML17334B1491987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program.
ML17334B1501987-10-0505 October 1987
Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program.
ML20212A3191986-10-0202 October 1986
Rev 1 to Procedure 12 PMP 4021 TRP.001, Reactor Trip Review
ML17324A9301986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.001, Maint Procedure for Repowering RHR Pump.
ML17324A9321986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.003, Maint Procedure for Repowering Pressurizer Backup Heaters.
ML17324A9331986-05-29029 May 1986
Rev 0 to Procedure 1MHP2140.082.005, Maint Procedure for Repowering Containment Valves.
ML17324A9341986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.304, Pressurizer PORV Cable Repair.
ML17324A9351986-05-29029 May 1986
Rev 0 to Procedure 1 Thp 6030 IMP.305, App R Post-Fire Repowering of In-Containment Valves.
ML17334A9711986-05-22022 May 1986
Rev 0 to Procedure 12-OHP 4023.100.001, Unit 1 Emergency Remote Shutdown.
ML20213F6011986-05-15015 May 1986
Rev 1 to Procedure PMP 6010.OSD.001, Offsite Dose Calculation Manual
ML17324A9001986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Iv,Training for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8991986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part Ii,Writers Guide for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML17324A8971986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part I,Specific Technical Guidelines for Donald C Cook Nuclear Plant.
ML18005A0161986-05-0101 May 1986
Rev 1 to Procedures Generation Package,Part III, Verification/Validation for Donald C Cook Nuclear Plant Emergency Operating Procedures.
ML20195C5361986-03-15015 March 1986
Public Version of Emergency Response Manual for DC Cook Nuclear Plant
ML20141D7121986-02-28028 February 1986
Rev 0 to Master Insp Plan
ML20137J6061985-12-17017 December 1985
Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 2 to Erp 2.07, Outside Agency Liaison, Rev 1 to Erp 2.08, Initial Assessment Group Runner & Rev 2 to Erp 5.01.W/860117 Release Memo
ML17334A9441985-11-0505 November 1985
Change Sheet 1 of Rev 9 to Spec DCCFP101QCN, Matl & Application Spec - Initial & Repair Installations, Revising App D Silicon Foam Scope of Work to Identify New Fire Barriers & for Cross Referencing Fire Zones
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Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept
1999-05-07
[Table view] |
Text
CHEM-NUCLEARSYSTEMS,LLC.140STONERIDGEDRIVECOLUMBIA,S.C.29210DESIGNDOCUMENTCOVERSHEETDOCUMENTIDNUMBER:ST-307REVISIONNUMBER:0PROJECTNUMBER:46628SECURITYSTATUS:PROPRIETARYNON-PROPRIETARY~xPERIOD:'ifeofthePro'ect+1earTITLE:StructuralEvaluationoftheD.C.CookUnit2SGLAPackaePREPAREDBY:DATE:81998TITLE:PrinciEnineREVIEWEDBY:DATE:TITLE:SeniorPro'ectEnineerREVISIONNOTES:CK~lmOILEOCOPYIIO.DOCUMENTCONTROLReceivedBy:DocumentDatedFrom:VerificationtoIndexBy:StorageShelfLocation:To:O'PDat'.Sr98ioie00SaVaioOSPDRADQCK050003ihP"PDR 04I"V,'lelIa'O0~4'"k4I CHEM-NUCLEARSYSTEMS,INC.140STONERIDGEDRIVECOLUMBIA,S.C.29210.DESIGNDOCUMENTREVIEWCHECKLISTDesignPackageIdentificationNoDate81998ST-307RevisionNo.ITEMYES1.ADesignInputssuchasdesignbases,regulatoryrequirements,codes,andstandardsareidentifiedanddocumented.1.BEffectofdesignpackageoncompliancewiththeSafetyAnalysisReportorCertificateofComplianceidentifiedanddocumented.2.Revisionnumberscorrectonthelistofdrawings?3.Assumptionsreasonable?4.Appropriateanalysismethodused?5.Correctvaluesusedfromdrawings?6.Answersandunitscorrect'7.Summaryofresultsmatchescalculations?8.Materialpropertiesproperlytakenfromcrediblereferences?9.Figuresmatchdesigndrawings?10.Computerinputcompleteandproperlyidentified'?11.Documentationofallhandcalculationsattached?12.MeetingminutesoftheDesignReview?NotApplicable,Explain1.BThereisnoSARorCertificateofComplianceforthisequipment.7.Resultsarenotsummarized.10.Nocomputeranalysisperformed.12.Nodesignreviewmeetingneeded.IndependentReviewer P~<.rAij"lgcA/VlII>4'h~ttpJn>ate~dIp4n'ipit TitleStructuraEvaluationoftheD:C:CookUnitS.G.L.A.PackaeGale.No.ST-307Rev.0Sheet1of10OBJKCTIVKStructuralevaluationoftheD.C.Cooksteamgeneratorlowerassembly(SGLA)packagetodemonstratethatitsclosuresprovidesufficientstrength.tomaintaintheirintegrityduringthetransportation.INTRODUCTIONAmericanElectricPower(AEP)companyhasreplacedthesteamgeneratorsattheirD.C.CookUnit2facility.Thesteamdomeportionsoftheoldsteamgenerators(OSGs)(Reference1)havebeencut.Thesteamgeneratorlowerassembly(SGLA)packageswillbetransportedtoBarnwellSouthCarolinafordisposal.ThesepackageshavebeenclassifiedasSCO-IIunder49CFRPart173(Reference2).Per49CFR173.427,theSCO-IIclassmaterialsarerequiredtobeshippedusingIP-2packages.BecauseoftheuniquesizeandshapeoftheSGLA,andcontrolledhandlingprocessduringthetransportation,anexemptionfrompackagingrequirementisrequestedfromtheDOT.Adetailedhandlingandshipmentplanisdevelopedandwillbeadheredtoduringthetransportationoftheseassemblies.TheabilityofthisplantoprovideanequivalentsafetyasthatofanSCO-IIobjectshippedinandIP-2packageformsthebasisofthisexemptionrequest.TheSGLAshaveseveralopeningsthathavebeenweldedshutforthetransportation.TheseopeningsandtheircircumferentiallocationsarelistedinTable1andareshowninFigure1.ThedetailsoftheclosureoftheseopeningsareshowninReference3.Thecutendofthesteamgeneratorswereclosedusing3"thickend-platesthatareweldedtothebodyusing3/8"filletwelds.TheseweldsweremadeaccordingtoAEPworkplanbutlackthequalityassurancedocumentation.Therefore,additionalattachmentisprovidedbyspeciallydesignedclipsthatareweldedtothesteamgeneratorbodyandtheendplate.DetailsoftheseclipsareprovidedinReference4.EvaluationsareprovidedinthisdocumentthatshowthatalltheclosuresoftheSGLAhavesufficientstructuralstrengthtomaintaintheirintegrityundertheloadingexpectedduringthetransportation.REFERENCES(1)CNSDrawingNo.C-110-B-46628-001,Rev.1,D.C.CookUnit2,SteamGeneratorGeneralLayout.(2)CodeofFederalRegulationsTitle49Part173.(3)CNSDrawingNo.C-110-B-46628-004,Rev.1,D.C.CookUnit2,SteamGeneratorContainmentDetails.(4)CNSDrawingNo.C-110-B-46628-003,Rev.1,D.C.CookUnit2,SteamGeneratorShearKeyandShieldPlateTie-Bar.(5)AISC,SteelConstnIctionManual,NinthEdition.
TitleStructuravaluation'oftheD:C.CookUnit2.G.L.A.PackaeGale.No.ST-307Rev.0Sheet2of10(6)AARManual,Rev.9,SectionNo.1,GeneralRules,1993.MATERIALPROPERTIESShellsSpecification:ASMESA-516Gr70MinimumYieldStrength,SMinimumUltimateStrength,S~dCddd=38,000psi=70,000psiWeldsSpecification:ASTMA-36MinimumYieldStrength,SMinimumUltimateStrength,S,=36,000psi=58,000psiRodSpecification:E-70xxElectrodesMinimumUltimateStrength,S=70,000psiALLOWABLESTRESSESStressesinthecapsandplugsandtheweldsareconservativelybasedontheAISC(Reference5)allowablevalues.~CCCdAllowablebendingstressAllowableshearstressWelds=0.66S=24,000psi=0.4S=14,400psiAllowableshearstressinfilletwelds=0.3SEVALUATIONOFTHECLOSURES=21,000psiTheclosuresofthesteamgeneratorpackageareevaluatedforthelargestaccelerationthe'ackagemayexperienceduringthetransportation.ThelargestaccelerationthattheSGLAwouldexperienceduringtheentireprocessofshippingandhandlingisduringtherailtransportation.AccordingtothegeneralrulesofAAR(Reference6),theseaccelerationsare3ginthelongitudinaldirection,2ginthelateraldirection,and2gintheverticaldirection.Conservatively, 0II~.lgj*,,0l7 TitleStructuravaluationof"theD:C.CookUnit.G.L.A.PackaeCaic.No.ST-307Rev.0Sheet3of103gaccelerationisassumedtooccurinalldirectionsandtheclosuresareanalyzedforthisloading.Itisalsoassumedthatthemassofthecomponentsusedforclosingtheopeningduringstorage-plates,manways,handholeslid,etc.-applytheinertialoadingtotheclosures.PrimaInlet4OutletNozzleClosuresTheprimaryinletandoutletnozzleclosures(Figure2)aremadeoftwoitems:Item-1:50.5inDia><'/4inthick><26inlong'hell.Itweightis,Wb--~x50Sx025x26x(1/12)x490=293lbsTotalclosureweight=142+293=435say450lbsConservativelyassumethatthecoverplatehasadiaof50.5inandthicknessof2.5in.Then,thecoverplateweight,W=(z/4)F505><2,5x(1/12)x490=1,420lbs,say1,5QQlbsTheinertialoadinadirectionnormaltothe'/4inplatewillbereactedbytheedgeshear.Theshearstressintheplateis:w=3x(450+1500)/(~x505x025)=148psi<<14,400psiTheplateisweldedtotheshellwithafullpenetrationweldwhichwillhavestrengthequaltoorlargerthanthebasemetal.Theweldsbetweentheshellandthenozzleare3/16"filletwhichwilldevelopashearstress,tNcia=3x(450+1500)/(~x50Sx0707x3/16)=278psi<<21,000psiTheinertialoadintheplaneofthecoverplate,willcausebendingandshearloadatthebaseoftheshell.Conservativelyassumingthattheentiremassislocatedattheendoftheshell,thebendingmomentatthebaseoftheshellis:M=3><(450+1,500)><26=152,100in-lbBendingstressintheshell,oba;,s=152,100/[x><(50.5/2)<0.25]=304psi<<24,000psiShearstressintheshell,g=3x(450+1500)/(xx50Sx025)=147psi<<14,400psi
'AI'Pi<
TitleStructurvaluation.'of,the.D.C.CookUnit.G.L.A.PackaeGale.No.ST-307Rev.0Sheet4of10Shearstressintheweldcausedbybendingmoment,wb~a;,s=152,100/[z>(50.5/2)><0.707X3/16]=573psiShearstressinthecausedbytheshearforce,z<,--3x(450+1500)/(7rx505x0707x3/16)=278psiCombinedshearstress,x=573+278=851psi<21,000psiManwaClosuresThemanwayclosures(Figure3)aremadeoftwoitems:Item-1:28inDia><'/4inthickplate.Itsweightis,W,=(rr/4)x28x0.25x(1/12)x490=44]bsItem-2:28inDia<'/4inthick><6.5inlongshell.Itweightis,Wb--rrx28x0.25x65x(1/12)x490=41ll"Totalclosureweight=44+41=85say100IbsConservativelyassumethatthemanwayhasadiaof28inandthicknessof6.5in.Then,themanwayweight,W=(rr/4)x28<6.5x(1/12)x490=1,135lbs,say1,200lbsTheinertialoadinadirectionnormaltothe'/4inplatewillbereactedbytheedgeshear.Theshearstressintheplateis:x=3x(100+1200)/(rrx28xO25)=177psi<<14,400psiTheplateisweldedtotheshellwithafullpenetrationweldwhichwillhavestrengthequaltoorlargerthanthebasemetal.Thewelds,between.the.shelland-thenozzleare'/4infillet-whichwilldevelopashearstress,tNela=3x(100+1200)/(rrx28x0707x1/4)=251psi<<21,000psiTheinertialoadintheplaneofthecoverplate,willcausebendingandshearloadatthebaseofthe.shell.Conservativelyassumingthattheentiremassislocatedattheendoftheshell,thebendingmomentatthebaseoftheshellis:M=3><(100+1,200)><6.5=25,350in-Ib 0~l.%p5kII"9tWf1 TitleStructuravaluationoftheD:C.CookUnit2.G.L.A.PackaeGale.No.ST-307Rev.0Sheet5of10Bendingstressintheshell,G~gdjgs=25~350/[7t(28/2)0.25]=165psi<<24,000psiShearstressintheshell,q=3x(100+1200)/(zx28x025)=177psi<<14,400psiShearstressintheweldcausedbythebendingmoment,trna'=25,350/[R><(28/2)X0.707><1/4]=233psiShearstressintheweldcausedbytheshearforce.vac~r=3x(100+1,200)/(itx28x0707x1/4)=251psiICombinedshearstress,x=233+251=484psi<21,000psiHandholeBlowdownShellDrainandWaterLevelNozzleClosuresTheseclosureshavethesamedesigndetailsasthemanwayclosures.Sincetheyaremuchsmallerinsizethanthemanwayclosure,thestressescalculatedforthemanwayclosureenvelopthestressesintheseclosures.EndlateClisEightclips(Figure4),inadditiontothe3/8"filletweldaroundthecircumferenceholdtheendplatesoftheSGLAs.Theseclipsaredesignedtoproviderestrainttotheendplateagainst3gaccelerationinalldirectionswithoutrelyingontheendplatetosteamgeneratorweld.Theendplatesare176indiameter,3inthickthatweigh,Wp=z/4><176><3><490/12=20,696lbssay21,000lbsTheeightclipssharetheinertialoadnormaltotheplatesurfaceequally.Therefore,loadoneachclipis:P=3X21,000/8=7,875Ibs TitleStructuravaluationoftheD.C.CookUnit.G.L.A.PackaeGale.No.ST-307Rev.0Sheet6of106"6"vltreessreeoonlsreoseesThisloadcausestheshearofsectionAA.Theaverageshearstressoverthissectionis:<=7,875/(6xl)=1,313psi<<14,400psiTheweldsonthehorizontalendreacttothisload.Assumingthatonlytheweldlegsparalleltotheloadreacttoit,theshearstressintheweldis:g,,i<--7875/(2x8x0Sx0707)=1,392psi<<21,000psiTheinertialoadparalleltotheplaneoftheendplateisassumedtobereactedbyonlytwoclipsthatareparalleltothedirectionoftheload.Inthiscasetheloadingontheclipsareasfollows:6"6"utforesereeooneoreeseese/2SorersreeoontoreesneesTheloadingoneachclipis:P=3x21,000/2=31,500lbs I~,~~4)IIIl-'%l~,~
TitleStructuralvaluationoftheD.C'.CookUnit2.G.L.A.PackaeGale.No.ST-307Rev.0Sheet7of10ShearstressonsectionBBis:x=31,500/(6xl)=5,250psi<<14,400psiBendingstressonsectionBBis:hobd;s=31,50036/(16)=15,750psi<24,000psiTocalculatethemaximumstressintheweldgrouponthesteamgenerator,theentiregroupofweldisassumedtoreactthe31,500loadandthetwo8inlegsonlyareassumedtoreacttothebendingmoment.Thestressesduetothesetwoeffectsareaddedtoobtainthemaximumweldstress.Shearstressdueto31,500lbsforce.'if~31,500/(22x0.5><0.707)=4,050psiShearstressintheweldduetobendingmoment,.z,,,=31,500@8/(6><8@0.5x0.707)=14,851psiCombinedshearstress,z=4,050+14,851=18,901psi<21,000psiCONCLUSIONSIthasbeenshowninthisreportthatalltheclosuresoftheSGLAhaveadequatestrengthtoreacttotheloadnormallyexpectedduringitshandlingandtransportation.ThestressallowablesbasedontheAISCcriteriaaresatisfiedbyallthecomponentsoftheclosureassemblywithalargemarginofsafety.SGLAswillbe,therefore,completelysealedandbehavelikeaunitizedbodyforwhichexemptionfrompackagingmayberequestedfromDOT.
'f~~t,il~ks~ea~Wgy,~8 TitleStructuravaluationoftheD.C:CookUnit.G.L.A.PackaeGale.No.ST-307Rev.0Sheet8of10Table1-LocationoftheProtrusionsontheD.C.CookSGLAProtrusionPrimaryInletNozzlePrimaryOutletNozzleHandholeNo.1HandholeNo.2CircumferentialLocationfromtheTop(Degrees)36.3143.790270PrimaryManwayNo.1PrimaryManwayNo.2308.7241.7Blow-DownNozzleNo.1Blow-DownNozzleNo.290270ShellDrain206.3WaterLevelTapEndPlate126.7Notes:(1)3"End-plateisusedtoclosethecutendoftheSGLA.
TitleStructuravaluationofthe-D.C:CookUnit2.G.L.A.PackaeGale.No.ST-307Rev.0Sheet9of10poHanway{2)00000o+PrimaryNozzle{2)OO270'OBlow-DownNozzle90'00Blow-DownNozzleShellDrainNozzleIMaterLevelTap180'iure-1D.C.CookSGLAProtrusionLocation-MT50.5"MT-26"S/~6Fiure-2PrimaNozzleCoverDetails VATitleStructuralEvaluationoftheD.C.CookUnit2S.G.L.A.PackaeGale.No.ST-307Rev.0Sheet10ofi0I361/21I28"g1/4T(P1/4MT-Fiure-3ManwaCoverDetailsMT-3SIDES1/245Typ3SIDESyP1/222.5I5R.S.G.75.13'iure-4End-PlateAttachmentDetails 0'
