L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels

License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels

ML12144A383
Person / Time
Site:	Davis Besse
Issue date:	05/23/2012
From:	Allen B FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-12-070
Download: ML12144A383 (19)

Text

FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 May 23,2012 L-12-070 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 License Amendment Request To Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels FirstEnergy Nuclear Operating Company hereby requests amendment of the operating license for the Davis-Besse Nuclear Power Station. The proposed amendment would revise Technical Specification 3.8.1, "AC Sources - Operating" to change the minimum voltage acceptance criterion for emergency diesel generator surveillance testing in surveillance requirements 3.8.1.8 and 3.8.1.14 from greater than or equal to 4031 volts to greater than or equal to 4070 volts. The proposed amendment would also add axis labels to Technical Specification Figure 3.7.18-1, "Maximum Allowable Steam Generator LeveL" The Enclosure provides a description and evaluation of the proposed amendment, including a copy of the existing Technical Specification pages marked up to reflect the proposed amendment and re-typed Technical Specification pages with the proposed amendment incorporated.

Approval of the proposed license amendment is requested by May 30, 2013, and the amendment would be implemented within 60 days of approval.

There are no regulatory commitments contained in this letter. If there are any questions, or if additional information is required, please contact Mr. Phil H. Lashley, Supervisor - Fleet Licensing, at 330-315-6808.

Davis-Besse Nuclear Power Station L-12-070 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on May ~3 , 2012.

Sincerely B:!s~en

Enclosure:

Evaluation of Proposed Amendment cc: NRC Region III Administrator NRC Project Manager NRC Resident Inspector Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

Utility Radiological Safety Board

Evaluationof the ProposedAmendment Page 1 ot7

Subject:

LicenseAmendmentRequestto Revisethe EmergencyDieselGenerator MinimumVoltageSurveillance Requirements,and Add FigureAxis Labels Tableof Contents 1.0

SUMMARY

D E S C R I P T I O. .N. . . . . . . ......2 2.0 D E T A I L E D E S C R I P T I O. .N. . . . . . . . ,.....2 3.0 T E C H N I C AELV A L U A T I O N ...............3 3 . 1 E v a l u a t i oonf M i n i m u m Voltage Change .....................3 3 . 2 E va l u a ti oonf A xi sL a belAddition ....,..........4 4.0 R E GU L A T OREYV A L U A T ION .,.... .....4 4 . 1 N o S i g n i fi ca nHta za rds Consider ation Analysis............ .......... ......4 4.2 Applicable Regulatory Requirements/Criteria ..............6 4.3 Conclusions.............. .................7 5 . 0 E N V I R O N M E N TC AO L NSIDERATION... ...........,7

6.0 REFERENCES

......... .........7 Attachments A. ProposedTechnicalSpecification Changes B. RetypedTechnicalSpecification Pages

Page2 of 7 1.0

SUMMARY

DESCRIPTION This evaluationsupportsa requestto amendOperatingLicenseNPF-3for the Davis-Besse NuclearPowerStation.The proposedchangewouldreviseTechnical Specification 3.8.1,"AC Sources- Operating" to changethe minimumvoltage acceptancecriterionfor emergencydieselgenerator(EDG)surveillance testingin surveillance requirements 3.8.1.8and 3.8.1.14fromgreaterthanor equalto (>)4031 volts(V) to > 4070V. The proposedchangewouldalsoadd axis labelsto Technical Specification Figure3.7.18-1,"MaximumAllowableSteamGeneratorLevel."

2 . 0 D ET A IL E D D E S C R IP T ION The proposedtechnicalspecification changesare providedin AttachmentA.

AttachmentA showsdeletionswith a strike-through and insertionsunderlined, with a verticallinein the marginshowingthe areaof change. Retypedtechnical specification pagesare providedfor information in AttachmentB.

The followingchangesare proposed:

1. Specification 3.8.1,"AC Sources- Operating" The EDGminimumvoltageacceptance specifiedin surveillance criterion r e q u i re me n3ts.8 .1 .8a n d3 .8.1.14willbe changed fr om4031V to 4070V as shownbelow.The specified timeof lessthanor equalto (<) 10 secondsand frequencyof > 58.8 hertz(Hz)are not revised.

Surveillance Requirement 3.8.1.8- Verifyeach EDGstartsfromstandby condition and achieves:

a. ln < 10 seconds,voltage> 4070V and frequency > 58.8Hz,and Surveillance Requirement 3.8.1.14 -YerifyeachEDGstartsand achieves:

a. In s 10 seconds,voltage> 4070V and frequency > 58.8Hz,and

2. Specification 3.7.18,"SteamGenerator Level" The followingX and Y axislabelswill be addedto TechnicalSpecification Figure 3 . 7 . 1 8 -. 1 X axislabel: STEAMSUPERHEAT fF)

Y axislabel: MAXIMUMALLOWABLE OPERATING LEVET(o/o)

UpdatedSafetyAnalysisReport,Subsection 8.3.1.1.4.1,"Emergency Diesel Generators," states that two redundant EDG units,one connected to essential4160V busC1 and the otherconnected to essential4160 V bus D1,are providedas onsite standbypowersourcesto supplytheirrespectiveessentialbusesuponlossof the normaland reservepowersources.The EDG is capableof attainingratedfrequency and voltageapproximately 10 secondsafterthe enginestartsignalis received.

Surveillance requirements 3.8.1.8.a and 3.8.1.14.a demonstrate thatthe EDGis capableof attainingthe requiredvoltageand frequencywithin10 secondsafterthe enginestartsignalis received.Technicalspecification basesassociated with surveillance requirements 3.8.1.8and 3.8.1.14statethatthe minimumvoltagelimitis

Pa g e3 o f7 basedon the voltagerequiredfor EDG breakerclosureand the minimumfrequencylimit is basedon the recommendations in SafetyGuide9 (Reference1).

Operatingexperienceindicatedthatthe minimumvoltagelimitspecifiedin surveillance requirements 3.8.1.8.a and 3.8.1.14.a may be nonconservative. A subsequent evaluationdemonstrated that this minimumvoltagelimitwas insufficientto ensure automaticclosureof the EDG outputcircuitbreaker.Thesefindingswere documented in FirstEnergy NuclearOperatingCompany'scorrectiveactionprogram.

The linechartshownin TechnicalSpecification Figure3.7.18-1wasrevisedas partof the conversionto the improvedtechnicalspecifications and submittedin Attachment1 of a supplementletterdatedAugust7,2008 (Reference 2). The changeto add axis labelscorrectsthe inadvertent omissionof the labelswhenFigure3.7.18-1was submittedin a letterdatedOctober21,2008 (Reference3) with the finalcopyof the improvedtechnicalspecifications.

3.0 TECHNICALEVALUATION 3.1 Evaluation of MinimumVoltageChange Accidentanalysescreditthe loadingof the EDG,followinga postulatedlossof offsite power,duringa lossof coolantaccident.The actualEDGstarthas historically been associatedwith the safetyfeaturesactuationsystemactuation.The EDG loadinghas beenincludedin the delaytime associated with eachsafetysystemcomponent requiringEDG supplied power followinga lossof offsitepower. This delaytime includes contributions fromthe EDG start,EDG loading,and safetyinjectionsystemcomponent actuation.The responseof the EDGto a lossof powermustbe demonstrated to be withinthisanalysisresponsetimewhenincluding the contributionsof all portions of the delay. The delaytimesassumedin the safetyanalysisfor the ESFequipment include the 10 secondEDGstartdelayand,if applicable, the appropriate sequencing delay.

Surveillance Requirement 3.8.1.8.a demonstrates thatthe EDGcan startfromstandby conditionsand achievethe requiredvoltageand frequencywithin10 seconds.

Surveillance Requirement 3.8.1.14.ademonstrates thatthe dieselenginecan restart from a hot condition,suchas subsequent to shutdownfrom normalsurveillances, and achievethe requiredvoltageand frequencywithin10 seconds.The 10 secondstart requirement supportsthe assumptions of the designbasislossof coolantaccident analysis.The minimumvoltagelimitis basedon the voltagerequiredfor EDG breaker closure,and the minimumfrequencylimitis basedon the recommendations in Safety G u i d e9 .

The proposedchangewill modifythe minimumvoltageacceptancecriteriafor s u r v e i l l a n ce re q u i re me n3ts.8 .1 .8.a and3.8.1.14.a. Theexisting minimum voltage acceptancecriterionof greaterthan or equalto 4031V will be increasedto a more restrictiveminimumvoltageacceptancecriterionof greaterthan or equalto 4070V.

The minimumacceptablevoltageof 4070V was determinedbasedon the bus voltage requiredby the EDG outputcircuitbreakervoltagepermissiverelaycircuitry.This circuitryrequiresthe voltageto be withina rangethat is 95 percentof the voltageon the low voltagesideof the meteringpotentialtransformer(120V), plusor minus2-percent

P a g e4 o l 7 to accountfor the settingtoleranceof the voltagepermissiverelay.The bus voltage rangeis then determinedby increasing the voltageby the transformerratioof 35 to 1, resulting in a rangeof 3910.2Vto 4069.8V.

The existingminimumfrequencyof > 58.8 Hz, requiredby surveillance requirements 3.8.1.8and 3.8.1.14,is acceptable per SafetyGuide9 and doesnot needto be changed.

3.2 Evaluation of Axis LabelAddition The proposedadditionof axislabelsto Technical SpecificationFigure3.7.18-1, "MaximumAllowableSteamGeneratorLevel"is an administrative changeto reflectthe axis labelsproposedduringthe conversionto improvedtechnicalspecifications, but inadvertently omittedwhenthe finaltypedpageswereforwardedto the NRC beforethe amendment was issued.

4,0 REGULATORY EVALUATION FirstEnergy NuclearOperatingCompanyproposesto reviseTechnicalSpecification 3.8.1, "AC Sources- Operating," to changethe minimumvoltageacceptance criterion for emergency dieselgenerator surveillancetestingin surveillancerequirements 3.8.1.8 and 3.8.1.14fromgreaterthanor equalto 4031voltsto greaterthanor equalto 4070 volts. The proposedchangewouldalsoadd axis labelsto TechnicalSpecification Figure3.7.18-1, "Maximum AllowableSteamGenerator Level."

The proposedsurveillance requirement changesaddressa nonconservative minimum voltageacceptancecriteriondiscoveredduringthe reviewof operatingexperience.The revisedsurveillance requirements helpto ensurethe availabilityof the standbyelectrical powersupplyto mitigatedesignbasisaccidentsand transientsand to maintainthe unit in a safeshutdowncondition.

The proposedadditionof axislabelsto Technical SpecificationFigure3.7.18-1, "MaximumAllowableSteamGeneratorLevel,"is an administrative changeto reflectthe axis labelsproposedduringthe conversionto improvedtechnicalspecifications, but inadvertently omittedwhenthe finaltypedpageswere forwardedto the Nuclear RegulatoryCommissionbeforethe amendmentwas issued.

4.1 No SignificantHazardsConsideration Analysis FirstEnergy NuclearOperatingCompanyhas evaluatedwhetheror not a significant hazardsconsideration is involvedwiththe proposedamendmentby focusingon the threestandards set forthin 10 CFR50.92."lssuance of amendment," as discussed below.

L Doesthe proposedamendmentinvolvea significantincreasein the probability or consequences of an accidentpreviouslyevaluated?

Response: No.

The proposedamendmentincreasesthe minimumrequiredemergencydiesel generatoroutputvoltageand addsaxislabelsto Figure3.7.18-1.The increase

P a g e5 o t7 in the minimumemergencydieselgeneratoroutputvoltageacceptance value in TechnicalSpecification 8.3.1surveillance requirements does not adversely affectany of the parametersin the accidentanalyses.The increasein minimumoutputvoltageensuresthat sufficientvoltageis availableto closethe emergencydieselgeneratoroutputbreaker.This conservative changeof the emergencydieselgeneratorvoltageoutputacceptancecriteriadoes not affect the probabilityor consequences of evaluatedaccidents,but ratherprovides assurancethat emergencydieselgeneratorswill providea sufficientvoltage for eventmitigation.The changeto add axislabelsto Figure3.7.18-1is administrative in nature.The proposedamendmentdoes not resultin failure modesthat couldinitiatean accident,or physicalplantmodifications that affect the operationor capabilityof systems,structuresor components to mitigate evaluatedaccidents.

Therefore,the proposedamendmentdoes not involvea significantincreasein the probabilityor consequences of an accidentpreviouslyevaluated.

2 . Doesthe proposedamendmentcreatethe possibilityof a new or differentkind of accidentfrom any accidentpreviouslyevaluated?

Response: No.

The proposedchangedoes not introducea new modeof plantoperationor involvea physicalmodification to the plant.Newequipmentis not installedwith the proposedamendment,nor doesthe proposedamendmentcauseexisting equipmentto be operatedin a new or differentmanner.The changeto add axis labelsto Figure3.7.18-1is administrative in nature.Sincethe proposed amendment doesnot involvea changeto the plantdesignor operation, no newsysteminteractions are createdby this change.The proposedchanges do not resultin any newfailuremodes,and thus cannotinitiatean accident differentfromthosepreviouslyevaluated.

Therefore,the possibilityof a new or differentkindof accidentfrom any previouslyevaluatedhas not beencreated.

3 . Doesthe proposedamendmentinvolvea significantreductionin a marginof safety?

Response: No.

The proposedamendmentdoes not affectemergencydieselgenerator performance as describedin the designbasisanalyses,includingthe capabilityfor the emergencydieselgeneratorto attainand maintainrequired voltageand frequencyfor acceptingand supportingplantsafetyloadsshould an emergencydieselgeneratorstartsignalbe received.The operability of the emergencydieselgeneratorcontinuesto provideemergencypowerto plant equipmentthat mitigatethe consequences of a transientor accident,and maintainsthe emergencydiesel generator's system'scapabilityto respond

Page6 of 7 withinthe timeassumedin the accidentanalyses. The changeto add axis labelsto Figure3.7.18-1is administrative in nature.

The proposedchangedoes not introducea new modeof plantoperationor involvea physicalmodification to the plant. The proposedamendmentdoes not introducechangesto limitsestablished in the accidentanalysis.

Therefore,the proposedamendmentdoes not involvea significantreductionin a marginof safety.

Basedon the above,FirstEnergy NuclearOperatingCompanyconcludesthatthe proposedamendmentdoes not involvea significanthazardsconsideration underthe standards set forthin 10 CFR50.92(c), and,accordingly, a findingof "no significant hazardsconsideration" is justified.

4.2 ApplicableRegulatoryRequirements/Criteria Changesdescribedin the licenseamendmentrequestcomplywith the following regulations; and continueto meetthe intentof the applicable GeneralDesignCriteria.

10 CFR Part50.36,"TechnicalSpecifications," requiresin paragraph50.36(cX2XiiXB)

Criterion2 thata technicalspecification limitingconditionfor operationbe established for a processvariable,designfeature,or operatingrestriction that is an initialcondition of a designbasisaccidentthat eitherassumesthe failureof or presentsa challengeto the integrityof a fissionproductbarrier.The steamgeneratorlevellimitingconditionfor operationsatisfiesCriterion2.

10 CFR Part50.36,"Technical Specifications,"requiresin paragraph 50.36(cX3) that technicalspecifications includesurveillance requirements relatingto test,calibration,or inspection to assurethatthe necessaryqualityof systemsand componentsis maintained, thatfacilityoperationwill be withinsafetylimits,and thatthe limiting conditionsfor operationwill be met.The technicalspecification basesfor limiting conditionfor operation3.8.1statesthat each EDG mustbe capableof starting, accelerating to ratedspeedand voltage,connectingto its respectiveessentialbus on detection of bus undervoltage, andthiswill be accomplished within10 seconds.

Surveillance requirements 3.8.1.8and 3.8.1.14verifythatthe emergency diesel generatorscan startfromstandbyconditionsand restartfrom a hot condition (respectively) and achievethe requiredvoltageand frequencywithin10 seconds.

10 CFR50,AppendixA, GeneralDesignCriterion (GDC)17,"ElectricPowerSystems,"

includesrequirements to ensurean onsiteelectricpowersystemis providedto permit functioningof structures, systems,and componentsimportantto safety.

GDC 18,"lnspection andTestingof ElectricPowerSystems," includesrequirements to ensureelectricpowersystemsimportantto safetyare designedto permitappropriate periodicinspectionand testingof importantareasand features.

Thereis no effecton the emergency dieselgenerator capabilityto supplythe minimum voltageand frequencyrequiredwithinthe time assumedin the safetyanalyses.The applicabletechnicalspecification surveillance will continueto verifythe capabilityof the

P a g e7 o f7 emergencydieselgeneratorto startand accelerateto the requiredspeedand voltage within10 seconds.Maintenance and monitoringof the emergencydieselgeneratorwill be maintained perthe Maintenance Rule(10 CFR50.65,"Requirements for monitoring the effectiveness of maintenance at nuclearpowerplants")and the MitigatingSystem Performance lndicatorProcess.

4.3 Conclusions Basedon the considerations discussedabove,(1) thereis reasonableassurancethat the healthand safetyof the publicwill not be endangeredby operationin the proposed manner,(2) suchactivitieswill be conductedin compliance with the Commission's regulations, and (3) the issuanceof the amendment will not be inimicalto the common defenseand securityor to the healthand safetyof the public.

5 . 0 E N V IR ON ME N T A L C ONSIDERATION The proposedamendmentwouldchangea requirement with respectto installation or use of a facilitycomponentlocatedwithinthe restrictedarea,as definedin 10 CFR 20, or wouldchangean inspectionor surveillance requirement.However,the proposed amendmentdoes not involve(i) a significanthazardsconsideration, (ii)a significant changein the typesor significantincreasein the amountsof any effluentsthat may be releasedoffsite,or (iii)a significantincreasein individualor cumulativeoccupational radiationexposure.Accordingly, the proposedamendmentmeetsthe eligibilitycriterion for categorical exclusionset forthin 10 CFR 51.22(c)(9).Therefore,pursuantto 10 CFR 51.22(b),no environmental impactstatementor environmental assessment needbe prepared in connectionwith the proposed amendment.

6.0 REFERENCES

1 . SafetyGuide9, "Selectionof DieselGeneratorSet Capacityfor Standby PowerSupplies," datedMarch10,1971.

2 . FirstEnergyNuclearOperatingCompanyLetterL-08-240,"Supplement to LicenseAmendmentRequest:Conversionof CurrentTechnicalSpecifications (C T S )to l mp ro ve T d e chnical ( lTS)- Volum es1,2,3,4,8, 10 ,

Specifications 12,13,14,and 16,TAC No.MD6398," datedAugust7,2008,Accession NumbersM1082270658 and ML082270669.

3 . FirstEnergy NuclearOperatingCompanyLetterL-08-338,"Copyof lmproved TechnicalSpecifications (lTS)TAC No. MD6398," datedOctober21,2008, AccessionNumberML08301 0076.

AttachmentA ProposedTechnicalSpecificationChanges PagesProvided.

The followingis a listof TechnicalSpecification 3 . 7 . 1 8- 1

• 3 . 7 . 1 8- 2

• 3 . 7 . 1 8- 3 3.8.1-6 3.8.1-11

• No changesto this page. Pageprovidedfor informationonly.

No Changesto ThisPage, SteamGeneratorLevel 3.7.18 PageProvidedfor Information Only 3.7 PLANTSYSTEMS 3.7.18 SteamGeneratorLevel LCO3.7.18 Water Levelof each steamgeneratorshall be:

a. Lessthanor equalto the maximumwaterlevelshownin Figure3.7.18-1 whenin MODE1 or 2;

b. s 96% OperateRangewith LCO3.3.11,"Steamand FeedwaterRuptureControlSystem(SFRCS)

Instrumentation,"Function1 (MainSteamLinePressure-Low)not bypassedwhenin MODE3;

c. s 96%OperateRangewithLCO3.3.11,Function1 bypassedand both mainfeedwater(MFW)pumpsnot capableof supplyingfeedwaterto the steamgenerators whenin MODE3: and

d. S 50 inchesStartupRangewithLCO3.3.11,Function1 bypassedand one or bothMFW pumpscapableof supplyingfeedwaterto the steamgeneratorswhen in M O D E3 .

APPLICABILITY: M O D E S1 , 2 , a n d3 .

ACTIONS NOTE-------

Enterapplicable Conditions and Required Actionsof LCO3.1.1,"SHUTDOWN MARGIN (SDM),"when highsteamgeneratorwaterlevelresultsin exceedingthe SDM limits.

CONDITION REQUIRED ACTION COMPLETION TIME A. Water levelin one or A.1 Restoresteamgenerator 15 minutes more steamgenerators leveltowithinlimit.

notwithinlimits.

B . Required Actionand 8.1 Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Timenotmet. AND 8.2 Be in MODE4. 12hours Davis-Besse 3.7.18-1 Amendment 279

No Changesto ThisPage, SteamGeneratorLevel 3.7.18 PageProvidedfor Information Only SU R V E IL L A N CREE QUIR E ME NTS SURVEILLANCE FREQUENCY s R 3 . 7 . 1 8 . 1 Verifysteamgeneratorwaterlevelto be within limits.

Davis-Besse 3.7.18-2 Amendment279

SteamGeneratorLevel

-l

<l Y

Jl UJI Al eo dl zl kl llnrccrptrblt ffiE0 Oprrrr.lng 8l Btg{ou 5l 3l 'o 3l 5oo ll Acctptlbl;

>l Ogrrrrlng xl

<l **glan

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Figure3.7.18-1 MaximumAllowableSteamGeneratorLevel Davis-Besse 3.7.18-3 Amendment279TBD

AC Sources- Operating 3.8.1 SURVEILLANCEREQUIREMENTS (continued SURVEILLANCE FREQUENCY sR 3.8.1.5 Checkfor and removeaccumulatedwaterfrom each 31 days daytank.

sR 3.8.1.6 Verifyintervalbetweeneach sequencedload block 31 days is withint 10o/oof designintervalfor each emergencyloadsequencerand eachemergency timedelayrelay.

sR 3.8.1.7 Verifythe fuel oil transfersystemoperatesto 92days transferfuel oil from fuel oil storagetank to the day tank.

sR 3.8.1.8 ---

'prelube

-;ilperiod.

il;;il; #3"'"=ffi  ;;;ilil Verifyeach EDGstartsfromstandbyconditionand 184days achieves:

a. In < 10 seconds,voltage> 40314070V and frequency> 58.8Hz; and

b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5Hz.

Davis-Besse 3.8.1-6 Amendment279TBD

AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY sR 3.8.1.14

t;ffi;;,,;;;; i

,153 ;;;;;,ilil--

5 minutesof shuttingdownthe EDGafterthe EDG has operated> t hourloaded> 2340kW and < 2600 kW.

Momentary transientsoutsideof loadrangedo not invalidate thistest.

2. All EDGstartsmay be precededby an engine prelubeperiod.

Verifyeach EDG startsand achieves: 24 months

a. In < 10 seconds,voltage> 4Oe+4070V and frequency> 58.8 Hz; and

b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5Hz.

Davis-Besse 3.8.1-11 Amendment279TBD

AttachmentB RetypedTechnicalSpecificationPages The followingis a listof the affectedpages.

3 . 7 . 1 8- 3 3.8.1-6 3.8.1-11

SteamGeneratorLevel 3.7.18 PageProvidedfor Information Only I

J IJJ I.IJ J

(,

z tr t

uJ tlrrrsccFirbla (L Op:rrtl,n3 o Buglou uJ J

m o

J J

l Accrptrth Oparrilng x irglon (0i&31 STEAMSUPERHEAT (OF)

Figure3.7.18-1(page1 of 1)

MaximumAllowableSteamGeneratorLevel Davis-Besse 3.7.18-3 Amendment TBD

PageProvidedfor Information Only AC Sources- Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued SURVEILLANCE FREQUENCY sR 3.8.1.5 Checkfor and removeaccumulatedwaterfrom each 31 days day tank.

sR 3.8.1.6 Verifyintervalbetweeneach sequencedload block 31 days is within! 10o/oof designintervalfor each emergencyloadsequencerand eachemergency timedelayrelay.

sR 3.8.1.7 Verifythe fuel oil transfersystemoperatesto 92 days transferfuel oil from fuel oil storagetank to the day tank.

sR 3.8.1.8 --

i.6ilil;;il; prelubeperiod.

i3J"il;;;;;;;,;;-

Verifyeach EDG startsfrom standbyconditionand 184days achieves:

a. ln < 10 seconds,voltage> 4070V and frequency> 58.8 Hz; and

b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5 Hz.

Davis-Besse 3.8.1-6 AmendmentTBD

AC Sources- Operating PageProvidedfor Information Only 3.8.1 SURVEILLANCEREQUIREMENTS SURVEILLANCE FREQUENCY sR 3.8.1.14

1Tilil;;i:'15"';;;;;*il--

5 minutesof shuttingdownthe EDGafterthe EDG has operated> t hourloaded> 2340kW and < 2600 kW.

Momentary transientsoutsideof loadrangedo not invalidate thistest.

2. All EDGstartsmay be precededby an engine prelubeperiod.

Verifyeach EDG startsand achieves: 24 months

a. ln < 10 seconds,voltage> 4070V and frequency> 58.8Hz; and

b. Steadystatevoltage>3744V and < 4400V, and frequency> 59.5Hz and < 60.5Hz.

Davis-Besse 3.8.1-11 AmendmentTBD