ML17333A355: 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)
 
(6 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 03/12/1996
| issue date = 03/12/1996
| title = Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
| title = Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
| author name = FITZPATRICK E
| author name = Fitzpatrick E
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| addressee name =  
| addressee name =  
Line 14: Line 14:
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 7
| page count = 7
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:CATEGORYj.REGULAT+INFORMATIONDISTRIBUTIONOZSTEM(RIDE)DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributiontACCESS.:GN-NBR.:9603200113DOC.DATE:96/03/12NOTARIZED:YESDOCKETFACIL:50.-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&Mi'chiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)
{{#Wiki_filter:t CATEGORY j.
REGULAT+ INFORMATION DISTRIBUTIONOZSTEM (RIDE)
ACCESS.:GN -NBR.:9603200113        DOC.DATE:   96/03/12      NOTARIZED: YES      DOCKET FACIL:50.-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME            AUTHOR AFFILIATION FITZPATRICK,E.       Indiana Michigan Power Co. (formerly Indiana & Mi'chigan Ele RECIP.NAME            RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
ApplicationforamendtolicenseDPR-74,removingTSsreshutdown6controlrodpositionindicationwhileinmodes3,4S5.NOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JCOPIESLTTRENCL1111RECIPIENTIDCODE/NAMEPD3-1PDCOPIESLTTRENCL11INTERN.gCENTERCBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOAC1111111011NRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDR11111111NOTETOALL"RIDSNRECIPIENTS)PLEASEHELPUSTOREDUCEWASTElCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.415"20B3)TOELIMINATEYOURNAMEFROMDXSTRKBUTXONLXSTS"'FORDOCUMENTSYOUDON'TNEEDlTOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL.11 IndianaMichigan~PowerCompanyPOBox16631Columbus,OH43216INOlANANlCHIGANPOWERMarch12,1996AEP:NRC:1248DocketNos.:50-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnit2PROPOSEDAMENDMENTTOREMOVETECHNICALSPECIFICATIONS3.1.3.3AND3.10.5,"RODPOSITIONINDICATORCHANNELS-SHUTDOWN,"TOACHIEVECONSISTENCYWITHDONALDC.COOKNUCLEARPLANTUNIT1ANDNUREG-1431.Thisletteranditsattachmentsconstituteanapplicationforamendmenttothetechnicalspecifications(T/Ss)forDonaldC.CookNuclearPlantunit2.Specifically,weareproposingtoremovetheT/Ssrelatedtoshutdownandcontrolrodpositionindicationwhileinmodes3,4,and5.Thefollowingunit2T/Ssareaffected:3.1.3.3and3.10.5andassociatedsurveillancesandbases.TheexistingCookNuclearPlantunit2T/SsrequirethatrodpositionindicationbeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.IfOPERABILITYcannotbeassured,thenumberofcontrolorshutdownrodsthatcanbewithdrawnislimitedtoasinglebankwhileperformingroddroptests.Thisrequirementisoverlyrestrictivesince,duringshutdownmodes,theabilitytoensureadequateshutdownmargincanbecompensatedbyanincreaseintheboronconcentrationofthereactorcoolantsystem.Inadditiontothereductioninunnecessaryrequirements,theproposed,amendmentwouldalsoaligntheaffectedunit2T/Sswiththeunit1T/SsandtheimprovedstandardtechnicalspecificationsissuedbytheNRCasNUREG-1431,Revision1.Attachment1providesadetaileddescriptionoftheproposedchanges,thejustificationforthechanges,andourdeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92.Attachment2containstheexistingT/Spagesmarked'76032001i39603i2PDRADQCK05000316PPDR00l~
Application for amend to license DPR-74,removing TSs re shutdown 6 control rod position indication while in modes 3, 4S5.
U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1248toreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandwillbereviewedatthenextregularlyscheduledNuclearSafetyandDesignReviewCommitteemeeting.ItisrequestedthattheproposedamendmentbeapprovedbyApril12,1996insupportoftheupcomingunit2refueling.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.ca~E.E.Fitzpatrick,VicePresidentSWORNTOANDSUBSCRIBEDBEFOREMEotaryPublicpitAttachmentcc:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett ATTACHMENT1TOAEP:NRC:1248DESCRIPTIONANDJUSTIFICATIONOFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDCDCOOKNUCLEARPLANTUNIT2TECHNICALSPECIFICATIONS ATTACHMENTTOAEP:NRC:1248DESCRIPTIONOFCHANGESPage1Thefollowingunit2technicalspecifications(T/S)3.1.3.3and3.10.5andassociatedsurveillancesandbasesareaffectedbytheproposedchange.TS34133DeletetheReactivityControlSystems,PositionIndicatorChannels-Shutdown,LimitingConditionforOperation(3.1.3.3)andtheassociatedsurveillance(4.1.3.3)(page3/41-22).TS3410.5DeletetheSpecialTestException,PositionIndicatorChannelsShutdown,LimitingConditionforOperation(3.10.5)andtheassociatedsurveillances(4.10.5.1and4.10.5.2)(page3/410-5).Also,deletethebasesreferencetoT/S3/4.10.5,PositionIndicatorChannel-Shutdown(pageB3/410-1)IndexDeletereferenceto"PositionIndicatorChannels-Shutdown,"fromthetechnicalspecificationIndex(pageIV).II.JUSTIFICATIONFORCHANGESTheaxialpositionofshutdownrodsandcontrolrodsisdeterminedbytwoseparateandindependentsystems:thebankdemandpositionindicationsystemandtheanalogrodpositionindication(ARPI)system.Thecurrentunit2T/SsrequiretheARPIsystemtobeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.Tosatisfythisrequirement,twosetsofARPIcalibrationsmustbeperformed.OnecalibrationisperformedonanindividualrodbankbasistosatisfytheARPIrequirementsduringroddroptestinginaccordancewithT/S3/4.10.5.Thesecondcalibrationisperformedatthecompletionofthe"bank"calibrationsequencetoensurethattherodsarecalibratedcorrectlytoaddressbankoverlap.Thesecalibrationsareredundantandtimeintensive.Additionally,inmodes3,4,and5,theboronconcentrationinthereactorcoolantsystem(RCS)isincreasedtoensurethatadequateshutdownmargin(SDM)isachievedandmaintainedinaccordancewithexistingCookNuclearPlantT/Ss.Thecalculationusedtoobtain ATTACHMENTTOAEP:NRC:1248Page2therequiredboronconcentrationtakesintoaccounttherelativepositionofthecontrolandshutdownrods.StrictproceduralcontrolsareinplaceatCookNuclearPlanttoensurethatanallrodsoutshutdownmarginismaintainedduringrodpositionindicatorcalibration.Theadjustmentofboronconcentrationtoassureadequateshutdownmargininmodes3,4,and5isalsosupportedbytheImprovedStandardTechnicalSpecifications(ISTS)forWestinghousePlants(NUREG-1431).TheISTSdoesnotcontainaT/Sforrodpositionindicationinmodes3,4,and5;however,thebasespositionforthemodes1and2T/Ssaddresstheshutdownmodesinthefollowingmanner."InshutdownMODES,theOPERABILITYoftheshutdownandcontrolbankshasthepotentialtoaffecttherequiredSDM(shutdownmargin),butthiseffectcanbecompensatedforbyanincreaseintheboronconcentrationoftheReactorCoolantSystem."Therefore,theassurancethatadequateshutdownmarginexistsforanallrodsoutconditioninmodes3,4,and5negatestheneedforrodpositionindicationinthesemodes.Technicalspecification3.10,5isa"specialtestexception"directlytiedtoT/S3.1.3.3.Specifically,itprovidesanexemptionfromthe"positionindicatorchannel-shutdown"requirementsduringroddroptesting.Deletionofthisspecificationisnecessarysincetheprimaryspecification3.1.3.3isbeingdeleted.ItisconcludedthatthedeletionofT/S3.1.3.3,PositionIndicationChannels-Shutdown,doesnotresultinareductioninsafetyastheimpactonshutdownmarginisadequatelycompensatedforbyanincreaseinboronconcentrationthatisconsistentwiththeguidanceofNUREG-1431.III.10CFR5092CRITERIAPer10CFR50.92,thisproposedchangedoesnotinvolveasignificanthazardsconsiderationbecausethechangedoesnot:involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3.involveasignificantreductioninamarginofsafety.
DISTRIBUTION CODE: A001D        COPIES RECEIVED:LTR          ENCL    SIZE:
Attachment1toAEP:NRC:1248Page3Criterion1TheboronconcentrationinthereactorcoolantsystemwillbehighenoughtoassureadequateSDMinmodes3,4,and5.Thecalculationtoobtaintherequiredboronconcentrationtakesintoaccountthepositionoftherods.Shutdownmarginisassumedasaninitialconditioninthesafetyanalysis.ThesafetyanalysisestablishesaSDMthatensuresspecifiedacceptablefueldesignlimitsarenotexceeded.AslongastheSDMissatisfied,nochangeintheprobabilityorconsequencesofanaccidentpreviouslyevaluatedwillresultfromtheproposeddeletionofthe"positionindicatorshutdown"specification.ItisnotedthatthischangeisconsistentwiththenewISTSapprovedbytheNRCasNUREG-1431,Rev.l.Criterion2TheabilitytoinsertthecontrolandshutdownrodsprovidedbytherodcontrolsystemisnotaffectedbytheOPERABILITYstatusoftheARPIsystem.Asmentionedpreviously,thereactorcoolantsystemboronconcentrationwillbehighenoughtoassureadequateSDMismaintained.Therefore,itisconcludedthattheproposedchangesdonotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Criterion3Themarginofsafetyrequirements,arenotaffectedbytheremovalofthisT/S.TherequiredSDMwhichisaninitialconditioninthesafetyanalysis,isunaffectedsincethereactorcoolantsystemboronconcentrationisincreasedtoaddressthe.potential"allrodsout"configuration.Basedontheseconsiderations,itisconcludedthattheproposedchangesdonot'involveasignificantreductioninamarginofsafety.}}
TITLE:    OR  Submittal: General Distribution NOTES:
RECIPIENT          COPIES              RECIPIENT        COPIES ID CODE/NAME        LTTR ENCL        ID CODE/NAME        LTTR ENCL PD3-1 LA                1    1      PD3-1  PD            1    1 HICKMAN,J                1    1 INTERN    . g    CENTER            1    1      NRR/DE/EMCB            1    1 CB        1    1      NRR/DSSA/SPLB          1    1 NRR/DSSA/SRXB            1    1      NUDOCS-ABSTRACT        1    1 OGC/HDS2                1    0 EXTERNAL: NOAC                        1    1      NRC PDR                1    1 NOTE TO ALL "RIDSN RECIPIENTS )
PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415"20B3) TO ELIMINATE YOUR NAME FROM DXSTRKBUTXON LXSTS "'FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR              12    ENCL  . 11
 
Indiana Michigan Power Company
                          ~
PO Box 16631 Columbus, OH 43216 INOlANA NlCHIGAN POWER March 12, 1996 AEP:NRC:1248 Docket Nos.: 50-316 U. S. Nuclear Regulatory Commission ATTN:     Document Control Desk Washington, D. C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant  Unit  2 PROPOSED      AMENDMENT TO REMOVE TECHNICAL SPECIFICATIONS  3.1.3.3 AND 3.10.5,     "ROD POSITION INDICATOR CHANNELS-SHUTDOWN," TO ACHIEVE CONSISTENCY WITH DONALD C. COOK NUCLEAR PLANT UNIT 1 AND NUREG-1431.
This    letter    and its attachments constitute an application for amendment        to  the    technical  specifications    (T/Ss)   for Donald C. Cook Nuclear Plant unit 2.             Specifically, we are proposing to remove the T/Ss related to shutdown and control rod position indication while in modes 3, 4, and 5. The following unit 2    T/Ss are affected:           3.1.3.3 and 3.10.5 and associated surveillances and bases.
The    existing Cook Nuclear Plant unit 2 T/Ss require that rod position indication be OPERABLE for each shutdown and control rod not fully inserted in modes 3, 4, and 5. If OPERABILITY cannot be assured, the number of control or shutdown rods that can be withdrawn is limited to a single bank while performing rod drop tests.       This requirement is overly restrictive since, during shutdown modes, the ability to ensure adequate shutdown margin can be compensated by an increase in the boron concentration of the reactor coolant system.
In addition to the reduction in unnecessary requirements, the proposed, amendment would also align the affected unit 2 T/Ss with the unit 1 T/Ss and the improved standard technical specifications issued by the NRC as NUREG-1431, Revision 1.
Attachment 1 provides a detailed description of the proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked
'76032001i3 9603i2                                                                00 PDR  ADQCK 05000316 PDR P                                                                                  l~
 
U. S. Nuclear  Regulatory Commission                AEP:NRC:1248 Page 2 to reflect the proposed      changes. Attachment 3 contains  the proposed T/S pages.
We  believe the proposed changes will not result in (1) a significant change in the types of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These  proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed at the next regularly scheduled Nuclear Safety and Design Review Committee meeting.
It  is requested that the proposed amendment be approved by April 12, 1996 in support of the upcoming unit 2 refueling.
In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.
ca~
E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME otary Public pit Attachment cc:   A. A. Blind G. Charnoff H. J. Miller NFEM  Section Chief NRC  Resident Inspector - Bridgman J. R. Padgett
 
ATTACHMENT 1 TO AEP:NRC:1248 DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNIT 2 TECHNICAL SPECIFICATIONS
 
ATTACHMENT TO AEP:NRC:1248                                        Page 1 DESCRIPTION OF CHANGES The  following unit    2  technical specifications (T/S) 3.1.3.3 and    3.10.5  and  associated    surveillances and bases are affected by the proposed change.
T  S  3  4 1 3 3 Delete the Reactivity Control Systems, Position Indicator Channels      -Shutdown,     Limiting Condition for Operation (3.1.3.3) and the associated surveillance (4.1.3.3) (page 3/4 1-22).
T  S  3  4 10.5 Delete    the    Special    Test Exception, Position Indicator Channels Shutdown,     Limiting Condition for Operation (3.10.5) and the associated        surveillances (4.10.5.1 and 4.10.5.2)
(page 3/4 10-5).
Also, delete the bases reference to T/S 3/4.10.5, Position Indicator Channel - Shutdown (page B 3/4 10-1)
Index Delete reference to "Position Indicator Channels - Shutdown,"
from the technical specification Index (page IV).
II. JUSTIFICATION      FOR CHANGES The  axial position of shutdown rods and control rods is determined by two separate and independent systems: the bank demand position indication system and the analog rod position indication (ARPI) system.
The    current unit    2 T/Ss require the ARPI system to be OPERABLE    for  each shutdown and control rod not fully inserted in modes 3, 4, and 5. To satisfy this requirement, two sets of ARPI calibrations must be performed. One calibration is performed on an individual rod bank basis to satisfy the ARPI requirements during rod drop testing in accordance with T/S 3/4.10.5.       The second calibration is performed at the completion of the "bank" calibration sequence to ensure that the rods are calibrated correctly to address bank overlap.
These calibrations are redundant and time intensive.
Additionally, in      modes 3, 4, and 5,   the boron concentration in the reactor coolant        system (RCS)   is increased to ensure that adequate shutdown margin (SDM) is achieved and maintained in accordance with existing Cook Nuclear Plant T/Ss. The calculation used to obtain
 
ATTACHMENT TO AEP:NRC:1248                                          Page 2 the required boron concentration        takes  into account the relative position of the control and      shutdown rods. Strict procedural controls are in place at        Cook Nuclear    Plant to ensure  that  an  all  rods out shutdown margin is maintained during rod position indicator calibration.
The adjustment      of boron concentration to assure adequate shutdown margin in modes 3, 4, and 5 is also supported by the Improved Standard Technical Specifications              (ISTS) for Westinghouse Plants (NUREG-1431). The ISTS does not contain a T/S for rod position indication in modes 3, 4, and 5; however, the bases position for the modes 1 and 2 T/Ss address the shutdown modes in the following manner.
      "In shutdown    MODES,   the OPERABILITY of the shutdown and control banks    has the  potential to affect the required SDM (shutdown margin), but this effect can be compensated for by an increase in the boron concentration of the Reactor Coolant System."
Therefore, the assurance that adequate shutdown margin exists for an all rods out condition in modes 3, 4, and 5 negates the need for rod position indication in these modes.
Technical specification 3.10,5 is a "special test exception" directly tied to T/S 3.1.3.3. Specifically,         it  provides an exemption from the "position indicator channel - shutdown" requirements during rod drop testing.           Deletion of this specification is necessary since the primary specification 3.1.3.3 is being deleted.
It is  concluded that the deletion of T/S 3.1.3.3, Position Indication Channels - Shutdown, does not result in a reduction in safety as the impact on shutdown margin is adequately    compensated    for by an increase in boron concentration that is consistent with the guidance of NUREG-1431.
III. 10 CFR 50 92 CRITERIA Per 10  CFR  50.92, this proposed change does not involve a significant    hazards consideration because the change does not:
involve    a  significant increase in the probability or consequences    of an accident previously evaluated,
: 2. create the possibility of a new or different kind of accident from any accident previously evaluated, or
: 3. involve  a  significant reduction in  a margin  of safety.
to AEP:NRC:1248                                          Page 3 Criterion  1 The boron  concentration in the reactor coolant system    will be high enough to assure adequate  SDM in modes 3, 4, and 5. The  calculation to obtain the required boron concentration takes into account the position of the rods. Shutdown margin is assumed as an initial condition in the safety analysis. The safety analysis establishes a SDM that ensures specified acceptable fuel design limits are not exceeded. As long as the SDM is satisfied, no change in the probability or consequences of an accident previously evaluated will result from the proposed deletion of the "position indicator shutdown" specification. It is noted that this change is consistent with the new ISTS approved by the NRC as NUREG-1431, Rev. l.
Criterion  2 The  ability to insert the control and shutdown rods provided by the rod control system is not affected by the OPERABILITY status of the ARPI system. As mentioned previously, the reactor coolant system boron concentration will be high enough to assure adequate SDM is maintained. Therefore,   it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
Criterion  3 The margin  of safety requirements, are not affected by the removal of this T/S. The required SDM which is an initial condition in the safety analysis, is unaffected since the reactor coolant system boron concentration is increased to address the. potential "all rods out" configuration. Based on these considerations, it is concluded that the proposed changes do not'involve a significant reduction in a margin of safety.}}

Latest revision as of 00:13, 4 February 2020

Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
ML17333A355
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 03/12/1996
From: Fitzpatrick E
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A356 List:
References
AEP:NRC:1248, NUDOCS 9603200113
Download: ML17333A355 (7)
v • d • e


Text

t CATEGORY j.

REGULAT+ INFORMATION DISTRIBUTIONOZSTEM (RIDE)

ACCESS.:GN -NBR.:9603200113 DOC.DATE: 96/03/12 NOTARIZED: YES DOCKET FACIL:50.-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Mi'chigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to license DPR-74,removing TSs re shutdown 6 control rod position indication while in modes 3, 4S5.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERN . g CENTER 1 1 NRR/DE/EMCB 1 1 CB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDSN RECIPIENTS )

PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415"20B3) TO ELIMINATE YOUR NAME FROM DXSTRKBUTXON LXSTS "'FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL . 11

Indiana Michigan Power Company

~

PO Box 16631 Columbus, OH 43216 INOlANA NlCHIGAN POWER March 12, 1996 AEP:NRC:1248 Docket Nos.: 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Unit 2 PROPOSED AMENDMENT TO REMOVE TECHNICAL SPECIFICATIONS 3.1.3.3 AND 3.10.5, "ROD POSITION INDICATOR CHANNELS-SHUTDOWN," TO ACHIEVE CONSISTENCY WITH DONALD C. COOK NUCLEAR PLANT UNIT 1 AND NUREG-1431.

This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss) for Donald C. Cook Nuclear Plant unit 2. Specifically, we are proposing to remove the T/Ss related to shutdown and control rod position indication while in modes 3, 4, and 5. The following unit 2 T/Ss are affected: 3.1.3.3 and 3.10.5 and associated surveillances and bases.

The existing Cook Nuclear Plant unit 2 T/Ss require that rod position indication be OPERABLE for each shutdown and control rod not fully inserted in modes 3, 4, and 5. If OPERABILITY cannot be assured, the number of control or shutdown rods that can be withdrawn is limited to a single bank while performing rod drop tests. This requirement is overly restrictive since, during shutdown modes, the ability to ensure adequate shutdown margin can be compensated by an increase in the boron concentration of the reactor coolant system.

In addition to the reduction in unnecessary requirements, the proposed, amendment would also align the affected unit 2 T/Ss with the unit 1 T/Ss and the improved standard technical specifications issued by the NRC as NUREG-1431, Revision 1.

Attachment 1 provides a detailed description of the proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked

'76032001i3 9603i2 00 PDR ADQCK 05000316 PDR P l~

U. S. Nuclear Regulatory Commission AEP:NRC:1248 Page 2 to reflect the proposed changes. Attachment 3 contains the proposed T/S pages.

We believe the proposed changes will not result in (1) a significant change in the types of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.

These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed at the next regularly scheduled Nuclear Safety and Design Review Committee meeting.

It is requested that the proposed amendment be approved by April 12, 1996 in support of the upcoming unit 2 refueling.

In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.

ca~

E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME otary Public pit Attachment cc: A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett

ATTACHMENT 1 TO AEP:NRC:1248 DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD CD COOK NUCLEAR PLANT UNIT 2 TECHNICAL SPECIFICATIONS

ATTACHMENT TO AEP:NRC:1248 Page 1 DESCRIPTION OF CHANGES The following unit 2 technical specifications (T/S) 3.1.3.3 and 3.10.5 and associated surveillances and bases are affected by the proposed change.

T S 3 4 1 3 3 Delete the Reactivity Control Systems, Position Indicator Channels -Shutdown, Limiting Condition for Operation (3.1.3.3) and the associated surveillance (4.1.3.3) (page 3/4 1-22).

T S 3 4 10.5 Delete the Special Test Exception, Position Indicator Channels Shutdown, Limiting Condition for Operation (3.10.5) and the associated surveillances (4.10.5.1 and 4.10.5.2)

(page 3/4 10-5).

Also, delete the bases reference to T/S 3/4.10.5, Position Indicator Channel - Shutdown (page B 3/4 10-1)

Index Delete reference to "Position Indicator Channels - Shutdown,"

from the technical specification Index (page IV).

II. JUSTIFICATION FOR CHANGES The axial position of shutdown rods and control rods is determined by two separate and independent systems: the bank demand position indication system and the analog rod position indication (ARPI) system.

The current unit 2 T/Ss require the ARPI system to be OPERABLE for each shutdown and control rod not fully inserted in modes 3, 4, and 5. To satisfy this requirement, two sets of ARPI calibrations must be performed. One calibration is performed on an individual rod bank basis to satisfy the ARPI requirements during rod drop testing in accordance with T/S 3/4.10.5. The second calibration is performed at the completion of the "bank" calibration sequence to ensure that the rods are calibrated correctly to address bank overlap.

These calibrations are redundant and time intensive.

Additionally, in modes 3, 4, and 5, the boron concentration in the reactor coolant system (RCS) is increased to ensure that adequate shutdown margin (SDM) is achieved and maintained in accordance with existing Cook Nuclear Plant T/Ss. The calculation used to obtain

ATTACHMENT TO AEP:NRC:1248 Page 2 the required boron concentration takes into account the relative position of the control and shutdown rods. Strict procedural controls are in place at Cook Nuclear Plant to ensure that an all rods out shutdown margin is maintained during rod position indicator calibration.

The adjustment of boron concentration to assure adequate shutdown margin in modes 3, 4, and 5 is also supported by the Improved Standard Technical Specifications (ISTS) for Westinghouse Plants (NUREG-1431). The ISTS does not contain a T/S for rod position indication in modes 3, 4, and 5; however, the bases position for the modes 1 and 2 T/Ss address the shutdown modes in the following manner.

"In shutdown MODES, the OPERABILITY of the shutdown and control banks has the potential to affect the required SDM (shutdown margin), but this effect can be compensated for by an increase in the boron concentration of the Reactor Coolant System."

Therefore, the assurance that adequate shutdown margin exists for an all rods out condition in modes 3, 4, and 5 negates the need for rod position indication in these modes.

Technical specification 3.10,5 is a "special test exception" directly tied to T/S 3.1.3.3. Specifically, it provides an exemption from the "position indicator channel - shutdown" requirements during rod drop testing. Deletion of this specification is necessary since the primary specification 3.1.3.3 is being deleted.

It is concluded that the deletion of T/S 3.1.3.3, Position Indication Channels - Shutdown, does not result in a reduction in safety as the impact on shutdown margin is adequately compensated for by an increase in boron concentration that is consistent with the guidance of NUREG-1431.

III. 10 CFR 50 92 CRITERIA Per 10 CFR 50.92, this proposed change does not involve a significant hazards consideration because the change does not:

involve a significant increase in the probability or consequences of an accident previously evaluated,

2. create the possibility of a new or different kind of accident from any accident previously evaluated, or
3. involve a significant reduction in a margin of safety.

to AEP:NRC:1248 Page 3 Criterion 1 The boron concentration in the reactor coolant system will be high enough to assure adequate SDM in modes 3, 4, and 5. The calculation to obtain the required boron concentration takes into account the position of the rods. Shutdown margin is assumed as an initial condition in the safety analysis. The safety analysis establishes a SDM that ensures specified acceptable fuel design limits are not exceeded. As long as the SDM is satisfied, no change in the probability or consequences of an accident previously evaluated will result from the proposed deletion of the "position indicator shutdown" specification. It is noted that this change is consistent with the new ISTS approved by the NRC as NUREG-1431, Rev. l.

Criterion 2 The ability to insert the control and shutdown rods provided by the rod control system is not affected by the OPERABILITY status of the ARPI system. As mentioned previously, the reactor coolant system boron concentration will be high enough to assure adequate SDM is maintained. Therefore, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

Criterion 3 The margin of safety requirements, are not affected by the removal of this T/S. The required SDM which is an initial condition in the safety analysis, is unaffected since the reactor coolant system boron concentration is increased to address the. potential "all rods out" configuration. Based on these considerations, it is concluded that the proposed changes do not'involve a significant reduction in a margin of safety.

Retrieved from "https://kanterella.com/w/index.php?title=ML17333A355&oldid=2425348"