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| {{#Wiki_filter:CATEGORYj.REGULAT+INFORMATION DISTRIBUTIONOZSTEM (RIDE)DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | {{#Wiki_filter:CATEGORY j.REGULAT+INFORMATION DISTRIBUTIONOZSTEM (RIDE)DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: |
| GeneralDistribution tACCESS.:GN
| | General Distribution t ACCESS.:GN-NBR.:9603200113 DOC.DATE: 96/03/12 NOTARIZED: |
| -NBR.:9603200113 DOC.DATE: | | YES DOCKET FACIL:50.-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E. |
| 96/03/12NOTARIZED: | | Indiana Michigan Power Co.(formerly Indiana&Mi'chigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| YESDOCKETFACIL:50.-316 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
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| IndianaMichiganPowerCo.(formerly Indiana&Mi'chigan EleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendtolicenseDPR-74,removing TSsreshutdown6controlrodpositionindication whileinmodes3,4S5.NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL11INTERN.gCENTERCBNRR/DSSA/SRXB OGC/HDS2EXTERNAL: | | Application for amend to license DPR-74,removing TSs re shutdown 6 control rod position indication while in modes 3, 4S5.NOTES: RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 1 1 INTERN.g CENTER CB NRR/DSSA/SRXB OGC/HDS2 EXTERNAL: NOAC 1 1 1 1 1 1 1 0 1 1 NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDSN RECIPIENTS |
| NOAC1111111011NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR11111111NOTETOALL"RIDSNRECIPIENTS
| | )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: |
| )PLEASEHELPUSTOREDUCEWASTElCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT. | | 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 PDR ADQCK 05000316 P PDR 00 l~ |
| 415"20B3) | | U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:1248 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. |
| TOELIMINATE YOURNAMEFROMDXSTRKBUTXON LXSTS"'FORDOCUMENTS YOUDON'TNEEDlTOTALNUMBEROFCOPIESREQUIRED:
| | 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 |
| LTTR12ENCL.11 IndianaMichigan~PowerCompanyPOBox16631Columbus, OH43216INOlANANlCHIGANPOWERMarch12,1996AEP:NRC:1248 DocketNos.:50-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | , 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 DESCRIPTION OF CHANGES Page 1 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. |
| DonaldC.CookNuclearPlantUnit2PROPOSEDAMENDMENT TOREMOVETECHNICAL SPECIFICATIONS 3.1.3.3AND3.10.5,"RODPOSITIONINDICATOR CHANNELS-SHUTDOWN,"
| | 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. |
| TOACHIEVECONSISTENCY WITHDONALDC.COOKNUCLEARPLANTUNIT1ANDNUREG-1431.Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantunit2.Specifically, weareproposing toremovetheT/Ssrelatedtoshutdownandcontrolrodpositionindication whileinmodes3,4,and5.Thefollowing unit2T/Ssareaffected:
| | 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. |
| 3.1.3.3and3.10.5andassociated surveillances andbases.TheexistingCookNuclearPlantunit2T/Ssrequirethatrodpositionindication beOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.IfOPERABILITY cannotbeassured,thenumberofcontrolorshutdownrodsthatcanbewithdrawn islimitedtoasinglebankwhileperforming roddroptests.Thisrequirement isoverlyrestrictive since,duringshutdownmodes,theabilitytoensureadequateshutdownmargincanbecompensated byanincreaseintheboronconcentration ofthereactorcoolantsystem.Inadditiontothereduction inunnecessary requirements, theproposed, amendment wouldalsoaligntheaffectedunit2T/Sswiththeunit1T/Ssandtheimprovedstandardtechnical specifications issuedbytheNRCasNUREG-1431, Revision1.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarked'76032001i3 9603i2PDRADQCK05000316PPDR00l~ | | 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). |
| U.S.NuclearRegulatory Commission Page2AEP:NRC:1248 toreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | | 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. |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedatthenextregularly scheduled NuclearSafetyandDesignReviewCommittee meeting.Itisrequested thattheproposedamendment beapprovedbyApril12,1996insupportoftheupcomingunit2refueling.
| | Attachment 1 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. |
| Incompliance withtherequirements of10CFR50.91(b)(1),
| | 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. |
| copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.ca~E.E.Fitzpatrick
| | 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. |
| ,VicePresident SWORNTOANDSUBSCRIBED BEFOREMEotaryPublicpitAttachment cc:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector | | 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. |
| -BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC:1248 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDCDCOOKNUCLEARPLANTUNIT2TECHNICAL SPECIFICATIONS ATTACHMENT TOAEP:NRC:1248 DESCRIPTION OFCHANGESPage1Thefollowing unit2technical specifications (T/S)3.1.3.3and3.10.5andassociated surveillances andbasesareaffectedbytheproposedchange.TS34133DeletetheReactivity ControlSystems,PositionIndicator Channels-Shutdown, LimitingCondition forOperation (3.1.3.3) andtheassociated surveillance (4.1.3.3) | | Based on these considerations, it is concluded that the proposed changes do not'involve a significant reduction in a margin of safety.}} |
| (page3/41-22).TS3410.5DeletetheSpecialTestException, PositionIndicator ChannelsShutdown, LimitingCondition forOperation (3.10.5)andtheassociated surveillances (4.10.5.1 and4.10.5.2) | |
| (page3/410-5).Also,deletethebasesreference toT/S3/4.10.5, PositionIndicator Channel-Shutdown(pageB3/410-1)IndexDeletereference to"Position Indicator Channels-Shutdown," | |
| fromthetechnical specification Index(pageIV).II.JUSTIFICATION FORCHANGESTheaxialpositionofshutdownrodsandcontrolrodsisdetermined bytwoseparateandindependent systems:thebankdemandpositionindication systemandtheanalogrodpositionindication (ARPI)system.Thecurrentunit2T/SsrequiretheARPIsystemtobeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.Tosatisfythisrequirement, twosetsofARPIcalibrations mustbeperformed.
| |
| Onecalibration isperformed onanindividual rodbankbasistosatisfytheARPIrequirements duringroddroptestinginaccordance withT/S3/4.10.5.
| |
| Thesecondcalibration isperformed atthecompletion ofthe"bank"calibration sequencetoensurethattherodsarecalibrated correctly toaddressbankoverlap.Thesecalibrations areredundant andtimeintensive.
| |
| Additionally, inmodes3,4,and5,theboronconcentration inthereactorcoolantsystem(RCS)isincreased toensurethatadequateshutdownmargin(SDM)isachievedandmaintained inaccordance withexistingCookNuclearPlantT/Ss.Thecalculation usedtoobtain ATTACHMENT TOAEP:NRC:1248 Page2therequiredboronconcentration takesintoaccounttherelativepositionofthecontrolandshutdownrods.Strictprocedural controlsareinplaceatCookNuclearPlanttoensurethatanallrodsoutshutdownmarginismaintained duringrodpositionindicator calibration. | |
| Theadjustment ofboronconcentration toassureadequateshutdownmargininmodes3,4,and5isalsosupported bytheImprovedStandardTechnical Specifications (ISTS)forWestinghouse Plants(NUREG-1431).
| |
| TheISTSdoesnotcontainaT/Sforrodpositionindication inmodes3,4,and5;however,thebasespositionforthemodes1and2T/Ssaddresstheshutdownmodesinthefollowing manner."InshutdownMODES,theOPERABILITY oftheshutdownandcontrolbankshasthepotential toaffecttherequiredSDM(shutdown margin),butthiseffectcanbecompensated forbyanincreaseintheboronconcentration oftheReactorCoolantSystem."Therefore, theassurance thatadequateshutdownmarginexistsforanallrodsoutcondition inmodes3,4,and5negatestheneedforrodpositionindication inthesemodes.Technical specification 3.10,5isa"specialtestexception" directlytiedtoT/S3.1.3.3.Specifically, itprovidesanexemption fromthe"position indicator channel-shutdown" requirements duringroddroptesting.Deletionofthisspecification isnecessary sincetheprimaryspecification 3.1.3.3isbeingdeleted.Itisconcluded thatthedeletionofT/S3.1.3.3,PositionIndication Channels-Shutdown, doesnotresultinareduction insafetyastheimpactonshutdownmarginisadequately compensated forbyanincreaseinboronconcentration thatisconsistent withtheguidanceofNUREG-1431.III.10CFR5092CRITERIAPer10CFR50.92,thisproposedchangedoesnotinvolveasignificant hazardsconsideration becausethechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.
| |
| Attachment 1toAEP:NRC:1248 Page3Criterion 1Theboronconcentration inthereactorcoolantsystemwillbehighenoughtoassureadequateSDMinmodes3,4,and5.Thecalculation toobtaintherequiredboronconcentration takesintoaccountthepositionoftherods.Shutdownmarginisassumedasaninitialcondition inthesafetyanalysis. | |
| Thesafetyanalysisestablishes aSDMthatensuresspecified acceptable fueldesignlimitsarenotexceeded.
| |
| AslongastheSDMissatisfied, nochangeintheprobability orconsequences ofanaccidentpreviously evaluated willresultfromtheproposeddeletionofthe"position indicator shutdown" specification.
| |
| Itisnotedthatthischangeisconsistent withthenewISTSapprovedbytheNRCasNUREG-1431, Rev.l.Criterion 2TheabilitytoinsertthecontrolandshutdownrodsprovidedbytherodcontrolsystemisnotaffectedbytheOPERABILITY statusoftheARPIsystem.Asmentioned previously, thereactorcoolantsystemboronconcentration willbehighenoughtoassureadequateSDMismaintained.
| |
| Therefore, itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. | |
| Criterion 3Themarginofsafetyrequirements, arenotaffectedbytheremovalofthisT/S.TherequiredSDMwhichisaninitialcondition inthesafetyanalysis, isunaffected sincethereactorcoolantsystemboronconcentration isincreased toaddressthe.potential "allrodsout"configuration. | |
| Basedontheseconsiderations, itisconcluded thattheproposedchangesdonot'involve asignificant reduction inamarginofsafety.}}
| |
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Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing 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 ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,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 ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,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 ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing 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 ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,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 ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
CATEGORY j.REGULAT+INFORMATION DISTRIBUTIONOZSTEM (RIDE)DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution t 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.NOTES: RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD3-1 PD COPIES LTTR ENCL 1 1 INTERN.g CENTER CB NRR/DSSA/SRXB OGC/HDS2 EXTERNAL: NOAC 1 1 1 1 1 1 1 0 1 1 NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR 1 1 1 1 1 1 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 PDR ADQCK 05000316 P PDR 00 l~
U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:1248 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 DESCRIPTION OF CHANGES Page 1 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.
Attachment 1 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.