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| | issue date = 03/15/1984 | | | issue date = 03/15/1984 |
| | title = Application to Amend License DPR-74,revising Tech Specs Re Flowrate for Flow Balance Test of Safety Injection Pumps | | | title = Application to Amend License DPR-74,revising Tech Specs Re Flowrate for Flow Balance Test of Safety Injection Pumps |
| | author name = ALEXICH M P | | | author name = Alexich M |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = DENTON H R | | | addressee name = Denton H |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000316 | | | docket = 05000316 |
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| =Text= | | =Text= |
| {{#Wiki_filter:REGULATORY INOR@ATIONDISTRIBUTION SYSTEM(RIDS)ACCESSION NBR8403200210DUC~DATE84/03/15NOTARIZEDNOFACIL:50316DonaldC.CookNuclearPowerPlantiUnit2~IndianaAUTHINANEAUTHORAFFILIATION ALEXICH~M.P. | | {{#Wiki_filter:REGULATORY IN OR@ATION DISTRIBUTION SYSTEM (RIDS) |
| IndianaIlMichiganElectricCo~RECIP,NAME RECIPIENT AFFILIATION DENTONtH~REOfficeofNuclearReactorRegulationr Director
| | ACCESSION NBR 840320 02 1 0 DUC ~ DATE 84/03/ 15 NOTAR I ZED NO DOCKET ¹ FACIL:50 316 Donald C. Cook Nuclear Power Pl anti Unit 2~ Indiana 05000316 AUTH INANE AUTHOR AFFILIATION ALEXICH~M.P. Indiana Il Michigan El ectr i c Co ~ |
| | RECIP,NAME RECIPIENT AFFILIATION DENTONtH ~ RE Office of Nuclear Reactor Regulationr Director |
|
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application toamenaLicenseDPH-74<revising TechSpecsreflowratefortlowbalancetestofsafetyinjection pumps'ISTRIBUTIUN CODE:IE2cSCOPIESRECEIVED:LTR ENCLSIZE:TITLE!Start-UpReport/RefuelingReport(50Dkt).NOTES:DOCKET¹05000316RECIPIENT IDCODE/NAME NRRORB1BC04INTERNAL: | | Application to amena License DPH-74<revising Tech Specs re f lowrate for tlow balance test of safety injection CODE: IE2c S COPIES RECEIVED:LTR ENCL SIZE: |
| IEFILE01'RR/DHFS'DIR 08NRR/OSI/CPBCOPIESLTTRENCL3111'11RECIPIENT IDCODE/NAME
| | pumps'ISTRIBUTIUN TITLE! Start-Up Report/ Refuel ing Report (50 Dkt). |
| .NRR/DHFSDEPY07NRR/DHFS/PSRB11 Rf/DDAMI/MIB 09COPIESLTTRENCL1]1EXTERNAL; ACRSNRCPDRNTIS.130251111LPDRNSIC0305lgTOTALNUHBEHOFCOPIESREQUIRED:
| | NOTES: |
| LTTR~ENCLb INDIANA&MICHIGANELECTRICCOMPANYP.O.BOX16631COLUMBUS, OHIO43216March.15,1984AEP:NRC:0860A DonaldC.CookNuclearPlantUnitNo.2DocketNo.50-316LicenseNo.DPR-7'4AMENDMENT TOTHEAPPLICATION FORUNIT2TECHNZCAL SPECIFICATION CHANGESFORCYCLE5RELOADMr.HaroldR.Denton,DirectorOfficeofNuclearReactorRegulation U.,S.Nuclear.Regulatory Commission Washington, D.C.20555 | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 04 3 INTERNAL: IE FILE 01 1 1 . NRR/DHFS DEPY07 1 |
| | 'RR/DHFS'DIR 08 1' NRR/DHFS/PSRB11 ] |
| | NRR/OS I/CPB 1 1 Rf /DDAMI/MIB 09 1 EXTERNAL; ACRS .13 5 LPDR 03 NRC PDR 02 1 1 NSIC 05 NTIS 1 1 lg TOTAL NUHBEH OF COPIES REQUIRED: LTTR ~ ENCL b |
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| ==DearMr.Denton:== | | INDIANA & MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March. 15, 1984 AEP:NRC:0860A Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-7'4 AMENDMENT TO THE APPLICATION FOR UNIT 2 TECHNZCAL SPECIFICATION CHANGES FOR CYCLE 5 RELOAD Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U., S. Nuclear. Regulatory Commission Washington, D. C. 20555 |
| Bythisletteranditsattachments, werequestanamendment totheapplication forTechnical Specification (T/S)changes,whichwasaddressed inourletterAEP:NRC:0860 datedMarch1,1984.Thisletterincludesadditional information relatedtotheseventhproposedchangeaddressed inAEP:NRC:0860; andrequestsoneadditional T/Schange.Thewordingoftheseventhchangehasbeenslightlymodifiedinthissubmittal tomakethechangeeasiertounderstand.
| | |
| Attachment 1tothisletteraddresses theSignificant HazardsConsideration, asrequiredtobesubmitted by10CFR50.91(a)(1),forthemodifiedversionoftheseventhproposedchangeofletterAEP:NRC:0860. | | ==Dear Mr. Denton:== |
| Theseventhproposedchangeconcerned theflowratefortheflowbalancetestfortheSafetyIn'jection (SZ)pumps'heSIpumpflowratewouldbeaffectedbyplannedmodifications toincreasetheminiflowoftheSZpumps.Theincreased miniflowwouldprovideaddedassurance ofadequatepumpcoolingwhilethepumpisoperating butnotinjecting tothecore.Znordertomakethephysicalmodifications forthischangeonareasonable timetable,wearerequesting anearlyindication byMarch23,1984oftheacceptability ofthisT/Schangerequest.Attachment 2tothisletteraddresses theadditional T/Schangethatisbeingrequested aspartoftheUnit2Cycle5reloadapplication andourSignificant HazardsConsideration analysispursuantto10CFR50.92forthischange.Attachment 3tothislettercontainstherevisedpagesfortheadditional T/Schanges(including themodifiedversionoftheseventhchangeproposedinAEP:NRC:0860).
| | |
| Thechangestotherevisedpagesare84032002l0 8403l5PDR*DOCK0500031hPPDRgrad>~.g~filee/I Mr.HaroldR.Dent~~AEP:NRC:0860A indicated byverticallinesontheright,handmaxginofthepage.TheT/Schangecontained inthisAttachment hasbeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheAEPSCNuclearSafetyandDesignReviewCommittee (NSDRC)attheirnextscheduled meeting.Attachment 4tothisletteristhesummaryofthesafetyevaluation performed byWestinghouse tosupportanincreasefrom30gpmto60gpminthesafetyinjection pumpminiflow.Asrequiredby10CFR50.91(b)(1),
| | By this letter and its attachments, we request an amendment to the application for Technical Specification (T/S) changes, which was addressed in our letter AEP:NRC:0860 dated March 1, 1984. This letter includes additional information related to the seventh proposed change addressed in AEP:NRC:0860; and requests one additional T/S change. |
| acopyof.thisamendedapplication isbeingtransmitted totheappropiiate officialoftheStateofMichigan.
| | The wording of the seventh change has been slightly modified in this submittal to make the change easier to understand. |
| Ourletter'EP:NRC:0860 transmitted theClassIVfeeleviedforthereviewoftheCycle5reloadofUnit2.WeconsidertheTechnical Specification changerequestscontained inthislettertobepartofthatx'eview.Therefox'e, webelievethatnofee,asdefinedin10CFR170.22,.isrequiredfortherequestsaddressed inthisletter.Thisdocumenthasbeenpreparedfollowing Corporate procedures whichincorporate a.reasonable setofcontrolstoinsureitsaccuracyandcompleteness priortosignature bytheundersigned.
| | Attachment 1 to this letter addresses the Significant Hazards Consideration, as required to be submitted by 10 CFR 50.91(a) (1), for the modified version of the seventh proposed change of letter AEP:NRC:0860. The seventh proposed change concerned the flowrate for the flow balance test for the Safety In'jection (SZ) pumps'he SI pump flowrate would be affected by planned modifications to increase the miniflow of the SZ pumps. The increased miniflow would provide added assurance of adequate pump cooling while the pump is operating but not injecting to the core. Zn order to make the physical modifications for this change on a reasonable time table, we are requesting an early indication by March 23, 1984 of the acceptability of this T/S change request. |
| Verytrulyyours,q5~M.P.exich4;~'VicePresident MPA/pbAttachments cc:JohnE.DolanW.G;'Smith, Ji.-BridgmanR.C.CallenG.CharnoffE.R.Swanson,NRCResidentInspector
| | Attachment 2 to this letter addresses the additional T/S change that is being requested as part of the Unit 2 Cycle 5 reload application and our Significant Hazards Consideration analysis pursuant to 10 CFR 50.92 for this change. |
| -Bridgman Mr.HaroldR.DentonAEPNRC0860AATTACHMENT 1TOAEP:NRC:0860ASIGNIFICANT HAZARDSCONSIDERATICN FORCERNGEINFLCNRATEFORTHESAFEZYINJECTICN PUMPSFECNBALAN~TEST | | Attachment 3 to this letter contains the revised pages for the additional T/S changes (including the modified version of the seventh change proposed in AEP:NRC:0860). The changes to the revised pages are 84032002l0 8403l5 PDR *DOCK 0500031h P PDR grad>~. g~ file e/I |
| 'Mr.HaroldR.DentoAEP:NRC:0860A Theseventhproposedchangeaddressed inletterAEP:NRC:0860 requested thefootnote(**)onpage3/45-6forT/S4.5.2.hbechangedtoread:**TotalSIS(singlepump)flow,including miniflow/shallnotexceed700gpmwithnomorethan640gpmbeingdelivered tothecore.Werequestthatthisproposedchangebemodifiedforclarity,toread:**Combined Loop1,2,3,and4ColdLegFlow(singlepump)(640gpm.TotalSIS(singlepump)flow,including | | |
| : miniflow, shallnotexceed700gpm.Theabovechangewillallowforincreased (miniflow) coolingoftheSafetyInjection pumpswhichprovidesincreased assurance ofadequate*pumpcoolingwhileusingminiflowcooling.Theincreaseinminiflowmayresultinasmalldecreasei:nflowfrom'thepumpstothecore.Westinghouse hasperformed asafetyevaluation oftheincreased SIpumpminiflowanddecreased injection flowtothecore.Thesummaryoftheirevaluation isenclosedasAttachment 4.Theresultsoftheirevaluation concluded thattheimpact'snegligible forlargebreakLOCAandan0increaseof86.1Finpeakcladtemperature (PCT)forthemostlimitingsmallbreakLOCA,basedonasensitivity analysisperformed onUnit1.TheadditionofthisincreaseinsmallbreakLOCAPCTtothecurrentD.C.CookUnit2smallbreakLOCAPCTof1668Fresultsina0valuewellbelowthe10CFR50.46limitof2200F.Basedondiscussions 0withyourstaff,weunderstand furtherinformation regarding theWestinghouse evaluation isneeded.Therefore, wewillsubmitadditional clarification oftheevaluation inthenearfuture.Wehavealsoperformed areviewoftheproposedflowrateontheintegrity oftheSIpumps.Ourreviewincludedacalculation todetermine theNetPositiveSuctionHead(NPSH)available totheSafetyInjection (SI)pumps.Inthecalculation weassumedthatSIwasintheinjection phaseandalignedwiththeRefueling WaterStorageTank(RWST);theRWSTwasatit'slowlowlevelsthewatertemperature was0100F;allsafetypumpswererunning(i.e.,ResidualHeatRemoval,Containment Spray,Centrifugal
| | Mr. Harold R. Dent AEP:NRC:0860A |
| : Charging, andSIpumps);andallpumpswereproducing maximumflow.Webelievetheassumedconditions constitute theworstcaseconditions fortheSIpumps.Theresultsofthecalculation indicated thatwiththeaboveconditions, therewouldbeaNPSHmarginofoversixteen(16)feetforbothoftheSIpumps.Therefore, theincreased flowrateiswithinthesafetyboundsofthepumprunoutandhasnosignificant adverseeffectontheintegrity ofthepumps.Basedontheabove,theproposedT/Schangemayresultinsomeincreasetotheconsequences ofapreviously analyzedaccidentormayreduceinsomewayasafetymargin,butitisourbeliefthattheresultsofthechangeareclearlywi.thinallacceptable criteriawithrespecttothesystemandcomponent's astheymayaffecttheSafetyAnalysisoftheplant.Thustheproposedchangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.
| | ~ ~ |
| Mr.HaroldR.Dento-5-AEP:NRC:0860A ATTACHMENT 2TOAEP:NRC:0860A ADDITIONAL TECHNICAL SPECIFICATION CHANGEREQUESTFORDONALDC.COOKNUCLEARPLANTUNITNO.2CYCLE5 Mr.HaroldR.Den-6-AEP:NRC:0860A TheeighthproposedchangeconcernsT/S3/4.10.5whichaddresses theRodPositionIndication (RPI)Channelsduringshutdown(MODES3,4,and5).Specifically, wearerequesting thatT/S3/4.10.5bechangedtoaddressthedemandpositionindicators insteadoftheindividual RPXs.Thereasonsandjustification forthischangeareasfollows:T/S4.1.3.4requiresroddroptimemeasurements offulllengthrodsbedemonstrated | | indicated by vertical lines on the right, hand maxgin of the page. The T/S change contained in this Attachment has been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee (NSDRC) at their next scheduled meeting. |
| ...following eachremovalofthereactorvesselhead,etc.T/S4.10.5statesrodpositionindication channelsshallbedetermined tobeOPERABLEbyverifying thedemandpositionindication systemandtherodpositionindication channelagreewithin12stepswithin24hourspriortothestartofroddroptimemeasurement... | | Attachment 4 to this letter is the summary of the safety evaluation performed by Westinghouse to support an increase from 30 gpm to 60 gpm in the safety injection pump miniflow. |
| Znordertoverifythe12stepagreement betweentheindividual RPZsandthedemandpositionindication system,theindividual RPIshavetobecalibrated.
| | As required by 10 CFR 50.91(b)(1), a copy of. this amended application is being transmitted to the appropiiate official of the State of Michigan. |
| TheRPZforeachindividual rodiscalibrated atthe~beginning ofafuelcyclewhenthereactorcoolantsystemisatoperating temperature.
| | Our letter'EP:NRC:0860 transmitted the Class IV fee levied for the review of the Cycle 5 reload of Unit 2. We consider the Technical Specification change requests contained in this letter to be part of that x'eview. Therefox'e, we believe that no fee, as defined in 10 CFR 170.22, .is required for the requests addressed in this letter. |
| Calibration isperformed atoperating temperature becausetheRPIsareextremely temperature sensitive andtherefore becomeincreasingly inaccurate overthelargetemperature changebetweenMODES5through3.Coiloperating temperature isnotestablished untiltheReactorCoolantSystem(RCS)reachesequilibrium afterascending throughMODES5,4,and3..Thecoiltakesapproximately six(6)hourstoreachequilibrium temperature, thusdelayingstartupofthereactor.Utilityexperience indicates thatthe(group)demandpositionindication systemshaveproventobeextremely reliableinWestinghouse reactors. | | This document has been prepared following Corporate procedures which incorporate a. reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned. |
| Demandpositionindication systemsarethemostaccuratemeansofdetermining rodpositionandareinfactusedtocalibrate theRPXs.Furthermore, theT/Ssrequirethatthereactorbemaintained inasubcritical, condition (k(0.99)topreventinadvertent criticality inMODES3,4,and5.Subcriticality canbeadequately maintained withsufficient boronconcentration andallbutoneshutdownorcontrolbankbeingfullyinserted.
| | Very truly yours, q5 ~ M. P. exich 4; ~'Vice President MPA/pb Attachments cc: John E. Dolan W. G;'Smith, Ji. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman |
| Criticality isnormallynotreacheduntiltheshutdownbanksandthreeofthefourcontrolbanksarefullywithdrawn. | | |
| T/S3.10.5willcontinuetorequireonlyoneshutdownorcontrolbankbewithdrawn fromthefullyinsertedpositionatatime,duringroddroptimemeasurements. | | Mr. Harold R. Denton AEP NRC 0860A ATTACHMENT 1 TO AEP:NRC: 0860A SIGNIFICANT HAZARDS CONSIDERATICN FOR CERNGE IN FLCNRATE FOR THE SAFEZY INJECTICN PUMPS FECN BALAN~ TEST |
| Therefore, webelievethereisadequatejustification. | | |
| fortheproposedchange,whichwouldeliminate thedelayinstartup.Thischangemayresultinsomeincreasetotheprobability orconsequences ofaprev'ously analyzedaccidentormayreduceinsomewayasafetymargin,butitisourbeliefthattheresultsofthechangeareclearlywithinallacceptable criteriawithrespecttothesystemorcomponents astheymayaffecttheSafetyAnalysisoftheplant.Thus,theproposedchangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CPR50.92.
| | 'Mr. Harold R. Dento AEP:NRC:0860A The seventh proposed change addressed in letter AEP:NRC:0860 requested the footnote (**) on page 3/4 5-6 for T/S 4.5.2.h be changed to read: |
| Mr.HaroldR.DentonAEP:NRC:0860AATTACHMENT 3TOAEP:NRC:0860A REVISEDTECHNICAL SPECIFICATION PAGESFORTHESEVENTHANDEIGHTHPROPOSEDCHANGES}} | | **Total SIS (single pump) flow, including miniflow/ |
| | shall not exceed 700 gpm with no more than 640 gpm being delivered to the core. |
| | We request that this proposed change be modified for clarity, to read: |
| | **Combined Loop 1, 2, 3, and 4 Cold Leg Flow (single pump) (640 gpm. Total SIS (single pump) flow, including miniflow, shall not exceed 700 gpm. |
| | The above change will allow for increased (miniflow) cooling of the Safety Injection pumps which provides increased assurance of adequate |
| | *pump cooling while using miniflow cooling. The increase in miniflow may result in a small decrease i:n flow from'the pumps to the core. |
| | Westinghouse has performed a safety evaluation of the increased SI pump miniflow and decreased injection flow to the core. The summary of their evaluation is enclosed as Attachment 4. The results of their evaluation concluded that the 0 impact 's negligible for large break LOCA and an increase of 86.1 F in peak clad temperature (PCT) for the most limiting small break LOCA, based on a sensitivity analysis performed on Unit 1. The addition of this increase in small break LOCA 0 PCT to the current D. C. Cook Unit 2 small break LOCA PCT of 1668 F results in a value well below the 10 CFR 50.46 limit of 2200 0 F. Based on discussions with your staff, we understand further information regarding the Westinghouse evaluation is needed. Therefore, we will submit additional clarification of the evaluation in the near future. |
| | We have also performed a review of the proposed flowrate on the integrity of the SI pumps. Our review included a calculation to determine the Net Positive Suction Head (NPSH) available to the Safety Injection (SI) pumps. In the calculation we assumed that SI was in the injection phase and aligned with the Refueling Water Storage Tank (RWST); |
| | 0 the RWST was at it's low low levels the water temperature was 100 F; all safety pumps were running (i.e., Residual Heat Removal, Containment Spray, Centrifugal Charging, and SI pumps); and all pumps were producing maximum flow. We believe the assumed conditions constitute the worst case conditions for the SI pumps. The results of the calculation indicated that with the above conditions, there would be a NPSH margin of over sixteen (16) feet for both of the SI pumps. |
| | Therefore, the increased flowrate is within the safety bounds of the pump runout and has no significant adverse effect on the integrity of the pumps. |
| | Based on the above, the proposed T/S change may result in some increase to the consequences of a previously analyzed accident or may reduce in some way a safety margin, but it is our belief that the results of the change are clearly wi.thin all acceptable criteria with respect to the system and component's as they may affect the Safety Analysis of the plant. Thus the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92. |
| | |
| | Mr. Harold R. Dento AEP:NRC:0860A ATTACHMENT 2 TO AEP:NRC:0860A ADDITIONAL TECHNICAL SPECIFICATION CHANGE REQUEST FOR DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 CYCLE 5 |
| | |
| | Mr. Harold R. Den AEP:NRC:0860A The eighth proposed change concerns T/S 3/4.10.5 which addresses the Rod Position Indication (RPI) Channels during shutdown (MODES 3, 4, and 5). Specifically, we are requesting that T/S 3/4.10.5 be changed to address the demand position indicators instead of the individual RPXs. |
| | The reasons and justification for this change are as follows: |
| | T/S 4.1.3.4 requires rod drop time measurements of full length rods be demonstrated ...following each removal of the reactor vessel head, etc. |
| | T/S 4.10.5 states rod position indication channels shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indication channel agree within 12 steps within 24 hours prior to the start of rod drop time measurement... |
| | Zn order to verify the 12 step agreement between the individual RPZs and the demand position indication system, the individual RPIs have to be calibrated. The RPZ for each individual rod is calibrated at the ~ |
| | beginning of a fuel cycle when the reactor coolant system is at operating temperature. Calibration is performed at operating temperature because the RPIs are extremely temperature sensitive and therefore become increasingly inaccurate over the large temperature change between MODES 5 through 3. |
| | Coil operating temperature is not established until the Reactor Coolant System (RCS) reaches equilibrium after ascending through MODES 5, 4, and 3.. The coil takes approximately six (6) hours to reach equilibrium temperature, thus delaying startup of the reactor. |
| | Utility experience indicates that the (group) demand position indication systems have proven to be extremely reliable in Westinghouse reactors. Demand position indication systems are the most accurate means of determining rod position and are in fact used to calibrate the RPXs. Furthermore, the T/Ss require that the reactor be maintained in a subcritical, condition (k (0.99) to prevent inadvertent criticality in MODES 3, 4, and 5. Subcriticality can be adequately maintained with sufficient boron concentration and all but one shutdown or control bank being fully inserted. Criticality is normally not reached until the shutdown banks and three of the four control banks are fully withdrawn. |
| | T/S 3.10.5 will continue to require only one shutdown or control bank be withdrawn from the fully inserted position at a time, during rod drop time measurements. |
| | Therefore, we believe there is adequate justification. for the proposed change, which would eliminate the delay in startup. |
| | This change may result in some increase to the probability or consequences of a prev'ously analyzed accident or may reduce in some way a safety margin, but it is our belief that the results of the change are clearly within all acceptable criteria with respect to the system or components as they may affect the Safety Analysis of the plant. Thus, the proposed change does not involve a significant hazards consideration as defined in 10 CPR 50.92. |
| | |
| | Mr. Harold R. Denton AEP: NRC: 0860A ATTACHMENT 3 TO AEP:NRC:0860A REVISED TECHNICAL SPECIFICATION PAGES FOR THE SEVENTH AND EIGHTH PROPOSED CHANGES}} |
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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
REGULATORY IN OR@ATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR 840320 02 1 0 DUC ~ DATE 84/03/ 15 NOTAR I ZED NO DOCKET ¹ FACIL:50 316 Donald C. Cook Nuclear Power Pl anti Unit 2~ Indiana 05000316 AUTH INANE AUTHOR AFFILIATION ALEXICH~M.P. Indiana Il Michigan El ectr i c Co ~
RECIP,NAME RECIPIENT AFFILIATION DENTONtH ~ RE Office of Nuclear Reactor Regulationr Director
SUBJECT:
Application to amena License DPH-74<revising Tech Specs re f lowrate for tlow balance test of safety injection CODE: IE2c S COPIES RECEIVED:LTR ENCL SIZE:
pumps'ISTRIBUTIUN TITLE! Start-Up Report/ Refuel ing Report (50 Dkt).
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 04 3 INTERNAL: IE FILE 01 1 1 . NRR/DHFS DEPY07 1
'RR/DHFS'DIR 08 1' NRR/DHFS/PSRB11 ]
NRR/OS I/CPB 1 1 Rf /DDAMI/MIB 09 1 EXTERNAL; ACRS .13 5 LPDR 03 NRC PDR 02 1 1 NSIC 05 NTIS 1 1 lg TOTAL NUHBEH OF COPIES REQUIRED: LTTR ~ ENCL b
INDIANA & MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 March. 15, 1984 AEP:NRC:0860A Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-7'4 AMENDMENT TO THE APPLICATION FOR UNIT 2 TECHNZCAL SPECIFICATION CHANGES FOR CYCLE 5 RELOAD Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U., S. Nuclear. Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
By this letter and its attachments, we request an amendment to the application for Technical Specification (T/S) changes, which was addressed in our letter AEP:NRC:0860 dated March 1, 1984. This letter includes additional information related to the seventh proposed change addressed in AEP:NRC:0860; and requests one additional T/S change.
The wording of the seventh change has been slightly modified in this submittal to make the change easier to understand.
Attachment 1 to this letter addresses the Significant Hazards Consideration, as required to be submitted by 10 CFR 50.91(a) (1), for the modified version of the seventh proposed change of letter AEP:NRC:0860. The seventh proposed change concerned the flowrate for the flow balance test for the Safety In'jection (SZ) pumps'he SI pump flowrate would be affected by planned modifications to increase the miniflow of the SZ pumps. The increased miniflow would provide added assurance of adequate pump cooling while the pump is operating but not injecting to the core. Zn order to make the physical modifications for this change on a reasonable time table, we are requesting an early indication by March 23, 1984 of the acceptability of this T/S change request.
Attachment 2 to this letter addresses the additional T/S change that is being requested as part of the Unit 2 Cycle 5 reload application and our Significant Hazards Consideration analysis pursuant to 10 CFR 50.92 for this change.
Attachment 3 to this letter contains the revised pages for the additional T/S changes (including the modified version of the seventh change proposed in AEP:NRC:0860). The changes to the revised pages are 84032002l0 8403l5 PDR *DOCK 0500031h P PDR grad>~. g~ file e/I
Mr. Harold R. Dent AEP:NRC:0860A
~ ~
indicated by vertical lines on the right, hand maxgin of the page. The T/S change contained in this Attachment has been reviewed and approved by the Plant Nuclear Safety Review Committee and will be reviewed by the AEPSC Nuclear Safety and Design Review Committee (NSDRC) at their next scheduled meeting.
Attachment 4 to this letter is the summary of the safety evaluation performed by Westinghouse to support an increase from 30 gpm to 60 gpm in the safety injection pump miniflow.
As required by 10 CFR 50.91(b)(1), a copy of. this amended application is being transmitted to the appropiiate official of the State of Michigan.
Our letter'EP:NRC:0860 transmitted the Class IV fee levied for the review of the Cycle 5 reload of Unit 2. We consider the Technical Specification change requests contained in this letter to be part of that x'eview. Therefox'e, we believe that no fee, as defined in 10 CFR 170.22, .is required for the requests addressed in this letter.
This document has been prepared following Corporate procedures which incorporate a. reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, q5 ~ M. P. exich 4; ~'Vice President MPA/pb Attachments cc: John E. Dolan W. G;'Smith, Ji. - Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman
Mr. Harold R. Denton AEP NRC 0860A ATTACHMENT 1 TO AEP:NRC: 0860A SIGNIFICANT HAZARDS CONSIDERATICN FOR CERNGE IN FLCNRATE FOR THE SAFEZY INJECTICN PUMPS FECN BALAN~ TEST
'Mr. Harold R. Dento AEP:NRC:0860A The seventh proposed change addressed in letter AEP:NRC:0860 requested the footnote (**) on page 3/4 5-6 for T/S 4.5.2.h be changed to read:
- Total SIS (single pump) flow, including miniflow/
shall not exceed 700 gpm with no more than 640 gpm being delivered to the core.
We request that this proposed change be modified for clarity, to read:
- Combined Loop 1, 2, 3, and 4 Cold Leg Flow (single pump) (640 gpm. Total SIS (single pump) flow, including miniflow, shall not exceed 700 gpm.
The above change will allow for increased (miniflow) cooling of the Safety Injection pumps which provides increased assurance of adequate
- pump cooling while using miniflow cooling. The increase in miniflow may result in a small decrease i:n flow from'the pumps to the core.
Westinghouse has performed a safety evaluation of the increased SI pump miniflow and decreased injection flow to the core. The summary of their evaluation is enclosed as Attachment 4. The results of their evaluation concluded that the 0 impact 's negligible for large break LOCA and an increase of 86.1 F in peak clad temperature (PCT) for the most limiting small break LOCA, based on a sensitivity analysis performed on Unit 1. The addition of this increase in small break LOCA 0 PCT to the current D. C. Cook Unit 2 small break LOCA PCT of 1668 F results in a value well below the 10 CFR 50.46 limit of 2200 0 F. Based on discussions with your staff, we understand further information regarding the Westinghouse evaluation is needed. Therefore, we will submit additional clarification of the evaluation in the near future.
We have also performed a review of the proposed flowrate on the integrity of the SI pumps. Our review included a calculation to determine the Net Positive Suction Head (NPSH) available to the Safety Injection (SI) pumps. In the calculation we assumed that SI was in the injection phase and aligned with the Refueling Water Storage Tank (RWST);
0 the RWST was at it's low low levels the water temperature was 100 F; all safety pumps were running (i.e., Residual Heat Removal, Containment Spray, Centrifugal Charging, and SI pumps); and all pumps were producing maximum flow. We believe the assumed conditions constitute the worst case conditions for the SI pumps. The results of the calculation indicated that with the above conditions, there would be a NPSH margin of over sixteen (16) feet for both of the SI pumps.
Therefore, the increased flowrate is within the safety bounds of the pump runout and has no significant adverse effect on the integrity of the pumps.
Based on the above, the proposed T/S change may result in some increase to the consequences of a previously analyzed accident or may reduce in some way a safety margin, but it is our belief that the results of the change are clearly wi.thin all acceptable criteria with respect to the system and component's as they may affect the Safety Analysis of the plant. Thus the proposed change does not involve a significant hazards consideration as defined in 10 CFR 50.92.
Mr. Harold R. Dento AEP:NRC:0860A ATTACHMENT 2 TO AEP:NRC:0860A ADDITIONAL TECHNICAL SPECIFICATION CHANGE REQUEST FOR DONALD C. COOK NUCLEAR PLANT UNIT NO. 2 CYCLE 5
Mr. Harold R. Den AEP:NRC:0860A The eighth proposed change concerns T/S 3/4.10.5 which addresses the Rod Position Indication (RPI) Channels during shutdown (MODES 3, 4, and 5). Specifically, we are requesting that T/S 3/4.10.5 be changed to address the demand position indicators instead of the individual RPXs.
The reasons and justification for this change are as follows:
T/S 4.1.3.4 requires rod drop time measurements of full length rods be demonstrated ...following each removal of the reactor vessel head, etc.
T/S 4.10.5 states rod position indication channels shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indication channel agree within 12 steps within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of rod drop time measurement...
Zn order to verify the 12 step agreement between the individual RPZs and the demand position indication system, the individual RPIs have to be calibrated. The RPZ for each individual rod is calibrated at the ~
beginning of a fuel cycle when the reactor coolant system is at operating temperature. Calibration is performed at operating temperature because the RPIs are extremely temperature sensitive and therefore become increasingly inaccurate over the large temperature change between MODES 5 through 3.
Coil operating temperature is not established until the Reactor Coolant System (RCS) reaches equilibrium after ascending through MODES 5, 4, and 3.. The coil takes approximately six (6) hours to reach equilibrium temperature, thus delaying startup of the reactor.
Utility experience indicates that the (group) demand position indication systems have proven to be extremely reliable in Westinghouse reactors. Demand position indication systems are the most accurate means of determining rod position and are in fact used to calibrate the RPXs. Furthermore, the T/Ss require that the reactor be maintained in a subcritical, condition (k (0.99) to prevent inadvertent criticality in MODES 3, 4, and 5. Subcriticality can be adequately maintained with sufficient boron concentration and all but one shutdown or control bank being fully inserted. Criticality is normally not reached until the shutdown banks and three of the four control banks are fully withdrawn.
T/S 3.10.5 will continue to require only one shutdown or control bank be withdrawn from the fully inserted position at a time, during rod drop time measurements.
Therefore, we believe there is adequate justification. for the proposed change, which would eliminate the delay in startup.
This change may result in some increase to the probability or consequences of a prev'ously analyzed accident or may reduce in some way a safety margin, but it is our belief that the results of the change are clearly within all acceptable criteria with respect to the system or components as they may affect the Safety Analysis of the plant. Thus, the proposed change does not involve a significant hazards consideration as defined in 10 CPR 50.92.
Mr. Harold R. Denton AEP: NRC: 0860A ATTACHMENT 3 TO AEP:NRC:0860A REVISED TECHNICAL SPECIFICATION PAGES FOR THE SEVENTH AND EIGHTH PROPOSED CHANGES
