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| | issue date = 07/16/1997 | | | issue date = 07/16/1997 |
| | title = Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing | | | title = Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing |
| | author name = BEMIS P R | | | author name = Bemis P |
| | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 12 | | | page count = 12 |
| | | project = |
| | | stage = Request |
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| =Text= | | =Text= |
| {{#Wiki_filter:CATEGORY1REGULRIINPORMATION'DISTRIBUTIOiOYSTEN (RIDE)ACCESSION NBR:9707230291 DOC.DATE: | | {{#Wiki_filter:CATEGORY 1 REGULR I INPORMATION'DISTRIBUTIOiOYSTEN (RIDE) |
| 97/07/16NOTARIZED: | | ACCESSION NBR:9707230291 DOC.DATE: 97/07/16 NOTARIZED: YES DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMES, P.R. Washington Public Power Supply System REClP.NAME RECIPIENT AFFILIATION Document, Control Branch (Document Control Desk) |
| YESDOCKETFACIL:50-397 WPPSSNuclearProject,Unit2,Washington PublicPowe05000397AUTH.NAMEAUTHORAFFILIATION BEMES,P.R.Washington PublicPowerSupplySystemREClP.NAME RECIPIENT AFFILIATION
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| : Document, ControlBranch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendtolicenseNPF-21,adding newminreactorvesselpressureversusreactorvesselmetaltemp(P/T)curves,applicable upto12Effective FullPowerYears.Changessupportvesselleaktesting.DISTRIBUTION CODE:BOOIDCOPIESRECEIVED:LTR IENCI,QSIZE:~+TITLE:ORSubmittal: | | Application for amend to license NPF-21,adding new min reactor vessel pressure versus reactor vessel metal temp (P/T) curves, applicable up to 12 Effective Full Power Years. |
| GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD4-2LACOLBURNgT COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD4-2PDCOPIESLTTRENCL11INTERNAL:
| | Changes support vessel leak testing. |
| ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3EXTERNAL:
| | DISTRIBUTION CODE: BOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution I ENCI, Q SIZE: ~+ |
| NOAC111111111011M7NRRDEEMCBNRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR1111111111NOTETOALL"RIDS"RECIPIENTS:
| | NOTES: |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 COLBURNgT 1 1 INTERNAL: ACRS 1 1 M7 1 1 NRR/DE/ECGB/A 1 1 NRR DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| 415-2083) | | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 |
| LTTR14ENCL13 WASHINGTON PUBLICPOWERSUPPLYSYSTEMP.O.Box968~Richland, Washington 99352-0968 July16,1997G02-97-144 DocketNo.50-397U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen:
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| | WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 July 16, 1997 G02-97-144 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
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| ==Subject:== | | ==Subject:== |
| WNP-2,OPERATING LICENSENPF-21REQUESTFORAMENDMENT TOTECHNICAL SPECIFICATIONS TOSUPPORTVESSELLEAKTESTING | | WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENTTO TECHNICALSPECIFICATIONS TO SUPPORT VESSEL LEAK TESTING |
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| ==References:== | | ==References:== |
| | : 1) Letter GO2-93-180, dated July 9, 1993, J. V. Parrish (SS) to NRC, "Request for Amendment to the Facility Operating License and Technical Specifications to Increase Licensed Power Level from 3323 MWt to 3486 MWt with Extended Load Line and a Change in Safety Relief Valve Set Point Tolerance" |
| | : 2) Letter G02-94-042, dated February 17, 1994, J. V. Parrish (SS) to NRC, "WNP-2 Operating License NPF-21 Request to Amend Technical Specifications to Support Hydrostatic Testing" |
| | : 3) Letter GI2-95-099, dated May 2, 1995, J.W. Clifford (NRC) to J.V. |
| | Parrish (SS) "Issuance of Amendment for Washington Public Power Supply System Nuclear Project No. 2 (TAC Nos. M87076 and M88625)" |
| | : 4) Letter GI2-94-148, dated May 27, 1994, L.M. Padovan (NRC) to J.V. |
| | Parrish (SS) "Issuance of Amendment for Washington Public Power Supply System Nuclear Project No. 2 (TAC No. M88839)" |
| | Re nest for Technical S ecification Amendment The Supply System hereby requests an amendment to the WNP-2 Technical Specifications in accordance with Title 10, Parts 50.90 and 2.101 of the Code of Federal Regulations. |
| | 970723029i 9'70716 PDR P |
| | ADQCK 0500039'7 PDR lllllllllilllllllllllllllllllilllllllll ~ggl |
| | ,".300."-8 |
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| | Page 2 Amendment to Technical Specifications to Support Vessel Leak Testing Specifically, the Supply System requests the addition of new minimum reactor vessel pressure versus reactor vessel metal temperature (P/T) curves, applicable up to 12 Effective Full Power Years (EFPY). The requested Technical Specification changes are necessary to support leak and hydrotesting in accordance with the American Society of Mechanical Engineers (ASME) |
| | Boiler and Pressure Vessel Code Section XI. |
| | Leak testing is a critical path item during our annual refueling outages. It is anticipated that the change described in this request can reduce the amount of time spent performing leak testing and thereby enhance personnel safety and outage schedule effectiveness. We request, therefore, that the requested amendment be issued in time to support the Spring 1998 refueling outage (R-13). Issuance of the requested amendment on or before May 1, 1998, will support our schedule. Details of the requested change are discussed below. |
| | Previ u Re u f rPr ure T m ure urveModification Reference 1 proposed new P/T curves under power uprate conditions for 32 EFPY. The basis for the 32 EFPY curves is found in Reference 1 and is not repeated herein. Reference 2 proposed hydrostatic testing utilizing an 8 EFPY curve that was developed using substantially the same methodology as the 32 EFPY curve. The difference in methodologies was identified on page 4 of Reference 2. The basis for hydrostatic testing is found in Reference 2 and is not repeated herein. The Reference 1 and 2 requests were approved by the NRC in References 3 and 4. |
| | The 12 EFPY curve in this submittal was developed using the same methodology as followed in Reference 2 utilizing a 12 EFPY temperature shift of 83.9'. |
| | Pur o e and U e of Pres ure/Tem erature Curve Pressure/Temperature Curves based on 12 EFPY of neutron fluence at power uprate conditions are used only for leak and hydrostatic testing conditions during non-nuclear heatup of the Reactor Pressure Vessel. It is possible to conduct leak and hydrostatic testing using the |
| | 'existing 32 EFPY curve. However, the testing conducted under the proposed 12 EFPY curves will result in a greater margin for worker industrial safety with no adverse impact to the public health and safety. |
| | Enhanced Worker Industrial afet Mar in Due to the lower total fluence level, the proposed 12 EFPY curves support use of a lower minimum reactor metal temperature at the required test pressure. The required minimum temperature for testing under the 12 EFPY curves is 185 degrees Fahrenheit. This is approximately 41 degrees Fahrenheit lower than that which would be required by testing using the 32 EFPY curve. |
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| | Page 3 Request for Amendment to Technical Specifications Support Vessel Leak Testing Significantly, then,,the 185 degree Fahrenheit reactor metal temperature corresponds to approximately a 200-210 degree Fahrenheit average Reactor Coolant System temperature (depending on the heat-up rate achieved and the time spent at the leak test temperature and pressure). The lower temperature of the 12 EFPY curves, therefore, provides a greater margin of industrial safety than would be provided using the 32 EFPY curve. The enhanced industrial safety margin is attributed to lower reactor water temperatures, higher remaining heat sink capacity, and avoidance of steam flashing. The margin of nuclear safety is actually increased by use of the proposed curves due to the lower allowed test temperature which increases the available heat sink for the RCS. Based on the foregoing, the margin of safety for the plant will not be reduced as a result of implementing the new 12 EFPY P/T curves. |
| | No Si nificant Hazards Consideration Determination The Supply System has evaluated the proposed change per the requirements of 10 CFR 50.92. |
| | The proposed addition of the 12 EFPY P/T curves for testing and non-nuclear heating does not represent a significant hazards consideration because it does not: |
| | : 1) Involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | The proposed 12 EFPY curve was developed using the same methodology as that used in the current 32 EFPY curve and the 8 EFPY curve. This methodology is consistent with the guidance provided in Regulatory Guide 1.99, Revision 2. |
| | Assumptions and parameters were the same as those used in the 8 EFPY curve calculation. However, fluence values used in the calculation were those for 12 EFPY. |
| | Use of the 12 EFPY curves on or before attainment of 12 EFPY of operation is equivalent to the previously approved use of the 32 EFPY curves on or before attainment of 32 EFPY of operation. |
| | Therefore, the proposed 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. |
| | The proposed change introduces no credible mechanism for unacceptable radiation release. |
| | The proposed change does not require physical modification to the plant. |
| | The 12 EFPY curves are consistent with the previously approved 32 and 8 EFPY curves. |
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| | Page 4 Request for Amendment to Technical Specifications Support Vessel Leak Testing Inservice hydrostatic or leak testing is not assumed to be an initiator of analyzed events. |
| | Since approval of the proposed amendment will ensure adequate protection of the reactor pressure vessel, it will not create the possibility of a new or different kind of accident from any previously evaluated. |
| | : 3) Involve a significant reduction in a margin of safety. |
| | The accident analyses for the plant as described in the FSAR are not affected by this proposed change. |
| | The 12 EFPY curves were developed using the same methodology as the 32 and 8 EFPY curves and thus involve no reduction in the margin of safety as previously evaluated. |
| | The margin of safety, relative to the available heat sink in the Reactor Coolant System, is actually increased by use of the proposed curves due to the lower allowed test temperature. |
| | Therefore, the proposed change does not involve a significant reduction in a margin of safety. |
| | A ment Cate orical Exclu ion The proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). The proposed change does not involve a significant hazards consideration, have a potential for a change in the types, or increase in the amount, of any effluents that may be released off-site; or involve an increase in individual or cumulative occupational radiation exposure. Therefore, per the requirements of 10 CFR 51.22(b), an environmental assessment of these changes is not required. |
| | In ernal and CNSRB Review This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. |
| | tate otification In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter. |
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| 1)LetterGO2-93-180, datedJuly9,1993,J.V.Parrish(SS)toNRC,"RequestforAmendment totheFacilityOperating LicenseandTechnical Specifications toIncreaseLicensedPowerLevelfrom3323MWtto3486MWtwithExtendedLoadLineandaChangeinSafetyReliefValveSetPointTolerance" 2)LetterG02-94-042, datedFebruary17,1994,J.V.Parrish(SS)toNRC,"WNP-2Operating LicenseNPF-21RequesttoAmendTechnical Specifications toSupportHydrostatic Testing"3)LetterGI2-95-099, datedMay2,1995,J.W.Clifford(NRC)toJ.V.Parrish(SS)"Issuance ofAmendment forWashington PublicPowerSupplySystemNuclearProjectNo.2(TACNos.M87076andM88625)"4)LetterGI2-94-148, datedMay27,1994,L.M.Padovan(NRC)toJ.V.Parrish(SS)"Issuance ofAmendment forWashington PublicPowerSupplySystemNuclearProjectNo.2(TACNo.M88839)"RenestforTechnical Secification Amendment TheSupplySystemherebyrequestsanamendment totheWNP-2Technical Specifications inaccordance withTitle10,Parts50.90and2.101oftheCodeofFederalRegulations.
| | Page 5 Request for Amendment to Technical Specifications Support Vessel Leak Testing Marku f Pr o ed han e provides copies of the impacted portion of the existing Technical Specifications. |
| 970723029i 9'70716PDRADQCK0500039'7 PPDR,".300."-8 lllllllllilllllllllllllllllllilllllllll
| | A clean version of the change as proposed is provided as Attachment 2. In order to be consistent with the Improved Technical Specifications the new 12 EFPY curves require that the figures in LCO 3.4.11 be renumbered. We have also included proposed changes to the Bases as Attachment 3. These changes are for your information only and will be made by the Supply System upon receipt of the approved amendment. We request thirty days to implement the amendment upon notification of its approval. |
| ~ggl a4III Page2Amendment toTechnical Specifications toSupportVesselLeakTestingSpecifically, theSupplySystemrequeststheadditionofnewminimumreactorvesselpressureversusreactorvesselmetaltemperature (P/T)curves,applicable upto12Effective FullPowerYears(EFPY).Therequested Technical Specification changesarenecessary tosupportleakandhydrotesting inaccordance withtheAmericanSocietyofMechanical Engineers (ASME)BoilerandPressureVesselCodeSectionXI.Leaktestingisacriticalpathitemduringourannualrefueling outages.Itisanticipated thatthechangedescribed inthisrequestcanreducetheamountoftimespentperforming leaktestingandtherebyenhancepersonnel safetyandoutagescheduleeffectiveness.
| | Should you have any questions or desire additional information regarding this matter, please call me or D. A. Swank at (509) 377-4563. |
| Werequest,therefore, thattherequested amendment beissuedintimetosupporttheSpring1998refueling outage(R-13).Issuanceoftherequested amendment onorbeforeMay1,1998,willsupportourschedule.
| | ectfully, P.. ail Drop PE23) |
| Detailsoftherequested changearediscussed below.PreviuReufrPrureTmureurveModification Reference 1proposednewP/Tcurvesunderpoweruprateconditions for32EFPY.Thebasisforthe32EFPYcurvesisfoundinReference 1andisnotrepeatedherein.Reference 2proposedhydrostatic testingutilizing an8EFPYcurvethatwasdeveloped usingsubstantially thesamemethodology asthe32EFPYcurve.Thedifference inmethodologies wasidentified onpage4ofReference 2.Thebasisforhydrostatic testingisfoundinReference 2andisnotrepeatedherein.TheReference 1and2requestswereapprovedbytheNRCinReferences 3and4.The12EFPYcurveinthissubmittal wasdeveloped usingthesamemethodology asfollowedinReference 2utilizing a12EFPYtemperature shiftof83.9'.PuroeandUeofPresure/TemeratureCurvePressure/Temperature Curvesbasedon12EFPYofneutronfluenceatpoweruprateconditions areusedonlyforleakandhydrostatic testingconditions duringnon-nuclear heatupoftheReactorPressureVessel.Itispossibletoconductleakandhydrostatic testingusingthe'existing 32EFPYcurve.However,thetestingconducted undertheproposed12EFPYcurveswillresultinagreatermarginforworkerindustrial safetywithnoadverseimpacttothepublichealthandsafety.EnhancedWorkerIndustrial afetMarinDuetothelowertotalfluencelevel,theproposed12EFPYcurvessupportuseofalowerminimumreactormetaltemperature attherequiredtestpressure.
| | Vice President, Nuclear Operations Attachments CC: EW Mershoff - NRC RIV KE Perkins, Jr. - NRC RIV, WCFO TG Colburn - NRR CR Wallis - EFSEC NRC Sr. Resident Inspector - 927N DL Williams - BPA/399 PD Robinson - Winston & Strawn |
| Therequiredminimumtemperature fortestingunderthe12EFPYcurvesis185degreesFahrenheit.
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| Thisisapproximately 41degreesFahrenheit lowerthanthatwhichwouldberequiredbytestingusingthe32EFPYcurve.
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| t.fIfII Page3RequestforAmendment toTechnical Specifications SupportVesselLeakTestingSignificantly, then,,the 185degreeFahrenheit reactormetaltemperature corresponds toapproximately a200-210degreeFahrenheit averageReactorCoolantSystemtemperature (depending ontheheat-uprateachievedandthetimespentattheleaktesttemperature andpressure).
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| Thelowertemperature ofthe12EFPYcurves,therefore, providesagreatermarginofindustrial safetythanwouldbeprovidedusingthe32EFPYcurve.Theenhancedindustrial safetymarginisattributed tolowerreactorwatertemperatures, higherremaining heatsinkcapacity, andavoidance ofsteamflashing.
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| Themarginofnuclearsafetyisactuallyincreased byuseoftheproposedcurvesduetothelowerallowedtesttemperature whichincreases theavailable heatsinkfortheRCS.Basedontheforegoing, themarginofsafetyfortheplantwillnotbereducedasaresultofimplementing thenew12EFPYP/Tcurves.NoSinificantHazardsConsideration Determination TheSupplySystemhasevaluated theproposedchangepertherequirements of10CFR50.92.Theproposedadditionofthe12EFPYP/Tcurvesfortestingandnon-nuclear heatingdoesnotrepresent asignificant hazardsconsideration becauseitdoesnot:1)Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
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| Theproposed12EFPYcurvewasdeveloped usingthesamemethodology asthatusedinthecurrent32EFPYcurveandthe8EFPYcurve.Thismethodology isconsistent withtheguidanceprovidedinRegulatory Guide1.99,Revision2.Assumptions andparameters werethesameasthoseusedinthe8EFPYcurvecalculation.
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| However,fluencevaluesusedinthecalculation werethosefor12EFPY.Useofthe12EFPYcurvesonorbeforeattainment of12EFPYofoperation isequivalent tothepreviously approveduseofthe32EFPYcurvesonorbeforeattainment of32EFPYofoperation.
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| Therefore, theproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
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| 2)Createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
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| Theproposedchangeintroduces nocrediblemechanism forunacceptable radiation release.Theproposedchangedoesnotrequirephysicalmodification totheplant.The12EFPYcurvesareconsistent withthepreviously approved32and8EFPYcurves.
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| Page4RequestforAmendment toTechnical Specifications SupportVesselLeakTestingInservice hydrostatic orleaktestingisnotassumedtobeaninitiator ofanalyzedevents.Sinceapprovaloftheproposedamendment willensureadequateprotection ofthereactorpressurevessel,itwillnotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated.
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| 3)Involveasignificant reduction inamarginofsafety.Theaccidentanalysesfortheplantasdescribed intheFSARarenotaffectedbythisproposedchange.The12EFPYcurvesweredeveloped usingthesamemethodology asthe32and8EFPYcurvesandthusinvolvenoreduction inthemarginofsafetyaspreviously evaluated. | |
| Themarginofsafety,relativetotheavailable heatsinkintheReactorCoolantSystem,isactuallyincreased byuseoftheproposedcurvesduetothelowerallowedtesttemperature.
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| Therefore, theproposedchangedoesnotinvolveasignificant reduction inamarginofsafety.AmentCateoricalExcluionTheproposedchangemeetstheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).
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| Theproposedchangedoesnotinvolveasignificant hazardsconsideration, haveapotential forachangeinthetypes,orincreaseintheamount,ofanyeffluents thatmaybereleasedoff-site; orinvolveanincreaseinindividual orcumulative occupational radiation exposure.
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| Therefore, pertherequirements of10CFR51.22(b),
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| anenvironmental assessment ofthesechangesisnotrequired.
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| InernalandCNSRBReviewThisTechnical Specification changehasbeenreviewedandapprovedbytheWNP-2PlantOperations Committee andtheSupplySystemCorporate NuclearSafetyReviewBoard.tateotification Inaccordance with10CFR50.91,theStateofWashington hasbeenprovidedacopyofthisletter.
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| Page5RequestforAmendment toTechnical Specifications SupportVesselLeakTestingMarkufProedhaneAttachment 1providescopiesoftheimpactedportionoftheexistingTechnical Specifications.
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| AcleanversionofthechangeasproposedisprovidedasAttachment 2.Inordertobeconsistent withtheImprovedTechnical Specifications thenew12EFPYcurvesrequirethatthefiguresinLCO3.4.11berenumbered.
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| WehavealsoincludedproposedchangestotheBasesasAttachment 3.Thesechangesareforyourinformation onlyandwillbemadebytheSupplySystemuponreceiptoftheapprovedamendment.
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| Werequestthirtydaystoimplement theamendment uponnotification ofitsapproval.
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| Shouldyouhaveanyquestions ordesireadditional information regarding thismatter,pleasecallmeorD.A.Swankat(509)377-4563.
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| : ectfully, P..ailDropPE23)VicePresident, NuclearOperations Attachments CC:EWMershoff-NRCRIVKEPerkins,Jr.-NRCRIV,WCFOTGColburn-NRRCRWallis-EFSECNRCSr.ResidentInspector
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| -927NDLWilliams-BPA/399PDRobinson-Winston&Strawn | |
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| STATEOFWASHINGTON
| | STATE OF WASHINGTON ) |
| ))COUNTYOFBENTON)
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| ==Subject:== | | ==Subject:== |
| RequestforAmendment toTStoSurtVeselLeakTestinI,P.R.BEMIS,beingdulysworn,subscribe toandsaythatIamtheVicePresident, NuclearOperations fortheWASHINGTON PUBLICPOWERSUPPLYSYSTEM,theapplicant herein;thatIhavethefullauthority toexecutethisoath;thatIhavereviewedtheforegoing; andthattothebestofmyknowledge, information, andbeliefthestatements madeinitaretrue.DATE,1997P..is'nt,NuclearOperations Onthisdatepersonally appearedbeforemeP,R.BEMIS,tomeknowntobetheindividual whoexecutedtheforegoing instrument, andacknowledge thathesignedthesameashisfreeactanddeedfortheusesandpurposeshereinmentioned.
| | Request for Amendment to TS to |
| G1VBNundermyhandandsealthis~&dayofS1997NotaryublicinanfortheSTATEOFWASHINGTON ResidingatMyCommission Expires
| | ) Su rt Ves el Leak Testin COUNTY OF BENTON ) |
| (~gg'LlI'l'elIlf((=e-"~lg~.~~:~~>)))1>iinl~>~ | | I, P. R. BEMIS, being duly sworn, subscribe to and say that I am the Vice President, Nuclear Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true. |
| ATTACKVH<2lT 1CurrentTechnical Specification PageswithProposedChanges}} | | DATE , 1997 P.. is |
| | 'nt, Nuclear Operations On this date personally appeared before me P, R. BEMIS, to me known to be the individual who executed the foregoing instrument, and acknowledge that he signed the same as his free act and deed for the uses and purposes herein mentioned. |
| | G1VBN under my hand and seal this ~&day of S 1997 Notary ublic in an for the STATE OF WASHINGTON Residing at My Commission Expires |
| | |
| | (~gg'Ll I'l'el I lf(( |
| | = e -" |
| | ~lg~. ~ ~: ~ |
| | ~>)))1>iinl~>~ |
| | |
| | ATTACKVH<2lT1 Current Technical Specification Pages with Proposed Changes}} |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17284A9101999-10-13013 October 1999
Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes
ML17284A8501999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown.
ML17284A8471999-07-29029 July 1999
Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level.
ML17284A8441999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a.
ML17284A8431999-07-29029 July 1999
Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring
ML17284A8401999-07-29029 July 1999
Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown.
ML17292B6891999-06-0303 June 1999
Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl
ML17292B6441999-04-20020 April 1999
Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630
ML17292B6321999-04-0707 April 1999
Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO
ML17292B4861998-12-17017 December 1998
Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125
ML17284A8071998-11-0909 November 1998
Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl
ML17284A7161998-08-0505 August 1998
Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1
ML17284A7051998-07-17017 July 1998
Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2
ML17292B3401998-04-16016 April 1998
Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi
ML17292B1301997-12-0404 December 1997
Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage
ML17292B0261997-08-14014 August 1997
Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line
ML17292A9401997-07-16016 July 1997
Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing
ML17292A8631997-05-20020 May 1997
Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615
ML17292A7561997-03-22022 March 1997
Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation
ML17292A5491996-10-15015 October 1996
Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl
ML17292A5381996-10-10010 October 1996
Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials
ML17292A4081996-08-0909 August 1996
Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971
GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996
Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage
ML17291B2781996-03-19019 March 1996
Application for Amend to License NPF-21,revising Containment Leakage Testing
ML17291B2071996-01-19019 January 1996
Application for Amend to License NPF-21 Re Primary Containment Leakage Testing
GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995
Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC
ML17291B0921995-10-26026 October 1995
Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys
ML17291A8421995-06-0606 June 1995
Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles
ML17291A8381995-06-0606 June 1995
Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59
ML17291A8321995-06-0606 June 1995
Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16
ML17291A7551995-04-25025 April 1995
Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1
ML17291A4791994-10-31031 October 1994
Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements
ML17291A4741994-10-31031 October 1994
Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys.
ML17291A4201994-09-26026 September 1994
Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis
ML17291A3941994-09-18018 September 1994
Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements
ML17291A3171994-08-0808 August 1994
Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program.
ML17291A2151994-07-12012 July 1994
Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits
ML17291A2201994-07-0808 July 1994
Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances
ML17290B1711994-05-0606 May 1994
Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication
ML17290B1551994-05-0505 May 1994
Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves.
ML17290A9631994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing
ML17290A9601994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations
ML17290A9551994-02-0808 February 1994
Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63
ML17290A9031994-01-13013 January 1994
Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation.
ML17290A8961994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements
ML17290A8781994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures
ML17290A8921994-01-0606 January 1994
Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2
ML17290A8391993-12-20020 December 1993
Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys.
ML17290A8181993-12-0606 December 1993
Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys
ML17290A8221993-12-0606 December 1993
Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H
1999-07-29
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17284A9101999-10-13013 October 1999
Application for Amend to License NPF-21,revising TS 3.3.6.1, Table 3.3.6.1-1, Primary Containment Isolation Instrumentation. Footnote (D) Is Removed Since Both Inboard & Outboard Trip Sys Are Now Functional in All Modes
ML17284A8501999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown.
ML17284A8471999-07-29029 July 1999
Application for Amend to License NPF-21,revising Tech Specs SR 3.5.2.2, Condensate Storage Tank Water Level.
ML17284A8441999-07-29029 July 1999
Application for Amend to License NPF-21,revising TS Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & 5.a.
ML17284A8431999-07-29029 July 1999
Application for Amend to License NPF-21,removing License Condition 2.C.(16),Attachment 2,Item 3(b) Re post-accident Neutron Flux Monitoring
ML17284A8401999-07-29029 July 1999
Application for Amend to License NPF-21,amending Tech Specs SR 3.8.4.6 of TS 3.8.5, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown.
ML17292B6891999-06-0303 June 1999
Application for Amend to License NPF-21,reflecting Change in Name of Washington Public Power Supply Sys to Energy Northwest.Marked-up Copy of Affected Pages of OL for Plant, Encl
ML17292B6441999-04-20020 April 1999
Application for Amend to License NPF-21,revising TS 3.4.11 to Replace Existing Reactor Pressure Temp Limit Curves by 000630
ML17292B6321999-04-0707 April 1999
Application for Amend to License NPF-21,requesting Mod to MCPR Safety Limits by 990930 to Allow Continued Power Operation at Plant Following Restart from R-14 RFO
ML17292B4861998-12-17017 December 1998
Application for Amend to License NPF-21,revising TS SR 3.8.1.8 to Allow for Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125
ML17284A8071998-11-0909 November 1998
Supplemental Application for Amend to License NPF-21, Requesting Minor Wording Changes to Clarify Intent of Proposed New License Section 2.B.(6).Addl Info That Describes Physical Storage of Matls,Encl
ML17284A7161998-08-0505 August 1998
Application for Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1
ML17284A7051998-07-17017 July 1998
Application for Exigent Amend to License NPF-21,modifying TS SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc, Battery E-B1-2
ML17292B3401998-04-16016 April 1998
Application for Amend to License NPF-21,modifying Requirement That cold-worked Austenitic Stainless Steel Used in Newly Designed ECCS Pump Suction Strainers Must Have Yield Strength Not Greater than 90,000 Psi
ML17292B1301997-12-0404 December 1997
Application for Amend to License NPF-21,modifying Min Critical Power Ratio Safety Limits by 980515 to Allow Continued Power Operation at WNP-2 Following Restart from R-13 Refueling Outage
ML17292B0261997-08-14014 August 1997
Application for Amend to License NPF-21,modifying Inservice Testing Requirements Specified in TS 5.5.6 for Inboard Primary Containment Isolation Valve on Transvering in-core Probe (TIP) Sys Nitrogen Purge Line
ML17292A9401997-07-16016 July 1997
Application for Amend to License NPF-21,adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 Efpys.Changes Support Vessel Leak Testing
ML17292A8631997-05-20020 May 1997
Application for Amend to License NPF-21,requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615
ML17292A7561997-03-22022 March 1997
Application for Amend to License NPF-21,modifying Response Time Testing Surveillance Requirements for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation
ML17292A5491996-10-15015 October 1996
Application for Amend to License NPF-21 to Modify TS for Secondary Containment & Standby Gas Treatment Sys to Reflect Revised Secondary Containment Drawdown & post-accident Analyses Results.Affidavit,Encl
ML17292A5381996-10-10010 October 1996
Application for Amend to License NPF-21,requesting Addition of Section 2B(6) Re Allowance of Storage of Byproduct, Source & Special Nuclear Materials
ML17292A4081996-08-0909 August 1996
Requests Amend to License NPF-21,revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971
GO2-96-089, Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage1996-04-24024 April 1996
Application for Amend to License NPF-21,modifying TS to Support Cycle 12,scheduled to Begin Subsequent to Spring 1996 Outage
ML17291B2781996-03-19019 March 1996
Application for Amend to License NPF-21,revising Containment Leakage Testing
ML17291B2071996-01-19019 January 1996
Application for Amend to License NPF-21 Re Primary Containment Leakage Testing
GO2-95-265, Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC1995-12-0808 December 1995
Application for Amend to License NPF-21,revising TS to Be Consistent w/NUREG-1434, STS GE Plants,Bwr 6, Including Improved TS Submittal,Consisting of Application of Selection Criteria,Ts,Comparison Document & NSHC
ML17291B0921995-10-26026 October 1995
Application for Amend to License NPF-21,revising TS to Reflect Replacement of Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys
ML17291A8421995-06-0606 June 1995
Application for Amend to License NPF-21,changing TS 6.0, Administrative Controls by Revising Assistant Managing Director,Operations & Plant Manager Position Titles
ML17291A8381995-06-0606 June 1995
Application for Amend to License NPF-21,modifying Index of TS by Deleting Ref to Bases Pages.Future Changes to Bases Info Will Be Evaluated Per 10CFR50.59
ML17291A8321995-06-0606 June 1995
Application for Amend to License NPF-21,modifying TS 6.9.3.2 by Adding Re to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications,Consistent W/Gl 88-16
ML17291A7551995-04-25025 April 1995
Application for Amend to License NPF-21,adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1
ML17291A4791994-10-31031 October 1994
Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements
ML17291A4741994-10-31031 October 1994
Application for Amend to License NPF-21,revising TS 3/4.1.3.1, Reactivity Control Sys.
ML17291A4201994-09-26026 September 1994
Suppl to 930709 Application for Amend to License NPF-21 Re Increase in Power Operation,Changing Power/Flow Maps in TS 3/4.2.6,3/4.2.7,3/4.2.8 & 3/4.4.1 & Bases to Reflect Use of Siemens Power Corp Staif Code for Stability Analysis
ML17291A3941994-09-18018 September 1994
Application for Amend to License NPF-21,changing TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements
ML17291A3171994-08-0808 August 1994
Application for Amend to License NPF-21,amending TS 4.0.5, Surveillance Requirements for Inservice Insp & Testing Program.
ML17291A2151994-07-12012 July 1994
Application for Amend to License NPF-21,requesting Amend to Ts,Relocating TS Table for Instrument Response Time Limits
ML17291A2201994-07-0808 July 1994
Application for Amend to License NPF-21,revising TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances
ML17290B1711994-05-0606 May 1994
Application for Amend to License NPF-21,revising TSs 3/4.3.7.5,3/4.4.2 & 3/4.5.1 for Main Steam Relief Valve Position Indication
ML17290B1551994-05-0505 May 1994
Application for Amend to License NPF-21,requesting Mod of Three Equipment Piece Numbers Included in Table 3.6.3-1, Primary Containment Isolation Valves.
ML17290A9631994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS to Support Hydrostatic Testing
ML17290A9601994-02-17017 February 1994
Application for Amend to License NPF-21,revising TS Section 6.0, Administrative Controls, Including Changing Reporting Relationship for QA Functions in Section 6.2.1.e of TS from Managing Director to Assistant Managing Director,Operations
ML17290A9551994-02-0808 February 1994
Application for Amend to License NPF-21,consisting of Changes to TS Table 3.6.3-1,for RCIC-V-8,increasing Stroke Time from 13 Seconds to 26 Seconds & Deleting Note (J) Reference from RCIC-V-8 & RCIC-V-63
ML17290A9031994-01-13013 January 1994
Application for Amend to License NPF-21,requesting Continued Plant Operation W/Eccs Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits of TS 3/4.3.3, ECCS Instrumentation.
ML17290A8961994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Changes to TS to Clarify Instrumentation Testing Requirements
ML17290A8781994-01-0606 January 1994
Application for Amend to License NPF-21,requesting Rev to TS to Relocate Requirements for Seismic Monitoring Instrumentation to FSAR & Plant Procedures
ML17290A8921994-01-0606 January 1994
Suppl to 930709 Application for Amend to License NPF-21, Increasing Licensed Power Level from 3,323 Mwt to 3,486 Mwt W/Extended Load Line Limit & Changing SRV Setpoint Tolerance to Include Changes to TS Paragraph 6.9.3.2
ML17290A8391993-12-20020 December 1993
Application for Amend to License NPF-21,revising TS 3/4.6.1.8, Drywell & Suppression Chamber Purge Sys.
ML17290A8181993-12-0606 December 1993
Application for Amend to License NPF-21,requesting TS Surveillance Requirement 4.6.6.1.b.3 Be Revised to Provide Appropriate Acceptance Criteria for Demonstrating Operability of Primary Containment Hydrogen Recombiner Sys
ML17290A8221993-12-0606 December 1993
Application for Amend to License NPF-21,adding Footnote to TS Table 4.3.7.5-1, Accident Monitoring Instrumentation Srs, Exempting Channel Calibr of Safety/Relief Valve Position Indicators from Spec 4.0.4 for 24 H
1999-07-29
[Table view] |
Text
CATEGORY 1 REGULR I INPORMATION'DISTRIBUTIOiOYSTEN (RIDE)
ACCESSION NBR:9707230291 DOC.DATE: 97/07/16 NOTARIZED: YES DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMES, P.R. Washington Public Power Supply System REClP.NAME RECIPIENT AFFILIATION Document, Control Branch (Document Control Desk)
SUBJECT:
Application for amend to license NPF-21,adding new min reactor vessel pressure versus reactor vessel metal temp (P/T) curves, applicable up to 12 Effective Full Power Years.
Changes support vessel leak testing.
DISTRIBUTION CODE: BOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution I ENCI, Q SIZE: ~+
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 COLBURNgT 1 1 INTERNAL: ACRS 1 1 M7 1 1 NRR/DE/ECGB/A 1 1 NRR DE EMCB 1 1 NRR/DRCH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 July 16, 1997 G02-97-144 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENTTO TECHNICALSPECIFICATIONS TO SUPPORT VESSEL LEAK TESTING
References:
- 1) Letter GO2-93-180, dated July 9, 1993, J. V. Parrish (SS) to NRC, "Request for Amendment to the Facility Operating License and Technical Specifications to Increase Licensed Power Level from 3323 MWt to 3486 MWt with Extended Load Line and a Change in Safety Relief Valve Set Point Tolerance"
- 2) Letter G02-94-042, dated February 17, 1994, J. V. Parrish (SS) to NRC, "WNP-2 Operating License NPF-21 Request to Amend Technical Specifications to Support Hydrostatic Testing"
- 3) Letter GI2-95-099, dated May 2, 1995, J.W. Clifford (NRC) to J.V.
Parrish (SS) "Issuance of Amendment for Washington Public Power Supply System Nuclear Project No. 2 (TAC Nos. M87076 and M88625)"
- 4) Letter GI2-94-148, dated May 27, 1994, L.M. Padovan (NRC) to J.V.
Parrish (SS) "Issuance of Amendment for Washington Public Power Supply System Nuclear Project No. 2 (TAC No. M88839)"
Re nest for Technical S ecification Amendment The Supply System hereby requests an amendment to the WNP-2 Technical Specifications in accordance with Title 10, Parts 50.90 and 2.101 of the Code of Federal Regulations.
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Page 2 Amendment to Technical Specifications to Support Vessel Leak Testing Specifically, the Supply System requests the addition of new minimum reactor vessel pressure versus reactor vessel metal temperature (P/T) curves, applicable up to 12 Effective Full Power Years (EFPY). The requested Technical Specification changes are necessary to support leak and hydrotesting in accordance with the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code Section XI.
Leak testing is a critical path item during our annual refueling outages. It is anticipated that the change described in this request can reduce the amount of time spent performing leak testing and thereby enhance personnel safety and outage schedule effectiveness. We request, therefore, that the requested amendment be issued in time to support the Spring 1998 refueling outage (R-13). Issuance of the requested amendment on or before May 1, 1998, will support our schedule. Details of the requested change are discussed below.
Previ u Re u f rPr ure T m ure urveModification Reference 1 proposed new P/T curves under power uprate conditions for 32 EFPY. The basis for the 32 EFPY curves is found in Reference 1 and is not repeated herein. Reference 2 proposed hydrostatic testing utilizing an 8 EFPY curve that was developed using substantially the same methodology as the 32 EFPY curve. The difference in methodologies was identified on page 4 of Reference 2. The basis for hydrostatic testing is found in Reference 2 and is not repeated herein. The Reference 1 and 2 requests were approved by the NRC in References 3 and 4.
The 12 EFPY curve in this submittal was developed using the same methodology as followed in Reference 2 utilizing a 12 EFPY temperature shift of 83.9'.
Pur o e and U e of Pres ure/Tem erature Curve Pressure/Temperature Curves based on 12 EFPY of neutron fluence at power uprate conditions are used only for leak and hydrostatic testing conditions during non-nuclear heatup of the Reactor Pressure Vessel. It is possible to conduct leak and hydrostatic testing using the
'existing 32 EFPY curve. However, the testing conducted under the proposed 12 EFPY curves will result in a greater margin for worker industrial safety with no adverse impact to the public health and safety.
Enhanced Worker Industrial afet Mar in Due to the lower total fluence level, the proposed 12 EFPY curves support use of a lower minimum reactor metal temperature at the required test pressure. The required minimum temperature for testing under the 12 EFPY curves is 185 degrees Fahrenheit. This is approximately 41 degrees Fahrenheit lower than that which would be required by testing using the 32 EFPY curve.
t.f If II
Page 3 Request for Amendment to Technical Specifications Support Vessel Leak Testing Significantly, then,,the 185 degree Fahrenheit reactor metal temperature corresponds to approximately a 200-210 degree Fahrenheit average Reactor Coolant System temperature (depending on the heat-up rate achieved and the time spent at the leak test temperature and pressure). The lower temperature of the 12 EFPY curves, therefore, provides a greater margin of industrial safety than would be provided using the 32 EFPY curve. The enhanced industrial safety margin is attributed to lower reactor water temperatures, higher remaining heat sink capacity, and avoidance of steam flashing. The margin of nuclear safety is actually increased by use of the proposed curves due to the lower allowed test temperature which increases the available heat sink for the RCS. Based on the foregoing, the margin of safety for the plant will not be reduced as a result of implementing the new 12 EFPY P/T curves.
No Si nificant Hazards Consideration Determination The Supply System has evaluated the proposed change per the requirements of 10 CFR 50.92.
The proposed addition of the 12 EFPY P/T curves for testing and non-nuclear heating does not represent a significant hazards consideration because it does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed 12 EFPY curve was developed using the same methodology as that used in the current 32 EFPY curve and the 8 EFPY curve. This methodology is consistent with the guidance provided in Regulatory Guide 1.99, Revision 2.
Assumptions and parameters were the same as those used in the 8 EFPY curve calculation. However, fluence values used in the calculation were those for 12 EFPY.
Use of the 12 EFPY curves on or before attainment of 12 EFPY of operation is equivalent to the previously approved use of the 32 EFPY curves on or before attainment of 32 EFPY of operation.
Therefore, the proposed 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.
The proposed change introduces no credible mechanism for unacceptable radiation release.
The proposed change does not require physical modification to the plant.
The 12 EFPY curves are consistent with the previously approved 32 and 8 EFPY curves.
Page 4 Request for Amendment to Technical Specifications Support Vessel Leak Testing Inservice hydrostatic or leak testing is not assumed to be an initiator of analyzed events.
Since approval of the proposed amendment will ensure adequate protection of the reactor pressure vessel, it will not create the possibility of a new or different kind of accident from any previously evaluated.
- 3) Involve a significant reduction in a margin of safety.
The accident analyses for the plant as described in the FSAR are not affected by this proposed change.
The 12 EFPY curves were developed using the same methodology as the 32 and 8 EFPY curves and thus involve no reduction in the margin of safety as previously evaluated.
The margin of safety, relative to the available heat sink in the Reactor Coolant System, is actually increased by use of the proposed curves due to the lower allowed test temperature.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
A ment Cate orical Exclu ion The proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). The proposed change does not involve a significant hazards consideration, have a potential for a change in the types, or increase in the amount, of any effluents that may be released off-site; or involve an increase in individual or cumulative occupational radiation exposure. Therefore, per the requirements of 10 CFR 51.22(b), an environmental assessment of these changes is not required.
In ernal and CNSRB Review This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.
tate otification In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.
Page 5 Request for Amendment to Technical Specifications Support Vessel Leak Testing Marku f Pr o ed han e provides copies of the impacted portion of the existing Technical Specifications.
A clean version of the change as proposed is provided as Attachment 2. In order to be consistent with the Improved Technical Specifications the new 12 EFPY curves require that the figures in LCO 3.4.11 be renumbered. We have also included proposed changes to the Bases as Attachment 3. These changes are for your information only and will be made by the Supply System upon receipt of the approved amendment. We request thirty days to implement the amendment upon notification of its approval.
Should you have any questions or desire additional information regarding this matter, please call me or D. A. Swank at (509) 377-4563.
ectfully, P.. ail Drop PE23)
Vice President, Nuclear Operations Attachments CC: EW Mershoff - NRC RIV KE Perkins, Jr. - NRC RIV, WCFO TG Colburn - NRR CR Wallis - EFSEC NRC Sr. Resident Inspector - 927N DL Williams - BPA/399 PD Robinson - Winston & Strawn
STATE OF WASHINGTON )
Subject:
Request for Amendment to TS to
) Su rt Ves el Leak Testin COUNTY OF BENTON )
I, P. R. BEMIS, being duly sworn, subscribe to and say that I am the Vice President, Nuclear Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.
DATE , 1997 P.. is
'nt, Nuclear Operations On this date personally appeared before me P, R. BEMIS, to me known to be the individual who executed the foregoing instrument, and acknowledge that he signed the same as his free act and deed for the uses and purposes herein mentioned.
G1VBN under my hand and seal this ~&day of S 1997 Notary ublic in an for the STATE OF WASHINGTON Residing at My Commission Expires
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ATTACKVH<2lT1 Current Technical Specification Pages with Proposed Changes
