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JAiNUARY P 3 1980Distribution,,OcketORB #3NRR ReadingLocal PDRNRC PDRDEisenhutRTedescoWGammi lJMillerLShaoRVol linerBGrimesTIppol itoSSheppardPPolkPCheckAtty, OELDOI&E (5)BJones (4)BScharf (10)tU'iI\Thl u"If fILE UJ)PIDocket No. 50-333Mr. George T. BerryGeneral Manager and ChiefEngineerPower Authority of the Stateof New York10 Columbus CircleNew York, New York 10019Dear Mr. Berry:STSGCMiles, OPARDiggsHDentonTERAJRBuchananThe Commission has issued the enclosed Amendment NoA.to FacilityLicense No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant.This amendment consists of administrative changes to the Technical Specifications in response to your request dated September 13, 1979.The modifications to the Technical Specifications revise and add specifications for several instrumentation requirements as previously approvedby Amendment No. 8, 14 and 40. In addition, errors and inconsistenciesin the existing Technical Specifications have been rectified.We have determined that the amendment does not authorize a change ineffluent types or total amounts nor an increase in power level, and willnot result in any significant environmental impact. Having made thisdetermination, we have further concluded that the amendment involves anaction which is insignificant from the standpoint of environmental impactand pursuant to 10 CFR 151.5(d)(4) that an environmental impact statement,negative declaration or environmental impact appraisal need not be prepared in connection with the issuance of this amendment.Since the amendment applies only to administrative details, it does notinvolve significant new safety inforattion of a type not considered by aprevious Commission safety review of the facility. It does not involvea significant increase in the probability or consequences of an accident,does not involve a significant decrease in a safety margin, and therefore does not involve a significant hazards consideration. We have alsoconcluded that there is reasonable assurance that the health and safetyof the public will not be endangered by this action.A copy of the Notice of Issuance is also enclosed.SI .IlYOfr1.IIKnIinaO FFICE ) .SU. . .OperatNP, C FORM " I P ýo7ý:,1jrCr.")?T.1r1-1Vig Reactors Br.nch #3SEE N -XT PAGE FOR rNCURRENCESSee page 221"/(0'ý.CFORM GO 01, byDivisioi Iof Operating Reactors RNAMEI.oDApý osures and ccs:IICrI).I-. . . . . . . . . .I, 19'-11 r -QIJ T ING, OF FICEQ9289-369q!). . .-. . . .
OFFICE.SQORB #3ORB #3IURNAME.NAFM397/8M040NRC FORM 318 (9-76) NRCM 0240.ORB0 3OfL DATI.l.i.11itI/80*US.tO(ý'fVERN MENT PRINTING/11y87OFFICE: 1979-289-369L1//9780-68
Mr.George T. Berry-2-January 23, 1980Enclosures:1. Amendment No. 48 to LicenseNo. DPR-592. Noticecc w/enclosures:Mr. Charles M. PrattAssistant General CounselPower Authority of the Stateof New York10 Columbus CircelNew York, New York 10019Director, Technical AssessmentDivisionOffice of Radiation Programs(AW-459)US EPACrystal Mall 2Arlington, Virginia 20460Mr. Peter W. LyonManager-Nuclear OperationsPower Authority of the Stateof New York10 Columbus CircleNew York, New York 10019U. S. Environmental ProtectionAgencyRegion II OfficeATTN: EIS COORDINATOR26 Federal PlazaNew York, New York 10007Mr. J. D. Leonard, Jr.Resident ManagerJames A. FitzPatrick NuclearPower PlantP. 0. Box 41Lycoming, New York 13093Director, Technical DevelopmentProgramsState of New York Energy OfficeAgency Building 2Empire State PlazaAlbany, New York 12223George M. Wilverding, LicensingLicensing SupervisorPower Authority of the Stateof New York10 Columbus CircleNew York, New York 10019Mr. Robert P. Jones, SupervisorTown of ScribaR. D. #4Oswego, New York 13126Oswego County Office Building46 E. Bridge StreetOswego, New York 13126
UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555POWER AUTHORITY OF THE STATE OF NEW YORKDOCKET NO.50-333JAMES A. FITZPATRICK NUCLEAR POWER PLANTAMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 48License No. DPR-591. The Nuclear Regulatory Commission (the Commission)A.B.C.D.E.2.has found that:of the State ofThe application for amendment by Power Authoritycomplies with the1979,13,New York (the licensee) dated Septemberof 1954, as amendedActEnergystandards and requirements of the Atomicset forth inregulations(the Act), and the Commission's rules and10 CFR Chapter I;the application,The facility will operate in conformity withof theprovisions of the Act, and the rules and regulationsCommission;theactivities authorizedThere is reasonable assurance (i) that thethe healthby this amendment can be conducted without endangering will bethat such activitiesand safety of the public, and (ii)regulations;Commission'sthewithconducted in complianceinimical to the commonThe issuance of this amendment will not beof the public; andsafetydefense and security or to the health andwith 10 CFR Part 51The issuance of this amendment is in accordancerequirements haveapplicableof the Commission's regulations and allbeen satisfied.to the Technical SpecifiAccordingly, the license is amended by changeslicense amendment, andthistocations as indicated in the attachmentNo. DPR-59 is herebyparagraph 2.C.(2) of Facility Operating Licenseamended to read as follows:(2)Technical SpecificationsAppendices A andThe Technical Specifications contained inhereby incorporatedare48,No.B, as revised through Amendmentthe facility inoperateshallin the license. The licenseeaccordance with the Technical Specifications.
- 23.This license amendment is effective as of the date of its issuance.FOR THE NUCLEAR REGULATORY COMMISSIONThomas Jlppolito,ChiefOperating Reactors Branch #3Division of Operating ReactorsAttachment:Changes to the TechnicalSpecificationsDate of Issuance:January 23,1980
ATTACHMENT TO LICENSE AMENDMENT NO. 48FACILITY OPERATING LICENSE NO. DPR-59DOCKET NO. 50-333withReplace the following pages of the Appendix "A" Technical Specificationsthe enclosed 99200201202203204205206209239
JAFNPPIU.V.surveillance tests, checks, calibrations, and examinations shall be performed within the specifiedThese intervals may be adsurveillance intervals.The interval as pertaining tojusted 25 percent.instrument and electric surveillance shall neverIn cases where theexceed one operating cycle.elasped interval has exceeded 100 percent of thespecified interval, the next surveillance intervalshall commence at the end of the original specifiedinterval.To disarm a rod drive electrically, the fouramphenol type plug connectors are removedfrom the drive insert and withdrawal solenoidsrendering the rod incapable of withdrawal.This procedure is equivalent to valving out theElectrical disarmingdrive and is preferred.does not eliminate position indication.W.Thermal Parameters1.2.3.4.X.ratioexLHGR18.58x8Transition Boiling - Transition boiling meansthe boiling region between nucleate and filmTransition boiling is the region inboiling.which both nucleate and film boiling occur intermittently with neither type being completelystable.1A, 3V, 3A,4A,48I,Staggered Test BasisA Staggered Test Basis shall consist oftMaximum Fraction of Limiting Power DensityThe Maximum Fraction of Limiting Power Density(MFLPD) is the highest value existing in thecore of the Fraction of Limiting Power Density(FLPD).Amendment No.High Pressure Water Fire Protection SystemThe High Pressure Water Fire Protection Systemconsists of: a water source and pumps; anddistribution system piping with associated postSuchindicator vavles (isolation valves).and-alvescurbvalves include the yard hydrantalarmflLvalve ahead of the water-the firstdevice on each sprinkler or water spray subsystem.Minimum critical power ratio (MCPR)-Ratio ofthat power in a fuel assembly which is calculated to cause some point in that fuel assemblyto experience boiling transition to the actualassembly operating power as calculated by application of the GEXL correlation (ReferenceNEDE-10958).Fraction of Limiting Power Density - Theof the linear heat generation rate (LHGR)isting at a given location to the designDesign LHGR's arefor that bundle type.13.4 KW/ft forandbundles7x7KW/ft forand 8x8R bundles.Electrically Disarmed Control Rod6schedule for a systems, subsystems,or other designeated components obby dividing the specified test ininto n equal subintervals.a.A testtrainstainedtervalb.The testing of one system, subsystem, trainor other designated component at the beginning of each subinterval.(
closure group.The water levelinstrumentation initiates protection forthe full spectrum of loss-of-coolantaccidents.steam line isolation valves, main steamdrain valves, recirc. sample valves(Group 1), initiates the HPCI and RCICTheand trips the recirculation pumps.instrulevellow-low-low reactor watermentation is set to trip when the waterlevel is 18 in. above the top of theThis trip activates theactive fuel.ECCS subsystems, andtheremainder ofstarts the emergency diesel generators.These trip level settings were chosen tobe high enough to prevent spurious actuation but low enough to initiate ECCSoperation and primary system isolationso that post-accident cooling can be accomplished and the guidelines ofFor1OCFR100 will not be exceeded.completethetoupbreakslargecircumferential break of a 24 in.recirculation line and with the tripsetting given above, ECCS initiation andprimary system isolation are initiatedin time to meet the above criteria.Reference paragraph 6.5.3.1 FSAR.Venturis are provided in the main steamlines as a means of measuring steam flowand also limiting the loss of massinventory from the vessel during a steamThe primaryline break accident.is rywell,theoutsidebreaklinesetting of 140 percent of rated steamflow in conjunction with the flowlimiters and main steam line valveclosure, limits the mass inventory losssuch that fuel is not uncovered, fueltemperature peak at approximately1,000 F and release of radioactivity tothe environs is below 10CFR100 guideReference Section 14.6.5 FSAR.lines.The high drywell pressure instrumentation is a diverse signal for malfunctions to the water level instrumentation and in addition to initiatingECCS, it causes isolation of Groups BFor the breaksand 3 isolation valves.discussed above, this instrumentationwill generally initiate CSCS operationbefore the low-low-low water levelinstrumentation; thus the results givenSeeabove are applicable here also.valveSpecification 3.7 for isolationAmendment No.3 ,4856
3.2IJAFNPPBASES (cont'd)The trip settings of 300 percent of designflow for this high flow of 40 F above maximumambient for high temperature are such thatuncovering the core is prevented and fissionproduct release is within limits.High radiation monitors in the main steamline tunnel have been provided to detectgross fuel failure as in the control rodWith the established settdrop accident.ing of 3 times normal background, and mainsteam line isolation valve closure, fissionproduct release is limited so that 10CFR100guidelines are not exceeded for this acciReference Section 14.6.2 FSAR.dent.The RCIC high flow and temperature instrumentationTheare arranged the same as that for the HPCI.trip setting of 300 percent for high flow and40 F above maximum ambient for temperature arebased on the same criteria as the HPCI.Pressure instrumentation is provided toclose the main steam isolation valves in therun mode when the main steam line pressureThe reactor pressuredrops below 825 psig.vessel thermal transient due to an inadvertent opening of the turbine bypass valveswhen not in the run mode is less severethan the loss of feedwater analyzed inSection 14.5 of the FSAR, therefore,closure of the main steam isolation valvesfor thermal transient protection when notin the run mode is not required.The reactor water cleanup system high flow temperature instrumentation are arranged similarThe trip settings areto that for the HPCI.such that uncovering the core is prevented andfission product release is within limits.The instrumentation which initiates ECCS actionAs for otheris arranged in a dual bus system.fashion,thisinvital instrumentation arrangedofeffectivenessthe specification preserves themaintenancewhenperiodsthe systen even duringAn exception toor testing is being performed.is beingtestingfunctionalthis is when logicperformed.The HPCI high flow and temperature instrumentation are provided to detect a breakTripping ofin the HPCI steam piping.in actuationresultsinstrumentationthisTripping logicof HPCI isolation valves.for the high flow is a 1 out of 2 logic.Amendment No.10, 37,30,48The control rod block functions are provided toprevent excessive control rod withdrawal so thatMCPR does not de-57I
3.2 BASES (cont'd)duct.Each pair is considered aThe trip logicseparate system.consists of any upscale trip on a singlemonitor or a downscale trip on bothmonitors in a pair to cause the desiredaction.the specification are adequate to assureThethe above criteria are met.efthepreservesspecificationfectiveness of the system during periodsof maintenance, testing, or calibration,and also minimizes the risk ofi.e, only oneinadvertent operation;service.ofoutchannelinstrumentTrip settings of 2.7 x l05 cpMfor the monitors in the refueling areaventilation exhaust ducts are based uponinitiating normal ventilation isolationand Standby Gas Treatment System operation so that most of the activityreleased during the refueling accidentis processed by the Standby Gas Treatmentsystem.Two air ejector offgas monitors areprovided and when their trip point isreached, cause an isolation of the airisolation isejector offgas line.initiated when both instruments reachtheir high trip point or one has an upscale trip and the other a downscaletrip. There is a 15 min. delay beforethe air ejector off
Design LHGR's are 18.5 KW/ft for 7x7 bundles and 13.4 KW/ft for 8x8 and 8x8R bundles. 3. Maximum Fraction of Limiting Power Density The Maximum Fraction of Limiting Power Density (MFLPD) is the highest value existing in the core of the Fraction of Limiting Power Density (FLPD). 4.
