|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:DONALDC.COOKNUCLEARPLANTUNIT1CYCLE12COREOPERATING LIMITSREPORTRevision1December199090i22602ii 90i2i9P13RAGOCK050003i5P*PDR COLRforDONALDC.COOKNUCLEARPLANTUNIT1CYCLE12)1.0COREOPERATING LIMITSREPORTThisCoreOperating LimitsReportforDonaldC.CookNuclearPlantUnit1Cycle12hasbeenpreparedinaccordance withtherequirements ofTechnical Specification 6.9.1.11. | | {{#Wiki_filter:DONALD C.COOK NUCLEAR PLANT UNIT 1 CYCLE 12 CORE OPERATING LIMITS REPORT Revision 1 December 1990 90i22602ii 90i2i9 P13R AGOCK 050003i5 P*PDR COLR for DONALD C.COOK NUCLEAR PLANT UNIT 1 CYCLE 12)1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 has been prepared in accordance with the requirements of Technical Specification 6.9.1.11.The Technical Specifications affected by this report are listed below: 3/4.1.1.4 3/4.1.3.1 3/4.1.3.3 3/4.1.3.4 3/4.1.3.5 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.6 Moderator Temperature Coefficient Movable Control Assemblies Group Height Rod Drop Time Shutdown Rod Insertion Limits Control Rod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor Nuclear Enthalpy Hot Channel Factor Allowable Power Level Page 1 of ll COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. |
| TheTechnical Specifications affectedbythisreportarelistedbelow:3/4.1.1.4 3/4.1.3.1 3/4.1.3.3 3/4.1.3.4 3/4.1.3.5 3/4.2.13/4.2.23/4.2.33/4.2.6Moderator Temperature Coefficient MovableControlAssemblies GroupHeightRodDropTimeShutdownRodInsertion LimitsControlRodInsertion LimitsAxialFluxDifference HeatFluxHotChannelFactorNuclearEnthalpyHotChannelFactorAllowable PowerLevelPage1ofll COLRforDonaldC.CookNuclearPlantUnit1Cycle122.0OPERATING LIMITSThecycle-specific parameter limitsforthespecifications listedinSection1.0arepresented inthefollowing subsections.
| | These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.11.2.1 Moderator Tem erature Coefficient (Specification 3/4.1.1.4) 2.1.1 The Moderator Temperature Coefficient (MTC)Limits are: The BOL/ARO-MTC shall be less positive than the value given in Figure l.The EOL/ARO/RTP-MTC shall be less negative than-3.35E-4 Ak/k/F.This limit is based on a T program with HFP T of 550 F avg avg where: ARO stands for All Rods Out BOL stands for Beginning of Cycle Life EOL stands for End of Cycle Life RTP stands for Rated Thermal Power HFP stands for Hot Full Thermal Power 2.1.2 The MTC Surveillance limit is: The 300 ppm/ARO/RTP-MTC should be less negative than or equal to-2.70E-4 Ak/k/'F at a vessel average)temperature of 550 F.Page 2 of 11 COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.2 Rod Dro Time Dro Hei ht (Specification 3/4.1.3.3) 2.2.1 All rods shall be dropped from 228 steps.2.3 Shutdown Rod Insertion Limit (Specification 3/4.1.3.4) 2.3.1 The shutdown rods shall be withdrawn to 228 steps.2.4 Control Rod Insertion Limits (Specification 3/4.1.3.5, and 3/4.1.3.1) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure 2.2.4.2 Successive Control Banks shall overlap by 100 steps.The sequence for Control Bank withdrawal shall be Control Bank A, Control Bank B, Control Bank C, and Control Bank D.2.5 Axial Flux Difference (Specification 3/4.2.1)2.5.1 The Allowable Operation Limits are provided in Figure 3.2.5.2 The AXIAL FLUX DIFFERENCE (AFD)target band during base load operations is+3Z,-3Z (not applicable for this cycle).2.5.3 The AFD target band is+5Z,-5Z for core average accumulated burnup>0.0 MWD/MTU Page 3 of 11 |
| Theselimitshavebeendeveloped usingtheNRC-approved methodologies specified inTechnical Specification 6.9.1.11.
| |
| 2.1Moderator TemeratureCoefficient (Specification 3/4.1.1.4) 2.1.1TheModerator Temperature Coefficient (MTC)Limitsare:TheBOL/ARO-MTCshallbelesspositivethanthevaluegiveninFigurel.TheEOL/ARO/RTP-MTC shallbelessnegativethan-3.35E-4Ak/k/F.ThislimitisbasedonaTprogramwithHFPTof550Favgavgwhere:AROstandsforAllRodsOutBOLstandsforBeginning ofCycleLifeEOLstandsforEndofCycleLifeRTPstandsforRatedThermalPowerHFPstandsforHotFullThermalPower2.1.2TheMTCSurveillance limitis:The300ppm/ARO/RTP-MTC shouldbelessnegativethanorequalto-2.70E-4Ak/k/'Fatavesselaverage)temperature of550F.Page2of11 COLRforDonaldC.CookNuclearPlantUnit1Cycle122.2RodDroTimeDroHeiht(Specification 3/4.1.3.3) 2.2.1Allrodsshallbedroppedfrom228steps.2.3ShutdownRodInsertion Limit(Specification 3/4.1.3.4) 2.3.1Theshutdownrodsshallbewithdrawn to228steps.2.4ControlRodInsertion Limits(Specification 3/4.1.3.5, and3/4.1.3.1) 2.4.1Thecontrolbanksshallbelimitedinphysicalinsertion asshowninFigure2.2.4.2Successive ControlBanksshalloverlapby100steps.ThesequenceforControlBankwithdrawal shallbeControlBankA,ControlBankB,ControlBankC,andControlBankD.2.5AxialFluxDifference (Specification 3/4.2.1)2.5.1TheAllowable Operation LimitsareprovidedinFigure3.2.5.2TheAXIALFLUXDIFFERENCE (AFD)targetbandduringbaseloadoperations is+3Z,-3Z(notapplicable forthiscycle).2.5.3TheAFDtargetbandis+5Z,-5Zforcoreaverageaccumulated burnup>0.0MWD/MTUPage3of11 | |
|
| |
|
| COLRforDonaldC.CookNuclearPlantUnit1Cycle12)2.6HeatFluxHotChannelFactor-F(Z)(Specifications 3.2.2)CFQF(Z)<---*K(Z)QPforP>0.5F(Z)<2*CFQ*K(Z)forP<0.5where:PTHERMALPOWERRATEDTHERMALPOWER2.6.1CFQ2.15forWestinghouse fuel2.6.2K(Z)isprovidedinFigure4forWestinghouse fuelPage4of11 COLRforDonaldC.CookNuclearPlantUnit1Cycle122.7NuclearEnthalHotChannelFactor-F(Specification 3/4.2.3)F<CFDH*(1+PFDH*(1-P))where:PTHERMALPOWERRATEDTHERMALPOWER2.7.1CFDH1.49forWestinghouse fuel2.7.2PFDH0.3Page5ofll COLRforDonaldC.CookNuclearPlantUnit1Cycle122.8Allowable PowerLevel-APL(Specification 3.2.6)APLminoverZforCFQ*K(Z)F(Z)*V(Z)*FQp2.8.1V(Z)isprovidedinTable1for+5%AFDtargetband2.8.2CFQandK(Z)areprovidedinCOLRSections2.6.1and2.6.2,respectively 2.8.3FpisprovidedinTechnica1Specification3.2.6Page6of11 Moderator Temperature Coefficient (MTC)MTCx10Ak/k/d6g.F f.000.50UnaceptablOpertion0.005C050orr-1.00-1.50AccptoblaOperaon-2.00-2.50-3.000io2030405060708090iooPERCENTRATEDTHERMALPOSER 0(fMLLYWITH221200OAIWM)0~~0~~~~2~00~~~~~~~~~"2'''000~~0~0.55;228)
| | COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12)2.6 Heat Flux Hot Channel Factor-F (Z)(Specifications 3.2.2)CFQ F (Z)<---*K(Z)Q P for P>0.5 F (Z)<2*CFQ*K(Z)for P<0.5 where: P THERMAL POWER RATED THERMAL POWER 2.6.1 CFQ 2.15 for Westinghouse fuel 2.6.2 K(Z)is provided in Figure 4 for Westinghouse fuel Page 4 of 11 COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.7 Nuclear Enthal Hot Channel Factor-F (Specification 3/4.2.3)F<CFDH*(1+PFDH*(1-P))where: P THERMAL POWER RATED THERMAL POWER 2.7.1 CFDH 1.49 for Westinghouse fuel 2.7.2 PFDH 0.3 Page 5 of ll COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.8 Allowable Power Level-APL (Specification 3.2.6)APL min over Z for CFQ*K(Z)F (Z)*V(Z)*F Q p 2.8.1 V(Z)is provided in Table 1 for+5%AFD target band 2.8.2 CFQ and K(Z)are provided in COLR Sections 2.6.1 and 2.6.2, respectively 2.8.3 Fp is provided in Technica 1 Specif ication 3.2.6 Page 6 of 11 Moderator Temperature Coefficient (MTC)MTC x 10 Ak/k/d6g.F f.00 0.50 Unac eptabl Oper tion 0.00 5 C 0 50 o r r-1.00-1.50 Acc ptobla Opera on-2.00-2.50-3.00 0 io 20 30 40 50 60 70 80 90 ioo PERCENT RATED THERMAL POSER 0 (f MLLY WITH 221 200 OAI WM)0~~0~~~~2~0 0~~~~~~~~~"2'''000~~0~0.55;228)~00~~'W~~~<<-~~00~~~~<<~~0~~~~~0 BANK C~~0~~~1.0 182):-X 0 450 0 4 4 4 100 0 O 0~0~~~~~oo>>~<<0~~0~0 (0,>25)0~~0~~~00~~%~0>>~~~~0~~~<<~~~~~~~0 on~~~0 0~>>~~~~~~~~0~~00 SANK D'.0~~\~~~00 0 0 0~0<<000 0~<<0~~0~~~oo 00 40.-"::(o,o): |
| ~00~~'W~~~<<-~~00~~~~<<~~0~~~~~0BANKC~~0~~~1.0182):-X045004441000O0~0~~~~~oo>>~<<0~~0~0(0,>25)0~~0~~~00~~%~0>>~~~~0~~~<<~~~~~~~0on~~~00~>>~~~~~~~~0~~00SANKD'.0~~\~~~00000~0<<0000~<<0~~0~~~oo0040.-"::(o,o): | | O.o (f ULLY IN I g g TII))0.2 o,g o.e 0.8 fRACTION OF RATKD THKRMAL I OWKR 4.0 FZCURE 2 ROD INSERTION LIMITS VERSUS'GKKIAL POWER 4 LOOP OPERATION Page 8 of ll (o.o,x.o)(sio~loo)(12~0,0~925)CKK HSCHT (FT)10 12 FIGURE 4 X{2)NOBÃALZXXD fg('Z)AS A FUNCTION OF CORE HZXGHT FOR MKSTZNGHOQSZ FUEL page 10 of 11}} |
| O.o(fULLYINIggTII))0.2o,go.e0.8fRACTIONOFRATKDTHKRMALIOWKR4.0FZCURE2RODINSERTION LIMITSVERSUS'GKKIALPOWER4LOOPOPERATION Page8ofll (o.o,x.o) | |
| (sio~loo) | |
| (12~0,0~925)CKKHSCHT(FT)1012FIGURE4X{2)NOBÃALZXXD fg('Z)ASAFUNCTIONOFCOREHZXGHTFORMKSTZNGHOQSZ FUELpage10of11}} | |
Revision as of 08:51, 6 July 2018
Similar Documents at Cook |
|---|
Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML17334A5961997-12-31031 December 1997
Rev 1 to DC Cook Nuclear Plant Unit 2 Cycle 12 Colr.
ML17334A5841997-11-30030 November 1997
Rev 2 to DC Cook Nuclear Plant Unit 1 Cycle 16 Colr.
ML17334A5641997-11-30030 November 1997
DC Cook Nuclear Plant Unit 2 Cycle 12 Colr.
ML17333B0661997-09-30030 September 1997
Rev 5 to DC Cook Nuclear Plant Unit 2 Cycle 11 Colr.
ML20141E9771997-05-31031 May 1997
Rev 1 to DCP Unit 1 Cycle 16 Colr
ML17333A8491997-04-30030 April 1997
Rev 0 to COLR DC Cook Nuclear Plant,Unit 1 Cycle 16.
ML17333A4391996-04-30030 April 1996
Rev 4 to DC Cook Nuclear Plant Unit 2 Cycle 11 Colr.
ML17333A3371996-02-29029 February 1996
DC Cook Nuclear Plant Unit 2 Cycle 10 Updated Colr.
ML17333A3351996-02-29029 February 1996
Rev 5 to DC Cook Nuclear Plant Unit 1,Cycle 15 Colr.
ML17332A9451995-09-30030 September 1995
Rev 4 to DC Cook Nuclear Plant Unit 1,Cycle 15,COLR.
ML17332A3691994-10-31031 October 1994
Rev 2 to Donald C Cook Nuclear Plant Unit 2 Cycle 10 Core Operating Limits Rept.
ML17331B3511994-04-11011 April 1994
Rev 3 to COLR for DC Cook Nuclear Plant Unit 1 Cycle 14.
ML17329A6811992-11-30030 November 1992
Rev 2 to DC Cook Nuclear Plant Unit 1 Cycle 13 Colr.
ML17329A5051992-05-31031 May 1992
Rev 1 to DC Cook Nuclear Plant Unit 2,Cycle 9 Core Operating Limits Rept.
ML17328A8191990-12-31031 December 1990
Rev 1 to DC Cook Nuclear Plant Unit 1 Cycle 12 Core Operating Limits Rept.
ML17328A7491990-09-30030 September 1990
Rev 0 to Unit 1 Core Operating Limits Rept.
ML17328A7501990-09-0404 September 1990
Rev 0 to Unit 2 Core Operating Limits Rept.
ML17325A4281987-08-31031 August 1987
Reload Safety Evaluation DC Cook Nuclear Plant Unit 1 Cycle 10.
ML20087G6881984-03-15015 March 1984
Rev 1,Suppl 1,to DC Cook Unit 2,Cycle 5 Sar
1997-09-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
[Table view] |
Text
DONALD C.COOK NUCLEAR PLANT UNIT 1 CYCLE 12 CORE OPERATING LIMITS REPORT Revision 1 December 1990 90i22602ii 90i2i9 P13R AGOCK 050003i5 P*PDR COLR for DONALD C.COOK NUCLEAR PLANT UNIT 1 CYCLE 12)1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 has been prepared in accordance with the requirements of Technical Specification 6.9.1.11.The Technical Specifications affected by this report are listed below: 3/4.1.1.4 3/4.1.3.1 3/4.1.3.3 3/4.1.3.4 3/4.1.3.5 3/4.2.1 3/4.2.2 3/4.2.3 3/4.2.6 Moderator Temperature Coefficient Movable Control Assemblies Group Height Rod Drop Time Shutdown Rod Insertion Limits Control Rod Insertion Limits Axial Flux Difference Heat Flux Hot Channel Factor Nuclear Enthalpy Hot Channel Factor Allowable Power Level Page 1 of ll COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.
These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9.1.11.2.1 Moderator Tem erature Coefficient (Specification 3/4.1.1.4) 2.1.1 The Moderator Temperature Coefficient (MTC)Limits are: The BOL/ARO-MTC shall be less positive than the value given in Figure l.The EOL/ARO/RTP-MTC shall be less negative than-3.35E-4 Ak/k/F.This limit is based on a T program with HFP T of 550 F avg avg where: ARO stands for All Rods Out BOL stands for Beginning of Cycle Life EOL stands for End of Cycle Life RTP stands for Rated Thermal Power HFP stands for Hot Full Thermal Power 2.1.2 The MTC Surveillance limit is: The 300 ppm/ARO/RTP-MTC should be less negative than or equal to-2.70E-4 Ak/k/'F at a vessel average)temperature of 550 F.Page 2 of 11 COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.2 Rod Dro Time Dro Hei ht (Specification 3/4.1.3.3) 2.2.1 All rods shall be dropped from 228 steps.2.3 Shutdown Rod Insertion Limit (Specification 3/4.1.3.4) 2.3.1 The shutdown rods shall be withdrawn to 228 steps.2.4 Control Rod Insertion Limits (Specification 3/4.1.3.5, and 3/4.1.3.1) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure 2.2.4.2 Successive Control Banks shall overlap by 100 steps.The sequence for Control Bank withdrawal shall be Control Bank A, Control Bank B, Control Bank C, and Control Bank D.2.5 Axial Flux Difference (Specification 3/4.2.1)2.5.1 The Allowable Operation Limits are provided in Figure 3.2.5.2 The AXIAL FLUX DIFFERENCE (AFD)target band during base load operations is+3Z,-3Z (not applicable for this cycle).2.5.3 The AFD target band is+5Z,-5Z for core average accumulated burnup>0.0 MWD/MTU Page 3 of 11
COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12)2.6 Heat Flux Hot Channel Factor-F (Z)(Specifications 3.2.2)CFQ F (Z)<---*K(Z)Q P for P>0.5 F (Z)<2*CFQ*K(Z)for P<0.5 where: P THERMAL POWER RATED THERMAL POWER 2.6.1 CFQ 2.15 for Westinghouse fuel 2.6.2 K(Z)is provided in Figure 4 for Westinghouse fuel Page 4 of 11 COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.7 Nuclear Enthal Hot Channel Factor-F (Specification 3/4.2.3)F<CFDH*(1+PFDH*(1-P))where: P THERMAL POWER RATED THERMAL POWER 2.7.1 CFDH 1.49 for Westinghouse fuel 2.7.2 PFDH 0.3 Page 5 of ll COLR for Donald C.Cook Nuclear Plant Unit 1 Cycle 12 2.8 Allowable Power Level-APL (Specification 3.2.6)APL min over Z for CFQ*K(Z)F (Z)*V(Z)*F Q p 2.8.1 V(Z)is provided in Table 1 for+5%AFD target band 2.8.2 CFQ and K(Z)are provided in COLR Sections 2.6.1 and 2.6.2, respectively 2.8.3 Fp is provided in Technica 1 Specif ication 3.2.6 Page 6 of 11 Moderator Temperature Coefficient (MTC)MTC x 10 Ak/k/d6g.F f.00 0.50 Unac eptabl Oper tion 0.00 5 C 0 50 o r r-1.00-1.50 Acc ptobla Opera on-2.00-2.50-3.00 0 io 20 30 40 50 60 70 80 90 ioo PERCENT RATED THERMAL POSER 0 (f MLLY WITH 221 200 OAI WM)0~~0~~~~2~0 0~~~~~~~~~"2000~~0~0.55;228)~00~~'W~~~<<-~~00~~~~<<~~0~~~~~0 BANK C~~0~~~1.0 182):-X 0 450 0 4 4 4 100 0 O 0~0~~~~~oo>>~<<0~~0~0 (0,>25)0~~0~~~00~~%~0>>~~~~0~~~<<~~~~~~~0 on~~~0 0~>>~~~~~~~~0~~00 SANK D'.0~~\~~~00 0 0 0~0<<000 0~<<0~~0~~~oo 00 40.-"::(o,o):
O.o (f ULLY IN I g g TII))0.2 o,g o.e 0.8 fRACTION OF RATKD THKRMAL I OWKR 4.0 FZCURE 2 ROD INSERTION LIMITS VERSUS'GKKIAL POWER 4 LOOP OPERATION Page 8 of ll (o.o,x.o)(sio~loo)(12~0,0~925)CKK HSCHT (FT)10 12 FIGURE 4 X{2)NOBÃALZXXD fg('Z)AS A FUNCTION OF CORE HZXGHT FOR MKSTZNGHOQSZ FUEL page 10 of 11
