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Withdrawal of Shutdown banks commenced May 23,'1992 at 0242 and initial criticality was achieved 6 hours and 24 minutes later.WCAP-13682,"The Nuclear Design and Core Management of the Turkey Point Unit 4 Nuclear Power Plant, Cycle 14", was the design source for verifying that acceptance criteria as specified in ANSI/ANS 19.6.1 were met.All tests performed for nuclear design verification meet their acceptance criteria.The contents of this report provide the documentation required by Technical Specification 6.9.1.1.H | Withdrawal of Shutdown banks commenced May 23,'1992 at 0242 and initial criticality was achieved 6 hours and 24 minutes later.WCAP-13682,"The Nuclear Design and Core Management of the Turkey Point Unit 4 Nuclear Power Plant, Cycle 14", was the design source for verifying that acceptance criteria as specified in ANSI/ANS 19.6.1 were met.All tests performed for nuclear design verification meet their acceptance criteria.The contents of this report provide the documentation required by Technical Specification 6.9.1.1.H | ||
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L-93-196 Attachment Page, 3 of 1'8 TABLE OF CONTENTS INTRODUCTION 1'.0, UNIT 4, CYCLE XIV CORE 1.1 Fuel Design Changes 1'Loading Pattern 1.3 Rod Pattern and Rod Drop Times 2.0 INITIAL CRITICALITY | L-93-196 Attachment Page, 3 of 1'8 TABLE OF CONTENTS INTRODUCTION 1'.0, UNIT 4, CYCLE XIV CORE 1.1 Fuel Design Changes 1'Loading Pattern 1.3 Rod Pattern and Rod Drop Times 2.0 INITIAL CRITICALITY 2.1 Inverse Count Rate Ratio (ICRR)vs.Dilution.2.'2 Critical Data 3.,0 SUMMPGtY OF'TESTS 3.1 Nuclear Heating 3.'2 Reactivity vs.Period 3'Boron Endpoints 3.,4 Rod Worth (ppm), Most Reactive Bank 3.'5 Rod Worth (pcm)3.6 Temperature Coefficient 3.7 Hot Zero Power (HZP)Differential Boron Worth 4.0 SHUTDOWN.MARGIN 5.0 POWER DISTRIBUTION MAPS 6.0'CRITICAL BORON CONCENTRATION 0 | ||
Count Rate Ratio (ICRR)vs.Dilution.2.'2 Critical Data 3.,0 SUMMPGtY OF'TESTS 3.1 Nuclear Heating 3.'2 Reactivity vs.Period 3'Boron Endpoints 3.,4 Rod Worth (ppm), Most Reactive Bank 3.'5 Rod Worth (pcm)3.6 Temperature Coefficient 3.7 Hot Zero Power (HZP)Differential Boron Worth 4.0 SHUTDOWN.MARGIN 5.0 POWER DISTRIBUTION MAPS 6.0'CRITICAL BORON CONCENTRATION 0 | |||
L-93-196 Attachment Page 4 of 18 1.0 UNIT 4 CYCLE XIV CORE'.1 Fuel Desi n Chan es Unit 4 Cycle, 14 fuel is essentially the same as Cycle 13 fuel with the exception that Cycle 14 fuel includes axial blankets and additional snag-resistant grids.Axial blankets, previously used in Turkey Point Unit 3 Cycle 13 core design are new to Unit 4.Axial blankets consist of a nominal 6 inches of natural VO~pellets at the top and bottom of the fuel pellet stack.Axial blankets are designed to reduce neutron leakage and therefor improve uranium utilization. | L-93-196 Attachment Page 4 of 18 1.0 UNIT 4 CYCLE XIV CORE'.1 Fuel Desi n Chan es Unit 4 Cycle, 14 fuel is essentially the same as Cycle 13 fuel with the exception that Cycle 14 fuel includes axial blankets and additional snag-resistant grids.Axial blankets, previously used in Turkey Point Unit 3 Cycle 13 core design are new to Unit 4.Axial blankets consist of a nominal 6 inches of natural VO~pellets at the top and bottom of the fuel pellet stack.Axial blankets are designed to reduce neutron leakage and therefor improve uranium utilization. | ||
Anti-snag mid-grids were included in the Unit 4 Cycle 13 design.The Unit 4 Cycle 14 design adds top and bottom anti-snag grids to the fuel assembly design.This addition wi;11 reduce the possibility of assembly damage during fuel handling.1.2 Loadin Pattern This section presents the as-loaded core configuration (Figure 1, page 5).1'.3 Rod Pattern and Rod Dro Times This section presents the Control and Shutdown Rod pattern and the Rod Drop Times for all rods as measured per Procedure 4-PMI-028..3,"RPI, Hot Calibration, CRDM Stepping Test, and Rod Drop Test" (Figure 2, page 6).All rods.meet the drop time limit of 2.4 seconds as per Technical Specification 3.1.3.4. | Anti-snag mid-grids were included in the Unit 4 Cycle 13 design.The Unit 4 Cycle 14 design adds top and bottom anti-snag grids to the fuel assembly design.This addition wi;11 reduce the possibility of assembly damage during fuel handling.1.2 Loadin Pattern This section presents the as-loaded core configuration (Figure 1, page 5).1'.3 Rod Pattern and Rod Dro Times This section presents the Control and Shutdown Rod pattern and the Rod Drop Times for all rods as measured per Procedure 4-PMI-028..3,"RPI, Hot Calibration, CRDM Stepping Test, and Rod Drop Test" (Figure 2, page 6).All rods.meet the drop time limit of 2.4 seconds as per Technical Specification 3.1.3.4. | ||
0 4l L-93-196 Attachment Page 5 af 18 FZGURE 1 TURKEY POZNT UNZT 4 CYCLE 14 CORE LOADZNG RR23 HF23 RR30 HF16 RR15 HF06 A I I NORtH I I PP26 SS35 R52 TT38 RR49 T740 SS33 R54 PP55 RR19 TT46 RR04 SS48 SS41 TT19 4M RR46 R57 SS20 R53 TT03 16M TT22 4'M RR27 R56 SS18 R51 7706 16IJ TT24 4M RR47 R55 TT48 RR07 SS29 SS47 RRO6 PP40 TT49 SS40 SS14 R61 TTOS 16M RR39 R59 TT30 8M RR33 R60 TT14 16M SS11 R58 SS39 TT50 PP33 RROS HF07 SS38 R66 TT41 TT31 4M SS24 R70 RR41 R65 TT16 16IJ T715 16M RR36 R65 RR11 SS10 SS01 TT33 SM SS17 R64 SS03 SS07 T734 SM RR10 SS09 T702 16M RR34 R69 RR51 R63 TT04 16M TT18 4M SS25 R67 SS37 R62 TT42 RR20 HF13 RR29 HF15 RR09 HF20 RR50 TT43 TT32 4M SS21 R77 TT16.TT20 16M 8M T711 RR35 16M R78 SS27 R74 SS16 TT35 SM RR25 R73 SS13 SS12 TT36 8M SS19 R72 SS15 TT27 SM RR40 RSO RR24 R71 TT12 16M TT28 4M SS26 R76 RR48 TT37 RR32 HF05 RR14 HF02 SS30 R84 T725 4M RR43 R53 TT09 16M RR26 SSOS SS28 R82 SS06 RR01 TT10 16M RR52 R81 TT26 4M SS43 R79 PP51 TT51 SS32 SS04 R89 T705 16IJ RR37 R86 TT21 SM RR38 R87 TT07 1QJ SS05 R85 SS44 TT45 PP45 RR12 8$46 SS34 RR13 TT52 RR42 R90 T723 4M TT01 16M S$23 R92 RR28 R91 TT17 4M T713 16M SS22 R95 RR44 RSS TT29 4M SS31 SS45 RR03 TT47 RR05 SS42 R101 TT44 RR45 TT39 SS36 R93 PP54 RR22 HF11 RR31 RR21 HF10 HF01 key: ASSY ASSY INS.PPxx Rxx RRxx zzM SSxx HFxx TTxx....PP Reload Cvcle 11 RR Reload Cycle 12 SS Reload Cycle 13 TT Feed CycLe',14 R Control Rod M MASA insert HF Hafniisa inserts xx Sequence amber zz Hwher of MASA fingers 4I 0 L-93-196 Attachment Page 6 of 18 FIGURE 2 TURKEY POINT UNIT 4 CYCLE 14 RCCA BANK PATTERN AND DROP TZMES A I I NORTH I I CB.B 1.39 CS 8 1.37 SB-A 1.34 SB A 1.34 CB-C 1.32 CB-D 1.35 CB.C 1.34 SB-B'.33 CB A 1.32 CB-A 1.35 SS.B 1.35 CB-8 1.37 CB-C 1.35 SS.B 1.37 CS C 1.34 CB 8 1.37 SB-A 1.36 CB A 1.37 CB.A 1.34 SS A 1.34 CB 0 1.34 SB 8 1.37'CBD 1.35 SB-B 1.35 CB.D 1.35 SB A 1.35 CB A 1.31 CS-A 1.32 SB A 1.36 CS-S 1.35 CB C 1.32 SB 8 1.35 CB C 1.34 CB-S 1.40 SB-S 1.32 CB A 1.33 CB-A 1.35 SS-S 1.30 CB.C 1.33 CB-D 1.34 CB-C 1.32 SS.A 1.33 SB A 1.35 CS~8 1.34 CB 8 1.35 keys RCCA RCCA TINE SB-x sec.CS-x SB Shutdown Bank CB Control Bank x Bank Identifier sec.Drop Time toDashpot li L-93-196 Attachment Page 7 of 18 2.0 XNITIAL CRITICALITY | 0 4l L-93-196 Attachment Page 5 af 18 FZGURE 1 TURKEY POZNT UNZT 4 CYCLE 14 CORE LOADZNG RR23 HF23 RR30 HF16 RR15 HF06 A I I NORtH I I PP26 SS35 R52 TT38 RR49 T740 SS33 R54 PP55 RR19 TT46 RR04 SS48 SS41 TT19 4M RR46 R57 SS20 R53 TT03 16M TT22 4'M RR27 R56 SS18 R51 7706 16IJ TT24 4M RR47 R55 TT48 RR07 SS29 SS47 RRO6 PP40 TT49 SS40 SS14 R61 TTOS 16M RR39 R59 TT30 8M RR33 R60 TT14 16M SS11 R58 SS39 TT50 PP33 RROS HF07 SS38 R66 TT41 TT31 4M SS24 R70 RR41 R65 TT16 16IJ T715 16M RR36 R65 RR11 SS10 SS01 TT33 SM SS17 R64 SS03 SS07 T734 SM RR10 SS09 T702 16M RR34 R69 RR51 R63 TT04 16M TT18 4M SS25 R67 SS37 R62 TT42 RR20 HF13 RR29 HF15 RR09 HF20 RR50 TT43 TT32 4M SS21 R77 TT16.TT20 16M 8M T711 RR35 16M R78 SS27 R74 SS16 TT35 SM RR25 R73 SS13 SS12 TT36 8M SS19 R72 SS15 TT27 SM RR40 RSO RR24 R71 TT12 16M TT28 4M SS26 R76 RR48 TT37 RR32 HF05 RR14 HF02 SS30 R84 T725 4M RR43 R53 TT09 16M RR26 SSOS SS28 R82 SS06 RR01 TT10 16M RR52 R81 TT26 4M SS43 R79 PP51 TT51 SS32 SS04 R89 T705 16IJ RR37 R86 TT21 SM RR38 R87 TT07 1QJ SS05 R85 SS44 TT45 PP45 RR12 8$46 SS34 RR13 TT52 RR42 R90 T723 4M TT01 16M S$23 R92 RR28 R91 TT17 4M T713 16M SS22 R95 RR44 RSS TT29 4M SS31 SS45 RR03 TT47 RR05 SS42 R101 TT44 RR45 TT39 SS36 R93 PP54 RR22 HF11 RR31 RR21 HF10 HF01 key: ASSY ASSY INS.PPxx Rxx RRxx zzM SSxx HFxx TTxx....PP Reload Cvcle 11 RR Reload Cycle 12 SS Reload Cycle 13 TT Feed CycLe',14 R Control Rod M MASA insert HF Hafniisa inserts xx Sequence amber zz Hwher of MASA fingers 4I 0 L-93-196 Attachment Page 6 of 18 FIGURE 2 TURKEY POINT UNIT 4 CYCLE 14 RCCA BANK PATTERN AND DROP TZMES A I I NORTH I I CB.B 1.39 CS 8 1.37 SB-A 1.34 SB A 1.34 CB-C 1.32 CB-D 1.35 CB.C 1.34 SB-B'.33 CB A 1.32 CB-A 1.35 SS.B 1.35 CB-8 1.37 CB-C 1.35 SS.B 1.37 CS C 1.34 CB 8 1.37 SB-A 1.36 CB A 1.37 CB.A 1.34 SS A 1.34 CB 0 1.34 SB 8 1.37'CBD 1.35 SB-B 1.35 CB.D 1.35 SB A 1.35 CB A 1.31 CS-A 1.32 SB A 1.36 CS-S 1.35 CB C 1.32 SB 8 1.35 CB C 1.34 CB-S 1.40 SB-S 1.32 CB A 1.33 CB-A 1.35 SS-S 1.30 CB.C 1.33 CB-D 1.34 CB-C 1.32 SS.A 1.33 SB A 1.35 CS~8 1.34 CB 8 1.35 keys RCCA RCCA TINE SB-x sec.CS-x SB Shutdown Bank CB Control Bank x Bank Identifier sec.Drop Time toDashpot li L-93-196 Attachment Page 7 of 18 2.0 XNITIAL CRITICALITY 2.1 INVERSE COUNT RATE RATXO (XCCR)vs DILUTXON The approach to criticality began May 23, 1993 at approximately 0242 when the stepping of shutdown banks began in accordance with Procedure 0-OSP-040. | ||
COUNT RATE RATXO (XCCR)vs DILUTXON The approach to criticality began May 23, 1993 at approximately 0242 when the stepping of shutdown banks began in accordance with Procedure 0-OSP-040. | |||
6,"Initial Crit'icality After Refueling.'" Criticality.was achieved approximately 6 hours and 24 minutes later on May.23, 1993 at 0906 by diluting 14,460 gallons of water with control bank D at 180 steps.Figure 3 (page 8)is a plot of the ICRR during the approach to criticality. | 6,"Initial Crit'icality After Refueling.'" Criticality.was achieved approximately 6 hours and 24 minutes later on May.23, 1993 at 0906 by diluting 14,460 gallons of water with control bank D at 180 steps.Figure 3 (page 8)is a plot of the ICRR during the approach to criticality. | ||
2.2 CRITICAL DATA Upon attaining criticality, the flux level was increased'o 1 x 10 amps on the reactivity computer to obtain critical data, as follows: Tavg=547.1'F Control Bank D=178 Steps Reactor Coolant System (RCS)Boron=1689 ppm Picoammeter Flux=1 x 10'N35 Flux N36 Flux 1.1 x 10 A 1.8 x 10' 4k 1.3 1.2 FIGURE 3 Turkey Point Unit 4 (1/M)on Approach to Criticality (1/M)DURING ROD WITHDRAWAL N31 Page 8 1'.1 0.9 0.8 N32 0 0 0 0 0 0 0 0 0.7 T'I 50 100 150 228 50 100 150 228 50 100 150 228 22 100 150 228 SHUTDOWN BANK A SHUTDOWN BANK B I CBAH I CB-C-H CBB I I CBD~(1/M)DURING DILUTION 1 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0 0 p 0 0 p 0 0 0 5000 10000 Gallons Water Added 15000 20000 | |||
DATA Upon attaining criticality, the flux level was increased'o 1 x 10 amps on the reactivity computer to obtain critical data, as follows: Tavg=547.1'F Control Bank D=178 Steps Reactor Coolant System (RCS)Boron=1689 ppm Picoammeter Flux=1 x 10'N35 Flux N36 Flux 1.1 x 10 A 1.8 x 10' 4k 1.3 1.2 FIGURE 3 Turkey Point Unit 4 (1/M)on Approach to Criticality (1/M)DURING ROD WITHDRAWAL N31 Page 8 1'.1 0.9 0.8 N32 0 0 0 0 0 0 0 0 0.7 T'I 50 100 150 228 50 100 150 228 50 100 150 228 22 100 150 228 SHUTDOWN BANK A SHUTDOWN BANK B I CBAH I CB-C-H CBB I I CBD~(1/M)DURING DILUTION 1 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0 0 p 0 0 p 0 0 0 5000 10000 Gallons Water Added 15000 20000 | |||
L-93-196 Attachment Page 9 of 18 3.0 | L-93-196 Attachment Page 9 of 18 3.0 | ||
Revision as of 01:52, 6 May 2019
| ML17352A206 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/20/1993 |
| From: | PLUNKETT T F FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-93-196, NUDOCS 9308300191 | |
| Download: ML17352A206 (40) | |
Text
ACCEI Etui.T~D DOCUMENT DIST I UTION SYSTEM REGULA~..Y INFORMATION DISTRIBUTIO ,SYSTEM (RIDS)ACCESSION NBR:930830019l DOC.DATE: 93/08/20 NOTARiZED:
NO DOCKET¹FACIL:50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION PLUNKETT,T.F.
Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
"Turkey Point Nucl'ear Plant Unit 4,Cycle XIV Startup Rept." W/930820 ltr.DISTRIBUTION CODE: IE26D COPIES RECEIVED LTR J ENCL I SIZE: I'ITLE: Startup Report/Refueling Report (per Tech Specs)NOTES: RECIPIENT lD CODE/NAME PD2-2 PD, COPIES LTTR ENCL, 1 1 RECIPIENT ID CODE/NAME RAGHAVAN,L COPIES LTTR ENCL 2 2 ZNTERNAL: AEOD/DSP/TPAB NUDOCS-ABSTRACT RGN2 FILE 01 EXTERNAL: NRC PDR 1 1 1 1 1 1 1 1 NRR/SR%3 EG IL NSIC 02 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS" FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 ik gF L-93-196 10 CFR 50.36 U.S~..Nuclear Regulatory Commission Attn: Document Control Desk.Washington, D.C.20555, Gentlemen:
Re: Turkey Point Unit 4 Docket No.50-251-Startu'Re ort In accordance with Technical Specification 6.9.1.1, the enclosed Startup Report is provided for Flori'da Power and Light Company Turkey Point Unit 4.The Unit 4 Cycle XIV Startup Report documents the first use of axial (natural uranium)blankets and snag-resistant spacer grids at the top and'ottom of the fuel assemblies.
If you have any questions, please contact us.Very, truly yours, T.F.Plunkett Vice President Turkey Point Nuclear TFP/RJT/rt
."Attachment cc: S.D.Ebneter, Regional Administrator, Region IIUSNRC Senior Resident Inspector, USNRC, Turkey Point Nuclear 9308300191 930820 PDR ADO'500025i PDR an FPL Group company
ATTACHMENT FLORIDA POWER 6 LIGHT COMPANY TUEQCEY POINT NUCLEAR PLANT UNIT O'YCLE XIV STARTUP REPORT
L-93-196 Attachment Page 2 of 18 INTRODUCTION This report contains the official summary of the Startup Physics Tests performed on Turkey Point Unit 4 at the beginning of Cycle XIV.The testing program was conducted in accordance with Turkey Point Plant Procedures, and meets the requirements of ANSI/ANS 19.6.1, Revision 0.(12/13/85),"Startup Physics Tests for Pressurized Water Reactors".
Withdrawal of Shutdown banks commenced May 23,'1992 at 0242 and initial criticality was achieved 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 24 minutes later.WCAP-13682,"The Nuclear Design and Core Management of the Turkey Point Unit 4 Nuclear Power Plant, Cycle 14", was the design source for verifying that acceptance criteria as specified in ANSI/ANS 19.6.1 were met.All tests performed for nuclear design verification meet their acceptance criteria.The contents of this report provide the documentation required by Technical Specification 6.9.1.1.H
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L-93-196 Attachment Page, 3 of 1'8 TABLE OF CONTENTS INTRODUCTION 1'.0, UNIT 4, CYCLE XIV CORE 1.1 Fuel Design Changes 1'Loading Pattern 1.3 Rod Pattern and Rod Drop Times 2.0 INITIAL CRITICALITY 2.1 Inverse Count Rate Ratio (ICRR)vs.Dilution.2.'2 Critical Data 3.,0 SUMMPGtY OF'TESTS 3.1 Nuclear Heating 3.'2 Reactivity vs.Period 3'Boron Endpoints 3.,4 Rod Worth (ppm), Most Reactive Bank 3.'5 Rod Worth (pcm)3.6 Temperature Coefficient 3.7 Hot Zero Power (HZP)Differential Boron Worth 4.0 SHUTDOWN.MARGIN 5.0 POWER DISTRIBUTION MAPS 6.0'CRITICAL BORON CONCENTRATION 0
L-93-196 Attachment Page 4 of 18 1.0 UNIT 4 CYCLE XIV CORE'.1 Fuel Desi n Chan es Unit 4 Cycle, 14 fuel is essentially the same as Cycle 13 fuel with the exception that Cycle 14 fuel includes axial blankets and additional snag-resistant grids.Axial blankets, previously used in Turkey Point Unit 3 Cycle 13 core design are new to Unit 4.Axial blankets consist of a nominal 6 inches of natural VO~pellets at the top and bottom of the fuel pellet stack.Axial blankets are designed to reduce neutron leakage and therefor improve uranium utilization.
Anti-snag mid-grids were included in the Unit 4 Cycle 13 design.The Unit 4 Cycle 14 design adds top and bottom anti-snag grids to the fuel assembly design.This addition wi;11 reduce the possibility of assembly damage during fuel handling.1.2 Loadin Pattern This section presents the as-loaded core configuration (Figure 1, page 5).1'.3 Rod Pattern and Rod Dro Times This section presents the Control and Shutdown Rod pattern and the Rod Drop Times for all rods as measured per Procedure 4-PMI-028..3,"RPI, Hot Calibration, CRDM Stepping Test, and Rod Drop Test" (Figure 2, page 6).All rods.meet the drop time limit of 2.4 seconds as per Technical Specification 3.1.3.4.
0 4l L-93-196 Attachment Page 5 af 18 FZGURE 1 TURKEY POZNT UNZT 4 CYCLE 14 CORE LOADZNG RR23 HF23 RR30 HF16 RR15 HF06 A I I NORtH I I PP26 SS35 R52 TT38 RR49 T740 SS33 R54 PP55 RR19 TT46 RR04 SS48 SS41 TT19 4M RR46 R57 SS20 R53 TT03 16M TT22 4'M RR27 R56 SS18 R51 7706 16IJ TT24 4M RR47 R55 TT48 RR07 SS29 SS47 RRO6 PP40 TT49 SS40 SS14 R61 TTOS 16M RR39 R59 TT30 8M RR33 R60 TT14 16M SS11 R58 SS39 TT50 PP33 RROS HF07 SS38 R66 TT41 TT31 4M SS24 R70 RR41 R65 TT16 16IJ T715 16M RR36 R65 RR11 SS10 SS01 TT33 SM SS17 R64 SS03 SS07 T734 SM RR10 SS09 T702 16M RR34 R69 RR51 R63 TT04 16M TT18 4M SS25 R67 SS37 R62 TT42 RR20 HF13 RR29 HF15 RR09 HF20 RR50 TT43 TT32 4M SS21 R77 TT16.TT20 16M 8M T711 RR35 16M R78 SS27 R74 SS16 TT35 SM RR25 R73 SS13 SS12 TT36 8M SS19 R72 SS15 TT27 SM RR40 RSO RR24 R71 TT12 16M TT28 4M SS26 R76 RR48 TT37 RR32 HF05 RR14 HF02 SS30 R84 T725 4M RR43 R53 TT09 16M RR26 SSOS SS28 R82 SS06 RR01 TT10 16M RR52 R81 TT26 4M SS43 R79 PP51 TT51 SS32 SS04 R89 T705 16IJ RR37 R86 TT21 SM RR38 R87 TT07 1QJ SS05 R85 SS44 TT45 PP45 RR12 8$46 SS34 RR13 TT52 RR42 R90 T723 4M TT01 16M S$23 R92 RR28 R91 TT17 4M T713 16M SS22 R95 RR44 RSS TT29 4M SS31 SS45 RR03 TT47 RR05 SS42 R101 TT44 RR45 TT39 SS36 R93 PP54 RR22 HF11 RR31 RR21 HF10 HF01 key: ASSY ASSY INS.PPxx Rxx RRxx zzM SSxx HFxx TTxx....PP Reload Cvcle 11 RR Reload Cycle 12 SS Reload Cycle 13 TT Feed CycLe',14 R Control Rod M MASA insert HF Hafniisa inserts xx Sequence amber zz Hwher of MASA fingers 4I 0 L-93-196 Attachment Page 6 of 18 FIGURE 2 TURKEY POINT UNIT 4 CYCLE 14 RCCA BANK PATTERN AND DROP TZMES A I I NORTH I I CB.B 1.39 CS 8 1.37 SB-A 1.34 SB A 1.34 CB-C 1.32 CB-D 1.35 CB.C 1.34 SB-B'.33 CB A 1.32 CB-A 1.35 SS.B 1.35 CB-8 1.37 CB-C 1.35 SS.B 1.37 CS C 1.34 CB 8 1.37 SB-A 1.36 CB A 1.37 CB.A 1.34 SS A 1.34 CB 0 1.34 SB 8 1.37'CBD 1.35 SB-B 1.35 CB.D 1.35 SB A 1.35 CB A 1.31 CS-A 1.32 SB A 1.36 CS-S 1.35 CB C 1.32 SB 8 1.35 CB C 1.34 CB-S 1.40 SB-S 1.32 CB A 1.33 CB-A 1.35 SS-S 1.30 CB.C 1.33 CB-D 1.34 CB-C 1.32 SS.A 1.33 SB A 1.35 CS~8 1.34 CB 8 1.35 keys RCCA RCCA TINE SB-x sec.CS-x SB Shutdown Bank CB Control Bank x Bank Identifier sec.Drop Time toDashpot li L-93-196 Attachment Page 7 of 18 2.0 XNITIAL CRITICALITY 2.1 INVERSE COUNT RATE RATXO (XCCR)vs DILUTXON The approach to criticality began May 23, 1993 at approximately 0242 when the stepping of shutdown banks began in accordance with Procedure 0-OSP-040.
6,"Initial Crit'icality After Refueling.'" Criticality.was achieved approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 24 minutes later on May.23, 1993 at 0906 by diluting 14,460 gallons of water with control bank D at 180 steps.Figure 3 (page 8)is a plot of the ICRR during the approach to criticality.
2.2 CRITICAL DATA Upon attaining criticality, the flux level was increased'o 1 x 10 amps on the reactivity computer to obtain critical data, as follows: Tavg=547.1'F Control Bank D=178 Steps Reactor Coolant System (RCS)Boron=1689 ppm Picoammeter Flux=1 x 10'N35 Flux N36 Flux 1.1 x 10 A 1.8 x 10' 4k 1.3 1.2 FIGURE 3 Turkey Point Unit 4 (1/M)on Approach to Criticality (1/M)DURING ROD WITHDRAWAL N31 Page 8 1'.1 0.9 0.8 N32 0 0 0 0 0 0 0 0 0.7 T'I 50 100 150 228 50 100 150 228 50 100 150 228 22 100 150 228 SHUTDOWN BANK A SHUTDOWN BANK B I CBAH I CB-C-H CBB I I CBD~(1/M)DURING DILUTION 1 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0 0 p 0 0 p 0 0 0 5000 10000 Gallons Water Added 15000 20000
L-93-196 Attachment Page 9 of 18 3.0
SUMMARY
OP TESTS This section provides a summary of the results of the low power physics tests for Unit 4, Cycle XIV along with the Nestinghouse design data.For each test, the acceptance criteria is listed at the bottom of the table.This report compares design and measured data using Difference and Percent Difference.
Difference
=Predicted-Measured For calculating Percent Difference, the equation is:~PredfctedValue 11&00 2tfeaauredVal ue 3.1 Nuclear He tin The point of adding Nuclear Heat was determined in accordance with Procedure 0-OSP-040.
6,"Initial Criticality After Refueling".
This is performed by establishing a small positive startup rate and measuring the flux level at which T, departs from its established steady state value.Nuclear Heating was measured to first occur at values presented on Table 3.1.1.T?LB'~1 1C FLUX LEVEL (AMPH)Pico Oter 1 S x 10 N-35 2.1 x 10 N-36 3.4 x 10 8 All physics tests were conducted at or below 1 x 10" amps on the picoammeter connected to N-44 to assure Nuclear Heating did not occur.
~l' L-93-196 Attachment Page 10 of 18 3.2 Reactivit vs.Period Reactivity Computer checkout was done in accordance with Procedure.0-0SP-040.6,"Initial Criticality After Refueling." This checkout is performed by inserting small positive and negative reactivities using rod motion.The period of the flux change is used to calculate the design reactivity.
The measured reactivity is taken directly from the reactivity computer.The results of this test are given in Table 3.2.1.TABLE 3.2.1: MEASURED REACTIVITY VS.DESIGN PERIOD (SEC)+151.2-249.6+78.3+129.1 MEASURED REACTIVITY (PCM)+39.0-33.'0+65.0+44.0 DESIGN REACTIVITY (P CM)+38.8 33~7+65.4+44.2 DIFF*+.5 2~1-.6-5 3.3*Acceptance Criteria is 4%for positive period.Boron End ints The Boron Endpoint measurement is a way, of measuring the steady state boron concentration of an under-rodded core (positive period in effect)or an over-rodded core (negat'ive period'n effect).In FPL's testing program the first case is an unrodded core and the second case is a core with the reference bank at the bottom.The Boron Endpoint is measured using Procedure 0-OSP-040.5,"Nuclear Design Verification." In this methodology a just-critical condition is established as near as practical to the required rod configuration.
The rods are then moved into the desired configuration and back to equilibrium.
The RCS boron concentration which was measured at equilibrium is then adjusted for the ppm worth of the rods.The results of the two boron endpoint measurements are given in Table 3.3.1.TABLE 3.3.1: BORON ENDPOINTS (ppm)MEASURED (ppm)1698 MESTINGHOUSE (ppm)1693 DIFFERENCE*(ppm)SB-B 1552 1547*Acceptance Criteria is+/-50 ppm.
41' L-93-196 Attachment Page 11 of 18 3.4 Rod'orth Most Reactive Bank Rod Worth was measured per Procedure O-OSP-040.5,"Nuclear Design Verification." The reference bank (highest predicted worth)was first inserted as the controlling bank was.withdrawn.
Then a dilution was used to adjust, the reference bank to approximately 30 steps from the bottom.Finally a Boron Endpoint (see section 3.3)was performed.
By graphing the rod worth, measured by the reactivity computer, versus rod insertion, a differential rod worth curve is generated..
By summing the differential worth an integral rod worth curve is generated and the bank worth determined.
The total bank worth is presented in Table 3.4.1.The Integral and differential bank worth of the reference bank is displayed in Figure 4 (page 12).TABLE 3.4.1: ROD,WORTH (pcm)MEASURED WESTINGHOUSE (pcm)(pcm)SB-B 1173 1189 DIFF*(+)1.4 3.5*Acceptance Criteria is less than 10%Remainin Banks Rod Worth cm R The remaining RCCA bank worth was measured per Procedure 0-OSP-040.5,"Nuclear Design Verification," using, the rod swap technicgxe.
This technique involves swapping the negative reactivity of the bank being inserted with the positive reactivity from the bank being withdrawn.
Each bank is sequentially swapped for the reference bank.The worth of each bank can then be determined from the integral rod worth curve.The results of this measurement are given in Table 3.5.1.TABLE 3.5.1: ROD WORTH (pcm)SB-A CB-A CB-B CB-C CB-D MEASURED (pcm)1052.3 1085.6 435.3 1093.0 635.9 WESTINGHOUSE (pcm)1098 1104 484'163 664 0 DIFF*()4.3 1.7.11.2 6.4 4.4 TOTAL 5475.1 5702 4.1 NOTE: The total rod worth includes the reference bank.*The acceptance criteria for rod worth measurements are: Individual banks within+/-15%or+/-100 pcm of design, whichever is greater and Total of all measured banks within+/-10%of design.
I 12 Q 6)~10 (0 Q~8 0 Ne C6 Q3 4 0$S~0)Cl INTEGRAL FIGURE 4 Differential and Integral Reference Bank Worth ORTH DIFFE EMTIAL WORTH Page 12 1400 1 200 1000 g)U3 Q 800~600~~U O 400 2 200 0 50 100 150 200 228 Rod Position (steps withdrawn)
L-93-196 Attachment, Page 13 of 18 3.6 Tem erature Coefficient The isothermal and moderator temperature coefficients were determined using Procedure 0-OSP-040.5,"Nuclear Design Verification." The isothermal temperature is measured by varying the moderator temperature below the point of adding nuclear heat.The reactivity change is then simply divided by the temperature change to obtain the isothermal temperature coef ficient.The moderator temperature coefficient is calculated from the isothermal temperature coefficient by subtracting the doppler coefficient.
The values determined for this testing sequence are presented on Tables 3.6.1 and 3.6.2 below: TABLE 3.6.1: ISOTHERMAL TEMPERATURE COEFFICIENT (pcm/F)MEASURED (pc/F)-1.44 WESTINGHOUSE (pcm/F)-.43 DIFF*(pcm/F)1.01*Acceptance Criteria is+/-2 pcm/F of design.TABLE 3.6.2: MODERATOR TEMPERATURE COEFFICIENT (pcm/F)MEASURED*(pcm/F).26 WESTINGHOUSE (pcm/F)1.27*Acceptance Criteria is<5 pcm/'F.3.7 HZP Differential Boron Worth The Hot Zero Power (HZP)Differential Boron Worth was measured using Procedure O-OSP-040.5,"Nuclear Design Verification." The worth of the reference bank is divided by the boron change from ARO to the reference bank fully inserted.The value obtained for this test is presented on Table 3.7.1.TABLE 3.7.1: HZP DIFFERENTIAL BORON WORTH (pcm/ppm)MEASURED (pcm/pr)8.56 WESTINGHOUSE (pcm/pe)8.32 DIFF*(pcm/pz)2.8*Acceptance Criteria<+/-15%.
4i L-93-196 Attachment Page 14 of 18 4.0 SHUTDOWN MARGIN The Shutdown Margin vas calculated prior to power escalation to verify adequate shutdown capability.
For this calculation, the total of the design rod worth (minus.the most reactive stuck rod)vere reduced by 7%.The results show adequate shutdown margin at Beginning of Life (BOL)and End of Life (EOL).The following is a summary of the data used: TABLE 4.1: UNIT 4, CYCLE XIV SHUTDOWN DATA HKP Control Rod North Re irement BOL EOL All Rods Inserted Less Most Reactive Stuck Rod (1)Less 7%6.28 6.72 5.84 6.25 Hot Full Power HFP to HKP Reactivit Insertion Reactivity Defects (Doppler, T,~, Void, Redistribution)
Rod Insertion Allowance (2)Total Requirements Shutdown Margin (1)-(2)'(%a@)Required Shutdown Margin (%wp)*Source: WCAP 13682 1.72 2.71 0.50 0.50 2.22 3.21 3.62 3.04 1.00 1.77 5.0 POWER DISTRIBUTION MAPS The core,was mapped using incore instrumentation for power levels of 30%, 50%and 100%.A summary of the results are presented-on pages 15 through 17.
0 FIGURE 5 SVNKARY OF 30X POUER FLUXHAP Page 15 HEASURED ASSEHBLY POMER AND PERCENT DIFF.TO EXPECTED PCMER INSTR.LOC.ONLY 15 14'13 12 11 10 9 8 7 6 5 4 3 2 1 0.349.0.824.0.222.0.232.-1.8.1~115.0.774.0.223.1.103.0.808.0.345.0.393., 3.7.1.110~0.386.0.941.1.272.1.328.1.4.'1.076.1.262.1.315.1.229.-0.7..2.7.1.298.1.100.0.9.0.366.1.286.0.900.1.284.1.103.1.304.'0.933.
0.348.-8.0.0.341.-0.3.1.083.1.198.0.817.1.337.1'.084.1.196.1.250..6.5.1.292.0.988.1.167.1.0.1.223.1'.331.4.0.1.255.1.202.1.339.1.292.3.3.1.0.1'94.~~~0.999.0.313.1.235.0.996.1.273.1'.056.1.261.0.786.0.228.0.5.1.109.1'267.1.330.1.207.1.222~4.5..2.1~1.252'.178.1.253.1.169.1.066.1.9..-7.7.1~208.1.218.-3.1~1.110.0.227.G~0.244: O.798.0.240.1.195.6.8.0.865.1.274.~3.8.0.908.1.384.5.7.1.122.1.294.1.278.1.238.-4.1.1.016..1.352.1.275.5.7.1.164.1.209.1.184.0.820.1.257.1.194.1.181.1.223.0.2.1.285.1.199.4.5;1.224.1.261.1.208.0.963.2.3.2.9..-3.6..1.211.0.843.1.326.-5.5.0.1.1.243'.996.-9.0.1.266.1.101.1.199.1.217.0.785.1.140.0.835.2.2.~~~0.238.0.7.0.231.0.361.1.162.0.411.1.337.1.035.8.5.1.368.7.0.1.331.1.051.-4.1.1.213.0.837.1.206.1.109.1.299..1.163.1.310.1.151.1.285.1.294.1.2.1.304.1.9.0.947.0.361.-4.9.1.246.1.045.0.338.0.411.1.087.1.255.1.227.1.258..5.0.1.275.1.346.1.097.0.376.0.327.0.779..4.6.1.125.0.243.6.9.0.809.1.191.2.7.6.4.0.249.0.236.0.843.D.344.0.9.POMER TILT IN UPPER HALF OF CORE (-,+)~(+,+)0.9974.0.9665~~~~~~~~~1.0486.0.9875 (--)~(+-)POUER TILT IN LOUR HALF OF CORE (-,+).(+,+)1.0087.1.0129~'~~~~~~~~0.98'l7.0.9966 (--)(+)"CORE AVERAGE AXIAL OFFSET 0.208 TOP TEN NUCLEAR F DELTA H 245 G14NI 309 B 7IC 260 F13LC 274 E12LF 273 E13HB 287 D11JD 185 N 5FL 293 D SFD 233 H11HL 198 L 4DJ FDHN*1.5422 FOHN>1.5359 FOHN"-1.5285 FOHN<1.5262 FDHK>1.5020 FDHN=1.4936 FOHN>1.4909 FDHHi1.4907 FOHNa1'.4859 FDHHa1.4787 LINITING 3 FO ELEVATIOHS (TOP 15X, BOTTOK 15X, AND'NIDDLE 7OX OF THE CORE)AXIAL POINT 28 1D 52 FO(Z)LIHIT 4.6052 4.3964 4.6400 HEAS.PERCENT SOURCE.FO(Z)TO.LIN.NO.ID 2.2654 50'81 402 G14XX 1.7459 60.29 417 F13XX 1.6294 64.88 322 P 7XX
15 FIGURE 6 QPQQRY OF 50X POWER FLUXHAP MEASURED ASSEHBLY POWER AND PERCEN'I DIFF, TO EXPECTED POWER INSTR.LOC.ONLY 14 13 12 11 10 9 8 7 6 5 4 3 Page 16.0.225.0.236.-0.2.0.226.0.386.2.0.~~1.245.1.242'.086.1'89.-1.6.1.318.1.195.-0.4.-5.3.1.031.0.342.0.801.1.111.0.774.1.103.0.773.0.324.0.379..0.382.0.962.1.282.1.080.1.253.0.870.1.253.1.075.1.264'.937.0.378..0.1~0.340.1.081.-0.6.1.280.1~277.-0.2.1.277.1.136..1.7.1.264..1.3.1.158.1.308.1.261.1.236.0.8..1.5.-3.5.1.065.0.340.0.811.1.319.1.105.1.307.0.991~1.177.1.214.1.197.0.995.1.272.1-067.1.262.0~810..0.226.J 1.133.1.278.1'96.1.8.1.182.1.221.1.206.1.157.1.232.0.0.1.182.1.136.-1.7.1.249.1.240.1.112.0.225.~0.239.H 0.794.1.332.0.7.0.902.1.304.1.8.1.264.1.206.0.815.1.164.1.210.-1.3.1.259.0.880~1.305.-1.3.0'.785.0.236.0.0..0.231.G~1.211~1.147.1.243.1.194.1.269.3.0.1.283.4.2.1.234.1.277.1.060.1.143.1.276.1.290.1 178.1.228 1.323.1.031.1.255.1.221.1.015.1.5.1.226.2.4.1.283.1.264.0.832.1.060..3.3.1.339.1.120.2.3.0.349.1.120.1.319.1.313.2.7.1.314.1.253.0.393.0.990.3.8.1~106.1~0.1.288.0.899.1.091.1~280.0.9.1.266.-1.2.0.942.0.375.1'21.1.179.1.299.1.170.1.296.0.799.-2.1.0.335.~~1.113.0.225.0.394.1.103.1.312~1.269.1.345.1.7.1.279.1.312.1.073.0.376.0.339.0.809.-0.9.1.150.0.809.1.145~2.4.0.821.0.339.-0'.0.240.5.8.0.246.0.231.POWER TILT IN UPPER HALF OF CORE (-,+).(+,+)1.0010.0.9787~~~~~~~~1.0284.0.9920 (-,).(+i)POWER TILT IN LOWER HALF OF CORE (-,+).(+,+)0.9978.0.9865~~~~~~~~~1.0128.1.0028 (,-).(+,-)CORE AVERAGE AXIAL OFFSET-0.272 TOP TEN NUCLEAR F-DELTA-H 274 E12LF 287 D11JD 307 8 9GC 273 E13NB 260 F13LC 309 8 7IC 245 G14NI 215 J14HG 179 H11JL 297 C11NC FOHN%1.5074 FDHK$1.5016 FDHK$1.4814 FDHN$1.4814 FOHN%1.4800 FDHN*1.4773 FOHN%1.4747 FDHN%1.4671 FDHN$1.4653 FOHN%1.4650 LINITING 3 FQ ELEVATIONS (TOP 15X, BOTTGH 15X, AND HIDDLE 70X OF THE CORE)AXIAL FQ(Z)KEAS.POINT L INIT FQ(Z)27 4.5936'.0692 52 4.6400 1.7941 10 4.3964 1.5974 PERCEHT SOURCE TO LIN.NO.ID 54.95 372 J14XX 61.33 384 J 2XX 63.66 431 E12XX
15 FIGURE 7 SUHHARY OF 100X FLUXNAP HEASURED ASSEHBL'Y POWER AND PERCENT DIFF.TO EXPECTED POWER-INSTR.LOC.OWLY-14 13 12 11 10 9 8 7 6 5 4 3 Page 17.0.269.0.286.13.9.0.270.0.359.0.742.1.119.0.860.1.184.0.919.0.380.0.441.13.6.1.081.1.162.-7.4~1.207.1.351.2.8.1.269.1.148.1.146.0.425.0.340.-2.4.0.864.1.026.1.145.1.151.-7.4.1.174~1.095.1.224.-6.8.1.087.1.162.-8.7.1.226.1.218.-1.4.1.226.1.001.1.243.1.002.1-206-1.240.1.183.0.995.1.216.1.059.0.410.0.970.1.232.1.003.1.225.0.986.1.221.0.987.1.174.0.976.0.424.9.3.1.090.1.235.0.379.0.871..0.281.J.18.4~.0.281.H 1.203.0.857..0.248.1.138.G..5.0.1.255'.190.1.156.1.270.3.1.1.324.1.275.1.323.3.0.1.335.1.6.0.982.1.226.-6.7.1.237.1.242.1.141.1.203.1.283.-0.2.1.226.1.206.-6.1.1.250.1.256.0.955.1.211.1.236.1.259.1.218.1~150.-2.2~1.274.~~~0~~1.012.1.319.0.3.1.263.1~221.-3.6.1.178.1.155.1.281.1.163.0.849.1.161.0.268.0.286.13.6.0'60.0.797.0.330.1.189.-5.2.1.063.1.043.1.230.~~~1.279.0.7.1.174.-5.6.1.004.1.200.1.325.-2.6.4.7.1.209.0.989.-3.3.1.251.1.189.~~~~~~~~~1.238.1.320.1.178.1.267.1.280.2.9.1.091.1.0.1.265.1'94.1.120;0.844.5.4~0.380..0.419.1.012.1.250.1.092.1.1.1.239.0;971.1.225..6.8,.0.419.,1.123.
1.334.1.257'.264.
-0.7.'l.194.1.059.1~145.-7.3.0.966.1.259.'1.073.0'11.0.439.13.0.~~~0.388.0.892.11.4.1.180.0.776.1.062.-2.0.0.837.0.388'.11.6.0.282.19.1.0.274.0.231.POWER TILT IN UPPER'ALF OF CORE (-,+).(+,+)0.9843.1.0014~~~~~~~~~1.0128.1.0015 ()(+-)POWER TILT IN LOWER HALF OF CORE (-,+).(+,+)0.9939~1.0010~~~~~~~~~'1.0005.'.0046 (-,)~(+,-)CORE AVERAGE AXIAL OFFSET 3.144 TOP TEN NUCLEAR F-DELTA-H 215 J14HG 165 P 7IN'07 8 9GC 227 J 2CG 257 G 2CI 245 G14HI 172 N 8NL 283-E 3CB 282 E 4DF 222 J 78C FOHN%I.5287 FDHK01~5057 FOHN~1.4991 FOHN=1.4787 FDHN*1.4773 FDHK>1.4495 FOHN-"1.4444 FOHN*1.4437 FDHN=1.4391 FDHN=1.4323 LIHITING 3 Fa ELEVATIONS (TOP AXIAL FQ(Z)POINT L I HI T 20 2.2585 6 2.0692 52 2.3223 15K, BOTTON 15X, AND NIDDLE 70X OF THE CORE')HEAS.PERCENT SOURCE FQ(Z)TO LIH.NO.ID 1.9780 12.42 372 J14XX 1.7324 16.27 379 J 7XX 1.9026 18.07 322 P 7XX 0 0 L-93-196 Attachment Page 18 of 18~'.0 CRITICAL BORON CONCENTRATION The critical boron concentration was calculated by adjusting a measured boron concentration to the equilibrium hot full-power, all rods out condition, as per Operating Procedure 1009.6,"Critical Boron Concentration-Full Power." For Unit 4, Cycle XIV, this calculation was performed at 600 Megawatt-days/metric-ton-uranium (MWD/MTU).
The following is a summary of the results.TABLE 6.1:
SUMMARY
OF CRITICAL BORON CONCENTRATION (ppm)MEASURED (ppm)WESTINGHOUSE DIFF*(ppm)(ppm)1170 1187 17*Acceptance Criteria+/-50 ppm.
4i'IS