ML20077R993

Cycle 19 Startup Rept

ML20077R993
Person / Time
Site:	Point Beach
Issue date:	08/16/1991
From:	Zach J WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-91-082, CON-NRC-91-82 DIRNP-91-155, NUDOCS 9108260302
Download: ML20077R993 (38)

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Wisconsin Elecinc POWER COMPANY 231 w Mcnoon. ro to 20e thoue u saa g4ai m73e DIRNP 15 5 NRC 0 8 2 August 16, 1991 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:

POCKETS 50-266 CYCLE 19 STARTUD REPORT POINT BEACH NUCLEAR PLANT UNIT 1 Enclosed herewith is a summary report of the startup and power escalation testing for the Point Beach Nuclear Plant Unit 1 following refueling 18. This report is intended to document in a concise format the results of the physics testing program and the unit systems response during the unit startup. The new fuel for this cycle consisted of 16 Optimized Fuel Assemblies (OFAs) with 4.0 weight percent U-235 and 12 OFAs with 3.6 weight percent U-235.

This is-the first cycle that incorporates Integral Fuel Burnable Absorbers (IFBAs) and axial blankets of natural uranium. This is also the first cycle not using secondary neutron source assemblies.

We are providing this report for the information of the NRC as requested by your staff.

Please contact us if you have any questions concerning this submittal Very truly yours, hDY h lyv James J. Zach Director Nuclear Power Copies to NRC Regional Administrator, Region III NRC Resident Inspector 9108260302 910816 ADOCK 05000266 PDR P PDR M[

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4 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT UNIT 1 CYCLE 19 STARTUP M AY,1991 BY P.N.KURTZ a

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T ABLE OF CONTENTS Em LIST OF TABLES lil UST OF FIGURES iv

.fBEFACE y SECTION 1.Q REFUEQMQ- 1 1.1 Fuel Movement I s 1.2' Core Design 2 SECTION 2.0 . CONTROL ROD OPERATIONAL TESTING S 2.1 Hardware Changes / Incidents 5 2.2 Rod Drop Times - .

5 2.3 ' Control Rod Mechanism Timing : 5 2.4: Rod Position Calibration 5

<-- SECTION 3.0 . THERMOCDUPLE AND RTD CAllBRATION '8 SECTION 4.0 PRESSURIZER TESTS 10 4.1 - Thermal Transients' to 4.2. Heater Capacity - 10 SECTION 5.0 '- CONTROL SYSTEMS 10-SECTION.33 TRANSIENTS 10 SECTION 7.0 - 'lNITIAL CRITICAUTY AND REACTMTY COMPUTER CHECKSI 1'1

.7,1' initial Criticality .

11 7.2 ' . Reactivity Computer Setup and Checkout 11 7.2.1 Setup ~ 11 7.2.2 Checkout 11 SECTION 8.0 3ONTROL ROD WORTH MEASUREMEtfI 14 8.1 . - Test Description :- .

14 18.2 Data Analysis and Test Results- 14 8.3 - Evaluation of Test Results 15 SECTION 9.0 . TEMPERATURE COEFFICIENT MEASUREMEtjIS 19-

u. SECTION 10.0. BORON WORTH AND ENDPOINT MEASUREMENTS 19-SECTION 11.0 POWER DISTRIBUTION 21 en I ,

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T A B L E O F C O N T E N T S (C O N T ' D)

SECTiON 12.0 XENON REACTIVITY 24 P

SECTION 13 0 SHUTDOWN MARGIN CONSIDERATIONS 24 SECTION 11.Q EXCORE DETECTOR BEHAVIOR 24 14.1 Intermediate Range Detectors 24 [

14.2 Power Range Detectors 24 SECTION 15.0 OVERPOWER. OVERTEMPERATURE AND DELTA FLUX SETPOINTS SALQLILATION 27 ;

15.1 Overpower and Overtemperature AT Setpoints 27 15.2 Delta Flux input 27 r SECTION 16 0 FUEL PERFORMANCE 30 ,

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SECTION

17.0 CONCLUSION

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- lable faQ2 31 RTD Calibration Check . . . .. . . . .. .. .. G 4-1 Heater Group Power Supply Roadings . . . . . . . . . 10 71 ReactMty Computer Checkout . .. .. .. . .. ... 12 72 ReactMty Computer Setup . . . .... . .. . .. . .. . 13 8-1 Critical Rod Configuration Data . .......... . . .. . 16 82 . Comparison of Inferred / Measured Bank Worths WP.h Design Predictions 17 10 1 Boron Worth and Endpoints .... . . . . ... . . . .. . 19 11 1 initial Power Escalation Flux Map Results . . . . . . . 21 13 1 Excess Shutdown Worth Avaltable for a Full Power Trip . .. ... . 24 14 1 Power Range Detector BOL Calibration Currents . . . . . . . .. 25

. 14 2 Axial Offset Contants , . ,, .. ... ....., ... . ... 25 15 1 - Overpower AT Constants . ... ... . . .. . . 28 15-2 Overtemperature AT Constants . .. . ,,, . . . ..... 29 l

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~11-Final Core Loading Pattern UIC19 . , . , , , . . . . . , , . . , , , . . . . , , , , . 3-1-2 BO L Burnup Data , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 21 PBNP UIC19 Cold Rod Drop Times (Full-Flow) , . . . . . . . . . . . ,, ,. 6 22 PBNP UIC19 Hot Rod Drop Times (Full Flow) . ..........,,. .. 7 8 Reference Bank Differential Worth . . . . . . . . . . . . . . . . ... .... 18 10-1 Boron Concentrations During BOL HZP Physics Testing . . . . . . . ... 20 11 1 Power Distribution at 28 Percent Power . , , . , , . . . ,,,,. ,......, 22 11 2 Power Distribution at 100 Percent Power . . . . , , . , . . . , , . . . , , , . . -23 14 1 Intermediate Range Detector Response to Power Level .... ... ,, 26 161 PBNP Unit One Primary Activity . . . . . . . . . . . . . . . . . , , , . . . . , , . . -31 M ,

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, PREFACE This report is intended to document in a concise fonnat the results of the physics testing program and una systems response during the startup of Unit I following Refueling 18.

Westinghouse performed the core design calculations for Unit 1 Cycle 19. The reactivity coefficients  !

were calculated based on estimated Cycle 18 burnup of 10,75C MWD /MTU, Actual bumup was l 10,748 MWD /MTU. Cycle 18 was ended on April 6,1991, with a poak assembly burnup of 45,071 MWD /MTU ard average assembly burnup of 31,024 MWD /MTU. Electrical power was first generated during Cycle 19 on Vay 21,1991.

l This repen Is intended primarily for the use of Wiscorisin Electric Power Company personnel as a readily accessible, complete compliation of reduced data. l b

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. s UNIT 1 CYCLE 19 STARTUP REPORT May 1991 1.0 RFFUEUNG 1.1 fuel Movemo.01 A core shuffle was performod with a maximum of 11 core locations empty at any glvon [

time. The shuffle started on April 22,1991 at 1000. The first objective was to unload twelve fuel assomtWies (F/As) containing bumable poison inserts. This gave the SFP crews the maximum amount of time to remove the bumatie poison Inserts before the F/As were needed to complete the shuffle, Excore detector count rates at the start of the core shuffle woro 110 CPS from N31, 120 CPS from N32 and 20 CPS from N40. Count ates ranged from 08 to 126 CPS from N31,52 to 124 CPS from N32 and 10 to 24 CPS on N40. Count rates at the end of the shuffle were 64 CPS from N31,60 CPS from N32 and 17 CPS from N40. The r secondary sources were permanently removed from the core accounting for the lower I counts at end of the shuffle.

Boron concentration was maintained above 2000 ppm at all times. Westinghouse conservatively calculated a minimum boron concentration of 1716 ppm was required to  :

keep the core shutdown by greater than 5 percent at all times during the shuffle. Basic >

restrictions were to allow no temporary repositions of fuel and that no more than three control rods would be out of the core at any tirno. Those restrictions were part of the refueling procedure (RP 1C) and wore adhered to at all timos.

There was one fuel handling incident invoMng slight damage to a F/A. A small section of the uppermost grid of F/A UO7 was tom and folded over. The fold was approximately 1 loch long and turned up about 1/4 of an inch. A manipulator overload trip occurred when removing the adjacent F/A (H85), The tom grid on UO7 was discovered by looking at the core with binoculars after H85 was removed. When UC7

• Was inspected at the periscope, it was not certain when the damage occurred because

' there were no shiny scratches. Westinghouse r9 commended that UO7 cculd be reused, with reasonat9e cortainty that the damage would remain stable and not cause further damage. UO7 was reloaded without incident. F/A H85 had no lod' cations of scratching

. or other damage on any of its faces.-

Minor bowing problems resulted in a fleid change to the fuel shuffle sequence, F/A >

U27 at core location L-9 leaned into a hole at location L 10. F/A T09 was temporarily placed in the END basket after unsuccessfully trying to reposition it into location L 10.

The manipulator was used to resoal F/A U27. F/A T09 was then moved into L 10 with

.so load deflections.

The source assemblies were removed from the core without incident, There were no significant mechanical problems with the fuoi transfer system.

The fuel shuffle onded on April 27,1991 at 0038.

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. . UIC19 Startup Repc4 Page 2 1.2 Core Deslan New fuel (X01. X28) for Cycle 19 consists of 16 OFAs with 4.0 w/o U-235 and 12 OFAs with 3.6 w/o U-235.

This is the first cycle that incorporates Integral Fuel Burnable Absorbers (IFBAs) and  ;

axial Liankets of natural uranium.  ;

1 This is the first cycle not using secondary source assemblies.

The as loaded core matches the initial core loading pattern. The core configuration is shown in Figure 11. Of the 121 F/As loaded,120 are OFAs and 1 is of the older standard design (from the SFP) in location G-7. The as-loaded bumups for each fuel assembly are shown In Figure 12.

All control rods used in Cycle 18 were reloaded for Cycle 19.

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• UtC19 Startup Report f Page 3 FIGURE 11 Fit. ! . CORE LOADING PATTERN UIC18 A6 A7 A8 R23 R19 R26 1H109 1N107 1N113 84 85 B6 t7 B8 89 t 10 P11 117 vi8 v20 v21 119 M?1 R146 R504 C3 C. 4 C5 C6 C7 C8 C9 C 10 C 11

$28 v03 vo6 105 104 102 voa vie $17 R96 RBs R137 D* 2 D3 D4 D5 D6 07 D. 8 D9 0 10 D 11 D 12 h67 vil $19 $25 U22 U15 v29 $26 $20 v02 P20 R92 4P147 4P144 R100 E2 t3 (* 4 (* 5 E6 E7 E* 8 E9 E 10 E 11 E 12 114 vi6 $30 U28 U03 118 008 U18 524 v04 127 R124 R132 R147 R94 F* 1 F2 fa 3 F* 4 F5 F* 6 F7 F8 F9 F 10 f 11 F 12 7 13 R09 vi6 103 U19 U05 125 007 T23 004 U17 108 V27 R14 1M115 R101 4P146 R97 R108 4P150 ss7 Rn9 1N104 G1 G2 G3 G4 G* 5 C 6 G7 G8 G9 G 10 G 11 G 12 G 13 R27 V17 T01 U23 128 U12 H85 U01 T24 U16 (12 v28 R28 1N103 R143 R129 R130 1H110 H. 1 M2 H3 H+ 4 H5 H6 N. 7 M8 Wa 9 U 10 M 11 N 12 M*13 R08 V19 110 U26 UO6 fl6 002 T1! 009 U20 111 v24 R20 1K101 R117 4P149 R87 RID 6 4P151 R95 1H102 l2 l3 14 l5 I6 17 l8 19 l 10 1 11 1 12 122 vil 523 U13 U10 113 U11 U24 521 v12 T21 R84 R136 R140 RB6 J2 J3 J. 4 J' 5 J6 J7 J8 J9 J 10 J 11 J 12 P17 v09 527 $31 U14 U25 U27 518 $29 v10 M68

$$6 R105 4P148 4P145 R99 K. 3 K. 4 K. 5 K6 K7 K8 K9 K 10 K 11

$22 V05 VOT 107 106 109 voi v13 532 R104 till R91 La 4 La 5 L6 L7 L8 $ L*10 H66 T20 v25 v22 v23 126 P23 R102 R125 M. 6 M7 p8 RIO R05 R21 1H105 1Mili 1hl12 e

.. VIC19 Startup Report l Page 4 FIGURE 12 UOL DURNUP DATA PthP UNif 1 $1Att OF CTCLE 19 1 2 3 4 5 6 7 8 9 10 11 12 13 1 04 132 $20 A 38646 42063 41190 tim 1170 1175 TOS U22 Xil V20 x18 V29 102 6 38062 27127 0 14426 0 14196 38351 118A 1199 itil 1208 itil 120C 118A fit x20 x02 v25 U02 V23 XO4 X26 124 C 39011 0 0 1?r:4 27217 12872 0 0 18591 1188 1218 121A 12ve 119A 1200 121A 1210 1188 103 x2r v01 UO3 11T RDS 119 U08 v11 x16 108 0 382T3 0 15255 29232 34126 0 34246 29294 15454 0 38100 118A 1210 120A 119A 118s 121A 1188 119A 120A 1218 litA U19 X10 005 115 v03 U25 via T16 U04 x11 U17 E 264,13 0 29096 38088 13188 27V90 12593 18457 29559 0 2T283 119s 121A 1194 1188 120A 1199 120A 1188 119A 121A 1199

$19 X28 V27 114 vil U28 vi6 U18 V02 121 vi6 116 T12 F 41600 0 13330 34466 13123 2TTB0 153*9 27875 12842 34447 13078 0 18479 1175 1216 1208 118s 120A 1198 1204 1199 120A 118e 1200 1218 118A 517 vif 001 x01 U16 V07 .52 vo8 U23 x12 U12 V28 $22 0 41594 14243 27523 0 28387 14862 29500 15262 28181 0 2T260 14518 41510 1178 1208 119A 121A 1198 120A 209 120A 1198 121A 119A 1208 1175 101 X23 V24 T22 V09 U13 v12 U24 v10 T21 vi9 X24 $29 H 38508 0 13150 34768 12634 27254 15464 27657 12809 34739 13106 0 41240 118A 1218 120s 1188 120A 1198 12CA 1198 120A 1188 1200 1218 1178 U26 x03 006 123 vo5 U15 v13 125 009 x08 U20 1 2T277 0 29136 38210 12258 28408 12510 37929 29155 0 27T20 119s 1214 119A 11Ba 120A 119s 120A 1188 119A 121A 1198 110 x21 v04 U10 120 x09 126 uit vo6 x22 111 J 38115 0 15763 29093 34190 0 34209 29406 15347 0 37858 118A 1218 120A 119A 1188 121A 1188 119A 1204 1218 118A T28 117 x06 vi8 U07 v21 x07 x19 T'3 K 38108 0 0 13106 27264 13140 0 0 38411 1188 1218 121A 1200 1194 1208 121A 1218 1184 TOT U14 x13 V22 125 U27 TD9 L 37952 27354 0 14182 0 27651 37709 118A 119s 1218 1208 1218 119s 118A

$27 528 106 M 40224 41850 37829 1175 1175 118A ASSEMSLY ID #

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. . A15tutLT FUEL REGION

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• VIC19 Startup Report Page5 2.0 SONTROL ROD OPERATIONALJESI!UQ 2.1 HardwartChanaos/ loc}d?Hta All control rods were carriod over from Cycle 18. The ARO poshion is 228 stops as specified in the Sotpoint Document and Proceduto FC 15.

2.2 B010100 Times Soo Figuros 21,2 2 and 2 3 showing a,t the rod drop times ard RCS condblons. M rod drop timos woro well within the Technical Specification Limit of 2.2 seconds to dashpot.

2,3 .GQukDUlQd MOGhADiam. Testing Normal gripper signal tracos were obtained on all rods.

2.4 Ecd.fpik!QaCalibration During hot rod drop testing, LVOT voltages were recorded at 20 stops and 200 steps to verify that the RPI coils woro responding normally. Onco fuli power operating corditions wore obtained, the APIS were aligned using the SPAN adjustment without ctanging the ZERO settings.

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. . VIC19 Startup Repo.1 Page 6 FIGURE 2-1 PBNP UiC19 COLD ROD DROP TIMES i 2 3 4 5 6 7 8 9 10 11 12 13 ,

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B  :.39 1.50 2.04 2.15 CA CD CA C 1.46 i.61 1.sa 2,07 2.20 2.19 ,,

CC CC D 1.A7 1.54 2.08 2.17

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CA $8 &B CA E 1.51 1.51 1.55 1.56 2.*6 2.13 2.17 2.10 _

64 CS CS 5A F- 1,46 1,56 1.52 1.48 2.10 2.18 2.17 2.09 CD CC CD G- 1.45 2,06 1.42 1.46 2.03 2.07 54 CB CB 5A H- 1.50 1.47 1.55 1.49 2.13 2.08 2.21 2.13 CA 50 $8 CA I-- 1.54 1.56 1.52 1.48 2.10 2.27 2.15 2.13 CC CC J 1.52 1.45 2.13 2.08 CA CD CA K 1.50 1.56 1. 6 2.17 2.19 2,'06

$4 $4 L 1.51 1.44 2.09 2.03 M

LEGEE BAN 8:

DATE 05/10/91 x.xx - Time to Dashpot (sec) x.xx - Ilme To Seat (se:) TEMP 193 *F

- Manlun drop time (dash) = C 7 1,61 FLOW 100 %

Minin n drop time (dash) = B 6 1.39 Average time (dash) = 1.50 PRES 359 PBIA

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. , UIC19 Startup Report Page 7 FIGURE 2-2 PBNP UiC19 HOT ROD DROP TIMES i 2 3 4 5 6 7 8 9 10 11 12 13 l l l A -

SA 5A B -

1.28 1.34 1.77 1.86 CA CD CA C -

1.28 1.34 1.36  !

1.78 1.92 1.82 CC CC i

.O 1.30 1.34 l 1.78 1.82 '

CA EB 50 CA E 1.34 1.31 1.32 1.32 1.83 1.82 1.82 1.79

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EA CB Ce 5A I F- 1.30 1.33 1.33 1,85 1,32 .

1.81 1.84 1.81 l CD CC CD G- 1.27 1.34 1.29 1.77 1.84 1.79 l 1A CB 08 54  !

H- 1.34 1.34 1.35 1.29 1.81 1.83 1.86 1.79 CA 5B $8 CA

'1 - i.32 1.34 1.32 1.30

+1.80 1.92 1.85 1.80 CC CC J 1.32-1,82 1.29 1.79 CA CD CA K 1.35 1.36 1.29 i 1.83 1.86 1.78 SA 54 L. 1.32 1.31 1.81 1,77 M

LEGEND DAhlE DATE 05/18/91 x.xx - tine to enshpot (sec) x.ma - Time To 'est (sec) TEMP 530 'F

. Meninsn drop time (dash) e C-9 1.36 FLOW 100 %

Mininst drop time (dash) e C 3 1.27 Average tine (dash) e 1.32 pggg yggg pggg f

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UIC19 Startup Report I Page 8 30 THERMOCOUPLE AND RIILCAUBRATION VERIFICATION During initial RCS heatup for Cycle 19, loop RTD's ard incore %rrnocouples were checked for l nortnal response throughout the heatup range of about 195'F . 530*F (HZP). Tr.ble 31 shows i the results. M 16 RTDs were within the expected 2*F deviation of each other throughout the r heatup. Core exit thermocouples responded norrnally. The same five thermocouples as for i Cycle 18 were OOS (A 7, F 13 H 7,14 and L 10).  ;

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l ' ' UIC10 Startup Report Page 9 11f1L1:1 ti L G Liftall U tLI5 PfD fIe?tti LlLi fantratvrf,3 from*epantt1.tttittanifL(*8)

LOOP A tot 0 L E G R 4018 194.9 249.3 310.0 351.5 404.3 455.0 502.8 528.8 R 4058 194.8 249.3 310.0 351.4 404.1 454.9 503.0 528.7 W 4028 194.8 249.4 310.2 351.7 404.2 455.2 503.3 528.9 W 4068 194.8 249.3 310.1 351.6 404.0 455.0 503.1 528.6 LOOP A

• HOT LEG R 401A 194.7 249.3 310.2 351.6 404.7 455.1 503.1 528.8

. A 405A 194.7 249.4 3 0.2 351.7 404.7 455.2 503.2 526.9 W 402A 194.6 249.2 310.2 351.6 404.4 455.1 503.0 528.6 w 406A 194.7 249.4 310.4 351.9 404.6 455.3 505.2 528.B LOOP B COLD LEG B 4038 194.8 249.3 310.3 351.7 404.7 455.3 503.2 528.7 B 407B 194.8 249.5 310.4 351.9 404.8 455.4 503.3 528.7 Y 4048 194.8 249.5 310.5 352.1 404.7 455.5 503.4 528,7 Y 40SB 104.8 249.5 310.6 352.2 404.7 455.5 503.4 528.7 (COP B a HOT LEG B 403A 194.7 249.5 310.6 352.1 404.6 455.4 503.3 528.7 8 407A 194.8 249.5 310.7 352.2 404.7 455.5 503.5 529.8 Y 404A 194.7 249.5 310.8 352.4 404.5 455.6 503.4 528.7 Y 408A 194.7 249.6 310.8 352.4 404.5 455, 503.5 528.7 RfD AVERAGE 194.8 249.4 310.4 351.9 404.5 455.3 503.2 528.7 S.G. TEMP 219.7 252.7 309.7 352.5 403.6 454.4 503.1 527.8 CORE Ex!T T/C 195.0 252.9 314.9 354.9 406.5 455.4 505.0 529.3

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UIC19 Startup Report Page 10 r- m 4.0 PRESSURIZER TESTS 4.1 Thermal Transients Pressurlier pressure increase rate with spray valves Ird!cated shut ard all heaters on was 12 psl/ min, This is typical and close to the nominal value of 14 psl/ min. During the thermal equilibrium test, Heater Group A was required to be on all of the time to maintain pressure with main spray valves shut. Spray valve effectiveness was normal with the A loop valve decreasing pressure at 128 psl/ min and the B loop at 131 psl/ min.

Spray bypass valve positions were such that spray line temperatures were maintained above 475'F.

4.2 Heater Canaegy Pressurizer heater capacity was determined from direct volt / amp readings on each group of heaters. Table 4-1 shows that heater capacity is above Technical Specification requirements of 100 KW minimum for the heater groups operational during emergency conditions (Groups A, C and D). Heater Group A current readings were greater than

. normal.

TABLE 41 HEATER GROUP POWER SUPPLY READINGS l-Cunent V Volta 0e KW Energy input Heater Group (amps) (volts) KW43xVxt/1000 A 323 480 268 B 230 485 194 C 228 477 188 D 227 480 189 E 225 475 185 TOTAL 1024 S.0 CONTROL SYSTEMS There were no difficulties encountered during heatup or startup of the pressurizer level, pressurlzer pressure and rod control systems.

6.0 TRANSIENTS There were no transient tests performed during startup or approach to full power. There were no violations of the fuel conditioning restrictions on power and rod stepping rates.  !

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e UIC19 Startup Report

. . Pago 11 7.0 INITIAL CRITICALITY AND REACTMTY COMPUTER CHECKS 7.1 Jnhlal Crhicalhv The approach to criticalky was made in two phases. The first stop, which bogan at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> on May 19,1991, was the withdrawal of control rods until Bank D reachod 100 steps. The reactor coolant boron concentration was then decreased by dilution  ;

unti criticality was achieved. The dilution rate averaged about 93 ppm /hr or 33 gpm.

Actual critical boron concentration was 5 ppm greator than estimated concentration of 1445 ppm. ICRR plots were maintained during each phase of the approach to criticalhy. M plots were as expectod with a more pronounced ' knee' In the dilution phase duo to the absenco of the secondary sources.  !

i The reactor conditions at the time of crhicality worn determined to be as follows:

Dato: May 19,1991  :

Time: 1000 P

. RCS Temperature. 530 'F RCS Pressure: 1985 psig Rod Position: Bank D at 173 steps Boron Concentration: 1450 ppm 7.2 HoactMtv Comouter Sotun and Cheel(out t t

7.2.1 .Brtyp Tablo 7 2 shows the reactMty computer setup results. Test 1 is a static test which tests for the reactMty zoro poltu. Test 2 is a dynamic test which inputs an exponentially increasing flux to test for a poshivo reactMty output.

7.2.2 Checkout

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Following criticality, acceptable zero power physics testing flux levels were determined. The flux level at which nuclear heat appeared was about 4

3 10 anips on the Keithley picosmmeter. Normal flux levels for physics testing are about one third the point of adding heat by procedure.

The reactivhy computer's response was also checked using actual are flux.

Cor trol Bank D was pulled from a ethical poshion to obtain distinctly different reactMty levels. For each reactMty level, flux doubling time es 1 measured with a stopwatch. Measured reactivhy was then compared to design reactMty calculated from the measured doubling time. Table 71 ,

shows the results. Differences were within 5 percent which is acceptable.

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, , UIC19 Startup Report Page 12

. TABLE 71 REACTMTY COMPUTER CHECKOUT Moasured Measured Calculated Difference DouUing ReactMty Douding M;D x 100 Time (sec) (pcm) Time (sec) D 72.2 53 71.0 +1% ,

i 56.8 60.5 59 8 -5%

39.1 81 40.2 2%

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TABLE 7 2 Clth 680 1 18 88 sl414C COMP tit StivP ukil CtCLt 0&tt gutWVP 6ttA I L stas 60/Mty 90tAL (ut) 1 19 05 07 8s 0 0.006094 0.97 16.9 DILAffo 020VP 1 2 3 4 5 6 8tfA FRACil0N 0.000199 0.001258 0.001130 0.002415 0.000880 0.000212 LAM 804 0.0128 0.03t5 0.1208 0.3216 1.e042 3.s608 thPut P0f NUMB (R 11 12 21 22 31 32 5ttllkG 1.2354 3.8438 1.3241 3.7692 1.1986 0.1939 Al L(Pt #1 LtLN 31W! f,31C t.h45 i M ,-  : N e_

Al Lt8f 42 fftt'8 ACE P0fst* lit 11 14 23 24 33 34 StillhG 1.2800 3.1100 1.2080 3.2180 1.4042 3.8608 At Ltft #1 M9 J i 11497 f ?M1 7. l t h LVeQJ ?_ i{h Al Ltil #2 __

i.') 41 p. <*

1111 1 tit P01 36 TO 9.000 (v0Lt D. P01 3' $*0Uto 8t 5.9112 At (1f1 #1 h As Ltst s2 ADA Pot 35 untlL AMPLit tle 14 (ano) auf Put 15 0.0 v0 Lit.

AMPLIFist WuMBit 11 12 21 22 31 32 Ak!Lif tte vetts . 8.68635 10.98234 9.86490 10.54147 7.68240 1.85076 AS Ltft 81 9 w90I o 36.1 4 htit m G4$ ) bilf r.D u /

A5 ttf' 82

'filt 2 sit Pot 26 to A80uf 0.7% v Pot 25 StilluG J.20 0.50 0.80 1.10 1.40 . 70 2.00 2.30 2.60 Pitt00 titC) 500.00 200.00 125.00 90.91 11,43 58.82 50.00 43.48 38.46 t 08tG ($tt) 346.57 138.63 86.64 63.01 49.51 40.77 34.66 30.14 26.h 085EAvt0 1 0 #1 34c 4 : Vt s i  % M _ _61M d 4 '< 7 3 0 91 M% 2 0 T 1 L 9>

06titv(010 f? .

EXPtttt0 RM0 (PCM 13.26 30.42 45.17 58.14 69.12 80.20 89.77 98,59 106.77 08sttyto two #1 13 f W VI 2 6Ie 2 M.I (O.I d.4 9Ta b '00*

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1 UtC19 Startup Report l Page 14 80 CONTROL ROD WORTti MEASUREMEMI l

8.1 Test Descilotion i The rod worth verification utillzing rod exchange (* rod swap') was divkfod into two parts. In the first part, the reactivity worth of the reference bank was obtained from reactMty computer measuromonts and boron endpoint data during RCS boron dilution.

In the second part, the critical holght of the referenco bank was moasured after exchange with each romalning bank.

In the rod exchange technique, the reference bank is defined as that bank whith the highest worth of all banks, control or shutdown, when inserted into the core alone. For this cycle the reference bank was Control Bank A (CA) as was the case in all prior rod swap tests.

Using the analog reactMty computer, reactMty measutoments were made during the intortion of Control Bank A from the fully withdrawn to the fully-inserted position. The average current (flux levol) during the meas 9romont was msintained within the physics testing range and temperature was held stead,r near 530"F. Critical boron concentration measuromonts (boron endpoints) were made before and after tho Insertion of Control Bank A (see Section 10.0). Figure 81 shows the results of the differential worih moasurormnts.

Starting at a critical position with the reference bank fully inserted and Control Bank C at 219 stops, a now critical contiguration at constant RCS boron concentration was established with Control Bank C fully inserted and Control Bank A at 05 stops. Control Bank C was then withdrawn and Control Bank A inserted to one step to establish tt e initial conditions for tbs next exchange. This soquence was repeated unta a critical position was estatAlshed for the reference bank with each of the other banks irxfMdually inserted. Criticality determinations before and after each exchange wore made with the roectMty computer.

The sequence of events during the rod exchange and a summary of the rod exchange data is presented in Table 8-1, 8.2 Data Analysis and Test Results The intogral reactMty worth of the measured bank is inferred from the swapped portion of Control Bank A by the following equation:

1 M E WX=Wp - Ao i - (a x)(A0 2) + WX where:

Wj - The inferred wo:th of e.ank X, pcm.

W$ = The measured worth of the reference bank, Control A, from fully withdrawn to fully inserted with no other bank in the core.

0

4

. . UtCto Startup Report Page 15 t

ax- A design correction factor taking into account the fact that the prosence of f another control rod bank is affecting the worth of the reference bank, i Aa, - The measured worth of the refotonce bank from the olevation at which the roactor is just critical with Bank X in the core to the reference bank fully withdrawn ecodition. This worth was moasurod with no other bank in the core.

40, - The measured worth of the reference bank from the fully inserted condition to the elevation at which the reactor was just ethical prior to the worth measuroment of Bank X, in this test Aa, is zero because Bank A was fully t inserted. '

W[ = Tfie worth of Bank X from the initlal position (befors the start of the exchange) to 228 stops. This worth is measurod by the normal ondpoint worth method.

Final values for the integral worth of control and shutdown banks hforred from the measutomont data are tabulated in Table 8-2. Values for a x, obtalnod from the design predictions, are also listed in Table 0 2.

8.3 Evaluation of Test Results A comparison of the measurod/ Inferred bank worths with design predictions is presented in Table 8-2.

in evaluating the test results, the standard revluw and acceptance critoria below were used.

Review Critoria:

8,3.1 The measured worth of the reference bank agrees with design predictions within 210 percent.

8.3.2 The inferred individual worth of each remaining bank agroes with design predictions within 115 percent or i100 pcm, whichever is greater, 8.3.3 The sum of the measured and inferred worths of all control and shutdown banks is less than 1.1 times the prodicted sum. '

t Acceptance Critoria:

The sum of the measured /inferrod worths of all control and shutdown banks is greater than 0.9 times the prodleted sum.

All review and acceptance critoria were mot. Although Control Bank B was outside the

• 15 percent part of critorion 8.3.2, it was within the 100 pcm limit. This is consistent  ;

with recent results from prior cycles.

f

-9

UIC19 Startup Report Page 16 lb.Q.LF Ih1 CRITICAL ROD CONFIGURATION DATA RCS CA Bank Bank Time Tavg Poshion Poshion

(*F) Steps Steps-CC 0310 530 1 219 CC 0336 530 95 1 SB 0401 530 1 220 SB 0413 530 64 1 SA 0436 530 1 217 SA 0451 530 127 i CB 0515 530 1 222 CB 0526 530 60 1 CD 0547 530 1 219 CD 0600 530 89 i Boron concentration was 1296 ppm, O

• i e .-

. i

^

, , UIC19 Startup Report l Page 17 l I

i IABLE 82  !

f

,QOMPARISON OF INFERRED / MEASURED BANK WORTHS  :

WITH DESIGN PREDICTIONS  !

l I

i w, = W[ Wj W[ (I P)/P x 100 j Bank X  ;

a*

pcm j pcm pcm _ pcm  %  :

CC 869 - 0.968 6 944- 994 5.0 '! t SB 1271 1.044 6 457 514 11.1 l SA 603 0.882 5 1252 1238 + 1.1 C8 i

- 1191 1.137 6 431 527 96 pcm i CD 853 1.000 5 853 903 '

5.5 CA 1779 1785- 0.4  ;

TOTAL 5716 5961 4.1 i

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'i+

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.i F

i

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, _ , , , , , , . , .,_,..,_-.,=,m-,m..,_,.,)

UIC19 Startup Report Page 18 FIGURE B-1 PBNP UNIT 1 CYCLE 19 BOL HZP REFERENCE BANK DIFFERENTIAL WORTH 20 ._

~

0 MIA$URED W11Hlh 110% OF DL1tCN 5 X MIASURED OUTSIDE 10% OF Ot51CN 18 9 2 a 17 h [4 16 =*

15 1 x 3 5 0 14 h ,

2 x 13 1 b

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• 0

' I I'I'!'!'I'I'I'!'I'I'I'I'I'I*I L' o 20 40 60 80 100 120 140 160 180 200 220 STEPS WITHDRAWN

?

UIC19 Startup R: port Page 19 0.0 TEMPERATUf1E CQEFFICIENT MEASQBEMENIS A noar all rods out isothermal temperature coefficient measurement was taken during zoto power physics testing. The measured value is the average of the recorded reaWor coolant syr, tem boatups and cooldowns. RoactMty from the reactivity computer and reactor coolant system temperature were recordod on an X Y plottor and two-pen recorder.

Moasured ARO lsothermal temperature coeff 6cient was 1.0 pcm/*F, within the review critoria of i3 pcm/*F of the design isothermal temperature coefficient of + 0.7 pcm/*F for 530*F and 1477 ppm.

10.0 BORON WORTH AND ENDPOINT MEASUREMENTS Figure 101 shows RCS boron concentration during zoro power physics testing. Table 101 shows results of the endpoint measurements. The measured boron worth was obtainod by dividing bank worth (pcm) into change in boron concentration between ondpoints. The review critorion of i 0.5 pcm/ ppm was met.

TABLE 10-1 DORON WORTH AND ENDPOINTS Endpoint Bank Worth Doron Worth Bank Design Hessured Design Measured Design Measured Configuration ppm ppm pcm pcm pcm/ ppm pcm/ ppm ARO 1400 1475 --- - - -

C ^ in 1279 1298 1785 1779 9.9 10.1 At measurement conditions (530*F)

_____m ___m_ - . . _ _ _ . _ _ _ _ _ _ . -

4

,. UIC19 Startup Roport

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' UIC19 Startup Report i Page 21 i i

. 11.0 POWER DISTRIBUTION  !

t TatWe 11 1 litustrates the margin of hot channel factors to their full power limit 6 during initial j power increase to full load. Flux maps were taken using ANSI Standard ANS 19.6.1 1985 as  ;

guidance. Allowed power levels were calculated using the relationships for FH arx1 FO versus  !

power level in Technical Specification 15.3.10.B.1.a.  !

Measured axial power distribution, compared to design, is shown in Figure 11 1 and 112.

f i

TABLE 11 1 f

INITIAL POWER ESCALATION ELUX MAP RESULTS .

L ALLOWED POWER  !

MAP DATE POWER TrilM.- BANK- AO  !

No. -% MISS. STEPS  %  !

FDH FQ i

l 1 05 21 91 28 0 83 84 -100 + 5.3 l 2 05 23 91 75 0 104 114 221 + 7.0 i 3 05 24 91 95 0 106 116 227 + 2.5

)

t 4- 05-24 91 99.8 0 107 116 227 + P.1 7 06-20-91 - 100 0 109 118 220 + 1.5 k

4 wwa-~'" ~

.. UtC19 Startup Report Page 22 FIGURE 111 POINT BEACH UNIT i CYCLE 19 CORE AVERAGE NORMALIZED AXIAL POWER DISTRIBUTION 28% POWER BOL LICEWD: DillCW CURyt - .-.. _ , MEASU8tD CURyt

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CORE HEIGHT (%)

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c. VICIO 6tanup Hepon Page 23 FIGURE 112 POINT BEACH UNIT i CYCLE 19 CORE AVERAGE NORMALIZED AXIAL POWER DISTRIBUTION HFP BOL E0XE ttGtND: OtllCN CURyt ~ * - * ~ MfASUttD CUR 4T 1.2 s'W' 7  % .

1.1

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. UIC19 Startup Report

, s Page 24 '

12.0 XENON >jlACTIVITY Xenon reactMty behavior data for Unit 1 Cycle 19 was supplied by Westinghouse separate from the WATCH data package. Point Beach code Xenon wel be run with a TDF1 d 0.95 and TDF2 of 1.2 to remain consistent with the Xenon Tables. Tables are supplied for BOL. MOL and EOL conditions.

- 13.0 SHUTDOWN MARGIN CONSIDERATIO_NS Rod swap results were within acceptance criteria and were accepted as valid proof d rod worth for shutdown margin determination. See Section 8.0 for rod swap detals. Thus WCAP 12903 Table 6.2 was accepted as a valid shutdown margin determination. Table 131 calculates the excess worth available to Unit 1 Cycle 19.

TABLE 131 EXCESS SBUTDOWN WORTH AVAILASLE FOR A FULL POWER TRIP e BOL (pcm) (pcm)

Shutdown Margin From WCAP 3000 ,

3800 Required Shutdown 1000 2770 Excess Worth 2800 1090 i .

14.0 EXCOf1E DETECTOR BEHAVIOR 14.1 Intermediate Ranae Detectors intermediate range detector currents versus power level are shown in Figure 141.

Intermediate range detector trip setpoints were the same as for Cycle 18. The trip setpoints were reached within the expected reactor power level range of 20 percent -

25 porcent. This shows that the core design changes for Cycle 19 had minimal impact on the intermediate range detector response.

14.2 Power Ranoe Detectors

Table 141 lists the Milt free" power tange detector calibration currents corresponding to -

100 percent power at BOL. These currents were calculated using the multi-map method at 100 percent power. The multi-map method was used as a conservative

- measure to ensure that core design changes that may have affected the power range detectors were accounted for.

Table 14 2 shows the chages in the installed axial offset constants. The changes are probably due more to the aging of the detectors since the last multi-map calibration than to Cycle 19 design changes.

t 9

= ,

amm+ -

a e .

/

U1019 Startup Haport e Page 25 Power range quadrant tM alarms are designed to alert for rapidly developing IMs.

Natural core tMs are eliminated by obtaining calitwation currents for the core with a tM.

A tM is trdicated only when actual currents deviate from the calibration currents even though the core already may have a IM before the start of the deviation. This practice complies with Technical Specifications and the Westinghouse position on core iM.

16BLE 141 POWER RANGE DETECTOR BOL CALIBRATION CURRENTS N41 N42 N43 N44 Cycle 16 T 242- 296 299 016 B 222 295 277 294 Cycle 17 T 239 277 290 293 4:

8 210 268 261 268 Cycle is T 208 - 244 260 265 8 186 236 236 243 Cycle 19 -T 236 267 205 262 8 - 210 264 258 263 TABLE 14 2 AXIAL OFFSET CONSTANTS N 41 N 42 N 43 N 44 Before L55 1.63 - 1.55 1.63

, After ~ 1.44 1,55 1.55 1.54 u

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=/'

• ' UIC19 Startup Report Pago 26 FIGURE 14-1 UiCi9 NI35 AND NI36 RESPONSE TO P0HER LEVEL 7 '

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• e r-e s UtC19 Startup Report Page 27 15.0 OVERPOWER AND OVERTEMPERATURE AT SEIEOINTD 15.1 Overoower and Overtemoerature AT Setooints Shown below are the equations from Technical Specification 15.2.3.1.D.4/5 effecdve during Cycle 19.

Overpower AT 1

, 3 7 6 i 7.,4 1 1 + tsS;

[581

,t t8+1 + / 5 8; 1 4 7

1+t 483 7s m

Overtemperature AT

. 1 l g, . g, ' T I

- T' + K,(F- P')- /( A I) 1 1 + 3t S) , 3 7, ,

,1 + t4 S, , 1 1 + t S, See Tables 151 and 15 2 for the constants associated with this cycle of operation.

15.2 Delta Flux inout to Qyertemoerature AT Sg1DQ101 The overtemperature AT setpoint is reduced when the excore detectors sense a percent power mismatch between the top and bottom of the core. The dead barx1 is 4 5 percent and 17 percent before the setpoints are reduced. For each percent (more than 5 percent) .

the top detector output exceeds the bottom detector, the setpoints are reduced an equivalent of 2 percent of the rated power. For each percent (more than .17 percent) the ~

bottom detector exceeds the top detector, the setpoints are reduced an equivalent of 2 percent of rated power.

a

.-ws ----e,a-,. es- ,~~-e-,.,# *w.%+--es,-4v,,,...r.,,-,+. .ww,,w-r-r# --,_-w-w#-m -v.,.-,c-, er-s,-. .5 -w  %-ws

o

.. UIC19 Startup Report Page 28 IAD1E_151 QYELT.OWER AT CQHSIN{lS AT, = lrdicated AT at rated power, *F T = Average tomrwrature,'F T' s $73 9*F K4 s 1.089 of rated power K

3

= 0.0202 for increasing T

= 0.0 for decroa*,ing T Ke = 0 00123 for T :: T'

= 0.0 for T < T t

s = 10 socords T

3

= 2 seconds for Rosemount or equNalont RTD

= 0 seconds for Sostman or equNalent RTD v4 = 2 seconds for Rosemount or equkalent RTD

= 0 6econds for Sostman or equNalent RTD 4

_. __m _ . _ _ _ _ _ _ _ _ . _ . _ _ . _ . __. _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

i .

1 e s l

l ,,. VIC19 Startup Report Page 29 TABLE 15 2

,QyERTEMPERATURE AT CONSTANTS AT, = Indicated AT at rated power, *F T = Average temperature, 'F T' s 573 9^F P = Pressurizer pressure, psig P' = 2235 psig K, s 1.30 K3 = 0.0200 K = 0.000791 3

v3 - 25 seconds t

2

= 3 seconds r

3 = 2 socorxis for Rosemount or equNalent RTD

- O seconds for Sostman or equNalent RTD t

4 = 2 seconds for Rosemount or equNalent RTD

- O seconds for Sostman or equivalent RTO

_ _ - - _ - - . _ _ - - _ - _ - - _ - - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ - _ . - _ - _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ - - _ _ - - _ _ _ - _ _ _ _ _ _ . . - _ _ - - - - - _ _ _ _ _ _ _ _ _ _ . _ - _ . _ _ . _ _ _ _ _ - . __ _m

• e e

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• , UIC19 Startup Report Page 30 16.0 f1)ELEt!RFORMANCE Figure 161 shows relatkely low coolant actMty just before refuding with still lower activity after refueling. There is no reason to suspect the presence of any leaking fuel at the start of Cycle 19.

17.0 .QQRCLV_SlQN The following results of startup testing should be highlighted.

17.1 The bank swap method for measuring rod worth producrxJ acceptable results. However, measured dWferential worth for the reference bank at higher core elevutions was greater than design which is typical. This results in larger deviations in rod swap worths for banks of srnaller worth.

17.2 Coro design changes locluding natural uranium tdankets and IFDAs did not significantly change the sensitMtles of the excore detectors.

17.3 During initial par escalation, the magnitude of core power distribution hot channel factors were typical, compared to those obtained in prior cycles.

The other Unit 1 Cycle 19 startup arvj refueling actMty results were hormal.

A c

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Unit One Reactor' Coolant Iodine Data

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Date 2R S*3 0 Unit-One Reactor Collant I-131 Activity (uCi/cc) Ma O Unit One Reactor Coolant I-133 Activity (uCi/cc:

---O-- - Unit One Reator ' Coolant Dose Equiv I-131 Activity

. . , . . .. .. ,. -. .. . . ~ . . , -- . . - . - . _ . - - . - . . . - . - . . . . , . . . , _ . - . . .