ML20248B283
| ML20248B283 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/08/1989 |
| From: | James Anderson, Cochrane M POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20248B273 | List: |
| References | |
| NUDOCS 8910030156 | |
| Download: ML20248B283 (163) | |
Text
{{#Wiki_filter:, _ _ _ _ _ - . _ _ _ _ _ _ t o CYCLE 7 START-UP PHYSICS TEST REPORT INDIAN POINT UNIT 3 SEPTEMBER 8. 1989 F ft WD h k h . k rira w Michael H. 't'ochrane 1 J%nJ.@nderson Reactor Engineer I SN e Reuctor Engineer [ h ppR ADOCK0500Lgfo# P
4 j EXECUTIVE SIMMARY/ ABSTRACT During February - June 1989, Indian Point Unit.3 was shutdown for a scheduled refueling / steam generator replacement. outage.- At the conclusion of the' outage a series of preoperational and power ascension tests were performed to verify-that reactor core Kinetics parameters and protection circuits were consistent with the plant safety analyses. A chronological summary of the testing and results are presented below:
. Test Result Core 1,oading Satisfactory RTD and Core Exit Thermocouple Measurements Satisfactory Initial Criticality Satisfactory Control Rod Worth Measurements Satisfactory Critical Boron Endpoint Measurements Satisfactory Isothermal Temperature Coefficient Measurements Satisfactory Reactor Thermal Power' Calculations / Nuclear
~1 instrumentation Celebrations Satisfactory Core Power 0.stribution Measurements Satisfactory Reactor Coolant System Flow Calculation Satisfactory Incore Excore Calibration Satisfactory Calibration of Overtemperature/ Overpower Protection Satisfactory Calibration of "High Taverage" Alarm Satisfactory The unit subsequently achieved full power on July 7, 1989.
This report contains detailed descriptions of the cycle 7 core and each of the tests listed above. I I i l
m', 1 TABLE OF CONTENTS Page No.
' 1.0' INTRODUCTION' 1-1 1.1 Plant Description -
1 1.2 Test Objectives 1-2 1.3 Relevant Design Information' 1-2 1.4. Sequence of Startup Events 1-3 1.5 Summary of Measured and Predicted Core Parameters 1-3 i. 2.0 MEASUREMENT TECHNIQUES 2-1 2.1 General 2-1 2.2 Reactivity Measurements 2-l' 2.2.1 Suberitical Measurements 2-1 2.2.2 Critical Measurements 2-2 2.3 Power Distribution Measurements 2-3 2.4' Instrumentation Calibration Data Collection 2-3 2.5 Thermal Power and Flow Measurements 2-4 3.0 TEST RESULTS 3-1 3.1' Core Loading 3-1. 3.2 Initial Criticality 3-1 3.3 Low Power Physics Tests 3-1 1 3.3.1 Preliminary Measurements 3-1 3.3.2 Boron Endpoints 3-3 3.3.3 Temperature coefficient 3-3 3.3.4 RCC Bank Worths 3-3 I 3.4 At Power Tests 3-3 3.4.1 RCS Flow Determination 3-3 3.4.2 Thermal Power Measurements 3-4 11 _______m___________m____ _ ___m ._
t' - s
- - TA3LE OF CONTENTS.
. Pega No. ,,., - -3.5. Movable Detector Flux Maps 3-4.
t. I 3.5.1 Low Power 3-4 [- 3.5.2 Intermediate Power 3-5 4 .3.5.3 Full Power 3-6 t 4.0 INSTRUMENT MEASUREMENTS / CALIBRATIONS- '4-1; 4.1 Incore Thermocouple, Wide Range and Narrow Range RTD Meas. 4'-1 4.2 Incore - Excore Calibration 4-1 4.3 Calibration of OPDT and OTDT Setpoints 4-2 4.4 Calibration of "High Tave" Alarm 4-2 APPENDIX A Core Loading Sequence A-1 APPENDIX B' Generation of Withdrawal B-1 Limits to Insure a Negative Moderator coefficient 111 _ _ - . . . __.___._.__.____._------m -- - - - - - - - " - - - -
. LIST OF FIGURES FIGURES TITLE PAGE NO. 1.1 Core Layout 1-7 1.2 Control and Shutdown Rod Locations 1-8 1.3 Burnable Absorber Configuration 1-9 3.1 ICRR During Core Loading 3-8 3.2 ICRR vs Bank Position 3-13 3.3 ICRR vs Cal. Dilution Water Added 3-14 3.4 Control Bank D Worth 3-15 3.5 Control Bank C Worth 3-16 l l 3.6 Control Bank B Worth 3-17 3.7 Control Bank A Worth 3-18 B.1 Boron Concentration vs Rod Position to Ensure a B-4 Negative MTC ' iv
~
LIST OF TABLES Table Title Page No. l 1.1 Core Design Parameters 1-4
'1.2 Summary of Measured and Predicted Parameters 1-5 3.1 Reactivity Computer Checkout Results 3-2 4.1 Results of Narrow Range RTD Measurement 4-3 4.2 Incore-Excore Calibration 4-4 B-1 Summary of Withdrawal Limit Calculations B-3 I
v
-m 7 ~1.0 . INTRODUCTION
'1.1 PLANT DESCRIPTION The Indian Point Unit.3 Nuclear Plant is a.four loop closed cycle pressurized light water moderate'd and cooled nuclear reactor operated by the New York Power Authority. The reactor core is designed to produce 3025 megawatts thermal power resulting in a net electrical generating capacity of 965 megawatts of electrical energy.
The Nuclear Steam Supply System was designed by Westinghouse Electric Corporation. The plant is located'on the east side of the Hudson River, approximately 30 miles north of New York City. 1.2 TEST OBJECTIVES This report documents the results of physics tests performed as part of the cycle 7 startup testing program: The objectives of the physics tests were: (1) to verify that the operating characteristics of the core are consistent with design predictions (2) to demonstrate that measured core parameters are consistent with values used in the Safety Analyses (3) to demonstrate that the core can be operated at licensed thermal power safely and within the limits of the Technical Specifications, and (4) to provide data for nuclear instrumentation calibration. l l l l-1 e
. . _ _ _ . - _ - _ _ - _ _ _ _ - _ _ . _ - - A
l
-1.3 REf.EVANT DESIGN INFORMATION
, Table 1.1 presents selected' design parameters of the Indian Point 3 Nuclear Plant. Figure 1.1 shows the core layout v:th control rods mechanical burnable absorbers, sources, and fuel enrichments. Figure 1.2 shows the layout of individual control and shutdown rods. The Cycle 7 core is a mixed core, containing both Westinghouse VANTAGE 5
- i. fuel.(Regions 9-1 and 9-2) and Westinghouse Optimized Fuel Assemblies 1
(OTA) (Regions 7-1,7-2,8-1 and 8-2). The VANTAGE 5 fuel includes four new design features not previously used at Indian Point 3. The new features are as follows: A: Integral Fuel Burnable Absorbers (IFBA) - Some of the new VANTAGE 5 fuel elements contain fuel pellets coated with a thin layer of zirconium diboride (ZrB2 ). This coating serves as a burnable poison for power shaping and Moderator Temperature Coefficient control, and replaces the standard Wet Annular Burnable Absorber (WABA) insert. The number of fuel rods containing IFBA coated pellets varies from assembly to assembly depending upcn the desired poison effect. Since this was a new feature at IP3, only half (approximately) of the burnable poisons in the cycle 7 core are IFBA. The remainder are of the previously used WABA type. Placement of both types of absorbers in the core will allow a comparison of the relative effectiveness of the new IFBA design. Figure 1.3 shows the number and location of IFBA and WABA poisons in the cycle 7 core. B: Axial Blankets and Part Length Burnable Absorbers - All VANTAGE 5 fuel assemblies contain six inch blankets of low enrichment 1-2
.- (natural) uranium at the top and bottom of the pellet stack to reduce core leakage. The burnable absorber in each VANTAGE 5 fuel assembly (IFBA or WABA) has no absorbing material in the. top and bottom twelve inches of the pellet stack. This causes a more gradual decrease in flux in the transition region between E
enriched and non-enriched (blanket) fuel pellets. C: Debris Filter Bottom Nozzle - The bottom nozzle of each VANTAGES-fuel assembly has been redesigned using a greater number of smaller diameter. flow. holes then previously used. This prevents larger pieces of debris from entering the fuel rod region while maintaining the same reactor coolant flowrate. D: Removable Top Nozzle - In order to facilitate possible fuel repair or consolidation, the top nozzle of each VANTAGE 5 fuel assembly is removable. Cutting of the top nozzle is no longer required to access the fuel pins. 1.4 SEQUENCE OF STARTUP EVENTS Following core loading, May 23 - May 27, 1989, a series of pre-operational tests were performed both in the cold shutdown and hot shutdown conditions. Initial cycle 7 criticality was achieved on June 22, 1989 followed by a program of low power physics tests. The unit was synchronized to the grid on June 24, 1989. Power escalation included stopping at approximately 10% power level increments above 50% for purposes of data collection and testing. Steady state full power operation began July 7, 1989. Cycle 7 startup. physics testing was completed on July 11, 1989 with the completion of the full power flux map. 1.5
SUMMARY
OF MEASURED AND PREDICTED CORE PARAMETERS Presented in Table 1.2 is a summary of selected results of zero power physics tests and at-power distribution measurements. 1-3
p : '-
. TABLE 1.1
. CORE DESIGN PARAMETERS
- Number of Fuel Assemblies 193 Region.7 16 Region 7 37 Region 8-1 44
. Region B-2 32-Region 9-1 32 Region 9-2 32 Lattice Configuration 15X15
- Number of fuel-rods per assembly 204 Fuel loading, MTU 88.97 Number of Assemblies Containing RCC Full Length 53 Number of-Absorber Rods per RCC-Assembly 20 Number of Control Rod Assembly Guide -
~ Thimbles per Assembly 20 Number of Instrumentation Thimbles per Assembly 1 Number of Grids 7 Heat Cutput, MWth 3025 Percent-Heat Generated in Fuel 99.5
-Hot Zero Power Coolant Temperature, 'F 547.0 Operating Pressure, psia 2250
Maximum Hot Channel ~ Factors (Design) Heat Flux F T. 2.32
.Nucleer Enthalpy Rise, FaH 1.56 Average' Linear. Power Density, kw/ft Fuel 6.24 Specific Power, kw/kg Uranium 34.00 Enrichments, w/o' Uranium 235 Region 7-1 3.20 Region 7-2 3.40 Regfon 8-1 3.20 s Region 8-2 3.60 Region 9-1 3.42 Region 9-2 3.80 i-
%#k 1-4 er l
l:; F TABLE 1.2
SUMMARY
OF MEASURED AND PREDICTED PARAMETERS FOR CYCLE 7
- 1. Reactivity Measurements 1.1 HZP Critical Boron Conc.-(ppm)
-(Acceptance Criteria: + 50 ppm)
Rod Position (RP) Measured (M) Predicted (P) M-P [ ARO 1487 ppm 1504 ppm -17 D IN 1387 1404 -17 D+C IN 1315 1323 -8 D+C+B.IN 1258 1259 -1 D+B+C+A IN 1120 1121 +1
.1. 2 Isothermal Temperature Coefficient (pem/*F)
(Acceptance Criteria: ' + 3 pcm/*F) Inferred MTC* RP M . P. M-P (pem/*F) ARO -0.94 -1,46 +0.52 + 0.92 D IN -2.27 -2.58 .+0.31 - 0.41 D+C IN -4.38 -4.60 .+0.22 - 2.52 1.3 RCC/RCCA Worth Measurements (pcm) (Acceptance Criteria: + 15% for individual banks, 110% for total) RP M P PCT. DIFF. D 838 pcm 860 pcm -2.6% C(D'IN) 654 691 -5.4 B(D+C IN) 509 558 -8.8 A(D+C+B..IN) 1175 1194 -1.6 Total 3177 3303 -3.8 1.4 Average differential boron worth (Acceptance criteria: 115%) M P PCT. DIFF.
- 8.72 pcm/ ppm -8.63 pcm/ ppm -1.2
- 2. Power Distribution 2.1 Low Power (24%) Technical Specification (TS) Measured **
Limit Value N F 1.9163 1.5586 AH T F 4.6400 2.3780 Q
*- Assumes -1.86 pcm/*F for doppler temperature coefficient 1-5
_. _ _ . . _ _ . _ _ . _ _ . . _ _ ..._______m____._m_ _ _ _ _ . _ _ _
TABLE 1.2 - Continued 2.2 Intermediate Power (50%) Measured ** TS Limit Value N F 1.7940 1.4985 AH T F 4.6400 2.1260 Q 2.3 Hot Full Power (100%) Measure ** TS Limit Value N F 1.5601 1.4389 LH T F 2.3207 1 9075 Q
** Includes Engineering and Nuclear Uncertainty 1-6
_______________M
+
FIGURE 1.1 CORE LAYOUT A B C D E 'F G H J K L M N P R ) 252 8814 742 102 922 722 1M 943 vse 24 vir u24 v37 uns _ 15 l l 1 & 26 331 562 a77 392 e69 432 a61 Mt act 1 & 29 _ _ g4 T61 U14 M7 ul6 v59 T43 W4 UT1 W5 u29 TFD ! _ . i 1925 a65 442 a67 592 att 12P117 a83 54Z mal 412 att 1932 TM f57 v57 u?O up9 T11 vet 734 ute una m3 f66 7 74
~ 13 MZ 462 ma4 12P94 352 12P96 a70 1p105 tot 12P107 aos 302 822 -
_ 12 u13 v53 755 v26 u6e va9 f58 vil una v02 T73 v56 ue2 012 522 au 12Pt21 362 142 192 12P93 aos en 312 12P114 a112 54Z 43Z 1 uit 73Z v48 a63 uM 382 vo 572 T71 112 un a106 T17 129107 v22 ato 705 12P112 u67 a76 f59 262 vio 292 us2 852 v42 a105 U31 692 11 1 WD V75 U22 U52 u59 T37 V27 768 vie 767 u65 U45 U15 U74 v34 10 l 782 422 a99 12P104 n97 12P124 622 1192 932 12P115 37z 12Poe a103 22Z M2 po v49 uts vis 9 fio v11 733 v20 U35 U20 T29 v13 712 v51 u26 a6z a104 12P99 a66 12P122 a93 042 a75 1222 a79 12P120 atop 12P111 a71 06Z .g UO3 T38 V28 739 vo6 751 ute TSO $2 fat v31 T42 v03 T47 uit 812 382 alot 12P113 212 12P118 752 802 122 12P106 a94 12P109 a90 40Z 90Z .y u'2 v61 706 v25 T25 v17 uit u36 u'4 vi9 f26 v23 fit v54 U27 702 a107 952 18z 132 a110 12P100 sitt 12P116 R95 242 66Z 912 an 712 g v35 use u37 u51 u60 763 v21 T49 vo9 T45 U76 ut6 uis U50 v36 C22 652 a46 12P95 342 63Z a113 12P101 512 052 282 12P103 a81 61Z 991 U21 v43 u61 v14 T69 U55 ft9 vos 727 u47 T44 v24 u63 W4 u'1 5 i
. . . _ . _ . I sn 49z a102 12P123 552 12P97 asp 12P110 on 12P10s mes 4M 792 4 !
u06 v55 773 V50 U58 v32 T62 v12 u57 vo5 760 v62 U33 ! 16P31 a62 502 as? 08Z atos 12P119 a74 15r a92 45Z a75 1p27 3 165 f56 v5a u'8 940 703 vor 104 u5s u69 v50 752 T41 ' l 1925 532 Mr aar 23r a73 4ar ateo 602 2 72 1 # 30 2 776 USO v41 u53 v60 7 72 v52 u?3 ve6 uo7 fee j 322 ear T7z 032 762 ss15 092 1 up5 v33 u39 U25 u01 v38 uz3 j -- . . l Insert No.-+xxx l Fuel Assembly No.-+xxx f g ) 270 --+- 90 #0RTM i 1 Fuel Assembly Key: Insert Key: TXX = 3.20% or 3.40% Enriched XXXZ = Plugging Device l UXX = 3.20% or 3.60% Enriched XXPXXX = Burnable Poison (WABA) VXX = 3.42% or 3.80% Enriched RXXX = Control / Shutdown Rod SSXX - Secondary Source 1-7 l 1
. FIGURE 1.2
, CONTROL AND SHUTDOWN ROD LOCATIONS
< - NORTH 90 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 R
P CD SC CD N CC CA SB SB CA CC M SA CE SA L CA SA CA K CD SD CC SD CD J SB SA SB 0 H SC CB CC CD CC CB SC 180 G SB SA SB F CD SD CC SD CD E CA SA CA D SA CB SA C CC CA SB SB CA CC B CD SC CD A 270 LEGEND: CA= CONTROL BANK A SA= SHUTDOWN BANK A CB= CONTROL BANK B SB= SHUTDOWN BANK B CC= CONTROL BANK C SC= SHUTDOWN BANK C CD= CONTROL BANK D SD=CHUTDOWN BANK D l-B i e
[. FIGURE 1.3
, BURNABLE ABSORBER CONFIGURATION I
< - NORTH 4 90 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 6 P.
R P 16W 32I 60I 60I 32I 16W N 16W 60I 12W 60I 16W M 60I 12W 12W 12W 22W 60I L 32I 12W 12W 12W 32I K 12W 12W J 60I 12W 12W 12W 12W 60I O H 12W 12W 12W 12W 180 G 601 12W 12W 32W 12W 60I F 12W 12W E 32I 12W 12W 12W 32I D 60I 12W 12W 12W 12W 60I C 16W 60I 12W 60I 16W B 16W 32I 60I 60I 32I 16W A 270 LEGEND: XXI= NUMBER OF IFBA COATED RODS IN FUEL ASSEMBLY XXW= NUMBER OF WABA INSERT RODLETS IN FUEL ASSEMBLY 1-9
F o L e. 2.0 MEASUREMENT TECHNIQUES 2.1 GENERAL The methods for physics test data acquisition can be grouped into four distinct areas: (1) reactivity measurements, (2) measurements of core power distribution (3) collection of instrumentation data, and (4) thermal power and flow measurements..The purpose of this section is to describe the methods.used in each-of these areas. 2.2 REACTIVITY MEASUREMENTS Measurements of core reactivity were performed both in suberitical and critical core conditions. In the suberitical mode, measurements were made during initial core loading and the approach to criticality. In the critical mode, measurements were pede t0 determice core kinetics parameters. 2.2.1 Suberitical Measurements During core loading, the core reactivity was monitored using the response of the two plant source range channels. Monitoring was accomplished by observing the normalized inverse count rate ratio (ICRR) for each channel as the core was loaded. During the approach to criticality, ICRR plots using data from the two plant source range channels were used to predict expected criticality. ICRR data were plotted ss a function of rod position during rod withdrawal, and as a functien of measured boron concentration during dilution. 2-1 m_-_ __ _ _ _ _ _ - . _ _ _ . _ _ _ _ _ _ i
~4' 2.2.2 Critical Measurements Small core reactivity changes were determined with the aid of a reactivity computer which'provided an on-line solution to the point kinetics equations.
Reactivity records were maintained on a continuous basis during each test via a strip chart recorder which logged the output from the reactivity computer. The input signal to the reactivity computer was provided by the Nuclear Instrumentation System (NIS) power range channels. During zero power measurements, one NIS power range channel was taken out of plant service and used as input to the reactivity computer. Signals from the top and bottom section were summed, and the common signal was input to the reactivity computer. Differential and integral worth of individual rod control cluster assemblies (RCCA) banks were obtained from the reactivity computer response to stepwise movement of the four control banks. During the measurement, the reactor was maintained, on the average, in the critical state. Isothermal temperature coefficient data were obtained by measuring the reactivity computer response to small temperature changes, a few degrees below design no load temperature. 1: 2-2 _._.m._____m___ - ___ _______m_____-___._
+
A n
~
Just critical boron concentration data were obtained from plant chemistry-
' boron analyses of reactor' coolant system samples (kCS) under equilibrium-conditions. . For boron concentration endpoints, corrections to the measured
, , . concentration utilized reactivity computer measurements of the reactivity difference between actual and design core configurations.
2.3 POWER DIf7RIBt'TIONS The Moveable Detector (M/D) Flux Mapping System was used to collect power distribution data. 'The power distribution measurements were performed at three different power plateaus'in order to verify: 1) proper core loading, 2)' design calculations, and'3) margin in hot channel factors. The M/D system was also used at a fourth plateau to provide data for excore calibration. Data from the M/D system was input to the INCORE 3D computer code to generate detailed three
' dimensional core power profiles. The INCORE 3D code combines measured flux distributions with design calculated power flux distribution to yield specific fuel rod powers, local burnup, core power tilts, core average axial' offset, etc.
2.4 INSTRUMENTATION CALIBRATION DATA COLLECTION At each stable power level (statepoint) during the power escalation program (approximately each 10% at and above 50%) measurements were made of RCS loop temperatures (Tavg and A T) Steam Cenerator pressure and NIS power range detector currents. NIS currents were read from the power range current meters.
.y Temperature and pressure data were obtained from the meters on the control board
- and from the plant-computer.
2-3
,. - - _ _ . _ , _ -__N._.-- c. - - , - - - . . _.-_-:-.-_x.a._.~_ _ _ _ ~ - - - - . - - . - _ - - - - - - - - _ . _ - ~ _ -- - - . - _ n..-A------ _ - _ _ - - _ _ _ . _ _ _ _ - - __
t ,
.; Core exit thermocouple and RTD data were obtained during isothermal measurements
. prior to criticality. f Correlations between incore axial power distribution and excore power range detector response were made through simultaneous measurement of core power level, excore detector currents and core power distributions (flux maps). 2.5 THERMAL POWER AND TLOW MEASUREMENTS 2.5.1 Core thermal power was determined by performing a heat balance across each of the steam generators. This measurement required the. accurate determination of steam generator pressure, feedwater inlet temperature, and feedwater flow. For each steam generator, steam pressure was taken from the main steam pressure recorder, feedwater temperature was taken from the resistance temperature detector (RTD) located in the feedwater header and feedwater flow was determined from the Leading Edge Flow Meters. 2.5.2 With the plant operating at approximately 89 percent power, a reactor coolant system flow determination was performed. The purpose of this calculation is to verify that RCS flow is at least as great as the flow assumed in the Final Safety Analysis Report. This procedure is performed prior to power escalation above 90 percent.at the beginning of each cycle. The procedure utilizes an energy balance with a secondary thermal power calculation and precision Thot and Teold measurements. 2-4 e
L 4 l l [ . 3.0 TEST RESULTS 3.1 CORE LOADING Core loading was accomplished.by adding fuel assemblies to the vessel fo11 ewing the prescribed sequence shown in Appendix A. ICRR data obtained from the NIS source range channels are presented in Figure 3.1. There were no unexpected changes in core reactivity during the loading of the fuel assemblies. 3.2 INITIAL CRITICALITY The approach to criticality began on June 21, 1989 at 1540 hours with the incremental withdrawal of shutdown and control banks. Primary System boron concentration during rod withdrawal was approximately 1750 ppm. Inverse count rate ratio data from the two source range channels during rod withdrawal are. shown in Figure 3.2. Criticality was achieved with the addition of reactor makeup water. Inverse cc,unt ratios during boron dilution are shown in Figure 3.3. Throughout the critical approach, count rates from the two so'srce ringe channels were consistent for monitoring of core reactivity. 3.3 LOW POWER PHYSICS TESTS 3.3.1 Preliminary Measurements Immediately following criticality, the upper limit of flux level for zero poser testing was established as about one decade below nuclear heating.
~
Nuclear heating was determined to begin at 3.0 x10 amps on intermediate range channel N-35. 3-1 _ _ _ _ _ _ . . _ _ _ . _ - _ . _ - - - _ . _ - . - . - - - - . _ . .m_.a----------
s - l : ). .Next a check of the reactivity computer performance was made by measuring four values of reactivity and comparing the value with that inferred from the resultant reactor period from parameters given in the core design-report. The results of.this test, given in Table 3.*1. indicate proper operation of the reactivity computer.
- o. TABLE 3.1 l
REACTIVITY COMPUTER CHECKOUT RESULTS Inferred Measured Difference Period Reactivity Reactivity (%) (sec)- (pem) (pem) 49.37 90.89 90.45 -0.48 98.80 54.69 54.67 -0.05 197.66 30.83 30.83 0.00 395.93 16.53 16.56 +0 13. 3-2
.___n __ . _ . . - _ . . - . - . _ _ _ - . _ - - -.-- -
g a
, -3.3.2 Boron Endpoints I
The just critical boron concentration was measured for five 1 rod configurations. _The test results were summarized in 1 Table'1.2 along with design predictions. 3.3.3 Temperature Coefficient Isothermal temperature coefficient measurements were performed at three core conditions as summarized in Table 1.2. The all-rods-out moderator-only temperature coefficient (MTC) was positive, thereby requiring calculation of rod withdrawal limits to insure a negative MTC as required by Technical Specifications. This calculation is presented in Appendix B. 3.3.4 RCC' Bank Worths
. Bank worth measurements were performed over the four individual control banks (in non-overlap mode). Measured and predicted integral worths of these four banks are sumarized in Table 1.2. Also, the differential and integral worth of each bank is shown as a function of bank position in Figures 3.4, 3.5, 3.6 and 3.7.
3.4 AT POWER TESTS 3.4.1 RCS Flow Determination On July 1, 1989 RCS flow was measured to be 389,064 gallons per minute. The flow assumed in the FSAR at the beginning of DNBR analyses is 332,240 gallons per minute. The actual measurement indicated that a margin of approximately 17.1 percent exists in RCS Flow. . 3-3
3.4.2' Reactor Thermal Power Measurements In order to provide protection against possible non-conservatism in initial nuclear instrumentation readings, the high flux reactor trip setpoint was reduced from the normal 108% value to approximately 65% prior to initial criticality. During startup, initial reactor thermal power measurements were made at approximately 20% power and the nuclear instrumentation was adjusted recordingly. The measurements were repeated at just below 50% power and the nuclear instrumentation was verified to be properly adjusted. The on shift Reactor Engineer independently reviewed both the 20% and 50% measurements prior to increasing reactor power. After -ae 50% measurement was performed, the high fluy trip setpoint was returned to its normal value, and thermal power measurements were performed once each day. 3.5 MOVEABLE DETECTOR FLUXMAPS 3.5.1 Low Power The initial flurmap of cycle 7 was taken at approximately 24 percent power without equilibrium Xenon. The purpose of this map was to verify proper core loading. The greatest deviation between predicted and measured average reaction rate integrals was 22.4 percent. (Each of the eight peripheral frel assemblies bordering the diagonal core axes exhibite; higher than expected deviations from design power. It is felt that the modeling of these assemblies was less accurate due to the placement of fresh burnable absorber assemblies in these twice burned fuel elements. Since the 8 3-4 l
i. ( t assemblies are operating at very low power, the 20 percent f deviation does not pose a hot channel' factor concern. The.. noted deviation has decreased with subsequent full power - core operation.) Based on a review of this map the core was
-determined to be properly loaded. A summary of parameters is presented below:
Date:- June 24, 1989 Map number: 7FCFM1 Power: 23.9%
. Rod Position: D/152 Steps (226 Steps = fully withdrawn)
Greatest Tilt: 1.58% Greatest FDH: 1.5586 Greatest FQ: 2.3780 Highest Deviation between measured & predicted integrals: 22.4% Core average axial offset: +0.638% 3.5.2 Intermediate Power The second fluxmap of cycle 7 was taken at approximately 50 percent power with equilibrium Xenon established. The purpose of this map 'was to verify that core power distribution and peaking factor predictions were consistent with measured values. The greatest deviation between predicted and measured average reaction rate integrals was 3-5
+19.2 percent. Based on a review of this map'it was l concluded that core power distribution and peaking' factor predictions were acceptable.. A summary of parameters is presented below:
Date: June 27, 1989 Map Number: 7FCFM2 Power: 49.8% Rod Position: D/183 steps Greatest. Tilt: 1.10% Greatest FDH: 1.4985 Greatest FQ: 2.1260 Highest Deviation between measured and predicted integrals: 19.2% (See Section 3.5.1)
. Core average axial offset: +5.014%
3.5.3 Full Power The initial full power flurmap of cycle 7 was taken on July 11, 1989. The purpose of this map was to verify that measured full power hot channel factors (FQ, FDH) were within Technical Specification limits. Based on a review of this map all power distribution parameters were within applicable limits. A summary of parameters is presented below. Date: July 11, 1989 Map Number: 7FCFM4 Power: 99.9% Rod Position: D/222 steps Greatest Tilt: 0.97% 3-6
k Full Fower - Continued Createst FDH: 1.4389 Most Limiting FQ: 1.9075 Highest Deviation between measured and predicted integrals: 21.7% (See Section 3.5.1) Core average axial offset: +3.598: 3-7
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ICRR DURING CORE LOADING A.J
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? p.
.- '4.0 INSTRUMENT MEASUREMENTS / CALIBRATIONS 4.1 Incore Thermocouple, Wide Range RTD and Narrow Range RTD Measurement-The primary purpose of this test was to verify that the narrow range RTD's were functioning properly. ~ This was accomplished by making comparative measurements of narrow range RTD'i at f
-five different temperatures (337, 406, 451, 501 and 546 'F) while the reactor coolant system was held in an approximately isothermal condition. Only narrow range RTD's that deviated from the mean by less than 0.5*F are used for reactor protection and control. The results of these measurements are.
' listed on Table 4.1.
Additionally, this test collected wide range RTD readings and core exit thermocouple readings at the same temperature plateaus.
-4.2 Incore - Excore Detector Calibration One full-core map and 5 quarter core maps were taken at approximately 89% powse to obtain calibation data for the excore instrumentation. These maps covered a range in axial offset from -11.3% to +4.4 % generated by insertion of control bank D. INCORE3D analyses provided a measured value of the core average axial offset which was used as the basis of the excore calibration. The results of the calibration are listed in Table 4.2.
4-1 1 _ _ _ . _ _ _ _ - . . _ _ _ _ . _ . . _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ __ __m-_
s l 1 I 4.3 Calibration of OPDT and OTDT Setpoints l i l Steam generator Tave and delta-T was measured at approximate power levels of 30, 50, 60, 70, 80 and 90%. Prior to exceeding nimety percent power, an extrapolation of full power values was ; calculated. The extrapolated full power values were used to recalibrates the overpower and overtemperature reactor j i protection setpoints. l l Extrapolated Full Power Temperatures Delta T (*F) Tavg (*F) Loop 31 54.9 565.5 Loop 32 54.1 565.8 Loop 33 53.2 566.1 Loop 34 54.0 565.3 4.4 Calibration of "High Tave" Alarm In order to ensure that Teold does not exceed 547.9'F, as specified in the cycle 7 safety analyses, the "High Tavg" alarm setpoint was verified to be set conservatively. This was based on calculations from the extrapolated full power core delta T listed in section 4.3. t-2 l \ --------_----_A
Table 4.1 RESULTS OF NARROW RANGE RTD MEASUREMENT DEVIATIONS FROM MEAN RCS TEMPERATURE (*F) Avg. T RCS ( F) 336.8* 405.7 450.7 500.7 546.4 RTD # 411A1 0.81 0.03 0.06 0.05 0.02 411A2 0.66 0.05 0.06 0.05 0.02 411A3 0.11 0.03 0.00 0.01 0.05 410B 0.37 0.09 0.16 0.08 0.01 411B 0.33 0.03 0.10 0.02 0.06 421A1 0.27 0.01 0.03 0.04 0.01 421A2 0.38 0.05 0.02 0.05 0.02 421A3 0.05 0.02 0.01 0.00 0.07 420B 0.43 0.02 0.05 0.06 0.01 421B 0.41 0.00 0.07 0.09 0.01 431A1 0.13 0.14 0.10 0.13 0.13 431A2 0.33 0.06 0.01 0.06 0.10 431A3 0.14 0.03 0.02 0.01 0.01 430B 0.41 0.15 0.07 0.13 0.14 431B 0.41 0.14 0.05 0.13 0.14 441A1 1.47 0.08 0.11 0.12 0.04 441A2 0.99 0.03 0.07 0.04 0.00 441A3 0.33 0.14 0.20 0.21 0.14 440B 0.36 0.17 0.19 0.25 0.13 441B 0.36 0.17 0.20 0.26 0.13
- Only 2 out of 4 reactor coolant pumps were operating at this temperature.
4-3
TABLE 4.2 - -RA12 (1 of 2) h 1; CY-7 INCORE-EXCORE CALIBRATION (7-1-89) CALIBRATION CURVES: DETECTOR EQUATION 41-T 112.4 .78 (AO) 41-B 122.7 .78 (AO) 42-T 155.8 .97 (AO) 42-B 148.6 .97 (AO) 43-T 146.1 1.03 (AO) 43-B 154.3 -1.03 (AO) 44-T 130.1 .90 (AO) 44-B 148.1 .90 (AO) I SUMMATION OF EXCORE DETECTOR DATA AND CALCULATIONS: INCORE POWER TOTAL MAP AXIAL POWER AVERAGE NORM. NORM. COMP. PERCENT ID OFFSET LEVEL DETECTOR CURRENT CURRENT CURRENT CURRENT DIFF. QC05 -11.303 .894 41-T 92.0 102.9 103.2 103.5 .32 41-B 117.7 131.6 131.9 131.6 .25 42-T 129.0 144.3 144.7 144.9 .09 42-B 142.3 159.2 159.7 159.6 .08 43-T 120.0 134.2 134.5 134.5 .02 43-B 148.0 165.5 165.9 165.9 .01 44-T 107.3 120.1 119.8 119.9 .15 44-B 142.0 158.8 358.4 158.3 .11 QC04 -8.674 .895 41-T 95.0 106.1 105.5 105.6 .04 41-B 116.7 130.4 129.6 129.5 .03 42-T 132.0 147.5 147.2 147.4 .14 42-B 141.0 157.5 157.2 157.0 .13 43-T 122.7 137.1 136.6 137.2 .39 43-B 147.0 164.2 163.8 163.2 .33 44-T 110.0 122.9 122.4 122.3 .08 44-B 140.0 156.4 155.8 155.9 .06 QCO3 -6.097 .892 41-T 96.3 108.0 108.0 107.6 .41 41-B 113.3 127.1 127.1 127.5 .34 42-T 133.7 149.9 150.0 149.9 .05 42-B 137.7 154.3 154.5 154.5 .05 43-T 124.7 139.8 140.1 139.8 .18 43-B 142.7 159.9 160.3 160.6 .16 44-T 110.7 124.1 124.5 124.6 .13 44-B 136.7 153.2 153.7 153.6 .10 QCO2 -4.175 .901 41-T 98.0 108.8 109.2 109.1 I
.09 41-B 113.0 125.4 125.9 126.0 .08 42-T 137.0 152.1 152.2 151.7 .31 42-B 137.0 152.1 152.2 152.7 .31 43-T 128.0 142.1 142.1 141.8 .18 43-B 142.7 158.3 158.3 158.6 .16 44-T 114.3 126.9 126.6 126.4 .15 44-B 137.0 152.1 151.6 151.8 .12 4-4
, _ _ _ _ __ _ . _ _ _ _ _ - - - - - - - - - - - - - - - - ' " - - - - - - - - - - - - ^ - - - - ^ - - - - - - ~ - ' - - ' ' - ~ ~ ~ '
3 [.: !
, , , TABLE 4.2 I (2 of 2)
.QC01 .392' . 891 41-T 100.0 112.2 112.1 112.1 .06 41-B 109.7 123.1 123.0 123.0 .06 42-T' 139.0 156.0 155.4 155.4 .01 1 42-B' 133.3 149.6 149.0 149.0 .01 l 43-T 130.3 146.3 146.1 145.7 .27 l
43-B. 137.7 154.5 154.3 154.7 .26 44-T 116.0 130.2 130.1 129.8 .27 44-B 132.0 148.1 148.1 148.4 .23 FCO3- 4.370 .923 41-T 106.6 115.5 115.6 115.8 .20 41-B 110.2 119.4 119.5 119.3 .20 I 42-T 147.3 159.6 159.8 160.0 .12 . 42-B 133.3 144.5 144.6 144.4 .13 . 43-T 138.7 150.2 150.2 150.6 .26 43-B 138.7 150.2 150.2 149.8 .26 44-T' 122.7 132.9 133.8 134.1 .22 44-B 132.4 143.5 144.4 144.1 .20 STOP.
*RDY*
4-5
.__._-___.m._______ . - . _ . - _ - _ _ _ _ _ . _ . _ _ _ _ _ _ _ _
APPENDIX A Core Loading Sequence for Indian Peint 3 Cycle 6/7 Outage The following pages are taken from IP3 Refueling Procedure 50P-RP-1, pages 210 through 318 A-1 _._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______m.____ _____ _ _ _ _ __ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ -
~
W NSD PHASE I FP-INT-R6 REV.0 A B C D E F G H J K L M N P R 282 5514 032 2':3 802 622 342 744 T10 U25 530 U36 T12 T6,
- 15 15 202 4P122 R94 12P692 R108 12P522 R86 4P112 512 16 842 719 u65 T46 U52 T72 u5' T76 U59 T27 R22
~
~ 14 182 R100 12P632 R80 12P412 R82 12P662 titt 12P392 R62 12P302 a66 07
$37 752 u64 713 U73 560 U44 869 U53 T28 u62 T56 561
- 13 372 12P422 R91 12P312 243 12P602 t?9 12P492 1 73 R87 12P752 12P622 252 T29 U70 T55 ue3 s54 U29 541 U14 e58 908 T73 u68 T33
~ 12 292 4P132 E95 12P8t2 211 12P772 262 152 a64 12P792 168 12P862 R73 4P102 322 T45 USS T35 U12 563 U34 T36 T49 T23 U24 848 U31 T24 U47 763 11 632 a102 12P542 153 12P832 R68 12P502 a63 12PS12 a89 12P472 192 12P332 R76 582 T11 T41 U50 873 UQ4 568 uo9 $70 U10 542 U26 540 U46 765 T34 10 062 12P562 R75 12P582 R90 12P742 242 552 1 72 12P372 142 12P842 a93 12P292 862 uit U69 544 uo6 T20 U22 730 T62 715 g
.U15 707 U33 574 U54 UC3 12P882 a65 12P652 R96 5 72 R71 082 a106 072 T40 T47 U20 843 RS3 352 a99 12P732 alto 12P362 8
T48 $53 742 750 T39 8 72 751 350 U19 738 T54 - 1222 12P762 R72 12P712 182 12P852 122 052 162 12P552 a113 12P532 a67 12P322 042 U32 U58 865 U13 T16 U37 702 T58 708 U18 T32 WO2 U57 7-5 71 U16 012 2112 12P352 156 12P572 2109 12PS22 R74 12P722 a78 169 12P442 12P402 t'88 022 T03 T74 U74 $38 U42 $51 u40 576 U38 862 U27 575 U75 764 704 6
. .. .. . .. .. . .. .~ . - __ -.-.
332 4P142 R103 12P342 184 12P702 tTT 092 112 12P612 13 12P682 298 4P162 2 72 T67 U72 T31 U21 $39 U39 T22 T68 70f U01 s67 U41 714 u67 T37 5 592 12P672 A97 12P872 222 12P432 2105 12P912 152 127892 2 70 12P382 212 1 726 U48 7 75 U05 549 Uc7 564 U30 547 U23 T60 v49 4 T25
)
245 284 12P802 A69 12P782 R85 12P452 R107 12P592 a61 12P482 Riot 141 546 766 U61 709 U71 559 U28 $55 U56 721 u63 T57 3 545 14 192 4P152 R92 12P902 R$1 12P462 R106 6P92 132 179 R11 T17 U76 T70 U51 T43 u66 761 u60 TOS E55 2 312 532 102 251 1192 5815 362 759 706 U17 508 U35 T18 T71 1
. ... s' . .. ..
0 ! l 0 o / \ 270 --+-- 90 eORTH I O 180 INITIAL CONDITIONS CYCLE VI-VII , PPtcTav' "' cat J8nuary, 26 1989 ,Act 210 " tesp seta Obte es98H' k
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PHASE I rp.!NT-R6 REV.0 G F' E D C B A 1 2 3 4 5 6 7 8 9
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SPENT FUEL PIT INITIAL CONDIT55NS SHEET 10F 6 I l-1 .* E8FECtivt D Afvr$ED cart January, 26 1989 ,,og LIi\ catt suGD 10$a 0? M esWeef a
T NSD PHASE I
. FP. INT.R6 REV.0' JJ HH GG FF EE DD CC 175 133 139 6pTl 20 165 355 009 642 637 338 335 1g 143 12P11x 1p47 1942 12943x 12P53x 3D41x tee C10 C2B 863 625 gg 862
.~. . . - . . . ..- . 834 .-
156 12P7x 1941 20P11 A9P4 42PB9x 12P36x 950 C39 351 C07 446 827 810 12 177 12P6K 1p50 17 A991 12P25x 12P9x 624 Sc2 tra 832 852 644 323 13 144 12P18x 42P94x C13 513 12932X 1946 12P44x 12P3x g "- 819 843 807 C27
- 829 247 20P23 1963 20P29 20P16 12P24x 12P37x 804 CSS 847 857 817 840 811 15 148 20P1 1p61 20P3 1p52 146 154 849 054 831 818 820 856 830 16 150 42P59x 20P17 1p59 12P46x 213 136 803 806 801 C29 608 805 g7 060 19 12P23x 1949 20P6 1
19 60 P0/IPs 147 339 836 826 321 853 C31. gg
- 312 12P1x 12P10x 1p53 178 452 A34 A39 R58 1 76 861 171 C03 108 Col I)g 20P24 1p55 1p48 tap 2 ASP 2 Ap4 baP3 406 430 A21 A32 A20 A13 A53 20 As23 89P6 12P15x 20P22 APS2 RS24 as27 A51 A37 A60 A55 A54 A45 A64 21
~
12P2x 12P13x RS25 12P14x 2 ops as28 RS22 A27 A61 A63 A31 A02 A43 A38 22
~. -. --
ASP 3 20P20 20P30 tope 20P9 20P18 20P19 A03 A16 A46 A33 A44 A49 A50 23 80P1 20P28 1962 20P26 teP4 SPs2 20P5 A28 A08 A17 A36 A04 A07 A15 24 20P25 1p54 : 1945 ASP 1 20P2 1p43 A47 A01 A29 A14 A41 g$ A23 8992 20P7 89P3 A9P2 12P16x 1957 A57 A12 A18 A05 A09 gg A11 ts21 20P13 89P1 s*P5 1p58 A9P5 A44 458 A42 A22 A40 A10 2 */ SPENT FUEL PIT INITIAL CONDITIONS SHEET 2 OF 6 t 58FECTivt can January, 26 1989 ,4cr { ({ AEVSED M
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20dL5 20E 3549 ?td962 149OX ?tditX L9dt42 LW2GZ L9415Z L2diZ V95 492 306 QZ 369 atS e90 849 40C S20 II _ . _I%A _ . .. 204Z4 35d2 6489X 200 ?td44X tt449X tdeZ LMZLZ 69dt91 v92 429 3ts cO 309 sat dsO urt 49E aiz sZr IS e6N 3sd9 ttes9X ta 4X tads 4X irdsLX lazOZ stdu V25 492 99 392 3ZG 328 41$ atS 356 s 39
. _ _ . . . _ .. 39..I ...... ...L6 ....
L2dtX Ltd$ZX 62dtWX ?49LX 12de0X tdZZZ vle dit 396 379 35L 895 406 a54 sol IE 5d3NI J037 dII INIIIY7 3ONOIIIONS SH331 C 04 9 t 38d301'^3 cvA1 reuno h' 29 L686 *'03 g w3A;51C avAa
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ss11 sia au 10 sesis aos 11
. .~ . . -. _
1962 sir . au 12 1etrz m31 13 12prz '2'6E 527 R23 34 as 15 su 16 as 17 1p132 ser 18 au 19 sie 20 atr 21 12ptsz sti 22 og , 23 s3a 24
,,, 25 taper ses . 26-cetta comuts 27 SPENT FUEL PIT INITIAL CONDITIONS SHEET 4 OF 6 3 L
EFFECTivt #EVIIED i~ oars January. 26 1989 , og O(_1'3 lt DATE is,.ev.s .. .
9 - p-
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PHASE I FP-INT-R6 REv.0 p BB AA Z Y X W V U T S'R Q P 12P102 A26 535 2B e61 s09 2I 12P12 so' 30
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NSD PHASE I FP-INT-R6 REY.0 l l' l l l N. M L K J H G F E D C B A 12P242 4712 506 753 28 SPLips Dreats 29 os 224 203 1sp 307 531 a53 a32 802 30 151 240 - 159 134 tse a21 Sie $24 Rie 31 149 135 137 195 244 l R71 3g . Rea a13 B01 433 e48 t . . ._. 161 140 215 145 RoS R24 oc6 RS4 0FA 33 xxxxxx xxxxxx winnnnt vuurvu xicocot xxxxxx xxxxxx 3 innnnrv xxxxxx winnnnr xxxxxx rinnnnt arrrrx xxxxxx *4 innnnnr innnnne innnnrr loooots loooocc iconotz xxxxxx inoontu locoopt looontz xicantu minnnne xxxxxx xxxxxx 35 SPENT FUEL PIT INITIAL CONDITIONS SHEET 6 OF 6 i mEvtSED
'o'a'[g ' January, 26 1989 ,,og b "
se6D tete 09 80 ov8tM'
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! ! El l I I I I I I I I I I I I I I 5 af I I I I I I I I I I I I I I I I n!= 1 1-1 I-1 I-l l-1 I-1 I-1 I1 I EfIt! Isl lei lel Isl lei lsl lel
- =Ef l l _! l l l l ! l l l l l l l l
! ggia i I'l I I I I I I I I I I I I I i eg j ~ l l I I I I i i I I I I I I I l i s'!- 1 I I I I I I I I I l l l l t I i Ei l I I i l I I I. I I I I I I I s af I I 1 I I I I I I I I I l- 1 I l l n!= l - 1 I-1 I-1 I-1 I-1 I-l l-1 I-l EE l l I l l l l l l l l l E l l l l l g Er l I I I I I I I I I I I I I I I skE l l2l l3l lCl l3l lWl l4l l3l l tt
, c = = g g
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5 3 3 0 3 3 5 0 5 EFFECTIVE e. REVISED DATE JanU8ry.26 eb'9 PAGE 4 # e8801914 ObH wkS2M'
~
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- ia l i I I I I I I I l l I I I I a !!~ l I I I I I I I I I I I I I l
= N'!- 1 I I I I I I I I I l l l l l E i5 El I i l l I I I I I I I I I I e! I I I I I I I i I i l I I I I s8 eI-1 I-1 I-1 I-l l-1 I-1 l-1 I-Ef l lil lel Isl l!I lEl lil IBl
; =EE l l l l l l I l l l l l l l l I i l I I I I I I l l ! l I I I I I i
gg m-j~" l l I I I I I I I I I I I I I I
! N'i- 1 I I I I i 1 I I i i l l I t I i EI I I I I I l I ! ! I I I I I I g af I I I I I I I I I I I I i i i I i se l l-l l-j l-l ;.[ i.l ll ;.l l 5 Ei l l I l l l l l l I l l l l l l g
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! j El l I I I I I I I I I I I I I I af I I I I I I I I I I I I I I i i s!e l I-1 I-1 I-1 I-1 I-1 I-1 I-1 I BilEl Iil 15l 151 lSl 15l lil 15l
- =EE l I l l l l l l l l l l l l l 'l I-I I i I I I I I I I l- 1 I I I I i f-:r!ai~ l i I I I I I I I I I I I I I I
! s I- 1 I I I i i i i i i i l I I t I i iI I i l l I I I I I I I i l I l
;* af I I I I I I I I I I I I l- I I I t!eI-I l-1 I1 I-1 I-1 I-1 I-1 I-1 l 5 EE I l l l l l l l l l I I l l l l i
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su l l l l ! I I I I I I I I I I I
.He l Isl l$1 lel Isl 15l 151 151 l U
I
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- REVISED DAYE January.26 1989 ,,3, 4 DATE NED 1014 09 80 es?O2949 e
. & Ns0 PHASE I FP-INT-R6 REV,0 w %3 (6 (.h ot (goQdst k P Nt ot C9 ot t b
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ggl"-I I I I I I l l l l l l l l l 5 emi~ l l I I I I I I I l l l l l l r s'i- i l I I I I I I I I I I I I I El E I ee l i I I I I I I I i i l I I I I I I I I I I I I I l l l l s!s I I .-l l-1 I-1 I-l l1 I-l l-BE l IEl 15l 15l lEl lEl l2l lEl
; =Ir l l I I I I I I I I I i l l l I gg!" l I I I I I I I I I I I I I I i -E i ~ l l I I I I I l' I I I I I l l l
- s' - 1 I I I I I I I I I I I I I t i il l I I I I i i l l I I I I I l 5 af I I I I I I I I I i l 1 i i i l i s!s i I-1 I1 I-l l-1 I-l i-l l-1 I l E EE l I I l I l l I l l l l l l l l EE l l I I I I I I I I I I I I I I
=lfl=l Isl lol lil 1:1 II Isl Igl 6
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.)
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8
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! ! El i I I I I I I I l l l 1 I I I
- ef I I I I I I I I I I I I I I I I n!= 1 1-1 I-1 I-1 I-l l-l l-l l-1 I Bf121 lEl lBI 19l IEl IEl lEl 15l
, =lf l l I I I I I I I I I I I I I I
! gia l i l l I I I I I I I I I I I I i g!!! ~ l o i I I I I I I I I I I I I I I
- N'!- 1 I I I I I I I I I I I I I i l i EI I I I I I I I I I I I I I I l g e! I I I I I I I I I I I I l- 1 I I i t!eI-I I-1 I-1 I-1 I-I l-I i-1 I-l l I Bf l l l l l l l l l l l l l l l l se l I I I I I I I I I I I I I I I
=Ir l Isl Igl Isl lel lel lel Isl l I
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@ b b b
- i y , g I
m 2 E E E E E I., is S s s s s ! ! ! ! $ $ 3 i s s N e r $0I@ECICli c zah h.h isi3NSIQ 9IC jg 2= +tu ar a.z:ba ta ::A :ta laa AbA sa gg $ S $ R E c E R E C E 2 E C E
$[Tg January.26 1989 pact '
es&D 1944 07-80 ev02Hf ____.__________m________ -"
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* !a l i I I I I I I I I I I I I I I 8 !!!~ l i I I I I I I I I l l l l l l
- a fi- 1 I I I I I I I I I I I I I I I
! j- El i I I I I I I I I I I I I I I af I I I I I I I I I I I I I I I I s!= l - 1 I-I i-1 I-1 I-1 I-1 I-1 I-I af l IEl IEl lEl lil 15l lil IEl l
; =EE I I l l l l l l l l l l l l l l
! !=I I I I I I I I I I I I I I I I l !!!~ l I i l i I I I I I I I I I I I i V'!- 1 I I I I I i l I I I I I I t I i EI I I I I I I I I I I I I I I-I
; mg I I I I I I I I I I I I l- 1 I l 5 s!= 1 1-I i-1 I-1 I-1 I-1 I-I i-1 I l 5 af I l l l l l l l l l l l l l l l
; su l l l l 1 I I I I I I I I I I I IEl
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! j El i I I I I I I I I I I I I i af I I I I I I I I I I I I I I I s8: I I-1 I-1 I-l l-1 I -.I i-l l-l EflEl Isl lil lEl lEl lEl lEl lE
- sim i l I I I I I I I I I I I I 1
! !" l I I I I I I 1. I I I I I I I l oggg!~ l I I I I I I I I I I I I I I i N' i-- I I I I I I I I I I I I I i 1 i il i I I I I I I I I I I I I I
- ma l I i l I I I I I I I I I I i t 8: I-I l-1 I-1 I-l l-l l-l l-1 I-l l Ef I l i I l l l l l l 1 l l l l g
Ef l I I I I I I I I I I I I I I I sim i lEl lel l=l lel Isl lel lal l I a s s 8 E & & G .
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m a E E 3 3 5 5 H H E 5 5 is 6 s s B B 8 ! E E E 2 2 B B B 5[ % te t. ., t, tg t e N t % n. -%
!e i* W
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- Q DATE o 3.u o,.m .umea
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!!!~ l l I I I I I I I I I I I I I m W i- 1 I I I I I I l l l l l l l l
! j El l I I I I I I I I I I I I l 5 af I I I I I I I I I I I I I I I s!= 1 - 1 I-1 I-1 I-l l-1 I-1 I-1 I- {'
Ef I l E l- l 0 l li l IEI I!l IEl IEl
; ula l l I I I I I I I I I I lI I I i" l I I I I I I I I I I I I I I i gg!~ l og i I I I I I I I I I I I I I i U'i- 1 I I I I I I I I I I I I I t I i il I I I I I I I I I I I I I I l 3
af I I I I I I I I I I I I I I I I s!= 1 1-1 I-1 I-1 I-1 I-1 I-1 I-1 I l I Ef I l l l l l l I I I I I I l l l g su l i I I I I I I I I I I I I I l nifl:1 Is! l.I l=l Isl I.I Isl I s_I I
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~ hNSD PHASE I pp,11T-R6 REY.0 E-! t -a Y$, N Mh TE M$ 42 Y N,tD bs M$ /dY bY3Fp e , e - o s m s ms 8- != I I I I l l I I I I I I I I I I
!!!~ l l I I I I I I I I I I I I I I a V !- I I I I I I l i I I I I I I I I
[ j eg i El i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I s!= 1 1-I i-1 I-1 I-1 I-1 I-1 I-1 I > Enlil lil lEl IBl IEl lEl lEl I Bl
; =He l I I I I I l l l l l I I I Il
? i- I I i l I I I I I I I I I I I I l k!!~ l l I I I I I I I I I I I I I I i W'!- 1 I I I I I I I I I I I I I t I i EI I I I I I I I I I I I I I I I
; ef I I I I I I I I I I I I l- 1 I l
; 68 I-I I-I I1 I-I I-1 I-1 I-1 I-l l 1 Er l l l l l I l l l l l l l ~l I l g se l l I I I I I I I l l I I I I I rif l
~
Isl lcl Isl Isl 151 l51 Isl I tl
~
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- e a s a g a a a a 5
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!S ! =r D' $ F :! F t ; J ? ?.4 :a c i f1 ?% c ::
1 ;: 4% $ !*%% $ +C 3; 6- !4 d. a$ m *I e:J* ;d d. )4 s9 [ej4 95 ACM D A D L t 'a O 4 o 4 'a O . C a 4 eg % ko n N ga g g g s i s ! = 5 s ! a 2 Is s I EFFECTIVE REVISED DATE January.26 1989 ;,,,, 23v- o*TE 8860 191407-80 es43Mt l
1 j w NSD PHASE 1 FP-INT-R6 REV.0 i hs S \ Qo
- 1
' s e st ee1: -
e : t dwt s I 8 ggi- 1 I I I I I I I I I I I I I I l' esi~ l i I I I I I I I I I I I I I
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! j5 El i I I I I I I i l I I I I i ed l l I I I I I I I I I I I I I s.l-l e ll l-l ;.i j.l ;.l j.l j.
Ef I IBl ISI lil IEl lil IEl l!I
=if l l l l I I I I I I I I I l l f gl" i I I I I I I i1 I I I I I I i eg j ~ l l I I I I I I I I I I I I I i s'i- 1 I I I I I I I I I I I I I r i il I I I I I I I I I I I I I I g e! I I I I I I I I I I I I I I I i s! I I-1 I-1 I-I i-I I1 I-1 I-I ,
En l I l l I I I l l l l I l l l l i
; su l I I I I I I I I I I I I I I I: I
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h
. R R R IC M M
$ I 8 i u E s ! !
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ET fI E% I Ro E M O7 D b EP K Uh
!= 3* : b 38 a L Ny sy?s % s; N 02 3o ?d % Nk s 30
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= 3a N
3! a s a s s a N " gg . .
$ 5 3 b h3 $ S ! !
EFFECTivt oATE January.26 1989 ,,og 231' DATE 8d801914 01 M ws/Orpf ____m.__- _ _ _ _ _ _ _ _ _ _ _ _
c l .
, i PHASE 1 FP-INT-R6 REV.0 i )
1 5-! NI N! ii Y0s i$s fks ils M$ kk i$ / W$ / 3 / i.13
- s s s s s s s s 3
8 8 jg ja i l I I I I I I I I I I I l l j 8 ssi~ l I I I I I I i i l i I I I I I L' s'!- l i l l I I I I i l l I I I I I E i 5 El I i l i I I I I I I I I I I I kW l l I I I l l I I I I I i i i i n!m I i-I i-1 I-1 I-l l-l l-1 I-I l Ell 5l IfI l51 IBl 15l lil 151 lEl
; =He l l I I I I I I I I I I I I I I
? ia l l I I I I I I I I I I I I I I l !!~ l i I I I I I I I I I I I I l l i s':- 1 I I I I I I I I I I I I i 1 I i EI I I I I I I I I I I I I I I I
; ed I I I I I I I I I I I I f I I I
; n! I - I i-I l-1 I-I i-1 I-1 I-1 I-l l l Ef I I I I I I I l l l l l l 1 l se l l I I I I I I I I I I I I I i
=He l 1:1 I:I I,1 II Irl l=1 lel l I
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&Nao I FP-INT-R6 REY.0 E-E b 5s k $
s $ hY Y s$ $ $s $s k $s Y sEk sY sWs $ s$ $ $s &s 8 ggia i i l I I I I I I I I I I I I I 8 og!~ l I I I I I I I I I I I I
- a s'!- 1 I I i I I i I i l i I I I I I I I I
! ! El l I I I I I I I I I I I I I I 5 ef i l i I I I I I I I I I I I I I n!= l - 1 I-1 I1 I-l l-1 I-1 I-l l-1 En I l51 151 l91 Ifl 15l 16l I5l l
, mie l l I I I I I I I I l l l l l I i- 1 I I I .I I I I I I I I I I I I l _!!~l l I I I I I I i i i I I I I l i s'i- 1 I I I I I I I I I I I I I r I i Ei l i I I I I I I I I I I I I l 3 ef I I I I I i l I i l l I l- l I I i t!= l l-I i-1 I1 I-l l-l l-I i-I l l l Br I I I l I I I I I I I I l l l l se l I I I I I I I I I I I I I I
=Is l = l lel lel lel Isl lol lel lel I
E E E E
!5 ,
I $ { 9.9 { {
. E g g g g g g
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EFFECTIVE ' cATE January.26 1989 ,,a, 23O . DATE
- htD1014GT N =69fM' f
PHASE I FP-INT-R6 REY.0 E! QdAj:get N
- S4 /j 0 /<0Yhy E' ' ^
D L'D s t e s $e $ 'E-ee C)- .
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ggia l I I I I I I I I l l l l l l 8 esi~ l I i l I I I I I I I I I l l l W'!- 1 I I i l I I I I I I I I I I l
! j El af I l I I I I I I I I I I i I !
I I I I I I I I I I l- 1 I I s!= 1 1-1 I-I i-1 I-l l-l l-l l-l EfIBl I!l I$l 15l lSl lSI l$l l$
- =Ef l l l l l l l l l l l l l l
! gg!" l I I I I I I 1. I I I I I I I i esi~ l I I I I I I I i I i l I I l i Pi- 1 I I I I I I I I l l l l l 1 i EI I i I I I i l l I I I I I i 5 af I I I I I I I I I I I I I I I g s! 1 I-1 I-1 I-1 I-I i-l l-1 I-l EE l l l l l l l l l l l l l l l l l 5 g Ef l I l l l l l l l l l l I I I I lal l~l
=Ef l lul lel lul lul l~l I I
= # w u l
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!b 5"! Ih o s $$u 3h as, 3 I3 4 k h- hU
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sssA ~ n' E b* h b b b b b
, MV0ED l EMECTivt oatE January.26 1989 ,. , 234 i ent I
m oseu c.m .. = w.
hNSD PHASE 8 FP-INT-R6 REV.0 E-! $$ bb - - d
% 6 s 35s h h~ hb E$ bE Sk h h f.i9~
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8 l I i i l i I I I l l I I I l l 8 _!ja
!~ l I I I I I I I I I I I I I I I
* = 0'i- 1 I I I I I I I I l l l l l l l
! j El l I I I I I I I I I I I I I I af I I i i l I I I I I I I I I I I t!= l - 1 I-1 I-1 I-1 I-1 I-1 i-l 1-l Bf I 15l 151 Isl I5I 151 l5l Isl I
- =551 1 I I I I I I I I I I I I l l
! gg!" l I I l l I I I I I I I l l l l l eg!~ l i I I I I l I i l I l i I i l i W':- 1 I I I I I i i l I i l l I l- l l EI I l l I I i l l I I I I l l l 5
af I l I i i l I I I I l l l- I I I 68s I l-1 I-1 I-1 I-1 I-1 I-l l-1 I l 1 Ef I I I l l l l l I I l l l l l I Er l I I I I I I I I I ! I I I i
=Islel 1:1 1:1 I:I lol Isl Isl Isl 1
- = =
l 5 h h
! 5 W !! E E E a
- e E E E E R R E E 5
is 5 5 E Bl! ! E E E E $ $ $ $ E E! %c %%t s tg 6 % 1R t sb ts %
!= E* !
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.... ~. . .. ..
177 12P6x 1950 17 A9P1 12P25x 12P9x 524 602 648 832 352 844 823 13 ' 144 12P18x 42P94x 12P32X 1946 12P44x 12P3x C13 813 B19 843 B07 C27
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RS23 99P6 12P15x 20P22 APS2 R$24 2827 A51 A37 A60 A55 AM M5 A64 21 12P2x 12P13x e525 12P14x 20P8 8528 2522 A27 A61 A63 A31 A02 A43 A38 22 Aap3 20P20 20P30 20P4 20P9 20pis 20P19 403 A16 A46 A33 A48 A49 A50 23 seP1 20P2s 16P62 20P26 seP4 ePs2 20P5 A28 AOS A17 A36 A06 A07 A15 24 20P25 1954 1945 AAP1 20P2 1943 25 A47 A01 A29 A14 441 A23 89P2 20P7 99P3 49P2 12P16X 16P57 A57 A12 A18 A05 A09 All 26 8521 20P13 99P1 99P5 1954 A9P5 27 A44 A58 A42 A22 A40 A10 SPINT FUEL PIT AFTER NEW FUEL LOAD SHEET 2 0F 6 > l REVISED sPsictivt oatt January, 26 1989 ,,og N DATE 1 l 9s601914 8188 =&'alMt
I,& l\ s i-h NSD PHASE 11 FP. INT.R6 REV.0 BB AA Z Y .X W V. U T S R Q P 18 . 252 241 226 237 219 209 1< 12P152 # 132 1p31 859 P57 P48 CIS COS C32 Ret M0 P27 PS6 USS e66 V36 WI 10 12P2Sx 1p29x 12P54x 12P33: t#44 12P50K 12M5x 1p142 12P622 ip232 545 P44 . C16 P14 C64 . C60 a44 P23 12P22 P03 12PS3 u65 . N5 una sto-yy 12P21x SPS11 12M2x 1 # 64 A9P3 42P62x 42P57u 12P262 12P192 12P59Z 1 # 28 s16 C59 Cc7 C22 C42 C50 m29 att P55 P12 uS6 s57 V37 W2 12 12P19M 42P75x 204 12P30x 1pH 4p?tu 42P63s # 22 1 # 192 12P332 12P562 12P112 822 C46 C12 P24 CO2 Cl4 att P20 P10 u66 R40 ue9 526 13 225 42P08x 248 A9P6 12P17N 42P71X 42P64X 4MZ 1p232 12P322 19 27 g4 B41 C05 P32 C24 c53 a76 als P64 P21 P01 UST 852 V38 W2
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T NSD
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- J N M L K J H G F E D C B A i 232 ssti a102 c2 an a72 12P652 10
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' U08 858 U14 set u29 s54 402 eM 07 n80 at00 182 252 a87 23 v54 e68 156 sel 113 752 s37 733 173 12P542 eM 512 14 a96 202 15 a62 24 532 U50 776 127 a22 146 ft9 set 128 12P452 a107 622 342 a111 282 492 ati se9 744 25 v55 tot f43 U28 85 5 112 169 a108 12PM2 a82 1192 251 102 12P82 12P902 032 se0 u35 s08 u17 26 s05 u5t u25 7 72 u44 302 cru2 402 233 27 v56 DOuuts V36 830 SPENT FUEL PIT AFTER NEW FUEL LOAD SHEET 4 0F 6 s AIVIIIO (FFECtlVE W catt January, 26 1989 ,,or est0 9894 5'* 08 **'82W
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AA Z Y X W V U T S R Q P 12P632 12P102 MZ 535 28
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#16z u67 34
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fur 6 8tmu D5 G PEC. /
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Afvi$gD Ea'Ya*' January, 26 1989 ,,c: bD D'" eso seu ones . vow _--_.-.________________-._---_--_-.________-----.____-----_.-.-_-_---J
1 T NSD I . PHASE 11 FP. INT.R6 REV.0 d i I l l 4 i I N M L K J H G F E D C B A 12P242 $$15 $$14 4P12 506 718 710 T53 28 i i 442 $PLTPN V57 DEBRIS gg Os 224 2c3 189
$07 131 253 432 t02 30 502 151 240 159 134 v58 Isa R21 816 524 R16 31
- . . .. - s . - ..
149 ' 135 137 195 244 a71 a64 als not ass nas 32 392 161 140 215 145 V59 805 R24 806 454 0FA 33 xxxxxx xxxxxx xxxxxx mm xxxxxx xxxxxx xxxxxx mm xxxxxx xxxxxx xxxxxx xxxxxx mm xxxxxx 34 rrrrry xxxxxx rrr m xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx r m rv rrrrry rur m xxxxxx xxxxxx xxxxxx 35 SPENT FUEL PIT AFTER NEW FUEL I4AD SHEET 6 OF 6 4 EFFECTivt AfvtSED caTg January, 26 1989 paar D'"
. . u n.. .mu.
_ . _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ __ ._ _ _ _ _ _ . . _ _ _ . _ _ _ _ _ _ _ . . . _ _ . . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _. _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . _ _ .____________._____________-m_ _ . _ _ _ _ .
e . T NSD PHASE I rp.!NT.R6 REV.0 4 N M L K J H G T E D C 1 A ssit s1s a66 10 SPs13 aos 11 1p42 s17 ase 12 16P122 R31 13 12P72 ts et.I
$27 R23 nos 15 s34 16 R52 17 .
1p132 sc2 18 ase 19 814 20 t17 21 12P182 sit 22 e68 23 532 24
, 25 12Pe2 505 26 CELL 2 somns 27 SPENT TUEL PIT INITIAL CONDITIONS SHEET 4 OF 6 s EFFECTivt Rfv!$tD cAvr January, 26 1989 , og DATE
.,a m. v.m ..w .
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page J42(Sraa4 W p!f a4 easer 4 ca n.3ee] ss..A 3 ,g (,)
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~
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; =If l l I I I I I I I l l I I I I I i i" l I I I l l I I I I I I I l i gg!~
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l l !!~ l l I I I I I I I I I l l l 1 l i V'!- 1 I I I I I I I I I l l l l l l i ii l l I I I I I I I I I I I I I af I l l I I I I I I I I I l- I I i t!e i l l I I I I I I I I I I I I I j ! ti l s l s l s l 21 s l ! ! ! I s i s l 2 ! s i s i s i s i s l g sk l l I I i l l I I I I I I I I l eff I I I I I I I I I I I I I I i l i ~ ~ ~ i - I . i g
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3. vg f.! 8 - 2 s:s:SES Sws:s2 k has k2,g$esest js :; a = a m a m a a s : a e : l E'l/s"' Jtnuary, 26 1989 ,,3, bb DA E 4.,,,...._,
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, PHASE !!! FP-INT-R6 REV.0 E-! k%k$ d gf hQM{f h % h[
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{ l $fl5lSlflflilel5lEl5lSl5lflSl:lel su l l I I I I I I I I I I I I I I mie l l I I I I I I I I I I I I I I I l' l l
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[ j fl i I I I I I I I I I I I I I I e! I I I I I I I I I I I I I I I I t!= 1 I I I I I I I I I I I I i ! I ElIiI!l5I5I!l5lEIil5IEl!l!l!l5l9l
- sie l I ! I I I I I I I I I I I I I i ia l l I I I I I I l l l l l l l l l _!!~l l I I I I I I I I I I I I I I i W'!- 1 I I I I I I I I I I I I i 1 I is iI I I l l I I I I I I I I I lI n! I l i I I I I I I I I i 1 I I I 68s I I I I I I I I I I I I I I I I l [ tilililililBlslEl!Isl5lEIElslelil
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hNSD PHASE If! FP. INT-R6 REV.0 l l l 1 E!lk{SE[3{d[1jhSENdtf%j#d5}fD C 4 S 5 2 la l= 4: e s e ,t t sd at J c ia i I I I I i i i ls 'llj~ll i l l I I I I - l l l l l l l l l l l ] l l l
- = V !- 1 I I I I I I I I I I I I I I I
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a NSD
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!*! hk k '$
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af I l l I I I I I I I I I 1 I I l 68: 1 I I I I I I I I I I I I I l l l ! ti l l I I I I I I I I I I I I I g sel.l .I l.I . l.I 1.1 1.1 1.1 mit i I I I I I I I I I I I I I I i I .
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j l ti l l I I I I 31 El 21 El i I g Er l I.I l.I 1. . I I I I I l-sif l l I I I I I I I I I I l l . I ! ! ! E e E E E I E E E E E s i= i. 62: I; et e mu spg te em g 4- 13 se Ig g i*! 3b r%mm Eh 3G E e$ Ib EG s - ws mh 2$ m- m EE $ sE g.E~ $b {T g I I I I I I I E I { q E E oa$ January, 26 1989 ,paos JW ISD WW M*W wo4NH O
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- NSD
.. PHASE !!! FP INT.R6 REY.0 G F E D C B A 1
752 462 tik Mt 1W362 vi9 003 T38 ute 154 2 R76 i & 31 RE3 12P732 12P642 704 765 WZ TM 374 $71 3 12PMZ R106 3110 16P28 114 T37 T24 f63 4 T64 WZ 192 169 792 822 840 875 U33 UO2 850 5 e93 s3r art 6 - 707 T32 751 u31 u41 12Pe62 168 93 kt 902 7 s72 ses ur un uzr 762 12P552 12P372 852 912 g u01 s42 sea vis uts 06Z t71 1222 12PG82 922 v11 T47 U32 T40 u24 9 SPENT FUEL PIT AFTER ENSERT CHANGEOUTS SHEET 1 OF 6 i i ansetwa cats January. 26 1989 pas Qg "Ev'5ED DATE l 08801914 89.m evW688
~
NSD J PHASE III FP-INT.R6 REV,0 JJ. HH GG- FF EE DD- CC 175 133 13e 6P72 ao 165 055 see M2 e37 e38 e35 10 nD11X 1p47 1eP62 tap 43 taps 3x 1apets 163 gg eM cto cae en e2s eu e62 156 1pra sp61 aoPit AoP4 &apets tap 36s e50 cat oli cor eu s2r - eso 12 177 1aP6K 1plo 17 A9Pt 12Pa5K 12P9x y3 e24 set e64 R32 052 - e64 e25
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. ct3 013 e19 N3 007 c27
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- e03 se6 set cat nos aos eso '
19 1P23N 1969 30P6 1960 Pe/ept 147 gg e39 e36 Sa6 . 821 e53 c31 012 1 arts taPion tes: 17e 176 1 71 tes gg A52 An Asp esa est cas cet 20PM 1p55 te48 sept Art eeP3 Ap6 Ao6 A3e - A21 A32 Ano A13 A53 2O es23 seP6 taPilu 30P22 APS2 e8M e827 gg As1 A37 Aeo Ass Au Ms AM 172X tap 13N es25 12P14E a0PS eta $ e822 A27. ut As Ali Act A63 43s 22 AeP3 apan seP30 30P6 aOPS 20P14 aOP19 A03 Ate M6. A33 468 M9 ASo 33 seP1 anpas sp62 aspa seP4 ePs2 acP5
. 45 AAS Atf Ah Ao6 Ao7 . A15 24 anpas irs 4 1p45 Aert aoP2 tems 25 M7 Ao1 Aa9 A14 M1 A23 seP2 asp 7 seP3 A9P2 tries 1p57 AST A12 A18 Aol AoD Att- 26 esti 30P13 e9Pt 09Ps ipSe A9P5 37 M4 ASS A62 A22 A40 Aio SPENT FUEL PIT AFTER TNSERT CHANG 50UTS SHEET 2 0F 6 ,
SPPECTivt . Oog REVISED DArg January, 26 1989 . c. Ol **T8 de i.w v.se . .
- hNSD PHASE ff! rp. INT-R6 REV.0 55 AA 2 Y' X W V U T S R Q P 18 52 201 336 57 219 asp 1912 131$2 # 132 632 1pStt Ftt 999 MT MS c5 cob CSI te9 Pic PI7 gg PS6 UWS See V36 taptex tap 39u tapleh tIP33r 1p44 13Plou adSk te143 tapar att jamat as ', apt 32 M5 P44 Cie P14 ces coo PD ,3 a44 Po3 965 MS una 1 810 tap 21M :Psti 13P4D DM 49P3 43PG2!,,D57K 1apa62 tap 192 13P991 a77 taps 12 n! gg 816 CS9 CST C22 c42 c50 aN E19 PS$ Pt2 Ute 857 V37 taPitu 4aPS$s See tap 30s ipse tapfen 4apen en te19 stof tapsst 35: tytit 13 sat cu Csa Pts con ese sia Pac Pio uu see ue9 s26 225 tareau 24a A9P6 tapin saPrix tape 4x 6per trast lapsta on tars 42 sais g4 a41 . col P32 c24 CS3 nF6 ats PM Ptt Poi ul7 352 V38 157 tap 471 43Pf3x 13P34X 20P21 &aPF3M tap 49u # 32 1eMI ett plot e67 1#24Z e14 ces por PM Cao als eso a49 mi ue7 Pts u7e sss 15 191 &arttu tas torio 239 - 43P70s 196 195 18PS2 1aP752 552 1aPSot 8814 c61 C19 M1 CM cti sto P11 Ps9 P19 PH ubs 856 Vs0 16 is 160 12 &arsen 4aP9tx tapess 212 172 tytit TR**4 eper met taPie g7 r aD car Pss pts C17 an au m3 pts g ato urt sas tarssa ersit tw fatan sapeem eaNo taptat 167 #t12 l#NB8 112 tap 912 nt gg .
sts cts P37 car Aa4 Ps6 Ps4 Pe6 Pse g us9 su we to 19e aos aGPt* &aNS 4aPFaK tap 212 M31 a82 18PR2 # 142 14 tap 2SI gg sas em Pts c43 Css Pos Peo M7 vi3 ase ses urt sis ialt 4 apt 9N cpF cp4 20P14 saPGIN 14P112 taPtn ten II9ME 132 6P92 Mt 20 M9 c3p est AS6 c34 c41 P51 PSI mas a58 m une at asa6 AS9 329 P3s col tapeau 1p31: sapeen tes: 1etot tapetz Ptr Pts ces Pat N6 aof Ps3 g,e3 tarnt as atoo un asz 21 sas T' laPSs act c8Pi &aPS3M 43PSSX sap 67E test tePS2 tweet itP2N PM tapet $42 22 Ass pu ces esa c45 a67 Pos set Pat nog ue1 sit _ n2 } 1 ape z54 m3 43NSM a42 taMa 1 # 33 1&tM 1R %IPPE tap 352 atol i # 122 23 Aas Pos c14 cu cet est Ps9 as6 use msg n27 un s33 acPts act ces saPett sapen 4aPra sein teact leisz inest2 atta tapsz est 24
. Aes Pea ce9 c52 cis ets esa en nos ny up sao us acP27 car taPa6s ano 4arr7m earfen ~N tett2 1 1730: t amot as ' tetet 25 i 442 Pm cm cas ces ars Peo ast pas
@6 att un s22 som ens 4 apse 1327 esp $n laPltX 1aPast tap 92 tam 81 'IPSIE a01 1aP9o! 612 26 Aas na ese sea cas nas Pts us a!' A62 un st9 we tams tarsa tap 3m tamix 4apeon tyter utsz tame 24Z 1arez 27 Alf Ps1 c49 C48 c51 a45 Pop e57 u?6 501 SPENT FUEL PIT AFTER INSERT CHANGE 0UTS SHEET ? 0F 6 ,
sPPscTivs arvtsso DATs January, 26 1989 pass 282 DAM ma i u v.m . .
hNSD PHASE III FP-INT-R6 REV.0 l N M L K J H G F E D C 3 A 12P69: 232 ssit sp27 l aas 12P M 12P652 93: sta veo AM T41 ur Ttt 844 965 U20 10
$n sesi3 5n span a76 a95 1est nios 11 v48 3o8 U52 s43 T31 767 T35 T45 T74 W 703 12pur 3sz 1paz an otz on 153 im en mz sif v61 e54 T44 u12 U21 873 338 uo6 ut3 12 an intzz 12,7n 2tt im faz 8tz v49 m31 853 363 839 Woe u42 T2e T16 13 iz pez tan an au 742 m 12Proz 12P74r anz 95 34 s27 ve.2 R23 m up uS9 ses 351 uz2 us7 45r 12P42z are an aso9 15 v50 a65 T3a T5s To2 no t42 t15 tas 1p5tz 412 12P44 59: Saz 12Pazz osz 15z ice s34 v63 sfo uop uso s76 uso use te 16 222 12P43r am a111 ano V51 e52 T26 T49 T36 T23 168 Tz2 foi 17 1p13z 43z 152 532 12P6u an 222 32r a1oz yg se2 v64 ur uso su uor ut vos T75 saz 12Ps9: 141 R91 245 atz nas m 19 V52 m36 M5 709 fM su T25 feo Uz3
( . . 12P67z M7 set 179 taart 192 14 a65 20 814 u48 705 e55 T79 m T17 mit 721 T57 46z 12P40 RN 37z 12P05z 36: alot Sir 1p26 21 v53 a17 T55 T29 859 TF1 To6 759 fel Wz 12P182 a92 172 173 IIz 12P53z 2o2 243 25z gg s11 u69 uot est ute M1 U29 854 943 soz 12Paoz e62 or a7 1st a97 aos 23 vu nas 756 ut T13 T52 s37 T33 7 73 tarsiz en 1p25 5tz 16 1pso att3 15 24
. s32 u50 T76 W T27 az2 fu W fi9 att T28 49 12P45z e69 62: 12psn sto3 34r 12r71z taz 25 v55 top f43 U28 855 T12 769 369 744 12Per 18: o3z a73 12r 12P54z 119z 251 1er ses ust u25 in we seo uss sos u17 26 3o2 mLL2 toz H3 27 v56 ocauts uu s30 SPENT FUEL PIT AFTER INSERT CHANGEOUTS SMEET 4 0F 6 ,
l
)
i EFFECtivg aEVISED otta January, 26 1989 pas, DATE 8801944 87 N *v33648
NSD - PHASE 122 FP-!NT.R6 REV.0-AA 2 Y X W V- U T 5 R Q P
\
- c. iassu nas tarioz mz 28
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- vos a via a vie a vao a was a was a vsa w um sts wr 32 ment meios arm ismu etar for not voi vs we een va ,,,e ses vss em 33 erz . 34 wr EE 35 serc.
SPENT FUEL PIT AFTER INSERT CHANGEOUTS SHEET 5 0F 6 l SPPECravE - para January, 26 1989 (~) Q d AEviSED : pas: LU \ DAT8 l l ISD 1914 pt.m =>Weef
- j PHASE III FP-INT-R6 REV.0 l
i 4 N M L K J H G F E D C B A 12p242 e90 n99 6P12 s06 T18 fic T53 28 442 SPLTPu V57 DEGRis 29 12Parz 08 224 203 1s9 807 831 R53 R32 R02 30 502 151 240 159 134 vs8 las att sie s24 ate 31 12rr22 149 135 137 195 2"
- R71 464 R13 R01 233 R48 32 392 161 140 215- 145 V59 ROS R24 806 254 DfA 33 xxxxxx == mm xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx mm xxxxxx xxxxxx xxxxxx xxxxxx 34 mm xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx xxxxxx mm == xxxxxx xxxxxx xxxxxx 35 SPENT FUEL PIT AFTER INSERT CHANGEOUTS SHEET 6 0F 6 s9Pactiv' DATE January, 26 1989 ,,c, ?85 W m6oseuv.m . .
_ _ . _ _ _ - . _ - - _ _ _ _ _ - - - - - - - - - - _ - - - - - - - _ - - - - ~ - , - _ _ - -
^
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/ (J l( JU IUl a .!. ! ~ l i I I I I I I I I F l l'1 I I m V'i- 1 I I I I I I I I I I I I I I I
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! V'i- 1 I I I I I I I I I I I I I -l I i iI i l i I I I I I I I I I I I I s
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- e a s s a s s a s a a s i
n= . is 5 5 f f i s E i 5 5 B B i i f 2 W k ' 5 w 5 4 e- E S hf b ij 8= lt h; ;?t ! s a n ?,Ie a n$31 4BEseBL96stE is . s ~ z - a . s - . 3 - s - I h' deb ji I g iffsi !N I EFFECTivg AtVISED Datt January, 26 1989 pact ' use ,el, e ee .s,eea, l 1 l . l' _ - _ _ _ - _ _ - _ - _ _ _ _ - _ - _ - _ .
h NSD
. PHASE IV rp. INT-R6 REV.0
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5-!MAdk3I25bE$ M2bil5352$31 a ia VI I I I I" IU I U iu l l 1 I I I l a !!~ l I l I I I l' I i i l l I I I I
~ = V'!- 1 I I I I i l l I I I l l l l l I l El l I I I I I I I I I I I I i l n! l I I I I I I I I I I I I l l 1 t!e i I=I I1 I-1 I-1 I1 I-1 I-1 I Ef l l l l l l l l l l l l l l l l
=Irlzl sl 1:1 jul l~l Iwl lui l~l
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g9 YE gg kl gg l RFFECTIV REVISED DATt January, 26 1989 pact - ** l tutD sesa s?-g8 wn/WB6et
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z ggia I " l* I V lll I I I I i 1: I I I I a sgj~ l i I f I I I I i l l F I I l l a V':- 1 I I I I I I I I I I I I I l l [ j fI e! I I I I I I I I I I I I I I I I i I I I I I I I I I l_ l I I I n!s I - 1 I-I l-1 I-1 i-1 I-l I-1 I-I af I l l l l l l l l l l l l l l l
; sif l lel Isl Isl lil 151 lel Isl l I ia l l l I I l l I I I I I I I I l l gg!~ l em l I I I I I I I I I I I I I I i V'!- 1 I I I I I I I I I I I I l 1 I i fI I I I I I l l I I I I I I l l s
e! ! 1 I I I I I I I I I i 1 I I I t!= l 1-I l=l !=l 1-l 1-l l=l l-1 I l 1 tilEl lEl ISl lil 15l lil 151 l p! g if I l l l l l l l l l l l l l l l sif I l l l l l l l l l l l l l l l 1 g I i g , I $ i I H E B I I i i I I I
- e a a s s a s i
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= r I@ h E 0 E RE gs $s IE55 u 6 ss+Es d 45sE9E d 5 i
2': ana448 bit st4mhttb ja a ! = 5 e ! e f z A z ! = 5 z I d $5 il II
!a EFFECT vt DAtt Qg RivtSED January. 26 1989 Pact L LJ 0*T'
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PHASE IV FP-INT-R6 REY.0 ; W W t 35 h s , !0 $ ^o i-! lig((}{Mgi%j{jjjjjggj$ a != 1 1 I I IV I Id l l l l l l I I a
!~ l I I I I I I I I I I I i 1. l l a l'!- 1 I I I I I I I I I I I I I I l
[ l EI I I I I I I I I I I I I I I I ef l l I I I I I I I I I I I I I I sEs l I=l l=l l=l l=l l=l l=1 1-l l ti l I I I I I I I I I I I I I I I
- Itisl Isl Isl lel lol Isl l=l lel l-
! ia l l i I I I i i I I I I I i l l E
l 3l~ l l I I I I I l l l l l l ! I I i V'!- l ! I I I I I I I I I I I I 1 I l L [ EI I I I I I I I .I I I I I I l~l s e! I J l l I I I I I I I I 1 I I I 68 l=l l=1 l-l l-l lI l=1 l=1 l=1 L j g ti l lui lel el lil lil lel lel I g sa l l I I I I I I I I I I I I I I l vit l I I I I I I I I I I I I I I I I E . I t i l l 5 f- n a a !! E s I
- a R R I I E E 5 la 5 I !
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l l EFFECTIVE oa?E January. 26 1989 past Q"
#EV!EED
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. 5-!MMlililih l l~ l l I IV I "
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! l El l I I I I I I I I I I I I I I t! I 1 I I I I I I I I I I I I I I s!= 1 - 1 I-1 I-1 l-l l-1 I-1 I-1 I-l Ef l I I I I I I I I I I I I l l l
. wir l lel Isl 11 lxl lel Isl Igl I
? ia l i I I I I I I I I I I I I I i l _!!~l l I I I I I I I I I I I I I I i V !- 1 I I I I I I I I I I I I i 1 I i il I i l i I I I I I I I I I I I
= t! l .I I I I I I I I I
- I I I I I i s!= 1 1-1 I-1 I-1 I-1 I-1 I-1 I-1 I j ! tiltl Igl lil lal Isl Isl Isl I s _I y
Er l l I I I I I I I I i l i I I I mie l i I I I I I I I I I I I I I I i I i i ! ! !! i f g i f f I A E E E .I E E
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, PHASE 1Y rp. m .R6 REY.0
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; sif l a l Isl Isl IEl Isl 151 Isl 151
- I I I I I l l l I I I I I I i i! '3g!"
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=E s e s e s, e h sh n$, hw eu m n 4 k E gg esu . -a es
!a A a i s ! : i e 5 5 s 3 3 EFFECTivt DATE Janua ry, 26 1989 Q/ REVISED DAtt pagg emneseust.m . w on m_._________m__ _ _ _ - _ _ _ . _ - - . -
h wso I PHASE IV FP-INT.R6 REV.0 i t i i , , \1 , \ 5-! h ' g I IU ll { a ia i I l' I ~ lv IV IV l' l' L IV I" I" I a l~ l l I I I I I I I I I I I I i l a N'i- 1 I I I I I I l l l l l l l I 1
! l El l I I I I I I I I I I I I ! 1 ta l i I I I I I I I I I I I I l l t!= l = l l=l 1-l l=1 1-l l=l l-l l-l El l l l l l l l l l l l l l l l l
, Is l le.1 lol II lel Ici lsl 131 l
! ia l I I I I I I I I I i l i I I l l _!~ ! l i I I I I I I I I I I I I I I i H'!- 1 I I I I I I I I I I i i 1 1 I i iI I i l l I I I I I I I I I i-l a
s! I l i I I I I I I I I I i I I i 65: I l=1 i=l l-l l-l l=l l=1 1-1 I j ! tilsl Isl lil Isl Isl Isl Is~l Isl g se l l I I I I I I I I I I I I I I In l I I I I I I I I I I I I I I I I i i i i g b b - b b i e n ! ! !! ! I
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h j?{ c.2; 1 rN 1.g APPENDIX B GENERATION OF WITHDRAWAL LIMITS TO ENSURE A.
. NEGATIVE MODERATOR COEFFICIENT As can be seen from Table 1.2 on page 1-5, the measured isothermal temperature coefficient for ARO Is -0.94 pcm/*F. It is assumed that -1.86 pcm/*F is the doppler temperature eve *ficient. Therefore, the moderator l- - temperature coefficient for ARO is M,P4)-(-3.66) = +0.92.
According to the predictions of the Nuclear Parameters-and Operations Package for Indian Point Unit 3 Nuclear Power Plant, Cycle 7 (NUPOP, WCAP-12169), Bank C must be inserted to a level of 110 steps to ensure a negative moderator temperature coefficient under the above conditions. This information is taken from NUPOP Table 4.3-2c. B-1 j
o, In order to draw a curve, withdrawal limits must be calculated for other boron concentrations. 1.et us postulate pulling the Bank C rods from the above position to 186 steps. Using Table 4.3-2c as we did before, we find that an increase of 0.64 pcm/*F is obtained. In order to offset this increase, it is necessary to lower the boron concentration by an amount determined from the equation provided on page'4-16 of the NuPOP. C B ( d Config.) X (C ref (Ppm) - C B B measured (ppm)) 100
= 0.97 X 1487 - C = 0.64 3
100 Therefore, C " 1421 ppm B This provides us with a second set of withdrawal limit conditions: C at 186 steps and C3.at 1421 ppm 4 B-2 _m._._. -._ _ . . . _ . . . _ _ _ . _ _ _ _ _ _ . _ - . _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - - . .
l l-. o Using the same basic technique, insertion limits can be calculated for any rod configuration or boron concentration chosen. Eleven other points were selected; the resvits are tabulated below: TABLE B-1
SUMMARY
OF WITHDRAWAL LIMIT CALCULATIONS Bank C Bank D Increase in MTC (pem/*F) Corresponding Pesition Position from original configu- decrease in (steps) (steps) ration of C/110 Boron (ppm) CB (Ppm) 110 0 0.00 0 1487 126 0 0.14 14 1473 146 20 0.31 32 1455 166 40 0.48 49 1438 186 60 0.64 66 1421 206 80 0.77 79 1408 226 100 0.86 89 1398 226 120 0.87 90 1397 226 140 0.88 91 1396 226 160 0.89 92 1395 226 180 0.90 93 1394 226 200 0.91 94 1393 226 226 0.92 95 1392 Figure B-1 presents the withdrawal limit curve. B-3 m--__ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ _ _
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- s. t ATTACHMENT ll TO IPN-89-059
' INFORMATION REGARDING THE NEW STEAM GENERATORS Il r
.i 2
E F l NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT i4 DOCKET NO. 50-286 DPR44 L:
STEAM GENERATOR REPl.ACEMENT The Power Authority replaced the four (4) Westinghouse Series 44 steam generators with new Westinghouse Series 44F steam generators during the cycle 6/7 refueling outage. The steam generators were replaced due to the significant degradation they had undergone as a result of pitting and denting corrosion and because of the significant impact that the required inspections and repairs had on plant availability, reliability and operations and maintenance costs. The new steam generators contain some significantly improved design features over the old steam generators as summarized below:
- 1. Inconel 690 Thermally Treated Tubing with a cobalt content of 0.015% maximum and with rows 1 through 8 stress relieved.
- 2. 405 stainless steel quatrefoil tube support plates.
- 3. A flow distribution baffle.
- 4. Three sets of 405 stainless steel anti-vibration bars.
- 5. Full depth hydraulic expanded tubes.
- 6. Increased blowdown capacity.
- 7. A one piece forged transition cone.
- 8. Four additional handhcles and an upper tube bundle inspection port.
- 9. A welded feedwater nozzle thermal liner.
- 10. 112 modular primary separators.
- 11. Flush tube to tubesheet welds.
Overall, these features are expected to provide much greater resistance to corrosion, increased reliability, maintainability, availability and lower radiation level buildup as compared to the oid steam generators. The naw steam generators were designed to provide the identical thermal output under normal conditions (3083 MWt total) as the old steam generators except with a lower moisture carryover of less than 0.1%. They were also designed to fit into the same envelope as the old steam generators and to provide the same response during accident conditions. Therefore, the replacement was performed under 10CFR50.59. To confirm the above design, a thermal performance test and a moisture carryover test were performed at 100% licensed power (3025 MWt tota!). The test results confirmed the steam generator thermal design and the reactor coolant flow remains well above that required by plant Technical Specifications. Also, the moisture carryover test showed the moisture carryover to be 0.01%, well within the design value. Therefore, the replacement of the steam generators has not had a significant impact on the thermal hydraulic performance of the plant.
i ATTACHMENT lilTO IPN-89-059 INFORMATION REGARDING THE HIGH PRESSURE TURBINE OPTIMIZATION PROGRAM NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR44
HIGH PRESSURE TURBINE OPTIMIZATION PROGRAM The Indian Point 3 turbine generator was originally rated and guaranteed to a steam flow equal to the licensed thermal power of the NSSS. The turbine was designed to pass 5% additional flow which has resulted in losses at the guaranteed point due to operating with the last steam admission valve partially open. During the 1989 refueling outage the high pressure (HP) turbine was optimized to move a majority l of the operating hours to a valve point. Operating on a valve point minimizes throttling losses and l thusincreases the unit efficiency. Part of the optimization was achieved by reducing the nozzle height and the control stage blade height. Reducing the area of the HP turbine inlet while maintaining the same steam flow forced the valves to open at lower load points. The second part of the HP optimization was to increase the control stage exit pressure to the optimum for the majority of operating hours. The control stage is a Rateau or impulse type design; the remaining HP stages are of the reaction type design. In the large size turbine that is applied to the nuclear cycle, the reaction type stage is inherently more efficient. For this reason, it is desirable to maximize the work performed in the reaction stages. Therefore, in order to increse the proportion of work performed by the reaction stages, the impulse chamber pressure must be increased. The desired increase in impulse chamber pressure was accomplished by installing new stationary l blading and by adjusting the gauging of the proper number of stationary rows in the HP blade path. In summary the HP Optimization Program included:
- 1. Two New Nozzle Blocks
- 2. Two New Rows of Triple Pin Control Stage Blades
- 3. Ten New Rows of Stationary Blades (5 GVN and 5 GNN)
- 4. Four New Rows of Reaction Blades (Two GVN and Two GNN)
Based upon HP turbine optimization calculations the anticipated heat rate improvements were set at 10 btu /kw-br for the new steam generators and 63 btu /kw-hr for the HP turbine optimization program for a total improvement of 73 btu /kw-br plus or minus the test tolerance of 18 btu /kw-br. The HP turbine optimization modification acceptance test ENG-348 was prepared, approved and successfully carried out in July,1989. This test demonstrated the heat rate decrease equal to or larger than the minimally acceptable 70 - 18 = 55 btu /kw-hr. Complete details of the HP turbine optimization are filed at indian Point 3 as Modification Package 88-03-055 TG.
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