ML19350D389

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Cycle 2 Core Performance Rept
ML19350D389
Person / Time
Site: North Anna 
Issue date: 03/31/1981
From: Ju J, Rotella T
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19350D386 List:
References
VEP-FRD-40, NUDOCS 8104150401
Download: ML19350D389 (50)
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{{#Wiki_filter:V EP-F R D-40 I e NORTli ANNA UNIT 1, CYCLE 2 CORE PERFORMANCE REPORT BY J.R.JU I T. S. ROTELLA t i I I ~ l I I Reviewed: Approved: (^ a-w C. T. Snow, Nuclear Fuel Engineer E.. dzit&,' Dire @ Nuclear Fuel Operation Group N cl Fuel Opehation Group Nuclear Fuel Operation Group Fuel Resources Department Virginia Electric & Power Company Richmond, Virginia I me.1mno wro 40/

CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which I they were specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular. THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICi1LAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use lI is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, I l tort, warranty, or strict or absolute liability), for any property damage, 1 mental or physical injury or death, loss of use of property, or other damage ( resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, infor=ation, or conclusions in it. l t f ,I 1 .I

i ACKNOWLEDGEMENTS l The authors would like to acknowledge the cooperation of the staff at North ( l Anna Power Station in supplying the basic data for this report. Special thanks are due Messrs. J. P. Smith, G. L. Amodeo, and A. K. White. Special thanks is also due to Ms. S. L. Kulp for her patience and accurate typing of this report. I I l l I I I

) i TABLE OF CONTENTS Section Page No. Classification / Disclaimer i A cknowledgements.................. il List of Tables iv Lis t o f Figures.....'............... v 1 Introduction and Summary............... 1 2 Burnup Follow 6 3 Reactivity Depletion Follow.............. 11 4 Power Distribution Follow. 13 5 Primary Coolant Activity Follow............ 38 6 Conclusions 42 References...................... 43 l llI I I I lI lI ,I iii l l-_

I LIST OF TABLES Table Title Page No. 4.1 Summary Table of Incore Flux Maps for Routine Operation.. 17

I lI lI I

I I I !I I 'I I I I I

LIST OF FIGURES Figure Title Page No. 1.1 Core Loading..................... 3 1.2 Movable Detector and Thermocouple Locations...... 4 1.3 Control Rod Locations................. 5 2.1 Core Burnup History.................. 7 2.2 Monthly Average Load Factors............. 8 2.3 Assemblywise Accumulated Burnup: Comparison of Measured with Predicted................ 9 2.4 Batch Burnup Sharing................. 10 3.1 Critical Boron Concentration versus Burnup - HFP,ARO.. 12 I 4.1 Assemblywise Power Distribution - N1-2-18 20 4.2 Assemblywise Power Distribution - N1-2-30 21 4.3 Assemblywise Power Distribution - Ni-2-47 22 4.4 Assemblywise Power Distribution - N1-2-52 23 4.5 Hot Channel Factor Normalized Operating Envelope... 24 4.6 Heat Flux Hot Channel Factor, F (Z) - N1-2-18...... 25 4.7 Heat Flux Hot Channel Factor, F (Z) - N1-2-3 0...... 26 4.8 Heat Flux Hot Channel Factor, F (Z) - N1-2-47...... 27 4.9 Heat Flux Hot Channel Factor, F (Z) - N1-2-52....... 28 l 4.10 Maximum Heat Flux Hot Channel Factor versus Burnup 29 4.11 Rod Bow Penalty on F 0 aH 1 1 4.12 Enthalpy Rise Hot Channel Factor versus Burnup 31 4.13 Target Delta Flux versus Burnup 32 4.14 Core Avercge Axial Power Distribution - N1-2-18..... 33 4.15 Core Average Axial Power Distribution - N1-2-30... 34 1 4.16 Core Average Axial Power Distribution - N1-2-47..... 35 4.17 Core Average Axial Power Distribution - N1-2-52..... 36 I 4.18 Core Average Axial Peaking Factor versus Burnup..... 37 5.1 Dose Equivalent I-131 Concentration versus Time..... 40 5.2 I-131/I-133 Ratio versus Time 41 3 v

I Section 1 INTRODUCTION AND

SUMMARY

On December 28, 1980 after more than eleven months of aperation, North Anna Unit I completed Cycle 2. Since the initial criticality of Cycle 2 on January 15, 6 1980, the reactor core produced approximately 64 x 10 MBTU (10,711 Megawatt days per metric ton of contained uranium) which has resulted in the generation of I 9 9 approximately 6.0 x 10 kwhr gross (5.6 x 10 kwhr net) of electrical energy. North Anna 1, Cycle 2 reached the end of full power reactivity at a core burnup of approximately 9,150 MWD /MTU at which point power operation was continued through a power coastdown. The unit was operated in the power coastdown mode, achieving an additional burnup of approximately 1561 MWD /MTU prior to shutting down for refueling. The purpose of this report is to present an analysis of the core performance for routine operation during Cycle 2. The physics tests that were performed during the startup of this cycle were covered in the North Anna 1, Cycle 2 Startup Physics Test Report and, therefore, will not be inclu'ded here. The second cycle core consisted of four batches of fuel. Three once burned batches were brought from Cycle 1 (Batches 1A2,2 and 3). One fresh batch was added to the Cycle 2 core. The North Anna 1, Cycle 2 core loading map specifying the fuel i batch identification, fuel assembly locations, burnable poison locations and source assembly locations is shown in Figure 1.1. Movable detector locations and thermocouple locations are identified in Figure 1.2. Control rod locations are shown in Figure 1.3. Routine core follow involves the analysis of four principal performance indicators. These are burnup distribution, reactivity depletion, power distribution, and primary coolant activity. The core burnup distribution is followed to verify both burnup symmetry and proper batch burnup sharing, thereby, ensuring that the fuel held over for the next cycle will be compatible with the new fuel that is inserted. Reactivity depletion is monitored to detect the existence of any abnormal reactivity' behavior, to I 1

I I determine if the core is depleting as designed, and to indicate at what burnup level refueling will be required. Core power distributicn follow includes the monitoring of 2 nuclear hot channel factors to verify that they are within the Technical Specifications limits, thereby ensuring that adequate margins to linear power density and critical heat flux thermal limits are maintained. Lastly, as part of normal core follow, the primary coolant activity is monitored to verify that the dose equivalent iodine-131 concen-tration is within the limits specified by the North Anna Unit 1 Technical Specifications, and to assess the integrity of the fuel. Each of the four performance indicators is discussed in detail for the North Anna 1, Cycle 2 core in the body of this report. The results are summarized below: I 1. Burnup Follow - The burnup tilt (deviation from quadrant symmetry) on the core was no greater than 10.5% with the burnup accumulation in each batch deviating from design prediction by less than 2.1% l 2. Reactivity Depletion Follow - The critical bet concentration, used to monitor reactivity depletion, was consistently within10.25% 6 K/K of the design prediction which is well within the 11% A K/K margin allowed by Section 4.1.1.1 of the l Technical specifications. 3. Power Distribution Follow - Incore flux maps taken each month indicated that the measured relative assembly power values were within 4% of the predicted values. All hot channel factors met their respective Technical Specifications limits. 4. Primary Coolant Activity Follow - The dose equivalent iodine-131 -2 activity level in the primary coolant at the end of Cycle 2 was approximately 1.1 x 10 -3 p Ci/gm. The average dose equivalent fodine -131 value during Cycle 2 was 8.9 x 10 p Ci/gm. This corresponds to less than 1% of the operating limit for the concentration of radioiodine in the primary coolant. In addition, the effects of fuel densification were monitored throughout the cycle. No densification effects were observed. I 2

I PICQ.1 1.1 NORD4 A*:NA 1 - CTCLE 2_ CCRE LOCISC I I a F W st L st J n C F 1 D C S A I l l l l 1 3 D45 C03 D14 l g D52 D07 D13 337 D19 Dil D51 l I l h[ 16* I ss sa-a+o 809 ws) An "U' M' 16F 12P 16P 3 ss I D23 339 C40 C15 C36 815 C07 C47 C39 303 009 SS D41 D39 C04 343 C13 351 C22 B33 C.8 314 CC6 040 316 5 16? 16P D33 B22 C03 C27 MS C30 317 C23 35D C51 C13 323 D37 D22 D30 306 C45 305 C20 324 C32 308 C38 312 C17 347 D06 D20 7 16? 16P I D31 E07 C43 546 C52 320 C1 A31 C28 302 '_51 4339 C49 342 D2* 12P f 12P D10 D43 321 C21 B 36 C37 327 C25 344 C24 332 C03 349 D12 D43 I 16? 16' D29 352 C16 C42 346 C29 319 C11 328 C12 C34 304 DOS D35 D5] C26 335 C-. 313 C31 320 C10 330 C50 D40 D42 I* g,* 16P 16P D15 341 C46 C35 C03 329 C19 Col C33 325 D49 12 SS I 4 D38 00' 310 311 334 301 "U? D34 t *, 158 12P

  • M D 3a De7 DL7 340 D02 D21 D44 I *.

16? 16P I '? D26 D04 D25 g I Ft'EL ASSEv.3LY DESIGN PAPW'ITERS A-htch 1A2l B-Batch 2 C-Batch 3I D-Batch 4 l initial Enrichment (w/o C235) 2.10 2.60 3.10 3.20 Asserely Type 17x17 17x17 17x17 17x17 I No. Of Assemblies 1 52 52 52 Puel Rods per Asse:nbly 264 264 264 264

  • Assembly identification
  • One or mre of the following:
a. PS - Primary Source Assembly I
b. SS - Secondary Source Assembly
c. xxP-Burnable Poison Assembly (xx - numoer of rods)

I I

FIGURE 1.2 NORTH AN'!A UNIT l-CYCLE 2 MOVABLE DETECTOR AND THERMOCOUPLE LOCATIONS I E F N M L E J H C F E D C' B A l O I 2 .l O O 2 O O 2 I O O v l O O O s O O s lE O O O l O O O O O O = O g O 9 O 1o I O e e 11 o l O O 22 l 13 g g l'I 14 O e ') O O is l 'I . - Movable Detector Location l C - Thermocouple Location ,I .I 4

NORTH M;WA 1 - CYCLE 2 FIGURE 1.3 CONTROL ROD LOCATIONS I R P N M L K .7 et C F E D C B A I I i 1 I A D A 2 3 SA SA SP 4 C B B C 5 SP SB SP en A B D C D E A 7 I SA SB SB SP SA S' D C C D l 9 SA SP SB SB SA 10 A B D C D B A I 11 SB SP SB SP C B B C 13 SP SA SA 1:. A D A 15 I Absorber Material: Ag-In-Cd Nurber of Clusters I Function 8 Control Bank D 8 Control Bank C 8 Control Bank B I 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 SP (Spare Rod Locations) I s

I Section 2 BURNUP FOLLOW The burnup history for the North Anna Unit 1, Cycle 2 core is graphically depicted in Figure 2.1. The North Anna 1, Cycle 2 core achieved a burnup of 10711 51WD/MTU. As shown in Figure 2.2, the average load factor for Cycle 2 was 80% when referenced to rated thermal power (2775 MW(t)). Radial (X-Y) burnup distribution maps show how the core burnup is shared among the various fuel assemblies, and thereby allow a detailed burnup distribution 3 analysis. The NEWTOTE computer code is used to calculate these assemblywise burnups. Figure 2.3 is a radial burnup distribution map in which the assemblywise burnup accumulation of the core at the end of Cycle 2 operation is given. For comparison purposes, the design values are also given. As can be seen from this figure, the accumulated assembly burnups were generally within 3.0% of the predicted values. In addition, deviation from quadrant symmetry in the corey as indicated by the burnup tilt factors, was less than +0.5%. The initial burnup tilt (0.75%) in the northeast quadrant for Cycle 2 resulted from the asymmetry caused by the power tilt that l occurred during Cycle 1. As Cycle 2 proceeded, a reduction of the burnup tilt in the northeast quadrant was observed until the power tilt shifted from the southwest quadrant to the northeast quadrant. This shif t of power tilt reinforced the existing burnup tilt and caused it to increase slightly in the northeast quadrant. l The burnup sharing on a batch basis is monitored to verify that the core is operating as designed and to enable accurate end-of-cycle batch burnup predictions to be made for use in reload fuel design studies. Batch definitions are given in Figure 1.1. l As seen in Figure 2.4, the batch burnup sharing for North Anna Unit 1, Cycle 2 followed l l design predictions very closely with each batch deviating less than 2.1% from design; this is considered excellent agreement. The good agreement between actual and predicted assemblywise burnups and batch burnup sharing indicate that the Cycle 2 core did deplete essentially as designed. I s

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Figura 2.3 UORTH AN'IA UNIT 1 - CYCLE 2 I ASSEMBLWISE ACCUMULATED BUR'iUP

  • COMPARISON OF MEASURED WITH PREDICTED (103 MWD /MrU)

R' F N n L K J H G F E D C B A l I 7.93 9.64 7.94 7.63 9.37 7.63 1 I 3.9 2.9 4.1 8.01 10.70 12.51 27.17 12.67 11.06 8.05 7.64 10.71 12.67 26.94 12.67 10.71 7.64 2 ll 4.8 -0.1 -1.3 0.9 0.0

3. 3 5.4 l

I 8.02 12.41 28.68 29.08 20.74 29.20 29.07 12.52 8.34 3 7.78 12.20 28.72-29.40 20.84 29.40 28.72 12.20 7.78 3.1 1.7 -0.1 -1.1 -0.5 -0.7 1_ 2 2.6

7. 2 7.99 27.31 20.e4 26.78 24.62 27.01 24.63 26.95 26.67 27.19 8.22 4

7.78 27.14 26.31 26.59 24.81 27.01 24.81 26.59 26.31 27.14 7.78 2.7 0.6 1.4 0.7 0.0 0.0 -0.7 1.5 1.4 0.2 5.7 l 7.63 12.11 26.31 29.11 21.82 28.64 23.22 28.58 21.84 29.02 26.37 12.67 8.23 5 7.64 12.20 26.31 29.12 21.73 28.92 23.14 28.92 21.73 29.12 26.31 12.20 7.64 -0.1 -0.7 0.0 0.0 0.4 1_0 O_1 -1.2 0.5 -0.1 0.2 1.9 7.7 I 10.75 26.77 26.46 21.50 27.08 22.37 27.03 22.47 27.34 22.04 27.00 28.83 11.07 6 10.71 28.72 26.59 21.73 27.18 22.49 27.02 22.49 27.18 21.73 26.59 28.72 10.71 0.4 0.2 -0.5 -1.1 -0.4 -0.5 0.0 -0.1 0.6 1.4

1. 5 0.4 3.6 7.77 12.58 29.07 24.67 28.43 22.23 28.27 21.49 28.15 22.46 28.36 24.77 29.20 12.42 7.64 7

I 7.63 12.67 29.40 24.81 28.92 22.49 28.62 21.40 28.62 22.49 28.92 24.81 29.40 12.67 7.63 1.8 -0.7 -1.1 -0.6 -1.7 -1.2 -1.2 0.4 -1.6 -0.1 -1.9 -0.2 -0.7 -2.0 0.1 9.18 26.85 20.99 27.18 22.75 26.77 21.19 24.10 21.23 26.96 22.99 26.99 20.80 27.50 9.68 9.37 26.94 20.84 27.01 23.14 27.02 21.40 23.73 21.40 27.02 23.14 27.01 20.84 26.94 9.37 8] -2.0 -0.3 0.7 0.6 -1. 7 -0.9 -1.0 1.6 -0.8 -0.2 -0.6 -0.1 -0.2 2.1 3.3 8 I - 7.79 12.59 28.92 24.60 28.45 22.55 28.17 21.06 27.87 22.53 28.49 24.85 29.11 12.86 8.01 7.63 12.67 29.40 24.81 28.92 22.49 28.62 21.40 28.62 22.49 28.92 24.81 29.40 12.67 7.63 9 2.1 -0.6 -1.6 -0.8 -1.6

0. 3

-1.6 -1.6 -2.6 0.2 -1.5 0.2 -1.0 1.5 5.0 10.92 28.87 26.97 21.88 26.92 22.36 26.72 22.52 27.06 21.69 27.09 28.66 11.16 10.71 28.72 26.59 21.73 27.18 22.49 27.02 22.49 27.18 21.73 26.59 28.72 10.71 10 2.0 0.5 1.4 0.7 -1.0 -0.6 -1.1 0.1 -0.4 -0.2 1.9 -0.2 4.2 7.87 12.48 26.41 29.28 21.73 28.07 22.82 28.15 21.62 28.81 26.73 12.47 7.95 t 11 7.64 12.20 26 3 '. 29.12 21.73 28.92 23.14 28.92: 21.73 29.12 26.31 12.20 7.64 l I 3.0 2.3 04 0.5 0.0 -2.9 -1.4 -?.7 -0.5 -1.1 1.A 2.? 4.1 >12l 8.06 27.05 26.40 26.88 24.68 26.92 24.45 27.09 26.12 26.95 8.21 i 7.76 27.14 26.31 26.59 24.81 27.01 24.81 26.59 26.31 27.14 7.78 3.6 -0.3 0.3 1.1 -0.5 -0.3 -1.5 1.9 -0.7 -0.7 5.5 I I 8.09 12.59 28.37 28.34 20.67 28.78 28.63 12.41 8.21 13 7.78 12.20 28.72 29.40 20.84 29.40 28.'72 12.20 7.78 4.0 3.2 -1.? -3.6 -0.8 -2.1 -0.1 1.7 53 7.93 11.11 12.56 27.11 12.38 10.71 7.82 g4 I 7.64 10.71 12.67 26.94 12.67 10.71 7.64 3.8 3.7 -0.9 0.6 -2.1 0.0 ?.4 7.98 9.50 7.53 15 7.63 9.37 7.63 I 4.4 1.4 -1.? BURNUP SHARING (103 M4D/KrU) MEASURED BATCH CYCLE 1 CYCLE 2 TOTAL a PREDICTED J-7. DIFFERENCE lI 1A2 17.09 7.01 24.10 BURNUP TILT l 2 17.73 10.32 28.05 !E 3 11.92 11.89 23.81 NW-0.9985 5 4 9.94 9 94 NE-1.0048 SW-0.9980 SE-0.9988 COFI. AVEMGE 10.71 lI 9 I

I NORTH ANA 1 - CYCLE 2 FIGURE 2.4 I BATCH BURNUP SHARING 30,000 BATCH 2 ,/5 i 28,000 E DESIGN / EEi [ EEi G A O O MEASURED / ~~ 26,000 BATCH 3 t 24*000 [ a[~ I y f " 000 ?[' 20,000 . ic - /"

WW e

18,000 Y./ 2 y I 7 16,000 _.3 ,JT 5 Y 1 ~ (E i14.000 7 ~F~ 0 ~ir[ [. l5 b 3[. l $ 12,000 I BATCH 4 4 10,000 _y' l Y 8,000 --.-y 6,000 W l W+ 4,000 W Y - + -' 2,000 +~ E 0 ig 0 2,000 4,000 6,000 8,000 10,000 12,000 i l CYCLE 2 CORE BURNUP (MWD /MTU) I 10

I Section 3 REACTIVITY DEPLETION FOLLOW I The primary coolant critical boron concentration is monitored for the purposes of following core reactivity and to identify any anomalous reactivity behavior. 4 The FOLLOW computer code was used to normalize " actual" critical boron concentration measurements to design conditions taking into consideration control rod position, xenon and samarium concentrations, moderator temperature, and power level. The normalized critical boron concentration versus burnup curve for the North Anna 1, Cycle 2 core is shown in Figure 3.1. It can be seen that the measured data compare to within 25 ppm of the design prediction. This corresponds to less than +0.25% AK/K, which is well within the +1% $/K criterion for reactivity anomalies set forth in Section 4.1.1.1 of the Technical Specifications. In conclusion, the trend indicated by the critical boron concentration verifies that the Cycle 2 core depleted as expected without any reactivity anomalies. I I I I i I I g 11

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O u +r v---r - r t.- :- O e i sije=i=g E=!Ei=E!EEi=i=JM==fse."- #s=-t !M5F IG ~~ n u _=_..r_=--.. ;=: =E1 =.,=._- .. r_.... $m== _ w _a=,=. = :_. u= ~ = - _ - - - -= +-- 1----+ .1 __g_[_,_,_____._,= , _- e g ____l=-.-g_.----,---t +- y t n-3_ _ _, _-- 1=: t= = =:= a E a: __[___..=.I_~__=_= _ *_.6._. ?;; ~ - - + - < - + - .t=;--+ ' -- 1-e y o _.__.-._-..'.'f--~-...;.;g---+- f7 -- d ? -4 O ,_t-+ :-- [.. _ +1 ~E7=1 C i'~C t = f* "* T~-~== ~ '~T~~~-. ~t ~-- N -t- --- g2=.4__ ..a nt t = C "'-"*^' l hy!i=[ ~ r k._ -

  • T

~~55'I* ~ ~~ s

=i= pt=s= _=.te=ts=isr

.=__r_=_=_y_=_==1=== __4_,__.,___. ~ " * ', ' ~ --"--*--f..-*-_- O .---g--- O __ ~ t'~ ;;:--[ 7 ! C t C 1~ U~~~- - 4 _ _.- o -_*;t.__._w._4------ I . - _ _ + ^ -.t . - - - -. -. - ~ - - - 4_--;n.; =,_-_g_7 - _ _ eg - n = :n- ::-~ -- p=]=12.- t_f';- --;. ....g;.e------ . - - - - +;g--- - t - - - ----T --- - - ! ;-~~ ~ { -.. _ _. _. - _.. + _. _ _.. _ _ ._ _ w _.; _.- 4 - g - -+- .__ _. ---I nn.._ _. : C_;t._ L._{~~"4 -+ 12]._.-- ' I."._2_ _$_.[._. . $ --- -j g -._ - _ - - - * - ~ " ' - ~ ~ ~ . I n_"...-- - -b~- o C ~ _ C$-* CO~-- ._,___2_ ~ *~.~.: O O O O O O O O O O O O O N O CC 'W 4 N I w4 p4 (Ndd)NOI1VHIN33NO3 NOH08 'TV3IIIVO I - --^ - - - -

POWER DISTRIBUTION FOLLOW Analysis of core power. distribution data on a routine basis is necessary to verify that the hot channel factors are within the Technical Specifications limits and to ensure that the reactor is operating without any abnormal conditions which could cause an " uneven" burnup distribution. Three-dimensional core power distributions are 5 duermined from movable detector flux map measurements using the INCORE computer program. A summary of all full-core flux maps taken since the completion of startup physics testing for North Anna 1, Cycle 2 is given in Table 4.1. Power distribution maps were generally taken at monthly intervals with additional maps taken as needed. Radial (X-Y) core power distributions for a representative series of incore flux maps are given in Figures 4.1 through 4.4. Figure 4.1 shows a power distribution map that was taken early in cycle life. Figure 4.2 shows a power distribution map that was taken near mid-cycle burnup. Figure 4.3 shows a mal5 that was taken late in Cycle 2 life. Figure 4.4 shows a map that was taken during coastdown operation. Most of the radial power distributions were taken under equilibrium operating conditions with the unit operating at approximately full power. In each case, the measured relative assembly powers were generally within 4% of the predicted values. The North Anna dnit 1 quadrant power tilt anomaly was described in the Cycle 1 Core Performance Report (VEP-FRD-34, December 1979) and in the Cycle 2 l Startup Physics Test Report (VEP-FRD-35, June 1980). Further evaluations of the power tilt behavior during Cycle 2 indicated that the measured quadrant tilt did not I l exceed 1% at full-power, equilibrium conditions. An important aspect of core power distribution follow is the monitoring of nuclear hot channel factors. Verification that these factors are within Technical Specifications limits ensures that linear power density and critical heat flux limits will 1 l not be violated, thereby providing adequate thermal margins and maintaining fuel I 13 l t

I cladding integrity. The Cycle 2 Technical Specifications limit on the axially dependent T heat flux hot channel factor, Fq(Z), was 2.10 x K(Z), where K(Z) is the hot channel factor normalized operating envelope. Figure 4.5 is a plot of the K(Z) curve associated T with the 2.10 F (Z) !imit. The axially dependent heat flux hot channel factors, Fq(7), 9 for a representative et of flux maps are given in Figures 4.6 through 4.9. Throughout Cycle 2, the measured values of F9(Z) were within the Technical Specifications limit. A summary of the inaximum values of all heat flux hot channel factors measured during Cycle 2 is given in Figure 4.10. As can be seen from this figure, there was approximately 15% margin to the limit at the beginning of the cycle, with the margin increasing substantially throughout cycle operation. N The value of the enthalpy rise hot channel factor, F A H, which is the ratio of the integral of the power along the rod with the highest integrated power to that of the average rod, is also routinely followed. The Technical Specifications limit for this I parameter is set such that the critical heat flux (DNB) limit will not be violated. Additionally, the F limit ensures that the value of this parameter used in the LOCA-AH ECCS analysis is not exceeded during normal operation. The Cycle 2 Technical Specifications limit on the enthalpy rise hot channel factor was set at 1.55 x (1+0.2(1-P)) x (1-RBP(BU)) where RBP(BU) is the thimble cell rod bow penalty and P is percentage of thermal power. The RBP(BU) values specified in the Technical Specifications are given in Figure 4.11. Because of the quadrant power tilt anomaly, revised control rod insertion limits were implemented during Cycle 2 initial operation to N preclude violations of the F Technical Specifications limit.6 By operating in accord-6H ance with the revised insertion limits, adequate margin between the measured value and the Technical Specifications limit for F AH, was maintained throughout Cycle 2 as indicated by Figure 4.12. i l 14

I Th6 Technical Specifications require that target delta flux

  • values be determined periodically. The target delta flux is the delta flux which would occur at conditions of full power, all rods out, and equilibrium xenon. Therefore, the delta flux is measured with the core at or near these conditions and the target delta flux is established at this measured point. Since the target delta flux varies as a function of burnup, the target value is updated monthly. Operational delta flux limits are then established about this target value. By maintaining the value of delta flux relatively constant, adverse axial power shapes due to xenon redistribution are avoided. The plot of target delta flux versus burnup, given in Figure 4.13, shows the value of this parameter to have been approximately -0.5% at the beginning of Cycle 2.

By the middle of the cycle, the value of delta flux had shifted to approximately -5%, and then shifted to approximately 0% by the end of Cycle 2 (excluding coastdown operation). This power shift can also be observed in the corresponding core average axial power distribution for a representative series of maps g!ven in Figures 4.14 through 4.17. In Map N1-2-18 (Figure 4.14) taken at approximately 570 MWD /MTU, the axial power distribution had a flattened cosine shape with a peaking factor of 1.124. In Map N1 30 (Figure 4.15) taken at approximately 4,490 MWD /MTU, the axial power distribution l l was peaked slightly toward the bottom of the core with an axial peaking factor of 1.131. In Map N1-2-47 (Figure 4.16) taken at approximately 8,811 MWD /MTU, the axial power distribution was peaked toward the bottom of the core with a peaking factor of 1.132. iI Finally, in Map N1-2-52 (Figure 4.17) taken during coastdown operation at approxi-mately 10,338 MWD /MTU, the axial power distribution was peaked heavily toward the top of the core with a peaking factor of 1.230. The history of P during the cycle can g be seen more clearly in the plot of P versus burnup given in Figure 4.18. z

  • Delta Flux = P -P x 100 where P = power in top of core (Mw(t))

t b t 2775 Pb = power in bottom of core (Mw(t)) 15

I I In conclusion, the North Anna 1, Cycle 2 core performed satisfactorily with power distribution analyses verifying that design predictions were accurate and that the values of the hot channel factors were within the limits of the Technical Specifications. I I I I ' I l 1 l 1 l 16 l l__________..____.______._ _ _ _ _., _. _ _ _. _, _ _... _ _ _ _.. _. _ ~.

W W W M M M M M M M M M M M M M M TABLE 4.1 t10RTH AtalA.Ut4IT 1 - CYCLE 2 SUMMART TABLE OF INCORE FLUX MAPS FOR ROUTINE OPERATICH I I i i i i T I H I I I I i l i l l l lF HOT CHAllNEL F ACTOR IF HOT CHANNEL FACTOR l TILT l l l l l 1 1 I I I a I aH I I I I I I I I I I I I I I I I I l l AXIAL l l HO. OF l l l l l BANK l CORE l l l l T i l l N p3l1 gg l HAP l l % l D I F-l l l AXIALl F 1 l l F lQUA010FFSETI BURHUP lMONITOREDI l tlut1BER l OATE IPOWER l(STEPS)l Z IASSY.I PItll POIllTl Q l ASSY. 1 Pill i AH I HAX. l LOC.l % l(HWO/NTUllTHIMBLES I I I I I I I I I l l I I i l 1 I I I I H1-2-15 1 2/7/80 1 99.0 1 228 11.113 i B10 l Ett l 45 11.762 i P09 I LK 1 1.387 11.00961 SW l 0.1271 300 1 48 l l l__ l i I I i 1 1 1 I I I I I I I i l H1-2-16 1 2/7/80 1 93.5 1 208 11.201 l B10 1 Ett i 46 11.902 l L13 l LM l 1.403 11.01381 SW l-7.2671 349 l 46 l l int I i I i l l I I I I I i 1 1 1 1 1 H1-2-18 12/14/80 1 99.8 1 213 11.124 I B10 1 Ett 1 45 11.776 i L13 i LN l 1.395 11.00971 S14 l-0.5531 570 1 47 I I I I I I I I I I I I I I I I I I I I N1-2-19 12/25/80 1 31.1 1 163 11.210 i K14 l 11N I 30 11.952 l L13 l LN l 1.502 11.01851 EU l-2.9601 809 l 43 I I I I I I I I I I l__ l l I I I I I I l H1-2-20 12/26/80 1 99.3 1 206 11.124 i B10 1 EH l 46 11.796 l L13 i LM i 1.434 11.01441 SW l-1.2501 824 1 45 l l l l l i I I I I I I I I I l l I I tj i tit-2-21 1 3/5/80 1 99.3 1 220 11.114 1 Bio I EH I 46 11.786 i P09 l LK l 1.407 11.01081 SW l-0.6591 1129 I 45 l l 1 I I I I I I I I I I I I I I I I I H1-2-22 1 3/5/80 1 98.5 1 213 11.156 l L13 l LN l 46 11.823 l L13 l LN I 1.416 11.01111 SW l-4.2651 1160 1 41 l 1 1 1 1 1 1 1 1 I I I I i I I I I I l Hi-2-24 13/17/80 1 99.7 1 221 11.114 1 B10 1 En 1 45 11.788 i P09 l HL l 1.407 11.00941 SW l-1.0181 1586 l 44 l 1 - 001 1 I I I I I I I i 1 i i i l l I I H1-2-25 14/15/80 1 99.3 1 220 11.109 i B10 1 EH I 46 11.743 i B09 1 FK l 1.397 11.00541 SW l-0.5801 2511 1 47 l l l l l I I i 1 1 1 1 I I i 1 1 I I I H1-2-26 1 5/5/80 1 99.9 1 222 11.116 I 810 1 EH I 46 11.737 l 809 l EL l 1.392 11.00301 SE_l-1.4981 3277 l 47 l l l l I I I I I I I I i 1 l____l l 1 l l til-2-27 l 5/9/80 l 99.8 l 221, 11.128 l 810 l EH l 46 11.742 1 009 l EL l 1.386 11.00401 SW l-2.3851 3450 1 47 l l 1 1 I I I I I I I I I I I l___. I I NOTES: HOT SPOT LOCATIOH3 ARE SPECIFIED BY GIVING ASSENBLY LOCATIOllS (E.G. H-8 IS THE CENTER OF CORE ASSENBLYI. FOLLOWED BY THE P1H LOCATIOtt (DEHOTED BY THE "Y" C00RDIllATE WITH THE SEVEllTEEN ROWS OF FUEL RODS LETTERED A THROUGH Q. Alto THE "X" COORDINATE DESIGilATED IN A SINILAR HAHilERI. IN THE "Z" DIRECTI0tt THE CORE IS DIVIDED IllTO 61 AXI AL POIllTS STARTIllG FR0t1 THE TOP OF THE CORE. T (1) F INCLUDES A 1.03 ENGINEERING UllCERTAIllTY AHO A 1.05 NEASUREMENT UNCERTAINTY. O H (2) F INCLUDES A 1.04 NEASUREMENT UNCERTAINTY. 4H (3) H1-2-17 WAS A PARTIAL HAP TAKEH FOR THE POWER TILT STUDY. ( 4 ) 111 2 3 WAS A PARTIAL HAP TAKEH FOR THE POWER TILT STUDY.

M M 'M M M M 55 M M M M M M M M M M M TABLE 4.1 (CONT.) l l l l l l T l H l l l l l l l l l l lF HOT CHANNEL FACTOR IF HOT CHANNEL FACTOR l TILT l l l l I I l l l 1 Q l AH I I I I I I I I I I I I I I I I I I i 1 i BANK l CcRE l l l l T l l l H I l l AXIAL l l HO. OF l I NAP l l % l D l E' I I I AXIAll F l l l F I lQUADl0FFSETl BJENUP IMONITOREDI l NUf18ER l OATE IPOWER llSTEPSil Z IASSY.! PINI POINTl Q l ASSY. I PIN l AH l NAX. l LOC.I % ltHWD/HTtt3lTHittBLES l l 1 1 I I I I I I I I I I I I I I I I H1-2-ra 15/22/eo I 99.8 l 21e 11.11C l C05 l EF l 46 11.714 l C05 l EF i 1.415 11.00331 HE l-1.9241 3947 l 44 1 1 I I I l .I I l___ ___I I I I I i 1 1 I I I N1-2-29 I 6/7/a0 1 23.5 1 152 11.249 i elo I EH I != 12.027 i L13 i LN I 1.504 11.01251 Su l-9.135l 4049 I 38 I I I I I I I I I I I I I I I I i 1 1 I to-2-30 16/23/80 1100.2 1 215 11.131 l Bio l En 1 46 11.698 i C05 l EF l 1.364 11.00351 t4E l-3.0961 4490 l 47 l l 1 1 I I I I I I I I I I l l I I 1 1 Hi-2-31 16/24/so I 99.7 1 207 11.196 1 Go2 i FE l 47 11.820 l CCS l EF i 1.416 11.00681 t4E l-7.6041 4525 l 39 l l t91 l l l l l l 1 1 I I I I I I I I I N1-2-33 17/12/a0 1 99.o i 215 11.11e i elo l EH l 47 11.661 l C05 l EF l 1.364 l1.00521 NE l-2.1641 5147 l 46 l 1 001 1 I I I I I I I I I I I I I I I l 141-2-35 17/30/80 l 97.9 l 218 11.147 l L13 l LN l 47 11.653 l C05 i EF l 1.351 11.00621 tJE l-3.4381 5762 1 47 l l l I I I I I I I I I I I I I I I I r. I H1-2-36 1e/11/a0 1 99.a 1 225 11.181 i L13 i Ln i 47 11.677 i CoS l EF i 1.344 11.00521 itE l-5.1941 6338 l 47 l oo I l 1 1 1 I I I I I I I l l l 1 l___ l l H1-2-37 1s/28/e0 1 99. 7 1 216 11.17e i elo l EH l 47 11.651 l C05 l EF l 1.341 11.00421 NE l-5.2271 6791 1 46 l l 1 1 I I I I i 1 l l l l l l l l l t Hi-2-37T1 9/9/80 1 31.9 1 182 11.184 i L13 i Ln i 29 11.790 i L13 i LH I 1.434 11.01521 Su l-1.1201 7325 1 38 I l I I I I I I I I I I I I I I I I I I H1-2-38 19/11/80 l 99.5 1 217 11.143 I elo l EH I 47 11.602 l C05 i EF l 1.336 11.00471 NE l-3.2901 7375 l 47 I I I I I I I I I I I I l l I i 1 I I I H1-2-39 19/13/80 l 98.7 l 215 11.234 l C05 l EF l 53 11.695 l Co5 i EF l 1.341 11.00921 HE l-8.6911 7449 1 47 l l 1 1 I I I I I I I I I I I I I I I I H1-2-40 19/14/80 1 99.3 1 215 11.096 i L13 i Ln 1 46 11.553 i C05 i EF i 1.333 11.00561 NE l-1.0471 7453 1 47 I I I I I I I I I I I I I I I I l l I I N1-2-41 19/21/80 1 99.0 1 207 11.156 i Bio 1 En 1 47 11.625 l CCS l EF l 1.344 11.00651 tlE l-5.2411 7730 l 46 l l 1 1 I l I I l 1 1 I I I i i l i I I H1-2-42 19/27/so 1100.0 1 199 11.251 l C05 l EF l 53 11.713 l Co5 I EF i 1.349 11.00701 ilE -10.7951 7976 l 47 l l l l l l 1 1 I I I I I I I I I I I l N1-2-43 19/28/80 l 99.0 1 204 11.240 l F05 l IN l 54 11.703 l C05 l EF i 1.341 11.00731 ttE l-9.158s 8005 1 46 I I I I I I I I I I I I I I I I I I I (5) H1-2-32 WAS A PARTIAL NAP TAKEH FOR AH I/E CALIBRATION. (6) N1-2-34 DID HOT H AVE THE REQUIRED HINIMUN HUMBER OF THIMBLES.

W M M M M M M M M M M M M M M M M M M T ABLE 4.1 ( CONT. ) I i l I i i T l ta l i i i 1 l l i l i iF HOT CHAHr:EL F AC10R lF HOT CHAtalEL F ACTOR l TILT l l l l l 1 1 I I I Q l AH I I I I i l i l I i l i 1 I I 1 l l l 1 DatE I CORE l i I l T I i i H l l lAX1AL l l 940. OF i 1 F1AP l l % I D l I I I l AXIALI F l l l F l lQUADIOFFSETl BURNUP INCHIT0nEDI l 14 UMBER l DATE lF0WER llSTEPSil Z lASSY.1 PItll FOIt4Tl Q l ASSY. 1 PIH l AH I HAX. ILOC.l % 1(ItWD/t1TUllTHIMBLE5 l l l l l 1 I I I I I I I .I I I I I I l H1-2-44 19/30/80 1 99.9 1 210 11.152 i L13 l LN l 47 11.596 l CCs l EF l 1.334 11.00741 HE l-4.1591 8109 l 47 l l 8781 1 I I I I I I I I I I I I I I I l H1-2-46 11o/17/eol 49.4 1 162 11.173 i L13 i Ln i 37 11.711 l Cos l EF i 1.408 11.01181 HE l-a.8961 e629 I 41 l l 1 1 I I I I I I I I I I I i 1 _l l l H1-2-47 110/22/solloJ.o i 22e 11.132 i L13 1 Let i 47 11.549 i Cos l EF i 1.326 11.00871 i4E l-2.2191 8811 1 46 l l l l l 1 1 I I I l l l l l l l 1 1 I H1-2-4s 110/31/e01100.1 1 22e 11.195 I tio l DE l 53 11.627 i Cos l EF i 1.323 11.00831 NE l-5.7131 9117 l 48 l l l l l l 1 1 I I I I I I I I I I I l H1-2-49 111/18/eo1 e7.o l 22e 11.116 i Cos i EF i 13 11.s22 l Cos l EF i 1.323 11.00721 HE I o.6891 9617 1 47 I I I I I I I I I I I l l l 1 1 I I I I Hi-2-so 111/24/e01 85.9 l 228 11.153 i Cos l EF i 12 11.575 i Cos i EF i 1.320 11.00001 itE l 3.3171 9820 1 47 l l 1 1 1 1 I I I l i I I I I I i ___ I I i H1-2-51 1 12/s/ col 72.s 1 22e 11.194 l Bo9 l EL l 12 11.624 l Bo9 l EL l 1.314 11.00521 t1E l 5.6261 10132 1 47 l e* 1 1 I I I l I l __ _ I I I I I I I I I I I Hi-2-s2 112/11/e01 68.o 1 22s 11.230 1 Bo9 I EL i 12 11.673 i Co5 l EF l 1.311 11.00531 tee l 8.3221 lo33S I 46 l l l l 1 I l I l____ _I I I I I l_' I I I (7) H1-2-45 WAS A PARTIAL NAP TAKEH TO VERIFY THE AGREE ENT BETWEE;4 INCORE AXIAL OFFSETS AND EXCORE AI VALUES. 5

I FIGURE 4.1 NORTH ANNA UNIT 1-CYCLE 2 I ASSEMBLYWISE POWER DISTRIBUTION N1-2-18 P00R MIU w I - = = u ne l n L n J n 4 L U C wegul Cit u I 4.tl. O.47. 6.71 but u t tites =FesuwE7 l =tasu*ca . o.s.. v.wl. v.t.. e.e. +.9

  • .J

.FCI DIF f t=ENCE. .vCI plFFtathCt. lenw. wrea. 1.!w. I.01 0.71 . c.71. I.ul 2 1.to. l.05. 0.75. l.It. v.97. 9.t= . 1.90 I J.7. 5.5. 10. 6.s. -u.# . -u.e. -w.g. O.sl. 1 35 4 1e. b.ws. v.9) l.8%. 9.ws. vevs. . 0.Fl 0.wJ. 0.95. l.19 e.77 3 I.lf. p.w. . v.wt. 1.09 0.fJ -t. 3.

0. 7.

J.0 T.* . -*.s. -J.c. -J.= let d.h. I 0 19. 0.t! . I.ps. l.lu. 8.sw. v.wa. I.Qw. 1 30. 1 05. . o.tl. u.tw 0.#5 0.el 1 0w. 1 00 1.0. 1.hv. l.93 . W.w%. 0.11. v.nh. l.ve 4.( 14 ' e.k. - J. e. -J. I. -J. o. - 1 0 . 45. 1.= l.4 . -u.6. I l.12 0.9e. 1 19 0.w f. 4 05. I.15. 0.71. 3.ls. 10% e.w?. 1 19. v.we. . 0.11 1 45. 1.14 o.sa 3 17 0.95. . 0.93 u.ws. 1 09 1 40 W.%e. 3.th 1.w5 . U.Ft F.o. -J.o. -t.2. -1.5. e.J. 3.% . -t.w. -J.0. u.w. -u./. -u.m. -1 9 6.w. 3.ul 1 03. 1 19 3 3W.

v. 5.

1 02 1.11 1.wJ. 4.li 1.l=. l.1= . 3 03 . v.w%. 1.u5 1 00. 1.87. 1 0e. 0.v5 . 1 13. u.ee. 1.lJ 3.wt 3.lp

1. u s.

9.* . 1.!! J.9

==.4.-J.2.-t.J. -l. n.n -h.7 . -1.= -t.3 . -d.h I 1.> 1.n v.a. I, 0.78 1.19 3 17. 0.9e. 8.uw. 0.93 I.00. l.10 l.It. l.Ju. 3.1,. 4.ws. s.uw. u.we. . o.73 l.I* p.74. 7 1 32. 0.9J. 1 0+ . 0.w3 1 85 v.w7. 3 5%. 0.95. . 0.%e. . u.ve. l.99 . 0 74. 1 24 -*. e. = =. J. - t. e. - I. /. G.4. -J.8 . **.I -*.4 -c.7 . -t.- . -c.h 1.0. -4.a 2.5. 35 I 3.u2. 1.lt. u.ve. 1.83. 0.ba d.pl 0.93. Betw 4 19 l.le. 3.wt 1.a) . J.wa . D.aF . b.4e. e

1. 0 T.

0.9.. 1.30. 0... . u wl 3 13 . v.w9. l.It . 0 91 1.dl 1 11 . 0.a9. 9.ww. 1

1.. v.wa 4.=

=.# -4.8 . -+.2. -t.6 -d.2. -J.J. *J.* -l.J. al.* -l.1 v.7 +J.4 t.5. l.. 4 17. 4 9e. l.ow. 0.ws. 1.lw 0.78 8.pd. 0.99. 1.1/. i.eu. 1 19 0 75. 1 19 . v.w%. 8.pv. . O.ws. 1.us. 0.ws. 3.//. 0.#= w 1 17. D.wi 1 14 t l.ww p.w?. I.le. 9.vM. 0 74 1.d4 . b.wn. -4.4. ~4.9 s.* 5.e. -J.J. -3.1 -1.5. -J.J . -4 4 -1.w l.a. 3.1. -u.o. -1.u 2.5 [ u.ws. 1.ul 1.10 . 1.vJ. 1.lv 4 02 3.11 1.lw. 1.wJ 1.It 0.ws. 1 19 1 01 3.ua le

1. l f. 1 10

. 0.v5 3.1 . 4 00. 8.l>. 1 00 1.48. 1.uJ 3.It I 1.us u.wn. -d.S. -2.2. 01 0.6.

  • .d

. -2.0. -J.4 -t.. l.4. -0.1 19 J.I . 31 3.15. 0.71 0.97 1.ub 1 17. D.we. 1 89. 1.u% 0.wt. 1.tv. u.9a 6.Tl 1 15 1.30. 0.F* 11 0.9e. 1 07 1 17 1.80 0.w3 1.tv. o.wo . 6.we. 4.vM 1 40 b.f. 2.* J.e. -e.1. -J.e. -1 0 -1.1 t.0. J.e. I.e. -u.* . -e.I 3.w. J.h I 0 79 0.11 1 80. 1 05 . c.4m. 1.Uw 0 71. u.Fw I.us. l.au. 3 09 12 0.et. 0.1%. . l.09. 1.0= l.co . 0 94. 1 80 . t.03 . v.75. D.e2. 1.ut S.7 J.6 -J.3. -d.e. -v.$. -0.4 l.e. u.t. -3.4

  • .6 J.J.

0.71. 4 13 0.ws. e.~ws. 3 1% 1.l>. O.ws. 0 9s l u.Il. 13 D.w.. 0.95. 1 17 0.70. v.wt. 1 30 l.co. 0.9= u.7% 3.7. I.5 -d.5. -1.* 0.A. e.t. 3.w. 1 3. -J.3 . 9.we. 3.tv. 1 01 0.71. 1.tw 1.ul 0.71 1.02 0.14. 16 1.!d. . v.e4. 1 19 l.co 0.f= I 07. 15. -1.4 3.w.

  • .e. 02.

0.1 s t e e. c o. e g e s. t e.s s******************71 O.at. avt= AGE 0.74 . o. 3 l 4 vasu .PCI OlFf Eat %CE. 15 u.fi 0.73. o.90. W ylall03 = t.. 01 3.i J.0. l 3,sq l l MAP NO. N1-2-18 DATE 2/14/80 POWER - 99.8% i N l CONTROL ROD POSITIONS F = 1.395 AT L13-LM INCORE TILT g ! E BANK C AT 228 STEPS F = 1.776 AT B10-EN NW - 0.998 Q g BANK D AT 213 STEPS 5 = 1. m E-0.m 7 A.O. --0.553 SW - 1.009

  • Includes uncertainties BURNDP = N570 WD/MTU SE - 0.997 l E i 5 20 l

l'--- _ -.. - -, ~,.

n ucG.,4., NORTH ANNA UNIT l-CYCLE 2 ASSEMBLWISE POWER DISTRIBUTION N1-2-3M I UUH U E1 usHlab _.4 m. .? L E J G .S f. 0..___C

5. __A 0.71 0.87. 0.71 s _ PREDICTE3 _._

~ ~ ~~~', PAEGIC7ED 1 MEASUAE0 alA5URED 0 75. 0.91 0.74 . PCT DIFFERENCE. I '~~ ~ ~ ~ ' ~'~ . ~0 72 1.06. 1.48. 0.97. 1 18 1.00. 0.72. 4.5.

4. 5.

4.0 ...PC7 01FFERENCE.

1. m.....,.

1.04 0.76 2 . 0.75. 1.01 1.13. 0.97 1 19 -5.1 -0. 0. -0. 0... 1._. 0. -34 .,,._____..._......_3.9_._0_6................................................. - -.......... I 1.13. 0 96_. 0.95. 1.16.0.73..__. 0.73. 1 16 0.95 0.96 . 0. 7 S. 1 17 0.95 0.96 1.10 0 95. 0.96 1.11 0.75_. 3._ -2. . -2. 7. - 4 5. 1.2. 3.1. 6.8 2.0. 1.8 0.1 I . 0.73. 0.81 1 05 1.09 1.09. 0.9 9_.l.09.. 1.09...1.05. 0.31. 0.73... _._. _ __... 1.09. 1 07. 0.44. 0.77. . 0.7. 0.82. 1 00 1.09 1.06. 0.96 1.06 4.8. 13. 0.8.

1. 2.

-0. 2. -2. 3. -2. 6 -3.0.

0. 0.

2.0. 3.1. . 0.72. 1.l*. 1.05. C.97 1.18 0.99 1.12 0 99 1.18. 0.97.. 1 05. 1 14. 0.7 2. 1 19. 0. 7 7. S I . -1.0. -1.0. -o.6. -0.. -0. 7. -2.= . -2. 5. -{.2. -C. S. C.O.. 1.2 3.8 . 0.71. 1.13 1.c4 0 97. 1.17. 0.9o. 1.0*. 0.9e. 1.11 0.97. 1 06 . 66... 1.00. 0.45 1.09 1 18 .l.02. 1.16. 1.02. 1.16. l.02. 1.18. 1.09 0.95. 1 00. I G.6 0.o 0.0. -0.7. -1 1. -1.9 . -1.9 -2.1 -1 1. -0.5. -0.2. 1.2. 3.2. ., _ _ _ 6 1.01. 0.9 e 1.09 1.17 1.01. 1.14. 1.00. 1 16 1.01 1.17 1.C9 0.96 1.C4 0.96. 1.la. 0.71._. . G.71 1.1 s. 0.9 o 1.09. 0 99 1.lo 1.00. 1.18. 1 00. 1.lo. 0.vv 1.09 7 . 0.9= . 1.17. 0.71.. 1.06 0.98 1.16 0 95. 1.14 0.96. . 0.7J 1.18 0.96 1.08. 0 96 1 14 -2.0. -1.6 -0.1 21. -0.3. -0.2 -1. 3. -2. 3. -2.0. -1.9. -1.9 -2.3. -2.2. -2.5. -2.9 I 1 12. 1.Di. 1.18. 0.94 1.18. 1.02. 1.12. 0.99 1.13. 0.97. 0.57 0.47. 0.5 7. 1.13 0.49 0.9 $ 1 11. 0.5e. 0.%1 t . 0.s5. G.97. 1.12 0.99. 1 10. 1 01 1.le. 0.93 1 15. 1.00. 1 09 - 1. 6._. _-2. 3 - 2. =... - 3. 0 -2 -2.u. 1 2..

3. o..

. - 2. 5. -C... -0. 6 - 1. 0. .1. 7.. - l. 5_._ - 1. 2 1.09 0.96 1.le. 0.71. 1 00. 1.16 0.99 1.00 1.18 I . 0.71 1.18. 0.96 1.09. 0.99 1.10 0.97 1.16

o. 4 7

_1. I.3.._0. 4 6..l.07. 0.+6 . l.21 0.75. _ 9 0.97,. 1.16 . 0.73. 1.16 0.96 1 05 2.3. -0.3. -0.3. -0.9 -1.5. -2.0. -2.9 -2.0. -2.6. -2.6 - 2. =. - 1. 9. -0. 6

2. 3.

S.O. 1C 1.u0. 09S 1 09 1.0 2.. 1.16 1.02. 1 18 1.00. 0.95 1.04 1 13 1.02..,1.la 1.05 I 1.00. 1.13. 1.01. 1.lo 1.10 0 9e 1.J3. 0.97 1.10. 1.18 1.01 1.13 -2.5 -1.5. -1.2. 0.3 0.7. 4.6... -3.0 -2 6 2.3.

2. 3.

1.0. 0.3.-10. i 3 1 0.72 1.16. G.w7 1.05 1.12. o.99 . G.71. 1.1=. 1.G5. 0.97 1.16. U.99 0.9e. 1.17 0.97 1.C7 1.17. 0.7s. 11 0.96 1.09 1.14 . 0.73. 1.17 1.0o. 0.98 1.8 2.1 s.3.) 2.0. 2.0 1.o.,0.f. J.S _. _-J.7a ;2 d. -2.6,.,-o.,* n-6.3 I 1.05 0.51 0.73 1.09 0.99_._1.09 1.99 0.73 0.81. 1 05 1.09 0.64. 0 77,. _ 12._ 1.05 1 07 1.10 l.0% 0.*S 0.7S. 0.82. l.06 1.08 -3.3. -3.3. -2.2

0. 3.

0.3 3.3 =.7 -0.8 17 1.3. 0.8 r I 1.13. 0.96.. 0.95. 1.1. 0. 7 3.. 0.96 ( 0.73. 1.1=. 0.9) __ 13 0 95. 1.1o. 0.77 0.93 1.10 0.95 . 0.75. 1.18. 0.95 -2.9 -1.5. 0.2. 1.3. 6.7 2.3. 2.9 0.3. -3.S 0.72. 1.00 l.la. 0.97. 1.18. I.00. 0.72 0.74 1.06 1.19 0.97 b.16 1 00. 0.73. le iI _... I

  • 9.. *._6
  • L. t.J. S... -0 3. a -1.5..01 l.3... _ _ _

l Siah0440 0.71 0.e7 0.7%. 6VERAGE b.7% 0.89 0.74 .PC7 01FFEAENCE. 19 l Qivia71Cm . _.1 9, _. 2-2. -1.1. l 5.. .l.3o. MAP NO. N1-2-30 DATE 6/23/80 POWER-100.0% 1.364* AT C5-EF INCORE TILT l CONTROL ROD POSITIONS F = AH t 1.698* AT B10-EN NW - 0.997 BANK C AT 228 STEPS F = l 1.131 NE - 1.003 BANK D AT 215 STEPS F = 7 A.0. = -3.096 SW - 1.000 t BURNUP = s4490 MWD /MTU SE - 1.000 I

  • Includes uncertainties 21

N u _ NORTH ANNA UNIT l-CYCLE 2 ASSEMBLYWISE POWER DISTRIBUTION N1-2-47 3 P00R ORIGINAL 4 P 4 M L E J M r F E D C 8 A PREDIC7E0 PRE DIC7E 0 0.70. 0.06. 0.70 I 7 ASU4ED--. . 0.74 v-0.tO s 0.73. s-- MEA 5URED 1-- .PC7 01FFERENCE. 4.7. 4.7. 4.1. .PC7 01FFERENCE. . 0.71. 0.97. 1 14. 0.97. 1.14. 0.97. 0.75.- - 2 . 0.74. 0.98. 1.14. 0.97. 1.15. 1.00. 0.74 I 1.3. 3.5. 4.8. 4.2. 1.0. 0.4 0.4 ...........................................i......e....sa.......-- 0.74 1.11. 0.9 S. 0 97. 1.12 0.97. 0.95. 1.11. 0.74 .. 0.75. 1.13. 0.95. 0.95. 1.10. 0.9S. 0.96. 1 14. 0.78 3 -.- 2 2 r-2.0.- 0 4 e--2. 0. -2 3. -l. 3.- l. 3. - 3.0. - 6.3 1.10. 1.09. 1.05. 0.83. 0.74 . 0 74. 0.83. 1.05. 1.09. 1.10. 1.01. . 0.7 5. 0.8 3, -1.06 s-1 10 r-1 00. 0.99 -1.07 s-1 10 s-1.07. - 0.8 5. 0.7 7. -- - - 4-1.3. 0.8. 1.3. 0.2. -1 7. -1.9. -2.8. 0.1. 2.0. 3.1 5.3. 1.11 0.71. - -. 0.71. l.Il. I.05. 0.99 1.18. 3.01. 1.14 1.01. 1.18 0 99. 1.05. I 1.18. 0.99. 1.06. 1.16. 0.76. 5 0.70. 1.09. 1.04 0.98 1.17. 0.99. 1.12. 0.99 4.8. 8.0. -1.7. -0.1. 0.4 1.5 . - 1. 4. - 1 4. -0.8. -0. 5. -0.5. -1. 0. -1.9. . 3...........................................................................e............. 1 18. 1.05. 1.18 1.05. 1.18. 1.05. 1 18 1.09. 4.95. 0.97. 0.97. 0.95. 1.09 1.09. 1.17 1.05. 1.16 1.03. 1.16 1.05. 1 18. 1.10. 0.97. 1 01. 6 0.97. 0.95 -1.2. -0 1.- 0.1. 0.4 2.0. 4.1 - ~~ I .--0.2 s-

0. 2. -0. 3.

-0. 8. -=0. 7 .--1 1. -1.1 1.14. 0.70 1.03. 1.19 1.03. 1.18. 1 01. 1.10. 0.97 . 0.'O. 1.14. 0.97. 1.10. 1.01 1.18. v-0..2 w-1 13 s-0.9 6.-l.08,-0 9 8 s-1 15.-l.01. - l.18 - - l.01 1-1.16 r-0.99 s-1.08. 0. 9 S.- 1.13. - C.7 0. 7-0.2 -1 2. -0.9 1.8 -0. 8. -0. 6. -1. 6. -2. 5. -F. 0. - 1. 4. -1. 2. -1. 5. -1. 3. -1 6. - 1.9 .......................................................................................c.................. I 1.01 1.12. 0.97. 0.86 ,-0. 86. 0. 9 7. 1.12 1 01.-1.14. 10S. 1 19. 0.98. 1.19. 1.05. 1 14 . 0. 83. 0.9 6. 1.11 0.99 1.12 1.03. 1 18. 0.98. 1.18. 1.03. 1 11. 0.99. 1.11 0.98. 0.49 8 l -1.5. -1.6. -2.3. -2.0. -1.3. 1.4 3.5 - 1. 5. -2 1. - 1. 7. -0. 9. -0.6 l . -3.5. -0.9. -1.0 l 1 18. 1 01. 1 10. 0.97. 1.14. 0.70. 1.03 1.1R. 1.03 1.19 0.70 1.14 0.97 1.10. 1.01 1.09 0.97. 1.17. 0.74 9 1.15. 0.99 1.17. 1.01 1.16. 0. 99. I 1.t-e--0 8.- -0. 8 ~. - l. 4. - 2. 0. --2 6. -3.7 . -2.0 .--1 8. - -1. 9. -1. 8. -1 2. -0. 0. 2.4. 4.7. 0.72. 1.13. 0.96. 1.08 0.99 1.05 1.18. 1.0 5. 1.18. 1.09 0.95. 0.97. 0.97. 0.95. 1.09. 1.18 1.05 1 18

1. 01 -.

10 - 1 15. - l.0 +. - 1 3 7 - 1.10. 0.96. . 3.99,-0 9 7. -l.10 s-1. L S -.-l. 0+.-l.14. 1 02. 1.1 4.3. 0.5. -0.3. -1.S. -3.6. -2.5. -2.3. -1 0. -0.9. 0.7 1.9. 1.9 I - 0.71 r 1.11-. -l.05. 0.99 e-1 18 -l.0; 1.14. 1.01.-1.18. 0.99. l.05 1.11. - 0.71*. 1 12. 0.73. 11 0.98. 1.17. 0.99. 1.06 . 0.72. 1.13. 1.06. 0.99 1 16. o.?' . 1 10 11 2.5.

1. 9.

1.9. l.3. 0.4. -1.9. -32. -3.3. -3.1 . -0.6. -0.2. 0.8. 1.05. 0.83 0.74 1.10 1.01 1 10. 1.09 . 0.83. 1.05 . 1.09 . 0.74 I 1.04. 0.97 1.07. 1.10. 1 0S. 0.84 0.75. 12 1 08 . 0.75. 0.84. 1.05. e--1 8.- 1.1.. -- 0. 4-. -- 1. 2. --3. 7. -3. 8. -2.4. - 0. 3. - 0.4. 20. 20.-- 1.15. 0.95. 0.97. 1.12. 0.97. 0.95. 1 11. 0.74 . 0.74 0.9S .-0.9 5 -l.13 .-C 75. - - 13 - l . 0.7 5 -. -l. 8 4- -C. 9 5,- 0. 9 3. - 1.0 8 l -1.7. 0.2. 1.9. 19 0.2. -3.9 . -3.4 24. 3.1. 1 . 0.71,- 0.97. -l.14 -C.9 7. 1.14.- 0.9 7 -0 71 v-- - . 0.73. 1 00. 1.13. 0.95. 1.12. 0.97. 0.72. 14 3.1. 3.4. -0.6. -1.2. -1.7 0.0. 1.9. .ee........ee..........eee.e......................--...e...........e' l ..............e- . 0.70. AVER AGE -~ 51a404R0 r o.70. - 0.8 8 .PC7 OIFFERENCE. 15- . 0.73. 0.87. 0 69. l OEv!&710N = 18 3.7. 1.0. -1.8 1.3 44 I MAP NO. N1-2-47 DATE 10/22/80 POWER - 100.0% N 1.326* AT C5-EF INCORE TILT CONTROL ROD POSITIONS F = I AH T l 1.549* AT L13-LM NW - 0.997 BANK C AT 228 STEM F = Q 1.132 NE - 3. M BANK D AT 228 STEPS F = i 7 A.0. = -2.219 SW - 0.996

  • Includes uncertainties I

r

! I NORTH ANNA UNIT l-CYCLE 2 FIGURE 4.4 ASSEMBLYWISE POWER DISTRIBUTION N1-2-52 l P00R D M Na I ~ *J M G p E O C a "6 a P N M L-K PAE01CTED 0 70 0.70 0.8m. PaEDICTED I 1 MEASURE 3 0.73 0.89. 0.73 MiaSuaED 4.2. 42. 4.1 . PCT DIFFERENCE. .PC7 glFFEnfNCE. . 0 71. 0.97. 1.13. 0.96 1.L3. 0.17 0.71 1.01 0.74. ~~ ~2 0.97 l.15 . G.98 . 0 74 1.14. I 4.1 4.7 15.

0. 3.
0. 3. 12 4.4.

0.74 1 11. 0.95. 0.97 1.12 0 97. 0.95. 1.11 0.74 ~~ 3 0 95. 0.96 1 13. 0.77 0.95 1.10. . 0 96. 8 13 0.76 -2.4 . -1.5 12. 2.4. 4.7 . 08. -2.0 2.3 2.6. I 1.05. 0.83. 0.74 1.09. 1.09. 1 10. 1.08 1.10. 0.83. 1 05 0 74 . 1.06. 1.09. 1.06. 0.85. 0.77. 4 1.40. 1 08. 0 99 1 07 0 76. 0.84. 0 1. -2.0. -2 2. -3.3 -0.7 12. 2.2. 4.4., __ 2.1. 1.3. 1.6. 0.99 1.05 1.11. 0.71 1.18. l.01 1.01. 1 14 1.05. 0.99. 1 18 I . 0 71 3.11 0.76 S 11% 1 11 0 98 1.16 0.99 l.06. 1 17. 0.99. . 0 7L 1 10. 1 05 0.99. ~. 4 2.' 7.1. -0 4. 1.0. -2 7 . -11 -2.6 "2 7 -0.8. . -0 2. -0 2. *0.S. -0.5 0.97. 1 05. 1 17. 1.04 1.17 1.05 1.18. 1.09. 0 95 . 0 97. 0.95. 1 09 1 18 1.10. C.9 7. 1.01 1.04 L.17 6 1.02 . 1 14 1 14 1.09 L.17 . 1 04 0 96 . 0 98 I -0.5. 0.1. 22. 4.5 -14 -2.3. -2.4 . -2.6 -0.0. -10. -l.4 0.9 0.9. 1 03 1.17 1.01. 1.10 0 97 1.13. 0 70. 1 17 1 03. 1.19 . 0.70. 1 13 0.97. 1.10 1.01 1.09. 0 97. 1.14. 0 72. "7 0.99. 1.14 1 00 1.00. 1.16 0.98. 1 14. 0.72. 1 13 0.97 1 08 1 9,. -3.0. -2.8. -2.8. -2.7 -2.6 - 2 3. - 2 0. - 1. 3. -0 2. 0.7 al.6

20. -0.2. -0 1 I

1.L2. 0.96. 0 86 1 14 1.01. 1.19. 0.98 1 19. l.04 1 04 l.12. 1 01 1.14 0.96 . 0.86. 1.00. 1 12. 0.99 0 89 8 1.12 1.!! 1 15 1 16 0.96 1 02 3 11 1.12 0.99 . 0.83. 0 96. -2.8 -27. - 1 3. -0. 3. 25 4.3. -2.3 -2.7 -2 5 -2.4 -28 -0.4 -0.5. -1.6 -2 5 1.13. 0.70. 1.01 1.10. 0.97. 1.03. 1.17. I . 1.01 1 17. 1 03. 1.19 . 1 13. 0.97. 1.10 0.70 1 17. 0.74 9 I.10. 0.98 0.99 1.14. 1 15 1 00 1 14 . 0.99. . 1 09 0.98. 1.13. 0.97 0.72 S.E. . -3 1 -1 8 -0.3.

0. 8.

3.8 -3.7 -3.0 -30 -27 -3.0. -1.4

23. -0.L

-0.1 1.09. 0.9 5. 0.9 7 T-1.17 1.05 1.18. 1.17 . 1.04 1 05 1.09 1.18 0.97 0 95 l . 1.10. 0.97 1.01 10 1.03 1.16 . L.14 1.13 1 01 0.97 1.10. 1.17 . 1 04 . 0 99 l -12. 0.7

1. 7.
4. 7.

-3.2. -1.9 -3.8. -3.3 -1.7 -0.6 23. 23. 0.4 I 1 11 0.71 0 99 1.05. L.18 1.0L 1 01 1 14 1 18 1 05. 0.99 0.71 l.11 _, Lt 0.74 1.07 1 14 1.17 0.99. 1.10 0.98. 1 16 . 0.98 0 72. 1 13. 1.07 1.00 2.7. 3.9. 20 . -0.9 -04 -3.3 -3.4 . -3.4 -l.9. 0.6. 2.1 21. 1.6 I 1.05. 0.83 0.74 1 10. 1.09 1.01 1 10 0.83. 1.05 1 09 0.74 1.10. 1 06. 0.86. 0.78 12 1 08. 1.06 0.97 1 09 1.06 0.7%. 0.84.

4. 7.

3.1 06 0.6. -3.6 . -1.9 -1 1. - 3.5 1.3 0.6 . 19 0.74 1 12 0.97 0.95. 1 11 I 0.95 0.97 0.74. 1 11 13 0.78 1 14 0 96 0.97 1.09 . 0.95 0.94. 0.76 1 14 3.2. 4.7. =0.5 1.6. 0.3 -3.S -2 6 33 26 3 13. 0.97 0 7L l.13 0.71 0.97 . 0.96. 3. 0.73 0 98 1 43 l.13 0.96. 0.73 1.00 I 1.4 3.2. 0.5. 0.0. -0.3 3.7 3.3. avfascs 0.70 0.70 0.am . PCT c l a s s a g 4C t. at Sta40anc OEvlattom . 0.F3 0.sr. 0.70 J.1 -0.4 1.9 4.1 .L.370 i MAP NO. N1-2-52 DATE 12/11/80 POWER - 68.0% 1.311* AT C5-EF INCORE TILT CONTROL ROD POSITIONS F = bH T 1.673* AT B9-EL NW - 0.997 BANK C AT 228 STEPS F = Q I 1

1. 2%

E-LW BANK D AT 228 STEPS F 7 A.O. = +8.332 SW - 0.996 BURNUP = N10338 MWD /MTU SE - 1.003

  • Includes uncertainties

I I HOT CHANNEL FACTOR NORMALIZED FIGURE 4.5 OPERATING ENVELOPE I I +4 t..+..+-:t*..**'

+

..o .. - +.. <.... ..U+- '^ . **-.i.f** *- - +* -4 +. t ^ . _ ; g.o. -*. t*** . '*.4. 44 ' L.+w u i, .i - T ...+4+ - L 4 .n

e6.0,1.00'1 w-

+. 4~_+..4,_.+ -4. a + .+.+ -4 o.- 7 +++ o -.+o ..+ 4 +i _ ' 4 o w.+ _--.h y j) 1*0 -A. .. * <..++.+.+ nm .-w + + - q4' + --+ Q* w. w 5

+

..:+++. 3 ., +. w r+.-4. f +++e a.++ ~++e< I E j+.-.+. 1 3

    • +

. +.. + - 1 .4< I + ++

++

1g. -+:,.+.-.. ++++-,+ n+ : 9 +. ..o -.+._ E .+: -- - +.+ + w+ +i - -.. +:. I. + +.. +. + +. - - - +- - .. + ++;:,..--: 1 08 8 .:.++ -.+... :

4 4<

u +e...+w+++.<+ , -. +-+-4..+.<,4..-. +++j +.+. L +. _

+++

++< . +. 1 .+4++.+. I o.++ u.-. +; ^-.+s+.+.++- - - - +.

+_

( .+++ p+++* +.+^ ^ .. + E +.+++ g: ++++.+++ s ++. -- ~*+* e% -o g a $.+.+++.&.. + +. I Q . +.-+ -- '++.+ ^+++; 7 , +.

1. n,44 0e6

.,, ~.,+ .t. . + ,.+++.

.,+

o t.,4 o - '+: .:.+. + .+ - -+.- .. + - - ----+., C g..4..m.+..+_ ~..+++:. -

'I 444

+4! - __+' =. ...+4+. . + -I r ..u ..~1._4. 4.o. g I H .+. 4: g -...., +...., ... _ -.++: =' .. +

  • .4

., j

o. [ _

+. + . _ + . w +.+.**+T

-.4

+.* t**** ti . n -- a

4. -

..~.,e..... 6..... ....+. +. +,, + 5 .....~.1..+.o..o..,~. .. 4 .. +..+ ....+ -.. 2.O,Q.4 ..l...-. . ~..- Q. .g~-_.....,-%.,. o.o. y" .t.. ,_........t .y e ....._!..t..............: -o. c-) .... ~. _.._......... -".L _.t._. ...q + . ~ ~g "g-I ,s ~" ~ ~ ~ 0.4 __.."4."...._-<_. ~...+...4_...1.,.._... 1 . 4.w +. o..-...-e.4..-+-.< . + + < ~.. <,.++....*.

-+

6 ..,,y..e,.4+ ..+. 4... 4,+< 4..+.4 :

  • * + **.

+.4..++<..: 4 4.+++ i ~4o.., t ..-...,.~.._.,. 4.u+..t+.4.++*.,.4, _. 4

t...

.-.o..,... . ~. .......,.4. .4..-. . +. +.4 .........4+..H..4 ~.g+_. ._.4.+. i I -....u...g~. + g +.*+- ++~L-+ ..* +. - ~ + + + - * .--++'-~..-~.*=+**.+44..+...+.---..+F f+ .o.-t. +- ; .+..- .. _.. + . -. +,4 ... + + < 4 +.-- .... +++ +-. :++++ . +.+_ - + ut - e t.+.. o-t - [ ..+.4.....u.-u'

.+

+.a J + +. ++. .++ . + + - .+.+; -- - ..v+ +4 +.n.* o.+ .m..m.+<

<+. 9+. e

-fa

w +..

.+.++.+.4.++t+.-.+ + .w.- . +.. ,. +. 4. 4.. ~m4+m... +

  • T. a.T_ *.**..

o a +. 4+.+. +.++ ...+: .+..;._. 0e2 . ++* _.e..++4 o++ +++ 44_ -+t-.-.4 +4 .-o. ,.++<.o ; ; -. 1

  • + <

...,T***.*... p...*J::.+++++. .+ 4

.--4.

+ +.. +.*.-.+ ,+. nh ~.--4+i ..+*4+ ..i +. 4.++.ua..+o..t***+.-.-.+o. ++ 4.. +. +.. +.,.. + < + -.1 n + + .~.+.I ...++.+4+v +. ... 4. 4 .o ...+l.. .--..++,t-+"; .+......-,..i......+,.4,.o.+4..+. a+.. + w.4 ~...,... + .+..,. ..+.+.4.+.. +;.-... ; 4..-.. .,4.+..&+4. + -. + I + +. - 4.. 4 .- 4 ++ !. +. 4...~em 4 6 6 ~~ ..4..++ .._.$t.A,.+++ .. * ~ - I ..4 + ....++p ..n,.+.,,.4.s.,+....i 4 n ... ~......+.+. * +.+. 1 ,4,+.4..+ .4 ....+.. ,4. 4o........ +4..-.. ..+,6... w k.+.. ..t..-. t 44.. .t... .... +. - * + w +4.4. l ..s..+ ..44..-. . +. t 0 2 4 6 8 10 12 0 CORE HEIGHT (FT,) TOP BOTTOM i l l I I I I 24

,a s NORTH ANNA UNIT l-CYQLE 2 I HEAT FLUX HOT CHANNEL FACTOR, FI(Z) x N1-2-18 I \\ i 4 e I 2.s ~. 7 ~. I 7 2.0 1 i^ W 4M MM W4 IA ,a=a ] q we A 44W4 2

===<=4 ta 1.5 = = Ie C t; sa. I Es3

  • U k

I IE 1.0 e o Ip ~ X t;' i ~ e I< M i i. 0.5 t I I i I i l i 0 k............... I L. 60 50 40 30 20 10 1 BOTTot. AXIAL POSITION (NODES) TOP I I 2"

l I NORTH A' NA UNIT l-CYCLE 2 FICURE 4.7 HEAT FLUX HOT CHANNEL FACTOR, Ff(Z) x N1-2-30 I ,*g l g j j 2.3 l I I j i I I 2.0 I' t l 1 I I l l t il i; xx I l 'N-g= ^ x x d]lt ,j* =, => IY 7 i;- I I' i { = sw

1,(=,:

, x q u x. x = i x x v =,,J. = I = 1.5 g I in ,I<o x A x ll J i x = W g I I i c i x 1.0 ll I=$ x e x "; I l i i. i i li p . x. x l I N l I4

4..

I iI x s j lj j 0.5 l ji ,!l r'. t ! l 7' i l I l I !i i ii i =! t l I i jl

  • i.l

.,t i ' i 8 'l'i i i ) i l1l' l ll .: i i !t

l j

l t I 2j lI', llj j i ! l l gl I,(l !i'i I i' i i ........!....ti.i .: I j i.l..' l l i:l l..!i...i..!..l.l...!.!..!...;.i;:...i..;..l............. O 60 50 40 30 20 10 1 AXIAL POSITION (NODES) TOP I BOTTOM I I 26

I FIGUP*" 4*8 NOR~H A'!N A l'!IT l-CYCLE 2 T HEAT FLUX HOT CHAl:NEL FACTOR, F,(Z) I x N1-2-47 I i l l i i i I I j l i I i l l i I j j 2.5 7 I l l i i i. l i i i i l I l i i t I !.l l l l I h, l l l I ? i i i l 1 i l I I __ _ _ _ i_ _ g I I i l .i l l g 2.0 i i l t I i I, I' I i i i 1 I l I 8 1 + 1 I <s% i i I, l i i i i i i s-i pg i g l i + i 4

x==

m x,- = =, i xxx I=x ,x. i xxx v xx 1.5 l x. xx xx xxxxx xxxxx i Ie l L" ix i j x O x mi i = e t i i x I l l M: O g f [ x N' M i i i t i Ia .8 6 l l I i i i t j i 1 g W x r ,2 .I l l l x i i = i l IO i i, i

1. 0 I

I I I' -8 i e s I 1 O_

  • =

i i x i x t i. i I i l t i l l l M i l i i i o i l ( 6 M 7 l j i i } I l ) i i l l g l 1 l I' 'l 1 l t Ii h 1 i, j I l i i t. I 0.5 7 j i i i i i i i f I l I t i I I i t 1 I i l i 7 l 7.............'......-............ i l 0 60 50 40 30 20 10 1 AXIAL POSITION (NODES) I BOTTOM TOP l \\ I I l

Figure 4.9 NORTH ANNA UNIT 1-CYCLE 2_ HEAT FLUX HOT CHA' GEL FACTOR. Ff(Z) M ur N1-2-52 l l 3.68 I 7 lI t I f I [ i I 2.94 T. I m m N I4 v .i i I Q

==e A j v 2.71 g Io E-U A N f, I= nun u ~ = w Q =m w x x g j 1.47 Ig .= I m=

====, w x= = = x p = l 3 = Ik = M. i W ] I 0.74 I i [ 1 i I i. 0 ......,. 3...,...,......,.............. e -.,... mur 'I 60 50 40 30 20 10 1 AXIAL POSITION (NODES) I BOTTOM TOP I 28 I

  • e--

e w-m m-- m - ww,,-_ww-- e,--,w_memm m _ -n, - - - - - - -, - - -w--

w---------v

M M M M 0 00, 2 t 1 M i m + i l ce 0 M O d p 0 e s 0, ru 0 s h 1 a c e e M M T R E, OTC G 0 r 0 A e M F 0, L 8 )U 2 E T N M t E N / M L A D C l m~ W l Y C M C 0 ( T . P 1 O s U 0 v N 0, P l U l M A R o 6 N N X U R N U B A L U F B l i E T T R M l O O R A O E 1 0 C N 0 l k M 0, l U 3l M 4 M .U. I

1 X

AM n-M 2 0 00, 4~ M I' 3 + M 0 0 0 0 0 0 0 2 0 8 6 4 2 2 2 1 1 1 1 M n b $td ah3o g* $d B s M M W = 1

NORTil ANNA UNIT l-CYCLE 2 FIGURE 4.11 ROD BOW PENALTY ON F H .06 .1 i I f .1 1 .os 7 i i t i l 2 i .04 _.l ..l 1 I 1 l .1 a, r m o m i g.o3 r T a ... jL ..j!I j ' l i lL g j a i 1 l I t' i I 1 ..q. .1 .r g.o2 p.. g 1 o .l. l 3 .[.i m

f. l fl kl..O :).:lj l

O:l. o'a .01 -j /. -1 + 1 r t' 0.0 ,'I l I O.0 5 10 15 20 25 30 35 Region Average Burnup (1000 MWD /MTU)

NORTil ANNA UNIT 1 - CYCLE 2 ENTilALPY RISE IIOT CilANNEL FACTOR vs. BIIRNIIP 1.6 ll } !..! L j!ll } l' !!-': il ! I I l Mi iIi

n

.m t ttt tu tt..;tt ..u.. . m 1:11 - t: I Adjustment due to-; Rod Bow Penalty l.5 ' '..} -. _z6 v o ti d O + 1,4 .g g O g M ) r 4 ..D d 9 G g O 1.3 M u M 1.2 O !!casured Tech. spec limit m m m m m m m i n iiillii n ii n n 1.1 0 2,000 4,000 6,000 8,000 10,000 12,000 CORE BURNUP (!!WD/KfU)

M M M 3 1 4 E M R 0 U 0 G 0, I i i F dj 12 i M ik i i i i } i C 0 l M j 0, b 0 i i 0 i C i } 1 i i M j i 9 i i i I 0 i i 0 2 i 0, ( M E. i i ) 8 U i X i C U f T 1 Y L l M l i / C F I D l M M1 A 3 i i I T P i f ( U i 0 T L i I E s N 0 P i N D v R i U U } 0, U i N T B O 5 6 R i MN A E } U G i B N R_ i i A A i l T i ER i O i I} i T MN N C R i 0 O i. 0 i 0, i i 4 U il M i ii ii. i i i O i 00 i M ) b i 0, i i 2 s i i i M ji i i. ) i d : M t 0 6 8 0 8 6 4 2 0 2 4_ 1 M n$ d:a4b g d % }[;A h ge 5 M M M M

NORTH ANNA UNIT l-CYCLE 2 FIGURE 4.14 CORE AVERAGE AXIAL POWER DISTRIBUTION N1-2-18 I I 1.5 7 F = 1.124 Z I A.O. = -0.5 me. I 1.2 g ( ( 4 MW44 M 444 4 4 44NMY I 4 4 4 4 4 n n a I st a.s 4 20.9 w N IM w A$ = 2 7 o 25 In v = N N O.6 2 IS ee. I am I N i

== 1 i' e l ~ e ) = I 0.3 2 e S I as I =. l O 2......... 3 60 50 40 30 20 10 1 BOTTOM AXIAL POSITICN (NODES) TOP I I 33

l I 1 l NORTH ANNA UNIT l-CYCLE 2 FIGURE 4.15 CORE AVERAGE AXIAL PCWER DISTRIBUTION I N1-2-30 i l l 1.5 7 i F' ' a L.131 E, l lI l A.O. E -3.0 i l i i I t 1.2 ~; = xxx I lx ",' Mi l Ixixxx } x, xi x: x ,x x .c = x-x ! x x x l I x ,I x x 2 x x t g 0.9 i = u x l N i I l l x l I ~ I3 .I C x 5 i. 8 en i N I I i i

  • l l

I

  • 5'a s O.6 i

2, i Ii I

-i

.I -l x I l i t l l I I it 7 ll I i j I l-x: l l t 1 0.3 l' j,l, l i i i 6 ll I i l H i j ii l i 1 i i

}

,i I, il'. I i s l li j l l I*i {1 g

  • l i

l g f

  1. l f

f I' l {! i i i I i i ! Ilt l i i 4

I

'!i i ,... {'.... ..........'.. !. j. .,.....i. ....i..'.....I.i.l......!.l.....l.'.'l.I l I o l i i 60 50 40 30 20 10 1 I BOTTOM AXIAL POSITION (NCCES) TOP I 1 I .I 3' l

_ ~ _ _ _ I NODI'H ANNA UNIT l-CYCII 2 FIGUPI 4.16 COPI AVERAGE AXIAL PCWER DISTRIBUTION N1-2-47 I I i l 1.5 I i I l l l -l l 4 i l i i i i i [ i i

  • A.O.= -2.0 l

i i i 3 ) i l l ~ l i i

  • l l

I i I i i l 6 i i 1 J l i I - l 1.2 i 6 i i l l i i i n 'i l i i l i x I 1 l l l*! l x. xx I !. x * *

  • x :

= = x x xx xx i x xx xx xx l 1 l i x I x x i .x x ,x x l . n u x x i F l I l f*x. i xx x: ) i l l 1 -x I a 0.9 x: x 1 i i l I w l i i i + s l l i 3

1.,

I i l j i ~ l l a i i i Ig i l l ^ i i u: 1 1 i e I x l 8 j l a Z t i i l l' i I v,s,0.6 l i i i i i l j I i i i l N i I i I l \\ I A i I ( x. i i i i i ? i i i 1 I i i i I i i l l [ i l l i i i 7 l I-l f i j I l I f xi i i I i i i i i l i i i l 0.3 I l l t .: i i i l i. 6 l lI i I l' l l j l i i i i i I i i i I j j e i iI l O I 60 50 40 30 20 10 1 ,g , um BOTTOM AXIAL POSITION (NODES) TOP {'I 35

l l W NCRTH ANNA UNIT l-CYCLE 2 FIGUPI 4e17 t i COPS AVERAGE AXIAL POWER DISTRIBUTION i N1-2-52 I le5 I e233 F = Z j I e +8e5

Ae0e

= I I _e. e e g 9 M e M tM I = i e = = le2 M g o e l e M M M M e M M M M M e o I M M MMMM M M M e e at M M M M at m' O M M e M tar im e e M MM MMM I at M M e e M M M e 2 0.9 u w e M N l! M IW wi e e' e e' M 9 M In = M e e g N Oe6 w e. I O M M e w M e I e o e i e Oe3 i w g I e 1 e 1 l 'l l e i e I w \\ o i I f t e. 1 I e e I e U l 0 l I

  • e e e e e e o e eI e e e e e o e e e oe e e e o ee e e e *
  • e es *
  • e ee el e **** ele e o e e e * *
  • 4*

e e' e 60 50 40 30 20 10 1 BOTTOM AXIAL POSITION (NODES) TOP lI l I

M M M M M M M M M M M M M M M M M M NORTH A!RIA UNIT l-CYCLE 2 FIGURE 4.18 CORE AVERAGE AXIAL PEAKING FACTOR VS. BURNUP n[ 1.4 U d 1.3 a i n. d N 1.2 4 g a g - cr - C .i - O. 3 C i O C O 8 1.1 4 1.0 3 0 2,000 4,000 6,000 8,000 10,000 12,000 CORE BURNUP (MWD /liTU)

I Section 5 PRIMARY COOLANT ACTIVITY FOLLOW I Activity levels of iodine-131 and 133 in the primary coolant are important in core performance follow analysis because they are used as indicators of defective fuel. Additionally, they are also important with respect to the offsite dose calculation values associated with accident analyses. Both I-131 and I-133 can leak into the primary coolant system through a breach in the cladding. As indicated in Section 3.4.8 of the North Anna Technical Specifications, the dose equivalent I-131 concentration in the primary coolant was limited to 1.0 p Ci/gm for normal steady state operation. Figure 5.1 shows the dose equivalent I-131 activity level history for the North Anna 1, Cycle 2 core. The data on Figure 5.1 shows that the core operated substantially below the 1.0 L Ci/gm limit during steady state operation (the spike data is associated with power transients and/or shutdowns). T,he average equilibrium dose equivalent I-131 concen- -3 tration during Cycle 2 was 8.9 x 10 Ci/gm which is less than 1% of the Technical -2 Specifications limit. This value is considerably less than value of 3.9 x 10 Ci/gm I that was reported in the Cycle 1 Core Performance Report (VEP-FRD-34, December 1979) The reduction of coolant activity likely results from some of the defective fuel being removed between Cycles 1 and 2. The ratio of I-131 to I-133 is used to characterize the type of fuel failure which is present in the reactor core. Use of the ratio for this determination is feasible because I-133 has a short half-life (approximately 24 hours) compared to that of I-131 (approximately eight days) so that for pinhole defects where the diffusion time through the defect is on the order of days, the I-133 decays out leaving I-131 dominant in activity, thereby causing the ratio to be 0.5 or more. In the case of large leaks, uranium particles in the coolant, and/or " tramp" uranium *, where the diffusion I

  • " Tramp" uranium consists of small particles of uranium which adhere to the outside of the fuel during the manufacturing process.

38

I I mechanism is negligible, the I-131/I-133 ratio will generally be less than 0.1. As shown in Figure 5.2, the I-131/I-133 ratio data points associated with equilibrium operation are generally within the range 0.510.2, indicating pinhole defects. iI Finally, the data on Figures 5.1 and 5.2 indicate that both the dose equivalent I-131 concentration and the I-131/I-133 ratio showed slight increases during the cycle. It is believed that this could have t,aen caused by the core power redistribution (both radial and axial) that occurred as described in the previous section of this report. It is also believed that these data indicate that no new defect events occurred during the cycle and that the original defect (s) did not degrade. I I ~ I [ I I I I l I I I lI

I FIGURE 5.1 I NORTH ANNA UNIT 1 - CYCLE 2 DOSE EOUIVALENT I-131 CONCENTRATION vs. TIME ~ ITECHNICAL SPECIFICATIONS LIMIT 6

  • 1

._.-...t-- r o 0___. 1 = _ s 9.__. l Q,,,, 1- -i4

.3-*

+5 f 4- -di_--- _ = - ' _ i-~f- -i.- pi. - 4 F i-i : ' l - 2 i i-p. d ;=_t :.~ _ _ :.j ;

f. '? _ '_ j L_ -L _ -

I- :- ' t - - 7 __ t -- _ 1-r y i:.-_-i =d- _i r-ist'.jrp : -i' r ; m F_tj hi-i_. :_ = j --j-- 5q_. hry; r-j l 1 j;-- 12 r :- -.. -j_ ::j --_ 7 J-u-==~= .}-- " L=h==- =- - _ _ H i- :_++ - g pi--~ :--- + ::.. _.h-ki _. --~: =- ';i j;. ---- % _ > =. l ---~ n - i i; 7 -- f- , L,_ J_ .p j-- d i- _ 4_. __ _ _i g3 j_ -. s -~ ii 4 A. s g__ -. j --- __ f . 2 2 i -.;_ p._ .ii__ -h j _f y _ :__ z 7.' - E_-3 i f ; L-. fi --yl-j W$ =:

l. 3.j~ - J _:- - -i - i' 2_j'! i-j--i.-. :if_ _ j:1-l_:

i.h.M ^?-

-.i--d;-- pj--H - h 5--i i.

i U1$-I-D b $21i9 N25-h-b3 '5_N'IN NN-sI-h.Y Z- ~'b-' 2- --b2E- -5 h-b;S= ~5 E-J.'--I3-5_^MN-5=-:_. J ~I ANS - --S .--e-- 7 . -. _. - ~ _ + g____ -~ -+ i 1 I^R -1 i i _ 0_ _ _ . c- ;.7 r,,- m- .c, =.,, ' ~- ~ , * ~ ~ 7.~ 5-. b) . p.- .i _

mi ry2 e
g-

-:li 2 g ' - p ._2-L- i_1. -y = _ -i_2_ 422i n-pi _=- d rj-in--c }-i: l

3
_ 2 h_^ -
i.c =;- --@

2".--i. ir..-- .i.;ir p-

-~ ;- p =_ q r

-L. .-1

= y+

_ _ y. _-+-i - ;i - -t2 =i 1,=i_ 5 <.%- _&+; --i:p i. !--a --. --- =.j = p :. --- _:. ;_ i-4=g _. _ _. = -i = i-;=j_:==..i ;+ t lu i m _ s. u ~ m - r.

  1. w

. -.'_ i -i l. z- ~a g i-I 'I ;7 C-: rxI-N5" r:.S-h=$-[-ICl{5-:-N-!~5-- g-- = _: + ~2. N:~NT} ~ ~~ d N'2':I ~ .c vi a _2 r - * = ~. ~5~ g ___ r 1 = -L. _ =j - V _ f _i ' E ~~ k. ~--k L ^3^S. i .2 :- N--:= ti h T-5 ^-5_$ :t-S'= -F-

L =:~ ^

.5n ~- H

1. i- - f-i

~~ i _~ " - - ~ - 1 ^ r O h .:.... p - c _- - " _ g. } 'h :n.-Q_-i - _-E y j 'z.: ~_.21-j 2_- ~ 'i' 3:j -g _.' : H _: iR J.:x :-~ -- _ _ ci}i i-p. G -'; 3-I ii-y._ .9 Q. 3 ~N~:b~5 ~1-5'NI=I-f~~~ 5-~ i D i:2 2-N 2 := ?i~'5 'd E' h 2.' hd -.-- 5_: ___.ND. '.~ ~ 5 ~~7 -J ;^ l 2-b l'~ - 5' 5~ - I

= : :-- =- - h=.--_--_=_q
r. _ __._ r- - =a -o =__=_ :-

==_

u.- _

,__.__ = =:=:- _. = m .--.--_a. w. u , lO ~ r-o - ~ o m -4 l i +--~-w-*-- or .i i o ro-S-Ce@*b b',h n. C l I N 4 t,0.. - j. 3 Oa 1-..%- i tO - 1; +! o - _ ww. m a e oc; ' 6 . y; a 3 I l

.e g
7. i- ; # - j

&_--.Tr 9 ~@g. 7 I g[ 7 1 J-M p=-i_:

2 4:j li_ kr

, 4. ; Wp; A _ _ - a i_,. :2.jiW-j q

h~ +-i. - r

- :== =i ===== t === -iW-t 174- -r--i== _i-i+ k=

+

l i;

==-r==:*4 =. i== :=H..e ? -

  • d =. =. i--Wa =-

tl e_ ~ + --N

  • N

'-8"*'N-*>*-- w.-*-% --*4 yyi -g,,- a l-l Q ~~~ 4y 2 e i -;. ,ia , _t-: 1 w, a (_ 1 H i-

, 7=

z-j i _s =p.-y 1 - 3 &= -. _ _ + = a . - L.a i;+ -. m - i=1 ..t i; =i-.--=. ; m _..

.=_ -ia.

~ i--k + :gs.u = + =_= - =iry= tm=, g l O ~ =- F - h +: L.= .+ ' -- i-_+& ^~ :i:

^i&.i. Li.1--i+ t ;& :.1 '-i:- - r -

^ r_=-t O' 3-- l m z=: 4:==.:_ _=:- =-+ ^ ~ -- ' ~'

t---

lw t-- T -.u.=-=

=. --
-{*= =:- -

-- - - - -~ - - - - ' ~ - - - - ' - - -#T----------~ ^ M 2 _ O t - - - - - - - - - - - - ~ * - - - t + ~ " ~ ~. ....s.-._-. ._.-_3 .--..J .__.,-,-_4.-.--._-. i i I 1 N = I -.-='.=a.9 =m- ^ W ____,_[.. y r.. v c-. . : ? i.

-i

=<-,i_ = - . s _c T y .. k.j cy, _n_- -:- --l-i -i s - m 1 _ _n Li s .ga .2-. r z a _.2. E _- 4 4 g f -L-%. .~.==--i.-~.i-=_=--,. -1: : a i - ~l ~ 1 -=- ^.:-

=i-h- i :

= =.. =

"i i l=13i-# ' i ri= ='- -1 Q : -i : _ r :-; = f q &-l: i.. i 2 -.ilpi' j gj -i ~.j; 1 - ^ r i-- c f.a. :.} i. p-a p- ; ;.- _ #-i-- jj :2-r.iw.iJ.~. y 2, , : - i-p_4. p L r -- - - g:_c z-d.-5:3 'i - 5 n I Ni-IN2m - - it h -i--N=_---F_E-- ~A_~=~-Nh :N N h-N I'd 42 E{=~2 --N : $ht~l'~ hN y s w - - u

m. y a

a- +- -u - n t ;_ 4 4. 2 4. -y 4 - r. y i; i 4 e_ ri . q=%t42.0 ir? M- -! _i_ _j :da g

-_t,-

. _ _r ;_. _-L1

j_ j e.=

i -i _ _.i_&_- . _i.r i _: s_ ; :::15 2__._-r--* -[._;-_ u i _ := = =_ g'.. ~_: = :: 55_ 9 5.-5 lm ' - ~ ' - ..k.... H - U-g: p.;-\\ ~ ~ 1_' 100 an=.m -- --- ~ + P.E F q-- n b= 1 nt : .i ^ -m:_. 1 - w 7 g p_.,.,- Z J h. \\ ~ x.. r-50 . 2 Ie m ^ i._ .g..__ H. _;J =.. = ^

3.

n W 3 Q

.{

m.. +~ ""i 'Y=* ~ ~ ~ ~ ' ~ '~~; ~ ~ ' - b O JAN FEB MAR APR MAY JUN JUL ACG SEP OCT NOV DEC I 1980 40

g FIGURE 5.2 3 NORTH ANNA UNIT 1 - CYCLE 2 1-131/I-133 RATIO vs. TIME - -, =.. _. -..._--.-_--..a I 2 _. 1

p 3___

m L T I I V I I f , *s I i C i i I I i i i a i } t t } 8 1 8 ! 8 !i t a + ! i t j i ,i. ..ii

,i i i

j iii, i i,i .ii, ,,iiiii,i I O ii.,,iii, e, i i, 3 I 10 -- 4g-pi+ia =

-+;:f n gg

' i i lii a i! 'l i 8 ' i t i i ri' l __ m., c u_: t-i gn=r:*r - -- "_m i. + + r.' _ _. _ - _ _ _______.y=_,_ =-+=_' s __. n = n 4 =5 = : : 9,, 8.. ~~.~=. --. -- __.-.p=~--*_ _ _. 7.._. - _ -. _ - *. = _ ~ - - _ - * -.. _ -, -. _ -, --_-g-__=.=a I 7__ T ---+,9 v 6._ ~ - _ _. _ _ _,.~ -_z m. - m 2 IPIN H0LE 5.. =;- _...==__a w--- .. = = _ =1 : =1. m+=. =.._.-.:...=..u =

.. ::==. y:: a.. a.: a__

=._a. _--. _ __ _. w_ _ 4%.y- _: _:__ ......c._a..____-.- 9 = w_ r111

=-z E==__ -_4,.... _. _ _ _, __-___.::_
r

. =.. _ _. t_- 7, _._ J _5 --,__._4 __.__--t-3e _. =*=w=- i 4_, ,_ g.. - m :+ _ m ' n I e_ ^ 3.- __. '- e e 2 e m I i >e N 2__ r ee m w 1 m_ i I i i LARCE LE AKS , ",k . i iii i i i. f I i i IAND/OR 10 - i 1 RAMP URANIUM 9-N"~! ? ~- 3_M'D' _~ ~ ~ ~ i r 21 ZT- ~ ~ ~@~ " i~ ZZ $ - ~ ~ ~ 8. = ^ " = z_-

7. %_

I 6.. w 5 I ~ . - _: e_ ;. 4.. _=_ _n _ t. e=.. :_........__-_.*.-__-_._23.;=.. m __..--.1_--__:j- =. -.. _.t -=~:- - - - - - -. = _ = - - - =

==_---. :- - s===-- 4_ =_.=._----:._:==__:_:.t=__=_=___.=--=:_._.-.__t-=--_=-_==.=-:----:==-._-._=====..-- - - - -.=_. n - - - + +._- 3. i i I i I L T T l 100 ,l [^ ,4. .M 4,__, A 4 i. ---*~:R .L.,___ u -r n n . -...=__. g.

~N

-a + s 1 .3 1 I g._.__ ce 50-n.-~ *. g . _ _ _..l _r .rth 1

_n-2 m --~$ ~-

=t==. 7

.

o I JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1930 41

I Section 6 CONCLUSIONS The North Anna 1 core has completed Cycle 2 operation. Throughout the cycle, all core performance indicators compared favorably with the design predictions and all core related Technical Specifications limits were met with significant margin during full power operation. No abnormalities in reactivity or batch burnup accuinulation were detected. The analysis of radiolodine data for Cycle 2 indicates that there are pinhole leaks in the fuel cladding, which were probably carried over from Cycle 1. Ilowever, based on the coolant activity level and the inability to observe any fuel defects during the refueling shuffle, it is concluded that the fuel defect level was low. l l I I 'I I \\ 42 l

REFERENCES 1) T. J. Kunsitis, T. K. Ross and J. H. Leberstlen, " North Anna Unit 1, Cycle 2 Startup Physics Test Report," VEP-FRD-35, June,1980. 2) North Anna Power Station Unit 1 Technical Specifications. 3) T. K. Ross, "NEWTOTE Code," NFO-CCR-6, August,1978. I 4) R. D. Klatt, W. D. Leggett, III and L. D. Eisenhart, " FOLLOW Code," WCAP-7482, February,1970. 'g 5) W. D. Leggett, III and L. D. Eisenhart, "INCORE Code," WCAP-7149, December, ,g 1967. 6) Letter from C. M. Stallings (Vepco) to H. R. Denton (NRC), Serial No.116, March 11,1980. I 43 -}}

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