ML20101U188

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Rev 0 to NE-895, North Anna Unit 2,Cycle 9 Startup Physics Tests Rept
ML20101U188
Person / Time
Site: North Anna Dominion icon.png
Issue date: 06/24/1992
From: Banning P, Hoffman E, Main A
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-453, NE-895, NE-895-R, NE-895-R00, NUDOCS 9207220274
Download: ML20101U188 (58)
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{{#Wiki_filter:' T VIHOINIA,I$1.ECTit!C AND POWEH COMl'ANY Hicnwoxu,Vinoixir count July 16, 1992 U.S. Nuclear Regulatory Commission Serial No. 92 453 Attention: Document Control Desk NA&F/EAH/EJW Washington, D.C. 20555 Docket Nos. 50 339 Ucense Nos. NPF-7 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPAt[Y MQBTH ANNA POWER STATION UNIT 2 CYCLE 9 SJARTUP PHYSICS TESTS REPORT. As required by North Anna Technical Specification 6.9.1, enclosed are five copies of the Virginia Electric and Power Company Technical Report NE-895," North Anna Unit 2, Cycle 9 Startup Physics Test Report." This report sumc.iarizes the results of the physics testing program performed after initial criticality of Cycle 9 on April 22,1992. Very truly yours, d tt f W. L Stewart Senior Vice' President - Nuclear Enclosures cc: U.S. Nuclear Regu'.atory Commission Region 11 101 Marietta Street, N.W. - Suite 2900 Atlanta, GA 30323 - Mr. M. S. Lesser s NRC Senior Resident inspector North Anna Power Station V d u: la 920722o274 92o624 PDR ADoCK 05o00339 P PDR

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1 TECilNICAL REPORT HE-895 - Rev. 0 NORTH AhNA UNIT 2,-CYCLE 9 STARTUP PilYSICS TEST REPORT ( f NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER JUNE 1992 N' [ 23k2 ~ PREPARED BY: m-E. A. Ildffman Dace REVIEWED BY: d 3dR+m% 6/J3)32 P. D. Banning d Date REVIEWED BY: L d')M-f6 'A. P. Main ~ Date

  1. 2 APPROVED BY:

D. Dziatfosz V Date QA Category: Nuc. car Safety Related Keywords: N2C9, "'.artup _1

5 CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whc.tsoever, express or implied, as L to their accuracy, usefulness, or applicability. In particular, THE Q COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR 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 aucharize its use by others, and any such use is expressly forbidden except with the prior writt m approval of the Company. Any such written approval shell itself be /.eemed 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, tort, warranty, or strict or absolute liability), for any p:;operty damage, mental or physical injury or death, loss of use of property, or othar damnge resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techn iques, information, or conclusions in it. s NE-895 N2C9 Startup Test Report Page 1 of 55

l-o e .i TABLE OF CONTENTS 4 PAGE a si Classification /Disclaimcr............................... 1 Table of Contents...................................... 2 3 List of Tables........................................ 4 List of Figures......................................... g Preface................................................. 5 Section 1 Introduction and Summary................... 7 ~ Section 2 Control Rod Drop Time tieasurements......... 16 Section 3 Control Rod Bank Worth Heasurements........ 21 ~ Section 4 Boron Endpoint and Worth Measurements...... 26 7 Section 5 Temperature Coefficient Measurement........ 30 m Section 6 Power Distribution Measurements............ 32 Section 7 References. 39 APPENDIX Startup Physics Tests Results and Evaluation Sheets........................ 40 NE-895. N2C9 Startup Test Report Page 2 of 55

F h LIST OF TABLES TAB 12 TITLE PAGE 1.1 Chronology of Tests................................... 10 2.1 llot Rod Drop T ime Summary............................ 18 3.1 Cot. trol Rod Bank Worth Summary........................ 23 4.1 Boron Endpoints Summary............................... 28 5.1 Isothermal Temperature Coefficient Summary............ 31 6.1 Incore Flux Map Summary............................... 34 6.2 Comparison of heasured Power Distribution Parameters With Their Technical Specification Limits............. 35 HE-895 N2C9 Startup Test Report Page 3 of 55

e o LIST OF FIGURES w~.s, FIGURE TITLE PAGE 1.1 Core Loading Map......... 11 1.2 Beginning of Cycle Fuel Assembly Burnups................. 12 1.3 Incore Movable Detector Locations....... 13 1.4 Burnabh Poison and Source Assembly Locations............ 14 1.5 Control Rod Locations............... 15 2.1 Typical Rod Drop Trace...................... 19 2.2 Rod Drop Time - Het Full Flow Conditions................. 20 3.1 Dank B Integral Rod Worth - HZP.............. 24 3.2 Bank B Differential Rod Worth - HZP.................... 25 4.1 Boron Worth Coefficient.................................. 29 6.1 Assemblywise Power Distribution - 30% Power.............. 36 n ~6.2 Assemblywise Power Distribution '/3% Power.............. 37 6,3 Assemblywise Power Distribution - 99% Power.............. 38 !!E-895 N2C9 Startup Test Report Page 4 of 55

L PREFACE The purpose of this report is to present the analysis and evaluation of the pl.ysics tests which were performed to verify that the North Anna 2, Cycle 9 core could be operated safely, and to make an initial evaluation of the performance of the core. It is not the intent of this te particular methods of testing or to present the h report to discuss detailed data taken. Standard test techniques and methods of data analysis were used. The test data, results and evaluations, together with q the detailed startup procedures, are on file at the North Anna Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief sumesry of each test, a comparison of the test results with design predictions, and an evaluation of the results. The North Anna 2 Cycle 9 Startup Physics Tests Results and 3 Evaluation Sheeta have been inc?uded as an appendix to provide additional information on the startup test results. Each data sheet provides the following information:

1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test.

These sheets provide a compact suma ary of the startuo test results in a consistent format. The design test conditions and design values of the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Powar's 1 Nuclear Analysis and Fuel Group. During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were NE-895 N2C9 Startup Test Report Page 5 of 55

i l met and to facilitate the preliminary comparison between measured and g predicted test-results, thus enabling a quick identification of possible problems occurring during the tests. . 4 C 6 NE-895 N2C9 Startup Test Report Page 6 of 55

I SECTION 1 INTRODUCTION AND

SUMMARY

On February 26, 1992 Unit No. 2 of the North Anna Power Station was shutdown for its eighth refueling. During this shutdown, 75 of the 157 fuel assemblics in the core were raplaced with 60 fresh fuel assemblics, 2 once burned fuel assemblies, 9 twice burned fuel assemblies, and 4 thrice burned fuel assemblies. The niath cycle core consists of

  • 1 sub-batches of fuel: four once-burned batches, two from Cycle 8 (batches 10A ~and 10B), one from cycle 7 (batch 9A), and one from North Anna 1 Cycle 4 (batch N1/6); four twice burned batches, two from Cycles 7 and 8

. (batches N1/10A and CB), one from Cycles 3 and 4 (batch SA), and one from North Anna 1 Cycles 7 and 8 (batch N1/9B); one thrice burned batch from n North Anna 1 Cycles 5, 6, and 7 (batch N1/7); and two fresh batches (batches 11A and 11B). The core loading pattern and the design parameters for.cach batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The incore instrumentation lor.ations are identified in Figure 1.3. Figure 1.4_ identifies the location and number of burnable poison rods and source assemblies for Cycle ~ 9, and Figure 1.5 identifles the location and number of control rods in the Cycle 9 core. On April 22, 1992 at 0038, the ninth cycle core achieved initial criticality. Following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the results of these tests follows: NE-895 N2C9 Startup Test Report Page 7 of 55

1. The measured drop time of each control rod was within the 2.7 sec_.id limit of Technical Specificaticn 3.1.3.4. 2. Individual control rod bank worths for the control rod banks were measured using the rod swap technique

  • and were found to be withit.

8.5% of the design predictions. The r.um of the individual control rod bank worths was measured to be within 1.1% of the design prediction. These res u'. ts are within the design tolerance of il5% or 100 pcm for individual bank worths (110% for the rod swap reference bank vorth) and the design tolerance of 1107. for the sum of the individual control rod bank worths. 3. Measured critical boron concentrations for two control bank configurations were within 43 ppm of the dcsign predictions. The ARO result was not within the design tolerance of 32 ppm, but met the Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 11% Ak/k of the design prediction. Further analysis was done to evaluate the impact of the boron misprediction on the safety analysis'. The safety analysis was not affected by the boron difference. 4. The boron worth coef ficient was measured to be within 0.7% of ti.e design prediction, which is within the design tolerance of 110%. 5. The isothermal temperature coe f fi cient for the all-rods-out configuration was measured to be withir. 0.67 pcm/'F of the design prediction. This result is within the design tolerance of 3 pcm/'F. The measured temperature coefficient of - 1. 75 pcm/

  • F NE-895 N2C9 Startup Test Report Page 8 of 55

meets the criterion of Technical Specification 3.1.1.4. Technical Specification 3.1.1.4 requires that the moierator temperature coefficient be less than +6.0 pcm/*F. When the Doppler temperature coefficient and a 0.5 pcm/'F *incertainty are accounted for, this requirement is met as long as the isothermal temperature coefficient is less than +3.75 pcm/'F. 6. Mode 1 (See Reference 4) core power distributions were within established design tolerantes. Generally, the measured core power distribution v.;s within

1. 87, o f the design predictions.

The heat flus hot channel factors, F-Q(T), and enthalpy rise hot channal factors, F-DHfM), were within the limits of Technical Specifications 3.2.2 and 3.2.3, respectively. In s u mn.a ry, the startup physics test results were acceptable. 3 Detailed results, together with specific design tolerances and acceptance 1 criter!s for each measurm ent, are presented in the appropriate sections of this report. s h ( NE-895 H2C9 Startup Test Report Page 9 o f 5:.

\\ ~ I i s c. ' }' ,. y 1 Table 1.1 NORTil ANNA 2 - CYCI.E 9 STARTUP PilYSICS TESTS CilRON01.0GY OF TESTS l. Referente I L - - Test Date Time Power Procedure Hot Rod Drop - Hot Full Flow 4/21/92 1100 llSD 2-PT-17.2 Zero Power Testing Range 4/22/92 0102 HZP 2-PT-94.0 Reactivity Computer Checkout 4/22/92 0128 HZP 2-PT-94.0 Boron Worth Coefficient - ARO 4/22/97 0430 llZP 2-PT-94.0 Boron Endpoint - ARO 4/22/92 0431 IlZP 2-PT-94.0 Temperature Coefficient - ARO 4/22/92 0442 IlZF 2-PT 94.0 Bank B Worth 4/22/92 0542 fi~ P 2-PT-94.0 Boron Endpoint - B in 4/22/92 0542 HZP 2-PT-94.0 Bank D Worth - Rod Swap 4/22/92 1119 HZP 2-PT-94.0 m a Bank C Worth - Rod Swap 4/22/92 1156 ilZP 2-PT-94.0 Bank A Worth - Rod Swap 4/22/92 1224 HZP 2-PT-94.0

  • a" Bank SB Worth - Rod Swap 4/22/92 1244 IlZP 2-PT-94.0 Bank SA Worth -: Rod Swop 4/22/92 1311 HZP 2-PT-94.0 Flux Map - P 5 30%

4/16/92 0427 30% 2-PT-21.1 Flux Map - 50% 5 P 5 75% 4/27/92 2230 73% 2-PT-21.1 t,, ' Flux Map - 95% 5 P 5 100%' S/01/92 0820 99% 2-PT-21.1 c ,e .h A 'o W*..y I ?. 8 f' NE-895 N2C9 Staitup Test Report Page 10 of 55

n -Figure 1.1 NORTH ANNA WIT 2 - CYCLE 9 CORE LOADING MAP R P 4 M L E J H S f ( D C s A l'9s I ht/7 i ss ( i 121 i G26 i xsa i 1 1 1 i i IN1/ leal sa i las I las i 11s 1 5/ int / leal I x12 1 554 1 6tt i v43 1 4t1 l 346 I te3 1 2 I I t I i 1 1 (_ I 9s i 11a i Its i les l 11s I tes i its I tia l 9e i i x23 1 2L7 I tte i v55 i SL4 I v46 1 3t2 i sta i v26 1 3 l_ l__' I li l_ II I I 98 1 los I las i lea i 11a i les I sta i lea i Its i !ss t 9s I l x27 1 v34 1 5LF 1 vl6 l all I v51 4 3L4 i vl4 1 6L 4 l v58 1 X25 1 4 .) I i. l. 1 l 1 l 1 l _ _l, 1 int /16al 11a l Its 1 les i Ina i 154 1 114 I.e4 l 1:a i los i its 11A lut/ leal I ass I su 1 6L3 I vel i ILS l ve9 i FL5 1 v17 l 2LP I v53 1 4L6 I sta l mar 1 5 l__I_ i __ I I l_ l i I I I I i ha i lin i tsA i 11a i 144 I los i Isa i los I tea i Ina i lea i tai i sa i l $s4. I ett j Y24 ) IL9 i v25 I /44 I v21 l v64 l v10 l Its i V03 1 5Le I sie i 6 l __ _ f. I I I I l., i I I I l l i I bl/ Sal 116 1 los I tia ! tea l los I tea i 11a i lea I les I loa i 114 6 les l Its t 96 i j %4 1 6te i v31 1 4to I v2e Iw r e ILS I vil i 161 i Y27 1 2ts i vu 1 4t3 i x34 l 7 l_ l 1 8_ l_ l _.1 _l_ l ___ i

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I I I I I i win i los i las I los I lla i lea. Ita I 94 8 11a 1 lea I 11a i los I tas I w!/6 8 min

  • I caz 1 vee I 6Le I Yu I R7 I..a ! IL2 I nos I st2 I vo5 1 It6 I v% i ett i F s4 i G27 \\

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a i i i I I~ i 1 I i 1 i l 1 1. I l 5A t its I tea 1 114 l 1oa 1 tot i tea 1 tes I !sa i 11a i lea i las I sa j i s49 I 6L6 I vet i 2t9 1 v26 1 v50 I via 1 v59 l vo? I 2L3 i Y22 1 5L5 I s52 I to - 1 1 1 _l i I I _. l __ l.. l l_ 1 I I IN1/ leal lla I its i 10s i lla i 10A l 11A ( 10m i 11A i 16s l 11s i Ita IMn'eal l I E49 ' 21 6 l SL3 1 v62' l 3L6 ) Y19 l eL9 i Vis l SL9 l v31 I bl5 I Ill i KIS I 1 '. f., __.__. I I I I 1 '__ I l. I I i 1 I I9 i los I las I tea i 18A 19s i lla i lea I its I its t 9a I i x31 I v53 1 4L5 I Y2n i IL7 L v57 I sta i v78 1 'L7 1 137 i K37 1 12 9a 11a 1 its e its 10s !!s W 94 l x52 l IL4 1 5L4 1 V29 l 4LZ l v54 1 6L7 l 2La I x4% 1 13 I I l I i l i 1 -1 1 IN1/neAl ha i its { 19s 1 11s l SA IN1/19al i Kll.8 $37 I 5L1 i V44.I 5t9 I S35 I s46 1 14 ~ 9a ML/7 l 9s ! i l--> sATCH I x24 i G46 l x39 l 15 4 1 4 AS$tM6LY 10 l i l 1 1 i FUEL A$5EMsLY DE5!GM PANAMETERS $Us sATCH -8 ML/6 Ml/7 N1/9s h1/18A 54 9a 9s 16A les l 11A Ils INITI AL ENRICHMENT 3.59 3,64 3.99 3.s8 3.59 3.se 4.61 3.99 4.21 4.s2 4.21 (W/0 U-2351 s#*0P At s0C 9 1253 29676 3/675 35 % 9 %153 23847 37191 23953 23752 0 0 (MwS/MIU). AS$3 sty IvPC 17 17 17xl? 17a17 17 17 17xlr 17x17 !?x17 17x12 17x17 17x17 17X17 NUMsER OF AS$fMA(IES 1 4 1 8 4 1 15 24 31 32 26 FUEL ROOS PfR ASSEM6tv 264 ] 2M 264 264 264 264 264 264 264 264 264 e NE-895 N2C9 Startup Test Report Page 11 of 55

0 -) I Figure 1.2 .o. NORTH ANNA UNIT 2 - CYCLE 9 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS o R P N M L E J H G F [ D C S A 1 x21 i cza I xsa i e' i saSa31 2983al 3A75el 1 W. d I 1 I I I alz l 554 8 6L1 I Y43 1 4La i 546 I me3 i l 351741 %1191 el 241a91 el.%2961 359351 2 __.) i I i l 1-I .I i uts I it? l Sie 1 v5s i St4 I v46 i $tt I sta 1 x16 l l 3n341 el el 1913el el 164%l el el 351971 3 I I I I I i i l i i I x27 l v34 l SL F 1 Y16 l IL3 4 v51 i SL4 i V14 1 6L 4 i v5a f x25 l l 3 %77! '9121) el 241641 ul 231831 el 251021 91 197491 Su 211 4 ~ L OTl EI T45 vt9 iL5.l YJ 7,1 2LZ.l Yb3,50, 3L1.i 35,%i 4 804 5t5.i ei 235..i e i m..I m i 24 4 i i 23 ei s i 3575,i i_ _i i i i i i i __ i .i i _.. i _i __ i I h04 14L4 4 Y24 1 3L9 l Y25 1 144 1 Y21 1 V44 I Y19 8 ILS i 102 i $La i Sie 1 1 365a61 61 252361 91 221786 246181 2;2841 246041 216311 el 251221 01 M0231 6 I l i l l__ l l l 1 i 1 i l i lJ4 1 6La I Yh3 4 4Le i v2e i v63 i ve/ I Ita I vil I i6t i v27 l 2ta ivw l 4L3 l x34 4 I 376751 Ol 191%l 91 243911 241341 22363) el 222931 23545l 242951 el 192491 41 345021 7 I l_. l I l I i l i l l__ _ f l__l l 8 l G02 1 v60 1 6LS l Y35 1 5t? l Y13 I IL2 1 XO9 1 3L2 i V05 l IL6 lY% l 4L6 I f 06 i G27 l l 301841 197%I 01 238961-el 242641 01 236471 %) 246371 91 234541 0' It?331 292L'l 8 1 l_ l._) 1._ l I I I .l _ l. I lI l 3 i X47 1 4t9 i V30 I til i YD* i V38 ) Y12 4 2Le i vea 4 Y4t 1 (St i 3LS I V49 4 6L2 1 x64 l l 388601 el 191691 of 24751l 242291 L'1924l el 229791 243591 24534l el 185831 el 39272] I l 1 1 I i l 1 ( ___,.1 l l l l~ f f I 5+9 1 6L6 i V06 4 2L9 i Y26 4 V54 I Yle i Yb9 I V02 4 2LS l V22 1 SL5 l s%2 1 1 359261 el 245391 el 229681 239124 241294 24e551 222181 el 244141 91 364118 18 I l_ l_ _l. l. l l_ I -l 1 I I l I i k o9 1 ZLo l St3 4 762 1 3L6 I Y19 I ti9 I Y15 l 3L9 l V31 1 6L5 i All i mit l I 356191 On 61 239291 81 242821 el 2462r,l el 237151 81 41 35146l J1 I I l l__ _4 I I 1 l _ 1-1 l 1 1 ) mil ! YS2 3 4t$ l YZ$ 1 ILF l V57 1 3Le i V28 1 4L7 1 Y37 l x37 l 5 357594 197641 el 244541 61 241&di el 246431 el 201421 3%491 12 I l_ _t l_ l __I 1 t 1 l I l I x52 i !Le i St6 i v29 1 =L2 I v54 1 6L7 1 2Le I a46 I I 35863) 91 el 184961 el 191961 el el 345671 11 I _I 1 1 I l l_ l i I I set i s37 i $L1 I v44 i $L9 i s35 6 uo4 i I 359911 360991 el 19ao44 el 3596el s uS41 14 1 I l l __ l __ I i 1 l x24 l c46 4 x39 I I_ _. _l-o EAWM i 196921 29%s31 393911 15 I l--> AsstnstY supuup l__l t i i I' r1E-895 N2C9 Startup Test Report Page 12 of 55

l Figure 1.3 NORTil ANNA UNIT 2 - CYCLE 9 INCORE MOVABLE DETECTOR LOCATIONS 9 P N N t t J H C F F_ p C 4 I i i i l 1 e I I i 1 1 I l I I I I I I i l i 1 i i I l Mo I i 2 1.I i i l I i I i i I i i .I I I I I I Mo 1 i i MD 1 Mo i i i i Mo i 5 l i-i-l l l-! l i i 1 I I Ma i l Mn l I Mo i i I l 4 I I l_ I I I i 1 1 I I,._. __ t I I i l i i l I i I i i 1 1 I I Mu I 6 Mo I i Mo 1 I ) l Mo l Mo I i Mo i s 1 1 1 I I i l 1. I i 1 I i i i i i i 1 i i i i I i l i I I i i Mo 1 I I MD 1 I Mo i l I i I 6 i i l 1 1 I I I I-1 1 1 I I I I 1 I I i 4 a 1 i e I I I I i i l i i 1 Mo 1 i i i Mo i I Mo I i i Mo 1 I Mo i I 7 I l-I l___I I I I i l_ 1 1 I i 1 I l 3 I I. 1 I I I I I I I I I i i i MD 1 1 Mo 1 i Mo i l i I i Mo I 1 l Mo i Mo i I a l l l 1 _1 1. l.. _1 i l i l I i i I 4. I I I I I I I I e i l I l l I I I I l 1 i Mo 8 i l i Mo i Mo i l 1 I I Mo I 9 I I I l I i l i i l I I I i 1 .I I l 4 i l I i I i i l i l I l i Mo 1 I i i Mc I i l i I Mo 1 1 Mo i to I-l l l l l-l -i l-l l l-l i i l i 1 MD 1 1 i Mo I i Mo i Mo I i i i 18 l_ I I I l _I l_ i i l ___.1 I i l I I I I I I I I I I 1 1 6 Mu I I I I Ma t i I f I Mo l Mo i at I_ i I i i l i i l__ I t, i I i i i I I 1 I i l i I I i i Mc l i Mo 1 I i 13 I I l_ 1 i l l __ I I I l a i i i l 1 i l 1 Mo I I i t nu I I i 14 l l I I I 4 Mo l i I 35 I I i l C Mo, Movable ootector location m

  • Locatiores not avantable to fluu inespring system for Cycle 9 h

i \\ ( NE-895 N2C9 Startup Tes.t Report Page 13 of 55

l l Figure 1.4 l NORTH ANNA UNIT 2 - CYCLE 9 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R P M M L E J M 4 F E D C 5 A 1 i ~i l l I I i 1 I l 2P EP 4 1 1 l l BP16tl i BP1611 1 I 2 1 1 4P 'lP Zsp i IbP l

  • P l

l 1 1 8P1841 sP1691 l $P1521 1 871701 BP1831 1 3 1 1 I l l l \\ l 1 1 I I l 20P 1 1 249 l S518 1 24P l 1 top i i i l i l SP136) i SP1641 i BP1591 1 8P1351 I i 4 l l $P ~~ l 20p I l 249 l P l 24P ~ 20P l 4P l 4 ~ ~ I I EP142) BP134l l SP1511 l 891441 1 BP1541 1 b71331 SP1811 8 5 1 1 ISP ~l i l=P 1 l l ~E l l ISP i i l SP1731 i RP1491 I i i l t SP14&l i 6P1741 8 6 i i i i i l i i l i l i 1 1 1 1 2P 1 1 2=P Q l 1 i 20P l 4 l l 24P l i 2P i l I l BP1641 i BP15al l I I BP1321 4 l 1 Epl571 1P16al I 7 l l 24p 20p l l 209 8 20P 1 20P 24P l ~ i i I ar1471 i SP13*l i BP1311 1 6P1501 l nP1341 1:P1461 I I e l I i l 1 i i i I l 1 i i l 1 1 i i 2P l i 24P 1 I l 4 200 l l l l 24P l l 29 l l l l BP163I I BP1561 I I I BP1291 l 1 i BP1551 i BF1671 1 9 l ! 1. l,4P ! l l i,4P i-i l l l5P 1 ( 8P1751 i BP1451 I l l I l BP1441 1 BP1761 1 18 ~ ~ 4P 20P 1 24P 20p 24 l 200 4 4P 1 1 i BP18el BP1281 1 tP1431 1 EP137: 1 SP1421 l BP1274 59179) l 11 l. I I top i i 249 ~ l GS17 24P 20p i ~ 1 i l BP1261 ] SP154l i SP153l l 8P4251 i i 12 l 4 ISP l i 246 i l 15P i 4P ] I t 5P1781 8P171) I &Pl414 1 SP1721 BP1771 1 13 I bri--l ,P l l l 1 I 1 SP1661 1 8p1651 I i 14 2P - 2 EURNABLE P0150m ROD CLUSTER l__l l t I i l i 4P - 4 EUENASLE PQ1$0N R00 ClusfER i i l l 1sp - 15 auRNAstE P0l$CN R00 CLUSTER I l i 1 15 20P - 20 EURNASLE POISON R00 CLUSTER l I l_I 24P - 24 BURNASLE P015% 900 CLIJATER SSwa - SECONDARY SOURCE NE-895 N2C9 Startup Test Report Page 14 of 55

Figure 1.5 s 110RT11 ANNA UNIT 2 - CYCLE 9 CONTROL ROD LOCATIONS a p w H L K J H C F E D C B A las' I \\ L*** 8 l l 1 i L*** C j Duttet I gg Inlet 2 , g g 1-6 l l 1 l I b 3 M-41 I l I I SA I I IA I g g g ~~ g lg l l l8 I I I

  • ~

t I sp i 1 58 l~ lYI I I I E8 y l lA l l8 i gT lC l lD l iB I IA I I =A i !,,1 l isol-1,.!

sA ;

17d a"* 90 l l D I. 1 I l C l I i g g [ l lD l 8 -i i i i_ i i y g I i i~ilY 'i ) i l LA l l l 52 l l SB l l l SA l I, ga gg l l D l lC i lD 1 18 A I ~ g g-g g sg [ l i l SP l l 1B l l SP I I g g U l 1C I 15 l l l3 l lC l l sr l l SA l l$ I I I I ~ I ;- I H-44 I I I I I 14 g g i i s i i n Loop I I I I Absorber Outlet I Heterial o' Ag In-Cd function M *" UI""I'#* RTH v 8 Control Sank D a - Control Bank C 8 Control Senk B Control Bank A 8 8 shutdown Sank SB Shuidown Bank $A 8 $P ($oare Rod Loca hons) 8 NE-895 N2C9 Startup Test Report Page 15 of 5

SECTION 2 CONTR0h ROD DROP TIME MEASURErtENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot ^ was less than or equal t.o the maximum allowed by Technical Specification 3.1.3,4. . The control rod drop times were measured in Mode 3' with the RCS Tavg above 500*F and all reactor coolant pumps operating. The rod drop times were measured by withdrawing a rod bank 229 steps, and removing the movable gr.ipper coil fuse and stationary gripper coil . fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The stationary gripper coil voltage and the Individual Rod Position Indication (1RPI) primary c il voltage signals were recorded to determine the rod drop time. - This procedure was repeated for each control rod. A '.thown on the sample rod drop trace in Figure 2,1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil l voltage when the stationary gripper coil fuse is removed. As the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a ; unction of control rod velocity. As the tod enters the. dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing. NE-895 NIC9 Startup Test Report Page 16 of 55

l-The measured drop times for sach control rod are recorded on Figure 2.2. The slowest, fastest, and aversgo drop times are summarized in Table 2.1. Technical " scification 3.1.3.4 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.7 seconds with the RCS at hot, full flow conditions. These test results ? e satisfied this limit. da ~ NE-895 N2C9 Startup Test Report Page 17 of 55

Table 2.1 NORTH ANNA UNIT 2 - CYCLE 9 STARTUP PilYSICS TESTS Il0T ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASilPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME B-06 1.83 sec. M-04 1,44 sec. 1.61 sec. NE-895 N2C9 Startup Test Report Page 18 of 55

i Figure 2.1 NORTH ANNA UNIT 2 - CYCLE 9 STARTUP PilYSICS TESTS l TYPICAL ROD DROP TRACS O Dashoot Boeom O Dashoot intiatbnQ Rod G First (8egmng Q Fret Drop Evot Mam m Trace) Upeumin Trace) / \\ / coa voaage Trace Rod Drop Tlrne gAAAAAAAAAA A vvVVVVVVV1j k ( N dllA A A A A l 60HzIRPI vvvvvvv V AAA Prtmery Coa vvvv1 w Trace aAAAAAAAAAAAAAAAAAAAAAAAAAAAA AAAAAA AAAAAAAA vvvvvvvwvvvvvvvvvvvvvvvvvvvyr yvvvv vvvvvvvvi 80Hz Trace (l! Usec) k. ROD DROP TIME MEASUREMENT NE-895 N2C9 Startup Test Report Page 19 of 55 - - - - ---~ ~ ~ ~

l l' i-l l Figure 2.2 NORTil ANNA UNIT 2 - CYCLE 9 STARTUP PHYSICS TESTS ROD DROP TIME - Il0T FULL FLOW CONDITIONS R P W M L E J M G F E D C 8 A l~ l i l i I I i 1 _.1 1 I I I_ I I I I I I I I i 1.63 I i 1.59 1 l 1.68 I I 2 1 l __I i l 1 1 i l I i i i i i i l I i I I i 1.65 I i 1.61 1 1 1 l 3 I I I I i i 1 1 I I i l I I I 1 I I l 1 i i ~ l i 1.64 1 1 1.73 1 1 I i 1.sa I i 1.64 1 1 4 1 1 I I i 1 1 1 _,. I _. I I I I I I I I I i 1 1 I I I l I i i I i 1.61 1 1 1 l I i 1.65 l 1 1 1 5 1 l _ ,,1 . _ __ I i 1 _t 1 i l 1 I i i l i l i I I i i l I i l i 1 i 1.&o I t 1,62 I i 1.sa i i 1.66 l l 1.55 I i 1.59 i i 1.a% 1 6 l I, _1 1 1 1 1 I i l. I l I I i I l i I I I I I I I I I I I I A' l l l 1.51 l i 1 62 I I I i 1.63 1 1 1 7 i l _.' a 1 l i l __ I 1 1 1 I I I I I I I I I I I 4 I I i i l I i l i 1.63 I I i 1.59 l l 1 1 1.55 I l i 1 1.69 I I a I i 1 1._,._. i 1 i i l_ 1 1 I I I I l i i i i I i 1 1 1 I I I I i l i i i i 1.64 i l 4 i 1.56 1 1 1.68 I I i i 1.46 I I l 9 I l __ t i I I I l I I i l I i i l I I I i i i i i i l i i 1 i i 1.64 I i 1.51 1 1 1.56 i i 1.54 1 1 1.54 I i 1.57 I i 1.64 l 10 I ( _t i i l 1 l _.1 1 I i i I i i i i i l I 1 1 i i i i i i i i 1 1.66 I I I I i 1 1.59 I I I i 11 i i l i I I i 1 l l I i i l I I i i 1 I I I i I 1 1 1 1.63 8 I 1.57 I I i 1 1.54 I i 1.62 1 1 12 I I I I l__] 1 1 1 I 1 1 I l I i 1 I I i 1 1 1 l l t 1.54 I i 1.65 I l I i 13 I I I i 1 1 i l i l I i l i i i i i i i 1.75 l 1 1.63 I i 1.75 I i 14 I I I I 1_, l 1 1 1 I i l l 1 I i 15 1 I l i 1 I I y.xx l--> Roo pop TN To os91 POT [NTRY ($fCl i I NE-895 N2C9 Startup Test Report Page 20 of 55

i SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique . The initial step of the rod swap 2 method diluted the predicted most reactiva control rod bank (hereaf ter referred to as the reference bank) into the core and measured its re activity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 9, Cont ol Bank B was used as the reference bank. After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the reference bank near full insertion. Initial statopoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position and recording the core reactivity and moderator temperature. From this po it.t. a rod swap maneuver was performed by withdrawing the reference bank several steps and then one of the other control rod banks (i.e., a test b1nk) was inserted to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank. NE-895 N2C9 Startup Test Report Page 21 of 55 = _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - _ - _ - _ _

The core reactivity, moderator temperature, and the dif ferential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver then was repeated in reverse such that the reference bank again was near full insertion with the test bank fully withdrawn from the core. This rod swap process was then repeated for each of the other control and shutdown banks. A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the. individual measured bank worths for the control and shutdown banks were within the design tolerance (i10% for the reference bank, and 15% or 100 pcm, whichever is greater, for the test banks). Thn sum of the individual measured rod bank worths was within 1.1% of the design prediction. This is well within the design tolerance of 110% for the sum of the individual control rod bank worths. The integral and dif ferential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order ~ to illustrate their-agreement. In _mmary, the measured rod worth values were satisfactory. NE-895 N2C9 Startup Test Report Page 22 of 55

Table 3.1 NORTc ANNA UNIT 2 CYCLE 9 STARTUP PilYSICS TESTS CONTROL R0D BAWK WORTH

SUMMARY

HEASURED PREDICTED PERCENT DIFFERENCE WCRTil WORTH (%) BANK (PCH) (PCH) (M-P)/P X 100 B-Reference Bank 1227.5 1288.0 -4.70 D 980.1 939.9 4.28 C 829.8 765.6 8.39 A 213.1 227.1 -6.16

  • SB 1066.8 988.8 7,89 SA 1009.0 1061.5

-4.95 Total Worth $326.3 5270.9 1.05

  • Difference Is less than 100 pcm.

-NE-b>s N2C9 Startup Test Report Page 23 of 55 q a

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Fig,ure 3.2 NORTil ANNA UNIT 2 - CYCLE 9 STARTUP PilYSICS TESTS BANK B DIFFERENTIA! ROD WORTil - IlEP BANK B WITil A1.L OTilER RODS OUT Ilifillill il 1111111 ill 11 litillfillifillili' 11*00 i l i f i l [77777777)7; ITGITTIT TT i7 X measured !TITiT i TUiT 10.50--77777-

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s, 106 120 IX 144 198 1M 150 192 304 216 135 i 0.00 s, i i,, H M 40 48 M M 7130 M N 8 18 0 BANK POSITION (STEPS) NE-895 N2C9 Startup Test Report Page 25 of 55 - - - - - _ _ _ _ _ _ _ _ _ _ _ _ - ^ ~ ' - * ^ ^ - - ~ - ~ -, _ _ _ _ _ _

SECTION 4 1 . BORON END?n1NT AND V'JRTH HEASUREMENTS i l Boron Endpoint With the reactor critic 61 at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected r.x! bank configurations to enable a direct comparison of measured boron endpoints j with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustmenta to the measured critical boron concentration values were made to account for of f-nominal control rod position and moderator temperature, if necessary. The r mults of these measurements are given in Table 4.1. As shown in t a Startup Physics Tests Results and Evaluation in-tnis table and Shnets given in che Appendix, the measured ARO critical boron-endpoint wlue was not within desigt tolerance, but did meet the requirements of Technical Specification 4.1.1.1.2 regarding core reactivity belance. The ARO endpoint exceeded its design tolerance of 32 ppm, but further analysis -showed no impact on the safety analysis. In summary, the boron endpoint results were satisfactory. - Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which tho' boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, PE-895-N2C9 Startup Test Report Page 26 of 55 .,e-.-i, e ,,w ,m., ,---u_ r 4

the value of the DBW over the range of boron endpoint concentrations was obtained. A plot of the boron concentration vert.us inserted control rod worth is shown in Fi ure 4.1. An indicated in this figure and in the Appendix, E the measured DBW was -6.86 pcm/ ppm. This is within 0.77, of the predicted value of -6.81 pcm/ ppm and is well within the design tolerance of 1107.. In summary, the measured boron worth coefficient was satisfactory. NE-895 N2C9 Startup Test Report Page 27 of 55

Table 4.1 NORTli ANNA UNIT 2 - CYCLE 9 STARTUP PilYSICS TESTS BORON ENDPOINTS StIMMARY I Measured Predicted Different.o Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm) ~1 ARO 2096 2053 +43 B Bank In 1917 1907* +10

  • The predicted endpoint for the B Bank in configuration has been adjusted for the difference between the measured and predicted

. lues of the endpoint taken at the ARO configuration as shown in the boron endpe'nt Startup Physics Test Results and Evaluation Sheets in the Appendix. NE-895 N2C9 Startup Test Report Page 28 of 55

Figure 4.1 NORTH ANNA UNIT 2 - CYCL.E 9 STARTUP PilYSICS TESTS BORON WORTH COEFFICIENT l 1,3co. _..j....................M...e...a..s..u..r.e...d....D. B._W.=.... 6.; 8. 6.. 1,200-R.+ + - + i ! m -+ ! --+.-- +< ls5 1 3,3 oo _.........._..D.4....................,.._..h..,.._..___..........._.....,..._.....!..... .f.., ........ s. t...,.... 3,ooo. l I N! l 1 -*- L \\ h-- -~ ~- -- L-ls-_ rl -a t i-.rl-.-...i-. --- 900-I i i ....1.s,i.;h+l ! 4 !.-{i;..-l l ^ E 800 .. 7..{...- x L- - -a--- < s ;-t, -'- t--*1 I j i i 700- -i i _..... E I s _..,.............;......,..............4.4,_..,...,.....i..........,.....l......... 800 _..I.... ;.,I....i.......i.......i......I..... .._.3 i si._....l. I _...I;i............l... I 5 ..s 300 I l { si l 1 i i i r w ....,......g..... {.....!.. ..,.........t.....,....j. t..... t _ i..Q...__......;..,.. 4... t.....;..._. I. j = 4oo. l l A l l l l i 8 2 _..j...4..... j..... ......,..... a..l.. .....i......!.. l .....!....,1..............4....4.........! %. 300 ............ 1...j:......... 1.....;... .'i.....l..._.....i!-..l. _ !s..ii... ......._. j l 1 i l I N ......1.. 200 i i i i i l% j i i N i i ii i + .i.++-*-++-+-+i ) }\\+++ +l< i 100-- 2 i i 1 I i I I. P. n i, I. I. i I 1 S I i l. 0 u 1910 18J0 1900 1970 1f00 2010 2033 2000 2W0 2000 2110 2iJO BORON CONCENTRATION (PPM) NE-893 N2C9 Startup Test Report Page 29 f 55

SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (1TC) a t. the all-rods-out condition is measured by contro111r.g the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a ? constant heatup or cooldown rate, and monitorlag the resulting reactivity changes on the reactivity computer. This test sequence includes a cooldown followed by a heatup. Reactivity was measured during the RCS cooldown of approximately 3.1'T and the RCS heatup of approximately 3.2'F. Reactivity and temperature data was taken from the reactivity computer and strip chart recorders. Ussug the statepoint method, the temperature coefficient was determinou by dividing the change in reactivity by the chans;c in RCS temperature. An X-Y

plotter, which plotted reactivity versus temparature, confirmed the statepoint method in calculating the ocasured ITC.

The predicted and measured isothermal temperature coef ficient valt.as are compared in Tabic 5 1, As can be seen from this summary and from the Startup Physics Test Results and Evriluation Sheet given in the Appendix, the measured icothermal temperature coefficient value was within the design tolerance of d3 pem/'F. The moderator temperature coefficient was determined to be +0.02 pcm/'F which met the requirements of Technical Specification 3.1.1.4. In summary, the measured result war. satisfactory. NE-895 N2C9 Startup Test Report Page 30 of 55

Table 5.1 N0lt*'. AN!ih UNIT 2 - CYCL.E 9 STARTUP PilYSICS TESTS ISOTilERMA1. TEMPERATURE COEPFICIENT

SUMMARY

ISOTilERMAl, TEMPERATURE COEFFICIENT BANK TEMPERATURE BORON (PCM/'F) POSITION RANGE CONCENTRATION y ('F) (ppm) C/D 11/U DIFFER. MEAS. PRED. (M-P) 544.2 D'213 to 2093 -1.77 -1.72 -1.75 -1.08 -0.67 547.4 n NE 895 N209 Startup Test Report Page 31 of 55

SECTION 6 POWER DISTRIBUTION HEASUREMENTS The core power distributions were measured using the movable incore detec+or flux napping system. This i.ystem consists of five fission chamber detectors whicu traverse fuel ar.acmbly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available locations monitored by the movable det.ectors for Cycle 9. For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full ccre, three-dimensional power distribut.lons are detmuined ftw this data using the Westinghouse computer program, INCORE. INCORE couples the measured voltages with predecermined 8 analytic power-to-flux ratios in order to determine the power distribution for the whole core. A list of the full-core flux maps taken during the startup test program and the measured values of the important power distribution parameters is given in Table 6.1. A comparison of these measured values with their Technical Specification limit s is given in Table 6.2. Flux Map 1 was taken at 30% power to verify the radial power distribution (RPD) predictioni, at low power. Figure 6.1 shows the measured RPDs from this flux map. Flux maps 2 and 3 were taken at 73% and 99% power 1cvels respectively with dif ferent control rod configurations. These radial power distributions. for these maps are given in Figures 6.2 and 6.3. The radial power distributions for the maps given in Figures 6.1, 6.2 and 6.3 show that the mearored relative assembly power values were generally within 1.8% of the predicted values. Further, the measered F-Q(Z) and NE-895 N20.9 Startup Test Report Page 32 of 55

s F-Dil(N) peaking factor valuet for the at power flux msps were within the limits of Technical Spe.ificatious 3.2.2 and 3.".3, respectively. In conclusion, the power distribution measurement results were considered to be acceptable with res~ct to tha design tolerances, the accident analysis acceptance critaria, and the Technical Specifitation limits. It is therefore ant!cipated that the care will continue to operate safely throughout Cycle 9. (' NE-895 N2C9 Startup Test Report Page 33 of 55

l TABLE 6.1 NORTl! ANNA UNIT 2 - CYCLE 9 STARTUP PliYSICS TESTS INCORE FLUX MAP

SUMMARY

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l Table 6.2 NORTil ANNA UNIT 2 CYCLE 9 STARTUP PilYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITil TilEIR TECllNICAL SPEC'tFICATION LIMITS F-Q(Z) Il0T F-Q(Z) Il0T F-Dil(N) 110T CilANNEL FACTOR

  • CilANNEL FACTOR **

C}lANNEL FACTOR (AT NODE OF HINIMUM MARGIN) MAP NO. MEAS LIMIT MARGIN MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN (%) (%) (%) 1 2.122 4.380 51.6 2.122 4.380 31 51.6 1.501 1.803 16.7 2 1.982 2.976 33.4 1.977 2.968 25 33.4 1.447 1.611 10.2 3

1.842 2.202 16.3 1.819 2.158 23 15.7 1.411 1.492 5.4
  • The Technical Specification's limit for the heat flux hot channel facter, F-Q(Z), is a function.- core height and power level.

The value for F-Q(Z) listed abo.. is the maximum value of F-Q(Z) The Technical Specification's limit listed above in the core. is evaluated at the plane of maximum F-Q(Z).

    • The value for F-Q(Z) listed above is the value at the plane of minimum margin.

The minimum margin va:tias listed above are the minimum percent difference between the measured values of F-Q(Z) and the Technical Specification's limit for each map. Tlio measured F-Q(Z) hot channel factors include 8.15% total uncertainty, NE 895 N2C9 Startup Test Report Page 35 of 55

i Ngure 6.1 NORTil ANNA UNIT 2 - CYCLE 9 STARTUP PilYSICS TESTS ASSEMilLYWISE POWER DISTRIBUTION 30% POWER 4 9 W M L M J H C f ( D C 8 4 8vt DIC)i D . 0.F3. 6.27. 9.23 PWilettifD . 9.24. 9.24 9.7%. Mt ASWT D 1 Mt A$urt D .PC f Dif f l Rf MCt. 26 2.3. 0.3 .PC f Dif f lPl N(f.. . 9.11. 4.4% l.0%. 4.44. 1.06. 6.4%. 4.31 . 0.32. 0.46. 1.96. 9.8%. 1.0%. 4.44. 9.33 2 3.6. 1.5 1.1. 0.8. -0.2. -2.4. -1.2 . e.4I, l. 7. 4.29 1.ta 1.so 1.26. 4.29. 1.17. 0.41 . 0.41. l.;6 1.27 h. 79. 1.31. 1.??. 1.27 1.16. 9.41. 1 + 0. 3. -0.7. -1.6 1,9. 0.9. 9.2. l.1. -9.R 6.2. 0.69. 8.7 ), 1.34 1.25. 1. 16. 1. 5 2. '.1%. l.24 l.36. 0.95 9.49. 0.46 8.93 1.34 1.26 1. 54. 1.3 4. 1.16. 1.2%. 1.15. 0.92 9.44. 4 6.4

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  • 3.1
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-0.2 . 4.31 0.45 1.06. 0.84 1.0% 0.4%. 0.31. 8.12. 0 47. 1.0% 0.42 1.06 0. 4 5. 0. 24 14 2.4 2.3 ~9.4. -2,4. -4.7 $.9. -5.8. '.14NDARD . 9.11 0.27 0.23 Avt W ACT M vlat10m . 6.t4. e.27. s 22. .PC T Dli t t ut Nct. 4% 1.4 =1 43o 2.1 -1.2 -4.6.

SUMMARY

MAP NO: N2-9-01 DATC 4/26/92 POWERI 30% CONTROL ROD POSITIONSs F-Q(Z) = ?.122 CORE TILT: D BANK AT 143 $TEPS F-DH(N) = 1.501 NW 1.0107 l NE 1.0035 i F(Z) e 1.348 SW 1.0008 l SE 0.9831 BURNUP a 7 PtWD/HTU A,0. = -3.518% NE-895 N2C9 Startup Test Report Page 36 of 55

Figure 6.2 NORTil ANNA UNIT 2 - CYCII 9 STARTUP PilYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 73% POWER R P M A L E J H G F t D C 8 A f*PtDltiLD . 4.*6. 0.38 8.76. I'FI Dit tf D Mi 4Lupt h . 9.76. 0.31. 9.F5. nt A%1W1.9 l .pCf cif f tpteett. 0.9. -6.5. -l.F .FCI Olf Flpl eett. 4.0.32. 8.41. 1,96 4.92. 1.99. 6.47. 4.12. 4.32. 6.47. 1.97 4.92 1.06. 0.4b. 8.31. P 9.4. 8.$. -0.4. 0.7 -2.2. -4.6

  • t.6 9.el. 1.34 1.25 1.76 l.29 1.26 1.75 1.84 6.41 9.41 1.11. 1.74. l.76. l.29 1.th. l.23 1.12. 0 41 1

-1.%. 1.7 l.4 4.0 -0.1 4.9. -1.5 1.2 -0.4 ...............................,................................. 9.44. 9.49 9.91 l.f9. 1.Fl. l.32. I.r*. 1.3% 1.21 1.79. 4 94 4.44 0.9C l.27 3.'t. 1.31 1.5= 1.37. l.t3 1.29 6.Vl 9.49 4 l.5. 4.1. -0 1.1 l.8 1.6. l.1 0.2. 4.9 0.9 8.4 . 0.32 1.13. l.29. 1.f%. 1.2%. 1.1A. 1.27. 1.14. 1.2%. 1.24 1.79 3.13 8.37 . 9.11 1.09 1.76. '..t3. 1.25 1.27. 1.34. 1.t2 1.7% 1.74. 1.t8. 1.12 8.32. S -3.4 3.8. -1.9 -4.2. 9.9 3.6 3.5 3.4. 2.8. 1.4. 0.6. +1.4. - 0. 3. . 0.e7 1.25. 1.78. 1.22. 1.09 I.'.2. 1.11. 1.12 3.99 1.25. 1.21............. 1.2% 0.47 . 9.46. 1.23 1.24. 1.F$. 1.19

1. l F, 1.16 1.1 F.

1.'3 I.27 1.21 1 74 0.46 6 .l.6 -1.6 -0.9. -0.2. 1.1.

4. 3.
4. 5.

E.I 3.3. 1.1. -9.4 -1.6. -1.7 . 9.26 1.09 1.26. l.32. 1.18. a 12. l.it. 1.F6 1.14 1.12. 1.13. 1.3? 1.26 4.99 9.26 0.76 1.09 1.25. 1.31 1.84. 1.12 1.70. I 11. 1.19 1.17 1.2P 1.31 1.24 1.91 0.76 7 9.h -0.2 -0.o. -0.6. v.) 0.6 5.5 S.3. 4.7. 4.3. 2.4 0,6. 1.4. -2.0. -2.3 ......0.93. l.'9 1.79 l. it. 1.12. 3.16. 1.1%. 1.?6. s it 1.74 8.?9 1.30 9.97 4.32 0.31 4./l. 0.92. 1.t&. n.30. a 19 1.14. 1.76 1.19 1,31 1.16 1.34 1.78 4.74. e.90. s.37 4 4.2. 0.4 -3.4. 9.4 1.5 1.6 0.0. 3.7. 3.6. 3.6. f4 -0.9 e.$ -1.7. -1.5 0.76 8.68 8.76 1.3.* . 1.18. 1.12. l.14 1,76 1.14. 1.17 1.18. 1.%F 4.76 1.19 J.27. 0.26. l.06 1.72. 1.31. 1.79. 1.1%. 1.11. l.79. 1.18. 1.16 1.24 l.31 1.7%. l.09 9.16 t 0.5. -1.9. -3.3 -0.8 1.8. f. f.9. 3.0. 3.5. 3.4. 2.5 -W.6 1.3. -1.4 -1,3. ...1.11 1.12, 1.09 l.?h 1.'1 l.P6 9.47 4.47. 1.25 1,71 1.2% l.09 I.12 9.45. 3.19 1.21 1.ft. l.Il. 1.15. n.12. 1.12. I.10 1.26 I.'2. 3.'4. 6.46 le . - 4. 6. -4. T. 0.1. 21/ 2.7 1.3. 3.1. P.!. 9.e, 0.6. 9.6. -1.1 1.4 0.32. 1.13, l.79 1.74 1.25.3.18.1.??.1.18.l.75.1.24. 1.T9 l.15. 9.32. 4.31 1.11. 1./S. 1.?6. l.76 1.16 l.71 1.16. 1.24 1.73. l.29 1.13. 4.31. 11 1.6. -1.6 -0.4 4.1. 1? 6.3. 0.7. -1.3. ~9.7 .-8.7 4.1. 0.6, -1.4 4.48. 0.91. 1.29 1.28. l.31 1.2%. 1.31. l.24. 1,79 s.91 e.49 f.41. 0.9 3. 1. 31. 1.12... ?9. 1.27 1.28. 1.19

1..'7 0.11. 6.49 It 1.4 1.7.

F.9 A.;

  • 1.4.

-1.* 2.3. *2.4 1.5. 0.7. 9.1. 4.41. 1.14 1.25. l.P6 l.79 1.76 1.25 1.;4 4.41 l.?6 1.2a. l.70 1.13. 0.41. 13 4.47. 1.16. 1.ai - 1.76 1.4 2.0. 4.5 - 1. 8. - ?. 4. -3.h. ~4.7

  • 2.5.

e.9. 0.32. 0.47. 1.6f. 0.92. 1.04 0.47. 9.32 6.31. 0.4F 1.96. 0.99 l.94 9.4%. 0.3e 14 9.L. 9.4

  • 0.9

+2.2. 3.% -4.1 -4.7 $f ANDakli 9.76. e.31 0.?6 AVIPACt DfVIAIION 8.26. 9.30. 9.?S .PC f O trf t pf eett. 15 1.F =l.341 9.1. 1.4 3.4. = St.tMM,4 gy, MAP N01 N2 9 02 DATER 4/27/92 POWER: 75% CONTROL ROD POSIT 10NSI F-QlZ1 a 1.982 C0RE TILTi D BANK AT 164 STEPS F DHINI 1.447 NW 1.0005 l NE 1.0060 t F(Z) = 1.268 SW 0.1997 i SE 0.9937 BURNUP t 36 MWD /NTU A.O.

  • 2.646%

NE-895 N209 Startup Test Report Page 37 of 55

Figure 6.2 NORTil ANNA UNIT 2 - CYC1.E 9 STARTUP PilYSICS TESTS ASSENDI, WISE POWER DISTRIBUTION 99% POWER R P N M L J H E F ( D C PPtDltit0 6.27. 9.11. 0.77. PPlDIClfD rT&Lut!D. 4,17. 9.15. 0.77. MB asupl 0 3 . PCT liltill4 WE. -0.2. -0.2. +l.3. .PCI Olfilpfhtt. 4.12 9.47. i.it. 0.90 1.lt. 0.47 6.12. 9.37. 0.47. 1.48 0.97 1.e4. 4.46. 6.37. t F.!. 9,1. l.!. -l.5. F.9 2.4. -0.0. . 0.41. l.Il 1.ti. 4.tb. l.28 1.7% 1.t3. 1.11 S.4l . 0.41. 1.30 1.12. 3.16 1.?7 1.T4. 1.tt. 1.12. 0.4'. 3 . - 4. 8. - 1. 8. 2.1. - 0.9. - 1. 8. 0.9. +0.5. 0.6 f.%. 0.44. 9.49. 1.7% 1.89 1.10. l.T7. 1.29 l.19 1.2% 9.a9 4.40. 4,40. 0.68. 1.74. 1.19. 1.10 4.27. 1.79 1.21 1.1/. 4.99 4.44 4 -4.4 1.% < 1.0. 0.6. 9.1. *$.0. 0.1 1.6. 1.9.

4. 7.

0.5. 0.52. l.Il 1.2%. l.f1 1.2%. 1.14. 1 T6. 1.18. l.t$. l.ft 1.t6. 3.11. 4.32. . 0.51, 1.07 I !!. 1.t!. 1.74 1.21. 1.50. 1. 21. 1. T9 1.26 1.2%. 1.19. 4.11. 5 -1.7 3.7 -2.4 1.9 0.7 f.8 f.8. f.9. f.8 1 %. -c.5 0.6. 1.4 . 0.47. 1.21. l. 1. 1.26 l.16. 1.14. 1.15 1.14. 3.86 1.76. l.70. 1.25. 0.68. D.46 1.?S. 1.87. 1.Tb. 1.16 1.19. 1.17. 1.29 1.t0. 1. t 7. .19. 1.22. 4.47. 6 2.t. 2.2 al.%. *G.9 e.4 3.4 3.9

4. 7.

3.6. 10 0.3. -1.5 -0.4. 9.78. l.11. l.7%. $.30. 1.18. 1.1%. 1.16. 1.77 1.16. 1.1% 1.19 . 54. I 76 1.11 0.tB . 1.tl - 1.13. 1.21. 1.ft 1.!!. 1.79. 1. '. l.09 9.27 7 . 8.16 4.99 l.21. l.74 1.17 1.34 -0.I -1.2. 1.7. al.4. -1.1 -l.1 4.4. 4.4 4.6. 4.4 f.7.. 3. -1.7 -2.1. -T.9 0.54 0,94 8. 24. 1. P ?, l.??. l.11. 1.27 1.16. 1.f'. l.11. 1.T7 l.it 1.50 0.99 0.1% 0.54. 9.97 1.16. 1.27. l.it. 1.?% 1.26. 1.25. l.12 1.16. 1.30 1.26. 1.to

0. 9 7. 9. >

8 -4.1 al.?. +1.8. *4.3. Ii 1.2 -0.6. 4.1 A.9. 3.9. 2.%. -1.4. l 7. l.1. -4.9 0.77. 1.10. 3.7%. 1.50. 1.18 1.1%. 1.8% 1.27. 1.16. 1.1%. 1.16 1.50, i.76. 4.12. 9.16. 9.T7. 1.07. 4.te. 1.ta 1.te 1.17. l.19. 1.50. 1.tt 1.74 J.tt. I./9 3.7%. 3.!?. 4.74 9 - 0.1. - F. 6.

3. 4. - l. T.

l.4 1.4 f.9. f.9. 1.9. 5.9 f.9. -0.7. 0.8. -0.7. -0.' 4.47 1.t3 1.19 l.7% 1.16. a 14 1.15 1.14. l.16 I.t6 1.19 1.23. 4.46. . 4.4%. 1.17. 1 19 1.t9. 1.39. 1.16. 1.14 1.1%. 3.11 1.27 1.!!. 3.T) 0.64 14 -4.9. -4.9 -0.4 2.6 2.7 1.2. 0.9 4.4 1.T. 1.1. 1.0 -4.1. -4.0 4.3F, 1.10 1.?%. 1.t2. l.7%. 3.15 1.?6. 1.14. 1.7%. 4.rt. 1.te. 3.11 9.52. m 11. 1. t

  • 1.1%. 1.7%. 4.T6. 1.18. t.T6, 1.87
1. t%. 4.15. 1.27. l.17. 4.12.

11 -1.2 -1.2 -4.4 21 1.1 0.1. 4.0. -1.2 -0.4. 4.3

1. 3.

4.0. 1.9. 0.49. 4.49. 1.th 1.19 1.T9. 1.27. 1.30. 1.19 1.T5. 4.49. 4.40 P.48 0.91. 1.24. 1.24 1.t?. 1.2%. 1.'6. 4.10 l.tn. 0.98 4.41. It 2.%.

2. 5.

f.1 4.2 -l.S -1.6. -F.4 -I.6. 1.0. 1.6 1.1 e.41. 1.11. 1.71. 1.2%

1. to. 1 7%. 1. 21. 1.18 0.61

. 9.42. 1.15. l.25 1.??. 1.2%. 1.ft. 1.lt. l.99 9.47. 11 2.5, T. !. - 1. 6. - 2. 5.

2. 7. -1. 6.

-4. 0 -2.4. 1.5. . 6.32 9.47. 1.19. 0.96 1.10 0.47. 0.54 . 9.12. 0.44 1.09 0. 94 1 06. 9.4%. 0.50 44 0.7, 0.7 1.0. 2.9 -3.6 -3.9. -4.3. $1&MD&kD . 9.t'. 0.33. 4.27 avl RAGE DIVl&llDM . 6.78. 4.13. 4.t6 . PCT D af f t P( MCf. '1 1.7 +1 tot 4.7 1.1 3.%.

SUMMARY

NAP NO: N2*9 03 DA1El L/01/92 F0WERI 99% CON 1ROL ROD POSITIONSs F-QtZ) a 1.842 CORE TILT: D 8ANK AT 228 STEPS "-DH(H) a 1.411 NW 0.9945 l NE 1.t069 l FlZ) = 1.210 $W 0.9978 l SE 0.9990 BURNUP 3 1$9 NWD/NTU A.u. 6 0.iJ2% NE-895 N2C9 Startup Test Report Page 38 of 55 AM

) SECTION 7 REFERENCES

1. A.11. Nicholson, " North Anna Unit 2, Cycle 9 Design Report,"

Technical Report NE-885, Revision 0, Virginia Power, April, 1992.

2. T. K. Ross, W. C. Beck. " Control Rod Reactivity Worth Determination By The Rod Su p Technique," VEP-FRD-36A, December, 1980.

F

3. W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149 December, 1967,
4. North Anna Unit 2 Technical Specifications, Sections 3.1.3.4,
3. 2. 2, 3. 2. 3, 3.1.1. 4 and 4.1.1.1. 2.
5. Letter from W.L Stewart (Virginia Po.cer) to the U.S.N.R.C., "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2:

Modification of Startup Physics Test Program - Insper.6or Followup Item 280, 281/88-29-01," Sorial No. 89-541, December 8,1989.

6. Memorandum from C.B.

,alloo and 2.T. Robins to Mr. R.G. McAndrew, " Evaluation of Measurv N2C9 IlZP ARO Critical Boron Concentration," April 22, 1992. NE-895 N2C9 Startup Test Report Page 39 of 55

l l APPENDIX STARTUP PilYSICS TESTS RESULTS AND EVALUATION SilEETS NE-895 N2C3 Startup Test Report Page 40 of 55

NORTH ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout Reference . Proc No /Seccion: 2-PT-94.0 Sequence, Step No: 3 11 Bank Pcsitions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: 228 CC: 228 CD:

  • Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature ('F): T'./6.0 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CD: 228 CC: g CD: 70 Below Nuclear Heating Date/TimeTestPer$rm"e*[: DI 'L8 12ff%. Heasured Parameter pc = Meas. Reactivity using p-computer Predicted Reactivity IV (Description) pg 5 M. T ' pe = N,0 Measured Value pt " " N*I 'Y Test %D =

  • L T4 '

-0. Y 'I Results e pt)/pt) x 10 E 5 4. 3 Design Value ID = ((p Reference WCAP 7905, Rev. 1 Table 3.6 V I FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable l Desie,' Tolerance is met Y ES,,_,,,,NO / YES ,_,,NO VI Acceptance Criteria is met Comments

  • At 11e Just Critical Position l

Allowable Range = + 46,5, - 4 (o. O Prepared By: Reviewed By: Is ^- h 4A1 Ni:- G95 N2C9 Startup Test Report Page 41 of 55

NORTil ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1 Test

Description:

HZP Boron Worth Coefficent Measurement 'leference Proc No /Section: 2-PT 94.0 Se,uence, S tep No: 7 II Bank Positions (Steps) RCS Temperature ('F): 54; Test Power Level (t F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating i III Bank Positions (Steps) RCS Temperature ('F): F 7est Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB:Mo/ing CC: 228 CD: 228 Below Nuclee,r Heating Date/ Time Test Performed: A=n2 w.o Measured Parameter IV (Description) aC, Soron iiorth Coefficient 9 c, 8 (o Heasured Value nCB"# ~~ Tese 1su4ts Design Value (Design Conditions) aCB = -6.81 ! 0.68 pcm/ ppa Reference Technical Report NE-885, Res. O FSAR/ Tech Spec Not Applicable V Accepttace Criterisl Reference Not Applicable Design Tolerance is met . A YES ,_,,,,NO VI Acceptance Criteria is met l YES ,_NO Comments Prepared By: Reviewed By: b, N "M NE-895 N2C9 Startup Test Report Page 42 of 55

NORTil ANNA POWER STATION UNIT 2 CYCII .4 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - ARO Reference Proc No /Section: 2-PT-94.0 Sequenca Step No: 4 II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 22t CA: 228 Other (specify): (Design) CB: 228 CC: 223 CD: 228 Below Nuclear Heating III Bank Positions (Steps) lRCSTemperature('F): ('f 6, '. Power Level (% F.P.): O Test Conditions SDA: 228 SDB: 228 CA: 228 i Other (Specify): I (Actual) CB: 228 CC: 228 CD: 223 Below Nacleat Heating l Date/ Time Test Pe r f o rr.ed : i. W3l 9/11-['T"L Meas Paremeter g (C ) AR0; Critical Boron Cone - ARG IV (Description) g Measured Value 3 Test (Design Cond) (C ) ARP ' B Results Design Value (Design Cond) CB = 2053 1 32 ppa. lTechnicalReport NE-865, Rev. O Reference D V FSAR/ Tech Spec aCB x C,5 1000 pcm B Acceptance Criteria Reference

Technical Specificatien 4.1.1.1.2 Design Tolerance is met

.,__,Y E S NO Acceptance Criterin is met Z YES NO VI 1 Comments laC3 = -6.78 pcm/ ppm D M B = l ( C ) A'IO ~ C l ; CB is design value. C B B l Prepared ny: N ceviewed By: ink s NE-895 N2C9 Startup Test. Report Pago 43 of 55

NORTil ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Isothermal Temperature Coefficient

  • ARO Reference Proc No /Section: 2-PT-94.0 Sequence Step Nn: 5' II Bank Positions (Steps)

RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 54'l.9 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: 228 CC: 228 CD:.2 l 3 Below Nuclent Heating l Date/ Time Test Performed: l Hldpk12 C-4 % 2 g Meas Parameter 150 IV (Description) (a T )ARO la thermal Temp Coeff - ARO 150 Test Measured Value (a 7 ) ARO = -1.7 5 pen /'r (CB =]cq3pp.) Results l (a T ) ARO * -L C9 Design Value ISO 0 pcs/'T (Cg =)C43 ppa) (Actual Cond) 150 Design Value (a 7 ) ARO = - 1.45 1 3.0 pcm/'T (Design Cond) (CB = 2053 ppm) Reference Technical Report NE-885. Rev. 0 V ISO Dop = -1.77 pcm/'F Acceptance FSAR/ Tech Spec aT 5 3.73*pcm/'T a7 Criteria f Reference TS 3.1.1.4 Technical Report NE-885, Rev. O I YES N0 I Design Tolerance is met VI Acceptance Criteria is set V YES NO Comments

  • l% certainty on aTMOD = 0.5 pcm/'F (

Reference:

memorandum f rom C. T. Snow to E. J. Lozito dated June 27, 1980). Prepared By: Nd Reviewed By: A N NE-895 N2C9 Startup Test Report Page 44 of 55

NORTH ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AMD EVALUATION SHEET I Test

Description:

Cnti Bank B Worth Heas. Rod Swap Ref. Bank Reference Proc No /Section: 2-PT-94.0 Sequene.e Step No 6 11 Bank Positions (Steps) lRCSTemperature('T): $47 Test Power Level (% F.P. ): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB:Hoving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 547.S Power Level (*. T.P. ): 0 Test Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB.Hoving CC: 228 CD: 22S Below Nuclear Heating Date/ Time Test Performed: Hinha 05G RET Measured Parameter I B ; Integral Worth of Cnti Bank B, (Description) All Other Rods Out IV REF g][, $ Test Heasured Value I = g Results l Design Value REF (Design Conditions) I = 1288 1 129 pcm g lTechnicalReportNE-885,Rev.O Reference If Design Tolerance is exceeded,_SNSOC shall evaluate impact of test rasult V FSAR/ Tech Spec on safety analysis. SNSOC may specify Acceptance that additional testing be performed. Criteria Reference VEP-FRD-36A /YES___,NO Design Tolerance is met VI Acceptance Critoria is met / YES _ _N0 Comments Prepared By: tu 'w Reviewed By: -NE-895 N2C9 Startup Test Report Page 45 of 55

NORTH ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Critical Boron Concentration B Bank In Reference Proc No /Section: 2-PT-94.0 Sequence Step No: 4 1 II Bank Positions (Steps) RCS Temperature ('F): $47 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: O CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 5 Wi Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: O CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: i

v42 /92 / orv2.

Meaa Parameter (C )'qg B; Critical Boron Cone - B Bank In IV (Lescription) I Hessured Value (C ) B Test (Design Cond) Results = Design Value C3 = 1864 + AC t (10 + 128.8/ loc I)PP8 B (Design Cond) B " kl@ 07p" 1 ff C ti PP l1echnicalReportNE-885,Rev.O -Reference FSAR/ Tech Spec l Not Applicable V Acceptance l Criteria Reference Not Applicable ! Design folerance is met V'YES ____NO l Acceptance Criteria is met

v"YES

_NO i VI Comments aC3 = -6.81 pcm/ppe Prev .M aC = (C )ARO - 2053 B B l i j Prepared By: bt tl N % bd DS i/M/k Reviewed By: i NE-895 N2C9 Startup Test Report l'ag e 46 of 53

NORTri ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSf%2 TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cnti Bank D Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-94.0 Sequence Step No: F II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions 3DA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: Moving CC: 228 CD: Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 5C. 2 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: Moving CC: 228 CD: Moving Below Nuclear Heating Date/ Time Test Performed: 4/2M J lilq Meas Parameter RS (Description) ID ; Int Worth of Cntl Bank D-Rod Swap IV RS ( Adj. tieas. Crit. Rpf Bank Test Measured Value I = '180.1 Position g {, steps) D Resulta y., Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) ID " M 0) + imposition = l'"10 steps) m. t.1 .w RS Design Value ID= 941 1 141 pce (Critical Ref Bank (Desigt. Cond) Position = 164 steps) Reference Technical Report NE-885, Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria Reference. VEP-FRD-36A Design Tolerance is mLt

- YE? y 0 VI Acceptance Criteria is met
./ Y2S J

Comments PreparedBy:k Db Reviewed By: kd b d et NE-895 N2C9-Startup Test Report Page 47 of 55

( NORTH ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cnti Bank C Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-94.0 Sequence Step No: 9 II Bank Positions (Steps) RCS Temperature ('F): 547 Power Level (1 F.P.): O Test Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: Moving CC:MovingCD: 228 Below ?!uclear Heating III Dank Positions (Steps) RCS Temperature ('F): po,8 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB Mc,ving CC:MovingCD: 228 Below Nuclear Heating Date/ Time Test Performed: 4/2 ';:./9 2. 6c Meas Parameter g3 (Description) IC ; Int Worth of Catl Bank C-Rod Swap (Adj. Meas. Crit. Ref Bank IV RS Test Measured Value I

  • D.6 Position = H9.0 steps)

C Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actua1 Cond) I = %"J.G t.115 Position = P49.(, steps) C RS Design Value IC= 765 t 115 pcm (Critical Ref tank (Design Cond) Position = 142 steps) Reference Technical Report NE-885, Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria Refarence VEP-FRD-36A Design Tolerance is met s YES NO YES N0 VI Acceptance Criteria is met v Comments b bu d Nw Prepared By: btk T>eb-Reviewed By: i NE-895 N2C9 Startup Test Report Page 48 of 55

NORTil ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cnti Bank A Worth Measurement Rod Swap Reference Proc No /Section: 2-PT-94.0 Sequence Step No: /0 3 II Bank Pcsitions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: Moving Other (specify): (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 54*7. Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: Moving Other (Specify): (Actual) CB: Moving CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: 4 ftd41 ItL4 Meas Parameter RS (Description) 13 ; Int Worth of Cnti Bank A-Rod Swap g3 ( Adj. Meas. Crit. Ref Bank IV Test Measured Value I = 2.13. l Position = n.9 steps) g Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) I = 2.7.1. l ! 100 Position =73.9 steps) A RS Design Value IA= 236 100 pcm (Critical Ref Bank (Design Cond) Position = 82 steps) Reference Technical Report NE-885, Rev. O, VEP-FRD-36A If Design Tcleracce is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria Reference VEP-FRD-36A Design Tolerance is met

s YES

__NO VI Acceptance Criteria is sat _<__.YES ___NO Comments Prepared By: ISb d EdL.te Reviewed By: 9. NV.-895 N2C9 Startup Test Report Page 49 of 55

NORTil ANNA POWER STATION UNIT 2 CYCII 9 STARTUP PilYSICS TEST RESULTS AND EVALUATION SilEET i I ' Test

Description:

Shutdown Bank B Worth Meas. Rod Swap Reference Proc No /Section: 2-PT-94.0 Sequence Step No: // 11 Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P. ): O Conditions SDA: 228 SDB:MovingCA: 228 Other (specify): (Design) CB: Moving CC: 228 CD: 228 Below Nuclear lleating 111 Bank Positions (Steps) RCS Temperature ('F): 547 4 Test Power Level (% F.P.): O Conditions SDA: 228 SDB:MovingCA: 228 Other (Specify): (Actual) CB: Moving CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: 4 l21/4 2. f UI4 Mess Parameter RS (Description) Igg; Int Worth of Shutdown Bank B-Rod Swap g3 (Adj. Meas. Crit. Ref P,ank IV Test Measured Value 1 = IO M Position = lf(,.0 sters) 33 Rasults Design Value RS (Adj, Meas. Crit. Ref Bank ( Actual Cond) I = 916.5 t L 4 8' Position = g g steps) SB RS ~79 1 147 Pcs (Critical Ref Bank Design Value I / SB (Design Cond) Position = 169 steps) Reference Technical Report NE-885, Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria Reference VEP-FRD-36 A l Design Tolerance is met IYES_,,__NO VI lAcceptanceCriteriaismet

L YES _.NO Comments Prepared By: YL IMb Reviewed W

NE-895 N2C9 Startup Test Report Page 50 of 55

U a0RTH ANNA POWER STATION UNIT 2 CYCLE + STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET )Q ' - ' Test Ducription: Shutdown Bank A Worth Meas. - Rod Swap Reference Proc No /Section: 2-PT-94.0 Sequence Step No: 11 ^ !BankPositions(Steps.) RCS Temperature ('F): 547 Power Level (% F.P

0

} J JA:MovingS9B: 2a CA: 228 lOther(specify): ) CB: Moving CC: 228 CD: 228 j Below Nuclear Heating M Ii ' 4r:k Positicas (Gteps) RCS Tempcate.e ('F): 4T 7 4 ? S~ Power Level (% F.P.): O Cat SDA:MovingSDB: 228 CA: 228 Other (Specify): (Ac m l CB: Moving CC: 228 CD: 228 Below Nuclear Heating } i Date/ Time Test Performed: ! V/2 Mf:. /3// hans Parameter g3 (Description) ISA; Int Worth of Shutdown Bank.\\-Rod Swap

.-dj. Meas. Crit. Ref Bank IV RS
  • /887 O Po8iti n */24.48teP8)

Test heasured Value,ISA Results ( Adj. Meas. Crit. Ref Bank Design -s'ue g3 Actual :. awl s 1 = /o4 4.i~: /5? Position =f 7g,g ste.ps) 33 i RS 1063 1 159'pcm (Critical Ref Bank Design '21ue I = SA (Design Cond) Position u 180 steps) u h deference Technical Repcr t NE-S85, Rev. O, VEP-FkD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSCC may specify that Accepance additional testing be performed. Criteria Reference VEP-FRD-36A /YES ___NO ' Design Tolerance is net VI Acce.ptance Criteria is met ' YES ,_,_,,NO Con.nents I 'IJ h 12 bb Reviewed By: / d,/ Prepared By: I NE-895 N2C9 Startup Test Report Page 51 of 55 i

NGR111 ANNA POWER STATION L* NIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth - Rod hap Reference Proc No !Section: 2-PT-94.0 Sequence Step Ho: / 2. II Bank Positions (Steps) RCS Temps. tre ('FT: 547 Tut Power Level _; F.P.): O Conditions SDA: Moving SDB: Moving CA: Moving Other (specify): (Design)- CB: Moving CC: Moving CD: Moving Belov Nuclear Heating III - Bank Positions (Steps) RCS Temperature (*F): Eh1 Test Power Level (7. F.P.): 0 Conditions SDA: Moving SDB: Moving CA: Moving Other (Specify): (Actual) EB :lloving CC: Moving CD: Moving Below Nuclear Heating Date/ Tin.e Test Pecformed: I /I21.l91 0M> Meas Parameter (Description) ITotal; Int Worth of All Banks - Rod Swap N IV Test Measured Value ITotal = 532.6 3 re-Results Design Value (Actual Cond) ITotal

  • F 2. 70 9 : 527 re-Design Value ITotal = 5272 1 527 pcm (Design Cond)

Reference Technical Report NE-885, Rev. O, VEP-FRD-36A ~ If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. Additional testing Acceptance must be performed. Criteria Reference 5EP-FRD-36A l-Design Tolerance is met / YE 4 ___NO VI Acceptance Criteria is met " YES _,._NO . Comments -Prepared By: bS$m M bd-w 'eviewed By: I II 9-l NE-895 N2C9 Startup Test Report Page 52 of 55

l NORTH ANNA POWER STATION UNIT CYCLE 9 STARTUP PHYSICS TPST RESULTS AND EVALUATION SHEET Test Descr:,otton: M/D Flux Map-At Power Reference i Proc No / dection: 2 PT-94.0,2-FT-21.1 Seouance Stoo No: gy [ Bank Positions (Steps) , Power Lavel (7. F.P. ): s$ n RCS Tempersture ('F):I Test Conditions SDA: 225 SDB: 225 CA: 08 I l.Other(sp.,ify): (Design) l CB 228 CO CD: Must have 18 thieblesu* Bank Postetens (Steps) i RCS Temperature ('F): 78 t-F Tes: Power Level (* F.P. ): 30.C'7o Conattionsi SDA: 203 3DB: 228 CA: 226 lOther(Spectfy): Actual) C3

23 225' CD
/43 q(, fA,% bLc5 Cate/ Time Test Pertornea:

-l Int 92 '( '17 l ' MAX. REL NUC ENTHALk TOTAL HEAT. NAXIMUM PD$. IV Maas Parameter: ASSY PVR RISE HOT l' LUX HOT INCORE ( Des cr tpe ton )

  • DIFF CHAN FACT CHAN FACT QUADRANT j(M-P)/P F-dN(N)

F-Q(Z) POWER TILT MeasuredValuelh10.96.4 la ! f,. bl 2 '72-b Oll Test -f O ' g r.e 9 Resu!u f ( Des ign Conas il <rt. =. e.iIig p gj Design Value NA NA S 1.0213 WCAP-7905 l !WCAP-7905 i Se W ence ) REV.1 f NONE { NONE lREV.1 I t V FSAR/ Tech Spec NONE Y" Acceptance; NONE

rtteria

= I i Reference NONE !TS3.2.3 TS ".2.2 j NONE l i Design Tolerance is met / YES N0 Acceptance Criterta is ont f_YES NO VI 20mments

  • As Recutrea

'* Must nave at least 16 thtmoles for quarter core Saos for multi point calibrattonn. ?recareo By: 0* db W R ytewee gy: NE-895 N2C9 Startup Test Report Page 53 of 55

l l NORTl! ANNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test Descriotton: M/D Flux Map-At Power Reference Proc ho / Section: 2-PT-94.0.2-PT-21.1 Sequence Sten Ho: 3 II Bank Positions (Steps) RCS Temperature ('F):T 11 R b 75% Test Power Level (% F.P. ): S Coaditican SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB 228 CC : CD:

  • Hust have 2 38 thimbles **

III Bank Positions (Steps) RCS Temperature ( *F):Trer Test Power Level (". F.P. ): '1Z.F 1 Conditions' SDA: 228 5DB: 228 CA: 228 0:: hor (Specify): (Actual) CB 228 CC 226 CD: # 8 st eu "ihm Wi j Date/ Time Test Perfo med: 4/21l9s .2 A 30 MAX. kEL NUC ENTRAL. TOTAL REAT MAXIMUM POS. IV Maas Parameter ASST PWR RISE Har ITEX HOT INCORE (Descuption)

7. DIFF CHAN FACT CHAN FACT QUADSANT (M-P)/P F-dH(N)

F-Q(Z) POWER TILT 5.3 % 4r Measured Value P3CAc 1.M6 . C -} 7 3 ,ocxn l Test +S % f*r Results

  1. " A" Design Value (usaign Conds) <*,".1'!,...,* ';'

NA NA 5 1.0207 VCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REY.1 V FSAR/ Tech Spec NONE E**"'*" '#8"* " NONE Acceptance Criterta Referenca NONE TS 3.2.3 TS 3.2.2 NONE Design Tolerance is est Y TES NO Acceptance Criterta is set / YES ,_NO VI Consents

  • As Recutred
  • '* Mus t nave a t least 16 thimbles for quarter core maps l

for multi point calibtations. Prepared By: N )OW Revxewed By: NE-895 N2C9 Startup Test Report Page 54 of 55

NORTH \\NNA POWER STATION UNIT 2 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND E'!ALUATION SHEET f Test De::cription: M/D Flux Map-At Power Reference i Proc No / Section 2-PT-94.0,2-PT-21.1 Sequence Step No: gg II Bank Positions (Steps) RCS Temperature ('F):T il p Test Power Level t; F.P.): 9 100% Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB : 228 CC. 228 CD: Must have 2 38 thimblas** III Bank Positions (Steps) RCS Temperature (*F): Tc.cr Test Power Level (% F.P. ): qq,46 % Conditions SDA: 228 SDB: 223 CA: 228 Other (Specify): (Actual) CB 228 CC : 228 CD: 22'( g g l Date/ Time Test Performed: l 5'-I42. 032c } MAX. REL NUC ENTHAL TOTAL HEAT MAXIMUM POS. IV Meas Parameter ASSY PVR RISE HOT FLUX HOT INCORE (Description)

DIFF CHAN FACT CHAN FACT QUADRANT (M-P)/P F-dH(N)

F-Q(Z) POWER TILT '- 4.9 % wA P 2 o..w I.4104

f. SIT 6

!,0089 Measured Value 49g g Test P c O.90 Results Design Value igggag (Design Conds) o,

  • e. i NA NA S 1.0211

!WCAP-7905 WCAP-7905 l REV.1 NONE NONE , REV.1 { Rsference

  • * * ' ' " " "~'

Y FSAR/ Tech Spec NONE NONE Acceptatice Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE Design Tolerance it; met / YES,_ NO Acceptance Criteria is met 7 YES NO 1 VI Coso nts

  • As Required

. ** Must have at leest 16 thiebles for quarter eire maps l for multi point calibratiot s. I- ~ Ah Prepared By: Reviewed By: -NE-895 N2C9 Startup Test Report Page 55 of 55 _____________ - ___ _ -}}

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