Text

Rev 0 to North Anna Unit 1 Cycle 9 Startup Physics Test Rept
	ML20077E619
Person / Time
Site:	North Anna
Issue date:	06/04/1991
From:	Main A, Nicholson A, Trace D; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
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ML20077E614	List: ML20077E610; ML20077E619;
References
	NE-840, NE-840-R, NE-840-R00, NUDOCS 9106110119
	Download: ML20077E619 (61)
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I TECliNICAL REPORT NE-840 - Rev. O I

I NORTil ANNA UNIT 1, CYCLE 9 STARTUP PilYSICS TESTS REPORT I

I NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES I VIRGINIA POWER MAY 1991 I

I

-Y A L \% 5/2)[9 g I PREPARED BY: u, A. 11. Nicholson Date REVIEWED BY: m L3 desbf

" D. A. Trace Date

~

/' 625 V/

REVIEWED BY: _ A. P. Main Date APPROVED BY:

' # "" r $~/2y/9, D. Dziadosz Data QA Category: Nuclear Safety Related Keywords: NIC9, Startup I

I !

1 CLASSIFICATION / DISCI. AIMER I

, The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the l Company), and they may not be appropriate for use in situations other than ;

those for which they have been specifically prepared. The Company tLorefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability, In pa r t. i cu l a r , Tile COMPANY MAKES NO WARRANTY OF MERCllANTABILITY OR FITNESS FOR A PARTICULAR

! PURPOSE, NOR SilALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING

'I OR USAGE OF TRADE, with respect to this report or any of the data, I

techniques, information, or conclusions in 4t. By making this report l available, the Company does not authorize its use by others, and any such use 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 orovided 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 propert.y damage, 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, l techniques, information, or conclusions in it.

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NE-840 NIC9 Startup Physics Tests Report Page 1 of 59

TABl.E OF CONTENTS i

y PAGE s

C l a ss i f i ca t ion /Di r,cla ime r . . ..............,... .... .... 1 Table of Contents.............. .......... ........... . 2 1.ist of Tables.......... ....... ..... .......... .. .. 3 I.ist of I'Jgures.. ....... ... ... ....... .. .. .. .. 4 I Preface. .......... . .. .. .. .. ...... ... . ... . 5 Section 1 Int rcxtuct ion and Summary. . . . . .. ... ...... 7 Section 2 Control Pod Drop Time Measurements. ...... 16 SocL %n 3 Control Rod Bank Worth Measurements........ 21 Section 4 Boron Endpoint and Worth Measurements...... 26 Section 5 Teinperature Coe f f icient Measurement . , . . 30 Section 6 Power Distribution Measurements., ..... ... 32 Section 7 References... .... ...... ...... .... . .. 39 i APPENDIX Startup Physics Tests Results and Evaluation Sheets.. . .... .. ... ... 40 t

NE-840 NIC9 Startup Physics Tests Report Page 2 ot ;9

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

l t LIST OF TABLES I *a AI I,C TITLE i

PAGE

.' . 1 Chronology of Tests...... . . . . . . . . . . . . . . . . . . . . . . . . . . 10 j 2.1 llot Rod Drop Time Summary.. . . . . . . . . . . . . . . . . . . . . . . . . 18 3.1 Control Rod Bank Worth Summary........................ 23 4.1 lio ron Endpo int s Summa ry . . . . . . . . . . . . . . . . . . . . . 28 1

5.1 Isothermal Temperature Coef ficient Summary. . . . . . . . . 31 l 6.1 Incore Flux Map Sumnary.... . . . . . . . . . . . . . . . . . . . . 34

! 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specification Limits. . . . . . . . 35 I

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1.lST OF FICURES FICURE TITI.E PAGE I

1.1 Core 1.oading Map.... . ........................... .. ... 11 1.2 lleginning of Cycle fuel Assembly flurnups. ... ... ....... 12 l

1.3 Available Incore Moveable Detector 1.ocations..... .. .... 13

! 1.4 Hurnable Poison and Source Assembly I.ocations. . . 14 1.5 Control R(xl I.ocalicns.. ... ... . . ..... . . .. ... 15 l

2.1 Typical Rod Drop Trace... ..... ............. . .... 19 l 1

2.2 Rod Drop Time - llot Full Plow Corulitions. ... ........ .. 20 3,1 llank 11 Integral kod Worth - IlZP. . .. ..... .. ........ 24

3.2 Bank 11 Dif ferential Rod Worth - IlZP. , ................... 25 4.1 lioron Worth Coefficient... ... . .... . .. ........... 29 6.1 As s emb l y v i s ti Power Dist.ribution - 24% Power... .. .... . 36 i

i 6.2 Assemblywis o Power Dist ribut ion - 70% Power. . ........ .. 37 l

6.3 Assemblywise Power Dist ribut ion - 997. Power. .. . ... .. 38 I

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NE-840 NIC9 Startup Physics Tests Report Page 4 of 59

. , _ _ = . . _ _ . _ . _ _ _ _ _ , __ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ . . . _ . . _ . _ _ - - _

~

V PREl' ACE This report presents the analysis and evaluation of the physics testr.

which were performed to verify that the North Annn 1, Cycle 9 core could I be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the ietailed data taken. Standard testing techniques and methods of data analysis were used. The test data ,

results and evaluations, together eith the detailed startup procedures, are on file at the North Anna Power Station. T' are fore , only a cursory discussion of these items is included in this report. The cnalyses presented include a brief summar of each test, a comparison of the test results with design predictior.s, and an evaluation of the results.

The North Anna 1, Cycle 9 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test result s. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test resultt 5) acceptance c r i t.e r i a , and ti) comments concerning the test. These sheets provide a compact summary of the startup 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 i design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and fuel Group! During the tests, the data sheets were used as guidelines both to verity that the proper test conditions were met and to facilitate, the preliminary NE-840 NIC9 Startup Phyrics Tests Report Page 5 of 59

i compar ison between measured e.nl predicted t est results, thus enabling a quick identification of possible problerns occuring during the tests, u

i i

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4 NE-840 NIC9 Startup Physics Tests Report i'a g e 6 of 59

SECTION 1 L

INTRODUCTION AND

SUMMARY

I On January 12, 1991 Unit No. I cf the North Anna Power Station shutdown for its eighth refueling. During this shutdown, 93 of the 157 fuel assemblics in th9 core were replaced with 68 fresh fuel assemblies, E one once-burned fuel assembly, and 24 twice-burned fuel e semblics. The ninth cycle core consists of 11 sub-batches of fuel: five once-burned batches, four f rom Cycle 8 (batches 10A,100,10C, and N2/98) and one f rom Cycle 7 (batch 9B); four twice-burned batches, one from North Anna 1 Cycles 5 and 6 (batch 7A), two from North Anna 1 Cycles 6 and 7 (batches 8A and 88), and one f rom North Anna 2 Cycles 4 and 5 (batch N2/ti); and two fresh batches (batches llA and 11B). The two fresh batches of fuel assemblies have top and bottom grids of Inconel-718 while the inner six l grids are made of Zircaloy-4 (all reload batches have eight grids made of Inconel-718). Cycle 9 incorporates a new burnable poison rod design made of BC4 in Alumina, which is available in various enrichments of Il 4C . Six core ;ocations occupied by neither control rcxl banks nor burnable poison assemblics will have demonstration thimble plugging devices inserted. Twenty-four peripheral assemblies will have baffle clips mounted on them to help protect against baf fle jetting degradation.

The center assembly, /?2 of batch 9B, is a test assembly which is part of the demonst ration corrosion prcgram, it contains several rods clad in Zirconium-based advanced alloys instead of the standard Zircaloy-4 1

NE-840 NIC9 Startun Physics Tests Report Page 7 of 59

l cladding as well as 18 replacement 1.9 w/o U-235 fresh fuel rext s .

Reference 1 provides a more detailed description of the Cycle 9 core.

The core loading pattern and the design parameters for each sub-batch ao shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2.

The available incore moveable detector loca' ions used for the BOC flux map analysis are identified in figure 1.3. Figure 1.4 id e n t. i f i e s the location and number of burnable poison rods and source assemblies for

[ Cycle 9, and Figure 1.5 identifies the location and number of cont rol rods y in the Cycle 9 core.

On March 7, 1991 at 2301, the r.inth cycle core achievnd initial cr i t ica l i t y . Following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the results of these tests follows:

1

1. The measured drop time of each control rod was within the 2.7 second limit of Technical Specification 3.1.3.4.

2. Individual cont;ol rod bank worths were measured using the rod swap technique ' and the results were within 3.4% of the design preuictions. The sum of the im.li". dual measured cont rol rcxl bank worthe was within 0.2% of the design prediction. These results a e within the design tolerance of 115% for individual bank worths (110% for the rod swap reference bank worth) and the design tolerance of 110% for the sum of the individual control rod bank worths

3. M e r..> u r ed critical boron concentrations for two control bank con f igu ra t ion., were within 32 ppm of the design pred ict ions .

NE-840 NIC9 Startup physics Tests Report page 8 of 59

I l

I These results were within the design tolerances and also met the t

Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 1 1 ', Ak/k of the design prediction.

4 The boron worth coef ficient measurement was within 1.2% of the design prediction, which is within the design tolerance of 110%.

5. The measured isothermal temperature coefficient (lTC) for the all-rods-out configuration was within 0.85 pcm/'F of the design prediction. This result is within the design tolerance of 13 pcm/'F. The measured ITC of -0.90 pcm/'F meets the Technical Specificat!nn 3.1.1.4 criterion that the moderator temperature coefficient (MTC) he less than or equal to 46.0 pcm/'F. When the Doppler temperature coefficient and a 0.5 pcm/'F uncertalaty are {

accounted for in the MTC limit, the MTC requirement is satisfied as long as tne ITC is less than or equal to +3.75 pcm/'F.

6. Mode 1 (See Reference 4) core power 2 stributions were within established design tolerances. Generally, the measured core power distribution was within 1.8% of the design predictions.

The heat flux bot channel factors, F-Q(T), and enthalpy rise hot channel factors, F- Dil( M) , were within the limits of Technical Specifications 3.2.2 and 3.2.3, respectively, in summary, all startup physics test tesalts were acceptable Detailed results, specific design tolerances and acceptante criteria for each measurement are presented in the following sections of this report.

NE-840 NIC9 Startup Physics Tests Report Page 9 of 59 l

l

3 Table 1.1 L

NORTil ANNA 1 - CYCI,E 9 STARTUP PilYSICS TESTS

' CilRON01,0GY OF TESTS lr Reference Test Date Timo Power Procedure 110t Rod Drop - Itot Full Flow 03/07/91 0930 IISD 1-PT-17.2 Zero Power Testing Kange 03/08/91 0005 llZP 1-PT-94.0 React.!vity Computer Checkout. 03/08/91 0032 IlZP 1-PT-94.0 Boron Endpoint - ARO 03/08/91 0320 ll7P 1-PT-94.0 lp 0436 IlZD 1-PT-94.0 Temperature Coefficient - ARO 03/08/91 Bank B Wortn 03/08/91 0534 ilZP 1-PT-94.0 g Boron Endpoint - B in 03/08/91 1105 llZP 1-PT-94.0 g Bank SA Worth - Rod Swar 03/08/91 1136 it ?.P 1-PT-94.0 Bank SB Worth - Rod Swap 03/08/91 1301 IlZP 1-PT-94.0 Bank A Worth - Rod Swap 03/08/91 1349 ilZP 1-PT-94.0 Bank C Worth - Rod Swap 03/08/91 1419 llZP l-PT-94.0 lp Bank D Worth - Rod Swap 03/08/91 1454 IlZP 1-PT-94.0 Flux Map - 24*. Power 03/10/91 1123 2 4 *. 1-PT-21.1 g Flux Map - Peaking Factor 03/11/91 1125 41?. 1-PT-21.1 g Verification Flux Map - Peaking Factor 03/12/91 1431 7 0 *. 1-PT-21.1 Verification Flux Map - Poaking Factor 03/13/91 0802 8 9 *. 1-PT-21.1

= Ve r i f i ca t. f or.

Flux Map - Peaking Factor 03/13/91 2358 94*. 1-PT-21.1 lp Verification Flux Map - Monitor FQ(Z)/K(Z) / 03/19/91 1108 9 9 *. 1-PT-21.1 Ilot Full Power Flux Map - Monitor FQ(Z)/K(Z) 03/25/91 1525 9 9 *, 1-PT-21.1 Flux Map - I/E Calibrat. ion 04/01/91 1402 9 9 *. 1-PT-21.1 Flux Map - 1/E Calibration 04/02/91 0627 9 9 *. 1-PT-22.2 lFluxMap-I/ECalibration l04/02/91 1727 99* 1-PT-22.2 I

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ll NE-840 NIC9 Startup Physics Tu.ts Report. Page 10 of 59 l

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i NE-840 NIC9 Startup Physics Tests Report Page !? of 59 J

Figure 1.3

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i NE-840 NIC9 Startup Physics Tests Report Page 13 of 59

, _ .._ _ ._ _.__ _ _ _.___ _ ._ _ _~___ _ _ __._._ _ ___._ _ _ _._ __.-

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Function Number of Cluster s Control Bank D 8 Control Bank C 8 Control Bank B 8 Control Bank A 8 thutdown Bank $B 8 Lhutdown Bank SA 8 SP ( Spar t. Rod Locations) 8 NE-840 NIC9 Startup Physics Tests Report Page 15 of 59

J lI j SECTION 2 il I

CONTR01,it0D DROP TIME MEASUREMENTS t

l The drop time of each control cod was measuted at hot full-flow

reactor coolant system (1:CS) conditions in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot i

jI was less than or equal to the maximum allowed by Technical Specification 3.1.3.4. The concrol rod drop times were measured in Mode 3' with the i RCS Tavg above 500'P and all reactor coolant pumps operating.

The rod d rop t imes were measured by withdrawing a rod bank to its ,

fully withdrawn position, and removint; the moveable gripper coil fuse and 1 stationary gripper coil fuse for the particular rod of the bank to be

!I j dropped. This allowed the rod to drop into the core as it would during ,

i a plant trip. The stationary gripper coil voltage and the Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded to

{

determine t he rod d rop t im e . This procedure was repeated for each control I

rod.

l As shown 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 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 function of control rod velocity. As the rod 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.

g xc.e o xice Sta, tup Physic, 1 cst,Repo,t Page le of se

._. .. .._. _..-.- - --. _ _- _. -.--.-- -.- -. __ - --._ - - - _. _- --~..

1 4

3 1

5 The measured drop times for each control rod are recorded on Figure 1

2.2. The slowest, f astest , and average drop times are surnmar f r.ed in Table i

j 2.1. Technical Specification 3.1.3.4 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot ent ry of 2.7 seconds with the RCS at hot, full flow conditions. These test results

! satisfied this limit.

1 il 4

1

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t

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I 1

i Table 2.1 NORTil ANNA UNIT 1 - CYCL.E 9 STARTUP PilYSICS TESTS Il0T ROD DR0l' TIME

SUMMARY

I ROD DROP TIME TO DASill'OT ENTRY I

SEOWEST ROD FASTEST ROD AVERAGE TIME I B-06 1.83 sec, 11 - 0 2 1.52 sec, 1.02 sec.

I I

I 1

g xE.se xic, - m.,,1csre,m K ,cm e. Is .< e

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l Figure 2.1 NORTil ANNA UNIT 1 - CYCI.E 9 STARTUP PIIYSICS TESTS TYPICAL. ROD DROP TRACE

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ROD DROP TIME MEASUREMENT I

5 NE-840 NIC9 Startup Physics Tests Report Page 19 of 59

9

I l.

I l'igu re 2.2 i

NORTil ANNA UNIT 1 - CYCL.E 9 STARTUI' l'IlYSICS TESTS

! ROD DROP TIME - 110T FUI.l. Fl.0W CONDITIONS i

lI 4

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. I _. l ._ l 1._ _, I _ _ l i l I l_. 1 I e I I i l i l I i l i j i I i 1 1.s* 1 1 1.6* I I I I 15 l I I I__i i 1._ I ____. l .- _. I 1 i i i i l 4 I l i 1,77 I l I.66 l l 1.67 I i 14 I . I 1 _ ____1 l l ___ I I i

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i lI i

lI j SECTION 3

!I I CONTR01. HOD llANK WORTil MEASUREMENTS

!I 1

4 Control rod bank worths were measured for the control and shutdown banks using tbc rod swap technique, The initial step of the rod swap l method diluted the predicted most reactive control rod bank (herea f t er i

jg referred to as the reference bank) into the core and measured its i

Sg reactivity worth using conventional test techniques. The reactivity I

changes resulting from the reference bank movements were recorded j continuously by the reactivity computer and were used to determine the

differential and integral worth af the reference bank. For Cycle 9, i

i Control Bank B was used as the reference bank.

1 After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron i

! concentration were stabilized with the reactor just critical and the 4

reference bank near full insert ion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully lE

[

inserted positton and recording the core rea c t. iv i t y and mcxh rator temperature. From this point, a rod swap maneuver was performed by j withdrawing the reference bank several steps and then one of the other control rod banks (i.e., a test bank) was inserted to balance the 2

i reactivity of the reference bank withdrawal. This sequence was repeated lI 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.

1 NE-840 NIC9 Startup Physics Tests Report Page 21 of 59 1

L __ _ _ _ _ _ . _ . . . _ _ . . _ . _ _ . _ _____ _ _ . _ _ _ . _ - _ _ _ _ . _ _ _ _ _

m l The core reactivity, moderator temperature, and the dif ferential worth of the reference bank were recorded with the reference bank at t he MCI' .

The rod swap maneuver then was repeated in reverse such that the ref erence bank again was near full insertion with the test bank fully withdrawn from the core. This rod swap process was then repeated ter 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 cont rol and shutdown banks were within the design tolerance ( 110'. for the reference bank, and 115* or 100 pcm, whichever is greater, for the test banks). The sum of the individual measured rod bank worths was w i t.h i n 0.2', of the design prediction. This is well within the tesign tolerance of 110' for the sum of the individual control rod bank worths.

The integral and dif f erential 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 illust rate their agreement. In summary, the measurea rod worth values wer< satisfactory.

I NE-640 NIC9 Startup Physics Tests Report Page 22 of 59 l

m Table 3.I NORTil ANNA UNIT 1 - CYC1.E 9 STARTUI' PilYSICS TESTS CONTROL. ROD BANK WORTil

SUMMARY

MEASURED l'KEDICTED PEEL t.N i DIFFERENCE WORTil WORTil ('4 )

14ANK (PCM) (PCM) (M-P)/l X 100 ll-Reference llank 1214.4 1207.0 0.6 i SA Sli A

897.6 1047.5 266.9 6'11.5 1040.6 256.2 0.7 0.7 3.4

C 807.8 819.8 -1.5 I D Total Worth 1004.8 5239.0 1014.3 5231.4

-0.9 0.2 I

liifference is less than 100 pcm.

I I

I -

1 I

NE-840 N1C9 Startup Physics Tests Report Page 23 of 59

= . . - - . - .

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I I

I 4

I

~ _ . _ _ _ _ _ _ _ _ . _ _ _

I

" I SECTION 4 r

BORON ENDPOINT AND WORTil MEASUREMENTS l I

l l

Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (KCS) boron concentrations were treasured at selected rod bank

, configurations to enable a direct comparison of measured boron endpoints with design predictions. For each c r it ica l boron concentration measurement, the KCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured i

I critical boron concentration values wcro made to account for off-nominal

, control rod posit ion and moderator temperature, if necessary, The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values

, were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical l Specification 4.1.1.1.2 regarding core reactivity balance. In summary, the boron er.opoint results were satis f actory.

i I Boron Worth Coefficient I

E The measured boron endpoint values provide stable statepoint data f rom which the boron worth coef ficient or dif ferential boron worth (DBW) was determined. By relating each endpaint concentration to the integrated rod worth present in the core at the time of the endpoint rneasurement, g xE. m xice ta,t, rhys ic,1est, x,o,t rame s - ,e

i 4

I

!I

, the value of the DFW over the range of boson endpoint concentrations was obtained, I

l A plot of the boron concent rat ion versus inserted cont a al rcx! wor t h is shown in Figure 4.1. As indicosed in this figure and in the Appendix, the measured DBW was 6.82 pcm/ ppm. This is within 1.2*. of t he predicted l value of -6,90 pcm/ ppm and is well within the design tolerance of 110;.

In summ:iry, the measured baron worth coefficient was satisfactory. ;

I i

t II 4

4

!I i

a

!I J

ll NE-8a Nic9 surtup Physics Te ts Report Page 27 of 59

_ _ . _ . _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ . . . . _ _ _ _ . __ __~._

4 1

j Tabic 4.1 NORTil ANNA UNIT 1 - CYCII 9 (TARTUP PilYSICS TESTS !

! Il0RON ENDPOIN.,

SUMMARY

i i

iI

,! i Measured Predicted Difforence

! Control Rod Endpoint Endpoint M-P I

Configuration (ppm) (ppm) (ppm) l '.

i ARO 2123 2091 +32 f

B liank in 1945 1948* -3 ig i

!

The predicted endpoint for the B Bank In configuration was i f aljusted for the differenco between the measured and predicted .

l values of the endpoint taken at the ARO con figurat ion <is shown

in tbc baron endpoint Startup Physics Tests Results and l Evaluation Sheets in the Appendix.

!I i

1 i

i

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lI jg sE-sco sic 9 startuP Physics T<sts report Paae 28 of 59 N

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[ l'is,ure 4.1 NORTil ANNA UNIT 1 - CYCL.E 9 STARTUP l'IlYSICS TESTS Il0RON WORTil COEFFICIENT I

I I

3 1,e00 -- Measured DBW = -6 82,pcm/ ppm i

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i 1eso 1suo 2000 20'2o 2040 .oso taso 21'c0 2iro 2140 BORON CONCENTRATION (PPM) l NE-640 NIC9 Startup Physics Tests Report Page 29 of 59 '

,I a

n I SECTION 5 I

TEMPERATURE COEFFILIENT MEASUREMENT i

The isothetmal temperature coefficient (lTC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS)

! temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity j changes on the reactivity computer. This t e s t. sequence included a i

cooldown followed by a heatup.

Reactivity was measured during the RCS cooldown of approximately S.5'r and the RCS heatup of approximately 3.3'F. Reactivity and ,

temperature data were taken from the reactivity computer and strip chart recorders. Using the statepoint me t hcxi , the temperature coefficient was I

determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured l ITC.

i The predicted and measured isothermal temperature coefficient values I

a re compared in Table 5.1. As can be seen f rom this summary and f rom the S ta rt u;) physics Tests Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of 13 pcm/'F. The mcxlerator temperature coef ficient was determined to be +0.85 pcm/'F which met the requirements of Technical Specification 3.1.1.4. In summary, the measured result was satisfactory.

NE-840 NIC9 Startup Physics Tests Report Page 30 of 59

l I l i Table 5.1 NORTil ANNA UNIT 1 - CYCL.E 9 STARTUl' l'ilYSICS TESTS ISOTilERMAL TEMPERATURE COEFFICIENT

SUMMARY

I . . ,

ISOTHERMAL TEMPERATURE COEITICIENT l BANK TEMi'ER ATURE BORON (PCM/'F)

POSITION RANGE CONCENTRATION ,

('F)

! (ppm) C/D ll/U AVE. DlFFER.

l MEAS. PRFD. (M-P) ,

i i

(

l 544.1 i D/204 to 2119 -0.73 -1.06 -0.90 -0.05 -0.85 j 549,6 i

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lI i

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I g xE-e40 N>ce te,< ,esx ,1c,T ,<,R ,,,< r s. 31 .< e

i l

l l SECTION 6 l I POWER DISTRIBUTION MEASUREMENTS The core power distributions were measuied using the moveable incore detector flux mapping system. This system consists of five fission chamber detectors which trsverse fuel assembly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available locations monitored by the moveable detectors for Cycle 9. For each traverse, the Ii detector voltage output is cont inuour. ly iron i t o r ed on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using the Westinghouse computer program, INCORE'. INCORE couples the measured voltages with predetermined 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 i program and the measured values of the important power distribution parameters is given in Table 6.1. A comparison of these measured values I with their Technical Specification limits is given in Table 6.2. Flux

Map I was taken at 24*. power to verify the radial power distribution (RpD) predictions at low power. Figure 6.1 shows the measured RPDs from this flux map. Flux maps 2, 3, 4, and 5 were taken at 41*., 70',, 891, and 94'.

power levels respectively with different control rod configurations.

I These flux maps were taken to check at power design predictions versus

, ennvired core power distributions at various operating conditions. The l

, radial power distribution for the 70*, power level flux map (flux map 3) is given in Figuru 6.2. Flux maps 6 and 7 were taken at a power level l x- x1ce ta,t , eh, m s T_ t , R ,o , t e. m - Se

1

,p l of 99'. to monitor FQ(Z)/K(Z) every seven ef fect ive f ull power days (Erl'D) in accordance with Technical Specification 4.2.2.2e. The radial power distribution for flux map 6 is given in Figure 6.3. The radial power 5 distributions for the maps given in Figures 6.1, 6.2 and 6. 3 show that the measured relvtive assembly power values were generally within 1. 7 'l.

of the predicted values ( 1. 8*. including flux maps 2, 4, 5, 7, and 8) .

Further, the measured F-Q(T) end F-Dit(M) peaking factor values for the at power flux maps were within the l i m i t s, of Technical Specifications 3.2.2 a rid 3.2.3, respectively. Flux maps 8, 9, and 10 were used to perform an Incore/Excore detector calibration.

In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptanco criteria, and the Technical Specification limit s . It is therefore anticipated that the core will continue to operate safely throughout Cycle 9.

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i NORTil ANNA UNIT 1 - CYCf.E 9 STARTUP l>llYSICS TESTS INCORE Fl.UX HAP

SUMMARY

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I NE-840 NIC9 Startup Physics Tests Report l'a ge 34 of 59

B I Table 6.2 NORTil ANNA UNIT 1 - CYCLE 9 STARTUP PilYSICS TESTS COMPARISION OF MEASURED POWER DISTRil1UT10N PARAMETERS WITil TilEIR TECilNICAL SPECIFICATION LIMITS I

I PEAE F-Q(T) llaT CilANNEl. FACTOR

F-Q(T) Il0T CllANNEL FACTOR **

(AT NODE OF MINIML.M MARCIN)

F-Dil(MJ ll0T CllANNEL FACTOR I MAP NO. MEAS LIMIT NODE MEAS LIMIT NODE MAKGIN (1)

MEAS 1.lMIT MARGIN

( *, )

1 2.239 4.380 38 2.239 4.380 3h 48.9 1.498 1.828 18.1 2 2.195 4.380 31 2,195 4.380 31 49.9 1.486 1.754 15.3 3 2.013 3.112 29 2.013 3.103 28 35.1 1.437 1.624 11.5 '

4 1.926 2.470 36 1.926 2.470 36 22.0 1.420 1.541 7.9 5 1.946 2.339 37 1.946 2.339 37 16.8 1.418 1.518 6 . t, 6 1.922 2.211 37 1.922 2.211 37 13.0 1.413 1.494 5.4 r I 7 8

1.915 1.911 2.203 2.207 36 37 1.915 1.911 2.203 2.207 36 37 13.1 13.4 1.417 1.421 1.493 1.494 5.1 4.9

The Yechnical Specification's limit for the heat flux bot channel factor, F-Q(T), is a function of core height and power level.

I The value for F-Q(T) listed above i r, the maximum value of F-Q(T) in the core. The Technical Specification's limit listou above is evaluated at the plane of maximum F-Q(T).

I ** The value for F-Q(T) listed above is the value at the plane of minimum margin. The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each map.

The measured F-Q(T) hot channel factors include 8.15% total uncertainty.

I I

I NE-840 NIC9 Startup Physics Tests Report Page 35 of 59

r s

I Figure 6.1 L

NORTil ANNA UNIT 1 - CYCLE 9 STARTUP PHYSICS TESTS 2 ASSEMilLYWISE POWER DISTRillVTION l 24% POWER R P h d i R J H C F E D C B &

. PW10lt il D 0.f4 0.51 4.t5 . Ivl Dit tl D ,

N A$dWt b . 9.26 0.55 . 0.t6 . m 4%upt D . 1

..PC I Dif f l FI NCE . 6.% 6.5 . 4.0 .PCI Clf il b1 MCI .

0.t9 U.58 1.07 0,F9 1,07 0.48 0.50

. 0.51 0.%8 1.11 0.67 1.10 0.59 0.10 7

%.9 0.4 5.1 2.7 f.% 3.1 0.2

......0.91 . l.1%............1. t f . l.14 . 1.1? 1.1% 1.78 1.16 0.54 -

0.3% 1.19 1.ta 1.1% 1,55 1.1% . 1.78 1.1% 0.11 5 1.4 . 1.7 0.6 . 9.1 0.1 0.1 0.1 0.7 -0.8 0.15 0.82 1.15 l.it 1.5% ...l.it 1.31 1.?? 1.55 0.82 0.1%

0.3* 0.84 1. 56 1.24 1.1% 3.24 1.51 1.Pl I.52 0.81 0.A% 4 1 3.4 0.%9 1.14 2.6 1.57 7.8 1.18 t0 4.79 1.2

.....1.14 1.1 1.34

-0.7 1.16

l.1

.....1.79 1.1 .

1.18 1.2 1.)?

1.0

.....1.14 0.%0 0.%0 1.16 1,55 1.14 1.51 1.16 1.%6 1.1% 1.28 1.17 1.30 1,43 0.29 %

1.3 1.5 1.7 1.7 1.6 1.7 l.6 0.5 1.7 -1.3 -1,6 -1.0 -l.0 0.$h I.?6 1.?! 1.29 1.06 1.29 1.15 1.29 1.06 .....1.79 1.21 .....1.26 0.5A 0.59 1.t* 1.13 1.10 1.08 1.11 1.14 1.29 1.0% 1.2% 1.10 1.75 0.%7 . 6 2.3 f.3 1.8 1.7 1.6 1.9 1.4 0.4 -1.0 5.1 3.t -1.4 1.4

...... .. , ...... ....., ... ...... ...... ...... ...... ...... ... 4 ....

0.2% 1.co 4.s4 .....1.3? 1.14 1.79 1.17..... 1.10 1.12 1.29 .....1.14 1.12 1.11 1.06 0.2%

0.th 1.07 1.1% 1.53 1.14 1.29 1.14 1.12 1.12 1.28 1.11 1.76 1.40 1.04 0.24 7 3.2 1.2 1.3 0.6 0.2 0.4 1.5 0.9 *0.1 0.6 - 1. 0 4.6 - 1.1 .% 1.6 0.51 0.76 . 31 1.?? 1.54 . 1.11 .....L.10 ...l.t6 1.30 1.15 1.54 1.72 1.51 0.F8 0.11 0.10 0.19 1.52 1.l? 1.34 1.11 1.3% 1.t1 1.2A 1.11 1.30 1.16 1.?? 0.78 0.31 8

-1.1 0.9 1.0 DJ 0.4 0.8 . 1.6 0.8 1.6 -1.7 3.2 -4.6 . -S.1 -0.7 0.0 0.2% l.00 1.11 .....1.52 1.14 1.?9 1.15 1.51 1.11 1.79 .....1.14 1.12 1.15 .....1.06 4.2%

0.7% l.06 1.1 % . l.it . 14 1.78 1.10 1.28 1.10 1.7b 1.12 1.30 1.17 1.06 0.2% 9 0.% -0.5 0.3 01 % -0.% -F.4 -1.4 -1.4 -2.6 1.4 1.1 -1.% . -0.2 1.5 0.58 ...1.te 1.21 1.29 .....1.06 1.29 1.11 1,29 1.06 1.74 1.21 1,76 0.%8 0.4A 1.71 1.73 1.5? 1.07 1.76 1.10 1.?% l.04 1.21 1.ft 1.26 0.59 to 0.4 0.5 1.5 2.1 0.5 -2.5 -F.1 -3.0 -?.5 1.4 0.% -0.2 f.I 0.10 1,14 1.57 1.18 1.29 .....1.1% 1.34 1.14 1.29 1.18 .1.17..... .....1.14 0.50 0.30 1.11 1.3% 3.21 1,79 1.17 1.51 1.12 1.?? 1.18 1.12 1.14 0.79 11 2.4 7.4 2.5 f.7 -0.4 *.i -7.1 -F.% -1.5 . -0.6 0.0 -0.S -0.6 0.33 0.Bt 1.15 1.?? 1.31 1.71 1.11 1.?? 1.1% 0.82 0.51 0.1% 0. 8's 3.16 1.73 1.11 1.70 1.10 1.20 . 1.51 0.67 6.51 17 4.3 3.5 2.6 0.4 -1.8 -1.8 -2,3 1.6 -1.4 -0.3 -0.4 0.54 1.16 1.tA 1.1% 1.53 1.1% 1.77 1.16 0.34 0.5% 1.20 1.79 . 1.12 1.31 1,11 1.2% 4.14 0.33 15 4.2 4.2 1.5 -1.5 1.5 -1.1 7.7 -l.S -0.4 0.50 0.%8 1.08 0.80 1.07 0.4A 0.30 0.11 0.61 1.09 0.81 1.0% 0.5F 0.79 14 4.2 4.4 1.6 1.4 -1.6 -2.1 ?.?

51&NDARD 0.2% 0.51 0.?4 A vl 6 AG6 .

dew!Affin 0.76 0.17 0.2% ..PC I Dif f f Wi mCt . 1%

al.50% 4.4 4.5 44 a I7

SUMMARY

MAP HO: N1-9-01 DATE: 03/10/91 POWER: 047.

CONTROL ROD POSITIONS: F-Q(T) = 2.239 CORE TILT:

D BANK AT 133 SifPS F-DHlM) i 1.498 NW l.014 l NE 0.991 i

F(2) = 1.417 LW l.007 l Lt 0.987 BURNUP

14 MWD /MTU A.O. = -14.08'4 NE-840 NIC9 Startup Physics Tests Report Page 3G of 59

l 1 Pigure 6.2 NORTil ANNA UNIT 1 - CYCL.E 9 ST ARTUP PilYSICS TESTS ASSEM14LYWISE POWEh DISTRittVTION 70'. POWE R W P 84 M 1 ll J H C l 1 D C 8 4 6tt DIC ll D 4.77 . 0.3% 0.77 let DIC 1l D ,

. MfAMalD . 9.f4 9.56 0.28 MI A%Wi p , 1

.PC I Dit f I Pl W.I . 3.S 3.t 7.e ..PCI Dief1Ftsett.

I ...... ...... ...... ...... ...... ...... .....

4.10 0.59 1.11 9.A9 1.11 0.49 0.30 0.31 . 4.%9 1.11 0.90 1.li 0.%9 0.%4 f 2.8 16 1.7 1.F 1.0 I

0.4 t.4 4.54 1.11 1.71 4.84 l.%% '.it 4.71 1.11 .....0.54 0.54 1.14 . 1.76 1.1% 1.1% 1.4% l.?* l.l? 9.54 3 7.8 t.8 f.7 0.4 0,4 0.6 0.7 4.9 8.6 I

6.1% 0.80 1.?? 8.19 1.50 1.FL 1.%0 1.49 1.7A 0.80 9.3%

0.14 0.87 8.51 8.T? l . .% ? . I il 3.11 1.8% l.17 9.A0 $.3% 4

?.I t.1 t.6 2.9 1.6 1.% 0.7 0.1 -0.1 0.6 4.5 0.40 1.10 1.77 .....1.46 1.79 1.1' 4.57 l.l* 1.41 1.16 1.?P 1.10 0.10 0.40 1.lf 1.29 1.18 8 .1? 1.17 8.%% l.16 1.79 l.1% l.7% l.07 0.?9 %

1.4 1,4 1.7 8.6 2.5 2.? 7.1 1.1 -0.0 1.0 -F.4 -3.1 1.7

,5 . .... ...... ...... .......... . ...... .. ... ......

0.%9 1.21 1.18 l ?9 1.16 l.11 1.11 1.31 .....1.16 1.?9 1.19 1.7% 0.49 9.60 1.7% 1.70 1.10 1.18 1. 5% 1.1% 1.57 8.8% 1.77 1.tk 1.?O 0.57 6 1.9 4.9 1.6 1.7 7.0 1.4 2.0 0.9 . 0.1 -1.7 -l,8 2.s 2.6 0.77 1.10 1.11 1.30 1.14 1.51 1.14 1.50 1.14 1.11 .....1.14 1.%0 6.1% l.10 0.??

8.26 1.10 1.14 1.30 1.14 1.5? 1.16 1.%? 1.14 1.31 1.14 1.76 1.11 1.07 0.?? 7 f.% 0.5 4.6 9.1 0.4 9.6 1.6 1.5 0.6 0.4 0.7 -2.6 2.6 1.0 2.%

4.3% 0.A8 n.nl 1.29 1.\? 1.11 1.10 1.7% 1.10 1.11 1.12 1.?0 1.31 0.86 8.3%

0.54 0.88 1.37 1.?! l.1% l.14 1.51 1.?7 1.?9 l.13 1.51 l.17 4.7A 6.hh 0.1% 8

-1,6 . 0.3 0.3 0.4 9.4 1.1 f.6 1.7 -0.4 0.4 -1.2 -?.8 2.7 F.! 1.1 I ...... ...... ...... ...... ..... ...... ..... .....

9.?? 1.10 4.15 1.30 1.14 1.31 1.14 1.10 .....1.14 1.51 1.14 1.14

.....1. 10 1.8%......

1.17 l.80 1.09

......0.?F 0.?a 9 0.?7 1.08 1.17 1.29 1.1% 1.31 1.17 n.?S 1.1% 1.F9 1.t1

-1.5 -1.6 -1.6 -0.4 8.6 -0.1 l.4 -l.4 1.? -1.5 -0.6 -1.7 *t.9 0.4 0.7 N ...... ...... .... 4 ... .. . .... ...... ...... ..... ..... ...... ...... ......

. 0.49 1,73 l.la 4.79 .....1.16 1.31 1.15 1.11 1.16 1.79 8.19 3.7% 0.49 6.%A l.29 1.19 , 1.52 1.17 8.19 1.11 4.24 n.!* 1.?O l.19 1.7% 0.h0 10

-1.8 -1.8 0.7 2.0 0.8 -1.1 -l.7 -?.1 1.% -0.8 0.4 1.% ?.4 1.79 1.?9 1.16 .....1.10 . ...9.40 t

0.50 4.10 1.?? 1.16 1.1% l.1? 3.1% I tt 0.16 1.10 1.17 4.19 I.79 1.11 1.40 1.17 1.78 1.36 l.?w 4.11 0.30 !!

4.0 0.0 0.7 I ) -0.1 -l.6 -1.6 1.9 0.9 -0.4 -0.4 0.8 0.6 9.5% 9.80 1.78 1.19 8.34 L.?l 1.30 1.19 1 ?S 0,80 9.11 0.1% 0.8? 1.10 1.19 1.75 1.19 1. ? A . 4.l? l.76 9.89 0.1% !?

I 1.9 1.6 1.8 0.? 1.6 1.6 -4.9 l.A -1.2 -0.7 . 1,1

. ...0.54 1.81 1.?= .....1.14 1.H 1.14 1.7% l.81 4.%

5. 54 1.l? 1.?1 1.13 1.31 1.4% 1.71 1.09 0.5% 11 1.1 0.7 0.3 1.4 -1.2 -1,6 1.7 1,6 -1,F I .........

M Aa404vh D( V I A f ! Lm 8.10 0.11 0.7 0.59 6.60 1.8 1.!!

1.37 4.A 0.89 0.89 9.1 9.28 0.28 0.5%

0.3%

1.11 1.09

-l.%

0.?P 0.??

4.%9 0.%A l.6 0.19 6.50

't.S A vl ft ACE

,.PCI Dlill pl MCI .

14 14

=0.A?% '.9 1.1 0.8

1.4

SUMMARY

MAP NO: H1-9-03 DATE: 03/12/91 POW [ R : 707 CONTROL POD POSITIONS: F -Ql) ) 2.013 COPE TILT:

D BAHk AT 186 STEPS F-OHIMI s 1.437 NW l.014 l NE 0.996 l_

)I Flzl 1.300 LW 1,000 t LL 0.990 BUPNUP s 47 MWD /M TU A.D. a -1.197 g xE . x1Ce - m- 1m_ ~ u o

.I lll Figure 6.3 NORTil ANNA UNIT 1 - CYCL.E 7 STARTUP P!!YSICS TESTS ASSEMBI.YWISE l'0WER DISTRIBUTION 99% POWER I p P lvt DIC110 h M l e J H 8.10 0.58 C

0.30

$ 1 0 C Svl DIC il D B A I . Me Aitwn D

.PCI Dlli n kt hcl .

0.31

. 0.17 0.60 4.%9 0.30 .

l.0 .

1.11 1.44 .

0.39 l.S 0.9%

0.9%

. 0.10 1.3 ,

1.14 1.84 0.61 0.64 0.31

0. %f .

, Ml abub'l D

.Pll Dlli t Pl hd .

l

?

3.8 0.? 1.s I

1.% 9.T . 0.5 . 0.7

.....4.14 1.10 4.74 1.14 1.11 . l.14 l.?? . 1.10 0. ;%

0.14 1.17 1.77 1.14 1.11 1.1% 1.27 8.11 . 0.4% %

. 2.1 F.0 0.7 . 0.0 . -0.0 0.5 0.6 l.F F.4

..... ...... S.A0 .. ... 1.7%...... ......1.74 ......1.19 ...... l.fa ...... ......

1.17 ......

1.7% . 0.84 ...4 %4 I

0 . 3, 1.37 0.5% 0.02 1,74 1.20 n.5P 1.?l I.?8 l.17 3.7% 0.00 0.54 4 1.* 1.1 ?.! 2.5 . 1.4 1.4 0.7 0.? -0.1 -0.2 -0.6

..... ... .4.c9 8.11 1.?4 1.1%1.78 ......L.14.... . 4.10...... ......1.14 ......

l.?8 ......

1.1% ...1.?* 1.10 .....0,38 o.it 1.09 1.?% l.17 l . tl 1.17 1. 54 1.16 1.?a 1.14 n.72 i.07 0.31 %

I 0.0 0.61 0.1 0.0 1.22 0./

0,9 1.18 1.1 1.7 1.30 1%

1.t' 1.9

?.8 3.4

0. 0 L.71 1.17 1.78 1.19 1.50 l.3%

3.8 3.1 3.l?

l.16 1.4 1.8 1.30 1.14 F./

0.8 1.49 1.10 l.0 4.74 1.7%

-2.1 0.8 -1.6 1.11 1.14 2.3

-2.6 1.t!

1.la . 8.%9

-7.7

-1.1 9.60

t.4 6

0.50 1.11 1.14 1.78 1.14 . l.30 1.11 n.ta 1.15 3.50 1.14 l F6 . 1.14 . 1.11 0.30 0.50 1.17 1.45 1.ta 1.14 1.51 . l.11 l.10 1.16 1.11 l.11 1.TA . 4.40 1.09 0.79 7 l.4 -0.4 . -0 4 -0.7 0.1 1.3 5.% 1.1 f.3 1.9 0.9 -1.8 3.4 1.4 f.9 .

O.\A 6.6, .....1.1' l.19 1.30 1.11 1.78 1.?1 1.?S 3.l? l. 10 l.19 1.51 0.4 0.%8 S.A1 0.91 1.58 1.19 1.3? l.1% 1.31 1.71 1.?9 8.11 1.29 4.14 1.17 0.91 0.16 8

-2.% 0.6 0.7 0.3 l.7 2.8 5.8 . 1.0 0.8 0.6 1.0 3.8 -3.4 1.1 -1.5 i ...... ...... ..... ... . ..... ...... ...... ...... ...... ......

0.50 1.13 1.44 1.T8 1.14 '.50 1.13 1.?A l.li 1.10 .....l.14 1.78 .....1.14 1.11 0. 10

. 0.79 1.10 1.11 1.77 1.1% 1.51 1.17 1.71 . l.8% 4.10 1.44 1.76 1.11 . l.l? 0.50 9 2.4 -2.4 ?.4 - 0. 4 . 1.% 0.7 0.8 0.8 0.0 -0.0 0.7 1.8 -l.0 -0.7 0.4 B.71 1.17 1.10 1.10 1.17 1.Z1 0.60 8

0.60 1.f& l.19 l.lt n.lt n.to 0.%9 1.18 1.18 . 1.11 n.tl 3 ?v l.nl I.ta 1.la 1.78 1.16 1.21 0.64 10

-2.9 -2.4 0.9 2.6 1.4 -1.0 1.0 -1.3 -0.7 -0.4 0.6 1.4 1.8 0.31 1.09 1.24 . 1.1% ...... 1.28 ..... 1.14..... ...1.50.1.14 . l.78...... 1.1% .....l.74 1.09 0.11 0.31 1.10 1.7% 1.18 . 1.ta 1.12 1,79 . 1.17 1.ta 1.1% 1.2% I.10 0.1? 11 0.4 0,8 1.1 L.1 I 0.1 . . . -0.0 al.?

0. 54 0.81 1.2% 1.17 1.TA

-l.2 1.19

-l.?

1.26

-0.4 1.17

-0.1 1.7%

0.7 0.81 0.6

.....0. %4 l 0.5% 0.82 . 1.28 1.14 1.16 1.17 1.2% 1.36 1.74 0.8'. 0.54 11 I

2.4 2.3 1.1 0.3 1.9 1.9 -?.7 -1.4 -1.1 0.0 -0.t 1.31 1.14 ..... ......

1.?? ......

.0.3%.... 1.10 ...l ?? .....l.14 1.40 0.3%.....

0.3% 1.11 1.t! 4.l? 1.30 1.11 1.16 1.08 0.34 11 1.1 0.9 -0.1 7.t -2.4 -3.0 -3.1 -2.0 0.2 I

0.51 0.61..... 3.84 0.9% 1.11 0.60 0.11 0.12 0.62 1.14 0.9% . l.10 0.49 0.10 44 0.9 2.1 0.1 -0.8 5.0 3.0 1.5 .

SIANDAkD . G.?0 0.18 0.79 . A W k Al.1 .

DIVlail0M 0.11 0.59 0.F8 . Pt i D if f t M ktt. . 1%

=l.06r s.4 0.4 -?.s = 1.%

SUMMARV MAP HO: N1-9-06 DATP t 03/19/91 PowtR: 9 9 '/.

CONTROL ROD POSITIONS: F-Qli) a 1.902 COR[ TILT:

D BANK AT 008 $f EPS F-DHIM) = 1.413 NW 1.012 l NE 0.947

I FlZ)

1.045 SW 1,000 l SE 0.990 BURNUP a 305 NWD/MTU A.D. * - 3 . 8 0.

NE-840 NIC9 Startup i'hysics Tests Report l' age 36 of 59

1 I Sl:CTION 7 L

K EIT.k ENCI;S

1. T. S. Psulk, " North 'nna Unit 1, Cycle 9 Design Report",

Technical Report NL 824, Fevision 0, Virginia l'ower , Februa r y , 1991.

2. T. K. Ross, W. C. lieck . " Cont rol kost React ivity Worth Det er minat ion I!y 1he Kcxl Swap Technique." Yl.P rKD-36A, Deceml.er , 1980.

3. W. I.eggett and 1,. Eisenhart, "1ho INC0Kl; Code ," WCAP 7149, December, 1967.

lp 4. North Anna l' nit 1 Technical Specifications, Sections 1.18, 3.1.3.4, 3.2.2, 3.2.3, 3.1.1.4, 4.1.1.1.2, arn! 4.2.2.2.

5. Letter from W. 1,. Stewart (Virginia Power) to the U.S.N.K.C. ,

"Surry Power Station Units 1 arul 2, Not th Anna Power Stat ion Unit s 1 arn! 2 : bit f icat ion of Startup l'hysics Test Program - Inspectos rollowup item 280, 281/88-29-01", Serial No.89-541, December 8, 1989.

I I

NE-840 NIC9 Startup Physics Tests Report Page 39 of 59

I I

I Al'I'END I X I STARTUP l'IlYSICS TESTS HESUITS AND EVAL,UA110N SilEl:TS I

I I

I I "-8" "' " """""*"" '"" "" " "- " ""

e $0Risi ANNA POVER STATION UNIT 1 CYCLE 9 L STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET i

I l Test Cescription: Reactivity Comput'r Checkout Reftrence Prec No /Section: 1*PT 94.0 Sequence Step No: 3 11 {BankPositions(Steps) lRCSTemperature('P): 547 Test Cc % 4ons Power Level (*. F.P. ): O SDA: :28 SDB: 228 CA: 228 Other (specify):

(Design) CB: :8 CC: 228 CD:

Below Nuclear Heating

!!! Bank Positions (Steps) RCS Temperature ('P): 549.0"G Test Power Level (% F.P.): O a

Conditions SDA: 228 SDB: 225 .A: 228 (Actual) CB: 228 Other (Spectiy):

CC:

g D: 95- Below Nuclear Heating Date/ Time Test Performed: l 3l? l4l LO'. 6 3. ' ,

Measured Parameter pe = Kea; leactivity free p computer IV (Description) pg = Predt.ted Reactivity i p,= .ss.o . so.o Measured Value pg = - % ,6 +d.9 Test Results jiD{= 1.0 % o.% '7o Dealgn Value

( Actual Conditions ) *D = ((pe pg)/pg) x 100% I 4.0.

Design Value (Design Conditions) *D = ((pe pg)/pg) x M s 4.M Reference WCAP 7905, Rev. 1. Table 3.6 V FSAR/ Tech Spec Acceptance Not Applicable Criteria Reference Not Applicable Dessgn Tolerance is met V VI YES ~ NO Acceptance Criteria is met : 7__.YES ___NO Comments At The Just critical Position Allcwable Range = 1 -$g 3 +MS Prepared By: MOu-M Gdk+ Revtewed By: Meb- P. 3n-NE-640 N1C9 Startup t hysics Tests Report Pan" 41 o f Y'

_____ - - -- ~

3 r NORTil ANHA POWER STATION UNIT 1 CYCLE 9 L STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1 - (PRELIMINARY ANALYSIS)

I

! Test Cescription: Critical Boron Concentration - ARO Reference ! Proc No /Section: 1 PT-94.0 Sequence Step Not t{

11 }Banr.Postssons(Steps) RCS Temperature ('r): $47 Test Conditional Powe r Leve l ( *. F . P . ) : 0 (Design) ! CDA: ::8 EDB: 208 CA: 228 Other (specify):

CB: 208 CC: 228 CD: 228 Below Nuclear Heating Bank Positions (Steps) RCS Temperature ('T): 'i'f 14 Test Conditions Power Level (% T.P.): O SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 208 CC: 228 CD: 228 Below Nuclear Heating l Date/ Time Test Performed:

7/6/'il S S O ta Meas Parameter g IV (Descriptton) (Cg ) AR0; Critical Boron Conc - ARO M

Measured Value (Cg ) Agg = 21 8 #

Test Results Design Value (Actual Cond) CB" I ^--- '

t' 9 'M Design Value (Design Cond) Cg a2091 1 50 ppe Reference Technical Report NE-824 "Sv. O V D Acceptance l- FSAR/ Tech Spec aC3xCB 5 1000 pcm Criteria Reference Technical Specification 4.1.1.1.2 Design Tolerance is set : ,,d_YES ,,_,_NO Acceptance Criteria is met : _r YES NO VI l Coseents aC B = o.90 pcm/ ppa for preliminary analysis D M C

3 = f(C3) ARD - CB l; C 3 is design value at actual conditions.

Prepared By: Mdt- L) fm -- -M Reyteved gy : i o *+

J

NE-84n NIC9 Startup Physics Tests koport Pa r,e 42 of 59

g -

i @ t.',4 tchM STATION UNIT 1 CYCLE 9

$, t ' @

Y GS TEST RESULTS AND EVALUATION SHEET I n. v.

t

, . ~ ~ --

(FINAL ANALYSIS)

est

Description:

Critical Boron Concentration ARO Refeter.cw ; Proc No /Section: 1*PT 94.0 Sequence Step No: yg II Bank Positions (Steps) RCS Temperature t 'T): 547 Test ConditionsI Power Level (*, T.P.): O SDA: ::S SDB: 228 CA: 228 Other (specify):

(Design) l CB: 2:8 CC: 208 CD: 208 Below Nuclear Heating 111 Bank Positions (Steps)

Test HCS Temperature ('T): N0 i Conditions Power Level (*. T.P.): 0 SDA: 228 SDB: 28 CA: 228 Other (Specify):

(Actual) CB: 228 CC: 228 CD: 2:8 Below Nuclear Heating l Date/ Time Test Performed:

il%H8 c.> 3 2o Mess Parameter IV (Description) 3 (Cg ) AR0; Critical Boron Conc ARO I Measured Value N Test (Cg ) ARO = 24 D Results Design Value i (Actual Cond) CB" M I # C EM Design Value (Design Cond) Cg =2091 2 50 ppe Reference Technical Report NE*824 Rev. 0 l

V D TSAR / Tech Spec aC3xCB s 1000 pce I Acceptance Criteria Reference Technical Specification 4.1.1.1.2 Design Tolerance is set : 'YES NO Acceptance Criteria is met : /YES NO VI I Consents aC C

D B = - 6.D %pn M

3 = l(C g) ARD C g l; C D is design value at actual conditions, g

Prepared By: 0, IDL(. a lv ~OYAn " S/ U, Reviewed By:

t g sE- 8:.o sic 9 startup enysics Tests Report Pas:e 43 of 59 i

E NORTH AhNA POVER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I '

Reference i Test Descriptton: !sothermal Temperature Coefftetent Proc No /Section: 1 PT 94.0 ARO Sequence Step No: g I II Test Conditions i Bane. Positions (Steps) l RCS Temperature ('T): 547 Power Level (% F.P.): O SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating

!!! Bank Positions (Steps) RCS Temperature ('T): T'%' e l '

Test Conditions Power Level (t F.P.): O SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) l CB: 228 CC: 228 CD: .24 ' Below Nuclear Heating I Date/ Time Test Performed:

?ldh ASG i

i Mens Parameter 150 i IV (Description) (a T IARO !sothermal Teep Coeff ARO Test 150 I Results Heasured Value (a T IARO = . o,9 0 pcs/'T (Cg =.2119 ppe) #

Design Value ISO (Actual Cond) (a T )ARO " ~ O 0 5 Pen /'r (C g m.21l9 ppm) f

. 150 (a T )ARO = -0.31 1 3.0 pcm/'T l Design Value (Design Cond)

(CB = 2091 ppe)

Reference lTechnicalReportNE-824Rev.O V

I Acceptance FSAR/ Tech Spec ISO aT S 3.75*pca/'r Dop aT = 1.75 pcm/'T I Criterta Reference TS 3.1.1.4 Technical Report NE 824 Rev. O I VI Design Tolerance is set Acceptance Criteria is set

.f YES _,,NO A YES _ _NO Comments i

Uncertainty on oTMOD = 0.5 pcm/'T (

Reference:

meenrandum f rom C. T. Snow to E. J. Lozito dated June 27, 1980).

P, epa,ed e,. s,s % Rev,e- e,. umus .

s NE-M40 NIC9 Startup Physics Tests Keport Pane 44 of 59

l I NORTH ANNA POWER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cnti I Referance Bank B Worth Meas.. Rod Swap kef. Bank l Proc No /Sectiont 1 PT-94.0 Sequence Step No: 6 I 11 Test Conditions

[BankPositions(Steps) RCS Temperature ('T): 547 l OtherPcwor Level (% T.P.):

O (Design) SDA: 228 SDBt 228 CA: 228 (specify):

CBidoving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('T): 6Y#'

Test Conditions Power Level (% T.P.): 0 l (Actual) SDA: 228 SDB: 228 CA: 228 CB:Hoving CC: 228 CDs 228 Other (Specify):

Below Nuclear Heating I Date/Tima Test Performed:

3lt191 0539 I Measured Parameter (Description)

I REr g ; Integral Worth of Cnt! Bank B.

IV All Other Rods Out Test Measured Value Results ! =

f c"14 4

4 P#

Design Value (Actual Conditions) I . /2 0*77. lal F "

Design Value (Design Conditions) !ggp B = 1207 : 121 pen Reference Technical Report NE-824 Rev. O If Design Tolerance is exceeded. SNSOC V FSAR/ Tech Spec shall evaluate impact of test result i Acceptance on safety analysis. SNSOC may specify Criteria --

that additional testing be performed.

Reference VEP FRD-36A Design Tolerance is met :

VI i Accyptance Criteria is met NES____NO Consents : 2YES _NO t

I

,,e,.,ed ,,, L ed "" Rev,e.e. 8,, && h

!g xx. m.e Nice ,m,t, ex.1 t. x.-t - 4, - "

I NORTil ANNA POWER STATION L' NIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALVATION SilEET (PINAL ANALYSIS) 1 Test Descriptten: Critical Boron Concentration B Bank in Reference l Proc No /Sectten: 1 PT 94.0 Sequence Step No: 7 11 Psnk Positions (Steps)

Test l T.:S Temperature ('P): 547 Power Level (i P.P. ): 0 I Conditionsi ,

(Design) I SDA: 228 SDB: 28 CA: 2:3 Other (specify):

CB: O CC: ::S CD: 228 Below Nuclear Heating 111 Bank Posttions (Steps)

Test RCS Temperature ('P):S/A'/

i Conditions l Power Level (% P.P.): O SDA: 2:8 SDB: 208 CA: 228 Other (Spectfy):

(Actual) { CB: O CC: 228 CD: 228 j Below Nuclear Heatang l Date/ Time Test Performed:

Slfl91 //O s' Meas Parameter IV (Description) (C )3g g; Critical Boron Conc B Bank In Measured Value (C )B " 19NFem Test B Results Design Value i (Actual Cond) Cg= /p/8 fagem f 2 7 ffm Design Value .

i (Design Cond) C Prev g = 1916 + ACg 1 (10 + 100.7/ locy l)ppe Reference lTechnicalReportNE-824Rev.0 '

V PSAR/ Tech Spec Acceptance Not Applicable I Criteria Reference lNotApplicable Design Tolerance is set : ,__ ES NO Acceptance Criteria is set : ,_,, ES NO VI I Comments acB * ~ b Y>

Prev AC B M

H 2091 I = (C 3)ARO

\

.s Prepared By: I 0 rf N

-j Reviewed Dy: '

Wb/

I I r. . . N1Ce 8t-t i-<~ ~< ~ - ""

E l

NORTil ANNA POWER STATION ll NIT 1 CYCLE 9 STARTUP PilYSICS TEST RESULTS AND EVALUATION SHEET (FINAL ANALYSIS) i 1

Reference Test

Description:

HZP Boren Worth Coef ficent Measurement Proc No /Section: 1 PT*94.0 Sequence Step No: 7 .,

11 Bank Positions (Steps) lRCSTemperature('T): 547 Test ,

I Conditions (Design)

', Power Level (% T.P.): 0 SDA: 228 SDB: 228 CA: 28 j Other (specify):

CB: Moving CC: 228 CD: 28

Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature ('T): 549.0 i Test Conditions SDAt 008 SDB: 228 CA: 2:8 Power Level (t T.P. ): O (Actual) Other (Specif y):

CB: Moving CC: 0:8 CD: 228 Below Nuclear Heating Date/ Time Test Performed:

$$/9{ o) .LO !

Measured Parameter IV (Description) aC3 , Baron Worth Coaf ficient t Measured Value aC3 = - 6, 9 2 Results i Design Value (Actual Conditions) aCB = 6.90 1 0.69 pes / ppa Design Value (Design Conditions) aC3 = 6.90 1 0.69 pcm/ppe Reference Technical Report NE*824 Rev. O FSAR/ Tech Spec Not Applicable I V Acceptance criterna Reference Not Applicable Design Tolerance is met ES _,.NO VI Acceptance Criteria is set I Consents ',.

__d(ES N0 I

Prepared By: h4 %

Reviewed By: 'l ~7 I

N};.840 NIC9 Sta rt up l'hys ics Tests Report Edf" "'

- ", se

NORTil ANNA POWER STATICN UNIT 1 CYCLE 9 STARTVP PHYSICS TEST RESULTS AND EVALVATION SHEET Reference Test Cescription: Cnt) Bank D Worth Measurement Rod Swap l Proc No /Section: 1 PT*94.0 Sequence Step Not q 11 Bang Pesitions (Steps) I Test RCS Temperature ('T): 547 Power Level (* T.P.): O Conditional SDA: 228 SDB: 228 CA: 228 Otner (specify):

i I (Design) l CB: Moving CC: 228 CD Moving. Below Nuclear Heating l Bank Positions (Steps) RCS Temperature ('F): M 'b Test Conditionsi Power Level ('. F.P.): O SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) { CB: Moving CC: 228 CD: Moving Below Nuclear Heating Date/ Time Test Performed:

31$1m /464 i

1 ras Parameter RS (Description) ID; Int Worth of Cnt! Bank D-Rod Swap lY -

. Ref Bank Test RS Measured Value ID = b/.S ( Adj . Meas Position . Crit

= /(,o steps)

Results Design Value (Actual Cond)

RS ( Ad). Meas. Crit. Ref Bank ID = /0/4.h f lMonition = it,0 steps)

Design Value RS (Design Cond)

ID = 1015 t 152 pce (Critical Ref Bank Position = 165 steps)

Reference Technical Report NE 824 Rev. O, VEP-FRD-36A If Design Tolerance is exceeded. SNSOC I V Acceptance FSAR/ Tech Spec shall evaluate impact of test result on saf ety analysis. SNSOC any specify that additional testing be performed.

Reference VEP-FRD-36A I Design Tolerance is met : [YES_,,NO VI Acceptance Criteria is set

.g %{ b Comments

,,,#,,,,,, Y E S_,,,,,,N O

,2 Prepared By: __ N8 Reviewed By: b I

i

r I

I NORTil ANNA 10WER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ; Teut Descr2ption: Catl Pank C Worth Measurement

Rod S ap Reference j Proc No /Secticn: 1 PT-94.0 Sequence Step ho lo I II Test Condi;fonsi Bank Posit 1ons (Steps)

SDA: 228 SDB: 228 CA: 228 RCS Temperature ('P): 547 Power Level (*. P.P.): 0 (Design) Other (spectfy):

CB: Moving CC:Movsng CD: 228 Below Nuclear Heating 111 Bank Positions (Steps) RCS Temperature ('P): SW. 5 Test Conditions Power Level (?, P.P.): 0 i SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: Moving CC; Moving CD: 228 Below Nuclear Heating I Date/ Time Test Performed:

.stal s i t'll8 Mens Parameter g3 I (Description) , IC; Int Worth of Cnt! Bank C Rod Swap IV I Test Results Measured Value Design Value IC g3

= 7 (Adj, Meas. Crit. Ref Bank P sition = fat 3 steps) g3 Adj. Meas. Crit. Ref Bank (Actual Cond) IC = SIM I Position " fM dateP8)

RS Design Value IC = 815 1 122 pce (Critical Ref Bank (Design Cond) ;

Position = 130 steps)

Reference I Technical Report NE-824 Rev. O, VEP FRD 36A l

If Des 1gn Tolerance is exceeded, SNbOC I V Acceptance PSAR/ Tech Spec shall evaluate impact of test result on safety analysis. SNSOC say specify that additional testing be performed.

Criteria Reference lVEP-TRD-36A Design Tolerance is met [ES ,, 40 I VI Consents Acceptance Criteria is set

, ,YES N0 I e Prepared By: M Reviewed By:

I I

I NE-840 NIC9 Sta rcup l'hys ics Tests R* port l'4;t' 4 'l of Yi l

I I NORTH AhNA P0hER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SilEET I

Test Descriptien: :nti Bank A Worth Measurement 5cd Swap Referenco l Proc No <Sectaen: 1 PT 94.0 Sequence Step No: 11 11 ' Bank Positions (Steps)

RCS Temperature ('P): 347 Test ,

Conditionst SDAt 205 SDB: ::S CA Moving Power Level s '. P.P. ): 0 (Design) { CB: Moving CC: ::S CD: 228 Other (specify):

Below Nuclear Heating 111 Bank Positions (Steps)

Test RCS Temperature ('T): 5T 7. 7 Conditions SDAt 228 SDB: 228 CA: Moving Power Level (7. P.P.): 0 I (Actual) CB: Moving CC: 225 CD: 226 Other (Specify): "

Below Nuclear Heating I i Date/Tien Test Performed:

}ISl91 I349

'MeasParameteri g3 (Description) l14 ; Int Worth of Cnti Bank A Rod Swap lY Test gg ( Adj. Meas. Crit. Ref Bank Measured Value lg = M.9 i Results Position =(,6 steps)

Design Value g3 ( Adj. Meas. Crit. Ref Bank I (Actual Cond) Ig = M. 2% foo Position = (,6 steps)

RS Design Value (Design Cond) 1 4

259 1 100 pcm (Critical Ref Bank Position = 67 steps)

Reference Technical Report NE 824 Rev. O, VEP PRD 36A I

If Design Tolerance is exceeded. S%0C V PSAR/ Tech Spec shall evaluate impact of test result on Acceptance safety analysis. SNSOC may specify that Criteria additional testing be performed.

Reference VEP itD 36A Design Tolerance is met VI Acceptance Criteria is set

_/ S _ NO I Comments

ES NO l

Prepared By: [ Reviewed By:

I I N- x= 81 - ~"< - " " "- " '"

1 I

l I NORTH ANNA POVER STATICN ll NIT 1 CYCLE 9 STARTUP PHYSICS TEST FESULTS AND LVALUATION SHEET R Test

Description:

Shutdown Pann B Worth Meas. Rod Swap Reference l Proc No /Sectien- 1 PT 94.0 Sequence Step No: l {,

'. I !BankPositions(Steps) lRCSTemperature('T):

Test i t.7 Power Level (*. T. P. ): O Conditionsi SDA: 228 SDB: Moving CA: 228 , Other (specify):

(Design) l CB: Moving CC: 228 CD: 28 lBelowNuclearHeating 111 Bank Positions (Steps)

Test RCS Temperature ('T): 80*9 Conditions SDA: 228 SDB: Moving CA: 228 Power Level (% F.P.): 0 I (Actual) CB Moving CC: 228 other (Specify):

CD: 228 Below Nuclear Heating Date/ Time Test Performed:

3/s / 91 13c l Meas Parameter g3 (Description)

ISB; Int Worth of Shutdown Bank B Rod Swap IV Test RS (Adj, Meas. Crit. Ref Bank Measured Value I = .

Results SB Position =/48.https)

Design Value p3 (Adj. Meas. Crit. Ref Bank (Actual Cond) I SB

=/04C./!/5G Position = /4 W.~2teps )

RS Design Value I SB (Design Cond) = 1039 i !$6 pce (Critical Ref Bank Position = 170 steps)

Referenco l

Technical Report NE*8?4 Rev. O, VEP FRD 36A i i

If Design Tolerance is exceeded SNSOC shall evaluate impact of test result on 1 V A ceptance FSAR/ Tech Spec safety analysis. SNSOC may specify that Criteria additional testing be performed.

Reference VEP-FRD-36A i Design Tolerance is met : S NO VI Acceptance Criteria is set : ,,, YES N0 Coenents 4

Prepared By: _#D Reviewed By:

s' NE-840 NIC9 Startup Physics Tests Report Pilge 51 of 59

s H NORTH ANNA POWER STATION UNIT 1 CYCLE 9 L ;

STARTUP PHYSICS TEST RESULTS AND EVALVATIOk SHECT 1

J Reference ~ Test Cescription: Shutdown Bank A horth Meas. - Rod Swap Proc No / Section: 1-PT 94.0 l Sequence Step No j)

I 11 Test Conditions l Bank festtions (Steps)

SDA: Moving SDB: 228 CA: 228

! RCS Temperett ro ('T): 547

, Power Level (?, T.P. ): O (Design) {Other(specify):

CB: Moving CC: 228 CD: 228 ; Below Nuclear Heating

!!! lBankPositions(Steps) RCS Temperature ('T): Me 9 Test Conditions SDA: Moving SDB: 228 CA: 228 Power Level (% T.P.): O (Actual) Other (Specify):

CB: Moving CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed:

3/9/ql // %

Mess Parameter g3 (Description) 134; Int Worth of Shutdown Bank A-Rod Swap IV Test RS (Adj. Meas. Crit. Ref Bank Hessured Value 133 = 897 d Results Position ago.3 steps)

Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) 134 = Sil . It ( W Position a go,3 steps)

RS Design Value Igg = 890 2 134 pcm (Critical Ref Bank (Design Cond)

Position = 142 steps)

Reference Technical Report NE 824 Rev. O, VEP-TRD 36A If Design Tolerance is exceeded, SNSOC V

shall evaluate tapact of test result on TSAR / Tech Spec Acceptance safety analysis. SHSOC may specify that Criteria additional testing be performed.

Ref t ance VEP-FRD-36A VI Design Tolerance is met Acceptance Criteria is cet . [Y Comeents --

. .LdE ES S _NO

,NO.

i Prepared By: / N Reviewed By:

SE-840 SIC 9 Startup Physics Tests Keport Pa y,c 52 of 59

I I NORT!! ANNA POWER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference

!TestCescrt ston: Total Rod Worth Red E.ap Proc so rSection: 1 PT-94.0 Sequence Step No:

11 l34 Bank festtions (Steps) RCS Temperature ('T): $47 5 Test Conditions Power Level (*. T.P. ): O (Design) SDA: Moving CB: Moving SDB: Moving CA Moving l Other (spectly):

CC:Movin;; CD: Moving l Below Nuclear Heating -

III Bank Positions (Steps) RCS Temperature ('F): 64 d. 4 Test I Conditions (Actus!)

SDA Mos ing SDB: Moving CA Meving Other (Specify):

CB: Moving CC: Moving CD: Moving Below Nuclear Heating Power Level (?, T.P. ): 0 Date/ Time Test Performed:

3l3 l*l l 09: >\

Mess Parameter '

( Des c r tpt ton ) I Total; Int W tth of All Banks Rod Swap IV I Test Results Measured Value Design Value I

Total

ND P (Actual Cond) I I Total " f'

) Design Value I Total = 5225 t 523 pen (Design Cond)

Reference Technical report NE-824 Rev. O, VEP FRD 36A If Design Tolerance is exceeded. SNSOC V

FSAR/ Tech Spec shall evaluate impact of test result on Acceptance safety analysis. SNSOC any specify that i Criteria additional testing be performed.

Reference VEP-FRD 36A Design Tolerance is met : #

VI Acceptance Criteria is met ES N0 ES Comments __,NO v

Prepared By: #

Reviewed By: N' e

I I " '""""""""*""'""""""" "" " " ' "

ATTACILMENT 7 I NORTil ANNA POWER STATION ll NIT 1 CYCLE 9 STARTUP PHYSICS TIST RE5ULTS AND EVALUATION SHEET Reference Test Descriptient M/D T1ux Map Banks D.C at Insert. Lisits Proc No / Section: 1 PT 21.'. Sequence Step ho: q)

!! l Bank Positions (Steps)

I Test Cenottions:

SDA: 228 SDB: 228 CA: 228

} RCS Temperature ('P):T

, Power Level (*. P.P. ): Ob Other (specify)

RE II (Desagn) l CB : 225 CC :

CD:

Must have 2 38 thiebles Bank Positions (Steps) RCS Temperature ('T): TW

i Test Conditions Power Level (% T.P.): 2 4. W 7 SDA: 228 SDB: 228 CA: 218 Other (Specify):

(Actual) CB : 228 CC : 42'8 CDs 6 53 g 3 4g e, Date/ Time Test Perforecid:

BlooI9 In t 2 3 I

I !V Mess Parameter (Description)

MAX. REL ASSY PVR

% DilT NUC ENTHAL RISE HOT CHAN TACT TOTAL HEATi QUADRANT CitAN TACT FLUX HOT POVER TILT RATIO (M P)/P T dH(M) T-Q(7)

I - W. M Hessured Value 4h tya &.HD QPTR Test ggg 2,434 I

(, o i q 13 Results p; torvo Design Value e in ~ ' s e.*

(Design Conds) I" . Iaba'A' NA NA 5 1.02 VCAP 7905 Reference 'VCAP 7905 REY.1 NONE NONE REV.1 TSAR / Tech Spec NONE ' ' *" ' ' ' " ' ' ' " ' " ' ' ' " ' ' " '

Acceptance NONE

'I Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE I ,

Design Tolerance is set Acceptance Criteria is set

,,,'YES

4 YES

,,,,, NO NO Coseants

Near Control Rod Insertion Lieits I ' 1 m c /

Prepared By: %[dv #

R Reviewed By: YN' I

g xx. m mce m ,t ~ , 1.m t m.-, t ~,, s. -2

ATTACHPENT 7 I NORTH ANNA POVER ETAT'ON UNIT 1 CYCLE 9 STARTUP PHYMit:S TEST 7:EEULTS AND EVALUATION SilEET l

Test

Description:

1/D Flux Msp At Power Reterence Proc No i Sectiont 1 PT 21.;

Sequence Step No: 43

!! Bank Positions (Steps; I Test Condittonsi SDA: 228 SDB: 228 CA: 228 l ECS Temperature ('T):Tp Power Level (*. T.P.):

Otner (specify) 21

( Des tan) CB : 228 CC : 228 CD:

Must have 2 38 thisbles 111 ' Bank Positicas (Steps) ECS Temperature ('T): L4 ti Test , '

Conditions. Power Level (% T.P.): '7 0. 0 3 /.

SDA: 228 SDB: 228 CA: 228 0';her (Specif y):

(Actual) CB : 228 CC : 228 CD: ley' g ,

Date/ Time Test Performed: M ,

3/s 2. /'l i M N ' $l MAX KEL I

NUC ENTHAL. TOTAL HEATi QUAURANT IV Meas Parameter ASSY PVR RISE HOT TLUX HOT POWER TILT (Description) 7. DITT CHAN TACT CHAN TACT RATIO (M P)/P T dH(N) T*Q(T)

I QPTR

~ h.1 7 P Test Hessured Value P 2 Mo / j,q y 7 /

2,op3 y

/, pg 3 '

I Results Desagn Value l;;;;;;i;;;

I ' 6 #* F (Design Conds) "i'"""' '

NA NA 5 1.02 WCAP 7905 Reference WCAP 1905 REV.1 NONE NONE REV.1 Y

- ,u.r.... ....... ,; , , . , , . ,, , . . . )

l TSAR / Tech Spec NONE Acceptance NONE I

Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE Design Tolerance is set : /_ YES NO Acceptance Criteria is set L YES NO VI Comments

As Required Prepared By-Reviewed By: -N b I

i NE.8:.0 NIC9 Startup Physics Tests Report P i r." M "I 59

I NORTH ANNA PO'aER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TTST RESULTS AND EVALUATIDH SHEET 1 !TestDescription: M/D Flux Map HTP, ARD, Eq. Xe Reference '

Proc So / Section: 1 PT 21.1 Sequence step ho: q$

I 11 Test Conditions Bank Positions (Steps) RCS Temperature ('T):7 Po.e r Leve l ('l, F.P.): b5 al SDA: 228 SDB: 228 CA: 228 Other (specify): Eq. Xe.

(Design) CB . 225 CC . 220 CD:

Must have 2 38 th: 4 1es 111 Bank Positions (Steps) RCS Temperature ('T): Tr ,( 1 i Test I Conditions (Actual)

SDA: 228 SDB: 228 CA: 228 CD : 228 CC 228 CD: 229 Pos e r Leve l ( % F. P. ): qq aq Other (Specify)t 4 L' T h . .L,1 ,.s

,M I Date/ Time Test Performed:

N MAP (s

? /19 /Gl c. f l10'?

I MAX. REL NUC ENTHAL) TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RIEE HOT l FLUX HOT POWER TIL1 (Description) % DIIT CHANFACTlCHANFACT RATIO I (M P)/P

..r.,

T dH(N) j F-Q(T) QPTR Measured Value ',,- l.4I3 1.922 l c); z; Results # '9 Design Value (Design Conds) ;" i * "" . ** ';;;;;;; t ;;NA I WCAP-7905 NA t 1.02 WCAP 7905 Reference I

REY.1 NONE NONE KEV.1

. 4 V ' "

TSAR / Tech Spec NONE b '" ' ' ' ' ""li I Acceptance NONE Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE I Design Tolerance is met Acceptance Criteria is set d YES L YES _ N0

_N0 VI Comments

As kequired I P, epa,ed ,,. wasu Re ie.e4 ,,, jf Mit-I

'I I E. m ~,ce t -t , r 1c ~ xe- 1 - " " ' "

---.h

I I NORTH ANNA F0kER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I heterence Test Descriptien: M/D Flux Map- N1 Calibration Proc No / Sectaen: 1 PT 22.2 Sequence Step No: Q(,

I 11 Test Conditions Bank Positions (Steps)

SDA: 228 SDB: 228 CA: 228 RCS Temperature ('T):Tptp 11' Power Level (*, T.P. ): 9515 Other (specify): *

(Design) CB : 228 CO . 228 CD: **

111 Bank Positions (Steps) ECS Temperature ('T): Trelsl' Test I Conditions (Actual)

SDA: 228 SDB: 228 CA: 228 CB : 228 CC 228 CD 11 g Power Level (*, T.P. ): 99 2f %

Other (Specify):

MAP B I Date/ Time Test Performed:

4/t/qf 6 Tm u tk t.b I IV (Deccription)

' MAX. REL Mens Parameteri ASSY PWR

DITT NUC ENTHAL RISE HOT CHAN TACT TOTAL HEAT QUADRANT TLUX HOT POWER TILT CHAN TACT RATIO (M P)/P T dH(N) F-Q(T) QPTR

'3' M Fe' (*41i M.-7 gT,7, 9 ,f @ ,

Heasured Value #*'9 t .9 4 L Test 4 '4 "* f* '- 1.0102 Results "^

Design Value l lp, ;;

(Design Conds) "i'""y'tM -

NA NA 5 1.02

' lWCAP7905 WCAP 7905 Reference l REV.1 NONE NONE REY.1 l .,

V Acceptance TSAR / Tach Spec { NONE

""""'"*"']I #'*" NONE Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE Design Tolerance is met / ES I' Acceptance Criterla is met Y

rf,' Y ES ,_,,NO N0 VI I

Comments

Must have at least 38 thimbles for a full core ilux map, or at least 16 thisbles for a quarter core flux map.

- As Required I

Pr.,a .d ,,. m u ./ ,e,,e.ed ,,. 6 #2 I

I x r. - ~1c"- ~<~ ~ ~ " < "

I I NORTH ANNA POVER STATION UNIT 1 CYCLE 9 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I 1 Reference Test

Description:

M/D Flux Map NI Calibration Proc No / Section: 1 PT-22.2 Sequence Step No: 99 I 11 Test Conditions Bank Positions (Steps)

SDA: 228 SDB: 228 CA: 228 RCS Temperature ('F):Tpty 11 Power Level (*, r.P. ): 9515 Other (specify): *

(Design) CB : 228 CC : 228 CD: **

!!! Bank Positions (Steps) RCS Temperature ('T): T"I

Test Power Level (t F.P. ): 94 24*/,

I Conditions (Actual)

SDA: 228 SDB: 228 CA: 228 CB : 228 CC : 228 CD:205 Other (Specify):

htM y I bate / Time Test Performed:

y/ /4/

Quantec Conc M4e 31 Tm u 6<.E.5 I

MAX, REL NUC ENTHAL TOTAL HEAT QUADRANT lY Meas Parameter ASSY PWR RISE HOT TLUX HOT POWER TILT (Description)

DirF CHAN FACT CHAN TACT RATIO (M P)/P F dH(N) F-Q( T) QPTR MA uA uA v4 Measured Value Test I Results Design Value ;;;;;;;i!

(Design Conds) "a'*"' * ;'.; NA NA s 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE I

REY.1 V TSAR / Tech Spec """'"**" '"'""'""

NONE NONE Acceptance I Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE Design Tolerance is met : L YES _NO I' Acceptance Criteria is met VI : Z YES _ NO I Comments

Must have at least 38 thimbles for a full core flux esp or at least 16 thimbles for a quarter core flux map.

J**AsRequired Prepared By: Ub vb/

I Reviewed By: -

I I x,. . m Nice m ,< , sysics rests x . ,t ~ , , se - e

1 i

NORTil ANNA POWER STATION UNIT 1 CYCL.E 9 STARTUP PilYSICS TEST RESULTS AND EVALUATION SilEET I Test

Description:

M/D Flux Map N1 Calibration keference Proc No / Section: 1-PT 22.2 Sequence Step No: yf I 11 Test Conditions Bank Positions (Steps)

SDA: 228 SDB: 228 CA: 228 RCS PowerTemperature Level (t F.P. ):('F):Tphp 9 15 il (Design) Other (specify):

CB : 228 CC : 228 CD: **

111 Bank Positions (Steps) RCS Temperature ('F): Tre f d i

Test I Conditions (Actual)

SDA: 228 SDB: 228 CA: 228 CB : 228 CC : 228 CD: A2)

Power Level (% F.P. ): 4 9 m A *',

Other (Specify):

M4r10 I Date/ Time Test Performed:

4b/98 g _p 3l *THi n 8 L t M g gg I IV Meas Parameter (Desc 1ption)

MAX. REL seSY PWR

DIFF NUC ENTilAL RISE HOT CHAN FACT TOTAL HEAT QUADRANT FLUX HOT POWER TILT CilAN FACT RATIO (M-P)/P F dH(N) F-Q(T) QPTR WA ud MA NA Measured Value I Test Results Design Value ;;;ll: ;; t M (Design Conds) "i'*"' * ' NA NA 5 1.02 WCAP-7905 WCAP-7905 Reference REY.1 I

NONE NONE REV.1 V FSAR/ Tech Spee, NONE NONE I Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 NONE Design Tolerance is met : f ,YES I' Acceptance Criteria is met NO VI

4 YES NO I Comments

Must have at least 38 thisbles for a full-cure ilux sap, or at least 16 thisbles for a quarter-core flux map.

- As Required Prepared By: W/ Reviewed By: ___

g .-

I g xE. m Nice m ,m p ~ ,1<s 1 - - ,1 - w -"

_

ML20077E619

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