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Rev 0 to NE-817, North Anna Unit 2,Cycle 8 Startup Physics Test Rept. W/910128 Ltr
	ML20028H860
Person / Time
Site:	North Anna
Issue date:	01/16/1991
From:	Hoffman E, Psuik T, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	91-030, 91-30, NE-817, NE-817-R, NE-817-R00, NUDOCS 9101310165
	Download: ML20028H860 (66)
	v • d • e

o ViHo Nir 1:uTTHW AND l'OWI H C(ptPANY ltsces>susu,vnuusuns unung January 28,1991 United States Nuclear Regulatory Commission Seriai No. 91 030 Attention: Document Control Desk NL&P/JYR:Jmj Washington, D.C. 20555 Docket No. 50 339 License No. NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS REPORT Per North Anna Power Station Technical Specification 6.9.1.3 enclosed are five copies of the Virginia Electric and Power Company Technical Report NE 817, " North Anna Unit 2, Cycle 8 Startup Physics Report."

Very truly yours, A b '

W. L. Stewart Senior Vice President - Nuclear Enclosures cc: United States Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 Mr. M. S. Lesser i

NRC Senior Resident inspector i

North Anna Power Station m1aangte P

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North Anna I Unit 2 Cycle 8 l Startup Physics

'l Report ;

Nticlear Analysis and Fuel

l Nuclear Engineering Services l

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VIRGINIA POWER l

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TECHNICAL REPORT NE-817 - Rev. O I

I l NORTH ANNA UNIT 2, CYCLE 8 1

STARTUP PHYSICS TEST REPORT I

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

8. @ N u h6 I PREPARED BY:

E. A. H8f fman Date REVIEWED BY: W8 #[ l/ Hl'll T. S. Psuik Date REVIEWED BY: /~ /d*T/

A. P. Main Data APPROVED BY:

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D. Dzid'dosz [ Dato i

l QA Category: Nuclear Safety Related Keywords: N2C8, Startup I

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I CLASSIFICATION / DISCLAIMER j I

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 whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCllANTABILITY 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 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 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 property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out

,E 5 of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

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rABl.E OF CONTENTS

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I PAGE i Classification /Disclaimor............................... 1 Ta b l e o f Co n t e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

!ist of Tables.......................................... 3 List of l'igurch......................................... 4 Preface..................................... ........... 5 I

Section 1 I n t rcxluc t ion a nd Summa ry . . . . . . . . . . . . . . . . . . .

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Section 2 Control Rod Drop Time Measurements......... 16 Section 3 Cont rol Rcx! llank Wort h Hensu rement s . . . . . . . . 21 Section 4 Doron Endpoint and Worth Hensurements...... 26 Section 5 Temperaturo Coefficient Mnanurement........ 30 Section 6 Power Distribution Measurements............ 33 Section 7 References................................. 41 Startup Physics Tests Results and I APPENDIX Evaluation Shoots...,....................

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L LIST OF FIGURES l'!GURE TITLE PACE a

1.1 Core Loading Map........... ............................. 11 1.2 Beginning of Cycle fuel Assembly Burnups. . . . . . . . . . . . . . . . . 12 1 1.3 Incore Instrumentation Locations......................... 13 1.4 Burnable Poison and Source Assembly Locations............ 14 1.5 Control Rod Locations.................................... 15 2.1 Typical Rod Drop Trace................................... 19 2.2 kod Drop Time - Hot Full Flow Conditions................. 20 3.1 Bank B Integral Rod Worth - HZP........... .............. 24 3.0 llank B Di f f e rent ia l Rod Wo rt h - HZP. . . . . . . . . . . . . . . . . . . . . . 25 4.1 Boron Worth Coefficient.................................. 29 6.1 Assemblywise Power Distribution - 28% Power.............. 37 6.2 Assemblywise Power Distribution - 72*. Power.............. 38 6.3 Assemblywise Power Distribution - 90% Power.............. 39 6.4 Assemblywise Power Distribution - 100% Power....... ..... 40 5

NE-817 N2CB Startup Test Report Page 4 of 63

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I j TAh!.E 01< CONTENTS PAGE

,I ig Classification / Disclaimer............................... I 1g T a b l e o f Co n t e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

, List of Tables.......................................... 3 List of T1gures............................... . . . . . . ... 4 Preface................................................. 5 Section 1 Introduction and Summary...................

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Section 2 Control Rod Drop Time Hensurements......... 16 Section 3 Control Rod Bank Worth Measurements........ 21 Section 4 Boron Endpoint and Worth Haasurements...... 26 Section 5 Temperature Coefficient Measurement........ 30 Section 6 Power Distribution Measurements............ 33 1

Section 7 References................................. 41 l APPENDIX Startup Physics Tests Results and Evaluation Sheets.................. . . ... 42 I

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! 1.IST OF TABl.ES TABLE TITLE PAGE I

, 1.1 Chronology of Tests................................... 10 g i

2.1 llot Rod Drop Time Summary.............................

g 18 3.1 Control Rod Bank Worth Summary........................ 23 4.1 Boron Endpoints Summary............................... 28 5.1 Isothermal Temperature Coefficient Summary............ 32 6.1 Incore Flux Map Summary............................... 35 i 6.2 Comparison of Measured Power Distribution Parameters "

With Their Technical Specifications Limits............ 36 I

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I NE-817 N2C8 Startup Test Report Page 3 of 63 g

a LIST OF FIGURES I FIGURE TITLE PAGE I

1.1 Cote Loading Map............ ............. ...... ....... 11 1.2 Beginning of Cycle Fuel Assembly Burnups................. 12 1.3 Incore Instrumentation Locations......................... 13 1.4 Burnable Poison and Source Assembly Locations............ 14 1.5 Control Rod Locations.................................... 15 2.1 Typical Rod Drop Trace................................... 19 2.2 Rod Drop Time - flot Full Flow Conditions. . . . . . . . . . . . . . . . . 20 3.1 Bank B Integral Rod Worth - IlZP.......................... 24 3.2 Bank B Differential Rod Worth - IlZP...................... 25 4.1 Boron Worth Coefficient.............................. ... 29 6.1 Assemblywise Power Distribution - 28% Power.............. 37 6.2 Assemblywise Power Distribution - 72% Power.............. 38 6.3 Assemblywise Power Distribution - 90% Power. . . . . . . . . . . . . . 39 6.4 Assemblywise Power Distribution - 100% Power............. 40 I

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PREFACE I

This report presents the analysis and evaluation of the physics tests which were performed to verify that the North Anna 2, Cycle 8 core could I be t ' orated 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 detailed data taken. Standard test techniques and methods of data analysis were used. The test data, results anti evaluations, together with the detailed t.tartup 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 summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.

The North Anna 2, Cycle 8 Startup Physics Tests Results and Evaluation Sheets are included 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 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 ritartup physics testing. The entries for the l design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and fuel Group . 3 During the tests, the data shents were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliminary g NE-817 s2Cs Startup Test Report Page 5 of 63

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comparison between measured and predicted test results, thus enabling a

, quick identification of possible problems occuring during the tests.

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L SECTION 1 INTRODUCTION AND

SUMMARY

I On \ugust 21, 1990 Unit No. 2 of the North Anna Power Station shutdown for its seventh refueling. During this shutdown, 78 of the 157 fuel assemblics in the core were replaced with 64 fresh fuel assemblies I and 14 twice burned fuel assemblies. Theeighthcyclecoteconskstsof 14 sub-batches of fuel: four once-burned batches from Cycle 7 (batches I 9A, 9 11 , N1/10A and N1/10B); seven twice-burned batches, one from North ,

1 Anna 1 Cycles 3 and 4 (batch N1/5), one from North Anna 2 Cycle 5 and North Anna 1 Cycle 4 (batch N1/6), one from North Anna 1 Cycles 5 and 6 (batch N1/7), one from North Anna 2 Cycles 2 and 3 (batch 4), one f rom North Anna 2 Cycles 3 and 4 (batch SA), and two f rom North Anna 2 Cycles 6 and 7 (batches 8A and 8B); one thrice-burned batch from North Anna 2 Cycles 5, 6, and 7 (batch 7A); and two fresh batches (betches 10A and 10B). The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The incore instrumentation locations are identified in Figure 1.3. Figure 1.4 I identifies the location and number of burnable poison rods and source assemblies for Cycle 8, and Figure 1.5 Identifies the location and number of control rods in the Cycle 8 core.

On November 1, 1990 at 1735, the eighth 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-817 N C8 Startup Test Report Page 7 of 63

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 control rod bank worths were measured using the rod swap technique' and the results were within 4.7% or 30 pcm of the de ign predictions. The sum of the individual measured control rod bank worths was within 1.0% of the design prediction. These results are within the design tolerance of 115% or 1100 pcm for individual bank worths (110% for the rod swap reference bank worth) and the design tolerance of 10% for the sum of the individual control rod bank worths.

3. Measured critical boron concentrations for two control bank configurations were within 10 ppm of the design predictions.

These results were within the design toler'.nces and also met the Technical Specification 4.1.1.1.2 criterion that the o";rall core reactivity balance shall be within 21% Ak/k of the design prediction.

4. The boron worth coefficient measurement was within 1.4% of the design prediction, which is within the design tolerance of 110%.

5, The measured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within 0.87 pcm/'F of the design prediction. This result is within the design tolerance of 13 pcm/'F. The measured ITC of -1.37 pcm/'F meets the Technical Specification 3.1.1.4 criterion that the moderator temperature coef ficient (MTC) be less than or equal to +6.0 pcm/'F. When the NE-817 N2C8 Startup Test Report Page 8 of 63

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'I Doppler temperature coefficient and a 0.5 pcm/'F uncertainty are accounted for in the MTC limit, the MTC requirement is satisfied i

as long as the ITC is less than or equal to +3.75 pcm/'F.

< 6. Mode 1 (See Reference 4) core power distributions were within established design tolerances. Generally, the measured core power distribution was within 2. 27. of the design predictions.

The heat flux hot channel factors, F-Q(T), and enthalpy rise hot channel factors, F-DH(M), were within the limits of Technical Specifications 3.2.2 and 3.2.3, respectively, i

In summary, all startup physics test results were acceptable.

Detailed results, specific design tolerances and acceptance criteria for each measurement are presented in the following sections of this report.

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I Table 1.1 NORTil ANNA 2 - CYCLE 8 STARTUP PilYSICS TESTS

, CilRON0 LOGY OF TESTS I

Reference Test Date Time Power Procedure Hot Rod Drop - Hot Full Flow 10/31/90 2330 HSD 2 PT-17.2 Zero Power Testing Range 11/01/90 1800 HZP 2-PT-94.0 Reactivity Computer Checkout 11/01/90 1831 IlZP 2-PT-94.0 Boron Endpoint - ARO 11/01/90 2110 llZP 2-PT-94.0 g Temperature Coefficient - ARO 11/01/90 2154 HZP 2-PT-94.0 g Bank B Worth 11/02/90 0008 llZP 2-PT-94.0 Doron Endpoint - B in 11/02/90 0330 llZP 2-PT-94.0 Bank D Worth - Rod Swap 11/02/90 0456 HZP 2-PT 94.0 Bank C Worth - Rod Swap 11/02/90 0657 HZP 2-PT-94.0 Bank A Worth - Rod Swap 11/02/90 0752 HZP 2-PT-94.0 Bank SB Worth - Rod Swap 11/02/90 0815 HZP 2-PT-94.0 Bank SA Worth Dcd Swap 11/02/90 0909 HZP 2-PT-94.0 Flux Map '.f4 Power 11/04/90 1530 28*. 2-PT-21.1 Plux Map - QPTR Verification 11/07/90 2300 72*. 2-PT-21.1 Flux Hap - QPTR Verification 11/08/90 1830 9 0 *. 2-PT-21.1 Plux Map - HFP 11/14/90 1400 100*. 2-PT-21.1 Flux Map - t/E Calibration 11/15/90 0600 100*. 2-PT-22.2 Flux Hap - I/E Calibration 11/15/90 1700 100*. 2-PT-22.2 I

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NE-817 N2C8 Startup Test Report Page 10 of 63

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B I;g NE-817 x2Cs startup Test Report rage 13 or 63 K

I Figure 1.4 NORTH ANNA UNIT 2 - CYCLE 8 BURNAllLE POISON AND SOURCE ASSEMBLY LOCATIONS W P N p L g J H G F E D C S A l i i l i I I i 1 i l I I I i i l i i l l I 4p 1 I 4p i I I 2 i i l i i l I i I .

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I I

I NE-8)? N2C8 Startup Test Report Page 14 of 63

~

r L

Figure 1.5 NORTil ANNA UNIT 2 - CYCLE 8 CONTROL ROD LOCATIONS I R P N N L K J H C F E D C 8 A 180 i Loop C l l l

l l Loop B 1 Outlet i l i i Inlet l N-41 Nl_l ^ ll sA Il l l 1 l

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8 8

shutdown Bank sB 8 shutdown Bank sA I sP (spare Rod Locations) 8 8

i NE-817 N2C8 Startup Test Report Page 15 of 63 1

F f)

SECTION 2 0

CONTROL ROD DROP TIME MEASUREMENTS The drop time of each cont'rol rod was measured at hot full-flow reactor coolant system (RCS) conditions in order to verify tht t Go time f rom initiation of the rod drop to the entry of the od into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.1.3.4. The control rod drop times were measured in Mode 3' with RCS Tavg above 500'P and all reactor coolant pumps operating.

The rod drop times were measured by withdrawing a rod bank to its fully withdrawn position, and removing the movable gripper coil fuse and stationary gripper coil fuse for the particular rod c,f 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 (IRPI) primary coil voltage signals were recorded to determine the the rod drop time. This procedure was repeated for each control rod.

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. A* the rod drops, a voltage is induced in the IRPI primary coll. The magnitude of this voltage is a f anction of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing e 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-817 N2C8 Startup Test Report Page 16 of 63 1

I The measured drop times for each cont rol rod are recorded on l'igure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 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 .;

satisfied this 'imit.

I-I I

I I

P NE-817 N2C8 Startup Test Report Page 17 of 63 A

s s

F Table 2.1 L

NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESTS Il0T ROD DROP T!HE

SUMMARY

I ROD DROP TIME TO DASilPOT ENTRY I

SLOWEST ROD FASTEST ROD AVERAGE TIME

~

I B-06 1.80 sec. C-09 1.44 sec. 1,59 sec.

1 I

I I

NE-817 N2CB Startup Test Report Page 18 of 63 1

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i Figure 2.2 I NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PliYSICS TESTS ROD DROP TIME - Il0T FULL FLOW CONDITIONS I

R P N M L E J H G F [ D C B &

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I I

g me.e1, x2ce St.,< ,1. < R., ,< e... 2e .< eS 0

SECTION 3 I

CONTROL ROD BANK WORTil MEASUREMENTS I

Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 8. The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereaf ter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank m;vements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 8, Control Bank B was used as the reference baak. -

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. Inicial statepoint 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 point, 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 bank) 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-817 N2C8 Startup Test Report Page 21 of 63 i

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 v

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 (110* for the reference bank,115% for each test bank worth greater than 600 pcm, and 100 pcm for each test bank worth of less than 600 pcm). The sum of the l

l Individual measured rod bank worths was within 1. 0 *. of the design prediction. This is well within the design tolerance of 110*. for the sum l of the individual control rod bank worths.

The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3. 2, respectively.

The design predictions ar.d the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.

I NE-817 N2C8 Startup Test Repcrt Page 22 of 63

L L Table 3.1 NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESTS CONTR0!. ROD BANK WORTil

SUMMARY

l HEASURED PREDICTED PERCENT DIFFERENCE WORTil WORTil (%)

BANK (PCM) (PCM) (M-P)/P X 100 D Referenco liank 1259.9 1264.0 -0.3 D 1025.7 999.0 2.7 I C A

710.3 330.5 739.8 307.7

-4.0 7.4

SB 976.6 996.4 -2.0 I SA Total Worth 1061.7 5364.7 1014.1 5321.0 4.7 0.8 1

Difforence is less than 100 pcm.

I I

NE-817 N2C8 Startup Test Report Page 23 of 6.

I Figure 3.1 NORTH ANNA UNIT 2 - CYCI.E 8 STARTUP PHYSICS TESTS BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN t

I t

1'300 2 L

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BANK POSITION (STEPS)

I 1 I NE-817 N2C8 Startup Test Report Page 24 of 63 I

Figure 3.2 NORTH ANNA UNIT 2 - CYCLE 8 STi.RTUP PHYSICS TESTS BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN I

I I

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BANK POSITION (STEPS)

NE-817 N2C8 Startup Test Report Page 25 of 63 1 1

I SECTION 4 I

BORON ENDPOINT AND WORTH HEASUREHENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank conf Qurations to enable a direct comparison of measured boron endpoints I 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. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position 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 and met the requirements of Technical Specification 4.1.1.1.2 regarding core reactivity balance.

In summary, the boron endpoint results were satisfactory.

I Boron Worth Coefficient The measured boron endpoint values provido stable statepoint data f rom which the boron worth coef ficient or dif ferential boron worth (DBW) was determinnd. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.

NE-817 N2C8 Startup Test Report Page 26 of 63 l

l A plot of the boron concentration versus inserted control rod worth I

is shown in l'igure 4.1, As indicated in this figure and in the Appendix, the DBW measured was -7.04 pcm/ ppm.. This is within 1,4% of the predicted value of -6,94 pcm/ ppm and is well within the design tolerance of 110%.

In summary, the measured boron worth coefficient was satisfactory.

I I

I NE-817 N2C8 Startup Test Report Page 27 of 63

I I Table 4.1 I

NORTH ANNA UNIT 2 - CYCLE 8 STARTUP PHYSICL TESTS DORON ENDPOINTS

SUMMARY

I Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm)

ARO 2073 2063 +10 B Bank In 1894 1890* +4 I

I

The predicted endpoint for the b Bank In configuration was adjusted for the dif ference between the measurt.d and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation I Shoots in the Appendix.

I I

I E

NE.e1, N2ce Sta, tup rest eeport 2e of es g Pase

I Figure 4.1 I

NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESTS BORON WORTil COEFFICIENT I I

I NORTH ANNA UNIT 2 CYCLE 8 PHYSICS TEST BORON WORTH COEFFICIENT Measured DBW = -7.04 pcm/ ppm 1,300 - ; .

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! - - -i--4-I--l I

i ! i 4- !--l-+j!-l 1 i .

300 l- l -+

l l 4-t--

i

!- 4 L-+i e! --

! i l I ;- l 4 L-4-I- - --

i l l I I

-.L' .-al.4-l .l' l I4 !;

L.. +l l l l

+-+-?-! - .a 200

! ' i l i !i I- +. - d--l--l-+l.-:I' '

!l i

]QQ 4 .1 - ' 4-.}

i

~ . 4 . .v .l' .'I t..

4 l

.l i. l _.Ii _.i -.'. ~.4 i

i' i' I

O 1500 1900 1920 1640 1960 1990 2000 2020 2040 2060 2000 2100 BORON CONCENTRATION (PPM)

I I

NE-817 N2C8 Startup Test Roport Page 29 of 63 l

J SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT I

The isothermal temperature coefficient (ITC) 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 changes on the reactivity computer. Typically, this test sequence includes a cooldown followed by a heatup; however, the heatup ITC was not within 1 pcm/'F of the cooldown ITC as specified in Station Procedure 2-PT-94.0, therefore; a second cooldown was done to remeasure the ITC.

Reactivity was measured during both RCS cooldowns of approximately 2.8'F. Reactivity and temperature data was taken from the reactivity computer and strip chart recorders. Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature An X-Y plotter, which I plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured ITC.

Tbo predicted and measured isothermal temperature coef ficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the NE-817 N2C8 Startup Test Report Page 30 of 63

design tolerance of 3 pcm/'F and met the requirements of Technical Ii i Specification 3.1.1.4, In summary, the measured result was satis factory.

I t

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1 Il i I'

ll ,

l' ll l

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NE-817 N2C8 Startup Test Report Page 31 of 63

+

F Table Sol L

NORTH ANNA UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

3 l

i ISOTHERMAL TEMPERATURE COEFFICIENT BANK TEMPERATURE BORON (PCM/'F)

POSITION RANGE CONCENTRATION

('F) (ppm) C/D C/D AVE. DIFFER.

1 #2 MEAS. PRED. (M-P) g 543.5 g D/228 to 546.3 2083 -1.25 -1.48 1.37 -0.50 -0.87 I

I I

I NE-817 N2C8 Startup Test Report Page 32 of 63

s

~

SECTION 6 i POWER DISTRIBUTION MEASUREMENTS l

The core power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in 46 core locations (see Figure 1.3). For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and I scanned for 61 discrete axial points by the PRODAC P-250 process computer.

Full core, three-dimensional power distributions are determined f rom this data using the Westinghouse computer program, INCORE3 . INCORE couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the powet 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 limits is given in Table 6.2. Flux Hap 1 was taken at 28% 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 and 4 were taken at 72%, 90% and 100% power levels with dif ferent control rod configurations. These flux maps were taken to check at power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2, 6.3 and 6.4. These figures show that the measured relative assembly power values wcre generally within 2.2% of the predicted values. Further, the measured F-Q(T) and F-DH(M) peaking factor values for the at power flux maps were NE-817 N2C8 Startup Test Report Page 33 of 63

i I

l l

within the limits of Technical Specifications 3.2.2 and 3.2.3, respectively.

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

E I

I I

I E

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NE-817 N2CB Startup Test Report Page 34 of 63

I TABLE 6.1 NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PIIYSICS TESTS INCORE FLUX HAP

SUMMARY

I I I l 1 l l l l 1 i i I l l l l l l l BuRNI l } F-Q(T) HOT I F DH(M) HOT l CORf f(l) l 2 l l l l NAP lMAPI l UP l l BANK l CHAM 4E L F ACION l CHNL.FACIDR l MAX l QPTR l AXIAL l NO.l l IKSCRIPfl0N lNO I Daft l MWD /IPWRi D l l l l l OF F l OF l l l l l Mfu l(2)lSitPSlasSVIPINlAalAtj l AS$YlPINIF-Deu Mil AMI At t f (2 31 Max lLOCl SE f lIH!Mi l l l l l 1 l 8 jPOINflF-Q(i) l l l lP0lNil l l l (%) 18LESI

! L . .L R irlii.04.,0l i. lT.l is0 inlwi 30 I ,.m Inlw! .s,, l 30 lmr,lanlv.l=,2lv,-!

l0PIR ViklF]C A f!DN l 2 lll*01 99l 63 l 72l 18% l H 5l IHj 29 l 2.041 l J 4l H!l 1.443 l 28 ll.102fl.elll NWl l.eSi 46 l l0PIR Vf RIF IC AflON l 5 Ill*04-901 88 l 901 204 l L 41 P!l 29 l 1.923 l L 41 Pil 1.423 l 29 11.23718.0041 NWI 4.16) 46 l I lHof FULL PowtR Im l4 l1144 90131% l1001228 l F 31 til 36 l 1. 684 l F S t (E l 1.414 1 56 14.22214.006l NW) -1.36l 44 l 1,l l l_ l l_l_l l l_i_1 l l 1 (_ _l l_1 N0f t$s H0f SPOf LOCAI10NS ARE SPECIFIED SV CIVING AS$tMSLV LOCAfl0NS ([.C. H-8 IS THE CENTER OF-CORZ ASSEMBLVI, i FULL DwtD By IM PIN LOCAIION (!!f M0f f D SY IHE "V" CDORDINAf E WifH IHE SEVINIEf N ROWS OF FUEL RODS LE T f t RED A ItStouCH R AND IHE "X" C00R0!NAf[ DESICMATED IN A $1 MIL AR MANNE R).

IN f Ht *2" DIRicil0N IT CORE IS DIVIDE D INTO 61 AxlAL PotMIS STARf!NG FROM IHE TOP OF THE CORE.

I 1. F-Otil INCluCES A 10f AL UNCERI AINTV of 1.0% X l.03.

2. QPf p - QUADRANT POWE R ilLI RAfl0.

3. MAPS $ AND 6 MRE QUARI!R CORE FLUX MAPS T AXEN FOR INCORf /tXCORE Call 8 pall 0N. ( t/E cal!8RAf!ON)

I I

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x2ce St.,<., T..< x. .,< .< es g xE.e 1, r. . 3 I

I Table 6.2 NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITil TilEIR TECIINICAL SPECIFICATION LIMITS I

I F-Q(T) HOT F-DH(M) HOT CHANNEL FACTOR

CHANNEL FACTOR MAP NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN

(%) ( 7. )

1 2.237 4.368 48.8 1.523 1.813 16.0 2 2.041 3.020 32.4 1.443 1.614 10.6 3 1.923 2.419 20.5 1.423 1.534 7.2 4 1.888 2.190 13.8 1.414 1.490 5.1 =

E

The Technical Specification's limit for the heat flux hot channel factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q(T) in the core.

The Technical Specification's limit listed above is evaluated at I the plane of maximum F-Q(T). The minimum margin values listed 3 above are the minimum percent difference between the measurqd values of F-Q(T) and the Technical Specification's limit for each g map. The measured F-Q(T) hot channel factors include 8.15% total uncertainty.

g I

I I

I NE-817 N2C8 Startup Test Report Page 36 of 63

I I Figure 6.1 NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 28% POWER R P N M L K J H C F E D C 8 A

. Pel DICit D . 0.23 . 4.27 . 0.23 . PRf DICTED .

, , ME ASUwf D .

' O.25 . 0.30 . 0.24 . MLAsuutD . l

. PCT DIFilRENCE . . 12.0 11.9 . 7.9 . .PC f DirFEJENCE.

. 0.31 0.61 . 1.07 0.82 1.01 . 0.61 . 0.31 .

0.34 . 0.64 . 1.13 . 0.86 1.13 . 0.63 . 0.32 2 7.3 4.2 5.2 5.2 5.0 . 3.5 3.6 5 .

0.34

. 0.35 2.5 .

1.16 4.19 2.3 1.33 . 1.24 . 1.32 . 1.24 . l.33 l.34 . I.27 . 1.35 . l.26 . 3.35 . I.19 . 0.35 .

0.9 . 2.3 2.1 1.5 1.4 1.16 . 0.34 .

2.5 3. 7 .

3 0.34 0.86 1.37 1.21 1.37 1.l? 1.37 . 1.21 . 1.37 . 0.86 0. 34

. 6.35 0.87 l.40 . 1.23 . 1.40 . l.19 . 1.38 . 1.21 1.36 . 0.85 0.34 . 4 1

I . 2.5 . 1. 3 . 2.0 1.3 2.5 . 2.3 . 0.9

-0.2 -0.6 -0.9 0.3

. 4.31 . 1.16 1.37 1.18 1.24 1.20 1.11 1.20 . 1.24 1.18 . 1.31 1.16 0.31 .

0.31 . 1.14 I.36 . 1.17 1.28 . l.23 . l.14 1.21 . 1.28 1.16 . 1.12 . 1.44 0.32 . 5 I . -l.9 . -1.9 0.61 0.4

-1.0 . -0.5 1.32 . 1.21 . 1.28 . l.05 . l.26 1.33 . 1.21 . 1.28 . 1.05 . 1.28 6.3 . 0.3 . 6.1

-0.5 .

0.3 2.4 1.5 .

2.5 .

1.01 1.1 .

1.3 0.61 0.99 1.26

-0.1 . I.6 . -3.4 1.05 . 1.24

-1.4 1.27 . l.04 . 1.25 . 1.16 . 1.30 . 0.62 .

0.7 -0.4 . -2.6 . -3.7 . -2.0 .

1.21 . 1.32 . 0.61 .

3.0 1.3 .

6 I . 0.23

. 0.24 . 1.10

. 7.9 .

1.07 . 1.24 2.4 .

. l.25 . 1.36 0.4 . -0.4 1.36 . 1.14 1.11 1.1

. l.25 . l.14 . 1.25 . I.14 . 1.25 . 1.18 . 1. 36 . 1.24 . l.07 . 6.23 .

. l.23 . 1.16 . 1.28 . 1.l4

. 1.2 . 1.6 . l.1 -0.0 . -0.9 . 2.1 -4.3 . 1.7 1.24

......, ...............+.... .............................................................. ..............

0.27 0.82 . l.32 . 1.16 . 1.09 . 0.95 . 1.25 1.16 1,10 1.22 0.90 . 1.25 . 0.95 . 1.09 . 1.16 . 1.32 . 0.82 . 0.27 .

1.06 0.23 .

0.6 . 0.4 .

?

0.29 0.8% , 1.32 1.16 1.09 . 0.95 . l.25 . 0.6A . 1.23 . 0.93 . l.05 1.11 . 1.29 . 0.82 . 0.27 8

. #.8 2.9 . 0.1 0.2 0.2 . 0.2 . -0.8 . 1.6 . *l.6 . -1.6 . a3.1 . -4.2 . -1.7 . 0.6 . 2.1 1 ..................... ............. ............. ............. ............. ............, ..............

. 0.25 1.07 1.24 . 1.36 1.14 . 1.25 . 1.14 . 1.25 1.44 1.25 . l.18 . 1.36 . 3.24 . 1.07 . 0.23 .

0.24 1.04 . 1.21 1.35 . 1.19 . 1.24 1.11 . 1.22 . 1.12 . 1.23 . 1.17 . 1.33 . l.23 . 1.04 . 0.23 9

. 7.9 1.0 . -2.5 . -1.1 . 9.2 -0.6 . -2.5 . 2,4 , - l . 7 . - 1. 7 . - 1. 3 . 2. 4 . 0.4 . 1.1 2.8 .

I

. 0.61 1.32 . 1.21 . 1.28 . 1.05 . 1.26 . 0.99 . 1.26 . 1.05 1.20 . 1.21 . 1.32 . 0.61 .

0.59 1.24 . 1.20 1.24 , 1 04 1.25 . 0.98 . 1.25 . 1.03 1.26 . 1.20 . l.32 0.63 10

-3.0 . 3.0 0.7 . 4.4 . -1.0 . -1.3 . -4.0 . - l . 4 . - 1. 5 . - 1. 3 . 0 . 6 . - 0.1 2.6

. 0.38 1.16 1.37 . l.18 . 1.28 . 1.20 1.11 . 1.20 1.28 1.18 . 1.37 1.16 0.31 .

I .

0.31 . l.16 0.1 . 0.1 .

1.37

. 0.34 . 0.86 . 1.37

. 0.35 . 0.87 1.18 0.2 . 0.4 . al.4 1.26 . 1.16 1,C1 . 1.37 1.34 . 1.20 . 1.36 al.3 1.10 . 1.18 . l.26

-1.2 . al.3

-l.7 .

1.17 . 1.37 . 1.21 . 1.37 1.17 0.6 .

1.34 . 1.17 . 0.32 .

0.7 1.0 .

0.86 . 0.34 .

I.16 . 1.35 . 1.19 . 1.36 . 0.87 . 0.35 .

2.2 11 12 I

. 3.1 . l.8 . 0.4 . 0.9 . -0.7 . -0.6 . -1.1 . -1.6 . -1.0 . 1.3 . 22.

. 0.34 1.16 . 1.33 . 1.24 . 1.32 . 1.24 . 1.33 . 1.16 0.34

. 0.35 . 1.I6 . 1.30 . 1.23 . 1.31 . 1.23 . 1.30 . 1.15 0.34 . 13

. 3.1 . 0.4 . -2,2 . -l.2 . -1.3 . -0.9 -1.7 . -0.6 . 2.0 .

l ." nudlir DEVI ATION

. 0.31 . 0.61 . 1.07 . 0.82 . 1.07 . 0.61 . 0.31

. 0 . 34 9.i .

0 67

.i

. 1.12

' "" . TiiTi:W 4.5 .. 0.454. 0 .. 1.0,7.

-0. . 0.60-i.6 . 0.31

. Tir. """ *"" "

0.25 . 0.29 . 0.25 .

-i.7 .

" 'sii14r ":

. PCT O!FFE9ENCE.

14 15 I

. =2.284 . . a.s . a.7 . a.8 . .

. 2.2

SUMMARY

I MAP N0s H2-8-01 CONTROL ROD POSITIONS:

DATES 11/04/90

-Q(Tl a 2.237 POWERI 28%

QPTR:

D BANK AT 150 STEPS F DH(M) = 1.523 NW l.011 l NE 0.996 I

I F(Z) r 1.372 SW 0.999 l SE 0.992 BURNUP a 18 NWD/MTU A.O. s -3.264%

i g No.e1, H2ce St ,<.,1. < e.g.,< e.s. S, .< eS

__ _ __ _ O_

I Figure 6.2 NORTH ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESTS ASSEMBLYWISE PCWER DISTRIBUTION 72% POWER H P N M L E J H C f f 0 C 8 A PWIDICIfD . ......0.25 . 0.31...... 0.25 PWf DIC14 0

. MF ASUWt 0 . . 9.27 0.32 . 0.26 Hf ASUWf D . 1

. PC I D if f f Wt hCE . 4.4 4.3 3.5 . .. PC T D !f Fl pl WCE .

4.32 0.63 1.10 4.90 1.10 . 0.63 0.32 4 . 34 0.66 1.14 0.95 1.13 4.64 0.33 2 3.2 4.7 2.9 . 2.9 2.1 2.6 2.1 .

0.3% l.12 1.28 1.23 l.31 1.23 1.28 1.12 0.3%

0.3% l.11 . l.30 1.26 . 1.34 1.25 1.30 1.14 0.3% 3 1.0 0.8 . l.6 . 2.7 2.4 1.6 1.7 1.7 1.7 0.3% 4.8% l.31 1.18 1.33 1.1% 1.33 1.18 1.31 0.6% 0.3%

0.3% 0.8% 1.33 1.20 . 1.36 1.18 1.3% 1.14 . l.31 . 0.84 . 0 . 34 4 0.9 0.7 1.1 . 1.9 2.6 . 2.6 1.4 . 0.4 . 0.5 . l.0 . -1.1 0.12 1.15 1.31 1.16 1.27 1.19 1.12 1.l* l.27 1.16 1.31 . 1.13 . 0.32 0.32 1.11 . l.31 . 1.16 1.28 . l.25 1.15 1.21 1.27 1.14 1.28 1.10 0.37 . %

. 1.3 . -l.3 0.2 . 0.3 0.4 . 2.7 2.4 1.6 0.2 -1.0 2.5 2.4 0.S

...........=..

0.63 1.28 . ...... l.18 . ......

l.27 . ...........................

1.12 1.28 . 1.02 1.28 .... 1.12. i 27 1.18 1.28 0.63 0.63 . l.29 l.19 4.24 1.14 . 1.3% l.04 1.29 1.11 1.24 . 1.15 1.25 0.62 6

. 0.6 0.6 . 0.4 . 1.0 . l.5 . 2.1 . 2.2 4.8 -0.4 1.8 -2.5 -2.5 . 1.1 0.25 1.10 . 1.23 . 1,32 1.18 . l.27 1.17 . 1.27 1.17 1.27 1.18 . L.32 1.23 1.10 . 9.25

~

0.26 1.11 . 1.23 . 1,32 . 1.14 . 1.27 . 1.19 . 1.29 1.17 . l.26 . 1.17 1.28 1.20 1.08 0.25 7

. l.9 0.9 4.5 0.1 . -6 2 . 0.3 . 2.0 . 2.1 . 0.3 0.7 . -1.3 -3.1 -2.4 -1.8 . al.1 .

0.31 4.90 1.3% l.15 1.10 . 0.98 . l.26 . 0.93 1.26 0.98 . l.f0 1.15 1.31 0 90 0.31 .

0.31 . 0.91 . 1.31 . 1.15 . 1.11 . 0.94 . 1.26 . 0.92 . 1.24 . 0.96 . 1.08 . 1.11 1.28 . 0.89 0.31 . 8 L.6 . 4.1 . 0.2 . 0.4 . 9.4 . 0.4 0.1 -0.8 . 1.7 -l.6 . -2.0 . *3.1 . -2.1 . -1.5 1.0 .

0.2% . 1.10 . l.23 . 1.12 . l.18 . 1.27 . 1.17 1.27 1.17 . 1.27 . 1.18 . 1.32 1.23 . 1,14 . 9.25 6.26 . 1.99 1.20 1.31 . 1.19 1.27 . 1.16 1.27 1.15 1.2% . 1.17 4 30 1.21 1.09 0.25 9 1.9 0.9 - 2. 3 . - 0.9 , 4.5 6.2 . -0.2 . -0.1 -1.8 1.9 . *l.2 , -1,7 . -1.0 1.1 -0.4 0.63 . 1.28 1.18 1.27 . l.12 1.28 . 1.02 . 1.28 1.12 1.27 1.18 1.28 0.63 0.61 1.24 1.17 1.28 . 1.12 1.29 . 1.02 1.27 l.nl 1.26 1.16 1.28 . 0.63 10 2.9 . 2. 9 . - 0. 5 . 4.4 0.2 . 0.3 . 4.4 +0.7 0.9 -0.5 03 +0.2 -0.3 .

0.32 1.13 . 1.31 1.16 1.27 1.19 1.12 . 1.19 1.27 1.16 1.31 1.13 0.32 0.32 . l.10 . 1.30 . 1.16 . 1.27 . 1.24 . 1.12 1.20 . 1.27 . 1.16 1.32 . 1.13 0.31 . 11 2.0 -2.9 -1.8 0.7 . *t.4 . 0.1 0.2 . 0.3 0.2 0.3 . 0.6 . 0.3 0.3 4.3% . 4.8% 1.31 . 1.18 . 1.33 1.15 1.33 . 1.18 . 1.31 . 0.8% . 0.35

. 6.34 0.45 . l.12 . 1.18 . 1,33 1.1%.l.33 1.18.l.32.0.86.0.35 12

, -l.0 0.2 . 0.7 . -0.0 -0.0 . 0.0 . 0.1 . 0.1 0.3 . 0.0 . 0.4

. 4.3% . 1.12 1.24 . 1.23 1.34 . 1.23 . 1.24 . 1.12 . 0.35 .

. 0. 34 1.13 . 1.27 1.22 . l.14 1.23 . 1.28 1.13 0.3% . 13 1.4 . 0. 7 . - 0. 7 . 0.5 . -0. 5 -0.1 0.1 0.3 0.8 .

4.32 . 4.63 1.10 0.9) 1.10 0.63 4.32

. 4.33 . 0.64 . 1.11 . 0.91 1.10 . 0.63 . 6.32 . 14

. 2.1 . 2.4 . 0.4 0.5 0.1 0.1 . -0.1 .

STANDARO . . 0.25 0.31 . 4.25 . . AvfpAGE .

DEVI A TIDM , 0.26 . 0.31 . 0.26 .PCI DIFFf WE NCE. 15 64.991 . 1.4 0.9 4.1 = 1.2 SLR91ARY HAP H0 K2 6 02 DATE: 11/07/90 POWERI 72%

CONTROL ROD POSITIONSI F-QtT) a 2.041 QPTRI W D BANK AT 185 STEPS F-DH(M) a 1.443 W 1.011 l NE 0.997 F(Z) = 1.302 SW 0.997 SE 0.995 BURNUP = 63 NWD/MTU A.D. = 1.0454 I

NE-817 N2C8 Startup Test. Report Page 38 of 63 l

. . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - 0

r I Mgure 6.3 NORTil ANNA UNIT 2 - CYCLE 8 STARTUP PilYSICS TESf5 ASSEMBLYWISE POWER DISTRIBUTJON 90% POWER R P N N L 0 J H C F C D C 0 A

~0 $hh 15h .3 t6 Pfkhhhhhh

. 3h[hiChkh'.

MEASURED . 0.27 0.33 . 0 27 . . ME AsuPtD . 1

.PCI DIFFE RENCf . 4.2 4.1 3.4 .PCI DlFFERENCf .

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

. 0.33 . 0.61 1.11 0.93 1.11 0.63 0.33 0.34 0.64 1.13 0.95 1.14 . 0.68 0.35 2

5. 2.1 1.9 . 1.9 . 2.1 2.6 . J.2 .

0.35 1.11 8.de '.22 . l.30 . 1.22. 1.27 1 11 . 0.35 0.35 1.12 1.27 1.24 1.32 1.24 1.29 1.13 . 0.35 3 1.5 1.1 . -0.0 1.3 1.2 . 1.2 1.5 . 1.6 . 1.8 a 0.35 . 0.84 . 1.30 1.17 1.32 1.15 . 1.12 . 1.17 . 4.30 0.84 0.35 .

0.35 0.85 . 4.31 1.18 . 1.34 1.17 1.33 . 1.17 . 1.29 0.6 0.35 . 6 t 0.33

. 1.5 1.11 0.7 1.30 1.2 1.15 . 1.27 1.5 1.9 1.20 1.9 .

1.12 0.2 1.20 0 . 3 . - a . . . 0 . 6 . - 0 .1 .

1.27 1.15 1.30 1.11 . 0.33

. 0.32 1.10 1.29 1.15 . l.28 1.23 . 1.16 1.21 . 1.27 . 1.14 1.27 . 1.10 0.3% 5 I . 0.63

. 0.63 1.4 -1.4 1.27 1.27 0.0 . -0.0 .

.-0.7.-0.3. 0.6 .

1.17 . 1.27 . 1.15 . 1.29 1.17 . 1.27 1.17 1.33 . 1.06 0.2 0.3 . 1.4 .

3.0 3.1 . 3.1 2.9 . l.6 1 03 0.t l.31 . 1.15 . 1.25 1.4 .

-0.7 0.0 . -1.6 . -2.3

. -1.1 . -1.1 .

1.29 . 1.15 . 1.27 1.17 1.27 1.14 . 1.2S 0.63 .

l.7 .

l.6 .

6 63 0.0 6 I I .

0.26 . 1.11 . 1.22 . l.31 0.26 0.9 1.11

-0.2 .

1.21 . 1.3t 0.8 0.b 1.19 . 1.28 . 1.17 1.18 . 1.27 . 1.21 . 1.31 . 1.18

-0.7 -0.7 2.8 .

1.27 2.8 0.32 . 0.93 . l.30 . 1.15 . l.10 . 0.99 1.27 . 0.93 . 1.27 . 0.99 1.17 0.9 .

1.26 . 1.19 . 1.31 1.28 . 1.17 . 1.27 . 1.!!

-0.1 . -1,2 . -1.4 .

1.10 . 1.15 . 3.30 0.93 A.32 1.22

-2.2 .

1.11 . 0. 2f 1.09 .'0.26

-1.8 . -1.t 7

0.32 I

0.93 1.29 1.14 1.11 . 0.99 1.27 0.93 . 1.26 . 0.98 . 1.09 1.11 . 1.27 . 0.92 . 0.32 8

. 0.7 . 0.4 . 1.1 02. 0.5 . 0.5 . 0.0 0.1 0.s 0.8 1.6 . 3.4 . 2.2 . 1.4 8.6 0.26 . 1.11 1. 22 . 1. ?.! > 1.19 1.28 t.17 1.27 1.17 . 1.28 . 1.19 1.51 . l.22 . 1.11 . 0.26

. 4.26 . 1.09 . 1.18 1.M9 1.19 1.28 1.17 . l.27 1.16 . 1.27 . 1.18 . 1.29 . 1.21 . 1.10 . 9.24 9

. 0.9 -1.8 . 3.2 . 1.3 . 0.6 . 0.3 . 0.3 . -0.3 -0.9 -1.0 . 0.5 -1,6 . -0.8 . 0.7 4. 2 .

. 0.63 . 1.27 . 1.17 1.27 . 1.15 . 1.29 1.0 3 . 1. 19 1.15 . 1.27 1.17 . 1.27 0.63

'I . 0.6L . 1.23

-3.2 . -3.2 . 0.4 1.16 1.28 . 1.16 1.0 . 0.5 .

1.30 0.4

. 1.03 . 1. ?8 . 1.14 . 1.27 . (.18 . 1 77 . 0.61 .

. 0.6 -0.6 . -0.G . *0.2 0.9 0.4 8.h 10

/

...............................................................4. ............. .......

. 0.33 1.11 . 1.30 1.15 . 1.27 . 1.20 . 1.12 . 1.20 . 1.27 1.15 . 1.30 1.11 . 4.33 .

4.32 1.09 . 1.29 . 1.16 . 1.27 . 1.20 . 1.12 1.20 . 1.27 . 1.15 1.31 . 1.12 . 0.33 , 11

. -1.7 -1.7 -0.8 . 1.0 . -0.1 . 0.0 . 0. 2 . - 0. 5 . 8.1 . 0,2 0.9 0.6 . 1.1 I . ... . ........ ........... .................................. ...... ..... ......

0.35 t i . 84 1.30 . 1.11 . 1.32 1.15 1.32 . 1.l? 1.30 . 0.84 . 0.35 .

7

. 0.35 . U.85 . 1.31 1.17 . 1. 31 . 1.14 . ( . 31 . J .17 . 1.29 . f.85 . 0.35 . 12 0.9 - 0.1 . - 0. 5 . = 0. 5 1.0 . 6.8 I

. -0,1 . 0.4 . -0.7 . -0.3 -0.2 .

. 0.35 . 1.11 . 1.27 1.22 . l.30 1.22 . 1.28 . l.21 . 0.35 .

0.35 . 1.12 . 1.26 1.21 1.29 1.22 . 1.27 . 1.11 . 8.15 . 13 0.1 . 0.9 . 1.1 . -1.4 . -0.8 . -0.7 . =0.3 . 0 6 . % ./ .

I

. 0.33 . 0.63 . 1.11 . 0.93 . 1.11 0.63 . 0.33 .

. 0.33 . 0.64 . 1.11 . 0.93 . 1.11 . 0.65 0.32 14

. 2.2 . 2.2 . 9.2 . 0.2 . *0.6 0. 2 . - 1.1 .

STANDARD . . 0.2+ 0.32 , 0.26 . . AvitACE .

DEVI ATION . 0..!? . 0.32 . 0.26 . .PCf OlffiD(NCE. j$

*0.967 . . 2.0 . 1.3 . 0.7 .

4.1

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

SUM 6 4 NAP N0s N2 8 03 DATE: 11/08/90 PouER: 90%

CONTROL ROD POSITIDHSt F-Q(T)

1.923 QPTR: ,

D BANK AT 204 STEPS F DHIN) = 1.423 HW 1.008 l NE 3.999 i

I F(Z) a 1.237 SW 0.997 i SE 0.997 DURNUP a 88 NWD/HTij A.O. s 0.167%

g e.m me S_-- e. . o

I l'igure 6.4 NORTil ANNA UNIT 2

CYCLE 8 STARTUP PilYSICS TESTS ASSEMBLYWISE POWER DI.STR11!UTION 100% POWFR ft P N M t E J H G F E O C 0 A Pitl B R l10 .

d.27 , 0.33 0.21 . . I 4 DICff0 MIASUPPO 0.28 0.34 . 9.2L . . f t Asupt . . 1

..PC I D111 t Wi m.f ., 4.7 4.7 3.8 .PC) DIFFl pt h(t .

0.33 . 0.63 1.11 . 0.9% 1.!! 9.6% 0.35 5 0.34 0.65 1.13 0.96 ' ** 9.6% . 4.34 . 2

. 4.6 2.5 1.8 I .e . 1.1 . 2.8 . 2.9 .

, 0.35 1. t v . 1.26 . 1.it 1.3t 1.22 . 1.26 . l.10 0. 55

. 0.3) 1.fi . 1.26 4.24 1.32 1.24 . 1 28 1.13 . 0. t6 3 1.) 8 . 9> -W,0 1.4 1.2 1.5 1.9 . 2.3 . 3.0 9.16......

. 0.8i . . ... I.79

. . . . . .1.16

. . .....1.31

. . . . . 1.15

. . . . .l.11 . I.M. 1.29 .... .0.84 . 4.3%

0.35 0.84 1.30 1.16 . 1.33 1.87 1.32 . 1.17 . 1.29 0.84 0.1% . 4

. 0.9 . 0.3 . 0.9 1.0 1.4 1.8 . 0.9 . 0.9 . 9.2 -0.2 . 4.3 .

l 0.35 1.10 1.29 . 1.1% l.27 . l.20 1.12 . l.20 1.27 1.15 . 1.29. . 1,10 d.35 l 4.32 . l.98 1.27 1.14 1.78 1,23 1.16 1.22 . l.29 1.14 1.26 1.09 4.35 5 l

, -2.5 -2.5 -1.8 . 0.6 . 0.2 3.1 S.1 2.2 . 1.0 . -4.3 . 4.9 l.1 2.1

4. 4% . 1,26 . l .16 . J ,2 7 1.47 1. '.d . 1.03 . l.30 . 1.17 . 1.21 . 1.16 1.?s 0.63 .

. 0.62 1.25 . 1.16 1.27 1.18 . 1.34 . t.07 1.33 1.18 1.26 . 1.14 1.2% 0.63 . 6 1.0 1.0 b.4 0.2 . 1.1 . 2.t . 5.0 2.1 . I .t . 1.3 . -2.2 -1.9 -0.1

.0.27. 1.11 . l.22 . 1.31 1.19 . 1.29 . J . l4 , I .28 1.48 . 1.29 . 1.19 . 1.31 1.22 1.11 . 0.27

. 0.2/ l.Il L.20 . 1.29 1.18 L.28 . 1.22 1,32 1.20 . 1.31 . l.19 l.26 1.19 . 1.49 . 0.26 7 2.7 . -0.1 . 1.4 -1.4 -0.4 -0.4 3.1 . 3.8 19. 1.4

0, i . - 3. * -2.4 . -2.1 . -l.4

. 0.33 . 0.9% 1.50 J.44 . .* 11 e,99 , 1.27 . 4.9'i 1.27 . 0.99 1.11 . 1.1% 1.30 . 0.9% . 4.33 .

. 0.34 0.94 . 1.28 1.44 1.ll . 1.00 1.28 . 0.95 . l.27 . 0.99 . 1.09 . 1.10 . 1.27 . 0 93 . 4.33 . 8 l . 2.7 . -0.2 - 1. 7 . - 0. 5 . 0.6 f.4 . 0.4 , l.6 0.1 . 0. 0 . - l .1 . 5.4 . -2.4 . *l.2 . 0.3 .

. 0.27 . 1.11 . l.22 1.31 , 1.19 1.24 . 1.88 1.& l.18 . 1.29 . 1.19 . 1,31 . 1.22 . 1.11 0.27 0.27 . 1.09 1.17 . 1 ?* l.19 1.t9 1.17 . 1.27 1.18 . 1.t9 . 1.19 . 1.2e . 1.21 1.11 0.27 . 9

. 2./ - 1,6 . - 3. 7 . - 1. 5 . 0.6 . 4.2 -0.6 . -0.6 -0.2 . 0.3 . -0.c . +l.7 . 0.7 -0.3 0.9

. 0.43 . 1.26 . 1.16 . 1.27 . 1.17 . 1.30 1.0A 1.30 . 1,17 1.27 1.16 1.26 . 0.63 .

t . 0.61 . l.21 1.15 . 1.28 1.18 < l.30 . l.04 . 1. 29 1.16 1.27 1.12 1.27 0.64 10 l . 3.7 . -3.7 -0.7 0.9 . 0.4 . 0. 3 . 0.4 . *0.7 . -0.7 0.4 0.8 . 0.7 1.5 l

0.35 1.10 1,29 . 1.15 . 1.2/ . 1.20 . I.12 . I.20 1.27 l. 5 1.29 . 1.10 0.35 .

. 0.32 , 1.09 1.28 . 1.14 . 1.27 . l.19 . 1.12 . 1.20 1.27 , 1.15 . 1.50 . (.12 0.33 . Il l . -l.2 . -1.2 . -0.4 . 1.1 . 0.4 -0.4 0. 2 . 0.1 . - 0. 7 0.2 . 1.1 . 1.1 . 2.0 .

l .. . .......... ... ...... ...... ....................... .......... ............. ..

l . 0.35 . 0.84 1.29 . 1.16 . l.31 1.15 1.31 . 1.16 1.29 . 0.84 0.3% .

l

. 4.3% , 0.8% 1.30 1.16 . 1.30 . 1.14 1.30 1.15 . 1.28 . 0.85 . 0.35 . 12 l .3 . 1.2 1.1 0.5 -1.0 . 0.9 . 1.1 . 0.7 . -0.4 . l.3 . 1.4 .

. 0.35 . I.10 . 1.26 1.22 . 1.30 . l..'2 . 1.26 . 1.10 0.35 .

~'

0.35 . 1.11 . l.24 1.19 1.28 . 1.20 . 1.24 . l.09 0.35 . 13 l.3 . 1.1 . -1.9 . -2.0 1,6 . 1. 6 .- -1.4 . -0.9 . 1. 5 .

. 0.33 0.63 1.11 0.9% 1.11 0.6.5 . 0.33 .

. 0.34 0.6% 1.12 0.95 1.10 . 0.62 0.32 . 14

. 3.6 . 3.6 . 9.0 0.t . -4.5 . -1.3 . -2.b .

SIAMDARD 0.27 0. 33 0.27 . . AvfRACE .

. DEVIATION . 0 . 215 . 0.3% . 0.2t . .PC T Olf Fl@4C '. l's

l.074 36- 1.5 . 0.7 .

1.4 ~

....... ....... d .. . . . . . . . . . . .... ... ...

l $1MMARY l

NAP NOI N2-8 04 DATEl 11/14/90 POWER: 100%

CONTROL ROD POSITIONS: F-Q(T) = 1.888 QPTR: <=

D BANK AT 228 STEPS F-DH(M)

1 A14 HW l.006 l NE 1.002 l l F(Z) i 1.202 M . 0.996 l SE 0.994 BURNUP = 315 MW3/MTU 4,0 = 1.361%

NE-817 N2C8 Startup Test Report Page 40 of 63 h

1 h

SECTION 7 d

REFERI.NCES

1. T. S. Psuik and P. D. Banning, " North Anna Unit 2, Cycle 8 Design Report," Technical Report NE-803, Revision G . Virginia Power, October, 1990

2. T. K. Ross, V. C. Beck, " Control Rod Reactivity Worth Determination By The Kid Swap Technique," VEP-FKD-36A, December, 1980,

3. V Leggn.t and L. Eisenbart, "The INCORE Code," WCAP 7149, Decerber, 196'i. -

GD

4. North Anna Unit 2 Technical Specifications, Sections 1.18, 3,1.3.4, 3.2.2, 3.2.3, 3.1.1.4 and 4.1.1.1.2. i 49 4

i I

(

NE-P1' N2C8 S.tartup Test Report Page 41 of 63 a

- _- - ____-_ - _________ ________-__ __- _ _ _ l

s f

L Al'PENDI X i 5TARTUP PilYSICS TESTS RESUI.TS AND EVAL,UATION SilEETS I

I I

E l

g xE.e1, mace St.m,1m E.,_ 1.. . . c - e5 1

I I NORTH ANNA POWER STATION UNIT 2 CYCI.E 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout Reference Proc No /Section: 2-PT 94.0 Sequence Step No:

11 Bank Positions (Steps) RCS Temperature ('F): $47 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

1 (Design) CB: 228 CC: 223 CD:

Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('P): 5 % ,l i Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specifv):

(Actua.) CB: 228 CC: 228 C'J Below Nuclear Heating

1 Date/ Time Test Performed:

n/, /u I ,s m Measured Parameter pg= Meas. Reactivity from p computer IV (Description) pt = Predicted Reacti',ity pe = -Soc 4 s s. o Measured Value pg= - 51. o 4 54.4 Teat gD a .;. y, o$f ) , g c/,

Results

'Jesign Value (Ac'.ual Conditions) %D = ((pe pg )/pt) x 100% $ 4.0%

Design Value (Dasign Conditions) %D = ((pe pg)/p )g x 100% $ 4.0%

Reference WCAP 7905, Rev. 1. Table 3.6 V FSAR/ Tech Spec Not Applicable Accepeance I Criteria Reference Not Applicable Design Tolerance is set YES N0 i VI Acceptance Criteria is set : YES _ NO Comments I

At The Just Critical Position Allowable Range " +55 , - 50 pcr

(

Prepared By: ,[V Reviewed By: '

?J E .

I NORTil ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP Pl!YSICS TEST RESULTS AND EVALUATION S!!EET (PRELIMINARY ANALYSIS)

I Test

Description:

Critical Boron Concentration - ARO Reference Proc No /Section: 2-PT-94.0 Sequence Step No II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 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): r% . Z.

Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 223 CA: 228 Other (Specify):

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

1il 19 0 EliiO t1eas Parameter g IV (Description) (CB ) AR0; Critical Boron Conc - ARO Hessured Value (CB ) ARO

WO EM I

Test g Results Desige Value g (Actual Cond) CB = MM 90 p Design Value (Design Cond) CB =2063 t 50 ppa Reference Technical Report NE-803 Rev. 0 $

g V FSAR/ Tech Spec aC3xC 5 1000 pcm 3 Acceptance Criteria Reference Technical Specification 4.1.1.1.2 5

Design Tolerance is met : /YES N0 Acceptance Criteria is set : ,Y,,YES N0 VI g Comeents acB = -6.94 pcm/ ppa for preliminary analysis W D H C3 = l(C B) ARO - CB l; CB is design value at actual ccnditions, t

Prepared By: W Reviewed By:

a NE-817 N2C8 Startup Test Report Pago 44 of 63 I

s I

NORTl! ANNA POWER STATION UNIT 2 CYCLE 8 i

STARTUP PilYSICS TEST RESULTS AND EVALUATION SHEET (FINAL ANALYSIS) i

, I Test

Description:

Critical Boron Concentration - ARO Reference Proc No /3ection: 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): 547

[ Test Power Level (% F.P.): 0

[ Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: 228 Below Nuc14ar Heating III Bank Positions (Steps) RCS Temperature ('F): T%. 4 Test -

Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 CC: 228 CD 228 Below Nuclear Heating -

Date/ Time Test Performed:

il/i h o allo Heas Parameter g IV (Description) (CB ) AR0; Critical Boron Conc - ARO Measured Value (CB ) A 0

PP M N Results Design Value (Actual Cond) CB* 90'3~^ GO Design Value (Design Cond) CB =2063 i S0 ppe Reference Technical Report NE-803 Rev. O D

V FSAR/ Tech Spec aCBxCB 5 1000 pce Acceptance Criteria Reference Technical Specification 4.1.1.1.2 Design Tolerance is met : YES _ NO Acceptance Criteria is met : YES ,_NO VI Coseants aCB " ~ 7 0 4 P C"/PP" D M CB = l(CB) ARO - C3 l; CB is design value at actual conditions.

I i Pre,are B,: u m NE-817 Revie.e4 B,, w e m N2C8 Startup, Test Re . t Page 45 of 63

I NORTH ANNA POWER STATION UNIT 2 CYCI.E 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Isothermal Temperature Coefficient - ARO Reference Proc h'o /Section: 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): S47 Test Conditions Power Level (% F.P.): 0 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): 5%9' Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 228 CA: 228 Other (Specify):

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

in/6ho 2t H -

Meas Parameter iso IV (Description) (a T )ARO Isothermal Temp Coeff ARO Test Measured Value ISO (a 7 )ARO * ~ I

37 Pen /'F (Cg =2c6Sppm)

' I Results 3 Design Value ISO (Actual Cond) (a T )ARO = *o.50 pcm/'F (CB " 3083PP") ' E W

ISO (a T )ARO = -0.69 i 3.0 pcm/'F Design Value (Design Cond) (CB = 2063 ppm)

Reference Technical Report NE-803 Rev. O 0

FSAR/ Tech Spec a s 3.7S*pcm/'F a E = -1.75 pcm/'F l ISO Acceptance l I

Criteria Reference TS 3.1.1.4, Technical Report NE-803 Rev. O Design Tolerance is met :

VI Acceptance Criteria is met : /[YES YES _NO NO Comments

Uncertainty on aTMOD = 0.S pcm/'T (

Reference:

memorandus from C. T. Snow to E. J. Lozito dated June 27, 1980).

NoT6 TE.5T V50 Two cceLDowN5, ere,a,eeB,, uwy ,eview,d ,,. amm g NC-817 N2C8 Startup Test Report Page 46 of 63

s

?

L

' NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1 Test

Description:

Cntl Bank B Worth Meas. , Rod Swap Ref. Bank Reference Proc No /Section: 2 PT 94.0 Sequence Step No:

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: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 643.6 '

g Test Power Level (*, F.P. ): 0 l Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

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

II / A /9o oco5 ly Heasured Parameter I REF Integral Worth of Cntl Bank B, (Description) B ; All Other Rods Out IV Test IB59. I pcm '

Measured Value I =

Results l Design Value I (Actual Conditions)

REF

" P

!B l Design Value REF B ,(Design Conditions) I g = 1264 1 126 pea Reference Te-inical Report NE-803 Rev. O If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result V FSAR/ Tech Spec on safety analysis. SNSOC may specify Acceptance that additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met : V YES NO g VI Acceptance Criteria is set : JYES NO

[ Comments i

Prepared By: @ d 'D M -w Reviewed By: Mb NE-817 N2C8 Startup Test Report Page 47 of 63

I NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET (PRELIMINARY ANALYSIS)

I Test

Description:

Critical Boron Concentration - B Bank In Reference Proc No /Section: 2-PT-94.0 Sequence Step No:

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: O CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 5%.3 g Test Power Level (% F.P.): 0 3 Conditions SDA: 228 SDB: 228 CA: 228 Uther (Specify):

(Actual) CB: O CC: 228 CD: 228 Below Nuclear Heating '

Date/ Time Test Performed:

n l z./9o os*s Meas Parameter g

IV .

(Description) (C )gB B; Critical Boron Conc - B Bank In Measured Value (CBB"

)M I Ob Test Results Design Value 3 (Actual Cond) j g CB" lOiO 8 28 PP M Design Value Prev (Design Cond) CB = 1880 + ACB i (10 + 126.4/laC Bl)PP" Reference Technical Report NE-803 Rev. O D

V FSAR/ Tech Spec aCBxCB s 1000 pcm 3 Acceptance Criteria Reference Technical Specification 4.1.1.1.2 g

Design Tolerance is met : / YES _ _,,NO Acceptance Criteria is met : IYES N0 VI g Comments aCB a -6.94 pcm/ ppm for preliminary analysis 3 AC B = (CB)A 0 2063 D

CB = l(CB) MB - C l; Cg is design value at actual conditions.

B E

Revie. m B ,. e m I ereparceB,: m m b NE-817 N2C8 Startup Test Report Page 48 of 63

I l 1

NORTl! ANNA POWER STATION UNIT 2 CYC1.E 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET (FIANL ANALYSIS) l I Test

Description:

Critical Baron Concentration - B Bank In Reference Proc No /Section: 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P. ): 0 I Conditions (Design)

SDA: 225 SDB: 228 CA: 228 CB: O CC: 228 CD: 228 Other (specify):

Below Nuclear Heating I III Test Conditions Bank Positions (Steps)

SDA: 228 SDB: 228 CA: 228 RCSTemperature('F):54.,.5 Power Level (% F.P.): O Other (Specify):

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

It / t./9 0 O'274 5 Meas Parameter IV (Description) (C )gB B; Critical Boron Cone - B Bank In Measurea Value (CB )B " ppm Test Results Design Value i (Actual Cond) CB" IW f F?rn I Design Value (Design Cond) CB = 1880.+ ACB Prev 1 (10 + 126.4/laC l) g ppm Reference Technical Report NE-803 Rev. O D

V FSAR/ Tech Spec aCBxCg 5 1000 pca I Acceptance Criteria Reference Technical Specification 4.1.1.1.2 I Design Tolerance is met Acceptance Criteria is met YES YES NO NO I VI Comments aC g=- M P hn AC

= (CB )A 0 - 2063 D

CB = l(Cg ) MB - C l; Cg is design value at actual conditions.

3 I

Prepared By: Mu223 % Reviewed By: (0,%AC I ""~*" ' "

l NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND CVALUATION SHEET (PRELIMINARY ANALYSIS)

I Test

Description:

HZP Boron Worth Coefficent Measurement Reference Proc No /Section: 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

l (Design) CD: Moving CC: 228 CD: 228 Below Nuclear Heating W III Test Bank Positions (Steps) RCS Temperature ('F): SS, y, / g Power Level (% F.P.): 0 g Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: Moving CC: 228 CD: 228 Below Nuclear Heating >

Date/ Time Test Performed:

t ih l 9 c, ::1110 /

Hessured Parameter IV (Description) aC g , Boron Worth Coefficient ac B E

Heasured V51ue = M ,0 9 pc ,[pph Test 3 Results Design Value (Actual Condalons) aCg = -6.94 i 0.69 pcm/ ppa Design Value (Design Conditions) aCB = -6.94 1 0.69 pen / ppa Reference Technical Report NE-803 Rev. 0 l FSAR/ Tech Spec Not Applicable V

Acceptance Criteria Reference Not Applicable Design Tolerance is met : 1 YES N0 g VI l Comments Acceptance Criteria is met : l YES _,,NO 5 I

Prepared By: Mwo T) A' Reviewed By:

O NE-817 N2C8 Sta'rtup Test Report Page 50 of 63

.I

NORTH ANNA POVER STATION UNIT 2 CYCLE 8 p /

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET (FINAL ANALYSIS)

I Test

Description:

HZP Boron Worth Coefficent Measurement Reference Proc No /Section: 2 PT-94.0 Sequence Step Not II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 I Conditions (Design)

SDA: 228 SDB: 228 CA: 228 CB: Moving CC: 228 CD: 228 Other (specify):

Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): d.A4, . 2. '

i Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB Moving CC: 228 CD: 228 Below Nuclear Heating

Date/ Time Test Performed:

g flllMO .a ll O s Measured Parameter IV (Description) aC B , Boron Worth Coefficient

I Measured Value , aCB" ~l ON P '

P p Results d Design Value (Actual Conditions) aCB = -6.94 1 0.69 pen / ppm Design Value (Design Conditions) aCB = -6.94 1 0.69 pca/ ppm Reference Technical Report NE-803 Rev. O I V Acceptance FSAR/ Tech Spec Not Applicable Criteria Reference Not Applicable Design Tolerance is set I VI Comments Acceptance Criteria is met gYES

_ YES NO

_,,,NO Prepaied By: Nd Af2,sul Reviewed By: kNYM k E NE-817 N2C8 Startup Test Report Page 51 of 63 I

J

I NORTH ANNA POWER STATION UNIT 2 CYCLE 8 I

STARTUP PHYSICS 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:

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: Moving CC: 228 CD: Moving Below Nuclear Heating l

as III Bank Positions (Steps) RCS Temperature ('F): FHe.3 ' g Test Conditions Power Level (% F.P.): 0 3 SDA: 228 SDD: 228 CA: 228 Other 3pecify):

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

11) : / 9 0 0976 Meas Parameter 33 (Description) ID ; Int Worth of Cntl Bank D-Rod Swap IV RS Test Measured Value ID = 80 27 7( Adj.Position Meas. Crit. Refsteps) a lW,.1 Bank /

Results Design Value RS ( Adj. Meas. Crit. Ref Bank (Actual Cond) ID

= 99 9 tiso Position = k.,(,.q steps) e RS Design Value ID = 1001 1 150 pcm (Critical Ref Bank (Design Cond) Position = 163 steps)

Reference Techn!41 Report NE-803 Rev. O, VEP-FRD-36A g

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 -- l 5

Reference VEP-FRD-36A Design Tolerance is met : ,,,:/.,Y ES NO VI Acceptance Criteria is set : v'YES , N0 Comments Prepared By: S M n_ b A -

Reviewed By: b_D DON -

NE-817 n2C8 startup rest neport Page 52 of 63 I

I NORTH ANNA POWER STATION UNIT 2 CYCLE 8 l']

t I

Reference STARTUP PHYSICS TEST RESULTS AND EVALUATION SilEET Test

Description:

Cntl Bank C Worth Measurement-Rod Swap Proc No /Section: 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 Conditions Other (specify):

I (Design)

SDA: 228 SDB: 228 CA: 226 CB: Moving CC: Moving CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): >~f.!Hfy rgf/6h, Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

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

/,;57 ///t./9 o Meas Parameter RS (Description) IC ; Int Worth of Cntl Bank C-Rod Swap

' I IV Test Results Measured Value IC RS

= 7 /O, (Adj. Meas. Crit. Ref Bank Position = no.tsteps)

I v Design Value (Actual Cond) IC RS 3 9* % ( Adj . Meas. Crit. Ref Bank f lll Position =,Ls.stteps)

Design Value I = 738 t 111 pcm (Critical Ref Bank (Design Cond) Position = 12S steps)

Reference Technical Report NE-803 Rev. O, VEP-FRD-36A I V FSAR/ Tech Spec If Design Tolerance is exceeded SNSOC shall evaluate impact of test result on safety analysis. SNSOC may specify that Acteptance additional testing be performed, I utiteria Reference VEP-FRD-36A Design Tolerance is met

1 YES NO VI Acceptance Criteria is met : _ DYES N0 Comments I

I Pre,ared ,,: ax - Reviewed ,,, >=~ &

NE-817 N2C8 Startup Test Report Page 53 of 63 I

l NORTH ANNA POWER STATION UNIT 2 CYCLE 8 (q STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET U R I Test

Description:

Cnti Bank A Worth Measurement Rod Swap g Reference Proc No /Section: 2-PT-94.0 Sequence Step No:

II Bank Positions (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): SV6.'/

Test Conditions SDA: 228 SDB: 228 CA: Moving Power Level (% F.P.): 0 g Other (Specify): 5 (Actual) CB: Moving CC: 228 CD: 228 Delow Nuclear Heating Date/Tlae Test Performed:

7l5 A // / J /10 Meas Parameter (Description)

RS IA ; Int Worth of Cnti Bank A - Rod Swap W

IV RS (Adj. Meas. Crit. Ref Bank g Test Measured Value IA = 3 30 Position =7 p steps) g Results Design Value RS (Adj. Meas. Crit. Ref Bank g (Actual Cond) IA

307*7Y loo m Position = 77,9 steps)

L) RS Design Value IA = 309 t 100 pcm (Critical Ref Bank (Design Cond) Position = 78 steps) l W

Reference Technical Report NE-803 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 performe.d.

Criteria Reference VEP-FRD-36A Design Tolerance is met : Y YES NO 3 VI Acceptance Criteria is set : X YES ,_,NO 5

Comments N

n Prepared By: , Reviewed By:

a s

l NE-817 N2C8 Startup Test Report Page 54 of 63 I_

NORTH ANNA POWER STATION UNIT 2 CYCLE 6 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B Vorth Meas. - Rod Swap Reference Proc No /Section: 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: Moving CA: 228 Other (specify):

(Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): S '/6. 3 I Test Conditions (Actual)

SDA: 228 SDB: Moving CA: 228 CB: Moving CC: 228 CD: 228 Power Level (% F.P.): O Other (Soecify):

Below Ntelear Heating Date/ Time Test Performed:

3 :Is ///M 10 I Meas Parameter (Description) g3 ISB; Int W rth of Shutdown Bank B Rod Swap I IV Test Results Measured Value RS I SB = 9/(,. (,

(Adj. Maas. Crit. Ref Bank Position a fn,pteps)

Design Value RS (Auj. Meas. Crit. Ref Bank (Actual Cond) I SB = 6 1 Nq Position =jg,,ptops)

I Design Value (Design Cond)

I = 995 t 149 pcm (Critical Ref Bank Position = 162 steps)

Reference Technical Report NE-803 Rev. O, VEP-FRD-36A m If Design ' Tolerance is exceeded, SNSOC g shall evaluate impact of test result on safety analysis. SNSOC may specify that V FSAR/ Tech Spec Acceptance additional testing be performed.

I Critoria Reference VEP-FRD-36A Design Tolerance is met I

~

VI Comments Acceptance Criteria is met X YES s d X YES NO I

I Prepared By: '3 Reviewed By:

2rv d

NE-817 N2C8 Startup Test Report Page 55 of 63

I 1

l NORT!! ANNA POWER STATIty; UNIT 2 CYCLE 8

( STARTUP PIIYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank A Worth Maas. - Rod Swap Reference Proc No /Section: 2 PT-94.0 Sequence Step Not II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 Conditions SDA: Moving SDB: 228 CA: 228 Other (specify):

(Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Fi;eps) RCS Temperature ('T): N f, . h Test Power Level (% F.P.): 0 g Conditions SDA: Moving SDB: 228 CA: 228 Other (Specify): 3 (Actual) CB: Moving CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed:

9 to1 tils/s o Meas Parameter RS (Description) ISA; Int Worth of Shutdown Bank A Rod Swap IV Test Measured Value RS (Adj. Meas. Crit. Ref Bank g Igg = 10 fa l . "1 Position =01.5 steps) g Results Design Value ( Adj. Maas. Crit. Ref Bank O (Actual Cond)

RS IO 'I i151 Position = In5 steps) g ISA =

O g RS Design Value ISA = 1013 i 152 pcm (Critical Ref Bank (Design Cond) Position = 165 steps)

Reference Technical Report NC-803 Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC g V FSAR/ Tech Spec shall evaluate impact of test result on safety analysis. SNSOC ray specify that g

Acceptance additional testing be performed.

Criteria Reference VEP-FRD 36A VI Design Tolerance is set : K YES ,NO g Acceptance Criteria is set : .2( YES N0 3 Comments I

Prnpared By: 8 2 Reviewed By: _ _ _

n 6 NE-817 N2C8 Startup Test Report Page 56 of 63

b L

NORTil ANNA POWER STATION UNIT 2 CYCLE 8 p STARTUP PHYSICS TEST RE3ULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth Rod Swap Reference Proc No /Section: 2.PT 94.0 Sequence Step Not l

I l

II Test lBankPositions(Steps) j Conditions SDA: Moving SDB: Moving CA: Moving RCS Temperature ('F): 547 Power Level (% F.P.): 0 Other (specify):

(Design) CB: Moving CC: Moving CD: Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): f'/:3.9 Test i Conditions SDA: Moving SDB: Moving CA: Moving Other (Specify):

(Actual) CB: Moving CC: Moving CD: Moving Below Nuclear Heating Power Level (* F.P.): O I Date/ Time Test Performed oeos lllt l*10 I Meas Parameter (Description) ITotal; Int Worth of All Banks - Rod Swap IV I Test Results Measured Value ITotal

b 3 d. 7 Design Value (Actual Cond) ITotal = 5'$2.l.O t 6 3 2.

Design Value ITotal = 5320 t 532 pcm (Design Cond)

Reference Technical Report NE-803 Rev. O, VEP-TRD-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 edditional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is not : .2 LYES ,,,,,,,,NO VI Acceptance Criteria is set : 1 YES ,NO Comments Prepared By: < d Reviewed By:

d NE-817 N2CB StArtup Test Report Page 57 of 63 l

_ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ . _ _ I

I NORTil ANNA POWER STATION UNIT 2 CYCLE 8 I

STARTUP PHYSICS TEST RESULTS AND EVALUATION SilEET I Test

Description:

M/D Flux Map - At power Reference Proc No /Section: 2-PT-21.1 Sequence Step No: e/1 II Bank Positions (Steps) RCS Temperature ('F): TREF il Test Power Level (*. F.P.): <307.

Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)

(Design) CB : 228 CC : 228 CD:

Must have 2 38 thimbles III Bank Pesitions (Steps) RCS Temperature ('F): FF0 h Test Conditions SDA: 228 SDB: 228 CA. 228 Po.er Level (f. F.P.): 2i./g Other (Specify):

g (Actual) CB : 228 CC : 228 CD: 150 Rc3 8.re n : m43 gem Date/ Time Test: "/4/90

Performed: 163o O.W EFFD 43 THIM6L r,5 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) 7. DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR 5.2%3 Pr.9 1.523 2.24'2 Test Results M " \, "

12.o%3 Pe.9 t.ois l

Design Value l l;; ;;; ;, ! -

(Design Conds) " . * *"' k;'; NA NA s 1.02 WCAP-7905 WCAP-7905 Reference REY.1 NONE NONE REV.1 FSAR/ Tech Spec """""" *"'

V NONE NA 3 Acceptance Criteria 5

Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met . ) LYES N0 Acceptance Criteria is met : ._& YES _NO VI Comments

As Required i

Pre,-ea,,,erm w ,e ,e.es ,,. ,

A194 2 g

NE-817 N2C8 Star' tup Test Report Page 58 of 63

I

'I NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Map-At Power Reference Proc No / Section: 2-PT-21.1 Sequence Step No: q3 II l Bank Positions (Steps) lRCSTemperature('F): TREF 11 Test Power Level (*. F.P. ): (75%

I Conditions (Design) l j

SDA: 22S SDB: 228 CA: 228 CB : 22S CC . 228 CD:

I Other (specify) lMusthave238 thimbles III lBankPositions(Steps) RCS Temperature ('F):

Test Power Level (*. F.P. ): '1.2.15 7.

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB . 228 CC 228 CD: 18 6 (,2 , g s w pfy m I- 1. (o E F P p Date/ Time Test: ll / 7 /90 Performed: @ MM6E I IV MAX. REL Meas Parameteri ASSY PWR NUC ENTHAL RISE HOT TOTAL HEAT QUADRANT FLUX HOT POWER TILT I (Description) '. DIFF (M-P)/P CHAN FACT F dH(N)

CHAN FACT F-Q(T)

RATIO QPTR I Test Results Measured Value 3.1% , P r o l4.77, , P 4.9 g ,qq3 l*3 89 1. 0117 Des ign Va lue i . in ... . ....

(DesignConds)lINZ.UaZ' NA NA 5 1.02 I Reference WCAP-7905 REV.1 NONE l

NONE WCAP-7905 REV.1 V FSAR/ Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.2.3 TS .?.2.2 TS S.2.4 Design Tolerance is met : 1 YES _,.__NO

X YES __, N0 I

Acceptance Criteria is met VI Comments

As Required I -

Prepared By: il j dv./ Reviewed By:

NE-817 N2C8 StaRtup Test Report Page 59 of 63 I

I I

NORTH ANNA POWER JTATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Map- NI Calibration 43 Reference Proc No / Section: 2 - PT- cru 22f2a.1,s. E

+ ./ Sequence Step No: 3Hf'.

~ru o..,... g 11 Bank Positions (Steps) RCS Temperature ('T):T il Test Power Level (*. F.P. ): gb59 g Conditions SDA: 228 SDB: 20S CA: 228 Other (specify):

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

III Bank Positions (Steps) RCS Temperature ('F):

Test Power Level (*. F.P. ): 90.o 7 %

Conditions SDA: 228 SDB: 2 2 P. CA: 228 Other (Specify):

(Actual) CB ' 228 CC : 228 CD: gay g7,.7 u wpj u 7g .

Date/ Time Tert: il /Fj/70 ** #

Performed: fgg N THig6tES MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) *. DIFF CHAN FACT CHAN FACT RATIO l

(M-P)/P F-dH(N) F-Q(T) QPTR l -

-l 'I % , Pa. 7 3 Measured Value 1'423 Test 4 5'/. , pc .9 f .*7 78 l.com 3 Results Design Value i ai . .. . . . . .

(Design Conds) l*'" ZO,*Z' NA NA s 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.1 V FSAR/ Tech Spec NONE ""'""'""" '"'"""' NA Accept;nce Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : LYES ___NO VI Acceptance Criteria is met : .25,YES __NO g g

Comments

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

- As Required Prepared By: ! /*Mu4[ Reviewed By: b NE-817 N2C8 Startup Test Report Page 60 of 63 I

.I

1 I

I NORTil ANNA POWER STATION UNIT 2 CYCLE 8 STARTVP PliYSICS TEST RESULTS AND EVA! NATION SilEET I Test

Description:

M/D Flux Map - HTP, ARO, Eq. Xe Reference l Proc No / Section: 2-PT 21.1 Sequence Step No: &

II lDankPositions(Steps; RCS Temperature ('F):T Rr.F 11 I _

Test Conditions l (Design) l SDA: 22S SDB: 228 CA: 228 CB : 228 CC . 22B CD:

Power Level (* F.P.): 95 5 Other (specif y): Eq. Xe.

Must have 2 38 thimbles III Bank Positions (Steps) RCS Temperature ('F):

Test Power Level (*, F. P. ): qq,qp'f, Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 CC . 228 CD: g , 3 f 9 2 M 'v% i r r.,

Date/ Time Test: Il- I 4 "i" 7A CI##

Performed: l'(00 N"

% ' % f H bL!2, MAX. REL NUC ENTHAL TOTAL llEAT QUADRANT IV Mens Parameter ASSY PWR RISE HOT FLUX 110T POWER TILT I (Description) *. DIFF (M P)/P CilAN FACT F-dll(N)

CHAN FACT F-Q(T)

RATIO QPTR I Test Measured Value 3 N 7., f r.9 4.1% > r e /t

[, qty l.7y6 1.0096 Results I

Design Value i on e.

e...

(Design Conds) I*',9 U; E,*W NA NA $ 1.02 I Reference WCAP-7905 REV.1 NONE NONE WCAP-7905 REV.1 V FSAR/ Tech Spec NONE a"d""*"" ''"'"' NA Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met . _X YES N0 I VI Comments Acceptance Criteria is met

As Required

y YES ,NO I 1 , . ,

Prepared By: b 4xdh/ Reviewed By:

NE-817 I N2C8 Startup Test Report Page 61 o f 6 3 I

, I 1

NORTl! ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PflYSICS TEST RESULTS AND EVALUATION SilEET I Test

Description:

M/D Flux Map- NI Calibration Reference , Proc No / Section: 2 PT-22.2 Sequence Step No:y6

!! Bank Positions (Steps) RCS Temperature l'P):T 11 Test Power Level (f. F.P.): Rb5 9 Conditions : SDA: 228 SDB: 228 CA: 228 Other (specify):

E g

(Design) CB : 228 CC : 22B CD: **

III Dank Positions (Steps) RCS Temperature ('T):

Test Power Level (*. F. P. ): 9 9. P7 7, Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 CC : 228 CD: 2Og Syl./ Wo/ere >

f.S9 Eff0 Date/ Time Test: I l

G "

Performed: c (,c o M T"t u 6m / '/q cca 849 MAX. REL NUC ENTilAL TOTAL llEAT QUADRANT

!V Mens Parameter ASSY PWR RISE 110T FLUX 110T POWER TILT (Description)

DIFF

, CilAN FACT CilAN FACT RATIO (M*P)/P F-dll( N) T-Q(T) QPTR d4 NA yA 6/A g Measured Value g Test Results Design Va'.ue ; ;;;;;;;;"i jj l '

i (Design Conds) i ' " " - NA NA 5 1.02 i WCAP-7905 WCAP-7905 l Reference REV.1 NONE NONE REV.1 V FSAR/Toch Spec NONE

""'""*""" "'""*"" NA Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerancs, is met : X YES NO Acceptance Criteria is met : .X.YES NO g VI 3 Comments

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

- As Required Prepared By: k 4t*[ Reviewed By:

' M h t6 hst M U if ,

ci fc,rg pp p, NE-817 N2C8 Startup Test Report Page 62 of 63 I

I I

NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET

Test Descriptton: M/D Flux Map- NI Calibration Reference l Proc No / Section: 2 PT 22.2 Sequence Step No: L/ f II ' Bank Positions (Steps)

' RCS Temperature ('F):Tp p 11 Test . Power Level (*. F.P. ): 9 15 Cone t tions l SDA: 228 SDB: 228 CA: 228 ' Cther (specify): *

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

I III Test Conditions l

lBankPositions(Steps)

SDA: 228 SDB: 228 CA: 228 RCS Temperature ('F):

Power Level (*. F.P.): t eo . I *f, Other (Specify):

(Actual) CB : .' 2 8 CC . 228 CD: g 3g g pju g -

Date/ Time Test: Il- /.E' io '7 Ol E F/'D Performed: 4 (ca rNM I IV Meas Parameter

/ -'Oci MAX. REL ASSY PWR

'F 2 r H t M NJ's !'/

NUCENTHALlTOTALHEAT' QUADRANT RISE HOT FLUX HOT PCWER TILT I (Description) *. DIFF (M-P)/P CHAN FACT F-dH(N)

CHAN FACT F-Q(T)

RATIO QPTR WA* UA Mi\ NA Measured Value Test Results I Design Value (Design Conds) ;di*""-

;;; l;"!'"

l:l NA NA 5 1.02 I Reference WCAP-7905 REV.1 NONE NONE WCAP-7905 REY.1 l

V Acceptance FSAR/ Tech Spec NONE

"*""*'"""l""" NA Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : $.YES NO I VI Comments Acceptance Criteria is met : Z YES NO

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

- As Required Prepared By: [' 7N b l It<[ Reviewed By: L -

N N li b t Ctade tl5 sj i,r C, Com ut o p .

NE-817 N2C8 Startup Test Report Page 63 of 63 l

NORTH ANNA POWER STATION UNTT 2 CYCLE 8 Q STARTUP PHYSICS TEST RESULTS AND EVA$UATION SHEET lLJ I Reference Test

Description:

Total Rod Worth - Rod Swap Proc No /Section: 2.PT-34.0 Sequence Step No:

Bank Positions (Steps) RCS Temperature (*F): 547 I II Test Conditions SDA: Moving SDB: Moving CA: Moving Other (specify):

Power Level (% F.P.): 0 (Design) CB: Moving CC: Moving CD: Moving Eelow Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): f'/3.3 Test Power Level (% F.P.): 0 Conditions SDA: Moving SDB: Moving CA: Moving Other (Specify):

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

caos IIl2.l90 I Meas Parameter (Description) ITotal; Int Worth of All Banks - Rod Swp IV Test Measured Value ITotal

Results 5 3 bY. 7 Design Value (Actual Cond) ITotal = 5 3 El. O t 6 31 Design Value ITotal = 5320 t 532 pcm (Design Cond)

Reference Technical Report NE-803 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 set : 1 YES N0 VI Acceptance Criteria is set : X YES ,,, _NO Comments Prepared By: - dd Reviewed By:

v NE-817 N2C8 Sta,rtup Test Report Page 57 of 63

I NORTil AMNA POWER STATION UNIT 2 CYCLE 8 I

STARTUP Pl!YSICS TEST RESULTS AND EVALUATION S!!EET a g

I Test

Description:

M/D Flux Hap - At power Reference Pr'c. No /Section: 2-PT-21.1 Sequence Step No: eff II Bank Positions (Steps) RCS Temperature ('F):T REF II Test Power Level (*. F.P. ): <307.

Conditions SDA: 228 SDB: 228 CA: 228 Other (specify) l (Design) C9 : 278 CC , 228 CD:

Must have 2 38 thimbles s III Bank Positions (Steps) RCS Temperature ('F): IF0' s Test Conditions Power Level (*. F.P. ): 77. /fy, g SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 CC : 228 CD:l$O N Se ce n : /743 ppm Date/ Time Test: "/4/90

Performed: I630 0.H4EFPO 43 THIM6L C5 MAX. REL NUC ENTHAL TOTAL llEAT QUADRANT 3 IV Meas Parameter ASSY PWR RISE ll0T FLUX HOT POWER TILT (Description) *. DIFF CilAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR I

Measured \,alue 5 2%fr.9 l.523 2.243 (.ot3 g, g. p l Test u Results -

Design Value (Design Conds) .**"' ~;a;

;;i;;;; 3 NA NA 5 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.1 V FSAR/ Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 l

Design Tolerance is met Acceptance Criteria is met

.X_YES

_X YES H0 50 I

VI

As Required l

Comments E I

Prepared By: id Reviewed By:

NE-817 N2C8 Star' tup Test Report Page 58 of 63 a_

I 1

NORTil ANNA POWER STATION UNIT 2 CYCLE B STARTUP PHYSICS TEST RESULTS AND EVALUATION SilEET I Test

Description:

M/D Flux Map-At Power Reference Proc No / Section: 2-PT-21.1 Sequence Step No: 43 II Bank Positions (Steps) RCS Temperature ('F): TREF 11

.g Test Power Level (*, F.P. ): (75%

g Conditions SDA: 228 SDB: 22S CA: 228 Other (specify)

(Design) CD : 228 CC . 228 CD:

Must have 2 38 thimbles III Dank Positions (Steps) RCS Temperature ('F):

Test Power Level (?. F.P.): 12.157.

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 CC : 228 CD: 185' (,2 , g sw pfu r y

1. (o EF P D Date/ Time Test: 11 / l / 9 0 .y6. M M6 M Performed:

MAX. REL NUC ENTHAL TOTAL !! EAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) *. DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR

^

3.1%,f'7A Measured Value g,q q l*3 98 1. Ol l 7 Test 4.7 % , P ' .9 Results - -

Design Value ,...

(Design Conds) .IOi nZ.D*

.. . , Z' NA NA 5 1.02 l I Reference WCAP-7905 REV.1 NONE NONE WCAP-7905 REV.1 l

V FSAR/ Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : _X_YES _ NO I VI Comments Acceptance Criteria is met

As Required

Y YES _ N0

!I Prepared By: Ibdw[ Reviewed By: /

NE-817 N2CB Star; tup Test Report Page 59 of 63 I

J

s f

NORTH ANNA POWER STATION UNIT 2 CYCLS B STARTUP PHYSlCS TEST RESULTS AND EVALUAYION SHEET I Test Descr2ption: M/D Flux Map-At Power Reference Proc No / Section: 2-PT-21.1 Sequence Step No: 4./ 3 II Bank Positions (Steps) lRCSTemperature(S F):T 21 l Test -

Power Level (*. F.P. ): (pbt

[ Conditions SDA: 228 SDB' 22B CA: 228

. Other (specify)

(Design) CB : 228 CC . 228 CD: * ; Must have 2: 38 thimbles III Dank Positions (Steps) RCS Temperature ('F):

Test Power Levn1 (*. F.P. ): 7.2.15 7.

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 CC 228 CD: 185' (,2.8 uwp/-r.w -

f.h EFPO Date/ Time Test: fi / "/ /90 y(c. ~7 NI M 6 Lt $

Performed:

1 !

MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Mens Parameter ASSY PWR RISE HDT FLUX HOT POWER TILT (Descriptien)

DIFF

. CHAN FACT CHAN FACT RATIO (M-P)/P l F-dH(N) F-Q(T) QPTR 3.1 % , f' r .9 Measured Value g'qq3 I'3 98 1.OH7 Tent 4.'7 7, , P 4.9 Results ,

Desir,n Va1ue ....

1 (Design Conds) .!*'Oi .i . .. . ,S Ii EI NA NA i 5 1.02 WCAP-7905 WCAP-7905 I Reference REV.1 NONE NONE REY.1 I i l I ) .",,u ..i n . . in ... . ;'U ti i n a' . s u i V FSAR/ Tech Spec NONE NA l Acceptance j

Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : . 1 YES' _ N0 Acceptance Criteria is met : Y YES ___NO l VI Comments

As Required 1

Prepared By: I MV.[ Reviewed By. 4 '

NE-817 N2C8 Startup Test Report Page 59 of 63 1

n NORTil ANNA POWER STATION UNIT 2 CYCLE 8 g STARTUP P}lYSICS TEST RESULTS N'D EVALUATION SHEET g I ! Test

Description:

M/D PNx Mai NI Calibration 43 Reference Proc No / Section: 2 PT 0272 ,th/ Sequence Step No: 9g E' ofu a + < . ,_ ~r... g II Bank Positions (Steps) } RCS Temperature ('t):T Test -

J Power Level (*. F. P. ): gh15y 9 11 E'

Conditions! SDA: 228 SDB: 228 CA: 228 Other (specify):

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

!!! Bank Positions (Steps) RCS Temperature ('F):

Test Power I,evel (i F.P. ): 90,o 7 %

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB . 228 CC : 228 CD: ; toy g 7,7 u w pj u m .

Date/Timo Tent: ll/P/90 Performed:

IF3o " T8'"'#~IS E g

MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) % DIFF CHAN FACT CHAN FACT RATIO (M P)/P F dH(N) ; F-Q(T) QPTR

-1 47,, P M Measured Value 1 423 ( . 7 /8 1.00 R2 Test 4 5'4, pt ,9 Resu1ts Design Value e i . . . ., ,

(Design Conds) I'3 EW, . .. , '

NA NA 5 1.02 WCAP-7905 WCAP-7905 g Reference REV.1 NONE NONE REV.1 5

l. V FSAR/ Tech Spec NONE NA Acceptanco Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 1

Design Tolerance is met : l YES _, N0 VI Acceptance Criteria is met : X YES _,,.NO g g

Comments

Must have at Icast 38 thimbles for a full-core flux map, or

! at least 16 thimbles for a quartar-core flux map. E l ** As Required g l

Prepared By: @ [m [ Reviewed By: N~

NE-817 N2C8 Startup Test Report Page 60 of 63 B

I NORTil ANNA POWER STATION UNIT 2 CYCLE 'J E STARTUP PHYSICS TEST RESULTS AND EVALUA fl0N SHEET E _ ;-, v I Test

Description:

M/S Flux Map - HTP, ARD, Eq. Xe I Reference Il Proc No / Section: 2-PT-21.1 Bank Positions (Steps)

Sequence Step No; v s' RCS Temperature ('F?:T Test Power Level (*. F.P. ): g~>st5p 21 I Conditions (Design) i SDA: 228 SDB: 228 CA: 225 CB : 228 CC : 228 CD:

Other (specify): Eq. Xo.

Must have 2 38 thimbles III Bank Positions (Steps) RCS Temperature ('F):

B T,est -

Power Level (*. F.P. ): 99 A p '/,

Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 CC : 228 CD: n p 3rr. t mogm .

Date/ Time Test: ll-I4*ib '9 rF##

Performed: IWo D ###

O % f H BLU S 5 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT I (Description) *

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

CHAN FACT F-Q(T)

RATIO QPTR 33% PrA E Measured Value [,qgq [, g y g, g ,o o g g, Test 4.17, , p t ,9 Results I Dasign Value (Design Conds) "y. am i

g .,A eg NA NA 6 1.02 I -

Reference WCAP-7905 REV.1 NONE NONE WCAP-7905 REV.1 I V Acceptance Criteria FSAR/ Tech Spec' NONE '\"'""**"" 8'""'" NA Reference NONE TS 3.2.3 75 3.2.2 TS 3.2 A Design Tolerance is met , ,,1.YES ,,,NO I VI Comments Acceptance Criteria is mot

As Required

_X,,,YES __ NO I

""8~" '

I """""'"

" """" "' ' M7'"

NE-817 N2C8 Startup Test Report Page 61 of 63

I I

NORTil ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PilYSICS TEST RESULTS AND EVALUATION SIIEET I Test

Description:

M/D Flux Map- NI Celibration Reference Proc No / Section: 2-PT-22.2 Sequence Step No:y(,

II Bank Positions (Steps) RCS Temperature ('F):T 11 Test Power Level (7. F.P. ): pb5 9 Conditions SDA: 228 SDB: 228 CA: 228 other (specify): *

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

III Bank Positions (Steps) RCS Temperature ('F):

Test Power Level (?, F.P. ): 9 9. P7 7, Conditions SDA: 228 'B: 228 CA: 228 Other (Specify):

(Actual) CB : 228 C: 228 CD: 2og Wl./ Wo/Mr4 -

Date/ Time Test: 0 - 8 C'9 0 f S9 Eff0 Performed: o r,c o 24 hu6m k We W MAX. REL tUC ENT}lAL TOTAL llEAT QUADRANT IV Meas Parameter ASSY PWR RISE !!OT FLUX }{0T POWER TILT (Description) 7. DIFF CliAN FACT CllAN FACT RATIO (M-P)/P F-dll(N) F-Q(T) QPTR

, Measured Value ;

Test j j Results Design Vulue ; y ;;; ;;** ;,; '

(l'esign Conds) % * ""- *' NA NA 5 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.1 E

, g 5 v FSAR/Toch Spec NONE ' ' "" ' " " * * * " * " '"''""'" NA trceptance Criteria Reference ,

NONE TS 3. ' .3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : X YES NO Acceptance Critoria is met : Y YES NO g VI g i

Comments

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

- As Required Prnyared By: a tie [ Reviewed By:

N A btct.au.-dly it o ge NE-817 N2C8 Startup Test Report Page 62 of 53

I NORTH ANNA POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test scription: M/D Flux Map- N1 Calibration Reference Proc No / Section: 2-PT 22.2 Sequence Step No: Lj7 II Bank cositions (Steps) RCS Temperature ('F):T REF 11 Test Power Level (?, F.P.): 95 5 Cond it ions SDA: 228 SDB: 228 CA: 228 3ther (specify): *

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

I III Test Conditions Bank Positions (Steps)

SDA: 228 SDB: 228 CA: 228 RCS Temperature ('F):

Powv Level (?. F.P.): ico.1 af, Othe- (Specify):

, (Actual) CB 228 CC 228 CD: np 3yg, g ,pfy g .

Date/ Time Test: II-/E'70 '701EFFD Performed:

i I IV Mens Parameter

/ 7Co MAX. REL NUC ENTHAL 2(r W LMft O I4 Cote NM TOTAL HEAT QUADRANT ASSY PWR RISE HOT FLUX HOT POWER TILT I (Description) % DIFF (M-P)/P CHAN FACT F-dH(N)

CHAN FACT F-Q(T)

RATIO QPTR VA NA I Test Measured Value MA* NA Results I Design Value ; ;;;;;;;i!lj (Design Conds) i'""*' NA NA 5 1.02 I Reference WCAP-7905 REV.1 NONE NONE WCAP-7905

REV.1 V FSAR/ Tech Spec NONE ""'"""" '**'"""' NA Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : <YES N0 I

Acceptance Criteria is met : V"YES NO VI Comments

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

- As Required Prepared By: I'[ idit/ Reviewed By:

cT becrue (46 II 4 fco<e ruog.

I NE-817 N2C8 Startup Test .teport Page 63 of 63 l

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ML20028H860

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