Text

Cycle 10 Startup Physics Test Rept
	ML20059K324
Person / Time
Site:	North Anna
Issue date:	12/23/1993
From:	Bowling M; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	94-023, 94-23, NUDOCS 9402020043
	Download: ML20059K324 (31)
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VinoNIA EtecTurc AND l'OWUn COMi*ANY

, Ricnxoxu,Vinoisir ener.1 l

January 14, 1994 United States Nuclear Regulatory Commission Serial No.

94-023-Attention: Document Control Desk NL&P/GSS R0 Washington, D.C. 20555 Docket Nos.

50-339 License Nos. NPF !

Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TESTS REPOFlT lo required by North Anna Technical Specification 6.s.1, enclosed are five copies of the Virginia Electric and Power Company Technical Report NE-963, " North Anna Unit 2, Cycle 10 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after initial criticality of Cycle 10 on October 26, 1993. The results of the physics tests were within required design tolerances and arP cable Technical Specification limits.

li Very truly yours,

/$ k M. L. Bowling, Manager Nuclear Licensing and Programs Enclosures cc:

U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 F

Mr. R. D. McWhorter NRC Senior. Resident inspector North Anna Power Station 240198 gggf,

9402020043 931223 PDR ADOCK 05000339 i

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VIRGINEA POWER

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TECHNICAL REPORT NE-963 - Rev. 0 NORTH ANNA UNIT 2, CYCLE 10 STARTUP PHYSICS TESTS REPORT n

NUCLEAR ANALYSIS AND FUEL WUCLEAR ENGINEERING SERVICES VIRGINIA POWER DECEMBER 1993 PREPARED BY:

<4/JWFS E. R. Makovksy

Date REVIEWED BY:

J bM IM:kaIf3 I

P. D. Bann'ing d

Date k

REVIEWED BY:

/2-D-95 A. P. Main Date APPROVED BY:

7 h[f)

D. Dziadsz

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Ddte' OA Category: Nuclear Safety Related-1 Keywords: N2C10, Startup

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CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report ' have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for 2se in situations other than those for which they have been specifically prepared.

The Company l

therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability.

In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL 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, techniques, information, or conclusions in it.

By making this report available, the Company does not authorize its use by others, and any such i

use is expressly forbidden except with the prior written approval of the i

Company. Any such written approval shall itself be deemed to incorporate l

the disclaimers of liability and disclaimers of warranties provided i

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, l

loss of use of property, or other damage resulting from or arising ~ out i

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

I i

l NE-963 N2C10 startup Physics Tests Report Page 1 of 57 3

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TABLE OF CONTENTS PAGE Classification / Disclaimer...............................

1 Table of Contents..

2 List of Tables.....

3 L is t o f Figu r e s.........................................

4 Preface..........

5 3

Section 1 Introduction and Summary...................

7 Section 2 Contr 1 Rod Drop Time Measurements.........

16 Section 3 Control Rod Bank Worth Measurements........

21 Section 4 Boron Endpoint and Worth Measurements......

26

?

Section 5 Temperature Coefficient Measurement........

30 Section 6 Power Distribution Hessurements............

32

^

Section 7 References.................................

40 APPENDIX Startup Physics Tests Results and Evaluation Sheets........................

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9 NE-963. N2C10 Startup Physics Tests Report Page. 2 of 57

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LIST OF TABLES j

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l TABLE' TITLE PAGE 1.1-Chronology of Tests...................................

10 2.1 Hot Rod Drop Time Summary.............................

18-3.1 Control Rod Bank Worth Summa ry........................

12 3-4.1 Boron Endpoints Summary................................

28 l

5.1 Isothermal Temperature Coefficient Summary............

31 6.1 Incore Flux Map Summary...............................

34 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits......................

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NE-963 N2C10 Startup Physics Tests Report Page 3 - of 57 1

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b LIST OF FIGURES i

i FIGURE TITLE PAGE 1.1 Co r e Load in g M a p.........................................

11

- t 1.2 Beginning of Cycle Fuel Assembly Burnups.................

-12 1.3 Available Incore Moveable Detector Locations.............

13 1.4 Burnable Poison and Source Ass <sably Locations............

14

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1.5 Control Rod Locations.....................................

15 i

2.1 Typical Rod Drop Trace...................................

19 t

2.2 Rod Drop Time - Hot Full Flow Conditions.................

20 t

L 3.1 Control Bank B Integral Rod Worth - HZP..................

24

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l 3.2 Control Bank B Differential Rod Worth -

HZP..............

25 4.1 Boron Worth Coefficient..................................

29

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6.1 Assemblywise Power Distribution - 29% Power..............

36 1

6.2 Assemblywise Power Distribution - 44% Power..............

37 6.3 Assemblywise Power Distribution - 73% Power.............

38 6.4 Assemblywise Power Distribution - 98% Power.............

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5 NE-963 LN2C10 Startup Physics Tests Report Page 4 of 57,

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PREFACE

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This report presents the analysis and evaluation of the physics tests

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-which were performed to verify that the north Anna 2, Cycle 10 core could-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 detailed data taken.

Stand'ard testing techniques and methods of data analysis were used. The test data, i

results and evaluations, together with the detailed startup procedures, are on file at the North Anna Power Station.

Therefore, only a cursory discussion of these items is included in this report.

The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of:the results.

l The North Anna 2,

Cycle 10 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 forrat. The

' design test conditions and design values - (at design conditions)c of the measured parameters were completed prior to the startup physics testing.

The entries for the design values were based on the calculations performed.

I by Virginia Electric and Power Cumpany's Nuclear Analysis and Fuel (

3 Group.

During the tests, the data sheets were used as guidelines both

- to verify th;t the proper test conditions were met and to facilitate the -

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'NE-963 N2C10 Startup Physics Tests Report Page 5 of 57 1

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preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests.

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.NE-963 N2C10 Startup Physics Tests Report

.Page.

6 of 57' l

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SECTION 1 INTRODUCTION AND

SUMMARY

On September 7, 1993 Unit No. 2 of the North Anna Power Station i

shutdown for its ninth refueling.

During this shutdown, 89 of the 157 fuel assemblics in the core were replaced with 64 fresh fuel assemblies, one once-burned fuel assembly and 24 twice-burned fuel assemblies.

The tenth cycle core consists of 10 sub-batches of fuel: three once-burned batches two from Cycle 9 (batches 11A and 11B) and one from Cycle 7 (batch 9A) ; five twice-burned batches, two from Cycles 6 and 7 (batches 8A and 88), one from Cycles 8 and 9 (batch 10B), one from North Anna 1 Cycles 7 and 8 (batch N1/9A), aad one from North Anna 1 Cycles 8 and 9 (batch N1/10C); and two fresh batches (batches 12A and 12B).

The two fresh i

batches, two once-burned batches, and one twice-burned batch have top and bottom grids of Inconel-718 while the inner six grids are made. of

. Zircaloy-4 (all other batches have eight grids made of Inconel-718).

Cycle 10, similar to Cycle 9, incorporated the. burnable poison rod r

design made of B C in Alumina, which is available in-various enrichments 4

of B C.

There are no thimble plugging devices inserted in N2C10.

A Reference 1 provides a more detailed description of the Cycle 10 core.

The core loading pattern and the design parameters for each sub-batch are shown in Figure 1.1.

Fuel assembly burnups are given in Figure 1.2.

The available incore moveable detector locations used for the BOC flux ~

3 t

map analyses are Identified in Figure 1.3.

Figure 1.4 identifies the location and number -of ' burnable poison rods and source" assemblies for l

NE-963 N2C10 Startup Physics Tests Report Page 7 of 57 ?

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'i Cycle 10, and Figure 1.5 identifies the location and number of. control rods in the Cycle 10 core.

On October 26, 1993 at 1808, the Cycle 10 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:

1.

The measured drop time of each control rod was within the 2.7

^

second limit of Technical Specification 3.1.3.4.

I

~ i 2.

Individual control rod bank worths were measured using the rod swap technique'e and the results were within 4.0% of the design

-i predictions. The sum of the individual measured control rod bank worths was within 1.4% of the design prediction.

These.results are 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 individua1' control rod bank worths.

i 3.

Measured critical boron concentrations -for two control bank configurations were within 24 ppe of the design predictions.

These results were within the design tolerances _and also met the Technical Specification 4.1.1.1.2 criterion that the overall core reactivity - balance shall be within 11% Ak/k' of-the design prediction.

4.

The boron worth coefficient measurement was within 1.5% of the design prediction, which.is within the design tolerance of 10%.

.NE-963 N2C10 Startup Physics Tests Report Page 8 of 57 -

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i 5.

The measured ' isothermal temperature coefficient (ITC). for the all-rods-out (ARO) configuration was within 0.40 pcm/*F of the 1

design prediction.

This result is within the design tolerance of 3 pcm/'F.

The Core Operating Limits Report (COLR) 2.'1.1 criteria requires that the moderator temperature coefficent (MTC) be. less than or equal to

+6.0 pcm/'F.

When the Doppler r.

temperature coefficient and a 0.5 pcm/*F incertainty are accounted for in the MTC calculatation, the MTC requirement.is satisfied as long as the ITC is less than or equal to +3.74 pcm/'F.

The measured ITC of -2.71 pcm/'F meets this criteria.

6.

Mode 1 (See Reference 4) core power distributions were within established design tolerances.

Generally, the measured core power distribution was within 3.9% of the design predictions.

J The heat flux hot channel factors, F-Q(Z), and'enthalpy rise hot' channel factors, F-DH(N), were within the limits of COLR Sections 2.5.1 and 2.6, respectively.

1 In summary, all startup physics test results were acceptable.

l Detailed results, specific design tolerances and acceptance criteria for.

each measurement are presented in the follow'ing sections of this report.

i

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NE-963 N2C10 Startup Physics Tests Report Page' 9 - of 57.

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Table 1.1 NORTH ANNA 2 - CYCLE'10 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power.

Procedure Hot Rod Drop - Hot Full Flow 10/25/93 1800 HSD 2-PT-17.2 Zero Power Testing Range 10/26/93 1910 HZP 2-PT-94.0 Reactivity Computer. Checkout 10/26/93-2005 HZP 2-PT-94.0 Baron Endpoint - ARO 10/26/93 2312 HZP.

2-PT-94.0-Temperature Coefficient - ARO 10/26/93-2353 HZP 2-PT-94.0-Bank B Worth 10/27/93-0142 HZP 2-PT-94.0' Boron Endpoint - B in 10/27/93 0555 HZP 2-PT-94.0 Bank D Worth - Rod Swap 10/27/93 0142 HZP 2-PT-94.0 Bank C Worth - Rod Swap 10/27/93 0142

'HZP-2-PT-94.0 Bank A Worth - Rod Swap 10/27/93 0142 HZP 2-PT-94.0 Bank SB Worth Rod Swap 10/27/93 0142 HZP-2-PT-94.0 7

Bank SA Worth - Rod Swap 10/27/93 0142 HZP 2-PT-94.0 i

Flux Hap - 29% Power-10/28/93 0330 29%

2-PT-21.1 Peaking Factor Verification 2-PT-21.2 t

& Power Range Calibration 2-PT-22.4 Flux Nap - 73% Power 10/30/93 1458 73% FT-21.1 Peaking Factor Verificaticn 2-PT-21.2 l

& Power. Range Calibration 2-PT-22.4 Flux Map - 98% Power 10/31/93 1644 98%

2-PT-21.1 Peaking Factor Verification 2-PT-21.2

& Power Range Calibratien 2-PT-22.4

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NE-963 N2C10 Startup Physics Tests Report Page 10 of 57

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FUEL RODS PER ASSEMBLY 2M 2M 2M 264 2M 2M FM 2M 2M 2M NE-963 N2C10 Startup Physics Tests Report Page 11 of 57 l

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NE-963 N2C10 Startup Physics Tests Report

.Page 12 of 57

e e' Figure 1.3 NORTH ANNA UNIT 2 - CYCLE 10.

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u i

l NE-963 N2C10 Startup Physics' Tests Report Page-13 of 57:-

' a 1

i l

)

Figure 1.4 NORTH ANNA UNIT 2 - CYCLE 10 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R

P N

N L

K J

H C

f E

D

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1 1

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l l BP295) BP282) l BPZ648 i BP2811 BP3041 l

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I t

NE-963 N2C10 Startup Physics Tests Report Page 14 ' of 57-

Figure 1.5 NORTH ANNA UNIT 2 - CYCLE 10 CONTROL ROD LOCATIONS R

P N

M L

K J

H G

F E

D C

B A

180" l

Loop A I

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outlet i

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i l

l Loop B Absorber Outlet inlet Material

.I Ag-In-Cd 0

Function Museber of Clusters Control Ba#* D 8

Control Bank C 8

Control Bank B B

Control Bank A 8

Shutdown BarA SB 8

Shutdown Bank SA 8

SP (Spare Rod Locations) 8 Called North' V

NE.963 N2C10 Startup Physics Tests Repol?-

Page 15 of 57

8

)

SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow-reactor coolant system (RCS) conditions in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the maximum allowed by Technical Specification F

3.1.3.4.

The control rod drop times were measured in Mode 3" with the

~

RCS Tavg above 500*F and all reactor coolant pumps operating.

The rod drop times were measared by withdrawing a rod bank 229 steps and then removing the moveable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant. trip.

The.

stationary gripper coil voltage and the Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded to determir.e 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.

As the rod a

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 i

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-963 N2C10 Startup Physics. Tests Report Page 16 of 57 '

t

i The measured drop times for each control rod are recorded on Figure 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 l

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 limit.

'+

?

i

~i I

s i

i I

i r

I P

i l

NE-963 N2C10 Startup Physics Tests Report Page-17 of 57-ar

Table 2.1 NORTil ANNA UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS-liOT ROD DROP TIME

SUMMARY

?

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME B-06 1.77 sec.

M-04 1,43 sec.

1.60 sec.

k v

NE-963 N2C10 Startup Physics' Tests Report Page 18 of 57

Figure 2.1 NORTil ANNA UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE Beginning Of Dashoot Bottom Of Dastat i

Initiation Of Rod (Beginning Of First (Beginning Of First Drop Event Mark Downtum in Trace)

Uptum in Trace)

~7

/

\\

/

W/A'/AW ".WA(

Stationary Grioper Coil Voltage Trace Annnnnnnnn n

VVVVVVVVV 60HzIRPI VVVVVVV Pnmam vvvv y0 ge e

Annnnnn!,nnnnnnnnnnnnnnnnnnnnn nnnnnn nnnnnnnn vvvvvvvvvvvvvvvvvvvvvvvvvvvvvvvvvvevvvvvvvt 60Hz Trace

-+

+-

a n u au one cycie ROD DROP TIME MEASUREMENT j

l NE-963 N2C10 Startup Physics Tests Report Page 19 of 57

4 4

Figure 2.2 NORTil ANNA UNIT 2 - CYCLE 10 STARTUP Pl!YSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R

P N

M 1

K J

H C

F E

D C

8 A

I I

4 i

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2 1

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l NE-963 N2C10 Startup Physics Tests Report -

Page. 20 of 57

i T

SECTION 3 4

1 CONTROL ROD BANK WORTH MEASUREMENTS j

Control rod bank worths were measured for the-control and-shutdown banks using the rod swap techniqueV.

The initial step of the rod swap method diluted the predicted most reactive control ' rod bank (hereafter 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 movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank.

For Cycle 10, Control Bank B was used as the reference bank.

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

concentratica were stabilized with the reactor just critical and the

]

reference bank at full insertion with the Control Bank D - slightly :

inserted. Initial statepoint data for the rod swap maneuver were obtained by leaving the reference bank at its fully inserted position and fully withdrawing all other banks and recording the ~ core reactivity f and moderator temperature. From this point, a rod swap maneuver was performed' by withdrawing the reference bank several steps and then inserting one j

of the other control rod banks (i.e.,

a test bank) 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 or near the _ initial statepoint condition.

This measured critical position (MCP) of the i

NE-963 N2C10 Startup Physics Tests Report Page 21 of 57

m i

.l 8

.)

bank fully inserted was used to determine the integral reactivity worth i

of the test bank.

The core reactivity, moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod. swap maneuver then was repeated in reverse such that the reference bank again was near full insertion with the test bank.

fully withdrawn from the core.

This rod swap process was then repeated for each of the other control and shutdown banks.

A summary of the test results is given in Table 3.1.

As shown,in this table and the Startup Physics Tests Results and Evaluation Sheets y

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 test banks of worth greater than 600 pcm. and 1100 pcm for test banks of worth less than or equal to 600 pcm.) The sum of the individual measured rod bank worths was within 1.4% of the design j

prediction. This is well within the design tolerance of 10% for the sum 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.

i The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfa'. tory.

4 k

NE-963 N2C10 Startup Physics. Tests Report

'Page

'22 of '57

e Table 3.1 NORTH ANNA UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

l MEASURED PREDICTED PERCENT DIFFERENCE I

WORTH WORTH

(%)

l BANK (PCM)

(PCM)

(M-P)/P X 100 B-Reference Bank 1263.5 1273.0

-0.7 D

1012.2 1001.2 1.1 C

850.6 835.2 1.8 A

243.2 233.9 4.0

SB 1118.4 1079.8 3.6 SA 955.1 946.7 0.9 Total Worth 5443.0 5369.8 1.4

Dif ference is less than 100 pcm.

NE-963 N2C10 Startup Physics Tests Report Page 23 of 57

Figure 3.1 NORTH ANNA UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1,400 PREDICTED i

i l

DATA

,m

-n 1,200

' "s' a \\i i

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MEASURED A

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DATA O 1,000

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.ix

M NE-963 N2C10 Startup Physics Tests Report Page 49 of 57 - NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Catl Bank C 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: 225 SDB: 225 CA: 225 Other (specify):

(Design)

CB: Moving CC:MovingCD: 225 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature ( *F): 54'7 Test Power Lavei (% F.P. ): O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual)

CB:P.oving CC:MovingCD: 225 Below Nuclear Heating Date/ Time Test Performed:

to l."n l93 01:42.

Meas Parameter RS (Description)

IC ; Int Worth of Cnti Bank C-Rod Swap IV RS (Adj. Meas. Crit. Ref Bank Test Heasured Value I

= 65.G Position = iM.t, s teps)

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

I

= 6 30. 2.

Position = 154.Gsteps)

C RS Design Value IC= 830 i 125 pea (Critical Ref Bank (Design Cond)

Position = 139 steps)

Reference Technical Report NE-958, 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 met v' YES

,,,_,,_NO VI Acceptance Criteria is met

/ YES

__,_NO.

Comments Prepared By:

D Reviewed By:

1 Y

NE-963 N2C10 Startup Physics Tests Report Page 50 of 57

i O

"I g

O

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IMAGE EVALUATION j/

4 th gf)[tf'fp

\\ ////p % [

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IMAGE EVALUATION

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TEST TARGET (MT-3)

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NORTH ANNA POWER STAT!DN UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET p

I Test

Description:

Cntl. Bank A 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. ): 0 g

Conditions SDA: 225 SDB: 225 CA: Moving Other (specify):

(Design)

CB: Moving CC: 225 CD: 22S Below Nuclear Heating L

III Bant Positions (Steps)

RCS Temperature ('FJ: 544' Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: Moving Other (Specify):

(Actual)

CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:

1Ola7 h3 01 *.'+2 Meas Parameter RS (Description)

IA ; Int Worth of Catl Bank A-Rod Swap IV RS (Adj. Meas. Crit. Ref Bank Test Measi.: red Value I

= M3. cl Position =/A.2 steps)

A Results y

Destgn Value

= 233.9 ( Adj. Meas. Crit. Ref Bank RS (Actual Cond)

I Position = ge.2 steps) f 4

RS Design Value IA= 240 100 pcs (Critical Ref Bank l;

(Design Cacd)

Position = 72 steps) um--.

Reference Technical Report NE-958, Rev. O, VEP-FRD-36A

~

i If Design Tolerance is exceeded, SNSOC

{

shall evaluate impact of test mult on V

FSAR/ Tech Spac safety analysis. SNSOC may specify that Acceptance additional testing be perforrW.

Criteria Reference VEP-FRD-36A Design Tolerance is met

..:C,YES NO VI Acceptance Criteria is set

/ YES NO Consents-Prepared By:'

Reviewed By:

J NNM NE-963 N2C10 Startup Physics Tests Report Page 51 of 57

=

NORTH ANNA POWER STATION UNIT 2 CYCLE 10

~

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

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

II Bank Positions (Steps)

Test RCS Temperature (*F): 547 Power Level (% F.P.): O Conditions l SDA: 225 SDB:MovingCA: 225 Other (specify):

(Design)l CB: Moving CC: 225 CD: 225 Below Nuclear Heating i

III Bank Positions (Steps)

RCS Temperature ('F): 6M Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB:MovingCA: 225 Other (Specify):

a (Actual)

CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:

lo/r7/M WW

{

Meas Parameter RS (Description)

ISB; Int W rth of Shutdown Bank B-Rod Swap

.e IV RS (Adj. Meas. Crit. Ref Bank Test Measured Value I

Results gg = ( H S.4 Position =l80.'lsteps)

Design Value g3 (Adj. Meas. Crit. Ref Bank (Actual Cond)

ISB = (OB.%

Position = lSo1 steps)

RS Design Value ISB = 1078 i 162 pcm (Critical Ref Bank (Design Cond)

Position = 177 steps)

Reference Technical Report NE-958, Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate wpact of test result on V

FSAR/ Tech Spec Acceptance safety analysis. SNSOC may specify that

[

Criteria additional testing be performed.

Reference VEP-FRD-36A Design Tolerance is met

/._YES N0 VI Acceptance Criteria is met

/ YES NO Comments Prepared By 3

Reviewed By: bNdNM SE-963 N2C10 startup Physics Tests Report Page 52 of 57

A e

NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Shutdown Bank A Worth 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:MovingSDB: 2 25 CA: 225 Other (specify):

(Design)

CB: Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (*F):5'*46 Test Power Level (% F.P.): O Conditions SDA:MovingSDB: 225 CA: 2 25 Other (Specify):

(Actual)

CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed :

io/tv/93 O t

't t Meas Parameter RS (Description)

ISA; Int W rth of Shutdown Bank A-Rod Swap IV

.g RS (Adj. Meas. Crit. Ref Bank 55-Test Measured Value I SA Position =1549 steps)

=

Results Design Value RS

( Adj. Meas. Crit. Ref Bank (Actual Cond)

I

= 9Nb' SA Position =l50.9 steps)

RS Design Value I

= 952 : 143 pcm (Critical Ref Bank SA (Design Cond)

Position = 157 steps)

Reference Technical Report NE-958, 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 met V YES NO VI Acceptance Criteria is met

_ELYES NO Comments

. Prepared By: b d NA Reviewed By:

l l

NE-963 N2C10 Startup Physics Tests Report Page 53 of 57 e

~~.

..n.

NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Total Rod Worth - Rod Swap bference Proc No /Sectir n: 2-PT-94.0 Sequence Step No:

e II Bank Positions (Sceps)

RCS Temperature ('F): 547 Test 3 Power Level (% F.P. ): O Conditions SDA: Moving SDB: Moving CA: Moving Other (specify):

(Design)

CB: Moving CC: Moving CD: Moving Below Nuclear Heating i

III Bank Positions (Steps)

RCS Temperature ('F): 54 ~7 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 Date/ Time Test Performed:

lb lL7 /9 3 O I : 'i t Meas Parameter (Description)

ITotal; Int W rth of All Banks - Rod Swap IV Test Measured Valua ITotal =

5443.o Results Design Value (Actual Cond)

ITotal = F 3 G,9.g l

Dasign Value ITotal = 5371 537 pcm I

(Design Cond)

Reference Technical Report NE-958, Rev. O, VEP-FRD-36A If Design Tolerance is exceeoed, SNSOC shall evaluate impact of test result on V

FSAR/ Tech Spec safety analysis.

Additional testing Acceptance must be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met YES

_,__NO VI Acceptance Criteria is met YES NO Comments Prepared By:

frI I/ lb-%

Reviewed By:

W D

NE-963 S2C10 Startup Physics Tests Report Page 54 of 57 l

e s

NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET lTestDescription: M/D Flux dap-At Power I

Reference i, Proc No / Section: 2-PT-94.0,2-PT-21.1 Secuence Step No:

] Bank Positions (Steps)

RCS Temperature ('F):Tpg il 11 Test Power Level (; F.P.): <30 Canditions:

SDA: 225 SDB: 225 CA: 225 Other (specify):

l (Design) I CB : 225 C::

Must have 2 38 thimbles **

CD:

l Tres f. l t

l III Bank Positions (Steps)

RCS Temperature ('F):

l Test Power Levei (T. F.P.): 29.o l'/.

f Conottionsl SDA: 225 SDB: 225 CA: 225 Other (Specify): Nf.a +Mmbks I

(Actual) !

CB : 225 CC.2 M CD: 05 Date/ Time Test Pe rf o rmeo :

l ioltS/t 5

"*'c

_.. ~

l MAX. REL ! NUC ENTHALITOTAL HEATlMAXIMUM PCS.

V Meas Parameteri ASSY PWR i RISE HOT t FLUX HOT IINCORE (Description s ;

. DIFF CHANFACT1CHANFACTjQUADRANT l(M-P)/P l

F-dH(N) l F-Q(Z) gPOWER TILT ld'4d : ^

i s 4 2.

2.3031 f.oM i S Measured Va lue su (,r Pi'.'i Test l

j Results Design Value

g ra;;;;.; e (Des 2gn Conds) t e, -....

NA NA

, S 1.0211

.WCAP-7905 l WCAP-7905 Reference REV.1

~

NONE NONE REV.1

!FSAR/COLR NONE NONE V

4 Acceptance.

)

l l

Criterza Reference NONE i COLR 2.5

. COLR 2.5.1 NONE

,_,,,YES d 40 Design Tolerance as set Acceptance Criteria is met

M YES

,,,,,,.90 VI l

Coenents i

As Recutred

- Must have at least 16 thimbles for quarter core saps for multi point calibrations.

M _ks-Prepa.reo By:

I h

Review o ay:

g SE-963 N2C10 Startup Physics Tests Report Page 55 of 57

s I

NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

M/D Flux Map-At Power Reference Proc No / Section: 2-PT-94.0,2-PT-21.1 Sequence Step No:

II Bank Positions (StensJ RCS Teeperature ('F):TR U

Power Level (% F.P.): Sb5%

Test Conditions, SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design)

CB : 225 CC.

CD:

Must have 2 38 thimbles **

III Bank Positions (Steps)

RCS Temperature ('F): Wa i*:-

Test Power Level (% T.P. ): 72.99 Conditions i

SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual)

CB : 225 CC. 2 25 CD: 1 r3 '

!Date/TimeTest Performed:

0/30l'/7 14:57 l; MAX. REL NUCENTHALiTOTALHEATlMAXIMUMP05.

IV Mens Parameter:

ASSY PWR RISE HOT FLUX HOT

'INCORE

( Description)

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

F-Q(Z)

POWER TILT

~7,42. G '

Measured Value:

62ch l. 'l 70 ' 2.I29 '

f.o267 /

j l S O-W Test Results Dasign Value ag(!M (Design Conds) 'r*~>

NA NA S 1.0208 i

VCAP-7905 VCAP-7905 Reference REY.1 NONE NOME REY.1 V

FSAR/COLR NONE NONE Acceptance; Criteria Reference NONE COLR 2.6 COLR 2.5.1 NONE Design Tolerance is set YES I NO Acceptance Criteran is met

/ YES _ NO VI Comments l

As Required

- Must have at least 16 thimbles for quarter core maps for multi point calibrations, h

Prepared By:

Reviewed By: b NE-963 N2C10 startup Physics Tests Report Page 56 of 57

______m_____-

- " ^-

r 4

e l-NORTH ANNA POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SEEET I

Test

Description:

M/D Flux dap-At Power Referenes Proc No / Section: 2-PT-94.0,2-PT-21.1 Seanance Step No:

II Banz Positions (Steps; RCS Temperature ('T):T 21 g b 100%

Test Power Level (% F.P.):

9 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Dasign)

CB : 225 CC : 225 CD:

Must have 2 38 thimbles **

l l

III Bank Positions (Steps)

RCS Tamperatura('F): TAEF Test Power Level (% F.P.): 99.Jy Concitionse SDA: 225 SDB: 225 CA: 225 Other (Specify):

l (Actual)

CB : 225 CC : 225 CD:.2.1 J l Date/ Time Test Perrormea:

10/31193 l b ; '1'+

l l

l l MAX. REL NUC ENTHALITCTAL HEATIMAXIMUM POS.

IV Mens Parameter: ASSY PWR RISE HOT 1 TLUX HOT INCOEE (Description)

. DIFF ;CHANFACTlCHANFACT QUADEANT (M-P)/P l

F-dH(N)

F-Q(2)

POWER TILT l ~ 5. Gfo t. 9 Measured Valuet -5.S?,r.1 IM I NI I*

Test l

Results Design Value l ' '" '" p ' il '

(Dasign Conds )l . * *= ~

NA NA s 1.0205 VCAP-7905l lWCAP-7905 I

l Reference REV.1 SONE NONE REV.1 V

FSAR/ COLE NONE

'a*"""

NONE Acceocance, l

l COLE 2.5.1 Criteria NONE Reference NONE COLE 2.6 Design Tolerance is sec

/ YES NO Acceptanca Criteria is met V YES

,,_,,,NO VI Comments

As Required

- Must have at least 16 thimbles for quarter core saps for multi point calibrations.

O-Prepareo By:

Reviewea By:

n d

SE-963 S2C10 Startup Physics Tests Report Page 57 of 57

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