ML20087L381

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Cycle 11,Startup Physics Tests Rept
ML20087L381
Person / Time
Site: North Anna Dominion icon.png
Issue date: 08/03/1995
From: Banning P, Main A, Tyrus Wheeler
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
References
NE-1039, NE-1039-R, NE-1039-R00, NUDOCS 9508250187
Download: ML20087L381 (58)
v • d • e


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VIRGINIA Eny:crufC A'ND POWER COMI%NY Iticiix o n n,V HUINIA 20261

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August 21, 1995 United States Nuclear Regulatory Commission Serial No.95-426 Attention Document Control Desk NL&P/JDH/ CMC Washington, D. C. 20555 Docket No. 50-338 License Nos. NPF-4 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TESTS REPORT For your information, enclosed are five copies of the Virginia Electric and Power-Company Technical Report NE-1039, Revision 0, entitled " North Anna Unit 2, Cycle 11 Startup Physics Tests Report."

Should you have any questio or require additional information, please contact us.

Very truly yours, M

oler, Vic sident - Nuclear Services Enclosure cc:

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

Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station O.L 950G2bO197 95o003 PDR ADOCK 05o00338 P

PDR

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W FL TECHNICAL REPORT NE-1039 - REV. O y

L r

L.

-I

[

NORTH ANNA UNIT 2, CYCLE 11

{

STARTUP PHYSICS TESTS REPORT D

[.

NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES

{

VIRGINIA POWER AUGUST 1995

-I

[-

1 PREPARED BY:

T. L. Wheeler Date i

l D.

"1/a1/15 REVIEWED BY:

P. D. Banning.

J Date REVIEWED'BY:

/VI

' I-2-I.

~

' A. P.' Ha in Date l

ff APPROVED BY:

D. Dziao3sz

[/

Date

=

QA Category: Nuclear Safety Related Keywords: N2C11, Startup m_

-_m___.__.__m_

L F'

L CLASSIFICATION / DISCLAIMER P

L The data, techniques, information, and conclusions in this report have F

been prepared solely for use by Virginia Electric and Power Company (the L

Company), and they may not be appropriate for use in situations other than p

L those for which they have been specifically prepared.

The Company I

.refore makes no claim or warranty whatsoever, express or implied, as i

L j

to their accuracy, usefulness, or applicability.

In particular, THE r(

COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING

[

OR USAGl; 0F 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 i

herein.

In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute I

(

liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

NE-1039 N2C11 Startup Physics Tests Report Page 1 of 57

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

1 Table of Contents................

2 I

3 List of Tables................

4 List of Figures.........................................

Preface.................................................

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

7 Section 2 Control 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 Measurements...

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

39 APPENDIX Startup Physica Test Results and Evaluation Sheets........................

40 I

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I NE-1039 N2C11 Startup Physics Tests Report Page 2 of 57

I g

LIST OF TABLES TABLE TITLE PAGE F

1.1 Chronology of Tests...................................

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

18 3.1 Control Rod Bank Worth Summary........................

23 4.1 Boron Endpoints Summary...............................

28 5.1 Isothermal Temperature Coefficient Summary......

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

34

!E 6.2 Comparison of Measured Power Distribution Parameters jg W ith Their Core Operating Limits.....................

35 I

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NE-1039 N2C11 Startup Physics Tests Report Page 3 of 57

E!

-\\

I:

LIST OF FIGURES em I

FIGURE TITLE PAGE 1.1 Core Loading Map.........................................

11 1.2 Beginning of Cycle Fuel Assembly Burnups.................

12 I,

1.3 Available Incore Moveable Detector Locations......

13 1.4 Assembly Insert Locations..............

14 1.5 Control Rod Locations....................................

15 2.1 Typical Rod Drop Trace................................

19 2.2 Rod Drop Time - Hot Full Flow Conditions.................

20 3.1 Control Bank B Integral Rod Worth - HZP..................

24 3.2 Control Bank B Differential Rod Worth - HZP...

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

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

36 6.2 Assemblywise Power Distribution - 74% Power..............

37 6.3 Assemblywise Power Distribution - 1007. Power.............

38 1

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NE-1039 N2C11 Startup Physics Tests Report Page 4 of 57

[

PREFACE h

h This report presents the analysis and evaluation of the physics tests which were performed to verify that the North Anna' 2, Cycle 11 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.

Standard testing techniques and methods of data analysis were used. The test data,

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 f

results with design predictions, and an evaluation of the results.

The North Anna 2,

Cycle 11 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 h

(design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) ccmments 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 (at design conditions) of the measured parameters were completed prior to the'startup physics testing.

The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group.

During the tests, the data sheets were used as guidelines both 1

to verify that the proper test conditions were met and to facilitate che NE-1039 N2C11 Startup Physics Tests Report Page 5 ci 57

E preliminary comparison between measured and predicted test results, thus a

enabling a quick identification of possible problems occurring during the tests.

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I NE-1039 N2C11 Startup Physics Tests Report Page 6 of 57

(/

(

SECTION 1 h

[

INTRODUCTION AND

SUMMARY

p p

On March 25, 1995 Unit No. 2 of the North Anna Power Station shutdown for its tenth refueling.

During this shutdown, 73 of the 157 fuel assemblies in the core were replaced with 64 fresh fuel assemblies, 1 once-burned fuel assembly, and 8 thrice-burned fuel' assemblies.

The a

eleventh cycle core consists of 8 sub-batches of fuel: three once-burned batches, two from Cycle 10 (batches 12A, and 12B) and one from North Anna 2 Cycle 7 (batch 9A); two twice-burned batches from Cycles 9 and 10 (batches 11A and 11B); one thrice-burned batch from Cycles 4, 5, and 6 (batch 6); and two fresh batches (batches 13A and'13B).

Batches 11 and 12 have top and bottom grids of Inconel-718 while the inner six grids are made of Zircaloy-4.

Batch 13 has top.and bottom grids of Inconel-718, six inner grids made of ZIRLO (ZIRLO provides improved corrosion resistance and dimensional stability under irradiation relative to Zircaloy-4 components), and one Inconel-718 protective grJd placed below the fuel and above the bottom nozzle for debris resistance.

All other batches are composed of 8 Inconel-718 grids.

Cycle 11, similar to Cycle 10, incorporated the burnable poison rod design made of B C in Alumina, which is available in various enrichments 4

I of B C.

There are no thimble plugging devices inserted in N2C11.

I 4

Reference 1 provides a more detailed description of the Cycle 11 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.

NE-1039 N2C11 Startup Physics Tests Report Page 7 of 57

as I:

These burnups are documented in reference 6.

The available incore moveable detector locations used for the BOC flux map analyses are identified in Figure 1.3.

Figure 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 11, and Figure 1.5 identifies the location and number of control rods in the Cycle 11 On May 31, 1995 at 0516, the Cycle 11 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.

2.

Individual control rod bank worths were measured using the rod swap technique 8'

and the results were within 5.6% of the design 2

predictions. The sum of the individual measured control rod bank worths was within 1.9% of the design prediction.

These results are within the design tolerance of 15% for individual bank worths

( 10*. for the rod swap reference bank worth) and the design tolerance of 110% for the sum of the individual control rod bank worths.

3.

Measured critical boron concentrations for two control bank f

configurations were within 8 ppm 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 NE-1029 N2C11 Startup Physics Tests Report Page 8 of 57

(.

i.

i reactivity balance shall be within 1% Ak/k of the design prediction.

)

4.

The boron worth coefficient measurement was within 4.1% of the design prediction, which is within the design tolerance of 10%.

I

(

-5.

The measured isothermal temperature coefficient (ITC) for the i

all-rods-out (ARO) configuration was within 0.34 pcm/'F of the i

design prediction..This result is within the design tolerance of 13 pcm/'F.

The measured ITC of -2.93 pcm/'F meets the Core Operating Limits Report (COLR) 2.1.1 criterion that the moderator temperature coefficient (MTC) be less than or equal to

+6.0 pcm/'F.

When the Doppler temperature coefficient and a 0.5 pcm/'F uncertainty are accounted for in the MTC limit, the MTC requirement is satisfied 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 1.7% of the design predictions.

l The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot I

channel factors, F-DH(N), were within the limits of COLR Sections 2.5.1 and 2.6, respectively.

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.

NE-1039 N2C11 Startup Physics Tests Report Page 9 of 57

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5 Il Table 1.1 NORTH ANNA 2 - CYCLE'11 STARTUP PilYSICS TESTS CHRONOLOGY OF TESTS I

I Reference Test Date Time Power Procedure Hot Rod Drop - Hot Full Flow 05/30/95 1400 HSD 2-PT-17.2 Zero Power Testing Range 05/31/95 0609 HZP 2-PT-94.0 Reactivity Computer Checkout 05/31/95 0658 HZP 2-PT-94.0 Temperature Coefficient - ARO 05/31/95 1046 HZP 2-PT-94.0 Boron Endpoint - ARO 05/31/95 1028 HZP 2-PT-94.0 Bank B Worth 05/31/95 1153 HZP 2-PT-94.0 g.

Boron Endpoint - B in 05/31/95 1153 HZP 2-PT-94.0 g

Bank D Worth - Rod Swap 05/31/95 1537 HZP 2-PT-94.0 Bank C Worth - Rod Swap 05/31/95 1630 HZP 2-PT-94.0 Bank A Worth - Rod Swap 05/31/95 1701 HZP 2-PT-94.0 Bank SB Worth - Rod Swap 05/31/95 1725 HZP 2-PT-94.0 Bank SA Worth - Rod Swap 05/31/95 1805 HZP 2-PT-94.0 Flux Map - 29% Power 06/02/95 0056 29%

2-PT-94.0 Peaking Factor Verification 2-PT-21.1

& Power Range Calibration 2-PT-21.2 2-PT-22.4 Flux Map - 74% Power 06/04/95 1125 74%

2-PT-94.0 Peaking Factor Verification 2-PT-21.1

& Power Range Calibration 2-PT-21.2 2-PT-22.4 Flux Map - 100% Power 06/12/95 1016 100%

2-PT-94.0 Peaking Factor Verification 2-PT-21.1

& Power Range Calibration

  • 2-PT-21.2 g.

2-PT-22.4 g.

I

  • Power range calibration calculation was performed which verified a

that the existing calibration was satisfactory.

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NE-1039 N2C11 Startup Physics Tests Report Page 10 of 57

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l NE-1039 N2C11 Startup Physics Tests Report Page 11 of 57 r.

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NE-1039 N2C11 Startup Physics Tests Report Page 12 of 57

I Figure 1.3

{

I I

l NORTH ANNA UNIT 2 - CYCLE 11 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS l

I R

P N

M L-K J

H G

F E

D C

B A

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}

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lI ll NE-1039 N2C11 Startup Physics Tests Report Page 13 of 57

+[,,'

S Figure 1.4 l

NORTH ANNA UNIT 2 - CYCLE 11 ASSEMBLY INSERT LOCATIONS I;

R P

N N

L E

J M

C F

L 0

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A I

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l l VSDA l VSDA I VSDA I I

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  • 8 0F BP RODS or SECONDARY SOURCE ID lBPese or VSDal - BP ASSEMBLY 10 or VSDA 1

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Il NE-1039 N2C11 Startup Physics Tests Report Page 14 of 57 i

I i.

Figure 1.5 I.

NORTH ANNA UNIT 2 - CYCLE 11 CONTROL ROD LOCATIONS 11 R

P N

N L

K J

N G

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B A

I 180 1

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l l

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l Control Bank C 8

Called l Control Bank 8 8

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v Shutdown Bank SB 8

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I I

I NE-1039 N2C11 Startup Physics Tests Report Page 15 of 57

m SECTION 2 E:

l' 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 less than or equal to the maximum allowed by Technical Specification was 3.1.3.4.

The control rod drop times were measured in Mode 3' with the RCS Tavg above 500'F and all reactor coolant pumps operating. -

The rod drop times were measured by withdrawing a rod bank 229 steps and 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 determine the rod drop time.

This procedure was repeated for each control rod.

I As shown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary gripper coil fuse is removed.

As the rod drops, a voltage is induced in the IRPI primary coil.

The magnitude of this voltage is a function of control rod velocity.

As the rod enters the dashpot region of the guide tube, its velocity slows eming a voltage decrease in the IRPI coil.

This voltage reacher, a minimum when the rod reaches the bottom of the dashpot.

Subsequent variations in the trace I

are caused by rod bouncing.

NE-1039 N2C11 Startup Physics Tests Re*, ort Page 16 of 57

[

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

(

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.

l l

1 I

NE-1039 N2C11 Startup Physics Tests Report Page 17 of 57

_______-______n

g Ii Table 2.1 I.I NORTil ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

I!

I R0D DROP TIME TO DASilPOT ENTRY I!

g;

_ S1 ROD mm 1 ROO m R m 11ME B-06 1.95 sec.

C-09 1.54 sec.

1.70 sec.

I' I

I; I

I Il I;

I; I

I!

NE-1039 N2C11 Startup Physics Tests Report Page 18 of 57

I 4

Figure 2.1 NORTl! ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE I,

I I

Beoinning Of Dashoot Bottom Of Dashoot initiation Of Rod (Beginning Of First (Beginning Of First Drop Event Mark Downtum in Trace)

Uptum in Trace)

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ROD DROP TIME MEASUREMENT One Cycte I

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1

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NE-1039 N2C11 Startup Physics Tests Report Page 19 of 57

5:

Figure 2.2 NORTil ANNA UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS I

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SECTION 3 I

CONTROL R0D BANK WORTH liEASUREMENTS I

Control rod bank worths were measured for the control and shutdown banks using the rod swap technique,s.

The initial step of the rod swap r

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 movements were_ recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank.

For Cycle 11, 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 concentration were stabilized with the reactor just critical and the reference bank near full insertion.

Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position with all other banks fully withdrawn 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 inserting one 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 reference bank with the test bank fully inserted was used to determine I

NE-1039 N2C11 Startup Physics Test.s Report Page 21 of 57

I:

I; the integral reactivity worth 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 l

shutdown banks.

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

As shown in i

this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance ( 10*

for the reference bank, 15% for test banks of worth greater than 600 pcm, and 100 pcm for test banks of worth less than or equal to 600 pcm.) The sum of the individual measured rod bank worths was within 1.9% of the design 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.

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

I I-I I

NE-1039 N2C11 Startup Physics Tests Report Page 22 of 57

I I

Table 3.1 NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

I MEASURED PREDICTED PERCENT DIFFERENCE

.I WORTH WORTH

( *. )

BANK (PCM)

(PCM)

(M-P)/P X 100 I

B-Reference Bank 1287.5 1292.0

-0.3 D

1032.5 1012.0 2.0 C

838.5 794.4 5.6 A

356.5 346.0 3.0

  • I SB 1118.5 1083.0 3.3 SA 1000.5 1002.0

-0.1 Total Worth 5634.0 5529.4 1.9 I

  • Difference is less than 100 pcm.

I I

I I

I I

I

. I NE-1039 N2C11 Startup Physics Tests Report Page 23 of 57

E m'

Figure 3.1 NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1300 3 I

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NE-1039 N2C11 Startup Physics Tests Report Page 24 of 57

L Figure 3.2 NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 10.00 i.i i l i

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NE-1039 N2C11 Startup Physics Tests Report Page 25 of 57

O Il SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS

]

Boron Endpoint With the reactor critical at hot zero power, reacto: coolanc system (RCS) boron concentrations were measured at selectad rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions.

For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks

~

at or very near a selected endpolat position. Adjustments to the measured critical boron concentration values were made to account for off-nomin 1 control rod position and moderator temperature, if necessary.

The results of these measurements are given in Table 4.1.

As shown g.

3 in this table and in the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances.

The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.1.1.1.2 regarding core reactivity balance.

In summary, the boron endpoint results were satisfactory.

I Boron Worth Coefficient The measured baron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated I.'

rod worth present in the core at the time of the endpoint measurement, NE-1039 N2C11 Startup Physics Tests Report Page 26 of 57

.I I

the value of the DBW over the range of boron endpoint concentrations was

.I obtained.

A plot of the boron concentration versus inserted control rod worth is shown in Figure 4.1.

As indicated in this figure and in the Appendix, the measured DBW was -7.00 pcm/ ppm. This is within 4.1*. of the predicted value of -6.73 pcm/ ppm and is well within the design tolerance of 107..

In summary, the measured boron worth coefficient was satisfactory.

I I

I I

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I ss. _, x2c11 sta,t, ehysics 1 eses.. m rase 27 of e7

E-I Table 4.1 NORTl! ANNA UNIT 2 - CYCLE 11 STARTUP PliYSICS TESTS BORON ENDPOINTS

SUMMARY

I I

Difference (

Measured Predicted i

f Control Rod Endpoint Endpoint M-P Configuration (ppm)

(ppm)

(ppm)

ARO 2018 2011 7

B Bank In 1834 1826*

8

  • The predicted endpoint for the B Bank In configuration was l

adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown g

in the boron endpoint Startup Physics Test Results and Evaluation g.

Sheet in the Appendix.

Il l

1 51 I

I I,

I!

Il I'

l l

l NE-1039 N2C11 Startup Physics Tests Report Page 28 of 57

=

L__.-____--

I I

Figure 4.1 NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT I

I Measured DBW = -7.00 pcm/ ppm I

1400

\\

I 1200 I

N 1000 h

800

\\

k I

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\\

6 600 I

\\

=

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200 N

O 1820 1840 1860 1880 1900 1920 1940 1960 1980 2000 2020 BORON CONCENTRATION (PPM)

I NE-1039 N2C11 Startup Physics Tests Report Page 29 of 57 t

1 5

I!

SECTION 5 TE9ERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the al1-rods-out condition is measured by controlling the reactor coolant system (RCS) ll us:

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.

I Reactivity was measured during the RCS cooldown of 3.2'F and RCS heatup of 3.2'F.

Reactivity and temperature data were taken from the reactivity computer and strip chart recorders.

Using the statepoint method, the temperature coefficient was d 15rmir:ed by dividing the change in reactivity by the change in RCS terperature.

An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured ITC.

I!

The predicted and measured isothermal temperature coefficient values are compared in Tab 1e 5.1.

As can be seen from this summary and from the Startup ehysics Test Results and Evaluation Sheet given in the Appendix, I'

the measured isothermal temperature coefficient value was within the design tolerance of 3 pcm/'F. The moderator temperature coef ficient was determined to be -1.18 pcm/'F which met the requirements of COLR Section 2.1.1.

In summary, the measured result was satisfactory.

I.

li xe-1e, w2c11 Sta m,,h, sics T.sts,,o m rase

, of s,

7 L

f l.

Table 5.1 I'

NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

ISOTHERMAL TEMPERATURE COEFFICIENT BANK TEMPERATURE BORON (PCM/*F)

POSITION RANGE CONCENTRATION l

(STEPS)

('F)

(ppm)

AVE.

DIFFER.

C/D H/U MEAS.

PRED.

(M-P) 543.8 D/207 to 2018

-3.13

-2.73

-2.93 -3.27 0.34 547.0 i

t NE-1039 N2C11 Startup Physics Tests Report Page 31 of 57

5:

I SECTION 6 POWER DISTRIBUTION MEASUREMENTS W!

The core power distributions were measured using the moveable incore detector flux mapping system.

This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations.

Figure 1.3 shows the available locations monitored by the moveable detectors for the ramp to full power flux maps for Cycle 11.

For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61

~

discrete axial points by the PRODAC P-250 process computer.

Full core, three-dimensional power distributions are determined from this data using a Virginia Power modified version of the Combustion Engineering computer program, CECOR'.

CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.

a A list of the full-core flux maps taken during the startup test program and the measured values of the important power distribution parameters are given in Table 6.1.

A comparison of these measured values I.

with their COLR limits is given in Table 6.2.

Flux map 1 was taken at 29% power to verify the radial power distribution (RPD) prediction

  • at low power.

Figure 6.1 shows the measured RPDs from this flux map.

Flux maps 2 and 3 were taken at 74% and 100% power, respectively, with different 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 and 6.3.

The radial power distributions NE-1039 N2C11 Startup Physics Tests Report Page 32 of 57 l

b for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured L

relative assembly power values were generally within 1.7% of the predicted values.

Further, the measured F-Q(Z) and F-DH(N) peaking factor values P

L for the at power flux maps were within the limits of COLR Sections 2.5.1 and 2.6, respectively. Flux maps 1, 2, and 3 were used to perform power range detector calibrations (flux map 3 verified that the existing calibration was satisfactory, thus no adjustments to the power range detector calibration were required).

In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the I

accident analysis acceptance criteria, and the COLR.

It is therefore

{

anticipated that the core will continue to operate safely throughout Cycle i

11. Reference 7 documents the flux maps.

l NE-1039 N2C11 Startup Physics Tests Report Page 33 of 57

~

I TABLE 6.1 g

NORTl! ANNA UNIT 2 - CYCLE 11 STARTUP PflYSICS TESTS INCORE FLUX MAP

SUMMARY

I l

i i l

8 l

l (4) j l

l l

l l

j j j i SURN1 l

l F-Q(2) HOT l F-DHEN) H0fl CORE F(2) 1 (2) I l

i MAP lMAPI l UP l l BANK l CHANNEL FACT 0R j CHNL.FACTORI MAX l CORE T!Lil AXIAll NO.l i

DESCRIPf!ON lNO.I DATE l MWD /IPWR1 D i l

l I 0FF l OF l I

l l

l l MTU l(%)lSTLPSI ASSYl AX1 All lASSVlF*DH(MalAX!All F(lli MAX (LOCl SET lTHIMI l

i j j

j j l

(POINilF-Q(2) l l

IPOINil j

l $ (2) IBLESI LOW POWt R T 06-02-95 8

ISO lEl 35 1 2.233 E l 1.499 1 35 !!.370 131

-7.251 Y i IP.F.V, (3) j 2 106-04-951 46 l 741 192 l B071 35 l 1.975 1 5071 1.430 1 35 11.25311.0131 SEl -3.548 46 l lHu t F UL L POwE R 1 3 106-12-951 325 11001 225 l 8071 35 1 1.882 1 8071 1.417 I 35 11.20411.0111 SE1 +1.59l 66 i i

1

_1 1

1, I l_t i

8I I

1 l

1

_I 1l I.

NOIES: HDT SP0f LOCATIONS ARE SPECIFIED SV CIVING ASSEMBLY LOCATIONS (E.C. H-6 IS l'HE CENTER-OF-CDRE ASSEMBLY)

AND CORE HEICHT (IN THE "2" DIRECTION THE CORE IS DIVIDED INTO 61 AX1 AL POIMf 5 ST ARflNG FROM THE TOP OF THE CORE).

(1) F-Q(2) INCLUDES A TOT AL UNCERT AINTY OF 1.05 X 1.03.

(2) CDRE TILT - DEFINE 0 AS IHE AVERAGE QUADRANT POWER TILT FROM CECOR.

(3) P.F.V. - PEAKINC F ACTOR VERIFICATION.

(4) MAPS 1, 2, AND 1 Wf RE USED FOR POWER RANCE DETECTOR CALIBRATIONS. THE CALIBRATION FOR FLUX MAP 3 VERIFIED THE ACCEPTABILITY OF THE EXISTING CALIBRAi!ON.

I I

I I

I:

I!

Ei l

NE-1039 N2C11 Startup Physics Tests Report Page 34 of 57 j

I I

Table 6.2 NDP.TH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS I

I PEAK F-Q(Z) HOT F-Q(Z) HOT F-Dil(N) HOT CHANNEL FACTOR

  • CllANNEL FACTOR **

CHANNEL FACTOR I

(AT NODE OF MINIMUM MARGIN) l MAP NO.

MEAS.

LIMIT NODE MEAS.

LIMIT NODE MARGIN MEAS.

LIMIT MARGIN

(%)

(%)

1 2.233 4.380 35 2.233 4.380 35 49.0 1.499

'1.806 16.9 2

1.975 2.941 35 1.972 2.934 30 32.7 1.430 1.604 10.8 3

1.882 2.190 35 1.882 2.190 35 14.0 1.417 1.490 4.8

  • The Core Operating Limit for the heat flux hot channel factor, F-Q(Z), is a function of core height and power level. The value for F-Q(Z) listed above is the maximum value of F-Q(Z) in the I

core.

The COLR limit listed above is evaluated at the plane of maximum F-Q(Z).

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

minimum margin.

The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(Z) and the COLR limit for each map.

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

I I

I I

I I

NE-1039 N2C11 Startup Physics Tests Report Page 35 of 57

n L.; i W:

I Figure 6.I II NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 29% POWER P

P M

M L

K J

H C

F E

D C

8 A

PREDICTED,

. 9.263 0.274 0.262.

PPEDICTE D ME ASURE D 1

l MEAGURED 0.259. 4.270. 0.259

. PCT DIF FERENCE.

-1.6.

-1.4

-1.1.

. PCT DIFFERENCE.

. 9.300. 8.659. 1.088 0.837 1.995. 0.660 0.300

. 9.29 2 0.645, 1.070 9.825. 1.084. 0.662 0.300.

-2.7

-2.0.

-1.6

-1.4

-l.0 8.3.

-0.1 0.356. 3.170. 3.338 1.238 1.287. 1.243. 1.332. 1.171. 0.356.

. 0.337 1.135. 1.301. 1.221. 1.253. 1.225. 1.326. 3.164. 0.351.

3

-5.4

-3.0

-2.2.

-1.4

-2.7.

-1.4

-0.5.

-0.2.

-1.4 8.356. 9.856. 1.354 1.287. 1.217. 1.181. 1.219. 1.288 1.353 0.855. 0.356.

. 0.362 s.845. 1.312. 1.254. 3.189 1.138 1.2s2 1.287 1.358. 0.858 0.359.

1.6.

-1.4.

-3,0

-2.3.

-2.3.

-3.7

-1.3

-4.1.

0.3 0.3.

1.8.

0.299. 1.179 1.355. 1.318 1.209 1.143 1.155 1.143 1.208. 1.317 1.352 1.167. 0.298.

0.308. 1.246. 1.364. 1.315. 1.193 1.120. 1.143. 1.141 1.215. 1.335 1.361. 1.185. 0.306 2.9.

3.9 0.7.

-0.3

-1.3.

-2.0

-1.0.

-0.2 0.5.

1.3 0.6

'1.5 2.5

.......0.659. 1.329 1.286. 1.299. 0.987 1.153 1.161. 1.15s 0.987. 1.207 1.283. 1.323 0.654 0.668. 1.369. 1.289. 1.191 s.*ts. 1.152 1.184. 1.163. 0.999. 1.224 1.500. 1.354 0.683 6

1.4 1.5.

0.2

-1.5.

-0.7

-0.1.

2.0 1.1.

1.3.

1.4 1.4 2.4.

4.4

.......0.249. 1.098. 1.217. l.214. 4.139 1.149. 1.225 1.212 1.226. 1.152. 1.138. 1.232. 1.229 1.074. 0.245.

0.250 1.099 1.246, 1.215. 1.132. 1.145. 1.227. 1.223 1.241 1.171. 1.156. 1.225. 1.268. 1.155. 0.263.

7 9.6.

0.9.

0.8.

0.1

-0.6.

-0.4.

0.1 1.0.

1.2 1.6.

1.5.

1.1.

3.2 7.5 7.0 0.269 0.427 1.278. 1.177. 1.150. 3.159 1.211. 1.139. 1.212 1.159, 1.151 1.177. 1.278 0.827. 8.269.

0.268. 0.834. 1.291. 1.175. 1.143. 1.153. 1.210. 1.145 1.227 1.188. 1.174. 1.200. 1.318. 0.874 4.283.

-0.6.

s.8 1.0

-0.1 e.7

-0.6.

-0.1.

0.5 1.2.

2.5.

2.0.

2.9 2.6.

5.7.

5.1.

. 0.245 1.s74 1.229 1.212. 1.134 1.152. 1.226. 1.212. 1.226. 1.150. 1.139 1.214 1.237. 1.090. 0.249.

0.245. 1.072. 1.224 1.200 1.116. 1.141 1.220. 1.212. 1.233 1.162. 1.160. 1.243. 1.273. 3.133. 0.252.

-0.3.

-0.2.

0.4

-0.9.

-2.0

-1.0

-0.5.

0.0 e.6 1.s 1.9.

2.4 3.0 4.0 1.4 0.654. 1.322. 1.283. 1.267. 0.987. 1.150. 1.161. 1.154. 0.987 1.209. 1.286 1.3 29. 0.659

. 0.648. 1.305. 1.266. 1.191 8.975. 1.141. 1.153 1.155. 0.998. 1.235. 1.319. 1.369. 0.690 10

  • 0.9

-1.3. - 1. 5.

-1.4

-1.2.

-0.8.

-0.7.

8.1.

1.1.

2.2 2.6 3.0 4.8.

6.298. 1.167. 1.352. 1.317 1.208. 1.143. 1.155. 1.143. 1.209 1.318. 1.355. 1.170 0.299 0.294. 1.151 1.334. 1.303. 1.185. 1.117. 1.132. 1.137. 1.214 1.355. 1.349 1.201. 0.310 1

^

-1.3

-1.4

-1.4

-1.1.

-1.9.

-2.3.

-1.9

-0.6.

0.5 2.8.

2.5.

2.7.

3.4

. e.356 0.855. 1.353. l.288.- 1.219 1.102. 1.217. 1.288. 1.354 0.856. 0.356.

0.350 9.840. 1.326. 1.252. 1.165 1.151. 1.296 1.289 1.170 0.871. 0.362 1

-1.6.

-1.8.

-2.1

-2.8.

-4.4

-2.6.

-0.9.

8.1.

1.2.

1.7.

1.6 9.356 3.171. 1.332. 1.243. 1.287. 1.218. 1.330. 1.170 0.356.

13 9.348. 1.142. 1.293. 1.201. 1.249. 1.231. 1.324. 1.176. 0.360.

-2.2.

-2.5.

-2.9

-3.4.

-3.0.

-0.6.

-e.4 0.5.

1.0 9.300. 0.660 3.095. 0.837 1.0&&. 0.659. 0.300

. 9.292. 6.648. 1.960 0.824 1.112. 8.664 0.301.

1

-2.7

-3.0.

-3.2.

-1.6 2.2.

e.7.

0.5.

STANDARD 6.262. 9.274 9.263.

AVERACE 1

0.240. 0.267. 8.266

. PCT DIFFERENCE.

DEyl ATIDN.

1.7

=

=1.419

-8.4

-2.3 1.3.

SUMMARY

MAP NO3 N2-11-01 DATE: 06/02/95 POWER: 29.30%

CONTROL ROD POSITIONSI F-Q(Z) s 2.233 CORE TILT:

Wl D BANK AT 130 STEPS F-DHIN) s 1.499 NW 0.994 l NE 1.009 l

i F(Z) s 1.370 SW 0.963 l SE 1.013 BURNUP =

7.5 MWD /MTU A.O. =

-7.25%

2 I!

1 NE-1039 N2C11 Startup Physics Tests Report Page 36 of 57 1

J

L Figure 6.2

[

NORTIl ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION

+

747. POWER R

P M

M L

M J

H C

F E

D C

8 8

PREDICTE D

. 9.291. 0.315. 0.290.

PHEDICTED MEASURED

. 0.284. 0.302. 9.283.

MEASURED I

f

. PCT DIFFERENCE.

24

-4.2

-2.4

. PCT DIFFERENCE.

e

. 0.302. 8.u5. 1.128 0.973. 1.137. 0.6 u. 0.302.

0.294. 0.651 1.107. 0.950. 1.!!5. 0.659 0.299 2

-2.6

-2.0.

-1 9.

-2.3.

-2.0.

-1.1.

-1.1.

. 0.352. 1.119. 1.279. 1.230. 1.298 1.234 1.281 1.120. 0.352.

0.331. l.085 1.253. 1.215. 1.259. 1.210. 1.264. 1.108. 0.344 3

-5.9.

-3.0

-2.0

-1.2.

-3.0.

-2.0

-1.3.

-1.0 2.1.

0.352. 0.827 1.285. 1.243. 1.190 1.167. 1.191 1.244 1.285. 0.826. 0.351.

4.3 54. 0.812. 1.245. 1.219. 1.171. 1.135. 1.174 1.231. 1.280 0.821, 0.349 4

0.7.

  • l.8.

-3.1.

-1.9

-1 6.

-2.7.

-1.4

-1.1.

-0.4.

-0.7.

-0.5.

0.301. 1.119. 1.286 1.282. 1.210. 3.147. 1.145. 1.146 1.210 1.281. 1.284 1.116. 0.300 0.307 1.147 1.286 1.269. 1.199. 1.141. 1.144. 1.347 1.215 1.295 1.276. 1.113. 0.291.

5 1.9 2.6 0.0

-1.0.

-0.9

-0.5.

-0.1.

8.1.

0.4 1.1.

-0.6.

-0.3.

-3.2.

0. M4 1.278. 1.242. 1.210. 1.122 1.184. 1.171. 1.181. 1.122 1.209 1.240 1.273. 8.u e.

0.670. 1.291. 1.243. 1.198. 1.121. 1.193. 1.202. 1.200 1.141. 1.223. 1.245. 1.283. 0.673.

6 0.8 1.0 0.0

-1.0.

-0.2 0.8.

2.6.

1.6.

1.7.

1.1.

G.4 0.8.

1. 9.

0.275 1.131 1.228. 1.187. 1.143 1.180 1.247 1.224 1.248. 1.183. 1.143. 1.184 1.221. 1.115. 0.271.

1.242. 1.167. 0.283.

7 1.2'.5. 1.271. 1.208. 1.159. 1.188.

. 9.275. 1.135 1.236. 1.189 1.142 1.183. 1.259.

17.

1.9.

2.1.

1.4 0.3.

1.7.

4.6.

4.5.

0.0 0.4 0.6.

8.1.

-0.1.

0.3.

0.9 0.310 0.963 1.290 1.163. 1.142. 1.170. 1.224 1.154. 1.225. 1.171. 1.143. 1.163. 1.290. 0.963 0.310 0.306 0.963. 1.292. 1.163. 1.146 1.175. 1.234. 1.170. 1.250 1.213. 1.167. 1.180 1.308. 1.009. 0.322.

8

-1.4 0.0 0.2.

0.0,

0.4.

0.4 0.8.

1.4.

2.1.

3.6.

2.1.

1.4 1.4 4.8.

3.8.

. 0.271 1.115 1.221. 1.184. 1.143. 1.183. 1.247. 1.225. 1.248. 1.181. 3.143. 1.187. 1.228. 1.131. 0.275.

9.269 1.107. 1.211 1.178. 1.139 1.185. 1. 256. 1. 236. 1. 265. 1. 20 3. 1. lu. 1. 211. 1. 256. 1.1%. 0. 273.

9

-0.9.

  • 0. 7.

-0.8.

-0.6.

-0.3.

0.2.

0.7.

1.0.

1.4 1.9 2.0.

2.0.

2.2.

3.1.

-0.8.

0.uo 1.273. 1.239. 1.209 1.122. 1.181. 1.171. 1.184 1.122. 1.210. 1.242. 1.278. 9. u 4 0.650 1.247. 1.226. 1.203. 1.121. 1.188. 1.176. 1.193. 1.139 1.236. 1.270, 1.310. 0.689.

10 1.5.

-2.0

-1.1.

-0.5.

-0.1.

0.6.

0.4 0.8.

1.4 2.2.

2.2.

2.5.

3.7.

0.300. 1.116. 1.284 1.281. 1.210. 3.146 1.146. 1.147. 1.210. 1.282 1.286. 1.119. 0.302.

9.295. 1.097 1.269. 1.273. 1.200. 1.136. 1.137. 1.145. 1.214 1.319. 1.321. 1.146. 0.310 11 1.6.

-1.7.

1,2.

-0.6.

-0.8.

-0.9

-0.7.

-0.1.

0.3.

2.9.

2.7.

2.5.

2.9.

q

'l O.351. 0.826. 1.285 1.244 1.191. 3.168. 1.190. 1.244. 1.285. 0.827. 0.352.

. 0.343 0.814 1.268. 1.222. 1.360. 1.145. 1.180 1.242. 1.305. 0.858. 0.355.

12 l l

-2.2

-1.4.

-1.4

-1.7.

-2.6.

-1.9

-0.9.

-0.1 1.5.

3.7.

1.0.

l 0.352. 1.120. I.288. 1.234. 1.298 1.230. 1.279 1.119. 0.352.

- l 4.3%. 1.099 1.253. 1.200. 1.255. 1.215. 1.260. 1.120. 0.357.

13 1.6.

-1.8.

-2.2

-2.8.

-3.4

-1.2.

  • l.5.

9.2.

1. 7.

0.302. 9.u6. 1.137 0.973. 1.128. 0.u S. 0.302.

9.2 %. 0.649 1.103. 0.957 1.143. 0.u3. 0.302.

14

-2.1.

-2.5.

-3.0.

-1.7.

1.3.

-0.2.

0.0.

STANDARD 9.290. 0.315. 0.291.

evtRACE 15 DEVIATION 0.265. 0.307 0.292.

. PCT DIFFERENC2.

1.6

-8.9.

-2.7.

0.4

=

=1.255 SUNNARY MAP NO N2-11-02 DATE: 06/04/95 POWER: 74.46%

I CONTROL RCD POSITIONS:

F-QtZ) = 1.975 CORE TILT:

l D BANK AT 192 STEPS F-DHIN) s 1.430 HW 0.995 l NE 1.004 I

FtZ)

= 1.255 SW 0.989 l SE 1.015 BURNUP = 45.8 MWD /MTU A.C. = -3.54%

NE-1039 N2C11 Startup Physics Tests Report Page 37 of 57

~

n ims.

E Figure 6.3 NORTH ANNA UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER l

R P

N N

L K

J H

G F

E D

C 8

A PREDICTED PREDICTED 0.300. 0.329 0.299 NE ASURE D 0.295. 0.323. 0.295.

nfasuRED.

. PCT DIFFERENCE.

-1.9

-1.9

-1.6.

. PCT DIFFERE NCE.

0.304 0.666. 1.131. 1.008 1.138. 0.667. 0.305.

. 0.297. 0.652 1.110. 0.984. 1.121. 0.669 0.304.

-2.6.

-2.0.

-1.9

-2.4

-1.6 0.3.

-0.1.

. 0.352 1.099. 1.260. 1.220. 1.296 1.224. 1.261 1.100. 0.352.

0.339 1.067. 1. 2 34 1.703. 1.247 1.202. 1.252 1.096. 0.351 3

-3.6.

-2.9

-2.0.

-1.4

-3.8.

-1.8.

-0.7

-0.4.

-0.2.

0.352. 0.820 1.263 1.229, 1.185. 1.163 1.184. 1.230. 1.264. 0.820 0.352.

0.352 0.804. 1.217. 1.205. 1.168 1.134. 1.172 1.224 1.262. 0.813 0.349

-0.1.

-1.9.

-3.7. - 1. 9.

-1.3

-2.5

-1.1.

-0.5.

-0.2

-0.8.

-0.7 0.304. 1.099 1.265. 1.270. 1.215. 1.151. 1.148. 1.151. 1.215 1.269 1.263. 1.097 0.303.

0.307. 1.113. 1.263. 1.267. 1.210 1.158 1.153. 3.155 1.221 1.278. 1.242. 1.091 0.302.

0.9.

1.3.

-0.2

-0.2.

-0.4 0.7 0.4 0.4 0.5

0. 7.

-1.7

-0.6.

-0.2.

............... 1.228 1.215 1.168. 1.198 1.178 1.196. 1.168 1.215. 1.225 1.255. 0.661.

0.666. 1.259 0.668 1.264 1.223 1.195 1.166. 1.213. 1.215. 1.217. 1.184 1.224 1.224. 1.261. 0.674 0.3.

0.4 0.4

-1.6

-0.1.

1.2.

3.1.

1. 7.

1.4 0.8.

0.0

0. 5.

2.0 0.283. 1.133 1.239. 1.181. 1.148. 1.195 1.255 1.232. 1.256. 1.198. 1.248. 1.179. 1.212. 1.118 0.280 0.284 1.133. 1.223. 1.179. 1.146. 1.200. 1.269 1.255 1.280. 1.221 1.161 1.182. 1.227. 1.165. 0.291 7

0.3 0.1.

0.3

-0.1

-0.2.

0.4 1.1.

1.9 1.9.

1.9 1.2.

0.3.

1.2.

4.2.

3.9

=

, 0.323. 0.9V8 1.288 1.159 1.145. 1.177 1.231 1.166 1.232. 1.178. 1.145 1.159 1.288. 0.998. 0.323.

0.327. 0.994. 1.277. 1.156 1.153. 1.184. 1.242. 1.183 1.2 56 1.216 1.165. 1.169. 1.288. 1.032. 0.333.

1.1.

-0.5

-0.9

-0.2 0.7.

0.6.

1.0.

1.4.

1.9.

3.3.

1.7.

0.8.

0.0.

3.3.

3.1.

9.280 1.118 1.212. 1.179 1.147 1.198 1.255. 1.232. 1.256 1.195. 1.148, 1.181. 1.219. 1.133. 0.283.

0.278. 1.106 1.!97 1.172 1.153 1.204 1.264. 1.244 1.272 1.211. 1.165. 1.196. 1.239 1.165. 0.287

-0.6 al.1

-1.3

-0.5.

0.5.

0.4 0.7 1.0

1. 2.

1.3.

1.5.

1.3.

1.6 2.9

1. 5.

. 0.661. 1.255 1.225 1.215. 1.168. 1.196 1.178 1.199. 1.168 1.215. 1.228 1.259. 0.666,

0.649 - 1.222. 1.211 1.211. 1.167. 1.199. 1.184 1.207 1.178 1.234. 1.244 1.289. 0.701.

10

-1.9

-2.6.

-1.1

-0.3.

-0.1.

0.2.

0.5 0.7 0.9 1.5.

1.3 2.3 5.3.

...s............

0.303 1.097 1.i43. 1.269 1.215 1.151. 1.148. 1.151 1.215. 1.270, 1.265. 1.099 0.304.

1 0.298. 1.080. 1.251. 1.262 1.206 1.143 1.150 1.151. 1.215. 1.300. 1.300. 1.127, 0.315.

-1.7.

-1.5

-1.0

-0.5.

-0. 7.

-0.7.

0.2.

0.0.

0.0.

2.3.

2.7.

2.5.

3.6.

0.352 0.820 1.264 1.230 1.184 1.163. 1.183. 1.229 1.264 0.820 0.352.

0.353 0.813 1.251. 1.212, 1.157. 1.146. 1.175. 1.225. 1.285. 0.865. 0.358.

0.5.

-0.9

-1.1

-1.5.

-2.3.

-1.5

-0.8

-0.3.

1.6.

5.5.

1.7.

0.352. 1.100. 1.261. 1.224 1.296 1.220 1.260 1.099. 0.352

0. 348 1.085. 1.239 1.195. 1.259. 1.205. 1.233. 1.100. 0.360 13 i

-1.2

-1.4

-1.8.

-2.3

-2.9

-1.2

-2.1.

0.0.

2.4 G.305. 0.667. 1.138 1.006. 1.131 0.666. 0.304 0.300 0.654. 1.111. 0.993. 1.144. 0.662. 0.304

  • 1.7.

-2.0

-2.4.

-1.5.

1.1

-0.5.

-0.2.

AVERAGE STANDARD 9.299 0.329 0.300.

.. PCT DIFFERENCE.

i DEVIATIDH 0.281. 0.322 0.301.

  • 1.128

-6.2.

-2.0.

0.4

=

1.4 I

SUMMARY

MAP HO: N2-11-03 DATE: 06/12/95 POWER: 100%

CONTROL RCD POSITIONS:

F-Q(Z) = 1.882 CORE TILT j

f D BANK AT 225 STEPS F-DHIN) = 1.417 NW 0.995 l NE 1.004 l

F(Z)

= 1.204 SW 0.991 l SE 1.011 BURNUP m324.5 MWD /MTU A.D. = -1.59%

B; i

NE-1039 N2C11 Startup Physics Tests Report Page 38 of 57

I E

SECTION 7 REFERENCES

1. P. D. Banning, " North Anna Unit 2, Cycle 11 Design Report",

Technical Report NE-1021, Revision 0, Virginia Power, May, 1995.

2. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
3. T. k'. Schleicher, "The Virginia Power CECOR Code Package", Technical Report NE-831, Revision 2, Virginia Power, March, 1994.
4. North Anna Unit 2 Technical Specifications, Sections 1.19, 3.1. 3.4, 3. 2. 2, 3.2.3, 3.1.1.4, 4.1.1.1. 2, and 4.2. 2. 2 and Core I

Operating Limits Report (COLR) for North Anna 2, Cycle 11 Pattern UM, Revision 0 (May, 1995) Sections 2.1.1, 2.5.1, and 2.6.

5. Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of Startup Physics Test Program - Inspector Followup Item 280, 281/88-29-01", Serial No.89-541, December 8, 1989.
6. R. F. Villaflor, " North Anna 2, Cycle 11 TOTE Calculations",

PM-605 Revision 0, May, 1995.

7. T. S. Psuik, et al, " North Anna 2, Cycle 11 Flux Map Analysis",

PM-608, Revision 0, and Addenda A and B, June, 1995.

I I

I I

. I I

il I

NE-1039 N2C11 Startup Physics Tests Report Page 39 of 57

A

+.

.-a-a

.a

~

=:

R I

g; A,,eNo1x STARTUP PIIYSICS TEST RESULTS AND EVALUATION Si!EETS I

li I

I I!

I; I

I I

I I

I Ne.1es, mc11 S _ e es,.m. T.m. e.--

e.

- - s>

I

~I NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHuti l

I Test

Description:

Zero Power Testing Range Dete:mination I

Reference Proc No / Section:. 2-PT-94.0 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature ( F): 547

.E Power Level (% F.P.): 0 5

Test 06er(specW):

Conditions SDA: 7'S SDB: 225 CA: 225 Below Nuclear Heating J

(Design)

CB: 9's CC:

CD:

III Bank Positions (Steps)

RCS Tempemture ( F): 5%8 Power Level (% F.P.): O l

Test 06er(spec @):

Conditions SDA: 225 SDB: 225 CA: 225 Below Nuclear Heating (Acmal)

CB: 225 CC: 2:25 CD: log Date/ Time Test Perfonned:

s/3il95 ceoci

.I Reactivity Computer Initial Flux i x to amps IV Background Reading Test Results I

FluxReading At U

Point ofNuclear Heating 6 X LO amps I

Zero Power i < 10 to to x to amps Testing Range I

Reference Not Applicable I

V FSAR/rech Spec Not Applicable Acceptance Criteria Reference Not Applicable l

/ YES NO Design Tolemnce is met **

j Acceptance Criteriais met" :

J YES NO VI

  • At The Just Critical Position Comments

" Design Tolemnce and Acceptance C:iteria are met if ZPTR I

is below the Point ofNuclear Heating and above background.

Prepared By: d3 d Reviewed By:

AM lg

!E NE-1039 N2C11 Startup Physics Tests Report Page 41 of 57

LT w

NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I:.

I Test

Description:

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

g II Bank Positions (Steps)

RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design)

CB:

?'4 CC:

Below Nuclear Heating CD:

I III Bank Positions (Steps)

RCS Tempemture ( F): 54 5. 7 Test Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):

h.

Conditions (Actual)

CB: 225 CC: 225 CD: 10 3 Below Nuclear Heating Date/ Time Test Performed:

SI3: 19 5 OM 5%

Measured Parameter p,= Measured Reactivity using p-computer (Description) p, = Predicted Reactivity IV Test Results pe " + H. T Measured Value p, = + 4 4.Cl g

%D = -O.cl 3

Design Value

%D = {(p, - pi)/ p,} x 100% s 4.0%

Reference WCAP 7905, Rev.1, Table 3.6 V

FSAP/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable

/ YES NO i

Design Tolerance is met Acceptance Criteria is met :

J YES NO l:

VI Comments

  • At The Just Critical Position 1

The allowable range will be set based on the above results, as well as the i

results &om the benchmark test.

6enchmark Tesv Resats -strop 9t,3 Allowable Range =

50 PM Prepared By: bOMR Reviewed By:

f E'

NE-1039 N2C11.etartup Physics Tests Report Page 42 of 57

I I

NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Critical Baron Concentration - ARO j

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

II Bank Positions (Steps)

RCS Tempemture (OF): 547

.j Test Power Level (% F.P.): ')

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

(Design)

CB: 225 CC: 225 CD: 225 Below Naclear Heating

,I III Bank Positions (Steps)

RCS Tempemture ( F): 5:47 g

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

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

(Acmal)

CB: 225 CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed-1 F/31j95 10 28 Measured Parameter l

(Desedption)

(C )% ; Critical Boron Concentration - ARO 3

j IV

'E Test Measured Value Results (Design Conditione)

(C )% =.;2018 3

Design Value I

(Design Conditions)

C, = 2011

  • 50 ppm Reference Technical Report NE-1021, Rev. 0 V

FSAR/ Tech Spec aC, x Ce s 1000 pcm l

Acceptance Criteria Reference Technical Speci5 cation 4.1.1.1.2 l

Design Tolerance is met

/

YES NO Acceptance Critedais met :

v YES NO VI l

Comments aCs = -6.68 pcm/ ppm'*

CsD = l(C )% - Col; C, is design value 3

I Prepared By: M D. M Reviewed By: M f' (A8[

g st-1o3, s2c11 see,eeg es, sic, rest, a.,e e e,e 3

e, sz

E NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Isothermal Tempemture Coefficient - ARO Reference Proc No / Section: 2-PT-94.0 Sequence Step No:

l II Bank Positions (Steps)

RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 l

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

(Design)

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

RCS Tempemture ( F): ses s -r41 Test Power Level (% F.P.): 0 g

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

E.

(Acmal)

CB: 225 CC: 225 CD: 2.o'7 Below Nuclear Heating

+

Date. Time Test Performed:

v/9i/93 lo :4<.,

Measured Parameter W

IV (Description)

(c/5 )uo ; Isothermal Tempenture Coeff-ARO Measured Value (c/so)ao = -2.9 3 pcmFF (C, = 2o6 ppm)

R ts Design Value (Actual Conditions)

(ejs )uo = - 3. 2.'7 pcmFF (Co = ao18 ppm)

Design Value (Design Conditions)

(a/S Juo = -3.33 a 3.0 pcmFF g;

(C3 = 2011 ppm) 3' Reference Technical Report NE-1021, Rev. 0 V

FSAR/COLR e/s s 3.75* pcmFF e r" = -1.75 pcmFF A cceptance Criteria Reference COLR 2.1.1, Technical Report NE-1021, Rev. 0

(

Design Tolerance is met v YES NO

(

Acceptance Criteria is met :

v YES NO VI Comments

  • Uncertainty on eTuao = 0.5 pcmFF (

Reference:

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

g Prepared By:Qd ~D Reviewed By /6~/ F /A26/~

NE-1039 N2C11 Startup Physics Tests R'eport Page 44 of 57

I

~

NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Control Bank B Worth Measurement, Rod Swap Ref. Bank l

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

(Design)

CB: moving CC: 225 CD: 225 Below Nuclear Heating I

III Bank Positions (Steps)

RCS Temperature ( F): m Test Power Level (% F.P.): 0 yg Conditions SDA: 225 SDB: 225 CA: 225 Other(specify):

(Actual)

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

II:63 Shtl9 5 Measured Parameter (Description)

Is" ; Integml Worth of Control Bank B, IV All Other Rods Out Test Results Measured Value Is* = 'M75 Design Value (Design Conditions)

Is* = 1292 e 129 pcm I

Reference Technical Report NE-1021, Rev. O g

V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis.

Criteria SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A I

Design Tolerance is met

/ YES NO VI Acceptance Criteria is met -

/ YES NO l

g Comments Prepared By: 7M 2 Ed Reviewed By: dd /~ /A#

I NE-1039 N2C11 Startup Physics Tests' Report Page 45 of 57

\\

l E";

NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 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 g

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

u (Design)

CB:

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

RCS Temperature ( F): 5% "I Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 0ther (specify):

(Acmal)

CB: 0 CC: 225 CD: 225 Below Nucle::r Heating Date/ Time Test Performed:

c h o /95 a e S3 h'

Measured Parameter (Description)

(C )Ma ; Critical Boron Concentration, Bank B In 3

IV Test Results Measured Value (Design Conditions)

(C)M3= 1sI4 3

Design Value (Design Conditions)

C = 1819 + AC P" * (10 + 129.2/lcC l) ppm 3

3 3

C = i e zG ppm 3

Reference Technical Report NE-1021, Rev. 0

(

V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable l

Design Tolerance is met v'

YES NO g'

Acceptance Cdteriais met :

/ YES NO VI aC = -6.73 pcm/ ppm Comments 3

AC Pm, (C )

- 2011 ppm 3

B I

Prepared By: /dKV[s Reviewed By:M2h l

l NE-1039 N2C11 Startup Physics Tests Report Page 46 of 57

I NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

I Test

Description:

HZP Boron Worth CoefHeient 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.): 0 I

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

(Design)

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

RCS Tempemture ( F): W7 Test Power Level (% F.P.): 0 g

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

{AC*30 CB: moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:

s/3@5 it: 53 j

Measured Parameter (Description) eC ; Baron Worth Coefficient 3

IV l

Test Results i

Measured Value eC

=

'7. 0 0 pcm/ ppm I

3 Design Value j

(Design Conditions) eC = -6.73 = 0.67 pcm/ ppm 3

Reference Technical Report NE-1021, Rev. 0 V

FSAR/ Tech Spec Not Applicable Acceptance l

i Criteria Reference Not Applicable I

Design Tolerance is met

/ YES NO Acceptance Criteriais met :

v YES NO VI

.g Comments I

Prepared By:bb Q M Reviewed By: /d/b r

I

~

NE-1039 N2C11 Startup Physics Tests Report Page 47 of 57

5 m

NORTH ANNA POWF.R STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET

(

~

I Test

Description:

Control Bank D Worth Measurement, Rod Swap Reference Proc No / Section: 2-PT-94.0 Sequence Step No:

l II Bank Positions (Steps)

RCS Temperature ( F): 547 h'

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

Other(specify):

Conditions SDA: 225 SDB: 225 CA: 225 (Design)

CB: moving CC: 225 CD: moving Below Nuclear Heating g

III Bank Positions (Steps)

RCS Tempemture ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Actual)

CB: moving CC: 225 CD: moving Below Nuclear Heating Date/Tjme, Test Performed:

5/3i/ W

/ 5~3 '?

Measured Parameter loRS ; Integral Worth of Control Bank D, (Description)

Rod Swap IV Measured Value Io"8 = 1032 6 (Adjusted Measured Critical Test Reference Bank Position = 169 steps)

Results IO12 (Adjusted Measured Critical RS Design Value Io

=

(Ac:ual Conditions)

Reference Bank Position = 169 steps)

Design Value loRS = 1011 152 pcm (Design Conditions)

(Critical Reference Bank Position = 166 steps)

Reference Technical Report NE-1021, Rev. O, VEP-FRD-36A V

FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall g

Acceptance evaluate impact of test result on safety analysis.

3 Criteria SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A h

Design Tolerance is met

/ YES NO VI Acceptance Criteria is met :

/ YES NO Comments g

n -.

E Reviewed Byhu ; h 5Vwf Prepared By:

/

7 wr i -

jy NE-1039 N2C11 Startup Physics Tests Report Page 48 of 57

.,x.,,

.: er

.u a,....,,-

,,u,..,.3.,,

.,...-..,_..n

-.u

4.

l NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

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

II Bank Positions (Steps)

RCS Tempemture ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

Below Nuclear Heating (Design)

CB: moving CC: moving CD: 225 III Bank Positions (Steps)

RCS Temperature ( F): G2 V Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other(specify):

Below Nuclear Heating (AC*2I)

CB: moving CC: moving CD: 225 Date/ Time est Performed:

i bl31 W Ml30

~

Measured Parameter Ic" ; Integral Worth of Control Bank C, (Description)

Rod Swap IV Measured Value Ic" = M6.g (Adjusted Measured Critical Test Reference Bank Position = /40 steps)

Results Design Value Ic" = 7 D 4 (Adjusted Measured Critical (Actual Conditions)

Reference Bank Position = /40 steps)

Design Value Ic" = 793 119 pcm (Design Conditions)

(Critical Reference Bank hsition = 135 steps)

Reference Technical Report NE-1021, L /. O, VEP-FRD-36A V

FSAR/I'ech Spec If Design Tolemnce is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis.

Criteria SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A I

Design Tolerance is met

[YES NO VI Acceptance Criteria is met -

t/ YES NO Comments n

n Prepared By:

Reviewed By:7A >. h f/3 /rf

/

l/

NE-1039 N2C11 Startup Physics Tests Report Page 49 of 57

-_-_-____-__n_

-m

-~ - - -

0o NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Control 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 l

Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: moving Other (specify):

(Design)

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

RCS Temperature ( F): 5%. '1 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: moving Other (specify):

(Actual)

CB: moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time]T st Performed:

l s/3 w a:m Measured Parameter 1 83 ; Integral Worth of Control Bank A, 4

(Description)

Rod Swap g

}hh8 (Adjusted Measured Critical Measured Value I RS

=

4 Te t Reference Bank Position = 92 steps)

Results

'3' 'b (Adjusted Measured Critical Design Value 1 ^8

=

4 (Actual Conditions)

Reference Bank Position = 92 steps)

Design Value I RS = 345 = 100 pcm 4

(Design Conditions)

(Critical Reference Bank Position = 84 steps)

Reference Technical Report NE-1021, Rev. O, VEP-FRD-36A V

FSAR/I'ech Spec If Design Tolerance is exceeded. SNSOC shall Acceptance evaluate impact of test result on safety analysis.

Criteria SNSOC may specify that additional testing be performed.

Reference VEP FRD-36A

/ YES NO Design Tolerance is met VI Acceptance Criteria is met :

/ YES NO Comments I'@

Reviewed By: A s h573 </7 Prepared By:

i e

g g

-- 1-c 11 e c.,,o m, z.. e.,,,,,,

=

=

=

I NORTH A.WA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

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

II Bank Positions (Steps)

RCS Tempemture ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: moving CA: 225 Other (specify):

I Below Nucfear Heating (Design)

CB: moving CC: 225 CD: 225 III Bank Positions (Steps)

RCS Tempemture ( F): A 7 I

Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: moving CA: 225 Other (specify):

l Below Nuclear Heating (Actual)

CB: moving CC: 225 CD: 225 Date/ Time Test Performed:

f/3i/W

/ ~7: 2(

Measured Parameter Is3RS ; Integml Worth of Shutdown Bank B, l

(Description)

Rod Swap IV

/ / / 6. 5~ (Adjusted Measured Critical R5 Measured Value Isa

=

Test Reference Bank Position = /83 steps)

Results Design Value IssRS = /063 (Adjusted Measured Critical (Actual Conditions)

Reference Bank Position =/03 steps)

Design Value Is3RS = 1082 162 pcm (Design Conditions)

(Critical Reference Bank Position = 177 steps)

Reference Technical Report NE-1021, Rev. O. VEP-FRD-36A l

V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis.

Criteria SNSOC may specify that additional testing be I

performed.

l Reference VEP-FRD-36A

.I

/ YES NO Design Tolerance is met VI Acceptance Criteria is met :

/YES NO Comments Prepared By-h-

Reviewed By

~~.4 MA 5~/w/ff i-i s g

"~ ~ " " - ""*' ~ ""'"

"- 31 I

J m.

NORTH ANN A POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Shutdown 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 Conditions SDA: moving SDB: 225 CA: 225 Other (specify):

g (Design)

CB: moving CC: 225 CD: 225 Below Nuclear Heating 3-III Bank Positions (Steps)

RCS Temperature ( F): i%

  • E Test Power Level (% F.P.): 0 g

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

(Acmal)

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

5l31,If(

IBO T 8

Measured Parameter I

Integral Worth of Shutdown Bank A.

SA (Description)

Rod Swap IV Measured Value Is4" = /000 2 (Adjusted Measured Critical Test Reference Bank Position = icy steps)

Results Design Value 1"=

/ CC Z-(Adjusted Measured Critical 34 (Actual Conditions)

Reference Bank Position = / C4 steps)

Design Value Isins = 1004

  • 151 pcm (Design Conditions)

(Critical Reference Bank Position = 165 steps)

Reference Technical Report NE-1021, Rev. O, VEP-FRD-36A V

FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis.

Criteria SNSOC may specify that additional testing be performed.

l~

1 k

1 Reference VEP FRD-36A

/ XES NO Design Tolerance is met VI Acceptance Criteria is met

/ YES NO l-Conunents t'

l) n n Prepared By:

Reviewed By: #~w s. M 5F'5'/ff l l

I)

NE-1039 N2C11 Startup Physics Tests Report Page 52 of 57 g

E

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k I

NORTH AN?JA POWER STATION UNIT 2 CYCLE 11 h

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET s

I Test

Description:

rotal Rod Worth, Rod Swap

[

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

II Bank Positions (Steps)

RCS Tempemture ( F): 547 I

Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: moving CA: moving Other (specify):

Below Nuclear Heating (Design)

CB: moving CC: moving CD: moving r

L III Bank Positions (Steps)

RCS Tempemture ( F): In Test Power Level (% F.P.): 0 c

Other (specify):

L Conditions SDA: moving SDB: moving CA: moving Below Nuclear Heating (Acmal)

CB: moving CC: moving CD: moving Date/ Time est Performed:

f/7/.f

//: f3 L

Measured Parameter Irow; Integral Worth of All Banks, (Description)

Rod Swap r

IV Measured Value Irow =

{(f 3 (-/

Test Results Design Value Irow = g ef, q (Actual Conditions)

Design Value Irow = 5527 = 553 pcm (Design Conditions)

Reference Technical Report NE-1021. Rev. 0, VEP-FRD-36A

(

V FSAR/rech Spec If Design Tolerance is exceeded SNSOC shall Acceptance evaluate impact of test result on safety analysis.

(

Additional testing must be performed.

Criteria Reference VEP-FRD-36A

/

f Design Tolemnce is met YES NO t

VI Acceptance Criteria is met

/ YES NO Comments

(

A 4

h h' Reviewed By: N db #v/rr Prepared By:

Y NE-1039 N2Cll Startup Physics Tests Report Page 53 of 57

...-7--~..

O

/

f'} i NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET g

Test

Description:

M/D Flux Map - At Power g,

I Reference Proc No / Section: 2-PT-94.0,2-PT-21.1, 2-PT-21.2 Sequence Step No.

3 II Bank Positions (Steps)

RCS Temperature ( F): Tur* 1 l

Power Level (% F.P.): s30 Test Other (specify):

Conditions SDA: 225 SDB: 225 CA: 225 Must have z 38 thimbles" CD:

(Design)

CB: ??S CC:

III Bank Positions (Steps)

RCS Temperature ( F): Teeq-Power Level (% F.P.): 29.3 E

Test W.

Other (specify):

Conditions SDA: 225 SDB: 225 CA: 225

'V f-T4 ='h (Actual)

CB: 225 CC: 225 CD: I3o Date/ Time Test Performed:

G /2./45' oo:SG Max. Relative Nuclear Enthalpy Rise Total Heat Flux Maximum Measured Assembly Hot Channel Hot Positive Power Factor ChannelFactor Incore g.

% DIFF FAH(N)

Fn(Z)

Quadrant g,

Parameter (Description)

Power Tilt yy (M-P)/P El st

~ 8 'M*"" 9 esu}ts

,.7,3. f.c h >,o.9

/. 'f 9 9 Z.2.53 l.c132 E-Measured Value Design Value

  • 10% for Pa.9 N/A N/A s1.0205 o
  • 15% for P,<0.9 (Design Conds)

(P, = assy pwr)

Reference WCAP-7905 None None WCAP-7905 g

Rev.1 3

Rev.I V

FSAR/COLR None F AH(N)st.49(1+03(1-P))

Fa(2)s438'K(Z)

None Acceptance Reference None COLR 2.6 COLR 2.5.1 None Criteria Design Tolerance is met

<YES NO Acceptance Criteriais met :

v'YES NO 3

Comments

  • As required
  • Must have at least 16 thimbles for quarter core maps -

for multi-point calibrations Prepared By:

W Reviewed By 6

I!

NE-1039 N2C11 Startup Physics Tests Report Page 54 of 57 I:

L r

l L

(j NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET f

I Test

Description:

M/D Flux Map - At Power f

Reference Proc No / Section: 2-PT-94.0,2-PT-21.1, 2-PT-21.2 Sequence Step No:

(

II Bank Positions (Steps)

RCS Temperature ( F): Tur 1 l

Test Power Level (% F.P.): 65sPs75 l

[

Conditions SDA: 225 SDB: 225 CA: 225 Other(speci&):

Must have a 38 thimbles" (Design)

CB: 225 CC: 225 CD:

(

III Bank Positions (Steps)

RCS Temperature ( F): r,.d-:l Test Power Level (% F.P.): ng 1,.

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

Conditions (Acmal)

CB: 225 CC: 225 CD: I92.

q4, TMIt.5 Date/ Time Test Performed:

b l4}c13T ll25 Max. Relative Nuclest Enthalpy Rise Total Heat Flux Maximum

[

Measured Assembly Hot Channel Hot Positive Parameter Power Factor Channel Factor Incore (Description)

% DIFF FAH(N)

Fo(Z)

Quadrant yy (M-P)/P Power Tilt

[

    • "Wa9 Measured value R

ts l.M5 1,o o'7

- 8.w.. RPD4c.cl 1,4 30 99 N/A N/A s1.0204 Design Value

  • 10% for P 0

(Design Conds)

  • 15% for P,<0.9 (P = assy pwr)

Reference WCAP-7905 None None WCAP-7905 Rev.1 Rev.I V

FSAR/COLR None F AH(N)sl A9(1+03(1-P))

Fo(Z)s2.19/P ' K(Z)

None Acceptance Criteria Reference None COLR 2.6 COLR 2.5.1 None Design Tolerance is met X YES NO Acceptance Criteriais met -

E Y E S.

NO Comments

  • As required

" Must have at least 16 thimbles for quarter core maps for multi-point calibrations Prepared By:hM. O b Reviewed By:

m NE-1039 N2C11 Startup Physics Tests Report Page 55 of 57

0:

O' NORTH ANNA POWER STATION UNIT 2 CYCLE 11 gi 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, 2-PT-21.2 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature ( F): Tag 1

Power Level (% F.P.): 95sPsf00 Test Conditions SDA: 225 SDB: 225 CA: 225 Other (specify).

g Must have a 38 thimbles" u

(Design)

CB: 225 CC: 225 CD:

III Bank Positions (Steps)

RCS Tempemture ( F): Sve) 3(r,.Q li Test Power Level (% F.P.): 99.99 /,

)

Other (specify):

Conditions SDA: 225 SDB: 225 CA: 225 (Actual)

CB: 225 CC: 225 CD: 2,25 Date/ Time Test Performed:

)

c,- n -9 s / io#4 m a.ru o o Max. Relative Nuclear Enthalpy Rise Total Heat Flux Maximum Measured Assembly Hot Channel Hot Posmve Parameter Power Factor Channel Factor Incore 9"*#*"*

@*5""F*i ")

Power Tilt IV (M-P)/P Test Measured value 41>F"

'9 Results i.4,7 i,g g2 g,ogg;

,a, p 1 0 Design Value

  • 10% for P,30.9 N/A N/A s1.0204
  • 15% for P,<0.9 (Design Conds)

(P, = assy pwr)

Reference WCAP. 7905 None None WCAP-7905 Rev.!

Rev.I V

FSAR/COLR None F AH(N)s t.4Hl+0.3(1-P))

F,(Z)s2.19/P

  • K(Z)

None Acceptance Reference None COLR 2.6 COLR 2.5.1 None Criteria Design Tolerance is met X YES NO l

Acceptance Criteria is met :

Y YES NO Comments

  • As required

" Must have at least 16 thimbles for quarter core maps for multi-point calibrations N. lbAA Prepared By: [27/@[h/

Reviewed By:

/

NE-1039 N2C11 Startup Physics Tests Report Page 56 of 57

NORTH ANNA POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

I Test

Description:

RCS Flow Measurement Reference Proc No / Section: 2-PT-27 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature ( F):Ta r 1

Test Power Level (% F.P.): 95sPs100 Other (specify):

Conditions SDA: 225 SDB: 225 CA: 225 6N-?'I

/CC%Fo -

(Design)

CB: 225 CC: 225 CD:

/

III Bank Positions (Steps)

RCS Temperature ( F):

Test Power Level (% F.P.):

Other (specify):

Conditions SDA: 225 SDB: 225 CA: 225 I

(Actual)

CB: 225 CC: 225 CD: 22r FEb E~F Ico ?. F'o u e.e Date/ Time Test Performed:

7/4/95 A + 0820 - 091o Measured Parameter Frow; Total RCS Flow Rate (Description)

IV Measured Value Frow =

3o5',v/( 6/'k/

Test Results Design Value Not Applicable (Actual Conditions)

Design Value Not Applicable (Design Conditions)

Reference Not Applicable V

FSARfrech Spec Frow a 275300 gpm Acceptance Criteria Reference Technical Specification 3.2.5 Design Tolerance is met

/ YES NO VI Acceptance Criteriais met :

/ YES NO I

Comments

  • As required Prepared By: hW Reviewed By:

?

I I

NE-1039 N2C11 Startup Physics Tests Report Page 57 of 57

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