ML20112E228

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Rev 0 to NE-1073, North Anna Unit 1 Cycle 12 Startup Physics Tests Rept, for May 1996
ML20112E228
Person / Time
Site: North Anna Dominion icon.png
Issue date: 05/31/1996
From: Main A, Mirilovich J, Nicholson A
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20112E194 List:
References
NE-1073, NE-1073-R, NE-1073-R00, NUDOCS 9606050191
Download: ML20112E228 (59)


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q1 North Anna

~

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JUnit 1 Cycle 12:

Startup Ph9 sics Tests: Report Y

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T INuclear Analysis andFuel NuclearEngineering & Services V

May;1996

+

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4 O

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VIRGINIA POWER

TECHNICAL REPORT NE-1073 - REY. O NORTH ANNA UNIT 1, CYCLE 12 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES VIRGINIA POWER MAY 1996 PREPARED BY:

IO' b

/.M.Mirflovich Date REVIEWED BY: d

- 5/ r/%

A. H. Nicholson Date REVIEWED BY:

8 8-ffp

'A. P.'Hain Date APPROVED BY:

fd D. DziadosY

[/

Date QA Category: Nuclear Safety Related Keywords: NIC12, Startup

i CLASSIFICATION / DISCLAIMER 1

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

The Company therefore makes no claim or warranty whatsoever, express or imp ad, 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 OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it.

By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein.

In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

NE-1073 N1C12 Startup Physics Tests Report Page 1 of 57

I TABLE OF CONTENTS 1

PAGE I

Classification / Disclaimer...............................

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

2 List of Tab1es..........................................

3 List of Figures.........................................

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

5 i

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

7 3'

ll f

Section 2 Control Rod Drop Time Measurements.........

17 Section 3 Control Rod Bank Worth Heasurements........

22

{

Section 4 Boron Endpoint and Worth Heasurements......

27 I1 Section 5 Temperature Coefficient Heasurement........

31 Section 6 Power Distribution Measurements............

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

40 APPENDIX Startup Phyrics Test Results and Evaluation Sheets........................

41 il I:

1 I

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NE-1073 NIC12 Startup Physics Tests Report Page 2 of 57

.m.

. ~.

1

,4 LIST OF TABLES 4

_ TABLE TITLE PAGE i

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

11 2.1 Hot Rod Drop Time Summary.............................

19 j

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

24 4.1 Boron Endpoints Summary...............................

29 l

5.1 Isothermal Temperature Coefficient Summa ry............

32 4

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

35 t

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

36 l

l 1

4 7

I i

T s

i NE-1073 N1C12 Startup Physics Tests Report Page 3 of 57

lI I

LIST OF FIGURES I

FIGURE TITLE PAGE 1.1 Core Loading Hap.........................................

12 1.2 Beginning of Cycle Fuel Assembly Burnups.................

13 1.3 Available Incore Moveable Detector Locations.............

14 1.4 Assembly Insert Locations................................

15 1.5 Control Rod Locations....................................

16 2.1 Typical Rod Drop Trace...................................

20 2.2 Rod Drop Time - Ilot Full Flow Conditions.................

21 3.1 Control Bank B Integral Rod Worth -

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

25 3.2 Control Bank B Differential Rod Worth -

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

26 4.1 Boron Worth Coefficient..................................

30 6.1 Assemblywise Power Distribution - 30% Power..............

37 6.2 Assemblywise Power Distribution - 74% Power..............

38 6.3 Assemblywise Power Distribution - 1007. Power.............

39 i

i I

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I NE-1073 NIC12 Startup Physics Tests Report Page 4 of 57

PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the North Anna Unit 1, Cycle 12 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 results with design predictions, and an evaluation of the results.

The North Anna Unit 1, Cycle 12 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results.

Each data sheet provides the following information:

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

These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values (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 NE-1073 NIC12 Startup Physics Tests Report Page 5 of 57

I I

to verify that the proper test conditions were met and to facilitate the preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests.

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Il NE-1073 NIC12 Startup Physics Tests Report Pgge 6 of 57

(

2 t

SECTION 1 j

l-INTRODUCTION AND

SUMMARY

4 i

On February 11, 1996 Unit No. 1 of the North Anna Power Station I

shutdown for its eleventh 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 twice-burned fuel assemblies.

The twelfth cycle core consists of 8 sub-batches of fuel:

three once-burned batches, two from Cycle 11 (batches 13A and 13B) and one from North Anna i

Unit ' 2, Cycle 9 (batch N2/11B); three twice-burned batches, two from-Cycles 10 and 11 (batches 12A and 12B) and one from Cycles 9 and 10 (batch I

11B), and two' fresh batches (batches 14A and 14B). Batches N1/11, N1/12 and N2/11 have top and bottom grids of Inconel-718 while the inner six grids are made of Zircaloy-4. Batches N1/13 and N1/14 have top and bottom grids of Inconel-718, six inner grids made of ZIRLO (ZIRLO provides improved corrosion resistance and dimensional stability under irradiation 4

relative to Zircaloy-4 components), and one Inconel-718 protective grid ll l

placed below the fuel and above the bottom nozzle for debris resistance.

Cycle 12, similar to Cycle 11, incorporated the burnable poison rod design made of B C in Alumina, which is available in various enrichments 4

k of B C.

There are no thimble plugging devices inserted in N1C12.

Due 4

to the conversion of the core barrel by pass flow from downflow to upflow during the NIC11/NIC12 refueling outage, no baffle clips were necessary

?

In N1C12 (to help protect against baffle jetting degradation). There are 28 vibration suppression damping assemblies inserted in peripherally i

NE-1073 N1C12 Startup Physics Tests Report Page 7 of 57

g Il loaded fuel assemblies that have non-rotated Zircaloy-4 grids. Reference 1 provides a more detailed description of the Cycle 12 core.

The core loading pattern and the design parameters for each sub-batch E'

are shown in Figure 1.1.

Fuel assembly burnups are given in Figure 1.2 and documented in Reference 6.

The available incore moveable detector locations used for the 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 12, and Figure 1.5 identifies the location I

and number of control rods in the Cycle 12 core.

On March 10, 1996 at 23:51, the Cycle 12 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.

l 2.

Individual control rod bank worths were measured using the rod swap technique and the results were within 2.9% 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 115% for individual bank worths

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

Il 3.

Measured critical boron concentrations for two control bank configurations were within 6 ppm of the design predictions. These NE-1073 N1C12 Startup Physics Tests Report Ppge 8 of 57

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 0.3% of the design prediction, which is within the design tolerance of 110%.

5.

The measured isothermal temperature coefficient (ITC) for the all-rods-out (ARO) configuration was within 0.60 pcm/'F of the design prediction.

This result is within the design tolerance

(

of 13 pcm/'F.

The measured ITC of -2.60 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 cure power distribution was within 1.5% of the design predictions.

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.

NE-1073 NIC12 Startup Physics Tests Report Pege 9 of 57

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

I I

In summary, all startup physics test results were acceptable.

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

Il Il I:

I I

I I!

I I

Il I

I I

I NE-1073 NIC12 Startup Physics Tests Report Page 10 of 57

l Table 1.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PilYSICS TESTS CHRONOLOGY OF TESTS I

I Reference Test Date Time Power Procedure I

Hot Rod Drop - Hot Full Flow 3/10/96 1110 HSD 1-PT-17.2 Zero Power Testing Range 3/11/96 0126 HZP 1-PT-94.0 Reactivity Computer Checkout 3/11/96 0236 HZP 1-PT-94.0 I

Temperature Coefficient - ARO 3/11/96 0612 HZP -

1-PT-94.0 Boron Endpoint - ARO 3/11/96 0615 HZP 1-PT-94.0 Bank B Worth 3/11/96 0759 HZP 1-PT-94.0 Doron Endpoint - B in 3/11/96 1200 IlZP 1-PT-94.0 Bank D Worth - Rod Swap 3/11/96 1259 HZP 1-PT-94.0 Bank C Worth - Rod Swap 3/11/96 1345 HZP 1-PT-94.0 I

Bank A Worth - Rod Swap 3/11/96 1418 HZP 1-PT-94.0 Bank SB Worth - Rod Swap 3/11/96 1451 HZP 1-PT-94.0 Bank SA Worth - Rod Swap 3/11/96 1524 HZP 1-PT-94.0 Flux Map - 30% Power 3/12/96 0845 30%

1-PT-94.0 I

Peaking Factor Verification 1-PT-21.1

& Power Range Calibration

  • 1-PT-21.2 1-PT-22.4 Flux Map - 74% Power 3/13/96 1034 74%

1-PT-94.0 Peaking Factor Verification 1-PT-21.1

& Power Range Calibration

  • 1-PT-21.2 1-PT-22.4 Flux Map - 100% Power 4/01/96 0825 100%

1-PT-94.0 Peaking Factor Verification 1-PT-21.1

& Power Range Calibration 1-PT-21.2 1-PT-22.4 I

  • Power range calibration calculation was performed which verified that the existing calfbration was satisfactory.

I I

NE-1073 N1C12 Startup Physics Tests Report Page 11 of 57

I I

Figure 1.1 NORTH ANNA UNIT 1 - CYCLE 12 CORE LOADING MAP a

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I NE-1073 NIC12 Startup Physics Tests Report Page 12 of 57

Figure 1.2 NORTH ANNA UNIT 1 - CYCLE 12 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R

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l NE-1073 NIC12 Startup Physics Tests Report Page 13 of 57

I 4

ll' Figure 1.3 NORTH ANNA UNIT 1 - CYCLE 12 AVAILABLE INCORE HOVEABLE DETECTOR LOCATIONS Jll R

P M

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F E

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I NE.10,3 s1c m sm e,e,, m T..m m e s,

Figure 1.4 NORTH ANNA UNIT 1 - CYCLE 12 ASSEMBLY INSERT LOCATIONS R

P N

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F E

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a a

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j NE-1073 N1C12 Startup Physics Tests Report Page 15 of 57

i:

I Figure 1.5 NORTH ANNA UNIT 1 - CYCLE 12 CONTROL ROD LOCATIONS i

j R

P N

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H C

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a A

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Control sank C 8

Control sank a 8

Control sank A 8

slwidown sank s8 8

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I I'

I I

NE.1 m N1cm se._,e,,ses1.ms

.,m 1e - 5,

SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS I

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 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.

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

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

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

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

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

Subsequent variations in the trace are caused by rod bouncing.

]

NE-1073 NIC12 Startup Physics Tests Report Ppge 17 of 57

. ~_

I 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 Specificat'.on 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.

In addition, red bounce was observed at the end of each trace which demonstrated that no control rod stuck in the dashpot region.

I I

I I

I I

I I

I I

NE-1073 N1C12 Startup Physics Tests Report Page 18 of 57

4 Table 2.1 l

^

NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME 4

4 B-06 2.03 sec.

C-09 1.58 sec.

1.73 sec.

(

f I

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1 4

l 4

\\

i NE-1073 N1C12 Startup Physics Tests Report Pgge 19 of 57 4

\\

I I

Figure 2.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE I

l 1I!

I innn Bottom Of Dashoot Bhe i. g Of Dashpot (Beginning Of F'irst Initiation Of Rod v..g Of First Drop Event Mark Downtum in Trace)

Uptum in Trace)

/

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l NE-1073 NIC12 Startup Physics Tests Report Page 20 of 57

Figure 2.2 1

NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R

P N

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NE-1073 N1C12 Startup Physics Tests Report Page 21 of 57

l I

I SECTION 3 I

1 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique ***.

The initial step of the rod swap I

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 12, Control Bank B was usec 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 near critical and the Il reference bank fully inserted.

Initial statepoint data for the rod swap maneuver were obtained with the reference bank at its fully inserted position and all other banks fully withdrawn, recording the core i

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 NE-1073 NIC12 Startup Physics Tests Report Page 22 of 57

t J

J the integral reactivity worth of the test bank.

The core reactivity, moderator temperature, and the differential worth of the reference bank I

were recorded with the reference bank at th MCP. The rod swap maneuver then was repeated in reverse such that the reference bank again was fully inserted 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 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 (110% for the reference bank,115% for test banks of worth greater than 600 pca, and 1100 pcm for test banks of worth less than or equal to 600 pcm.) The sum i

of the individual measwed rod bank worths was within 1.9% of the design prediction. This is well within the design tolerance of 110% for the sum

)

.ot' 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 seasured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.

NE-1073 NIC12 Startup Physics Tests Report Page 23 of 57 m

I I'

Table 3.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

I I

MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH

(%)

BANK (PCM)

(PCM)

(M-P)/P X 100 B-Reference Bank 1233.5 1270.0

-2.9 D

970.0 995.5

-2.6 C

781.8 783.1

-0.2 A

361.0 368.8

-2.1

  • SB 1026.4 1030.2

-0.4 g

SA 975.7 1003.1

-2.7 5

Total Worth 5348.4 5450.7

-1.9 I

g

. D m er...e 1 1e., tha. - P..

I I

I I

I I

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NE-1073 NIC12 Startup Physics Tests Report Page 24 of 57

1 Figure 3.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PlfYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER 2005 WITHDRAVN 1

e m

II l

'g 1200 s

1 EB 1,

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25 50 75 100 125 150 175 200 225 B BANK POSITION (5 steps / div)

NE-1073 NIC12 Startup Physics Tests Report P, age 25 of 57

'I I

Figure 3.2 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN l

l lI l

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NE-1073 NIC12 Startup Physics Tests Report Page 26 of 57

SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected 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 ac or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal

. control rod position and moderator temperature, if necessary.

The results of these measurements are given in Table 4.1.

As shown in this table and in the Startup Physics 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.

Boron Worth Coefficient The measured boron 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 rod worth present in the core at the time of the endpoint measurement,

-NE-1073 N1C12 Startup Physics Tests Report Page 27 of 57

I!

I the value of the DBW over the range of boron endpoint concentrations was 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 tha Appendix, the measured DBW was -6.70 pen /ppe. This is within 0.3% of the predicted value of -6.68 pcm/ ppa and is well within the design tolerance of 10%.

In summary, the measured boron worth coefficient was satisfactory.

E I

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I; I

I I

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NE-1073 NIC12 Startup Physics Tests Report Page 28 of 57

Table 4.1 NORTil ANNA UNIT 1 - CYCLE 12 STARTUP PilYSICS TESTS BORON ENDPOINTS

SUMMARY

Measured Predicted Difference I

Control Rod Endpoint Endpoint M-P Configuration (ppm)

(ppm)

(ppm) a ARO 2036 2040

-4 B Bank In 1852 1846*

6

  • The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown I

in the boron endpoint Startup Physics Tese Results and Evaluation Sheet in the Appendix.

I I

I l

]

L a

NE-1073 N1C12 Startup Physics Tests Report Page 29 of 57

g I

Figure 4.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured DBW = -6,70 pcm/ ppm 1,400 I

l 1,200 s

~

I 1,000 I

\\

=E" I

e E

I l-600 6

I e

400 3

200

~

N\\

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o 1,840 1,880 1,920 1,960 2,000 2,040 BORON CONCENTRATION (PPM)

I I

NE-1073 NIC12 Startup Physics Tests Report Page 30 of 57

SECTION 5 l

l TEMPERATURE COEFFICIENT MEASUREMENT 4

4 The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.

Reactivity was measured during the RCS cooldown of 3.4'F and RCS heatup 4

of 3.5'F.

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

Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity ' by the change in RCS temperature.

An X-Y plotter, which i

plotted reactivity versus temperature, confirmed the statepoint method d

in calculating the measured ITC.

The predicted and measured isothermal temperature coefficient values are compared in Table 5.1.

As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of 3 pcm/'F. The moderator temperature coefficient was determined to be -0.85 pcm/'F which met the requirements of COLR Section 2.1.1.

In summary, the measured result was satisfactory.

NE-1073 NIC12 Startup Physics Tests Report Pgge 31 of 57

Il I;

Table 5.1 NORTil ANNA UNIT 1 - CYCLE 12 STARTUP PilYSICS TESTS ISOTilERNAL TEMPERATURE COEFFICIENT

SUMMARY

I' I

ISOTilERMAL TEMPERATURE COEFFICIENT E

BANK TEhrt.RATURE BORON (PCM/'F) 5 POSITION RANGE CONCENTRATION (STEPS)

('F)

(ppm)

AVE.

DIFFER.

C/D ll/U MEAS.

PRED.

(M-P) 544.6 D/216 to 2036

-2.50

-2.70

-2.60 -3.20 0.60 548,1 I

I I

I I

I I

I I

I NE-1073 NIC12 Startup Physics Tests Report Page 32 of 57

i l

l SECTION 6 POWER DISTRIBUTION MEASUREMENTS 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 12.

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 8

analytic power-to-flux ratios in order to determine the power j

distribution for the whole core.

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

A comparison of these measured values with their COLR limits is given in Table 6.2.

Flux map 1 was taken at 30% power to verify the radial power distribution (RPD) predictions at low power.

Figure 6.1 shows the measured RPDs from this flux map.

Flux maps 2 and 3 were taken at 74% and 100% power, respectively, with dif ferent control rod configurations. These flux maps were taken to check at power design predictions and to measure core power distributions at i

various operating conditions.

The radial power distributions for these I

maps are given in Figures 6.2 and 6.3.

The radial power distributions NE-1073 N1C12 Startup Physics Tests Report Page 33 of 57

I I:

for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured i1 relative assembly power values were generally within 1.57. of the predicted values.

Further, the measured F-Q(Z) and F-DH(N) peaking factor values 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 maps 1 and 2 verified that the existing calibrati'n was satisfactory, thus no adjustments to the power range detector calibration were required). The flux map analyses are documented in Reference 7.

In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR.

It is therefore anticipated that the core will continue to operate safely throughout Cycle 12.

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NE-1073 NIC12 Startup Physics Tests Report Page 34 of 57

TABLE 6.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS INCORE FLUX HAP

SUMMARY

I I

l 1

1 I

(1) l I

i e

i i

i 1

l BURNI l

F-0(2) Hof F-DH(N) H0il CORE F(2) 1 (2) l l

l l

MAP MAPL l UP l 15ANK l CHANNEL FAC10R CHNL.F ACTORl MAX l CORE TILil AXIAll NO.1 l

DESCRIPTION INO.i DATE l MWD /IPWil D 1 I

l l OFF 1 OF l l

1 I i Miu l(2)l$fEPSIA$$VIAXIAll l ASSVIF-OH8 Mil AX8 All F(2)) MAX ILOCl SET ITHIMI i

l l

1 i l i

IPOINilF-0(25 l 1

lP0tMil l

l l (%) ISLESI lL - R lrl0,.,.l 5 l ni is, l w l 3 l 2.,4. l w l 5,2 l si !.,AAl 00,.l w l -4.i3l r d I P.F.V.

( 31 l 2 103 13-968 25 i Fel 213 i N06l 31 1 1.905 l N061 1.432 1 26 11.22311.00281 MW1 2,071 46 l lt#1T FULL POWER 1 3 104 01-%l 721 11001 225 l N06l 36 1 1.850 1 N06l 1.400 1 35 11.21414 008F1 NEl -2.841 46 l I

l_ I i

1I 1I 1

ll 1

1 1

1l l_1 1

NOTES: HOT SPOT LOCATIONS ARE SPECIF ED SV CIVING ASSEM0LY LOCATIONS (E.C. H-8 IS THE CENTER-OF-CORE ASSEMBLY)

AND CORE HEIGHT (IN THE "2" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROM THE Top 0F THE CORE).

(1) F-0(2) INCLUDES & TOTAL UNCERTAINTY OF 1.05 X 3.03.

1 (2) CORE TILT - DEFINED AS THE AVERACE QUADRANT POWER YlLT FROM CECOR.

(3) P.F.W.

  • PEAP ING FACTOR VERIFICATION.

1 (s.' MAPS 1, F, AND 3 WERE USED FOR POWER RANCE DETECTOR CALIBRATIONS. THE CALinRATION FOR FLUX MAPS 1 Anu 1 vtRIFIED THE ACCEPTA31LITY OF THE EXISTINC CALIMATION.

I I

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NE-1073 N1C12 Startup Physics Tests Report Page 35 of 57

I Table 6.2 lIl NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PilYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS t

ll PEAK F-Q(Z) HOT F-Q(Z) HOT F-DH(N) HOT CHANNEL FACTOR

  • CHANNEL FACTOR **

CHANNEL FACTOR (AT N0DE OF MINIMUM MARGIN) g!

MAP g'

NO.

MEAS.

LIMIT NODE MEAS.

LIMIT NODE MARGIN MEAS.

LIMIT MARGIN

(%)

(%)

1 2.246 4.380 31 2.246 4.380 31 48.7 1.512 1.805 16.2 W

2 1.905 2.956 31 1.898 2.919 26 35.0 1.432 1.606 10.8 3

1.850 2.190 36 1.850 2.190 36 15.5 1.400 1.490 6.0

  • 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 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 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

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Il NE-1073 N1C12 Startup Physics Tests Report Page 36 of 57

(

Figure 6.1 NORTH ANNA UNIT 1 - CYCLE 12 STARTUP PHYSICS TESTS

(

ASSEMBLYWISE POWER DISTRIBUTION 30% POWER R

P M

M i

K J

H C

F E

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8 A

PREDICIED

. 4.264. 4.344. e.259 PREDICTED MEASumED 0.254. 9.298. 9.255.

MEASURED 1

. PCT DIFFERENC2 2.2.

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. PCT DIFFERENCE.

. 0.354. 0.644. 1.101. 0.843. 1.109. 0.645. 4.334.

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2

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. 4.374 1.153. 1.327. 1.197. 1.250. 1.214. 1.549. 1.163. 0.566.

3 0.9.

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. O.357. 0.832. 1.291. 1.26.

1.198. 1.142. 4.199. 1.266. 1.264. 4.429. e.353.

. 0.371. e. 642. 1.241. 1.249. 1.171.' 1.146. 1.149 1.275. 1.299. 4.425. e.352.

4 3.9.

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-0.4 0.334. 1.162. 1.292'. 1.267. 1.164. 1.146. 3.144. 1.146. 1.147. 1.264. 1.245. 1.154. 8.333.

. 8.355. 1.231. 1.524 1.278. 1.1 F9. 3.115. 1.156. 1.144. 1.191. 1.265. 1.213. 1.148. e.540.

5 5.8.

5.9.

2.5.

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0.0 0.4.

0.0.

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. e.644. 1.351. 1.270. l.149. 1.029. 1.154. 1.167. 3.156. l.829. 1.187. 1.264. 1.342. 0.643.

. 0.713. 1.404. 1.293. 1.184. 1.032. 1.347. 1.183. 1.154. 1.054. 1.145. 1.255. 1.542. 0.696.

6 3.6.

3.6.

1.8.

-0.7.

8.3.

0.8.

1.4.

1.6.

0.9.

-0.1.

-0.7.

0.0,

1.4.

. 9.259 1.112. 1.228. 1.204. 1.144. 1.135. 1.224 1.222. 1.226. 1.154. 1.144. 1.197. 1.228. 1.097. 9.256.

. 0.267. 1.144. 1.274. 1.220. 1.149. 4.151. 1.219. 1.255. 1.273. 1.152. 1.139. 1.175. 1.228. 1.142. 0.265.

7 3.2.

3.3.

3.4.

1.7.

8.4.

1.3.

3.8.

2.6.

3.8.

1.2.

-4.4

-1.8.

0.0.

4.1.

3.6.

. 4.367. 0.841. 1.241. 1.182. 1.147. 1.166. 1.228. 1.224. 1.225. 1.104. 3.144. 1.143. 1.242. 0.841. 9.307.

. e.316. e. 94 7. 1.311. 1.195. 1.139 1.173. 1.240. 1.245. 1.240. 1.172. 1.137. I.1 2. 1.259. 0.940. 0.313.

8 2.8.

3.s.

2.3.

1.1.

-0.6.

e.7.

1.6.

1.4.

1. 3.

e.4.

-I.e. - 1. 7.

  • l.8.

2.0 1.7.

0.254. 1.096. 1.219. 1.196 1.142. 1.137. 1.223. 1.222. l.227. 1.137. 1.145. 1.200. 1.229. 1.113. 9.259

.. 0.262. 1.121. 1.243. 1.264. l. h 54. 1.140. 1.238. 1.224. 1.218. 1.103. 1.120. 1.173. 1.286. 1.104. 9.254.

9 2.4.

2.3.

2.0.

4.0.

-0.7.

4.3.

0.5.

e.1.

-0.7.

3.3.

-2.2.

-2.3.

-1.9.

-0.8.

-1.9.

. 0.643. 1.341. 1.263. 1.186. 1.028. 1.135. 3.167. l.839. 1.430. 1.190. 1.278 1.!52. e.644.

0.694. 1.372. 1.242. 1.196. 1.054. 1.135. 1.158. 1.122. 1.003. I.161. 1.228. 1.328. 0.673.

le 2.2.

2.3.

1.5.

0.9.

0.6.

4.0.

-0.7.

-1.5.

-2.6.

2.5.

  • 3.3.

2.4.

-2.2.

. e.333. 1.150.1.245.1.264. 1.186. 1.145. 1.144. 1.146. 1.164. 1.264. 1.292. 1.163. 0.358.

. 0.339. 1.173. 1.547. 1.249. 1.192. 1.134. 1.13e. 1.122. l.146. 1.24 5. 1. 267. 1.119. 8.331.

11 2.0.

2.0.

1.7.

2.0.

0.5.

-0.6.

al.6.

-2.1.

-3.6.

-1.8.

-2.8.

2.4.

2.1.

0.353. 0.828. 1.287. 1.266. 1.198. 1.142. 1.199. 1.267. 1.291. e.833. 8.357.

. 0. 560. 0. 644. 1. 304. 1. 266. 1.182. 1.164. 1.1 F8. 1. 24 0. 1. 212. 0. 833. 0. 3 54 12 2.1.

l.3.

1.0.

0.0.

-1.4

-1.5.

-1.7.

  • 2.1.

1.5.

e.8.

-0.9.

. 0.569. 1.162. 1.547. 1.226. l.282. 1.222. 1.547. 1.164. 0.374.

. 0.372. 1.179. 1.546. 1.215. 1.263. 1.241. 3.323. 1.146. 4.567 13 0.9.

0.7.

-0.1.

-0.9.

-1.5.

-0.9.

-1.4.

al.6.

  • 0.9.

. 0.334. 0.684 1.199 0.843. 1.101. 0.644. 8.358.

. e.34 7. 0. 645. 1.10 3. 0. 884. 1.121. 0. 641. 0. 334.

14 2.6.

c.1.

-0.5.

e.0.

l.7.

0.4.

-1.1.

STANDARD

. 9.259. 0.368. e.260 AVERAGE DEVI ATIDM

. e.254. 9.104. 6.263.

. PCT O!FFERENCE.

15 1.5 al.090

-2.0.

-e.1.

1. 3.

=

e L

Ster 1ARY NAP NO: H1-12-01 DATEI 05/12/96 POWERI 30%

CONTROL ROD POSITIONSI F-Q(Z) a 2.246 CORE TILTI D BANK AT 152 STEPS F DHIN) = 1.512 NW 1.0076 l NE 1.0007 I

F(Z)

= 1.384B SW 1.0051 l SE 0.9666 BURNUP s 5 MWD /NTU A.0. s -4.13%

I I

t i

w NE-1073 NIC12 Startup Physics Tests Report P{ ige 37 of 57 s

. ~.

I I

Figure 6.2 NORTil ANNA UNIT 1 - CYCLE 12 STARTUP PilYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 74% POWER R

P N

M L

K J

H C

F E

e C

8 A

PREDICTED

. e.244. 4.349. 4.285.

PREDICTED MEASURED

. s.278. 4.333. e.279.

MEASURED

. PCT DIFFERENCE.

-2.8.

-4.6.

2.5.

. PCT WIFFERENCE.

. 8.34 2. 0.691.1.137. 0.996.1.144. 0.692. e.342.

. 4.3%. 0.674.1.112. 0.972.1.138. e.695. 8.342.

2

-1.7.

-1.9.

-2.2. - 2.4.

al.3.

0.5.

e.2.

8.370. 1.122. 1.30 4.1.215.1.249.1.249. 1.302. 1.128. e.369

. 8.%5. 1.104. 1.278.1.196.1.2%. l.204.1.299.1.122. e.373.

3

-1.4.

-1.6.

-1.7.

-2.5.

2.6.

-1,2.

-e.2.

8.0.

8.4.

e.357. 8.414. 1.237. 1.229. 1.174 1.169. 1.175. 4.229 1.234. e.811. 0.354.

. 0.365. 0.814. 1.218. 1.212.1.152.~ 1.1%.1.165.1.233.1.2%. e.407. 4.352.

2.2.

e.e.

1. 5.

-l.4.

-1.9.

-2.8.

-0.9.

8.3.

4.1.

-0.5.

-0.5.

4.341. 1.121. 1.238 1.239. 1.167. 1 14 7. 1.134. 1.14 7. 1.184. 1. 238. 1. 234. 1.111. e. 3 57.

. e.352.1.164. 1.254.1.242. 1.101.1.133. 3.133. 1.15e. 1.192. 1.240.1.217. 3.186. e.339.

3.1.

3.8,

1.3.

e.2.

-0.5.

  • l.2.

-0.5.

(.5.

e.4.

8.2.

-1.3.

-0.5.

0.7.

. e.695. 1. 30 5. 1. 232. 1.184. 1.1%. 1 159. 1.173. 1.154. 1.135. 1.187. 1.228. 1. 294. 0.691

. 0.789. 1.332. 1.245. 1.183. 1.139. 1.174. 1.193. 1.144. 1.146. 1.169. 1.222. 1.297. 0.748 6

2.8.

2.1.

1.8.

-0.4.

e.3.

1.3.

1.7.

1.9.

1.8.

e.2.

0.5.

-e.1.

1.2.

. e.284. 1.147. 1.220. 1.175. 3.146. 1.157. 1.239. 1.228. 1.241. 1.168. 1.146. 1.173. 1.212. 1.133. 0.281.

. 0. 268. 1.164. 1.241. 1.105. 1.15e. 1.175. 1 291. l.267. 1.296. 1.162. 1.149. 1.162. 1.212. 1.165. e.288.

1.4.

1.5.

1.7.

e.9.

e.4.

1.5.

4.2.

3.2.

4.4.

1.9.

e.3.

0.9.

0.0 2.9.

2.3.

. 8.348 4.994 1.287. 1.169. 1.137. 1.173. 1.226. 1.231. 1.231. 1.174. 1.137. 1.169. 1.264. 0.994. c.148.

. e.351. 1.003. 1.297. 1.173.1.13e. 3.185.1.253.1.254.1.258.1.191.1.138. l.154.1.2M.1.004. 8.350 0.9.

0.9.

0.7.

8.4

-0.5.

1.0.

2.2.

2.2.

2.2.

1.5.

0.8.

-0.9.

-1.7.

1.4.

0.6.

. e. 281. 3.133. I.212. 1.172. 1.145. 1.154. 1. 239. 1.224. 1.241. 1.154. l.14 7. 1.176. 1.221. 1. 3 47. 0. 245.

. 9.283. 1.139 1.218. 1.175. 1.141. 1.165. 1.254. 1.242. 1.247. 1.145. 1.134. 1.164. 1.210. 1.146. 6.276.

9 e.7.

0.6.

0.5.

6.2.

-0.3.

e.6.

1.2.

1.1.

e.5.

-l.1.

-0. 7.

-1 8.

-0.9.

8.1.

-2.9.

0.691. 1.297 1.227. 1.186. I.135. 1.157. 1.173. 1.164. 1.136. 1.184. 1.232. 1.305. 0.695.

0.694. 1,300. 1.233. 1.192. 1.140 1.169. 1.177. 1.157. 1.122. 1.178. 1.234. 1.295. 0.701.

1 8.4 e.3.

8.4.

e.5.

0.5.

l.0,

0.3.

-0.3.

-1.2.

-0.9.

-1.5.

-e.7.

e.4.

8.357. 1.lle. l.233. 1.237. 1.186. 1.147. 1.134. 1.148. 1.167. 1.240.1.239. 1.121. s.341,

8.338. 1.115. 1.24 8. 1.253. 1.190. 1.145. 1.131. 1.137. 1.165. 1. 2%. 1.232. 1. !!4. e.341.

1 0.4 0.4.

e.7.

1. 3.

8.3.

-e.2.

  • e.6.
  • 1.0.

-1.4.

-0.3.

-0.5.

-0.6.

-0.4.

e.354. e all. 1.235. 1.229. 1.174. 1.169. 1.174. 1.229. 1.238. 8.814. 0.357.

. 0.354 f.815. 1.239. 1.225.1.1%. 3.155. 1.164. 1.212. 1.229. e.828. 0.352.

1 e.0.

e.4.

0.4.

-0.3.

-1.5.

-1.2.

-1.1.

-4.4

-0.7.

e.7.

-1.5.

. e.369. 1.121. 1.302. 1.219. 1.289. 1.215. 1.301. 1.!!2. 0.371.

. 0.370. 1.122. 1.295. 1.205. 1.264. 1.244. 1. 2 74. 4.149. e. 369.

13 e.2.

8.1.

-e.5.

-1.2.

-1.7.

-0.9

-2.1.

-1.2.

-0.4.

. 0. 34 2. 4.492. 1.144. 0.996. 1.137. e.691. e. 342.

. e.344 0.684. 1.131. 0.949. 1.153. 0.684. 4.338.

I e.8.

-0.6.

-1.1.

-0.7.

1.4.

-e.5.

-0.9.

STANDARD

. e.285. 8.349. e.286.

AVERAGE DEVIATION 0.273. e.346. e.288.

. PCT O!rFERENCE.

1.1

=e.928

-4.0.

-1.0.

e.9.

=

SUMMARY

MAP NO: N1-12-02 DATE: 03/13/96 POWER: 74%

CONTROL ROD POSITIONS:

F-Q(Z) = 1.905 CORE TILT:

D BANK AT 213 STEPS F DH(N) = 1.432 NW 1.0028 l NE 1.0015 I

F(Z)

1.223 SW 1.0005 l SE 0.9953 BURNUP

25 MWD /MTU A.O.=

2.07%

NE-1073 NIC12 Startup Physics Tests Report Page 38 of 57

1 l

l

\\

Figure 6.3 m

NORTil ANNA UNIT 1 - CYCLE 12 STARTUP Pl!YSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R

P N

M L

E J

H C

F E

D C

8 A

I moicrEn

. e.29e. e.355. e.2s9.

m olcrEn.

MEASURED

. e.203. e.346. e.284.

MEASUREo 1

. PCT DIFFERENCE.

-2.5.

-2.6.

1.7.

.PCr off fERENCE.

. e.347. 0.692.1.125. 0.995.1.3 50. 0.693. e.347

. e.339. e.676. l.095. e.971.1.114. 0.695. e.348.

2

-2.2.

-2.3.

-2.4.

-2.5.

-1.4.

8.3.

0.5.

. e.377. 1.113. 1. 288. 1.264. 1.281. 1.2 04 1.289. 1.112. e.376.

. e.375. 1.089. I.260.1.17e.1.239. 1.146. 1.286. 1.118. 0.394.

3

-0.4.

-2.1.

-2,2.

-2.5.

-1.3.

-1.5.

-0.3.

e.6.

4.8.

l 0.363. 0.819. 1.234. 1.221. 1.178. 1.168. 1.179. 1.221. 1. 233. e.417. e. 360.

. e.366. 0.413.1.202. 3.194. 1.154. 1.138.1.168. 1.220. 1.234. 0.014. 4.358.

4 1.0.

-0.7.

-2.6.

-1.9.

-2.1.

-2.5.

-e.9.

-0.1.

8.1. - 0. 3.

-0.6.

. e.346. 1.!!!. 1.234. 1.235. 1.20e. 1.153. 1.15e. 1.153. 1.199. 1.234.1.231.1.102. e.342.

. e.352. 1.1 %. 1.241. 1.234. 1.192 4.138. 1.148. 1.157. 1.205. 1.234. 1.293. 1.093. 0.352.

5 1.8.

2.2.

0.6.

4.2.

-0.7.

-l. 3.

-0.2.

e.4.

0.5.

0.3.

-2.5.

-0.8.

2.9

. e.695. 1. 292. 1. 223. 1.201. 1.154. 1.173. 1.175. 1.171. 1.154 1.20e.1.226.1.285. 0.692.

. e. 70 3. 1. 30 7. 1. 226. 1.186. 1.157. 1.192. 1.203. 1.198. 1.168. 1.203.1.209.1.279. e.699 6

1.1.

1.2.

e.2.

-1.3 0.3.

1.5.

2.4.

2.3.

1.3.

e.3.

-0.9.

-0.5.

0.9.

I

. 8.289 1.132. 1.205.1.179. 1.152. 3.171.1.235.1.222.1.236. 1.174. 1.152.1.177. 1.198.1.119. e.286.

e.299. 1.14 0. 1. 219. 3.183. 1.151. 1.109. 1.291. 1.266. 1.294 1.199 1.15 7. 1.165. 1.192. 1.139. e. 290.

7 0.5.

0.7.

1.2.

e.3.

-0.1.

1.5.

4.6.

3.6.

4.8.

2.2.

e.4.

-1.1.

-0.6.

1.8.

1.5.

l

. 6.354. 0.993. 1.288. 1.167. 1.149. I.175. 1.220. 1.224. 1.224. 3.176. 1.149. 1.164. 1.20e. e.993. e.354

. e.354. 0.992. 1.274.1.164.1.140. 1.187. 1.249.1.253.1.255. 1.201. 1.153. 1.156.1.251.1.083. e.357.

8 0.0.

-0.1.

-0.5.

-0.3.

-0.8.

1.0.

2.4.

2.4.

2.5.

2.1.

e.3.

-1.0.

-2.3.

1.0.

0.7.

. e.286. 1.119 1.194. 1.176. 1.151. 1.172. l.234 1.222. l.237. 1.172. 1.152. 1.179. l.205. 1.132. e.289

. 8.285. 1.114. 1.192. 1.175. 1.155. 1.182. 1.251. 1.237. 1.245. 1.163. 1.147. 1.170. 1.201. 1.148. 8.286.

9 I

-0.3.

-0.4.

-0.5.

-0.1 0.3.

e.8.

1.3.

1.2.

e.7.

-0.8.

-0.5.

-0.8.

-e.3.

1.4.

  • 1.1.

. e.692. 1.245, 1.220. 1.199. 3.153. 1.171. 1.175. 1.174. 1.155. 1.201. 1.224. 1.292. 0.695.

. 0.687 1.271. 1.219. 1.206. 1.160. 1.182. 1.179. 1.172. 1.146. 1.196. 1.208. 1.381. e.735.

le

-0.7.

-1.1.

-0.1.

0.5.

0.6.

e.9.

4.3.

-0.1.

-0.7.

-0.5.

-1.3.

0.7.

5.7.

. e.342. 1.102. 1.239. 1.234. 1.199. 1.153. 1.150. 1.154 1.20e.1.235.1.235. l.Ill. 8.346.

. e. 341. 1.101. 1. 2 35. l. 248. 1. 20 3. 1.149. 1.143. 1.14 3. 1.142. 1. 24 2. 1. 240. 1.121. e.356.

-0.3.

0.1.

e.4.

l.2.

e.3.

-0. 3.

-0.6.

-0.9.

-1.5.

e.5.

0.5.

0.9.

2.4.

. e.368. 9.417. 1.232. 1. 221. 1.178. 1.168. 1.178. l.221. 1.234. 0.419. e.363.

l

. e.367. 0.822. 1.234. 1.2 4 7. 1.158. 1.15e. 1.163. 1.205. 1.234. 0.839. e.368.

12 2.1.

e.6.

0.5.

-0.3.

-1.7.

-1.5.

-1.3.

-1.3.

e.0.

2.4.

1.4.

. e.376. 3.112. 1.289 1.204. 1.281. 1.200. 1.248. 3.!!3. 0.377.

. e.377. 1.115. 1.285. 1.189. 1.251. 1.184. 1.258. 1.102. e.378.

13 0.5.

e.3.

-0.3. - 1. 2.

-2.4.

-1.4.

  • 2.4.

-1.0.

e.5.

. e.347. 0.693. 1.138. 0.995. 1.123. 0.692. 4.347.

9.354 0.693. 1.127. 0.990. 1.131. 0.686. 9.344.

14 2.2.

0.0.

-0.3.

-0.6.

e.8.

-0.9.

-1.0.

STANDARD

. 8.249. 9.355. s.290.

AvtRAGE DEVIA!!OM e.381. 9.357. e.292.

. PCT DIFFERENCE.

15

=1.041 4.s.

e.5.

e.7.

1.2

=

I

SUMMARY

HAP N01 N1-12-03 DATE: 04/01/96 POWER: 100%

CONTROL ROD POSITIONS:

F-Q(Z) = 1.850 CORE TILT:

D BANK AT 225 STEPS F-DHIN) = 1.400 NW 0.9987 l NE 1.0017 i

FtZ)

= 1.214 SW 0.9999 l SE 0.9997 BURNUP = 721 HWD/HTU A.O. = -2.84%

NE-1073 N1C12 Startup Physics Tests Report Pgge 39 of 57

I I

SECTION 7 I

REFERENCES

1. T. S. Psuik, " North Anna Unit 1, Cycle 12 Design Report", Technical Report NE-1063, Revision 0, Virginia Power, February, 1996.
2. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
3. T. W. Schleicher, "The Virginia Power CECOR Code Package", Technical Report NE-831 Revision 3, Virginia Power, July, 1995.
4. North Anna Unit 1 Technical Specifications, Sections 1.19, l

=

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 Operating Limits Report (COLR) for North Anna 1, Cycle 12 Pattern BL, Revision 0 (February,1996) 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. J. M. Mirilovich, " North Anna Unit 1, Cycle 12 TOTE Calculations",

PM-642 Revision 0, March, 1996.

7. R. A. Hall, et al, " North Anna 1, Cycle 12 Flux Hap Analysis",

g, PM-646, Revision 0, and Addenda A and B, March-April, 1996.

5 I

8. R. T. Robins, " Reload Safety Evaluation, North Anna 1 Cycle 12 Pattern BL", Technical Report NE-1058, Revision 0, January, 1996.

I I

I I

I I

NE-1073 NIC12 Startup Physics Tests Report Page 40 of 57

I APPENDIX I

STARTUP PliYSICS TEST RESULTS AND EVALUATION SHEETS I

1 I

I I

I I

I

[

s NE-1073 N1C12 Startup Physics Tests Report Page 41 of 57

. -_=_

I l

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET g

l 1

Test osseripeon: Zaro Power Tesens Range Determination Reference Proc No/ 8ec8ere 1-PT 94.0 Sequence Step No:

l 11 Bank Posnions (Steps)

RCS Tempensture (T): 547 l

Test Power Lmel(% F.P.): 0 Condsons sDA: 22s son: 22s cA: 22s Other(specay):

l l

(Desian)

Ca: 22s CC:

CD:

Below Nucinar Heaung m

Bank Possens (Steps)

RCSTemperature (4): 5 %.9 g!

1 Test PowerLevel(% F.P.): 0 W

Constions SDA: 22s Soe: 22s CA: 225 Olhar(spedfy):

(Actual)

CB: 22s CC: 220 CD: 92 Below Nucisar Heating l'

DatarTime Test Performed:

3/st /%

o n-26 I

- Computerir

  1. empo Flux Background Roadng 1.f xio g,

IV Test Results Flur Reading At l

Point Of Nudear Hesung s =;vici amps Zero PowerTesting Range q w so-5 to iot to-5 dnps I

Reference NotApplicable V

FSAR/ Tech Spec NotApplicable Acceptance Crtteria Reference Not Apphcable Design Tolerance is met" :

V YES NO Acceptance Criteria is met":

/ YES NO M

  • Ame. lust CrMcd PosWon Comments " Design Tolerance and Acomptance Criteria are met if ZPTR g

is below the Point of Nuclear Hosting and above %.warxi.

5 Prepared By: o C % '31_

Reviewed By: bd I<

NE-1073 N1C12 Startup Physics Tests Report Page 42 of 57 Il

i NORTH ANNA POWER STATION UNIT 1 CYCLE 12 l

)

l STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l

1 Test

Description:

ReactMty Computer Checimut j

Reference Proc No / Secean-1-PT 94.0 Sequence Sten No:

11 Bank Poellions (Steps)

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

l Constions soA: 225 som: 225 cA: 225 other(specify):

l (Design) cs: 225 cc:

cD:

Below Nuclear Heating

{

111 Bank Positions (Steps)

'RCS Temperature (T): 5'T T. 1 '

Test Power Level (% F.P.): 0 Condsons soA: 225 son: 225 CA: 225 Other(specify):

)

(Actual) ca: 225 cc: 224 'co: Ha '

Below Nuclear Heating Data / Time Test Performed:

l 3/n /es oz. se Parameter p,= Measured Rescuvity using p-computer (Description) pr Predicted Reactivity l

IV i

Test l

Results Measured Value p = Fl c.m, -29 pown f

PF Fl pce, -2.3 3 pc.m l

%De 0 %, 2 5 yo Design Value

%D= {(p.- pJ/pJ x 100% s 4.0 %

l Reference WCAP 7905, Rev.1, Table 3.6 l

V FSAR/ Tech Spec NotApplicable

[

Acceptance j

Criteria Reference Not Applicable I

i Design Toleranos is met V _YES NO l

Acceptance Criteria is met :

/ YES NO l

VI

  • At The Just Crthcal Postbon l

Comments The allowable range will be set based on the above results, as well as results from the benchmark test.

Allowable Range = - 29 pc m de +50Fe.M Prepared By: M8.[

Reviewed By: NNLIL Q 1 m i

i f

.NE-1073 NIC12 Startup Physics Tests Report Page 43 of 57 3

l

I I

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS. TEST RESULTS AND EVALUATION SHEET l

I Test CW,;.: Cdtical Baron Concentration - ARO Reference Pme No /Section:

1 PT-94.0 Sequence Step No:

11 Bank Positions (Steps)

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

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

5 (Design)

CB: 225 CC: 225 CD: 225 Below Nuclear Heating l

ill Bank Positions (Steps)

RCS Temperature ( F): 649,I Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA-225 Other(specify):

a (Actua0 C8: 225 CC: 225 CD: 225 Below Nuclear Heating E

Date/ Time Test Performed:

S/lI/'t&

O 7 2. 0 Measured Parameter (Cs)"m Critical Boron Concentration - ARO (Dw' Gcs.).

v IV Test g

Results Measured Value (Cs)"g 2036 m

(Design Conditions)

I Design Value Cs= 2040

  • 50 ppm (Design Conditions)

Reference Technical Report NE-1063, Rev. 0 V

FSAR/ Tech Spec aCs x Cs* s 1000 pcm Acceptance Criteria Reference Technical Specification 4.1.1.1.2 Design Tolerance is met YES NO l

Acceptance Criteria is met :

V YES NO VI Comments aC, = -6.64 pcm/ ppm C.' = l(Q )%e-Cal; C is design value Prepared By:.

/

Reviewed Bhd A NE-1073 NIC12 Startup Physics Tests Report Page 44 of 57 I

)

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 i

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I.

Test Descriphon: Isothermal Temperature Coefiknent - ARO i

Referanos Proc No / SecSore 1-PT-94.0 M=nce Step No:

}

11 Bank Positions (Steps)

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

Conditions SDA: 225 808: 225 CA: 225 Other(specify):

i (Design)

C8: 225 CC: 225 CD: 225 Below Nuclear Heating I

Ill Bank Pooltions (Steps)

RCS Temperature (T): 594.4-59g.t Test PowerLevel(% F.P.): 0 i

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

}

(Actua0 CB: 225 CC: 225 CD 2.l G Below Nuclear Hasting I

Data /rTimel Test Performed:

3 ll 4&

O(, t 2.

i Measured Parameter (a "pno; isothermalTemperature r

l C A " --.)

Coef5cient - ARO IV Test Measured Value (a "pno = - 2 &

pcmFF r

l Results (Cs= 2 03G ppm) i Design value (Actual Conditions)

(a "pno = @qpcm8F r

i (Cs= 2.038' ppm) i r'

.. Value j

(Design Conditions)

(a " no =

-3.16

  • 3 pcm8F r

(Cs= 2040 ppm)

Reference Technical Report NE-1063, Rev. O I

V FSAR/COLR a "s 3.75 pcm&

r l

Acceptance a "= -1.75 pcmFF r

l Criteria Reference COLR 2.1.1, Tocht)ical Report NE-1063, Rev. O i

Design Toleranceis met NO 1

Acceptance Criteria is met :

YES No i

VI l

Comments ' Uncertainty on aTo = 0.5 pcm8F (

Reference:

memorandum from i

C.T. Snow tq E.J.1,0zito dated June 27.1980.)

Prepared By:. j Reviewed By:

'D. drD 1

i' NE-1073 N1C12 Startup Physics Tests Report Page 45 of 57 i

I I

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l

l Test Descrip8on: Contml Bank 8 Worth Measurement, Rod Swap Ref. Bank Reference Pm No / Secuart 1-PT-94.0 Sequence Step No:

ll Bank Positions (Steps)

RCS Temperature (T): 547 Test Power Level (% F.P.): 0 g'

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

3 (Design)

C8: movine CC: 225 CD: 225 Below Nuclear Hasting ill Bank Positions (Steps)

RCSTemperature(%: 'N8.5 l

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

l{

(Actual)

Ca: n wins cc: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:

3/llMfe 07 '5cl Measured Parameter 1 "; integralWorth Of Coritml Bank B, l

(C : AZ+.)

AB Other Rods Out Test Measured Value Is"= /235.5 Results Design Value 3

(Design Conditions) is"= 1270

  • 127 pcm Reference Technical Report NE-1063, Rev. O I

ff Design Tolerance is e SNSOCshal V

FSARTTech Spec evaluate impset of test result on safety analysis, gl Acceptance SNSOC rney specify that additional testing Criteria be perfomni Reference VEP-FRD-36A Design Tolerance is met

/ YES NO g

Acceptance Criteria is met :

/ YES NO E

VI Comments g

.n

/)

/i Prepared By:'M 3. /k-Reviewed By:

' [

/

M NE-1073 N1C12 Startup Physics Tests Report Page 46 of 57 I

_--=

1 i

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 i

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test Descriphon: Crttial Baron conoontrahon - B Bank in l

Reference Proc No / Section:

1-PT-94.0 Escuence Step Nc:

l Il Bank Positions (Steps)

RCS Temperature ('T): 547 Test Power Level (% F.P.): O Conditions sDA: 225 SDB: 225 CA: 225 other(specify):

(Design) ca:

O cc: 225 CD-225 Below Nuclear Heating

}

111 Bank Positions (Steps)

RCS Temperature ('T): 54g 3

~

i Test Power Laval(% F.P.): 0 l

Conditions sDA: 225 son: 225 CA: 225 other(specify):

(Actua0 ca:

o ec: 225 CD: 225 Below Nuclear Heating

{

Datomme Test Performed:

1 S/it 19 L 07:5cl 4

Measured Parameter (Cs)"s; Critical Baron Cere

.Li, (F::4"s.)

B Bankin IV Test Results Measured Value (Cs)"s=

18 5.2 1

j (Design Conditions) l j

Design Value Cs = 1850+ACs * * (10 + 127.0/lmCal) ppm (Design Conditiorm)

C=

)S4(o ppm i

Reference Technical Report NE-1063, htev. 0 l

V FSAR/ Tech Spec Not ApFA Lie Acceptance i

Criteria Reference Not Applicable j

Design Tolerance is met M_.YES NO i

Acceptance Crtteria is met :

V YES NO j

VI l

Comments aCs = -6.68 pcm/ ppm

}

AC * = (Cs)"m-2040 ppm 1

A Prepared By:k OM Reviewed By:

/

/

\\

t NE-1073 NIC12 Startup Physics Tests Report Page 47 of 57 1

i

I-I NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l

I Test M ' ?Mi: HZP Baron Worth CoefRcierd Measurement Reference Proc No /Section:

1-PT 84.0 Mance S;.9 No:

11 Bank Positions (Steps)

RCS Temperature M: 547 Test Power 1.svol (% F.P.): 0 g

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

5 (Design)

Ca: movino ec: 225 CD: 225 Below Nuclear W+E.s ill Bank Positions (Steps)

RCSTemperature(%: sys.3 g'

Test '

PowerLaval(% F.P.): O Corustions SDA: 225 808: 225 CA: 225 Other(specify):

(Actuno Ca: movine cc: 225 cD: 225 Below Nuclear Heating l

Data / Time Test Performed:

S/tt )9(,

e7: Sci Measured Parameter sC ;

Baron Worth Coef5cient (P 44=.)

l',

i IV Test Results Measured Value sCe = - (o, '70 I:

Design Value aCs =

-6.68 m 0.67 pcm/ ppm (Design Conditions)

Reference Technical Repest NE-1063, Rev. O V

FSAR/ Tech Spec Notp Acceptance Criteria Reference Not Applicable Design Tolerance is met V YES NO g

Acceptance Criteria is met :

V YES NO 3

VI Comments in

/9 A Prepared By:

'D M c Reviewed B :

d Y

Y A

l, NE-1073 NIC12 Startup Physics Tests Report P4ge 48 of 57 I

l l

l NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Contml Bank D Worth Measurement, Rod Swap Reference Proc No /8ection:

1.PT.ed.0 Sequence Step No:

11 Bank Poettions (Stape)

RCS Temperature (T): 547 Test Power Level (% F.P.): O Conditions SDA: 225 808: 225 CA: 225 other(specify):

(Design)

Ca:===mo oc: 225 CD: movine Below Nuclear Heating ill Bank Positions (Simps)

RCS Temperature (T): s4 7.

Test PowerLevel(% F.P.): O Conditions SDA: 225 80s: 225 CA: 225 other(specify):

(Actumf)

Cs:

mo ec: 225 Co: novins Below Nudear Heating Dalemme Test Performed:

4/o l8tG rz5,og Measured Parameter lo"; integral Worth of Control Bank D.

(Description)

Rod W IV Measured Value 1 "= MO (Ad>sted Measured Cracal Test Reference Bank Poshon = 161 steps)

Results Ce.;yi Value (Actuel Conditions) lo"= %55 (Adjusted giCracal Reference Bank Position =JVs Dee;,.. Value (Design Conditions) lo"= 995

  • 149 pcm (Crtlical Reference Bank Position = 167 steps)

Reference Technical Report NE-1063. Rev. 0.VEP-r nD 36A FSAR/ Tech Spec NDesign Toleranos is e. SNSOC shat V

evatuste impact of test result on safety analysis.

Acceptance SNSOc rney specify that additonal testmg Criteria be performed.

Reference VEP-FRD 38A Design Tolerance is met J YES NO Acceptance Criteria is met :

V YES NO VI Comments

\\

a Prepared ByM2 'M Reviewed By:

/

cv NE-1073 NIC12 Startup Physics Tests Report P(ige 49 of 57

I NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET ll 1

Test

Description:

Control Bank C Worth Measurement, Rod Swap Reference Proc No / Section-1-PT-64.0 Sequence Sten No:

11 Bank Positions (Steps)

RCS Temperature (T): 547 Test Power Laval(% F.P.): 0 g

Conditions SDA: 225 808: 225 CA: 223 Other(spoolfy):

3 (Design)

CB: movine CC: movine CD: 225 Below Nuclear Heating lli Bank Posthons (Steps)

'RCS Temperature (T): 547,2.

l Test Power Level (% F.P.): 0 Condibons SDA: 225 SDB: 225 CA: 225 Other(specffy):

(Actual)

C8: movire CC: moving CD: 225 Below Nuclear Heating l

Date/ Time Test Performed:

sht1%

1345 g

Measured Parameter ic"; integralWorth of CorWol Bank C, l

(C::_W)

Rod Swap IV Measured Value ic" = 9 51.S (A4usted Measured Catlical Test g

Reistence Bank Pooldon = iFI steps)

E Results Design Value (Actual Conditions)

Ic"= 783 I (A4usted Measured Criboni Referenos Bank Position = 8 3 I steps)

Ces;gn Value I

g (Design Conditions)

Ic"= 777

  • 117 pcm g

l (Critical Reference Bank Position = 136 steps) l Reference Technical RW NE-1063. Rev. 0,VEP-FRD-SSA FSAR/ Tech Spec if Design Tolerance is excesdod, SNSOC shas V

evatuste impset of test renun on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be periormed.

Reference VEP-FRD 36A g

Design Toleranceis met V

YES No 5

._ Acceptance Criteria is met :

d YES NO VI Comments s/1 b /7 Prepared By:

'd.

Reviewed By:

m I~ f W NE-1073 N1C12 Startup Physics Tests Report Page 50 of 57

b 1

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEei i

Test DwW : Control Bank A Worth Measurement, Rod Swap Reference Proc No/Section:

1-PT-94.0 Seguence Sten No:

ll Bank Positions (Steps)

RCS Temperature (*F): 547 Test Powerlevel(% F.P.): O Condibons SDA: 225 SDB: 225 CA: nains Other(spedy):

{

(Design)

CE: nmino CC: 225 CD: 225 Below Nuclear Hasting 111 Bank Positions (Steps)

RCS Temperature ("F): 5'Ar13 Test Power Level (% F.P.): 0

[

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

(Actual)

  • CB: navire CC: 225 CD: 225 BelowNuclear Hasting Date/Tane Test Performed:

[

s/n N, uns Measured Parameter 1 "*; integral Worth of Control Bank A, 4

(Description)

Rod ha=p m

(

IV Measured Value 1 "= W (W h N 4

Test Reference Bank Position = 8D steps)

Results De.;w Valus

.[

n (Actual Conditions) la = 3 6,b,%

(Adjusted Measured Cribcal ns Reference Bank Position = 4o steps)

[

Design Value (Design Conditions) la = 378

  • 100 pcm ns j

(Cribest Reference Bank Posibon = 89 steps)

L Reference Technical Report NE-1063. Rev. 0,VEP-FRD-36A FSAR/ Tech Spec if Design Toleranceis e, SNSOC shaR V

evniuste impact of test result on safety analysis.

Acceptance SNSOC may specify that addibonal testing Criteria be performed Reference VEP-FnD 36A Design Tolerance is met V

YES NO Acceptance Criteria is met :

V YES NO Comments

{

/) M Prepared By.-

Reviewed By:

NE-1073 NIC12 Startup Physics Tests Report Page 51 of 57

I I

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l

i Test C-,

4 Shutdown Bank 8 Worth Measurement, Rod Swap l

1 Reference Proc No / Section,

1-PT-04.0 Secuence Sten No:

11 Bank Posthons (Stepe)

RCS Temperature M: 547

{

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

3 (Design)

Ca: noving CC: 225 CD: 225 Below Nuclear Hoshng ill Bank Positions (Steps)

RCS Temperature (T): 547.q gl Test PowerLevel(% F.P.): 0 Conditions SDA: 225 SDs: noving CA: 225 Other(specify):

ll (Actual)

CB: noving CC: 225 CD: 225 Below Nuclear Heating Datamme Test Performed:

s/n/g 14:=51 Measured Parameter In"; integral Worth of Shutdown Bank B, (Des-b'A,n)

Rod W l

IV Measured Value In"= 30%.d (A4usted Measured Cdtical Test Reference Bank Position = 17 I steps)

Results Design Value (Actual Conditions)

Im"= 8030.1 (Aqusted Measured Cdhcal Reference Bank Position = 19i steps) 04n Value (Design Conditions)

In"= 1033 a 155 pcm l

(Critical Referanoe Bank Position = 173 steps)

Reference Technical Report NE-1063. Rev. 0.VEP-FRD-36A FSAR/ Tech Spec if Desgn Toleranceis ah, SNSOC shall V

evatuste impact of test result on safety analysis.

Acceptance SNSOC may specify that addthonal teshng Criteria be performed Reference VEP-FRD-36A Design Tolerance is met

/ YES NO

{

Acceptance Crtteria is met :

YES NO VI Comments n

InA P

ared By:

9.M Reviewed By:

NE-1073 NIC12 Startup Physics Tests Report Page 52 of 57 I

l NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Shutdown Bank A Worth Measurement, Rod Svap Reference Proc No / Section:

1-PT-94.0 Sequence Sten No:

I Bank Positions (Steps)

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

(Design)

CB: moving CC: 225 CD: 225 Below Nuclear Heating 111 Bank Positions (Steps)

RCS Tetperature ( F): gi,r, Test Power Level (% F.P.): 0 I

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

(Actual)

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

.to.we:ot ow, scr2+

Measured Parameter ns l

la ; integral Worth of Shutdown Bank A, l

(Description)

Rod Swap l

IV Measured value Im"8=

T75/7 (Adjusted Measured Critical Test Reference Bank Position = /R steps)

Results Design Value l

(Actual Conditions)

Inns = foo3.1 (Adjusted Measured Critical Reference Bank Posthon = t62. steps)

I Design Value ns (Design Conditions)

In = 1008 e 151 pcm (Critical Reference Bank Posibon = 169 steps)

Reference Technical Report NE-1063. Rev. 0.VEP-FRD-36A

{

FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall V

evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing b

Criteria be performed.

Reference VEP-FRD-36A

{

Design Tolerance is met

< YES NO Acceptance Criteria is met :

YES NO VI

[

Comments Prepared By: 4t/ 7 ud Reviewed By: 2/. b S/.,/g 7-N S NE-1073 N1C12 Startup Physics Tests Report Page 53 of 57

I I

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 gl STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1

Test C::41=i: Total Rod Worth, Rod Swap l

Reference Proc No / Section:

1-PT-94.0 Sequence Step No:

il Bank Positions (Steps)

RCS Temperature (*F): 547 gl Test Power Level (% F.P.): 0 g1 Conditions SDA: moving SDB: moving CA moving Other(specify):

(Design)

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

lll Bank Positions (Steps)

RCS Temperature (*F):

gg Test Power Level (% F.P.): 0 -

Conditions SDA: moving SD8: moving CA noving Other(specify):

l, (Actual)

CB: moving CC moving CD: moving Below Nuclear Heating DateNime Test Performed:

3-//~94 0 7 5 *1 1

Measured Parameter h.o IntegralWorth of All Banks, (Description)

Rod Swap 1

IV Measured value h.,= 6% 3,4 Test Results Design Value g

(Actual Conditions) h w=

53 $0, 3 5

l' Design Value (Design Condibons) h.,= 5461

  • 546 pcm Reference Technical R=aart NE-1063. Rev. 0,VEP-FRD 36A FSAR6sch Spec if Design Toleranceis e SNSOC shat v

evaluate impact of test result on safety analysis.

g!

Acceptance Additional testmg must be performed.

Criteria J

Reference

. VEP-FRD-36A Design Tolerance is met S

NO Acceptance Criteria is met :

YES NO g1 VI E

Comments Prepared By: Mh Reviewed By: A/'vNW 7 +/-14

>N4" NE-1073 NIC12 Startup Physics Tests Report Page 54 of 57

l NORTH ANNA POWER STATION UNIT 1 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test Des.Wc M/D Flux Map-At Power Reference Pme No / Sectkn* 1 PT-94.0,1 PT-21.1.1-PT-21.2 Sequence SteD No:

11 Bank Positions (Steps)

RCS Temperature ("F): Tny z 1 1

Test Power Level (% F.P.): s 30 Conditions SDA: 225 SDB: 225 CA: 225 Other(specify):

(Design)

CB: 225 CC:

CD:

Must have a 38 thimbles" til Bank Posthons (Steps)

RCS Temperature ( F): W Test Power Level (% F.P.):.:2M/

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

(Actual)

CB: 225 CC:.:125~ CD: /S"I-

//4 77/,,rfd>

Data / Time Test Performed:

l f//2/>/1 O CVS~~

Maximum Relative Nuclear 0W TotalHeat Maximum Measured Assemt#

Rise Hot Flux Hot Positive incore Parameter Pumer %DIFF Channel Factor Channel Quadrant IV (Description)

(M-P)/P FAH(N)

Factor Fo(Z)

PowerTilt i

Test Measured 4 f /$ 7 o.9 Resutts value S:0 A s o.1 l' &

2* 3 VS

/* 0 5 Design Value a10% for Pa a0.9 (Design a15% for P 4.9 N/A N/A s1.a213 Conditions)

(Paa essy power)

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

FSAR/COLR None FAH(N)st.49(1+0.3(1.P))

Fo(Z)s4.38*K(z)

None I

Acceptance Criteria Reference None COLR 2.6 COLR 2.5.1 None l

Design Tolerance is met

/ YES NO Acceptance Criteria is met :

,/YES NO VI

  • As required Comments

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

[

Prepared By:

Reviewed By:

a_

ett

- r

~

NE-1073 NIC12 Startup Physics Tests Report Page 55 of 57 Y*

E je I

)

NORTH ANNA POWER STATION UNIT 1 CYCLE 12 g

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 4

i Test

Description:

M/D Flux Map - At Powe,r i

Reference Proc No / Sechon: 1.PT-94.0.1 PT-21.1.1-PT-21.2 Secuence Step No:

11 Bank Positions (Steps)

RCS Temperature (*F): Tns,e 1 Test Power Level (% F.P.):65 s P s 75 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

~

(Design)

CB:

225 CC: 225 CD:

Must have a 38 thimbles **

l 111 Bank Positions (Steps)

RCS Temperature (T:J Tiysp.

i Test Power Level (% F.P.): 7ef.or %

Conditions SDA: 225 SDB: 225 CA: 225 Other(specify): *((, f4imbles l

l (Actual)

CB:

225 CC-225 CD: 213 Date/ Time Test Performed:

g

^

3113l4(,

10: 3 81 3

Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive incore Parameter Power %DIFF ChannelFactor Channel Quadrant i

IV (Description)

(M-P)/P FAH(N)

Factor Fo(Z)

PowerTBt Test Measured f5PD Ao,*l, 8{.4'1c I' I Results value RPO 4c.4.-8f.6%

El j

Design Value 410% for P a0.9 i

i (Design a15% forPa 0.9 N/A N/A s 1.020e u

c l

Conditions)

(Ps = assy power) l i

Reference WCAP-7905. Rev.1 None None WCAP-7905 j

Rev.1 V

FSAR/COLR None FAH(N)s1A9(1+0.3(1-P))

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

None 3

j Acceptance E

{

Criteria Reference None COLR 2.6 COLR 2.5.1 None I

i Design Tolerance is met V YES NO l

Acceptance Criteria is met :

I YES NO l

VI

  • As required Comments

" Must have at least 16 thimbles for quarter core maps for multi-point calibrations 1

1

.8. [

Reviewed By:

li Prepared By:

4 4

NE-1073 NIC12 Startup Physics Tests Report Page 56 of 57 I

l NORTH ANNA POWER STATION UNIT 1 CYCLE 12 l

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

M/D Flux Map - At Power Reference Proc No / Section: 1-PT 94.0.1 PT 21.1.1-PT-21.2 Sequence Step No: 37 ll Bank Positions (Steps)

RCS Temperature ("F): Tur

  • 1 Test Power Level (% F.P.):95 s P s 100 Conditions SDA: 225 SDB: 225 CA 225 Other(specify):

(Design)

CB: 225 CC: 225 CD:

Must have a 38 thimbles" 111 Bank Positions (Steps)

RCS Temperature ( F): Sto. P P Test Power Level (% F.P.):

so o.o n Y.

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

D/2.2.s (Actual)

CB: 225 CC: 225 CD:.225 l

Date/ Time Test Performed:

l 4(tl% 0 ans-Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive incore Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description)

(M-P)/P FAH(N)

Factor Fo(Z)

PowerTilt Test Measured 4.8% rw f7. 2 o.9 O

I'O /7 Results value F a % A & 4 o.9 Design Value s10% for P a0.9 (Design 15% for P <0.9 N/A N/A s 1.0209 i

Conditions)

(P = assy power) i Reference WCAP-7905. Rev.1 None None WCAP-7905, Rev.1 V

FSAR/COLR None FAH(N)s1.49(1+0.3(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 Criteria is met -

X YES NO VI

  • As required Comments

" Must have at least 16 thimbles for quarter core maps for multi-point calibrations l

1 Prepared By: /2MMYdd Reviewed By:

) Ik ('[dac2rA

[

NE-1073 N1C12 Startup Physics Tests Report Page 57 of 57

_._4 m

=.-4+

' -* 'i-"*-

""'O l

I i

l l

ENCLOSURE 2 fJORTH ANNA UNIT 1 CYCLE 11 CORE PERFORMANCE REPORT i

I i

i l

l i

l I

t i

i i

(

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