Text

Cycle 8,Startup Physics Test Rept
	ML18143B353
Person / Time
Site:	Surry
Issue date:	07/31/1985
From:	Stewart W, Woody S; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S; Office of Nuclear Reactor Regulation
References
	85-544, VEP-NOS-18, NUDOCS 8508080586
	Download: ML18143B353 (66)
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~I Surry Unit 2, Cycle 8

Startup* Physics Test Report Nuclear Operations Department

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VEP-NOS-18 SURRY UN IT 2, CYCLE 8 STARTUP PHYSICS TESTS REPORT Reviewed By:

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E. S. Hendrixson, Engineer Nuclear Fuel Ope~ation 8508080586 850731 1

PDR ADOCK 05000281 P

PDR by S. B. Woody Approved By:

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C. T. Snow, Supervisor Nuclear Fuel Operation Operations and Maintenance Support Subsection Nuclear Operations Department Virginia Power Richmond, Virginia July,1985

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t CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Power (the Company), and they may not be appropriate for use in situations other than those for which they were specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or

implied, as to their

accuracy, usefulness, or applicability.

In particular, THE COMPANY MAKES NO WARRANTY OF 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.

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SECTION 1

2 3

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APPENDIX A APPENDIX B TABLE OF CONTENTS TITLE Classification/Disclaimer..................

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

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

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

Preface......................... *...........

Introduction and Summary...................

Control Rod Drop Time Measurements.........

Control Rod Bank Worth Measurements........

Boron Endpoint and Worth Measurements......

Temperature Coefficient Measurement........

Power Distribution Measurements............

References.................................

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

Deviation Report for the All-Rods-Out Flux Map...................................

ii PAGE NO.

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LIST OF TABLES TABLE TITLE PAGE NO.

1. 1 Chronology of Tests................................

4 2.1 Hot Rod Drop Time Summary..........................

12 3.1 Control Rod Bank Worth Summary.....................

17

4. 1 Boron Endpoints Summary............................

22 5.1 Isothermal Temperature Coefficient Summary.........

26 6.1 Incore Flux Map Summary............................

30 6.2 Comparison of Measured Power Distribution Para-meters With Their Technical Specifications Limits...

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.I LIST OF FIGURES FIGURE TITLE 1. 1 Core Loading Map.........................................

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

1.3 Incore Instrumentation Locations.........................

1.4 Burnable Poison and Source Assembly Locations............

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

2. 1 Typical Rod Drop Trace...................................

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

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

3. 2 Bank B Differential Rod Wor.th - HZP......................

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

5.1 Isothermal Temperature Coefficient - HZP, ARO............

6. 1 Assemblywise Power Distribution - ARO, 3~£ Power..........

6. 2 Assemblywise Power Distribution - 22~£ Power..............

6.3 Assemblywise Power Distribution - 46% Power..............

6.4 Assemblywise Power Distribution - 66% Power..............

6.5 Assemblywise Power Distribution - 100% Power, Equilibrium Xenon........................................

iv PAGE NO.

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9 13 14 18 19 23 27 32 33 34 35 36

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I PREFACE The purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 8 core could be operated safely, and to make an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard test techniques and methods of data analysis were used.

The test data, results and evaluations, together with the detailed startup procedures, are on file at the Surry 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 comparision of the test results with design predictions, and an evaluation of the results.

The Surry 2, Cycle 8 Startup Physics Tests Results and Evaluation Sheets have been included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format.

The design test conditions and design values of the measured parameters were completed prior to startup physics testing. The entries for the design values were based on the calculations performed by Virginia Power's Nuclear Engineer ing Group 1* During the tests, the data sheets were used as guidelines both 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.

Appendix A of this report contains the final completed and approved version of the Startup Physics Tests Results and Evaluation Sheets.

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I SECTION 1 INTRODUCTION AND

SUMMARY

On March 20, 1985, Unit No. 2 of the Surry Power Station was shutdown for its seventh refueling. During this shutdown, 60 of the 157 fuel assemblies in the core were replaced with fresh fuel assemblies. The eighth cycle core consists of 5 batches of fuel: one thrice-burned batch from Cycles 5,6, and 7 (Batch 7B), one twice-burned batch carried over from Cycles 6 and 7 (Batch 8), two once-burned batches carried over from Cycle 7 (Batches 9 and Sl/9C), and one fresh batch (Batch 10). The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2.

The incore instrumentation locations are identified in Figure 1. 3.

Figure 1. 4 identifies the location and number of burnable poison rods and source assemblies for Cycle 8, and Figure 1.5 identifies the location and number of control rods in the Cycle 8 core.

On June 27, 1985 at 0634, the eighth cycle core achieved initial criticality. Following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the results of these tests follows:

1.

The drop time of each control rod was confirmed to be within the 1.8 second limit of the Surry Technical Specifications 2 *

2.

Individual control rod bank worths for all control rod banks were measured using the rod swap technique 3 and were found to be within 3.7% of the design predictions. The sum of the individual control rod bank worths was measured to be within O. 7% of the design prediction. These results are within the design tolerance of +/-15%

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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.

Critical boron concentrations for two control bank configurations were measured to be within 4 ppm of the design predictions.

These results were within the design tolerances and also met the accident analysis acceptance criterion.

The boron worth coefficient was measured to be within 4.1% of the design prediction, which is within the design tolerance of +/-10%,

and met the accident analysis criterion.

The isothermal temperature coefficient was measured to be within 0.6 pcm/°F of design prediction. This result is within the design tolerance of +/-3 pcm/ °F and also meets the accident analysis acceptance criterion.

Core power distribution for HZP and at-power conditions were generally within 6.5% of the predicted power distribution. For all maps, the hot channel factors were measured to be within the limits of the Technical Specifications.

However, at 3% power a quadrant power tilt of 4.35% was measured, and at 22% power a quadrant power tilt at 2.83% was measured.

Both tilts were measured in the upper NW quadrant (N41). All measured parameters were within the limits of the Technical Specifications and met their respective accident analysis a~ceptance criteria.

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/I In summary, all startup physics test results were deemed acceptable.

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

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Table 1.1 SURRY 2 - CYCLE 8 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Test Date Time Power Hot Rod Drop-Full Flow 06/27/85 0405 HSD Reactivity Computer Checkout 06/27/85 0946 HZP Temperature Coefficient-ARO 06/27/85 1307 HZP Bank B Worth 06/27/85 1527 HZP Boron Endpoint-B In 06/27/85 1929 HZP Bank D Worth - Rod Swap 06/27/85 1945 HZP Bank C Worth - Rod Swap 06/27/85 2030 HZP Boron Endpoint-ARO 06/28/85 1109 HZP Bank A Worth - Rod Swap 06/28/85 1328 HZP Bank SB Worth - Rod Swap 06/28/85 1454 HZP Bank SA Worth - Rod Swap 06/28/85 1524 HZP Flux Map-ARO 06/29/85 0227 3%

Flux Map -

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06/29/85 2031 22%

Flux Map - 46%

07/03/85 0227 46%

Flux Map - NI Calibration 07/06/85 2239 66%

Flux Map - NI Calibration 07/07/85 0253 62%

Flux Map - NI Calibration 07/07/85 0543 65%

Flux Map - HFP, Eq. Xenon 07/22/85 1048 100%

4 Reference Procedure 2-PT-7.2 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-PT-28.11 2-0P-57, 2-PT-28.2 2-0P-57, 2-PT-28.2 2-0P-57, 2-PT-28.2 2-0P-57, 2-PT-28.2 2-0P-57, 2-PT-28.2 2-0P-57, 2-PT-28.2 2-0P-57, 2-PT-28.2

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14 1--1--1--1--1--1--1--1 I

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I 15 1 __ 1 __ 1 __ 1 4P -- 4 BURNABLE POISON ROD CLUSTER BP -- 8 BURNABLE POISON ROD CLUSTER 16P --16 BURNABLE POISON ROD CLUSTER 20P --20 BURNABLE POISON ROD CLUSTER SSx --SECONDARY SOURCE 8

I\\

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N IOOP C otmBI' Figure 1.5 SURRY UN IT 2 - CYCLE 8 CONTROL ROD LOCATIONS M L K

J H

G F

E D

180 1 I

A D

A v

IJX)P C INLET 90~

Absorber Material A<rin-cd N-41 A

SA D I SA A

N-44 lOOP A C

B B I C

SA B

SB SP D

C SP SB C

SP SB D

C SB SP B

SA A

D Nt.MBER OF CLUSTERS Control Bank D Control Bank C Cmtrol Bank B Caltrol Bank A Shutdown Bank SB Shutdown Bank SA SP (Spare !bl locations) 8 8

8 8

8 9

SA B

C SP SB D

B SB SP C

I SB SP\\

D I B SP SB B

C SA I

A C

B A

IJX)P B mIB1' N-43 A

SA D

SA A

N-42 LOOP A LOOP B

/OOTIET

-270° 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15

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a SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot RCS conditions in order to confirm satisfactory operation and to verify that the rod drop times were less than the maximum allowed by the Technical Specifications.

The hot control rod drop time measurements were run with the RCS at hot, full flow conditions ( 547 °F, 2235 psig) and are described below.

The rod drop time measurements were performed by first withdrawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod. This allows the rod to drop into the core as it would in a normal plant trip.

The data recorded during this test are the stationary gripper coil voltage, the LVDT (Linear Variable Differential Transformer) primary coil voltage and a 60Hz timing trace which are recorded via a visicorder. The rod drop time to the dashpot entry and to the bottom of the dashpot are determined from this data. Figure 2.1 provides an example of the data that is recorded during a rod drop time measurement.

As shown in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary coil fuse is removed. A voltage is then induced in the LVDT primary coil as the rod drops. The magnitude of this voltage is a function of the rod velocity. When the rod enters the dashpot section of its guide tube, the velocity slows causing a voltage decrease in the LVDT coil. The LVDT voltage then reaches a minimum as the rod reaches the bottom of the dashpot.

Subsequent variations in the trace are caused by the rod bouncing. This procedure was repeated for each control rod.

10 l

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1*,.

1*

I.,

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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 3.12.C.l specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 1.8 seconds with the RCS at hot, full flow conditions. All test results met this limit.

11

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Table 2.1 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-12, 1.26 sec.

K-8, 1.11 sec.

1.21 sec.

ROD DROP TIME TO BOTTOM OF DASHPOT SLOWEST ROD FASTEST ROD AVERAGE TIME C-7, 1.90 sec.

G-13, 1.78 sec.

1.83 sec.

12

DASH POT TO IZOD BOTTOM llM Figure 2.1 TYPICAL ROD DROP TRACE 51A1\\0NP-.R'( GRIPPER COi L \\l 0-....:T~=---___..

DROP Tl ME TO D1'S\\-\\ POT

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p Figure 2.2 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS N

M L

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I 11.218 I 11.229 I I

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11. 791 I I

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5 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 ___ 1 11.156 I 11.208 I 11.218 I 11.198 I 11.229 I 11.218 I 11.250 I 11.791 I 11.801 I 11.833 I 11.854 I 11.823 I 11.801 I 11.896 I 6

__ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I I __

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I 11. 229 I I 1. 229 I I

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11. 229 I I

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I 11.218 I I

I 11.197 I 11.229 I I

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I 11.801 I 11.833 I I

I 11.834 I I

I 9 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 11.208 I I 1.229 I 11.229 I 11.219 I 11.218 I 11.208 I 11.229 I 11.812 I 11.864 I 11.854 I 11.844 I 11.832 I 11.822 I 11.833 I 10 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I

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11.250 I 11.187 I I

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11. 198 I I

I 11.833 I 11.833 I I

I 11.864 I 11.823 I I

12 I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I I

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I 1. 208 I 11. 198 I I

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11. 781 I I

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13 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I

11.218 I 11.219 I 11.250 I I

I

11. 843 I

11. 823 I I 1. 864 I I

1 ti I __ I __ I __ I __ I __ I __ I __ I I

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I 15 I __ I __ I __ I I--> ROD DROP TIME TO I

I DASHPOT ENTRY (SEC)

I ___ I--> ROD DROP TIME TO BOTTOM OF DASHPOT(S[C) 14

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SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtained for all control and shutdown banks using the rod swap technique. The first step in the rod swap procedure was to dilute the most reactive control rod bank (hereafter referred to as the reference bank) into the core and measure its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer 4 and were used to determine the differential and integral worth of the reference bank (Control Bank B).

At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized such that the reactor was critical with 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 and recording the core reactivity and moderator temperature. At this point, a rod swap maneuver was performed by withdrawing the reference bank while one of the other control rod banks (i.e., a test bank) was inserted. The core was kept nominally critical throughout this rod swap and the maneuver was continued until the test bank was fully inserted and the reference bank was at the position at which the core was just critical. This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest and was used to determine the integral reactivity worth of the test bank. Statepoint data (core reactivity, moderator temperature, and the differential worth of the reference bank) were recorded with the reference bank at the MCP. The 15

I I.

I.,

I I

I 1

I I

rod swap maneuver was then performed in reverse order such that the reference bank_ once again was near full insertion and the test bank was once again fully withdrawn from the core. The rod swap process was then repeated for all of the other control rod banks (control and shutdown).

A summary of the results for these _tests is given in Table 3.1.

As shown by this table and the Startup Physics Tests Results and Evaluation Sheets given in Appendix A, the individual measured bank worths for all of the control and shutdown banks were within the design tolerance (+/-10% for the reference bank and +/-15%

for the test banks).

The sum of the individual rod bank worths was measured to be within 0.7% 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, all measured rod worth values were satisfactory.

16

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1.

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I Table 3.1 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH BANK (PCM)

(PCM)

(M-P)/P X 100 B-Reference Bank 1305 1353

-3.5%

D 1173 1194

-1.8%

C 842 812 3.7%

A 381 374

1. 9%

SB 1034 1010 2.4%

SA 1128 1161

-2.9%

Total Worth 5863 5904

-0.7%

17

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1.

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I L u Q_

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0:::

0 3:

_J a:

0:::

0 w I--z

>--i 0

0

~

N 0

0

~

N 0

0 lD 0

Cl

~...

0._,

en 0

~

'd" 0

FIGURE 3,l SURRY UNIT 2 *- CYCLE 8 BOL PHYSICS TEST BANK B INTEGRAL ROD WORTH -

HZP BANK B WITH ALL OTHER ROOS OUT PREDICTED llE MEASURED

'.~

I"'

I' 11

'u

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~

~-1,,~

1~.

Mil

--.~... "-

I' 1,..

40 80 120 160 200 BANK POSITION (STEPS) 18 228

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Cl Cl N..-

Cl Cl Cl

~Cl 1--Cl z*

w'St a:::

w u....

u....a

~Cl

0.

N Cl Cl FIGURE 3.2 SURRY UNIT 2 -

CYCLE 8 BOL PHYSICS TEST BANK B DIFFERENTIAL ROD WORTH -

HZP BANK B ~ITH ALL OTHER ROOS OUT PREDICTED lK MEASURED

~ "'

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40 80 120 160 200 BANK POSITION (STEPS) 19 228

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SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions.

For each measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. The critical boron concentration was then measured.

If necessary, an adjustment to the measured critical boron concentration was made to account for off-nominal core conditions, i.e., for rod position and moderator temperature.

The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, all the measured critical boron endpoint values were within their respective design tolerances. All measured values met the accident analysis acceptance criterion.

In summary, all results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient was determined. A plot of the boron concentration as a function of integrated reactivity can be constructed by relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement.

The value of the boron coefficient, over the range of boron endpoint concentrations, is 20

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I

~--~-------

obtained directly from this plot.

The boron worth plot is shown in Figure 4.1. As indicated in this figure and in the Appendix, the boron worth coefficient of reactivity was measured to be -7.68 pcm/ppm. The measured boron worth coefficient is within 4.1% of the predicted value of -8.01 pcm/ppm and is within the design tolerance of +/-10%. The measurement result also met the accident analysis acceptance criterion. In summary, this result was satisfactory.

21

I I

I ARO Table 4.1 SURRY UN IT 2 - CYCLE 8 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

(ppm)

(ppm) 1431 1427 4

B Bank In 1261 1263*

-2

The predicted endpoint for the B Bank in configuration has been adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown* in the boron endpoint Startup Physics Test Results and Evaluation Sheets in Appendix A.

22

2400 2000 1600

I:

u N

£L w -

i-1200 i-u a:

w 600 a::::

400 f-o 1200 FIGURE 4.l SURRY UNIT 2 - CYCLE 8 BOL PHYSICS TEST BORON WORTH COEFFICIENT l!J ENDPOJNT MEASUREMENTS

--~

r,..._

' r--....

f--

_.ie. = - 7.68 pcm/ppm r...........

oCB

' 'I'-.

~

I',._ -

1240 1280 1320 1360 1400 1440 BORON CONCENTRATION (PPM) 1480 1520

I I

I SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) measurement is generally accomplished by controlling the RCS heat gains/losses with the steam dump valves to the condenser, establishing a constant and uniform and/or steam generator blowdown heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer.

These measurements were performed at very low power levels in order to minimize the effects of non-uniform nuclear heating, thus, the moderator and fuel were approximately at the same temperature (between 543-548 °F) during these measurements. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level was maintained constant or slightly increasing during these measurements.

An isothermal temperature coefficient measurement was performed at the ARO control rod configuration.

Reactivity measurements were taken during both RCS heat up and the cooldown ramps during which the RCS temperature varied approximately 3°F.

Reactivity was determined using the reactivity computer and was plotted against the RCS temperature on an x-y recorder. The temperature coefficient was then determined from the slope of the plotted lines.

The x-y recorder plot of reactivity changes versus RCS temperature for the measurement is shown in Figure 5.1.

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 Sheets given in Appendix A, the measured isothermal temperature coefficient value was within the 24

I I

I design tolerance of +/-3 pcm/°F and met the accident analysis acceptance criterion. In summary, the measured result was satisfactory.

I I

I

-s I

I I

I 25 I

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I BANK POSITION ALL RODS OUT Table 5.1 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

ISOTHERMAL TEMPERATURE COEFFICIENT TEMPERATURE BORON (PCM/°F)

RANGE CONCENTRATION (OF)

(ppm)

COOL DIFFER.

HEATUP DOWN AVER. FRED.

(M-P) 543.7 to 1458

-4.88

-4.40

-4.641-5.27 0.63 547.1 i

26

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I-

~ -

~

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Figure 5.1 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT HZP, ARO I

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r **

I TEMPERATURE (°F) 27 I

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I SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the incore movable detector flux mapping system. This system consists of five fission detectors which traverse fuel assembly instrumentation thimbles in 50 core locations (see Figure 1.3). For each traverse, the detector output is continuously monitored on a strip chart recorder. The output is also scanned for 61 discrete axial points by the PRODAC P-250 process computer.

Full core, three-dimensional power distributions are then determined by analyzing this data using the Westinghouse computer program, INCORE 5

INCORE couples the measured flux map data with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.

A list of all the flux maps taken during the test program together with a list of the measured values of the important power distribution parameters is given in Table 6.1. The measured power distribution parameter values are compared with their Technical Specifications limits in Table 6.2. Flux Map 1 was taken at low (3%) power. This flux map serves as the base case design check.

Figure 6.1 shows the resultant radial power distribution associated with this flux map.

This map indicated the presence of a quadrant power tilt of 4.4% but all measured hot channel factor values were within their Technical Specifications limits.

Flux Maps 2, 3, 4, and 7 were taken over a wide range of power levels and control rod configurations. These flux maps were taken to check the at-power design predictions and to measure core power distribution at various operating conditions. These maps also provide incore/excore calibration 28

I I

I data for the nuclear instrumentation system.

The radial power distribution for these maps is given in Figures 6.2 through 6.5. These figures show the measured relative assembly power values are generally within 6. 5~~ of the predicted values, and the quadrant power tilt ratio decreased significantly during power ascension.

In conclusion, all power distribution measurement results were acceptable with respect to -the design tolerances, the accident analysis acceptance criteria, and the Technical Specification limits. It is therefore anticipated that the core will continue to operate safely throughout Cycle 8.

29

TABLE 6.1 SURRY UNIT 2 -

CYCLE 8 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

I I

BURNI I

F-Q(T) HOT I

F-DH(N) HOT CORE F(Z)

I I

UP I IRANK CHANNEL FACTOR I

CHNL.FACTOR MAX I

I QPTR AXIALI NO. I MAP IMAP DATE MWD/IPWRI D

I I

I F(XY) I OFF I OF I DESCRIPTION INO.

MTU I(%) I STEPS I I

AXIAL I

I AXIAL!

I I

I SET ITHIMI I

I I

IASSYIPIN POINT F-Q( T) IASSYI PIN F-DH(N) POINTI F(Z) I I MAX ILOC

(%1 IBLESI I

__ I_I __ I __ I ___

I __ I_

__ I __ I __ I __ I _

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I ARO I

6-29-85 01 3 I 228 I P081 00 11, 2.395 I L04 I IH 1.543 15 11.50511.48611.0441 NW 29.461 38 I I

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22% POWER MAP I

2 6-29-85 1 I 221 154 I LOii i IH 34 2.240 I L041 IH

1. 532 34 11.42711.45211.0281 NW -10.191 44 I I

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46% POWER MAP I

3 7-3-85 31 I 461 157 I P081 00 33 2.067 I L04 I IH

1. 490 33 11.34711.41211.0181 NW

-8.211 42 I I

I I

66% NI CAL. ( 51 I

4 7-6-85 1201 661 164 I N071 JL 35 2.016 I N07 I. JL

1. 461 34 11.32411.40011.0151 NW

-9.221 41 I I

I I

HFP, EQ. XENON I

7 7-22-85 3901100 I 191, I J03 I OF 35 1.848 I J03 I OF

1. 1,21 34 11.23911.37711.0091 NW

-6.161 41 I L,.)

0 NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEMBLY LOCATIONS (E.G. H-8 IS THE CENTER-OF-CORE ASSEMBLY)

FOLLOWED BY THE PIN LOCATION ~DENOTED BY THE "Y" COORDINATE WITH THE FIFTEEN ROWS OF FUEL RODS LETTERED A THROUGH O AND THE 'X" COORDINATE DESIGNATED IN A SIMILIAR MANNER).

IN Tiff "Z" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROM THE TOP OF THE CORE.

1.

F-Q(T) INCLUDES A TOTAL UNCERTAINTY OF 1.08.

2.

F-DH(N) INCLUDES A MEASUREMENT UNCERTAINTY OF 1.04.

3.

F(XY) IS EVALUATED AT THE MIDPLANE OF THE CORE.

4.

QPTR -

QUADRANT POWER TILT RATIO.

5.

FLUX MAPS 5 AND 6 WERE QUARTER-CORE MAPS TAKEN FOR PRELIMINARY EXCORE DETECTOR CALIBRATION.

I I

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Table 6.2 SURRY UN IT 2 - CYCLE 8 STARTUP PHYSICS TESTS COMPARiSION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS F-Q(T) HOT F-DH(N) HOT CHANNEL FACTOR*

CHANNEL FACTOR+

MAP NO.

MEAS LIMIT MARGIN/ MEAS LIMIT MARGIN

(%)

1 2.40 4.17 42.6 1.54 2.00 23.0 2

2.24 4.36 48.6 1.53

1. 91 19.9 3

2.07 4.36 52.6 1.49

1. 80 17.2 4

2.02 3.33 39.4 1.46

1. 71 14.6 7

1. 85 2.18 15.2 1.42 1.55 8.4

The Technical Specification's limit for the heat flux hot channel factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q CT) in the core. The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T). The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each map. All measured F-Q(T) hot channel factors include 8% total uncertainty.

+

The measured values for the enthalpy rise hot channel factor, F-dH(N), include 4% measurement uncertainty.

31

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I R

p N

Figure 6. 1 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ASSEMBL YWISE POWER DISTRIBUTION ARO, 3% POWER M

L K

J H

G F

[

D C

B PREDICTED 0.33 0.37 0.33 PREDICTED MLASURED

PCT DIFFER ENCL 0.35. 0.38. 0.34

3.1,

0.9,

1.1.

MEASURED

.PCT DIFFERENCE.

i:ii*:*i:ii*:*;:ii*:*;:ii':*i:ii':*i:ii':*i:ii':

0.37. 0.71. 1.10. 1.16. 1.08. 0.70. D.36.

3.8.

3.1.

2.3.

1.8.

1.0

1.1

1.1,

i: 44 * :

i : io * : * ; : ; i * :

i : i4 * : * ; : 2i * :

i : i4 * :

i : ii* : * ; : oo * :

o: 44 * :

. 0.46. 1.07. 1.26. 1.38, 1.29. 1.36. 1.20

1.02

0.43

4.3.

6.5. 5.5.

2.7.

1.3.

1.2.

1.1.

1.1 * -1.9.

o:44*:*o:i;*:*i:22*:*i:2i*:*;:2;*:*;:;o*:*;:2;*:*;:2i*:*;:22*:*i:i;*:*i:44*:

. 0.46. 0.96. 1.32. 1.35. 1.24. 1.33. 1.22. 1.25. 1.20. 0.90

0.43

3.4.

5.1.

7.8.

5.6.

3.0.

1.9.

1.3. -1.6. -1.7. -1.8. -1.9,

i: ii*:*;: ii*:* i: 22 *: *;: 2i *:

i: ie *:

i: i4 *:*;:ii*:* i: i4 *: *;: ie *:

i: 2i *:

i: 22 *:*;:ii*:* o: ;; *:

. 0.37. 1.04

1.28. 1.31

1.24

0.98. 1.22. 0.94

1.15. 1.24. 1.20. 0.99. 0.35.

3. 2.

3. 2 *

4. 3.

3. 7 *

5. 0.

II. 8.

3. 2 *

0. 2. -2. S. -1. 8. -1. 9. -1

9. -2. 1 *

i: ii* :

i: ii*:* i: 2e *: *;: ie *: *;: 2i *: *;: i4 *: *;: 2i *:

i: i4 *: *;: 2i * :

i: ie *:

i: 28 *:*;:ii*:* i: ii*:

0.71

1.23 o 1.32

1,22 o 1,29

1.18 o 1.23 o 1.14

1,22

1.17

1,28

1.19 A 0.68

3.3.

3.3,

3.2.

3.1

3.6.

3.6. 2.7.

0.3 * -2.8. -1.3, -0.1. -0.11 * -2.1

A

i:i4*:*;:ii*:*;:;4*~*i:2;*:*i:i4*:*;:;4*:*;:;8*:*;:ie*:*;:ie*:*;:;i*:*o:ii*:*;:2;*:*;:;i*:*;:ii*:*o:ii*:

0.35. 1.11. 1.39. 1.25. 0.97. 1.18. 1.21. 1.11. 1.19. 1.13

0.94. 1.23

1.33

1.05

0.33

3.4.

3.4.

3.4

3.6. 3.8.

3.4.

2.9. 2.4. 1.0. -1.0. -0.1.

2.1. -1.3 * -2.4 * -2.4.

i:ii*:*i:;4*:*;:2i*:*;:i;*:*;:;i*:*;:ii*:*;:i8*:*;:oi*:*;:oa*:*,:2i*:*;:;i*:*;:i;*:*;:2i*:*;:;4*:*o:ii*:

. 0.39. 1.18. 1.32

1.36. 1.24. 1.25. 1.12. 1.11

1.08

1.19

1.18 *. 1.30, 1.24

1.11

0.37.

3.4.

4.o.

4.4.

3.8.

2.9.

1.4. -0.2 * -1.0 * -0.2. -o.4. -2.9 * -2.8. -2.5 *

o:i4*:*;:oi*:*;:i4*:*;:i;*:*o:i4*:*;:;4*:*;:;8*:*;:oe*:*;:;e*:*;:;4*:*o:i4*:*;:2;*:*i:ii*:*;:oi*:*o:i4*:

. 0.34. 1.08. 1.34. 1.24. 0.98. 1.17. 1.18. 1.08. 1.17

1.13. 0.92. 1.16

1.29. 1.04

0.33

0.1.

0.1.

2.2.

4.4.

2.3.

0.3. -o.o. -o.s. -1.3. -2.4. -4.4. -3.7 * -3.1 * -2.8.

* * *... :. o: ii. :. i : ii. :. i : 28. :. i : i 8. :. i : 2i. :. i : i 4. :. i : 20. :. i : i 4. :. i : ii. :. i : i e. :. i : 28. :. i : ii. :. o: ii. :.......

. 0.69. 1.20. 1.27. 1.17. 1.25. 1.14. 1.20. 1.13. 1.23. 1.14

1.22. 1.14

0.66

o.*1

0.1 * -D.5. -1.4. -0.3.

0.2. -0.1 * -0.9. -2.0. -3.6. -4.8 * -4.8. -4.8.

o:;;*:*;:o;*:*i:22*:*;:2i*:*;:;e*:*o:i4*:*;:;i*:*o:i4*:*;:,e*:*i:2i*:*;:22*:*,:o;*:*o:ii*:

. 0.36. 1.D2. 1.22. 1.25. 1.17. 0.93. 1.18. 0.93. 1.15. 1.21. 1.16

0.95. 0.34.

1.0.

1.0. -o.o. -1.4. -1.1. -o.8. -o.6. -1.2 * -2.3 * -4.5. -s.2 * -5.5 * -4.8.

- - - - o:44*:*o:i;*:*i:22*:*i:2i*:*;:2;*:*;:;o*:*;:2i*:*;:2i*:*;:22*:*o:i;*:*o:i4*:*******

0.45

0.92. 1.21

1.25. 1.19. 1.30. 1.18. 1.21. 1.16. 0.86

0.41

1.8.

0.6. -1.4. -1.8. -1.6. -0.2. -2.2 * -5.1. -5.3. -6.0 * -6.1 *

......... i: 44... i: oo... i: ii... i : 34... i: 2i... i: 34... i: ii... i: 00... i: 44.........

STANDARD DEVIATION

=1. 941 0.45. 0.99. 1.17. 1.34. 1.28. 1.28. 1.09. 0.93. 0.41.

1.8. -1.4 * -2.2. -D.1.

0.8. -4.S. -8.3. -7.S. -6.1

0.35 0.69 1.07 1.14 1.07 0.69 0.35 o.36. 0.10. 1.09. 1.11

1.01. o.64. o.32.

1.8.

2.0. 2.D. -2.S. -6.3 * -7.7. -8.5.

0.33 0.37 0.33 0.34 0.35 0.31 2.0

-6.9

SUMMARY

AVi:RAGE

.PCT DIFFERENCE.

=

2.6 MAP NO: S2 1 CONTROL ROD POSITIONS:

DATE:

F-Q(T) 6/29/85

= 2. 395 POWER:

3%

QPTR:

D BANK AT 228 STEPS F-DH(N) = 1.543 F(Z)

= 1.505 F(XY)

= 1.486 BURNUP

=

32 0 MWD/MTU NW 1.044 I NE 0.994

1----------

sw 1.002 I SE 0.960 A,O =

29.46(%)

2 3

4 5

6 7

8 9

10 11 12 13 111 15

I I

I R

Figure 6.2 SURRY UNIT 2 - _CYCLE 8 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION p

N 14 PRlDICHD 14[ASUR£D

PCT DI HER ENCE.

L K

22% POWER J

H G

0.32. 0.35. 0.32.

. 0.33

0.36. 0.33

3.7. 3.3

2.8.

r E

0. 3 7. 0. 70. 1. Oli. 1. 02

1. Oli. O. 70. O. 37.

. 0.39. 0.71. 1.06. 1.0li. 1.06. 0.71. 0.37.

li.1.

1.3.

2.1

2.0.

2.1

1.2.

1.1

D

.C B

PREDICTED MEASURED

PCT DI HER ENCL

i:,i*:*i:i,*:*i:ii*:*;:ii':*i:i,*:*;:ii*:*;:ii":*i:i,*:*i:,i*:

O.li9. 1.09. 1.23. 1.35. 1.25. 1.31i. 1.23

1.05. O.li6.

4.1.

li.1.

1.3. 1.2. 1.1

0.7.

1.1

1.1. -2.1 *

. O.li7

0.96

1.26. 1.30. 1.22. 1.31

1.22

1.30

1.26

0.96. O.li7.

. O.li8. 0.99. 1.31. 1.33. 1.23. 1.31

1.22. 1.28

1.21i

0.91i. O.li7

2.3.

3.2

1i.1.

2.8.

1.2. -0.2 * -0.1 * -1.1 * -1.5. -1.1.

0.2 *

o:ii*:*i:o,*:*i:ii*:*i:i~*:*i:ii*:*o:i,*:*i:ii*:*o:i,*:*i:ii*:*i:ii*:*i:ii*:*i:i,*:*i:ii*:

. 0.37. 1.06. 1.29. 1.33

1.20. 0.97

1.21

0.95

1.16. 1.27

1.24. 1.05

0.38.

1.2. 1.2. 2.2. 3.5. 2.7. 2,'4. 1.2. O.li. *0.3. *1.0. -1.9. 0.2. 2.5.

i:io*:*;:ii*:*;:io*:*;:;i*:*;:i,*:*i:ii*:*i:i;*:*i:ii*:*;:;,*:*i:ii*:*i:io*:*i:ii*:*i:10*:

0.71. 1.23. 1.32. 1.18. 1.16. 1.14. 1.23. 1.13. 1.11i. 1.16. 1.28. 1.21

0.71 *

- 1.5

1.4.

1.1.

1.1

1.8. 1.9. 1.8.

o.9. -o.4 * -1.0 * -1.8. -o.4

1.2.

A

. 0.32. 1.0'4

1.33. 1.22

0.9'4, 1.12. 1.17. 1.09, 1.17. 1.12. 0.9'4. 1.22. 1.33, 1.0'4

0.32.

. 0.3'4. 1.07. 1.36. 1.23. 0.95, 1.13. 1.19. 1.11

1.18. 1.12. 0.93. 1.19. 1.32. 1.04. 0.32.

11.1

2.9.

1.6.

1.2.

o.8.

1.0. 1.6. 1.5. o.8 * -0.1. -1.3. -2.2. -1.2. -o.3 * -0.2 *

o:i;*:*i:oi*:*;:i,*:*;:ii*:*i:ii*:*i:i;*:*;:io*:*i:i;*:*i:ii*:*i:ii*:*i:io*:*i:ii*:*;:i,*:*;:ii*:*i:i;*:

. 0.37. 1.06. 1.26. 1.33. 1.21. 1.22. 1.11. 1.12. 1.09. 1.19. 1.18. 1.29. 1.22. 1.02. 0.35.

ii.ii.

3.2.

1.1.

1.2. o.9. 1.2. 1.1.

1.1i. -0.1 * -1.1. -1.8. -2.0. -1.5. -o.4

o.5.

o:i2*:*;:04*:*i:ii*:*;:ii*:*i:i4*:*;:ii*:*i:ii*:*i:oi*:*i:ii*:*i:ii*:*o:i4*:*i:ii*:*i:ii*:*i:i,*:*i:ii*:

. 0.31i

1.06. 1.33

1.22. 0.95. 1.12. 1.18

1.10. 1.18. 1.10

0.92. 1.18. 1.32

1.05

0.33.

4.7. 2.2. -0.6.

0.1.

0.9. 0.5. 0.2. 0.9. 0.6. -1.6. -2.2. -2.9. -1.0. 0.7

1.8.

* * * * * *: *o:io*:

i:ii.:

i:io* :* i:i1*: *i: i,*: *i:ii" :*i:ii*: *i: ii": *i:i, *:

i: ii" :*i:io*: *;:ii": *i:1i*: * * * * * * *

, 0.70. 1.21. 1.30. 1.17. 1.15. 1.12. 1.21. 1.10. 1.12. 1.13. 1.26. 1.20. 0.71 *

. -0.1. -o.8. -o.3.

o.5

0.2. -o.o. -o.o. -1.4 * -2.4. -2.9 * -3.4 * -1.1

1.5.

o:ii*:*;:o,*:*;:ii*:*;:i~*:*i:ii*:*i:i4*:*;:io*:*o:i,*:*i:i1*:*i:ii*:*;:ii*:*i:o,*:*i:ii*:

0.38

1.06. 1.27. 1.29. 1.17. 0.91i. 1.19. 0.92. 1.12. 1.25. 1.23

1.03

0.37

1.8.

1.8.

1.2.

o.4.

o.ii. -0.2. -o.8. -2.9. -1i.2. -2.3 * -2.2. -1.1.

o.8.

- - - - o:,i*:*i:ii*:*i:ii*:*;:io*:*;:ii*:*i:i;*:*;:ii*:*;:ii*:*;:ii*:*i:ii*:*i:,i*:*******

. 0.'49. 0.98. 1.26. 1.30. 1.21

1.28. 1.17. 1.25

1.22. 0.93. 0.46.

4.4.

2.8.

0.4. 0.3 * -o.s. -2.4. -4.0. -3.7. -3.1. -2.3 * -0.4.

...... :. i: 4 i. :. i : 04. :. i : ii. :. i : ii. :. i : 24. :. i : ii. :. i : 2 i. :. i : 04. :. i: 4 i. :.......

STANDARD DEVIATION

= 1. 342

0.49. 1.08. 1.21i. 1.29. 1.17. 1.28. 1.16. 1.00. 0.46.

4.2.

4.0.

2.2. -3.0. -5.3. -4.2. -4.1 * -3.7. -1.7.

* * * * * * :

i: ii * :

o: io * :

i : oii * :

i : ii* :

i : iii * :

i: ii* :

i: ii* : * * * * * * *

o.38. o.73. o.97. o.98. 1.01

o.68. o.35.

li.O. 4.2. *6.2. -4.1 * *2.8. *3.3 * *li.3 *

. o.32. o.35. o.32.

. 0.31i. 0.31i

0.32.

4.5. -2.1. -2.2.

SUMMARY

AVERAGE

.PCT DIFFERENCE.

1.9 MAP NO: S2 2 CONTROL ROD POSITIONS:

DATE:

6/29/85 F-Q(T)

= 2.240 F-DH(N) = 1.532 F(Z)

= 1. 427 POWER:

22%

QPTR:

D BANK AT 154 STEPS NW 1.028 I NE 0.997

1----------

sw 1.002 I SE 0.973 F(XY)

= 1.452 BURNUP

=

1 MWD/MTU A.O = -10.19(%)

33 2

3 5

6 7

8 9

10 11 12 13 111 15

I I

I Ill Figure 6.3 SURRY UNIT 2 - CYCLE C STARTUP PHYSICS TESTS ASSEMBL YWISE POWER DISTRIBUTION 46% POWER M

l k

J H

G

[

0 C

I

- - - i'Rcoicico**:

, 0.33, 0.35. 0.33 *

0.311

0.37

0.311

11.6 *

...2.

3.3 *

- - - itcoicico**

MlASURCO

PCT DI H [RCIICC.

o:;1*:*0:,0*:*;:o;*:*;:o;*:*,:o;*:*o:io*:*o:;,*:

D.39

D.71

1.05. 1.03

I.OS

0.71

0.311.

11.0. 0.7. 1.6. 1.5. 1.7. 1.0. 0.9.

M[ASUR[O

PCT DI FF[IIICIIC[.

o:.;1*:*;:o.;*:*;:ii*:*i:;i*:*;:i;*:*;:;i*:*;:i;*:*;:o.;*:*o:iii*:

, 0.119. 1.08

1.22

l,JJ

1.22

1.32 -. 1.22

1.05

0.116

11.0.,.o. 0.7

0.11 * -0.11 * *0.2. 1.0. 0.9. *3.2 *

o:.; i * :

o: ;6 * :

i : is* : * ; : ii* : * ; : i; * : * ; : ; ; * :

i : ii * : * ; : ii* : * ; : is* :

o: ;6 * : *;,:iii* :

. 0.1111. 0.911

1.211

I.JI

1.22. I.JO

1.20

l.ln

1.23. 0.93

O.ti7

1.6.

2.0.

2.0

1.11

0.6 * -0.6 * *0.11 * *1.5 * -2.2 * -2.6 * -1.2 *

* ;,: ie *: *; :oii *:*;:is":* i :ie *:*;:ii.*:*;,:;;*:*; :i; *:

o: ;s *:

i: ii.*:

i: ie *:

i: is*:*;:;,.;*:*;,: ie *:

0.38

I.OIi

1.26. 1.211

1.111

0.97

1.22

0.96

1.111

1.26

1.22

1.03

O.JII

o.,. 0.1

0.2'. 0.5.

1.1

2.2. 0.1.,.,.

,.,. -1.2. -2.9. -1.1

0.9.

o: io * :

i : ii * :

i : ii* :

i : ii.* :

i : iii * :

i : ; ; * : * ; : ii* :

i : ; ; * :

i : ; ii* : * ; : i 6 * : * ; : ii* :

i : ii * : *;,: io * :

0.71

1.21

1.29. 1.16.,.,...,.,11. 1.23.,.,11. 1.17. 1.16. 1.26. 1.19. 0.71

o.,

0.1 * -o.o. -o.6. 0.11.

1.3. 0.11. 1.6. 2.2. -0.1. *3.o. -1.6. 0.11.

A

. o: jj. :. i: i,j. :. i: ii. :. i: ii. :. o: ;;. :. i: ii" :. i: ii. :

i: ii. :. i: ii. :. i: ii. :

o: is" :. i: ii* :

i: ii* :

i: i,j * :

o: jj * :

0.311. 1.05. 1.32. 1.22. 0.95. 1.13. 1.20. 1.12. 1.20. 1.111. 0.94. 1.17. 1.30. 1.03. 0.33.

II.II. 1,9. 0.1

0.2. 0.3. 0.11.

0.11. 0.9. 1.0. 1.0. *1.0. *3.11. *1.11. *0.3

0.0 *

. o: is. :. i: o i. : : i : 2i. :. i:; i. :. i: ii. :. i: 22. :. i: ii. : T ii* :. i: ii. :. i: ii. :

i : ii. :. i: ii. :

i: ii* :. i: oi * :

o: ;; * :

0.37. 1.04. 1.23. 1.32. 1.23. 1.23. 1.12. 1.111. 1.11

1.21

1.111. 1.27. 1.21. 1.01

0.36.

3.9.

2.3. 0.2. 0.9.

1.11.

1.2. 0.9. 0.9. *0.2. -1.0. *2.1. -2.11. -1.11.

0.2.

1.11 *

,

;;*:*;:o;*:*i:;2*:*;:22*:*;,:;s*:*i:i;*:*i:;;*:*;:;;*:*;:i;*:*i:;;*:*o:;;*:*i:22*:*i:;i*:*i:o;*:*;,:;;*:

0.34

1.05

1.31

1.22. 0.96. 1.13. 1.19. 1.12. 1.19. 1.11. 0.93. 1.111. 1.31

1.0II. 0.34

11.11

2.0. -o.7. o.3.

1.11. o.6. o.o. 0.11. -o.o. -1.5. -2.1. -2.1. -1.2. o.9. 3.o.

- - - - o:io*:*i:i;*:*;:i;*:*;:;i*:*;:;.;*:*i:;;*:*;:22*:*;:;;*:*;:;.;*:*;:;i*:*;:2;*:*;:2;*:*0:10*:*******

0.70. 1.20. 1.29. 1.16. 1.14. 1.12. 1.22. 1.12. 1.12. 1.13. 1.25. 1.111. 0.70.

-0.11 * -0.11. -0.1. -o.3 * -0.11 * -0.1 * -o.o. -o.6 * -1.6 * -2.5 * -3.11 * -2.0 * -o.o ~

o: ie *: *;: oai *: *;: ;; *:

i: ie *:*;:ii*:*;,:;~;:* i: ii*:* o: ;; *: *;:ii.*:*;: ie *:

i: is*:* i: oii *: * ;,: ie *:

. 0.311. 1.05. 1.26

1.27

1.16. 0.94. 1.20. 0.95

1,14

1.25

1.23. 1.03

0.37

1.1. 1.1. 0.5. -0.11.--0.7. -0.11. -0.5. -0.5. -2.0. -2.2. -2.2. -1.11. -0.2 *

0.117

0.96

1.25. 1.29. 1.21. 1.31

1.21

1.29

1.25. 0.96

0.117 *

0.119. 0.97 * ].25

1.27

1,19. 1.30. 1.21

1.27. 1.23. 0.94

0.117

3.1

1.7 * -0.11 * -1.3. -1.11 * -1.2. *0.6. -1.11. -2.0. -2.1 * -0.2.

.. *.... :. i,: iii.:. i: i,,i. :. i: ii. :. i: ii. :. i: ii" :. i: ii. :. i: ii. :. i: i,,i. :. i,: iii. :.......

STANDARD OCVIATION C 1,165

O.ti9. 1.08

1.22. 1.30. 1.21. 1.30. 1.19. 1.02. 0.117.

3.5.,.o. 1.1 * -1.9 * -1.11, -1.3. -1.0. -1.6 * -1.5 *

- - - - o:;1*:*0:,0*:*,:o;*:*;:o;*:*,:o;*:*o:io*:*o:;,*:*******

o.39

o.73

1.os. 1.00. 1.02

o.69. o.37 *

,.o. 11.1....... -1.5. *1.6 * -1.3 * -1.0.

0.33

0.35. 0.33.

0.34

0.35. 0.32.

11.5. *1.6. *1.7.

SUMMARY

AV[RAG[

.l'CI OIH[R[NCC.

=

1.11 MAP NO: S2*8-3 DATE:

7/ 3/85 POWER:

46%

CONTROL ROD POSITIONS:

f-Q( T) 2.067 QPTR:

D BANK AT 157 STEPS f-DH( N) = 1.490 NW 1.018 I NE 0.995

1----------

f(Z) 1.347 sw 1.005 I SE 0.982 f(XY)

1.412 BURNUP 31 MWD/MTU A.O

-8.21(%)

34 2

3 5

6 7

II 9

10 11 12 13 15

I I

I R

p N

Figure 6.4 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 66% POWER M

L I(

J H

G f

E D

C 8

PREDICTE"D PREDICTED MEASURED

PCT DI ffERENCE.

. 0.34. 0.38. 0.34.

. 0.35. 0.38. 0.35.

0.9.

0.5.

0.4,

MlASURED

PCT O I ffERENCE.

0.39. 0.72. 1.04

1.03. 1.04

0.72. 0.39.

. 0.40, 0.73. 1.05. 1.04. 1.04. 0.71. 0.39.

2.3

1.9.

1.2.

0.5

0.1. -0.5. -0.5.

. 0. 49. 1. 04. 1

19. 1. 3 1. 1. 21

1, 31

1. 19. 1. 04. 0.1,9.

. 0.50

1.06. 1.21. 1.32. 1.22. 1.30

1.18. 1.03. 0.48.

2.3.

1.9.

1.5.

0.2. -0.2. -0.5. -0.5. -2.2.

0:49*: *o:96.: * ;:2j*: *; :21*: *; :20*: * ;:29*: * ;:20*: *; :2,*: * ;:23*: *o:96.: *o:49.:

. 0.49. 0.98. 1.26. 1.29

1.21

1.30. 1.20

1.28

1.23. 0.95. 0.48.

1.1.

1.5.

1.9.

1.6

0.8.

0.1. -0.1.

0.6. -0.5. -1.1. -1.2 *

. 0.39. 1.04. 1.23. 1.26. 1.15. 0.96. 1.21. 0.96. 1, 1~. 1.26

1.23. 1.04. 0.39 *

. 0.39. 1.04. 1.24. 1.28, 1.17. 0.97. 1.22

0.97. 1. 17

1.26. 1.21. 1.03

0.39.

0. 5.

0. 8.

1. 5.

1. 1 *

1. 1.

0. 9 *

1. 0.

1. 1 *

0. 4. - 1. 7. -1. 2. -o. 2.

. o: 72.:. i: i 9. :. i: 28. :. i: i 5. :. i: i 5. :. i: i j. :. i: 22. :. i: i j.:. i: i 5. :. i: i 5.:. i: 28. :. i: i 9.:. o: 72. :

. 0.73. 1.21. 1.29. 1.16. 1.16. 1.14. 1.24. 1.14. 1.16. 1.16. 1.26. 1.18. 0.71.

1.1. 1.1. 0.9. 0.4. 0.8. 1.3. 1.5. -1.2. -0.7. 0.4. -1.0. -1.4. -1.0.

A

. o: j4. :. i: 04. :. i: j i. :. i: 20. :. o: 96.:. i: i j. :. i: 20. :. i: i2. :. i: 20.:. i: i j. :. o: 96. :. i: 20. :. i: j i.:. i: 04. :. o: j4. :

. 0.35. 1.06. 1.33. 1.21. 0.96. 1.14. 1.21. 1.14. 1.21. 1.14. 0.96

1.21

1.30. 1.02. 0.34.

1.8.

1.7.

0.8.

0.1.

D.6.

1.4.

1.3.

0.9.

0.7.

0.9.

0.8. -0.9. -1.7. -1.9.

. 0.38. 1.03. 1.21. 1.30. 1.21. 1.23. 1.13. 1.14. 1.13. 1.23. 1.21. 1.30. 1.21. 1.03. 0.38.

. 0.38. 1.05. 1.23. 1.30. 1.21. 1.23. 1.11,. 1.16. 1.13. 1.23. 1.20. 1.31. 1.22. 1.02. 0.37.

1.9.

1.7. 0.7. 0.1. 0.6. 1.4. 1.5. 0.4. 0.0. -1.0. 0.8. 0.2. -1.4. -1.5.

. 0,3q. 1,0q. 1.31. 1.20. 0.96. 1.13. 1.20. 1.12. 1.20

1.13. 0.96. 1.20. 1.31. 1.04. 0.34.

. 0. 34. 1. 04. 1. 30. 1. 20. 0. 96. 1. 14. 1. 21. 1. 15

1. 21. 1. 11. 0. 9q. 1. 18. 1. 30. 1. 04. 0, 34.

. -0.3. -0.4. -0.5. -0.2.

0.0.

0.6

1.3,

1.8.

1.2. -1.9. -1.9. -1.4. -0.5. -0.2. -0.7.

. 0.72. 1.19. 1.28. 1.15. 1.15

1.13. 1.22. 1.13. 1.15. 1.15. 1.28, 1.19. 0.72.

. 0.71. 1. 19, 1.28. 1.17. 1.17. 1.14. 1.23. 1.13

1. 14. 1.13. 1,2q. 1.18. 0.72.

. -0.5. -0.6.

0.2.

1.5.

1.2.

1.0. 0.6. -0.3. -1.4. -2.3. -2.6. -0.8.

1.1.

. o: j 9. :. i : 04. :. i : 2j. :. i : 26. :. i : i;. :. o: 96. :. i : 2 i. :. o: 96. :. i : i;. :. i : 26. :. i : 2 j. :. i : 04. :. o : j 9. :

. 0.39. 1.04. 1.24. 1.28. 1.16. 0.95. 1.20. 0.95. 1.14. 1.24. 1.20. 1.02. 0.39.

0.3.

0.8.

1.5.

0.8. -0.2. -0.8. -1. 1. -1.5. -1.8. -2.4. -1.8 * -0.3.

. 0.49. 0.96. 1.23. 1.27. 1.20. 1.29. 1.20. 1.27. 1.23. 0.96. 0.49.

. 0.49. 0.97. 1.25. 1.27. 1.19. 1.28. 1.18. 1.25. 1.21. 0.94. 0.47.

1.2.

1.3.

1.4. 0.1. -0.8. -0.9. -1.4. -2.1. -2.2. -2.6. -2.7.

. 0.49. 1.04. 1.19. 1.31. 1.21. 1.31. 1.19. 1.04. 0.49.

. 0.49. 1.05. 1.19. 1.29. 1.20. 1.28. 1.16. 1.01. 0.47.

1.2

1.2. 0.2. -0.8. -0.9. -1.7. -2.3. -2,5. -2.7,

. 0.39. 0. 72. 1.04. 1.03. 1.04. 0. 72. 0.39.

. 0.39

0.73. 1.03. 1.02. 1.02. 0.70. 0.38

1.2.

1.2. -0.8. -1.1. -1.8. -2.1. -2.4.

STANDARD D[VIATION

~o.670

. 0.34. 0.38. 0.34.

. 0.35. 0.37. 0.34.

1.4. -1.8. -1.8.

AVERAGE

. PCT DI FrERENCE.

1, 1

SUMMARY

MAP NO: S2 4 DATE:

7/ 6/85 POWER:

66%

CONTROL ROD POSITIONS:

F-Q(T) 2.016 QPTR:

D BANK AT 164 STEPS F-DH(N) 1.461 NW 1.015 I NE 0.998

1----------

F(Z)

= 1.324 SW 1.004 I SE 0.983 F(XY)

1.400 BURNUP 120 MWD/MTU A.O

-9.22(%)

35 2

5 6

7 8

9 10 11 12 1 3 14 15

I I

R p

N Figure 6.5 SURRY UNIT 2 - CYCLE 8 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER, EQUILIBRIUM XENON M

L K

J H

G F

E D

C B

a:ii*:*o:iio*:*o:ii*:

PREDICTED PREDICTED MEASURED

PCT DIFFERENCE.

, 0.37. 0,41, 0.37.

3.7. 3.4. 3.7.

MEASURED

PCT DIFFERENCE.

o:ii*:*o:ji*:*i:oi*:*i:08*:*i:oi*:*o:ji':*o:ii':

, 0.40, 0.72. 1.07. 1.09. 1.07. 0,71. 0.39,

2.9.

1.2. 1.6.

1.5,

1.9. -0.1. -0.5.

o: 48 * :

i : oi * :

i : i j * :

i : ii* :

i : i; * :

i : ii* :

i :. ; j * :

i : oi * :

o: 48 * :

. 0.49. 1.03. 1.17. 1.30. 1.21. 1.29. 1.17, 1.01. 0.47.

2.5.

1.0. 0.4.

0.9.

0.0. -0:2. -0.1. -0.5, -2.1,

. o: 48. :. o: 94. :. i : ii. :. i : ii. :. i : ii. :. i: 28. :. i : ii. :. i : 25. :. i : ii. :. o: 94. :. o: 48. :

, 0,49. 0.95, 1.20. 1.25, 1.19, 1.28. 1.18. 1.24, 1.19. 0.93. 0.48.

0.9.

0.7, -0.2, 0.3.

0.3. -0.3. -0.3, -0.5. -1.1. -1.5, 0.2.

o: ii*:* i: oi *:

i: ii* :

i: iii*:*;: ii* :

o:ij *:

i: ii*:

o: i1 *: * ; : ; i *: *;:iii* :

i: 2i *: *;: 02 *:

o: ii*:

. 0.39, 1.01. 1.21. 1.25. 1.16. 0.97. 1.21, 0.97. 1.17, 1.24. 1.19. 1.02. 0.40,

. -0.4. -0.4. -0.1.

0.6,

0.0. 0.0.

0.1.

0.6.

0.5. -0.5. -l.8.

0.3.

2.6.

o:12*:*;:i1*:*;:2i*:*i:ii*:*i:2;*:*;:;i*:*i:ii*:*;:;i*:*;:2i*:*i:ii*:*;:2i*:*;:;1*:*o:ii*:

. 0.72, 1.17. 1.25. 1.16. 1.21. 1.16. 1.24. 1.16. 1.22, 1.16. 1.24. 1.17. 0.72.

o.o. -o.o. -0.1. -0.6. o.o. 0.5.

0.7.

1.1.

0.9. -0.3. -1.3. -0.2.

1.2.

A

o:ii*:*;:oi*:*i:2i*:*i:ii*:*o:i1*:*i:ii*:*i:2i*:*i:;.. *:*;:2i*:*;:;i*:*o:i1*:*i:ii*:*i:29*:*i:oi*:*o:ii':

. 0.37. 1.06. 1.29. 1.19. 0.96, 1.15. 1.22. 1.15. 1.23. 1.16, 0.97. 1.17, 1.28, 1.05. 0.36,

2.6.

1.4.

0.4.

o.o, -0.3,

0.1.

0.7. 0.9.

1.2.

0.9, -0.1. -1.2. -0.5. -0.2, -o.o.

. 0.40. 1.08. 1.21, 1.28. 1.21. 1.23. 1.14. 1.16. 1.14, 1.23, 1.21. 1.28, 1.21, 1.08. 0.40,

. 0. 41. 1. 10. 1. 22. 1. 28. 1. 21. 1. 24. 1. 15. 1. 17. 1. 15. 1. 24, 1. 20, 1. 27, 1. 20, 1. 08.. 0. 40,

2.3.

1.5.

0.4.

0.3.

0.2.

0.4.

0.7.

1.0.

0.7.

0.1, -0.6, -1.0, -0.6.

0.1.

0.8,

. o: ii.:. i: 05.:. i: ii.:. i: ii. :. o: 97.:. i: ii.:. i: ii.:. i: iii.:. i: ii.:. i: ii.:. o: ij. :. i: ii.:. i: 29.:. i: 05.:. o: ii. :

. 0.37. 1.06. 1.27. 1.18. 0.97. 1.15. 1.22. 1.15. 1.22. 1.16. 0.97. 1.18. 1.29. 1.06. 0.37.

2,6. 0.8. -1.3. -0.6,

0.2.

0.2,

0.2. 0.6.

0.7.

0.3. -0.2. -0.B.

0.0. 0.8.

2.0.

- ooooooooooroooooooooooooooooooooooooooo********************oooooooooooooooooooooooo*********************

. 0. 72, 1. 17. 1. 25. 1. 16. 1. 21. 1. 15. 1. 2 3. 1. 15

1. 21. 1. 16. 1. 25. 1. 17

0. 72,

, 0.71. 1,15. 1.24. 1.17. 1.21. 1.15. 1.24. 1.15. 1.20, 1.15. 1.24, 1.18, 0.72,

. -1.4. -1.4. -0.8.

0.2.

0.3. -0.2. *0.8, -1.1. -0.8, 0.8.

1.0.

. 0.39

1.02. 1.21, 1.24. 1.16. 0.97. 1.21. 0.97. 1.16. 1.24. 1.21

1.02, 0.39.

, 0.39. 1.02. 1.21. 1.24, 1.16. 0.97. 1.21. 0.96. 1.14. 1.23. 1.20, 1.02, 0,39.

o.6. o.6. cr.4.

0.1. -0.1. -0.2. -0.1. -o.9. -1.6. -1.0. -o.a.

0.1

o.9.

* * * * * *:

o: lf8 *:

o: 94 *:

i: ii*:*;: 2i *:

i: ii*:*;: 25 *:*;:ii*:* i: ii*:*;: 2i *:*a: iii*:* o: 48 *: * * * * * * *

. 0.50, 0.96. 1.21. 1.25. 1.18. 1.27. 1.17. 1.23. 1.19. 0.93. 0.49.

2;7, 1.7,

0.1. -0.4. -0.8. -1.0. -1.4. -1.6. -1.6. -1.6.

0.7.

STANDARD DEVIATION

=0.946

, 0.48. 1.02. 1.17. 1.29. 1.21. 1.29. 1.17. 1.02. 0.48.

. 0.50. 1.06. 1,19. 1.27. 1.19. 1.27. 1.15

1.00. 0.48.

3.4.

4.0.

1.6. -1.5. -2.0. -1.8. -1.9. -2.1. -0.8.

. 0.39. 0.72. 1.05. 1.08. 1.05. 0.72. 0.39.

. 0.40. 0.74. 1.03. 1.06. 1.03. 0.70. 0.38.

4.0.

4.1. -2.1. -1.7. -1.5. -1.7. -2.0.

. 0.36. 0.40. 0.36.

. 0.37. 0.39. 0.35.

4.2. -1.4. -1.4.

SUMMARY

AVERAGE

PCT DI FF ER ENCE *.

1.0 MAP NO: S2 7 CONTROL ROD POSITIONS:

DATE:

7/22/85 F-Q(T)

= 1.848 F-DH(N) = 1.421 F(Z) 1.239 POWER:

100%

QPTR:

D BANK AT 194 STEPS F(XY)

BURNUP

= 1. 377

=

390 MWD/MTU 36 NW 1.009 I NE 1.000

1----------

sw 0.999 I SE 0.992 A.O =

-6.16(%)

2 3

4 5

6 7

6 9

10 11 12 13 14

I I

ii I

I I

I I.

I SECTION 7 REFERENCES

1.

M.

E. Paul, "Surry Unit 2, Cycle 8, Design Report," NE Technical Report No. 446, Virginia Powe~, April, 1985.

2.

Surry Power Station Technical Specifications, Sections 3.12.C.1 and 3.12. B.1.

3.

T. K. Ross, W. c.. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.

4.

"Technical Manual for Westinghouse Solid State Reactivity Computer,"

Westinghouse Electric Corporation.

5.

W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 1967.

37

I I

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l 1

I I

II 1*

I

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I.

I I

APPENDIX A STARTUP PHYSICS TESTS RESULTS AND EVALUATION SHEETS 38

I

.1 I

I

1.

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I I*

I I

.I

1*

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I I

2-PT-28.11 Pate 1 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN

98S I

Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments Test

Description:

Reactivity Computer Checkout Sequence Step *No: LI Station Procedure: 2-PT-28.11 Bank Positions (Steps)

RCS Temperature (°F): 547 Power Level(% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB: 228 CC: 228 CD:

Below Nuclear Heating

At the just crit. position Bank Positions (S'teps)

RCS Temperature (°F): ~'"I, Power Level(% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB: 228 CC: 228 CD: I 6 7 Below Nuclear Heating Date/Time Test Performed:

fo / ;J. 7 /'65 Oq'/b Measured Parameter Pc= Measured p using p-computer (Description) pt= Inferred p from reactor period Pc = +:)7,5' -31.~

- 'f3,o

+ l/8. 'J.

Measured Value

Pt = +~1. S-

~~'3.0

+SO,O

~= 0,0).

- 3," ~- -?,., l

- 3,, '/.

Design Value (Actual Conditions)

%D = [(pc-pt)/pt] X 100% S: 4.0%

Design Value

'Xf*= [(pc-pt)/pt] X 100% S: 4.0%

(Design Conditions)

Reference WCAP 7905, Rev. 1, Table 3.6 FSAR/Tech Spec Not Applicable Reference Not Applicable Design Tolerance is met

lYES _NO Acceptance Criteria is met Allowable Range= + t/'6 YES _NO*

C f~M/

-43 p, ff\\

Evaluated By:

Recommended for I/ 9 Approval By : _C=---...

J.;.:......a:Llccw=.c....;;.... __

NFO Engineer A.l

I.

1.

1*

I I

I

.ll

Attachment 1 Page 2 of 18 SURRY POWER STATION UNIT 2 CYCLE 8

, 1985 STARTUP PHYSICS TEST RESULTS ANO EVALUATION SHEET JUN I

Test

Description:

Critical Boron Concentration - ARO Reference Station Procedure: 2-PT-28.11 Sequence Step No:5" II Banlt Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228

SDB: 228 CA: 228 Other (specify):

(Design)

CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F): S"lh, 1 Test Power Level(~ F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual)

CB: 228 CC: 228 CD: 228 Below Nuclear Heating Date/Time TeS't Performed:

IP/-z et es-

/101 Meas Parame~er IV (Description)

M*

(CB)ARO; Cri~ical Boron Cone - ARO Measured Value (CB)Jo = '"'~' fr""

Test Results Design Value (Actual Cond)

CB= 1427 +/- 50 ppm Design Value (Design Cond)

CB= 1427 +/- 50 ppm Reference NE Technical Report No 446 V

FSAR/Tech Spec aC x CBS 15,115 pcm B

Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met

7 YEs _NO Acceptance Criteria is met

_YES _NO VI Comments ac = -8. 01 pcm/ppm for preliminary analysis B

d..c.

~ -7, ]';).

a f'lm/ PP"' +or f;na I Qn4ly s.'s C-leted Bya~\\b.~

Test Engineer Evaluated By: f!' /.1,f,i._* -

Recommended for

~ {)

A.2 Approval By : _C---"-_""".../._._~---

fl.'FO Engineer

I I,

I I

I

1 I

I I

I

1 I

I I

2-PT-28.11 Page 3 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN I

Test

Description:

Isothermal Temperature Coefficient -

ARO Reference Station Procedure: 2-PT-28.11 Sequence Step No:"

II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design)

CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F): SI/ 7 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual)

CB: 228 CC: 228 CD: ~13 Below Nuclear Heating Date/Time Test Performed:

f'n/'J.7/BS"

/3 07 Meas Parameter IV (Description)

ISO (a T )ARO Isothermal Temp Coeff - ARO Test Measured Value (ar;o) ARO = -4, f&,'/

pcm/°F (CB = l'l3J ppm)

Results Design Value (Actual Cond)

(ar;o) ARO = ~ 5, ;;17 pcm/°F (CB = Jq 3) ppm)

ISO (a T )ARO= -5.31 +/- 3.0 pcm/°F Design Value (Design Cond)

(CB= 1427 ppm)

Reference NE Technical Report No 446 FSAR/Tech Spec ISO aDop _ -1. 70 pcm/°F V

a T S 0.80 pcm/°F T.-

Acceptance Criteria Reference TS 3.1.E, NE Technical Report No 446 Design Tolerance is met

4YES _NO VI Acceptance Criteria is met

_YES _NO Comments

Uncertainty on "T

= 0.5 pcm/°F (

Reference:

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

Completed By: ¥),y.ll.>M>:\\

Test Engineer Evaluated By:

Recommended for Approval By: !'I~

c.2~

NFO Engineer A.3 J

I I

I I,

I I

1*

I I,,

I I

I'*.

I SURRY POWER STATION UNIT 2 CYCLE 8 2-PT-28.11 Page 13 of 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN

,t 198S I

Test

Description:

M/D Flux Map - HZP, ARO Reference Station Procedure: 2-PT-28.2, 2-0P-57 Sequence Step No: 7 II Bank Positions (Steps)

RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): - 3 Conditions SDA: 228 SDB :. 228 CA: 228 Other (specify)

(Design)

CB : 228 cc: 228 CD:

Must have~ 38 thimbles III Bank Positions (Steps)

RCS Temperature(°F): 5<f 7, L Test Power Level (% F.P.):

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

(Actual)

CB: 228 cc: 228 CD : z

.. ;z. 'B' 38 ~~~'"=>

Date/Time Test Performed:

&/zq lt5""

ozz..c MAX. REL NUC ENTHAL TOTAL HEAT QUADRM'T IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description)

% DIFF CHAN FACT.

CHAN FACT RATIO (M-P)/P F*tui(N)

F-Q(T)

QPTR

-i.3.X f..- F;-,3= /.0'1 Measured Value

-f.5"~ f...-~

=0.)2 I,5"4-3

2. 39S-

/. 0 '+4 Test

N Results Design Value t 10\\ far Pi~ 0.9 rff.61r'1.ss11+.,c1-P)J F~(Z) S 4.36 z K(Z)

(Design Conds) t 1s: far Pi< 0.9 S i.02 (Pi* AHy. Pwr.)

WCAP-7905 WCAP-7905 Reference REV.l NONE NONE REV.l V

FSAR/Tech Spec NONE NA NA NA Acceptance Criteria Reference NOfl."E TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met

_YES _KNO Acceptance Criteria is met

-25..YES _NO VI Comments

As Required

A ~I~ (':,ro?t ~

-rk. ~~.J Qf>T(<. "'4-~ -+-k.. k_,.*,r

..r....L-. -,s d.t....J-J. A-ll h..+ ~

~

w~ o..=y+..lk...

Completed By: ~ll), \\b~

Test Engineer Evaluated By: f_O_~

c4:J~

Recommended for Approval By:

A.4 NFO Engineer

I I

SURRY POWER STATION UNIT 2 CYCLE 8 2-PT-28.11 Page 4 of 18 STARTUP PHYSfCS TEST RESULTS AND EVALUATION SHEET I

Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments Test

Description:

Cntl Bank B Worth Meas.,Rod Swap Ref. Bank Station Procedure: 2-PT-28.11 Sequence Step No: [3 Bank Positions (Steps)

RCS Temperature (°F): 547 Power Level (% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (specify):

CB:Moving CC: 228 CD: 228 Below Nuclear Heating Bank Positions (Steps)

RCS Temperature (°F): 5'1'1,S Power Level(% F.P.): 0 SDA: 228 SDB: 228 CA: 228 Other (Specify):

CB:Moving CC: 228 CD: 228 Belo~ Nuclear Heating Da'te/Time Test Performed:

0/~1/BS-

/!;';)J Measured Parameter I~F;In'tegral Worth of Cntl Bank B, (Description)

All Other Rods Out Measured Value IREF _

B -

1306 pc.m Design Value (Actual Conditions)

I~F = 1353 +/- 135 pcm Design Value (Design Conditions)

I~F = 1353 +/- 135 pcm Reference NE Technical Report No 446 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result FSAR/Tech Spec on safety analysis. SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A Design Tolerance is met

XYEs _NO

KYEs _NO Acceptance Criteria is met Test Engineer Evaluated By:

Recommended for Approval By :

A.5 ti~

C~!J. L NFO Engineer

I I

2-PT-28.11 Page 5 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Critical Boron Concentration - B Bank In Reference Station Procedure: 2-PT-28.11 Sequence Step No: q II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design)

CB:

0 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F):S45,~

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

(Actual)

CB:

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

fo/;;.7/55

/'iJ'I Meas Parameter IV (Description)

M (C:B)B; Critical Boron Cone. - B Bank In Measured Value (C )M =

B B I J G l ppm Test Results Design Value I ;>. (p 3. + ;) 7 ppm (Actual Cond)

CB =

Design Value (Design Cond)

Prev I

I CB= 1259 + ~CB

+/-(10 + 135.3/ aC

)ppm B

Reference NE Technical Report No 446 V

FSAR/Tech Spec ac x CB~ 15,115 pcm B

Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met

*YES _NO Acceptance Criteria is met

_YES _NO VI Comments ac = -8.01 pcm/ppm for preliminary analysis B

~cPrev = (C) M B

BARO

-1427 d..e,.. =

B

-7,7J f'C 11'1 I f('lf'\\ -/or /;,,q I aflalys:.s Completed By: Q.~.u~

p:'est Engineer Evaluated By: r.11/L-

c. 2.~

Recommended for Approval By:

A.6 NFO Engineer JUN

I I

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SURRY POWER STATION UNIT 2 CYCLE 8 Page 6 of 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Cntl Bank D Worth Measurement-Rod Swap Reference Station Procedure: 2-PT-28.11 Sequence Step No: I I II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design)

CB:Moving CC: 228 CD:Moving Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature ( °F) : S'I 5, 4 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual)

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

CJl'J 7 /p,5 I q~s Meas Parameter (Description)

I~S;Int Worth of Cntl Bank D - Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_

D -

/J 73 pc.,n Position = l8B steps}

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

IRS_ 1/11 :!

D -

I 7r pc.1n Position = Jt;e, steps)

Design Value I~S= 1192 +/- 179 pcm (Critical Ref Bank (Design Cond)

Position= 193 steps)

NE Technical Report No 446, Reference VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V

FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

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

*YES _NO VI Acceptance Criteria is met

_YES _NO Comments Completed By:

Evaluated By:

Recommended for Approval By:

A. 7 c.J.~

NFO Engineer

I I

1* I I

2-PT-28.11 Page 7 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 JUN

, 1985 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Cntl Bank C Worth Measurement-Rod Swap Reference Station Procedure: 2-PT-28.11 Sequence Step*No: /~

II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level Ci F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design)

CB:Moving CC:Moving CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F): S'/4, J Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual)

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

(p /:;7 /B !,

~030 Meas Parameter (Description)

RS le ;Int Worth of Cntl Bank C - Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS=

C 8 '1;)

f'C,,ri Position = I 3/ steps)

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

IRS= 8 t;). ! 121.- f'C,"'

C Position= 131 steps)

Design Value IRS= 815 C

. +/- 122 pcm (Critical Ref Bank (Design Cond)

Position= 147 steps)

NE Technical Report No 446, Reference VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of t~st result on V

FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met XYEs _No VI Acceptance Criteria is met

\\)(._ YES _NO Comments Completed By:

Evaluated By: /'/,//tL---

Recommended for J

Q Approval By :~C::..__. ____. -~---'---'"-----

NFO Engineer A.8

I I

I

=-

SURRY POWER STATION UNIT 2 CYCLE 8 2-PT-28.11 A ttachrnent 1 Page 8 of 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Reference II

. Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments Test

Description:

Cntl Bank A Worth Measurement-Rod Swap Station Procedure: 2-PT-28.11 Sequence Step No: I..3 Bank Positions (Steps)

RCS Temperature (°F): 547 Power Level (% F.P.): 0 SDA: 228 SDB: 228 CA:Moving Other (specify):

CB:Moving CC: 228 CD: 228 Below Nuclear Heating Bank Positions (Steps)

RCS Temperature (°F): S"{(,p,(:;

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

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

/p/J.8/B ~

/ 3J8 Meas Parameter (Description)

I!5;Int Worth of Cntl Bank A - Rod Swap (Adj. Meas. Crit. Ref Bank Measured Value IRS_

A - 381 p,rn Position= 7'7 steps)

Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) r!5= 37~ t 10Q p~,n Position = 7/p steps)

Design Value r!5= 406 +/- 100 pcm (Critical Ref Bank (Design Cond)

Position= 101 steps)

NE Technical Report No 446, Reference VEP-FRD-36A, NFO-TI-2:2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on FSAR/Tech Spec safety analysis. SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A Design Tolerance is met

lYES _NO Acceptance Criteria is met YES _NO Evaluated By:

Recommended for Approval By:

A.9

~/~!~

c.--1 ~

NFO Engineer

I I

I SURRY POWER STATION UNIT 2 CYCLE 8 2-PT-28.11 PAge 9 of 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN 4 1985 I

Test

Description:

Shutdown Bank B Worth Meas. - Rod Swap Reference Station Procedure: 2-PT-28.11 Sequence Step No: 11 II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB:Moving CA: 228 Other (specify):

(Design)

CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F): Sll~, 'I Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB:Moving CA: 228 Other (Specify):

(Actual)

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

/;J/;;Ble;S--

}"/.61.(

Meas Parameter (Description)

RS ISB;Int Worth of Shutdo~"Il Bank B - Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS=

SB

/03"/ pun Position= J~;;. steps)

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

IRS_ /010 t.

SB-

/S;) pc.~Position = /fe,'J. steps)

Design Value r::= 1022 +/- 153 pcm (Critical Ref Bank (Design Cond)

Position= 172 steps)

NE Technical Report No 446, Reference VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is.exceeded, SNSOC shall evaluate impact of test result on V

FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

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

~ YES __NO VI Acceptance Criteria is met

_YES _NO Comments Completed By, q.U:\\ \\~w,-1 est Engineer oL Evaluated By:

Recommended for Approval By:

A.10 C,2.~

NFO Engineer

I I

I 2-PT-28.11 Page 10 ot 18 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN

' 198!,

I*

Test

Description:

Shutdown Bank A Worth Meas. - Rod Swap Reference Station Procedure: 2-PT-28.11 Sequence Step*No: /.S-II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA:Moving SDB: 228 CA: 228 Other (specify):

(Design)

CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F): ~~s.,

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

(Actual)

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

'/;)e, Jes-IS;).'-1 Meas Parameter (Description)

RS ISA;lnt Worth of Shutdown Bank A - Rod Sv~p IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_

SA-11 l,

pc.,m Position = JBosteps)

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

I!!= JI' I +/- 17"( ('t-m Position = I t3o steps)

Design Value 1RS=

SA 1152 +/- 173 pcm (Critical Ref Bank (Design Cond)

Position= 188 steps)

NE Technical Report No 446, Reference VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V

FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

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

iYES _NO VI Acceptance Criteria is met YES _NO Comments Completed By,C:r.*~, Uii,.lsl>1.

.Test Engineer Evaluated By:O* lttL-Recommended for Approval By:

A.11 C..2 Le>

NFO Engineer

I I

I 2-PT-28.11 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET A ttechrnent 1 Page 11 of 18 JUN

, 198S I

Test

Description:

Total Rod Worth - Rod Swap Reference Station Procedure: 2-PT-28.11 Sequence Step No: /6 II Bank Positions (Steps)

RCS Temperature (°F): 547

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

(Design)

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

RCS Temperature (°F) : S '15, LJ Test

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

(Actual)

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

(i;/;;.7/gr;

/9'15 Meas Parameter (Description)

!Total;Int Worth of All Banks - Rod Swap IV 5"B~3 Test Measured Value 1Total =

pcm Results Design Value 6~otj.:t ~90 f'C f'I)

(Actual Cond) 1Total =

Design Value

!Total= 5940 +/- 594 pcm (Design Cond)

NE Technical Report No 446, Reference VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V

FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.

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

f_YES _NO VI Acceptance Criteria is met YES _NO Comments C-leted By:q.\\)J.~

Test Engineer Evaluated By: /'LJL-c..1L Recommended for Approval By:

A.12 NFO Engineer

I

-I I

I I

=-

2-PT-28.11 Page 12 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 JUN

, 198S STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

HZP Boron Worth Coefficent Measurement Reference Station Procedure: 2-PT-28.11 Sequence Step*No:,V/A II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design)

CB:Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F):.SI.J,n}

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

(Act:ual)

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

ft,/';).e/e,s-

}lt>'f Measured Parameter IV (Description) ac Boron Worth Coefficient B

Measured Value.

ac = -7,6<!>

f'&tn/ ff"'

B Test Results Design Value (Actual Conditions) ac = -8.01 +/- 0.80 pcm/ppm B

Design Value (Design Conditions) ac = -8.01 +/- 0.80 pcm/ppm B

Reference NE Technical Report No 446 FSAR/Tecb Spec aC x CBS 15,115 pcm B

V Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met

'/.

9Jt"YES _NO VI Acceptance Criteria is met

_YES _NO Comments Completed By, ~-~,~

est: Engineer Evaluated By: /'I 1/,L c.2~

Recommended for Approval By:

A.13 NFO Engineer

I I

'I I

I I --

I I

I 2-PT-28.11 Page 14 of 18 *

SURRY POWER STATION UNIT 2 CYCLE 8

'STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

M/D Flux Map - At Power Reference Station Procedure: 2-PT-28.2, 2-0P-57 Sequence Step No: ~d II Bank Positions (Steps)

I RCS Temperature (°F):TREF +/-1 Test Power Level(\\ F.P.): -

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

(Design)

CB : 228 cc: 228 CD:

Must have~ 38 thimbles III

. Bank Positions (Steps)

RCS Temperature(°F): S60 Test Power Level (% F. P. ) : '+'

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

(Actual)

CB : 22S... cc : 228 CD: 157 42- +k,r"",1\\J.CL."o>

Date/Time 'fest Performed:

7/3/~5 o::i~b MAX. REL NUC ENTHAL TOTAL HEAT QUADRA?l.'T JUN

,l -

IV

!'Jeas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description)

DIFF CHAN FACT CHAN FACT RATIO (M*P)/P F-AH(N)

F-Q(T)

QPTR

+- "* ~ ~ i., ~-,.,:,.~

/.4'fo J,o67 Measured Value l,01e, Test rf'#,, ~ +.r P ~ 0,3't Results Design Value

t 10\\ for P1 :t 0.9 (Design Conds) :t is: for P1 < 0.9 NA NA S 1.02 (Pi

usy. Pwr.)

WCAP-7905 WCAP-7905 Reference REV.l NONE NONE REV.1 FOR POWER ~ 50%

FSAR/Tech Spec NONE

~1.ss11+.Jc1-i>>1 F~(Z) S 4.36 x lt(Z)

NA FOR POIIER > 50%

V F~(Z)S2.18/P x lt(Z)

Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met y

XYES _NO Acceptance Criteria is met YES _NO VI Comments

As Required Completed By:q,U), \\~

\\Test Engineer Evaluated Recommended for Approval By: c..:J~

NFO Engineer A.14

I I

I SURRY POWER STATION UNIT 2 CYCLE 8 2-PT-28.11 Page 13 of 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN

, 198S I

Test

Description:

M/D Flux Map - HZP, ARO Reference Station Procedure: 2-PT-28.2, 2-0P-57 Sequence Step No: q3 II Bank Positions (Steps)

RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): - 3 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)

(Design)

CB : 228 cc : 228 CD:

Must have~ 38 thimbles III Bank Positions (Steps)

RCS Temperature(°F): S65 Test Power Level (% F. P * ) : &, 5. S Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual)-..*

CB : 228 cc: 228 CD: /h4 41 +k~~~b Date/Time Test Performed:

7/,18~

l.

). 3 6 MAX. REL NUC E?li"THAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HiJT FLUX HOT PO\\i.7ER TILT (Description)

% DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-tJi(N)

F-Q(T)

QPTR

-z.,i. hr f,_; I,~'/

Measured Value 1.4/o I

~.o.,,

l.otS Test

'.(. e. :. tJ,617 Results i-;),7'/. *r D-13 Design Value

% 10% for Pi~ D.9 r".61r'1.ss11+.3Cl*P>J F~(Z) s 4.36 a: 1:(Z)

(Design Conds)

% 1s: for P1 < D.9 S 1.02 (Pi* Assy. Pwr.)

WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.1 V

FSAR/Tech Spec NONE NA NA NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met

*YES _NO Acceptance Criteria is met

_YES _NO VI Comments

As Required C-leted By,~-~,~

Test Engineer Evaluated By:~LLA,..*---

Recommended for Approval By:

A.15 CJ.~

NFO Engineer

I I

I 2-PT-28.11 Page 16 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN

, 198~

I Test

Description:

M/D Flux Map - At Power, NI Calibration Reference Station Procedure: 2-PT-28.2, 2-0P-57 Sequence Step No:~~

II Bank Positions (Steps)

RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): -

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

(Design)

CB : 228 cc: 228 CD: **

III Bank Positions (Steps)

RCS Temperature(°F): s-~4 Test Power Level(% F.P.): C,-:J.o Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): Q"~.,*h-r - Co-,£ (Actual)

CB : 228 cc : 228 CD: l1B 1/..,,J.. yr,,...,) t-L,., s f ow.-r d;!>i.r: L"' t; o"'

Date/Time Test Performed:

V<ilvt"5 o.~ nof ~fpl;cql>/r:,.

7)7/f)~

03oo l?~~~c;:

MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description)

% DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-lui(N)

F-Q(T)

QPTR Measured Value NA fJA NA NA Test Results Design Value

+/- 101; for P1 ~ D.9 (Design Conds) +/- is: for Pi< 0.9 NA NA S 1.02 (Pi* Assy. Pwr.)

WCAP-7905 WCAP-7905 Reference REV.l N0t-.7E N0?'\\7E REV.l V

FSAR/Tech Spec NONE r"'~l.55(1+.3(l*P)]

Fi(Z)S2.1&/P z ~(Z)

NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met j..

7 YES _NO Acceptance Criteria is met

_YES _NO VI Comments

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

- As Required Evaluated By:

Test Engineer Recommended for r1 Approval By : _.C_. ___ ___;..J. _.___._..=.,~

NFO Engineer A.16

I.

I I

I*

I 2-PT-28.11 Page 17 of 18 SURRY POWER STATION UNIT 2 CYCLE 8 STARTUP PHYSICS TEST RESULIJ"S AND EVALUATION SHEET JUN

'185 I

Test

Description:

M/D Flux Map - At Power, NI Calibration Reference Station Procedure: 2-PT-28.2, 2-0P-57 Sequence Step No:~S" II Bank Positions (Steps)

RCS Temperature (°F):TREF +/-1 Test Power Level ci F.P.): - 70 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):*

(Design)

CB: 228 cc: 228 CD: **

III Bank Positions (Steps)

RCS Temperature(°F): 5'-S Test Power Level(\\ F.P.): '=,S.o Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): Oucrtter _ Ci.rt:

(Actual)

CB: 228 cc: 228 CD: /, 1 f/lJ ~ wi.a (' J t4... s powu dis{,.'but:o" Date/Time Test Performed:

y.,/ 1Ji:S Cl'I'~ ~ot ci ppn,.. 1o1~.

7/1/es o~s-o 17+h,~ok.s MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description)

DIFF CHAN FACT CHAN FACT RATIO (M*P)/P F*AH(N)

F*QCT)

QPTR Measured Value rJA tJ A

/JA NA Test Results Design Value z llli for P1 ~ 0.9 (Design Conds) z is: for P1 < o.,

NA NA

£ 1. 02 (Pi* A.1117. J'wr.)*

WCAP-7905 WCAP-7905 Reference REV.l NONE NONE REV.1 V

FSAR/Tech Spec NONE 1"~1.55[1+.3(1*P)J r1cz:,s2.1e1P

KCZl NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met

.2LYES _NO Acceptance Criteria is met

~YES __NO VI Comments

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

~

at least 16 thimbles for a quarter-core flux map.

I

- As Required Compl~ted By:O:lli,~

U'est Engineer Evaluated Recommended for Approval By: c.2~

NFO Engineer A.17

I I

I SURRY POWER STATION UNIT 2 CYCLE 8 2-PT-28.11 Page 18 of 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN

, 1985 I

Test

Description:

M/D Flux Map - HFP, ARO, Equilibrium Xenon Reference Station Procedure: 2-PT-28.2, 2-0P-57 Sequence Step No: 4" II Bank Positions (Steps)

RCS-Temperature (°F):TREF +/-1 Test Power Level Ci F.P.): 95 +/- 5 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): Eq. Xenon (Design)

CB: 228 cc: 228 CD:

Must have~ 38 thimbles III Bank Positions (Steps)

RCS Temperature(°F): 57'{

Test Power Level(% F.P.): 100 /.

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

(Actual)

CB: 228 cc: 228 CD: M~

41 -i~ imb /e-s Date/Time Test Performed:

7/zz/e~

/O:i./8 MAX. REL NUC Efl."THAL TOTAL HEAT QUADRM"T IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description)

% DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F*lili(N)

F*Q(T)

QPTR

+ 11,o'J. for-P.

I.a, l~~

1.4;)_ I J. B4~

I.DOC/

Measured Value Test If-f. J ~ IOT ~::037 Results Design Value

+/- 10'1 for Pi~ 0.9 (Design Conds) +/- 1s: for Pi< o.,

NA NA S 1.02 (Pi* Aasy. Pwr.)

WCAP-7905 WCAP-7905 Reference REV.l NONE NONE REV.1 V

FSAR/Tech Spec NONE r"~1.ss11+.3Cl*P>J ricz,s2.1a/P z ECZ>

NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met

+/-YES _NO Acceptance Criteria is met YES _NO VI Comments

As Required Completed By, 11/ Ilk Evaluated By: /'! lJ_L-

/Test ngineer Recommended for c.J~

Approval By:

NFO Engineer A.18

I I

1 I

I I

I Appendix B DEVIATION REPORT FOR THE ALL-RODS-OUT FLUX MAP 39

rio. :n ~oilla.,iu Rev. O.

IEVIATI Oi tt:PCf.T SURRf PGER STATIO~.

ADM-2j.6 Appendix I Figura B-1 Page l of 6

o 7 198 I

u..,,t 2 CY':,'e ~) *Hoe gwcoload: p2w:1k t,'/f r:eh':P (GPTR.)) abt?,t1W kU:t'n!

(3 ~II (!o.,,...~ £!wt m~,., g.,f t?:"PCP?Si'n:10fe/" 3& opwer cv*th t:a.!f Cor:tn:f I

I I

I o,,-

C HUMAN ERROR a*PROCEDURE/DRAWI NG ERROR O COMPONENT FAILURE ODES I GN 1

CENVIRONHENJ.AL ___ j(OTHER(SPECIFY) Tb& poke:k'< cw;se. it '3!0 ~.ss,rme.fr,'Ss

£c+P a:55..ewk/,, reAcb'v,'f;t d*'>b:*'kttHs:n,d,icL,\\ 4tmwP:n e-i: low "oiu:e::e l:exxfa fo//2:<<,*~ refue(c'to~,

1 JNITIAL N:rlOH/~

,4 c~v,'cw 0£ +4, meau1,..-k{ ¢0:W 00c.f:'r,ne,.;( fb,,;f +(4 I

tl1F4SHCW aeTJ?- ex.ceeded ff& des,'jn 3u.o'k/i'~, An e-14,'hme-f fkeR Gpye,

£fw,. mep 54 mll be.. m ea <y,..-5:c:K' '3"'-I et1 a(vire.R a+/- a e QCP<'I 1'w6ff l;: 3 O ~~

O'IHCII l.allT alN)ITICIN DA'n: {p-zq -'FJS-I FORJrlARO TO 9il FT SlFERVl~

QAD( MIE J D a 1151) g/c,u Tl CAL CJ STEADY I!

STATE CCliPCICNT' / SYS I EM STATUS 17 NIii: NC1T I P' 1 CAT1 C2II

( ADM H. I

APP A J I

lj~

T.~YV~TI...

DE~

~1:"~R a,JI" SI.PERVISOR

.~4C--t DAn:~-d-'. -~ F TIJC /N,! 1 I -*r ____________

F_miARD

...... 11111111111111111TO

...... s_lPT.....,._CP_E_~_n_ooslllllllllll ____________

z WRITIEN ~

I

~-REPORTABLE.

I I

OREPORTABLE, TYPE:

DAYS CllOCFR.21 DATE VERI P'IG IIY DATE DJSTRIBUT"IOO GOPY TO:

0SES OCTS CNRC 0STATION HANAGEHENT OCORPORATE HANAGEHENT

W'lll.MM l STE\\'1ART Vice President Nuclear Operations July 30, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Steven A. Varga, Chief Operating Reactors Branch No. 1 U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

VIRGINIA POWER SURRY POWER STATION Nuclear Operations Department Post Office Box 26666 One James River Plaza Richmond, Virginia 23261 VIRGINIA POWER Ser'ial No.85-544 NOD: ESH Docket No. 50-281 License No. DPR-37 UNIT 2, CYCLE 8 STARTUP PHYSICS TEST REPORT For your information, enclosed are five copies of the Virginia Power Topical Report VEP-NOS-18, "Surry Unit 2, Cycle 8 Startup Physics Test Report".

Should you have any questions, please contact us.

Very truly yours, Enclosures cc:

Dr. J. Nelson Grace Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station

ML18143B353

Text

SUMMARY

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1.412 BURNUP 31 MWD/MTU A.O

SUMMARY

1.400 BURNUP 120 MWD/MTU A.O

SUMMARY

Description:

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