ML18141A196

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Cycle 7 Startup Physics Test Rept.
ML18141A196
Person / Time
Site: Surry Dominion icon.png
Issue date: 10/31/1983
From: Hendrixson E, Lozito E, Snow C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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ML18141A195 List:
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VEP-NOS-7, NUDOCS 8311090247
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VEP-NOS-7 Vepco SURRY UNIT 2, CY!'CLE 7 STARTUP PHYSICS TEST REPORT NUCLEAR OPERATIONS DEPARTMENT Virginia Electric and Power Company

VEP-NOS-7 SURRY UN IT 2, CYCLE 7 STARTUP PHYSICS TEST REPORT BY E. S. Hendrixson Reviewed By: Approved By:

C. T. Snow, Supervisor Nuclear Fuel Operation Subsection Subsection Nuclear Fuel Operation Subsection Nuclear Operations Department Virginia Electric and Power Co.

Richmond, Va.

October, 1983

CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Company (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 pripr 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.

i

ACKNOWLEDGEMENTS The author would like to acknowledge the cooperation of the Surry Power Station personnel in performing the tests documented in this report. Also, the author would like to express his gratitude to Mr. C. T. Snow for his aid and guidance in preparing this report.

ii

TABLE OF CONTENTS SECTION TITLE PAGE NO.

Classification/Disclaimer.................. i Acknowledgements. . . . . . . . . . . . . . . . . . . . . . . . . . . ii List of Tables ................... _. . . . . . . . . . iv List of Figures. . . . . . . . . . . . . . . . . . . . . . . . . . . . v Preface.................................... vi 1 Introduction and Summary................... 1 2 Control Rod Drop Time Measurements......... 10 3 Control Rod Bank Worth Measurements........ 15 4 Boron Endpoint and Worth MeB;surements...... 20 5 Temperature Coefficient Measurement........ 24 6 Power Distribution Measurements............ 27 7 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 APPENDIX *startup Physics Test Results and Evaluation She~ts ...*. ~*..... ............... 35

/

iii

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......... 25

6. 1
  • Incore Flux Map Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 6.2 Comparison of Measured Power Distribution Param-eters With Their Technical Specifications Limits... 30 iv

LIST OF FIGURES FIGURE TITLE PAGE NO.

1.1 Core Loading Map. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1.2 Beginning of Cycle Fuel Assembly Burnups ................ . 6 1.3 Incore Instrumentation Locations......................... 7 1.4 Burnable Poison and Source Assembly Locations............ 8 1.5 Control Rod Locations.................................... 9 2.1 Typical Rod Drop Trace. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 2.2 Rod Drop Time - Hot Full Flow Conditions................. 14 3.1 Bank B Integral Rod Worth - HZP.......................... 18

-~ 3.2 Bank B Differential Rod Worth - HZP...................... 19 4.1 Boron Worth Coefficient.................................. 23 5.1 Isothermal Temperature Coefficient - HZP, ARO............ 26 6.1 Assembly*Power Distribution - HZP, ARO................... 31 6.2 Assembly Power Distribution - 46.5% Power................ 32 6.3 Assembly Power Distribution - HFP, Eq. Xenon............. 33 V

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 7 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 cur~ory 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 Surry 2, Cycle 7 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 Vepco's Nuclear Fuel Engineering 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. The Appendix to this report contains the final completed and vi

approved version of the Startup Physics Tests Results and Evaluation Sheets .

. vii

SECTION 1 INTRODUCTION AND

SUMMARY

On June 30, 1983 Unit No. 2 of the Surry Power Station was shutdown for its seventh refueling. During this shutdown, 61 of the 157 fuel assemblies in the core were replaced with fresh fuel assemblies. The seventh cycle core consists of 6 sub-batches of fuel: one once-burned batch from Cycle 6 (sub-batch 8A), two twice burned sub-batches that were carried over from Cycle 5 (sub-batches 7A2 and 7B2), one thrice burned sub-batch that was carried over from Cycle 4 (sub-batch 6B5), and two fresh sub-batches (sub-batch 9A and sub-batch Sl/9C). The core loading pattern and the design parameters for e_ach 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 7. Figure 1. 5 identifies the location and number of control rods in the Cycle 7 core.

On September 25, 1983 at 1902,

  • the seventh cycle core achieved initial criticality. Following criticality, startup physics tests were performed as outlined in Table l_. l. 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 and were found to be within
5. 6% of the design predictions. The sum of the individual control 1

rod bank worths was measured to be within O. 9% of the design prediction.

  • These results are within the design tolerance of +/-15%

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

3. Critical boron concentrations for two control bank configurations were measured to be within 24 ppm of the design predictions.

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

4. The boron worth coefficient was measured to be within 2.5%.of the design prediction, which is within the design tolerance of +/-10%

and met the accident analysis criterion.

5. The isothermal temperature coefficient for the ARO cpnfiguration was measured to be within O. 55 pcm/ °F of design predictions. This is within the design tolerance of +/-3 pcm/°F and met the accident analysis acceptance criterion.
6. Core power distributions at HZP indicated measured assemblywise power values to be somewhat larger than the established design tolerance. These higher-than-expected power values were accompanied by a quadrant power tilt ratio (QPTR) which at hot-zero-power, was measured to be approximately 2.9%, but decreased to O. 7% at full power. Core power distributions for various at-power conditions were generally within 8% of the predicted power distributions. these deviations of power 2

distribution at HZP had no adverse consequences since, for all maps, the hot channel factors were measured to be within the limits of the Technical Specifications.

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

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

3

Table 1.1 SURRY 2 - BOL CYCLE 7 PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 9/21/83 0830 HSD PT-7 Reactivity Computer Checkout 9/25/83 2200 HZP PT28 .11 (B)

Boron Endpoint-ARO 9/26/83 0958 HZP PT28. ll(C)

Temperature Coefficient-ARO 9/26/83 1021 HZP PT28. ll(D)

Flux Map-ARO 9/26/83 1547 HZP OP-57, PT28.2 Bank B Worth 9/26/83 2330 HZP PT28.ll(E)

Boron Endpoint-B In 9/27/83 0716 HZP PT28 . .ll(C)

Bank D Worth - Rod Swap 9/27/83 0811 HZP PT28. ll(F)

Bank C Worth - Rod Swap 9/27/83 0849 HZP PT28. ll(F)

Bank A Worth~ Rod Swap 9/27/83 0920 HZP PT28. ll(F)

Bank SB Worth - Rod Swap 9/27/83 0947 HZP PT28. ll(F)

Bank SA Worth - Rod Swap 9/27/83 1020 HZP PT28. ll(F)

Flux Map - NI Calibration 9/29/83 0912 46.5% OP-57, PT28.2 Flux Map - NI Calibration 9/29/83 1458 53.9% OP-57, PT28.2 Flux Map - NI Calibration 9/29/83 2054 66.0% OP-57, PT28.2 Flux Map - HFP, Eq. Xenon 10/5/83 1210 100% OP-57, PT28.2 4

Figure 1. 1 SURRY UN IT 2 - CYCLE 7 CORE LOADING MAP I

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12P 12P 2 BP 16P ss 16P BP 3 16P 20P 4P 20P 16P 4 BP 16P 16P

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Figure 1.5 SURRY UNIT 2 - CYCLE 7 CONTROL ROD LOCATIONS R P N H L K J H G F E D C B A 180° I LOOP B LOOP C OUTLET INLET 1 N-41

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Control Bank D 8 Control Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 SP (Spare Rod Locations) 8

I SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at cold and 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 Techntcal 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 10

bouncing. This procedure was repeated for each control rod.

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.1 2 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

Table 2.1 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TEST HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME K-6, 1.29 sec. P-6, 1.20 sec. 1. 25 sec.

ROD DROP TIME TO BOTTOM OF DASHPOT SLOWEST ROD FASTEST ROD AVERAGE TIME G-9, 2.04 sec. M-12, 1.87 sec. 1. 97 sec.

12

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  • l SURRY UNIT 2 - CYCLE 7 BOL PH!SICS TEST TYPICAL ROD DROP TRACE

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--- *-~ -- *-- ***-.*

- --1---..----,--1-f---~--~--- -- . I

. --- _* I

-+--+--.J---l-+--+ 1-....J-~---* - * - * - - ...

.. - .. .1 .

--TlHl~. TRAC.E~STA-r\oN:Bu~

.. . . . fRr;QUENc'i

Figure 2.2 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TEST ROD DROP TIME - HOT FULL FLOW CONDITIONS R p N M L K J H G F E D C B A I

I I I I I I I I 1

---.---1--1--1-.--1---.---

I 1. 211 I I 1. 26 I I 1. 25 I 2 I 11.9111 li.981 11,941 I 2 1--1--1--1--1--1--1--1--1-.-*-1 I I I I 1 . 23 I I 1. 25 I I I I 3 I I I I 2. 01 I I 1. 93 I I I I 3 1--1--1--1--1--1--1--1--1--1--1--1 I I 1

  • 22 I I 1 . 22 I I I I 1
  • 23 I I 1 . 28 I I 4 I I 1* 90 I I 1
  • 911 I I I I 1* 95 I I 2. 01 I I 11 1--1--1--1--1--1--1--1--1--1--1--1--*1--1 I *.I I I 1. 25 I I I I I I 1. 28 I I I I 5 I I I I 1, 98 I I I
  • I I I 1 . 98 I I I ,I 5 1--1--1--1--1--1--1--1--1--1--1--1--1--1 I 1. 20 I I 1
  • 21 I I 1. 29 I I 1. 27 I I 1. 25 I I 1. 24 I I 1. 28 I 6 11.961 11,941 12.011 11,991 11,961 11,971 12.011 6 1--*

I 1--1--1--1--1--1--1--1--1--*-1--1--1--1--1--1 I I 1.22 I I I I 1 .25 I I 1 .26 I I I I 1.26 I I I 7 I I I 1. 99 I I I I 1. 93 I I 2. 02 I I I I 1. 99 I I I 7 1--1--1--1--1--1--1,--1--1--1--1-*--1---1--1--1--1 I I 1

  • 211 I I I I 1
  • 28 I I I I 1 . 24 I I I I 1
  • 28 I I 8 I I 2.03 I I I I 1.96 I I I I 1;97 I I I I 2.03 I I 8 1--.1--1--1--1--1--1-.-1--1--1--1--1-.--1--1--1--1 I I I 1. 25 I I I I 1. 25 I I 1, 26 I I I I 1. 23 I I I 9

1--1--1--1--1--1--1--1--1--1--1--1--1--1--1--1I I I I 1. 93 I I I I 1, 96 I I 2. 011 *1 I I I -1. 96 I I 9 I 1.21 I I 1.24 I I 1.28 I I 1.25 I I 1.29 I I 1.23 I I 1.22 I 10 I 1.89* I I 2.04 I I 2.01 I I 2.01 I I 1,99 I I 1.94 I I 1,93 I 10 1--1--1--1--1--1--1--1--1--1--1--1--1--1 I I I I 1.26 I I I I I I 1,29 I I I I 11 1--1--1--1--1--1--1--1--1--1--1--1--1--1I I I I I 1. 97 I I I I I I 1 ;99 I I I 11 I I 1.23 I I 1.22 I I I I 1.26 I I 1,24 I I 12 .I 1--1--1--1--1--1--1--1--1--1--1--

11,871 11,971 I I 11.971 11.9111 1

  • I 12 I I I I 1, 23 I I 1 . 26 I I I I 13 1

I I I

--1--1-.--1--1--1--1--1--1--

I 1. 93 I I 1. 911 I I I 1I 13 I I 1* 27 I I 1. 28 I I 1* 23 I I I I I I I I 1.97 I 14 1_ _ 1 2.02

__ 1--1--1--1--1 1,98

__ 1I 14 15 I I I I 15 I I I I 1_ _ 1_ _ 1_ _ 1 R* P ~ ff L K J H G F E D C B A 1--1 I I m ROD DROP TIME TO DASHPOT ENTRY (SEC *. )

I I* - ROD DROP TIME TO l_~I BOTTO~ OF DASHPOT (SEC.)

14

SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtained for all control and shutdown banks using the rod swap 3 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 st~tepoint 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

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 the Appendix, 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 -*o. 9% of the design prediction. This is well within the design tolerance of +/-10% for the sum of the individual control rod bank worths.

The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. Figure 3. 2 indicates that the measured differential rod worth for Control Bank B is somewhat different from the predicted differential rod worth. However, the measured integral rod worth demonstrates good agreement with the design prediction (-3. 3%),

therefore this test met the acceptance criteria and design tolerance. In summary, all measured rod worth values were satisfactory.

16

Table 3.1 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TEST CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH BANK (PCM) (PCM) (M-P)/P X 100 B-Reference Bank 1254 1297 -3.3%

D 1121 1146 -2.2%

C 776 794 -2.3%

A 469 444 5.6% (25 pcm)

SB 799 830 -3.7%

SA 1116 1077 3.6%

Total. Worth 5535 5588 -0.9%

17

Figure 3. 1 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TEST BANK B INTEGRAL ROD WORTH - HZP B BANK WITH ALL OTHER ROOS OUT

- - PREDICTED M 11ERSURED

  • o 0

N 0

0 N-0 0

l

c I--

a::: 0 . ... ~

0 0 3: ""

. ...J i'

I*

er: It a:::: '"'- '

0 ~

lLI 0 1-- ..... "

<X) z ,I I"

I

'I

.. I' 0

Ill, '

'lit' **r,. '

-

  • 1,i 0 40 80 120 160 200 228 BANK POSITION (STEPS) 18

l Figure 3.2 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TEST BANK B DIFFERENTIAL ROD WORTH - HZP B BANK WITH ALL OTHER ROOS OUT

- - PREDICTED llE 11EASURED 0

0 C\J I

I I

I I

I 0

0 I a...

LLJ 0

'u

""I<.

~ '

1- ,

,o (f) lu

... " /

I:<=? . c.-

I Uco .HII:

a...

I/

~

' "' ~

I l

J:.

1-o a::o

~

~c... ..:~ tf. ~

0~

3: .

J f *-1 ..

j "'

ll . ,. * ,

f

- :II I I

_J it '

I a: ~

-o I 1-0 "

z*

LLJ~ I i a:: It I LLJ I LL I LLo "

-o

0. ~

,C\J

\IC n.N I

,jll ,

... ~

~-

I

\

- r--

'0 H 0

. i-00 40 BO

  • 120 160 200 226 BANK POSITION (STEPS) 19

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 tabl~ and in the Startup Physics Test Results and Evaluation Sheets given in the Appendix, all 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

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 -8.09 pcm/ppm. The measured boron worth coefficient is within 2.5% of the predicted value of -8.30 pcm/ppm and is well within the design tolerance of +/-10%. The measurement result also met the accident analysis acceptance criterion. In summary, this result was satisfactory.

21

Table 4.1 SURRY UN IT 2 - CYCLE 7 BOL PHYSICS TEST BORON ENDPOINTS

SUMMARY

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

ARO 1379 1403 -24 B Bank In 1224 1220* 4

  • 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 the Appendix.

22

.Figure 4. 1 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TEST BORON WORTH "COEFFICIENT l!IENDPOJNT nERSUREnENTS 1--l--1---l---1--l--l---1---l---1---1---1--1--'--I-- 1--- - - --1--1--1-- -1--1--1-- -- - -- -

,__ a

.!!1!.._ac * -8.09 pcm/ppm

- ' - *-1--,---1-- --1--+--+--1--+--1-i--

  • B I: 1600 u

a_

1--1--1---l---1--l---l--1--l-+--1--1-I -J-l--1-1-l--l-1-1-l---l---i--ll-,--lf-lf--J-I--J--f** .__ t--l-~--lf-ll~~~f-l-+---i--t--1 *-+---1---1--1-1-1-~--1-1-1-1-1--+--*-

~ 1""----+--+--J--J--+--+-~-+-+-+--~-+-+--I---J---f---l---i---i-l---l--

t- I~:-.....:.

- 1 2 00 -f-~~-1--1--1--l-+-+-+-+--J--J--J--J--J--J--J--J--J--J--J--J--l-~--1--1--l--l---1---I---I---!

....... r--,....

t-u a:

~ 800

-~---1--1----l---1--I-- ,-..

r--.... ,__

1--l---1---l--l-+--J-+-+-+--l--1--l-+--l--l--~"'k--l--1-1---1-+--+--*l-l-l--l-l-l--l--l-l l--1--1---l---l---1---l---1---l---l---1---1-- i---,1--1-1-11-ll--=l~~

........ r-.......

=- - --

40Q ........ r-........

-+--1---1--1--l--l--l--l--l--l--lf , - - - --t-t-1--t-l-l-l--'1~1---1--1-- -t--+*--t-*-

r--,....

l-lf--t-1-- t - * - + - - l - - t -

  • t -
  • 1 ~ 1 - ' - - - t - - l - - -4,-1--- -
  • 1 -
  • _ , _ _ _ , _ '.:::::,. f;::::: __ ,_ t - - t - -

i-....._

t-+-+-+-+-+-+-+-+-+--1----1--*~-i--- **- - - *-- --- ---**- --* - ~ - - - -- - - . *- ~ - - *-

r----.. ....

0 -

1220 1240 1260 1280 1300 1320 1340 1360 1380 BORON CONCENTRATION lPPMl

SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient measurement was accomplished by controlling the RCS heat gains/losses with the steam dump valves to the condenser, and/or steam generator blowdown establishing a constant and uniform heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer. This measurement was performed at a very low power level in order to minimize the effects of non-uniform nuclear* heating, thus, the moderator and fuel were approximately at the same temperature (between 542-546 °F) during the

.measurement. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level was maintained constant or slightly increasing during the measurement.

An isothermal t"emperature coefficient measurement was performed at the ARO configuration. Reactivity measurements were taken during both RCS heatup and cooldown ramps during which the RCS temperature varied approximately 4°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 plots of reactivity changes versus RCS temperature for each measurement are 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 the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of +/-3 pcm/°F and met the accident analysis acceptance criterion. In summary, the measured results were satisfactory.

24

Table 5.1 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

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

POSITION RANGE CONCENTRATION (OF) (ppm) COOL DIFFER.

HEATUP DOWN AVER. FRED. (M-P)

ALL 542.3 RODS to 1380 -5.23 -5.03 -5.13 -5.68 0.55 OUT 545.7 25

Figure 5.1 SURRY UN IT 2 - CYCLE 7 BOL PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT HZP, ARO

- ..i* ...

... ~- "...

'7, ~

..-"I

~

- .... r,.._.

,11.:.;;

'""' .. II"'*

i~...,

~"' ....

-~...

~

na

... ~

!..l

  • ~

VERTICAL SCALE 10.00 pcm/inch HORIZONTAL SCALE 1°F/inch ' ....

TEMPERATURE (°F) 26

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 moni tared 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 full-core 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 zero power.

This flux map serves as the base case design check. Figure 6.1 shows the resulting radial power distribution associated with this flux map. This map indicated the presence of a quadrant power tilt (2. 9%) and some assemblywise relative power values in excess of the design tolerance, but all measured hot channel factor values were within the Technical Specifications limits. Flux Maps 2 and 5 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 27

distributions at various operating conditions. These maps also provide incore/excore calibration data for the nuclear instrumentation system.

The radial power distributions for these maps are given in Figures 6.2 and 6.3. These figures show that the measured relative assembly power values are generally within 8% of the predicted values, and that the quadrant power tilt ratio decreased significantly during power ascension.

In conclusion, all power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the Technical Specification limits. It is therefore anticipated that the core will continue to operate safely throughout Cycle 7.

28

TABLE 6. 1 SURRY UN IT 2 - ,CYCLE 7

  • BOL PHYS ICS TESTS INCORE FLUX MAP

SUMMARY

1 2 BURN F-Q(T) HOT

  • f-DH(N) HOT CORE f(Z) 4 UP BANK CHANNEL FACTOR CHNL. FACTOR MAX 3 QPTR AXIAL NO.

MAP MAP DATE MWP/ PWR D f(XY) Off Of DESCRIPTION NO. MTU (%) STEPS AXIAL AXIAL SET THIM ASSY PIN POINT f-Q(T) ASSY PIN f-DH(N) POINT f(Z) MAX LOC ( %) BLES ARO 1 9-26-83 0 0 211 E10 IH 14 2.439 E10 IH 1.519 14 1.562 1.491 1.029 NE 31.52 38 46.5% POWER 2 9-29-83 10 47 178 C10 GH 31 1.943 L13 MN 1.459 24 1. 275 1. 424 1. 011 NE 0.16 38 5

HFP, EQ. XENON 5 10- 5-83 198 100 228 po IH 33 1. 761 L10 GH 1.420 34 1. 177 1. 378 1.007 NE -1. 35 38 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 SEVENTEEN ROWS OF FUEL RODS LETTERED A THROUGH RAND THE 'X" COORDINATE DESIGNATED IN A SIMILAR MANNER).

IN THE "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. MAPS 3 AND 4 WERE QUARTER-CORE FLUX MAPS TAKEN FOR INCORE/EXCORE DETECTOR CALIBRATION.

Table 6.2 SURRY UNIT 2 - CYCLE 7 BOL 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 2.44 4.18 41.6 1.52 1.86 18.3 2 1.94 4.36 54.9 1.46 1. 72 15 .0 5 1. 76 2.18 19.2 1.42 1.55 8.4

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

30

Figure 6.1 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION

  • HZP, ARO R p- N H L K J H G F E D C B A PREDICTED **** PREDicri:o* .*
  • MEASURED .
  • MEASURED .
  • PCT DIFFERENCE. .PCT DIFFERENCE *
  • 0.37. 0.73. 1.09. 1.15. 1.09. 0.73. 0.37- *
  • 0.36 . D.74. 1.15. 1.23 . 1.19
  • 0.73
  • 0.36 . 2
  • -3.5. 1.0. _5.5. 6.7
  • 9.0. -0.2 * -3.8.
*o: ii;*:* j: ai *:
  • j: jg*:* j: 2i * :: i: 2i":
  • j: 2i *: *;: ;9 *:
  • j: ai": *a: ii;*:
  • 0.46
  • 0.99
  • 1.18 . 1.24
  • 1.33
  • 1.27 . 1.19 . 1.01 . 0.45 . 3
  • -3,5 . -3.5 . -0.7. 2.3
  • 8.6 . 4.8 * -0.2 * -2.4 * -3.9 .
  • a:ii,*:* a:aii": * ;: ;r: *,:2i* :*,:2j*:*;: ;;*:*;:2r:
  • j:2i*: *;: ;6*:
  • a:aii*:
  • a:4r:
  • 0.46 . 0.81
  • 1.12 . 1.20. 1.24. 1.16 . 1.26 . 1.2J
  • 1.17 . 0.85
  • 0.47
  • 4
  • -2.9. -2.9 * -3.2 . -2.4 . 0.8. 0.6 . 2.5 * -0.1
  • 1.0
  • 1.7 * -0.2 *
  • a:i;*:*;:a2*:*;:;;*:*~:ii*:*i:2;*:*;:ai*:*j:2;*:*j:ai*:*j:2;*:*o:ii*:*j:i;*:*i:a2*:*a:i1*:
  • 0.36 . 0.99. 1.13
  • 0.97. 1.22. 0.98 . 1.20 . 1.UO . 1.25 . 1.00 . 1.23 . 1.04 . 0.35 . 5

, *2.9 * -2.9 * -1.7 . -1.5 * -2.3 * -4.7. -4.1 * -2.5 . 0.4

  • 1.8
  • 6.7 . 1.7 . -4.4
  • oo*o****************************************************************************************
  • 0.72'. 1.17. 1.21. 1.24. 0.98. 1.22. 1.19. 1.22. 0.98. 1.24. 1.21. 1.17. 0.72 .
  • 0.72. 1.16. 1.21 . 1.25. 0.96. 1.16. 1.12. 1.17. 0.97. 1.28. 1.26. 1.20. 0.69. 6
  • -0.9 * -0.9 . -0.1
  • 1.6 . -1.5 . *4.9. -5.8 . -4.6 * -0.7
  • 3.3
  • 4.0
  • 1.9 * ~4.3-.
  • a: 49 *:
  • i:ai *:*;:ii*:* j:22 *:
  • i :ai *: *; :2i *:*a: ii*:* j:; i *:*a: ii*:* j:2j *:
  • i: aj *:
  • j: 22 *:
  • j: jg*:*; :ai *:*a: 49 *:

, 0.45. 1.04 . 1.20. 1.23 . 1.04. 1.19 . 0.96. 1.08. 0.96 . 1.17 . 1.04 . 1.24 . 1.25 . 1.17 . 0.54 . 7

, -9.9 . -3.4

  • 1.0 . 1.5
  • 2.1 . -1.1 * -3.5 . -4.2 * -3.2 . -2.8 . 2.4 . 2.3
  • 4.9
  • 8.6
  • 8.5 *
  • a:ai*:*;:jii*:*;:2i*:*j:j6*:*j:2i*:*;:i,*:*;:;i*:*;:;ii*:*;:;;*:*;:;;*:*;:2i*:*j:j6*:*;:2i*:*j:iii*:*a:ai*:
  • 0.75
  • 1.07 . 1.22. 1.17. 1.23 . 1.16. 1.08. 1.11 . 1.09 . 1.14_. 1.26 . 1.19 . 1.28 . 1.22 . 0.89
  • 8

.-10.0. -5.9

  • 0.9. o.6 . o.3 * -1.4 . -3.2. -2.8. -2.6 * -2.6
  • 2.3
  • 2.3
  • 6.2 . 7.8
  • 6.6 *
  • a:iii*:*j:oi*:*;:i9*:*;:22*:*;:ai*:*;:2j*:*a:99*:*j:ji*:*a:ii*:*;:2j*:*;:aj*:*i:22*:*i:i9*:*i:ai*:*a:ii9*:
  • 0.45, 1.02. 1.19. 1.22. 1.02. 1.18. 0.93. 1.08 .. 0.97. 1.18. 1.12. 1.24. 1.22. 1.11, 0.52, 9
  • -9,9. *4.9
  • 0.1
  • 0.2 , 0.3 . -2.2 * -6.0, -3.8. -2.~ * -2.4 . 10.2 . 2.3
  • 2.6. 3.3
  • 4.4 *
                • o:12*:*;:;;*:*,:2i*:*;:2ii*:*a:ia*:*;:22*:*;:;i*:*;:22*:*a:ia*:*;:24*:*;:2i*:*;:j;*:*a:12*:*******

, 0.72. 1.17. 1.21. 1.24. 0.94. 1.15. 1.15. 1.19. 0.98. 1.30. 1.33. 1.13. 0.70. 10

  • 0.1
  • 0.1
  • 0.2
  • 0.3 * -3.7. -5.6. -3.6. -2.5 . 0.8 . 5.0 , 10.2 * -3.6 . -2.7 *
  • 0.37. 1.02. 1;15. 0.96. 1.25, 1.03. 1.25. 1.03 . 1.25 , 0.98. 1.15 . 1.02. 0.37 .
  • 0.35 . 0.98 . 1.11 . 0.99 . 1.20 . 0.99 . 1.22 . 1.00 . 1.23 . 1.06
  • 1.19 . 1.00 . 0.35
  • 11
  • -4.0 * -4.0. -4.0
  • 0.3 * -3.9 * -3.3 . -2.4. -2.6 . -1.2 . 7.7
  • 3.5 * -2.4 . -J.9 *
                • a:4;*:*a:iii*:*;:;6*:*;:2i*:*;:2i*:*;:i;*:*;:2i*:*;:2i*:*j:;i*:*a:iii*:*a:ii1*:*******
  • 0.43
  • 0.77 . 1.15 . 1.21 . 1.21 . 1.15 . 1.20 , 1.25 . 1.21
  • 0.85
  • 0.45 . 12
  • -a.o . -8.o. -o.6. -1.8 . -1.8. -2.1 * -2.6
  • 2.1
  • 3.8. 1.8 * -3.5 *
                • o:4;*:*;:oi*:*;:;9*:*;:2;*:*;:2i*:*;:2;*:*;:;i*:*;:oi*:*o:iii":*******
  • 0.45 : 1.02 . 1.18
  • 1.18. 1.20. 1.21
  • 1.22
  • 1.05 . 0.47 . 13
  • -4.3 * -0.6. -1.2 , -2.1 . -2.0. 0.1
  • 2.8 , 1.9 * -0.6 *
                • o:i;*:*o:1i*:*;:oi*:*j:j;*:*i:ai*:*a:1i*:*a:i1*:*******
  • o.37. 0.11 . 1.05. 1.14. 1.12. o.75. o.38. 111
  • -0.6. -2.5. -4.4. -1.6. 2.0 . 2.7 . 2.8 .

"""stAiiiJAiio**** . . ... .. ... .. ..:.o: 50. : . i>: 84. : . o: 50. : ..... * * * * * * . * *  : ***. AvERAci:* ** :

DEVIArlON

  • o.47 . o.82 . o.~1 . .PCT DIFFERENCE. 15

.. 2.402 * -5.8 . -2.6 . 2.5 . 3.2

SUMMARY

MAP NO: S2 1 DATE: 9/26/83 POWER: OI CONTROL ROD POSITIONS: F-Q(T) = 2.439 QPTR:

D BANK AT 211 STEPS F-DH( NI 1.519 NW 0.984 I NE 1.029 F(Z) 1.562 -----------1----------

sw 0.968 I SE 1.019 F(XY) 1.491 BURNUP 0 MWD/HTU A.O = 31.52(%)

31

l Figure 6.2 SURRY UN IT 2. - CYCLE 7 BOL PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 46.5% POWER R p N M L K J H C f E D C B ,.

PREDICTED

  • 0.50
  • 0.82. 0.50. ***~~ii&i~ii&"""
  • MEASURED *
  • 0.52 . 0.86 . 0.52.
  • MEASURED *
  • PCT DIFFERENCE. 4.4
  • 4.2. 4.4. .PCT DIFFERENCE.

00 b:ii"""b:i~***;:bi"""i:bi 000 i:~i"""b:i~***b:ii 00

  • 0.38 . 0.74. 1.08
  • 1.09 . 1.09. 0.74 . 0.40. 2

. *0.5 * -0.1

  • 0.9 . 1.0. 1.8 . 0.3
  • 4.5
  • 0.50 1.05 1.19 1.19 1.20

. 0.49

  • 1.04. 1.18
  • 1.19
  • 1.19
  • 1.18. 1.19
  • 1.08 . 0.52 .

1.19 1.19 1.05 0.50 3

  • -o.6 * -0.5 . -0.2. -0.5 * -1.1 * -1.1
  • 0.2. 2.8 . 4.4 *
  • 0.49. 0.87
  • 1.17 . 1.23 * *1.22 . 1.17
  • 1.22 . 1.23 . 1.17
  • 0.87
  • 0.49 *
  • 0.49 . 0.85 . 1.16
  • 1.21
  • 1.21
  • 1.14
  • 1.21
  • 1.23 . 1.18 . 0.88 . 0.51
  • 4
  • *1.5. -1.4. -0.8 * *0.9. -1.3 . -2.3. -1.2. 0.2
  • 1.0. 1.8
  • 3.7 *
    • b:ii"i:b~***i:ii'"'b:ii'""i:ii'"'i:bii:i;***;:~i"i:ii""'b:ii"""i:ii'""i:b~***b:ii"'
  • 0.38
  • 1.02. 1.14. 0.97 . 1.21
  • 0.99
  • 1.20. 1.00
  • 1.23 . 0.99
  • 1.17
  • 1.07
  • 0.41
  • 5

.* .0.73

-1.5. -1.5. -2.0. -2.3 * -2.1 * -4.3 * *4.2 . -2.7

  • o.o . -0.1
  • 0.6
  • 3.4
  • 6.1
  • 1.18 1.21 1.22 0.94 1.22 . 1.20 1.22 0.94 1.22 1.21 1.18 0.73
  • 0.73. 1.17. 1.19. 1.18. 0.91 . 1.17.* 1.14. 1.17. 0.93. 1.23 . 1.22. 1.22. 0.77. 6
  • -0.1 . -0.1. -2.1 * -3.5 . -2.9 * -3.9 * -4.9 * -l.6 * -1.0. o.8
  • 1.0 . 3.4
  • 5.l *
  • 0.49 . 1.06. 1.18. 1.21 . 1.02 . ,.21 . 1.01 . 1.15 . 1.01 . 1.21 . 1.02 . 1.21
  • 1.18
  • 1.06 . 0.49 .
  • 0.49. 1.06. 1.18, 1.19. 0.98. 1.17. 0.99. 1.11 . 0.99. 1.19. 1.04. 1.24. l.22, 1.10. 0.51
  • 7
  • -0.2. -0.2 * -0.1 * *1.5. -3.6 , *2.7. -2.3 * -3.0 . -1.9. *1.5*. 2.1 . 2.1
  • 3.5
  • 4.3. 4.1 .
  • ~:i;*:*i:~i*:*;:ii*:*;:ii*:*i:ii*:*;:;i*:*i:i~*:*;:;i*:*i:;~*:*i:ii*:*;:ii':*;:;i*:*;:;i*:*;:bi*:*o:ii*:
  • 0.81
  • 1.07. 1.19 a 1.15 . 1.22 . 1.17. 1.12 . 1.14 . *1,11
  • 1.16 . 1.26 . 1.18 . 1,23
  • 1.11 : 0.85 . 8
  • -o.3 * -0.5 * -0.2. -o.7; -1.3 * -1.6. -1.8 . -2.0 * -2.2. -2.2 . 2.1 . 2.1
  • 3.6 . 3.9. 4.9 .
  • o:~i*:*;:bi*:*;:;i*:*;:ii*:*;:oi*:*;:ii*:*;:o;*:*;:;;*:*;:b;*:*;:i;*:*;:bi*:*;:i;*:*;:;i*:*;:bi*:*b:~i*:
  • 0.49 . 1.07
  • t.22 . 1.22 . 1.01
  • 1.17
  • 0.96 . 1.11 . 0,98
  • 1.17 . 1.04 . 1.24 . 1.24 . 1.11
  • 0.52 . 9
  • -0.2. 1.6
  • 3.3 . o.5. -1.3 . -2.1. -4.a*. -3.7
  • 73.1 * -1.2
  • 1.9
  • 2.1
  • 4.6 . 5.2
  • 6.1 .
                • o:1i*:*i:ii*:*i:i;*:*i:ii*:*a:i~*:*i:ii*:*;:io*:*;:ii":*b:i~*:*i:ii":*i:ii":*1:;i*:*b:ii*:*******
  • 0.76. 1.21 . 1.23. 1.21
  • 0.90. 1.16. 1.14, 1.1.7. 0.92. 1.23. 1.23 . 1.24. 0.77. 10 3.3
  • 3,3
  • 1.5. *1.3 . *3.7 . *5,1 * *5.2 * *4,1 * *1.4
  • 0.3 . 1.8 . 5.1 , 5.3 *
  • ~:ii*:*i:o~*:*i:ii*:*b:ii*:*i:ii*:*i:&i*:*i:i;*:*;:oi*:*i:ii*:*a:ii*:*i:ii*:*i:oii*:*b:ii*:
  • 0.40 , 1.08
  • 1.21
  • 0.98 *. 1.19
  • 0.98 , 1.17 . 0.98 , 1.21 . 1.01 , 1.20 . 1.08
  • 0.40 . 11 4.2. 4.2, 4.2. -1.3 . -3.7 . -4.8 . -6.5 * -4.7 * -1.6. 1.4 , 2.9 , 4.1
  • 4.7 .

. . . . . . . : .o: iii.:. o: ii.:. i: ii":. i: ij":. i: ii.:. i: ii.:. i:ii.:. i: ii.:. i: ii":. o: i,. : . o: iii.: ...... .

  • .0;52. 0.91
  • 1.23. 1.19. 1.19. 1.12. 1.18. 1.22. 1.19. 0.89. 0.51 , 12 5.1
  • 5.1
  • 4.9. -2.6. -3.o . -4.o * -3.9. -0.1. 1.3
  • 3.1
  • 3.9.
                • b:;~*:*i:o;*:*;:ii*:*i:ii*:*i:io*:*;:;i*:*;:ii*:*;:o;*:*~:;b*:*******
  • 0. 52 , 1, 10 . 1. 20 , 1. 16 . 1. 18
  • 1. 19
  • 1. 21 . 1. 08
  • 0, 51
  • 13 4.9. 4.9 . 1.1 . -2.5 , -2.0 . -o.o. 2.2
  • 3.2 , 3.5 .
                  • b:ii***b;i~***;:oi***;:bi***;:61***6:1ii***b:ii*********

0.41 . 0.78. 1.09. 1.09. 1.09. 0.76. 0.39. 111 4.9 . 4.8 . . 1.8 , 1.1 , 1.9

  • 2.2 . 2.2
  • STANDARD ****************0.52 ~: sc, *, *o:a2 °-: *o:;o *******-*-.....
  • AVERAGE
  • OEVIArlON 0.85 . 0.51 .
  • PCT 01 HEKENCE. 15

=1.6.J5 4.4, 3.6. 2.4. = 2.6

SUMMARY

HAP NO: S2*7* 2 DATE: 9/29/83 POWER: 471 CONTROL ROD POSITIONS: F*Q(T) = 1.943 QPTR:

D BANK AT 178 STEPS F*OH(N) = 1.459 NW 0.984 I NE 1.011 f(Z) = 1.275 -----------1----------

sw 0.994 I SE 1.011 f(XY) = 1. 424 BURNUP = 10 MWO/MTU A.O = 0.16(%)

32

Figure 6.3 SURRY UNIT 2 - CYCLE 7 BOL PHYSICS TESTS ASSEMBL YWISE POWER DISTRIBUTION HFP, EQUILIBRIUM XENON R p N H L K J H G F E 0 C a A

' ... PREii i c:ri:ii ...  :*o:;i*:*~:ii*:*o:;i*: ................

PREDICTED *

, MEASURED * , 0.55

  • 0.90. 0.55,
  • MEASURED *

,PCT DIFFERENCE. , 2;8

  • 2.8. 2,8, , PCT DI ffERENCE.
  • o:40***0:1;***i:09***;:i6***,:oi***o:1;:**o:40**
  • 0.39 . 0.75, 1.09
  • 1.17. 1.09, 0.74. 0.41
  • 2

, -0.1. -0.2. 0,3

  • 0.5 . 0.7, -0.9. 4.5,
  • o:so*:*,:oi*:*i:i;*:*i:ii':*i:ii*:*i:ia*:*i:i;*:*i:02*:*o:so*:
  • 0.50
  • 1.01
  • 1.14. 1.17
  • 1,19
  • 1.16
  • 1.14
  • 1.04
  • 0.53
  • l
  • -0.1 * -0.1. -o.4. -o.5 * ~1.3 * -1.3. -o.9. 2.4. 4.5 *
  • o:so*:*o:i6*:*i:i1*:*i:ii*:*i:ii*:*i:i;*:*i:ii*:*i:ii*:*i:i1*:*o:i6*:*o:so*:
  • o.49. o.85
  • 1.12. 1.18. 1.18. 1,11. 1.11. 1.18. 1.14. o.88
  • o.52
  • 4
  • -2.2. -1.2 * -o.8 * -0.1. -1.0 * -1.5 ** -1.3. -o.8
  • 0.1. 2.1
  • 3.2.
  • o:i;*:*i:oi*:*i:ii*:*o:;;*:*i:ii*:*i:oi*:*i:ii*:*i:oi*:*i:ii*:*o:ii*:*i:ii*:*i:oi*:*o:ii*:

, 0.39

  • 0,99. 1.11
  • 0.97. 1.20
  • 1.01
  • 1.20
  • 1.01
  • 1.21
  • 0.96
  • 1.14
  • 1.04
  • 0.41
  • 5
  • -2.2. -2.2. -1.9 * -1.4. -1.1. -2.5 * -2.5 * -1.9. -o.6. -0.2. 0.9
  • 2.5
  • 3.9.
'o: 74.: . i: i1t. : *i: ii. : 'i: ii . : . i: oi.:. i: ii. : . i: iii. : . i: ii' : . i: oi.: . i:2 i . : . i: ii. : . i : i". :. o: 74. :
  • o.74
  • 1.14. 1.16 . 1.11. o.99. 1.20 . 1.11
  • 1.21
  • 1.01 . 1.22. 1.19
  • 1.11
  • 0.11 . 6
  • -0.2. -0.2, -1.6 * -3.3 * -2.1 * -1.9 * *2.7 * -1.5. 0.1
  • 0.7. 1.0
  • 2.4
  • 3.4.
  • o:;i*:*i:oa*:*i:i1~:*;:ii*:*;:oi*:*i:ii*:*i:oi*:*i:i;*:*i:oi*:*i:ii*:*i:oi*:*i:ii':*i:i1*:*i:aa*:*o:;i*:
  • 0.51
  • 1.08. 1.19. 1.18
  • 0.99. 1;19 . 1.02
  • 1.14 . I.OJ
  • 1.22
  • 1.04
  • 1,20
  • 1.20. 1.11 . 0.55
  • 7
  • *3. 7 , -0. 4 ** 1. 6 , -0. 4 * -3. 7 * -1. 8 * -0. 8 * - I
  • l
  • 0. 0
  • 0. 4
  • 1. 7
  • l. 7
  • 2. J
  • 2. 8 *. 2. 6 *

. :*o:aa*:* i: i6*: *;:io* :*;:i .. * :* i:ir :* i: ii*:* i: i.. *:

  • i:*i; *: *;: i4 *:
  • i:i;*: 'i :zi*:
  • i: i4 *:
  • i :iii*:* i: i6.: *o:aa *:
  • 0,64. 1,14. 1.22. 1.16
  • 1.24. 1,19
  • 1.14
  • 1.15
  • 1.14. 1.19. 1.25
  • 1.16
  • 1.23 ** 1.19 . 0.92.
  • 8
  • -3.7.* -1.s. 1.8. 1.4. 1.0. 0.3 * -o.5 .- -0.2. -o.o. -o.o. 1.1. 1.1. 2.3
  • 2.9
  • 4.6.
  • o:si*:*1:oa*:*i:11*:*;:ia*:*i:oi*:*i:2i*:*i:oi*:*;:i;*:*i:oi*:*i:2i*:*i:oi*:*;:ii":*i:i1*:*i:oi*:*o:;i*:

, 0.51

  • 1.06. 1,17. 1.19
  • 1.04
  • 1.21
  • 1.00
  • 1,14
  • 1.02. 1.21
  • 1.03
  • 1.20
  • 1.21
  • 1,13
  • 0.57. 9
  • -3.7. -1.8. 0.1
  • 0.1. 1.0. -o.4 * -2.1 .* -1.3 * -0.5. -o.5 ;_ o.3
  • 1.1
  • 2.8 . 4.5
  • 1.0 *

....... :*0:14* :*;: 14'.: *;:;r :* i'.ii" :*;:oi *:

  • i:22*:
  • i:io*: *_;:22*:
  • i'.oi *:
  • i:ii *:
  • i: is*:* i: i4.:
  • 0:14*: ** .....

, 0.75. 1.14. 1.18. 1.23. 1.00. 1.19. 1.17. 1.20. I.DO. 1.21. 1.18. 1.1,8. 0.77. 10

, 0.1

  • 0.1
  • 0,5
  • 1.0. -1.2. -2.9 * -3.0 * -1.8 * *0.4-. *-0.2. 0.3
  • 3.2
  • 3.7 *
  • o:ii*:*i:oi*:*;:;i*:*a:9i*:*i:22*:*;:oi*:*;:ii*:*i:oi*:*i:22*:*o:ii*:*i:ii*:*i:oi*:*o:ii*:

, 0.40. 1.03

  • 1.14. 1.00. 1.20
  • 1.01
  • 1.18
  • 1.00. 1.21 . 0.99 , 1.15
  • 1.04
  • 0.41
  • 11 1.5. 1.5. 1.5_. 1.0, -1.4. -2.6 * -4.2. -2.8. -0.1. o.3
  • 1.9
  • 3.1
  • 3.3 *

.' .... ' :.o: 50. : 'o: 86. : * ;: ii. : . i: ii. : . i: ii. : . i: i;. : . i :ii. : . i : i. : . i : ii . : .o: 86. : 'o: 50. : ...... .

~

  • 0.52
  • 0.88 . 1~16
  • 1.19 , 1.18
  • 1.12 . 1,15
  • 1.16 . 1.14
  • 0.88
  • 0.52 , 12
  • 2-~, 2.9. 2.1 * -0.1 * -0.9. -2.8 * -3.l * -0.4. 0,8
  • 2.4
  • 3.3 *

.' ..... :.o: 50. : . i:02. : . i: i5' : . i : ia. : . i:ii . : . i: ia. : . i: i5. : . i:02. : .o: 50. : ... * .. *

  • 0.52. 1.04. 1.16. 1.16
  • 1.17
  • 1.17. 1.17. 1.04
  • 0.52
  • ll 2.5. 2.1
  • 1.0. -1.8 * -2.8 * -1.0. 1,5. 2.5. 2.9 *
                  • a:40***0:1;***i:oi***;:;6***i:ai***o:i5***0:&o*********
  • 0.40. 0,77. 1.09. 1.16. 1.10. 0,76, 0.40. 14 2.1
  • 2.4. 0.3 * -0.1
  • 1,0 , 1.5 , 1.5 *

""'srANoAiio"" ****************o:;i***o:aa:**o:si****************  :****AvEiiAcE***:

DEVIAflON , 0.55 . 0.90 , 0.54 .

  • PCT DIFFERENCE. 15

=1.228 2,7

  • 2.J
  • 1.5. C l,7

SUMMARY

MAP NO: S2 5, DATE: 10/ 5/83 POWER: 10oi CONTROL ROD POSITIONS: F-Q(T) = 1.761 QPTR:

0 BANK AT 228 STEPS F-OH( NI = 1. 420 NW* 0.969 I NE 1.007 F(Z) = 1.177

1----------

sw 0.997 I SE 1.007 F(XYI = 1.376 BURNUP = '196 HWO/HTU A.0 = -1.35(1) 33

l I

SECTION 7 REFERENCES

1. M. E Paul and A.P. Main, "Surry Unit 2, Cycle 7, Design Report," NFE Technical Report No. 290, Vepco, July, 1983.
2. Surry Power Station Technical Specifications, Section 3. 1. E, 3 .12. C .1.
3. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By
  • Toe Rod Swap Technique, 11 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.

34

l APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS 35

2-PT-28."ll Attachment 9 Page 1 of 37 SURRY POWER STATION UNIT 2 CYCLE 7 SEP 1 7 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout Reference Pree No /Section: 2-PT-28.11/APP.B Sequence Step No: G II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F .P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Des1gn) CB: 228 CC: 228 CD: +. Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): ~43.8 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB: 228 CC: 228 CD: /di Below Nuclear Heating

.. Date/Time Test Performed:

q/~~11'S '].. 2. oo Measured Parameter Pc = Meas. Reactivity -using p-computer IV (Description) . pt= Inferred p from reactor period

--'/D.() -30.0 4,/.S-Pc = -5:r.O Z,.f!'.S" Measured Value pt =-~2. -/ffJ.Jf -30.0 Z.,(D. i ~/.rt Test %D = -3.Z - -1.0 o.lJ -2.3 -o. G' Results Design Value (Actual Conditions) %D = [(pc-pt)/pt] X 100% S 4.0%

Design Value (Design Conditions) %D = [(pc-pt)/pt) X 100% S 4.0%

Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/Tech Spec *Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met  : v'YES _NO VI Acceptance Criteria is met  : LYES _NO Comments I

  • At the- just critical position Allowable Range=+/- s-5' p~

Completed Evaluated By:

Recommended for Approval By: c.j.~-

NFo Engineer A.l

2-PT-28.11 Attachment 9 Page 2 of 37 SURRY POWER STATION UNIT 2 CYCLE 7 SEP l 7 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l Test

Description:

Critical Boron Concentration - ARO Reference Pree No /Section: 2-PT-28.ll/APP.C Sequence Step No: 7" II Bank Positions (Steps) . RCS Temperature (OF): 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

  • 111 Bank Positions (Steps) RCS*-.. Temperature ( 0 :F): 5~3.,

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

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

. tJ/;i,/93 O'f 58 **1/:,/*

Meas Parameter

    • M IV (Description) (~B)ARO; Critical Boron'Concentration*- ARO M* .

Measured Value (CB)ARO = / 3 7? fff{'I Test.

Results Design Value (Actual Cond) CB= P,Jo3 +. 5"0 f p~

Design Valu.e (Design Cond) CB =1403 +/- 50 ppm Reference VEP-PSE-NFE-290 V FSAR/Tech Spec ci:C x. CB :S 15 , 115 pcm B

Acceptance Crit_eria Reference UFSAR Section 14.2.5 Design Tolerance is met  : +YES _NO Acceptance Criteria is met  : _YF.S __NO VI Comments ct* = -B.30 pcm/ppm for preliminary analysis CB cl. C8 : -8.0'l pc111/pf'rn ./Jr ../f;.,.4/ Ol'IQ/'/5;-5 f*j. JJ/ I Completed By:<!Jt~ s ng eer Evaluated By:. ____

Recommended for Wri1.__-=--

Approval By: c .NFO

..1.~

Engineer A.2

2-PT-28.11 Attachment 9 Page 3 of 37

, SURRY POWER STATION UNIT 2 CYCLE 7 - SEP 1 7 1983 STARTUP PHYSICS TEST RES ULTS AND EVALUATION SHEET I Test

Description:

Isothermal Temperature Coefficient~ ARO Reference Proc No /Section: 2-PT-28.11/APP.D Sequence Step No: 8 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Des-ign) CB: 228 CC: 228 CD: 228 Below Nuclear Heating --

III .. Bank Positions (Steps) RCS*-.Temperature (°F):!;LJy./

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

(Actual) CB: 228 CC: 228 CD: ~;ie Below Nuclear Heating

.. *- Date/Time Test Performed:

9/:J.r;,/B3 ___: }OJI Meas Parameter IV (Description) ISO Isothermal Temp Coeff - ARO

~a T )ARO Test Measured Value ( ISO) _ -£".J3 pcm/nF_ (CB = /jB:)ppm) a T ARO -

Results Design Value (Actual Cond) T )ARO=-5,,~+/-,,£?pcm/'F (CB =J380ppm) *

(a ISO ISO (a T. ) ARO = -5.41 +/- 3.0 pcm/DF Design Value (Design Cond_) (CB = 1403 ppm)

Reference VEP-PSE-NFE-290

V FSAR/Tech Spec a-T s 0. 43**pcm/°F a T - -2.07 pcm/°F Acceptance Criteria Reference TS 3.1, VEP-FRD-NFE-290 Design Tolerance is met  : -}ns _No VI Acceptance Criteria is met . : _YES _NO Comments

  • Uncertainty on~ = 0.5 pcm/°F (

Reference:

memorandum MOD

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

Completed By: l:R~u~ Evaluated By: (.1.~

(Ji{~~weD . Recommended for Approval By:

NFC Engineer A._3

. 2-PT-28.-11 Attachment 9 Page 4 of 37 SEP l ? *19e3 SURRY POWER STATION UNIT 2 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Map - Hot. Zero Power, All Rods Out Reference Proc No / Section: 2-PT-28.2*, OP-57 Sequence Step No: 9 II Bank Positions (Steps) RCS Temperature (°F): TREF +/-i*

Test Power Level (% Full Power): - 0 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'-/7. I *

'Test Power Level (% Full Power): Z %

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

(Actual) CB : -228 CC : 228. CD: Zn-_-

_3 B f./,, imbler Dat"e/Time Test

  • Cf/l.6/63 ' ...... - .

~

Perfor~ed: . . /SL/7.

MAXIMUM REL. NUCLEAR ENTHALPY TOTAL HEAT. . QUADRANT IV Measured ASSEMBLYWISE RISE HOT CHANNEL FLUX HOT CHANNEL POW'ER TILT Parameter PERCENT DIFF. -*

FACTOR .. FACTOR RATIO .,

(M-P)/P -~ FT QPTR bl{ Q

& ~'t = l,/2. f Test /().Z "*

+

Results Measured 10.2%_~ ,:,01 /.33 + I. 5 2.0 /. 02. '1 Value u,.qt*fr,, "'s.: ()'. 7S Design +/-10% For Pl..~O. 9 rNMfl.55[1+0.2(1-P)]

..

  • F~S(4.36) x K(z)

Value +/-15% For Pi<0.9 s 1.02

Reference REV.1 NONE NONE REV.l FSAR/

V Tech Spec NONE* NA NA NA Acceptance Criteria Reference NONE Tech Spec 3.12 Tech Spec 3.12 TS 3.12 The Minimum F~(z) Margin is '//. 6 %

Design Tolerance is met  : _YES ,,.,-NO Acceptance Criteria is met : ,,,-YES _NO VI Comments Completed Byot~ :t C gin r

.~ Evaluated By:

Recommended for Approval By:

NFO Engineer A.4

... 2-PT-28. 11 *...

Attachment 9

  • Page 5 of 37 SURRY POWER STATION UNIT 2 CYCLE 7 SEP 1 7 1983 *
  • STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
  • I Test

Description:

Cntl Bank B Worth_Meas.,Rod Swap Ref *. Bank Reference Proc No /Section: 2-PT-28.11/APP.E Sequence Step No: 10 II Bank Positions (Steps) RCS Temperature (OF): 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 I

III Bank Positions (Steps) RCS**.. Temperature ( OF) : .s "tS: °I Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

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

.... Date/Time Test Performed: ... ..

'r I:I. 1, I i.3 ..1330'* * -.* ..

~-- ., . . * ..

REF .

Measured Parameter I B ;Integral Worth of Cntl Bank B, (Description) All Other Rods Out IV REF _

Test . Measured Value 1 B - I{).. SJ./ pcm Results

- Design Value (Actual Conditions) 1 REF .:_

J~C/1 -

-I- /30 pc.m B ~

Design Value ti (Design Conditions) 1REF = 1297 +/- 130 pcm B

Reference VEP-PSE-NFE-290

+f Design Tolerance is exceeded, SNSOC

- shall evaluate impact of test result FSAR/Tech Spec on safety analysis. SNSOC may specify*

V that additional testing be performed.

Acceptance Criteria Reference VEP-FRD-36!

Design Tolerance is met  : _"YES _NO VI Acceptance Criteria is met  : ~YES __NO Comments Completed Evaluated By: -Z,, J . ~

Recommended for

  • A
  • 0 Approval By : C. J. ~

NFO Engineer A.5

.*, ;~ ;;:*:.**:* ..

,- ,*.: :_. ~--- - *2-PT-28;11

  • A*# - ,, .*

. *:*-.:*.-~:-:**:_. ..

  • 0 Attachment 9 Page 6 of 37

~

SURRY POWER STATION UNIT 2 CYCLE 7 SEP 1 7 1983 STARTUP PHYSiCS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - B Bank In Reference Proc No /Section: 2-PT-28.11/APP.C Sequence Step No: //

II Bank Positions (Steps) RCS Temperature (°F): 547 Test 1-------------------------------.----------! Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 2.28 CA: 228 Other (specify):

  • (Design) CB: O
  • CC: 228
  • CD: 228 Below Nuclear Heating III.**. .. Bank Positions (Steps) RCS Temperature (°F): 5""/.5. ~

Test *

  • Power Level (% F .P.): 0 Conditions SDA: 228 SDB: 228
  • CA: 2.28 Other (Specify):

(Actual) CB: 0 CC: 228. CD: 228 Below Nuclear Heating Date/Time Test Performed: - .. *'

  • -~_-: *=* - -* .. C'/,'1/7/13 0.7/6*.

Meas Parameter *-***

I *.

  • M IV (Description) (~B)B; Critical Boron Cone - B Bank In Measured Value * (CB)~ = / t<tl J{ PP m Test Results Design Value (Actual Cond)

Design Value *

(Design Cond) CB = 1244 + ~c~rev +/-(10 + 129. 7 / I ac B

.1 )ppm Reference VEP-PSE-NFE-290 V FSAR/Tech Spec aC x CBS 15,115 pcm B

Acceptancei---------------------+-----------------------------------------------------------

Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met  : ~YES ____NO Acceptance Criteria is met  : ~ S ____NO VI "c = -8.30 pcm/ppm for preliminary analysis B

Comments AC:rev = (CB)~0 -1403 Completed By:

. c,-~~

Tb :t E gin .

Evaluated By: "',,;;,

Recommended for

,4.. ~~

Approval By: c~!J.~

NFO Engineer

  • A.6
  • 2-PT-28;11
  • Attachment 9*

Page 8 *of 37 SURRY POWER STATION UNIT 2 CYCLE 7 SEP 1 7 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Bo~on Worth Coefficent Measurement ~

Reference Proc No /Section: 2-PT-28.ll/APP.E Sequence Step No: N~

II Bank Positions (Steps) RCS Temperature (OF): 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): S'/3 .. 7 Test Po-wer Level (%. F .P.): 0 Conditions . SDA: 228 SDB: 228 CA: 228 Other (Specify}:

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

. Cf/tltlk~ c,q.sg Measured Para.meter IV (Description) ac Boron Worth Coefficient

. B '

Measured Value a CB

= - t. oa, f C 111 / f'P (h Test.

Results Design Value (Actual Conditions) *a CB

= -8.30 -+ 0- ~ 3 fCWI /p.()W1 Design Value (Design Conditions) ac B

= -8.30 +/- 0.83 pcm/ppm Reference VEP-PSE-NFE-290 FSAR/Tech Spec ac X CB s 15,115 pcm B

V Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met  : vn;s _No VI Acceptance Criteria is met  : J:=YES* __NO Comments Completed Evaluated By: -r:::m A- ~

Recommended for t1 C' Approval By: ..a::C_..=J'-**....:...~~..;...;;;.=--

NFO Engineer

2-PT-28.-11

. *, .. :' . -. ' - ... Attachment 9 Page 9 of 37

  • SURRY POWER STATION UN IT 2 CYCLE 7 SEP l 7 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank D Worth Measurement-Rod Swap Reference Pree No /Section: 2-PT-28.11/APP.F Sequence Step No:13 II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F. p *.) : 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Des"i.gn) . CB:Moving CC: 228 *cD:Moving Below Nuclear Heating

' - -- "III Bank Pos*itions (Steps) RCS Temperature (OF): 5'#5'.S-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/!ime Tes~--- Performed: .*iii_\? '*.:*.::*~.--
  • _ IJ /~rt/,-~ -: 08'/I :_>,, ... ,.

Meas Parameter - *-'***

RS - . ~

(Description)

  • ID ; Int* Worth of Cntl Bank D-Rod Swap '*

IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_ II~/ j)~P1 Position._= ti'/ steps)

D-Results Design Value (Adj. Meas_. Crit~ Ref Bank (Actual Cond) I~S= IJJ/(p +/- 172. /c_A'J Position = ;ffsteps)

Design Value I~S= 1141 +/- 171 pcm (Critical Ref Bank (Design Cond) * . Position= 198 steps)

Reference VEP-PSE-NFE-290, 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  : -~S__NO VI Acceptance Criteria is met  : _ S __NO Comments Completed By:(7$ -~~ e Eng er*

  • Evaluated By: <Yi?/~~

Recommended for * ~ 0 Approval By : C. J. ~

1'~0 Engineer A.8

  • . _-:.-! _* 2-PT-28 ;11 Attachment 9 Page 10 of 37*

SEP 1 7 1983 SURRY POWER STATION UNIT 2 CYCLE 7 STARTUP PHYSICS TEST RESULTS "AND EVALUATION SHEET I Test

Description:

Cntl Bank C Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-28.11/APP.F Sequence Step No:/4 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:Moving CD: 228 Below Nuclear Heating III * : Bank Positions (Steps) RCS Temperature (OF): S-.J/-S:~

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:* . -
  • q/~7/?3 *or4'1 -_

Meas Parameter -

. *Rs *

(Description) Ic ;Int Worth of Cntl Bank C-Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_ rtrJIP j>C/17 Position~ /3~teps)

C -

Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) I~S=1fJf ! Jlf/ /£/11 Positic;>n = (35' steps)

'Design Value IRS_ 799 +/- 120 pcm (Critical Ref Bank C -

(Design Cond) Position= 160 steps)

Reference VEP-PSE-NFE-290, 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 Acceptanc.e additional testing be performed.

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

S,ns

_YES _NO

_NO Comments Evaluated By: %Id~  ?

Recommended for Approval By C . .!I_ A-cw NFO Engineer A._9

~. . ...

. . :*_ .:;. :.- 2-PT-28.11

-~ ....

..-. *~ .- .

Attachment 9 Page 11 of 37 SURRY POWER STATION . .UNIT i CYCLE 7 SEP 1 'l 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Cntl Bank A Worth Measurement-Rod Swap Reference Pree No /Section: 2-PT-28.11/APP.F Sequence Step No: 15 II Bank Positions (Steps) RCS Temperature (OF): 547  !

Test Power Level (% F .P.): O Conditions SDA: 228 SDB: 228 ** CA:Moving O:t:her (specify):

(Design) CB:Moving CC: 228 CD: 228* Below Nuclear Heating III Bank Positions (Steps) RCS** Temperature (°F): £"15-3 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA:Moving Other* (Specify):

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

Date/Time Test Performed: ..

- - 9/~7 /B3 01JO *-*

Meas Parameter -

Rs*.

(Description) I A ; Int Worth of Cntl Bank A - Rod Swap IV (Adj. Meas. Crit. Ref Bank IRS_

'.fest Measured Value A- 461 pelf\ Position*= 10 s1:eps.)

Results Design Value (Adj. Meas. Crit. Ref* Bank (Actual Cond) I!s= l{~'f :t fOO pG~. Position = C/0 steps)

Design Value r!s= 464 +/- 100 pcm (Critical Ref Bank (Design Cond) * - Position= 119 steps)

Reference VEP-PSE-NFE-290, 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 .. ....,Ln:s _NO VI Acceptance Criteria is met  : _£,n:s _NO Comments Evaluated By: t: /,f/JL Recommended for Approval By: c.:!..L.w NFO Engineer A.10

2-PT-28 .*11 Attachment 9 Page 12 of 37 SEP 1 7 19S3

, SURRY POWER STATION UNIT 2 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B )vorth Meas. - Rod Swap Reference Proc No /Section: 2-PT-28.11/APP.F Sequence Step No: 16 II Bank Positions (Steps) RCS Temperature (OF): 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 ~eating III Bank Positions (Steps) RCS Temperature (OF): S-"l"f.. ~

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: .. .

q/~11~~ .. OC//.17 C.)

Meas Parameter *"~.;, ../.

RS *

(Description) ISB;Int Worth of Shutdown Bank B-Rod Swap IV (Adj. Meas. Crit. Ref Bank Rs_

Test Measured Value 1 SB- '191/ /cPJ Position = J3r steps)

Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) I~:= '!30 Z 12>/e~ Position = J'3f steps)

  • Des_ign Value 1::= 841 +/- 126 pcm (Critical Ref Bank (Design Cond) Position = 165 steps)

Reference VEP-PSE-NFE-290, 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 an~lysis. SNSOC may specify that Acceptance additional testing be performed.

C+iteria Reference VEP-FRD-36A Design Tolerance is met  : ~ S __NO VI Acceptance Criteria is met  : _YES __NO Comments Completed Byof:e~ gin r .

Evaluated By:

Recommended for Approval By:

~

c .. 1 ~

NFC Engineer

  • A.11.

2-PT-28.11 Attachment 9 Page 13 of 37 SEP l 7 19B3 SURRY POWER STATION UNIT 2 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank A Worth Meas. - Rod Swap Reference* Proc No /Section: 2-PT-28.11/APP.F Sequence Step No:/7 II Bank Positions (Steps) RCS Temperature (OF): 547

. Test Power Level (% F.P.): C)

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 (OF): 5" #"/. #

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:

q/1,7/g-3 JtJ2.0

.Meas Parameter RS (Description) ISA;Int Worth of Shutdotiin Bank A-Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value IRS_

SA- I /I IP I'" Position.= JtjJ steps)

Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) IRS= /{)11 SA

+/- //;Z ~A Position*= /9 3 steps)

Design Value I~!= 1016 +/- 161 pcm (Critical Ref* Bank (Design Cond) Position= 191 steps)

Reference VEP-PSE-NFE-290, 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  : VYES _NO VI Acceptance Criteria is met  : JZ'YES _NO Coliiments Completed ,Evaluated By:

Recommended for Approval By: c.J.~

NFO Engineer A~l2

2-PT-28.11 Attachment 9 Page 14 of 37

  • SURRY POWER STATION UNIT 2 CYCLE 7 SEP 1 7 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth - Rod Swap Reference Pree No /Section: 2-PT-28.11/APP.F Sequence .Step No: N/A II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (% F.P.): 6 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 (OF): S-4S-.

Test Power Level (% F.P.): 0 Con,ditions SDA:Moving SDB:Moving CA:Moving Other (Specify):

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

  • 9/:t-7/?'g IJ!J/**

Meas Para.meter (Description) ITotal;Int Worth of All ~anks - Rod Swap IV Test Measured Value* 1Total = 5'S-3S- pe.P?

Results

.. Design Value (Actual Cond) 1Total = 5'~8B + - ~59 j?cn?

- Design Value 1 = 5618 +/- 562 pcm Total (Design Cond)

Reference VEP-PSE-NFE-290,' 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 A~ceptance additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met  : ~S_NO VI Acceptance Criteria is met  : _YES _NO Comments Completed B y ~ ngin ~r Evaluated By: °I~

Recommended for Approval By : c.:J.~.

NFO Engineer A.13

2-PT-28.11 Attachment 9 Page 31 of 37

  • SURRY POWER STATION UN IT 2 CYCLE 7 SEP l 7 1983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description : M/D Flux Map - At Power, NI Calibration, FCFM Reference Proc No I Section: 2-PT-28.2, OP-57 Sequence Step No: L/S II. Bank Positions (Steps) RCS Temperature (OF): TREF +/-1 Test Power Level (% Full Power): - 50 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)

(Design) CB : 228 cc : 228 CD:

  • Must have~ 38 thimbles*

III Bank Positions (Steps) RCS Temp~rature(°F): .s-si Test Power Level (% Full Power): 4/o. 5 1,,

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

(Actual) CB : 228 cc : 228 CD: 170 "3S t/...',mbl~5 Date/Time Test Performed: Cf /29/53 O'j I ;l -

MAXH!UM REL. NUCLEAR ENTHALPY TOTAL HEAT QUADRANT IV Measured ASSEMBLYWISE RISE HOT CHANNEL  : FLUX HOT CHANNEL POWER TILT Parameter PERCENT DIFF. FACTOR FACTOR RATIO

-- (M-P)/P N T QPTR F~H FQ.

Test -'7,S. 7.* .for P = '*' 7 H*II Results Measured I, ~51 /, 1 q3 J,011:;)

Value G,/7* .f.,, f *'I

= O,SJ Design +/-10% For P1.~0.9.

--. Value +/-15% For P.<0.9 1

NA NA ~ 1.02 WCAP-7905 WCAP-7905

- Reference REV. 1 NONE NONE REV.l For P > 0.5 FSAR/ NONE ~Mfl.55[1+0.2(1-P)] Fi~(2.18/P) x K(z)

V Tech Spec F~~(4.36) x K(z) NA Acceptance For P ~ 0.5 Criteria Ref"erence NONE Tech Spec 3.12 Tech Spec 3.12 TS 3.12 The Minimum F~(z? Margin is 5'1. q %

- Design Toler.a.nee* is met- - .*.: *{-YES . _NQ - ... '. "

"Acceptance Criteria is met : _YES _NO VI -

Comments

  • As Required Completed- ~y, .

/

t(~ .

Tes Engineer Evaluated By:{:'~.~

A.14 Recommended for Approval By: C 1, J~ P

~

2-PT-28. ll Attachment 9 Page 33 of 37 SEP 1 7 1983

. .

  • SURRY POWER STATION UNIT 2 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description :M/D Flux Map-At_Power,NI Calibration, QCFM Reference Pree No I Section: 2-PT-28.2, OP-57 Sequence Step No: Lj (p II Bank Positions (Steps) RCS Temperature (OF) :TREF. +/-1 Test Power Level (% F .P.): - 60 Conditions SDA:. 228 SDB: 228 CA: 228 Other (specify)

(Design) CB : 228 cc : 228 CD:

  • Must have 2 16 thimbles
  • III Bank Positions (Steps) RCS* Temperature (°F): !"51 Test Power Level (% F .P.): 5'~, 1 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 cc : 228 CD: l'f:4 11 ..f:.{,.~ ,,,.b/e5 Date/Time Test Performed: 1/z9/B3 I l/58 .

Measured Parameter MAXIMUM RELATIVE ASSEMBLYWISE (Description) POWER PERCENT DIFFERENCE

' [ (Measured - Predicted)/Predicted]

- ~.o i:, +or H*S p -- /, ;i I Measured *.

Value IV Test

'-/, <J 2 /or p 6--11

= O,'fO Results

+/- 10% For P.l. ~ 0.9 Design Value (Design Conditions) +/- 15% For P.l. < 0.9 WCAP-7905 Reference REV.1

- Design Tolerance is met  : LYES _NO V

Comments

  • As Required* .

-~-:- . __ _.,... - - ,.._ ,- ~

A.15

2-PT-28.11 Attachment 9 Page 35.of 37

,. , ,

  • SURRY POWER STATION UNIT 2 CYCLE 7 SEP 1 7 l.983 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description :M/D Flux Map-At Power,NI Calibration, QCFM Reference Pree No/ Section: 2-PT-28.2, OP-57 Sequence Step No: J./7 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:

  • Must have~ 16 thimbles III Test Conditions Bank Positions (Steps)*

SDA: 228 SDB: 228 CA: 228 RCS.._ Temperature(°F): 563 Power Level(% F.P.):

Other (Specify)_:

,,.o (Actual) CB : 228 CC : 228 CD: 18:3

/1 tL.:mb/e.5 Date/Time Test Performed: t//z 9/ 83 Measured Parameter MAXIMUM RELATIVE ASSEMBLYWISE (Description) POWER PERCENT DIFFERENCE

[(Measured - Predicted)/Predicted]

- J.e r: /, :i.. I Measured Value IV '1, Ii~ p*

Test e *ii Results

+/- 10% For P.l. ~ 0.9 Design Value (Design Conditions) +/- 15% For P.l. < 0.9 WCAP-7905.

Reference REV.1 Design Tolerance is met . LYEs __NO V

Comments

  • As Required .

.:--~~~¥~~~<~-j~~.~-:.*~~---_ - -~ :~:::: ~=--~* .. :~--- ~:-~~----*~:-.. _.. ~ ...-~;~-:~:-- -.. ~ ..... - ~-...;. *---~ --:._~-~ <=.. ..

Complet~~ ~YEW~~fj n ~

,Co;, .~Ev~lua~e~ ~y'i

,-***.* *Recommended for.

( ' /; /)JG*** .

C'_**J r f - ~ * -

  • -* .c,'. * * ._, :** * -
  • Approval By: ~

NFO Engineer A.16.

2-PT-28 .11 Attachment 9 Page 36 of 37 SEP 1 7 1983

< ' * , SURRY POWER STATION UNIT 2 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description : M/D Flux Map - Full Power Equilibrium Xenon Reference Pree No I Section: 2-PT-28.2, OP-57 Sequence Step No: l/8 II Bank Positions (St~ps) RCS Temperature (OF): TREF +/-1 Test Power Level (% Full Power): 95 +5/-0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)

(Design) CB : 228 cc : 228 CD:.

  • Must have 2: 38 thimbles III Bank Positions (Steps) RCS Temperature (°F): 573 Test Power Level (% Full Power): )00 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):

(Actual) CB : 228 cc  : 228 CD: :J;;J8 3g i:;l,. *. rn b ie-S Date/Time Test ~

Performed: 10/5/8::, 1:J:10 MAXIMUM REL. NUCLEAR ENTHALPY TOTAL HEAT QUADRANT IV Measured ASSEMBLYWI SE. RISE HOT CHANNEL  : FLUX HOT CHANNEL POWER TILT

.Parameter PERCENT DIFF. FACTOR FACTOR RATIO (M-P)/P N FT QPTR F~H Q Test i./ ,VJ,., A~ p =0,'7:).

Results Measured A-e>

Value p .:0,57 J,~).O /. 7r;) I ,007{

7,() 'I. fdr k'f Design +/-10% For Pl..2:0. 9

Value +/-15% For P.<0.9 NA NA S 1.02 l.

WCAP-7905 WCAP-7905

  • Reference REV. 1 NONE NONE REV.l V ~ FSAR/ NONE F~l.55[1+0.2(1-P)J F~S(2.18/P) x K(z)

Acceptance Tech Spec NA Criteria Reference NONE Tech Spec 3.12 Tech Spec 3. 12 . TS 3.12 Th! Minimum F~(.~) Margin is H,.2  %

Design Tolerance is met  : L.YES _NO Acceptance Criteria is met  : ..1:...YES __NO VI Comments t As _R_:J~~-:;d,,:*;;~~>::~~~>>,- _*.:.) -** .. - *- .------ *.. -

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  • ... ,... ~-
    • Evaluated By: * * * * .)

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Recommended for * *.

. Approval By:

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