ML19325D837

Rev 0 to NE-751, Surry Unit 1 Cycle 10-A Startup Physics Tests Rept.

ML19325D837
Person / Time
Site:	Surry
Issue date:	10/31/1989
From:	Dziadosz D, Pierce N, Trace D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18151A931	List: ML18151A930 ML19325D837
References
NE-751, NE-751-R, NE-751-R00, NUDOCS 8910260311
Download: ML19325D837 (60)

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.r TECilNICAL REPORT NE-751 - Rev.~0 r

'I SURRY UNIT' 1, CYCLE 10A STARTUP PIlYSICS TEST REPORT ,

I  :

I NUCLEAR ANALYSIS AND FUEL I- POWER ENGINEERING SERVICES  ;

. VIRGINIA POWER l OCTOBER, 1989 L

. 4 I

l l

l PREPARED BY: flYS- q /gdP9 N.-S. Pierce Date REVIEWED BY: V //3/34 l D. A. Trace Date APPROVED BY: b '

D. Dziadosz Date QA Category: Nuclear Safety Related Keywords: S1010A, Startup I

I

b l' . .

I ,

L CLASSIFICATION / DISCLAIMER The data, techniques,; information, and conclusions in this report have p been prepared solely for use by Virginia Electric and Power Company (the g Company),' and they may not be appropriate for use in situations other than

• those for which they have been specifically ' prepared. The Company

[

therefore makes no. claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCilANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SilALL ANY. WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING

'0R 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 I herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out l of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

I I

NE-751 SIC 10A Startup Test Report Page 1 of 58

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TABLE OF CONTENTS PAGE

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Classification / Disclaimer............................... 1 Table of Contents....................................... 2 List of Ta'bles..........................................

3 List of Figures......................................... 4 Preface.......................-.......................... 5

.Section 1 Introduction and Summary................... 7 Section 2 Control Rod Drop Time Measurements.........

I 16 Section 3 Control Rod Bank Worth Measurements... .... 21

', Section 4 Boron Endpoint and Worth Heasurements...... 26 Section 5 Temperature Coefficient Measurement........ '30 Section 6 Power Distribution Measurements.... ....... 33 l Section 7 References................................. 40 APPENDIX Startup Physics Tests Results and Evaluation Sheets........................ 41 l

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I NE-751 S1C10A Startup Test Report Page 2 of 56 i

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LIST OF TABLES 1 i I i

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7 TABLE TITLE PAGE .

I 1.1 ' Chronology of Tests...................................

10 ,

'2.1 Hot Rod Drop Time Summary.............................. 18 i I~I 3.1 Control Rod Bank Worth Summary........................ 23 4.1 Boron Endpoints Summary............................... 28 f 5.1 . Isothermal Temperature Coefficient Summary..........., 32 ,

6.1 Incore Flux Map Summary............................... 35 j 6.2 Comparison of Measured Power Distribution Parameters f p With Their Technical Specifications Limits............ 36 1'.

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NE-751 "1C10A Startup Test Report Page 3 of 58

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• LIST OF FIGURES i.

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FIGURE L TITLE PAGE~

1.1. Core loading Map......................................... 11 1.'2 ~ Beginning of Cycle Fuel Assembly Burnups................. 12 t

I '1.3 Incore Instrumentation Locations......................... 13 a

)

i 1.4- Burnable Poison and Source Assembly Locations............ 14

, 1.5 Control Rod Locations.................................... 15 i 2.1 Typical Rod Drop Trace................................... 19 2.2 Rod Drop Time - Hot Full Flow Conditions................. 20 i 3.1 Bank B Integral Rod Worth - IlZP.......................... 24 ,

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• 3.2 Bank B Differential Rod Worth - IIZP...................... 25 1

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4.1 Boron Worth Coefficient.................................. 29  !

6.1 Assemblywise' Power Distribution - 26% Power.............. 37 [

_ 6.2 Assemblywise Power Distribution - 65% Power.............. 38 6.3 Assemblywise Power Distribution - 100% Power............. 39 i

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I NE-751 SIC 10A Startup Test Report Page 4 of 58 I. . _ . _ _ _ _-. _ _ _ . . . . _ . _ _ _ . - _ _ _ _ . - _ _ _ - _ _ _ ~ _ . _ . _ . . . _ _ . - _ _ .

-l '

L PREFACE A +

L .

The purpose of this= report is to present the analysis and evaluation of the physics tests which were performed to verify that the Surry. Unit

• 1, Cycle 10A core could be operated safely, and to make an initial evaluation of the performance of the core. It is not the intent of this 'i report to discuss the particular methods of . testing or to present the detailed data taken. Standard test techniques and methods - of data l

!L=.l.

i 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 eacit test, a comparison of the test results with design predictions, and an evaluation I- of the results.

The Surry 1 Cycle 10A Startup Physics Tests Results and Evaluation

. Sheets have been included as an appendix to provide additional information l on the startup test results. Each data sheet provides the following i

information: 1) test identification, 2) test conditions (design), 3) test  !

3 conditions (actual), 4) test results, 5) acceptance criteria, and 6)

comments concerning the test. These sheets provide a compact summary of i

the startup test results in a consistent format. The design test conditions and design values of the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group . 2 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

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, measured and predicted test results,. thus enabling a quick identification

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SECTION 1 J INTRODUCTION AND

SUMMARY

t On September 14,1988. Unit 1 of the Surry ?ower Station was shutdown for maintenance. During Cycle 10', there were indications of fuel failure in the core. During the outage, a single failed assembly was located and e

replaced. The remaining assemblies were then moved back into the core.  ;

Since a full-core off load took place, startup - physics testing was required. Due to a change in the Cycle'10 core Icading, the balance of the cycle will be referred to as Cycle 10A. The Cycle 10A core consists of 19 subbatches of fuel; eight once-burned batches, one from Cycle 6 I

(batch 8B7), three from Cycle 7 (batches 9AS, 9B5 and 9B7) and four from Cycle 9 (batches 11A1, 11A2, 11B2, 11B3); four twice burned batches, one I

from Cycles 6 and 7 (batch 8B3), two from Cycles 7 and 9 (batch 9B4 and 9A4), and one from Cycles 8 and 9 (batch 10A3); four thrice burned

l. batches, one from Cycles 6, 8 and 9 (batch 8B4) and three from Cycles 7, I-l "W 8, and 9 (batches 9A3, 9B3 and S2/9B2); and three fresh batches (batches l 12A, 12B2 and S2/12A1). The core loading pattern and the design Fuel assembly burnups parameters for each batch are shown in Figure 1.1.

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 10A, and Figure 1.5 identifies the location and number of control rods in the Cycle 10A Core.

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On July 5, 1989 at 0647, the Cycle 10A core achieved criticality.

- Following criticality, startup physics tests were performed as outlined  ;

I in Table 1.1. A summary of the results of these tests follows:

1

'1. The ' drop time of each control rod was confirmed to be within the I

2.4 second limit of Surry Technical Specification 3.12.C.I.

2. Individual control rod bank worths for the control rod banks were >

measured using the rod swap technique8 and were' found to be within 7.3% of the design predictions. The sum of the individual control rod bank worths was . measured to be within 2.5% of the design prediction. These results are within the design tolerance of 115% for individual bank worths ( 10% for the rod swap reference bank worth) and the design tolerance of 10% for the sum of the individual control rod bank worths.

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 coef ficient was measured to be within 4.6*. of the design prediction, which is within the design tolerance of 10%. L

5. The isothermal temperature coefficient for the all-rods-out configurntion was measured to be within 1.96 pcm/'F of the design prediction. This result is within the desigt. tolerance of 3 I "" "' ' ^ " ' " " " " " " ' " " "

I I

pcm/'F, and also meets the requirements of Technical l

Specification 3.1.E.1.

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!B 6. Core power distributions for at power conditions were within .

established design tolerances. Generally, the measured core

. -power distribution was within 7 . 3*. of the predicted power distribution. The heat flux hot channel factors and enthalpy rise hot channel factors, F-Q(T) and F-DH(N) respectively, were within the limits of the Technical Specification 3.12.B.I.

In summary, the startup physics test results were acceptable.

Detailed results, together with specific design tolerances and acceptance

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criteria for each measurement, are presented in the appropriate sections ,

g l of this report.

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Table 1.1 '

iI SURRY 1 CYCLE 10A STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS i

L3 i Reference

! Test. Date Time Power Procedure

! Hot Rod Drop Timing Test 7/4/89 0100 llSD 1 PT-7.2 I Zero Power Testing Range 7/5/89 0850  !!ZP 1-PT-28.11 I

l Reactivity Computer Checkout 7/5/89 1004  !!ZP 1-PT-28.11  !

Boron Endpoint

• ARO 7/5/89 1529 Il2P 1 PT-28.11 Temperature Coefficient - ARO 7/5/89 1950  !!ZP 1-PT-28.11 i Dank B Worth 7/5/89 2119 flZP 1-PT-28.11 i I Boron Endpoint - B in 7/6/89 0310 ilZP 1 PT-28.11 Bank D Worth - Rod Swap 7/6/89 0424 ilZP 1 PT-28.11 Bank C Worth - Rod Swap 7/6/89 0915 llZP 1 PT-28,11 '

I Bank A Worth - Rod Swap 7/6/89 1002 liZP 1-PT-28.11 Bank SB Worth - Rod Swap 7/6/89 1111  !!ZP 1-PT-28.11 i Bank SA Worth - Rod Swap 7/6/89 1254 HZP 1 PT-28.11 l Flux Map - Power Distribution 7/7/89 1929 26% 1-PT-28.2 i 5 Verification 1-0P-57 Flux Map Hot Channel Pactor 7/8/89 1846 65% 1 PT-28.2 I

. Verification 1-OP-57 >

Plux Map - I/E Calibration 7/8/89 2224 65% 1-PT-28.2 7 1-0P-57 1-PT-28.2 I 7/8/89 Flux Map - I/E Calibration 2357 65%

1-0P-57 Flux Map - HPP ARO equilibrium 7/19/89 0929 100% 1-PT-28.2 i

,1-OP-57 I

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I LI-l NE-751 SIC 10A Startup Test Report Page 10 of 58

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I NE-751 SIC 10A Startup Tes;t Report Page 12 of 58

LI l

Figure 1.3 SURRY UNIT 1 - CYCLE 10A INCORE INSTRUMENTATION LOCATIONS

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1 I-I I NE-751 S1010A Startup Test Report Page 13 of 58

L I

Figure 1.4 SURRY UNIT 1 - CYCLE 10A t

BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS 4

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I NE-751 SIC 10A Startup Test Report Page 14 of 58

I L

I SURRY UNIT 1 - CYCLE 10A CONTROL ROD LOCATIONS

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I NE-751 SIC 10A Startup Test Report Page 15 of 58

p I  !

I SECTION 2 l rI l l CONTROL ROD DROP TIME MEASUREMENTS r

i I The drop time of each control rod was measured at hot full-flow RCS l

conditions in order to confirm satisfactory operation and to verify that the time from initiation of the rod drop to the entry of the dashpot be less than the maximum allowed by the Technical Specification 3.12.C.l.

l The hot control rod drop time measurements were run with the RCS at hot,  !

full flow conditions (547'T, 2235 psig).

The rod drop time measurements were performed by first withdrawing ,

f a rod bank to its fully withdrawn position, and then removing the movable I

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 and the LYDT (Linear Variable Differential Transformer) primary coil voltage. The rod drop time is determined from this data. Figure 2.1 l 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 l coil fuse is removed. A voltage is then induced Jn the LYDT primary coil as the rod drops. The magnitude of this voltage la 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 I NE-751 SIC 10A Startup Test Report _

Page 16 of 58

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

i I l I  !

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

, 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 j 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 i

I seconds with the RCS at hot, full flow conditions. The test results met I this limit.

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' I SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS l IlOT ROD DROP TIME

SUMMARY

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ROD DROP TIME TO DASHPOT r.NTRY I

SLOWEST ROD FASTEST ROD AVERAGE TIME

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l I ROD DROP TIME TO BOTTOM OF DASHPOT l 7

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SLOWEST ROD FASTEST ROD AVERAGE TIME  !

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B-08 1.87 sec. P-10 1.74 sec. 1.80 sec.  !

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l NE*751 SIC 10A Startup Test Report Page 18 of 58

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I NE-751 S1C10A Startug Test _Refjort _

a Pane 19 of 58

e i

t I l Figure 2.2  ;

SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS  :

ROD DROP TIME - IlOT FULL FLOW CONDITIONS i I j R P N N 6 5 J H 0 F t D C $ 6  !

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NE-751 SIC 10A Startup Test Report Page 20 of 58

+

= -

I i SECTION 3

I i

CONTROL ROD BANK WORTH MEASUREMENTS l.

W Control rod bank worth measurements were obtairied for the control i

and shutdown banks using the rod swap technique . 8 The first step in the rod swap proceduru was to dilute the most reactive control rod bank j (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 and were used to determine the dif ferential 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 I concentration were stabilized such that the reactor was criticci 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 l (i.e., a test bank) was insuted. 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) e 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. Statopoint data (core reactivity, moderator I NE-751 SIC 10A Startup Test Report _

Page 21 of 58

l i

l I

temperature, and the differential worth of the reference bank) were  !

recorded with the reference bank at the MCP. The rod swap maneuver was  !

I 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 f from the core. The rod swap process was then repeated for the other control rod banks (control and shutdown).

I 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 the control and shutdown banks were within the design tolerance (110% for the reference bank and 115% for the test banks), The sum of the individual rod bank worths was measured to be within 2.5% of the design prediction. i

. This is well within the design tolerance of t10% for the sum of the  ;

individual control rod bank worths.  ;

I The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively.

I I The design predictions and the measured data are plotted together in order i

i l Lo illustrate their agreement. In summary, the measured rod worth values i were satisfactory.

,I 1

I r 1I I

I NE-751 SIC 10A Startup Test Report Page 22 of 58

4 qi I 1 Table 3.1 1

SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS 1 CONTROL ROD BANK WORTH

SUMMARY

l I i I MEASURED PREDICTED PERCENT DIFFERENCE  !

WORTil WORTH ( *. ) i BANK (PCM) (PCM) (M-P)/P X 100  ;

I D C

B-Reference Bank 1271.6 1153.7 916.8 1271 1089.6 854.7 0.05 5.88 7.27 i

I A SB SA 331.1 1068.9 953.3 353.4 1017.3 971.2

-6.31 5.07 1.84 i

Total Worth 5695.4 5557.2 2.49 i I i I

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BANK B INTEGRAL ROD WORTH - HZP i BANK B WITH ALL OTHER RODS OUT I

2400 MEASURED I

PREDICTED I

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!I l

l

. NE- 751 S1010A Startup Test Report Page 24 of 58

n ,

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\

I Figure 3.2

[

SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS BANK B DIFFERENTIAL ROD WORTH - HZP BANK B WITH ALL OTHER RODS OUT I

L I

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MEASURED 1

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I NE-751 SIC 10A Startup Test Report Page 25 of 58

7 i

l

,I l SECTION 4 I i

f EORON ENDPOINT AND WORTH MEASUREMENTS I Boron Endpoint l

With the reactor critical at hot zero power, reactor coolant system boron concentrations were measured at selected rod bank configurations I to enable a direct comparison of measured boron endpoints with design  !

predictions. For each measurement, the RCS conditions were stabilized f

I with the control banks et or very near a aelected endpoint position. The  ;

critical boron concentration was then measured. If necessary, an i adjustment to the measured critical boron concentration *sas made to [

account for off-nominal core conditions (rod position and moderator temperature).

The results of these measurements are given in Table 4.1. As shown j r

in this table and in the Startup Physics Tests Results and Evaluation I i

Sheets given in the Appendix, the measured critical boron endpoint values [

were within their respective design tolerances. The measured values met the accident analysis acceptance criterion. In summary, the boron  ;

I endpoint results were satisfactory.

I  :

Boron Worth Coefficient i The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW)

I 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

.NE 751 SIC 10A Startup Test Report ,

Page 26 of 58

f i

t 4

l i

of the endpoint measurement. The value of the boron coefficient, over  !

the range of boron endpoint concentrations, is obtained directly from this j Pl ot.

The boron worth plot is shown in Figure 4.1. As indicated in this i

figure and in the Appendix, the boron worth coefficient was measured to  !

r be -7.52 pcm/ ppm. The measured boron worth coef ficient is within 4.6% '

I of the predicted value of -7.88 pcm/ ppm and is within the design tolerance i

of 110*.. In summary, the measured boron worth was satisfactory. l I i I

I 4 I

I NE-751 SIC 10A Startup Test Report Page 27 of 58

I  !

)

Table 4.1 I

j SURRY UNIT 1 CYCLE 10A STARTUP PHYSICS TESTS  !

DORON ENDPolNTS

SUMMARY

T I Measured Predicted Difference

, g Control Rod Endpoint Endpoint M+P (

g Configuration (ppm) (ppm) (ppm) i ARO 1427 1451 -24 B Bank In 1258 1266* -8

• t

• The predicted endpoint f or the B Bank in cor.figurat ion has been adjusted for the difforence between the measured and predicted values of the endpoint taken at the ARO conf 1puration as shown I

j in the boron endpoint Startup Physics Test Results and Evaluation -

Shoots in the Appendix.  !

I  ;

l  !

I .

l I  :

I P I

NE-751 SIC 10A Startup Test Report Page 28 of 58

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I i

SECTION 5 L

TEMPERATURE COEFFICIENT MEASUREMENT I The isot ermal temperature coefficient (ITC) measurement at the all rods- out condition is 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 ef fects of non uniform nuclear heating.

thus, the moderator and fuel were approximately at the same temperature I

(between 543'T and 547'T) during these measurements.

-l Reactivity measurements were taken during the RCS heatup and cooldowr.

ramps during which the RCS temperature varied approximately 3.0'T.

Reactivity was determined using the reactivity stripchart recorder and temperature was recorded on the average RCS temperature stripchart. The temperature coefficient was then determined from the change in these parameters. The change in reactivity divided by the change in temperature yields the isothermal temperature coefficent.

Lg The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the l

Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient vclue was within the

!I I

NE-751 SIC 10A Startus Test Resort Pane 30 of 58 l

i '

[

lI' :-

l l

i

' design ~ tolerance of 13 pca/'F and met the requirements of Technical I j  !

(, Specification 3.1.E.1. In summary, the measured result was satisfactory. l t

i L3 .

,l .

,a 1 1

I .

l.

I  !.

t

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v.

Table 5.1 SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

ISOTHERMAL TEMPERATURE COEFFICIENT r

BANK TEMPERATURE BORON (PCM/'F)

POSITION RANGE CONCENTRATION

('F) (ppm) COOL HEAT

• DIFFER.

DOWN UP MEAS. PRED. (M-P)

,' I 546.5 D/219 to 1425 -3.50 --- -3.61 -5.57 1.96 543.5 543.4 D/219 to 1425 ---

-3.65 -3.61 -5.57 1.96 546.0 546.2 I 1425 -3.67 -3.61 -5.57 1.96 D/219 to 543.2 I * = AVERAGE OF THREE MEASUREMENTS I

I I

I I

I I

I NE*751 SIC 10A Startup Test Report Page 32 of 58 l

I i l l SECTION 6  :

POWER DISTRIBUTION MEASUREMENTS  ;

l The core power distributions were measured using the incore movable  !

detector flux mapping system. This system consists of five fissien detectors which traverse fuel assembly instrumentation thimbles in 44

~

core locations (see Figure 1.3). For each traverse, the detector output I is continuously monitored on a strip chart recorder. The output is also i

scanned for 61 discrete axial points by the PRODAC P-250 process computer, i I

Full core, three dimensional power distributions are then determined by analyzing this data using the Westinghouse computer program, INCORE , 8 INCORE couples the measured flux map data with predetermined analytic I

power-to-flux ratios in order to determine the power distribution for the r whole core.

A list of the full-core flux maps taken during the test program l together with a list of the measured values of the important power distribution parameters is given in Table 6.1. The measured power I distribution parameter values are compared with their Technical Specifications limits in Table 6.2. Flux Map 10 was taken at 26% power  ;

and served as the base case design check. Flux maps 11 and 16 were taken  !

I at different power levels and control rod configurations. These flux maps were taken to check the at power design predictions and to measure core I

power distributions at various operating conditions. The radial power distributions for the full-core maps are given in Figures 6.1, 6.2 and 6.3. These figures show that the measured relative assembly power values are generally within 7.3% of the predicted values.

I NE-751 SICl0A Startup Test Report Page 33 of 58

I I  !

I  !

l In conclusion, the power distribution measurement. results were I 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 safeiy throughout I Cycle 10A.

)

i I  :

J j

l.

lI 1'

l t l

ll l

I NE-751 SIC 10A Startup Test Report Page 34 of 58

'I l TABLE 6.1 I SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS -

INCORE FLUX MAP

SUMMARY

I .

I ie i i 4 e I

• i l I I i  !

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I NE-751 SIC 10A Startup Test Report _ ,_ _ _____

._. Page ._ 35 _ of 58 _ _ _ _

y i

I ,

Table 6.2 I SURRY UNIT 1 - CYCLE 10A STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS l

WITH THEIR TECHNICAL SPECIFICATION LIMITS

~

F-Q(T) HOT F-DH(N) 110T 1 CHANNEL FACTOR

• CilANNEL FACTOR i MA, NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN l

( *. ) (%) l

,I 10 11 2.12 1.98 4.64 3.57

$4.4 44.7 1,55 1.47 1.90 1.71

.8.4 14.0 .

16 1.79 2.32 22.3 1,44 1.55 7.1

• i

• The Technical Specification's limit for the heat f1ux 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's 11ait listed above is evaluated at  !

the plane of maximus F-Q(T). The minimum margin values listed i i above are the minimum percent difference between the measured -

values of F-Q(T) and the Technical Specification's simit for each ,

map. The measured F-Q(T) hot channel factors include 8% total  !

I uncertainty.

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I I l I l!

SECTION 7  !

REFERENCES j I-D.'A. Trace, "Surry Unit 1 Cycle 10A Design Report "

1.

Technical Report NE-676, Revision 1 Virginia Electric and Power

.I Company,'JJune, 1989.

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

3. W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, '

December, 1967.

4. Surry Technical Specifications, Sections 3.12.C.1 I 3.'12.B.1. and 3.1.E.1. i i

4 I  :

I '

l l.

I ,

I

.NE-751 SIC 10A Startup Test Report Page 40 of SS

ii s .

m ,

l

'1 r

r P

?

APPENDIX I STARTUP PHYSICS TESTS RESULTS l

AND EVALUATION SilEETS

)

I t

I .

p i f

I. 4 r

I I

I NE-751 SIC 10A Startup Test Report Page 41 of 58

. . - -. .- , - - - ~ --

1-PT-28.1 Attm hmes Page 1 of ;

agt! 20 TJ i  !

SURRY POWER STATION UNIT 1 CYCLE 10A

,-iI. ,

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout .

Reference Proc No /Section: 1-PT-28.ll Sequence Step No: ) ,

-II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): l (Design) CB: 225 CC: 225 CD:

• Below Nuclear. Heating ,

III Bank Positions (Steps) RCS Temperature ('F): Md '

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

' I-. Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB: 225 CC: 225 CDt LSA Below Nuclear Heating Date/ Time Test Performed: ~

7 %C1 \D0%

'g Measured Parameter pe = Meas. Reactivty using p-computer s~'ii$- ,

d

g. IV (Description) pg = Inferred React from react period. -

+ u, \, '/'

, ,a c

=

-- 3G Measured Value pg= bM ~M*6 -

^

Test %D = O '

Results b ' '

Design Value .jfI" I*'i.;'

(Actual Conditions)

~

, %D = ((pc Pg)/pt) x 100% 5 4.0%

'"~

qW,y. N ICA.Tt w A 4: q .2e p 772 W44 l (Design Conditions)- %D = .((pe pg )/p g) x 100% 5 4.0% 7 Reference WCAP 7905, Rev. 1, Table 3.6 > , -e : ,

@+At ,

V FSAR/ Tech Spec Not Applicable . . , ,g ,

Acceptance r-';"ih Criteria Reference Not Applicable *'

Design Tolerance is met  : !XES NO VI Acceptance Criteria is met : /YES NO Comments

.I.

• At The Just Critical Position MN< b Allowable Range = ! 3 O ce.4 i

Prepared By: .

Reviewed Bf: #2@ a NE-751 SIC 10A Startup Test Report Page 42 of 58

j I

1-PT-28.13 1 Attachment 1 l Page 2 of 18

! I -

gg JUN 2 91SM J

I,. SURRY POWER STATION UNIT 1 CYCLE 10A STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET lg I Test

Description:

Critical Boron Concentration.- ARO  ;

g Reference Proc No /Section

1-PT-28.11- Sequence Stop No: 4 II lBankPositions_(Steps) RCS Temperature (*F): 547 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225' Other (specify):

- (Design) CB: 225 CC: 225 CD: 225 ; Below Nuclear Heating ,

III Bank Positions (Steps) RCS Temperature ('F): M .4 Test Power Level (% F.P.): 0 I Conditions (Actual)

SDA: 225 SDB: 225 CA: 225 CB: 225 CC: 225 CD: 225 Other (Specify):

Below Nuclear Heating

. Date/ Time Test Performed

I.

~

O l Tlf I S"?.9 Meas Parameter g IV (Description) (CB ) AR0; Critical Boron Cone - ARO

• l" M

'I Test Results.

ed Valaw Design Value (CB) ARO

• I H 2"7 ppm

. fjf.yk Le (Actual Cond) CB" # E PE*'

l'I, Design Value (Design Cond) CB =1451 50 ppm ""

I Referenca NE Technical. Report No. 676, Rev. 1 g

.m.

V FSAR/ Tech Spec aCBxCB 5 15.115 pcm Acceptance [h!

Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met #

I- Acceptance Criteria is met

YES

[,YES

_N0

_N0

~

VI I. Comments aCB = -7.88 pcm/ ppm for preliminary analysis em . 4C g> -7.fg %Am ( R *t.)

,J nm a

Prepared By: Reviewed By: -

I age MM

.NE-751 S1010A Startup Test Report

i 1-PT-28,11 i Attachment 1  :

Page 3 of 18 l jg 2, 9 M

~

SURRY POWER STATION UNIT 1 CYCLE 10A '

STARTUP Pl!YSICS TEST RESULTS AND EVALUATION SilEET I Test

Description:

Isothermal Temperature Coefficient - ARO

. I; Reference Proc No /Section: 1-PT-28.11 Sequence Step No 5 ,

II Bank Positions (Steps) RCS Temperature ('F): 547 i Test Power' Level (*. F.P. ): O Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating

.I_

III Bank Positions (Steps) RCS Temperature ('F): 6W4 Test Power Level (*. F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

.I (Actual) CB: 225 CC: 225 CD: Q\1 C Below Nuc1 car Heating  ;

Date/Tiine Test Performed:

.( 7-s -m two Meas Parameter ISO IV (Description) (a T )ARO Isothermal Temp'Coeff - ARO

~ ' U* I Test Measured Value (' ISO)ARO T = - p i p o/ 4 (CB "l % PPS)

Results

~ ' s Design Value ISO (Actual Cond) (a T )ARO * ~ 6*T l Pcm/'F (CB*l42] ppa) lI l

I ISO 3.0 pcm/'F (a T )ARO = -5.32 >

' Design Value fyl,'A l (Design Cond) (CB = 1451 ppe) -

1 - .. -

lg Reference NE Technical Report No. 676, Rev. 1 Q,i .

1g '

V ISO Acceptance FSAR/ Tech Spec aT s 0.77*pcm/'F aTDop = -1 73 Pcm/'F I

Criteria Reference TS 3.1, NE Tech Report No. 676, Rev. 1 Design Tolerance is met NO I

VI Acceptance Criter.1- is met

/[yIS YES NO Comments

• Uncertainty on aTMOD = 0.5 pcm/'F (

Reference:

memorandum from C. T. Snow'to E. J. Lozito dated June 27, 1980).

O a f .

Prepared By:A .dk) i l Reviewed By: d I '

Page 44 of 58 NE-751. S1C10A Startup Tes_t Report_ __ ___ _ .__ _

t I 1-PT-28.1.j AttOthessi Page 4 of K31 $ Ct .

I SURRY POWER ST.'. TION UNIT 1 CYCLE 10A STARTUP PHYSICS TEST RESULTS AND EVALUATION SilEET I l Test

Description:

Cntl Bank B Worth Meas., Rod Swap Ref. Bank l I. Reference Proc No /Section: 1-PT-28.11 Sequence Step No: 6 II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 lI' Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

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

.III Bank Positions'(Steps) RCS Temperature ('F): 5%.5 Test Power Level (% F.P.): 0

.g Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify): ,

'g (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear lienting Date/Tisc Test Performed:

. ]l$/81 2 / .' ll REF Measured Parameter I B ; Integral Worth of Catl Bank B, 'F.'

All 0ther Rods Out

'^ '

(Description)

TV REF l Test Measured Value I B

/ 2 7/. l.  ; rMak ,

Results m Design Value REF d,@

(Actual Conditions) "

IB /27/ 4 (

l Design Value REF O M9 #

(Design Conditions) Ig = 1271 1 127 pcm

Referesses. W . W S T==hme==L RepeetIBev 676 ', .

If Design Tolerance is exceeded, S ,

shall evaluate impact of test result ,, ,p, V FSAR/ Tech Spec on safety analysis. SNSOC may specify'. '

i'-

Acceptance that additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met  : DES NO VI Acceptance Criteria is met : / YES NO

, x ,. ,,

Prepared By: -- Reviewed By: H,WR I

g - NE-75151C10A Startup Test Report Page 45 of 58 l3

. - _ . _ . - . _ _ . _ . _ . . . . , . . . ~ . ___ _ . _ _ . . _ _ _ _ _ _ .

l

E[- l 1-PT-28.11  !

Attachment 1 1 Page 5 of 18 I j F vut, JUN 2 9 5 )

, SURRY POWER STATION UNIT 1 CYCLE 10A i STARTUP PHYSICS TEST RESULTS AND EVALUATION SilEET I

'I, I.

Reference Test

Description:

Critical Boron Concentration - B Bank In-Proc No /Section: 1-PT-28,11 Sequence Step No: 7

g' II Dank Positions (Steps) RCS Temperature ('F)

547 E ~a** P "ar 'avat ( F P-): o Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): .

(Design) CB: 0 CC: 225 CD: 225 Below Nuclear Heating i Bank Positions (Steps) RCS Temperature ('F):f W .I III 1 Test Power Level (% F.P.): 0 I Conditions (Actual)

SDA: 225 SDB: 225 CA: 225 CB: O CC: 225 CD: 225 Other (Specify):

Below Nuclear lleating Date/Tima Test Performed:

, 7 - (.e - M C 310 Meas Parameter IV (Description) (C )3B D; Critical Boron Conc - B Bank In t

Measured Valna 12.bl y e "

I Test Results Design Value (C)$=

3 bb W,-T (Actual Cond) CB" I Of "

Design Value Prev

^

(Design Cond) CB = 1290 + ACB (10 + 127.1/laC Bl) ppa no g

I.. Reference NE Technical Report No. 676, Rev. 1 V FSAR/ Tech Spec aCBxCB 5 15,115 pcm 7 7

Acceptance M+:1 Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met  : /YES NO Acceptance Criteria is met : M ES NO

'I VI Comments aCB = -7.88 pcm/ ppm for preliminary analysis Prev =

M AC B I CU'6 (Cg)ARO - 1451

~7.S'T % pm ( A wrt ) '"'

Prepared By: f0 -f s v Reviewed By: _A- a I

NE-751 SIC 10A Startup Test Report Page 46 of 58

'l-PT-28.11'

' W- Atterhasent 1 Page 6 of 1-;

W . . ,

p ,% .NN ?. 3 IS l SURRY POWER STATION UNIT 1 CYCLE 10A 1

I. STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Boron Worth Coefficent Measurement.

Reference Proc No /Section: 1 PT-28.11 Sequenca Step No: 7

. II Bank Positions (Steps) RCS Temperature ('F): 547 .j I Test Conditions (Design)

SDA: 225 SDB: 225 CA: 225 CB: Moving CC: 225 CD: 225 Power Level (% F.P.): 0 Other (specify):

Below Nuclear Heating J i

III Bank Positions (Steps) RCS Temperature (*F): INC. l Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

(Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating

- I- ,

Date/ Time Test Performed:

7 /6l %9 O'51 O Measured Parameter

.g IV (Description) aCB , Boron Worth Coefficient .

3  :

I Measured Value aCB" - 7 5' 2.

I Test Results

/m

,pg .. ,

l%kkf Design Value g (Actual Conditions) '

l aCB" O '"

• O '

• M%Q' . .

Design Value . <x~-x l-(Design Conditions) aCB = -7.88 i 0.79 pcm/ppe -

n' ReW4)IWhshntes* Respere unO 476&f^ ~

FSAR/ Tech Spec aCBxCB s 15,115 pcm ,,

y ,

t .

Acceptance

. I- Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met  : [ YES _NO VI Acceptance Criteria is met  : / YES ,NO Comments MIMA Prepared By: Reviewed By:

l l NE-751 S1C10A Startup Test Report Page 47 of 58 t

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

1-PT-28.11 Attcchment

. Page 7 of 3

JUN 2 3 9 i 3 SURRY POWER STATION UNIT 1 CYCLE 10A g STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I- 'lest

Description:

Cutl Bank D Worth Measurement-Rod Swap Reference . Proc No /Section: 1-PT-28.11 Sequence Step No: 9

. II Bank Positions (Steps) RCS Temperature ('F): 547

'E. Test Power Level (*. F.P.): 0 W Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):

(Design) CB: Moving CC: 225 CD: Moving Below Nuclear Heating l III Bank Positions (Steps) RCS Temperature ('F): 6VS4 Test Power Level (*. F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):

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

l 7-G-[9 O '4 'L 't j- Meas Parameter RS pa. (Description) ID ; Int Worth of Cnti Bank D-Rod Swap . ,

1l IV 3 (Mj. Meas. Crit. Ref Bank Test Me.isured Value d Ih = lif3 7,0cm Position = 197 steps)

Results Design Value RS (Adj. Meas. Crit. Ref Ban k- d M'.

(Actual Cond) I D " #00 # cJosition f

= f 9 T steps)  :.j$k '

pg Design Value ID = 1085 i 163 pcm (Critical Ref Bank. . . h;

! (Design Cond) Position = 185 st L_

~

ReSesemose - k N F Repost No; 676 .VEP- 4 NPU-TI-2'.2A ' '.

If Design Tolerance ,is exceeded, SNSOC 2'

shall evaluate impact of test result on l3 V FSAR/ Tech Spec safety analysis. SNSOC may specify that

,5 Acceptance additional testing be performed.

Criteria Reference VEP-FRD-36A

'I Design Tolerance is met  :

1. YES _NO VI Acceptance Criteria is met  : Z YES _ NO '

Comments 4;

Prepared By: Reviewed By: -

I NE-751 SIC 10A Startup Test Report Page 48 of 58

J

<. I

[ .

1-PT-28.11 ]

.c Attotbeent j Page 8 of

~

]

tl W A32 9*.D I SURRY POWER STATION UNIT 1 CYCLE 10A

I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I' Test

Description:

Cnti Bank C Worth Measurement-Rod Swap ,

JI Reference' Proc No /Section: 1-PT-28.11 Sequence Step No: 10 II Bank Positions (Steps) RCS Temperature ('F): 547 iI ,_

Test Conditions (Design)

SDA: 225- SDB: 225 CA: 225 CB: Moving CC: Moving CD:-225 Power Level (* F.P.): 0 Other (specify):

Below Nuclear Heating III Bank Positions (Steps) RCSTemperature('F):6V/,.(p '

Test Power Level (* F.P. ): 0 ,

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

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

7/(c/F'1 O /15 Meas Parameter RS 6 (Description) IC ; Int Worth of Cnti Bank C-Rod Swap .

IV RS (Adj. Matt. Cdt. Ref S:nk i Test Measured Value IC

• N- @ fr Pod tinn a tw etape)

I. Results Design Value RS (Adj. Meas. Crit. Ref Bank WJ '

(Actual Cond)- IC "y @b'7 re , Position = e6/ steps)

Design Value IC = 844 1 127 pcm (Critical Ref Bank -

(Design Cond) Position = 143 steps)

I' Reference 6 Nt" Technica1D Report- No. 676, . VEP-FRD- 1 NFO-TI-2.2A - -

I S&dly If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on l

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

. Reference VEP-FRD-36A

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

.I Comments r

repared By, d' Reviewed By: ,Y I 1 NE-751 S1010A Startup Test Report Page 49 of 58

i l-PT-28.11 Attethment 1 Page 9 of j

JG ; ' ;;

SuRRy r0vER STATION UNIT 1 CrCtE loa  ;

E E STARTUP PilYSICS TEST RESULTS.AND EVALUATION SHEET

3 I Test

Description:

Catl Bank A Worth Measurement-Rod Swap I

g Reference Proc No /Section: 1-PT-28.ll Sequence Step No: 11 II Bsnk Positions (Steps) RCS Temperature ('F): 547 i Test Power Level (*. F.P.): 0

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

(Design) CB: Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): f'/4 0 Test Power Level (* F.P.): 0 3

!g Conditions SDA: 225 SDB: 225 CA: Moving Other (Specify):

lg (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:

7/4k9 /002-  ;

Meas Parameter RS l (Description) I4 ; Int Worth of Catl Bank A - Rod Swap .

IV g3 (Adj. Mass. Crit. Ref Br.= k l _

Test Measured Value I A *DI rem Position = ?^ ***p-)  :

Results i Design Value RS (Adj. Meas. Crit. Ref Bankwn M I (Actual Cond) I 4

=

gem Position a to stope)- ' t.?' -

RS Design Value I g a 355 i 100 pca (Critical Ref Bank ,aggi (Design Cond) Position = 72 steps) - - -

I ReferessenQ M E T8ehmtsek R @ A M M ; e _

NFO-TI-2.2A

• y If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on

'E V Acceptance FSAR/ Tech Spec safety analysis. SNSDC may specify that 5 additional testing be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is eet  : / YES NO VI Acceptance Criteria is met  : / YES NO Comments -

.I_

• Prepared By: c / Reviewed By:

• 6 l

~ NE-751 S1C10A Startup Test Report Page 50 of 58

q

-l

,[ , 1-PT-28.11 l

<W Attachment Page 10 of I JW10 3 CA I l

SURRY POWER STATION UNIT 1 CYCLE 10A )

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test

Description:

Shutdown Bank B Worth Meae. - Rod Swap I Reference Proc No /Section: 1-PT-28.11 Sequence Step No: 12 l

. II Bank Positions (Steps) RCS Temperature ('F): 547  !

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

(Design) CB: Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): W6 2-Test Power Level (% F.P.): 0 m' Conditions SDA: 225 SDB: Moving CA: 225 Other (Specify):

'g (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Datie/ Time Test Performed:

7/4/P9 ////

[ Maas Parameter RS (Description) ISB; Int Worth of Shutdown Bank B-Rod Swap -

IV RS Im I Test Measured Value T 3D M b" 2 IP(Adj. Position Meas. =Crit.

1PS Refsteps)~ Bank

. Results ,

Design Value RS (Adj. Meas. Crit. Ref , s , . D, ..

(Actual Cond) I gg =,10 ccm Position = ,p5 stepshirigg,$ 'i RS Design Value I SB = 10261 154 pcs (Critical Ref Ban %f.py .

(Design Cond) Position = 172 st I-4 9 ,

TT-2.2A :< ..

If Design Tolerance is exceeded, SNSOC l- shall evaluate impact of test result on "

1g V FSAR/ Tech Spec safety analysis. SNSOC may specify that

,3 Acceptance additional tenting be performed.

Criteria Reference VEP-FRD-36A

,I' Design Tolerance is met  : [YES___NO

,j VI C ""*"t*

Acceptance Criteria is met

f YES NO gs Prepared By: .J y [ Reviewed By:  ?!// / 0^/

d

.I NE-751 S1010A Startup Test Report Page 51 of 58

I-t t I

$ 4 - '

L  ; .

J

.1-PT-28.1~.

Attethme2i Page 11 o; J

)

w,.

SURRY POWER STATION UNIT 1 CYCLE 10A  !

lE( g STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test

Description:

Shutdown Bank A 'n' orth Meas. - Rod Swap 'l I. Reference Proc No /Section: 1-PT-28.11- Sequence Step No: 13

. II- Bank Positions (Steps) RCS Temperature ('F): 547 ,

Test- Power Level (% F.P.): O

.I. Conditicus SDA: Moving SDB: 225 CA: 225 Other (specify):

'(Design) CB: Moving CC: 225 CD: 225 Below Nuclear Heating ,

RCS Temperature ('F): SYMF III Bank Positions (Steps)

Test Power Level (% F.P.): 0  ;

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

I (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:

ll 9/0/gg Meas Parameter

/2:5y RS (Description) ISA; Int Worth of Shutdown Bank A-Rod Swape .

IV "

..dj. Mecs. Crit. RofBd l

Test Measured Value I Rs{ = M 3. b ,m(. pe,itgen , f97 sg.p.) <

Results I~I Design Value RS *

(Adj. Meas. Crit. Ref ? 'jgy* - , .

L (Actual Cond) Igg =

Position = str7 stepsXdh  ?

!I l

Design Value I = 971 1 146 pca (Critical Ref Bants*m sMb ,

de i (Design Cond)

Position.= 164 s l .....w.+...

i- -yjtygg$t$ lFf M "~"

j N O TI-2'~2A .

,, g, 3 1 _

If Design Tolerance is exceeded, SNSOC ,,  ;

shall evaluate impact of test result on

.g V FSAR/ Tech Spec safety analysis. SNSOC may specify that

'W Acceptance additional testing be performed. '

, Criteria Reference VEP-FRD-36A l Design Tolerance is met  : / YES NO VI Acceptance Criteria is met : V YES NO

-I' Comments e

- g;y Prepared By.

l -./ Reviewed By: l /heh I

- NE-751 51010A Startup Test Report Page 52 of 58

P l-PT-28.13 4

' Attactusent 1 s >

Page 12 of gi 2 .; .C I - - . . . . . . .

SURRY POWER STATION UNIT 1 CYCLE 10A STARTUP Pl!YSICS TEST RESULTS AND EVALUATION SilEET i

r Lgi I Test

Description:

Total Rod Worth - Rod Swap {

lg. Reference Proc No /Section: 1-PT-28.11 Sequence. Step No: 13

• II Bank Positions (Steps) RCS Temperature ('F): 547 ,

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

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

._ (Design) CB: Moving CC: Moving CD: Moving Below Nuclear lleating

III Bank Positions (Steps) RCS Temperature ('F): 5'f 5.5 5

Test Power Level (% F.P.)

0 i g Conditions SDA: Moving SDB: Moving CA: Moving Other (Specify): -

jg (Actual) CB: Moving CC: Moving CD: Moving Below Nuclear IIcating l'- -

Date/ Time Test Performed:

~1/t /2-1

• Ii 9 Meas Parameter (Description) ITotal; Int Worth of All Banks - Rod Swap-l- IV l re t. Measured Value ITotal " I N 'Y p6 m Results Design Value' y 5 y /, L em tkN1 (Actual Cond) ITotal " t 55(, ,cm 1 D n .

W Design Value (Design Cond)

ITotal = 5555 2 556 pce .

{ ,

j s,q u, .

i l

. .hda +.tM/4lkN a

~ ~

k.'L - <- {k.

If Design Tolerance is exceeded, SNSOC" M shall evaluate impact of test result on , s. ,

V FSAR/ Tech Spec safety analysis. SNSOC may specify that 'N I Acceptance Criteria Reference addit ~1onal testing be performed.

VEP-FRD-36A Design Tolerance is met  : / YES N0 VI Acceptance Criteria is met  : / YES NO

.QQ Prepared By: keviewed By: / #f

-I

- NE-751 SIC 10A Startup Test Report Page 53 of 58

.I -

e-ee ms ep y www-epree e g ww e .i- e wge v-gy g w p-sv www ws w M

l i

1-PT-28.ll l Attethment j Page 13 of l

Nil ; O SURRY POWER STATION UNIT 1 CYCLE 10A

,.i STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1 Test

Description:

M/D Flux Map - Low power <

Re f e rer'ce Proc No / Section: 1-PT-28.2,1-OP-57 Sequence Step No: 41 )

l

. II Bank Positions (Steps) RCS Temperature ('F): TREF 11 Test Power Level (% F.P.): <30 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify) ,

(Design) CB : 225 CC : 225 CD:

• Must have 2 38 thimbles

]

III Bank Positions (Steps) RCS Temperature ('F): SCJ Test Power Level (% F.P.): QL]

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

'I- (Actual) CB : 225 CC : 225 CD: G3 Date/ Time Test: '-M*/RD Performed:

$ Q + - - <5 MAX.NEL NUC ENTHAL TOTAL HEAT QUADRANT.

I' IV Meas Parameter RISE HOT ASSY PWR FLUX HOT POWER TIL M T M.*PE

-(Description)  % DIFF CHAN-FACT CHAN FACT RATIO" *"9'f '

(M-P)/P F-dH(N) F-Q(T) QPTR ,,

.E C A D s Measured Value b 100 '

Test

]* '

l.$%(, Q,tMq M%-

Results yDN '

Design Value ;ggp;; '

(Design Coods) m a= *=

• NA NA 5 1.0 7

&& MWQ;t N V FSAR/ Tech Spec NONE NA g .n .

Acceptance -

,?3 pI ,

Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12

" M *. '

Design Tolerance is met  : NO v.wh

,I Acceptance Criteria is met : ES NO l VI l

Comments

• As Required L **The design value of QPTR is the sum of the .003 design l prediction tilt # and the 1.02. uncertainty identified im% '

L WCAP-7905.

g ._ .__ .._._

l Prepared By: Reviewed By:

I

[

g ..

.g. NE-751 S1010A Startup Test Report Page 54 of 58

)

l-PT-28.11 j Attachment '

Page 14 of  :

I ..u = ;

SURRY POWER STATION UNIT 1 CYCLE 10A i STARTUP PHYSICS TEST RESULTS AND EVALUATION S!!EET .

, 1 I Test Describtion: M/D Flux Map-At Power,NI Calibration I. Reference , Proc No / Section: 1-PT-28.2, 1-0P-57 Sequence Step No: g II Bank Positions (Steps) RCS Temperature ('F):T REF 21 I

Test Power Level (% F.P.): ~ 70  :

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

(Design) . CB . 225 CC : 225 CD: **

III Bank Positions (Steps) PCS Temperature ('F): %6 Test Power Level (*. F.P. ): (,3 4 Conditions SDA: 225 SDB: 225 CA: 225 I (Actual) CB : 225- CC : 225 CD: tSL4 Other (Specify): ,

Date/ Time Test: t-3-959 i Performed: gp g MAX. REL NUC ENTHAL TOTAL !! EAT QUADRANT IV Heas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT I- (Description) *. DIFF (M-P)/P CHAN FACT CHAN FACT F-dH(9) F-Q(T)

RATIO QPTR

08u 4 N jl*0 %f 6 4 1 00") $*

l Test Measured Value gg (,q g { .9Ty g, $l(-Og lI I

Results Design Value (Design Conds) i g = p; m*= => NA NA s 1.02 4A w4 :.Sih:kh k',.S

~

h ;Wi 3 V FSAR/ Tech Spec NONE NA I Acceptance

.g Criteria 5 Reference NONE TS 3.12 TS 3.12 TS 3.12 l

L Design Tolerance is met  : MES NO Acceptance Criteria is met  : . / YES NO VI I Comments

• Must have at least 38 thimhles for a full-core flux map, or at least 16 thi&bles for a quarter-core flux map.

• • As Required g l PreparedBy:if . . Reviewed By: Le!-

LI

~

\ l 1

age 58

• NE-751 SIC 10A Startup Test Report

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

i I.

1-PT-28.1 l Attechmen.>

o Page 15 o

.,ai .

SURRY POWER STATION UNIT 1 CYCLE 10A STARTUP Pi!YSICS TEST RESULTS AND EVALUATION SilEET l

'I Test

Description:

M/D Flux Map-At Power,NI' Calibration  :

Reference Proc No / Section: 1-PT-28.2, 1-0P-57 Sequence' Step Nos 45 II fBankPositions(Steps) RCS Temperature ('F):T 21 I I Test Conditions (Design)

SDA: 225 SDB: 225 CA: 225 CB : 225 CC : 225 CD: ** l Power Level (% F.P.): RE$0 Other (specify): *

~

?

III Bank Positions (Steps) RCS Temperature ('F): TM Test Power Level (% F.P. ): GS ~2.

~:

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

(Actuc1) CB : 225 CC : 225 .CD: t ~6 M Date/ Time Test: 'I - S - 1 S I Performed: ggQq j 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-dH(N) , F-Q(T) ,

O p1'R I Test Measured Value 1 o.9 o Pi, *M,-ssi

1. C90 $ 'N l b ODO goethecade

1. W wi Results 6mAKiuk '

Design Value . .,....

'(Design Conds) i0 2,I'4!,'

NA NA 5 1.02 ,

?*pi'h r b V FSAR/ Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12

/YE!V

~

Design Tolerance is met  : ,_,NO Acceptance Criteria is met  : M ES NO VI I Comments

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

• • As Required e 3r Prepared Bf L . O !) - 1 Reviewed By: /

l

- NE-751 S1010A Startup Test Report Page 56 of 58

)

I l-PT-28.ll '

At tcchme::t Page 16 of l.

.x , \

I SURRY POWER STATION UNIT 1 CYCLE 10A STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET i

I Test

Description:

M/D Flux Map At Power,NI Calibration Reference Proc No / Section: 1-PT-28.2, 1-0P-57 Scquence Step No: 46 II Bank Positions (Steps) RCS Temperature ('F):TRE 11 I Test Conditions

.(Design)

SDA: 225 SDB: 225 CA: 225 CD : 225 CC : 225 CD: **

Power Level (% F.P.): ~$0 Other (specifr):

• 1

. III Bank Positions (Steps) RCS Temperature ('F): 76 6 Test Conditions Power Level (P. F.P.): 4,q 9 ]

.' SDA: 225 SDB: 225 CA: 22S Other (Specify):

(Actual)' CB : 225 CC : 22S CD: \30 ,

y Date/ Time Test: ].S y Performed: qy7 i MAX, REL NUC ENTHAL TOTAL HEAT QUADRANT L IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT .

l- (Description) *. DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR l' I Test Measured Value 1 c.9e 69.eg-84%

q,qo } , y6[ *gg

~

i .C::cc,-

t l

Results gg34,9'g,g QooMe{

i Design Value  ; g gi; ...

7'****: l l

t (Design Conds) "i *

• a > NA NA 5 1.02.

.?

I V Acceptanca FSAR/ Tech Spec NONE

'""*'""' ' b " """ " " NA 2,u w "

g- Criteria E- Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met  : MS, NO Acceptance Criteria is met  : MS ,__NO VI I Comments

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

• • As Required Prepared By L M I Reviewed By:

i NE-751 51C10A Startup Test Report Page 57 of 58

g. - . . . - . . . . -_.- - - . . - - . - - . . - . . . . . . _ - . . . .

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,3 1-PT-38.1 Attachsen i Page 17 o '

$R 3 9 W SURRY POWER STATION UNIT 1 CYCLE 10A STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1

l Test

Description:

M/D Flux Map - HFP, ARD, Eq. Xe j Reference Proc No / Section: 1-PT-28.2, 1-OP-57 Sequence Step No: 47 -;

II Bank Positions (Steps) RCS Temperature ('F):Tggy 21

g Test 'i Power Level (% F.P.)

95 2 5

,5 "d***

(Design)

"' S ^' 225 S "' 225 c^' 225 CB : 225 CC : 225 CD: *

'h*r (8Pecify): Eq. Xe.

i Must have 2: 38 thimbles III Bank Positions (Steps) RCS Temperature ('F): T1fI Test l Power Level (*. F.P.):\C0 %

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

' (Actua1) CB : 225 CC : 225 CD: 6b

'. Date/ Time Test: 1- R- %9 D Performed: gg U, MAX. REL NUC ENTHAL TOTAL !! EAT QUADRANT IV Meas 'Paraset.or ASSY PWR RISE HOT FLUX HOT POWER TILT (Description)

I.  % DIFF (M-P)/P ,

CHAN FACT CHAN FACT F-dHfN) F-Q(T)

RATIO QPTR v.e g d ~

,m,e  ?

9 i

Measured Value I 'M '

q uh rI*5% :S-R u ts ' * '

I'O g De.i V.1.e . : . . ... ~~-

(Desi Conds) bU E** NA NA s 1. 0 5 ,i g ,, g ,7 Acceptance Criteria Reference NONE TS 3.12 TS 3.12 1

TS 3.12 I VI Design Tolerance is met Acceptance Criteria is met

/k

_TYES NO NO Comments

• As Required

'-I *

, g,..

i

'i' Prepared By. s 'll) \

.a Reviewed By: k}

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