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Rev 0 to NE-1148, Surry Unit 2,Cycle 15 Startup Physics Test Rept
	ML20199B071
Person / Time
Site:	Surry
Issue date:	01/05/1998
From:	Bloom D, Lawrence D, Psuik T; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
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References
	NE-1148, NE-1148-R, NE-1148-R00, NUDOCS 9801280176
	Download: ML20199B071 (56)
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qSi ry Unit 2, Cycle 15

{

Startup Physics:

[

Test Report l

}

I Nuclear Analysis and Fuel Nuclear Engineering & Services.

Decentber,1997 qge i ;tR 1 ',6 y),$,: 3,s g i eon Wh*

l'IRGINIA Poller eva e

-o TECHNICAL REPORT NE-1148 - Rev. O SURRY UNIT 2, CYCLE 15 STARTUP PilYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING AND SERVICES.

VIRGINIA POWER DECEMBER 1997 PREPARED BY 8 [Ih

/2 #9)

D. T. Blooe Date REVIEWED BY:

ININ97 "T.

q Paul Date REVIEWED BY:

A8#/hid

/h&f7 I

D. C. Lawrence Date he APPROVED BY:

D. Dzid60sz 47 Date QA Category: Nuclest Safety Related Keywords: SPS2, S2C15, Startup

l.

Cl.As5IFICATION/ DISCLAIMER 4

The data, techniques, information, and conclusions in this report have i

been prepared solely for use by Virginia Electric and Power Company (the Compt.ny), and they may not be appropriate for use in situations other than those for which they have been specifically prepared.

The Company thereforn makes no r.laim or warranty whatsoever, express or implied, as i

i to their accuracy, usefulness, or applicability.

In particular. Tile l

COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A ARTICULAR PURPOSE, NOR SilALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it.

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

the disclaimers of liability and disclaimers of warranties provided f

heroin.

In no event shall the Company be liable, under t.ny_ legal theory whatsoever (whether t.ontract, tort, warranty, or strict or absolute t

liability), for any property damago, 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.

1 NE-1148 S2CIS Startup Physics Tests Report Page 1 of 56

l 0

TABLE OF CONTENTS PAGE 1

l

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

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

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

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

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

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

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

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

21 Section 4 Boron Endpoint and Worth Measurements......

26 Section 5 Temperature Coefficient Measurement........

30 Section 6 Power Distribution'Heasurements............

32 Suction 7 References.................................

39 APPENDIX Ste'. tup Physics Test Results and Evaluation Sheets........................

40 NE-1148 S2C15 Startup Physics Tests Report Page 2 of 56

c l.IST OF TABLES TABl.E TITI.E PAGE 1.1 Chronology of Tests...................................

10 2.1 flot Rod D rop Ti me Summa ry.............................

18 3.1 Cont rol Rod Bank Worth Summary........................

23 4.1 llo r on End po i n t s S u mma ry...............................

18 5.1 Inotharma l Temperature coef ficient Summary............

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

34 6.2 Comparison of Heasured Power Dittribution Parameters

'Jith Their Core Operating Limits......................

35 NE-1148 S2C15 Startup Physics Tests Report Page 3 of 56

4 LIST OF FIGURES FIGURE TITLE PAGE l

1.1 Core Loading Map.........................................

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

12 1.3 Incore Thimble Locations.................................

13 l

l 1.4 Burnable Poison Locations.............................. 14 1.5 Con t ro l R od Loca t ion s....................................

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

19 l

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

20 l

3.1 Bank B Integral Rod Worth -

HZP..........................-

24 l

3.2 Bank B Differential Rod Worth - HEP......................

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

29 6.1 Assemblywise Power Distribution - 30% Power..............

36 6.2 Assemblywise Power Distribution - 69% Power..............

37 6.3 Assemblywise Power Distribution -1001 Power..............

38 i

i l

y l

l NE-1148 S2C D Startup Physics Tests Report Page 4 of 56 l'. -, _. _ _ _ _.,.. _ _. _, _.

__,.._._l

PREPACE This report presents the analysis and evaluation of the ph sics tests

/

which were performed to verify that the Surry 2 Cycle 15 core could be operated safely, and makes an initial evaluation of the 1.orformance 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, coupled with the detailed startup procedures, are on file at the Surry Power Station.

Therefore, only a cursory discussion of these items is included in this report.

The analyses presented include a brief summary of each test, a compar.aon of the test results with design predictions, and an evaluation of the results.

The Surry 2 Cycle 15 Startup Physics Test Results and Evaluation Shoots are included as an appendix to provide additional information on the startup test results.

Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test.

These sheets provide a compact summary of the sta tup test results in a consistent format.

The de11gn test conditions and design values at these design conditions for the measured parameters were completed prior to the startup physics testing.

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

During the tests, the data shoots were used as guidelines both to verify that the proper test conditions were met and to facilitate the NE-1148 S2C15 Startup physics Tests Report page 5 of 56

preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests.

i NE-1148 S2C15 Startup Physics Tests Report

'Page 6 of 56

SECTION 1 INTRODUCTION AND

SUMMARY

)

On - October 6, 1997, Surry Unit 2 shut down for Its fourteenth refueling.. During this shutdown, 57 of the 157 fuel assemblies in the core were replaced with 56 fresh assemblies and 1 once-burned assembly, i

The Cycle 15 core consists of seven sub-batches of fuels two fresh batches (batches 17A' and 178); three once burned batches, two from cycle 14 (batches 16A and 16B), and one from Surry 1 Cycle 13 (batch S1/15A);

and two twice burned batches (batchen 15A and ISB).

The core loading pattern and the design parameters for each sub-batch are-shown in Figure 1.1.

Beginning-of-cycle (BOC) fuel assembly burnups are given in Figure 1.2.

The incore thimble locations available during startup physics testing are identified in Figure 1.3.-

Figure 1.4 identifies the location and number of burnable poison rods for Cycle 15, while Figure '1.5 identifies the control rod locations.

l The Cycle 15 core achieved -initial criticality at 1213 on October 30, 1997.

Startup Physics tests, with the exception of hot rod drops, were peforend after criticality an outlined in Table 1.1.

Hot rod drops t

were performed ' prior to criticality.

A summary of the physics test results follows.

t 1.

The nearured drop time of each control rod was within the 2.4

- second limit of Technical. Specification 3.12.C.1..

NE-1148 S2C15 Startup Physics Tests Report Pa,e 7 of 56

2.

The reference control rod bank was measured with the dilution method, and the result was within 3.0% of the design prediction.

Individual control rod bank worths were measured using the rod swap technique '8 and all results were within 3.6% of the design 8

pred ictions. The sum of the individual measured control rod bank worths was within 0.6% of the design prediction. All results were within the design tolerance of 115% for individual bank worths (110% for the rod swap reference bank worth) and the design tolerance of 110% for the sum of the individual control rod bank korths.

3.

Measured critical borca concentrations for two control bank configurations were within 3 ppe of the design predictions. The all-rods-out (ARO) result was within the 50 ppa design tolerance, and met the Technical Specification A.10. A criterion that the overall core reactivity balance shall be within 11% Ak/k of the design prediction.

The reference bank in critical boron concentration was within its design tolerance.

4.

The boron worth coefficient measurement was within 4.1% of the design prediction, which is within the design tolerance of 110%.

5.

The measured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within 1.29 pcm/'F of the design prediction.

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

The measured ITC was -1.43 pcm/'F.

When the Doppler temperature coefficient

(-1.69 pcm/'F) and a

0.5 pcm/'F uncertainty are accounted for in the +6.0 pcm/'F MTC limit of the NE-1148 S2C15 Startup Physics Tests Report Page 8 of 55

~

Core Operating Limits Report (COLR) Section 2.1, the HTC requirement is satisfied as long as the ITC is less positive than 3.81 pcm/'F.

6.

Noasured core power distributions were within established acceptance criteria and COLR limits.

The average relative assembly power distribution measured / predicted percent difference was 1.8% or less for the three initial power ascension flux maps.

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

channel factois, F-Dil(N), were within the limits of COLR Sections 2.3 and 2.4 respectively.

Note that since there are no 1,0 PAR assemblics in this cycle, the FdH limits for all assemblies are the same.

In summary, all startup physics test results were acceptable.

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

NE-Il48 S2CIS Startup Physics Tests Report Page 9 of 56

Table 1.1 i

SURRY 2 - CYCLE 15 STARTUP PilYSICS TESTS CilRON0h0GY OF TESTS Reference Test Date Time Power Procedure llot Rod Drop - llot Full Flow...

10/29/97 1700 llSD 2-NPT-RX-014 Zero Power Testing Range.......

10/30/97 1302 IlZP 2-NPT-RX-008 Reactivity Computer Checkout...

10/30/97 1340 llZP 2-NPT-RX-008 Boron Endpoint - AR0...........

10/30/97 1800 llZP 2 NPT-RX-008 Boron Worth Coefficient - ARO..

10/30/97 1800 llZP 2-NPT-RX-008 Temperature Coef ficient - ARO.,

10/30/97 1810 llZP 2 NPT-RX-008 i

Bank B Worth...................

10/30/97 1930 llZP 2-NPT-RX-008 Boron Endpoint - B in..........

10/30/97 2330 llZP 2-NPT-RX 008 Bank D Worth --Rod Swap.......

10/31/97 0037 il%P 2-NPT-RX-008 Bank C Worth - Rod Swap........

10/31/97 0117 ilZP 2-NPT-RX-008 Bank A Worth - Rod Swap........

10/31/97 0155 ll2P 2-NPT-RX-008 l

Bank SB Worth - Rod Swap....

10/31/97 "220 llZP 2-NPT-RX-008 Bank SA Worth - Rod Swap.......

10/31/97 0254 ilZP 2-NPT-RX-008 Flux Map - 30% Power...........

10/31/97 2327 29.6%

2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008 6 Power Range Calibration Flux Map - 69% Power...........

11/02/97 1843 68.8%

2-NPT-RX-002 Peakina Factor Verification 2-NPT-RX-008 6 Power Range Calibration Flux Map -100% Power...........

11/07/97 1000

-99.8%

2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008 6 Power Range Calibration l

l t

b NE-1148 S2C15 Startup Physics Tests Report Page 10 of 56

1 o

4 Fig ue 1.1 SURRY UNIT 2 CYCLE 15 CORE LOADING MAP e

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NE-1148 S2C15 Startup Physics Tests Report Page 11 of 56

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l NE-1148 S2C15 Startup Physics Tests Report Page 13 of 56

Figure 1.4 SURRY UNIT 2 - CYCIE 15 BURNAB12 POISON LOCATIONS R

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NE-1148 S2C15 Startup Physics Tests Report Page 14 of 56

s Figure 1.5 SURRY UNIT 2 - CYCLE 15 CONTROL ROD LOCATIONS-R P

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NE-1148 S2C15 Startup Physics Tests Report Page 15 of 56

]

SECTION 2 CONTR01, ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tave of 54715'F) in order to verify that the time from initiation of the rod drop to the entry of the rod !nto the dashpot was less than or equal to the maximum allowed by Technical Spucification 3.12.C.I.

The rod drop times were measured by withdrawing a bank to its fully withdrawn position and tripping all eight evntrol rods within the bank by opening the reactor trip breakers. This allowed the rods to drop into thn core as they would during a plant trip. The Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded for each rod in the bank to determine each rod's drop time.

This procedure was repeated for each bank.

As abown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the increase in IRPI coil voltage when the reactor trip breakers are opened.

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

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

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

This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Suosequent variations in the trace are caused

=

by rorf ncing.

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 f

\\

NE-1148 S2C15 Startup Physics Tests Report Page 16 of 56

.a

- 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 seconds with the RCS at hot, full flow conditions.

The test results satisfy this limit.

In addition, rod be nm as observed at the end of

-each trace whic.h' demonstrated that no ' control rod stuck :in the dashpot region.

l NE-1148 S2C15 Startup Physics Tests Report Page 17 of 56

o Table 2.1..

s SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY 4

SLOWEST ROD FASTEST ROD AVERAGE TIME B-06 1.35 sec.

F-04*

1.25 sec.

1,29 sec.

Rods M-06, K-04, H-lI;.:, and P-08 also had drop times of 1.25 sec.

4 I

I

.s NE-1148 S2C15 Startup Physics Tests Report

'Page 18 of 56

Figure 2.1 SURRY UNIT 2 - CYCLE 15 STARTVP PHYSICS TESTS TYPICAL ROD DROP TRACE sucIwwInc or tasurer (beginning og first downturn in trace) 1 INITIATION OF B00 DOOP BOI1tM OF DASMPCr EVENT Muut (beginning of first upturn in trace)

STATIONART CRIPPER COIL VOLTAGE TRACE 2

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AA A Affil A A A AAAA m son IR,I raIMAtr V V I lif v V W Yl VIi yvvV COIL VOLTACE TRACE AAAAAAAAAa, A A A A A A A A A A A A A A A A A 4 A A A AA A A A.(AAAAAA l A A A A A A A A, 5 V Y,V V W Y v v V V V V Y y y y y i y y y y g y v y 'd i y y i e i = w iyVVWvv.F V V V Vvvv 60H TRACE i

TIME --*-

NE-1148 S2C15 Startup Physics Tests Report Page 19 of 56

Figure 2.2 SURRY UNIT CYCL 2 15 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS-a P

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NE-1148 32C15 Startup Physics Tests Report Page 20 of 56

SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique . The initial step of the rod swap 8

method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniquea, The reactivity changes resulting from the reference bank movements-were recorded.

continuously by the reactivity computer and were used to determine the i

differential and integral worth of the reference bank.

For Cycle 15, i

Control Bank B was used as the reference bank.

After the completion of the reference ' bank reactivity worth measurement,.the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the

-reference bank near full insertion.

Initial statepoint data for tha rod swap maneuver were obtained by moving the reference bank to its fully inserted position with all other banks fully withdrawn and recording the core reactivity and moderator temperature.

From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps and - then ole of the other control rod banks (i

a. a test bank) was inserted to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the ; ore was just critical or near e

the initial statepoint reactivity. This measured critical position (MCP) of the reference bank with the test bank fully inser M eas used to NE-1148 S2C15 Startup Physics Tests Report Page 21 of 56

determine the integral reactivity worth of the test bank.

The core reactivity, moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the itCP. The rod swap maneuver then was repeated in reverse such that the reference bank again was fully inserted with the test. bank fully withdrawn from the core.

This rod swap process was then repeated for each of the other control and shutdown banks.

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

As shown in this table and the Startup Physics Test Results and Evaluation Sheets given 'in the Appendix, all of the individual measured bank worths for the control and shutdown banks were within the design tolerance (110% for the reference bank, 115% for test banks worth greater than 600 pce, and 1100 pcm for test banks worth less than or equal to 600 pcm). The. sum of the individual measured rod bank worths was within 0.6% of the design prediction. This is well within the design tolerance of 110% for the sum of the individual control rod bank worths.

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

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

NE-1148 S2C15 Startup Physics Tests Report Page 22 of 56

e c.

-Table 3.1

. SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH

(%)

BANK (PCH)

(PCM)

(M-P)/P X 100 B-Reference Bank 1537.0 1492.0 3.0 D

1005.0 1022.4

-1.7 C

881.0 914.0

-3.6 A

196.0 200.8

-2.4*

SB 1225.0 1243.5

-1.5 SA 803.0 809.1

-0.8 Total Worth 5647.0 5681.8

-0.6

Dif fe ence is less than 100 pcm.

NE-1148 S2C15 Startup Physics Tests Report Page 23 of a6 -

4 Figure 3.1

(

SURRY UNIT 2 - CYCIE 15 STARTUP PHYSICS TESTS g

BANK 8 INTEGRAL R00 VORTE - HZP ALL UT1tER RODS VITHDRAVN 1000 2

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NE-1148 S2C15 Startup Physics Tests Report' Page 24 of 56

Figure 3.2 SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS BANK B DIITERENTIAL ROD'WORTE - HZP ALL OTHER RODS WITHDRAVN 16 mi l'

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NE-1148 S2C15 Startup Physics Tests Report Page 25 of 56

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

For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. /idjustments to the measured critical baron concentration values were made to account for off-nominal control rod position and moderator temperature, if neceasary.

The results of these measurements are given in Table 4.1.

As shown in this table and in the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The all-rods-out (ARO) endpoint comparison to the predicted value met the requirements of Technical Specification 4.10.A regarding core reactivity balance.

In summary, the boron endpoint results were satisfactory.

Baron Worth Coefficient The measured boron endpoint values provide stabic statepoint data from which the boron worth coef ficient or dif ferential baron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint ecasurement.

NE-1148 S2C15 Startup Physics Tests Report Page 26 of 56

the value-of-the DBW over the range of boron endpoint concentrations was obtained.

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

As indicated in this f3r,ure und in the Appendix, the measured DBW was -7.39 pcm/ ppa. This is within 4.1% of the predicted value of -7.10 ' pcm/ ppm and 'Is well' within the design tolerance of 110%.

In summary, the measured boron worth coefficient was satisfactory.

NE-1148 S2C15 Startup Physics Tests Report Page 27 of 56

Table 4.1 SURRY UNIT 2 - CYCI.E 15 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

(ppa)

(ppe)

ARO.

1901 1898 3

B Bank In 1693 1693*

2

The predicted endpoint for - the B Bank In configuration was-adjusted for the difference between the measured and predicted -

values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheet in the Appendix.

- NE-1148 S2C15 Startup Physics Tests Report Page 28 of 56 4

Figure 4.1 SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured DBW a.7.39 pcm/ ppm 1900

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NE-1148 S2C15 Startup Physics Tests Report Page 29 of 56

SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the all-rods.out condition is measured by controlling the reactor coolant system (RCS) temperature through varying the steam generator blowdown

flow, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.

This test sequence includes a cooldown followed by a heatup.

Reactivity was measured during an RCS cooldown of 3.0*F and an RCS heatup of 2.6'F.

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

Using the statepoint method, the temperature coef ficient was determined by dividing the change in reactivity by - the change in RCS temperature.

An X-Y plotter, which

. plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured ITC.

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

As can be seen from this summary and from the Startup Physics Test Results and_ Evaluation Sheet given in_the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of 13 pcm/'F.

Accounting for the Doppler temperature coefficient (-1.69 pcm/'F) anl a 0.5 pcm/'F uncertainty, the moderator temperature coef ficient was 0.76 pcm/'F, which meets the requirement of Core Operating Limits Report Section 2.1.

In summary, the measuted result was satisfactory, t

NE-1148 S2C15 Startup Physics Tests Report

'Page 30 of 56

Table 5.1 SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/ F)

D-BANK TEMPERATURF BORON POSITION RANGE CONCENTRATION C/D

.H/U AVE.

DIFFER.

'(.F)

(ppm)

MEAS.

PRED.

(M-P) 543.8 214/215 to 1896

-1.50

-1.35 -1.43

-2.72 1.29 548.3

.NE-1148 S2C15 Startup Physics Tests Report Page 31 of 56

I SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the movable incore detector flux mapping system.

This system consists of five fission chamber detectors which traverse fuel assembly instrumentation.himbles depicted in Figure 1.3.

For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the FRODAC P-250 process computer.

Full core, three-dimensional power distributions are determined from this data using the CECOR code'.

CECOR couples the measured voltages with predetermined analytic signal-to power conversions, pin-to-box factors, and average coupling coefficients in order to determine the power distribution for the whole core.

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

A comparison of these measured values with their Technical Specification limits as specified in the COLR' is given in Table 6.2.

Flux map 2 was taken at approximately 30% power to verify the radial power distribution (RPD) predictions at low power.

Figure 6.1 shows the measured RPDs from this flux map.

Flux maps 3 through 4 were taken near 69% and 100% power, respectively, with different control rod configurations. These flux maps were taken to check at power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 through 6.3.

These figures show that the average relative assembly power distribution measured / predicted percent NE-ll48 S2C1'. Startup Physics Tests Report Page 32 of 56

difference was 1.8% or less for the three maps.. The measured F-Q(Z)-and F-Dil(N) peaking factor values -for all flux maps were within the limits of - the Core. Operating Limits Repott (COLR) Sections 2.3 and 2.4, respectively. Flux maps 2 and 3 were used to recalibrate the power range excore detectors. Power range detector calibration contants based on flux map 4 measurements verified the existing calibration from map 3 was satisfactory.

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

It is therefore anticipated that the core will continue to operate as designed throughout Cycle 15, NE-1148 S2C15 Startup Physics Tests Report Page 33 of 56

TABLE 6.1 SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

l l

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1 1

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No.1 1

DESCRIPTION ING.

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1. F-O(FI INCLUDES A T0f At UNCERI AINTY OF l.08.

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DEFleED AS TE AVERAGE GUADRANT PONER 1111 FROM CECOR.

1. I ACH MAP NAS USED 10 PtRFORM A M AEING F ACTOR WERIFICAf10N ANO A MnN R WANCE EXCout DE TECTOR CAL ISRATIDet. IE Flux MAP 4 CallDRAll0N VERIFilD IE (IISilNG CALIBRAll0N.

l NE-1148 S2C15 Startup Physics Tests Report Page 34 of 56

t - o Table 6.2 SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS COMPARISON OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS l

Il-PEAK F-Q(Z) HOT--

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

CHANNEL FACTOR **

CHANNEL FACTOR //

(AT NODE OF MINIMUM MARGIN) l MAP MEAS LIMIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN NO.

(%)

2 2.041 4.501 19 2.041 4.501 19 54.7 1.556 1.890 17.7 3

1.836 3.270 19 1.836 3.270 19 43.9 1.503 1.706 11.9 4

-1.773 2.324 34 1.728 2.254 19 23.3 1.497 1.561

-4.1

The Technical Specification's limit for the heat flux hot channel factor, F-Q(Z), is a function of core height and power level.

The values for F-Q(Z) listed are-the maximum value of F-Q(Z) in the core.

The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(Z).

- The value for F-Q(Z) listed above is the value at the plane of minimum margin. The minimum margin values listed are the minimum -

r'ircsnt difference between the measured values of F-Q(Z) and the Technical Specification's limit at that node for each map.

.The measured F-Q(Z) hot channel factors include 8% total uncertainty.

Since all fuel assemblies in the core are-SIF fuel (i.e. there are no lopar assemblies), the FdH(N) limit for all assemblies is the same.

1 NE-1148 S?C15 Startup Physics Tests Report Page 35 of 56

Figure 6.1 SURRY UNIT 2 - CYCLE 15 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 30% POWER 9

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SUMMARY

NAP NO: $2-15-02 DATE: 10/31/97 POWER: 29.6%

CONTROL R00 POSITIONS:

F-EH Z ) a 2.941 QPTR:

D BANK AT 191 STEPS F-DHIN) = 1.556 NW 0.9856 i NE 1.0142 i

FlZI

1.230 SW e.9665 i SE 1.b138 BURMUP

5.0 MWD /MTU A.O. a 6.752%

l NE-1148 S2C15 Startup Physics Tests Report

~Page 36 of 56

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0.5.

2.3.

0.327. 0.522. 0.974. 0.841. 0.974. 0.522. 0.327.

. 0.343. 0.524. 0.974. 0.8M. 0.99). 0.524. 0.379 l(

4.4.

4.4 0.0.

0.6.

1.7.

4.4 0.5 EfANDARO

, 0.262. 0.303. 0.262.

AWERACE DEVI A tlON

. 9.262,0.305. 9.2%.

.PCI DIFFERENCE.

3(

al.314 9.2.

0.7 1.6.

=

1.4 j

SUMMARY

NAP NO: $2-15-04 DATE: 11/07/97 POWERt 99.83%

CONTROL R00 POSITIONS:

F-OtZ1 a 1.773 GPTR D BANK AT 228 STEPS F-DHIN) = 1.497 NW 0.9904 l NE 1.0077 1

F(Z)

= 1.088 SW 0.9906 l SE 1.0112 l

BURNUP =

178 MWD /MTU A.O. = -0.722%

NF.-1148 S2C15 Startup Physics Tests Report Page 38 of 56

SECTION 7 REFERENCES

1. T. S. Paulk and C. B. LaRoe, "Surry' Unit 2 Cycle 15 Design Report",

Technical Report NE-1146, Revision 0, October, 1997.

2. T. K. Ross, W. C. Beck. " Control' Rod Reactivity Worth Determination By The Rod Swap Techniquc," VEP-FRD-36A, December, 1980.

3. Letter from W. L. Stewart (Virginia-Power) to the U.S.N.R.C.

"Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of.Startup Physics Test Program - Inspector Followup Item 280, 281/88-29-01", Serial No.89-541, December 8, 1989.

4. T. W. Schleicher, " Reactor Power Distribution Analysis Using a Hoveable In-Core Detector System and the TIP/CECOR Computer Code Package", VEP-NAF-2, November, 1991.

5. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, 4.10,A, and 5.3.A.6.b.

6. " Core Operating 1.imits Report Surry 2 Cycle 15 Pattern UZ, Revision.0", September, 1997.

NE-1148-S2C15 Startup Physics Tests Report Page 39 of 56

APPENDIX STARTUP PilYSICS TEST RESULTS AND EVALUA1 ION SHEETS

\\

NE-1148 S2C15 Startup Physics Tests Report Page 40 of 56

. s SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I,

Test Descriptiort; Zero Power Testing Range Determination

_Reforence Proc No / Section:

2.NPT.O.X-008 Sequence Step No:

11 Bank Positions (Steps)

RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):

(Design)

CB:

229 CC:

CD:

Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature ( F):5'I74 Test Power Level (% F.P.): O Conditions SDA: 229 SDB: 229 CA:

229 Other (speelfy):

(Actual)

CB:

229 CC: 21'l CD: IW Below Nuclear Heating Date/ Time Test Performed:

10/30)97 13 0:2.

Reactivity Computer Initial Flux Background Reading o# amps 8

IV

%uUy ew.es.,+ si.t. 4 3h w%s Test Results Flux Reading At Point Of Nuclear Heating 3 o x 16*' ar es 4

Zero Power Testing Rar.ge i < 10" to lo y 16 amps Reference Not Applicablo V

FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met"

/ YES NO Acceptance Criteria is met" :

V_YES

__ NO Vi

At The Just Critical Position Comments " Design Tolerance and Acceptance Criteria are met if ZPTR is below the Point of Nuclear Heatirg and above background.

O Prepared By: OM,_ 9.

Reviewed By:

NE-1148 S2015 Startup Physics Tests Report Page 41 of 56

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Reactivity Computer Clieckout Reference Psoc No / Section:

2 NPT-RX-008 Sequence Step No:

RCS Temperature ( F): 547 11 Bank Positions (Steps)

Power Level (% F.P.): 0 Test Conditions SDA: 229 SDB: 229 CA-220 Other (specify):

Below Nuclear Heating (Design)

CB. 229 CC:

CD:

RCS Temperature ( F): 54 r.5 Ill Bank Positions (Steps)

Power Level (% F.P.): O Test Conditions SDN 229 SDB: 229 CA: 229 O'her(specify):

(Actual)

CB: 229 CC: 22.9 CD:._/09 Below Nuclear Heating Date/ Time Test Performed:

I o /Wo /ot'~l 13Wo Measured Parameter Pe= Measured Reactivity using p-computer (Description)

Pt= Predicted Reactivity IV Results Measured Value pc= M.O i #I9' #

Test Pt" -4 5,'i s d*f

%D=

3 /, ~ 1 2-

%D= {(Pc Pt)/ } x 100% s 4.0 %

Pt Design Value WCAP 7005, Rev.1. Table 3.6 Reference

. SARTI'ech Spec Not Applcable V

Acceptance Not Applicable Criteria Reference Design Tolerance is met

/ YES NO V YES NO Acceptance Criteria is met :

VI

At The Just Critical Position The allowable range will be set based on the above results, as well as Comments results from the benenmark test.

Allowable Rango = ' N/"" b "

/"#

>k.

Reviewed By: d O. -

Prepred By: _

NE-1148 S2C15 Startup Physics Tests Report Page 42 of 56

. s SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1

Test

Description:

Critical Boron Concentration ARO Reference Proc No / Section:

2 NPT RX-008 Sequence Step No:

11 Bank Positions (Steps)

RCS Temperature (*F): 547 Power Level (% F.P.): O Test Conditions SDA 229 SDB: 229 CA' 229 Other(specify):

(Design)

CB: 229 CC: 229 CD: 229 Below Nuclear Heating ill Bank Positions (Steps)

RCS Temperature ( F): iv7, o Power Level (% F.P.): O Test Conditions SDA: 229 SDB: 229 229 Other(specify):

(Actual)

C9: 229 CC: 229

' 3.

229 Below Nuclear Heating Date/Tirpe Test Performed:

lo/30/47 1600 Measured Parameter (Cs)"ARo; Critical Boron Concentration - ARO (Descr:ption) l IV Test Results Measured Value (Cs)"Ago=

id/ ppm r

(Design Conditions)

Design Value Ce = 1898

50 ppm (Design Conditions) l Reference Technical Repc,it NE 1146. Rcv. O V

FSARRech Spec loCBxCB l s;1000 pcm Acceptance Criteria Reference Technical Specification 4.10.A

/

Design Tolerance is met YES NO Acceptance Criteriais met :

YES NO VI Comments ace = -7.09 pcm/ ppm CB a l(C )"ARo - C l; CB s design value B

B i

nM M

Prepared By:

AI Reviewed By:

l'(/

NE-1148 S2C15 Startup Phyr.ics Tests Report Page 43 of 56

- e

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

1sothermal Temperature Coefficient. ARO l

Reference Proc No / Section:

2 NPT RX-008 Sequence Step No:

11 Bank Positions (Steps)

RCS Temperature ( F): 547 Power t.evo' (% F.P.): C Test Conditions SDA-229 SDB: 229 CA: 229 Other (specify):

(Design)

CB: 229 CC: 229_ CD: 229 Below Nuclear Heating RCS Temperature ( F): fy4 6 ill Bank Positions (Steps)

Power L.evel(% F.P.): 0 Test Conditions SDA: 229 SDB: 229 CA: 229 Other(specify):

(Actual)

CB: 229 CC: 229 CD: Zl'//tif Below Nuclear Heating Datemrge Tpst Performed:

/0/30/f7

/U/o Measured Parameter (ar )ARO:

IsothermalTemperature Coefficieni-QRO (Description)

(apso)Agg, -- f,4 3 pcmFF IV Test Measured Value (Cs= /89[/ ppm)

Results nasign Value (aT'* )ARO= "I' 13.0 pcmFF (Actual Conditions)

(Cs= /696 ppm)

Design Value (Design Conditions)

(oT'* )ARO"

2.7013.0 pcmFF (Cs= 1893 ppm)

Technical Report NE 1148. Rev. O Reference n'5 s 3.81

pcmfF V

FSAR/COLR

= -1.69 pcmFF or Acceptance COLR 2.1.1 Technical Report NE 1146, Rev. 0 Criteria Reference

/ YES

.NO Design Tolerance is met Acceptance Criteriais met : _ ] YES NO VI

Uncertainty on aTuoo = 0.5 pcmfF (

Reference:

memorandum from Cornments C.T. Snow to E.J. t.ozito dated June 27,1980.)

.2 A f).'?

Roviewed By: kb Pra ard By:

I' y

NE-1148 S2C15 Startup Physics Tests Report Page 44 of'56

SURRY POWER STATION UNIT 2 CYCLE 15 c

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Control Bank B Worth Measurement, Rod Swap Ref. Bank Reference Proc No / Section:

2-NPT RX-008 Sequence Step No:

11 Bank Positions (Steps)

RCS Temperature ( F): 547 Test Power level (% F.P.): O Conditions SDA: 223 SDB: 229 CA-229 Other (specify):

(Design)

CB: moving CC: 229 CD: 229 Below Nuclear Heatind lll Bank Positions (Steps)

RCS Temperature ( F): Sc/4,, f Test Power Level (% F.P.): O Ccnditions SDA' 229 SDB: 229 CA* 229 Other (specify):

(Actual)

CB: moving CC: 229 CD: 229 Below Nuclear Heating Datemnie Test Performed:

10/b/47 l910 Measured Parameter is"E'; integral Worth of Control Bank B, (Description)

AllOther Rods Out IV Test Measured Value la"E'=

f f3 7 pcm Results Design Value (Design Conditions) is"E'= 1492 i 149 pcm Eeference Technical Report NE-1146, Rev. O If Design Tolerance is exceeded, SNSOC shall V

FSAR/ Tech Spec evaluate impact of test result on safety ar.alysis.

Acceptanco SNSOC may specify that additional testing Criteria be perfo med.

Reference VEP FRD-36A

/

Design Tolerance is met

YES NO f

/ YES NO Acceptance Criteria is met :

VI Comments A

/1 Prepared By:

I-Reviewed By: c/

/'

/

NE-1146 S2Cl3 Startup Physics Tests Report Page 45 of 56

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Critical Boron Concentration - B Bank in Reference proc No / Section:

2-NPT RX-008 Sequence Step No:

11

' E,ank Positions (Steps)

RCS Temperature ( F): 547 Power Level (% F.P.): 0 Test Conditions SDA: 229 SDB: 229 CA* 229 Other (specify):

(Design)

CB:

O CC: 229 CD: 229 Below Nuclear Heating ill Bank Positions (Steps)

RCS Temocrature ( F): gg j Power Level (% F.P.): O Test Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):-

(Actual)

CB:

O CC: 229 CD: 229 Below Nuclear Heating Datefrime Test Performed:

t0 l30lM

'h 3 0 (C)"el Critical Boron Concentration, Measured Parameter B

B Bank in (Description)

IV Test Results Measured Value (Ce)"s= \\(, %

ppm (Design Conditions)

Des 1 n Value Ce = 1688 + ACs Pm i(10 + 149.2/laCol) ppm 9

(Des 1 n Conditions)

Ce = l@[

i 31 ppm 9

Technical R s. port NE 1146, Rev. 0 Reference V

FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable d YES NO Design Tolerance is met Acceptance Criteria is met :

/ YES NO VI Comments oCB = -7.10 pcm/ ppm 6Cs "* = (Cs)"ARO - 1898 ppm Prepared By: b [ b Reviewed By: A03 NE-1148 S2C15 Startup Physics Tests Rt. port Page 46 of 56

, s SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

HZP Boron Worth Coefficient Measurement Reference Proc No / Section:

2 NPT.RX-008 Sequence Step No:

ll Bank Positions (Steps)

RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):

(Design)

CB: moving CC: 229 CD: 229 Below Nuclear Heating 111 Bank Positions (Steps)

RCS Temperature { F): 5C1.0 Test Power Level (% F.P.): O Conditions SDA-229 SDB: 229 CA-229 Other (specify):

(Actual)

CB: moving CC: 229 CD: 229 Below Nuclear Heating Date/ Time Test Performed:

schols 1 moo Measured Parameter aCs; Boron Worth Coefficient (Description)

IV Test l

Results Measured Value aCs =

7,3%

pcm/ ppm l

Design Value aCs =

7.10 t 0,71 pcm/ ppm (Design Conditions)

Reference Technical Report NE 1I40, Rev. O V

FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met

_/_ YES NO Acceptance Criteria is met :

/ YES NO VI Comments k

Prepared By: bN Reviewed By:

NE-1148 S2C15 Startup Physics Tests Report Page 47 of 56

~ - -

GURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Control Bank D Worth Measurement, Rod Swap Reference Proc No / Section:

2 NPT RX-008 Sequence Step No.-

11 Bank Positions (Steps)

RCS Temperature ( F): 547 Power Level (% F.P.): 0 Test Conditions SDA: 229 SDB: 229 CA-229 Other (specify):

(Design)

CB: moving CC: 229 CO: moving Below Nuclear Heating 111 Bank Positions (Steps)

RCS Temperature ( F): 5 %.5 Power Level (% F.P.): O Test Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):

(Actual)

CB: moving CC: 229 CD: moving Below Nuclear Heating Date/ Time Test Performed:

lb/ 3tl9"'l OOV$~7 Measured Parameter lo ; integralWorth of Control Bank D, ns Rod Swap (Description)

IV Measured Value lo = 100f pem (Adjusted Measured ns Critical Reference Bank Position = i1.9 steps)

Test Results Design Value

[

(Actual Conditions) lo =

l0'2,2..N B:.m (Adjusted Measured ns Critical Reference Bank Position a i2A steps)

Design Value ns (Design Conditions) lo = 1026 t 154 pcm (Critical Reference Bank Position = 143 steps)

Technical Report NE 1146. Rev. O,VEP FRD 36A Reference FSAR/rech Spoc if Design Tolerance is exceeded, SNSOC shall

. evaluate impact of test result on safety analysis.

V SNSOC may specify that additional testing Acceptance Criteria be performed.

Reference VEP FRD 36A NO Design Toleranceis met 2 YES NO Acceptance Criteria is met :

_/ YES VI Comments Prepared By: DN MdkW Reviewed By: fLD4 NE-1148 S2C15 Startup Physics Tests Report Pago 48 of 56

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

. ~

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Control Bank C Worth Measurement, Rod Swap l

Reference Proc No / Section:

2 NPT RX-008 Sequence Step No:

ll Bank Positions (Steps)

RCS Temperature ( F): 547 Power Level (% F.P.): O Test Conditions SDA-229 SDB: 229 CA-229 Other (specify):

(Design)

CB: moving CC: moving CD: 229 Below Nuclear Heating ill Bank Positions (Steps)

RCS Temperature ( F): 54(,5 Power Level (% F.P<): 0 Test Conditions SDA: 229 SDB: 229 CA-229 Other (specify):

(Actual)

CB: moving CC: meving C.D: 229 Below Nuclear Heating Date/ Time Test Performed:

ID/3L/97 Olil'1 Measured Parameter Ic"8; Integral tVorth of Control Bank C, Rod Swap (Description) 1 Ic"8" W pcm (Adjusted Measured IV Measured Value j

Critical Reference Bank Position = 10 ~1 steps)

Test Resulta Design Value RS.

9 IQ,0 pcm (Adjusted Measured IC (Actual Conditions)

Critical Reference Bank Position = lO'T rteps)

Design Value (Design Conditions)

Ic"8= 912 137 pcm (Critical Reference Bank Position = 118 steps)

Technical Report NE ii46 Rev. O.VEP FRD 36A Iteference FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall evalua:e impact of test result or, safer / anclysis.

V SNSOC may specify that additional testing Acceptance be performed.

Criteria VEP-FRD 36A Reference Design Tolerance is met v/, YE3

_NO Acceptance Criteria is met :

/ YES NO VI Comments Prepared By: _hN kLddhrun Reviewed By: Abbd NE-1148 S2C15 Startup Physics Tests Report Page 49 of 56

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Contro! 3ank A Worth Measurement, Rod Swap Reference Proc No / Section:

2.NPT.RX.008 Sequence Step No:

ll Bank Positions (Steps)

RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 229 SDB: 229 CA moving Other (specify):

(Design)

CB: moving CC: 229 CD: 229 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature ( F): 6%,3 Power Level (% F.P.): O Test Conditions SDA* 229 SDB: 229 CA moving Other (specify):

(Actual)

CB: moving CC: 229 CD: 229 Below Nuclear Heating Date/ Time Test Performed; to/Si /9~?

OM55' Measured Parameter IA s; integralWorth of Control Bank A, (Description)

Rod Swap IV Measurcd Value IA"$

k3(o pcm (Adjusted Measured 8

Test Critical Reference Bank Position =

39 steps)

Results Design Value (Actual Conditions) lARs= 200,6 Pem (Adjusted Measured Critical Reference Bank Position = 39 steps)

Design Value 8= 201 100 pcm (Design Conditions) lA (Critical Reference Bank Position = 39 steps)

Reference Technical Report NE.1146. Rev. O. VEP FRD 36 A FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall V

evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be performed.

Reference VEP.FRD 36A Design Tolerance is met i YES NO Acceptance Criteria is met :

V YES NO y

VI Comments Prepared By: DNdw Reviewed By: (4 3..l W N NE-1148 S2C15 Startup Physics Tests Report Page 50 of 56

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Shutdown Bank B Worth Measurement Rod Swap I

Reference Proc No / Section:

2 NPT RX-008 Sequence Step No:

RCS Temperature [F): 547 11 Bank Positions (Steps)

Power Level (% F.P.): O Test Conditions SDA: 229 SDB: moving CA-229 Other (specify):

(Design)

CB: moving CC: 229 CD: 229 Betow Nuclear Heating RCS Temperature ( F): Ol6W 111 Bank Positions (Steps)

Power Level (% F.P.): O Test Conditions SDA-229 SDB: moving CA: 229 Other(specify):

(Actuat)

CB: moving CC: 229 CD: 229

_ Below Nuclear Heating Daterrime Test Performed:

to/3 /T7 OM30 Iss ; Integra1 Worth of Shutdown Bank B, as Measured Parameter l

Rod Swap (Description) lse"'" 17 6 re.m (Adjusted Measured IV Measured Value CriticalReference Bank Position a l'12_ steps)

Test Results Design Value nse IM3.f rcm (Adjusted Measured (Actual Conditions) lse Critical Reference Bank Position = l *f 2 steps)

Design Value nsa 1242 i186 pcm (Design Conditions) ise (Critical Reference Bank Position = 186 steps)

Technical Report NE 1146, Rev. O, VEP FRD 36A Reference il Design Tolerance is exceeded, SNSOC shall FSAR/ Tech Spec evaluate impact of test result on safety analysis.

V SNSOC may specify that additional testing Acceptance be performed.

Criteria

,VEP FRD 36A Raference

,NO

[ YES Design Tolerance is met No Acceptance Criteriais met :

V YES VI Comments AQhwb~

db Reviewed By:

Prepared By: _

NE-1148 S2C15 Startup Physics Tests Report Page 51 of 56

SURRY POWE, JmTION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Shutdown Bank A Worth Measurement. Rod Swap Reference Proc No / Section:

2 NPT RX 008 Sequence Step No:

ll Bank Positions (Steps)

RCS Temperature ( F): 547 Power Levrj (% F.P.): 0 Test Conditions SDA: moving SDB: 229 CA 229 Other (specify):

(Design)

CB: moving CC: 229 CD: 229 Below Nuclear Heating RCS Temperature ( F): Ss.r. Y s~

ill Bank Positions (Steps)

Power Level (% F.P.): 0 5%.4,./pk1 Test Conditions SDA: moving SDB: 229 CA 229 Other(specify):

(Actual)

CB: moving CC: 229 CD: 229 Below Nuclear Heating Date/ Time Test Performed:

to/u /9 7 oz:sM Measured Parameter ISA 8;integralWorth of Shutdown Bank A, Rod Swap (Description)

IV Measured Value IsA"8= 603 m

(Adjusted Measured Critical RLference Bcrik Position =

9 5' steps)

Test Results Design Value IA s= 6di. / /(*

(Adjusted Measured (Actual Conditions)

S Critical Reference BarA Position = 9 fsteps)

Design Value (Design Conditions)

ISA s= 810 t 122 pcm (Critical Reference Bank Position = 99 steps)

Technical Report NE 1146. Rev. 0 VEP FRD 36A Reference FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.

V SNSOC may specify that additional (esting Acceptance 6

Criteria be performed.

Reference VEP FRD-36A Design Tolerance is met

/_YES

_NO Acceptance Criteria is met :

/ YES NO VI Comments MQMd kk%

Reviewed By:

Prepared By:

NE-1148 S2C15 Startup Physics Tests Report Page 52 of 56

^

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEE Test

Description:

Tetal Rod Worth, Rod Swap I

Re'erence Proc No / Section:

2-NPT RX-008 Sequence Step No:

RCS Temperature ( F): 547 11 Bank Positions (Steps)

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

Below Nuclear Heating (Design)

CB: moving CC: moving CD( moving RCS Temperature ( F): 546 5~

ill Bank Positions (Stcps)

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

Below Nuclear Heating (Actual)

CB: moving CC: moving CD: moving Daterrirpe Test Performed:

ol30IC;7 (9'3 O ITotai;integralWorth of AllBanks, Measured Parameter Rod Swap (Description)

IV Measured Value ITotal: F6 tl7 pcm Test Results Design Value (Actual Conditions)

ITotal: 66 E,l.6 pcm l

Design Value (Design Conditior.t)

ITotat= 5683 t 568 pcm Technical Report NE 1146. Rev. O. VEP FRD 36A Reference if Design Tolerance is exceeded, SNSOC shall FSAR/ Tech Spec evaluate impact of test result on safety analysis.

V Additional testing must be performed.

Acceptance Criteria rVEP-FRD-36A Reference NO Design Telerance is met d YES 7 YES NO Acceptance Criteriais met -

VI Comments Reviewed By: (bh DkMM Prepared By:

NE-1148 S2C15 Startup Physics Tests Report p3Ae 53 of 56

AT7ACJW I SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

IND Flux Map. At Power Reference Proc No / Section:

2-NPT RX-008,002 Sequence Step No:

11 Bank Positions (Steps)

RCS Temperature (F): TREF i 1 Yest Power Level (% F.P.): s: 30 Conditions SDA: 229 SDB: 229 CA 229 Other (specify):

CD:

Must have 2 38 thimbles" (Des 1 n)

CB: 229 CC:

9 lli Bank Positions (Steps)

RCS Temperature ( F): Tace Test Power Level (% F.P.): 29.'55 Conditions SDA: 229 SDB: 229 CA 229 Other (specify):D (Actual)

CB: 229 CC: A CD: 19I Date/Timc Test Performed:

16/5th'/ @.252'7 Maximum Relative Nuclear Enthalpy Total Heat Maxinium Measured Assembly Rise Hot Flux Hot Positive incore Parameter Power %DIFF ChannelFactor Chann'aj Quadr.nnt IV (Description)

(M P)/P FAH(N)

Factor Fo(Z)*

Power Tilt Test Measured

-%'3 P t o.'t t

- 0H 8.ol+2 Results value 8.8 T! 4 0.9 Design Value t10% for Pik0.9 (Design 115% for Pic0.9 N/A N/A s 1.02 (P a assy power)

Conditions) i Referenee WCAP.7905, Rev.1 None None WCAP.7905, Rev.1 V

FSAR/ cot.R None FAH(N)si 56(1+0.3(1 P))

Fo(Z)s4.64*K(Z)

None Acceptance Criteria Reference None COLR 2.4 COLR 2.3 None Design Tolerance is met v YES NO Acceptance Criteria is met :

v YES NO VI

As required Comments

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

)

Prepaied By:

k@ h Reviewed B Me v

NE-1148 S2Ct5 Startup Physics Tests Report Page 54 of 56

krrAcc(mesT "I

SURRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l

Test De:cription: M/D Flux Map At Power Reference Proc No / Section:

2-NPT-RX 008.002__

Sequence Step No:

il Bank Positions (Steps)

RCS Temperature (#F): TREFi1 Power Level (% F.P.): 65 s: P s: 75 Test Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):

(Design)

CB: 229 CC: 229 CD:

Must have :t 38 thimbles" lil Bank Positions (Steps)

RCS Temperature ( F): g gg Power Level (% F.P.): 4s,52.

Test Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):

(Actual)

CB: 229 CC: 229 CD: 7.6 i g Mur5 Date/ Time Test Performed:

n (s.(97 Ih43 Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive incore

'arameter Power %DIFF Channel Factor Channel Quadrant IV (Description)

(M P)/P FAH(N)

Factor FoIZ')

Power Till Test Measured

-41% lit 3

,, o 3

,,9 3 g, I,oo9$

S A 0 p,

Results value Design Value 110% for Pt10.9 (Design 115% for Pico.9 N/A N/A s1.02 (P a assy power)

Conditions) i Reference WCAP.7905. Rev.1 None None WCAP 7905 Rev.1 1

V FSAR/COLR None FAH(N)si.56(1+0.3(1 P))

Fo(Z)s2.3UPT4Z)

None Acceptance cot.R 2.4 COLR 2.3 None Criteria Reference None 4

Design Tolerance is met

/ _ YES NO Acceptance Criteria is met :

/ YES

_NO VI

As required Comments

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

)

() M n

Prepared By:

Reviewed Gy:

7 y

s NE-1148 S2C15 Startup Physics Tests Report Page 55 of 56

6URRY POWER STATION UNIT 2 CYCLE 15 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

M/D Flux Map At Power Reference Proc No / Section:

2 NPT.RX-008.002 Sequence Step No:

ll Bank Posttions (Steps)

' RCS Temperature ("F): TREF t i Power Level (% F.P.): 95 s P s 100 Test Conditions SDA: 229 SDB: 229 CA: 229 Other (specify):

(Design)

CB:

229 CC: 229 CD:

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

RCS Teraperature ( F): 513.o *F Power Level (% F.P.): qq e,34 Test Cory:litions SDA:

3 SDB: 229 CA: 229 Other (specify):

(Actual)

CB:

's.

CC: 229 CD: 7.7.6 3g4g g Date/ Time Test Nrformed; ul./e7 i

ocs MSximum Relattve Nuclear Enthalpy TotalHeat Maximum Measured Assembly Rise Hot Flux Hot Positive incore l

, Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description)

(M P)/P FAH(N)

Factor Fo(Z)

Power Tilt Test Measured 4.t'* M U *M l'08$7 M

S M N ' S I'

b Ndig 7_

Results value Design Value 110% for Pi k0.9 (Design tis % for P c0,9 N/A N/A s 1.02 i

Conditions)

(Pi e assy power)

Reference WCAP.7905, Rav.1 None Noaa WCAP 7905, Rev.1 V

FSARICOLR None rah (w>si.ssti.e.3(1.P))

rotz)s2.32/P K(z)

None Acceptance Criteria Reference None COLR 2.4 COLR 2.3 None Design Tolerance is met

/ ES NO Acceptance Criteria is me't

M ES NO VI

' As required Comments

" Must have at least 16 tnlmbles for quartar core maps for multi-point calibrations b

m n

Prepared By: A I N o r//u e -

Reviewed kI e[ _U_

(

NE-1148 S2C15 Startup Physics Tests Report Page 56 of 56

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