Text

Rev 0 to Surry Unit 2 Cycle 12 Startup Physics Tests Rept
	ML18151A671
Person / Time
Site:	Surry
Issue date:	06/30/1993
From:	Trace D; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	93-443, NE-943, NE-943-R, NE-943-R00, NUDOCS 9307290150
	Download: ML18151A671 (62)
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REGULA~Y. I~fORMATION DISTRIBUTIO.,YSTEM (RIDS)

ACCESSION NBR:9307290150 DOC.DATE: 93/06/30 NOTARIZED: NO DOCKET#

FACIL:50-281 Surry Power Station, Unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION TRACE,D.A.

Virginia Power (Virginia Electric & Power Co.)

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

Rev Oto "Surry Unit 2 Cycle 12 Startup Physics Tests Rept."

W/930723 ltr.

DISTRIBUTION CODE: IE26D COPIES REC~IVED:LTR.1_ ENCL~

SIZE:

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TITLE: Startup Report/Refueling Report (per Tech Specs)

NOTES:lcy NMSS/SCDB/PM.

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RECIPIENT ID CODE/NAME BUCKLEY,B AEOD/DSP/TPAB NUDOCS-ABSTRACT RGN2 FILE 01 NSIC COPIES LTTR ENCL 2

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1 PLEASE HELP US TO REDUCE WASTE! CONTACT TIIE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATE YOUR NAME FROM DISTRIBUTION I.JSTS FOR DOCUMENTS YOU DON'T NEED!

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f VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 23, 1993 United States Nuclear Regulatory Commission

~ttention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 Serial No.93-443 NL&P/CGL RO Docket Nos.

50-281 License Nos.

DPR-37 UNIT 2 CYCLE 12 STARTUP PHYSICS TESTS REPORT As required by Surry Technical Specification 6.6.A.1, enclosed are five (5) copies of the Virginia Electric and Power Company Technical Report NE-943, Revision 0, entitled "Surry Unit 2, Cycle 12 Startup Physics Tests Report." This report summarizes the results of the physics testing program.performed after initial criticality of Cycle 12 on May 4, 1993. The results of the physics tests were within the applicable Technical Specification limits.

Very truly yours,

~Id~

M. L. Bowling, Manager Nuclear Licensing & Programs Enclosures - Surry Unit 2, Cycle 12 Startup Physics Tests Report (5 copies) cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 9307290150 930630

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i TECHNICAL REPORT NE-943 - Rev. 0 SURRY UNIT 2, CYCLE 12 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER JUNE 1993

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PREPARED BY :__;,~--=---v__;;_"'"'..a=a::'-':.._"'_-_._

..... ~, ;;J D. A. Trace

. Date REVIEWED BY: dJl,._..

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~~::,k, REVIEWED BY: ___ /J--..l... ~-=-..._-... _'-"-~.:~----'=- ~

D. C. Lawrence Date APPROVED BY: 2> ~<".'.'.. ~h*h3 D*. Dz.i' i:iosz Date QA Category: Nuclear Safety Related Keywords: SPS2, S2C12, Startup

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

The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability.

In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING.

OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions.. in it.

By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written* approval of the Company.

Any such written approval shall itself be deemed to incorporate the disclaimers of liability and.disclaimers of warranties provided herein.

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

of this report or the data, techniques, information, or conclusions in it.

NE-9.43 S2C12 Startup Physics. Tests Report Page 1 of 58

TABLE OF CONTENTS

PAGE 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 T~me Measurements........ ;

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

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

27 Section 5 Temperature Coefficient Measurement........

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

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

41 APPENDIX.

Startup Physics Test Results and Evaluation Sheets........................

42

\\....

NE-943 S2Cl2 Startup Physics Tests Report

Page 2 of 58

LIST OF TABLES TABLE TITLE PAGE

1. 1 Chronology of Tests......................... _........ *...

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

19 3.1 Control Rod Bank Worth Summary................... ~....

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

29 5.1 Isothermal Temperature Coefficient Summary............

32 6.1 Incore Flux Map Summary...............................

35 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specification Limits.............

36 NE-943 S2C12 Startup Physics Tests Report Page 3

of 58

LIST OF FIGURES FIGURE

. TITLE PAGE

1. 1 Core J;.oading Map....... -...................... _....... *......

12

1. 2 Beginning of Cycle Fuel Assembly Burnups.................

13

1. 3 Incore Thimble Locations.................................

14 1.4

_Burnable Poison *and Source Assembly Locations............

15

1. 5 Control Rod Locations............... *......... *............

- 16

2. 1 Typica 1 Rod Drop Trace...................................

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

21 3.1 Bank B Integral Rod Worth -. HZP..........................

25 3.2 Bank B Differential Rod Worth - HZP......................

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

30 6.1 6.2 6.3 6.4 Assemblywise Power Assemblywise Power Assemblywise Power Assemblywise.Power Distribution Distribution Distribution Distribution

- 30%

- 57%

- 90%

- 100%

NE-943 S2Cl2 Startup Physics Tests Report Power..............

Power..............

Power.............

37 38 39 40 Page 4 of 58

PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 12*core could be operated safely, and makes an initial evaluation of the performance o~

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 comparison of the test results with design predictions, and an evaluation of the results.

The Surry 2, Cycle 12%Startup Physics Test Results* and Evaluation Sheets are included as an appendix to provide additional information on the startup test results.

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

These sheets provide a compact summary of the startup* test results in a consistent format.

The design test conditions and design values at 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 calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1

During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the NE-943 S2Cl2 Startup Physics Tests Report Page 5 of 58

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

NE-943 S2C12 Startup Physics Tests Report Page 6 of 58

"'-*,.. ~..

SECTION 1 INTRODUCTION AND

SUMMARY

On March 6, 1993 Surry Unit 2 shut down for its eleventh refueling.

During this shutdown, 69 of the 157 fuel assemblies in the core were replaced with 68 fresh assemblies and one once-burned assembly. The Cycle 12 core consists of eight sub-batches of fuel: two fresh batches (batches 14A and 14B); three once-burned *batches, two from Cycle 11 (batches 13A and 13B) and one from Surry 1 Cycle 6 (batch Sl/8B); and three twice-burned batches, all from Cycles ~O

and 11 (batches 12A, 12B and 12C).

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 and secondary source locations for Cycle 12, while Figure 1.5 identifies the control rod locations.

During system pressurization prior to initial criticality, it was discovered that a pressurizer safety valve (PSV) began. simmering near normal operating pressures (2235 psig)°, causing the loop seal to not completely form, which resulted in the valve leaking., A safety analy_sis was performed which showed that operation at 2135 psig ( 100 psi below

.6 normal operating pressure) was acceptable.

The safety evaluation and applicable Technical Specification changes were verbally presented to the NRC with approval obtained *prior to the initial startup.

Written NE-943

S2C12 Startup Physics Tests Report Page 7

of 58

confirmation from the NRC was received shortly thereafter. 7 After the appropriate reactor trip setpoints were reset to compensate for the lower operating pressure, the Cycle 12 core achieved initial criticality at 2101 on May 4, 1993.

Following criticality, startup physics tests. were performed as outlined in Table 1.1.

Even though the physics tests were performed at approximately 2135

psig, the physics predictions, which were calculated assuming an operating pressure of 2235 psig, were not modified. Op~rating at 100 psi below normal operating conditions has a negligible impact on physics parameters. Therefore, changes to the design predictions were not deemed necessary.

A summary.of the physics test results follows.

1.

The measured drop time of each control rod was within the 2.4 second limit of Technical Specification j.12.c.1.

2.

The reference control rod bank was measured with the dilution method, and the result was within 2.3% of the design prediction.

Individual control rod bank worths were measured using the rod swap technique 2 a 3 and the results were within 6.9% of the design predictions.

The sum of the individual measured control rod bank worths was within 1.7% of the design prediction.

These results are within the design tolerance of +/-15% for individual bank worths

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

3.

Measured critical boron concentrations for two control bank configurations were within 51 ppm of the design predictions. The NE-943 S2C12 Startup Physics Tests Report Page 8 of 58

all-rods-out (ARO) result was not within the 50 ppm design tolerance, but met the Technical Specification 4.10.A criterion that the overall core reactivity balance shall be within +/-1%. Ak/k of the design prediction.

Further analysis was performed to confirm the boron misprediction had no adverse affect on the safety analysis 4

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

4.

The boron worth coefficient measurement was within 1.4% of the design predict.ion, which is within the design tolerance of +/-10%.

5.

The measured isothermal temperature coefficient ( ITC) for the aH-rods-out configuration was within O.41 pcm/°F of the design prediction.

This result is within the design tolerance of +/-3 pcm/°F.

The measured ITC was -0.77 pcm/°F.

When the Doppler temperature coefficient

(-1.69 pcm/°F) and a

0.5 pcm/°F uncertainty are accounted for in the +3.0 pcm/°F MTC limit of Technical Specification 3.1.E.1, the MTC requirement is satisfied as long as the ITC is less than 0.81 pcm/°F.*

6.

Measured core power distributions were within established acceptance criteria and Technical Specification limits~

Generally, the measured core power distribution was within 2.0%

of the design predictions.

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

were within the limits of Technical Specification Section 3.12.B.1.

NE-943 S2C12 Startup Physics Tests Report Page 9

of 58

In summary, all startup physics test results were acceptable.

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

NE-943 S2C12 Startup Physics Tests Report Page 10 of 58

-~.. :

Table 1.1 SURRY 2 - CYCLE 12 STARTUP PHYSICS TESTS CHRONOLOGY. OF TESTS Test Date Time Power Hot Rod Drop - Hot Full Flow 4/30/93 0340 HSD Zero Power Testing Range 5/ 4/93 2219 HZP Reactivity Computer Checkout 5/ 4/93 2311 HZP Boron Endpoint* - ARO 5/ 5/93 0315 HZP Temperature Coefficient - ARO 5/ 5/93 042.4.

HZP Bank B Worth 5/ 5/93 0620 HZP Boron Endpoint - B in 5/ 5/93 0930 HZP Bank D Worth - Rod Swap 5/ 5/93 1020 HZP Bank C Worth - Rod Swap 5/ 5/93 1118 HZP Bank A Worth - Rod Swap 5/ 5/93 1207 HZP Bank SB Worth - Rod Swap 5/ 5/93 1229 HZP Bank SA Worth - Rod Swap 5/- 5/93 1307 HZP Flux Map - 30% Power 5/ 6/93 0902 29.7%

Peaking Factor Verification

& Power Range Calibration Flux Map - 57% Power 5/ 8/93 0703 57.2%

Peaking Factor Verification

& Power Range Calibration Flux Map - 90% Power 5/ 9/93 1246 89.9%

Peaking Factor Verification

& Power Range Calibration Flux Map - 100% Power 5/29/93 0653 99.9%

Peaking Factor Verification

& Power Range Calibration NE-943 S2C12 Startup Physics Tests Report Page Reference Procedure 2-NPT-RX-007 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008.

2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-002 2-NPT-RX-005 2-NPT-RX-002 2-NPT-RX-005 2-NPT-RX-002 2-NPT-RX-005 2-NPT-RX-002 2-NPT-RX-005 11 of 58

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- Unavailable Location NE-943 S2C12 Startup Physics Tests Report Page 14 of 58

Figure 1.4 SURRY UNIT 2 - CYCLE 12 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R

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8 NE-943 S2C12 Startup Physics Tests Report Page 16 of 58 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15

SECTION 2 CONTROL ROD DROP TINE HEASUREHENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tavg of 547+/-5°F) in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the.maximum allowed by Technical Specification 3.12.C.l.

Even though this test was performed at approximately 2100 psig, which is 135 psi below normal operating pressures, the test conditions. were performed near the actual cycle operating pressure of 2135 psig.

The slightly lower testing condition RCS pressure would not impact any results presented here.

The rod drop times were measured by withdrawing a bank to its fully withdrawn position, and removing the movable and stationary gripper coil

~:

fuses for the particular rod to be...dropped.

This allowed the rod to drop into the core as it would during a plant trip.

The stationary gripper coil voltage and the Individual Rod Position Indication (!RPI) primary coil voltage signals were recorded to determine the rod drop time.

This procedure was repeated for each control rod.

As shown on the sample rod drop trace inF.i:gure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage-when the stationary gripper coil fuse is removed.

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

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

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

This voltage reaches a minimum when the rod NE-943 S2Cl2 Startup Physics Tests Report Page 17 of 58

"i._..

reaches the bottom of the dashpot.

Subsequent variations in the trace are caused by rod bouncing.

The measured drop times for each control rod are recorded on Figure

.2.2.

The slowest, fastest, and average drop times are summarized in Table 2.1.

Technical Specification 3.12. C.1 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.

satisfied this limit.

NE-943 S2Cl2 Startup Physics Tests Report The test results Page 18 of 58

Table 2.1 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST RODS AVERAGE TIME M-06 F-06 1.38 sec.

C-07 1.24 sec.

1.28 sec.

P-06 NE-943 S2Cl2 Startup Physics Tests Report Page 19 of 58

Figure 2.1 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE au rn a a....

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. ROD CROP TIME MEASUREMENT NE-943 S2C12 Startup Physics Tests Report Page 20 of 58

R Figure 2.2 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS p

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I __ I NE-943 S2C12 Startup Physics Tests Report Page 21 of 58

SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control* and shutdown banks using the rod swap technique 2 > 3

The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the ret:erence bank) into the core and measured its reactivity worth using conventional test techniques.

The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank.

Control Bank B was used as the reference bank.

For Cycle 12, 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 the 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 one of the

other control rod banks (i.e. 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 core was just critical or near the initial statepoint reactivity. This measured critical position (HCP) of the reference bank with the test bank fully inserted was used to NE-943 S2Cl2 Startup Physics Tests Report Page 22 of 58

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 HCP.

The rod swap maneuver then was repeated in reverse such that the reference bank again was fully inserted with the test bank fully withdrawn 'from the core.

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

A summary of the test results is given in Table 3*.1.

As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance (+/-10% for the reference bank, +/-15% for test banks worth greater than 600 pcm, and +/-100 pcm for test banks worth less than or equal to 600 pcm).

The sum of the individual measured rod ba:nk worths was within 1. 7% of the design prediction.

This is well within the design tolerance of +/-10% for the sum of the individual control rod bank worths.

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

The design predictions and the measured data are plotted together in order to illustrate their agreement.

In summary, the measured rod worth values were satisfactory.

NE-943 S2C12 Startup Physics Tests Report Page 23 of 58

B-Re D

C.

A SB SA Tota BANK ference 1 Worth Table J.1 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH

(%)

(PCM)

(M-P)/P X 100 Bank 1539.0 1504.0 2.3 891.3 925.5

-3.7 761.0 784.0

-2.9 317.6 341.0

-6.9*

1005.9 1012.3

-0.6 1098.5 1144.0

-4.0 5613.3 5710.8 *

-1. 7

The difference is less than 100 pcm.

\\

NE-943 S2C12 Startup Physics Tests Report Page 24 of 58

1,500 1,400 1,300 1,200 1,100 1,000

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S2C12 Startup Physics Tests Report Page 25 of 58

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NE-943 S2Cl2 Startup Physics Tests Report Page 26 of 58 L

SECTION 4 BORON ENDPOINT AND WORTH KEASUREHENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant. system (RCS) boron concentrations were measured at selected

rod bank configurations to enable a direct comparison of measured boron endpoints.

with design predictions.

For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were:made to account for off-nominal control rod position and moderator temperature, if necessary; The results of th~se 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 all-rods-out (ARO) critical boron endpoint value was not within its design tolerance (+/-50 ppm), but did meet the requirements of Technical. Specification 4.10.A regarding core rea~tivity balance.

A review of the safety analysis was performed and showed that there were no adverse consequences resulting from the design tolerance not being met'.

In summary, the boron endpoint results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated NE-943 S2C12 Startup Physics Tests Report Page 27 of 58

rod worth present in the core at the time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.

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

As indicated in this figure and iri the Appendix, the measured DBW was -7.40 pcm/ppm.

This is within 1.4% of the predicted value of -7.30 pcm/ppin and is well within the design tolerance of +/-10%.

In summary, the measured boron worth coefficient was satisfactory.

NE-943 S2C12 Startup Physics Tests Report Page 28 of 58

Table 4.1 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS BORON ENDP.OINTS SUHHARY Measured Predicted Control Rod Endpoint Endpoint Configuration (ppm)

(ppm)

ARO 1961 1910 B Bank In 1753 1755*

Difference M-P (ppm)

+51

-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 Phy~ics Test Results and Evaluation Sheet in the Appendix.

NE-943 S2C12 Startup Physics Tests Report Page 29 of 58

1,600 1,500 1,400 1.,300 1,200 1,100

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Figure 4.1 SURRY UNIT 2

CYCLE.12 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured DBW= -7.40 pcm/ppm

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NE-943 S2C12 Startup Physics Tests Report Page 30 of 58

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.

sequence includes a cooldown followed by a heatup.

This test Reactivity was measured during an RCS cooldown of approximately 5.6°F and an RCS heatup of 3.0°F.

Rea.~tivity and temperature data was taken from the reactivity computer and strip chart recorders.

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

An X-Y plotter, which 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 +/-3 pcm/°F.

Accounting for the Doppler temperature coefficient (-1.69 pcm/°F) and a 0.5 pcm/°F uricert~,inty, the moderator temperature coefficient was 1.42 pcm/°F, which meets the requirements of Technical Specification 3.1.E.1.

In summary, the measured result was satisfactory.

NE-943 S2Cl2 _Startup Physics Tests Report Page 31 of 58

BANK POSITION D/207

. -... ***~

Table 5.1 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/°F)

TEMPERATURE BORON RANGE CONCENTRATION C/D H/U AVE.

DIFFER.

(.OF)

(ppm)

MEAS. PRED.

(M-P) 542.0 to 1958

-0.36

-1.17 -o. 77

-1.18 0.41 548.0 NE-943 S2C12 Startup Physics Tests Report Page 32 of 58

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

This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles 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 PRODAC P-250 process computer.

Full *core, -

three-dimensional power distributions are d.etermined from this data using the Westinghouse computer program, INCORE 5

INCORE couples the measured voltages with predetermined analytic p~wer-to-flux ratios 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 and the measured values of the important power distribution parameters are given in Table 6.1. A comparison of these measured values with their Techn.ical Specification limits is given in Table 6.2.

Flux map 1 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 2 through 4 were taken near 57%,

90% 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 6.4.

These figures show that the measured relative assembly power values were generally within 2.0% of the predicted values.

The measured F-Q(Z) and F-DH(N) peaking factor values for all flux maps NE-943 S2C12 Startup Physics Tests Report Page 33 of 58

were within the limits of Technical Specification 3.12.B.1. AU maps were used to recalibrate the power range excore detectors.

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 Technical' Specification limits.

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

NE-943 S2C12 Startup Physics Tests Report Page 34 *of 58

TABLE 6.1 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS INCORE FLUX KAP.

SUMMARY

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CZJ IBLESI

--:--=-:-==---'-'--='--'-'--'-'-'-*-'--'-'-'--'--'--' _1_, __ 1_1 I

LOW POWER I 1 IS-6-931 11 I 301 1S2 IF 41 OOI 50 I Z.340 IF 41 001 I.S54 I 30 ll.43911.0061 MEI -3.661 44 I I P.F.V.

I Z I s-a-931 za I S71 l6!i I Olli HII 30 I Z.llS I F 41 001 1.499 I 30 ll.33311.0031 NEI -3.Sll 40 I I P.F.V.

I 3 I S* 9-931 S7 I 901 Z03 I F 41 001 26 I 1.942 I F 41 OOI 1.444 I 30 ll.ZSlll.0031 NEI +Z.371 41 I I

FULL POWER I 4 I S-29-931 646 11001 ZZ4 I Olli HII 32 I 1.890 IF 41 001 1.424 I 31 11.zze11*.0011 NEI +O.Z71 46 I I

I_I I __ I_I __ I_I_I __ I __ I_I_I __ I __ I __ I __ I_I __ I_I NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSENBLY LOCATIONS (E.G. Ha IS THE CENTER-OF-CORE ASSENBLYJ, FOLLOWED BY THE PIN LOCATION (DENOTED BY THE "Y" COORDINATE WITH THE FIFTEEN ROWS OF FUEL RODS LETTERED A THROUGH O AND THE "X" COORDINATE DESIGNATED IN A SINILAR NANNER).

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

l. F-QCZJ INCLUDES A.TOTAL UNCERTAINTY OF 1.08.

Z. POWER TILT - DEFINED AS THE AVERAGE QUADRANT POWER TILT FRON INCORE.

3. P.F.V. - PEAKING FACTOR VERIFICATION

4. EACH NAP WAS USED TO PERFORlt A POWER RANGE EXCORE DETECTOR CALIBRATION.

NE-943 S2C12 Startup Physics Tests Report Page 35 of 58

/

Table 6.2 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH.. THEIR TECHNICAL SPECIFICATION LIMITS PEAK F-Q(Z) HOT F-Q(Z) HOT F-DH(N) HOT CHANNEL FACTOR*

CHANNEL FACTOR**

. CHANNEL FACTOR

. (AT NODE OF MINIMUM MARGIN)

MAP MEAS LIMIT. NODE MEAS LIMIT

.NODE MARGIN MEAS LIMIT MARGIN NO.

1 2

3 4

(%)

2.340 4.628 30 2.340 4.628 30 49.4 1.554 1.889

17. 7 2.115 4.048 30 2.115.4.048 30 47.8 1.499 1.760 14.8 1.942 2.549 26 1.942 2.549 26 23.8 1.444 1.607 10.1 1.890 2.321 32 1.882 2.292 26 17.9 1.424 1.560 8.7

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 Spe~ification'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 m1n1mum margin.

The minimum margin values listed are the minimum percent 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.

NE-943 S2C12 Startup Physics Tests Report Page 36 of 58

R p

-~-.. -

Figure 6.1 SURRY UNIT 2 - -CYCLE 12 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 30% POWER N

L IC J

H G

F E

D PREDICTED o.za D.34 o.za.

C II IIEASURED

PCT DIFFERENCE.*

o.za

o.34

o.z8.-

1.0

0.5. 1.9

PREDICTED IIEASURED

.PCT DIFFERENCE *

o.31. o.64. 1.ca. a.al 1.08. a.64. o.31

o.33. o.63. 1.01. o.ao. 1.09. o.6(,. D.33.

6.1 ** -1.4. -0.1. -o.a. 1.4. 3.z. 5.7 *

o.38. 1.14. l.Z9. 1.za. 1.za. J.Z9. l.Z9. 1.14. o.38 *

0.40. 1.17. l.Z7. l.Z7. l.Z6. 1.30. 1.33. l.Zl

D.41.

5.3. Z.l. -1.9. -1.4. -1.4. l.Z. 3.1

5.9. 9.6 *

0.38. 0.88

1.35

1.38

l.3Z

l.Z3

l.3Z. 1.38

1.35 * *o.88

0.38.

0.40. 0.90. 1.34. 1.39. 1.35. l.Z4. 1.34. l.4Z. 1.40. 0.92. 0.39.

6.1

1.7. -0.9. 0.7. Z.3. J.O. 1.3. Z.9 *. 3.4. 3.9. Z.7 *

. 0.31. 1.14. 1.35. l.Z8. 1.24 1.18. 1.17. 1.18. l.Z4. l.Z8 1.35. 1.14 0.31 *

0.31

1.15

1.34

l.Z8

I.ZS. l.Z3

l.ZO

l.ZO

l.Z7

1.31

1.35

1.14

0.31 *

. -0.6. 0.6. -0.8. -o.o ~ 0.9. 4.Z. Z.8. 1.9. Z.5. z.z. -0.5. -a.a. -0.5 *

0.64 l.Z9. 1.38. 1.24. 0.99 1.06 1.05 1.06 0.99. 1.24 1.38 l.Z9 0.63 *

. 0.63. l.Z9. 1.37. l.ZZ. 1.00. 1.08. 1.07. 1.06. 1.01. 1.26. 1.38. l.Z6. 0.61 *

-o.6*. -o.6. -a.a. -1.s. o.9. Z.6. 1.1.

o.3. 1.z, 1.s. D.4. -2.6. -3.3

A

O.Z7

l.D7

l.Z9

l.3Z

1.18

1.05

1.01

1.10

Loz _- 1.06

1.18

l.3Z

l.Z8. 1.07

O.Z7

z 3

5 6

O.Z7. 1.os*. l.Z7

1.30. 1.16

1.05. 1.04

1.11 ; I.OZ. 1.06

l.ZO

l.Z6

l.Z3*. 1.01

O.Z6

7

. -0.7. -Z.l. -1.z. -1.a. -1.6. D.l. Z.4. 0.7. -0.8. 0.3. 1.4. -4.6. -4.3. -5.4. -4.4 *

. 0.34. o,ao

l.Z8. l.ZZ

1.16

1.05

1.09

1.14. l.lZ

1.06. 1.17. l.Z3. l.Z8

0.80. 0.34 *

. 0.32

0.78. l.Z3. l.ZO. 1.15

1.05

1.12

1.14 *. 1.11

1.06

1.17

1.17

l.Z3. 0.78

0.33

8

-4.Z. ~z.a. -3.7. -1.6. -1.0. 0.4. Z.6. 0.6. -0.4. 0.3. -o.z. -4.6. -4.Z. -3.0. -3.5.

O.Z7. 1.06 l.Z7. 1.31. 1.18. 1.05. 1.01. 1.10. I.OZ. 1.06. 1.19 1.32. J.Z9. 1.07. 0.27

. O.Z5. 1.00. l.Zl. l.Z8. 1.18. 1.06. 1.03. 1.12. 1.02. 1.05. 1.19. 1.31. l.Z6. 1.04. O.Z6.

9

. -6.4. -5.3. -5.4. -Z.3. ~-7. 0.6. Z.3. l.Z. *o.z. -1.Z. -0.l. -0.8. -Z.3. -3.l. -3.Z.

. 0.63. l.Z8. 1.37. 1.23. 0.99. 1.05. l.D5. 1.06-. 0.99. 1.24. 1.38. 1.30. 0.64 *

0.59. l.ZO. 1.34. l.Z5. 1.00. J.08. 1.07. 1.06. 0.99. J.Z4. 1.40. l.Z8. 0.61.

-6.6. -6.7. -Z.l. 1.5. 1.8. Z.Z. 1.8. 0.0. -0.9. 0.1. 1.5. -1.2. -3.9 *

o.31

1.-14

1.35. 1.z1

1.24. 1.1a. 1.16

1.18. 1.z4

1.za

1.36

1.15

o.31.

. 0.30

1.10. 1.33

1.30. 1.26. 1.20

1.19. 1.19

1.23

1.28. 1.37

1.16. 0.31 *

. -3.Z. -3.2. -1.l. 1.8. 2.0. Z.l. Z.l

D.6. -0.7. 0.3. 1.3. 0.9. -0.7 *

. 0.37. 0.88. 1.35. 1.37. 1.32. l.Z3. 1.32. 1.38. 1.35. 0.89. 0.38.

. 0.38. 0.89. 1.37. 1.40. 1.34. 1.25. 1.32. 1.36. 1.35. D.89. 0.39.

0;2. a.a. 1.1. 1.8. 1.a. 2.0. -o.3. -1.1 * -o.s. o.5. 3.7 *

0.37. 1.14. 1.29.. J.Z9. 1.28. 1.28. 1.29. 1.14. 0.38 *

. 0.38. 1.18. 1.32. 1.31

l.Z9. 1.27. l.Z7. 1.13. 0.38.

1.7. 3.2. 2.5. 1.8. 0.5. -1.5. -Z.l. -1.4. 1.6 *

0.31

0.64. 1.08. 0.81. 1.08. 0.64. 0.31 *

0.32. 0.66. 1.11. 0.81. 1.07. 0.63. 0.30.

3.2. 3.1. z.a. o.3. -1.0. -1.s. -2.3.

STANDARD DEVIATION

=l.667 0.2a o.34

e.za

0.2a. o.35. o.z1.

2.8.

l

Z *. -o. 9

AVERAGE

.PCT DIFFERENCE.

=

Z.D NAP NO:

S2~12-0l CONTROL ROD POSITIONS:

D BANK AT 152 STEPS SuttNARY DATE:

5/ 6/93 F-QCZJ

= 2.340 F-DH(NJ = 1.554 F(ZJ

= 1.439 BURNUP

=

11 tlWD/NTU NE-943 S2C12 Startup Physics Tests Report POWER:

29.77.

QPTR:

NW 1.0010 NE 1.0058 SW 0.9969 SE 0.99&3 A.O.=

-3.664%

Page 37 of*ss 10 11 12 13 14.

15

R p

Figure 6.2 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS ASSEKBLYWISE POWER DISTRIBUTION 57% POWER N

l I(

.J H

G F

E D

C B

PREDICTED

O.Z9. 0.37 0.30.

PREDICTED IEASURED

O.Z9. 0.37. 0.30.

IEASURED

PCT DIFFERENCE.

-0.6. -0.9. -0.6.

.PCT DIFFERENCE

0.3Z 0.65 1.10 0.85 1.10 0.65 0.3Z

0.34

0.64

1.09

0.84

l.09

0.66

0.35 *

6.6. -1.5 - -1.0. -1.5. -1.0. 1.4. 8.3 *

o.38 1.13. 1.z1. 1.za. 1.za 1.za. 1.z1 1.13. o.38 *

. 0.40. 1.16. l.Z5. 1.Z7. 1.Z7. 1.ZB. l.Z9. 1.19. 0.41.

5.7. Z.3. -1.a. -o.3. -1.1

o.z. 1.3. 5.5. a.z *

0.38-. 0.118.: 1.3Z 1.35. 1.30. 1.ZZ 1.30 1.35. l.3Z. o.aa. 0.38.

0.41

0.89. 1.31

1.34

1.31.. 1.Z3

1.31. 1.37

1.35

0.90

0.39 **

6.5. 1.a. ~o.9. -1.1

o.4. 1.z. o.a. 1.4. z.z. z.a. z.5.

0.3Z. 1.13. J.3Z. 1.Z6 l.Z3. 1.18 1.16 1.18. l.Z3 1.Z6 l.3Z. 1.13 0.3Z

0.32. 1.13. 1.31. ).ZS. 1.zz. 1.ZO. 1.18. 1.19. 1.2s*. 1.27. 1.31

1.13. 0.3Z.

-1.z. 0~1. -0.11. -o.3. ~a.a. i;1. 1.1. 1.4. 1.3. 1.1. -1.2. -o.3. 1.1 *

0.65. 1.Z7. 1.35 1.Z3 1.03 1.07. 1.06 1.07. 1.03. l.Z3*. 1.35. l.Z7. 0.64 *

0.6;4

1.26

1.34

1.Zl

1.03

1.10

1.09

1.08

1.04 ** 1.Z3

1.33

1.Z4

0.63 *

-1.2 ~ -1.2. ~o.a. -1.0. o.4. 2.1. 1.9. _1.3. o.9. -0.2. -1.5. -2.2. -1.9

A

o.z9. 1.09. 1.28. 1.30 1.18*

1.01. 1.03. 1,1z 1.04. 1.01. 1.1a: 1.30. 1.za. 1.09. o.Z9.

1 z

3 4*

5 6

0.28. 1,07. 1.Z6. 1.28. 1.16. 1.08. 1.07 ~ 1.14. 1.05. 1.08. 1.17. l.Z6. 1.Z3. 1.04. 0.28.

7

. -4.1 * *Z.3. -1.2. -1.Z. -1.Z. 1.8. 3.5. 2.3. 1~2. 0.7. -1.1. -3.3. -3.11. -4.5. -3.9 *

0.36

0.85 1.27 *. 1.21,. _ 1.15

L06

1.11. 1.16

1.13. 1.07. 1.16

1.22

1.211_. 0.115

0.36 *

. 0.35. 0.82. 1.26. 1.21. 1.16. 1.08. 1.15. 1.18. 1.14. 1.07. 1.15. 1.17. 1.23. O.IIZ. 0.35.

8

~4.3. -3.3. -1.2. -o.z. D.8. Z.2. 3.8. 2.1. 0.8. 0.3. -1.Z. -3.7. -3.9. -2.9. -2.6 *

, 0.28. 1.09. 1.27. l.Z9. 1.17. 1.06. 1.03. 1.12. 1.04. 1.07. 1.18. 1.30. 1.211. 1.10. 0.29.

0.27. 1.04. 1.22. 1.ZB. 1.111. 1.07. 1.03. 1.12. 1.05. 1.08. 1.18. 1.25. 1.24. 1.07. 0.28.

9

. -4.1. -4.0. *4.2. -1.2. 0.7. 0.4. -0.2. 0.6. 1.0. 0.5. 0.1. -4.1. -2.B. -Z.1 * -1.4.

0.64 1.27. 1.35. 1.ZZ 1.02. 1.06. 1.06. 1.07. 1.03. l.Z3. 1.35. 1.28. 0.65.

0.61. 1.21. 1.33. 1.Z3. 1.03. 1.06. 1.07. 1.08. 1.03. 1.23. 1.37. 1.Z6. 0.64.

. -4.2. -4.3. -1.5. 0.7. 0.4. 0.0. 0.9. 0.6. -0;1. 0.0. 0.9. -1.6. -1.5.

0.32 1.13 1.32 1.25 1.23. 1.17 1.16 1.111. 1.23 1.26. 1.33. 1.14. 0.32

0.31

1.11

1.31. 1.Z6. 1.23. 1.111. 1.17. 1.18. 1.22. 1.27. 1.36. 1.16. 0.32.

-1.9. -1.9. -0.8. 0.7. 0.3. 0.6. 1.6. 0.3. -1.1. 0.11. 2.4. 2.2. O.J.

0.38 0.117 1.3Z 1.35. 1.30 1.Zl 1.30 1.35 l.3Z 0.118. D.38 *

0.38. 0.811

1.33

1.35

1.30

1.23

1.30. 1.35

1.34

0.90

0.40

0.6. 0.6. 0.6*. 0.3. 0.2. 1.0. 0.3. -0.5. 1.0. 2.6. 4.1 *.

0.38 1.13 1.Z7 1.Z8 1.28 1.28 1.27 1.13 0.311 *

0.39

l.111

1.30

1.211

1.27

1.25. 1.25

1.16

0.39 *

2.7. 4.8. Z.4. 0.0. *1.1. -2.2. -2.Z. Z.5. 3.2.

D.3Z D.65. 1.10. 0.115. 1.10. 0.65. 0.32 *

0.33*. o.67. 1.1z. a.as. 1.01. o.63. 0.31.

4.a. 3.11. z.2. -o.a. -z.3. -2.2. -2.1.

STANDARD DEVIATION

=).5611

O.Z9 D.37 O.Z9 *

0.30. 0.37. 0.29;

2.1. 0.3. -2.4.

AVERAGE

.PCT DIFFERENCE *

= 1.8 NAP NO: *S2-12-02 CONTROL ROD POSITIONS:

D BANK AT 16S STEPS SUHNARY DATE~ S/ 8/93 F-OlZ) = 2.11S F-DH(N) = l.lt99 f(Z)

1.333 BURNUP

28 NWD/NTU NE-943 S2C12 Startup Physic~ Tests Report POWER:

S7.2Y.

OPTR:

NW 1.0010 NE 1.0026 SW 0.9972 SE 0.9991 A.O. = -3.508%

Page 38 of 58 10 11 12 13 14 15

R p

Figure 6.3 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS ASSEHBLYWISE POWER DISTRIBUTION 90% POWER N

L IC J

H C

F E

D PREDICTED 0.31 0.40 0.32 NEASURED

0.31. 0.39. 0.31.

C II

PCT DIFFERENCE.

-z.o * -z.z.* -2.0

PREDICTED IEASURED

.PCT DIFFERENCE.

0.32 0.65 l.lZ 0.91 1.12 0.65 0.3Z

- 0.34. 0.65 *.I.ID

0.90. 1.10

0.66

0.35 *

6.0. -1.Z. -1.5. -1.11. -1.5. l.O. 11.4 *

0.38. 1.11. l.Z4. l.Z7. l.ZII. l.Z7. l.Z4. 1.11. 0.38 *

0.40

1.13

l.Z3 * *l.Z7

l.Z7

l.Z7

l.Z6

1.17

0.41.

5.Z. Z.4. -1.Z. 1.1. -0.7. 0.3. 1.0. 5.5. 11.4 *

. 0.38. 0.86. l.Z8 l.3Z. l.ZII. l.Zl l.Z8 1.32 1.28 0.86 0.38

o.41. 0.118

1*.28

1.31. 1.29. 1.22. 1.29. 1.33

1.31. 0.119

ci.39

5.9. 1.8. -0.4. -0.7. 0.7. 1.5. 0.8. 1.0. 2.1. 3.2. 2.7 *

~.................................................................................... -....

0.32. 1.11. 1.28. l.Z4 1.22 1.111 1.16 1.18 1.22 l.Z4 1.28 1.11. 0.32.

. 0.32. 1.11

1.28. 1.24. 1.22. 1.20. 1.17. 1.19. 1.24. 1.25. 1.28. 1.11. 0.33 *

-1.5. -0.0. -0.5. -0.2. -0.4. 1.5. 1.5. 1.4. 1.1

0.9. -0.4. -0.l. 0.3.

o.65 1.24. 1.32. 1.22 1.08 1.09. 1:011 1.09 1.09 1.22 1.32 1.24 o.65

o.64.* 1.z3

1.31

1.22

1.09

1.11.* 1.09

1.10

1.10

1.22 *. 1.31

1.22

o.64 **

-1.5. *1.5. -0.6. -0.4. 0.7. Z.l. 1.3. 1.1. 1.3. 0.1. *l.O. -1.11. 01.9

A

0.31. 1.12

1.27

1.211. 1.111

1.09

1.06

1.14

J°.07

1.09

1.18

1.28. 1.27

1.11

0.31

l z

3 4

5 6

0.29. 1.09

1.25. 1.26

1.17. 1.11

1.09

1.16 ** 1.08

1.10. 1.17

1.24

1.23

1.07

0.30

7

-4.3. -2.6_.. -1.5. -1.l * -0.4. 1.8. 3.1. 1.8, 0.9. 0.11. -0.8. -Z.9. -3.3. -3.11. *3.2.

0.39

0.91

1.27

1.20

1.15. 1.011

1.13. 1.18. 1.-15. 1.08

1.16

1.21

1.211

0.91

0.40 *

0.38 * -0.117. 1.25

1.20

1.16

1.10

1.16. 1.20. 1.16

1.09

1.14

1.17

1.23

0.811

0.38 *

8

-4.5. ~3.4. -1.5. -0.4.

0.11. z.o. 3.3. 1.6. *o.5. 0.2. -1.l. *3.4. -3.6. *2.7. -2.7.

0.30 1.11 1.26. 1.27. 1.17. 1;09. 1.05. 1.14. 1.06. 1.09. 1.18. 1.28. l.Z7. 1.12. 0.31 *

0.29. 1.07. 1.22. 1.26: 1.111. 1.09. 1.06. 1.14. 1.07. 1.10. 1.18. 1.23. 1.24. 1.09. 0.30.

9

-4.3. *3.9. -3.6. -0.9. 0.8. 0.5. 0.1. 0.4. 0.4. 0.2. o.o. -4.0. -2.11. -Z.4. -2.3.

o.65 1.24 1.32

1.22

1.011. 1.09

1.08

1.09. 1.09

1*.22

1.32

1.24

o.65

. 0.63. 1.19. 1.30. 1.22. 1.08. l.D9. 1.09. 1.10. 1.09. 1.23. 1.34. 1.22.*0.64.

-3.6. -3.6. -1.2*. 0.6. 0.4. 0.4. 1.1. 0.8. 0.2. 0.5. 1.1 * -1.11. *l.9 *

0.32. 1.10. 1.28. l.Z4. 1.22. 1.111. 1.15. 1.18. 1.22. 1.24. 1.211. 1.11

0.32.

0.3Z. 1.08. 1.27. 1.24.* 1.22. 1.19. 1.18. 1.19. 1.22

1.25. 1.31. 1.12

0.3Z *

. -1.9. -1.9. -0.9. 0.4. 0.3. 0.9. 2.0. 1.0. -0.2. 1.0. 2.0. 1.5. 0.2.

0.38 0.86 1.28 1.32 l.ZII 1.20 l.ZII 1.32 1.28 0.117. 0.38

o.38. o.86. 1.29. 1.32. l.Z8. 1.22. 1.21. 1.31. 1.z9

0.1111 _. o.4o *

. -0.I.

O.l.

0.4. 0.3. 0.5. 1.3. -0.1. -o:8. 0.4. Z.l

3.1.

0.38 1.10 l.Z4 l.Z7 l.Z8 l.Z7 1.24 1.11 0.38

0.39. 1.1'4

l.Z6. 1.27

l.Z7. l.Z4

I.Zl

1.10

0.39 *

. 1.5. 3.0. 1.7. 0.3. -0.7. -2.0 *. -Z.3. -0.7. 2.5.

STANDARD DEVIATION

=l.4111 NAP NO:

S2-12-03 CONTROL ROD POSITIONS:

D BANK AT 203 STEPS 0.3Z 0.65 l.lZ 0.91'. l.lZ 0.65 0.3Z

0.33. 0.67. 1.13. 0.91

1.10. 0.64. 0.32.

3.0. z.z. *o~7. -0.9. -1.7. -2.0. -Z.4.

0.31 0.40 0.31

0.32. 0.40. 0.31.

0.6. -0.3. -1.7.

POWER:

89.97.

QPTR:

AVERAGE

PCT DIFFERENCE

z*. 1.7 SutlttARV DATE:. 5/ 9/93 F-Q(ZJ

= 1.942 F-DH(N) = 1.444 NW 1.0016 NE 1.0031 F(ZJ

= 1.251 SW 0.9973 SE 0.9979 BURNUP

=

57 NWD/NTU A.O.= +2.3737.

NE-943 S2C12 *startup Physics Tests Report Page

. 39 of 58 10 11 IZ 13 14 15

R p

Figure 6.4 SURRY UNIT 2 - CYCLE 12 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER N

N l

IC J

.H G.

F ****

E D

PREDICTED

0.3Z. D.40 0.3Z.

C B

NEASURED

0.31. 1.40. 0.3Z.

-. ~1.z. -i.z. o.4.

PREDICTED IEASURED

.PCT DIFFERENCE *

PCT DIFFERENCE.

0.3Z 0.65 1.11. 0.9Z 1.11 D.65. 0.3Z

0.34. 0.64. 1.09. 1.90. 1.11. D.67. 0.34.

6.6. ~l.5. -1.4. -1.4. 0.4. Z.7. 5.5 *

0.38. 1.09. l.Z4. l.Z5. 1.za. I.ZS. l.Z3.*1.09. 0.38 *

0.40. 1.lZ. 1.21. l.ZS. 1.26. 1.26. 1.26. 1.15. 0.4Z.

s.1. 2.z. -2.1. -o.4. -1.1. o.6. 1.9. s.4. 9.9.

..... ~........................................................................

o.38. o.86. 1.28. 1.31

1.za. 1.20 1.z8. 1.31. 1.za o.86. o.38 *

0.41

0.87

1.26.

1.30

l.Z9

l.Zl. 1.28

l.3Z

1.31

0.89. 0.40.

. 6.6. 1.1. -1.1 * -o.s. o.a. 1.0. o.s. 1.0. 2.4. 3.7. 4.o *

0.3Z. 1.09. 1.28. 1.23. l.Z4. 1.18 1.17 1.18. 1.24 1.23 l.Z8. 1.09 0.3Z

0.3Z

1.09

1.26

l.Z3 ** l.Z3

1.20

1.18

1.zo

1.25

l.Z5

1.Z7

1.10

0.33.*

~z.z. -0.1: -1.0 ** -o.5. -o.z. 1.6. 1.4. *1.4. 1.4. 1.0. -o.6. 1.0. z.9 *

~..............................................................................

. 0.65. 1.24. 1.31. 1.23. 1.11. 1.11

1.09 I.II. 1.11. 1.23. 1.31. 1.23. 0.65.

0.63. l.Zl. 1.29. 1.z2. l.lZ. 1.14. 1.11. 1.13. 1.13. l.Z4. 1.30. l.ZZ. 0.64.

-z.z. -2.Z. -1.3. -1.3. 0.7. 2.Z. 1.3. 1.5. 1.9. 0.4. -0.9. -1.l. -0.6

A

~.........................................

0.31

1.10. 1.25

1.28

1.18

1.11

1.07. 1.-15

l.08

1.12

1.18. 1.28

1.25

1.10. 0.31

l z

3 5

6

o.3o. 1.oa. 1.23

1.25

L16

1.1z

1.11.: 1.1a. 1.09

1.u

1.18

1.z4

1.21

1.06

0.30

1

-2.5. -2.3. -2.2. -1.a*. -1.s. o.a. 3.s. 2.1. 1.4. 1.3. -o.3. -2.s. -3.o. -3.7. -z.a *

0.40. 0.91

1.27. 1.20. 1.16. 1.09. 1,14. 1.19. 1.17. 1.09. 1.17. 1.20. 1.27 *. 0.91. 0.40.

o.39. o.a9. 1.24. 1.18. 1.15. 1.09. 1.19. 1.21. 1.11. 1.10. 1.16. 1.16. 1.23. o.9o. o.39.

a

. -:2.5 * -2.4 * -2.z * -1.2 * *l.3

o.4

3.* 7

2.1

o.6

o.3 * -o.9 * -3.2. -3.4 * -1.6. -1.6.

0.30 1.10 1.25 1.27. 1.18 1.11

1.07. 1.15 1.08. 1.12. 1.18 1.28. 1.26. 1.10 0.31 *

0.30. l.D6. 1.19

1.25

1.18

1.10

1.07

1.16 ; 1.09

1.11

1.18

1.26. J.Z4

1.09.. 0.31

9

. -2.5. -3.5. --4.5. -1.6. -0.1. -o.3. 0.1. 0.1. 0.1. -o.8. -o.4. -1.3. -1.4. -1.z. -o.a *

0.64. l.Z3. 1.30. 1.23. 1.11

1.11. 1.09. 1.11. 1.11. l.Z3. 1.31

l.Z4. 0.65.

. 0.61. 1.18. l.Z8. l.Z3. 1.11

1.11. 1.10. l.lZ. 1.11. 1.24. l.3Z. l.Z4. 0.65.

~ *4.5. -4.5. -1.a,. o.z. 0.1

o.z. o.a. 0.1. -o.3. 0.1. o.s. 0.1. -0.1.

0.3Z 1.09 1.27 l.Z3 l.Z3 1.18 1.17 1.18. 1.24. 1.23 1.28. 1.09. 0.3Z.

0.3Z. 1.07. 1.Z6. l.Z3. l;Z3. 1.18. 1.18. 1.18. 1.23. 1.25. 1.31

l.lZ. 0.33.

*1.7. *l.7. *0.9. o.z. -o.z; O.l

1.0. 0.0. -a.a. l.Z. z.z. Z.5. z.z.

0.38 0.86 l.Z8 1.31. l.Z8 1.20 1.28

1.31

1.28 0.86

0.38.

0.39 ** 0.86. l.Z8

1.30

l.Z7

1.20

1.27. 1.30

1.29

0.89. 0.40.

1.0. 0.1. 0.2. -o.6. -o.a. 0.1. -0.1. -o.9. o.6. 3.o. 5.1 *

0.38. 1.09. 1.23. l.Z6. 1.28. 1.25. 1.23. 1.09. 0.38.

0.39. 1.14. 1.26. 1.24. 1.25. 1.22. 1.21. 1.09. 0.40.

z.9. 4.7. 1.a. -1.1. -1.a. -z.3. -2.z. -o.3. 3.a.

0.32 0.65. 1.11 0.92 1.11. 0.65. 0.32

o.34. 0:61. 1.1z. 1.91. 1.oa. o.63. o.3Z.

4.7 *. 3.5. 1.6. -0.9. -z.s. -2.3. *2.1

STANDARD DEVIATION

=l.529 0.32 D.40 D.3Z.

0.3Z. 0.40. 0.31.

1.6. *D.D. *2.5.

AVERAGE

.PCT DIFFERENCE *

= 1.7 "AP NO:

S2-12-04 CONTROL ROD POSITIONS:

D BANK AT 224 STEPS SUNNARY*

DATE:

..5/29/93 F-Q(ZJ

= 1.890 F-DH(NJ = 1.424 F<ZJ

= 1.228 BURNUP

=

646 "WD/NTU NE-94~ S2Cl2 Startup Physics Tests Report POWER:

99.97.

QPTR:

NW 0.9989 SW 0.9947 NE 1.0069 SE 0.9994 A.O. = +0.2717.

Page 40 of 58 10 11 lZ 13 14 15

SECTION 7 REFERENCES

1. D. A. Trace, "Surry Unit 2, Cycle 12 Design Report",

Technical Report NE-932, Revision 0, Virginia Power, April, 1993.

2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," 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.Ann~ 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. "Evaluation of Measured S2C12 HZP ARO Critical Boron Concentration",

memorandum from C.B. LaRoe and R.T. Robins to J.W. Henderson,

.dated May*5, 1993.

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

6. "Safety Evaluation Supporting Operation of Surry 2 Cycle 12 with 100 P&I RCS Pressure Reduction Surry Power Station Unit 2'",

memorandum from K.L. Basehore to J.A. Price, dated May 3, 1993.

1. "Surry Unit 2 - Issuance of'.. A.*ndment Re:

Operating at Reduced Reactor Coolant System Nominal Operating Pressure (TAC No. M86358)",

letter from G.C. Lainas (NRC) to W.L. Stewart (VP), dated May *14, 1993.

8. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1,.

3.12.B.1, 3.12.C.1, and 4.10.A.

NE-943 S2C12 Startup Physics Tests Report Page 41 of 58

APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-94*3 S2C12 Startup Physics Tests Report Page 42 of 58

I

-Reference II Test Conditions (Design)

... **~

SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Zero Power Testing Range Determination Proc No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (OF): 547 Power Level (1 F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):

CB: 225 CC:

CD:

Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature ( °F): S"""°.o Test Power Level (1 F.P.): 0 Conditions SDA: 225 SDB: 225 *cA: 225 Other (Specify) : 'P"'~!:> s~< : '2.1 (Actual)

CB: 225 CC: ;z.~I CD: qg Below Nuclear Heating Date/Time Test Performed:

'5/'+-/q"3 22\\°I Reactivity Computer IV Initial Flux Background Reading 5'.'5 ~ 10 amps

_ Flux Reading At

.... "'~..:.pt~f-Nuclear

~.S",r.. 10-'7 Heating amps Test Results Zero Power

-i Testing Range l.O

><: 10 to ID x.. ID amps Reference Not Appli'.cable V

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

~YES _NO VI Acceptance Criteria is met**

iYES,_' _NO Comments

At The Just Critical Position

- Design Tolerance and Acceptance Criteria are met if ZPTR is below Point of Nuclear Heating and above background.

Prepared By:~~~~

Reviewed By: t>.vl. l~

NE-943 S2C12 Startup Physics Tests Report Page 43 _ of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Reactivity Computer Checkout Proc No /Section: 2-NPT-RX-008 Sequence Step

. Bank Positions (Steps)

- RCS Temperature (°F):

Power Level (% F.P.):

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

CB: 225 CC:

CD:

Below Nuclear Heating No:

547 0

Bank Positions (~fteps)

RCS Temperature ( °F): <;; 4 7 Power Level (l F.P.): 0 SDA: 225 SOB: 225 CA: 225 Other (Specify):

prf'~S "'.-~

CB: 225 CC: 2. 'l. '2. CD : q "-l Below Nuclear Heating Date/Time Test Performed:

5/1-+/q'";

2 ~ t \\

Measured Parameter Pc = Heas. Reactivity using p-compute (Description)

Pt = Predicted Reactivity Pc =

5 '3. O

- 5 i w.,_

r Measured Value Pt =

5 3. '<SC,

- S" 2. :~5( 1,;' /6f IL

/qJ M,t- _- __.....

a --

-ID=

- I. Co5

- 3.**n*

Design Value ID= {(pc-Pt)/pt} x 100:. :S *4.0:

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

~YES -

NO Acceptance Criteria is aet

.,L.YES _NO

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

Allowable Range=

+ so Prepared By: l). f. /4iJ.&cw

,,~~~

Reviewed By:'1-"~..v.,,!'

J NE-943 S2C12 Startup Physics Tests Report Page 44 of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance

.Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Critical Boron Concentration - ARO Pree No /Section: 2-NPT-RX-008 Seq1,1ence Step Bank Positions (Steps)

RCS Temperature (OF):

Power Level (1 F.P.):

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

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

RCS Temperature (OF):

Power Level (% F.P.):

No:

547 0

5'17, '-I 0

SDA: 225 SDB: 225 CA: 225 Other (Specify) : _P R~SS/4 R.<: ZI!

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

. 5/5'/'f3

.3:ts Heas Parameter H

(Description)

_(CB)

.. _Critical Boron Cone - ARO ARO*

Measured Value M

(Design Cond).

(CB) ARO = I 9 t. I ff"'

M'e:lg;-*;:*lue

- -'P (Design Cond)

CB= 1910 +/- 50 ppm Reference Technie;al Report NE-932, Rev. 0 D

FSAR/Tech Spec aCB x CB :s; 1000 pcm Reference Technical Specification 4.10.A Design Tolerance is met

_YES YNO Acceptance Criteria is met V'fES _NO aCB = -7.23 pcm/ppm D

H CB= I (CB) ARO - CB I ; CB is design value.

S"' PS I Er Prepared By:

Reviewed By: ~

~t..._

NE-943 S2Cl2 Startup Physics Tests Report Page 45 of 58

I Reference II Test Conditions (Design)

- III' Test Conditions (Ac"tual)

IV Test Results V

Accep"tance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Isothermal Temperature Coefficient Pree No /Section: 2-NPT-RX-008 Sequence Step Bank Posit ions (Steps)

RCS Temperature (°F):

Power* Level (% F.P.):

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

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

- ARO No:

547 0

Bank Positions (Steps)

RCS Temperature (°F): SYr."'

Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (Specify):.ll 3S P':,I ~

CB: 225 CC: 225 CD: "°'

Below Nuclear Heating Da-ce/Time Tes"t Performed:

5/5 {"1'5 O'i ~ 'l '-t

-Meas Parameter

ISO (Description)

(a T )ARO Isothermal Temp Coeff - ARO ISO pcm/°F (CB =i9S~ppm)

Measured Value (a T )ARO = "."'0.,-,

Design Value ISO

t~.o

~~ual~ond)

(a T *)ARO = -1. l~,. pcm/°F (CB = ICf~ppm)

ISO Design Value (a T )ARO = -1. 63 +/- 3. 0 pcm/°F (Design Cond)

(CB = 1910 ppm)

Reference Technical Report NE-932, Rev. 0 ISO Dop FSAR/Tech Spec a T

~ 0.81*pcm/°F a T = -1. 69 pcm/°F Reference TS 3.1.E, Technical Report NE-932, Rev. 0 Design Tolerance is 111et

J YES NO Acceptance Criteria is met JYES =NO

Uncertainty on aTHOD = 0.5*pcm/°F (

Reference:

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

Prepared By:L~~

Reviewed By:

NE-943 S2C12 Startup Physics Tests Report Page 46 of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments

-* ~--~...

SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Cntl Bank B Worth Meas.,Rod Swap Ref. Bank Proc No /Section: 2-NPT-RX-008 Seq_uence Step No:

Bank Positions (Steps)

RCS Temperature (°F): 547 Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):

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

RCS Temperature (°F):

Power Level (%. F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (Specify):

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

~ /5' /'13 J2 ~ Jrnt,.zo *lo REF Measured Parameter I B ; Integral Worth of Cntl Bank B, (Description)

All Other Rods Out REF I ~'3°!

Measured Value I B =

f....-- -

Design Value REF (Design Conditions)

I B = 1504 +/- 150 pcm Reference Technical Report NE-932, Rev. 0 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result FSAR/Tech Spec on safety analysis. SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A Design Tolerance is met

9Es NO Acceptance Criteria is met

_YES _,' _NO

/

/"'I.11 Prepared By: V1/dld/

Reviewed By:7~./. tiA<.. e~

f,/,. ~

.ifo/1"s NE-943 S2C12 Startup Physics Tests Report Page 47 of 58

I

Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments

'\\,,...

SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Critical Boron Concentration.. - B Bank In Pree No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (°F): 547 Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):

CB:

0 CC:. 225 CD: 225 Below Nuclear Heating Bank Posit.ions (Steps)

RCS Temperature (°F):

Power Level (% F.P.): 0 SDA:* 225 SDB: 225 CA: 225 Other (Specify):

CB:

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

.'56-1'13 l'>~~D Meas Parameter H

(Description)

(CB)B; Critical Boron Cone - B Bank.;In H

/7,3 Measured Value (CB)B =

(Design Cond)

~-.* __......

Prev Design Value CB = 1704 + ACB

+/- (10 + 150.4/laCBl)ppm (Design Cond)

CB = /7,, ppm ;! 30.~

Reference Techni,:al Report NE-932, Rev. 0 FSAR/Tech Spec Not Applicable Reference Not Applicable -

/

Design Tolerance is met

~~

_NO Acceptance Criteria is met* :

._NO aCB = -7.30 pcm/ppm Prev H

- let~/ - 1'110,i:; ?/

ACB

= (CB)ARO - 1910 -

.II

__ /]

'//dll /[~V Reviewed By:/~/.

Prepared By:

I I

NE-943 S2C12 Startup Physics Tests Report Page 48 of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results.,._

V Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AMO EVALUATION SHEET Test

Description:

HZP Boron Worth Coefficent Measurement Proc No /Section:

2-NPT-RX-008 Sequ~nce Step No:

Bank Positions (Steps)

RCS Temperature (°F): 547 Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):

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

RCS Temperature (°F):

Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (Specify):

CB:Hoving CC: 225.

CD: 225 Below Nuclear Heating Date/Time Test Performed:

5"/:;-/f'~

I f)lf Measured Parameter (Description) aCB, :Boron Worth Coefficient Measured Value aCB = -7."IO

~

Design Value (Design Conditions) aC8 = -7.30 +/- 0.73 pcm/ppm Reference Technical Report NE-932, Rev. 0 FSAR/Tech Spec Not Applicable Reference Not Applicable Design Tolerance is met.

/vEs _NO Acceptance Criteria is met DES ~NO Prepared By: 111(/Uf Reviewed By: ~J. ~.e, NE-943 S2Cl2 Startup Physics Tests Report Page 49 of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV

Test Results V

Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Cntl Bank D Worth Measurement-Rod Swap Proc No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (OF): 547 Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):

CB:Hoving CC: 225 CD:Moving Below Nuclear Heating Bank Positions (Steps)

RCS Temperature (°F):

Power Level (% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (Specify):

CB:Hoving CC: 225 CD:Moving Below Nuclear Heating Date/T_ime Test Performed:

t.

/J ~ ;*

Meas Parameter RS (Description)

Io ;* ~tit Worth of Cntl Bank D-Rod Swap (Adj. Meas. Crit. Ref Bank RS Measured Value In = 'i3'1 I.'>

Position = JI)&/ steps)

_Design Value RS (Adj. Meas. Crit. Ref Bank r#.!f11~ ~'d)

Io = /125.5J /jgPosition = //)'f _steps)

RS Design Value Io= 923 +/- 138 pcm (Critical Ref Bank (Design Cond)

Position= 119 steps)

Reference Technical Report NE-932, Rev. 0, VEP-FRD-36 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on FSAR/Tech Spec safety analysis. SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A

/

Design Tolerance is met

~ES NO Acceptance Criteria is 11et ES _NO*

A J/1' Prepared By:

1/11.,,.., *--**

Reviewed NE-943 S2Cl2 Startup Physics Tests Report Page 50 of 58 A

I Reference II Test Conditions (Design)

III Test.

Conditions (Actual)

IV Test*

Results SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Cntl Bank C Worth Measurement-Rod Swap Pree No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (OF): 547.

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

CB:Moving CC:MovingCD: 225 Below Nuclear Heating Bank Positions (Steps)

RCS Temperature (OF):

Power Level (% F.P.): 0 SDA: 225 SOB: 225 CA: 225 Other (Specify):

CB:Moving CC:MovingCD: 225 Below Nuclear Heating Date/Time Test Performed:

~1~/~1

-** I //{j.

Meas Parameter RS (Description)

Ic ; Int.-Worth of Cntl Bank C-Rod Swap RS

~{p/ (Adj. Meas. Crit. Ref Bank Measured Value Ic = ":J.=18 !iJi,~osit~on =.,G, steps)

Design v*alue 7S~~ 11~(Ad

M C.

R f B k RS

/.(, I J

eas.

ri t.

e an

~~l..CO.d) le =*:;;;.;!Jf't Position = t:I{, steps)

'RS Design Value Ic = 779 +/- 117 pcm (Critical Ref Bank (Design Cond)

Position= 102 seeps)

~

Reference Technical Report NE-932, Rev. o, VEP-FRD-36 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V

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

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

/_:YES ~NO VI Acceptance Criteria is met

_LYES _NO Comments

/

Prepared By:

Reviewed NE-943 S2Cl2 Startup Physics Tests Report Page 51 of 58 A

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results V

Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS rEsT RESULTS AND EVALUATION SHEET Test

Description:

Cntl Bank A Worth Measurement-Rod Swap Pree No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (OF).: 547 Power Level (I F.P.): 0 SDA: 225 SDB: 225 CA:Moving Other (specify):

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

RCS Temperature (OF):

Power Level (%. F.P.): 0 SDA: 225 SDB: 225 CA:Hoving Other (Specify):

CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date/1'.ime Test Performed:

!2C'7 Meas Parameter RS.

(Description)

I

.. lnt Worth of Cntl Bank A-Rod Swap A,

Measured Value RS 317

~Adj. Meas. Crit. Ref Bank IA

=

Position = ti, l steps)

Design Value RS (Adj. Meas. Crit. Ref Bank

,* * -~* a1:...ceind)

IA

=-_-~Hf :! /OD Position = GI steps) i RS Design Value IA= 338 +/- 100 pcm (Critical Ref Bank (Design Cond)

Position= 64 steps)

Reference Technical Report NE-932, Rev. 0, VEP-FRD-36 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on FSAR/Tech Spec safety analysis. SNSOC may specify that additional testing be performed.

Reference

.VEP-FRD-36A Design Tolerance is met

~Y~S _NO Acceptance Criteria is met

. _YES _NO

~

Prepared By:

Reviewed NE-943 S2Cl2 Startup Physics Tests Report Page 52 of 58 A

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV.

Test Results V

Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Shutdown Bank B Worth Meas. - Rod Swap Proc No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (°F): 547.

Power Level (% F.P.): 0 SDA: 225 SDB:HovingCA: 225 Other (specify) :

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

RCS Temperature (°F):

Power Level (% F.P.): 0 SDA: 225 SDB:HovingCA: 225 Other (Specify) :

CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date;imr-Test Performed:

s- ', I '?3 112'1 Meas Parameter RS (Description)

I5B; Int:* Worth of Shutdown Bank B-Rod Swap RS I lJ05", CJ (Adj. Meas. Crit. Ref Bank Measured Value IsB =

Position = 12.2.steps)

Design Value RS

[0/'2) (Adj. Heas. Crit. Ref Bank

,*. - --* a-l--CMl'd)

IsB

=_-

~

+/-1~2 Position = IZ'Z. steps)

~

RS Design Value IsB = 1011 +/- 152 pcm (Critical Ref Bank (Design Cond)

Position= 131 step

~

Reference Technical Report NE-932, Rev. 0, VEP-FRD-36 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on FSAR/Tech Spec safety analysis. SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A

/

Design Tolerance is met

~S. NO Acceptance Criteria is met ES =NO

.ti I'

Prepared By: 1{/,11,. U;L.

Reviewed By:~ t?

I'. I f ~11~

I 5/ cs; 7 NE-943 S2Cl2 Startup Physics Tests Report Page 53 of 58 s)

A

SURRY POWER STATION UNIT 2 CYCLE 12.

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Shutdown Bank A Worth Meas. - Rod Swap Reference Proc No /Section: 2-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level (% F.P.): 0 Conditions SDA:HovingSDB: 225 CA: 225 Other (specify):

(Design)

CB:Hoving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (°F):

Test.

Power Level (% F.P.): 0 Conditions SDA:MovingSDB: 225 CA: 225 Other (Specify):

(Actual)

CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date Tzme Test Performed:

~ ~, q3 13,0-,

I Meas Parameter RS.

(Description).

IsA; Int Worth of Shutdown Bank A-Rod Swap IV RS J{)'/~

(Adj. Meas. Crit. Ref Bank_

Test Measured Value 1sA =

~

Position = l"3"fsteps)

Results Design Value RS J

(Adj. Meas. Crit. Ref Bank

.... ~11.~-l -Coild) 1sA

=-_- f 'iL/.v: Iii.Position = 11'1 steps)

- RS Design Value 1sA = 1140 +/- 171 pcm (Critical Ref Bank (Design Cond)

Position = 151 step s)

Reference Technical Report NE-932, Rev. 0' VEP-FRD-36 A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V

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

Criteria Reference VEP-FRD-36A

/

Design Tolerance is met

~S NO VI Acceptance Criteria is met

_YES _NO Comments t/f.

Prepared By:

. y,1.;..e -*.. ~

I l

I Reviewed By: 7~

,,,I. $d2-o/ ~/ 1° 3

~.,,111 NE-943 S2Cl2 Star~up Physics Tests Report Page 54 of 58

k-.

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test Results -

V Acceptance Criteria VI Comments

-... ~...

SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Total Rod Worth - Rod Swap Proc No /Section: 2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

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

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

RCS Temperature (OF):

Power Level (1 F.P.): 0 SDA:H9ving SDB:Hoving CA:Hoving Other (Specify):

CB:Hoving CC:Hoving CD:Moving Below Nuclear Heating Oat /T'me Test Perfo_91ed:

~ ~'13 0.31.?

Meas Paralieter (Description) 1Total; Int Worth of All Banks - Rod Swap Measured Value 1Total =,.-~ l" 'I

?

.,..)

_Design Value 5710.4 i f7/

'J,.

,:a-1-Gcm'd) 1Totar---=:

_._.~

Des.ign Value ITotal = 5695 +/- 570 pcm (Design Cond)

Reference Techni;:al Report NE-932, Rev. 0, VEP-FRD-36 If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on FSAR/Tech Spec safety analysis. Additional testing must be performed.

Reference VEP-FRD-36A Design Tolerance is met

~YES --NO Acceptance Criteria is met

~YES ~NO 1

I/)

,A A

Prepared By:

f Li,,

Reviewed By:~.)-~

.'S"/s-/tff3

,;/~ ~...,

NE-943 S2Cl2 Startup Physics Tests Report Page 55 of 58

- ... '7 SURRY POWER STATION UNIT 2 CYCLE 12

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

H/DFlux Hap-At Power Reference Proc No/ Section: 2-NPT-RX-008,002 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): ~30 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify) :

(Design)

CB : 225 cc:

CD:

Hust h~ve ~ 38 thimbles**

III Bank Positions (Steps)*

RCS Temperature( °F) : ~

5 Test Power Level(% F.P.): 24.1fc Conditions SDA: 225 SOB: 225 CA: 225 Other (Spe~

(Actual)

CB : 225 CC : '1'2 CS-CD: '~°'

l\\4 Dat~/Time Test Performed:

6/tnlC,'?

h<3 MAX *. REL I

NUC ENTHAL TOTAL HEAT,HAXIHUH POS IV Heas Parameter ASSY PWR RISE HOT FLUX HOT INCORE I

(Description)

% DIFF CHAN FACT CHAN FACT !QUADRANT (K-P)/P F-dH(N)

F-Q(T)

POWER TILT

-(..7 i. P<>,o'l

z.3--iO i.a: >.5"~

-Measured. Value L...;-s'"i G,S'"E> 5c, Test -_, __. --*-*

1.1.r'L r5a.4 Results Design Value t Ill fs: Pl a l.t I s: 1.0211 (Design Conds) t In fer Pl C l.t NA NA

<*i*---->

WCAP-79a5 I

jWCAP-7905 Reference REV.l NONE NONE I REV. l I

FSAR/Tech Specl i

V NONE 1'1.i.MC 1+.J( I.Pl I r~1z1 s....

1111 I NONE Acceptance Criteria Reference NONE TS 3.12.B TS 3.12.B NONE Design Tolerance is met

LYES _NO Acceptance Criteria is aet

4YES ~NO VI Comments

As Required

- Hust have at least 16 thimbles for quarter core maps for mu1.w-point calibration.s.

I\\

Prepared By:,y_ r;~

Reviewed B.

lll1 ~b -~ -

NE-943 S2Cl2 Startup Physics Tests Report Page 56 of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test... _';

Results V

Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

H/D Flux Hap-At Power Proc No/ Section: 2-NPT-RX-008,002 Sequence Step No:

Bank Positions (Steps)

RCS Temperature (°F):TREF +/-1 Power Level(% F.P.): 50%$1'~ 75%

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

CB: 225 cc: 225 CD:

Kust have~ 38 thimbles**

Bank Positions (Steps)

RCS Teaperature(°F): s-, :3*

Power Level (% F.P.): S'1, \\

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

,CB : 225 cc: 225 CD:\\C.~

qo ~\\fft~\\ c.S ~

Date/Time Test Performed:

~ /.4:f*/q~

(") G1~t>

KAX. REL NUC ENT8AL TOTAL HEAT,HAXIHUM POS Keas Parameter ASSY PWR RISE HOT FLUX HOT INCORE (Description)

% DIFF CHAN FACT CHAN FACT !QUADRANT (H-P)/P F-dH(N)

F-Q(T)

!POWER TILT Measured Value S.6' fi ~6.~

L-00 '\\l\\

~- - __.....

'S,l t. ~., 1.4 a,o.o

l* n cs-Q,44 5.

Design Value a llll 1v**1 a **,

I.

(Design Conds) a UI -

1 c **,

NA NA

<*1 *....,. llw,)

I ~ 1.0212 WCAP-7905 I

iWCAP-7905 Reference REV.l NONE NONE REV. l FSAR/Tech Spec NONE r'aai.JW... JCl*P)I r~r:nsz.D/P

1c1, !

NONE I

Reference NONE TS 3.12.B TS 3.12.BI NONE Design Tolerance is met

~s _NO Acceptance Criteria is met YES _NO l

As Required

- Hust have at least 16 thimbles for quarter core maps for multi-point calibrations.

Prepared BC ~ ~ u ~ ~ d\\ ~

D.

Reviewed By:,~j~J J

I NE-943 S2C12 Startup Physics Tests Report Page 57 of 58

I Reference II Test Conditions (Design)

III Test Conditions (Actual)

IV Test.... t'1i Results

V Acceptance Criteria VI Comments SURRY POWER STATION UNIT 2 CYCLE 12 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

H/D Flux Hap-At Power Pree No/ Section: 2-NPT-RX-008,002 Sequence Step No:

Bank Positions (Steps)

RCS Temperature ( 1F):TREF +/-1 Power Level(% F.P.): 95%.SPS SDA: 225 SDB: 225 CA: 225 Other (specify):

CB: 225 cc :* 225 CD:

_ Must have ~ 38 thimbles**

Bank Positions (Steps)

RCS Te*perature( 1F): s,&.\\.~

Power Level~(% F. P.) : 'l'i.C\\\\.t SDA: 225 SDB: 225 CA: 225 Other (Specify): Cu:S ~

CB: 225 cc: 225 CD:

Z.l3S" p~

Date/JtmekTest Performed:

S2'i *~

(11,.,54

~,,.,)........

MAX. REL NUC ENTHAL TOTAL HEAT MAXIMUM POS Meas Paraaeter ASSY PWR

RISE HOT FLUX HOT INCORE (Description)

% DIFF CHAN FACT CHAN FACT QUADRANT

-(H~P)/P F-dH(N)

F-Q(T)

POWER TILT ls,"\\ le.* f'? "° :,

Measured Value

~q10 r~.,

I. ~'2.~

!ll!lf- -* - -*....

\\. 'oi ()

,.oce,o Design Value a 111 -

s a,.,

(Design.Conds) am -

,1 c,.,

NA NA IPJ *--,.In.I S 1.0212 WCAP-79.,05 IWCAP-7905 Reference REV.1 NONE NONE REV.l FSAR/Tech Spec NONE -

r1-.JiO*.J(l*P>I r~msz.n/P

au I NONE Reference NONE

.TS 3.12.B TS 3.12.B NONE

/

Design Tolerance is met

~/v/s' No*

Acceptance Criteria is met

=:iZYES _NO

\\

As Required

- Hust have at least 16 thimbles for quarte.r core aaps for multi;point calibrations.

Prepared By.:

ri*G ~~ 'Id I u7£I h. j) -

Reviewed By: ~ ?J I

V NE-943 S2Cl2 Startup Physics Tests Report Page 58 of 58 100%

ML18151A671

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