Text

Startup Physics Test Rept,Surry Unit 1,Cycle 14
	ML18152A057
Person / Time
Site:	Surry
Issue date:	12/20/1995
From:	Clemens C, Laroe C, Paul M; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Ebneter S; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	96-004, 96-4, NE-1055, NE-1055-R, NE-1055-R00, NUDOCS 9601250198
	Download: ML18152A057 (58)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 11, 1996 Mr. Stewart D. Ebneter, Administrator United States Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323

Dear Mr. Ebneter:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TESTS REPORT Serial No.96-004 NLOS/RPC Docket No.

50-280 License No. DPR-32 As required by Surry Technical Specification 6.6.A.1, enclosed is the Virginia Electric and Power Company Technical Report NE-1055, Revision 0, entitled "Surry Unit 1, Cycle 14 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after initial criticality of Cycle 14 on October 19, 1995.. The results of the physics tests were within the applicable Technical Specification limits.

Very truiy yours, M. L. Bowling, Manager*

Nuclear Licensing & Operations Support Enclosure - Surry Unit 1, Cycle 14 Startup Physics Tests Report cc:

U.S. Nuclear Regulatory Commission - 5 copies Attention: Document Control Desk Washington, D. C. 20555 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 9601250198 951220 PDR ADOCK 05000280 P

PDR 25CC61

TECHNICAL REPORT NE-1055 - Rev. 0 SURRY UNIT 1, CYCLE 14 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER DECEMBER 1995 PREPARED BY: /.// &~/

C. D. Clemens REVIEWED BY: :£:~-

REVIEWED BY :_'-1,4.1.. hJ~J........ _/{_:J----1, __ _

i:11':Paul i,k/:L*

,-4. "'

,..7 Date

,z/2..,:,/q!>

Date Date APPROVED BY: ]).~

/~r'p_r D.D~ Date QA Category: Nuclear Safety Related Keywords: S1Cl4, 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-1055 SlC14 Startup Physics Tests Report Page 1 of 56

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 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 Measurements............

32 Section 7 References...... *................ *... *.....

39 APPENDIX Startup Physics Te.st Results and Evaluation She~ts........................

40 NE-1055 S1C14 Startup Physics Tests Report Page 2

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LIST OF TABLES TABLE TITLE PAGE

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

10

2. 1 Hot Rod Drop Time Summary..... *..... *................

18 3.1 Control Rod Bank Worth Summary........................

23

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

28 5.1 Isothermal Temperature Coefficient Summary............

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

34 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits......................

35 NE-1055 SlC14 Startup Physics Tests Report Page 3 of 56

LIST OF FIGURES FIGURE TITLE

1. 1 Cor~ Loading Map......*............*.....................

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

1.3 Incore Thimble Locations..*.*.*.**.*.*****......*....*...

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

PAGE 11 12 13 14 1.5 Control Rod Locations....................................

15

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

19

2. 2 Rod Drop Time - Hot Full Flow Conditions.................

.20

3. 1 Bank B Integral Rod Worth - HZP..... *....................

24

3. 2 Bank B Differential Rod Worth - HZP......................

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

29 6.1 Assemblywise Power Distribution - 27% Power..............

36 6.2 Assemblywise P6wer Distribution - 54% Power........ ~.....

37 6.3 Assemblywise Power Distribution -100% Power..............

38 NE-1055 S1C14 Startup Physics Tests Report Page 4

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,.*.,.!I

PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 1, Cycle 14 core could be operated safely, and makes an initial evaluation of the performance of the core.

It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken.

Standard test techniques and methods of data analysis were used.

The test data, results, and evaluations, 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 1, Cycle 14 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 :z;-esults, 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 conaitions 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-1055 S1C14 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.

NE-1055 S1C14 Startup Physics Tests Report Page 6

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. I

SECTION 1 INTRODUCTION AND SUKHARY On September 8, 1995 Surry Unit 1 shut down for its thirt~enth refueling.

Between Surry 1 Cycle 13 and Surry 1 Cycle 14, a power uprating took place. The rated thermal power was increased from 2441 MWt to 2546 MWt.

During shutdown, 81 of the 157 fuel assemblies in the core were replaced with 64 {resh assemblies, one once burned assembly, and 16

twice-burned assemblies. The Cycle 14 core consists of eight sub-batches of fuel:

two fresh batches (batches 16A and 16B); three once-burned batches, one from Cycle 8 (batch 10) and two from Cycle 13 (batches ISA and lSB~; three twice-burn*ed batches, one from Cycles 8 and 9 (batch 10),

and two from Cycles 12 and 13 (batches 14A and 14B); and one thrice-burned batch from Cycle 10, 12, and 1~ (batch 12B).

The core loading pattern and the design parameters for each sub-ha t:ch are shown in Figure l, 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 14, while Figure 1.5 identifies the control rod locations.

The Cycle 14 co~e achieved initial criticality at 17:51 on October 19, 1995.

Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the physics test results follows.

NE-1055 SlC14 Startup Physics Tests Report Page 7 of 56

1.

The measured drop time of each control rod was within the 2.4 second limit of Technical Specification 3.12.C.1.

2.

The reference control rod bank was measured with the dilution method, and the result w_as_within -1.3% of the design prediction.

Individual control rod bank worths were measured using the rod swap technique 2 > 3 and all results were within -9.4% of the design predictions. The sum of the individual measured control rod bank worths was within -4.8% of the design prediction.

All results were within the design toleran.ce of +/-15% for individual bank worths (+/-10% for the rod swap reference bank worth) and the desi$n.

tolerance of +/-10% for the sum of the individual control rod bank worths.

... ~

3.

Measured critical boron concentrations for two control bank c9nfigurations were within 29 ppm of the design predictions. The all-rods-out (ARO) result was within the 50 ppm design tolerance, and met the Technical Specification 4.10.A criterion that the overall core reactivity balance shall be within +/-1% 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 1.2% of the design prediction, which is within the design tolerance of +/-10%.

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 tha design tolerance of +/-3 NE-1055 SlC14 Startup Physics Tests Report Page 8

of 56 ta,_* *

. J pcm/°F.

The measured ITC was -2. 79 pcm/ °F..

When the Doppler temperature coefficient

(-1.69 pcm/ 1F) and a

0.5 pcm/°F uncertainty are accounted for in the +3.0 pcm/ 1F HTC limit of the Core Operating Limits Report (COLR)

Section 2.1, the HTC requirement is satisfied as long as the ITC is less positive than 0.81 pcm/ 1F *

6.

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

The average relative.

assembly power distribution measured/predicted percent difference was 1.9t or less for the three initial power ascension flux maps.

The heat flux hot channel fa~tors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of COLR Sections 2.3 and 2.4, respectively.

In summary, all startup physics test results were acceptable.

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

NE-1055 SIC14 Startup Physics Tests Report Page 9

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Table 1.1 SURRY 1 - CYCLE 14 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Test Date Time Power Hot Rod Drop - Hot Full Flow.*. 10/18/95 2200 HSD Zero Power Testing Range....... 10/19/95 2000 HZP Reactivity Computer Checkout *** 10/19/95 2055 HZP Boron Endpoint - ARO......*.**. 10/19/95 2315 HZP Boron Worth Coefficient - ARO **

10/19/95 2315 HZP Temperature Coefficient - ARO *.

10/20/95 0008 HZP Bank B Worth.*****..*..**...**. 10/20/95 0136 HZP Boron Endpoint - Bin....****** 10/20/95 0545 HZP Bank D Worth - Rod Swap *..*.**. 10/20/95 0802 HZP Bank C Worth - Rod Swap....*..* 10/20/95 0919 HZP Bank A Worth - Rod Swap....**.. 10/20/95 0953 HZP Bank SB Worth - Rod Swap....... 10/20/95 1014 HZP Bank SA Worth - Rod Swap...**.* 10/20/95 1215 HZP Flux Map - 27% Power *.*....*... 10/21/95 2314 27.2%

Peaking Factor Verification

& Power Range Calibration Flux M?p - 54% Power..***..*.*. 10/24/95 0201 54.1%

Peaking Factor Verification

& Power Range Calibration Flux Map -100% Power........... 11/03/95 1041 100.0%

Peaking Factor Verification

& Power Range Calibration NE-1055 S1C14 Startup _Physics Tests Report Page Reference Procedure 1-NPT-RX-007 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-008 l-NPT-RX-002 l-NPT-RX-005 l-NPT-RX-008 l-NPT-RX-002 l-NPT-RX-005 l-NPT-RX-008 1-NPT-RX-002 1-NPT-RX-005 l-NPT-RX-008 10 of 56

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4 BURNABLE POISON ROD CLUSTER ZOP -

ZD BURNABLE POISON ROD CLUSTER SSx -

SECONDARY SOURCE FSIL -

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3 5

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Figure 1.S SURRY UNIT 1 - CYCLE 14 CONTROL ROD LOCATIONS N

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Control Bank C Control Bank B Control Bank A Shutdown Bank SB Shutdown Bank SA

- 270° NE-1055 SlC14 Startup Physics Tests Report Page 15 of 56 l

2 3

4 s

6 7

8 9

10 11 12 13 14 15

SECTION 2 CONTROL ROD DROP TIKE KEASUREKENTS 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.

approximately 2252 psia.

This test was performed at The rod drop times were measured ~y withdrawing a bank to its fully withdrawn position and tripping all eight control rods within the bank by opening the reactor trip breakers. This allowed the rods to drop into the core.as they would during a plant trip.

The stationary gripper coil voltage and the Individual Rod Position Indication (!RPI) primary coil voltage signals were recorded fo;- each rod in the bank to determine each rod's drop time.

This procedure was repeated for each bank.

As shown on the ~ample rod drop trace in Figure 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 rod velocity.

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

This voltage reaches a minimum when the rod reaches the bottom of the dashpot.

Subsequent variations in the trace are caused by rod bouncing.

NE-1055 SIC14 Startup Physics Tests Report Page 16 of 56

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.

The test results satisfy this limit.

NE-1055 S1Cl4 Startup Physics Tests Report Page 17 of 56

Table 2.1 SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS HOT ROD DROP TIKE SUKHARY ROD DROP TIKE TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-08 1.37 sec.

L-05 1.26 sec.

1.30 sec.

NE-1055 S1Cl4 Startup Physics Tests Report Page 18 of 56

,r"'

1

Figure 2.1

sURRY UNIT 1 - CYCLE *14 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE 9>> m Of Dlltax CBIQL**ao a Fn:.

~snTra::a, I

..--------+----------fStz:1:x&f~

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£ ROD DRO? TIM: MEASUR:M:NT NE-1055 S1Cll..*~::.n::u,) Ph*.

c:, Te5ts Report

R Figure 2.2 SURRY iJNIT 1 - CYCLE 14 STARTUP 'P:IY~:I.;s TESTS ROD DROP TIME -

HOT FULL FLOW CONDITIONS p

N L

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I __ I NE-1055 S1Cl4 Startup Physics Tests Report Page 20 of 56 l

z 3

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SECTION 3 CONTROL ROD BANK WORTH KEASUREKENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique2,,. The initial step of the rod swap 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 techniques.

The reactivity changes resulting from the ~eference bank movements were recorded continuously by t~e 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 14,

. 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 (MCP) of the reference bank with the test bank fully in~erted was used to NE-1055 S1C14 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 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, all of the individual measured bank worths for the control and shutdown banks were within the design tolerance (+/-10I 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 6qo pcm).

The sum of the individual measured rod bank worths was within -4. Bl 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, th.e measured rod worth values were satisfactory.

NE-1055 S1C14*Startup Physics Tests Report Page 22 of 56

,1(,

Table 3.1 YCLE 14 STARTUP PH~SICS TESTS SURRY UNIT 1

C CONTROL. ROD BANK WORTH

SUMMARY

HEASUR WORTH (PCH)

ED PREDICTED PERCENT DIFFERENCE BANK B-Reference Bank D

C A

SB SA Total Worth 0

1 3

1412.

1044.

728.

260.8 1055.4 1053.3 5553.9

Difference is less th an 100 WORTH (PCH) 1430.0 1112.6 803.6

. 276.4 1130.2 1078.3 5831.1 pcm.

NE-1055 S1Cl4 Startup Physics Tests Report

(%)

(M-P)/P X 100

-1'.3

-6.2

-9.4

-5,6*

-6.6

-2.3

-4.8 Page 23 of 56

1500 1400 I

1300 1200 1100 z 1000 0

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800 0

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100 I

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Figure 3.1 SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS ~ITHDRAWN 1.

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50 75 100 125 150 175 200 225 B BANK POSITION (5 STEPS/ DIVISION)

NE-1055 S1C14 Startup Physics Tests Report Page Predicted Measured 24 of 56

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40 80 120 160 200 8 BANK POSITION (5 STEPS/ DIVISION)

.\\'~-10'i'i.c: 1r.1t..c:+-'!rt1:n Ph\\*sfrs Tests Reoort Page Predicted Measured 25 of 5 6

SECTION 4 BORON ENDPOINT AND WORTH KEASUREKENTS 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 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.

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 rod worth present in the core at the time of the endpoint measurement,

~E-1055 S1Cl4 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 versus inserted control rod worth is shown in Figure 4.1. As indicated in this figure and iµ the Appendix, the measured DBW was -7.17 pcm/ppm.

This is within 1.2% of the predicted value of -7.26 pcm/ppm and is well within the design tolerance of +/-10%.

In summary, the measured boron worth coefficient* was satisfactory.

NE-1055 SIC14 Startup Physics Tests Report Page 27 of 56

Table 4.1 SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS BORON ENDPOINTS SUKKARY Measured Predicted Control Rod Endpoint

~ndpoint Configuration (ppm)

(ppm)

ARO 1754 1783 B Bank In 1557 1557*

Difference M-P (ppm)

-29 0

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-1055 S1Cl4 Startup fhysics Tests Report Page 28 of 56

Sf 0

e:.

~

1=

0

~

a:

1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

1540 J

I I

Figure* 4.1 SURRY UNIT 1 - CYCLE 14 START~P PHrSICS TESTS BORON WORTH COEFFICIENT Measured DBW= -7.17 pcm/ppm

'11,

' ' ' ' 1,

' ' II-I I

1550 1580 1600 1620 1640 1660 1680 1700 BORON CONCENTRATION (PPM)

NF.-10S5 s1r.1L. St'lrtnn Phvsir.s TP.c::ts RPnort Paee

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1720 1740 1760 29 of 56

SECTION 5 TEMPERATURE COEFFICIENT KEASUREKENT 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, an aborted heatup, and another cooldown.

Reactivity was measured during the first RCS cooldown at a

temperature range of 3.4 1F and the second RCS cooldown at a temperature range of 3.2 1F.

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

Using the statepoint method, ~he 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 ITO.

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/ 1F.

Accounting for the Doppler temperature coefficient (-1.69 pcm/ 1F) and a 0.5 pcm/°F uncertainty, the moderator temperature coefficient was -0.60 pcm/ 1F, which meets the requirement of Core Operating Limits Report Section 2.1. In summary, the measured result was satisfactory.

NE-1055 SIC14 Startup Physics Tests Report Page 30 of 56 ti:\\

BANK*

POSITION D/214 Table 5.1 SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/ F)

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

.DIFFER.

( F)

(ppm) iJ1 fJ2 MEAS. PRED.

(M-P) 544.3 to 1752

-3.24 -2.34 -2.79 -4.08 1.29 548.3 NE-1055 S1C14 Startup Physics Tests Report Page 31 of 56

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 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 determined from this data using the CECOR code'.

CECOR couples the measured voltages with predetermined

~nalytic 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 and the measured values of the important *power distribution parameters are given in Table 6.1. A comparison of these mea_sured vaiues with their Technical-Specification limits is given in Table 6.2.

Flux map 1 was taken at approximately 27% power to verify the radial power distribution (~PD) predictions at low power.

Figure 6. 1 shows the measured RPDs from this flux map.

Flux maps 2 through 3 were taken near 54%

and 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 difference was NE-1055 S1C14 Startup Physics Tests Report Page 32 of 56

~* I

1.9% or less for the three maps.

The measured F-Q(Z) *and F-DH(N) peaking

~~ctor values for all flux maps were,,.-ithin ;;he limits of the Core Operating Limits Report (COLR) Sections 2.3 and 2.4, respectively.

Note that separate F-DH(N) values are reported for SIF and LOPAR assemblies, which allows comparison to separate limits for the two types of fuel in the COLR.

Flux maps 1 and 2 were used to recalibrate the power range excore detectors.

A power range detector calibration based on flux map 3 verified the existing calibration was sa~isfactory.

In conclusion, the power di.stribution 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 14.

NE-1055 S1C14 Startup Physics Tests Report Page 33 of 56

TABLE 6.1 SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS INCORE FLUX KAP

SUMMARY

I I

1 I

I 3

I I

I IIURICI I

I F-QCZ> ll>T F-llfCNJ ll>T I

I 11AP IIIAPI I

IP I IUNK I CHANNEL FACTOR CIICL.FACTDR I

I DESCRIPTION IND. I DATE I IIIID/IPIIRI D

I I

I I NTU ICZ>ISTEPSI_ASS_Y..,l-,.-X--1-AL.......,.I_F ___

Cl_(Z_>_

ASSY I F-Otf(N)I I

I I

I

. I I POINT I I

I SIF I

1....,...,, ________ 1_1 1 __ 1_1 __ 1 __ 1 ___ 1 ___ 1 __

1 ___ 1 I LESS THN 30% PWR I 1 II0-22-951 6 I 271 166 I Ell I 30 I

2.045 I Lll I

1.477 I I ITWH SD% AND 75% I 2 IJ0-24-951 211 I ~I 1111 I Ell I 30 I

l.~l I Ell I

1.465 I I CRT THAN 95% PWR I 3 lll-03-951 360 llOOI 227 I LOS I 41 I

1.7711 I Ell I

l.~32 I I

I_I I __ I_I __ I __ I __

I I __

I I

2 I

I 3

I I

I F-DHtN> HOT I CORE FCZ>

POWER I

I I

I NAP INAPI I OtHL.FACTDR I

IWC TILT I AXIALI ND. I I

DESCRIPTION IND. I DATE I

I I

I OFF I OF I I

I I

I ASSY I F-DHCN>IAXIALI FCZ>I MAX ILDCI SET ITHIHI I

I I

LDPAR iPDINTI I

I I

CZ> IILESI

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1 __

1 ___ 1 __, __ 1 __,_1 __ 1_1

1 LESS THN 30% PWR I 1 110-22-951 HOii I

1.127 I lO ll.211lll.OOIII SEI -6.11111 ~2 I I ITWN SO% AND 75% I 2 IJD-24-951 HOii I

J.166 I 30 ll.221111.0071 SEI -S.691 ~3 I I CRT THAN 95% P11R I 3 lll-03-951 HOii I

1.210 I 30 11.14511.00III SEI -S.161 40 I I

I_I I __

I I __ I __ I __ I_I __ I_I NOTES: HOT SPOT LOCATIONS ARE SPECIFIED IY CIVIHC ASSENILY LOCATIONS CE.;. HOii IS THE CENTER-OF-CORE ASSEMBLY>,

AND CORE.HEIGHT CIN Tl£ *z-DIRECTION Tl£ CORE IS DIVIDED

INTO 61 AXIAL POINTS ST ARTINC FRO!t THE TOP OF THE CORE).

1. F-Cl(Z) INCLUDES.A TOTAL UNCERTAINTY OF 1.011.

2. POWER TILT -

DEFINED AS THE AVERAGE CIUADRANT POWER TILT FRON CECOR.

3. EACH HAP WAS USED TO PERFORH A PEIJCJNC FACTOR VERIFICATION AHD A POWER RANCE EXCORE DETECTOR CALIBRATION.

Tl£ FLUX HAP 3 CALIBRATION VERIFIED THE EXISTI~ CALIBRATION.

NE-1055 S1Cl4 Startup Physics Tests Report Page 34 of 56

Table. 6.2 SURRY UNIT 1 - CYCLE 14 STARTUP PHYHCS TESTS COMPARISON OF HEASURED POWER DISTRIBUTION PARAHETERS WITH THEIR CORE OPERATING LIHITS I

I F-Q(Zl HOT I

I PEAIC F-Q(Zl HOT I CHANNEL FACTOR**

I I

CHANNEL FACTOR* I (AT NODE OF NINIIIUII IWICIN)

F-DH(Nl HOT CHANIEL FACTOR (SIF)

F-DHCN) HOT CHANEL FACTOR

<LDPAl!l l~~I l...,.,,=,.....,.....,..,,.-=,...,.,=,,,=-.,--:-,:=,-,--~~~~~~~--~~~~-,-~~-

1 NAP IIIEAS I UNIT INODEI 1£AS I LINH INODEI IWICIN IEAS ILINITI IWICIN 1EAS ILINITI IWICIN I ND. I I

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1 IZ.0451 4.6Za I 30 I Z.8451 4.6Za I 30 I 55.a 11.477 l1.9Dll ZZ.3 l1.1Z7 fl.6',0I 31.3 I

I Z

11.9411 4.Zal I 30 I 1.9411 4.Zal I 30 I 5".7 11.465 11.7751 17.5 11.166 11.5311 Z3.8 I

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11.11a1 Z.3Zl I 41 I 1.11a1 Z.3Zl I 41 I Z3.4 11.oz 11.5601 a.z 11.ZlO 11.3461 10.1 I

1 __ 1 __ 1 __ 1_1 __

1 __ 1_1 ___ 1 __ 1 __ 1 ___ 1 __

, __ 1 ___ 1 Th<I Tuchnical Specification"s li*it for the heat flux hot channel factor, F-Q(Zl, ls

function of core height and power level.

The valuus for F-Q(Zl listed are the aaxi... value of F-QCZ) in th<I cora.

The Technical Specification"s li*it listed above is evaluated at the plane of aaxi... F-QCZ) *.

Th<I value for F-Q(Zl listed above is the value at the pl.,. of aini.,.. aargin.

The *ini... aargin values listed are the aini... percent diffarGnCa bet-the -asur.cl values of F-QCZ) and the TaclVlical Specification"s liait at that node for each aap.

The -asured F-Q(Zl hot c:hmvMll factors include az total uncertainty.

NE-1055 S1C14 Startup Physics Tests Report Page 35 of 56

R p

Figure 6.1

.. SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS ASSEKBLYWISE POWER DISTRIBUTION N

PREDICTED IEASIH:D

PCT DIFFERENCE.

27% POWER L

r:

.J H

F E

I.ZS<,

D.Z7a. o.z~ *

1.Z76. o.Z67. o.zao *

-z.a. -Ii.a. -1.5 *

o.Z63. 1.558. 1.D95. 0.909. 1.095. 1.558. I.Z63 *

D.Z6Z. 1.553. 1.17Z. 1.864. 1.090

1.5,86. I.Z71 *

-0.l. -D.9. -Z.1. -5.0. -D.S.

4.9.

3.3

D C

PREDICTED IIEASURED

.PCT DIFFERENCE *

D.Z4Z. 0.975. 1.Z74. 1.Z73. 1.Z60. 1.Z73. l.Z74

0.975. I.Z4Z.

D.Z4S

D.974

l.Z69

1.Z55

1.zz7

1.Z611

l.Z91

1.994. I.Z59

z.z. -D.1. -0.li. -I.Ii. -Z.6. -o.3.

1.4.

1.9.

6.6 *.

o.Z47. 0.793. 1.187. 1.346. l.31Z. 1.zaz. l.31Z. 1.346. 1.187. 1.793. I.Z47 *

o.Z51

0.79&. 1.178. 1.343. 1.311

l.Z77. 1.311

l.35Z. 1.195. I.SOD

O.Z4S.

l.S.

0.7. -0.7. -o.z. -D.l. -D.li. -D.1.

D.li.

1.7.

l.D.

1.5

I

O.Z63

0.977. 1.1&5. 1.336. 1.Z93. l.Z63; l.Z75. l.Z63. l.Z93. 1.338. 1.186. 0.977. D.Z63 *

O.Z69. 0.999. 1.19&. 1.347. l.ZS5. 1.Z7S. l.Z7a. l.Z53. l.Z78. l.33D. 1.1az. 1.97&. D.Z64

Z.3.

Z.3.

1.1.

o.a. -0.6.

l.Z.

D.Z. -D.7. -1.z. -1.6. -1.4.

D.l.

D.3 *

0.557. l.Z7l

1.339. l.Za7

l.Z04

l.ZZ5

l.ZOl'. 1.ZZ7

l.Z04

l.Za7. 1.339

l.Z7l

0.557 *

0.567. l.Z93. 1.343. l.Z46. 1.139. l.Z03. l.Z04. 1.198. l.14Z. l.Z66. 1.333. l.Z611. 0.557.

1.a.

0.3. -3.Z. -5.li. -1.a.

D.Z. -Z.3. -5.l. -1.6. -1.5. -D.Z.

0.0

A

. O.ZS4

1.094. l.Z69. 1.307. 1.zsa. 1.zz4. 1.164. 1.134. 1.167. 1.zz5. l.Z59. 1.307. l.Z69. 1.094. o.za4

L

o.zaa

1.101

1.Z97

1.313

1.Z3a

1.1&a

1.uz

1.106

1.uz

1.190

1.zu

l.Z9S

1.zsa

1.091

o.zao *

1.

1.6.

l.Z.

Z.3.

D.5. -1.6. -3.0. -4.5. -Z.5. -4.7. -Z.9. -1.4. -1.7. *D.S. -0.3 ~ -1.Z *

O.Z77. 0.907. l.ZS6. l.Z79. l.Z73. I.ZOO. 1.134. 1.059. 1.135. l.ZOl. l.Z73. l.Z79. l.ZS6. 0.907. O.Z77 *

o.z90. o.aa5. 1.Z6Z. 1.za5. 1.zsa. 1.1a1. 1.10a. 1.039. 1.109. 1.186. 1.Z6Z. 1.z11

1.zz5. o.a68. o.Z69.

a 4.7. -Z.4.

0.4.

D.5. -1.1. -1.5. -z.z. -1.9. -z.z. -1.Z. -1.a. -1.6. -Z.5. -4.3. -3.l *

o.za4. 1.094. 1.Z69. 1.307. 1.Z59. 1.zz5. 1.166. 1.134. 1.165. 1.zz4. 1.zsa. 1.307; l.Z69. 1.094. o.za<, *

o.za5, l.09Z. l.Z71

l.3Zl. l.ZS6. l.ZlZ. 1.143. 1.11a. 1.141. 1.1ao. l.Z48. 1.313. l.Z69. l.089. o.za3.

o.5. -o.z.

o.z.

1.1.

z.1. -1.1. -z.o. -1.5. -z.1. -3.6. -1.a.

1.5.

o.o. -o.5.

-o.<,

HAP NO:

CONTROL D BANK

. *o.557

l.Z71

1.339. l.ZS7. l.Z04

1.zz7. l.ZOl

1.zzs. l.Z04

1.za7. 1.339. l.Z71

0.557 *

0.556

l.Z59. 1.353. 1.Z96. 1.156. 1.186. 1.190

l.Zll

1.158. l.Z91

1.373. l.Z9S. 0.570 *

-o.z. -0.9.

1.0.

0.7. -4.0. -3.3. -1.0. -1.l * -3.S.

D.3.

Z.5.

Z.l.

Z.Z

O.Z63. 0.977. 1.186. 1.336. l.Z93. l.Z63. l.Z75. l.Z63. l.Z93. 1.336. 1.1&5. D.977". O.Z63 *

O.Z66

0.99Z

l.ZlZ. 1.371

1.311

l.Z66. l.ZS5. l.Z76. l.3Z5. 1.363. l.ZZ6. l.Oll

O.Z71

1.1

1.6.

Z.l.

Z.6.

0.6.

0.3.

o.a.

1.1.

z.s.

z.o.

3.4.

3.S.

3.Z *

o.Z47

0.793. 1.1&7. 1.346. l.31Z 1.za,. l.31Z 1.346 1.1&7 0.793. D.Z47 *

. O.Z67

0.819. l.ZZO

1.37&

1.344

l.303

1.335

1:375

l.ZZ3

o.~5

O.Z65

a.3.

3.4.

z.a.

Z.4.

z.4.

1.6.

1.a.

z.z.

3.1.

6.6*.

7.5 *

o.z~z

0.975

l.Z74

l.Z73

l.Z60

l.Z73

l.Z74

o.975

I.ZliZ- *

O.Z51. 1.003. 1.306. l.Z96. l.Z65. l.Z93. 1.zao. 0.997. D.Z53.

3.6.

z.a.

z.5.

1.9.

o.4.

1.6.

o.5.

z.3.

4.6

STANDARD DEVIATION

=1.556 Sl-14-0l ROD POSITIONS:

AT 166 STEPS

o.Z63. o.5sa. 1.09S. o.909. 1.095. o.5sa. o.Z63 *

. 0,Z65. 0.570. 1.111. O.S91i. 1.133. 0.570. O.Z69.

0.9.

Z.l.

1.5. -1.7.

3.5.

z.z.

Z.6 *

. O.ZS4, 0.278. O.ZS4.

. 0.296. O.Z7S. O.Z91.

Ii.I

0.1

Z.4.

SUHHARV DATE: 10/22/95 POWER:

27.2%

F-QIZ> = 2.045 QPTR:

NW 0.9939 F-DHIH) = l.477 SW 1.0067

'SIF' F-DHIH) = l.127 FIZ) =

1.283

'LOPAR' BURHUP =

6.0 HWD/HTU A.O. = -6.881%

HE SE A\\IERACE

. :PCT DIFFERENCE.

= 1.9 0.9919 l.007(,

NE-1055 SlC14 Startup Physics Tests Report Page 36 of 56 14 l:,

.._._)

R p

Figure 6.2 SURRY UNIT 1 CYCLE 14 STARTUP PHY::rcs TESTS ASSEHBLYWISE POWER DISTilBUTION N

PREDICTED IIEASlRED

. PCT DIFFERENCE.

54% POWER I(

J H

G 1.29a

1.293

1.29a

I.Za9

I.ZB3

1.293 *

-3.1. -3.7. -1.a.

F E

O.Z7l

11.569

1.107

1.9~

1.107 D.569 I.Z7l *

o.267

o.559

1.179

l.&95

1.096

o.sa1

a.z75 *

-1.z * -1.7. -Z.6 *

-4.Z * -1.l

z.o

1.6

D C

PREDICTED IIEASU!ED

.PCT DIFFERENCE *

D.249. 0.975. l.Z61. I.Z67. l.ZS3 l.Z67 I.Z61 0.975 0.249 *

o.253. o.964. 1.243. I.Z37. 1.zz3. 1.zsa. 1.267. o.985

o.zsa.

1.7 *

-1.2 *

-1.4 *

-z.r, *

-Z.4 *

-D.7

0.5

1.1

3.6

O.ZY.

0.797

1.174 l.329

1.295 I.Z7l 1.295 1.330 1.174 0.797

O.ZY. *

0.253. o.794

1.152. 1.318. 1.2a1. 1.26". 1.292

1.333. 1.180

o.ao5. 0.255.

-0.1 *

-0.3 *

-1.9 *

-1.9.

-1.6.

-1.5.

-o.z

0.2

0.6

1.1 *

-0.5

I

0.211

o.977. 1.112. 1.323. 1.280. 1.256. 1.265. 1.2S6 1.280 1.323. 1.112. o.977. o.z11 *

0.272. 0.979. 1.177. 1.337. I.Z76. I.Z69. 1.271

1.253. l.Z72. 1.323. 1.1a2. 0.980." O.Z67.

o.4

0.2

o.4

1.1 *

-o.3

1.1

o.r,.

-0.2 *

-o.6

o.o

o.a.

o.3 *

-1.6

o.S6a. 1.zsa. 1.323. 1.214. 1.2~7. 1.zza. 1.zo1. 1.229 1.z11 1.274 1.323. 1.zr.a. o.569 *

0.511

1.26". 1.325. 1.z59. 1.11a. 1.218. 1.221

1.21a. 1.179. 1.262. 1.319. 1.257. o.5611.

D.4 *

o.r,

0.2 *

-1.l *

-3.Z * -1.a.

1.1 *

-0.9 *

-3.l *

-0.9 *

-0.3 *

-o.l *

-0.l

0.29a 1.101 1.263. 1.290

1.252. 1.226. 1.111. 1.151

1.1ao 1.22a 1.2Y.

1.290

1.263. 1.101. 0.29a *

0.299

1.109. 1.Z7D

1.291

J.Z4Z. 1.206. 1.143. 1.141

1.157. 1.209. 1.240

1.271

1.254

1.109

0.295

0.4

0.2

o.5

0.1 *

-o.8 * -1.7. -2.9 *

-1.9 *

-1.5 *

-1.1 *

-1.5 *

-a.a

0.1 *

-1.0

o.293 o.933 1.250

1.269. 1.263. 1.205. 1.151

1.G111

1.152 1.206 1.263

1.269. 1.250. o.93'o

o.Z93 *

o.301

o.915

1.250

1.273

1.z55

l.196

1.137

1.014

1.1~2

1.197

1.2Y.

1.259

1.zz5

o.890

0.282

2.1. -1.9.

o.o.

o.3. -D.6. -0.1. -1.2. -1.7. -o.9. -a.a. -o.7. -o.8. -1.1. -4.6. -3.a.

0.29a. 1.101. 1.263. 1.290. 1.254

1.228. 1.179. 1.151

1.179 1.226 l.Z52. 1.290

1.263. 1.101. 0.298 *

O.Z98". 1.107. 1.267. 1.302. 1.279. 1.223. 1.166. 1.146. 1.169. 1.201

1.247

1.291

1.259. l.093. 0.291

0.2 *

-0.1

o.3

o.9

2.0 *

-o.4 *

-1.1 *

-o.5 *

-o.9 *

-2.1 *

-o.4

0.1 *

-o.3 *

-1.3 *

-2.2

HAP NO:

CONTROL D BANK o.569 1.2sa. 1.323. 1.274. 1.211. 1.229. 1.201 1.228 1.211 1.274 1.323. 1.zr.a o.569 *

0.569

l.256

l.333

l.286

1.186. 1.197

l.206

l.226

1.192

1.283

l.3'o3

1.272. D.571

0.1 *

-0.2

l.l

0.9 *

-2.5 *

-D.l *

-o.l *

-2.0

0.7

1.5

LI.

0.4.

0.211 o.977

1.112

1.323

1*.280

l.256

1.265

l.256

1.280 1.323 1.112

o.977

0.211 *

o.z1r,

o.992. 1.196. 1.355. 1.289. 1.261

1.283. 1.274

1.512. 1.360

1.206

1.000

0.216

1.z

1.6

2.0

z.4

0.1.

1.5.

1.a

1.5..

2.5

2.8

2.9

2.t,

1.a

0.2Y.,. 0.797

l.174 l.330 l.295 1.271 1.295 1.329 l.174 0.797

0.2S4

0.272. 0.819. 1.200

1.353. 1.313. 1.283. 1.314

1.353. 1.207

0.8"3. D.267.

1.2.

2.8.

2.2.

1.1.

1.4.

1.5.

1.8.

2.9.

5.8.

5.1 *

0,249

U.975

l.261

l.267

l.ZS3

1.267 l.261 0.975

0.249 *

0.255

o.994.* 1.281

1.280

1.252

1.278

1.259

o.991

o.zsa

2.6

2.0

1.6.

1.1 * -1.l.

0.9 *

-0.1

1.7

3.6

STAHD,ll!D DEVIATION

=l.175 Sl-14-02 ROD POSITIONS:

AT 181 STEPS

0.271

0.569

1.107

0.93',

1.107 0.569 0.271

0.271

0.576. 1.115. 1.920

1.127. 0.575. 0.275.

0.2

1.2

1.7.

-1.6

1!7

l.O

1.6 *

0.298. 0.293. 0.298

D.303

0.292

0.301.

1.7. -0.6.

1.0

SuttttARY DATE: 10/24/95 POWER:

54.1%

F-Q!Zl

= 1.941 QPTR:

NW 0.9926 F-DH!Nl = 1.465 SW

1. 0064

'SIF' F-DH!Nl = 1.166 f(Z) =

1.228

'LOPAR' BURNUP

=

28 HWD/HTU A.O. =

-5.687%

NE SE A\\IERACE

.PCT DIFFERENCE.

=

1.3 0.9945 1.0065 NE-1055 S1C14 Startup Physics Tests Report Page 37 of 56

R p

Figure 6.3 SURRY UNIT 1 - CYCLE 14 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTIO:-l N

PREDICTED MEI.SIRED

PCT DIFFEJ!£NCE.

L 100% POWER It

.J H

C:

0.312. 1.312. 1.312.

D.306. 1.307. 1.310.

-1.9. -1.6. -1.6 ~

F E

0.281

o.577. 1.108. 1.966. 1.108. o.577

0.281 *

o.z75. o.566. 1.087. 1.951

1.105. 1.595. 1.Z85.

-z.o *

-1.9 *

-1.9 * -1.6 *

-1.2.

3.1

1.6

D C

PREDICTED MEASURED

.PCT DIFFERENCE *

0.257

0.965

1.236

1.247

1.20

1.247

1.Z36

0.965

O.Z57 *

I.Z6Z. D.9"6. I.Zl3. l.Zl8. l.Z07. l.Z38. l.Z42. 0.973. D.Z68.

1.8. -1.9. -1.9. -Z.3. -z.6. -o.7.

1.4.

o.a.

4.3 *

0.262. 0.799. 1.154. 1.302. 1.276. 1.ZS9. J.276. 1.302

l.l~

D.799. 0.26Z *

D.Z60

1.790

l.lZO. 1.28ft. l.Z64

l.Z48. l.27D. l.30Z

1.155. o.aoo. D.Z60 *

-1.9. -1.2. -Z.9. -1.4. -1.0. -D.9. -o.4.

D.D.

D.l.

D.l. -0.8

I

D.281

0.967. 1.151

1.303. l.Z75. l.Z53. 1.261

1.253. l.Z75

1.303. 1.153. 0.968

o.za1 *

. 0.281

0.969

l.lt,8

l.31Z

l.Z73

l.Z64

l.Z65

l.Z53

l.Z73

1.299

l.lt,6

0.96Z

O.Z79 *

-0.l.

1.Z. -0.3.

D.7. -o.z.

D.9.

0.3. -0.l. -1.Z. -0.3. -1.7. -1.6. -0.9 *

0.577. 1.236. l.Z98. l.Z69. l.ZS6. l.Z43. J.ZZZ. l.Z45. l.ZS6

1.269. l.Z98. 1.236

0.577.

0.576. l.Z30

1.za7. l.Z45. l.Z45. I.Z41

l.Z4D

1.zt,5. 1.ZS3

l.Z6Z. l.Z87. l.ZZ9. 0.577 *

-o.z. -1.4. -o.9. -1.9. -o.9. -a.z.

1.5.

o.o. -a.z. -o.5. -o.9. -o.6 **

o.o

A

D.31Z. 1.106. l.Z"6. l.Z73. l.Z5Z. l.Z4Z. l.ZD4. 1.184

I.Z06. l.Z44

l.Z53. l.Z73. l.Zt,7

1.106. 0.312 *

~-;

4

.!~-.

0.317. 1.10a. l.Z38. 1.263. l.Z38. l.ZZ7. 1.1ao. 1.178. 1.19". 1.Z39. 1.zt,t,. l.ZSZ. l.Z39. 1.117. D.31(,.

7 1.7.

D.Z. -0.7. -o.a. -1.z. -1.z. -z.o. -o.5. -1.0. -0.4. -0.7. -1.7. -D.6.

J.D.

D.7 *

0.31Z. 0.966. l.Z38. 1.Z55. l.Z59. l.ZZD

1.183. l.1Z6. 1.185. l.ZZD

1.Z59. l.Z55. l.Z3a. 0.966. D.31Z *

0.335. D.97Z. 1.Z3". 1.250. l.Z50. l.Zll. 1.171. 1.119. 1.180. 1.zz7. l.Z57. 1.2(,7. l.ZZ6. 0.9611. 0.31Z.

~

7.t,.

0.6. -0.3. -O.t,. -0.7. -D.7. -1.D. -1.6. -D.4.

D.6. -D.Z. *0.6. -1.D.

D.2.

0.1 *

D.31Z. 1.106. 1.Zt,6. 1.Z73. 1.Z5Z. 1.24(,. 1.206. 1.18ft. l.ZD(o. 1.Z43. 1.252. l.Z73. 1.zt,7. 1.106. 0.312 *

D.317. 1.107. 1.2(,1

1.275. 1.272. l.Z43. 1.196. 1.178. 1.199. 1.ZZ9. l.25Z. l.Z77. l.25Z

1.115. D.313.

1.7 *.

0.1. -0.4.

D.l.

1.6. -~.J. -D.9. -0.5. -D.4. -1.l

D.D.

D.3.

0.4.

o.a.

HAP NO:

CONTROL D BANK

D.577. l.Z36. l.Z98

1.269. l.ZS6. 1.245. 1.Z22. l.Z43. 1.Z56

1.269. l.Z98. 1.236. D.577 *

D.572. 1.ZJ5. 1.299. 1.Z78. l.Z55. 1.2zz. 1.Zl9. J.Z46. 1.Z6Z

1.281

1.317. l.Z54

D.592.

-a.a *

-1.7

D.D

o.7 *

-D.1 * -1.8 *

-D.3

D.Z

0.5

1.0

J.4

1.5

2.7 *

D.281

D.968. 1.153. 1.303. l.Z75. l.Z53. 1.261

J.Z53. 1.Z75

1.303. 1.151

D.967. D.281 *

D.Zal

D.970

1.163

1.325

1.281.* l.251

1.Z73

J.Z6(o

1.300

l.3Z8

1.178

D.987

o.zaa *

-0.2.

1.z.

a.a.

1.1.

o.4. -o.z.

o.9.

1.9.

z.o.

2.1.

z.2 *

D.Z62. D.799. 1.154. l.3DZ. 1.276. 1.259. 1.276. 1.302. I.I~. 0.799: 0.26Z *

D.279. D.811. 1.166. 1.308. 1.273. 1.261

1.284. 1.31(,

1.175. a.ala. O.Z7D.

6.5.

1.5.

1.0.

0.4. -0.3.

0.2.

D.6.

0.9.

1.9.

4.9.

Z.9 *

D.257. D.965. l.Z36. l.Z47. 1.Z40

1.Z47. l.Z36. 0.965. O.Z57 *

D.Z60

0.972. l.24Z. l.Z49. l.23Z. 1.253. 1.z2a

D.97Z. D.263.

a.,.

o.8.

o.5.

0.1. -0.1.

o.5. -0.1.

a.a.

2.3

STANDI.RD DEVU.T ION cJ.110 Zl-14-03 ROD POSITIONS:

AT 227 STEPS

o.z81. o.577. 1.10a. 1.966. 1.108. o.577. o.2a1.

- o.za1. o.581. 1.119. J.977. 1.139. o.583. o.2a1.

o.z

o.6.

1.1

1.1

2.a.

1.0

o.a.

. 0.31Z. 0.31Z

0.312.

0.327. 0.318

0.320

4.6.

z.o.

z.6.

SUHHARY DATE: 11/03/95 POWER: 99.987.

F-QCZ) = 1.778 QPTR:

HW 0.9916 F-DHCN) = 1.432 SW

l. 0025

'SIF' F-DHCNJ = 1.210 FlZ) =

1.145

'LOPAR' BURNUP =

360 11WD/11TU A.O. = -5.0637.

HE SE AVERACE

.PCT DIFFERENCE.

E 1.1 0.9976 l.0083 NE-1055 SlC14 Startup Physics Tests Report Page 38 of 56 JO 11 11 14 15

SECTION 7 REFERENCES

1. R. F. Villaflor, "Surry Unit 1, Cycle 14 Design Report",

Technical Report NE-1045, Revision O, October, 1995.

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 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 Dis.tribution Analysis Using a Moveable 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. S.S. Kere, "Reload Safety Evaluation Surry 1 Cycle 14 Pattern OJ",

Technical Report NE-1032, Revision 0, August, 1995.

7. C. B. LaRoe, "Surry 1, Cycle 14 TOTE Calculations",

Calculation Note PM-623, Revision O, October, 1995.

8. R. A. Hall, "Surry 1, Cycle 14 Flux Hap Analysis, Calculation Note PM-625, Revision O, October, 1995.

9. C. B. Laroe, "Surry 1, Cycle 14 Flux Hap Analysis",

Calculation Note PM-6~5, Revision O.A, October, 1995.

10. M. E. Paul, "Surry_ 1, Cycle 14 Flux Map Analysis",

Calculation Note PM-625, Revision O.B, November, 1995.

NE-1055 S!C14 S~artup Physics Tests Report Page 39 of 56

APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-1055 S1Cl4 Startup Physics Tests Report Page 40 of 56

.)

SURRY POWER STATION u*N~ 1 CYCLE 14*

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET J: :

Test

Description:

Zero Power Testing Range De+ermination

,..~eferer.ce Froc No I Section:

1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level {°hi_.F.P.): o Concfrtions SDA:

22.7 SOB: '227.

CA:

'227 Other (specify):

(Design)

CB:

22.7 cc:

CD:

Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): S"i&

Test Power Level(% F.P.): O Conditions SDA:

22.7 SOB:

'227 CA:

227 Other (specify):

(Actuan CB:

221 CC:

CD:

Below Nuclear Heating Datemme Test Performed:

10 "°' I crs

'2b00 Reactivity Computer Initial

_q Flux Background Reading J.;,t.. X /0 amps IV Test Results Flux Reading At

. -'1 Point Of Nuclear Heating 3 i< lo amps Zero Power Testing Range IX 10-8 to

-6

10 -1,. IO amps R*eference Not Applicable V

FSAR/Tech Spec Not Applicable Acceptance

.

Criteria. ~eference Not Applicable

Design Tolerance is met..... _{_ YES

__ NO*

Acceptance Criteria is met.... :

YES NO VI

At The Just Critical Position Comments... Design Tolerance and Acceptance Criteria are met_if ZPTR is below the Point of Nuclear H~ating and above b~ckground.

Prepared By:~ 'o. ~ Reviewed By: 7' /. /A~.

1*~-*'"'=-= (:*""'"'. C'-..,-..,*P"\\

r'h\\*c:-irc::-

TPc:::~c:::

Pnr'\\l"')rt P 2 ~ e t, 1 0 : 5 'S

SURRY POWER.STATION UNtt 1 CYCLE *14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Reactivity Computer Checkout Reference Proc No I Section:

1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps)

RCS T einperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA:

Z27 SOB:

227 CA:

227

Other (specify):."'

(Design)

CB:

'227 cc:

CD:

Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): 5Ll-1,Z Test

. Power Level (% F.P.): 0 Conditions SDA:

'227 SOB: 227 CA:

227 Other (specify):

(Actual)

CB:

'227 CC: ~1 CD: l~

Below Nuclear Heating Date/Time Test Performed:

10'10.Jq:,

lo S'S" Measured Parameter Pc= Measured Reactivity using p-computer (Description) p,= Predicted Reactivity IV Test Results Measured Value Pc= -3rr

~o p,= -:-l.t)

+'+O.S

%D= - :2. c..

-:l,o Design Value

%D= {(Pc-pJ/pJ X 100%::: 4.0 %

Reference WCAP 7905, Rev. 1, Table 3.6 V

FSAR/Tech Spec Not Applicable Acceptance Criteria Reference.

Not Applicable Design Tolerance is met

-"'-YES

__ NO Acceptance Criteria is met :

v' YES NO VI

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

Allowable R~nge =

Prepared By:~ J) ~ *Reviewed By/..-/. ~

~E-1055 S1Clh Start~p Physics Tests Report Paee 4~

of 56

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Critical Boron Concentration -ARO Ref~rence Pr.:,c No / Section:

1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level(%.F.P.): O Conditbns SDA:

227 SOB: '227 CA:

227 Other (specify):

(Design)

CB:

221 CC: '227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): 54,. ~

Test Power Level(% F.P.): O Conditions SDA:

227 SOB: '227 CA:.

227 Other (specify):

(ActuaO CB:

221 CC: '221 CD:

227 Below Nuclear Heating Date/Time Test Performed:

\\O/ LO. /°'IS

~"3: \\S" Measured Parameter (Ca)"' ARo: Critical Boron Con~entration - ARO (Description)

IV Test Results Measured Value (Ca)"'ARo=

l t SL{

(Design -Conditions)

Design Value Ca= 1783 +/- 50 ppm (Design Conditions)

Reference Technical Report NE-1045, Rev. 0 V

FSAR/Tech Spec a:Ca x Ca0 ~ 1000 pcm Acceptance Criteria Reference Technical Specification 4.1 O.A Design Tolerance is met if YES

__ NO Acceptance Criteria is met :

JYES NO VI Comments CIC6 = -7.21 pcm/ppm C6 ° = l(C6)M ARo-Cal: C6 is desigr, value

/l

/1

-""' /'l Prepared By: A-~~

Reviewed By: 'f/jJj)j/j/

(

(/

\\

~*i:--inc;c: c;,r~:. C::+-,n*t-11, P!w~ics Tests Reoort Page 43 of 56

\\.

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

lsothennal Temperature Coefficient - ARO F.eference Pree No / Section:

1-NPT-RX-008 Sequence Step No:

II Bank Positions {Steps)

RCS Temperature (°F): 547 Test Power Level(% f:_P.): 0 Conditions SOA: 227 SOB: 227 Ck. 227 other (specify):

(Design}

CB:

227 CC:

227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): S~i.1 Test Power Level (% F.P.): O Conditions SDA: 227 SOB: 227 Ck. 227 Other (specify):

(ActuaO CB:

227 CC: 227 CD:

~l~

. Below Nuclear Heating Date/lime Test Performed:

\\0 /'d.O /ctS 00~0~

Measured Parameter (ex ISO T

)ARO, Isothermal Temperature (Description}

Coefficient - ARO IV Test Measured Value (ex ISO T

)ARO - -~.,ct pcmf'F Results (Cs=

IIS'L\\

ppm)

Design Value (exTISO)ARO = -Lt.OB °!3.opcmf'F

. (Actual Conditions)

(Cs= r1s4 ppm)

Design Value (Design Conditions)

(ex ISO T

)ARO -

-3.81 :1:3.0 pcml°F (Cs=

1783 ppm)

Reference Technical Report NE-1045, Rev. 0 V

FSAR/COLR a.Tiso~ 3.81* pcmfF Acceptance a./0 P = -1.69 pcmf'F Criteria Reference COLR 2.1.1, Technical Report NE-1045, Rev. 0.

Design Tolerance is met

~ YES

_NO Acceptance Criteria is met :

~YES NO VI Comments *Uncertainty on cx:Tt.1oo = 0.5 pcmfF (

Reference:

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

/),,,., /7 Prepared By:~~~

Reviewed By: 1/d4J/,J/(/

I,.., f

SURRY POWER STATION UNIT 1 CYCLE 14

c...*

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

'Te:st Cescription: Critical Boren Concer.tr.:i'Jc ri

a Ssnk In Reference Proc No / Section:

1-NPT-RX-008

Sequence Step No:

II Bank Positions (Steps)

RCS Temperatur:,e (°F): 547 Test Power Level (% F.P.): O Conditions SDA:

227 SOB:

227 CA:.

227 Other (specify):

(Design)

CB:

0 CC:

227 CD:

227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): SL{,,,

Test Power Level(% F.P.): O Conditions SDA:

227 SOB:

227 CA:.

227 Other (specify):

(ActuaO CB:

0 CC:

227 CD:

'227 Below Nuclear Heating Datemme Test Performed:

10/~{'iS" 05'~45 Measured Parameter (Cst 1e:

Critical Boron Concentration, (Description) 8 Bank In IV Test Results Measured Value (Cs)Me=,ss, f>~O'\\

(Design Conditions)

Design Value Ce=

1586+ACe Prev +/- (10 + 143.0/ja:C81)ppm (Design Conditions)

Ce=ISS'i+/- "30 ppm Reference Technical Repqrt NE-1045, Rev. O V

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

-- YES

__ NO Acceptance Criteria is met :

YES NO VI Comments aC8 = -7.26 pcm/ppm

!:::..Cs Prav =

M (C8) /.'RO - 1783 ppm

,4/) / /) 17/l

~

Prepc:red By: LL i), ~

~

\\.1 Reviewed By:

'/ {,/ II.,/:c_.Vf/

I;

{I

(

N!:-105.'i S1C1!, Ster!'..) P":,*sics Tests ~:eoort Page 45 of 56

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

HZP Boron Worth Coefficient Measurement Reference Pree No / Section:

1-NPT-RX-008 3equence Step No:

II Bank Positions (Steps)

RCS Temperature {°F): 547 Test Power Level(% f:.P.): O Conditions SDA: 227 SOB: 227 CA: 227 Other (specify}:

(Design)

CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): SL\\,.~

Test Power Level(% F.P.): O Conditions SOA: 227 SOB: 227 CA:

227 Other (specify):

(Actual)

CB: moving CC: 227 CD: 227 Below Nuclear Heating Datemme Test Performed:

,o /tC\\ leis d-°3.:' 5 Measured Parameter a:Cs; Boron Worth Coefficient (Description)

IV Test Results Measured Value a:Cs =

-7r \\"1 P'-"" /Ppm.

Design Value cxC8 =

-7.26 :1: 0.73 pcm/ppm (Design Conditions)

Reference Technical Report NE-1045, Rev. 0 V

FSAR!fech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met

../ YES

__ NO Acceptance Criteria is met :

7YES NO VI Comments

,,,/1

/J/717 Prepared By: il.,(l_"""°)'\\-LLJL_

Reviewed By:

~A#-/__il!/

/ "'-/ {I

\\

~E-1055 S1C14 Startup Physics Tests Report Pa~e 46 of 56 I"

(;

(.... _/

~-.J

- I

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

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

1-N?T-RX-ODB Sequence Step No:

II Bank Positions (Steps)

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

227 SDB:

227 CA:

227 Other (specify):

(Design)

CB: moving CC:

227 CD:

227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): SL.fi. I Test Power Level (% F.P.): a Conditions SDA:

227 SDB:

227 CA:

227 Other (specify):

(Actual)

CB: moving CC:

227 CD:

227 Below Nuclear Heating Datemme Test Performed:

,o/~/95 01: 3Co Measured Parameter I REF.

B I Integral Worth Of Control Bank B, (Description)

All Other Rods Out IV Test Measured Value I REF_

B It.\\\\~ pc.m Results Design Value 16 REF= 1430 +/- 143 pcm (Design Conditions)

Reference Technical Report NE-1045, Rev. 0 If Design Tolerance is exceeded, SNSOC shall V

FSAR!rech Spec 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

___::!__ YES

__ NO Acceptance Criteria is met :

J YES NO VI Comments

/)~

f/"/

Prepared By: ~

~Q.....A-Reviewed By: if}(l(#(J/

I V 1 NE-1055 S1C}4 StArtun ?h~sics Tests Re~ort PAge 47 of 56

I I I

i !

I I l

I i

I I I

I !.

I I !

.... ~.. ~

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Control Bank D Worth Measurement. Rod Swap

.Reference Proc No./ Section:

1-NFT-RX-OOB Sequence Step No:

II Bank Positions (Steps)

RCS Temperature ('1F): 547 Test*

Power Level (% F.P.): O Conditions SDA:

227 SOB:

227 CA:

227 Other (specify):

(Design)

CB: moving cc:

227 CD: moving Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): s+7!1 Test Power Level(% F.P.): O Conditions SDA:

227 SDB:

227 CA:.

227 Other (specify):

(Actual)

CB: moving CC:

227 CD: moving Below Nuclear Heating Datemme Test Perfonned:

10 /~/,s, oSo'l,.,,

Measured Parameter

. 1ls; Integral Worth of Control Bank 0, (Description)

Rod Swap IV Measured Value

. lo RS= {O#, (

(Adjusted Measured ~ritical

'Test Reference Bank Position= /3'tr; steps)

Results Design Va1u*e (Actual Conditions) lo Rs= If Jz, C, (Adjusted Measured Critical*

Reference Bank Position = tn.s steps)

Design Value 10 Rs= 1109 ::1: 166 pcm (Design Conditions)

(Critical Reference 3ank Position= 154 steps)

Reference Technical Report NE-1045, Rev. 0, VEP-FRD-3SA FSAR/Tech -Spec If Design Tolerance is* exceeded, SNSOC shall V

evaluate impact o~ test result on safety analysis.

..!...::ceptance SNSOC may specify that additional testing Criteria be performed.

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

_.,_YES

__ NO Acceptance Criteria is met :

/

YES NO VI

=:omments 4

/

//1~{

-:-e pa red By: _1""'"c"'-"v

,,_...;...v...;...,vV....;..>~_._~_-_

Reviewed By: ~

..2./!.J.

NE-1055 S1Cl4 Start,ip Physics Tests Report Page 43 cf 56

't. !

. -~-. -

SURRY POWER STATION UNIT 1 CYCLE 14 S 7" ARTUP PHYSICS TEST RESULTS P.ND EVALUATION SHEET I

Test

Description:

Control Bank C Worth Measurement, Rod Swap Reference Proc No I Section:

1-NPT-RX-OOB Sequence Step No:

II Bank Positions (Steps}

RCS Temperature -(°F): 547 Test Power Level(% F.P.): o Conditions SDA: 227 SOB: 221 CA:.

227 Other (specify):

(Design)

CB: moving CC: moving CD:

227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature {°F): S-4-7. G, Test Power Level(% F.P.): O Conditions SDA: 227 SOB: 227 CA:.

227 Other (specify):

(Actual)

CB: moving CC: moving CD: 227 Below Nuclear Heating Date/Time Test Performed:

lo/L?/'15', c61l'i Measured Parameter le RS; Integral Worth of Control Bank C, (Description)

Rod Swap IV Measured Value I RS_

e -

1z-r.;

(Adjusted Measured Critical Test.

Reference Bank Position=,os steps)

Results Design Value (Actual Conditions)

I RS_

e -

Sc,3. G, (Adjusted Measured Critic;al Reference Bank Position = 'io.r steps)

Design Value (Design Conditions}

le Rs= 800 :1: 120 pcm (Critical Reference Bank Position= 104 steps)

Reference Technical Report NE-1045, Rev. 0, VEP-FRD-36A FSAR/Tech $pee If Design Tolerance is exceeded, SNSOC shall V

evaluate impact of test result on safety analysis.

Acceptance SN SOC may specify that additional testing Criteria be performed.

Reference VEP-FRD-3SA Design Tolerance is met

~YES

__ NO Acceptance Criteria is met :

,I' YES NO VI Comments Prepared By:

,d-.c_ / C/xi.../ {-v Reviewed By: ~~

j./

.,.;t

\\,*t'"-1f"\\:;::: ~ir,,

C'... --+-,,-.. [l!...,.r~*,..c Tnc-~C' Pr,r>il"'"'IT"'t-P:;o~

49 nf s,;

/ *

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

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

SURRY POWER STATION UNIT 1 CYCLE 14

~~.

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

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

1-NPT-RX-008 Sequence Step No:

II Bank Positions {Steps)

RCS Temperature {°F): 547.

Test Power Level{% F.P.): O Conditions SDA: 221 SDB: 221 CA: moving Other {specify):

(Design)

CB: moving cc: 227 CD:

227 Below Nuclear Heating Ill Bank Positions {Steps)

RCS Temperature fF): S-4-7. ~

Test Power Level{% F.P.): o Conditions SDA: 227 SDB: 227 CA: moving Other (specify):

(ActuaQ CB: moving CC: 227 CD:

227 Below Nuclear Heating Datemme Test Performed:

.,c/z,A~,, O~S'J Measured Parameter IA Rs; Integral Worth of Control Bank A, (Description)

Rod Swap IV Measured Value JARS: 2'°.i (Adjusted Measured Critical Test Reference Bank Position = ~-i steps)

Results*

Design Value (Actual Conditions)

IA Rs= z,G...4-(Adjusted Measured Critical.

Reference Bank Position= '9-5.i steps)

Design Value

~. I (Design Conditions) 1/s=:: 285 :1: 100 pcm (Critical Reference.Bank Position= 53 steps)

Reference Technical Report NE-1045, Rev. 0, VEP-FRD-3SA 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.

~YES

_NO Acceptance Criteria is met :

YES NO VI Comments

. Prepared By: ~ c/¥ NE-1055 S1Cl4 ~tartup Physics Tests Report Page SO of 56

..,... :.. ~ -*

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

Shutdown Bank B Worth Measurement. Rod Swap Reference Proc No I Section:

1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps)

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

227 SOB: moving CA:

227 Other (specify):

(Design)

CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature (°F): £"4-7-"2-Test Power Level(% F.P.): O Conditions SDA:

227 SOB: moving CA:

227 Other (specify):

(ActuaO CB: moving cc: 227 CD:

227 Below Nuclear Heating Date/Time Test Performed:

10/20('1~ J 1014-Measured Parameter Isa RS; lnteg~I Worth of Shutdown Bank B, (Description)

. Rod Swap 10:S. I-IV Measured Value Isa RS=~. (Adjusted Measured Critical Test

, to/k/;<

Reference Bank Position= /4-/. 6 steps)

Results D~.sign Value ll'Jo.Z-(Actual Conditions)

Isa RS= +/3/. L (Adjusted Measured Critical R'V ~

s Reference Bank Position= /4/.G"steps)

Design Value (Design Conditions) lsls= 1130 :t: 170 pcm (Critical Reference Bank Position= 158 steps)

Reference Technical Report NE-1045, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V

evaluate impact of test result on safety analysis..

Acceptance SN SOC may specify that additional-testing Criteria be performed.

Reference VEP-FRD-36A Design Tolerance is met

~YES

__ NO Acceptance Criteria is met :

..,,, YES NO VI Comments Prep3red By: _;._~..:...~~-C/v?....;;....L~/L Reviewed By: ~- 2,U

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

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

1-NPT-RX-OOB Sequence Step No:

II Bank Positions (Steps)

-i RCS Temperature fF): 547 Test Power Level(% F.P.}: O Conditions SDA: moving SOB: 221 CA:

227 Other (specify):

(Design)

CB: moving CC:

227 CD:

227 Below Nuclear Heating Ill Bank Positions (Steps)

RCS Temperature {°F): S'+7. 2:-

Test Power Level(% F.P.): O Conditions SDA: moving SOB: 227 Ck.

227 Other (specify):

(Actual)

CB: moving cc: 221 CD:

227 Below Nuclear Heating Date/Time Test Performed:

10 /;;:.o/e;s.,

/ 7-/S Measured Parameter ls.a.RS; Integral ~orth of Shutdown Bank A, (Description)

Rod Swap IV Measured Value ISARS= /053.? (Adjusted Measured Critical Test Reference Bank Position= l'f-1. z. steps)

Results Design Value (Actual Conditions)

I RS_ /o7~-} (Adjusted Measured Critical SA Reference Bank Position = /fl. Zsteps)

Design Value (Design Conditions)

ISARS= 1076 +/- 161 pcm (Critical Reference Bank Position= 148 steps)

Reference Technical Report NE-1045, P~'-'* 0, VEP-FRD-35A FSAR/Tech Spec If Design Tolerance is _exceeded, SNSOC shall

v evaluate impact of tes*t *result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be perionned.

Reference VEP-FRD-36A Design Tolerance is met

~YES

__ NO Acceptance Criteria is met :

,/ YES NO VI Comments Prepared By: /Z--1: v¥ Reviewed By: ~g.LJ

(/

~~-]055 S1C1~ Startup Physics Tests Report Page 52 of 56

~

SURRY POWER STATION UNIT 1 CYCLE 14 s-1ARTUP PHYSICS TEST RESULTS Al"f[, F\\ALUATION SHEET I

Test

Description:

Total Rod Worth, Rod Swap Reference Proc No / Section:

1-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps)

RCS Temperature (°F): 547 Test Power Level (% F.P.): O *

Conditions SDA: moving SDB: moving Ck. moving Other (specify):

(Design)

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

RCS Temperature (°F): 5f1. J Test

~

,v, -

~

lu~1/

Power Level(% F.P.): a Conditions SDA: moving SOB: moving Ck moving Other (specify):

(Actuaij CB: moving CC: moving CD: movipg Below Nuclear Heating Datemme Test Performed:

io I 'Z-0 /o,,; J Ol',;b Measured Parameter lrcrta1; Integral Worth of All Banks, (Description)

Rod Swap IV Measured Value lrctai== S553. i Test Results. Design Value (Actual Conditions) lrcta1=

5S31

I

. Design Value (Design Conditions) lrcmr 5830 +/- 583 pcm Reference Technical Report NE-1045, Rev. 0, VEP-FRD-36A FSAR!f ech Spec If Design Tol~rance is e~ceeded, SNSOC st")all V

evaluate impact of test result on safety analysis.

Acceptance Additional testing must be performed.

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

_L_YES

__ NO Acceptance Criteri9 is met :

YES NO VI Comments Prepared B;': /~ VJ{/!-

Reviewed By: ~

g/LJ Page 53 of 56

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

MID Flux Map - At Power Reference Proc No I Section:

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

II Bank Positions (Steps)

RCS Temperature (""F): T REF :1: 1

-Tes'l Power Level(% F.P.): s 30 Conditions SDA:

227 SOB: 227 CA:

227 Other (specify):

(Design)

CB:

227 CC:

CD:

Must have ~ 38 thimbles-.

Ill Bank Positions (Steps)

RCS Temperature (°F):,-n:/

Test Power Level(% F.P.):.2 7, 'Z-1, Conditions SDA: 227 SOB: 227 CA:

227 Other (specify):

(Actual)

CB:

227 CC: ;i..z.7 CD: /'-b

,//'.).. /&h(6 {e J Datemme Test Performed:

/ oP-z/9S-02..S"1 I

Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%D1FF Channel Factor Channel Quadrant IV (Description)

(M-P)/P Fti.H(N)

Factor F0 (Z)

Power Tilt Test Measured

-S';#f]o r'~,9

/, 417'1

,;JI O '( :s--

t,c,o7t:.

Results Value 8,3f, /1£.9

/,/27 tf (0,?'-7.)

Design V~lue :t10% for P1 :t0.9 (Design

t15% for Pi<0.9 NIA NIA s 1.02 Conditions)

(P1 = assy power)_

Reference WCAf'-7905, Rev. 1 None None WCAf'-7905, Rev.1 V

FSAR/COLR None F ~ H(N)' s 1.55(1+0.3(1-P)) Fc(Z)s4.64"K(Z)

None Acceptance Criteria Reference None COLR 2.4 COLR2.3 None Design Tolerance is met..

~YES

__ NO Acceptance Criteria is met :

_x.. YES NO VI

As required Comments ** Must have at least 16 thimbles for quarter core maps for m:.ilti-point calibrations

!;i,ls FLl.H(N) Limit is applicable to all assemblies, except for the LOPAR assemblies loaded into locations L-2, E-2, M-3, D-3, N-4, C-4, P-5, B-5, H-8, P-11, B-11, N-12, C-12, M-13, D-13, L-14, and E-14.

The L.in:iit for these locations is: F Ll. H(N)s:1.346(1 +0.3(1-P))

~I~

rflf. ( J/JJ~

Prepared B:/

~~ (l Reviewed By:

I I I 1 I// - "'

~E-1053 SlCl~ Sta~~c~ Phvsics Tests Report Page 54 of 56

.~: I

SURRY POWER STATI.ON UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

MID Flux Map - At Power Reference Proc No / Section:

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

II Bank Positions (Steps)

RCS Temperature ('"'F): T REF: 1 Test Power Level (% F.P.):50 s P s 75.

Conditions SDA:

227 SDB: '227 Ck.

227 Other (specify):

(Design)

CB:

227 CC:

'227 CD:

Must have::!': 38 thimbles**

Ill Bank Positions (Steps)

RCS Temperature (°F): --rn; Test Power Level (% F.P.): 5'-1. I °/.

Conditions SDA:

227 SDB: 227 Ck.

227 Other (specify):

(Actual)

CB:

227 CC:.. 227 CD:

IS I Datemme Test Performed:

Jo/-:z..'-1/is oz.:ot

~3 -f'1imhl(:.s Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%DIFF Channel Factor Channel Quadrant IV (Description)

(M-P)/P F!::.H(N)

Factor F0 (Z)

Power Tilt Test Measured

-3,2. "/..

P'?' o.'t

l,o/r,S I. 'ti/ I,

/.oot,5

~ 1. 7. *!.,

p~ 0,"I

Results Value

'*'" I, #=

( (), l,,; CJ(.)

Design Value t10% for P1 o1:0.9 (Design t 15% for Pi<0,9 NIA

NIA

~ 1.02 Conditions)

(P1 = assy power)

Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 V

FSAR/COLR None FAH(N)' ~1.56(1+0.3(1-P)) Fc(Z) ~2.32/P"K(Z)

None Acceptance Criteria Reference None COLR 2.4 COLR 2.3 None Design Tolerance :s met

--2L*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 calibrations

This Ft:.. H(N) Limit is applicable to all assemblies, except for the LO PAR assemblies loaded into locations L-2, E-2, M-3, D-3, *N-4, C-4, P-5, 8-5, H-8, P-11, 8-11, N-12,*c-12, M-13, D-13, L-14, and E-14.

The Lir'lit for these locations is: FAH(N)~1.346(1+0.3(1-P))

Reviewed By: f".l..Q::n--lL.~

r, - -

... -~

SURRY POWER STATION UNIT 1 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

Test

Description:

MID Flux Map - At Power Reference Pree No I Section:

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

II Bank Positions (Steps)

RCS Temperature (""F): T REF :1: 1 Test Power Level (% F.P.):95 ~ P ~ 100 Conditions SDA: 227 SDB: 227 CA:

227 Other (specify):

(Design)

CB:

227 CC: 227 CD:

Must have :i!: 38 thimbles-Ill Bank Positions (Steps)

RCS Temperature fF):

S73 Test Power Level (% F.P.): 11.,,,_

Conditions SDA: 227 SDB: 227 CA:

227 Other (specify):

(Actual)

CB:

227 CC: 227 CD: 227 l\\ 0 -\\-h, ""'o \\e.!,

Datemme Test Performed:

11h,/115 I 0./1 - 1$:J l(

Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive In.core Parameter Power%D1FF Channel Factor Channel Quadrant l\\l (Description).

{M-P)/P

Ff>.H{N)

Factor F0 {Z)

Power TIit Test Measured

-2. '\\ % P~.CJc

/.'/'!,2. l')

\\. oof f Results

. Value 7.L# '" r~.qo

/.,% JO l,.')

/. 77g

{ o. "11.)

Design Value :10% for P1 i0.9 (Design

15% for P;<0.9 NIA NIA

t. 1.02 Conditions)

(P; = assy power)

Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 V

FSAR/COLR None FAH(N)1 ~1.56(1+0.3(1-P)) Fc(Z)~2.32/P"K(Z)

None Acceptance Criteria Reference None COLR 2.4 COLR2.3 None 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 calibrations

Tliis Ft:.. H(N) Limit is applicable to all assemblies, except for the LO PAR assemblies loaded into locations L-2, E-2, M-3, D-3, N-4, C-4, P-5, B-5, H-8, P-11, B-11, N-12, C-12, M-13, 0-13, L-14, and E-14.

(fl £..:....._+

J.~r.o The Limit for these IOC9tions is: FAH(N)~1.346(1+0.3~ C...U l~,. ~ 'i'1 -

Prepared By:

~,f A J ()j Reviewe~* \\_ ~ -~ a__c J

l D

j

"'r::-10')c; SJr. 1.'.. St:i:-ten.Phvsics Tests Reoort Pa.;e 56 of 56

'- l

ML18152A057

Text

Dear Mr. Ebneter:

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