ML092230234

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Cycle 23 Startup Physics Tests Report
ML092230234
Person / Time
Site: Surry Dominion icon.png
Issue date: 08/10/2009
From: Funderburk C
Dominion, Virginia Electric & Power Co (VEPCO)
To:
Region 2 Administrator
References
09-527 NE-1578, Rev 0
Download: ML092230234 (53)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 10, 2009 United States Nuclear Regulatory Commission Regional Administrator - Region II Sam Nunn Atlanta Federal Center Suite 23 T85 61 Forsyth Street, SW Atlanta, Georgia 30303-8931 Serial No.:

09-527 NLOSlvlh Docket No.:

50-280 License No.: DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 CYCLE 23 STARTUP PHYSICS TESTS REPORT As required by Surry Technical Specification 6.6.A.1, enclosed is the Virginia Electric and Power Company (Dominion) Technical Report NE-1578, Revision 0, entitled "Surry Unit 1 Cycle 23 Startup Physics Tests Report."

This report summarizes the results of the physics testing program performed following initial criticality of Cycle 23 on May 11, 2009.

The results of the physics tests were within the applicable Technical Specification limits.

If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.

Very truly yours, C. L. Funderburk, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None

cc:

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 16 E15 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Resident Inspector Surry Power Station Serial No.09-527 Surry 1 Cycle 23 Startup Physics Tests Report, Rev. 0 Page 2 of2

Technical Report Cover Sheet Page 1 of 51.

Rev. 0 NDCM-3.11 TECHNICAL REPORT No. NE-1578 Rev. 0.

SURRY UNIT 1 CYCLE 23 STARTUP PHYSICS TESTS REPORT Surry Power Station Unit 1 Nuclear Analysis and Fuel NUCLEAR ENGINEERING DOMINION July 2009 t/q/o~

Date Or IZJr?/Q~

Date Approved By:

7/2(feR

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  • ~%e AL Approved By:

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Reviewed By: ---t-t--+--I"'----------j!>"--- 07/oB/oO, Date Prepared By: /L,-<4....:l!b.4~,,-=,-'--,----

j7 J. D. Gill Key Words: S1C23, SPTR (June2006)

CLASSIFICATIONIDISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion (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 CaMPANY 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 ofthe 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.

S1C23 Startup Physics Tests Report Page 2 of 51

TABLE OF CONTENTS ClassificationIDisclaimer...........................*...*...............................................................................2 Table of Contents 3

List of Tables.,.*..*..*..**..*.............*.........*.*.*...**.*.***.*.........*.................*...*.*...*.*..*...*...*.**.**...*...........4 List of Figures.................................*.................._

5 Preface 7

Section 1 -- Introduction and Summary 9

Section:2 -

Control Rod Drop Time Measurements 17 Section 3 -

Control Rod BankWorth Measurements 21 Section 4 -

Boron Endpoint and Worth Measurements 27 Section 5 -

Temperature Coefficient Measurement 31 Section 6 -- Power Distribution Measurements.._

33 Section7 -- Conclusions 41 Section 8 -- References 43 Appendix -

Startup Physics Test Summary Sheets

.45 NE-1578 Rev. 0 S1C23 StartupPhysicsTests Report Page 3 of51

LIST OF TABLES Table 1.1

- Chronolo~ of Tests 12 Table 2.1

- Hot Rod Drop Time Summary 18 Table 3.1

- Control Rod Bank Worth Summary 23 Table 4.1

- Boron Endpoints Summary 28 Table 4.2

- Boron Worth. Coefficient 29 Table 5.1 - Isothermal Temperature Coefficient Summary 32 Table 6.1 - Incore Flux Map Summary 35 Table 6.2 - Comparison ofMeasured Power Distribution Parameters with their Core Operatmg Limits 36 Table 7.1 - Startup Physics Testing Results Summary 42 NE-lS78 Rev. 0 S1C23 StartupPhysics Tests Report Page 4 of 51

LIST OF FIGURES Figu.re 1.1 - CoreLoadingMap 13 Figure 1.2 - Beginning of Cycle Fuel Assembly Burnups (GWDIMTU) 14 Figure 1.3 - Available Ineore Moveable Detector Locations 15 Figuret.4 - Control Rod Locations 16 Figure 2.1 - Typical Rod Drop Trace 19 Figure 2.2 - Rod Drop Time - Hot Full Flow Conditions 20 Figure3.1 - Control Bank B Integral Rod Worth - HZP 24 Figure 3.2 - Control Bank B Differential Rod Worth - HZP 25 Figure 6.1 - Assemblywise Power Distribution 26.1% Power 37 Figure 6.2 - Assemblywise Power Distribution 67.5% Power 38 Figure 6.3 - Assemblywise Power Distribution 99.89% Power 39 NE-1578Rev. 0 S1C23 Startup Physics TestsReport Page 5 of 51

NE-1578 Rev. 0 This page is intentionally left blank.

S1C23 StartupPhysics Tests Report Page 6 of51

PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 1, Cycle 23 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 testing techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at 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 ofthe test results with design predictions, and an evaluation oftheresults.

The Surry Unit I, Cycle 23 startup physics tests 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 results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer! reviewer initials.

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

The entries for the design values were based on calculations performed by Dominion's Nuclear Analysis and Fuel Group.

The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits.

NE-1578 Rev. 0 SlC23 Startup Physics Tests Report Page 7 ofSl

NE-1578 Rev. 0 This page is intentionally left blank.

SlC23 Startup Physics TestsReport Page 8 of51

SECTION1-INTRODUCTION AND

SUMMARY

On 19 April 2009, Unit No.1 of Surry ~ower Station completed Cycle 22 and began refueling [Ret 1]. During this refueling, 65 ofthe 157 fuel assemblies in the core were replaced with 61 :fresh Batch 25 assemblies and four twice-burned S1I22B assemblies. The Cycle 23 core consists of 12 sub-batches of fuel: four fresh batches (SI/25A, Sl/25B, S1I25C, and SI/25D),

four once-burned batches (SI124A, S1I24B, S1I24C, and SI/24D), three twice-burned batches (S1I23A, S1I23D, and S1I23E) last irradiated in SIC22, and one twice-burned batch last irradiated in Sle2l (S1/22B). All batches are ofthe SIFIP+Z2fuel type [Ref 1, Ref. 8].

The Westinghouse SIFIP+Z2 fuel assembly design incorporates ZIRLO fuel cladding, intermediate grids, guide tubes, instrumentation tubes, and debris resistance features that arepart of the Westinghouse PERFORMANCE+ design. SIFIP+Z2 assemblies are of the same basic design as SIFIP+Z, but use a slightly longer (0.2 inch) fuel pin and bottom end plug to enhance resistance to fretting wear, along with other small dimensional changes [Ref. 1].

This cycle uses only Westinghouse's Integral Fuel Burnable Absorber (IFBA) fuel product. All physical changes for IFBA are internal to the fuel rod cladding, with no apparent difference from discrete BP fuel assemblies in any external features. The IFBA design involves the application of a thin (0.0003125 inch) coating of ZrB2 on the fuel pellet surface during fabrication. Pellets with the IFBA coating.are placed in specific symmetric patterns in each fresh assembly. typically affecting from 16 to 148 rods per assembly. The top and bottom 6 inches of the fuel pellet stack in the IFBA rods will contain pellets that have no IFBA coating, and have a hole in the center (annular). This additional void space helps accommodate the helium gas that accumulates from neutron absorption in Zr~. IFBA rods generate more internal gas during operation because neutron absorption in the ZrB2 coating creates helium gas in addition to the fission gas created during irradiation ofthe fuel. Therefore, the initial pressure is setlower so the internal pressure early in lifetime may be lower [Ref. 5].

NE-1578 Rev. 0 SIC23 Startup Physics Tests Report Page 9 ofSl

Note that there are no thimble plugging devices or secondary sources inserted in Surry Unit 1 for this cycle. The cycle design report [Ref I] provides a more detailed description of the Cycle 23 core.

The S1C23 full core loading plan [Ref. 8 and Ref. 11] is given in Figure 1.1 and the beginning of cycle fuel assemblyburnups [Ref. 6] are given in Figure 1.2. The available incore moveable detector locations used for the flux map analyses [Ref. 7] are identified in Figure 1.3.

Figure 1.4 identifies the location and numberofcontrol rods in the Cycle 23 core [Ref. 1].

According to the Startup Physics logs, the Cycle 23 core achieved initial criticality on 11 May 2009 at 01:02 [Ref. 14].

Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. This cycle used the FTI Reactivity Measurement and Analysis System (RMAS) to perform startup physics testing. Note that RMAS v.6 [Ref. 9] was used for S1C23 Startup Physics Testing. The tests performed are the same as in previous cycles.

A summary ofthe test results follows.

The measured drop time of each control rod was within the 2.4 second Technical Specification [Ref. 4] limit, as well as the 1.93 second administrative limit [Ref. 10].

Individual control rod bank worths were measured using the rod swap technique [Ref. 2].

For the purpose of this test, a bank. was defined as 'fully inserted' when it was 2 steps off the bottom of the core [Ref. 13]. The sum of the individual measured control rod bank worths was within -2.3% of the design prediction. The reference bank (Control Bank: B) worth was within -

3.2% of its design prediction (corresponding to 41.8 pcm).

The other control rod banks were within +/-4.2% (-4.2% was recorded for Shutdown Bank B, which corresponds to a difference of 48.9 pcm) of the design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within -fJ.7 pcm of the design prediction. These results are within the design tolerances of +/-15% for individual banks worth more than 600 pcm

(+/-lO% for the reference bank worth), +/-100 pcm for individual banks worth 600 pcm or less, and

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

NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 10 ofSl

Measured critical boron concentrations for two control bank configurations (ARO and B-bank in) were within +22 ppm of the design predictions. These results were within the design tolerances and also met the Technical Specification [Ref. 4] criterion that the overall core reactivity balance shall be within +/-1% &ik: of the design prediction.

The boron worth coefficient measurement was within -1.6% of the design prediction, which is within the design tolerance of +/-10%.

The measured isothermal temperature coefficient (ITC) for the all-rods-out (ARO) configuration was within -0.420 pcmfF ofthe design prediction. This result is within the design tolerance of +/-2.0 pcmf'F.

Core power distributions were within established design tolerances.

The measured assembly power distributions were within +/-5.1% of the design predictions, where a +5.1%

maximum difference occurred in the 26.1% power map in assembly B7.

The heat flux hot channel factors, FQ(z), and enthalpy rise hot channel factors, F~, were within the limits of the COLR [Ref.B].

All power flux maps were within the maximum incore power tilt design tolerance of2% (QPTR~1.02).

The total RCS Flow was successfully verified as being greater than 273000 gpm as required by Surry Technical Specifications [Ref. 4].

The total RCS Flow was measured as 286190 gpm, 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 ofthis report.

NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 11 of Sl

Table 1.1 SURRY UNIT I-CYCLE23 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 05110/09 1057 HSD I-NPT-RX-014 Reactivity Computer Checkout 05/11/09 0158 HZP I-NPT-RX-008 Boron Endpoint - ARO 05111/09 0158 HZP 1-NPT-RX-008 Zero Power Testing Range 05111/09 0158 HZP I-NPT-RX-008 Boron Worth Coefficient 05/11/09 0158 HZP I-NPT-RX-008 Temperature Coefficient - ARO 05/11/09 0247 HZP I-NPT-RX-008 Bank B Worth 05/11/09 0331 HZP I-NPT-RX-008 Boron Endpoint - B in 05111/09 0547 HZP I-NPT-RX-008 Bank A Worth - Rod Swap 05/11109 0550 HZP I-NPT-RX-008 Bank SA Worth - Rod Swap 05/11/09 0550 HZP I-NPT-RX-008 Bank C Worth - Rod Swap 05/11/09 0550 HZP I-NPT-RX-008 Bank D Worth - Rod Swap 05/11109 0550 HZP 1-NPT-RX-008 Bank SB Worth - Rod Swap 05111/09 0550 HZP I-NPT-RX-008 Total Rod Worth 05/11/09 0550 HZP I-NPT-RX-008 FluxMap-less than 30% Power 05/11/09 2024 26.10010 I-NPT-RX-Q02 Peaking Factor Verification I-NPT-RX-008

& Power Range Calibration I-NPT-RX-005 Flux Map - 65% - 75% Power 05/13/09 0246 67.50%

1-NPT-RX-002 Peaking Factor Verification I-NPT-RX-008

& Power Range Calibration I-NPT-RX-Q05 Flux Map - 95% - 100% Power 05/15/09 1638 99.89%

I-NPT-RX-002 Peaking Factor Verification I-NPT-RX-008

& Power Range Calibration I-NPT-RX-005 RCS Flow Measurement 06/01109 1400 HFP I-NPT-RX-009 NE-1578 Rev. 0 S1C23Startup Physics Tests Report Page 12 of51

Figure 1.1 SURRY UNIT 1-CYCLE 23 CORE LOADING MAP VEP-NES-l'fl\\!!'

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Figure 1.2 SURRYUNIT1-CYCLE 23 BEGINNING OFCYCLE FUEL ASSEMBLY BURNUPS (GWDIMTU)

R p

11 M

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8 I 40.711 0.001 23.74/ 22.641 22.231 23.081 23.181 0.001 23.181 23.181 22.141 22.791 23.581 O.OO{ 40.871 I 40.791 0.001 23.441 22.781 22.111 23.141 23.111 0.001 23.111 23.141 22.111 22.181 23.43/

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I 37.611 0.001 0.001 19.161 0.001 18.571 0.001 23.271 0.001 lB.BBI 0.001 18.S'!1 0.001 0.001 37.421 1 31.641 0.001 0.001 19.041 0.001 18.651 0.001 23.181 0.001 lB.791 0.001 19.031 0.001 0.001 31.551 10 11 12 13 15 1 40.751 O.OOt 2B.131 23.701 21.981 19.141 2~.Blt 18.691 22.291 23.651 23.491 0.001 41.111 I 40.791 0.001 23.241 23.891 22.151 18.751 23.211 18.651 22.181 23.711 23.231 0.001 40.811 I 40.151 0.001 0.001 19.671 23.511 0.001 22.231 0.001 23.591 19.971 0.001 0.001 40.061 I '10.121 0.001 0.001 19.781 23.751 0.001 22.161 0.001 23.791 19.781 0.001 0.001 40.131 I 41.481 0.001 0.001 23.101 19.091 22.641 19.001 23.601 0.001 0.001 41.681 I 41.661 0.001 0.001 23.251 19.011 22.791 19.031 23.261 0.001 0.001 41.731 I 41.131 0.001 0.001 0.001 23.561 0.001 0.001 0.001 41.581 I 41.571 0.001 0.001 0.001 23.461 0.001 0.001 0.001 41.551 I 39.501 40.80(

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Figure 1.3 SURRY UNIT 1 - CYCLE 23 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R

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9 10 11 12 13 14 15 NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 15 of51

Figure 1.4 SURRY UNIT 1 - CYCLE 23 CONTROL ROD LOCATIONS R

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9 10 11 12 13 14 15 D = Control Bank D C =Control Bank C B =Control Bank B A = Control Bank A SB = Shutdown Bank SB SA = Shutdown Bank SA NE-1578 Rev. 0 S1C23 Startup Physics TestsReport Page 16of 51

SECTION 2 -

CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured in hot shutdown with three reactor coolant pumps in operation (full flow) and with Tave greater than 530 OF as per I-NPT-RX-014.

'Ibis verified that the time to entry of a rod into the dashpot region was less than or equal to the maximum allowed by Technical Specification 3.12.C.l [Ref. 4].

Surry Unit 1 Cycle 23 used the rod drop test computer (RDTC) in conjunction with the Computer Enhanced Rod Position Indication (CERPI) system.

The CERPI system equipment replaced the Individual Rod Position Indication (IRPI) system.

The rod drop times were measured by withdrawing. all banks to their fully withdrawn position and dropping all of the 48 control rods by opening the reactor trip breakers. This allowed the rods to drop into the core as they would during a plant trip.

The current methodology acquires data using the secondary RPI coil terminals (/3 & /4) on the CERPI racks for each rod.

Data is immediately saved to the rod drop test computer (ROTC) which computes the rod drop time automatically.

Original data is also saved as an ASCII file and burned to a CD-R. Further details about the ROTC can be found in [Ref. 12].

A typical rod drop trace for S1C23 is shown in Figure 2.1. 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.l2.C.1 [Ref. 4] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. These test results satisfied this technical specification limit as well as the administrative limit [Ref. 10] of 1.93 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region.

NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 17 of51

Table 2.1 SURRY UNIT 1 - CYCLE 23 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME P-8 1.39 sec.

N-7, L-5, P-6, 1.26 sec 1.29 sec.

K-4, M-12 NE-1578 Rev.0 S1C23 Startup Physics TestsReport Page 18 of 51

Figure 2.1 SURRYUNIT 1 - CYCLE 23 STARTUP PHYSICS TESTS TYPICAL RODDROP TRACE I

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Figure 2.2 SURRY UNIT 1 - CYCLE 23 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R

p N

ML K

J H

G F

E D

C B

A 1.28 1.27 1.28 1.29 1.29 1.27 1.26 1.28 1.31 1.26 1.29 1.26 1.27 1.29 1.27 1.30 1.27 1.37 I,

1.26 1.32 1.29 1.29 1.39 1.29 1.38 1.31 1.32 1.28 1.32 1.28 1.28 1.28 1.27 1.27 1.31 1.30 1.29 1.27 1.28 1.26 1.28 1.28 1.30 1.29 1.29 1.31 1.27 1.33 IX.xxI

> Rod drop time to dashpot entry (sec.)

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13 14 15 NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 20 ofSl

SECTION 3 -

CONTROL ROD BANKWORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique [Ref. 2].

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

For Cycle 23, Control Bank B was.used as the reference bank. Surry 1 targeted a dilution rate of 1100 pcmIhr for the reference bank measurement.

During the N1C19 startup physics testing campaign, a control rod became stuck 011 the bottom eventually forcing a reactor trip to fix the problem. A theorized potential cause of the stuck rod issue was the presence of debris near the upper core plate interfering with the rod grippers when the control rods were manually inserted to the fully inserted position of 0 steps withdrawn. A possible solution to this issue for startup physics testing was to avoid requiring control rods to be manually inserted to 0 steps. To accomplish this, an evaluation ofthe startup physics testing process was performed [Ref. 13], concluding that the definition of fully inserted for control rod positions used in startup physics testing could be changed from 0 stepswithdrawn to a range of 0 to 2 steps withdrawn. The S1C23 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

After completion ofthe reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor near critical and the reference bank near its full insertion. Initial statepoint data (core reactivity and moderator temperature) for the rod swap maneuver were next obtained with the reference bank at its fully inserted position and all other banks fully withdrawn.

Test bank swaps proceed in sequential order fromthe bank with the smallest worth to the bank with the largest worth. The second test bank should have a predicted worth higher than the first bank in order to ensure the first bank will be moved fully out before the second bank:is fully NE*1578 Rev. 0 S1C23 Startup Physics Tests Report Page 21 of51

inserted.

The rod swap maneuver was performed by withdrawing the previous test bank (or reference bank: for the first maneuver) several steps and then inserting the next test bank to balance the reactivity of the reference bank withdrawal.

This sequence was repeated until the previous test bank was fully withdrawn and the current test bank was nearly inserted. The next step was to swap the rest ofthe test bank in by balancing the reactivity with the withdrawal ofthe reference bank, until the test bank was fully inserted and the reference bank was positioned such that the core was near the initial statepoint condition. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth ofthe test bank.

The core reactivity, moderator temperature, and differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver was repeated for all test banks. Note that after the final test bank:was fully inserted, the test bank was swapped with the reference bank until the reference bank was fully inserted and the last test bank was fully withdrawn.

Here the final statepoint data for the rod swap maneuver was obtained (core reactivity and moderator temperature) in order to verify the reactivity drift was within procedural limitations for the rod swap test.

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

As shown in this table and the Startup Physics Test Summary Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance of +/-10% for the reference bank, +/-15% for test banks ofworth greater than 600.pcm, and +/-100 pcm for test banks of worth less than or equal to 600 pern. The sum of the individual measured rod bank worths was within -2.3% ofthe design prediction. This is well within the design tolerance of +/-10% for the sum ofthe 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 [Ref. 1] andthe measured.

data areplotted together in order to illustrate their agreement. In summary, the measured rod worth values were found to be satisfactory.

NE*1578Rev. 0 SlC23 Startup PhysicsTestsReport Page 22 of51

Table 3.1 SURRY UNIT 1-CYCLE 23 STARTUP PHYSICSTESTS CONTROL ROD BANKWORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE(%)

BANK (PCM)

(PCM)

(M~P)IP X 100 D

1073.2 1094.2

-1.9 B - Reference 1275.2 1317

-3.2 C

942.0 973.8

-3.3 A

229.3 230.0

-0.3*

SB 1108.0 1156.9

-4.2 SA 905.1 892.2

+1.4 Total Bank Worth 5532.6 5664.1

-2.3

  • Note: For Bank A, (M-P) =-0.7 pern.

NE-1578 Rev. 0 S1C23 StartupPhysics Tests Report Page 23 of 51

1400 1200 1000 400 200 o

Figure 3.1 SURRY UNIT 1 - CYCLE 23 STARTUP PHYSICS TESTS CONlROL BANK B INTEGRAL ROD WORm - HZP ALL OTHER RODS WITHDRAWN

-- ~

r-.

~ \\,

~

1:

\\

~

~

\\

-'\\

1

\\

""l

'\\

~

~

\\...

'\\

\\..

~

~

1\\

-~

1"'lI: ~

);~

-Measured

_Predicted o

50 100 150 BANK POSITION (STEPS) 200 250 NE-1578 Rev. 0 SlC23 Startup Physics TestsReport Page24of 51

10.0 9.0 8.0 7.0 s:

WI-!:i! 6.0 e:.

J;

~o3:5.0 Q

~

Ii!i=

~4.0 W

LL.

LL.

is 3.0 2.0 1.0 0.0 Figure 3.2 SURRY UNIT 1 - CYCLE 23 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALLOTHER RODSWITHDRAWN It I

\\.

I Il Ii

...~

\\

I III Il\\

~

\\*

I 1&

I,

~

"'"1

"\\

Iff

~

rI.,

-Measured

_Predicted o

50 100 150 BANK POSITION (STEPS) 200 250 NE-1578 Rev. 0 S1C23 Startup Physics TestsReport Page25 of 51

NE-1578 Rev. 0 This page is intentionally left blank S1C23 Startup Physics Tests Report Page 26 ofS1

SECTION 4 -

BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (ReS) 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 Res 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, as necessary.

The results ofthese measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Summary Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements ofTechnical Specification 4.l0.A [Ref. 4] regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepointdata 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, the value of the DBW over the range of boron endpoint concentrations was obtained.

A summary of the measured and predicted DBW is shown in Table 4.2. As indicated in this table and in the Appendix, the measured DBW was well within the design tolerance of

+/-10%. In summary, the measured boron worth coefficient was satisfactory.

NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 27 ofS1

Table 4.1 SURRYUNIT 1-CYCLE23 STARTUP PHYSICS TESTS BORONENDPOINTS

SUMMARY

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

(ppm)

(ppm)

ARO 1645 1623

+22 B BankIn 1473 1470*

+3 II: 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 Summary Sheet in the Appendix.

NE-1578Rev. 0 S1C23 Startup Physics Tests Report Page 28 ofSl

Table 4.2 SURRY UNIT 1-CYCLE 23 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

(pcm/ppm)

(porn/ppm)

(M-P)fP x 100

-7.41

-7.53

-1.6 NE-1578 Rev. 0 SlC23 Startup Physics Tests Report Page29of 51

NE-1578 Rev. 0 This page is intentionally left blank..

SlC23 Startup PhysicsTestsReport Page 30 of 51

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 with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.

Reactivity was measured during RCS heatup of +3.14l>p, followed by RCS cooldown of

-3.3l<Jp.

Reactivity and temperature data were taken from the reactivity computer.

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

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 Summary Sheet given in the Appendix, the measured isothermal temperature coefficient value 'Was within the design tolerance of +/-2 pcrnf'F. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -1.682 pemJ OF, a predicted DTC of -1.80 pcm/ OF, and a measurement uncertainty of +0.5 pcm/ OP, is +0.62 pcm/ OF. It thus satisfies the COLR criteria

[Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pcm/0p.

NE-1578 Rev. 0

. S1C23 Startup Physics Tests Report Page 31 of51

Table 5.1 SURRYUNIT 1-CYCLE 23 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATIJRE COEFFICIENT

SUMMARY

BANK TEMPERATURE BORON ISOTHERMAL TEMPERATURE COEFFICIENT RANGE ("F)

O:CMfF)

POSITION CONCENTRATION LOWER. UPPER HEAT-COOL-AVG.

I DIFFER (STEPS)

LIMIT LIMIT (ppm)

UP DOWN MEAS PRED i

(M-P)

I D/205 546.04 549.38 1636

-1.801

-1.563

-1.682 i -1.262

-0.420 NE-1578 Rev. 0 S1C23Startup PhysicsTests Report Page 32 of51

SECTION 6 -

POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the moveable incore detector flux mapping system.

This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations.

Figure 1.3 shows the available locations monitored by the moveable detectors for the ramp to full power flux maps for Cycle 23.

For each traverse, the detector voltage output is continuously monitored on a recorder, and scanned for 610 discrete axial points.

Full core, three-dimensional power distributions are determined from this data using a Dominion-modified version of the Combustion Engineering computer program, CECOR [Ref.

3].

CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.

A list of the full-core flux maps [Ref. 7] 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 COLR limits is given in Table 6.2. Flux map I was taken at 26.1% power to verify the radialpower distribution (RPD}predictions at low power.

Figure 6.1 shows the measured RPDs from this flux map.

Flux maps 2 and 3 were taken at 67.5% and 99.89% 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 and 6.3.

The radial power distributions for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured relative assembly power values deviated from the design predictions by at most

+5.1% in the 26.1% power map,

~3.4% in the 67.5% power map, and +3.2% in the 99.89%

power map. The maximum quadrant power tilts for the three power maps are +0.46 % (1.0046),

+0.28 % (l.0028), and +0.30% (1.0030), respectively.

These power tilts are within the design tolerance of2% (1.02).

NE-1578 Rev. 0 S1C23 Startup Physics Tests Report Page 33 of51

The measured FQ(z) and F~ peaking factor values for the at-power flux maps were within the limits ofthe COLR [Ref. 8]. Flux Maps 1,2, and 3 were used for power range detector calibration or to confirm existing calibrations. The flux map analyses are documented in [Ref 7].

In conclusion, the power distribution measurement results are considered acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR [Ref 8].

It is therefore anticipated that the core will continue to operate safely throughout Cycle 23.

NE-1578 Rev. 0 SIC23 Startup Physics Tests Report Page 34 of51

Table 6.1 SURRYUNIT1-CYCLE 23 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

I Burn Bank Peak FQ(Z) Hot F~ Hot (2)

CoreFz Core Tilt (3)

No.

Axial Map Map up Power Channel Factor (1) Channel Factor Max Of Description No.

Date MWD/

(%)

D Offset Thimbles Axial Axial Max ILoe I

MTU Steps Assy Point FQ(Z)

Asrry F~

Point Fz

(%)

LowPowcr 1

05/11109 1

26.1 173 Lll 25 2.263 M7 1.521 26 1.375 1.0046 SE

+6.275 46 Int. Power (4) 2 05/13/09 19 67.5 195 Il2 23 1.970 Ell 1.493 21

.1.234 1.0028 SE

+5.720 46 Hot Full Power 3

05/15/09 102 99.89 227 Ell 33 1.866 Ell 1.482 30 1.168 1.003C SE

+3.281 46 NOTES: Hot spot locations are specified by giving assembly locations (e.g. H-8 is the center-of-core assembly) and core height (in the "Z" direction the core is divided into 61 axial points starting from the top ofthe core). FluxMaps 1, 2, and 3 were used for power range detector calibration or were used to confum existing calibrations.

(1) FQ(Z) includesa total uncertainty of 8%

(2)

F~ includesno uncertainty.

(3) CORETILT - definedas the averagequadrantpowertilt fromCECOR. "Max" refers to the maximum positive core tilt (QPTR> 1.0000).

(4) Int Power - intermediate power flux map.

NE-1578 Rev. 0 SlC23 Startup Physics Tests Report Page 35 cfS1

Table 6.2 SURRY UNIT 1 - CYCLE 23 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak FQ(z) Hot FQ(Z) Hot F~ Hot Map Channel Factor*

Channel Factor**

Channel Factor (At Node ofMinimwn Margin)

No.

Meas, Limit Node Meas.

Limit Node Margin" Meas.

Limit Margin"

(%)

(%)

1 2.263 4.570 25 2.263 4.570 25 50.48 1.521 1.906 20.20 2

1.970 3.368 23 1.967 3.334 19 41.00 1.493 1.712 12.79 3

1.866 2.323 33 1.835 2.264 21 18.95 1.482 1.561 5.06

  • The Core Operating Limit for the heat flux hot channel factor, FQ(z), is a function of core height and power level. The value for FQ(z) listed is the maximum value of FQ(Z) in the core.

The COLR [Ref. 8] limit listed is evaluated at the plane ofmaximum FQ(z).

    • The value for FQ(Z) listed above is the value having the lowest margin to the limit.

The minimum margin values listed above are the minimum percent difference between the measured values ofFQ(Z) and the COLR limit for each map.

The measured FQ(Z) hot channel factors include 8% total uncertainty.

Measured F1'H data includes no uncertainty.

$ Margin (%) = 100*(Limit-Meas.) / Limit NE~1578 Rev. 0 S1C23 Startup Physics Tests Report Page 36 of 51

Figure 6.1 -

ASSEMBLYWISE POWER DISTRIBUTION 26.1%POWER R

p M

L H

G E

D C

B A

PR£DICTEO MEASURED

,PeT DIFFER£NCE,

,265.

.275.

.261.

,269,

,288,

.264.

1.3.

4.9.

1.5.

PREDICTED MEASURED

  • peT DIFFERENCE, 1

~

I

.288 *.478. 1,045.*870. 1,040 *. 477** 287.

.288.

.478. 1.049.

.877. 1.047.

.484.

.287.

-,1,

.0.

.4.

,8 *

,6.

1.4.

-.1.

.391. 1.015. 1.136. 1.238. 1.092

  • 1.239
  • l.Bi. 1.015,

.391.

. 389. 1.015.1.133.1.236. 1.099. I,m. 1.131. 1.008.*391.

-.5.

.0.

-.3.

-.2.

.6,

-.2,

-.5,

-.7.

.2.

.':388':'i:iii':'i:295':'i: 227':'i:376':'i:350':'i:383':'i:i29':'i:i95':'i:iii':":387':

.389. 1.123. 1.299. 1.221.1.361.1.322. 1.366.1.215.1.277. 1.114 ** 386.

4

.4.

.1,

.3.

-.5,

-1.1.

-2,0,

-1.2.

-1.2.

-1.3.

-.6,

-.4.

.':i82':' i:009': '1:293':'i: 390':'i:303':'i:323':'i:272':'i:333':' i: 306':'i:38S':'i:i90':'i:006':: 28i':

.285. 1.016. 1. 292. 1.m, 1.290

  • 1.302. 1.m. 1.314, 1.286, 1. 354, 1.287. 1.006.

,279.

5 1.1.

.7.

-.1.

-1.3.

-1.0.

-1.6,

-1.5.

-1.4.

-1.6.

-2.5.

-,3.

.0,

-.5.

I I

I ***

~

~ ***

~

I I

I I

I I

I I ********

,471, 1.129,1,227

  • 1.307. 1.187. 1,285, 1.117, 1.289.1.187. 1.301. 1.221. 10m..469,

.479. 1.147.1.213. 1.305. 1.175. 1.269.1.106. 1.276.1.169. 1.28-4. 1.214. 1.130..479, 6

1.8.

1.5,

.5.

-.2.

-1.0.

-1.3.

-1.0.

-1.0.

-1.6.

-1.3.

-.6,

.4.

2,2.

:247':'i:02S':'i:ii9':'i:378':'i:lii':'i:i90':Tii2':":976':'1:1i3':'i:288':'i:32r: 'i:37i':'i:225':'i:020':" :24:1':

,253,1.049.1.259,1.390.1.327, 1.279.1.094,

,967.1.110.1.279,1,311.1.356,1,240,1.072.

,255.

7 2,5, 2.4.

3.2.

.9.

-.2.

-.9.

-1.5.

-.9.

-.2.

-.7.

-.9,

-1.1.

1,2.

5.1.

4.4.

..:265':":853':'i:083':'i: 347':'i:i73':'i:ii9':' ':977':'i:oio':" :977':'i:ii9': 'i: 272':'i:347':'i:083':" :853':" :265':

.*275 ** 863.1.086, 1.350. 1.265. 1.108,

.965. 1.000,

.970, 1.115. 1,269. 1.347.1.096,

,864,

,271, 8

3.7.

1.1.

.3.

.2,

-.6,

-.9.

-1.2.

-1.1,

-.7.

-,3.

-.3.

.0, 1.2.

1.3.

2.1,

..:244':'i:021':'i:i26':'i:37i':'i:324':' i:289':'i:ii3':" :976':'i:iii':' i:290':'i:33i':'i:378':'i:229':' i:iJ25':" :247':

,248,1.031, 1.233. 1.370, 1.306.1.273. 1.096.

,965. 1.097.1.293. 1.331. I,m, 1.235, 1.032,

,m.

9 1.5.

1.0.

.6.

-,1,

-1.3,

-1.2.

-1.5.

-1.1.

-1.4.

.2.

.0.

.2.

.6.

.8.

1.9.

.....,...":469':'i:i26':'i:ii2':'i:30i':' i:i88':'i:2S9':'1:1i7':'i:i85':'i:i87':'1:307':'i:i26':'i:i29':" :47i*:"..*..*

,474, 1.142. 1.224. 1.292. 1.171. 1.263.1.108.1.277. 1.180.1.309,1.231

  • 1.133..466.

10 1.2, 1.5.

.2.

-.7.

-1.4.

-2.0.

-.8.

-.7,

-.6.

.1.

.4.

.3.

-.9.

..:i81':'i:007':'i:i9il':'i: 389':'i:307':'i: 333':'i:27i':'i:323':'i:303':'i: 390':'i:292':'i:009':": 28i':

,283. 1.015. 1.291, 1.382. 1.300. 1.326,1.277

  • 1.320. 1.290. 1.394. 1.301.1.016.. 282.

11

.9.*8,

,1,

-,5.

-.5.

-.5,

.3.

-,2.

-1.0.

,3..7..7.*2,

,.,.,.,.:..:387':'i:12i':'i:i95':' i:229':'i:383':'i:350':'i:376':'i:'227':'i:29.4*:'ni2':" :388':*'*"*,*

.*391. 1.123. 1.294. 1.230. 1.387. 1.362. 1.385. 1.233. 1.305. 1.140.. 395.

12

,9,

.2.

-.1.

.1.

.3.

.9 *

.7.

.5,

.8.

1.6.

2.0.

........:..:39i':'i:oi5':' i:i37':'i:239':'i:092':'i:i38':'i:i36':'i:OiX:":391*:**....**

.391. 1.017. 1.142, I,m. 1.119. 1.256,1.154. 1.028.* 395.

13

.1.*2 *.5.1.1.2.5.1.5.1.6.1,2.1.4.

........:..:287':" :477':'i:04o':":870':'i:045':" :478':" :i88*:..***,..

.288.

.482. 1.057.

.883. 1.060.

.486,

.291.

14

.2..9.1.6.1.6.1.4.1.5.1.3.

STANDARD DEVIATION

=,906

.261.

,275.

.265,

.273.

.281.

.269.

4.6.

2.3.

L 7

  • AVERAGE

,PCT DIFFERENCE.

= 1.0 15 Summary:

Axial Offset (%) = +6.275 Power:

26.1%

0.9997 0,9957 1.0001 1.0046 Date: 05/1112009 FQ{Z) =

2.263 QPTR:_-=.;;..;;;..;;..:._I----';:.;.;....;;.;;..;....._

F~:;

1.521 Fz =

1.375 Bumup :;

1 MWDIMTU MapNo: 81-23-01 Control Rod Position:

D Bank at 173 Steps NE-1578 Rev. 0 S1C23 StartupPhysicsTests Report Page 37 of 51

Figure 6,2-ASSEMBLYWISE POWER DISTRIBUTION 67,5% POWER R

P N

M K

H G

E o

c B

A PREDICTED MEASURED

, Per DIFF£RENCE.

..:i87':" :30i':" :283':

.288.

.304,

,284.

.4 *

.8.

.6.

PREDlCTEO MEA5lJRED

, PeT DIFnRENCE.

1 4

6

. 301..497. 1.069..922. 1.065..496.. 301.

. 301..498,1.073.. A27.

1.070..499.. 3Gl.

  • 1.

.1,

,4.

.5.

,5 *

.6,

.0.

.':400::'i:Oii':'i:i30':'i:i32':'i:097':'i:233' :'i:iii': 'i:oi2':" :400':
  • . 395. 1.013. 1.130.1.233. 1.106
  • 1.236, 1.131. 1.010.. 396 *

-1.4.

.1.

.0.

.1.

.8.

.3.

.1.

-.2.

-1.0.

..:398':'i:ior:'i: 268':'i.205':'i: 344':'i:ns':'i:350':'i:i07':'i:267":Ti07':..:397':

,399. 1. lOB

  • 1.275. 1. 203. 1.340. 1. 327. 1. 352. 1. 206
  • 1.263. 1.105.

,397,

.3..1.

,6.

-.1.

-,3,

,7..1.

-.1.

-.3.

-.2.

-.2.

..:295':'i:007':'i:266':'i:m':' i:284':'i:305':'i:253':'i:ii:!,:.i:287': 'i: 354':'i:264':'i:005':": 295':

.297.1.013.1.265. 1.344. 1.274,1.280.1.247. 1.309. 1.283.1.345.1.266. 1.004..285.

  • 5.

.6.

-,1.

-.8.

-.8.

-2.0.

-.5.

-.4.

-.4.

-.6,

.2.

-.1.

-3.4,

..:490':'i:ii5':'i:i05':'US8':'i:iis' :'i:287':'i:iii':'i:290':'i: 2i9': Tisi':'i:2oi':'1:1i2':' ':489':

.493. 1.130. 1.2G7. 1.292. 1,212. 1.275. 1.116, 1.284

  • 1.211. 1.279, 1.201. 1.125.*493.

.5.

.5.

. 2.

  • 3.

-. 5.

-1.0.

-. 5.

-. 5.

..6.

-. 3.

.0.

. 3.

.9.

..:269':'i:052' :.i:ii5':'i: i4;":'i: iii': 'i:29i':'i:i30':" :999':'i:i3i.*:'i:i90':.i:307':'1:342':'i:2ii':.i:048":'.:266':

.270. 1.058.1.234.1.348.1.308. 1.284,1.121 **994.1.126. 1.286.1.303. 1.340.1.232. 1.0S0 *. 273.

. 4 **6 *

.7.*1.

-.3.

-.6,

-.8.

-.5.

-.4.

-.3.

-.3.

-.1 *.S.

3.0.

2.3.

..:292':" :907' :'i:090':'i: ii?':'i:2;4":'i:ii3':' i:ooo':'i:04o':'i:ooo':'i:i23': 'i:2i.4':* i:3i7':'i:09O':" :907':" :i92':

.292 *. 910.1.094,1.315. 1.244. 1,116,

.994,1.033 **995. 1.122.1.254

  • 1.319. 1.095 ** 911.*293.

8

.1.*3..4,

-.2.

-.8.

-.7.

-.6.

-.7.

-.5.

-.1..0..1..4..4..3.

..:266':'i:048':'i:iii':'i:34i':'i:307':'i:i90':'Gil':" :999':'Gio':'i: i91':'i:313':'i: 347':'i:i25':'i:05i':" :269':

. 267, 1.052. 1.225, 1,335

  • 1.284. 1.278. 1.124.

.903. 1.U7. 1.294. 1.314

  • 1. 348. 1.224
  • 1.047.

,264.

9

.3.

.4.

.2.

-.5.

-1.8.

-,9.

-.6.

-.6.

-1.2.

.2.

.1.

.1.

-,1.

-.5.

-1.9.

.........":489':'i:i2i':' i:20i': 'i: 283':'i:2i9':'i:29O':.Eli':.i:287':'i:ii9':'i:289':'i:205':'i:i25':" :490*:*..,**..

.491.1.132.1.198. 1.273. 1.213. 1.290

  • 1.119, 1.282. 1.217. 1.294. 1.208,1.121,

.478.

10

.5.*9.

-,2.

-.8.

-.5..G.

-.3.

-.4.

-.1,

.4 *.2.

-.3.

-2.6.

.:::m':'i:005':'i: i64":' i:354':'i:2S7': 'i: i14': 'i:ii3":'i:305':'i:iir: 'i: 3SS':'i:266':'i:007':":296':

.295.1.004.1.258.1.344. 1.285.1.315.1.250.1.302.1.278.1.370.1.274,1.007.

,293.

11

,1.

-.1.

-,5.

-.7.

-.2..1.

-.3.

-.2.

-.5.

1.1..6..0.

-.9.

........ :..:397':'i:107':'i:26S': '1:207' :'i: 350': 'i: 3is':'i:i4i':'i:i05': 'i:268':'i:ios':": 39S*:**..,**,

.389.1,100.1.262.1.209.1.364.1.329.1.352.1.211.1.279. 1.121 ** 395.

12

-2.2.

-.6.

-.4..2.1,0.*8 **5.

,5 *.9.1.2.

-.6 *

........:..:400':Toii': 'i:i31':'i:m':'i:09S':'i:iii':'i:i30': 'i:Oii':" :401*:*..*****

    • 398. 1.009. 1.134,1.245.1.117.1.245.1.141. 1.022 *. 405.

13

-.5.

-.3..3,1.0,1.8.1.1.

,9..9.1.0.

.....,..:..:30i':" :496':'i:001;': ":92f:' i:069':' ':498':" :i0i*:*..*....

. 294.*497.1.076 ** 934.1.084 ** 503 ** 304.

14

-2.0,

.3.

1.0.

1.3.

1.3.

1.1.

1.0 *

      • .STANDARD"':

..,....,....****:** :i83':":302':" :281*:'***,******,****

',..AVEAAGE'..:

DEVIATION

.285.

.305.

.291.

  • PeT DIFFERENCE.

15

~.568

.9.

1.3.

1.3.

.6 Summary:

Power: 67.5%

0.9990 0,9997 0.9984 1.0028 Axial Offset (%) = +5.720 Date:

05/1312009 FQ(Z) =

1.970 QPTR:_....::.:,::;..::..:....:~+-...;;.;.;;..::..:....:'---

F~ '"

1.493 Fz =;

1.234 Burnup =

19 MWD/MTU Map No: 81*23-02 Control Rod Position:

. D Bank at 195 Steps NE-1578 Rev. 0 S1C23 Startup Physics TestsReport Page 38 of51

Figure 6.3 -

ASSEMBLYWISE POWER DISTRIBUTION 99.89% POWER R

p N

L K

H G

F o

c A

PREDICTED MEASURED

  • PC:T DIFFERENCE.

.296.

. 314.

. 291 *

.298.

.321.

.294.

  • 8.

2.0.

.8

  • PREDICTED MEASURED
  • PeT DIFFERENCE*
  • 303.

.:iOO. 1.065.

.954. 1.061.

.498.

.302.

.303.

.501. 1.070.

.960. 1.066.

.499.

.302 *

.1..2..4 *.6.. 5*.1.

-.1.

":399':" :99i.*:'i:iu': 'i:iis':'i:099':'i:iiiJ':'i:iii':":991':" :399':
    • 392.*992. 1.112
  • 1.220. 1.107. 1.222. 1.112 ** 989 **39i.

-1. Ii *

.1.

.0.

.2.

.7.

.3.

,0.

-.2.

-.5.

.396.1.081.1.240. 1.192. 1.328. 1.305.1.334.1.193. 1.240.1.080 ** 39Ci.

.398.1.083.1.248. 1.191. 1.325. 1.314.1.335.1.192. 1.237.1.079 ** 395 *

.6.*2..6.

-.1.

-.3..7..1.

-.1.

-.2.

-.1.

-.2.

.297 **986. 1.2n. 1.338. 1.288. 1.30i

  • 1.255.1.315.1.290. 1.337.1.237.* 985.. 297.

.300.

.997. 1.241. 1. 331. 1.279. 1. 284

  • 1.249. 1.309. 1.284
  • 1. H2
  • 1. 239,

,983.

.288.

1.0.

1.1.

.1.

-.5.

-.7.

-1.8.

-.5.

-.5.

-.5.

-.4.

.2,

-.2.

-2.8 *

                      • r' ********* * *******************************************************************************.**

.493. 1.107.1.192. 1.292. 1.279. 1.309. 1.143. 1.312. 1.279.1.287

  • 1.18~. 1.104.. 492.

,497.1.116. 1.195. 1.291. 1.271

  • 1.29~
  • 1.137.1.303.1.264. 1.279.1.184, 1.105.. 496.

.8.

.8.

.3.

-.1.

-.6.

-1.0.

-.5.

-.7.

-1.2.

-.6.

-.4.

.1.

.9.

.':i79': 'i:oso':'i:iii':'i:iii':' i:;i4':'i:3i;':'i:i58':' i:oi~':' i:m': 'i:iii':' i:iog':' i:326': 'i:iio':'i:047': ":i77':
  • 281
  • 1.059.. 1.227
  • 1.333. 1.306. 1.303
  • 1.147
  • 1.022
  • 1.151
  • 1.303. 1.299
  • 1.311. 1.216
  • 1. 080.

.283.

  • 6 **9.1.2 *.1.

-.~.

-.7.

-.9.

-.7.

-.6.

-.7.

-.8.

-1.2.

,5.3.2.2.5.

6 I **,

~ ****

.306 *. 941. 1.093. 1.305. 1.256.1.144.1.030. 1.070, 1.030. 1.144.1.257

  • 1.305, 1.094.

,941 ** 306.

.305 ** 944. 1.095. 1.]01. 1.239. 1.134. 1.022. 1.062. 1.023

  • 1.141. 1.253. 1.302, 1.098.* 948.

.308.

8

-.2.

.4.

.1.

-.3,

-1.4.

-.9.

-.8.

-.8.

-.7.

-.3.

-.3.

-.2.

.4.

.7.

.7.

.276. 1.047. 1.210.1.326. 1.309.1.312. 1.158. 1.029.1.158.1.313

  • 1.315. 1.H1. 1.213.1.050.. 279.

.277. 1.051. 1.213.1.322. 1.294. 1.301. 1.149. 1.021.1.145.1.318. 1.3H

  • 1.332
  • 1.213. 1.048.. 276.

9

.2.

.4.

.3.

-.3.

-1.2.

-.8.

-.8.

-.8.

-1.1.

.4.

.0.

.0.

.0.

-.2.

-1.3.

........:..:492':'i:iil4':'i:i88':'i:i87':'i:279':'i:31.2::'i:i43' :'i: 309':'i:i79':'i:i9Z':'i:ig2':' i:io7':" :493*:*....***

.495.1.116.1.189. 1.281. 1.273.1.304

  • 1.136.1.301.1.274.1.297.1.196. 1.106..483.

10

.7.1.1..0.

-.4.

-.5.

-.6.

-.6.

-.7.

-.3 **4.* 3.

-.1.

-2.0.

..:297':" :985':'i:ii7': 'i:337':'i:29i':'i:ns':'i:2is':'i:307':'i:288':'i: 338':'i:239': ":936':" :297':

.298 **987.1.235, 1.332.1.290.1.315.1.250.1.299.1.268.1.355.1.251 **.988 ** 296.

11

.4.

.3.

-.2.

-.4.

-.1.

.0.

-.4.

-.7.

  • 1,5.

1.3.

.9.

.2.

-.6.

........:..:396':'i:080': *i:2.iO*:*i:i94':'i: 33.4':'i:305':'i:i29': Tig2':'1: 240':'i:osi':" :396*:******..

.392.1.078. 1.239. 1.198

  • 1.350. 1.314. 1.m.1.196.1.255.1.102.* 393.

12

-1.0.

-.2.

-.2.

.4.

1.2.

.6.

.3.

.3.

1.2.

2.0.

-,7.

..... ".:..:399':" :99i':'i:iii':'i:iig':'i:099':'i:iis':'i:iii':": 900::' *:399*:..**....

. 398.

,989. 1.116. 1.230. 1.113. 1.231. 1.128

  • 1.005.

.40S.

U

-.Z.

-.2 **4 **9.1.2.1.1.1,4.1.4.1.7.

........:": 302':":499':'i:061':" :954':'i:065':": 500':": 303':*...... *

.295.

. 500. 1.072.

.966. 1.083.

.507.

.307.

14

-2.3..J.

1.0.1.2.1.6.1.5.1.4

  • STANDARD DEVIATION
    • 577
..:29i':":3i5':":i95*:*..**..*..**..

.295.

.319.

  • 301
  • 1.3.

1.4.

1.6.

AVERAGE

  • PeT DIFFERENCE.

~.,

15 Summary:

Power: 99.89%

0.9994 0.9983 0.9992 1.0030 Axial Offset (%) = +3.281 Date:

05115/2009 FQ(Z) =

1.866 QPTR:_....::.:..;.::.::...;:...--+-.....::.:.:;..;..:;.:~

F~ =

1.482 Fz =

1.168 Bumup =

102 MWDIMTU Map No: 81-23-03 ControlRodPosition:

D Bank at 227 Steps NE-1578 Rev. 0 S1C23 StartupPhysics TestsReport Page 39 of51

NE-1578 Rev. 0 This page is intentionally left blank.

S1C23 Startup PhysicsTests Report Page 40 of51

SECTION 7 -

CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 1 Cycle 23 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, technical specification limits, or COLR limits.

It is anticipated, based on the results associated with the S1C23 startup physics testing program, that the Surry 1 core will continue to operate safelythroughout Cycle 23.

The Programs Review Checklist (PRC) and Controlled Documents Summary (CDS) were reviewed as a part of this technical report in accordance with NDCM 3.11, Rev. 12. No impact to any programs or controlled documents was identified as a result ofthe review; therefore a PRe and CDS will not be attached to this technical report or to any associated engineering transmittal.

The data herein is simply intended to summarize the S1C23 startup physics testing program for information only and meet the requirements of Surry Technical Specification 6.6.A.1.

This report does not have any impact on the Surry Operating License, Technical Specifications, or the design, the function, or any calculation associated with a SSC. Furthermore, this report does not perform or involve any test or temporary modification.

Activity screening (in the form of an Activity Checklist) is thus not required.

Because the PRC and CDS review did not flag any programs or controlled documents as impacted by the data herein, no Activity Checklist will be attached to this technical report or any associated engineering transmittal per NDCM 3.11, Rev.

12.

NE-1578 Rev. 0 SlC23 Startup Physics Tests Report Page 41 ofSl

Table 7.1 STARTUP PHYSICS TESTING RESULTS

SUMMARY

Measured Predicted Diff (M-P) or Design Parameter (M)

(P)

(M-P)/P,%

Tolerance Critical Boron Concentration (HZP ARO), ppm 1645 1623 22

+/-50 Critical Boron Concentration (HZP Ref Bank in). POOl 1473 1470 3

+/-27 Isothermal Temp Coefficient (HZP ARO), pcm/F

-1.682

-1.262

-0.420

+/-2 Differential Boron Worth (HZP ARO). pcm/ppm

-7.41

-7.53

-1.6%

+/-10%

Reference Bank Worth (B-bank dilution), pcrn 1275 1317

-3.2%

+/-10%

S8-bank Worth (Rod Swap), pcm 1108 1157

-4.2%

+/-15%

SA-bank Worth (Rod Swap), pcm 905 892 1.4%

+/-15%

D-bank Worth (Rod Swap), pcm 1073 1094

-1.9%

+/-15%

C-bank Worth (Rod Swap), porn 942 974

-3.3%

+/-15%

Rod Worth s 600 pcm:

A-bank Worth (Rod Swap), porn 229 230

-1.0

+/-100 Total Bank Worth, pcm 5533 5664

-2.3%

+/-10%

S1C23 testing time:

6.2 hrs

[criticality 05/11/09 @ 0102 to end of rod swap 05/11/09 @0715]

Recent Startups:

S2C22 testing time:

6.2hrs S1C22 testing time:

8.0 hrs S2C21 testing time:

5.8 hrs S1C21 testing time:

5.0 hrs S2C20 testing time:

8.0 hrs 51 C20 testing time:

7.6 hrs NE-1578 Rev. 0 SlC23 Startup Physics Tests Report Page42 of 51

SECTION 8 -

REFERENCES 1.

D. B. Livingston, "Surry Unit 1, Cycle 23 Design Report," Technical ReportNE-1568, Rev.

0,May 2009 2.

R. W. Twitchell, "Control Rod ReaetivityWorth Determination By The Rod Swap Technique," Topical Report VEP-FRD-36-Rev. 0.2-A., September 2004 3.

D. A Pearson, "The Virginia Power CECOR Code Package," Technicab Report NE-0831, Rev. 8, August 2004 4.

Surry Units 1 and 2 Technical Specifications, Sections 3.12.C.I, 3.12.F.l, 4.10.A.

5.

R. W. Twitchell, "Operational Impact ofthe Implementation ofWestinghouse Integral Fuel Burnable Absorber (!FBA) and the Removal ofFlux Suppression Inserts (PSIs) for Surry Unit 1 Cycle 21," Technical ReportNE-1466, Rev. 0, January 2006 6.

C. D. Roecker, "Surry Unit 1 Cycle 23 TOTE Calculations and Detailed. Isotopics,"

Calculation PM-1303, Rev. 0, May, 2009 7.

J. L. Meszaros et al, "Surry Unit 1 Cycle 23 Flux Map Analysis," Calculation PM-1304, Rev. 0, and Addenda A - B, May 2009 8.

R. K. Fawls, "Reload Safety Evaluation Surry 1 Cycle 23 Pattern NXS," EVAL-ENG-RSE-SIC23,Rev.O,March,2009 9.

S. B. Rosenfelder and S. S. Kere, "RMAS v6 Verification," Calculation PM-I075, Rev. 0, May, 2005

10. W. R. Kohlroser, "Administrative Limits on Hot Rod Drop Time Testing for Use as Acceptance Criteria in 1/2-NPT-RX-014 and 1/2-NPT-RX-007," Engineering Transmittal ET-~AF-97-0197,Rev.0,August,1997
11. J. L. Meszaros, "Surry Unit 1 Cycle 23 Full Core Loading Plan," Engineering Transmittal ET-~AF-08-0099,Rev. 0, November, 2008
12. N. A. Yonker, "Validation ofRod Drop Test Computer for Hot Rod Drop Analysis,"

Calculation PM-I044, Rev. 0, November, 2004

13. A. H. Nicholson, "Justification For Defining 0 To 2 Steps Withdrawn As Fully Inserted When Measuring Control And Shutdown Banks During The Surry Startup Physics Testing Program," Engineering Transmittal ET-NAF-06-0046, Rev. 0, April, 2006.

14.

J. L. Meszaros, "Surry Unit 1 Cycle 23 Startup Physics Testing Logs and Results",

Memorandum MEMO-NCD-20090034, Rev. 0, May 2009 NE-1578 Rev. 0 SlC23 Startup Physics Tests Report Page 43of51

NE-1578 Rev. 0 This page is intentionally left blank.

S1C23 Startup Physics Tests Report Page 44 ofSl

APPENDIX -

STARTUP PHYSICS TEST

SUMMARY

SHEETS NE-1578 Rev. 0 S1C23 StartupPhysics TestsReport Page 45 of51

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