ML052220506

Technical Report NE-1454, Rev. 0, Surry Unit 2, Cycle 20 Startup Physics Tests Report.

ML052220506
Person / Time
Site:	Surry
Issue date:	08/03/2005
From:	Meszaros J, Schnitz A Dominion
To:	Office of Nuclear Reactor Regulation
References
NE-1454, Rev 0
Download: ML052220506 (50)

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TECHNICAL REPORT NE-1454- REV. 0 SURRY UNIT 2, CYCLE 20 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES DOMINION August, 2005 Prepared by:

Prepared by: "&--

A. C. Schnitz 8.3.0s Date Reviewed by:

S. S. Kere Date Reviewed by:

M. J. Fanguy Date Approved by:

QA Category: Safety Related Keywords: S2C20, S2CK, SPTR, Startup Physics Tests Report Page 1 of 50

CLASSIHCATION/DISCLAIMER 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 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.

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TABLE OF CONTENTS CLASSIFICATION/DISCLANER ..................................................................................................................... 1 TABLE OF CONTENTS...................................................................................................................................... 3 LIST OF TABLES................................................................................................................................................ 4 LIST OF FIGURES.............................................................................................................................................. 5 PREFACE............................................................................................................................................................. 6 SECTION 1 .INTRODUCTION AND

SUMMARY

........................................................................................... 8 SECTION 2 .CONTROL ROD DROP TIME MEASUREMENTS............................................................... -18 SECTION 3 .CONTROL ROD BANK WORTH MEASUREMENTS........................................................... 22 SECTION 4 .BORON ENDPOINT AND WORTH MEASUREMENTS........................................................ 28 SECTION 5 .TEMPERATURE COEFFICIENT MEASUREMENT............................................................. 32 SECTION 6 .POWER DISTRIBUTION MEASUREMENTS......................................................................... 34 SECTION 7 .REFERENCES............................................................................................................................ 42 APPENDIX ......................................................................................................................................................... 44 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 3 of 50

LIST OF TABLES TABLE 1.1 CHRONOLOGY OF TESTS ........................................................................................................ 11 TABLE 2.1 HOT ROD DROP TIME

SUMMARY

.......................................................................................... 19 TABLE 3.1 CONTROL ROD BANK WORTH

SUMMARY

.......................................................................... 24 TABLE 4.1 BORON ENDPOINTS

SUMMARY

............................................................................................. 29 TABLE 4.2 BORON WORTH COEFFICIENT............................................................................................... 30 TABLE 5.1 ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

............................................... 33 TABLE 6.1 INCORE FLUX MAP

SUMMARY

............................................................................................... 36 TABLE 6.2 COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS ............................................................................. 37 NE-1454Rev . 0 S2C20 Startup Physics Tests Report Page 4 of 50

LIST OF FIGURES FIGURE 1.1 CORE LOADING MAP .............................................................................................................. 12 FIGURE 1.2 BEGINNING OF CYCLE FUEL ASSEMBLY BURMJPS ....................................................... 13 FIGURE 1.3 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS .......................................... 14 FIGURE 1.4 BURNABLE POISON & FLUX SUPPRESSION INSERT LOCATIONS ................................ 15 FIGURE 1.5 CONTROL ROD LOCATIONS .................................................................................................. 16 FIGURE 2.1 TYPICAL ROD DROP TRACE .................................................................................................. 20 FIGURE 2.2 ROD DROP TIME .HOT FULL FLOW CONDITIONS.......................................................... 21 FIGURE 3.1 CONTROL BANK B INTEGRAL ROD WORTH .HZP ......................................................... 25 FIGURE 3.2 CONTROL BANK B DIFFERENTIAL ROD WORTH .HZP ................................................. 26 FIGURE 6.1 ASSEMBLYWISE POWER DISTRIBUTION 30% POWER .................................................. 38 FIGURE 6.2 ASSEMBLYWISE POWER DISTRIBUTION 70% POWER.................................................. 39 FIGURE 6.3 ASSEMBLYWISE POWER DISTRIBUTION 100% POWER ................................................ 40 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 5 of 50

PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry Unit 2, Cycle 20 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 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 Unit 2, Cycle 20 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results, These are the revised and condensed evaluation sheets introduced last year. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values (at design conditions) of the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on calculations performed by Dominions Nuclear AnaIysis and Fuel Group. During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occurring during the tests.

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SECTION I INTRODUCTION AND

SUMMARY

On 24 April 2005, Unit No. 2 of the Surry Power Station shut down for its nineteenth refueling [Ref. 13. During this shutdown, 61 of the 157 fuel assemblies in the core were replaced with 56 Eresh Batch 22 assemblies, 4 Batch S1/19B assemblies last inadiated in SlC18, and one Batch S2/18B assembly last irradiated in S2C17 [Ref. 81. The Cycle 20 core consists of 8 sub-batches of fuel: two fresh batches (S2/22A and S2/22B), two once-burned batches (S2121A and S2/21B), three twice-burned batches (S2/20A, S2/20B, and S2/18B), and one twice-burned batch from Suny Unit 1 (S1/19B). Batches S2/20, S2/21, and SZ22 are of the SIF/P+Z2 fuel type.

The other batches are of the Westinghouse SIF/P+Z design [Ref. 8).

Both Westinghouse SLF/P+Z and SIF/P+Z2 he1 assembly designs incorporate ZIRLO fuel cladding, intermediate grids, guide tubes, instrumentation tubes, and debris resistance features that are part of the Westinghouse P E R F O W C E + design [Ref. 11. The SIFA?+Z2 design used in batches S2/22A, S2/22B, S2/21A, S1/21B, S2/20A, and S2/20B is similar to the SIF/P+Z design used in batches S1/19B and S2/18B. The differences in the P+Z2 design include the following

[Ref. 131: the overall assembly length has increased by 0.2 inches, the fuel rod length has increased by 0.2 inches, the top Inconel grid elevation increases by 0.2 inches, the fuel holddown spring height is slightly decreased, the fuel rod top end plug length has decreased by 0.1 inch, and the bottom end plug is longer by 0.2 inches. These dimensional changes result in a small net increase in the fission gas plenum volume of the fuel rod. The bottom of the active fuel region for both the SIF/P+Z and SIF/P+Z2 fuel is the same.

The burnable poison rod design for this cycle is B4C in Alumina, which has an active absorber Iength of 127.1 inches and is available in various B4C enrichments. The burnable poison rods are of the same design as in previous cycles.

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Note that there are no thimble plugging devices or secondary sources inserted in Surry Unit 2 for this cycle. [Ref. 11 provides a more detailed description of the Cycle 20 core.

The S2C20 full core loading plan [Ref. 121 is given in Figure 1.1 and the beginning of cycle fuel assembly bumups [Ref. 61 are given in Figure 1.2. The available incore moveable detector locations used for the flux map analyses [Ref. 71 are identified in Figure 1.3 and the cycle 20 burnable poison locations are detailed in Figure 1.4. Figure 1.5 identifies the location and number of control rods in the Cycle 20 core [Ref. 11.

According to the Startup Physics logs, the Cycle 20 core achieved initial criticality on 22 May 2005 at 05:47. 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 R M A S v.6 was used, for the first time, in S2C20 [Ref. 161. The tests performed are the same as in previous cycles. A summary of the test results follows.

The measured drop time of each controI rod was within the 2.4 second Technical Specification [Ref. 41 limit, as well as the 1.61 second admimstrative h i t [Ref. 111.

Individual control rod bank worths were measured using the rod swap technique [Ref. 21,

[Ref. 51, incorporating the recommendations of (Ref lo]. The sum of the individual measured control rod bank worths was within 0.3% of the design prediction. The reference bank (Control Bank B) worth was w i t h -3.1% of its design prediction (corresponding to 44.3pcm). The other control rod banks were within +2.7% (-2.7% was recorded for Bank SB, which corresponds to a difference of 28.4 pcm) of the design predictions, which was the greatest percent dfference of all control rod banks with design predictions greater than 600 pcm. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within +13.9 pcm of the design prediction. These results are within the design tolerances of '15% for individual banks worth more than 600 pcm ('10% for the rod swap reference bank worth), '100 pcm for individual banks worth 600 pcm or less, and *lo%for the sum of the individual control rod bank worths.

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Measured critical boron concentrations for two control bank configurations (ARO and B-bank in) were within 7 ppm of the design predictions. These results were within the design tolerances and also met the Technical Specification [Ref. 41 criterion that the overall core reactivity balance shall be within '1% Auk of the design prediction.

The boron worth coefficient measurement was within +0.14% 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 -0.60 pcrn/"F of the design prediction. This result is within the design tolerance of '2.0 pcd0F.

Mode 1 (see [Ref. 41) core power distributions were within established design tolerances.

The measured core power distributions were within +4.0% of the design predictions, where a

-4.0% maximum difference occurred in the 25.8% power map. The heat flux hot channel factors, FQ(z),and enthalpy rise hot channel factors, FL, were within the limits of COLR Sections 3.3 and 3.4, respectively. All power flux maps were within the maximum incore power tilt design tolerance of 2% (QPTR 5 1.02).

The total RCS Flow was successfully verified as being greater than 273000 gpm as required by Technical Specification 3.12.F.1. The total RCS Flow was measured as 295094 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 of this report. The screening (PRC, CDS, and ASC) for this technical report will be included in the engineering transmittal that implements and distributes the report.

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Table 1.1 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 05/21/05 1958 HSD 2-NPT-RX-014 Reactivity Computer Checkout 05/22/05 0755 HZP 2-NPT-RX-008 Boron Endpoint - ARO 05/22/05 0755 HZP 2-NPT-RX-008 Zero Power Testing Range 05/22/05 0755 HZP 2-NPT-RX-008 Boron Worth Coefficient 05/22/05 1223 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 05/22/05 0835 HZP 2-NPT-FX-008 BankB Worth 05/22/05 0923 HZP 2-NPT-RX-008 Boron Endpoint - B in 05/22/05 1223 KZP 2-JYFT-RX-008 Bank A Worth - Rod Swap 05/22/05 1223 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap 05/22/05 1223 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 05/22/05 1223 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap 05/22/05 1223 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap 05/22/05 1223 HZP 2-"T-RX-008 Total Rod Worth 05/22/05 1223 HZP 2-I"-RX-008 Flux Map - less than 30% Power 05/23/05 1950 25.8% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 Flux Map - 65% - 75% Power 05/24/05 1640 66.5% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-00 8

& Power Range Calibration 2-NPT-RX-005 Flux Map - 95% - 100% Power 05/29/05 1239 99.98% 2-NPT-RX-002 Peaking Factor Verification 2-WT-RX-008

& Power Range Calibration 2-NPT-RX-005 RCS Flow Measurement 06/02/05 1546 HFP 2-NPT-RX-009 NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page 11 of 50

Figure 1.1 SURRY UNIT 2 - CYCLE 20 CORE LOADING MAP SURRY UNIT 2 - CYCLE 20 FULL CORE LOADING PLaN PAGE 1 of 2 REVISION NO. 0 R P N M L K J B G F E D C B A VEP-NES-NAF NORTH t

goD 9

10 11 12 TNCORS DEVTCE DESCRIPTIONS: 13 RCC- FULL LENGTH CON'PROb ROD 3P- 3 BURNABLE POISON ROD CLUSTER 14 5P- 5 BURNABLE POISON ROD CLUSTER 2OP- 20 BURNABLE POISON ROD CLUSTER 15 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 12 of 50

Figure 1.2 SURRY UNIT 2 - CYCLE 20 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R P N M L K J H G F e D C B A 1 1 2 2 3 1 40.741 0.001 0.001 21.801 0.001 21.681 0.00 0.001 41.03 3 I 40.971 0.001 0.001 21.511 0.001 21.531 0.001 0.001 40.911 4 4 5 5 6 6 7 1 8 8 9 9 10 10 11 11 12 12 13 13 14 14 15 15 R P N K L I7 J H G P E D C B A NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 13 of 50

Figure 1.3 SURRY UNIT 2 - CYCLE 20 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R P N M L K

- J H G F E D C B A MD MD MD 7

MD MD MD MD MD MD 8 MD MD MD MDm MD MDMD MD 9

MD 10 MD MD MD 11 MD MD MD MD MD 12 MD MDMD 13 MD MD 14 MD m 15 MD - MoveableDetector

• - Locations Not Available For Flux Map 1,2, or 3 for S2C20 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 14 of 50

Figure 1.4 SURRY UNIT 2 - CYCLE 20 BURNABLE POISON LOCATIONS SURRY UNIT 2 - CYCLE 20 FULL CO- LOADING PLAN REVISION NO. 0 PAGE 2 of 2 VEP-NES-NAF CORE XSY BP

-CORE ASSY corn

- ASSY BP

- LOC 502 ID 54T ID BPI168 M C EO 6 -7m-ID IA3C c10 ,

ID 29T ZD BP1178 GO 2 POT BP1169 C06 31T Nl1 37T BP1198 LO3 41T BP1192 PO7 3 8T BP1175 Mll 08T BP1184 KO3 47T BP117 9 M07 O4T BP1162 Kl1 23T BP1160 HO 3 32T BP1166 If07 26T . BP1157 F11 275 5P1153 PO3 35T Bpi181 DO7 21T BPll6l D11 221 BP1190 E03 52T BP1195 B07 S1T BP1171 c11 34T BP1197 LO4 11T BP1191 NO8 53T BP1164 L12 17T BPll88 504 O2T BP1144 xo e 06T BPI152 512 09T BP1149 004 24" BP115.0 QO 8 16T BPI146 Q12 14T BPI145 EO 4 07T BP1185 COB 39T. BPI165 El2 03" BP1186 NO3 33T BP1193 PO9 45T BPll74 f13 30t BP1599 NO 5 28T BP1187 M09 152 BP1117 K13 48T BP1177 KO5 20T BP11S9 H09 05T BP1163 H13 43T BP1167 F05 19T BPI155 DO9 18T BP1151 F13 02T BP1180 DO5 13T BP1189 B09 46" BP1170 El3 55T 581196 C05 44T BP1194 NLO 50T BP1182 514 3 6T BP1172 NO 6 49T BP1183 Ill0 25T BP1156 014 56T BPI173 LO6 lo? BPI154 El0 12T BP1158 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 15 of 50

Figure 1.5 SURRY UNIT 2 - CYCLE 20 CONTROL ROD LOCATIONS R P N M L K J H G F E D C B A 180' 1

2 3

4 5

6 7

goo D C C D 270' 8 SA SB SB SA 9

~ ~ ~~ -

A B D C D B A 10 SB SB 11 C B B C 12 SA SA 13 A D A 14 15 0'

D = Control Bank D SB = Shutdown Bank SB C = Control Bank C SA = Shutdown Bank SA B = Control Bank B A = Control Bank A NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 16 of 50

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SECTION 2 CONTROL ROD DROP T I M MEASURlEMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tavg of 547 -r- 5 O F ) in order to verify that the time to the entry of the rod into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.12.C.1

[Ref. 41.

Surry Unit 2 Cycle 20 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 (IWI) system. The rod drop times were measured by withdrawing all banks to their fully withdrawn position and dropping all 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.

Data was previously acquired using the primary WI coil terminals (/1 & 12) for each rod.

Traces that printed from the Yokogawas were used to detennine initial quality, while binary output was saved to diskette for further analysis using ACRAWin32 software. The new methodology acquires data using the secondary RPI coil terminals (/3 & /4) on the CERF'I racks for each rod. Data is immediately saved to the rod drop test computer (RDTC) which computes the rod drop time automatically. Original data is also saved as an ASCII file and burned to CD-R.

Further details about the RDTC can be found in [Ref. 141.

A typical rod drop trace for S2C20 is pictured in Figure 2.1. The measured drop times for each control rod are recorded on Figure 2.2 in accordance with station procedure 2-NPT-RX-014. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C.l [Ref. 41 specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. This Technical Specification requires that the RCS is at hot, full flow condtions. These test results satisfied this technical limit as well as the administrative limit [Ref.

113 of 1.61 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region.

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Table 2.1 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME .

F-06 1.426 sec. 1 L-05 1.268 sec 1.304 sec.

A ROD F-06 1.426 sec. 1.313 sec.

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Figure 2.1 SURR.Y UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 20 of 50

Figure 2.2 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R P N M L K J H G F E D C B A 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 1 x.xxx I===> Rod drop time to dashpot entry (sec.)

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SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique [Ref. 21, [Ref. 51. 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 20, Control Bank B was used as the reference bank. Note that reference bank dilution rate was increased, for the first time at Surry Unit 2, to 1100 p c d h r from 600 pc&. This increase is justified in [Ref. 1.51 and is compatible with the RMAS system used in startup physics testing.

After completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor near critical and the reference bank fully inserted. Initial statepoint data for the rod swap maneuver were obtained with the reference bank at its fully inserted position and all other banks fully withdrawn, recording the core reactivity and moderator temperature. As recommended [Ref. lo], the test bank sequence used for rod swap was to exchange test bank with test bank, instead of returning to the initial condition after each test bank measurement (as done for previous cycles).

Test bank swaps proceed in sequential order from the 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. 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 fuIly withdrawn and the test bank was nearly inserted. The next step was to swap the rest of the test bank in by balancing the reactivity with the withdrawal of the reference bank, 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 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 22 of 50

condition. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the 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 then repeated for the remainder of the 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 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 Results and Evaluation 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 of worth greater than 600 pcm, and '100 pcm for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was within -0.3% 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 [Ref. 11 and the measured data from station procedure 2-NPT-RX-008 are plotted together in order to illustrate their agreement.

In summary, the measured rod worth values were satisfactory.

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Table 3.1 SURRY UNlT 2 - CYCLE 20 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

YlB - Reference C

(PCM) 1361.7 1081.9 743.8 (PCM) 1406.0 1061.8 748.4 (M-PYP X 100

-3.1

+1.9

-0.6 A 249.1 235.2 +5.9(a)

SB 1022.6 1051.O -2.7 SA 1019.8 994.9 +2.5 I Total Bank Worth 1I 5478.9 5497.4 -0.3 (a) M - P = 13.9 pcm NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page.24 of 50

Figure 3.1 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN I

4Predicted

+Measured 0 50 100 150 200 BANK POSITION (STEPS)

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Figure 3.2 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 0 50 100 150 200 250 BANK POSITION (STEPS)

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SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS 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 Appendur, the measured critical boron endpoint values were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.10.A [Ref. 41 regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

Boron Worth Coef'ficient 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, 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.

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Table 4.1 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 1997 2004 -7 B Bank In 1803.4 1797" +6.4 i

• 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.

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Table 4.2 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS BORON WORTH C O E m C E N T Measured Predicted Percent Boron Worth Boron Worth Difference (%)

(PCdPPm) (PCdPPd (M-P)/P x 100

-7.04 -7.03 +O. 14 NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page 30 of 50

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SECTION 5 TEMPERATURJ3 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 the RCS cooldown of -3.34F and RCS heatup of 3.15F.

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. Plots of reactivity versus temperature confirmed the statepoint method in calculating the measured ITC.

The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of k2 pc&. The measured ITC of -1.863 pcm/F meets the Core Operating Limits Report (COLR) 3.1.1 criterion [Ref. 91 that the moderator temperature coefficient (MTC) be less than or equal to +6.0 pcm/?F. When the Doppler temperature coefficient [Ref. 11 of -1.82 pcml?? and a 0.5 pcdF uncertainty are accounted for with the MTC limit, the MTC requirement is satisfied as long as the ITC is less than or equal to +3.68 pcm/F.

NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 32 of 50

Table 5.1 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS ISOTHEiRMAL TEMPERATURE COEFFICIENT

SUMMARY

TEMPERATURE BANK RANGE ("F)

POSITION ...._.._.._._...________._l.l.___..___l_....~.,

LOWER 1 UPPER (STEPS)

LIMIT LIMIT Dl207 -1.982 I/ -1.745 1 -1.863 -1.267 1 -0.596 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 33 of 50

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 20.

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. 31. 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. 71 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 1 was taken at 25.8% power to verify the radial power distribution (RPD) predictions at low power.

Figure 6.1 shows the measured RPDs from this flux map. Flux maps 2 and 3 were taken at 66.5%

and 99.98% 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

+4.0% in the 25.8% power map, -2.9% in the 66.5% power map, and -3.4% in the 99.98%

power map. The maximum quadrant power tilts for 25.8%, 66.5%, and 99.98% power maps were

+0.57% (1.0057), +0.57% (1.0057), and 4 . 6 7 % (1.0067), respectively. These power tilts were within the design tolerance of 2% (1.02).

NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page 34 of 50

The measured FQ(z)and FZ peaking factor values for the at-power flux maps were within the limits of COLR Sections 3.3 and 3.4 [Ref. 91, respectively. Flux Maps 1, 2, and 3 were used for power range detector calibration or were used to confirm existing calibrations. The flux map analyses are documented in [Ref. 71.

In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR [Ref. 91. It is therefore anticipated that the core will continue to operate safely throughout Cycle 20.

NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 35 of 50

Table 6.1 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Bum Peak FQ(z)Hot FrH Hot Core Fz No.

Bank Core Tilt (2) Axial Of Map Map Date up Power D .._._I.___._._

C h ~._,._._.I..._...

~ nFactor e I-,-.--.-.-

l ( 1) Channel

--r Factor

~ ___...I.I_ _.__I Max..__.I._.._._

~ Offset Thim-Description No. MWD/ (%) Steps Assy /Axial[

MTU lpointl Q F (z) i ASSY FZH j

Axial i Point; Fz I Max h (%)

I bles Low Power 1 05/23/05 2 25.8 170 H3 I 26 12.203 H3 1 1.545 26 i1.317 1.00571 SE 4 . 8 6 2 43 Int.Power(3) 2 05/24/05 15 66.51 186 H3 j 26 11.930 H3 1.500 23 11.186 1.00571 SE +1.216 43 Hot Full Power 3 05/29/05 176 99.98 I 228 52 i 19 1.808 D7 I 1.467 21 11.125 1.00671 SE +1.996 43 NOTES: Hot spot locations are specified by giving assembly Iocations (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 of the core). Flux Maps 1,2, and 3 were used for power range detector calibration or were used to confirm existing calibrations.

(1) FQ(z)includes a total uncertainty of 1.08 (2) CORE TILT - defined as the average quadrant power tilt from CECOR. "Max" refers to the maximum positive core tilt (QPTR > 1.0000).

(3) Int. Power - intermediate power flux map.

NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 36 of 50

Table 6.2 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PAEUMETERS WITH THEIR CORE OPERATING LIMITS Peak FQ(z)Hot FQ(z)Hot HF

! Hot Map Channel Factor* Channel Factor** Channel Factor (At Node of Mnimum Margin)

No. Meas. Limit Node Meas. Limit Node Margin Meas. Limit Margin

(%I (%I 1 2.203 4.582

.____"__I.___..._._.

~

26.__.I__.. .. 2.203

~ " ._~

4.582 26 51.92 1.545 1.907 ... 18.98

• 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 above is the maximum value of FQ(Z) in the core. The COLR [Ref. 91 limit listed above is evaluated at the plane of maximum FQ(z).

• • The value for FQ(z) listed above is the value at the plane of minimum margin. The minimum margin values listed above are the minimum percent difference between the measured values of FQ(z) and the COLR limit for each map.

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

NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page 37 of 50

Figure 6.1 SURRY UNIT 2- CYCLE 20 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 25.8% POWER MAP .SZ-I(-OIA . . . . ,.:':,  :. .. .,.: . CHMfNt 3

-. '-.I*.:. .

MEASURED AND PREDICTED ASSEMBLYW R P N M L K J H 0 F E D C B A

.. .239. -261. ..................

. MEASURED ..

1 PREDICTED MEASURED 238. -239.

.261. .241. . PREDICTED

.................. I

.. ,300. ,513. 1.053. .837. 1.054. 313. .298.

2 2

.302. -516. 1.061. -848. 1.063.

. -314. 1.082. 1.288. 1.262. 1.312. 1.262. 1.285. 1.076. .311.

315. .296.

3 . -309. 1-091. 1.293. 1.266. 1.345. 1.270. 1.283. 1.066. -301. 3

. .3f2. ,620. ,618. 1.143. 1.390. 1.332. 1.2%. 1.333. 1.388. 1.138. .610. .314.

4 .. -311. 1.163. 1.393. 1.326. 1.282. 1.325. 1.379. 1.123. .611, -312. 4

.. .304. 1.080. 1.138. 1.207. 1.284. 1.270. 1.285. 1.270. 1.283. 1.207. 1.143. 1.086. ,306.

5 5

.303. 1.076. 1.132. 1.189. 1.m. 1.258. 1.268. 1.257. 1.267.

. -515. 1.288. 1.387. 1.281. 1.155.- 1.285. 1.241. 1.285. 1.155. 1.282. 1.390. 1.291. .516.

1.178. 1.137. 1.0s. 294.

. -512. 1.282. 1.389. 1.302. 1.150. 1.267. 1.213. 1,270. 1.147. 1.275. 1.397. 1.300. ,522. 6 6

.. .ZS.

.238. 1.053. 1.262. 1.332. 1.268. 1.283. 1.179. 1.168. 1.177, 1.282, 1.268. 1.332. 1.263. 1.054. -238.

7 1.045. 1.248. 1,326. 1.267. 1.273. 1.155. 1.149. 7.167, 1.279- 1.274. 1.358. 3.202. 1.086. .w. 7

.. .258. .836. 1.312. 1.296. 1.284. 1.240. 1.166. .876. 1.162. 1.238. 1.283. 1.2%. 1.311. .835. .W.

8 1.155. .M9. 1.156. 1.238. 1.290. 1.309. 1.319. 8

-259. .831. 1.304. 1.289. 1.273. 1.231.

. .238. 1.054. 1.264. 1.333. 1.269. 1.282. 1.176. 1.161. 1.173. 1.280. 1.266. 1.330. 1.261. 1.052. -238.

.827. .258.

9 . ,238. 1.055- 1.265. 1.325. 1.248. 1.275. 1.180. 1.169. 1.170. 1.291. 1.275. 1.341. 1-267. 1.052. ,238. 9

.. -516. 1.291. 1.390. 1.282. 1.155. 2.283. 1.238. 1.281. 1.153. 1.279. 1.386. 1.286. 315.

x o . 1.311. 1.388. 1.269. 1.155. 1.312. 1.249. 1.289. 1.m. 1.285. 3.401. 1.293.

10

- -306. 1.086. 1.143. 1.207. 1.283. 1.269. 1.283. 1.267. 1.281. 1.206. 1.137. 1.079. .304.

.514. 10 11 . .307. 1.087. 1.133. 1.182. 1.277. 1.277. 1.289. 1.279. 1.299. 1.198. 1.135. 1.079. .3of. 11 12 ,.-.........................................................................................

-314.

-305.

.618. 1.138.

-611. 1.126.

1.387.

1.383.

1.332.

1.336.

1.295.

1.305.

1.330.

1.346.

1.388.

1.408.

1.141.

1.145.

,617. -311.

,604. .305. 12 13 ..........................................................................

m -311. 1.075. 1.28s. 1.261. 1.320. 1.260.

.308. 1.068- 1.282. 1.265. 1.322. 1.283-1.286.

1.322-1.481.

1.098.

e314.

.314. 13

. -298. 513. 1.053. -836. 1.052. .512. "300.

. 14 14

.293. -512- 1.056.

.. 239.

.845.

,261.

1.075.

.=a.

S25. .305.

15 15

.233. ,262. -242.

A P N M L K J H G F E D C B A Summarv:

Map No: S2-20-01 Control Rod Position:

D Bank at 170 Steps Date: 05/23/2005 FQ(z) = 2.203 F,", = 1.545 QPTR: 0.9972 0.9984 1

Power: 25.8%

0.9987 1.0057 Fz = 1.317 Axial Offset (%) = 4 . 8 6 2 Burnup = 2 MwD/MTu NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 38 of 50

Figure 6.2 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 70% POWER

.. .. .. ... .. .. . .+.: . "

. .+;$.;: .: ...

.:. ATTACHMENT 3 YAP .se-K-o2A: ..... ..+! ...'i-

. z , . .-:.. '. .

., ...'i;........ .:.. ,

? <

, , . .:. j

. . .. L

.,:?? L I i,... . . . MEASURED AND PREDICTED ASSRBLYUISE WUER DISTRIWIION R P N M L F J H G F E D C 6 A

. PREDICTED .

. .254. ,282. .255.

1 . MASURED .

.................. . .256. .284. .257.

PREDICTED MEASURED 1

.. AO.

.317.

.szs.

.528.

7.065.

1.076.

.a74.

,882.

1.066.

1.672,

.m.

-525.

-308.

.306. 2 2

.. .325. 1.074. 1.262. 1.247. 1.297. 1.247. 1.261. 1.068. -323.

.320. 1.076. 1.268. 1.261. 1.314. 1.252. 1.259. 1.061. -313. 3 3

.. .323.

.3z3. ,631. 1.130. 1.362. 1.307. i.278. 1.308. 1,361. 1.126. .m. -325.

4

-630. 1.134. 1.362. 1.304. 1.266. 1.302. 1.359. 1.117. .627. ,325:

.. -314. 1.072.

.314. 1.071.

1.125.

1.121.

1.200.

1,188.

1.275.

1.267.

1.264.

1.35.

1.278.

1.~67. 1.257.

1.265. 1.275.

1.266, 1.200.

1.180.

1.129.

1-131. 1.078.

1.077. -316.

.309. 5 5

.. .527. 1.262. 1.360. 1.273. 1.193. 1.296. 1.248. 1.296. 1.193. 1.273. 1.362. 1.265. .528.

.532. 6 6

.528. 1.264. 1.358. 1.272. 1.183. 1.281. 1.230.

. -254. 1.065. 1.247. 1.307. 1.263. 1.295. 1.196. 1.181. 1.194. 1.293. 1.263. 1.307. 1.248. 1.066. .254.

1.287. 1.189. 1.269. 1.369. 1.273.

7 ..........................................................................................................................

-254. 1.069. 1.254. 1.302. 1.251. 1.280. 1.173. 1.167. 1.187. 1.290. 1.267. 1.325. 1.261. 1.086. .258. 7 8

. -279.

276.

-873. 1.297.

,872. 1.296.

1.27E.

1.270.

1.278.

1.248.

1.246.

1.232.

1.179.

1.168.

.903. 1.176. 1.245.

.898. 1.174. 1.239.

1.277.

1.281.

1.277. 1.296.

1.287. 1.303.

-873.

.869.

.279.

-278. 8

. 3 4 . 1.066. 1.248. 1.308. 1.263. 1.294. 1.793. 1.175. 1,190. 1.292. 1.262. 1.306. 1.246. 1.065- -254.

9 .............................................................................................................................

.m. 1.068. 1.250. 1.307. 1.273. 1.292. 1.793. 1 . m . 1.203. 1.304. 1.~70. 1.315. 1.253. 1.067. .252. 9 10 ..........................................................................................................

4 -528. 1.265.

-529. 1.270.

1.362.

1.359.

1.273.

1.267.

1.193.

1.189.

1.295. .1.245; 1.304. 1.250.

1.293.

1.303.

1.191.

1.498.

1.272. 1.359.

1.277. 1.374. .1.268.

1.262. ,527.

-528. 10 11

.. ~-315. 1 6 . 1.m.1.129. 1.200. 1.275- 1.264.

i.on. 1.~18. 1.175. 1.265. 1.264. 1.275. 1.271. 1.2~16. 1.194. 1 . m 1.071.

1.277. 2.263. 1.274. 1.199. 1.125. 7.071. .m4.

......................................................................................................... .314. 11 12 ...........................................................................................

.33.

,318.

.631. 1.125.

,624. 1.112, 1.360.

1.353.

1.307.

1.306.

1.277.

1.283.

1.306.

1.317.

1.360.

1.377.

1.129.

1.f32.

.631.

.618.

.3P.

,315. 12

. 322. 1.067. 1.260. 1.246. 1.296. 1.246. 1.261. I.073. ,325.

13

-320. 1.060. 1.256. 1.249. 1.305.

.. .308. 324. 1.070. .874. 1.091.

.525. 1.066.

1.267.

1.065.

1.292.

.524.

t.088.

.310.

.326. 13 14 14 304.

.. .253. -284. ..Z9.

.255.

.883.

282. Zk.

.536. .315.

15 15 R P N M L K J H G F E D C 6 A Control Rod Position: FQ(z) = 1.930 QPTR: 0.9973 0.9997 D Bank at 186 Steps F:", = 1.500 0.9974 1.0057 Fz = 1.186 Burnup = 15 MWD/MTU Axial Offset (%) = +1.216 NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 39 of 50

Figure 6.3 SURRY UNIT 2 - CYCLE 20 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 99.98% POWER MAP S2-K-03A A T l ' A m 3 MEASURED AM) PREDICTED A6SEMBLWISE WWER DISTRIBUTXON R P N . M L K J H G F B D C B A

........_.........I ......................... ............... <.,

. PREDICTED , . .267. .302. .269. . PRFDICrED .

1 . MEASURED . . .269. .303. .270. . HERSDRED . 1

,......-.......,.. ................................................. ((...... ...._.._..........

. .312. .s20. 1.063. .92a. 1.070. .sm. .3101 2 . .312. .S31. 2.079. ,936. 1.077. .531. .310. 2

. . . . . . . . . . . . . . . . . . . . . . . I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. .m.1.045. 1.226. 1.230. 1.282. 1.230. 1 . 2 2 5 . 1.010. .325.

3 . .322. 1.047. 1.231. 1.243. 1.296. 1.235. 1.226. 1.037. .322. 3

. . 3 x . .m.1.103. 1.332. 1.282. 1.266. 1.283. 1.131. 1.100. . m 2 . .m.

4 . ,324. .630. 1.105. 1.332. 1.280. 1.256. 1.280. 1.330. 1.092. .630. .327. 4

. .315. 1.044. 1.099. 1.192. 1.275. 1.271. 1.283. 1.271. 1.275. 1 . 1 9 1 . 1.103. 1 . 0 4 8 . .317.

5 . .314. 1.039. 1.092. 1.181. 1.268. 1.265. 1.277. 1.267. 1.269. 1.174. 1.102. 1.047. .307. 5

. . 5 3 0 . 1.226. 1.330. 1.273. 1.276. 1.326. 1.267. 1.327. 1.276. 1.273. 1.332. 1.229. .530.

6 . .528. 1.222, 1.324. 1.271. 1.269- 1.316. 1.260. 1.324. 1.279. 1.272. 1.339. 3.236. .534. 6

.2a. 1.069. 1.230. 1.282. 1.269. 1.315. 1.224. 1.199. 1.222. 1.323. 1.269. 1.282. 1.231. 1.070. .z67.

7 . .267. 1.066. 1.227. 1.272. 1.257. 1.311. 1.205. 1.190. 1.220. 1.326. 1.277. 1.303. 1.245. 1.089. .271. 7

,.......... 1 . . . . . . . . . . I . . . . . . . . . . . . . . . . . . . . . .............................................................................

0 . .299.

.3OO.

.927. 1.282.

.924. 1.274.

1.265.

1.252.

1.282.

1.255.

1.265.

1.252.

1.196.

1.186.

.936. 1.193.

.932. 1.193.

1.264.

1.263.

1.281.

1.290.

1.265.

1.277.

1.282.

1.289.

.926.

.921.

,299.

.298. 8 9

.. .268.

,267.

I .

1.070.

1.066.

1.231.

1.225.

1.283.

1.272.

1.270- 1.324. 1.221.

1.261. 1.317. 1.221.

1.193.

1.195.

1.219.

1.227.

3.312.

1.341.

1.268.

1.281.

1.281.

1.293.

1.230.

1.238.

1.068.

1.071.

,267.

-265. 9

.....~..........................................................*............................._.............,............

. .530. 1.229. 1.332. 1.273. 1.276. 1.325. 1.264. 1.324. 1.274. 1.272. 1.129. 1.226. .529.

10 . .528. 1.225. 1.321- 1.260. 1.272. 1.338. 1.272. 1.335. 1.289. 1 . 2 8 2 . 1.349. 1.236. . 5 3 2 . 10 11

.317. 1.048. 1.103. 1.192. 1.275. 1.271. 1.282. 1.269. 1.274. 1.191. 1.099.

.314. 1.037. 1.087. 1.166. 1.265. 1.273. 1.285. 1.260. 1.289. 1.130.

1.099.

1.043.

1.045.

... I . . . .

.315.

................................................................................................. ...*.316. 11

. .328. .632. 1.100. 1.330. 1.282. 2.265. 1.281. 1.331. 1.103. .632. .326. ....

12 . .317. .m.1 . 0 8 5 . 1.324. 1.183. 1.272. 1.293. 1.346. 1.104. .as. .3w. 12

. ,325. 1.040. 1.724. 1.230. 1.282. 1.230. 1.226. 1.005. .329.

I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . .

13 . .m.1.031. 1.221. 1.233. 1.asi. 1.247. 1.250. 1.056. .327. 13

. ,310. .m. 1.070. .92a. 1.069. .527. .m.

14 . .305. .537. 1 .ox. . 9 m . 1.091. .537. .316, 14 15

.. .268. ,270.

.302.

.305.

.267.

.277. 15 R P N M L K J I1 0 P B D C B A Summary:

Map No: S2-20-03 Control Rod Position:

D Bank at 228 Steps Date: 05/29/2005 F&T) = 1.808 F,", = 1.467 QPTR i:i9zz I L:A)i; Power: 99.98%

Fz = 1.125 Axial Offset (70) = +1.996 Burnup = 176 h4WDMTU NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 40 of 50

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NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 41 of 50

SECTION 7 REFERENCES

1. R. W. Twitchell, "Surry Unit 2 Cycle 20 Design Report", Technical Report NE-1446, Rev. 0, May 2005

2. T. R. Ross and W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Techque," Topical Report VEP-FRD-36AYDecember 1980

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

4. Surry Units 1 and 2 Technical Specifications, Sections 3.12.C.1,4.10.A.

5. Letter from W. L. Stewart (Virginia Power) to the USNRC, "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

6. S. B. Rosenfelder, "Surry 2 Cycle 20 TOTE Calculations", Calculation PM-1082, Rev. 0, May 2005

7. R. A. Hall et al, "Surry 2, Cycle 20 flux Map Analysis", Calculation PM-1081, Rev. 0, and Addenda A and B, May 2005

8. T. R. Flowers, "Reload Safety Evaluation Surry 2 Cycle 20 Pattern BP", Technical Report NE-1442, Rev. 0, March 2005

9. Appendix to Technical Report NE-1442 "Reload Safety Evaluation, Surry 2 Cycle 20 Pattern BP", "Core Operating Limits Report Surry 2 Cycle 20 Pattern BPI' Rev. 0, March 2005

10. P. D. Banning, "Implementation of RMAS for Startup Physics Testing", Calculation PM-0824, Rev. 0, March 2000

11. 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", Eng Transmittal ET-NAF-97-0197, Rev. 0, August 21, 1997

12. C. D. Clemens, "Surry Unit 2 Cycle 20 Core Loading Plan", Eng Transmittal ET-NAF 0003, January 2005 NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page 42 of 50

13. T. R. Flowers, Reload Safety Evaluation Suny 2 Cycle 18 Pattern GW, Technical Report NE-1310, Rev. 0, February 2002

14. N.A. Yonker, Validation of Rod Drop Test Computer for Hot Rod Drop Analysis, Calculation PM-1044, Rev. 0, November 2004

15. R. W. Twitchell, Implementation of VEP-FRD-36-Rev. 0.2-A for Surry Units 1 and 2, Eng Transmittal ET-NAF-04-0075, September 2004

16. S . B. Rosenfelder and S. S . Kere, RMAS v6 Verification, Calculation PM-1075, Rev. 0, May 2005 NE-1454 Rev. 0 S2C20 Startup Physics Tests Report Page 43 of 50

APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-1454Rev. 0 S2C20 Startup Physics Tests Report Page 44 of 50

ii; -

Surry Power Station Unit 2 Cycle 20 Startup Physivs Test Summarv Sheet Formal Tests (Page1 of 6) 5 P

Design Criteria Date/

Acceptake Time of Prepared 0

References 1.) NE-1446, Rev. 0 2)Memorandum from C.T. Snow to E.J. tozito, dated June 27,1980 3.)WCAP-7905, Rw. 1 4.) ET-NAF-05-0033, RW. 0

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I References 1.) NE-1446, hev. 0 I -No I P

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'3.)WCAP-7 ,5, Rev. 1 4.) ET-NAF-O&0033, Rev. 0 VI 0

$wry Power Station Unit 2 Cycle 20 Starkip PP - s Test -

Summary Sheet Fo;rj?al Tests (Page 3 of 6:

r I Design Danw Crfterla Acceptance Time a Prepared I I I [the cantrol rods at the rod ImWtlcm limits. t I I References 1,I NE-1448,Rev. 0 2.j Wlemorandwri from C.T. Snowto.E,J;Loztto, dated June 27,1980 3.) WCAP-7905, Rev. 1 4.) ET-NAF-05-0033,Rev, 0

2.) Memorandum from C.T. Snowio EJ. l=ozito,datedqune 27,1980 3.)WCAP-7905, RW. 1 .. ..

4.) ET-NAF-05-0033, Rev. Q .. t . .,

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,Total Heat Flux Hot Channe4 Factor, F W ) -

Fpor I.&Ob NIA F&)S(2.WPJK(Z) [COLR 3.31 NfA bf yes Mat@ to COLR LlmlL -No MaxtmumPositive moore Qkdralit POrvufitt TIIb 1. 0 0 6 7 I 5 I -023 References 1.) NE-1446, Rev. 0 N/A

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-No NIA 2.) M8mNafldUm from C.T. Snow to E.J. Lozito, dated June 27,1980 3.) WCAP-7905, Rev. 1 4.) ET-NAF-05-0033, Rev. 0

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0 2.) Memorandum from C.T. Snow to E.J. lozlio, dated June 27, 1980 3.) WCAP-7905, Rev. 1 4.)ET-NAF-05-0033, Rev. 0