ML073040014

Cycle 21 Startup Physics Tests Report

ML073040014
Person / Time
Site:	Surry
Issue date:	08/17/2006
From:	Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation, Region 2 Administrator
References
06-529
Download: ML073040014 (54)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 17, 2006 United States Nuclear Regulatory Commission Serial No.: 06-529 Regional Administrator - Region II NLOS/vlh Sam Nunn Atlanta Federal Center Docket No.: 50-280 Suite 23 T85 License No.: DPR-32 61 Forsyth Street, SW Atlanta, Georgia 30303-8931 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 CYCLE 21 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-1487, Revision 0, entitled "Surry Unit 1, Cycle 21 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after the initial criticality of Cycle 21 on May 25, 2006. The results of the physics tests were within the applicable Technical Specification limits.

Please note that although this report is for Surry, the reference to an issue during "N1 C1 9" startup testing on page 23 of the enclosure refers to North Anna Unit 1 Cycle 19. 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

Serial No.06-529 Surry 1 Cycle 21 Startup Physics Tests Report, Rev. 0 cc page 1 of 1 cc: U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Mr. S. R. Monarque U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. S. P. Lingam U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. N. P. Garrett NRC Senior Resident Inspector Surry Power Station

Technical Report Cover Sheet Page 1 of 51 Rev. 0

~Domtinion-I NDM31 Atahmn-TECHNICAL REPORT No. NE-1487 SURRY UNIT 1, CYCLE 21 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING DOMINION JULY 2006 Prepared By:-z 6 6~

J. B. Duo Date Reviewed, By.

ýýes! aros Date Reviewed By: 7/ o/o6 Date Approved By: 7/Zo /0 T'A' c *'her 'Date QA Category: Nuclear Safety Related Key Words: S1iC21, S1 CL, SPS1, Startup Physics Test Report, SPTR (June 2006)

CLASSIFICATION/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.

NE-1487 Rev. 0 S 1C21 StartupPhysics Tests Report Page 2 of 51

TABLE OF CONTENTS CLASSIFICATION/DIS CLAIM ER ........................................ ............................................... 2 TABLE OF CONTENTS .................................................................................................. 3 LIST O F TABLES ................................................................................................................... 4 LIST O F FIGU RES ................................................................................................................... 5 PRE FA CE .................................................................................................................................. 6 SECTION 1 - INTRODUCTION AND

SUMMARY

............................ 7 SECTION 2 - CONTROL ROD DROP TIME MEASUREMENTS ............................. 17 SECTION 3 - CONTROL ROD BANK WORTH MEASUREMENTS ....................... 23 SECTION 4 - BORON ENDPOINT AND WORTH MEASUREMENTS .................... 29 SECTION 5 - TEMPERATURE COEFFICIENT MEASUREMENT ......................... 33 SECTION 6- POWER DISTRIBUTION MEASUREMENTS ..................................... 35 SECTION 7- REFERENCES ........................................... 43 APPENDIX - STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS ... 45 NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 3 of 51

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

..................................... 25 TABLE 4.1 - BORON ENDPOINTS

SUMMARY

............................ 30 TABLE 4.2 - BORON WORTH COEFFICIENT ............................. 31 TABLE 5.1 ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

....... 34 TABLE 6.1 - INCORE FLUX MAP

SUMMARY

............................. 37 TABLE 6.2 - COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS ...................................... 38 NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 4 of 51

LIST OF FIGURES FIGURE 1.1 - CORE LOADING MAP .......................................................................... 12 FIGURE 1.2 - BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS ...................... 13 FIGURE 1.3 - AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS ........... 14 FIGURE 1.4 - BURNABLE POISON 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 D INTEGRAL ROD WORTH - HZP ................... *..... 26 FIGURE 3.2 CONTROL BANK D DIFFERENTIAL ROD WORTH - HZP ............. 27 FIGURE 6.1 - ASSEMBLYWISE POWER DISTRIBUTION 28.2% POWER ....... 39 FIGURE 6.2 - ASSEMBLYWISE POWER DISTRIBUTION-69.7% POWER ....... 40 FIGURE 6.3 - ASSEMBLYWISE POWER DISTRIBUTION 99.97% POWER ...... 41 NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 5 of 51

PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 1, Cycle 21 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 1, Cycle 21 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 Dominion's Nuclear Analysis 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.

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 6 of 51

SECTION 1 - INTRODUCTION AND

SUMMARY

On 23 April 2006, Unit No. 1 of the Surry Power Station shut down for its twentieth refueling [Ref. 1]. During this shutdown, 62 of the 157 fuel assemblies in the core were replaced with 60 fresh Batch 23 assemblies and two Batch 18 assemblies last irradiated in $2C17 [Ref. 8].

The Cycle 21 core consists of 11 sub-batches of fuel: five fresh batches (S 1/23A, S 1/23B, S 1/23C, S 1/23D, and S 1/23E), two once-burned batches (S 1/22A and S 1/22B), and four twice-burned batches (S1/21A, S1/21B, $2/18B, and $2/18C). Batches S1/21, S1/22, and S1/23 are of the SIF/P+ZIRLO+2 fuel type. Batch S2/18 is of the SIF/P+ZIRLO design [Ref. 1].

Both Westinghouse SIF/P+ZIRLO and SIF/P+ZIRLO+2 fuel assembly designs incorporate ZIRLO fuel cladding, intermediate grids, guide tubes, instrumentation tubes, and debris resistance features that are part of the Westinghouse PERFORMANCE+ design [Ref. 1]..

The SIF/P+ZIRLO+2 design used in batches S 1/23A, S 1/23B, S 1/23C, S 1/23D, S 1/23E, S 1/22A,

$1/22B, S1/21A, and S1/21B is similar to the SIF/P+ZIRLO design used in batches $2/18B and

$2/18C. The differences in the P+ZIRLO+2 design include the following [Ref. 13]: 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+ZIRLO and SIF/P+ZIRLO+2 fuel is the same.

This is the first Surry cycle to use Westinghouse's IFBA fuel product. All physical changes for IFBA are internal to the fuel rod cladding, with no apparent difference from existing fuel assemblies in any external features. The IFBA design involves the application of a thin (0.0003125 inch) coating of ZrB 2 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).

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 7 of 51

This additional void space helps accommodate the helium gas that accumulates from neutron absorption in ZrB2 . IEFBA rods generate more internal gas during operation because neutron absorption in the ZrB 2 coating creates helium gas in addition to the fission gas created during irradiation of the fuel. Therefore, the initial pressure is set lower so the internal pressure early in lifetime may be lower [Ref. 8].

In addition to the IFBA rods, several discrete burnable poison rod assemblies were also used for S1C21. The burnable poison (BP) rod design for this cycle is B 4 C in Alumina which is available in various B 4C enrichments [Ref. 1]. Flux suppression inserts (FSIs) have been removed from Surry I for this cycle (the last eight Surry 1 cycles had FSIs to reduce neutron fluence at specific reactor vessel weld locations) [Ref. 8]. In conjunction with the FSI removal, the active burnable absorber length for Surry 1 Was changed from the 135.5 inch design (which was compatible with the FSIs) to the 127.1 inch design similar to the BP product currently in use at Surry 2 [Ref. 5].

The S1C21 full core loading plan [Ref. 12] is given in Figure 1.1 and the beginning of cycle fuel assembly burnups [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 and the Cycle 21 burnable poison locations are detailed in Figure 1.4. Figure 1.5 identifies the location and number of control rods in the Cycle 21 core [Ref. 1].

According to the Startup Physics logs, the Cycle 21 core achieved initial criticality on 25 May 2006 at 02:04. 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 was used for S1C21 Startup Physics Testing. The tests performed are the same as in previous cycles. A summary of the 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. 11].

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 8 of 51

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

[Ref. 16], incorporating the recommendations of [Ref 10]. The sum of the individual measured control rod bank worths was within -2.2% of the design prediction. The reference bank (Control Bank D) worth was within -2.6% of its design prediction (corresponding to 31.7 pcm). The other control rod banks were within +/-3.2% (-3.2% was recorded for Bank B, which corresponds to a difference of 38.1 pcm) of the design predictions, which was the greatest percent difference 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 -9.8 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 10% for the sum of the individual control rod bank worths.

Measured critical boron concentrations for two control bank configurations (ARO and D-bank in) were within 7.3 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%Ak/k of the design prediction. The boron worth coefficient measurement was within +1.75% 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 -0.416 pcm/F of the design prediction. This result is within the design tolerance of +/-2.0 pcm/°F.

Core power distributions, as measured by startup flux mapping, were within established design tolerances. The measured core power distributions were within +5.6% of the design predictions, where a -5.6% maximum difference occurred in the 28.2% power map. The heat flux hotchanelfacors hot channel factors, FQZandentalp FQ(Z), and enthalpy rie hot cannl rise ht fctosFH channel factors, N I 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 < 1.02).

N-E-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 9 of 51

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 286074 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, NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 10 of 51

Table 1.1 SURRY UNIT 1 - CYCLE 21 CHRONOLOGY OF TESTS Reference Test Date Time I Power Procedure Hot Rod Drop-Hot Full Flow 05/23/06 1446 HSD 1-NPT-RX-014 Reactivity Computer Checkout 05/25/06 0249 HZP NPT-RX-008 Boron Endpoint - ARO 05/25/06 0249 HZP 1-NPT-RX-008 Zero Power Testing Range 05/25/06 0249 HZP 1-NPT-RX-008 Boron Worth Coefficient 05/25/06 0249 HZP 1-NPT-RX-008 Temperature Coefficient - ARO 05/25/06 0325 HZP 1-NPT-RX-008 Bank D Worth 05/25/06 0419 HZP 1-NPT-RX-008 Boron Endpoint - D in 05/25/06 0541 HZP 1-NPT-RX-008 Bank A Worth - Rod Swap 05/25/06 0552 HZP 1-NPT-RX-008 Bank C Worth - Rod Swap 05/25/06 0559 HZP 1-NPT-RX-008 Bank SA Worth - Rod Swap 05/25/06 0613 HZP 1-NPT-RX-008 Bank B Worth - Rod Swap 05/25/06 0638 HZP 1-NPT-RX-008 Bank SB Worth - Rod Swap 05/25/06 0626 HZP 1-NPT-RX-008 Total Rod Worth 05/25/06 0419 HZP 1-NPT-RX-008 Flux Map - less than 30% Power 05/27/06 0211 28.2% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT-RX-005 Flux Map.-65% - 75% Power 05/27/06 2111 69.7% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT-RX-005 Flux Map - 95% - 100% Power 06/02/06 0859 99.97% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT-RX-005 RCS Flow Measurement 06/05/06 1400 HFP 1-NPT-RX-009 NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 11 of 51

Figure 1.1 SURRY UNIT 1 - CYCLE 21 CORE LOADING MAP SURRY UNIT 1 - CYCLE 21 FULL CORE LOADING PLAN PACM1 of 2 REVISION NO2. I VEP-25ES-NAF A a C n 8 F G 14 J K 5L M W P P I.5 208 1 4SF, 1 068 RCC 5P .RCC 5P RCCC 14 29r 43F 55H 430 51H. 28F 399 ....

NO3TH 3P RCC 208 ý 3p 13 28 4914 10H4 0514 3814 H 0441M 41 14C 1CC 14CC. 1CC 12 26P 4214 3714 32G 19(; 150 12G R4.C2 22H _ 444M 40, 3P," ROC 20P RCe 3P 11 518F 56H 20H 070 49b 23G 3511 16G 580 260 241H 60H 231 RCC RCC RCC RCC RCc RCC 14CC 10 48F 11H 520 51G 40G 29H 290 30H 370 6004 36G3 1211 428 F~II__ R1CC RC RCC ACC 9 06H 200 110 32H 020 440 039 26H 280 180 01H 54H 37F 273I RCC 20P 20P RCC RC- 20P - 20P 5RCC 8 20I3114 390 560 528 371H 250 33H 380 59G 27m 31G 34G 36H 080 39n4 5P ReC RCC RCC 1RCC 7 319 510"R021H 100 05G 2714 240 540 22( 25*4 27. 170 08H 48H 23F RCC RCC IRCC RCC RCC RCC RCC 6 27P 16H 35G 460 45G 31H 5003 28H 48G 53G 470 1.51 571n 3P 1,CC "20? RCC 3P 56F1 461 2314 21G 570. 09G 402 0P06 30G 0D3 21IH 59H I49F 14CC RCC RCC RCC 35F 43H4 29M4 4IG 130 14G 04G 33G 18H 42H 46F MOORE85DEVICE DESCRIPTIO4NS: 3P RCC 20P RCC 38 3 RCC- FULL LENGTH COMROL AD0D 540 52H 14H 03H 34H 07H 0914 57 H 418 3P- 3 DURNhUL2 POXS0N ROD CLUSTER RCC 5P RCC 5P ACC 2 5P- 5 B1*B4LE P* WN ROD CEtT8 208-- 20 HURNMIX,14P00 RO0 CI-lTLIR 34F 47F 45H 550 50HI 36 848 1

3214 18DOI Prepared , .. h dl-Dat 1 Crcncuence By: ______Pate:____

Reviewed By, t ate! Ph Approved By: t. SL/1104 Appxoved By: Date; 5i NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 12 of 51

Figure 1.2 SURRY UNIT 1 - CYCLE 21 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R P / N H L. K J H G F E fl C B A 1 I 41.441.33.821 41.501 ASURED I I 41.691 33.711 41.701 j PREDICTED I 2 I 34.521 38.791 0.001 17.711 0.001 38.731 34.121 S34.471 38.73! 0.001 17.821 0.001 38.751 34.45I 3 1 43.021 0.001 0.001 0.001 0.001 0.001 0.001 0.001 43.031 I 43.051 0.OOj 0.001 0.001 0.001 0.001 0.001 0.00o 43.051 4 1 43.071 0.001 0.001 22.111 22.401 22.201 22.511 22.391 0.001 0.001 43.071 1 43.041 0.00] 0.001 22.11! 22.401 21.941 22.411 22.131 0.001 0.001 43.041 5 1 37.82! 0..001 0.00! 22.05! 17.92! 23.21! 0.001 23.17! 17.74! 21.951 0.00! 0.00! 38.02!

138.131 0.001 0.00! 22.11! 17.881 23.241 0.00! 23.221 17.831 22.121 0.00! 0.00! 38.121 6 1 37.81f 0.00( 22.50! 17.89( 20.46! 0.001 20.511 0.001 20.541 17.85! 22.30f 0.00! 38.861 1 37.961 0.001 22.111 17.811 20.471 0.001 20.551 0.001 20.531 17.831 22.101 0.001 38.781 7 I 43.401 0.00! 0.00! 22.501 23.201 0.00! 22.03! 17.781 22.10! 0.001 23.301 22.391 0.00! 0.001 42.98!

1 42.921 0.001 0.001 22.42! 23.23( 0.001 22.15! 17.77! 22.151 0.00! 23.251 22.421 o.0ol 0.001 42.92j 8 1 33.721 17.701 0.001 21,951 0.001 20.621 17.511 38.221 17.671 20.541 0.00! 22.041 0.001 18.211 34.041 I 33.711 17:771 0.001 21.911 0.001 20.491 17.711 37.741 17.711 20.481 0.00! 21.91! 0.001 17.771 33.711 9 1 43.17! 0.00! 0.001 22.501 23.25! 0:001 22.061 17.811 22.42! 0.001 23.271 22.63! 0.00! 0.001 43.341 1 42.921 0.001. 0.001 22.421 23.25! 0.001 22.141 17.77! 22.16! 0.001 23.23! 22.42! 0.00! 0.00! 42.92!

0 .38.93 0.001 22.37! 18.01! 20.60j 0.00! 20.43! 0.00! 20.571 18.06! 22.10! 0.00! 38.38!

1 38.781 0.001 22.10! 17.83! 20.53! .0.001 20.551 .0.00! 20.471 17.811 22.10! 0.00! 38.80!

11 I 38.181 0.001 0.001 22.00 17.841 23.241 0.001 23.351 17.921 21.951 0.00! 0.001 38.041 I 38.171 0.001 0.001 22.11! 17.831 23.22! 0.00! 23.25[ 17.88! 22.11! 0.001 0.00! 38.16!

1 2 1 43.091 0.00! 0.00! 22.431 22.26! 22.131 22.36! 22.191 0.001 0.001 43.11!

1 43.04! 0.001 0.00! 22.12! 22.411 21.941 22.40! 22.111 0.00! 0.001 43.04!

3 1 43.091 0.001 0.001 0.001 0.001 0.00! 0.00! 0.001 43.211 I 43.051 0.001 0.00! 0.001 0.00! 0.00! 0.001 0.00! 43.051 1

4 1 34.33[ 38.92! 0.001 17.80! 0.00! 38.561 34.31!

I 34.45 38.751 0.00! 17.821 0.00! 38.731 34.471 1

15 1.41.551 33.711 41.44!

I 41.701 33.71! 41.70!

R P . N M L K J H G F D C B NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 13 of 51

Figure 1.3 SURRY UNIT 1 - CYCLE 21 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R P N M L K J H G F E D C B A IJMDH- 1 2

MD t t 4 ~-+ t-1 I MD MD 3 MD MD MD 4

MD MD MD 5

IlMDj I MD( IMD [III D MDI IMD 6

MD MD MD MD MD MD MD MD 7 8

MD MD MD MD MD MD 9

MD MD MD MD 10 MD MD MD MD II MD__ MD_MD1 MD I 11 12 MD MD MD IMD

-4 MD + 4 + + MD MD 13 MD MD 14 MD MD +

4 4 4 15 IMDI MD - Moveable Detector

• • - Locations Not Used For Flux Map 1 for S1C21

• - Locations Not Used For Flux Map 1, 2, or 3 for S1C21 NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 14 of 51

Figure 1.4 SURRY UNIT 1 - CYCLE 21 BURNABLE POISON LOCATIONS SURRY UNIT I - CYCLE 21 FULL CORE LOADING PLAN REVISION NO. 1 PAGE 2 of 2 VEP-1WI.S--ff BP CORE LOCATIOnS CORE COEASSY COR-'E ASSY BP OORE ASSY BP LOC 12) I-nC ID ID LOC ID ID G14 14 5511 11P1215 1109- 51 I1214 COs 46H BF1219 J14 B2'12 13 P09 *5411 9E1212 HOS 40H DPI201 1313 13 4911 11P1223 Cos 3711 BP12 05 "IS 591 BP1218 H13 113 38H BP1207 B08 3311 SP1204 203 52H BP1217 L13 LI 47H Los 3611 W.1203 103 3411 B51200 L03 57-H BP1216 C11 56f Sli 140? 3911 5.9-202 till 111 3511 ZP12 06 1107 5511 SuP111 G02 45A S11210 Nil 111 6011 11P1220 PD7 48H1 ,6,1209 J02 501H BP1208 Prepared By: Dt:Conv~rence 13y: __________

ReVieWed By. Da~teT/4 App~rnw d -By: Date: sfh/oke Approv~ed By: r' mt Date:

NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 15 of 51

Figure 1.5 SURRY UNIT 1 - CYCLE 21 CONTROL ROD LOCATIONS R P N M L K i H G F E D C B A 1800 7 1 A D A 2 SA SA 3 C B B C 4 S [SB SB 5 A B D C D B A 6 SA SB SB SA 7 90o D C C D 270o 8 SA SB SB SA 9 A B D C D B A 10 F1

____ ___[S C

B I ___I___I___

B B iC 11 12 SA SA 13 A D A 14 15 00 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-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 16 of 51

SECTION 2 - CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured in hot shutdown with three RCPs in operation (full flow) and with Tve greater than 530 F as per 1-NPT-RX-014. This verified that the time to the entry of the rod into the dashpot was less than or equal to the maximum allowed Technical Specification 3.12.C. 1 [Ref. 4].

Surry Unit 1 Cycle 21 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 into the core by opening the reactor trip breakers. This allowed the rods to drop into the core as they would during a plant trip.

Data prior to SIC20 was previously acquired using the primary RPI coil terminals (/1 &

/2) for each rod. Traces that printed from the Yokogawas were used to determine 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 CERPI 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. 14].

As shown on the typical rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by quick increase of voltage. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a sharp voltage decrease. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. In each trace, there should be an evident oscillation in the voltage curve after it has reached that bottom of the dashpot. This "bounce" indicates that the rod has not gotten stuck in the dashpot. Subsequent variations in rod drop trades are caused by rod bouncing.

NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 17 of 51

The measured drop times for each control rod are recorded on Figure 2.2 in accordance with station procedure 1-NPT-RX-014. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C. 1 [Ref. 4] specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 seconds for all rods.

These test results satisfied this technical limit as well as the administrative limit [Ref. 11] 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-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 18 of 51

Table 2.1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD" AVERAGE TIME P-08 1.39 sec. L-05 & M-12 1.25 sec 1.30 sec.

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 19 of 51

Figure 2. 1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE Time Stamp Of Rod Drop: Path of ASCIr Rod Drop Dta File: -

Rod____

Re p ........ .... --! I- . ...... _ _ +_+'+___

.......I...+ ._ 1+ J ....... ~.. _ +. .+°_tm a14* + ...* --1+......+- --- - .... *' -- ---v - - +-

++Ij,

"*L + 'lm. ,,,gge

...a C+.... .. .....

+++ m+:+

..- . - +

washeotTiii tB (A(

NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 20 of 51

Figure 2.2 SURRY UNIT 1 - CYCLE 21 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

1.28 2 1.29 1.28 1.28 3

1.29 1.30 1.32 4

1.29 1.26 1.28 1.31 5

1__

___ ___1.25 __ _ 1 11.28 1 __

11.27 6 1.26 1.29 1.30 1.28 1.27 1.36 7

1.28 1.31 1.29 1.30 8

1.39 1.31 1.38 1.30 9

1.34 1.29 1.32 _1.30 .

10 1.29 1.29 1.27 1.29 1.31 1.29 1.31 111 il.28 ___ ___ [jl= _.29 VN I= . 11 12 1.25 1.26 1.28 1.32 13 1.30 1.31 14 1.32 1.27 1.36 15

===> Rod drop time to dashpot entry (sec.)

NE-1487 Rev. 0 R1C21 Startup Physics Tests Report Page 21 of 51

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NE- 1487 Rev. 0 SI1C21 NE-1487 Rev. 0Startup Physics Tests ReportPae2of5 Page 22 of 51

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. 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. Surry 1 used a dilution rate of 1100 pcm/hr for the reference bank measurement. For Cycle 21, Control Bank D was used as the reference bank.

During the N1C19 startup physics testing campaign, a control rod became stuck on bottom eventually forcing a reactor trip to fix the issue. 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 (0 steps withdrawn).

A possible solution to this theory for startup physics testing was to avoid requiring control rods to be manually inserted to 0 steps. To accomplish this, an evaluation of the startup physics testing process was performed [Ref. 15], concluding that the definition of fully inserted for control rod positions used in startup physics testing could be changed from 0 steps withdrawn to a range of 0 to 2 steps withdrawn. The S 1C21 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

After completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were allowed to stabilize 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 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 NE-1487 Rev. 0 SI C21 Startup Physics Tests Report Page 23 of 51

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 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 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 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 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 -2.2% 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 D) are shown in Figures 3.1 and 3.2, respectively. The design predictions [Ref. 1] and the measured data from station procedure 1-NPT-RX-008 are plotted together in order to illustrate their agreement.

In summary, the measured rod worth values were satisfactory.

INE- 1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 24 of 51

Table 3.1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM) (PCM) (M-P)/P X 100 D - Reference 1198.3 1230.0 -2.6 B 1159.3 197.4 -3.2 C 815.9 816.6 -0.1 A 277.0 286.8 -3.4 (a)

SB 1004.1 1025.5 -2.1 SA 979.3 997.4 -1.8 Total Bank Worth 5433.9 5553.6 -2.2 (a). M - P = -9.8 pcm NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 25 of 51

Figure 3.1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS CONTROL BANK D INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 140 120 0 - -

,.~~,*

.---. .1 ~ ~~.,.,...... ..... ..

100(0 '

bjuu -

--- Measured (d) w -a- Predicted:

600-H 400- - - " - ' "- ":

ki 0

0 50 100 150 200 250 Bank Position (steps)

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 26 of 51

Figure 3.2 SURRY UNIT 1- CYCLE 21 STARTUP PHYSICS TESTS CONTROL BANK D DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 10.0 9.0 8.0 IV 7.0 0 .6.0 -

10 - Measured 5.0 --- Predicted 0

'-4 4.J 4.0

'4-3.0 2.0-1.0-0.0O 0 50 100 150 200 250 Bank Position (steps)

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 27 of 51

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NE-1487.ReV. 0 1C21 Startup Physics Tests Report

.RS Page 28 of 51

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 Appendix, 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. 4]

regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, 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 t 10%.

In summary, the measured boron worth coefficient was satisfactory.

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 29 of 51

Table 4.1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 1692 1693 -1 D Bank In 1533 1526* +7

• The predicted endpoint for the D Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheet in the Appendix.

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 30 of 51

Table 4.2 SURRY UNIT 1- CYCLE 21 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

(pcmlppm) (pcm/ppm) (M-P)/P x 100

-7.54 -7.41 -1.75 NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 31 of 51

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NE-1487 Rev. 0 S 1 C21 Startup Physics Tests Report Page 32 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 the RCS heatup of +3.04OF, followed by the RCS cooldown of -3.03TF. 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 t2 pcnmF. The measured ITC of -2.009 pcrrmF meets the Core Operating Limits Report (COLR) 3.1.1 criterion [Ref. 9] that the moderator temperature coefficient (MTC) be less than or equal to +6.0 pcmroF. When the Doppler temperature coefficient [Ref. 1] of -1.81 pcnr'oF and a 0.5 pcm/rF uncertainty are accounted for with the MTC limit, the MTC requirement is satisfied as long as the ITC is less than or equal to +3.69 pcm/°F.

NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report page 33 of 51

Table 5.1 SURRY UNIT 1- CYCLE 21 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

TEMPERATURE ISOTHERMAL TEMPERATURE COEFFICIENT BANK BORON (PCM!0 F)

POSITION . .. U" .... CONCENTRATION-iE2 --.-..-.....

(OSITEPS) - R LOWER UPPER (ppm)RAIO H-EAT- COOL- AVG. DIFFER (STEPS) LIMIT LIMIT (ppm) UP l DOWN MEAS PRED (M-P)

D/210 546.63 550.08 1684 -2.022 -1.996 -2.009 -1.593 1 -0.416 NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 34 of 51

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 21.

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 1 was taken at 28.2% 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 69.7%

and 99.97% 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

-5.6% in the 28.2% power map, -5.4% in the 69.7% power map, and -4.3% in the 99.97%

power map. The maximum quadrant power tilts for 28.2%, 69.7%, and 99.97% power maps were

+1.29 % (1.0129), +0.46 % (1.0046), and +0.46% (1.0046), respectively. These power tilts were within the design tolerance of 2% (1.02).

The measured FQ(Z) and FN peaking factor values for the at-power flux maps were within the limits of COLR Sections 3.3 and 3.4 [Ref. 9], respectively. Flux Maps 1, 2, and 3 were used NE- 1487 Rev. 0 , S1C21 Startup Physics Tests Report Page 35 of 51

for power range detector calibration or were used to confirm existing calibrations. The flux map analyse.! are documented in [Ref. 7].

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. 9]. It is therefore anticipated that the core will continue to operate safely throughout Cycle 2 1.

NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 36 of 51

Table 6.1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Bum Bank Peak FQ(Z) Hot F,, Hot Core Fz Core Tilt (2) Axial o.

Of Map Map Date up Power Channel Factor (1) Channel Factor Max Description No. MWD/ D ..

W Assy Axial, ......M offsetTmbl MTU Assy MTUSteps StepsAssPoint ia FQ(Z) F" Point Fz Max Loc (%)

Low Power 1 05/27/06 3 28.20 172 H13 30 12.202 H13 1.551 30 1.319 1.01291 NE +2.686 41 Int. Power (3) 2 05/27/06 17 69.70 194 C8. 25 (1.919 C8 1.511 23 1!.179 1.0046 NE +2.626 42 Hot Full Power 3 06/02/06 155 99.97 228 H1l 32 1.778 Hl 1.466 30 11.134 1.0046! NE +1.660 42 NOTES: Hot spot locations are specified by giving assembly locations (e.g. 1H-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-1487 Rev. 0 SR1C21 Startup Physics Tests Report Page 37 of 51

Table 6.2 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak FQ(Z) Hot FQ(z) Hot FN Hot Map Channel Factor* Channel Factor** Channel Factor (At Node of Minimum Margin)

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

(%) (%)

1 2.202 4.628 30 2.183 4.582 26 52.36 1.551 1.896 18.20 2 1.919 3.279 25 1.907 3.254 22 41.40 1.511 1.702 11.22 3..1.778..

1..77 232.257 3 20 21...8 1 1.5..0 3 1.778 2.321 32 1.770 2.257 20 21.58 1.466 1.560 6.03

• 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. 9] 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% total uncertainty.

NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 38 of 51

Figure 6.1 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 28.2% POWER R P N M L .K J m 3 P D C 8 A

• PREDICTED . 2*8*5.34.28* PREDICTED

• MEASURED . .283 . .360 . .283 . . MEASURED . 1 PCT DIFFERENCE. -. 8 . -3.6 . -. 7 . PCT DIFFERENCE.

.. 33.4 .......... i1*'*. " ".9 . . 1'5'7*l:." 27

":'i' 1.2"' -' 9 **'

2'" ..... ..........

.334 . .527 . 1.183 . .991 . 1.160 . .526 . .330 . 2

-.1 . .0 . .i . -.1 . .3 . -.1 . .6 .

.. .. .. .. .. .. .. . .. . .. .. .. .. ... . .. .. . . .. . . .. . L.. . . . . . . . . . . . . . . . . . . . . . . . . . ..

.352 . 1.079 . 1.087 . 1.306 . 1.318 . 1.303 . 1.084 . 1.072 . .351 .

.345 . 1.078 . 1.087 . 1.310 . 1.331 . 1.313 . 1.092 . 1.082 . .351 . 3

-2.1. -. 1. .. .. . .8 . .8 . 1.0 . .1.

. .845 . "3441.096 1.'2 2 . 1. 2 i18. 4 ....l.'*......

1' ' 1.230 . 1.0l9.'0 .849 " .34

.343 . .841 . 1.099 . 1.229 . 1.257 . 1.309 . 1.268 . 1.244 . 1.110 . .864 . .354 . 4

-. 2 . -. 5 . .2 . -. 2 . .2 . 2.0 . 1.2 . 1.1 . 1.3 . 1.8 . 1.8 .

.296 . 1.038 . 1.082 . 1.152 . 1.319 . 1.227 . 1.322 . 1.226 . 1.319 . 1.156 . 1.091 . 1.056 . .305 .

.296 . 1.041 . 1.072 . 1.125 . 1.304 . 1.210 . 1.321 . 1.234 . 1.334 . 1.175 . 1.121 . 1.077 . .297 . 5

-. 1 . .2 . -. 9 . -2.3 . -1.2 . -1. 4 . . 0 . .6 . 1.2 . 1.7 . 2.7 . 2.0 . -2.7 .

.492 . 1.052 . 1.213 . 1.312 . 1.195 . 1.190 . 1.283 . 1.188 . 1.196 . 1.319 . 1.225 . 1.073 . .517 .

.489 . 1.048 . 1.205 . 1.302 . 1.182 . 1.177 . 1.269 . 1.189 . 1.207 . 1.342 . 1.255 . 1.099 . .530 . 6

-. 6 . -. 4 . -. 6 . -. 8 . -1.1.. -1.1 . -1.1 . .1 . 1.0 . 1.7 . 2.4 . 2.4 . 2.6 .

.284 . 1.132 . 1.279 . 1.239 . 1.220 . 1.188 . 1.188 . 1.300 . 1.185 . 1.189 . 1.225 . 1.250 . 1.298 . 1.156 . .287 .

.277 . 1.121 . 1.273 . 1.232 . 1.213 . 1.178 . 1.179 . 1.291 . 1.184 . 1.199 . 1.245 . 1.283 . 1.336 . 1.204 . .297 . 7

-2.1 . -1.0 . -. 4 . -. 6 . -. 5 . -. 8 . -. 7 . -. 6 . -. 1 . .8 . 1.6 . 2.7 . 2.9 . 4.1 . 3.5 .

.370 . .979 . 1.302 . 1.273 . 1.316 . 1.285 . 1.307 . 1.020 . 1.300 . 1.284 . 1.320 . 1.280 . 1.313 . .990 . .374

.349 . .962 . 1.288 . 1.263 . 1.315 . 1.275 . 1.296 . 1.011 . 1.295 . 1.294 . 1.336 . 1.304 . 1.344 . 1.010 . .380 . 8

-5.6 . -1.8 . -1.1 . -. 7 . - l. . -. 8 . -. 9 . -. 8 . -. 4 . .7 . 1.2 . 1.9 . 2.4 . 2.1 . 1.6 .

.285 . 1.147 . 1.290 . 1.245 . 1.224 . 1.191 . 1.192 . 1.306 . 1.189 . 1.190 . 1.226 . 1.250 . 1.296 . 1.151 . .288 .

.278 . 1.129 . 1.273 . 1.227 . 1.195 . 1.172 . 1.175 . 1.291 . 1.169 . 1.205 . 1.237 . 1.263 . 1.310 . 1.159 . .282 . 9

-2.6 . -1.6 . -1.4 . -1.4 . -2.3 . -1.6 . -1.4 . -1.2 . -1.7 . 1.3 . .9 . 1.1 . 1.1 . .6 . -2.3 .

.514 . 1.069 . 1.223 . 1.318 . 1.197 . 1.192 . 1.287 " 1.193 . 1,200 . 1.320 . .1.226 . 1.073 . .516 .

.507 . 1.054 . 1.204 . 1.297 . 1.177 . 1.166 . 1.277 . 1.184 . 1.196 . 1.321 . 1.230 . 1.074 . '.505 . 10

-1.5 . -1.4 . -1.5 . -1.6 . -1.7 . -2.1 . -. 8 . -. 8 . -. 3 . .0 . .3 . .1 . -2.3 .

.304 . 1.053 . 1.090 . 1.156 . 1.320 . 1.229 . 1.325 . 1.231 . 1.325 . 1.160 . 1.094 . 1,057 . .305 .

.299 . 1.035 . 1.073 . 1.142 . 1.308 . 1.222 . 1.333 . 1.229 . 1.310 . 1.148 . 1.093 1 1.054 . .302 . 11

-1,7 . -1.7 . -1.5 . -1.2 . -. 9 . -.5 . .6 . -. 1 . -1.1- . -1.0 . .0 . -. 3 . -. 9 .

.347 . .848 . 1.096 . 1.231 . 1.256 . 1.287 . 1.258 . 1.237. . 1.102 . .853 . .349 .

.334 . .835 . 1,085 . 1.225 . 1.258 . 1.299 . 1.266 . 1.239 . 1.104 . .864 . .342 . 12

-3.8 . -1.6 . -1.1 , -. 5 . .2 . .9 . .6. .2 . . 2 . 1.3 . -2.0 .

i

......;.. ........................... i"i o " "i ; " i i " 'il i " " ; I" i.... "i...

o "I""" *..........

.351 . 1.073 . 1.085 . 1.305 . 1.321 . 1.310 . 1.091 . 1.084 . .355 .

.346 . 1.063 . 1.083 3.314 1 . 1.349 . 1.326 . 1.104 . 1.093 . .358 . 13

-1.3 . -. 9 . -. 3, .6 . 2.1 . 1.3 . 1.1 . .8 . 1.0 .

.329 . .527 . 1.159 . .994 . 1.165 . .529 . .336..

. 319 . .526 . 1.164 . 1.004 . 1.179 . .535 . .338 . 14

-3.0 , -. 3 , .4 . 1.0 . 1,2 . 1.1 . .9 .

• STANDARD .286 . .375 . .286 . . . AVERAGE DEVIATION . .280 .. 376 . .288 . PeT DIFFERENCE. 15

= .913 -2.2. .5 . 1.0. 1.2 R P N M L- K J H G F E D C B A Summary:

Map No: S1-21-01 Date: 05/27/2006 Power: 28.2%

Control Rod Position: FQ(Z) = 2.202 QPTR: 0.9907 1.0129 D Bank at 172 Steps FN = 1.551 0.9899 1.0065 Fz.= 1.319 Axial. Offset (%)=+2.686 Burnup = 3 MWD/MTU A NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 39 of 51

Figure 6.2 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 69.7% POWER R P N M L K J H G F E D C a A

• PREDICTED ... 301 . .396 . .301. . PREDICTED S MEASURED .300 . 389 299 . . EASURED

.PCT DIFFERENCE. -. 3 . -1.9 . -. 6 . PCT DIFFERENCE.

.348 . .541 . 1.160 . 1.022. 1.156 . .540 . .342 S.349 . .543 . 1.164 . 1.023 . 1.154 . .530 . .340 .2

. .4 .3 .3 . 1. -.1 -1.9 . -,6 .

........................................... 1.. -. 1. -1....9. -. 6.......

.367 1.060 1.083 1.285 1.292 .. 1.282 1.080 .*1.072 .. 365

.361 1.084 1.087 1.291 1.303 . 1.286 . 1.079 . 1.072 . .361 .3

-1.6. .4 . .4 . .5. .9 . .3. -. 1. 0. -. 9.

.359 .8.61 .1.097 .1.220 .1.235 .1.257 .1.233 1.228 1.3096 .8.62 .. 362

.361 * .863 . 1.108 . 1.224 . 1.240 . 1.275 . 1.241 . 1.222 . .100 .868 .365 .4

.................................... 4. 1. ........................................

.3 . 4 . 1 . . . 9 . 1.3 .54 5 1.217 5 . 1 2. . 3. . . . 1 . . 1.058 .338

.313 . 1.054 . 1.086 . 1.147 . 1.310 . 1.209 . 1.295 . 1.218 . 1.318 . 1.164 . 1.108 . 1.068 . .310 .5

.5. .7. -. 1. -. 7. -. 4. -. 7. .2.. -3 . . ..

4 .7. 1.5. 1.0. -2.7.

.512 3.056 1 . 1.207 . 1.310 . 1.235. 1.194 . 1.269 . 3.192 . 1.234 . ,314 . 1.214 . 3.071 . .532

.513

• 1.060

• 1.205 1.298 1 . 1.228 , 1.189 . 1.269 . 1.189 . 1.234 . 1.322 . 1.228 . 1.085 * .539 . 6

.2. .4 * -. 2. -. 9 -. 6. -. 4. .0. -. 2. .0. .6. 1.1 1.4. 1.4.

.302 1.141 . 1.267 . 3.225 . 1.212 . 1.193 1.188 .290 . 3.184 . 1.193 . 1,235 . 1.230 . 1.278 . 3.156 . .304

.298 1.141 . 1.278 . 1.225 . 1.208 . 1.187 . 1.184 . 1.285 . 1.174 . 1,191 . 1.221 . 1.243 . 1.304 . 1.187 .309 . 7 1.4 . .0..- ..... .. .0 -. 3. -. 5. -. 3. -. 4. -. 9. -. 1. .5. 1.1. 2.0. 2.7. 1.7.

......... "i ......'............i " ....Ii '... .. . '- ..".... .... .... ...i.. .... ..i.. .... .... ..'. .. ...... ............. ..'...

.395 1 .016 1.283 1.251 1.2393 1 .272 . .297 1 .025 1.289 . .270 . .291 1.254 1 .289 1 .023 .397

.374

• 1.007 . 1.280 . 1.248 . 1.289 . 1.267 . 1.292 . 1.021 . 1.285 . 1.270 . 1.297 . 1.270 . 1.326 . 1.007 . .393 . 8

-5.4 . -. 9 - -. 3 . -. 3 . -. 1 . -. 4 . -. 4 . -. 4 * -. 4 . .0 . .4

• 1.3 . 2.9 . -1.4 . -1.1

.303 1.152 . 1.276 . 1.229 . 1.215 . 1.195 . 31:90 . 1.294 . 3.387 1 .193 1.214 . 1,230 1 3.277 1 1 -,152. .305

.296 1.142 . 1.2866 1.218 , 1.194 . 1.184 . 1.185 . 1.291 . 1.182 . 1.193

• 1.216

• 1.236

• 1.284 . 1.141 . .295 . 9

• -2.1 . -. 9 . -. 7 * -. 9 , -1.7 * -. 9 . -. 5 * -. 2 . -. 4

• 0 * .2 . .5 * .6 . -. 9 . -3.1 .

.531 . .069 . 3234 . 3135 1 .235 1.1394 . 3272 1,1915 1 .237 .1.314 .1.214 1 .070D .531

.526 . 1.061 . 1.200 1.297 . 1.224 . 1.188 . 1.273

• 1.194 . 1.233 . 1.309 . 1.213

• 1.066 . .516 . 10

-. 9 * -. 7 . -1.1 , -1.3 . -. 9 * -. 5 . .1 * -.1 -.3 . -. 4 . .1 . -. 3 :2.7 .

.318-. 1.057 . 1.092 . 1.157 . 1.315 . 1.217 . 1.294 . 1.218 . 1.317 . 1.159 . 1.093 . 1.058 .318

.314 . 1.043 . 1.076 . 1.137 . 1.306 . 1.219 . 1.310 .1.222 13.308

• 1.142

• 1.091 . 1.052 314 . 11

-1.2. -1.3. -1.5. -1.7. -. 7. .2. 1.2. .4. -. 7 -1.4. -. 1. -. 5. -1.3.

.362 . .862 ., 1.096 . 1.219 . 1.234 . 1.258

• 1.236

• 1.222 . 1.100 . .865 . .362

.350 . .848 . 1.082 . 1.214 . 1.240 . 1.275

• 1.247 . 1.226 . 1.104 . .883 * .354 . 12

-3.2 * -1.6 . -1.2 , -. 4 . .5 . 1.3 .9 .4 . .3 . 2.2 * -2.2

........ ......... i: ... '.i: .. o' i.' ... ' .i.i ' i . .....

.. i .o.... i . 8 ..  : : ............

.365 .1.072 .1.080 .1.283 .1.293 1.2866 1.085 .1.082 .. 368

.360

• 1.059 . 1.077 . 1.293 . 1.324

• 1.304 . 1.096 . 1.091 . .373 . 13

-1.4. -1.3. -. 3. .8. 2.4 1.4. 1.0. .9. 1.4.

..... .. i l'... " .. ..i..ioi ................... '.i.ii : :; i : "..i.i * ' ..... ..

.342 .. 541 .1.157 .1.023 .1.161 .. 542 .. 348

.326 .538. 1.161: 1.035. 1.177 .548. .351, 14

. -4.7 . -. 6 . .4 .1.3

• 1.4

• 1.2 . 1.0 .

STANDARD ... 301...397....301 . . AVERAGE ' .

DEVIATION .292 .398 . .304 . PCT DIFFERENCE. 15

= .842 -3.1 .4 . 1.1 . = .9 R P N M L K J H G F E D C B A Summary:

Map No: S1-21-02 Date: 05/27/2006 Power: 69.7%

Control Rod Position: FQ(Z) = 1.919 QPTR: 0.9977 1.0046 D Bank at 194 Steps FN, = 1.511 0.9938 1.0039 Fz = 1.179 Axial Offset (%) = +2.626 Burnup- 17 MWD/MTU NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 40 of 51

Figure 6.3 SURRY UNIT 1 - CYCLE 21 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 99.97% POWER R P N N L K J N G F E D C B A

• PREDICTED .. 307 .408 .. 3017 PREDIC TED NEASURED M . .307 . .405..306 . MEASURED .

.PCT DIFFERENCE. . .1 . -. 7 . -. 3 . PCT DIFFERENCE.

• .347'.

.. .54 . 1.144". 1.4 . 1.140 . .540 .. .342. ..

.349 . .543 . 1.149 . 1.050 . 1.139 . .530 . .340 . 2

.6 . .4 . .4 . .2 . -. 1 . -1.8 . -. 4 .

.3

. . . 1.0

.. . " 1.. 9

. .1.26 . 1.*. . . .2 .0 . .34 ."

.365 . 1.065 . 1.074 . 1.271 . 1.275 . 1.265 . 1.066 . 1.053 . .366 .

-. 5 . .8 . .5 . .5 . ..5 ... ..3 .. . . .0 .. . . .4 ... . .5

................................. .. . . 5

.360 . .854 . 1.088 . 1.210 . 1.224 . 1.242 . 1,222 . 1.207 . 1.086 . .854 . .362 .

.362 . .858 . 1.102 . 1.215 . 1.229 . 1.257 . 1.229 . 1.213 . 1.093 . 864 . .366 . 4

.3 . .4 . 1.3 . .5 . .4 . 1.2 . . 6 .. .5 . .7 . 1.1 , 1.1.

.314 . 1.028 . 1.07. . 1.159 . 1.324 . 1.222 . 1.26. . 1.22. . 1.322 . 1.159 . 1.0.2 . 1. -36. .319. .

.314 . 1.032 . 1.078 . 1.150 . 1.321 . 1.215 . 1.282 . 1.224 . 1.329 . 1.169 . 1.103 . 1.048 . .312 .

.1 . .4 . -. 1 . -. 8 . -. 2 . -. 5 . .1 . .3 . .5 . .9 . 1.9 . 1.1 . -2.2 .

.314 . 1.047 . 1. 0200 . 1.120 . 1.3021 . 1.220 . 1.2782 . 1.217 . 1.350 . 1.323 . 1.134 . 1.057 . .5312

.516 . 1.046 . 1.198 . 1.318 . 1.299 . 1.217 . 1.277 . 1.218 . 1.303 . 1.332 . 1.217 . 1.069 . .538 . .6

-. 3 . -. 1 . -. 2 . -. 2 . -. 2 . -. 3 . -. 1 . .0 . .2 . .7 . 1.1 . 1.2 . 1.2 .

... 309 . 1.130 . 1.251 . 1.216 . 1.318 . 1.219 . 1.210 . 1.305 . 1.207

.304 . 1.123 . 1.246 . 1.213 . 1.215 . 1.216 . 1.209 . 1.304 . 1.205 .. 1.221 1.219 .. 1.226 1..19 .. 1.228 1.220 .. 1.276 1.259 .. 1.167 1.140 . .31...

.314 . 7

. -1.6 . -. 6 . -. 2 . -. 3 . -. 2 . -. 3 . , -.1 . -. 2 . .2 . .5 . .7 . 1.3 . 2.3 . 1.3 .

.340 . 1.045 . 1.262 . 1.2138 . 1.279 . 1.2161 . 1.320 . 1.3052 . 1.305 . 1.229 . 1.279 . 1.240 . ý1.265 . 1.0467 . .3409

.390 . 1.034 . 1.254 . 1.232 . 1.276 . 1.276 . 1.309 . 1.050 . 1.302 . 1.283 . 1.284 . 1.249 . 1.282 . 1.032 . .404 . a

• -4.3 . -1.1 . -. 7 . -. 5 . -. 2 . -. 4 . -. 3 . -. 3 . -. 2 . .3 . .4 . .7 . 1.3 . -1.6 . -1.2 .

.309 . 1,138 . 1.258 . 1.219 . 1.220 . 1.221 . 1.213 . 1.309 . 1.209 .1.219 . 1.219 . 1.219 . 1.257 . 1.137 . .311.

.304 . 1.128 . 1.248 . 1.207 . 1.198 . 1.210 . 1.207 . 1.305 . 1.199 . 1.229 . 1.224 . 1.223 . 1.258 . 1.124 . .304 . 9

• -.1.8 . -. 9" . -. 7 . -. 9 . -1.8 . -.9 . -. 5 .' -. 3 . -. 9 . .8 . .4 . .3 . .0 . -1.1 . -2.2 .

. .. ... .. .. .. . . .. . . . . . . . . . . 1. . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2

... .. . . . . . . . . . ... . . . . . . . . . . . 0.. . . . . . . . . . . . . . . .. .

.531 . 1.056 . 1.204 . 1.323 . 1.302 . 1.220 . 1.280 . 1.221 . 1.303 . 1.323 . 1.204 . 1.056 . .531 .

.527 . 1.053 . 1.194 . 1.310 . 1.293 . 1.214 . 1.282 . 1.219 . 1.304 . 1.323 . 1.204 . 1.052 . .516 . 10

-. 7 . -. 3 . -. 8 . -i.0 . -. 7 . -. 5 . '.1 . -.1 . .1 . .0 . .0 . -. 5 . -2.8 .

..318 . 1.036 . 1.082 . 1.160 . 1.323 . 1.221 . 1.282 . 1.223 . 1.326 . 1.161 . 1.083 . 1.036 . .318..

.316 . 1.027 . 1.072 . 1.148 . 1.317 . 1.223 , 1.298 . 1.227 . 1.319 . 1.154 . 1.085 . 1.033 . .315 . 1i

-. 8 . -. 8 . -1.0 . -1.0 . -. 4 . .2 . 1.3 . .3 . -. 5 . -. 6 . .2 . -. 3 . -1.2 .

.362 . .854 . 1.086 . 1.208 . 1.223 . 1.243 . 1.225 . 1.211 . 1.090 . .857 . .362 .

.353 . .844 . 1.076 . 1.203 . 1.225 . 1.252 . 1.232 . 1.216 . 1.096 . .875 . .359 . 12

-2.4 . -1.2 . -. 9 . -. 4 . .2 . .7 . .6 . .4 . .6 . 2.1 . -1.1 .

.. ..i. .. i ;. .'i.. 8 6..'i. .* .."i.. i *. i. .. l ; .. .. i ;. i........ lo ; I"i ; 'i .......... i * .. . ..

.365 . 1.050 . 1.066 . 1.263 . 1.269 . 1.266 . 1.070 . 1.058 . .368.

.360 . 1.038 . 1.061 . 1.263 . 1.279 . 1.276 . 1.083 . 1.069 . .373 . 13

-1.2 . -1.1 . -. 5 . .1 . .8 . .8 . 1.2 . 1.0 . 1.5 .

................................. o...ii o* [~ i ; i; i .. " [.. * [.........

.342 . .540 . 1.141 . 1.049 . 1.145 . .541 . .347.

.328 . .535 . 1.138 . 1.053 . 1.153 . .546 . .351 . 14

-3.9 . -. 9 . -. 2 . .4 . .7 . .9 . 1.0 .

STANDARD . .307 . .408 . .307 . . AVERAGE .

DEVIATION .299 . .407 . .308 . PCT DIFFERENCE. 15 S.686 . -2.8 . -. 2 . .4 . = .7 0 P N 14 1. K J H G F 0 D C B A Summary:

Map No: S1-21-03 Date: 06/02/2006 Power: 99.97%

Control Rod Position: FQ(Z) = 1.778 QPTR: 0.9986 1.0046 D Bank at 228 Steps F," = 1.466 0.9939

• 1.0029 Fz = 1.134 Burnup = 155 MWD/MTU NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page w 41 of 51

This page is intentionally blank.

NE-1487 Rev. 0 S1C21 Startup Physics Tests Report Page 42 of 51

SECTION 7 - REFERENCES

1. C. D. Clemens, "Surry Unit 1 Cycle 21 Design Report", Technical Report NE-1480, Rev. 0, May 2006

2. R. W. Twitchell, "Control Rod Reactivity Worth 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", 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. R. W. Twitchell, "Operational Impact of the Implementation of Westinghouse Integral Fuel Burnable Absorber (IFBA) and the Removal of Flux Suppression Inserts (FSIs) for Surry Unit 1 Cycle 21," Technical Report NE-1466, Rev. 0, January 2006

6. D..M. Rohan, "Surry Unit 1 Cycle 21 TOTE Calculations", Calculation PM-1 139, Rev. 0, May 2006

7. R. A. Hall et al, "Surry Unit 1, Cycle.21 Flux Map Analysis", Calculation PM-1138, Rev. 0, and Addenda A - B, May 2006

8. T. R. Flowers, "Reload Safety Evaluation Surry 1 Cycle 21 Pattern RB", Technical Report NE-1479, Rev. 1, May 2006

9. Appendix to Technical Report NE-1479 "Reload Safety Evaluation, Surry 1 Cycle 21 Pattern RB", "Core Operating Limits Report Surry 1 Cycle 21 Pattern RB Revision 1,"

May 2006

10. P. D. Banning, "Implementation of RMAS for Startup Physics Testing", Calculation PM-0824, Rev. 0 and Addendum, 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. R. D. Kepler to T. A. Brookmire, "Surry Unit 1 Cycle 21 Core Loading Plan", Engineering Transmittal ET-NAF-05-0098, Rev. 1, May 2006

13. T. R. Flowers, "Reload Safety Evaluation Surry 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 NE-1487 Rev. 0 S-1C21 Startup Physics Tests Report Page 43 of 51

15. 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," Eng Transmittal ET-NAF-06-0046, Rev. 0, April 2006.

16. R. W. Twitchell, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," Technical Report NE-1378, Rev. 1, September 2004 NE-1487 Rev. 0 R1C21 Startup Physics Tests Report Page 44 of 51

APPENDIX - STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-1487 Rev. 0 S 1C21 Startup Physics Tests Report Page 45 of 51

4 Surry Fowmr Station Unit 1 Cycle 21 Startup Physics Test Sumnmary Sheet - Fomo.1Tests (Page I of 6) 00 Moasurad Value DatigaOdtarta J Acceptarioe Criteria Criterfa Aocpan. r 'peer bFTRkgrcaczmd < ZZPTR < PQAH V e ej L to 6 b8aW~groufl= wnpaJ~ WA~ N/A $fk4ý 91M ps POAHI= 4121 amps (m~w r~tiit) The allcmible rarp ia~eat 1 tho IWflr 6; p- m d th'e, measured ro~iIts or the pie.

~afiv~}

(p~k~a cmead~ benc~h tes -NO N COO PraocdWloW Sench Tost Results

%DYpo-ptfipll}x 100% t zo- pc

%D= Maibl we Ct, (C1~I~~ pm

_____4 CJp ~ *-So ppm ja:qrr.& X A(CO)A 2f 1000iii M4. TO.*rsign Oor~do,) 4(.u-QA pM e~g= -7A poarippm w -N C12 73__ te2p*nS-(. 69 p aWF "0

_______ AM: 6.PvMTICOLR 3A. -9

&0~) -No -No 16ýY 1230;d-,12:3pcm j iAN/

Mriow= 1TNE-1480, Rievi 0 Z~) Momorandum from CT. Stmowto E.J. Lozito, ddatd Juz'i 27, 1990 3,) WCAP-7M5, Rev. 1 0

4.) ET NAF-06-'003, Rev. 0

Surry Po~wer Station Unit I Cycle 21 Startup Physics -Test Summrray Sheet - Forjfl -Tests (Page 2 of 6) moa"Ured V*ju Deign oritr AcOMtanoe Criteria A Crtterlix ,op~ i~Timo of 0

(C&15_27+4(CO)AM0 +/-27PPrnI ,4~

2CL..ppn' A~a~ . p (Io atgwA V/A ve (Q)~___+/-27 ppnm NovL oacv -7,41 j, .74 pm/ppm WfA YeNA__6 C/)

~~3'4RY 2U.pp9 10)Q0pan~Ip __ yA 0+

. NIA I

_ 0_ _ Ioss _ _ P=e N oIV Wim, I-cWOI CD

____Q c JaxMa.Dmpm~&~O %j / _ WA

_11 *M lvX(mea& - Dloes4~o- WA NON/ NIAL CD

{Pe'm 4 -

j(Qomar. s  %

1a)M( WA-N WA

{ 8 T*4 1197. q__15% N/A Wie#ces 1,) NE-1480, ff1v. 0 2.1 MammarWUM fimm CT. Snow to III Lcaio, dated June 27, 19B0

~)WGAI>-7905~, ReV.

0 4.) ET NAF4&_'O(ý3,. f:Wv. 0L LA

00 Surry Power Station Unit 1 Cycle 21 Startup Physics Test Summary Sheet - Formal Tests (Page 3 of 6)

Design Critec Date/

Measured Value I Design Criteria__ _ _ _I _

Acceptance Criteria Criteria

_ _ Crtri cceptance MtReviewer M Time of Preparer 00 Met _rtrie Test Map Power LevW (% Foll Power) - ,

Max Relative Assembly Power, ¶/IIFF (M-PYP

' 9

+/--0% for P1N.1y

%0HF %fPi 1-.9  :*1$%/forP4<.0 NIA __No WIA OA Ii

____ for Pk"O.9 (PI WSYPOwer)"'

Nuclear Enthalpy Rise Hot Channel Factor, FPAHiN)

FalN(N)= l-____-____ ANIA___

FAHN)S1,56(1+0.5(1-P)) IOLR83,41 J No COO Total Heat Flux Hot Channel Factor, -Q(Z)

FckZ) 2.

IN/A FQ(Z)_<4.64Ný4Z [OOLR 3.3]

MargIn to COLR Lk'nft=

NIA

,y No Maximum Poasitive trioore Quadrant Power Tilt CD 3 Tlif= ~s.(2 _5lZC N/A NA 0 -_No, Most Positive Measured To Predicted FDH Oifference/ Core Locationr Hil (or any of lts eighth core partners) . 42-I0I. "4

%DiFF=-,'L..  % N/A  : 14.90A WA Note that ifthis crieria is not met, a flux v Yes I-map must be taken at <30% power, with __ No the control rods at the rod insertion limits.

References i.) NE-1480, Rev. 0 CD 2.) Memorandum from C.T. Snow to E.J. Lozito, dated June 27. 1980 3.) WCAP-7905, Rev. 1 00 4.) ET NAF-06-43053, Rev. 0 0h

Surry Power Station Unit 1 Cycle 21 Startup Physics Test Summary Sheet - Formal Tests (Page 4 of 6)

I 1.

00 Design - __

Design Acceptance Time Preparerd Measured Value Design Criteria Acceptance Criteria Criteria Criteria Met Date?

- .of [Reviewer I

0 Map PaorLevel (% Ful Power) --_ 2 max Relative Assembly Power, %WIFPF (M-PYP

.10%,or Fpt,.9 2.L yes

%0[FF= 2L%% lor Pi Po,9 j-15% for PrcO.9 N/A No N/A y-A/

- ,PkO.9 , =asy powr)'",

Nuclear Enthalpy Rise Hot Channel Factor, FAH(N)

CIO CD) 1,o].... ...' '* 1A Total Heat Flux Hot Channel Factor, FQ(Z)

F*(Z{(2P):K(Z) [0OLR 3*3 *A Ye F.(Z)= I_ __in _ to COLR Umft- 70, UC 01,__ NO Mwadmum Positive Incore Qua*rant Power Tilt CD r N/A yes NIA

________________ _______________________ __________,___,__,,,,,,,No____.....__

-No References 1.) NE-1480, Rev. 0 2.) Memorandum from C.T. Snow to E.J. Lozito, dated June 27, 1980 3.) WCAP-7905, Rev. 1 4.) ET NAF-06-0053, Rev. 0 4.

Surry Power Station Unit I Cycle 21 Startup Physics Test Summary Sheet - Formal Tests (Page 5 of 6) 00 Desig Acceptance Date/ Prepared Measured Value Design Criteria Acceptance Criteria ritera Met ofReviewer met Test 0 Map Power Level (% Ful Power) 9-1,1 Ma Re, tx e Assembly Power, %DIFF(M-PYP

+/-10%for Pý: 0.9 _.* YeS

%DIFF= %forPi*'O.9 +/-15% for P,<0.9 NIA -No N/A A2 %for pkQ. (PI assy pgwe)-' W ,.D Nuclear Enthelpy Rise Hot Channel Factor, FAH(N) r+:

FAH(N ,'(* ANA No Total Heat Flux Hot Channal FactoW, FQ(Z)

(I.770 A ~vvwFd2iPR4/FK(Z) [COUR 3.3] o...o GO~ N/A N/A 0 FdZ))= . '1-7P) Margin to COLR Umrit=- -No 0 Maximum Positive Incore Cuadrant Power Tilt

_il <_1.0 NIA N/A YesN j N/A 0

0I References 1.) NE-1 480, Rev. 0.

.2.) Memorandum from C.T. Snow to EJ. Lozito, dated June 27, 1980

3) WCAP-7905, Rev. 1 4,) ET NAF-06-0053, Rev. 0 CD 0

Sheet - Formal Tests (Page 6 of 6) 00 2.) Memorandum from C.T. Snow to E.J. Lozito, dated June 27, 1980 3.) WCAP-7905, Rev. 1 4.) ET NAF-06-0053, Rev. 0 CD 0

C4 C0