ML003781899

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Surry Power Station Unit 2 Cycle 17 Startup Physics Tests Report
ML003781899
Person / Time
Site: Surry Dominion icon.png
Issue date: 12/21/2000
From: Sarver S
Virginia Electric & Power Co (VEPCO)
To: Reyes L
Region 2 Administrator
References
-RFPFR, 00-657, NLOS/MM
Download: ML003781899 (61)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 21, 2000 Mr. Luis A. Reyes, Administrator Serial No.: 00-657 United States Nuclear Regulatory Commission NLOS/MM Region II Docket No.: 50-281 Atlanta Federal Center License No.: DPR-37 61 Forsyth St., SW, Suite 23 T85 Atlanta, GA 30303-8931

Dear Mr. Reyes:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 17 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-1261, Revision 0, entitled "Surry Unit 2, Cycle 17 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after the initial criticality of Cycle 17 on October 30, 2000. The results of the physics tests were within the applicable Technical Specification limits.

If you have any questions or require additional information, please contact us.

Very truly yours, S. P. Sarver, Acting Director Nuclear Licensing and Operations Support Enclosure - Surry Unit 2, Cycle 17 Startup Physics Tests Report Commitment Summary: There are no new commitments as a result of this letter.

cc: U. S. Nuclear Regulatory Commission - 5 copies Attention: Document Control Desk Washington, DC 20555-0001 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

DominIonm Surry Unit 2 Cycle 17 Startup Physics Tests Report NuclearAnalysis

& Fuel Nuclear Engineering

& Services December,2000

TECHNICAL REPORT NE-1261 - REV. 0 SURRY UNIT 2, CYCLE 17 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES DOMINION GENERATION DECEMBER, 2000 PREPARED BY: .,_-/,

JI) reitlow Date REVIEWED BY:__ W__ D T. L. Wheeler Date REVIEWED BY: d f i d41410 D. C.gLrence Date APPROVED BY. DaZ/ 71o C. B. LaRoe Date QA Category: Safety Related Keywords: S2C 17, Startup

CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

NE- 1261 $2C 17 Startup Physics Tests Report Page I of 58

TABLE OF CONTENTS PAGE Classification/Disclaimer .................................................................................. 1 Table of Contents .......................................................................................... 2 List of T ables ................................................................................................ 3 List of Figures .............................................................................................. 4 Preface ............................................................................................................... 5 Section 1 Introduction and Summary ......................................................... 7 Section 2 Control Rod Drop Time Measurements ................................... 17 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 ............................................................................... 41 APPENDIX Startup Physics Test Results and Evaluation Sheets .......... 42 NE-1261 $2C17 Startup Physics Tests Report Page 2 of 58

LIST OF TABLES TABLE TITLE PAGE 1.1 Chronology of Tests ............................................................................. 11 2.1 Hot Rod Drop Time Summary ............................................................. 19 3.1 Control Rod Bank Worth Summary .................................................... 25 4.1 Boron Endpoints Summary .................................................................. 30 4.2 Boron Worth Coefficient ................................................................... 31 5.1 Isothermal Temperature Coefficient Summary .................................... 33 6.1 Incore Flux Map Summary ................................................................. 36 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits ...................................................... 37 NE-1261 S2C17 Startup Physics Tests Report Page 3 of 58

LIST OF FIGURES FIGURE TITLE PAGE 1.1 Core Loading M ap ............................................................................ 12 1.2 Beginning of Cycle Fuel Assembly Burnups ...................................... 13 1.3 Available Incore Moveable Detector Locations .................................. 14 1.4 Burnable Poison Locations ................................................................. 15 1.5 Control Rod Locations ........................................................................ 16 2.1 Typical Rod Drop Trace ................................................................... 20 2.2 Rod Drop Time - Hot Full Flow Conditions ...................................... 21 3.1 Control Bank B Integral Rod Worth - HZP ...................................... 26 3.2 Control Bank B Differential Rod Worth - HZP ................................ 27 6.1 Assemblywise Power Distribution - 29% Power ............................... 38 6.2 Assemblywise Power Distribution - 66% Power ............................... 39 6.3 Assemblywise Power Distribution -100% Power .............................. 40 NE-1261 S2C17 Startup Physics Tests Report Page 4 of 58

PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry Unit 2, Cycle 17 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 17 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results.

Each data sheet provides the following information: 1) test identification, 2) test 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 the calculations performed by Dominion Generation's Nuclear Analysis and Fuel Group (Reference 1). During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliminary comparison between measured and predicted NE-1261 S2C17 Startup Physics Tests Report Page 5 of 58

test results, thus enabling a quick identification of possible problems occurring during the tests.

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SECTION 1 INTRODUCTION AND

SUMMARY

On October 1, 2000 Unit No. 2 of the Surry Power Station shutdown for its sixteenth refueling. During this shutdown, 56 of the 157 fuel assemblies in the core were replaced with fresh assemblies. The Cycle 17 core consists of 7 sub-batches of fuel:

three once-burned batches from Cycle 16 (batches 18A, 18B and 18C); two twice-burned batches from Surry 1 Cycles 15 and 16 (batches S1/17A and S1/17B); and two fresh batches (batches 19A and 19B). The fresh batches are of a similar design to the Westinghouse batch 18 fuel (fresh fuel in Cycle 16).

In Cycle 17, a BPRA product with an active absorber length of 127.1 inches is used. Cycle 17, similar to Cycle 16, incorporated the burnable poison rod design made of B 4C in Alumina, which is available in various enrichments of B 4C. There are no thimble plugging devices, flux suppression inserts, or secondary sources inserted in $2C 17.

The core loading pattern and the design parameters for each sub-batch are shown in Figure 1.1. Beginning of cycle fuel assembly burnups are given in Figure 1.2 and documented in Reference 6. The available incore moveable detector locations used for the flux map analyses are identified in Figure 1.3. Figure 1.4 identifies the location and NE-1261 $2C17 Startup Physics Tests Report Page 7 of 58

number of burnable poison rods for Cycle 17, and Figure 1.5 identifies the location and number of control rods in the Cycle 17 core.

On October 30, 2000 at 0315, the Cycle 17 core achieved initial criticality. Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1.

A summary of the results of these tests follows:

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

The S2C 17 startup was the second time that the new RMAS Reactivity computer, described in Reference 11, was used at Surry. Individual control rod bank worths were measured using the rod swap technique (References 2 and 5). The sum of the individual measured control rod bank worths was within 1.2% of the design prediction and the reference bank worth was within 0.5% of its design prediction. The other control rod banks were within 12.1% or 27.9 pcm (for bank "A") of the design predictions. 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.

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Measured critical boron concentrations for two control bank configurations were within 20 ppm of the design predictions. These results were within the design tolerances and also met the Technical Specification 4.1 0.A criterion that the overall core reactivity balance shall be within +/-1% Ak/k of the design prediction.

The boron worth coefficient measurement was within 1.60% 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 1.05 pcm/F of the design prediction. This result is within the design tolerance of -3 pcm/nF. The measured ITC of -1.395 pcm/IF meets the Core Operating Limits Report (COLR) 2.1.1 criterion that the moderator temperature coefficient (MTC) be less than or equal to +6.0 pcm/nF. When the Doppler temperature coefficient and a 0.5 pcm/°F uncertainty are accounted for in the MTC limit, the MTC requirement is satisfied as long as the ITC is less than or equal to +3.81 pcm/IF.

Measured core power distributions were within established design tolerances.

Generally, the measured core power distributions were within 13.8% of the design predictions. The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of COLR Sections 2.3 and 2.4, respectively.

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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.

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Table 1.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drops - Hot Full Flow 10/29/00 0329 HSD 2-NPT-RX-014 Boron Endpoint - ARO 10/30/00 1035 HZP 2-NPT-RX-008 Reactivity Computer Checkout 10/30/00 1035 HZP 2-NPT-RX-008 Zero Power Testing Range 10/30/00 1046 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 10/30/00 1140 HZP 2-NPT-RX-008 Bank B Worth 10/30/00 1227 HZP 2-NPT-RX-008 Boron Endpoint - B in 10/30/00 1558 HZP 2-NPT-RX-008 Bank A Worth - Rod Swap 10/30/00 1600 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap 10/30/00 1614 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap 10/30/00 1627 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 10/30/00 1710 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap 10/30/00 1729 HZP 2-NPT-RX-008 Flux Map - 30% Power 11/01/00 2358 29% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 Flux Map - 68% Power 11/04/00. 1435 66% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 Flux Map - 100% Power 11/08/00 1600 100% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 NE-1261 $2C17 Startup Physics Tests Report Page 11 of 58

Figure 1.1 SURRY UNIT 2 - CYCLE 17 CORE LOADING MAP R P N M L K J H G F E D C B A I 7A* I 7A*

I 17B 03B 31lB 17B* 17B* 1 19B I17B* 19B I 17B* I 17B*

54B 42B 47P 51iB 50P 34B 40B 17A* 19A 19B 18C 19B 18C 19B 19A 17A*

3 01B 06P 29P 34N 33P 31N 49P 12P 13B 17A* 17B* 19B 18B 19A 18B 19A 18B 19B 17B* 17A* 4 28B 41B 39P 15N 08P 07N 21P 28N 41P 46B 05B 17B* 19A 19B 18C 19A 18C 19A 18C 19A 18C 19B 19A 17B*

5 35B 14P 45P 53N 23P 32N 22P 41N 25P 52N 38P 27P 57B 17B* 19B 18B 19A 18C 18B 18B 18B 18C 19A 18B 19B 17B* 6 53B 55P 11N 24P 33N 19N 02N 17N 5ON 09P 14N 35P 52B 17A* 19B 18C 19A 18C 18B 18B3 18C 18B 18B 18C 19A 18C 19B 17A* 7 27B 30P 42N 19P 36N 04N 23N 51N 21N 05N 47N IIP 39N 56P 30B 17A* 17B* 19B 18B 19A 18B 18C 18A 18C 18B 19A 18B 19B 17B* 17A* 8 12B 49B 43P 12N 05P 18N 30N 0IN 38N 08N 02P 26N 32P 43B 19B 17A* 19B 18C 19A 18C 18B 18B 18C 18B 18B 18C 19A 18C 19B 17A* 9 26B 34P 46N 1lP 44N 22N 24N 43N 25N 09N 37N 07P 55N 31P 25B 17B* 19B 18B 19A 18C 18B 18B 18B 18C 19A 18B 19B 17B* 10 39B I 46P 16N 16P 35N 27N ION 03N 40N 26P 13N 52P 45B 17B* 19A 19B 1 19A I8C 19A 18C 19A 18C 19B 19A 17B*

11 60B loP 51P 49N 03P 45N 04P 48N 15P 54N 36P 13P 59B 17A* 17B* 19B 18B 19A 18B 19A 18B 19B 17B* 17A* 12 06B I 56B I 44P 29N 18P 20N 28P 06N 53P 44B I 20B 17A* 19A 19B 18C 19B 18C 19B 19A 17A* 13 14B 20P 48P 57N 37P 56N 40P 17P 02B 17B* 17B* 19B 17B* 19B 17B* 17B* 14 38B 33B I 54P 50B 42P 55B I 37B D ---

Batch Assembly rD I 7A*

24B 17A*

08B 17A*

29B

  • Assembly is from Surry 1 15 FUEL ASSEMBLY DESIGN PARAMETERS SUB-BATCH SI/17A SI/17B 18A 18B 18C 19A 19B INITIAL ENRICHMENT 3.8092 4.0073 3.8272 4.1015 4.2560 4.1037 4.2552 (W/O U-235)

BURNUP AT BOC 17 41453 40254 19475 21479 20415 0 0 (MWD/MTU)

ASSEMBLY TYPE 15x15 15x15 15x15 15x15 15x15 15x15 15x15 NUMBER OF ASSEMBLIES 20 24 1 28 28 28 28 FUEL RODS PER 204 204 204 204 204 204 204 ASSEMBLY I I NE-1261 S2C17 Startup Physics Tests Report Page 12 of 58

Figure 1.2 SURRY UNIT 2 - CYCLE 17 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R P N M L K J H G F E D C B A 7'31,B 1 144439141788 4466'7 54B 42B 47P I51B 50P 34B I 40B 2

42607 38456 0 377821 0 138614143023 01B I 06P 29P 34N I 33P 1 31N 49P I 12P 13B 3 38367 0 0 1171581 0 17391 0 0 139006 28B 41B 39P I 15N 08P 07N 21P 28N 41P 46B 05B 39075 40165 0 22859 0 22572 0 4 22734 0 40040 38283 35B 14P 45P 53N 23P 32N 22P 41N 25P 52N 38P 27P 57B 44080 0 0 21392 0 210681 0 21158 0 5 22161 0 0 43410 53B 55P llN 24P 33N 19N 02N 17N 50N 09P 14N 35P 52B 38595 0 22748 0 22250 17963 23041 18294 21747 0 6 22799 0 38689 27B 30P 42N 19P 36N 04N 23N 51N 21N 05N 47N liP 39N 56P 30B 44168 0 16909 0 21285 18023 22768 22862 23001 18078 21248 7 0 17166 0 44277 12B 49B 43P 12N 05P 18N 30N O1N. 38N 08N 02P 26N 32P 43B 19B 41338 38131 0 22503 0 23269 22592 19475 22596 23004 0 22154 8 0 37908 41162 26B 34P 46N O1P 44N 22N 24N 43N 25N 09N 37N 07P 55N 31P 25B 44324 0 17040 0 21217 17806 23306 22478 23112 18424 20814 9 0 16951 0 44480 39B 46P 16N 16P 35N 27N ION 03N 40N 26PI 13N 52P 45B 384251 0 1227491 0 121944118114123170 1179311220111 0 1228161 10 0 138635 60B lOP I 51P 49N I 03P 45N 04P I 48N I15P 54N 36P I 13P 59B 11 434984 0 0 219381 0 1205771 0 1214151 0 21969 0 0 43741 06B 56B 44P 29N 18P1 20N 28P1 06N 53P 44B 20B 384611399551 0 122984 0 22439 12 0 1227401 0 140286 38824 14B 20P1 48P 157NI 37P 56NI 40P I 17PI 02B 383311 0 13 0 17085 0 17180 0 0 38288 38B 33B 54P 50B 42P 55B 37B 42835 39064 14 0 37550 0 138458142166 24B 08B 29B 15 44077 41391 44400 D ---. Assembly ID 10 Assembly Bumup (MWD/MTU)

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Figure 1.3 SURRY UNIT 2 - CYCLE 17 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R P N M L K J H G F E D C B A MD** I MD 2 I 4 + + 4 4 4 MD MD MD MD 3 MD_ 4 MD 4 4 4 MD MD MD 4 M M [MDI DD**L IM D**' IMD** MDT__ MD 5 MD MD MD 6 MD MD MD MD MD 7 MD** MD** MD MD MD** MD 8 MD MD MD MD 9 MD MD MD MD 10 II jMD L-jIMDI J- IMD,__I 11 MD MD MD MD 12 4 4--4--+-+ +/- 1*-

MD MD 13

.1. J. 4-4-4-4 MD MD** 14 MD M MDM MD 15 MD - Moveable Detector

    • - Locations Not Available For Flux Mapping System for Cycle 17 NE-1261 S2C17 Startup Physics Tests Report Page 14 of 58

Figure 1.4 SURRY UNIT 2 - CYCLE 17 BURNABLE POISON LOCATIONS R P N M L K J H G F E D C B A 1

2 5P I 20P 20P 20P I 5P 1-I-,

BP8321BP816 BP804 BP817[BP833 3 20M 20P 20P 20M BP824 BP792 BP793 BP825 4 BP834 BP831 P808 P848BP800 BP849PP809 BP826 P8381 5 20P 20M 8P 8P 20M 20P BP823 BP815 BP84C BP841 BP810 BP8 18 6 20P 4P 8P 8P 4P 20P BP799 BP855 BP847 BP842 BP850 BP794 7 20P 20P 20P 20P BP807 BP803 BP801 BP805 8 20P 4P 8P 8P 4P 20P BP798 BP854 BP8461 IBP843 BP851 BP7951 9

20P 20M 8P 8P 20M 20P BP822 BP814 BP845 BP844 BP811 BP81S 10 5P I 20M 4P I20PI 4P I20M I 20M I5P BP835JBP8301 BP813 BP853[BP802jBP852jBP8121 jBP827[BP8391 11 20M 20P 20P 20M BP829 BP797 BP796 BP828 12 5P I 20P 20P 20POL 5P BP836[BP821 BP806 BP820BP837 13 14 15 8P- 8 Burnable Poison Rod Cluster 5P - 5 Burnable Poison Rod Cluster, Asymmetric 4P - 4 Burnable Poison Rod Cluster 20P- 20 Burnable Poison Rod Cluster 20M- 20 Burnable Poison Rod Cluster, Mixed enrichments NE-1261 $2C17 Startup Physics Tests Report Page 15 of 58

Figure 1.5 SURRY UNIT 2 - CYCLE 17 CONTROL ROD LOCATIONS R P N M L K J H G F E D C B A SB I A D 4 A 2 4 4 A 4 4 D 4 4 A .4 SB SA SA 3

+ 4 + 4 4 4 4 1 +/-

C B B C 4

__ _ I_ SBI _ I__I _I__ _JSBJ _ _I 5 A B D C D B A 6 SA SB SB SA 7 D C C D 8 SA SB SB SA _ 9 A B D C D B A 10

___ 4 4 4 4 4 4 4 .4 + 4

  • SB SB 11 4 4 4 4 4 4 .4 .4 + + -t 4 C B B C 12 4 4 4 .4 .4 .4 *4 + 4*

SA SA 13

.4 .4 .4 .4 .4 4 +/- 4-A D A 14 I -1 Absorber Material: Ag-In-Cd 15 Function Number of Clusters Control Bank D 8 Control Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 NE-1261 S2C17 Startup Physics Tests Report Page 16 of 58

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

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. The Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded to determine the drop time of each rod.

As shown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the increase of the IRPI coil voltage. As the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing.

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The measured drop times for each control rod are recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C.1.3 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 seconds for all rods. This Technical Specification requires that the RCS is at hot, full flow conditions. These test results satisfied this limit. In addition, rod bounce was observed at the end of each trace which demonstrated that no control rod stuck in the dashpot region.

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Table 2.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-06 1.40 sec. M-06 1.25 see. 1.29 sec.

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Figure 2.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE Time (seconds)

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Figure 2.2 SURRY UNIT 2 - CYCLE 17 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 I

1.28 1.27 1.29 2 1.28 1.27 1.29 4-4 1.26 4-4-1 1.31 1.31 3 1.26 1.28 1.26 1.29 1.30 4 1.28 1.30 4 4-1.27 1.29 5 1.27 1.29 1.28 1.25 1.31 1.30 1.40 1.29 1.36 6 1.31 1.28 1.26 1.30 7 1.26 1.30 1.29 1.30 8 1.30 1.30 1.26 1.30 9 1.29 1.28 1.32 1.30 1.33 1.29 11.32 10 1.291.301.281.321.331.29.123 11 1.27 . 11.27

.2 1.291 1.29. 1.27 12 1.26 1.30 13 1.33 1.27 1.31 14 12721. 1 .2 15 Fx-: >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 (References 2 and 5). 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 17, Control Bank B was used as the reference bank.

After the 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 in Reference 11, 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).

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Test bank swaps proceed in sequential order form 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 previous test 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 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.

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A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance (- 10% for the reference bank, - 15% for test banks 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 1.2% 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 B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.

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Table 3.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM) (PCM) (M-P)/P X 100 B-Reference Bank 1364.3 1371.0 -0.5 D 983.9 974.9 +0.9 C 756.3 774.8 -2.4 A 258.8 230.9 -12.1*

SB 1219.1 1201.6 +1.5 SA 1021.1 985.2 +3.6 Total Worth 5603.5 5538.4 +1.2

  • Difference is less than 100 pcen.

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Figure 3.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN

-1 1600 I\I

~ ii- -

1400 1200 U

U 1000 04

--I 0

Measured S800

-Predicted tm S600 H

400 I

i 200 0

0 50 100 150 200 250 Bank Position (steps)

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Figure 3.2 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 10 9

8 7

  • J0 0

SI:

10 0

6 5

I\V -- Measured

Predicted 0

44

'.4 S* 4 3

2 1

0 0 50 100 150 200 250 Bank Position (steps)

NE-1261 S2C17 Startup Physics Tests Report Page 27 of 58

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

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the NE-1261 $2C17 Startup Physics Tests Report Page 28 of 58

time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.

A summary of the measured and predicted DBW is shown in Table 4.2. As indicated in this table and in the Appendix, the measured DBW was well within the design tolerance of +/--10%. In summary, the measured boron worth coefficient was satisfactory.

NE-1261 S2C17 Startup Physics Tests Report Page 29 of 58

Table 4.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 2018 1998 20 B Bank In 1823 1819* 4

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

NE-1261 $2C17 Startup Physics Tests Report Page 30 of 58

Table 4.2 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

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

-7.00 -6.89 1.60 NE-1261 $2C17 Startup Physics Tests Report Page 31 of 58

SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature by varying blowdown flow to the steam generators, 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 3.91'F and RCS heatup of 4.64'F. 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 -3 pcm/°F. The moderator temperature coefficient was determined to be 0.295 pcm/°F which met the requirements of COLR Section 2.1.1. In summary, the measured results were satisfactory.

NE-1261 $2C17 Startup Physics Tests Report Page 32 of 58

Table 5.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

ISOTHERMAL TEMPERATURE BANK TEMPERATURE BORON COEFFICIENT (PCM/OF)

POSITION RANGE CONCENTRATION Cool- Heat AVE DIFFER (STEPS) (OF) (ppm) down -up MEAS PRED (M-P) 543.07 D/213 to 2018 -1.096 -1.693 -1.395 -2.440 1.045 547.71 _ 1 1 1 1 1 NE-1261 S2C17 Startup Physics Tests Report Page 33 of 58

SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the moveable incore detector flux mapping system. This system consists of up to 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 17. For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using a Virginia Power modified version of the Combustion Engineering computer program, CECOR (Reference 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 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 29% 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% and 100% power, respectively, with different control rod configurations. These flux maps were taken to check at-power design predictions and to NE-1261 $2C17 Startup Physics Tests Report Page 34 of 58

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 were all within 13.8% of the predicted values. Further, the measured F-Q(Z) and F-DH(N) peaking factor values for the at-power flux maps were within the limits of COLR Sections 2.3 and 2.4, respectively. Flux maps 1, 2, and 3 were also used to perform power range detector calibrations. The flux map analyses are documented in Reference 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. It is therefore anticipated that the core will continue to operate safely throughout Cycle 17.

NE-1261 S2C17 Startup Physics Tests Report Page 35 of 58

Table 6.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Bum Bank Peak F-Q(Z) Hot(l) F-DH(N) Hot Core F(Z) Core Tilt Axial No.

Map Map up Pwr D Channel Factor Channel Factor Max (2) off of Description No. Date MWD/ % Steps Assy Axial F-Q(Z) Assy F-DH(N) Axial F(Z) Max Loc set Thim MTU Point Point (C%) Bles Low Power 1 11/2/00 4.1 29 166 K5 26 2.092 J4 1.524 26 1.271 1.0250 NW 3.453 38 Int. Pwr(3) 2 11/4/00 34.8 66 185 K5 30 1.907 J4 1.479 26 1.189 1.0161 NW 1.426 42 PotFull Pwr 3 11/8/00 169 100 220 F5 30 1.785 F5 1.461 19 1.13211.0099 NW 2.230 42 NOTES: Hot spot locations are specified by giving assembly locations (E.G. H-8 is the center-of core assembly) and core height (in the "Z" direction the core is divided into 61 axial points starting from the top of the core).

(1) F-Q(Z) includes a total uncertainty of 1.05 X 1.03.

(2) CORE TILT - defined as the average incore quadrant power tilt from CECOR.

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

(4) MAPS 1, 2, and 3 were used for power range detector calibrations.

NE-1261 $2C17 Startup Physics Tests Report Page 36 of 58

Table 6.2 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak F-Q(Z) Hot F-Q(Z) Hot F-DH(N) Hot Map Channel Factor* Channel Factor** Channel Factor (At Node of Minimum Margin)

No. Meas. Limit Node Meas. Limit Node Margin Meas. Limit Margin I (%) (%__)

1 2.092 4.312 26 2.079 4.312 23 51.79 1.524 1.892 19.45 2 1.907 3.272 30 1.899 3.272 21 41.96 1.479 1.721 14.06 3 1.785 2.112 30 1.770 2.112 15 16.19 1.461 1.560 6.35

  • The Core Operating Limit for the heat flux hot channel factor, F-Q(Z), is a function of core height and power level. The value for F-Q(Z) listed above is the maximum value of F-Q(Z) in the core. The COLR limit listed above is evaluated at the plane of maximum F-Q(Z).

"**The value for F-Q(Z) listed above is the value at the plane of minimum margin. The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(Z) and the COLR limit for each map.

The measured F-Q(Z) hot channel factors include 8.15% total uncertainty.

NE-1261 S2C17 Startup Physics Tests Report Page 37 of 58

Figure 6.1 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 29% POWER R P M L K i H G F E D) C

. PREDICTED. . 0.195 0 205 . 0 195 PREDICTED MEASURED 0.202 . 0.211 . 0:199 MEASURED

.PCT DIFFERENCE. 4.0 2.7 . 2.3 .PCT DIFFERENCE

. 0.276 . 0.482 1.008 0.595 1.010 . 0.485 . 0.276 0.283 . 0.501 1.052 0.610 . 1.032 0 .499 0.282 2.8 . 3.8 4.3 . 2.5 2.2 . 2.9 . 2.0 1.063 . 1 296 .1.310 . 1.282 ,1.311 1298 1 1.065. 0 296

  • 0.296 1
  • 0.303 . 1.090 . 1 343 1 379 . 1.292 . 1.334 . 1.327 . 1.083 0.296 2.4. 2.5. 3-6 5.3 0.8 . 1.8 2.2 1.7 0.0 .

11351 1740 3 11352 1 349

. 0.297 . 0.605 . 1.305 . 1 348 0.305 . 0.619 - 1.321 . 1.386 1 .392 . 1.361 . 1 378 1 388 1.323 . 0 605 0.297 2.8 . 2.3 1.3 2.8 3.0 . 1.6 . 1.9 2.9 1-3 -0.2 . 0.0

. 1.067 .1.310 . 1.334 . 1.327 11292 .1.296. 1.293 , 1. 328 1.335 . 1.310 . 1 067 . 0 275 .

00.274 5 . 0.283 1.100 . 1.353 1 .398 1 0368 1.327 1 .323 1.315 1.346 1 337 1.288 1 .070 0 _313 3.0 . 3.1 . 3.3 4.8 3.1 2.7 2.0 1.7 1.4 0.22 . 1.7 . 0-3 13.8

.0.485 .1.301 . 1.354 - 1.332 . 1.178 .1.170 .1.203 . 1.170. 1 .178. 1.332 . 1 354 . 1.302 . 0.485 .

6 . 0.499 . 1.339 1.387 . 1.354 1 .205 1.198 1 232 1.187 1. 188 1.329 . 1.341 1 .294 0 .489 .

2.8 . 2.9 . 2.5 . 1.7 - 2.3 2.4 . 2.4 1.4 0.8 0.2 -1.0 . 0.6 0-7 ,

.0.195

  • 1.014 .1.316 . 1.357 - 1.297 - 1.172 .1.177 .1.213 1. 178 1.173 1.297 . 1.357 . 1.316 . 1.014 0.195 7 0.200 . 1.042 1.358 1.383 1 _313 1.193 1.205 1 .232 1.186 1 173 1 289 . 1.337 . 1 300 1.002 0. 192 2.5 . 2.8 - 3.2 . 2.0 1.2 1.8 2.4 1.6 0.7 0.0 0 7 . 1.4 . 1.2 . -1.1 -1.7 1.215 . 1.206 1.301 . 1.345 . 1.2886 0.598 0.206 0.206 . 0.598 . 1.288 . 1.345 1.301 1 206 . 1.215 . 1.209-.

8 0.209 . 0.608 1.307 . 1.360 .1.292 . 1.223 1.236 . 1.219 1. 212 1: 196 1.288 _ 1.327 . 1.265 _ 0.575 0.197 1.5 . 1.6 . 1.5 . 1.1 0.7 . 1.4 1.7 0.8 . -0.2 0.8 -0.9 . 1.3 . 1.8 . 3.8 4.0

.0.195 . 1.014 .1.316 . 1.357 . 1.297 . 1.173 .1.178 , 1.213 1177 1 .1.172 . 1.297 . 1.357 . 1.316 . 1 014 0:195 .

9 0 196 . 1.015 1.317 . 1.379 1 .371 . 1.207 1 .2084 . 1.216 . 1.159 . 1 172 1.285 _ 1.341 1.291 . 0.982 0 .182 0.3 . 0.1 0.1 . 1.6. 5.7 . 2-9 2.2 0.2 -1.6 0.0 0-9 . 1.1 . 1.9 3.1 6.9 0.485 1.302 . 1.354 1.332 . 1.179 1 170 . 1203 . 1 170 1.178 1.332 1.354 . 1.302 0 485 10 0.477 . 1.262 1.353 1.356 . 1.201 1 .217 . 1.197 1. 150 1.161 1.313 1.349 . 1.278 0 465 10

17. 3.0. 0.1 17 1.9 4.0 -0.6 . 1.7 . 1.5 -1.4 . 0-4 . 1.9 -4.2 .

00275 . 1.067 . 1 311 .1.335 . 1.328 1 328 1 335 11310 1.067 . 0.275' .

1 294 1.297 - 1.293 11 0 .269 1.046 . 1.299 1.330 1 319 1.274 1.240 . 1.251 . 1.288 1 296 '1.278 1 039 0 266 11 2.0 20. -0.8. -0.3. 07 1.5 . 4 4 . 3.2 . 3.0 2-9 2.5 2.6 _3.2 1 306 0.606

.....4i.........

. 0.297 . 0.606 . 1.306 . 1'350 . 1.353 . 1.341 . 1 352 . 1.350 . 0.297 12 . 0.289 . 0.597 1.284 . 1.317 1.294 1.287 . 1.303 1 _302 1 .257 0.569 0.279 12

-2.8 -1.5 -1.7 . -2 4 -4.4 . -4.0 -3.6 -3.5 8 -6.1 -6.0.

.1.311 . 1.283 . 1 313 . 1.299 1 065 0.296 0.296 . 1.065 , 1'299 13 0 290 1.040 . 1.260 1 263 1.236 . 1.264 1 252 1 .025 . 0.282 13 2.1 -2.4 _2.9 3.7 -3.7 3.6 . 3.6 3.8 . 4.7 0.276 . 0.485 1 011 0 595 1 011 0 485 0.276 0:971 0:575 . 0.975 - 0:467 0.266. 14 14 0.265 . 0.468

-4.0 _3.5 -39. 3-5 35 3.7. 3.8 STANDARD 0-195 0 205 . 0.195 AVERAGE 15 DEVIATION 0.179 0.196 01880 .PCT DIFFERENCE. 15

.. 723

.. -8.2 -4.6 -3.8 = 2.4 R L K H G F E D B A Summary Map No: S2-17-01 Date: 11/02/2000 Power: 29.10%

Control Rod Position:

D Bank at 166 Steps F-Q(Z) = 2.092 F-DH(N) = 1.524 F(Z) = 1.271 QPTR: 1.0250 0.9937 + 1.0059 0.9753 Burnup = 4.1 MWD/MTU A.O. = 3.453 NE-1261 S2C17 Startup Physics Tests Report Page 38 of 58

Figure 6.2 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 66% POWER R P N M L K 3 H G F E D C B A

  • PREDICTED .. 0211 .0.227 .0.211 . PREDICTED MEASRED . 0.218 . 0.231 . 0.214 . MEASURED I

.PCT DIFFERENCE. 3.4 . 2.1 . 1.4 . PCT DIFFERENCE.

0.287 . 0.4197 . 1.033 . 0.640 . 1.035 . 0.499 . 0.287.

2 . 0.292 . 0.513 . 1.072 . 0.652 . 1.048 . 0.501 . 0.290 .

2.1 . 3.1. 3.7 . 1.9 . 1.3 . 0.3 . 1.1 .

0.307 -1.057 .1.274 .1.298 .1.273 1.299; 1 . 1.276 .1.058 0.307

3. 0.305 . 1.075 . 1.312 . 1.361 . 1.279 . 1.317 . 1.300 . 1.075 . 0.305 .3

-0.6 . 1.7 . 3.0 . 4.9 . 0.5 . 1.4 . 1.9 . 1.5 . -0.5 .

0.308 . 0.614 . 1.277 . 1.320 . 1.322 . 1.317 . 1.322 . 1.321 . 1.278 . 0.614 . 0.308.

4. 0.312 . 0.620 . 1.286 . 1.348 . 1.353 . 1.324 . 1.345 . 1.364 . 1.299 . 0.614 . 0.305 . 4 1.4 . 1.1. 0.7 . 2.1 . 2.3 . 0.5 . 1.7 . 3.2 . 1.7 . 0.0 . -0.8 .

0.285 . 1.059 . 1.281 . 1.313 . 1.314 . 1.283 . 1.281 . 1.283 . 1.314 . 1.313 . 1.282 . 1.059 . 0.285.

5 0.289 . 1.077 . 1.306 . 1.358 . 1.343 . 1.310 . 1.303 . 1.310 . 1.344 . 1.326 . 1.267 . 1.048 . 0.276 . 5 1.5 . 1.7 . 1.9 . 3.4 . 2.3. 2.1 . 1.7 . 2.0 . 2.3 . 1.0 . -1.1. -1.1 . -3.1 .

0499 .1.278 .1.325 .1.31i7 .1.226 .1.189 .1.215 .1.18;9 .1.226 .1.318 .1.325 .1.278 .0.499

.. 0.506 . 1.296 . 1.340 . 1.324 . 1.245 . 1.214 . 1.245 . 1.217 . 1.265 . 1.331

  • 1.319 . 1.267 . 0.494 . 6 1.3 . 1.4 . 1.1. 0.5 . 1.5 . 2.1 . 2.4 . 2.4 . 3.2 . 1.0 . -0.4 . -0.8 . -1.0 .

. 0.212 . 1.037 . 1.303 . 1.326 . 1.286 . 1.191 . 1.202 . 1.236 . 1.202 . 1.191 . 1.287 . 1.326 . 1.303 . 1.037 . 0.212 .

7 . 0.214 . 1.050

  • 1.323 . 1.333 . 1.286 . 1.204 . 1.231 . 1.261 . 1.224 . 1.212 . 1.293 . 1.314 . 1.291 . 1.031 . 0.210 . 7 1.0. 1.3. 1.5. 0.5. -0.1. 1.1. 2.5. 2.1. 1.8. 1.7. 0.5. -0.9. -0.9. -0.6. -1.1.

0.227 0.643 1.277 1.320 1.284 1.218 1.237 1.234 1.237 . 1.218 1.284 1.320 1.277 0.643 02 8 0.227. 0.645: 1.280. 1.318. 1.252 . 1.226 1.260 . 1.253 . 1.252 . 1.236 . 1.288 . 1.313 . 1.262 . 0.625 . 0.220 . 8

  • 0.3 . 0.4 . 0. 2 . _-0. 2 . -2 .5 . 0.7 . 1.8 . 1.6 . 1.2 . 1.5 . 0.3 . -0.5 . -1.2 . -2.8 . -3.0 .

0.212 . 1.037 . 1.303 . 1.326 . 1.287 . 1.191 . 1.202 . 1.236 . 1.202 . 1.191 . 1.287 . 1.326 . 1.303 . 1.037 . 0.212.

9 . 0.211 . 1.030 . 1.293 . 1.337 . 1.350 . 1.222 . 1.232 . 1.250 . 1.201

  • 1.194 . 1.284 . 1.319 . 1.287 . 1.014 . 0.199 . 9

-0.5 . -0.7 . -0.7 . 0.8 . 4.9 . 2.5 . 2.5 . 1.1. -0.1.

. 0.2 .

......... .......... .......... .......... .......... .......... .......... .......... .......... . ........ -0.2 . -0.5 . -1.2 . -2.2 . -6.0 .

.0.499 . 1.278 . 1.325 . 1.318 . 1.226 . 1.189 . 1.216 . 1.1829 . 1.226 . 1.318 . 1.325 . 1.2738 .0.499.

10 . 0.488 . 1.236 . 1.319 . 1.338 . 1.250 . 1.242 . 1.222 . 1.182 . 1.218 . 1.309 . 1.323 . 1.263 . 0.487 . 10

-2.2 . -3.3 . -0.4 . 1.5 . 2.0 . 4.4 . 0.5 . -0.6 . -0.7 . -0.7 . -0.1 . -1.2 . -2.6 .

0.285 . 1.060 . 1.282 . 1.313 . 1.314 . 1.284 .1.281 . 1.283 . 1.314 . 1.313 . 1.282 . 1.059 . 0.285.

11 . 0.278 . 1.035 . 1.269 . 1.312 . 1.309 . 1.271 . 1.246 . 1.257 . 1.290 . 1.292 . 1.261 . 1.040 . 0.279 . 11

-2.3 . -2.3 . -1.0 . -0.1 . -0.4 . -1.0 . -2.8 . -2.1 . -1.8 . -1.6 . -1.6 . -1.8 . -2.1 .

.0.308 .0.614 .1.278 .1.322 .1.323 .1.317 .1.323 .1.321 .1.278 .0.614 . 0.308 .

12 . 0.295 . 0.604 . 1.259 . 1.291 . 1.261 . 1.278 . 1.283 . 1.277 . 1.237 . 0.587 . 0.291 . 12

-4.1 . -1.6 . -1.5 . -2.3 . -4.7 . -3.0 . -3.0 . -3.4 . -3.2 . -4.3 . -5.5 .

0.307 .1.059 .1.276 .1.300 .1.274 2 .300 .1.276 .1.058 .0.307 13 . 0.301 . 1.036 . 1.243 . 1.261 . 1.254 . 1.256 . 1.204 . 1.012 . 0.293 . 13

-2.0 . -2.1 . -2.6 . -3.0 . -1.5 . -3.4 . -5.6 . -4.4 . -4.5 .

0.287 . 0.500 . 1.035 . 0.641 . 1.035 . 0.500 . 0.287.

14 . 0.277 . 0.485 . 1.002 . 0.624 . 1.000 . 0.476 . 0.274 . 14

-3.5 . -3.0 . -3.2 . -2.5 . -3.4 . -4.7 . -4.6 .

STANDARD . 0.212 . 0.227 . 0.212 . AVERAGE 15 DEVIATION .0.194 . 0.218 . 0.204 . .PCT DIFFERENCE. 15

-1.391 -8.3 . -3.9 . -3.5 . . 1.9 R P N M L K 3 H G F R D C B A SummarY Map No: S2-17-02 Date: 11/4/2000 Power: 65.56%

Control Rod Position: F-Q(Z) = 1.907 QPTR: 1.0161 1.0083 D Bank at 185 Steps F-DH(N) = 1.479 0.9935 0.9822 F(Z) = 1.189 Bumup = 34.8 MWD/MTU A.O. = 1.426 NE-1261 $2C17 Startup Physics Tests Report Page 39 of 58

Figure 6.3 SURRY UNIT 2 - CYCLE 17 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R L K H G F E D A PREDICTED 0.221 0.242 " 0 221 PREDICTED 0 .227 0 246 0.224 0 MEASURED MEASURED 2 6 1.6 1.5 .PCT DIFFERENCE.

.PCT DIFFERENCE.

.'0 289 .

. 0.289 .0.500. 1-036 . 0-684 . 1.037 0.502

. 0.292 0.512 1 066 0 693 . 1.053 0.514 0.295 2 1.3 2.3 2.9 1.3. 1.5 2.3 2.1

. 0.309 . 1.034 - 1:244". 1.278 . 1.260 . 1.279 . 245 1.035 . 0.309 0.309 . 1.043 . 1 270 1.329 1.259 . 1.295 1.272 . 1.056 0 314 0.0 . 0-9 2.1 4.0 -0.1 1.3 2.1. 2.0 1-6 0.613 . 0.310.

.0.813 . 1.249 19296 . 1.299 . 1.298 . 1 299 . 1.297 a 1.250' 44 . 0 3.

0.3] . 1.300 . 1.318 1 336 1.272 0 .616 0 .309 0.615 . 1.243 . 1.313 1.321 1.8 0.4 . -0.4 .

0. 0.4. -0.5 13. 17 0.1 1.5. 3.0 1.252 . 1.300 1.315 . 1 286 . 1.276 1.286 . 1.316 1.253 . 1:036 . 0.287

.0.287 1.0] 1.300

. 1.306 1.293 . 1.309 1.343 1 313 1 241 . 1 028 0 281

5. 0.290 . 1.04 1.268 . 1.334 . 1 335 2.6 . 1.5 1.5 1.3 . 1.7 2.0 . 10. I.0 0.8 . 2 1 1.0 . 1 1.2 .

1.238 . 1.223 . 1.310 1.319 1-300 . 1.247 0.502

.'0.502 . 1.21 1.300 . 1.319 . 1 -309 . 1.223 1.306 1. 313 1.319 1. 242 1.265 1.248 . 1 343 1.332 1.297 1.241 0.499

. 0.506 . 1.2!

0.7 . 1.6 2.2 . 2. 0 2.5 . 1.00 -0.2 0.5 0 -0.5 0.8 0. 0.5 0.4 .

. 1.039 . 0 221 .

. 0.221 . 1.039 . 1.24 1.302 . 1 289 . 1.225 , 1.237 . 1 267 . 1.237 ,1.225 . 1 289 1.302 111.282 1.298 . 1.295 1.276 . 1 038 0.220 7 7 . 0 .223 . 1.047 1.2! 1.303 . 1.280 1.232 . 1.261 . 1.289 1.257 1.245 1.6. 1.6 0 7 . -0.6 0.4 0.2. 06.

0.5 . 0.8 1. 0.0. -0.7. 0.6 20. 1.8 1 279 . 1 302 1[.264 0687 0 *0.242,

. 0.242. 0.687 . 1.24 1.302 .... 279* . 1.2480 1.268 1 263 . 1.268 1.240 11.256 1 .286 1 .280 . 1.282 1.260 1 288 . 1:301 0 .669 . 0 236 8 0 241 . 0.685 1.24 1.294 . 1.242 . 1.244 1.5 . 1.3 . 1.1 1.6 0.7 . 0.0 -0.6 . 2.5 2.3 0.2 -0.3 -0. 0 6 . 2.9 0.3 .

1 289 . 1.302 11 282 1.039 . 0.221 0.221

  • 1.039 . 1.24 1.302 1.289 . 1.225 1.238 . 1 267 . 1.237 1.225 1.296 1.306 11:277 . 1.026 0.213 9 9 . 0.219 1.028 1.12 1.308
  • 1.346 . 1 251 . 1.264 . 1.279 .1.234 . 1.238 1.1 0.5 0.3 0.4 . -1.3 -3.6 0.4 4.4. 2.2 2.2. 10. 0.2.

1.319  : 1.300 11 247 . 0.502 0 502 1..2 47 1.300 1.319 . 13310 . 1.223 1 238 1 223 . 13107 17491 173.1A331.1.273 1.245 .1.218 .1.307. 1 319 . 1.314 11.245 0 496 10 10 . 0.489 . 1.24 -1.2 4.0 -0.2 0.0 1.1 0.1

-2.6 . 3 .8. -0.7. 1.2. 1.6. 0.5 . -0.4 1 316 1 300 . 1.253 11.036 . 0.287 .

1.253 1.300 . 1.316 1.287 . 1 277 1.286 12 0.280 . 1.0:46 .

1.299 1.282 1.243 11.028 . 0.284 11 11 0 280

0. 1 _.0* 10 . 1.239
  • 1.297 . 1.311 1.276 1.245 1 .264

-0.8 -2.4 1-.7 3 -1.4 -0.8 -0 8 -1.0

-2.5 . -2 .5 . -1.1 -0.2 . -0.4

.0.3: 10 1.300 1.299 1.300 1.297 1.250 0.613 0.310

. 0.613 1.250 . 1 297 00.298 12 12 . 0.3(20 1271 1 244 1.264 . 1.265 1.2860 1 216 . 0.593

. 0.604 . 1.233 3 -4.2 -2.7 . -2.6 -2.9 -2.7 -3.3 -3.7

.1 -1.5. -1.3 -2.0 1.280 1i261 *1.280" .1.245 , 1 035 . 0 309*

0.309 . 1 035 1.245 1 240 1.240 1 . 183 0.996 0.298 13 13 0.304 . 1.018 1 .218 1 .245

-1.7 -1.7 . -2.2 -2.7 -1.7 -3.1 . -5.0 . -3.8 -3.7 0.289 . 0.502 1.038 0.685 1.038 . 0.502 0 289 0.667 . 1:005 . 0.481 0.278 14 14 0 284 . 0.490 1.008

-1.9 . -2.5 -2.8 2.6 . -3.1 -4.2 -4.0 0 221 0:242 0:221 . AVERAGE STA1 DARD DEVE ATION 0.234 0.214 .PCT DIFFERENCE. 15 15 0. 208

-1. 164 -5.9 -3.4 -3 .2 = 1.6 R K H G F E D Summary Map No: S2-17-03 Date: 11/08/2000 Power: 99.98%

Control Rod Position: F-Q(Z) = 1.785 QPTR: 1.0099 1.0093 0.9931 I 0.9877 D Bank at 220 Steps F-DH(N) = 1.461 F(Z) = 1.132 Burnup = 169 MWD/MTU A.O. = 2.230 NE-1261 S2C17 Startup Physics Tests Report Page 40 of 58

SECTION 7 REFERENCES

1. M. A. Hofmann and R.W.Twitchell, "Surry Unit 2, Cycle 17 Design Report", Technical Report NE- 1259, Revision 0, Dominion Generation, October, 2000.
2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
3. T. W. Schleicher, "The Virginia Power CECOR Code Package", Technical Report NE 831, Revision 4, Virginia Power, August, 1998.
4. Surry Unit 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, 4.10.A, 5.3.A.6.b, and Core Operating Limits Report (COLR) for Surry 2, Cycle 17 Pattern UP, Revision 0 (August, 2000) Sections 2.1.1, 2.3, and 2.4.
5. Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units 1 and 2, Surry 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. C. D. Clemens, "Surry 2, Cycle 17 TOTE Calculations", PM-853, Revision 0, October, 2000.
7. R. A. Hall, et al, "Surry 2, Cycle 17 Flux Map Analysis", PM-859, Revision 0, and Addenda A and B, October, 2000.
8. T. R. Flowers, "Reload Safety Evaluation, Surry 2 Cycle 17 Pattern UP", Technical Report NE-1252, Revision 0, August, 2000.
9. Appendix to "Reload Safety Evaluation, Surry 2 Cycle 17 Pattern UP", "Core Operating Limits Report Surry 2 Cycle 17 Pattern UP" Revision 0, August 2000.
10. Engineering Transmittal NAF 2000-00878 from N. P. Wolfhope to C. B. LaRoe, "Review of Surry Unit 2, Cycle 17 Core Loading Plan, Rev 0", June 28, 2000.
11. P. D. Banning, "Implementation of RMAS for Startup Physics Testing", PM-824, Revision 0, March, 2000.
12. Westinghouse, "Flux Suppression Insert Assembly Design Report Prepared for Virginia Electric and Power Company Surry Nuclear Power Station 1 (Revision 1)",

September 23, 1993.

NE- 1261 S2C 17 Startup Physics Tests Report Page 41 of 58

APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-1261 $2C17 Startup Physics Tests Report Page 42 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - ARO Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (F):  ;,

Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter (Ce)M,.o; Critical Boron Concentration - ARO (Description)

IV Test Results Measured Value (C 9 )MAo=  ; 0 19, ppm (Design Conditions)

Design Value Ce = 1998 +/- 50 ppm (Design Conditions)

Reference Technical Report NE-1259, Rev. 0 V FSARJTech Spec IaCE x C.DI < 1000 pcm Acceptance Criteria Reference Technical Specification 4.10.A Design Tolerance is met / YES NO Acceptance Criteria is met v 1'YES NO VI Comments aC3 = -6.84 pcmlppm C9 0 = I(C9 )Mo"- Cel; C9 is design value I - w/1 - /1/

Prepared By: & _ _. Reviewed By: I - ,#/WO-I I NE-1261 S2C17 Startup Physics Tests Report Page 43 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer Checkout Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No 11 Bank Positions (Steps) RCS Temperature (uF) 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC:

  • CD: Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (oF): -2y Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 CC: . CD: /- Below Nuclear Heating Date/Time Test Performed:

/i3o/oo /0, Measured Parameter Pc= Measured Reactivity using p-computer (Description) Pt= Predicted Reactivity IV Test Pc= _.., - ý C C-, ,

Results Measured Value pt=-2. ,'16/ zi, 30 rt-z"

%D= /.* .- c,. ,,

Design Value %D= {(Pc - p)/Pj x 100% < 4.0 %

Reference WCAP 7905, Rev. 1, Table 3.6 V FSARJTech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : 7 YES NO Acceptance Criteria is met //YYES NO VI

  • At The Just Critical Position Comments The allowable range will be set based on the above results and/or the pre-critical bench test.

Pre-critical Bench Test Results = //' /

Allowable Range = 4-11 /

Prepared By: _ Reviewed By: A/F NE-1261 S2C17 Startup Physics Tests Report Page 44 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ITest

Description:

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

II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC:

  • CD: Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): .'/6.3 Test _Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 CC: -*L.a" CD: ;acO Below Nuclear Heating Date/Time Test Performed:

Reactivity Computer Initial Flux Background Reading .20,r amps IV Test Results Flux Reading At Point Of Nuclear Heating /. 6i[- 7 amps Zero Power Testing Range 2.5/t'-9 to q.c[-* amps Reference Not Applicable V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met*** . YES NO Acceptance Criteria is met**: ._. YES NO VI *At The Just Critical Position Comments ** Design Tolerance and Acceptance Criteria are met if ZPTR is below the Point of Nuclear Heating and above background.

Ai /ii7i' Prepared By: ___ ____ _-__ __ _ Reviewed By: _______

NE-1261 S2C17 Startup Physics Tests Report Page 45 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Isothermal Temperature Coefficient - ARO Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (uF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating Bank Positions (Steps) RCS Temperature (OF): ,/3 - "

III Power Level (% F.P.): 0 Test Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 CC. 228 CD: 213 Below Nuclear Heating Date/Time Test Performed:

j0/3 I_,

o/o iI:_q Measured Parameter (CtTISO )*; Isothermal Temperature (Description) Coefficient - ARO IV Measured Value (aTISO)o= --. 3t* pcm/oF Test Results (CB= ýz 0 ppm)

Design Value (Actual Conditions) (ars°)ARo= - +/-..Hc+3.0 pcm/PF (Cs= . ppm)

Design Value (Design Conditions) 1 (CtT So)-O= -2.62 +/-3.0 pcm/PF (CB= 1998 ppm)

Reference Technical Report NE-1259, Rev. 0 V FSARICOLR < 3.81

  • pcm/ OF
  • xT Acceptance aTDOP = -1.69 pcm/°F Criteria Reference COLR 2.1.1,Technical Report NE-1259, Rev. 0 S.

._ ... _ N -

Design Tolerance is met / YES NU 7 YES __NO Acceptance Criteria is met VI 0

Comments *Uncertainty on aTMoD = 0.5 pcm/ F (

Reference:

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

Prepared By: . . Reviewed By:

NE-1261 S2C17 Startup Physics Tests Report Page 46 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank B Worth Measurement, Rod Swap Ref. Bank Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (0F)- 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: moving CC: 228 CD: 228 Below Nuclear Heating IIl Bank Positions (Steps) RCS Temperature (OF): >17 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter IBREF; Integral Worth Of Control Bank B, (Description) All Other Rods Out IV Test Measured Value isREF= 1 o

  • pcm Results Design Value (Design Conditions) isREF= 1371 +/- 137 pcm Reference Technical Report NE-1259, Rev. 0 And Engineering Transmittal NAF 2000-0120, Rev. 0 If Design Tolerance is exceeded, SNSOC shall V FSAR/Tech Spec evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be performed.

Reference VEP-FRD-36A Design Tolerance is met : NO

"--'-7 YES YES Acceptance Criteria is met : NO VI Comments Prepared By: 6aý Reviewed By:

V NE-1261 S2C17 Startup Physics Tests Report Page 47 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - B Bank In Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 0 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (0F): 91*47.3 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter (CB)MB; Critical Boron Concentration, (Description) B Bank In IV Test Results Measured Value (C8 )M=

B= - ppm (Design Conditions)

Design Value CB = 1799 + ACB (10 P,+/-v_+ + 137.1/jcCBI) ppm (Design Conditions) CB = '\ +/- 30 ppm Reference Technical Report NE-1259, Rev. 0 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met V- YES NO Acceptance Criteria is met v YES NO VI Comments aCB = -6.89 pcm/ppm ACB Prey = (CB)MARO - 1998 ppm Prepared By: *f\L_ Reviewed By: "X NE-1261 S2C17 Startup Physics Tests Report Page 48 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Boron Worth Coefficient Measurement Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (0 F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (0F): S-7 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter aCa; Boron Worth Coefficient (Description)

IV Test Results Measured Value aCs = 7. O 0 pcm/ppm Design Value aCe = -6.89 +/- 0.69 pcm/ppm (Design Conditions)

Reference Technical Report NE-1259, Rev. 0 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met * " YES NO Acceptance Criteria is met YES NO VI Comments Prepared By: Q.\C.L,

, Reviewed By:ýý"V" NE-1261 S2C17 Startup Physics Tests Report Page 49 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank A Worth Measurement, Rod Swap Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:

I Bank Positions (Steps) RCS Temperature (0 F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: moving Other (specify):

(Design) CB: moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (f):

  • j Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB. 228 CA: moving Other (specify):

(Actual) CB: moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

I ClVIlC: (Qcc __________

Measured Parameter IARS; Integral Worth of Control Bank A, (Description) Rod Swap IV Measured Value IARS= (Adjusted Measured Test Critical Reference Bank Position = @ steps)

Results Design Value (Actual Conditions) IARS= 2*- 7 0- (Adjusted Measured Critical Reference Bank Position = ( *

  • c steps)

Design Value (Design Conditions) [ARS= 241 +/- 100 pcm (Critical Reference Bank Position = 70 steps)

Reference Engineering Transmittal NAF 2000-0120, Rev. 0. VEP-FRD-36A FSARiTech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be performed.

_Reference VEP-FRD-36A Design Tolerance is met V- YES_ NO Acceptance Criteria is met 7YES NO VI Comments Prepared By: C"\ "- 4 ,-ýý Reviewed By _ý  : l__

NE-1261 S2C17 Startup Physics Tests Report Page 50 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank C Worth Measurement, Rod Swap Reference Proc No / Section. 2-NPT-RX-008 Sequence StL-= Nco II Bank Positions (Steps) RCS Temperature ('°F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: moving CC: moving CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (uF): q 7. '3 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: moving CC: moving CD: 228 Below Nuclear Heating Date/Time Test Performed:

(c1 XCC C I ___

Measured Parameter IcRS; Integral Worth of Control Bank C, (Description) Rod Swap IV Measured Value IcRs R--i.S 7 (Adjusted Measured Test Critical Reference Bank Position = 2_- steps)

Results Design Value (Actual Conditions) lcRS 7- (Adjusted Measured Critical Reference Bank Position = I".7. . steps)

Design Value (Design Conditions) IcRs= 779 +/- 117 pcm (Critical Reference Bank Position = 140 steps)

Reference Engineering Transmittal NAF 2000-0120, Rev. 0. VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria _be performed.

Reference VEP-FRD-36A Design Tolerance is met : V" YES NO Acceptance Criteria is met : V YES NO VI Comments Prepared By: (\4' i' ,, Reviewed By: -ýe* 1.6'c-NE-1261 S2C17 Startup Physics Tests Report Page 51 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 SHEET STARTUP PHYSICS TEST RESULTS AND EVALUATION Swap

=I Test

Description:

Control Bank D Worth Measurement, Rod Proc No / Section: 2-NPT-RX-008 Sequence Step No Reference 0 II Bank Positions (Steps) RCS Temperature ( F): 547 Power Level (% F.P.): 0 Test Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

BelwNcler rIe l n (Design) CB: moving CC: 228 CD: moving Below Nuclear Hleating RCS Temperature ()F): S% ý S Ill Bank Positions (Steps)

Power Level (% F.P.): 0 Test Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: moving CC: 228 CD: moving Below Nuclear Heating Date/Time Test Performed:

(Cf 2 c/ C f,&YjCC IDRS Integral Worth of Control Bank D, Measured Parameter (Description) Rod Swap RS=. (Adjusted Measured IV Measured Value Critical Reference Bank Position = I L-(f, C steps)

Test Results Design Value (Actual Conditions) 1,RS= 9-74, (Adjusted Measured Critical Reference Bank Position = I Q4. 0 steps)

Design Value IoRS= 978 +/- 147 pcm (Design Conditions)

(Critical Reference Bank Position =169 steps)

Engineenng Transmittal NAF 2000-0120, Rev. 0, VEP-FRD-36A Reference FSARITech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.

V Acceptance SNSOC may specify that additional testing be performed.

Criteria Reference VEP-FRD-36A jj YES NO Design Tolerance is met is met VYES NO A* tr'ria (trit VI Comments I

Prepared By: /_ . I Reviewed By: 7*

NE-1261 S2C17 Startup Physics Tests Report Page 52 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

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

II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: 228 CA: 228 Other (specify):

(Design) CB: moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): c? -7.-Z_

Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: 228 CA: 228 Other (specify):

(Actual) CB: moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter ISRS; Integral Worth of Shutdown Bank A, (Description) Rod Swap IV Measured Value ISARS= iCZ (Adjusted Measured Test _Critical Reference Bank Position =( r -.-7 steps)

Results Design Value (Actual Conditions) 1 RSA C= (Adjusted Measured Critical Reference Bank Position = t L. '7 steps)

Design Value (Design Conditions) Is*RS= 985 +/- 148 pcm (Critical Reference Bank Position = 170 steps)

Reference Engineering Transmittal NAF 2000-0120. Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be performed.

Reference VEP-FRD-36A Design Tolerance is met * - YES NO Acceptance Criteria is met

  • YES NO VI Comments Prepared By: 0i -- w r Reviewed By: _"e<

NE-1261 S2C17 Startup Physics Tests Report Page 53 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test

Description:

Shutdown Bank B Worth Measurement, Rod Swap Dejaran Mv / 0rtinn 2-N PT-RX-008 Sequence Step No II Bank Positions (Steps) RCS Temperature ( F) 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: moving CA: 228 Other (specify):

(Design) CB: moving CC. 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): *-7 3 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: moving CA: 228 Other (specify):

(Actual) CB: moving CC: 228 CD: 228 Below Nuclear Heating Date/Time Test Performed:

(721 ___--___-________7____

Measured Parameter IsBRSe Integral Worth of Shutdown Bank B, (Description) Rod Swap IV Measured Value IseRS= I'2A* ) (Adjusted Measured Test Critical Reference Bank Position = {C 8. ( steps)

Results Design Value (Actual Conditions) IseRs=

RS -C , (,C (Adjusted Measured Critical Reference Bank Position = . %[ steps)

Design Value (Design Conditions) IsBRS= 1204 +/- 181 pcm (Critical Reference Bank Position = 198 steps)

Reference Engineenng Transmittal NAF 2000-0120. Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.

Acceptance SNSOC may specify that additional testing Criteria be performed.

Reference VEP-FRD-36A Design Tolerance is met " YES NO Acceptance Criteria is met " V" YES NO VI Comments r-. }

Prepared By: Ck\*&\c AK. . Reviewed By: _ _ _ _ _

NE-1261 S2C17 Startup Physics Tests Report Page 54 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

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

II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: moving CA: moving Other (specify):

(Design) CB: moving CC: moving CD: moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): f Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: moving CA: moving Other (specify):

(Actual) CB: moving 'CC: moving CD: moving Below Nuclear Heating Date/Time Test Performed:

Measured Parameter IT==; Integral Worth of All Banks, (Description) Rod Swap IV Measured Value 1IT=== ,.., pcm Test Results Design Value (Actual Conditions) IT= "SS". pcm Design Value (Design Conditions) IT,,= 5558 +/- 556 pcm Reference Engineering Transmittal NAF 2000-0120, Rev. 0, VEP-FRD-36A FSARITech Spec If Design Tolerance is exceeded, SNSOC shall.

V evaluate impact of test result on safety analysis.

Acceptance Additional testing must be performed.

Criteria Reference VEP-FRD-36A Design Tolerance is met V' YES NO Acceptance Criteria is met V' YES V NO VI Comments Prepared By:*ý',*o A6'N  %-.P,-- Reviewed By: -__-

NE-1261 S2C17 Startup Physics Tests Report Page 55 of 58

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Map - At Power Reference Proc No I Section: 2-NPT-RX-008 ,002 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (UF): TREF +/- 1 Test Power Level (% F.P.): < 30 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC:

  • CD:
  • Must have > 38 thimbles**

III Bank Positions (Steps) RCS Temperature (OF): "_

Test Power Level (% F.P.): ,7 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 CC: .2Z? CD: /16 Date/Time Te t Performed: .Y 7" Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive Incore Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FAH(N) Factor FG(Z) Power Tilt Test Measured 4-517 /? , '7 o.9

/3 < a,__, /.? _- /1o;5.7 Results Value /"3.j'/

Design Value +/-10% for P i >0.9 N/A N/A < 1.0202 (Design +/-15% for Pi<0.9 Conditions) (Pi = assy power)

Reference WCAP-7905. Rev. I None None WCAP-7905,Rev.1 NE-1259, Rev. 0 NE-1259, Rev. 0 V FSARICOLR None FAH(N)51.56(1+0.3(1-P)) FQ(Z)54.40"K(Z) None Acceptance Criteria Reference None COLR 2.4 COLR 2.3 None Design Tolerance is met  : YES N0 Acceptance Criteria is met " "7 YES NO VI *As required Comments Must have at least 16 thimbles for quarter core maps for multi-point calibrations

ýa f/ 7 Prepared Reviewed By:

Page 56 of 58 NE-1261 S2C17 Startup Physics Tests Report

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

MID Flux Map - At Power Reference Proc No I Section: 2-NPT-RX-008 ,002 Sequence Step No:

II Bank Positions (Steps) RCS Temperature (UJF): TREF +/- 1 Test Power Level (% F.P.): 65 < P < 75 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD: Must have > 38 thimbles**

III Bank Positions (Steps) RCS Temperature (OF): T7-e -V Test Power Level (% F.P.): 45". ., 5,.

Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 CC: 228 CD: / 4*.- Ž.  ;-,,.. ble5 Date/Time Test Performed:

Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive Incore Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FAH(N) Factor Fo(Z) Power Tilt Test Measured S. 47 P 0 01 1 Results Value _?.3 p<o.9 l. -79 1.907 Design Value *10% for P1i 0.9 (Design *15% for Pi<0.9 N/A N/A < 1.0202 Conditions) (Pi = assy power)

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

_NE-1259. Rev. 0 NE-1259. Rev. 0 V FSARICOLR None FAH(N):51.56(1+0.3(1-P)) F0(Z)<2.201P-K(Z) None Acceptance Criteria Reference None COLR 2.4 COLR 2.3 None Design Tolerance is met v "-YES NO Acceptance Criteria is met

  • v YES NO VI As required Comments Must have at least 16 thimbles for quarter core maps for multi-point calibrations Prepared By: (6 7 Reviewed By:  ;..*6 ,-

NE-1261 S2C17 Startup Physics Tests Report Page 57 of 58

/

SURRY POWER STATION UNIT 2 CYCLE 17 STARTUP PHYSICS TEST RESULTS AND EVALUATION'SHEET I Test

Description:

M/D Flux Map - At Power Reference Proc No / Section: 2-NPT-RX-008 ,002 Sequence Step No:

II Bank Positions (Steps) RCS Temperature ('F): TREF +/- 1 Test Power Level (% F.P.): 95:< P 100 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Design) CB: 228 CC: 228 CD:

  • Must have > 38 thimbles"*

iII Bank Positions (Steps) RCS Temperature (OF): "T7--.

Test . _Power. Level (% F.P.): ý . 5j' Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):

(Actual) CB: 228 -CC: 228 CD: ,o Date/Time Test Performed:

Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive Incore Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FAH(N) Factor Fa(Z) ,,,,Power Tilt Test Measured 5-)/.

$0 0 ,>.1 t.j - E " b0 OK I '

Results Value 16; <0.9 Design Value +/-10% for P, 20.9 (Design +/-15% for Pj<0.9 N/A N/A 1.0202 Conditions) (PI = assy power)

Reference WCAP-7905, Rev. 1 None None WCAP-7905,Rev. 1 NE-1259, Rev. 0 NE-1259, Rev. 0 V FSAR/COLR None FAH(N)!51.56(1+0.3(1-P)) Fo(Z):2.20/P*K(Z) None Acceptance III Criteria Reference None COLR 2.4 COLR 2.3 None Design Tolerance is met : " YES NO Acceptance Criteria is met - YES NO VI 'As required Comments Must have at least 16 thimbles for quarter core maps for multi-point calibrations

" 1?

/'7.

Prepared By: 21ý a/,,/"" Reviewed By:_

-I NE-1261 S2C17 Startup Physics Tests Report Page 58 of 58

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