ML022060509

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Cycle 18 Startup Physics Tests Report
ML022060509
Person / Time
Site: Surry Dominion icon.png
Issue date: 07/16/2002
From: Sarver S
Virginia Electric & Power Co (VEPCO)
To: Reyes L
Region 2 Administrator
References
02-458
Download: ML022060509 (60)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 16, 2002 Mr. Luis A. Reyes, Administrator Serial No.: 02-458 NLOS/mm United States Nuclear Regulatory Commission Docket No.: 50-281 Region II License No.: DPR-37 Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23 T85 Atlanta, GA 30303-8931

Dear Mr. Reyes:

VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 2 CYCLE 18 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-1326, Revision 0, entitled "Surry Unit 2, Cycle 18 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after the initial criticality of Cycle 18 on April 20, 2002. 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, Director Nuclear Licensing and Operations Support Enclosure

Commitment Summary: There are no new commitments as a result of this letter.

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

0 0 Dominion",

Surry Unit 2, Cycle 18 Startup Physics Tests Report NuclearAnalysis and Fuel Nuclear Engineering& Services June, 2002

TECHNICAL REPORT NE-1326 - REV. 0 SURRY UNIT 2, CYCLE 18 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES DOMINION JUNE, 2002 PREPARED BY.e _2' f4</15r q M. T. Langschwager Date REVIEWED BY:_____

T. L. Wheeler Date REVIEWED BY. - (4_1O0 M. J. Fanguy Date APPROVED BY: ( z C. B. LaRoe Date QA Category: Safety Related Keywords: S2C18, S2CI, Startup Physics Tests Report

CLASSIFICATION/DISCLAIMER in this report have been prepared solely The data, techniques, information, and conclusions other they may not be appropriate for use in situations for use by Dominion (the Company), and no claim prepared. The Company therefore makes than those for which they have been specifically In as to their accuracy, usefulness, or applicability.

or warranty whatsoever, express or implied, OR FITNESS THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY particular, TO ARISE A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED FOR this report or any of the COURSE OF DEALING OR USAGE OF TRADE, with respect to FROM the Company information, or conclusions in it. By making this report available, data, techniques, the prior its use by others, and any such use is expressly forbidden except with does not authorize to incorporate of the Company. Any such written approval shall itself be deemed written approval event shall the of liability and disclaimers of warranties provided herein. In no the disclaimers or under any legal theory whatsoever (whether contract, tort, warranty, or strict Company be liable, loss of use of for any property damage, mental or physical injury or death, absolute liability),

of damage resulting from or arising out of the use, authorized or unauthorized, property, or other or conclusions in it.

this report or the data, techniques, information, Page 1 of 56 Report NE-1326 S2C18 Startup Physics Tests

TABLE OF CONTENTS PAGE C lassification/D isclaim er .................................................................................. 1 Table of C ontents ......................................................................................... 2 L ist of T ables .................................................................................................... 3 List of Figures ................................................................................................... 4 P reface .............................................................................................................. 5 Section 1 Introduction and Summary ....................................................... 6 Section 2 Control Rod Drop Time Measurements .................................. 15 Section 3 Control Rod Bank Worth Measurements ................................ 20 Section 4 Boron Endpoint and Worth Measurements ............................. 26 Section 5 Temperature Coefficient Measurement .................................. 30 Section 6 Power Distribution Measurements ......................................... 32 Section 7 References ................................................................................ 39 APPENDIX Startup Physics Test Results and Evaluation Sheets .......... 40 NE-1326 S2C18 Startup Physics Tests Report Page 2 of 56

I I LIST OF TABLES TABLE TITLE PAGE 1.1 Chronology of Tests .............................................................................. 9 2.1 Hot Rod Drop Time Summary ........................................................... 17 3.1 Control Rod Bank Worth Summary .................................................. 23 4.1 Boron Endpoints Summary ................................................................. 28 4.2 Boron Worth Coefficient .................................................................... 29 5.1 Isothermal Temperature Coefficient Summary ................................... 31 6.1 Incore Flux Map Summary ................................................................ 34 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits .................................................... 35 NE- 1326 S2C 18 Startup Physics Tests Report Page 3 of 56

LIST OF FIGURES TITLE PAGE FIGURE 10 1.1 Core Loading M ap ................................................................................

11 1.2 Burnable Poison Locations ..................................................................

.................................. 12 1.3 Available Incore Moveable Detector Locations

....................................... 13 1.4 Beginning of Cycle Fuel Assembly Bumups 14 1.5 Control Rod Locations .........................................................................

18

.2.1 Typical Rod Drop Trace .......................................................................

...................................... 19 2.2 Rod Drop Time - Hot Full Flow Conditions HZP ........................................ 24 3.1 Control Bank B Integral Rod Worth -

- HZP .................................. 25 3.2 Control Bank B Differential Rod Worth Power ................................ 36 6.1 Assemblywise Power Distribution - 25%

67% Power ................................ 37 6.2 Assemblywise Power Distribution -

Power ............................... 38 6.3 Assemblywise Power Distribution - 100%

Page 4 of 56 NE-1326 $2C18 Startup Physics Tests Report

I I PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry Unit 2, Cycle 18 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 repoTt. 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 18 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 bEsed on the calculations performed by Dominion'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 test results, thus enabling a quick identification of possible problems occurring during the tests.

NE-1326 S2C18 Startup Physics Tests Report Page 5 of 56

SECTION 1 INTRODUCTION AND

SUMMARY

On March 24, 2002 Unit No. 2 of the Surry Power Station shut down for its seventeenth were replaced with 60 refueling. During this shutdown, 101 of the 157 fuel assemblies in the core twice burned fresh assemblies, 40 twice burned assemblies from Surry Unit 1, and one additiona~l fuel: two. batches assembly from Surry Unit 2. The Cycle 18 core consists of 8 sub-batches of loaded from -Cycle 15 (batch 16B); three loaded fresh in Cycle 17 (batches 19A and'l 9B); one batch S I/18B); and two fresh batches previously burned' in Surry Unit 1 (batches S1/177, S1/18A, and to the Westinghouse batch batches (batches 20A and 20B). The fresh batches are of a similar design 19 fuel (fresh fuel in Cycle 17).

inches is used. Cycle In Cycle 18, a BPRA product with an active absorber length of 127.1 in Alumina, 18, similar to Cycle 17, incorporated the burnable poison rod design made of B4 C plugging devices, flux which is available in various enrichments of B4C. There are no thimble suppression inserts, or secondary sources inserted in $2C 18.

The core loading pattern is shown in Figure 1.1. Figure 1.2 identifies the location and moveable detector locations number of burnable poison rods for Cycle 18. The available incore used for the flux map analyses are identified in Figure 1.3. Beginning of cycle fuel assembly Page 6 of 56 NE-1326 $2C18 Startup Physics Tests Report

bumups are given in Figure 1.4 and documented in Reference 6. Figure 1.5 identifies the location and number of control rods in the Cycle 18 core.

On April 20, 2002 at 11:59, the Cycle 18 core achieved initial criticality (Reference 11).

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.I.

The RMAS Reactivity computer, described in Reference 10, was used for the S2C 18 startup.

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 2.9% of the design prediction and the reference bank worth was within 1.2% of its design prediction. The other control rod banks were within 7.9% (Bank "C") 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), - 10 0 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 were within 27 ppm of the design predictions. These results were within the design tolerances and also met the Technical Specification 4.10.A criterion that the overall core reactivity balance shall be within ' 1%

Ak/k of the design prediction.

NE- 1326 S2C 18 Startup Physics Tests Report Page 7 of 56

the design prediction, which The boron worth coefficient measurement was within 6.0% of is within the design tolerance of : 10%.

for the all-rods-out (ARO)

The measured isothermal temperature coefficient (ITC)

This result is within the design configuration was within 0.8 pcmrrF of the design prediction.

Operating Limits tolerance of +/-3 pcm/fF. The measured ITC of -0.51 pcm/°F meets the Core coefficient (MTC) be less than or Report (COLR) 2.1.1 criterion that the moderator temperature coefficient and a 0.5 pcm/IF uncertainty.are equal to +6.0 pcm/'F. When the Doppler temperature is satisfied as long as the ITC is less than or accounted for in the MTC limit, the MTC requirement equal to +3.81 pcm/F.

design tolerances. Generally, the Measured core power distributions were within established of the design predictions for relative assembly measured core power distributions were within 4.0%

of the design predictions for relative assembly powers greater than or equal to 0.9, and within 4.4%

factors, F-Q(Z), and enthalpy rise hot channel powers less than 0.9. The heat flux hot channel 2.3 and 2.4, respectively.

factors, F-DH(N), were within the limits of COLR Sections Detailed results, specific design In summary, all startup physics test results were acceptable.

are presented in the following sections of tolerances and acceptance criteria for each measurement this report.

Page 8 of 56 NE- 1326 S2C 18 Startup Physics Tests Report

I I Table 1.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drops - Hot Full Flow 4/18/02 1523 IISD 2-NPT-RX-014 Boron Endpoint - ARO 4/20/02 1322 HZP 2-NPT-RX-008 Reactivity Computer Checkout 4/20/02 1322 HZP 2-NPT-RX-008 Zero Power Testing Range 4/20/02 1322 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 4/20/02 14.31 HZP 2-NPT-RX-008 Bank B Worth 4/20/02 1544 HZP 2-NPT-RX-008 Boron Endpoint - B in 4/20/02 1544 HZP 2-NPT-RX-008 Bank A Worth - Rod Swap 4/20/02 1915 HZP 2-NPT-RX-008 Barn C Worth - Rod Swap 4/20/02 1930 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 4/20/02 1951 HZP 2-NPT-PRX-008 Bank D Worth - Rod Swap 4/20/02 2008 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap 4/20/02 2026 HZP 2-NPT-RX-008 Flux Map - 25% Power 4/22/02 0525 25% 2-NPT-RX-002 Peaking Factor Verification 2--NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 Flux Map - 67% Power 4/23/02 1555 67% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 Flux Map - 100% Power 4/29/02 0800 100% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

& Power Range Calibration 2-NPT-RX-005 NE- 1326 $2C 18 Startup Physics Tests Report Page 9 of 56

Figure 1.1 SURRY UNIT 2 - CYCLE 18 CORE LOADING MAP SURRY UNIT 2 - CYCLE 18 FULL CORE LOADING PLAN PAGE 1 of 2 REVISION NO. 0 K J H G F E D C B A R P N M L VEP -NES-NAF 07C -48S 31C 3EP RCC IRP RCC 2 sSC 40R 45P 45R I 32C 40C 224C4C L S - 531' I 3

5BP 20BP RCC 120,BP RCC 20BP 53P NORTH 471' 16R 50P 41R 39R 56C A *F 45C~ 5 ~ 7 6O ~6 u& 4 RCC 20BP I RCC in Io20BP' 19R 05R, 13P 32R 5OC 51C 29P' 5 j53' Al I' 120BP2 RCC 203P' 20BP RCC 20BP 5BPI 34C -SOR I24R 1_23P11R I21P' 04? 08P I18R J251' 08OR 51R, 48C 6 R .CC 20BP RCC 20BP RCC 20BP AOD I P RCC 2 CC 20BP RCC 2 1CJ 37R 16P 09R 06P 46R 30C 7 12 L OkI t31 2~- - ,~t-~ --

3BP RCC 20BP 20BPI RCC RCC 20BP 54R

  • 1D *O 33R 56P 01C 07P' 8 13C 53RC 8 -1 30Pr I 8 2 RCC' 20BP RCC RCC 52P 07R I41P 47B

_w_ an'v* ARO 321' 05P 351 900 36B I 44P 36R 46P 02P . . I 9 20BP RCC RCC 20B3P 20BP ROC 3BP 3BP RCC 20BP 51P 371P 53P 15R lIP 1OR 31P 43R 18C 29C 59R 34P 23R 19P 26R 20 BOAP RCC 20RP RCC

.T__C_*

RCC 20BP RCC 20BP F CC 4SP I03R 24P 34R 20P 38R 05C 06C 52R 17P 3OR 20BP 04R 09P 48P 03R 2031' 20BP RCC RCC 12082 20SP 5BP 1I 5BP RCC 20BP 147C 49R 06R 03P 9*D rp I AP 17R 115P I13R 42R 35C 31R2 2P 18P _CB C 12 RCC 20BP RCC 20BP 20OBP RCC 20BP RCC 52t 29R 12R 27P 14R 44C 49C 25R 14P 40P 36C 13 RCC 20BP RCC 20BP 5BP 20BP INCORE DEVICE DESCRIPTIONS: 54P 22R 42P 57R 48R 33C 37C 5OR 44R 14 RCC- FULL LENGTH CONTROL ROD RCC 3BP RCC RCC 3BP 3BP- 3 BURNABLE POISON ROD CLUSTER 1 OC 42C 39C 17C 56R 36P 47R 5BP- 5 BURNABLE POISON ROD CLUSTER 15 20BP- 20 BURNABLE POISON ROD CLUSTER 20C 51B 02C Date: 12 /iq 101 Concurrence By:

Date: i1810"?

Prepared By: -IZ Date: 2 Reviewed By: Wýýte: Wigj/ 0 1 Approved By:

Approved~ By :*.ý? Date: i-uIa Page 10 of 56 NE- 1326 S2C 18 Startup Physics Tests Report

I I Figure 1 2 SURRY UNIT 2 - CYCLE 18 BURNABLE POISON LOCATIONS SURRY UNIT 2 - CYCLE 18 FULL CORE LOADING PLAN REVISION NO. 0 PAGE 2 of 2 VEP-INES-NAF BP CORE LOCATIONS CORE ASSY BP CORE ASSY BP CORE ASSY BP LOC ID ID LOC ID ID LOC ID ID J02 40R BP944 G06 35R BP927 GI0 03R BP924 002 45R BP951 B06 09R BP941 El0 34R BP936 L03 60R BP969 C06 46R BP953 CIO 38R BP964 K03 55R BP966 207 53R EP945 Nil 49R BP971 H03 16R BP916 M07 28R BP934 Mi1 06R 8P955 F03 41R EP957 K07 21R 3P920 KII 31R BP943 E03 39R SP968 P07 02R SP925 FII D11 17R BP932 L04 27R EP954 D07 33R BP937 13R BP960 J04 19R BP938 B07 54R BP950 Cli 42R BP975 G04 05R BP933 NOS 36R BP917 L12 25R BP962 E04 32R BP963 C08 07R BP918 312 29R BP935 N05 58R BP970 P09 59R 8P946 G12 12R 8P928 M05 24R BP961 M09 23R BP931 E12 14R BP956 K05 11R BP942 K09 26R BP926 L13 50R BP973 F05 18R BP929 F09 15R BP922 K13 44R BP959 D05 08R 8P965 D09 1CR BP940 H13 22R BP919 C05 51R 3P974 209 43R BP949 F13 57R BP952 N06 37R BP958 Nio 52R BP967 B13 48R BP972 L06 01R BP930 LI0 04R BP939 J14 56R BP947 J06 20R IP923 JID 30R BP921 G14 47R BP948 Prepared By Date: jiiithvj Concurrence By: A k Date:

Reviewed By: Date:.,/m%/01 Approved By: 1-7AZ/I/ Date: Y/

Approved By: Date:

NE- 1326 S2C 18 Startup Physics Tests Report Page 11 of 56

Figure 1.3 SURRY UNIT 2 - CYCLE 18 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS L K J H G F E D C B A R P N M 1

MD 2

MD 3

MD MD MD 4

MD MD MD MD MD 5 M4D MD** MD 6

MD MD MD MD 7 MD MD MD MD MD** 8 MD MD MD** MD rD^A*

9 MD MD DMD MD^

MD 10 MD -MD MD M~D MD 11 MD MD MD 12 MD IMD*

MD 13 MID 14 MD MD 15

,MD" MD - Moveable Detector A - Locations Not Available For Flux Map 1

  • - Locations Not Available For Flux Map 2
    • - Locations Not Available For Flux Mapping System for Cycle 18 Page 12 of 56 NE-1326 S2C18 Startup Physics Tests Report

Figure 1.4 SURRY UNIT 2 - CYCLE 18 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS SURRY 2 CYCLE 18 READINGS 00/00/00 - 00/00/00 LOCATION 1205 4/10/02 17.12.57 ASSEMBLYWISE ACCUMULATED BURNUP MEASURED AND PREDICTED (1000 MWD/MTU)

R P N M L K J H G F E D C B A 144.94 144.77 40351 40.84 45.271 44.77 MEASURED!

1PREDICTED 1 44.99 40.301 0.001 22.09 0.001 40.681 45.971 2

1 45.74 40.491 0.00 22.08 0.00 40.4 45.741 3 42.951 0.001 0.00! 17.341 0.001 17.121 0.001 0.001 43.301 3 I 42.97 0.00o 0.00o 17.131 0.00 17.13j 0.001 0.03! 42.97 4 40.781 35.941 0.001 17.401 0.001 21.58 0.001 17.731 0.00! 35.721 41.031 4 1 40.91! 35.99 0.00j 17.87! 0.00o 21.47! 0.00j 17.87 0.00 35.99 40.91!

5 45.72!

,45.69 0.001 0.00 0.001 0.00! 23.521 23.35 0.001 23.28 0.00o 23.511 22.56!

22.501 23.28 23.541 0.001 23.35 0.00 23.631 0.00j 0.00! 0.oo0 0.00! 45.69!

45.261 6 40.561 0.00 17.941 0.001 23.541 0.001 21.57! 0.001 23.601 0.001 17.76!

I 40.471 0.001 17.871 0.001 23.38 0.00 40.07 6 0.00 21.47I 0.00 23.38! 0.00 17.87j 0.001

--- ----------------------------------------------------------------------------------------------------40.47 7 44.541 0.00! 17.081 0.001 23.46! 0.001 21A81j 22.321 21.85I 144.81 0.00 17.13 0.00! 23.591 0.00 17.07I 0.00! 44.41!

0.00 23.2** 0.00 22.04 22.28 22.4! 0.00 23.29 0.00 17.13 0.00 44.81 8 I 41.03! 21.831 0.00! 20.871 22.84! 21.411 22.321 38.13j 22.301 21.521 22.27!

21.37 0.00! 22.21! 40.42! 8 40.87 22.04! 0.00! 21.47j 22.57! 21.47 22.30! 38.37! 22.30! 20.47! 22.57! 21.47 0.00! 22.04 40.87 9 ,44.821 0.00! 16.89! 0.00! 23.33! 0.001 21.80! 22.481 21.59!

44.8!* 0.00 17.13 0.00! 23. 571 0.0 18.81 0.001 14351 9

0.00! 23.29! 0.00 22.04! 22.28, 22.04! 0.00!

23.29! 0.001 17.13 0.00! 44.81 1 10 I 40.14! 0.001 17.301 0.001 23.591 0.001 21.18 0.00! 23.491 0.001 17.651 0.001 40.361 40.47 0.00 17.87 0.00 23.38 0.00 21.4 10 0.00 23.38 0.00! 17.87

0.00 40.47 11 41 0.00 0.00!1 23.39 0.001 23.23! 22.76! 22.85 45.69 0.00! 23.53! 0.00! 0.001 45.741 11 0.00! 0.00 23.35 0.00 23.28 22.56 23. 8 0.00 23.35 0.00 0.00! 45.89!

12 40.85! 35.991 0.00! 17.821 0.00! 20.71! 0.00! 17.711 0.00! 35.68! 40.77! 12 40.91~ 35.99! 0.00! 17.87 0.00! 21.47! 0.00! 17.87! 0.00! 35.9! 40.91k 13 142.80! 0.001 0.001 16.851 0.001 16.!88! 0.00! 0.00! 42.481 13 422.97! 0.00! 0.00 17.13 0.00 17.13! 0.00! 0.00! 42.97 14 I45.42! 39.88! 0.00! 21.951 0.00! 39.92! 45.641 45.74! 40.49 0.00! 22.08 1 0.00! 40.49! 45.7414 15 44.39 40.30 45.06!

44.77 40.84 44.77 15 1

R P N M L K a H G F E D C a A NE- 1326 S2C 18 Startup Physics Tests Report Page 13 of 56

Figure 1.5 SURRY UNIT 2 - CYCLE 18 CONTROL ROD LOCATIONS L K J H G F E D C B A R P N M 1

2 D A A

3 SA SA C 4 B

C B 5

SB SB B A 6 C D A B D 7

SB SB SA SA D 8 C C D

9 SB SB SA SA B A 10 C D B D A

11 SB SB C 12 B B C

13 SA SA 14 D A A

Absorber Material: Ag-In-Cd I 15 Function Number of Clusters Control Bank D 8 8

Control Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA Page 14 of 56 NE- 1326 S2C 18 Startup Physics Tests Report

I I 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.

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 NE- 1326 $2C 18 Startup Physics Tests Report Page 15 of 56

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.

Page 16 of 56 NE- 1326 S2C 18 Startup Physics Tests Report

I I Table 2.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME I F-06 1.39 sec. I M-12 1.25 sec. 1.29 sec.

1.29 sec. -j NE-1326 S2C18 Startup Physics Tests Report Page 17 of 56

Figure 2.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE Page !8 of 56 NE- 1326 $2C 18 Startup Physics Tests Report

Figure 2.2 SURRY UNIT 2 - CYCLE 18 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 4 I 7 F- 4 F I

11.29 1.28 1.28 2 1.27 1.31 3 1.27 1.31 1..27 1.26 1.27 1.30 1.27 1.30 4 1.271.26 f---I F 4--I .4 .5. L 1.26 1.30 5 1.26 130 1.26 1.27 1.30 1.30 1.39 1 _28 1 "* 6 1.28 1.29 1.30 1.27 7

1.27 1.29 1.27 i.31 8

1 29E 1.29 1.29 1 1_ , 1.27 9 1-29 1.29 1.29 1.28 1.33 1.29 I _30 10 1.912 .81,33 1.29 130 1.27 1.30 1.30 11 1.27 1.25 1.26 1.30 1.27 12 1

1.25 1.26 --- 1-----+ 1.30 F 1.27 1.29 1.29 13

-? I t-I 4 4- -

1.33 11.28 1.30 1 14

-. I I F 4 15

[*-j > Rod drop time to dashpot entry (sec.)

NE- 1326 S2C 18 Startup Physics Tests Report Page 19 of 56

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 18, 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 10, the test bank sequence used for rod swap was to exchange test bank with test bank.

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 Page 20 of 56 NE- 1326 $2C 18 Startup Physics Tests Report

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.

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 2.9% of the design prediction. This is well within the design tolerance of -t10% for the sum of the individual control rod bank worths.

NE- 1326 S2C 18 Startup Physics Tests Report Page 21 of 56

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 worth values plotted together in order to illustrate their agreement. In summary, the measured rod were satisfactory.

Page 22 of 56 NE-1326 S2C18 Startup Physics Tests Report

I I Table 3.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED WORTH PERCENT WORTH DIFFERENCE (%)

BANK (PCM) (M-P)/P X 100 B-Reference Bank 1415.9 1433.0 -1.2 D 1005.1 1049.3 -4.2 C 740.0 803.4 -7.0 A 209.6 208.2 +0.7*

SB 1081.6 1140.1 -5.1 SA 1016.7 1000.3

,Total Worth +1.6 5468.7 5634.2 -2.9 5634.2 -2.9

  • Difference is less than 100 pc.-m.

NE-1326 S2C18 Startup Physics Tests Report Page 23 of 56

Figure 3.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600 1400 1200 o 1000 0 *-Predicted7

-U--Measured z

S800 4

600 Z

400 200 0

100 150 200 250 0 50 BANK POSITION (STEPS)

Page 24 of 56 NE- 1326 S2C 18 Startup Physics Tests Report

I I Figure 3.2 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12 0~

I.

I 2

-- l- Predicted 0 Measured n

uJ 2

0*

0 50 100 150 200 250 BANK POSITION (STEPS)

NE- 1326 $2C 18 Startup Physics Tests Report Page 25 of 56

SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint system (RCS) boron With the reactor critical at hot zero power, reactor coolant to enable a direct comparison of concentrations were measured at selected rod bank configurations measured boron endpoints with design predictions. For each critical boron concentration banks at or very near a selected measurement, the RCS conditions were stabilized- with the control concentration values were made to endpoint position. Adjustments to the measured critical boron if necessary.

account for off-nominal control rod position and moderator temperature, shown in this table and in the The results of these measurements are given in Table 4.1. As in the Appendix, the measured critical Startup Physics Test Results and Evaluation Sheets given tolerances. The ARO endpoint boron endpoint values were within their respective design Specification 4.1 O.A regarding comparison to the predicted value met the requirements of Technical were satisfactory.

core reactivity balance. In summary, the boron endpoint results Boron Worth Coefficient data from which the boron The measured boron endpoint values provide stable statepoint determined. By relating each endpoint worth coefficient or differential boron worth (DBW) was core at the time of the endpoint concentration to the integrated rod worth present in the endpoint concentrations was obtained.

measurement, the value of the DBW over the range of boron Page 26 of 56 NE- 1326 $2C 18 Startup Physics Tests Report

I I 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-1326 S2C18 Startup Physics Tests Report Page 27 of 56

Table 4.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 2114 2087 27 B Bank In 1918 1904* 14

  • 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-1326 $2C18 Startup Physics Tests Report Page 28 of 56

I I

Table 4.2 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT NE-1326 S2C18 Startup Physics Tests Report Page 29 of 56

SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT is measured by The isothermal temperature coefficient (ITC) at the all-rods-out condition steam generators, controlling the reactor coolant system (RCS) by varying blowdown flow to the the resulting reactivity changes on establishing a constant heatup or cooldown rate, and monitoring the reactivity computer.

and RCS heatup of 3.26TF.

Reactivity was measured during the RCS cooldown of 3.19'F computer. Using the statepoint Reactivity and temperature data were taken from the reactivity the change in reactivity by the method, the temperature coefficient was determined by dividing confirmed the statepoint method change in RCS temperature. Plots of reactivity versus temperature, in calculating the measured ITC.

values are compared in Table 5.1.

The predicted and measured isothermal temperature coefficient Test Results and Evaluation Sheet As can be seen from this summary and from the Startup Physics coefficient value was within the design given in the Appendix, the measured isothermal temperature was determined to be 1.171 pcmP/F tolerance of -3 pcm/fF. The moderator temperature coefficient In summary, the measured results were which met the requirements of COLR Section 2.1.1.

satisfactory.

Page 30 of 56 NE-1326 $2C18 Startup Physics Tests Report

I I Table 5.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

NE-1326 S2C18 Startup Physics Tests Report Page 31 of 56

SECTION 6 POWER DISTRIBUTION MEASUREMENTS incore detector flux The core power distributions were measured using the moveable chamber detectors which traverse fuel mapping system. This system consists of up to five fission Figure 1.3 shows the available assembly instrumentation thimbles in up to 50 core locations.

ramp to full power flux maps for Cycle 18.

locations monitored by the moveable detectors for the on a strip chart recorder, For each traverse, the detector voltage output is continuously monitored P-250 process computer. Full core, three and scanned for 61 discrete axial points by the PRODAC this data using a Dominion modified version dimensional power distributions are determined from (Reference 3). CECOR couples the of the Combustion Engineering computer program, CECOR ratios in order to determine the power measured voltages with predetermined analytic power-to-flux distribution for the whole core.

startup test program and the measured A list of the full-core flux maps taken during the are given in Table 6.1. A comparison of these values of the important power distribution parameters 6.2. Flux map 1 was taken at 25% power measured values with their COLR limits is given in Table at low power. Figure 6.1 shows the to verify the radial power distribution (RPD) predictions and 3 were taken at 67% and 100% power, measured RPDs from this flux map. Flux maps 2 These flux maps were taken to check at respectively, with different control rod configurations.

distributions at various operating conditions.

power design predictions and to measure core power in Figures 6.2 and 6.3. The radial power The radial power distributions for these maps are given Page 32 of 56 NE- 1326 S2C 18 Startup Physics Tests Report

I I distributions for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured relative assembly power values were within 4.0% of the design predictions for relative assembly powers greater than or equal to 0.9, and within 4.4% of the design predictions for relative assembly powers less than 0.9. 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 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 18.

NE-1326 S2C18 Startup Physics Tests Report Page 33 of 56

Table 6.1 SURRY UNIT 2 - CYCLE 18 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 (%) Bles Low Power 1 4/22/02 3.0 25 160 J4 30 2.099 M10 1.496 30 1.319 1.0072 SW 0.946 41 Int. Pwr (3) 2 4/23/02 24.0 67 187 D10 26 1.913 DIO 1.465 26 1.215 1.0015 NE 3.293 43 Hot Full Pwr 3 4/29/02 203.0 100 230 F4 30 1.773 DI0 1.441 30 1.134 1.0026 NE 2.111 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.

NE-1326 $2C18 Startup Physics Tests Report Page 34 of 56

Table 6.2 SURRY UNIT 2 - CYCLE 18 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

(%) (%)

1 2.099 4.628 30 2.095 4.582 26 54.28 1.496 1.910 21.68 2 1.913 3.438 26 1.898 3.403 22 44.23 1.465 1.716 14.63 3 1.773 2.315 30 1.744 2.251 19 22.52 1.441 1.560 7.63

  • 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).

"**Thevalue 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% total uncertainty.

NE-1326 $2C18 Startup Physics Tests Report Page 35 of 56

Figure 6.1 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 25% POWER R P N M L K J H G F E D C B A

  • 0.208 . 0.230 . 0.206 . . PREDICTED
1. 0.213 . 0.231 . 0.207 . MEASURED 2.1 . 0.8 . 0.6 . .PCT DIFFERENCE.
  • 0.268 . 0.457 . 0.984 . 0.7:6 . 0.977 . 0.454 . 0.266.

2 0.270 . 0.466 . 1.008 . 0.790 . 0.983 . 0.460 . 0.267 . 2 0.* . 1.8 . 2.4 . 0.6. . 1.2 . 0.

  • 0.313 . 1.076 . 1.269 . 1.288 . 1.256 . 1.282 . 1.261 . 1.065 . 0.309.

3 0.313 . 1.078 . 1.289 . 1.336 . 1.254 . 1.285 . 1.267 . 1.068 . 0.308 . 3 0.0 . 0.2 . 1.5 . 3.7 . -0.1 . 0.3 . 0.4 . 0.3 . -0.3 .

...62i..............6..6*i.*;*i.~.2.i~~.2..i.............i6.......*..6+*i~6...*i.*.6.....

0.321 . 0.648 . 1.295 . 1.394 . 1.352 . 1.340 - 1.346 . 1.387 . 1.285 . 0.649 . 0.327.

4. 0.323 . 0.647 . 1.279 . 1.400 . 1.367 . 1.341 . 1.348 . 1.393 . 1.288 . 0.642 . 0.321 . 4 0.7 . -0.1 . -1.2. 0.5 . 1.1 . 0.1 . 0.2 . 0.4 . 0.2 . -1.1. -1.7 .

0.269 . 1.076 . 1.291 . 1.288 . 1.324 . 1.281 . 1.271 . 1.280 . 1.322 . 1.288 . 1.302 . 1.089 . 0.272.

5 0.273 . 1.089 . 1.301 . 1.305 . 1.329 . 1.286 . 1.272 . 1.280 . 1.324 . 1.295 . 1.272 . 1.069 . 0.267 .

1.4 . 1.2 . 0.8 . 1.3 . 0.4 . 0.4 . 0.1 . 0.0. 0.1 . 0.5 . -2.4 . -1.9 . -1.8 .

0.457 . 1.268 . 1.392 . 1.324 . 1.147 . 1.246 . 1.250 . 1.250 . 1.147 . 1.327 . 1.399 . 1.277 . 0.460.

6. 0.466 . 1.289 . 1.397 . 1.297 . 1.139 . 1.246 . 1.246 . 1.244 . 1.142 . 1.315 . 1.371 . 1.256 . 0.457 . 6 2.0 . 1.6 . 0.3 . -2.0 . -0.7. 0.0 . -0.3 . -0.5 . -0.4 . -0.9 . -2.0 . -1.6 . -0.6 .

0.205 . 0.980 . 1.286 . 1.350 . 1.282 . 1.251 . 1.177 . 1.111 . 1.177 . 1.248 . 1.283 . 1.356 . 1.293 . 0.986 . 0.206.

7 0.210 . 1.006 . 1.329 . 1.362 . 1.275 . 1.249 . 1.183 . 1.109 . 1.163 . 1.236 . 1.263 . 1.314 . 1.276 . 0.998 . 0.208 .

.. 2.4 . 2.6 . 3.3 . 0.9 . -0.5 . -0.2 . 0.5 . -0.2 . -1.2 *. -0.9 . -1.6 . -3.1 . -1.3 . 1.2 . 0.9 .

.0.229 . 0.787 . 1.260 . 1.345 . 1.274 . 1.253 . 1.115 . 0.800 . 1.115 . 1.253 . 1.274 . 1.345 . 1.260 . 0.787 . 0.229.

8 0.234 . 0.801 . 1.280 . 1.352 . 1.263 . 1.251 . 1.119 . 0.802 . 1.113 . 1.247 . 1.257 . 1.322 . 1.247 . 0.791 . 0.229 .

1.8 . 1. 8 . 1.6 . 0.5 . -0.9 . -0.1 . 0.4 . 0.2 . -0.1 . -0.5 . -1.3 . -1.7 . -1.0 . 0.5 . -0.12 .

9 0.209 . 0.999 . 1.306 . 1.363 . 1.285 . 1.252 . 1.189 . 1.128 . 1.193 . 1.216 . 1.262 . 1.333 . 1.274 . 0.974 . 0.197 . 9

. 1.3 ,. 1.3 . 1.0 . 0.5 . 0.1 . 0.2 . 0.7 . 0,8 . 0.9 . -3.0 . -1.7 . -1.3 . -1.0 . -0.7 . -4.3 .

0.460 . 1.277 . 1.400 . 1.328 . 1.149 . 1.253 . 1.254 . 1.250 . 1.149 . 1.326 . 1.393 . 1.269 . 0.457.

10 , 0.464 . 1.286 . 1.407 . 1.332 . 1.153 . 1.267 . 1.268 . 1.251 . 1.129 . 1.308 . 1.382 . 1.258 . 0.453 . 10 0.8 . 0.6 . 0.5 . 0.3 . 0.3 . 1 .2 . 1.1 . 0.1 . -1.7 . -1.3 . -0.8 . -0.9 . -0.82 .

11

  • 0.274 . 1.097 . 1.310 . 1.294 . 1.331 . 1.295 . 1.301 . 1.283 . 1.301 . 1.276 . 1.282 . 1.068 . 0.267 . 11 0.7 . 0.7 . 0.5 . 0.3. 0.5 . 1.0 . 2.1 . 0.0 . -1.9 . -1.0 . -0.7 . -0.9 . -0.9 .

0.327 . 0.650 . 1.286 . 1.389 . 1.348 . 1.343 . 1.354 . 1.396 . 1.296 . 0.649 . 0.321 .

0 12 0.331 . 0.653 . 6 1.350 . 1.351 1.348 . 1.369 . 1.277 . .649 . 0.315 . 12 1.1 . 0.6 . 0.5 . 0.5 . 0.2 . 0.6 . -0.4 . -1.9 . -1.5 . 0.1 . -1.7 .

0.309 . 1.066 . 1.263 . 1.284 . 1.258 . 1.290 . 1.271 . 1.078 . 0.314 .

13 . 0.311 . 1.074 . 1.271 . 1.291 . 1.265 . 1.288 . 1.220 . 1.050 . 0.308 . 13 0.6 . 0.7 . 0.6 . 0.6 . 0.5 . -0.2 . -4.0 . -2.5 . -1.6 .

.............'6 ' '6I * ' ' * .... " ' * .....+ * ..........

6 8 .

  • 6...... 6
  • 6 ... ' . ..

0.266 . 0.455 . 0.978 . 0.787 . 0.986 . 0.458 . 0.269.

14 . 0.272 . 0.459 . 0.988 . 0.799 . 1.025 . 0.455 . 0.263 . 14 2.1 . 0.9 . 1.0 . 1.6 . 4.0 . -0.7 . -2.0 .

. . ................... ............... 61* * 'i................. i............ ...

STANDARD .. 0.207 . 0.230 . 0.209 . AVERAGE .

15 DEVIATION . 0.209 . 0.234 . 0.216 . PCT DIFFERENCE. 15

=0.870 1.1 . 1.9 . 3.6 . = 1.0 R P N M L K J H G F E D C B A MAP NO: S2-18-01 DATE: 4/22/02 POWER: 25.3%

CONTROL ROD POSITIONS: F-Q(Z) = 2.099 CORE TILT:

D BANK AT 160 STEPS F-DH(N) = 1.496 NW 1.0062 NE 0.9939 F(Z) = 1.319 SW 1.0072 j SE 0.9927 BURNUP = 3 MWD/MTU A.O. = 0.946 NE-1326 $2C18 Startup Physics Tests Report Page 36 of 56

Figure 6.2 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 67% POWER R P N M L K J H G F E D C B A

  • 0.229 . 0257 .0.227 .. PREDICTED
1. 0.231 . 0.256 . 0.227 ." MEASURED 0.8 . -0.6 . 0.1 . POT DIFFERENCE.
  • 0.280 . 0.475 . 1.017 . 0.852 . 1.010 . 0.472 . 0.277 .
2. 0.279: 0.478 . 1.028 . 0.849 . 1.013 . 0.480 . 0.280 . 2

-0.2 . 0.7 . 1.2 . -0.4 . 0.3 . 1.7 . 1.0 .

  • 0.324 . 1.065 .1.246 . 1.281 . 1.253 . 1 276 . 1.239 . 1.055 . 0.320.

3 0.319 - 1.058 . 1.254 . 1.310 . 1.235 . 1.277 . 1.249 . 1.062 , 0.320 . 3

-1.4 . -0.6. 0.6 . 2.3 . -1.4 . 0.1. 0.8 . 0.7. 0.2 .

0.332 . 0.656 . 1.263 . 1.360 . 1.321 .1.320 .1.316 . 1.355 -1.255 . 0.657 0.337.

4 0.330 . 0.648 . 1.240 . 1.359 . 1.334 . 1.335 . 1.327 . 1.370 . 1.262 . 0.654 . 0.334 . 4

-0.5 . -1.2 . -1.8 . -0.1 . 1.0 . 1.2 . 0.8 . 1.1 . 0.6 . -0.5 . -1.0 .

0.280 . 1.065 .1.260 . 1.266 . 1.307 . 1.271 1.262 . 1.270 . 1,305 . 1.267 . 1.269 . 1.076 . 0.283.

1 5 5 0.280 . .065 . 1.253 . 1.256 . 1.304 . 1.279 . 1.276 . 1.282 . 1.317 . 1.272 . 1.251 . 1.064 . 0.273 .

0.1 . 0.0 . -0.5 . -0.8 . -0.2 . 0.6 . 1.1 . 1.0 . 0.9 . .04 . -1.4 . -1.2 . -3.3

6. 0.476 . 1.249 . 1.355 . 1.289 . 1.191 . 1.259 . 1.272 . 1.266 . 1.212 . 1.309 . 1.352 . 1.243 . 0.477 . 6 0.6. 0.4 . -0.3. -1.4 . -0.6 . 0.6 . 1.4 . 0.9 . 1.2 . 0.1 . -0.9 . -0.6. 0.1 .

.0.226 . 1.012 . 1.278 . 1.319 . 1.272 . 1.256 . 1.195 . 1.133 . 1.195 . 1.253 . 1.272 . 1 323 . 1.283 1.017 .0.227.

7 . 0.227 . 1.021 . 1.297 . 1.320 . 1.265 . 1.256 . 1.205 . 1.142 . 1.193 . 1.257 . 1.268 . 1.300 . 1.281 1.037 . 0.230 . 7 0.7 . 0.9 . 1.5 . 0.1 . -0.5 . 0.0 . 0.8 . 0.8 . -0.1 . 0.3 . -0.3 . -1.7 . -0.2 . 2.0. 1.5 .

.0.257 . 0.853 . 1.256 . 1.322 . 1.264 1.256 . 1.136 . 0.832 . 1.136 .1.256 . 1.264 . 1.322 . 1.256 . 0.853 . 0.257.

8 . 0.257 . 0.853 . 1.258 . 1.321 . 1.252 . 1.258 1.144 . 0.839 . 1.143 . 1 262 . 1.263 , 1.318 . 1.256 . 0.858 . 0.257 . a 0.1 . 0.0 . 0.2 . -0.1 . -0.9 . 0.2 . 0.7 . 0.8. 0.6. 0.4 . 0.0. 3 . 0.0 . 0.6 . 0.1 .

0.227 . 1.017 . 1.284 . 1.324 . 1.273 . 1.254 . 1.199 .1.140 .1.199 . 1.258 . 1.272 . 1.319 . 1.278 . 1.012 . 0.226.

9 . 0.226 . 1.013 . 1.277 . 1.326 . 1.297 . 1.264 . 1.209 . 1*.152 . 1.214 . 1.255 . 1.273 . 1.324 . 1.281 . 1.011 . 0.216 . 9

-0.4 . -0.4 . -0.5 . 0.2 . 1.9 . 0.8 . 0.9 . 1.1 . 1.2 . -0.2. 0.0 . 0.4 . 0.2 . -0.1 . -4.4 .

0.476 . 1.251 . 1.365 . 1.309 . 1.199 . 1.258 . 1.258 . 1.254 . 1.199 . 1.308 . 1.359 . 1.244 .0.474.

10 . 0.470 . 1.224 . 1.357 . 1.314 . 1.201 . 1.268 . 1.272 . 1.262 . 1.195 . 1.306 . 1.380 . 1.251

  • 0.472 . 10

-1.4 -2.2 . -0.5 . 0.3 . 0.2 . 0.8 . 1.1 . 0.6 . -0.4 . -0.2 . 1.6 . 0.5 . -0.5 .

0.283 . 1.076 . 1.270 . 1.267 . 1.306 . 1.272 .1.264 . 1.272 . 1.308 1.267 . 1.260 . 1.065 . 0.280.

11 . 0.278 . 1.061 . 1.262 . 1.265 . 1.308 1.279 . 1.286 . 1.277 . 1.301 . 1.242 . 1.257 . 1.064 . 0.279 . 11

-1.5 . -1.5 . -0.7 . -0.2 . 0.1 . 0.6 . 3.8 . 0.3 . -0.5 . -2.0 . -0.3 . -0.1 . -0.3 .

0.337 . 0.657 . 1 .255 . 1.356 .1.317 . 1.321 . 2.322 .1.361 .1.264 . 0.8556 . 0.332

12. 0.329 . 0.653 . 1.253 . 1.355 : 1.313 . 1.324 . 1.316 , 1.340 . 1.241 . 0.649 . 0.324 . 12

-2.4 . -0.6 . -0.2 . -0.1 . -0.3 . 0.2 . -0.5 . -1.6 . -1.8 . -1.1 . -2.3 .

13. 0.319 . 1.056 . 1.239 . 1.274 . 1.252 . 1.272 , 1.202 . 1.038 . 0.318 . 13

-0.3 . 0.0 . -0.1 . -0.2 . -0.2 . -0.7 -3.6 . -2.5 . -2.0 .

..... . . "'...;i ... ....6i... ' ' ;6 ... ;6 + ; 6; 4 ' '6

' '............ ....* 6 ;.........

0.277 .0.472 . 1.011 . 0.853 . 1.017 .0.475 . 0.280 14 0.279 .0.472 . 1.010 . 0.854 . 1.034 .0.468 . 0.274. 14 0.7 . 0.0 . -0.1 . 0.1 . 1.6 . -1.4 . -2.2 .

STANDARD . 0.227 . 0.258 . 0.229 AVERAGE 15 DEVIATION . . 0.224 . 0.258 . 0.232 . PCT DIFFERENCE 15

=0.739 -1.5 . 0.1 . 1.2 . = 0.8 R P N M L K J N G F E D C 8 A MAP NO: S2-18-02 DATE: 4/23/02 POWER: 66.64%

CONTRQL ROD POSITIONS: F-Q(Z) = 1.913 CORE TILT:

D BANK AT 187 STEPS F-DH(N) = 1.465 NW 1.0008 J NE 1.0015 F(Z) = 1.215 SW 1.0001 SE 0.9975 BURNUP = 24 MWD/MTU A.O. = 3.293 NE-1326 $2C18 Startup Physics Tests Report Page 37 of 56

Figure 6.3 SURRY UNIT 2 - CYCLE 18 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R P N M L K J N G F E D C B A

...............' ..6....' . .. . .............

  • 0.241 . 0.277 . 0.239 . PREDICTED

. 0.245 . 0.278 . 0.241 . MEASURED 1.5 . 0.7 . 0.6 . PCT DIFFERENCE.

.."6 ................. .................................. . . .. . .. . .. . .. . . .

0.281 . 0.479 . 1.026 . 0.910 . 1.020 . 0.476 . 0.279.

2. 0.281 . 0.484 . 1.044 . 0.912 , 1.027 . 0.487 . 0.283 .2

-0.1 . 1.1 . 1.8 . 0.2 . 0.6 . 2.3 . 1.4.

.."6....'.'i.6.."."i......"i....'."i....".'i...'."i....'."..6.i'."....i'.

0.325 . 1,040 . 1.219 . 1.267 . 1.250 . 1.262 . 1.213 . 1.031 . 0.321.

3 0.326 . 1.034 . 1.230 .1.306 . 1.232 . 1.265 . 1.224 . 1.041 . 0.323 . 3 0.3 . -0.5 . 0.9 . 3.1 . -1.5 . 0.2 . 0.9 . 1.0 . 0.7 .

4 . 0.330 . 0.644 i 1.205 . 1.332 . 1.316 . 1.320 . 1.307 . 1.343 . 1.238 . 0.650 . 0.334 . 4

-0.8 . -1.3. -2.5. -0.1 . 1.11 1.1. 0.8 . 1.0 . 0.8 . -0.5 . -1.0 .

0.282 . 1.040 . 1.232 . 2.255 . 1.308 . 1.272 . 1.262 . 1.272 . 1.307 . 1.255 . 1.241 . 1.050 . 0.284.

. 0.281 : 1.037 . 1.224 . 1.252 . 1.307 . 1.281 . 1.274 . 1.284 . 1.320 . 1.270 . 1.217 . 1.037 . 0.281 . 5

-0.4 . -0.7 . -0.3 . -0.7 . 0.6 . 1.0 . 1.2 . 1. . 1.3 . -1.9 . -1.2 . -0 . .

6 0.479 . 1.217 . 1.319 . 1.270 . 1.264 . 1.279 . 1.280 . 1.286 . 1.285 . 1.312 . 1.322 . 1.214 . 0.481 6 0.3 . 0.0 . -1.0 . -2.9. -0.7 . 0.5 . 1.1 . 0.8 . 0.9 . 0.2 . -1.1 . -0.7 . 0.2 .

. 0.238 .1.021 .1.264 .1.299 .1.273 .1.276 .1.218 .1.156 .1.217 .1.273 . 1.273 .1.304 .1.269.1.026 .0.238 .

7 0.240 . 1.030 . 1.280 . 1.295 . 1.259 . 1.274 . 1.232 . 1.167 . 1.223 . 1.281 . 1.271 . 1.279 . 1.264 . 1.043 . 0.241 . 7 1.2 . 0.8 . 1.2 . -0.3 . -1.1 . -0.2 . 1.2 . 1.0 . 0.5 . 0.7 . -0.2 . -1.9 . -0.4 . 1.7 . 1.2 .

.0.276 . 0.910 . 1.252 . 1.307 . 1.263 . 1.267 . 1.159 . 0.861 . 1.159 . 1.267 . 1.263 . 1.307 . 1.252 . 0.910 . 0.276.

8 . 0.284 . 0.914 . 1.252 : 1.303 . 1.251 . 1.268 . 1.168 . 0.870 . 1.174 . 1.286 . 1.266 . 1.303 . 1.249 . 0.908 . 0.274 . 8

  • 2.9 . 0.30. 0.07. -0.4 . -1.0 . 0.01. 0.7 i. . 1.3 . 1.5 . 0.2 . -0.4 . -0.2 . -0.3 . -0.5 .

0.238 .1.026 .1.26i9 .1.304 .1.274 .1.274 .1.221 .1.163 .1.221 .1.277 .1.273 .1.300 .1.265 .1.021 .0.238

. 0.239 . 1.021 , 1.259 . 1.301 . 1.290 . 1.281 . 1.230 . 1.177 . 1.247 . 1.265 . 1.273 . 1.305 . 1.268 . 1.021 0.230 G . 9 0.2 . -0.5 . -0.8 . -0.2 . 1.3 . 0.5 . 0.7 . 1.3 . 2.1 . -1.0 . 0.0 . 0.4 . 0.3 . 0.0 . -3.1 .

0.480 . 1.223 . 1.337 . 1.310 . 1.274 . 1.277 . 1.269 . 1.274 . 1.274 . 1.309 . 1.332 . 1.217 . 0.478.

10 .0.472 . 1.190 : 1.325 . 1.311 1.277 . 1.282 . 1.282 . 1.283 . 1.270 . 1.311 . 1.355 . 1.229 . 0.483 . 10

-1.7 . -2.7 . -0.9 . 0.1 . 0.2 ,. 0.4 . 1.0 . 0.7 . -0.3 . 0.1 . 1.7 . 0.9 . 1.0 .

0.284 . 1.050 . 1.241 . 1.256 . 1.308 . 1.273 . 1.263 . 1.274 . 1.309 . 1.255 . 1.232 . 1.040 . 0.282.

S .0.279  : 1.035 : 1.232 . 1.253 . 1.306 . 1.275 . 1.286 . 1.275 . 1.291: 1.246 . 1.238 . 1.047 . 0.284 . 11

-1.6 . -1.4 . -0.7 . -0.2 . -0.1 ,. 0.2 . 1.8 . 0.1i . -1.4 . -0.8 . 0.5 . 0.6 . 0.7 .

.... ... .... .. .. .. ... ........i ~.[. ]

i....i....i....[.~

....

  • i i . .~ i . . ...... ].* i.... .........

0.338 . 0.654 . 1.228 . 1.330 .1.298 . 1.307 . 1.303 . 1.334 . 1.236 . 0.653 . 0.332 12 . 0.339 . 0.651 . 1.224 . 1.321. 1.279 . 1.301 . 1.292 : 1.311 . 1.220 . 0.654 : 0.332. 12 0.4 . -0.4 . -0.4 . -0.6 . -1.5 . -0.5 . -0.8 . -1.7 . -1.3 . 0.2 . -0.2 ,

.. .... .. ... i.ii.ii... ... i.... i ~ i ... i i 'i...... i i~ ~ i 1 i i.........

' ' ii ...............

0.321 . 1.031 . 1.214 . 1.263 . 1.251 . 1.268 . 1.219 . 1.040 . 0.325.

13 . 0.320 . 1.029 . 1.206 . 1.250 . 1.233 . 1.255 . 1.175 . 1.017 . 0.321 . 13

-0.3 . -0.2. -0.6 . -1.0 . -1.4 . -1.0 . -3.6 . -2.2 . -1.3 .

. .. .. ... ... ..i ....

..'2 6 6 *' 2.....  ; [' 2 4 ' '6 i i 2.........

i 'i i 6...............

0.279 . 0.476 . 1.020 . 0.910 . 1.026 . 0.479 . 0.281.

14 0.285 . 0.475 . 1.015 . 0.911 . 1.051 . 0.474 . 0.276 . 14 2.0 . -0.3 . -0.5 . 0.0 . 2.4 . -1.0 . -1.9 .

STANDARD . 0.239 . 0.277 . 0.241 . DIAVERAGEN.

15 DEVIATION . . 0.236 . 0.277 . 0.245 . PCT DIFFERENCE. 15

=0.712 -1.3 . 0.1 . 1.8 . = 0.9 R P N M L K J H G F E D C B A

SUMMARY

MAP NO: S2-18-03 DATE: 4/29/02 POWER: 99.96%

CONTROL ROD POSITIONS: F-Q(Z) = 1.773 CORE TILT:

D BANK AT 230 STEPS F-DH(N) = 1.441 NW 1.0004 j NE 1.0026

- - I------

F(Z) = 1.134 SW 0.9997 SE 0.9993 BURNUP = 203 MWD/MTU A.O. = 2.111 NE-1326 $2C18 Startup Physics Tests Report Page 38 of 56

SECTION 7 REFERENCES

1. R. W. Twitchell, "Surry Unit 2, Cycle 18 Design Report", Technical Report NE -1323, Revision 0, Dominion, April, 2002.
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-83 1, Revision 6, Virginia Power, April, 2002.
4. Surry Unit 2 Technical Specifications, Sections 3.12.C.1, 4.10.A.
5. Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units I and 2, Surry Power Station Units I and 2: Modification of Startup Physics Test Program - Inspector Followup Item 280, 281/88-29-01", Serial No.89-541, December 8, 1989.
6. B. C. Armstrong, "Surry 2, Cycle 18 TOTE Calculations", PM-0928, Revision 0, April, 2002.
7. C. D. Clemens, et al, "Surry 2, Cycle 18 Flux Map Analysis", PM-0932, Revision 0, and Addenda A and B, April, 2002.
8. T. R. Flowers, "Reload Safety Evaluation, Surry 2 Cycle 18 Pattern GW", Technical Report NE 13 10, Revision 0, February, 2002.
9. S. S. Kere "Approved Reload Safety Evaluation, Surry 2 Cycle 18 Pattern GW", ET No. NAF 2002-0028 Revision 0, March, 2002.
10. P. D. Banning, "Implementation of RMAS for Startup Physics Testing", PM-824, Revision 0, March, 2000.
11. Surry Power Station Unit 2 Control Room Narrative Log, April 20, 2002.

NE- 1326 $2C 18 Startup Physics Tests Report Page 39 of 56

APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE- 1326 S2C 18 Startup Physics Tests Report Page 40 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Reactivity Computer unecKout No:

Reference Proc No / Section: 2 -NPT-RX-008 Sequence Step Sequence Step No:

Bank Positions (Steps) RCS Temperature (OF): 547 ii Power Level (% F.P.): 0 Test CA: 230 Other (specify):

Conditions SDA: 230 SDB: 230 CD: Below Nuclear Heating (Design) CB: 230 CC: *

  • II1 Bank Positions (Steps) RCS Temperature (OF): /

Test Power Level (% F.P.): 0 230 Other (specify):

Conditions SDA: 230 SDB: 230 CA:

CD: Below Nuclear Heating (Actual) *1 CB: 230 CC:

Date/Time Test Performed:

I.,/S,; , ,3 O- *2

"/""7 -" L..- ... ._ __

Measured Parameter Pc= Measured Reactivity using p-computer (Description) Pi= Predicted Reactivity IV 3 *,-/o-Test.

f Results. Measured Value .P=

%D= 0o/7%, -V.7?;t Design Value %D= {(Pc - pt)/pj x 100% <4.0 %

IReference CWOAP 7905, Rev. 1, Table 3.6 V FSARITech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met YES NO Acceptance Criteria Is met

  • 17YES 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 = "t 90l, - /;' .0e AllowableRange= /o,0P e.-A , /,1o.,O0crL Prepared By: !Z_ Reviewed By: .

NE-1326 S2C18 Startup Physics Tests Report Page 41 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Zero Power Testing Range Determination Reference Proc No/.Section:, 2-NPT-RX-008 SequenceStep No:

II Bank Positions (Steps) RCS Temperature ("F): 547 Test ._ Power Level (% F.P.): 0 Conditions SDA:. 230 SDB: 230 CA: 230 Other (specify):

(Design). CB: 230 CC: -CD:

  • Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): */7 Test Power Level (% F.P.): 0 Conditions SDA: 230 SDB: 230. CA: 230 Other (specify):

(Actual) CB: 230 CC: CD: Below Nuclear Heating Date/Time Test Performedl:

-112010-_*_3_* _3_*_- _......

Reactivity Computer-Initial -

Flux Background Reading I.. Ox(o amps IV .. . . . . ... .

Test . ..

'Results Flux Reading.At.. .- 7 Point Of Nuclear Heating 3.6 /a amps

.-  ?

Zero Power Testing Range 2-OX/a to I. *X/O amps Reference Not Applicable V FSARJTech Spec Not Applicable Acceptarce ......

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.

Prepared By:_______ Reviewed By: bcZ k NE-1326 S2C18 Startup Physics Tests Report Page 42 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - ARO 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: 23Q SDB: 230 CA: 230 Other (specify):

(Design) CB: 230 CC: 230 CD: 230 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): 5/Y6. 7?

Test _Power Level (% F.P.): 0 Conditions SDA: 230 SDB: 230 CA: 230 Other (specify):

(Actual) CB: 230 CC: 230 CD: 230 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter (CB)Mo; Critical Boron Concentration - ARC

"* (Description)

IV Test S.Results Measujred.Value. . (CB) o= .. / / ppm

"(DesignConditions)

Design Value Ca = 2087 50 ppm (Design Conditions)

Reference Technical Report NE-1323, Rev. 0 V FSAR/Tech Spec laCa x Caj

  • 1000 pcm Acceptante Criteria Reference Technical Specification 4.10.A Design Tolerance is met " v-YES NO Acceptance Criteria is met *._ZYES NO VI comments aC8 -6.78 pcm/ppm CD= (C6f M - Cil; C. is design value I.. --

Prepared By: , Reviewed By:. i./ I "-* A NE-1326 S2C18 Startup Physics Tests Report Page 43 of 56

"_ SURRY POWER STATION UNIT 2 CYCLE 18 SHEET STARTUP PHYSICS TEST-RESULTS AND EVALUATION

- ARO I Test

Description:

Isothermal Temperature Coefficient 2-NPT-RX-008 Sequence Step No:

Reference Proc No / Section:

iI Bank Po'sitions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 SDA: 239 SDB: 230 CA: 230 Other (specify):

Conditions (Design) CB: 230 CC: 2.30. CD: 230 Below Nuclear Heating RCS Temperature (OF): 6'13 - 'F III Bank Positions (Steps)

Level (% F.P.): 0 Test .Power SDA: 230 SDB: 230 CA: 230 Other (specify):

Conditions CB: 230 CC: 230 CD: ;OW**' Below Nuclear Heating (Actual) ,

Date/TimeTest Performed:

Measured Parameter .(aT ISO)Ao; Isothermal Temperature (Description) Coefficient ARC IV to.:.ISO _ -O,'P pcrn/F

  • Test Measured Value .) ' pco Results "- (Cs= aPLi. ppm)

Design Value ISO 3 3+

(T o)o= - _-3.0 pcm/)F.

(Actual Conditions) -- (CB= -11 ( ppm)

Design Value (isO)A.. -1.57 +/-3.0 pcmPF (Design Conditions) ( CB= 2087 ppm) .

(Cs= 2087 ppm)

Reference . Technical Report NE-1323, Rev. 0 FSARPCOLR aT 0: 3.82

  • pcrll OF V-aoP = -1.68 pcm/F Acceptance 0 Criteria . Reference COLR 2.1.1,Technical Report NE-1323, Rev.

7V YES

  • NO Design Tolerance is me Acceptance Criteria Is met . "-7YES N Vl memorandum from Comments *Uncertainty on caTmw = 0.5Spcrn/°F (

Reference:

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

Prepared By: "c "Y 4- Reviewed By:. / l_

Page 44 of 56 NE-1326 S2C18 Startup Physics Tests Report

SURRY POWER-STATION UNIT 2 CYCLE 18 SHEET STARTUP PHYSICS TEST RESULTS AND EVALUATION Rod Swap Ref. Bank Test

Description:

Control Bank B Worth Measurement, --

Squnc Aite Li'~

Proc No I Section: 2-NPT-RX-008 ýRCS Temperatr Sequence (Step NO:

Reference (F:57 Bank Positions (Steps)

Power Level (% F.P.): 0 Test Conditions SDA: 23&. SDB: 230 CA: 230 -Other (specify):

Below Nuclear Heating (Design) CB: moving. CC: 230 CD: 230.

RCS Temperature (OF):-5t/-7 III Bank Positions (Steps)

Power Level (% F.P.): 0 Test Conditi6ns SDA: 230 SDB: 230 CA: 230 Other (specify):

{ &

(Actual) CB: moving CC: 230 CD: 230 3elow Nucdear r-l-atlng Date/Time Test Performed:

13REF; Integral Worth Of Control Bank B, Measured Parameter (Description) All Other Rods Out IV lB .'.=

SREF_ I / / ,.

.)4 c Test Measured Value Results Design Value IBIEF- 1433 143 pcm (Design Conditions)

Reference "Technical Report NE-1323. Rev. 0 And Engineering Transmittal NAF 2002-0038, Rev. 0 If Design Tolerance is exceeded. SNSOC shall FSARJTech Spec evaluate impact of test result on safety analysis.

V SNSOC may specify that additional testing Acceptance be performed.

Criteria VEP-FRD-36A Reference V YES. NO Design Tolerance Is met mr)

Acceptance Criteria Is met : V Tr*0 - .-

Vl Comments Prepared By: Reviewed By:,

NE-1326 S2C18 Startup Physics Tests Report Page 45 of 56

-SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration -'B B1rik In Reference Proc No'/ Section: 2-NPT-RX-008 Sequence Step No:

!I Bank Positions'(Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 23Q SDB: 230 CA: 230 Other (specify):

(Desigh) CB: 0 CC: 230 CD: 230 Below Nuclear Heating IIl Bank Positions (Steps) - RCS Temperature (OF): 59-/7 Test Power Level (% F.P.): 0 Conditions SDA: 230 "SDB: 230 CA: 230 Other (specify):

(Actual) CB: 0 CC: 230 CD: 230 Below Nuclear Heating Date/Time Test Performed:

Measured Parameter (CB)ms; Critical Boron Concentration, (Description) B Bank In IV Test Results." Measured.Value (CB),- ppm .

(Design Conditions)

Design Value Ca 1877 + ACB Prev + (10 + 143.311aCB) ppm (Design Conditions) CB = 109O _ 31 ppm .

Reference Technical Report NE-1323, Rev. 0 V FSAR/Tech Spec Not Applicable Acceptan.ce II ._!

Criteria Reference Not Applicable Design Tolerance is met

  • vŽ*YES. NO Acceptance Criteria is met * "YES . -NO.

VI Comments aCB = -6.82 pcm/ppm ACB PrMv = (CB)MARO - 2087 ppm Prepared By. 11AV-1P -- 7 Reviewed By;:2(* Z$

NE-1326 S2C18 Startup Physics Tests Report Page 46 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET R f r n

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

II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 230D SDB: 230 CA: 230 Other (specify):

(Design) CB: moving CC: 230 CD: 230 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (OF': 5-4-,

"lest Power Level (% F.P.): 0 Conditi6ns SDA: 230 SDB: 230 CA: 230 Other (specify):

(Actual) CB: moving CC: 230 CD: 230 Below Nuclear Heating Date/Time Test Performed:

Q4-11/0 -Z1/3.zI I Measured Parameter aC-; Boron Worth Coefficient (Description)

IV Test Results Mea[ured Value- ac, 7 cm/pPm Design Value aC8 = -6.82 _ 0.68 pcm/ppm (Design Conditions) r~eference

,1 Report Technical '02' Qlr n I

V r-SAW I ech Spec Not Applicable Acceptance Criteria Reference jNot Applicable Design Tolerance is met : V YES NO Acceptance Criteria is met : v1 YES 7 NO Vi omments I A

Prepared By": Reviewed By: \

NE-1326 S2C18 Startup Physics Tests Report Page 47 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET

. II Test

Description:

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

Reference II Bank Positions (Steps) RCS Temperature (OF): .547 R

Power Level (% F.P.): 0 Test SDA: 230 SDB: 230 CA: moving Other (specify):

Conditions LJM Yuk I n *?A nir W

(Design) RCS Temperature (OF): 1-/7 IIl Bank Positions (Steps)

SCB: moving'"CC:- ý*23 G: .:,40.

power Level (% F.P.): 0 Test Other (specify):

Conditions SDA: 230 SDB: 230 CA: moving Below Nuc.ear Heating (Actual) CB: movlng6 CC: 230 Cb: 230 Daterrime Test Performed:

. .... Q 0 IARS; Integral Worth of Control Bank A, I I, Measured Parameter (Description) Rod Swap ARS_ " . (Adjusted Measured IV Measured Value

-Test. Critical Referience Bank Position to. steps)

Design Value Results (Actual Conditions)

IARS ?ORiZ. (Adjusted Measured' Critical Reference Bank Position = 5-6. &o steps)

Design Value IARS= 210 +/- 100 pcm (Design Conditions)

(Critical Reference Bank Position = 60 steps)

Reference Engineedng Transmittal NAF 2002-0038, Rev. 0, VEP-FRD-36A FSARITech Spec IfDesign Tolerance Is exceeded, SNSOC shall evaluate Impact of test result on safety analysis.

V SNSOC may specify that additional testing Acceptance Criteria ebe performed.

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

  • YES NO Acceptance Criteria is met
  • VI Comments Prepared By:7Tff Reviewed BY:

Page 48 of 56  !

NE-1326 S2C18 Startup Physics Tests Report

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank C Worth Measurement, Rod Swap 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: 2PD SDB: 230 CA: 230 Other (specify):

(Design) CB: moving CC: moving CD: 230 Below NuclearLUI HeatingF0,-.\ b ,',f 7

. " ' ,=,"=*,*".-"* -r ...... I,,,

III Bank Positions (Steps) IK, lemperiature t rl. -, 4y '-7 Power Level (% F.P.): 0 Test Other (specify):

Conditions SDA: 230 SDB: 230 CA: 230 CB: moving CC: moving CD: 230 Below Nuclear Heating (Actual)

Date/Time Test Performed:

.1" g -. '/ v I Q:1 Measured Parameter lo; Integral Worth of Control Bank C, (Description) Rod Swap IV Measured Value CRS= 7 q & (Adjusted Measured Test Critical Reference Bank Position = Jlii".1 -.steps)

Results Design Value 0(d e a (ActualConditions) IcRS= (03, L (Adjusted Measured Critical Reference Bank Position = 119. I steps)

Design Value (Design Conditions) leaS= 799 +/- 120 pcm (Critical Reference Bank Position = 127 steps)

Reference Engineering Transmittal NAF 2002-0038, Rev. 0, VEP-FRD-36A FSAR/ITech 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.

IReference eference - VEP-F*RD-36iA

_YES NO Design Tolerance is met :

Acceptance Criteria is met" V YES NO Vi Comments'

/!A., A-L

__ _ _ _ _I , A. . /1 C Prepared By: K'frk*aj'

/

Reviewed By:

NE-1326 S2C18 Startup Physics Tests Report Page 49 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Rod Swap I Test

Description:

Shutdown Bank A Worth Measurement, 2-NPT-RX-008 B sequence Step No:

Reference) Proc No/ Section:

Il Bank Positions (Steps) R*S Temperature (OF): 5147 Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: 230 CA: 230 Other (specify):

CB: moving CC: 230 CD: 230 Below Nuclear Heating (Design)

P Bank Positions (Steps) rCS Temperature (fF): 6'z"7 III Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: 230 CA: 230 Other (specify):

(Actual) CB: moving CC: 230 CD: 230 'Below Nuclear Heating Date/Time Test Performed: ..

7/a.y!

Measured Parameter ISR; IntegralWorth of Shutdown Bank A, (Description) Rod Swap RS=. , (Adjusted Measured IV Measured Value Critical Reference Bank Position I.6' steps)

Test Results Design Value (Actual Conditions) I RS 000 'R (Adjusted Measured Critical Reference Bank Position = 5 . ?' steps)

De~sign Value IsAR= 1000 150 pcm (Desian Conditions)

S(Critical Reference Bank Position = 157 steps)

Reference. Engineering Transmittal NAF 2002-0038, Rev. ;0 VEP-FRD-36A FSAPjTech Spec IfDesign 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 IVEP-FRD-36A

+

YES NO Design Tolerance is met *

/ YES NO Acceptance Criteria is met: .

Vl Comments

- A1 -

Reviewed By:

Prepared By:

NE-1326 S2C18 Startup Physics Tests Report Page 50 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank D Worth Measurement, Rod Swap 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: 23Q,. SDB: 230 CA: 230 JOther (specify):

(Design) CB: moving CC: 230 CD: moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): 5L/ 7 Test Power Level (% F.P.): 0 Conditions SDA: 230 SDB: 230 CA: 230 Other (specify):

(Actual) CB: moving CC: 230 CD: moving Below Nuclear Heating Date/Time.Test Performed:

Measured Parameter ID ; Integral Worth of Contro! Bank D, (Description) Rod Swap IV Measured Value ID 00*. / (Adjusted Measured Test -.. Critical Reference Bank Position-= I5/. 0.steps)

Results Design Value (Actual Conditions) 10 /0 q161. '2 (Adjusted Measured Critical Reference Bank Position = 1/"q t steps)

Design Value (Design Conditions) InRS= 1047 +/- 157 pcm (Critical Reference Bank Position = 164 steps)

Reference Engineering Transmittal NAF 2002-0038.Rev. 0. VEP-FRD-36A FSAR/Tech Spec IfDesign Tolerance is exceeded, SNSOC shall V 1evaluate impact of test result on safety ahalysis.

Acceptance SNSOC may specify that additional testing Criteria be performed.

Reference IVEP-FRD-36A Design Tolerance is met : -/ YES NO Acceptance Criteria is met : I/YES NO VI Comments Prepared By. Reviewed By: ag. (/} // .

. / .11-y l J I Jw NE-1326 S2C18 Startup Physics Tests Report Page 51 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B 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: 230, SDB: moving CA: 230 Other (specify):

(Design) CB: moving CC: 230 'CD: 230 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): 51/7 Test Power Level (% F.P.): 0 "

Conditions SDA: 230 SDB: moving CA: 230 Other (specify):

(Actual) CB: moving CC: 230 CD: 230 Below Nuclear Heating Date/Tirr~e T st Performed:

(I Measured Parameter IsB's; Integral Worth of Shutdown.Bank B, (Description) Rod Swap IV Measured Value IssR:

R  ! 91. (Adjusted Measured Test.. . Critical Reference Bank Pdsition = Gi* steps)

Results Design Value 1 (

(Actual Conditions) IsaRS= L/0, I (Adjusted Measured

_ Critical Reference Bank Position = i4/.

  • steps)

Design Value (Design Conditions) IS8RS= 1143 +/- 171 pcm (Critical Reference Bank Position = 178 steps)

Reference Engineering Transmittal NAF 2002-0038, Rev. 0. VEP-FRD-36A FSARITech Spec IfDesign 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

  • 3 t A .

Prepared By: !LA 1L91 Reviewed By:

jr/'-01 I I D/V NE-1326 S2C18 Startup Physics Tests Report Page 52 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ITest

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): 5'zl 7 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 Dat~efrime 0lest 0/VPerformed:

/.z z Measured Parameter ITo,; Integral Worth of All Banks, (Description) Rod Swap IV Measured Value IT, 'q*,a,7pcm Test Results Design Value (Actual Conditions) ,.o,' *pcm Design Value (Design Conditions) IrT~u= 5631 +/- 563 pcm

,Reference Engineering Transmittal NAF 2002-0038. Rev.0, VEP-FRD-36A FSAR/Tech Spec IfDesign Tolerance is exceeded, SNSOC shall V -evaluate impact of test result on safety analysis.

Acceptance Additional testing must be performed.

Criteria Reference IVEP-FRD-36A I

Design Tolerance is met v- YES NO Acceptance Criteria is met - YES NO VI Comments I

Prepared By: Reviewed By:__

V

/ I 0 NE-1326 S2C18 Startup Physics Tests Report Page 53 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Map - At Power Reference

!1 Proc No / Section:

Bank Positions (Steps) 2-NPT-RX-008 ,002 Sequence Step No:.

ROS Temperature (0 F):

TREF 1I Test "Power Level (% F.P.): _ 30 Conditions SDA: 230 SDB: 230 CA: 230 Other (specify):

(Design) CB: 230 CC:

  • CD: Must have : 38 thimbles*"

III Bank Positions (Steps) RCS Temperature (OF): Trmv Test IPower Level (% F.P.): 05. 3 Conditions SDA: 230 SDB: 230 CA: 230 Other (specify):

(Actual) CB: 230 CC: 2,3O CD: IoO SDatelrime Test Performed:

L T~b*..

,-/;t a/oa 0s-5:;s SMeasured Assembly Rise Hot :1 Flux Hot Positive Incore Parameter Power %DIFF . Channel Factor Channel Quadrant IV (Description) (M-P)/P - FAH(N) Factor F0 (Z) Power Tilt Tes.t Measured -7.Q% Poý_ 19.9.

Results .. Value. 04

'(Design Design Val ++/-151Y6%for

+/-e

+/-15% for P1<0.9 Pi ) "".9 7 NIA N/A *;1.0204 Conditions) (P91 assy power)

Reference WCAP-7905, Rev. I None None WCAPF-7905,Rev.i NE-1323, Rev. 0 NE-1323, Rev. 0 V FSARICOLR None FAH-(N):1.56(1+0.3(1-P)) F,(Z)*4.64"K(Z) None Acceptance Criteria Reference I

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: WL *nLC.O_' " Reviewed By: .

NE-1326 S2C18 Startup Physics Tests Report Page 54 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ITest

Description:

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

II Bank Positions (Steps) RCOS Temperature (OF): TREF _ 1 Test Power Level (% F.P.): 65*_ P *- 75 Conditions SDA: 23Q SDB: 230 CA: 230 Other (specify):

(Design) CB: 230 CC: 230 CD:

  • Mustfhave > 38 thimbles**

III Bank Positions (Steps) RCS Temperature (iF): c oc Test Power Level (% F.P.): ( (.

Conditions SDA: 230 SDB: 230 CA: 230 Other (specify):

(Actual) CB: -230 CC: 230 CD: i "-

Date/rime Test Performed: Ll.ý _rA 1-11, Lle_ý 11 v. - -

Maximum Reiative 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 F0 (Z) Power Tilt Test Measured -4.1k P O" -'I Results Value; A (. o .9/.

e_, *_.. _* _.

Design Value +/-10% for P, >0.9

< 1.0203 (Design +/-15% for Pj<0.9 N/A N/A Conditions) (PI = assy power)

Reference WCAP-7905, Rev. 1 None None WCAP-7905,Rev.1 NE-1323, Rev. 0 NE-1323, Rev. 0 I r None None FAH(N)Wl.56(1+0.3(1-P)) Fa(Z)2.32/PK(Z)

V FSARICOLR Acceptance 4.

COLR 2.4 COLR 2.3 None Criteria- - Feference None

______________ ____________ I _____

Design Tolerance is met : V YES NL)

Acceptance Criteria is met : __YES ____ NO___

VI *As required Comments **Must have at least 16 thimbles for quarter core maps for multi-point calibrations A

iL Prepared By: /1  %-&QY4//3/- Reviewed By: e,"

V-V*

NE-1326 S2C18 Startup Physics Tests Report Page 55 of 56

SURRY POWER STATION UNIT 2 CYCLE 18 STARTUP PHYSICSTEST RESULTS AND EVALUATION SHEET I Test

Description:

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

SII Bank Positions (Ste'ps_) :,,.. RCS Temperature (OF):-TREF-1 Test *-- oPower Level (% F`.P.): 95:< P:5< 100 Conditions SDA: 230 SDB: 230 CA. 230 Other (spe'cify):

(Design) CB: 230 CC: 230 CD: " Must have> 38 thimbles" iII Bank Positions (Steps) RCS Temperature (OF): - ",,

Test Power Level (% F.P.): , '.. ,

Conditions SDA: 230 SDB: 230 CA: 230 Other (specify):

(Actual)

I m CB: 230 CC: 230 CD: Rkao Date/Time Test Performed:

-/ 41*, A7N*

! .0*C-)o Maximum Relatlve Nuclear Etithalpy 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 F0 (Z) Power Tilt Test Measured va*.ei -3.6 3-. ".'

. ./.0.* ) / ."-: .o Results 0 0-:L--

Design Value +/-10% for P,>0.9 (Design +/-15%for P1<0.9 N/A N/A S 1.0203 Conditions) (P,= assy power) I-Reference WCAP-7905, Rev. I None None 'WCAP.7,05.Rev.1 NE-1323, Rev. 0 NE-1323. Rev. 0 V . - 'FSAP-COLR None FAH(N):1.56(1÷0._3(i-P)) Fa(Z)<S2.32/P-K(Z} None Acceptance f 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 Prepared By: Reiwe Bý'

  • ° Reviewed y _.___-__

-. o ; - * ... , * ;

NE-1326 S2C18 Startup Physics Tests Report Page 56 of 56

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