ML022060509

From kanterella
Jump to navigation Jump to search
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)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 16, 2002 Mr. Luis A. Reyes, Administrator United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23 T85 Atlanta, GA 30303-8931 Serial No.:

NLOS/mm Docket No.:

License No.:

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 02-458 50-281 DPR-37

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 Nuclear Analysis 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 f4</15r q

_2' 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 The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

NE-1326 S2C18 Startup Physics Tests Report Page 1 of 56

TABLE OF CONTENTS PAGE C lassification/D isclaim er..................................................................................

1 Table of C ontents.........................................................................................

2 L ist of T ables....................................................................................................

3 L ist 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 FIGURE TITLE PAGE 1.1 Core Loading M ap................................................................................

10 1.2 Burnable Poison Locations..................................................................

11 1.3 Available Incore Moveable Detector Locations.................................. 12 1.4 Beginning of Cycle Fuel Assembly Bumups.......................................

13 1.5 Control Rod Locations.........................................................................

14

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

18 2.2 Rod Drop Time - Hot Full Flow Conditions......................................

19 3.1 Control Bank B Integral Rod Worth - HZP........................................ 24 3.2 Control Bank B Differential Rod Worth - HZP.................................. 25 6.1 Assemblywise Power Distribution - 25% Power................................ 36 6.2 Assemblywise Power Distribution - 67% Power................................ 37 6.3 Assemblywise Power Distribution - 100% Power...............................

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

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 refueling. During this shutdown, 101 of the 157 fuel assemblies in the core were replaced with 60 fresh assemblies, 40 twice burned assemblies from Surry Unit 1, and one additiona~l twice burned assembly from Surry Unit 2. The Cycle 18 core consists of 8 sub-batches of fuel: two. batches loaded fresh in Cycle 17 (batches 19A and'l 9B); one batch loaded from -Cycle 15 (batch 16B); three batches previously burned' in Surry Unit 1 (batches S1/177, S1/18A, and S I/18B); and two fresh batches (batches 20A and 20B). The fresh batches are of a similar design to the Westinghouse batch 19 fuel (fresh fuel in Cycle 17).

In Cycle 18, a BPRA product with an active absorber length of 127.1 inches is used. Cycle 18, similar to Cycle 17, incorporated the burnable poison rod design made of B4C in Alumina, which is available in various enrichments of B4C. There are no thimble plugging devices, flux 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 number of burnable poison rods for Cycle 18. The available incore moveable detector locations 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 boron worth coefficient measurement was within 6.0% of the design prediction, which is within the design tolerance of : 10%.

The measured isothermal temperature coefficient (ITC) for the all-rods-out (ARO) configuration was within 0.8 pcmrrF of the design prediction. This result is within the design tolerance of +/-3 pcm/fF. The measured ITC of -0.51 pcm/°F 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/'F. When the Doppler temperature coefficient and a 0.5 pcm/IF 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/F.

Measured core power distributions were within established design tolerances. Generally, the 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% of the design predictions for relative assembly powers less than 0.9. 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.

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.

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 1 322 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 VEP -NES-NAF R

P N

NORTH Al I' SURRY UNIT 2 - CYCLE 18 FULL CORE LOADING PLAN PAGE 1 of 2 REVISION NO. 0 M

L K

J H

G F

E D

C B

A sSC 2 4C 07C 3EP 40R L

S 24C A *F RCC 5BP 20BP

-48S RCC 45P RCC 120,BP 471' 16R 20BP RCC 20BP' I in Io 19R 29P' 31C IRP RCC 45R I 32C RCC 20BP 50P 41R 40C 531' 53P 39R 45C ~

~

~

u&

6O 5

7 6

05R, 13P 32R 2

56C 5OC 3

51C j53' 120BP2 RCC 203P' 20BP RCC 20BP 5BPI 34C -SOR I24R 1_23P11 R I21P' 04? 08P I18R J251' 08OR 51R, 48C 900 13C R

2

.CC 20BP RCC 20BP AOD I P

1CJ 37R 12 L

Ok I t31 2~-

,~t-

~

3BP RCC 20BP RCC' 20BP 20BPI RCC

  • 1D
  • O RCC ARO 321' 20BP 53RC 30Pr I

8

-1 8

2 RCC 52P 07P' 05P 351 RCC 2

CC 20BP RCC 16P 09R 06P 46R 30C 54R 07R I41P 01C 47B 36B I 44P 36R 46P I

02P 3BP RCC 20BP 20BP RCC RCC 20B3P 20BP ROC 3BP 29C 59R 34P 23R 19P 26R 51P 371P 53P 15R lIP 1OR 31P 43R 18C 20

.T__C_*

BOAP RCC 20RP RCC RCC 06C 147C 20BP 52R 5BP 49R 44C INCORE DEVICE DESCRIPTIONS:

RCC-FULL LENGTH CONTROL ROD 3BP-3 BURNABLE POISON ROD CLUSTER 5BP-5 BURNABLE POISON ROD CLUSTER 20BP-20 BURNABLE POISON ROD CLUSTER RCC 17P 20BP 06R RCC 49C 37C F

20BP CC 04R 09P 3OR RCC 03P 20BP 25R 5OR 39C 20BP RCC 14P 20BP 44R RCC 17C 20BP 29R RCC 54P 3BP 56R 20C 4SP I03R rp I AP 31R2 2P 18P 20OBP 12R RCC 42P 3BP 47R 02C 40P 20BP 22R RCC 36P 51B 24P 34R 20P 38R 05C 2031' RCC 12082 20BP RCC 20SP 17R 115P I13R

_C B C

RCC 27P 20BP 57R RCC 1 OC 20BP 14R 5BP 48R 42C RCC 52t 33C 5BP 42R 36C Prepared By: -IZ Date: 12 /iq 101 Concurrence By:

Reviewed By:

Wýýte:

Wigj/

0 1 Approved By:

Approved~ By :*.ý ?

Date: i-uIa 35C 4

5 6

7 8

9 1I 12 13 14 15 Date: i1810"?

Date:

2 Page 10 of 56 NE-1326 S2C 18 Startup Physics Tests Report I

48P 03R RCC 20BP 33R 56P RCC

_w_

an'v*

9*D

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 LOC ID G06 35R B06 09R C06 46R 207 53R M07 28R K07 21R P07 02R D07 33R B07 54R NOS 36R C08 07R P09 59R M09 23R K09 26R F09 15R D09 1CR 209 43R Nio 52R LI0 04R JID 30R BP ID BP927 BP941 BP953 EP945 BP934 3P920 SP925 BP937 BP950 BP917 BP918 8P946 BP931 BP926 BP922 BP940 BP949 BP967 BP939 BP921 CORE LOC GI0 El0 CIO Nil Mi1 KII FII D11 Cli L12 312 G12 E12 L13 K13 H13 F13 B13 J14 G14 ASSY ID 03R 34R 38R 49R 06R 31R 17R 13R 42R 25R 29R 12R 14R 50R 44R 22R 57R 48R 56R 47R Prepared By Date: jiiithvj Concurrence By: A k Reviewed By:

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

Approved By:

Date:

BP ID BP924 BP936 BP964 BP971 8P955 BP943 BP932 BP960 BP975 BP962 BP935 8P928 BP956 BP973 BP959 BP919 BP952 BP972 BP947 BP948 Date:

Date: Y/

NE-1326 S2C 18 Startup Physics Tests Report Page 11 of 56 CORE ASSY BP LOC ID ID J02 40R BP944 002 45R BP951 L03 60R BP969 K03 55R BP966 H03 16R BP916 F03 41R EP957 E03 39R SP968 L04 27R EP954 J04 19R BP938 G04 05R BP933 E04 32R BP963 N05 58R BP970 M05 24R BP961 K05 11R BP942 F05 18R BP929 D05 08R 8P965 C05 51R 3P974 N06 37R BP958 L06 01R BP930 J06 20R IP923 I

I

Figure 1.3 SURRY UNIT 2 - CYCLE 18 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R

P N

M MD MD**

MD MD MD L

K J

H G

MD M4D MD MD MD^

MD MD MD MD**

MD MD MD

,MD" MD MD MD MD IMD*

MD MD MD F

E D

C B

A MD MD MD MD MD MD MID MD M~D MD MD MD MD MD**

MD MD MD MD

-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 rD^A*

1 2

3 4

5 6

7 8

9 10 11 12 13 14 15 DMD

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 40351 45.271 MEASURED!

1 144.77 40.84 44.77 1PREDICTED 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!

0.001 0.001 23.521 0.001 23.511 22.501 23.541 0.001 23.631 0.00!

0.00! 45.261

,45.69 0.00 0.00! 23.35 0.00o 23.28 22.56! 23.28 0.00 23.35 0.00j 0.oo0 45.69!

6 40.561 0.00 17.941 0.001 23.541 0.001 21.57!

0.001 23.601 0.001 17.76!

0.00 40.07 6

I 40.471 0.001 17.871 0.001 23.38 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 0.00! 23.591 0.00 17.07I 0.00! 44.41!

144.81 0.00 17.13 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!

0.00!

23. 571 0.0 18.81 0.001 14351 9

44.8!* 0.00 17.13 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 10 40.47 0.00 17.87 0.00 23.38 0.00 21.4 0.00 23.38 0.00! 17.87 0.00 40.47 11 41 0.00 1

0.00! 23.39 0.001 23.23! 22.76! 22.85 0.00! 23.53!

0.00!

0.001 45.741 11 45.69 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 1

45.74! 40.49 0.00! 22.08 0.00! 40.49! 45.7414 15 44.39 40.30 45.06!

15 44.77 40.84 44.77 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 R

P N

M L

K J

H G

F E

D C

B A

C SB A

B SA D

SA A

B SB C

Absorber Material: Ag-In-Cd Function N

Control Bank D Control Bank C Control Bank B Control Bank A Shutdown Bank SB Shutdown Bank SA A

D SA B

D C

SB C

SB D

C B

SA A

D umber of Clusters 8

8 8

8 8

8 Page 14 of 56 NE-1326 S2C 18 Startup Physics Tests Report SA SB SB SA SA SA A

B SB D

C D

SB B

A I

A D

A C

B B

C 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15

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

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.

NE-1326 S2C18 Startup Physics Tests Report 1.29 sec.

-j I

I 1.29 sec.

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

11.29 4

I 4

F 1.28 1.28 1.27 1.31 1.29

-?

I t-I 4

4-1.33 11.28 I

I F

4 1.29

[*-j

> Rod drop time to dashpot entry (sec.)

1.30 1 1.28 1.29 1.30 1.27 1.27 1.29 1.27 i.31 1 29E 1.29 1.29 1 1_

1.27 1.912

.81,33 1.29 130 NE-1326 S2C 18 Startup Physics Tests Report 1.26 1-29 1.27 1.26 1.27 1.30 f---I F

4--I

.4

.5.

L 1.26 130 1.27 1.30 1.25 1.26 1.30 1.27 1

1-----+

F 2

3 4

5 6

7 8

9 10 11 12 13 14 15 I

1.27 1.31 1.30 1..27 1.26 1.27 1.26 1.30 1.27 1.30 1.30 1.39 1 _28 1 "*

1.29 1.29 1.28 1.33 1.29 I _30 1.27 1.30 1.25 1.26 1.30 1.27 Page 19 of 56 7 F-

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 -t 10% 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 plotted together in order to illustrate their agreement. In summary, the measured rod worth values 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

BANK B-Reference Bank D

C A

SB SA

,Total Worth MEASURED WORTH 1415.9 1005.1 740.0 209.6 1081.6 1016.7 5468.7 PREDICTED WORTH (PCM) 1433.0 1049.3 803.4 208.2 1140.1 1000.3 5634.2 5634.2

-2.9 PERCENT DIFFERENCE (%)

(M-P)/P X 100

-1.2

-4.2

-7.0

+0.7*

-5.1

+1.6

-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

S800 z

4 600 Z

400 200 0

50 100 150 200 250 BANK POSITION (STEPS)

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

  • -Predicted7

-U--Measured 0

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

0 n

uJ 2

0*

0 50 100 150 200 BANK POSITION (STEPS)

NE-1326 $2C 18 Startup Physics Tests Report

-- l-Predicted Measured 250 Page 25 of 56

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

Page 26 of 56 NE-1326 $2C 18 Startup Physics Tests Report

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 I

I

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

SUMMARY

  • 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.

Page 28 of 56 NE-1326 $2C18 Startup Physics Tests Report Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm)

(ppm)

(ppm)

ARO 2114 2087 27 B Bank In 1918 1904*

14

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 The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) 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 3.19'F and RCS heatup of 3.26TF.

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/fF. The moderator temperature coefficient was determined to be 1.171 pcmP/F which met the requirements of COLR Section 2.1.1.

In summary, the measured results were 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 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 18.

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 Dominion 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 25% 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 67% and 100% power, respectively, with different control rod configurations. These flux maps were taken to check at power design predictions and to measure core power distributions at various operating conditions.

The radial power distributions for these maps are given in Figures 6.2 and 6.3. The radial power 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).

"**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% 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 12 0.331. 0.653.

6 1.350.

1.351 1.348. 1.369.

1.277.

0.649 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.

5 0.280.

1.065

. 1.253.

1.256.

1.304

. 1.279

. 1.276 1.282. 1.317. 1.272

. 1.251 1.064 0.273 5

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 G

0.230.

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 ; ' ' ii i i~ ~ i 1 i i.........

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.

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

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

Reference ii Test Conditions (Design)

II1 Test Conditions (Actual)

IV Test.

Results.

  • 1 Test

Description:

Reactivity Computer unecKout Proc No / Section:

2 Bank Positions (Steps)

-NPT-RX-008 SDA:

230 SDB:

230 CA:

230 CB:

230 CC:

CD:

Bank Positions (Steps)

SDA:

230 SDB:

230 CA:

230 CB:

230 CC:

CD:

Date/Time Test Performed:

I.,/S,;

,3 O-

  • 2 Sequence Step No:

RCS Temperature (OF): 547 Power Level (% F.P.): 0 Other (specify):

Below Nuclear Heating RCS Temperature (OF):

/

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

Below Nuclear Heating

"/""7 L..-

Measured Parameter Pc= Measured Reactivity using p-computer (Description)

Pi= Predicted Reactivity 3 *,-/o-Measured Value.P=

f

%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 Sequence Step No:

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

Page 42 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:

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

"(Design Conditions)

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 STARTUP PHYSICS TEST-RESULTS AND EVALUATION SHEET I

Test

Description:

Isothermal Temperature Coefficient - ARO Reference Proc No / Section:

2-NPT-RX-008 Sequence Step No:

iI Bank Po'sitions (Steps)

RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA:

239 SDB:

230 CA:

230 Other (specify):

(Design)

CB:

230 CC:

2.30.

CD:

230 Below Nuclear Heating III Bank Positions (Steps)

RCS Temperature (OF): 6'13 -

'F Test

.Power Level (% F.P.): 0 Conditions SDA:

230 SDB:

230 CA:

230 Other (specify):

(Actual)

CB:

230 CC:

230 CD: ;OW**'

Below Nuclear Heating 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 +

(Actual Conditions)

(T o)o= -

_-3.0 pcm/)F.

(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 V-FSARPCOLR aT 0: 3.82

  • pcrll OF Acceptance aoP = -1.68 pcm/F Criteria

. Reference COLR 2.1.1,Technical Report NE-1323, Rev. 0 Design Tolerance is me 7 V YES

  • NO Acceptance Criteria Is met.

"-7YES N

Vl Comments *Uncertainty on caTmw = 0.5Spcrn/°F (

Reference:

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

Prepared By: "c "Y

4-Reviewed By:.

l_

/

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

SURRY POWER-STATION UNIT 2 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Reference Test Conditions (Design)

III Test Conditi6ns (Actual)

IV Test Results V

Acceptance Criteria Test

Description:

Control Bank B Worth Measurement, Rod Swap Ref. Bank Squnc Aite Li'~

Proc No I Section:

2-NPT-RX-008 Bank Positions (Steps)

Sequence (Step NO:

ýRCS Temperatr (F:57 Power Level (% F.P.): 0 SDA:

23&. SDB:

230 CA:

230

-Other (specify):

CB: moving. CC:

230 CD:

230.

Bank Positions (Steps)

Below Nuclear Heating RCS Temperature (OF):-5t/-7 Power Level (% F.P.): 0 SDA:

230 SDB: 230 CA:

230 Other (specify):

CB: moving CC:

230 CD:

230 Date/Time Test Performed:

Measured Parameter 3elow Nucdear r-l-atlng 13REF; Integral Worth Of Control Bank B, (Description)

All Other Rods Out Measured Value Design Value (Design Conditions)

Reference FSARJTech Spec Reference Design Tolerance Is met SREF_

I

/

=

lB.'.

.)4 /.

c IBIEF-1433 143 pcm "Technical Report NE-1323. Rev. 0 And Engineering Transmittal NAF 2002-0038, Rev. 0 If Design Tolerance is exceeded. SNSOC shall evaluate impact of test result on safety analysis.

SNSOC may specify that additional testing be performed.

VEP-FRD-36A V

YES.

NO Acceptance Criteria Is met :

V Tr*0 Vl Comments Prepared By:

Reviewed By:,

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

{

-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.

Reviewed By;:2(*

Z$

-- 7 NE-1326 S2C18 Startup Physics Tests Report 11AV-1P Page 46 of 56

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

'Reference ITest

Description:

HZP Boron Worth Coefficient Measurement Proc No / Section:

2-NPT-RX-008 Sequence Step No:

II Test Conditions (Design)

Ill "lest Conditi6ns (Actual)

Bank Positions (Steps)

SDA:

230D SDB:

230 CA:

230 CB: moving CC:

230 CD:

230 Bank Positions (Steps)

A Date/Time Test Performed:

Q4 -11 /0

-Z 1/3.zI RCS Temperature (°F): 547 Power Level (% F.P.): 0 Other (specify):

Below Nuclear Heating RCS Temperature (OF': 5-4-,

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

Below Nuclear Heating Measured Parameter aC-;

Boron Worth Coefficient (Description)

Mea[ured Value-ac, 7

cm/pPm Design Value aC8 =

-6.82 _ 0.68 pcm/ppm (Design Conditions) r~eference Technical Report

,1

'02' Qlr n r-SAW I ech Spec Not Applicable Reference jNot Applicable Design Tolerance is met V YES NO Acceptance Criteria is met :

v1 YES 7 NO Reviewed By:

\\

NE-1326 S2C18 Startup Physics Tests Report IV Test Results V

cceptance Criteria I SDA:

230 SDB:

230 CA:

230 CB: moving CC:

230 CD:

230 Vi omments Prepared By":

I A

Page 47 of 56 I

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

. II Reference II Test Conditions (Design)

IIl Test Conditions (Actual)

Test

Description:

Control Bank A Worth Measurement, Rod Swap Proc No / Section:

2-NPT-RX-008 Sequence Step No:

Bank Positions (Steps)

R RCS Temperature (OF):.547 Power Level (% F.P.): 0 SDA:

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

LJM Y I uk

  • ?A n

W nir SCB: moving'"CC:- ý*

23 G:

.:,40.

Bank Positions (Steps)

SDA:

230 SDB:

230 CA: moving CB: movlng6 CC:

230 Cb:

230 Daterrime Test Performed:

Q 0

Measured Parameter RCS Temperature (OF):

1-/7 power Level (% F.P.): 0 Other (specify):

Below Nuc.ear Heating IARS; Integral Worth of Control Bank A, (Description)

Rod Swap IV

-Test.

Results V

Acceptance Criteria VI Comments Measured Value Design Value (Actual Conditions)

Design Value (Design Conditions)

Reference FSARITech Spec A

RS_

(Adjusted Measured Critical Referience Bank Position to. steps)

IARS

?ORiZ.

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

I ARS= 210 +/- 100 pcm (Critical Reference Bank Position = 60 steps)

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

SNSOC may specify that additional testing ebe performed.

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

  • YES NO Prepared By:7Tff NE-1326 S2C18 Startup Physics Tests Report Reviewed BY:

Page 48 of 56 I I

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 Nuclear Heating

,=,"=*,*".-"* -r......

LUI I,,,

F0,-.\\ b ', f 7

III Test Conditions (Actual)

IV Test Results V"

Acceptance Criteria Bank Positions (Steps)

SDA:

230 SDB: 230 CB: moving CC: moving CA:

230 CD:

230 Date/Time Test Performed:

.1" g

'/ v I Q:1 IK, lemperiature t rl. -, 4y '-7 Power Level (% F.P.): 0 Other (specify):

Below Nuclear Heating Measured Parameter lo; Integral Worth of Control Bank C, (Description)

Rod Swap Measured Value CRS=

7 q (Adjusted Measured Critical Reference Bank Position = Jlii".1 -. steps)

Design Value 0(d e

a (ActualConditions)

Ic RS=

(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 evaluate impact of test result on safety analysis.

SNSOC may specify that additional testing be performed.

Reference Vi Comments' Design Tolerance is met Acceptance Criteria is met" VEP-F*RD-36iA

_YES NO V YES NO 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

/

eference I

SURRY POWER STATION UNIT 2 CYCLE 18 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 B

sequence Step No:

Il Bank Positions (Steps)

R*S Temperature (OF): 5147 Test Power Level (% F.P.): 0 Conditions SDA: moving SDB:

230 CA:

230 Other (specify):

(Design)

CB: moving CC:

230 CD:

230 Below Nuclear Heating III Bank Positions (Steps)

P rCS Temperature (fF): 6'z"7 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!

IV Test Results V

Acceptance Criteria

+

Measured Parameter (Description)

Measured Value Design Value (Actual Conditions)

De~sign Value (Desian Conditions)

ISR; IntegralWorth of Shutdown Bank A, Rod Swap RS=.

(Adjusted Measured Critical Reference Bank Position I.6' steps)

I RS 000 'R (Adjusted Measured Critical Reference Bank Position =

5

?' steps)

IsAR= 1000 150 pcm S(Critical Reference Bank Position = 157 steps)

Reference.

Engineering Transmittal NAF 2002-0038, Rev. ;0 VEP-FRD-36A FSAPjTech Spec If Design Tolerance Is exceeded, SNSOC shall evaluate Impact of test result on safety analysis..

SNSOC may specify that additional testing be performed.

Reference IVEP-FRD-36A Design Tolerance is met YES NO Acceptance Criteria is met:.

/ YES NO Vl Comments Prepared By:

A1 Reviewed 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 If Design 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. (/} //

NE-1326 S2C18 Startup Physics Tests Report

. /

l J

I Jw

.11-y 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: ! 91.

R (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 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 t

3 A

Prepared By: !LA 1L91 Reviewed By:

I I

D/V NE-1326 S2C18 Startup Physics Tests Report jr/'-01 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 lest Performed:

0 /.z 0/V 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 If Design 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 VI CommentsI Design Tolerance is met Acceptance Criteria is met Prepared By:

v-YES YES NO NO Reviewed By:__

/

I V

NE-1326 S2C18 Startup Physics Tests Report 0

Page 53 of 56 I

SURRY POWER STATION UNIT 2 CYCLE 18 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:.

!1 Bank Positions (Steps)

ROS Temperature (0 F): TREF I

1 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 Val

+/-e

+/-15% for Pi

)

"".9 7 (Design

++/-151Y6%for P1<0.9 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 I

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:

nLC.O_'

WL

  • 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 Test Conditions (Actual)

IV Test Results V

Acceptance Criteria- -

Bank Positions (Steps)

SDA:

230 SDB:

CB: -230 CC:

230 CA:

230 230 CD: i "-

Date/rime Test Performed:

RCS Temperature (iF):

c oc Power Level (% F.P.): ( (.

Other (specify):

11

v.

Maximum Reiative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive Incore Parameter Power %DIFF Channel Factor Channel Quadrant (Description)

(M-P)/P FAH(N)

Factor F0(Z)

Power Tilt Measured

-4.1k P O"

-'I Value; A

e_, o.9/.

(.

Design Value (Design Conditions)

Reference FSARICOLR Feference

+/-10% for P, >0.9

+/-15% for Pj<0.9 (PI = assy power)

WCAP-7905, Rev. 1 NE-1323, Rev. 0 None N/A None r

I 4.

None FAH(N)Wl.56(1+0.3(1-P))

COLR 2.4 N/A None Fa(Z)2.32/PK(Z)

COLR 2.3 I

Design Tolerance is met Acceptance Criteria is met :

V YES

__YES

< 1.0203 WCAP-7905,Rev.1 NE-1323, Rev. 0 None None NL)

NO___

VI Comments

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

L Prepared By: /1 %-&Q Y4//3/-

Reviewed By: e,"

V-V*

NE-1326 S2C18 Startup Physics Tests Report i

Page 55 of 56 Ll.ý _rA 1-11, Lle_ý

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 Test Conditions (Actual)

IV Test Results Bank Positions (Steps)

SDA:

CB:

230 SDB:

230 CA:

230 CC:

230 CD:

Date/Time Test Performed:

-/ 41*,

A7N*

.0*C-)o 230 Rkao RCS Temperature (OF):

Power Level (% F.P.):

Other (specify):

Maximum Relatlve Nuclear Etithalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive Incore Parameter Power %DIFF Channel Factor Channel Quadrant (Description)

(M-P)/P FAH(N),

Factor F0 (Z)

Power Tilt Measured

-3.6 ".'

0 0-:L--

va*.ei 3-.

0

./..*

) /

.o 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 NE-1323, Rev. 0 None None

'WCAP.7,05.Rev.1 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 y

Reviewed Bý'

NE-1326 S2C18 Startup Physics Tests Report

-. o ;

  • ° Page 56 of 56 I

m

Retrieved from "https://kanterella.com/w/index.php?title=ML022060509&oldid=5436031"