ML11306A024

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Cycle 24 Startup Physics Tests Report
ML11306A024
Person / Time
Site: Surry Dominion icon.png
Issue date: 02/14/2011
From: Funderburk C
Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:
Region 2 Administrator
References
11-087
Download: ML11306A024 (48)
v • d • e


Text

ý#Domi nion' Dominion Resources Services, Inc.

Innsbrook 1Iechnical (,:enter 5000 Dominion BoulevIard, 2SE, Glen Allen, VA 23060 February 14, 2011 United States Nuclear Regulatory Commission lal No.:

Regional Administrator - Region II LOS/GDM Marquis One Tower Docket No.:

245 Peachtree Center Ave., NE Suite 1200 License No.:

Atlanta, Georgia 30303-1257 11-087 RO 50-280 DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 CYCLE 24 STARTUP PHYSICS TESTS REPORT As required by Surry Technical Specification 6.6.A.1, enclosed is the Virginia Electric and Power Company (Dominion) Surry Unit 1 Cycle 24 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed following initial criticality of Cycle 24 on December 1, 2010. The results of the physics tests were within the applicable Technical Specification limits.

If you have any questions or require Mr. Gary Miller at (804) 273-2771.

Sincerely, C. L. Funde urk, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None additional information, please contact C(Lr I)Uký

~N

Serial No.11-087 S1C24 Startup Physics Tests Report, Rev. 0 Page 2 of 2 cc:

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J. S. Wiebe NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Resident Inspector Surry Power Station

Serial No.11-087 Docket No. 50-280 Attachment SURRY UNIT 1 CYCLE 24 STARTUP PHYSICS TESTS REPORT February 2011 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit 1 Page 1 of 46

Serial No.11-087 Docket No. 50-280 Attachment 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.

Page 2 of 46

Serial No.11-087 Docket No. 50-280 Attachment TABLE OF CONTENTS Classification/Disclaimer.......................................................................................................

2 Table of Contents...........................................................................................................................

3 List of Tables..................................................................................................................................

4 List of Figures.................................................................................................................................

5 Preface..............................................................................................................................................

6 Section 1 -

Introduction and Summary...............................................................................

7 Section 2 -

Control Rod Drop Time M easurements...........................................................

15 Section 3 -

Control Rod Bank W orth M easurements......................................................

20 Section 4 -

Boron Endpoint and W orth M easurements....................................................

25 Section 5 -

Temperature Coefficient M easurement.........................................................

28 Section 6 -

Power Distribution M easurements.................................................................

30 Section 7 -

Conclusions........................................................................................................

37 Section 8 -

References...............................................................................................................

39 Appendix -

Startup Physics Test Summary Sheets...........................................................

40 Page 3 of 46

Serial No.11-087 Docket No. 50-280 Attachment LIST OF TABLES Table 1.1 - Chronology of Tests...........................................................................................

10 Table 2.1 - Hot Rod Drop Time Summary........................................................................

16 Table 3.1 - Control Rod Bank Worth Summary................................................................

22 Table 4.1 - Boron Endpoints Summary...............................................................................

26 Table 4.2 - Boron Worth Coefficient....................................................................................

27 Table 5.1 - Isothermal Temperature Coefficient Summary.............................................

29 Table 6.1 - Incore Flux Map Summary................................................................................

32 Table 6.2 - Comparison of Measured Power Distribution Parameters with their Core Operating Limits...............................................................................................

33 Table 7.1 - Startup Physics Testing Results Summary.......................................................

38 Page 4 of 46

Serial No.11-087 Docket No. 50-280 Attachment LIST OF FIGURES Figure 1.1 - Core Loading Map.............................................................................................

11 Figure 1.2 - Beginning of Cycle Fuel Assembly Burnups (GWD/MTU)...........................

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

13 Figure 1.4 - Control Rod Locations......................................................................................

14 Figure 2.1 - Typical Rod Drop Trace........................................................................................

17 Figure 2.2 :- Rod Drop Time - Hot Full Flow Conditions....................................................

18 Firgure 2.3 - Rod Drop Times Trending.................................................................................

19 Figure 3.1 - Control Bank B Integral Rod Worth - HZP....................................................

23 Figure 3.2 - Control Bank B Differential Rod Worth - HZP.............................................

24 Figure 6.1 - Assemblywise Power Distribution 28.57% Power.........................................

34 Figure 6.2 - Assemblywise Power Distribution 63.75% Power..........................................

35 Figure 6.3 - Assemblywise Power Distribution 99.90% Power.........................................

36 Page 5 of 46

Serial No.11-087 Docket No. 50-280 Attachment PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 1, Cycle 24 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 Surry Power Station.

Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.

The Surry Unit 1, Cycle 24 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 results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer/ reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations performed by Dominion's Nuclear Analysis and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits.

Page 6 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION I -

INTRODUCTION AND

SUMMARY

On October 24, 2010, Unit No. 1 of Surry Power Station completed Cycle 23 and began refueling [Ref. 1]. During this refueling, 64 of the 157 fuel assemblies in the core were replaced with 64 fresh Batch S1/26 assemblies [Ref. 8]. The Cycle 24 core consists of 10 sub-batches of fuel: four fresh batches (S1/26A, Sl/26B, S1/26C, and S1/26D), four once-burned batches (S1/25A, S1/25B, S1/25C, and S1/25D), and two twice-burned batches (S1/24C, S1/24D). All batches are of the SIF/P+Z2 fuel type [Ref. 1].

The Westinghouse SIF/P+Z2 fuel assembly design incorporates ZIRLO fuel cladding, intermediate grids, guide tubes, instrumentation tubes,.and debris resistance features that are part of the Westinghouse PERFORMANCE+ design. SIF/P+Z2 assemblies use a slightly longer fuel pin and bottom end plug to enhance resistance to fretting wear [Ref. 1].

This, cycle uses only Westinghouse's Integral Fuel Burnable Absorber (IFBA) fuel product. The IFBA design involves the application of a thin (0.0003125 inch) coating of ZrB 2 on the fuel pellet surface during fabrication. Pellets with the IFBA coating are placed in specific symmetric patterns in each fresh assembly, typically affecting from 16 to 148 rods per assembly.

The top and bottom 6 inches of the fuel pellet stack in the IFBA rods will contain pellets that have no IFBA coating, and have a hole in the center (annular). This additional void space helps accommodate the helium gas that accumulates from neutron absorption in ZrB2. IFBA rods generate more internal gas during operation because neutron absorption in the ZrB2 coating creates helium gas in addition to the fission gas created during irradiation of the fuel. Therefore, the initial pressure is set lower so the internal pressure early in lifetime may be lower [Ref. 5].

Note that there are no thimble plugging devices or secondary sources inserted in Surry Unit 1 for this cycle. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 24 core.

Page 7 of 46

Serial No.11-087 Docket No. 50-280 Attachment The Si C24 full core loading plan [Ref. 8 and Ref. 11 ] is given in Figure 1.1 and the beginning of cycle fuel assembly burnups [Ref. 6] are given in Figure 1.2. The available incore moveable detector locations used for the flux map analyses [Ref. 7] are identified in Figure 1.3.

Figure 1.4 identifies the location and number of control rods in the Cycle 24 core [Ref. 1].

According to the Startup Physics logs, the Cycle 24 core achieved initial criticality on December 1, 2010 at 05:55 [Ref. 14]. Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. This cycle used the FTI Reactivity Measurement and Analysis System (RMAS) to perform startup physics testing. Note that RMAS v.6 [Ref. 9] was used for S 1 C24 Startup Physics Testing. The tests performed are the same as in previous cycles.

A summary of the test results follows.

The measured drop time of each control rod was within the 2.4 second Technical Specification [Ref. 4] limit, as well as the Surry Unit 1 1.93 second administrative limit

[Ref. 10].

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

For the purpose of this test, a bank was defined as 'fully inserted' when it was 2 steps off the bottom of the core [Ref. 13]. The sum of the individual measured control rod bank worths was within -2.5% of the design prediction. The reference bank (Control Bank B) worth was within

-2.5% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within +3.0% of the design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category),the difference was within -1.8 pcm of the design prediction.

These results are within the design tolerances of + 15% for individual banks worth more than 600 pcm (+ 10% for the reference bank worth), +/- 100 pcm for individual banks worth 600 pcm or less, and + 10% for the sum of the individual control rod bank worths.

Measured critical boron concentrations for two control bank configurations, ARO and B-bank in, were within the design tolerances and the Technical Specification criterion [Ref. 4] that the overall core reactivity balance shall be within + 1% Ak/k of the design prediction. The boron Page 8 of 46

Serial No.11-087 Docket No. 50-280 Attachment worth coefficient measurement was within +1.9% 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 +0.217 pcm/°F of the design prediction. This result is within the design tolerance of +2.0 pcm/°F.

Core power distributions were within established design tolerances.

The measured assembly power distributions were within +5.4% of the design predictions, where a +5.4%

maximum difference occurred in the 28.57% power map in assembly D3. The heat flux hot channel factors, FQ(Z), and enthalpy rise hot channel factors, FAH, were within the limits of the COLR [Ref. 8].

All power flux maps were within the maximum incore power tilt design tolerance of 2% (QPTR < 1.02).

The total RCS Flow was successfully verified as being greater than 273000 gpm and greater than the limit in the COLR (276000 gpm), as required by Surry Technical Specifications

[Ref. 4]. The total RCS Flow was measured as 285675 gpm.

In summary, all startup physics test results were acceptable. Detailed results, specific design tolerances and acceptance criteria for each measurement are presented in the following sections of this report.

Page 9 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 1.1 SURRY UNIT 1 - CYCLE 24 CHRONOLOGY OF TESTS I

I

ýReference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow Reactivity Computer Checkout Boron Endpoint - ARO Zero Power Testing Range Boron Worth Coefficient Temperature Coefficient - ARO Bank B Worth Boron Endpoint - B in Bank A Worth - Rod Swap Bank SA Worth - Rod Swap Bank C Worth - Rod Swap Bank D Worth - Rod Swap Bank SB Worth - Rod Swap Total Rod Worth Flux Map - less than 30% Power Peaking Factor Verification

& Power Range Calibration Flux Map - 65% - 75% Power Peaking Factor Verification

& Power Range Calibration Flux Map - 95% - 100% Power Peaking Factor Verification

& Power Range Calibration RCS Flow Measurement 11/28/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/01/10 12/02/10 12/03/10 12/13/10 12/07/10 1649 0650 0650 0650 1143 0737 0832 1143 1102 1102 1102 1102 1102 1102 1633 0939 1215 1100 HSD HZP HZP HZP HZP HZP HZP HZP HZP HZP HZP HZP HZP HZP 1-NPT-RX-014 1 -NPT-RX-008 1-NPT-RX-008 1 -NPT-RX-008 1 -NPT-RX-008 1-NPT-RX-008 1-NPT-RX-008 1 -NPT-RX-008 1-NPT-RX-008 1 -NPT-RX-008 1 -NPT-RX-008 1-NPT-RX-008 1 -NPT-RX-008 1-NPT-RX-008 1 -NPT-RX-002 1 -NPT-RX-008 1 -NPT-RX-005 1-NPT-RX-002 1-NPT-RX-008 1 -NPT-RX-005 1 -NPT-RX-002 1 -NPT-RX-008 1 -NPT-RX-005 1 -NPT-RX-009 28.57%

63.75%

99.90%

HFP Page 10 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 1.1 SURRY UNIT 1 - CYCLE 24 CORE LOADING MAP SURRY UNIT I - CYCLE 24 FULL CORE LOADING PLAN REVISION NO.

0 VEP-NES-NAF ORTH A

B C

D K

F~

6 157,7 H

.7 K

PACF I of I

4 N

P R

i5 186 60.1 18K 601 270' R'C RCC RCC 41J 341 020 061 022 33J 44J RCC 6CC 461 054 041 045 13K 051 046 055 473 6CC We 6CC6CC 261 036 030 51K 59K 21K 56K 49K 029 033 24J RCC RCC 391 060 028 02K 32K 003 14K 001 31K 03K 032 053 421 RCC RCC RCC OCC RCC R4C WIC 29J 031 46K 35K 016 45K 20K 44K 015 36K 53K 039 353 R6C RCC ReC BeC 551 023 047 55K 001 41K 009 IlK 01l 43K 004 60K 044 024 51 R6CC RCC BCC RCC 21K 064 07K 28K 05K 24K 06K 25K 16K 22K 09K 26K 08K 063 17K BCC RCC 4CC 6?C 58.1 019 042 58K 006 426 010 12K 012 39K 008 61K 040 018 49J 6CC RCC RCC WeC RCC PrC RCC 36J 048 52K 34K 014 39K 21K 40K 013 30K 48K 050 31J 6CC RCC 403 057 031 01K 37K 005 15K 002 33K 04K 02"1 058 37J BeC 6CC BCC R(-'

23J 034 026 50K 54K 29K 51K 41K 025 035 281 C3rIPT[OS:

R4CC BCC CONTROL ROL) 483 059 043 049 10K 052 038 056 45J 6CC RCC RCC 38.1 323 021 062 017 303 431 14 13 12 10 9

8 INCOWE DEVICE I RCC FULL LENWH 54J I 19K I 50.

Is0 Prepared B3y: e,

.ae; %U/~ 10 6evie.vd By:

ae

/

Approved By Wt:4z b Approved By: ____________

Dae ______1__

Page 11 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 1.2 SURRY UNIT 1 - CYCLE 24 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWD/MTU)

R P

N M

L K

J H

G F

E D

C B

A 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 14 1 41.251 I 41.241 40.451 1 40.501 44.291 0.001 44.581 0.001 1 44.421 24.961 44.621 1 44.681 24.551 44.561 I 41.331 40.301 0.001 0.001 0.001 40.481 41.231 1 41.261 40.321 0.001 0.001 0.001 40.461 41.221 1 42.171 0.001 o.001 0.001 24.591 0.001 0.001 0.001 I 41.641 0.001 0.001 0.001 24.461 0.001 0.001 0.001 2.731 0.001 0.001 20.061 25.011 24.281 25.151 20.031 0.001 2.401 0.001 0.001 19.931 25.121 24.261 25.231 19.921 0.001 0.001 0.001 20.911 23.391 0.001 24.511 0.001 23.411 20.421 o.001 0.001 20.521 23.241 0.001 24.481 0.001 23.261 20.521 0.001 20.351 23.211 0.001 20.571 24.471 20.221 0.001 23.761 0.001 19.981 23.311 0.001 20.251 24.551 20.201 0.001 23.311 0.O0j 25.151 0.001 20.071 0.001 20.511 0.001 20.101 0.001 0.001 25.231 0.001 20.71 0.001 20.381 0.001 20.081 0.001 MEASURED I PREDICTED 41.271 41.641 0.001 42.001 0.001 42.371 0.001 0.001 41.051 0.001 0.001 41.271 19-87l 0

-001 40.261 19.981 0.001 40.361 25.031 0.001 0.001 44.461 25.161 0.001 0.001 44.591 24.52 24.52 44.09 44.59 1 0.001 24.551 24.351 24.461 24.701 20.391 24.371 20.241 24.811 24.521 24.221 24.751 0.001 24.791 1 0.001 24.521 24.271 24.521 24.541 20.251 24.331 20.251 24.541 24.521 24.271 24.521 0.001 24.521 91 0.001 0.001 25.131 0.001 20.571 0.001 20.391 0.001 20.121 0.001 25.311 0.001 0.001 44.311 1 0.001 0.001 25.161 0.001 20.085 0.001 20.381 0.001 20.111 0.001 25.23j 0.001 0.001 44.381 1 40.181 0.001 19.981 23.411 0.001 20.141 24.471 20.251 0.001 23.281 20.201 0.001 40.751 140.361 0.001 19.981 23.311 0.001 20.201 24.551 20.251 0.001 23.311 19.981 0.001 40.501 1 41.071 0.001 0.001 20.581 23.281 0.001 24.561 0.001 23.481 20.731 0.001 0.001 41.281 141.271 0.001 0.001 20.521 23.261 0.001 24.481 0.001 23.241 20.521 0.001 0.001 41.23j 1 42.111 0.001 0.001 20.021 25.101 24.491 24.991 20.251 0.001 0.001 42.491 1 42.371 0.001 0.00o 19.921 25.231 24.261 25.121 19.931 0.001 0.001 42.401 1 41.361 0.001 0.001 0.001 24.501 0.001 0.001 0.001 42.181 1 41.641 0.001 0.001 0.001 24.461 0.001 0.001 0.001 41.641 1 41.101 40.621 0.001 0.001 0.001 40.281 41.511 1 41.221 40.461 0.001 0.001 0.001 40.321 41.261 1 44.541 24.911 44.351 1 44.561 24.551 44.681 4

5 6

7 8

9 10 11 12 13 14 15 Page 12 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 1.3 SURRY UNIT 1 - CYCLE 24 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R

P N

M L

K J

H G

F E

D C

B A

I MD t

-t

+

I MD 2

3 MD MD MD MD MD MD

+

MD 4

MD MD MDI MDI

[MD II I

M D M D IMD A

MD MD MD A

MD MD MD MD MD MD MD MD MD MD MD A

MD MD MD MD 5

6 7

8 9

A MD MD MD MD MDI MD MD

[MD MD MD MD MD MD MD MD

-+

4 t-4-+

4 10 11 12 13 14 15

+

MD MD A

MD MD MD, MD - Moveable Detector

+ - Locations Not Used For Flux Map 1, 2, or 3

- While data was obtained for this thimble for flux map 1, it was not used in the analysis (was deleted by the CECOR code package).

A - Locations Not Used For Flux Map 3 Page 13 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 1.4 SURRY UNIT 1 - CYCLE 24 CONTROL ROD LOCATIONS R

P N

M L

K J

H G

F E

D C

B A

1800 1

4 4

4 4

A D

A A

A 4

4 4

4

.4-4 4

4 SA SA 4

4 4

4 4

4-4 4

4 4

C B

B C

2 3

4 5

6

-4 4

4 4

4 4

4-4 4

4 4

4 SB SB SB SB

-4 4

4 4

4 4

4-4 4

4 4

4 A

B D

C D

B A

900 SA SB SB SA D

C C

D SA SB SB SA 7

2700 8

9 A

B D

C D

B A

_ [

_ [SB j j_ j j

j SB] j

_1 ]

C B

B C

4 4

4 4

4 4--4 4

4 4

10 11 12 13 14 15 SA SA SA SA 4

4 4

4 4

4 4

4 A

D A

SB4 SB 00 D = Control Bank D C = Control Bank C B = Control Bank B A = Control Bank A SB = Shutdown Bank SB SA = Shutdown Bank SA Page 14 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION 2 -

CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured in hot shutdown with three reactor coolant pumps in operation (full flow) and with Tawe greater than 530 'F per 1-NPT-RX-014.

This verified that the time to entry of a rod into the dashpot region was less than or equal to the maximum allowed by Technical Specification 3.12.C. I [Ref. 4].

Surry Unit 1 Cycle 24 used the rod drop test computer (RDTC) in conjunction with the Computer Enhanced Rod Position Indication (CERPI) system. The CERPI system equipment replaced the Individual Rod Position Indication (IRPI) system.

The rod drop times were measured by withdrawing all banks to their fully withdrawn position and dropping all of the 48 control rods by opening the reactor trip breakers. This allowed the rods to drop into the core as they would during a plant trip.

The current methodology acquires data using the secondary RPI coil terminals (/3 & /4) on the CERPI racks for each rod. Data is immediately saved to the rod drop test computer (RDTC) which computes the rod drop time automatically. Original data is also saved as an ASCII file and burned to a CD-R. Further details about the RDTC can be found in [Ref. 12].

A typical rod drop trace for S I C24 is shown in Figure 2.1. The measured drop time for each control rod is recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Figure 2.3 shows slowest, fastest, and average drop times for Surry 1 cycles 17-24. Technical Specification 3.12.C.1 [Ref. 4] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. These test results satisfied this technical specification limit as well as the administrative limit [Ref. 10] of 1.93 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region.

Page 15 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 2.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME B-06, F-08, P-08 1.39 sec.

M-12 1.26 sec 1.30 sec.

Page 16 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 2.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE

/

Time Stamp Of R.Dbrop:

R d d

.Graph of J13 z -*

Path of A

}

Beginning of Toro qDashpot Entry (Extreme drop S

in Voltage) 1 Initiation of Rod Drop Event Mark i1-I

__~~~:1~hi i~fi I

/

iIl FH Hltl_

h1_

.m

\\I

_ I 1 17, 1_111ZIIA Bottom of Dashpot j

Bounce Indicating Rod is NOT Stuck I

ILl ~'FKKKII] EEIZP{IL~

1.

!\\

y

'I I

I I

i I

I I

I I

Time (5) Amphltde (V) aial hp~dRdDofm:L3$di~

TrIgge 0.00 03 J.I

~~~~~~~

ZZ~J0

~

~C~mao.~e 1.31 Seconids L

I Page 17 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 2.2 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R

P N

M L

K J

H G

F E

D C

B A

1 1.2 1.321 1.28 1.28 1.29 1.28 1.29 I

I I

I I

4 1.30 1.29 1.30 1.29 I

I I

I I

I I

1 4

4 1.27 1.28 1.29 1.33 1.27 1.3 3

2 3

4 5

6 7

8 9

1.27 1.27 1.28 1.29 1.30 1.28 1.39 1.30 1.31 1.30 1.31 1.39 1.31 1.39 1.31 1.31 1.28 1.33 1.29 1.29 1.29 1.28 1.30 1.33 1.30 1.31 1.29 1.28 1.33 1.30 1.31 I

I I

I I

I I

I 4

4 4

4 1.28 1.29 1.28 1.29

¶ 1

1 1

1

¶ 1

4 4

4 4

1.26 1.28 1.29 1.33 1.28 1.29 1.26 1.33 I

I 1

4 4

4 4

4 4

4 10 11 12 13 14 15 1.31 1.28 4

4 4

4 4

4 4

4 1.33 1.27 1.35 1.33 1.35 4

4 4

4

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

Page 18 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 2.3 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING Slowest Rod Time -- Fastest Rod Time Average Time 2.5 1

2.4 TechnicalSpecificatioh Limit 2.4 seconds 2.3 2.2 2.1 2

Administrative Limit 1.93 seconds 1.8 1.7 1.6 t

1.5

+

I 1.4 1.3 1.2 ____ ____------

1.2 1.1 17 18 19 20 21 22 23 24 Cycle Page 19 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION 3 -

CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique [Ref. 2]. The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 24, Control Bank B was used as the reference bank. Surry 1 targeted a dilution rate of 1100 pcm/hr for the reference bank measurement.

During the NIC19 startup physics testing campaign, a control rod became stuck on the bottom eventually forcing a reactor trip to fix the problem. A theorized potential cause of the stuck rod issue was the presence of debris near the upper core plate interfering with the rod grippers when the control rods were manually inserted to the fully inserted position of 0 steps withdrawn. A possible solution to this issue for startup physics testing was to avoid requiring control rods to be manually inserted to 0 steps. To accomplish this, an evaluation of the startup physics testing process was performed [Ref. 13], concluding that the definition of fully inserted for control rod positions used in startup physics testing could be changed from 0 steps withdrawn to a range of 0 to 2 steps withdrawn. The SI C24 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

After completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor near critical and the reference bank near its full insertion. Initial statepoint data (core reactivity and moderator temperature) for the rod swap maneuver were next obtained with the reference bank at its fully inserted position and all other banks fully withdrawn.

Test bank swaps proceed in sequential order from the bank with the smallest worth to the bank with the largest worth. The second test bank should have a predicted worth higher than the first bank in order to ensure the first bank will be moved fully out before the second bank is fully Page 20 of 46

Serial No.11-087 Docket No. 50-280 Attachment inserted. The rod swap maneuver was performed by withdrawing the previous test bank (or reference bank for the first maneuver) several steps and then inserting the next test bank to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the previous test bank was fully withdrawn and the current 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 near the initial statepoint condition. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank.

The core reactivity, moderator temperature, and differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver was repeated for all test banks. Note that after the final test bank was fully inserted, the test bank was swapped with the reference bank until the reference bank was fully inserted and the last test bank was fully withdrawn.

Here the final statepoint data for the rod swap maneuver was obtained (core reactivity and moderator temperature) in order to verify the reactivity drift was within procedural limitations 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 Summary Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance of + 10%- for the reference bank, + 15% for test banks of worth greater than 600 pcm, and + 100 pcm for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was within -2.5 % of the design prediction. This is well within the design tolerance of +10% for the sum of the individual control rod bank worths.

The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions [Ref. 1] and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were found to be satisfactory.

Page 21 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 3.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM)

(PCM)

(M-P)/P X 100 D

944.0 972.6

-2.9 B - Reference 1382.9 1418.0

-2.5 C

913.1 940.0

-2.9 A

234.4 236.2

-0.8*

SB 1065.5 1098.2

-3.0 SA 902.7 916.7

-1.5 Total Bank Worth 5442.7 5581.8

-2.5

  • Note: For Bank A, (M-P) = -1.8 pcm.

Page 22 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 3.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600 1400 1200 1000 a ~800 m

-4 JJi a 600 H - Measured

--E-Predicted 400 200 0

0 50 100 150 200 250 Bank Position (steps)

Page 23 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 3.2 SURRY UNIT I - CYCLE 24 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12.0 10.0 8.0 V

9 6.0 4.0 2.0 Measured

-U-- Predicted 0.0 0

50 100 150 Bank Position (steps) 200 250 Page 24 of 46

Serial No.11-087 Docket No. 50-280 Attachment 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, as necessary.

The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Summary 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 0.A [Ref. 4] regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

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

A summary of the measured and predicted DBW is shown in Table 4.2. As indicated in this table and in the Appendix, the measured DBW was well within the design tolerance of

+ 10%. In summary, the measured boron worth coefficient was satisfactory.

Page 25 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 4.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

(ppm)

(ppm)

ARO 1551 1586

-35 B Bank In 1370 1362*

+8

  • 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 Summary Sheet in the Appendix.

Page 26 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 4.2 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

(pcm/ppm)

(pcm/ppm)

(M-P)/P x 100

-7.64

-7.50

+1.9 Page 27 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION 5 -

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

Reactivity was measured during the RCS cool down of-3.35°F, followed by the RCS heat up of +3.16'F. Reactivity and temperature data were taken from the reactivity computer. Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature.

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 Summary Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of +2 pcm/PF. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -2.149 pcm! 'F, a predicted DTC of -1.81 pcm/ 'F, and a measurement uncertainty of +0.5 pcm/°F, is +0.161 pcm/°F. It thus satisfies the COLR criteria

[Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pcm/°F.

Page 28 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 5.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

BANK TEMPERATURE BORON ISOTHERMAL TEMPERATURE COEFFICIENT RANGE (°F)

(PCM/°F)

P O S IT IO N

..........*.=.:...*...L...............

C O N C E N T RA T IO N r...........*.-........

z.....-.....................................................

(STEPS)

LOWER UPPER HEAT-COOL-I AVG.

DIFFER LIMIT LIMIT (ppm)

UP DOWN MEAS PRED (M-P)

D/204 543.89 547.26 1543

-2.400

-1.898

-2.149

-2.366

+0.217

_ i Page 29 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION 6 -

POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the moveable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available, locations monitored by the moveable detectors for the ramp to full power flux maps for Cycle 24.

For each traverse, the detector voltage output is continuously monitored on a recorder, and scanned for 610 discrete axial points.

Full core, three-dimensional power distributions are determined from this data using a Dominion-modified version of the Combustion Engineering computer program, CECOR [Ref. 3, Ref. 15].

CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.

A list of the full-core flux maps [Ref. 7] taken during the startup test program and the measured values of the important power distribution parameters are given in Table 6.1.

A comparison of these measured values with their COLR limits is given in Table 6.2. Flux map 1 was taken at 28.57% 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 63.75% and 99.90% power, respectively, with different control rod configurations. These flux maps were taken to check at-power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3.

The radial power distributions for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured relative assembly power values deviated from the design predictions by at most

+5.4% in the 28.57% power map, +4.1% in the 63.75% power map, and +3.7% in the 99.90%

power map. The maximum average quadrant power tilts for the three power maps are +1.48 %

(1.0148), +1.01 % (1.0101), and +0.59% (1.0059), respectively. These power tilts are within the design tolerance of 2% (1.02).

Page 30 of 46

Serial No.11-087 Docket No. 50-280 Attachment The measured FQ(z) and FNH peaking factor values for the at-power flux maps were within the limits of the COLR [Ref. 8]. Flux Maps 1, 2, and 3 were used for power range detector calibration or to confirm existing calibrations.

In conclusion, the power distribution measurement results are considered acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR [Ref. 8].

It is therefore anticipated that the core will continue to operate safely throughout Cycle 24.

Page 31 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 6.1 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

BuM M Bank Peak FQ(Z) Hot Fne Hot (2)

Core Fz Core Tilt (3) Axial No.

Map M

Date up Power Channel Factor (1) Channel Factor Max Of Of Description No.

MWD/

(%)

Axial Axial Steps Assy o

QZ) Assy i

Fz Max Loc MTU Pot Point:

Low Power 1

12/02/10 2.8 28.57 169 E03 26 :2.201 D12 1.524 26 1.354 1.0148i NE +4.092 47 Int. Power (4) 2 12/03/10 12 63.75 191 N05 24 1.969 D12 1.480 26 1.237 1.0101: NE +3.486 48 Hot FullPower 3

12/13/10 345 99.90 229 D12 31 1.854 K04 :1.437 30 1.179 1.00590 NE +2.359 41 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). Flux Maps 1, 2, and 3 were used for power range detector calibration or were used to confirm existing calibrations.

(1) FQ(Z) includes a total uncertainty of 8.15%

(2)

FH includes no uncertainty.

(3) CORE TILT 7 defined as the average quadrant power tilt from CECOR. "Max" refers to the maximum positive core tilt (QPTR > 1.0000).

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

0 Page 32 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 6.2 SURRY UNIT 1 - CYCLE 24 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Map Peak FQ(Z) Hot FA. Hot Channel Factor Channel Factor No.

Meas.

Limit Node Margins Meas.

Limit MarginS

_(%)

__(%)

1 2.201 5.000 26 55.98 1.524 1.894 19.54 2

1.969 3.922 24 49.80 1.480 1.730 14.45 3

1.854 2.503 31 25.93 1.437 1.560 7.88 The measured FQ(Z) hot channel factors include 8.15% total uncertainty. Measured FH data includes no uncertainty.

$ Margin (%) = 100*(Limit - Meas.) / Limit Page 33 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 6.1 -

ASSEMBLYWISE POWER DISTRIBUTION 28.57% POWER Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta = (M - A)xI00/A R

P N

M L

K J

H G

F E

D C

B A

0.2661 0.4061 0.265 1

0.260 0.400 0.2611 2.27 1.53 1.361 0.3071 0.5011 1.0321 1.0531 1.0231 0.5051 0.309 2

0.299 0.489 1.009 1.045 1.011 0.4881 0.299 2.70 2.49 2.31 0.77 1.21 3.471 3.21 0.4241 1.1 81 1.1841 1.3021 1.141 1.2701 1.1781 1.1221 0.4361 3

0.414 1.089 1.154 1.258 1.145 1.261 1.1561 1.089 0.4141 2.32 2.67 2.63 3.48

-0.37 0.68 1.891 3.09 5.40 0.3951 1.1271 1.3361 1.3841 1.2701 1.1621 1.2611 1.3851 1.3401 1.1461 0.3991 0.384 1.102 1.299 1.359 1.258 1.187 1.258 1.361 1.300 1.102 0.3841 1 2.96 2.24 2.86 1.83 0.99

-2.09 0.23 1.75 3.09 3.96 3.941 0.301 1.1071 1.3071 1.2871 1.2571 1.2181 1.1471 1.2171 1.2711 1.3331 1.3451 1.1091 0.302 5

0.294 1.071 1.289 1.280 1.249 1.213 1.156 1.216 1.250 1.281 1.289 1.071 0.294 2.28 3.34 1.43 0.51 0.63 0.38

-0.79 0.10 1.68 4.08 4.36 3.58 2.70 0.483 1.1501 1.3531 1.2431 1.0321 1.2231 1.1541 1.2291 1.044 1.2691 1.3811 1.1751 0.501 6

0.483 1.144 1.350 1.245 1.042 1.234 1.175 1.238 1.042 1.2441 1.3491 1.143 0.483

-0.04 0.51 0.20

-0.19

-0.92

-0.91

-1.79

-0.71 0.22 1.981 2.411 2.80 3.77 0.2561 0.987 1.2351 1.2371 1.1961 1.2201 1.1541 1.1881 1.1581 1.2291 1.2141 1.254 1.2771 1.0501 0.2701 7

0.259 1.002 1.251 1.250 1.212 1.238 1.172 1.207 1.172 1.237 1.209 1.249 1.248 1.0001 0.2581

-1.32

-1.46

-1.25

-1.06

-1.35

-1.48

-1.55

-1.58

-1.20

-0.68 0.39 0.421 2.30 5.05 4.561 0.394 1.009 1.099 1.153ý 1.1221 1.1491 1.1831 1.1661 1.183 1.1521 1.1511 1.1891 1.1541 1.0571 0.4071 8

0.397 1.037 1.135 1.179 1.151 1.175 1.210 1.192 1.210 1.175 1.151 1.179 1.135 1.0361 0.3971

-0.65

-2.66

-3.21

-2.20

-2.50

-2.20

-2.20

-2.21

-2.211

-1.97 0.02 0.89 1.64 2.05 2.541 0.254 0.9781 1.219 1.219 1.1681 1.2001 1.1371 1.1731 1.1301 1.237 1.2171 1.2651 1.2701 1.020 0.2641 9

0.259 1.000 1.248 1.249 1.209 1.237 1.172 1.207 1.172 1.238 1.212 1.249 1.250 1.002 0.259

-1.90

-2.161

-2.31

-2.39

-3.36

-3.00

-3.02

-2.83

-3.61

-0.091 0.43 1.31 1.58 1.76 1.88 0.4761 1.129 1.322 1.2121 1.0061 1.1891 1.1411 1.2061 1.0321 1.255 1.3751 1.163 0.4901 10 0.483 1.143 1.349 1.244 1.042 1.238 1.175 1.234 1.042 1.245 1.349 1.143 0.483

-1.54

-1.21

-1.99

-2.55

-3.41

-3.92

-2.89

-2.31

-0.99 0.78 1.92 1.761 1.47 0.290 1.056 1.265 1.2541 1.2171 1.1791 1.1241 1.1921 1,2331 1.2951 1.3181 1.0921 0.299 11 0.294 1.071 1.289 1.281 1.250 1.216 1.156 1.213 1.249 1.280 1.289 1.071 0.294

-1.501

-1.41

-1.88

-2.14

-2.61

-3.02

-2.80

-1.73

-1.25 1.14 2.27 1.92 1.731 0.383 1.083 1.2731 1.3291 1.2241 1.1671 1.2521 1.3701 1.3261 1.1521 0.3891 12 0.384 1.102 1.300 1.361 1.258 1.187 1.258 1.359 1.299 1.102 0.384

-0.38

-1.74

-2.08

-2.33

-2.68

-1.71

-0.51 0.81 2.09 4.56 1.41 0.407 1.070!

1.1331 1.2381 1.133!

1.2621 1.187!

1.1171 0.429!

13 0.414 1.090 1.156 1.261 1.145 1.258 1.154 1.089 0,414

-1.59

-1.84

-2.01

-1.84

-1.03 0.31 2.83 2.58 3.68 0.2981 0.481!

0.9971 1.0351 1.0101 0.4971 0.3061 14 0.299 0.488 1.011 1.045 1.009 0.489 0.299

-0.34

-1.42

-1.41

-0.97 0.07 1.55 2.28 0.2581 0.3971 0.2601 15 0.261 0.400 0.260

-0.98

-0.68 0.02 AVERAGE ABSOLUTE PERCENT DIFFERENCE =

1. 9 STANDARD DEVIATION 1.115 Summary:

Map No: S1-24-01 Date: 12/02/2010 Power: 28.57%

Control Rod Position:

F0(z) = 2.201 QPTR:

1.0029 1.0148 D Bank at 169 Steps FN = 1.524 0.9777 1.0046 Fz=

1.354 Buu =

2.84 MAxial Offset (%) = +4.092 Burnup =

2.8 MWD/MTU Page 34 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 6.2 -

ASSEMBLYWISE POWER DISTRIBUTION 63.75% POWER Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta =

(M - A)xI00/A R

P N

M L

K J

H G

F S

D C

B A

0.2821 0.4301 0.2801 0.277 0.428 0.278 1.75 0.57 0.82 0.3131 0.5121 1.0501 1.0981 1.0401 0.5161 0.314!

0.306 0.501 1.029 1.094 1.031 0.500 0.306 2.28 2.13 2.02 0.39 0.83 3.10 2.48 0.4221 1.098I 1.1688 1.2941 1.1421 1.2591 1.1591 1.0961 0.4251 0.417 1.074 1.142 1,252 1.151 1.255 1.143 1.074 0.418 1.25 2.26 2.28 3.38

-0.80 0.29 1.40 2.071 1.651 0.3991 1.1061 1.3041 1.350 1.249 1.159 1.2441 1.3511 1.3041 1.117 0.4001 0.388 1.084 1.270 1.331 1.242 1.179 1.242 1.332 1.2711 1.08411 0.388 2.87 1.99 2.64 1.44 0.57

-1.72 0.12 1.43 2.58 3.02j 3.03 0.3091 1.095 1.2811 1.2691 1.243 1.1931 1.1441 1.2111 1.2591 1.3131 1.311 1.087 0.3021 0.301 1.058 1.262 1.261 1.241 1.209 1.153 1.212 1.242 1.261 1.262 1.058 0.3011 I

2.581 3.51 1.49 0.62 0.16

-1.34

-0.77

-0.04 1.35 4.12 3.901 2.741 0.311 I

0.4971 1.141 1.3291 1.2371 1.0731 1.2301 1.1721 1.2371 1.0741 1.2561 1.3471 1.155 0.508 0.4968 1.134 1.324 1.238 1.081 1.240 1.176 1.244 1.081 1.2381 1.3231 1.133 0.496 1

0.16 0.61 0.35

-0.06

-0.73

-0.80

-0.31

-0.57

-0.61 1.441 1.821 1.95 2.42 0.2741 1.0131 1.2321 1.2271 1.1951 1.2311 1.1651 1.1971 1.1621 1.2331 1.206 1.2321 1.2621 1.0591 0.284 7

0.276 1.024 1.247 1.236 1.208 1.244 1.177 1.208 1.177 1.243 1.206 1.2361 1.245 1.023 0.2761

-0o5

-1.03

-1.17

-0.77

-1.07

-1.06

-1.01

-0.95

-1.26

-0.78

-0.021

-0.301 1.36 3.51 2.911 0.424 1.0701 1.1221 1.155 1.123 1.158 1.193 1.174 1.192 1.161 1.147 1.1768 1.1531 1.1021 0.4321 8

0.426 1.087 1.144 1.174 1.150 1.176 1.210 1.191 1.210 1.176 1.150 1.174 1.1441 1.087 0.4261 I -0.44

-1.55

-1.90

-1.58

-2.30

-1.55

-1.41

-1.44

-1.47

-1.26

-0.24 0.151 0.811 1.411 1.291 0.273 1.0081 1.2261 1.2191 1.189 1.221 1.154 1.1841 1.150 1.243 1.208 1.240 1.2541 1.0301 0.275 0.2761 1.023 1.245 1.236 1.206 1.243 1.177 1.208 1.177 1.244 1.209 1.236 1.2471 1.024 0.276

-1.051

-1.431

-1.50

-1.42

-1.40

-1.73

-1.94

-1.961

-2.27

-0.09

-0.101 0.351 0.531 0.631

-0.371 0.4901 1.1211 1.3051 1.217 1.058 1.213 1.147 1.216 1.0681 1.2381 1.3301 1.1391 0.494 10 0.496 1.133 1.323 1.238 1.081 1.244 1.176 1.240 1.081 1.238 1.324 1.1341 0.4961

-1.13

-1.03

-1.38

-1.70

-2.17

-2.51

-2.45

-1.94

-1.19 0.03 0.45 0.45

-0.381 0.2981 1.0451 1.2421 1.235 1.221 1.187 1.111 1.185 1.2201 1.2661 1.2791 1.0691 0.303I 11 0.301 1.058 1.262 1.261 1.242 1.212 1.153 1.209 1.241 1.261 1.262 1.0581 0.3011

-1.09

-1.24

-1.59

-2.07

-1.73

-2.03

-3.61

-2.00

-1.73 0.42 1.38 1.03 0.68 I

0.384 1.068 1.252 1.319 1.242 1.167 1.237 1.336 1.290 1.128 0.3941 12 0.388 1.084 1.271 1.332 1.242 1.179 1.242 1.331 1.270 1.084 0.388

-0.92

-1.45

-1.50

-0.98

-0.03

-1.02

-0.44 0.36 1.58 4.091 1.501 0.412 1.061 1.133 1.249 1.149 1.258 1.165 1.095 0.430 13 0.418 1.074 1.143 1.255 1.151 1.252 1.142 1.074 0.417

-1.37

-1.22

-0.92

-0.49

-0.20 0.51 2.01 1.96 3.23 0.302 0.4961, 1.025 1.092 1.038 0.508 0.312 14 0.306 0.500 1.031 1.094 1.029 0.501 0.306

-1.44

-0.72

-0.57

-0.21 0.90 1.47 1.84 0.272 0.427 0.279 15 0.278 0.428 0.277

-2.16

-0.28 0.69 AVERAGE ABSOLUTE PERCENT DIFFERENCE =

1.4 STANDARD DEVIATION 0.920 Summary:

Map No: S 1-24-02 Date:

12/03/2010 Power: 63.75%

Control Rod Position:

F0(z) = 1.969 QPTR:

1.0030 1.0101 D Bankat 191 Steps FN = 1.480 0.9858 1.0011 Fz =1.237 p =

1.237 MAxial Offset (%) = +3.486 Burnup =

12 MWD/MTU Page 35 of 46

Serial No.11-087 Docket No. 50-280 Attachment Figure 6.3 -

ASSEMBLYWISE POWER DISTRIBUTION 99.90% POWER Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta = (M - A)x00/A R

P N

M L

K 1l 0.3141 0.5141 2

0.308 0.505 1.93 1.78 0.4161 1.064 1.144 3

0.415 1.044 1.124 0.15 1.881 1.801 0.3951 1.0741 1.274 1.315{

0.387 1.056 1.243 1.300 2.14 1.69 2.481 1.19 0.3091 1.0551 1.2511 1.2581 1.2441 5

0.304 1.030 1.236 1.243 1.2421 1.73 2.47 1.24 1.17 0.161 0.5011 1.1221 1.2971 1.2401 1.1501 6

0.501 1.117 1.294 1.2401 1.1561 0.09 0.47 0.25 0.001

-0.491 0.2851 1.0151 1.2291 1.2121 1.2101 1.256 7

0.287 1.022 1.237 1.221 1.225 1.269

-0.54

-0.72

-0.68

-0.72

-1.24

-1.041 0.4421 1.104!

1.1191 1.1461 1.124 1.1721 8

0.444 1.119 1.141 1.166 1.158 1.191

-045

-1.31

-1.91

-1.68

-2.90

-1.60 0.2841 1.0061 1.2131 1.2021 1.2031 1.2471 0.287 1.021 1.235 1.221 1.222 1.268

-1.10

-1.45

-1.74

-1.59

-1.57

-1.65 0.4941 1.0991 1.2731 1.2201 1.1381 10 0.501 1.117 1.293 1.239 1.157

-1.45

-1.65

-1.53

-1.50

-1.67 0.3001 1.0161 1.2171 1.2231 1.228 11 0.304 1.030 1.236 1.2431 1.243

-1.41

-1.40

-1.54

-1.62

-1.201 0.3841 1.0431 1.229 1.2911 12 0.387 1.056 1.243 1.301

-0.67

-1.22

-1.15

-0.77 0.4111 1.0351 1.118 13 0.415 1.044 1.125

-0.95

-0.87

-0.631 0.306 0.503 14 0.308 0.505

-0.571

-0.49 15 AVERAGE ABSOLUTE PERCENT DIFFERENCE =

i.i STANDARD DEVIATION 0.715 J

H G

F E

0 C

B A

0.2921 0.4501 0.2911 0.288 0.446 0.289 1.53 0.81 0.78 1.0441 1.134 1.0361 0.5111 0.3131 1.026 1.125 1.028 0.505 0.308 1.76 0.81 0.78 1.26 1.67 1.2721 1.150 1.2491 1.1361 1.0611 0.4241 1.241 1.147 1.243 1.125 1.044 0.415 2.48 0.23 0.51 1.02 1.65 2.10 1.2311 1.1621 1.2291 1.3151 1.2681 1.0761 0.3941 1.226 1.171 1.226 1.301 1.243 1.056 0.387 0.41

-0.77 0.27 1.04 2.01 1.92 1.72 1.2031 1.152 1.2261 1.2541 1.2861 1.2591 1.0441 0.3051 1.2241 1.160 1.227 1.243 1.243 1.236 1.030 0.3041

-1.751

-0.68

-0.11 0.90 3.50 1.83 1.36 0.281 1.254ý 1.187J 1.2591 1.1431 1.2491 1.3041 1.1261 0.5071 1.265 1.190 1.268 1.157 1.239 1.293 1.117 0.501

-0.87

-0.29

-0.67

-1.25 0.82 0.82 0.82 1.15 1.203 1.218 1.2011 1.2551 1.2181 1.2171 1.2421 1.0381 0.293 1.212 1.228 1.213 1.268 1.222 1.221 1.235 1.0211 0.287

-0.721

-0.82

-1.02

-1.04

-0.29

-0.34 0.54!

1.641 1.961 1.2141 1.194 1.2121 1.173 1.153 1.1671 1.1471 1.151 0.4551 1.230 1.208 1.230 1.191 1.158 1.166 1.1411 1.1191 0.444

-1.271

-1.16

-1.45

-1.52

-0.44 0.11 0.551 2.851 2.55 1.1931 1.2091 1.1861 1.2641 1.2241 1.2251 1.2451 1.0371 0.2921 1.213 1.228 1.213 1.269 1.225 1.221 1.237 1.0221 0.2871

-1.65

-1.58

-2.23

-0.43

-0.12 0.35 0.61 1.461 1.881 1.244 1.175 1.2491 1.1491 1.2451 1.2991 1.1231 0.500 1.268 1.190 1.265 1.156 1.240 1.294 1.117 0.501

-1.911

-1.27

-1.25

-0.60 0.41 0.42 0.54

-0.171 1.214I 1.1511 1.2151 1.2301 1.2631 1.2561 1.041 0.3061 1.227 1.160 1.225 1.242 1.243 1.236 1.030 0.3041

-1.06

-0.75

-0.84

-0.98 1.63 1.58 1.091 0.651 1.225 1.170 1.2281 1.3071 1.2651 1.0951 0.3901 1.226 1.171 1.226 1.300 1.243 1.056 0.387

-0.041

-0.09 0.15 0.50 1.75 3.73 0.84 1.240 1.149 1.2491 1.1371 1.0611 0.4261 1.243 1.147 1.241 1.124 1.044 0.415

-0.211 0.21 0.61 1.18 1.67 2.75 1.0261 1.1291 1.0401 0.5121 0.3131 1.028 1.125 1.026 0.505 0.308

-0.20 0.33 1.36 1.31 1.65 0.283 0.4471 0.291I 0.289 0.446 0.288

-1.951 0.13 1.07 Summary:

Map No: S1-24-03 Control Rod Position:

D Bank at 229 Steps Date:

12/13/2010 FQ(z) = 1.854 FN =

1.437 Power: 99.90%

QPTR:

1.0020 1.0059 0.9881 1.0040 Fz= 1.179 B p 1.179 3Axial Offset (%) = +2.359 Bumnup =

345 MWD/MTU Page 36 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION 7 -

CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit I Cycle 24 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, technical specification limits, or COLR limits. It is anticipated, based on the results associated with the S I C24 startup physics testing program, that the Surry 1 core will continue to operate safely throughout Cycle 24.

Page 37 of 46

Serial No.11-087 Docket No. 50-280 Attachment Table 7.1 STARTUP PHYSICS TESTING RESULTS

SUMMARY

Measured Predicted Diff (M-P) or Design Parameter (M)

(P)

(M-P)IP,%

Tolerance Critical Boron Concentration (HZP ARO), ppm 1551 1586

-35

+/-50 Critical Boron Concentration (HZP Ref Bank in), ppm 1370 1362

+8

+/-29 Isothermal Temp Coefficient (HZP ARO), pcm/F

-2.149

-2.366

+0.217

+/-2 Differential Boron Worth (HZP ARO), pcm/ppm

-7.64

-7.50

+1.9%

+/-10%

Reference Bank Worth (B-bank, dilution), pcm 1383 1418

-2.5%

+/-10%

SB-bank Worth (Rod Swap), pcm 1066 1098

-3.0%

+/-15%

SA-bank Worth (Rod Swap), pcm 903 917

-1.5%

+/-15%

D-bank Worth (Rod Swap), pcm 944 973

-2.9%

+/-15%

C-bank Worth (Rod Swap), pcm 913 940

-2.9%

+/-15%

Rod Worth < 600 pcm:

A-bank Worth (Rod Swap), pcm 234 236

-1.8

+/-100 Total Bank Worth, pcm 5443 5582

-2.5%

+/-10%

S1C24 testing time:

7.0 hrs

[criticality 12/01/10 @ 0555 to end of rod swap 12/01/10 @ 1252]

Recent Startups:

S2C23 testing time:

9.4 hrs S1C23 testing time:

6.2 hrs

$2C22 testing time:

6.2 hrs

$1C22 testing time:

8.0 hrs

$2C21 testing time:

5.8 hrs S1C21 testing time:

5.0 hrs Page 38 of 46

Serial No.11-087 Docket No. 50-280 Attachment SECTION 8 -

REFERENCES

1.

J. R. Young, "Surry Unit 1, Cycle 24 Design Report," Engineering Technical Evaluation ETE-NAF-2010-0056, Rev. 0, November 2010

2.

R. W. Twitchell, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," Topical Report VEP-FRD-36-Rev. 0.2-A, September 2004

3.

J. G. Miller, "The CEBRZ Flux Map Data Processing Code for a Movable In-core Detector System," Technical Report NE-1581, Rev. 0, September 2009

4.

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

5.

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

6.

K. L. Kennett, "Surry Unit 1 Cycle 24 TOTE Calculations and Detailed Isotopics,"

Calculation PM-1409, Rev. 0, November, 2010

7.

J. L. Meszaros et al, "Surry Unit 1 Cycle 24 Flux Map Analysis," Calculation PM-1411, Rev. 0, and Addenda A - B, December 2010

8.

R. K. Fawls, "Reload Safety Evaluation Surry 1 Cycle 24 Pattern OWL," EVAL-ENG-RSE-S 1 C24, Rev. 0, October, 2010

9.

S. B. Rosenfelder and S. S. Kere, "RMAS v6 Verification," Calculation PM-1075, Rev. 0, May, 2005

10. W. R* Kohlroser, "Administrative Limits on Hot Rod Drop Time Testing for Use as Acceptance Criteria in 1/2-NPT-RX-014 and 1/2-NPT-RX-007," Engineering Transmittal ET-NAF-97-0197, Rev. 0, August, 1997
11. B. R. Kinney, "Surry Unit 1 Cycle 24 Full Core Loading Plan," Engineering Transmittal ET-NAF-10-0031, Rev. 0, April, 2010
12. N. A. Yonker, "Validation of Rod Drop Test Computer for Hot Rod Drop Analysis,"

Calculation PM-1044, Rev. 0, November, 2004

13. A. H. Nicholson, "Justification For Defining 0 To 2 Steps Withdrawn As Fully Inserted When Measuring Control And Shutdown Banks During The Surry Startup Physics Testing Program," Engineering Transmittal ET-NAF-06-0046, Rev. 0, April, 2006.
14. J. L. Meszaros, "Surry Unit 1 Cycle 24 Startup Physics Testing Logs and Results",

Memorandum MEMO-NCD-20100078-0-0, December 2010

15. J. G. Miller, "The CECOR Flux Map Analysis Code for a Movable In-core Detector System," Technical Report NE-1582, Rev 0, September 2009 Page 39 of 46

Serial No.11-087 Docket No. 50-280 Attachment APPENDIX -

STARTUP PHYSICS TEST

SUMMARY

SHEETS Page 40 of 46

Serial No.11-087 Docket No. 50-280 Attachment Surry Power Station Unit 1 Cycle 24 Startup Physics Test Summary Sheet - Formal Tests (Page 1 of 6)

Deeign Dat Criteria Acceptanoe Time of Prepared Value Desgn Criteria Acceane_ Crfte Met Criteria het Test flewer ZPTR-background e ZPTR < POAH

/ZYes O6E I

__L bakron NIA N/A fiI o

backound = I

  • utatc amps N

f~-

-P-96=.L'fl f-* S m

Ip(pN

-PaIN x 100%

4.0 %3

04.

, eý,.

(measured reacivty)

The allowable range Is set to the larger L Yes WI/iO pi_.S:Q

_-',1I of the measured results or the pre-f tia (predIotld reactiMy) bA NO WA Pre-criticai Bench Test Results

%=

p - pflpt} x 100%

=

Allboabale range

_0...pcm (Ca)V= 'rIg ppm (C)oz1 15 50

=ppm IUCe X ACO)*l*OI m1000 porn (Wil. To esi cands.)

C M

Cp-T.S. 4.1A*A ]

Yes Y Yes i/Ao (Ai.odsincnd, XaCO)AAO-(A) Ao-(C)ARog*

pp PP OCs!ý -7.42 pcm/ppm

,NO No (O)O

=

CmOst jgw'

+/- 2 pmrn/F gTý IO<3.69 pcrnf V/Yes Yes 0"_l_

A -

(I

&rAT" pF where.

(ogýI) ; 6.0 pCetF [COLR 3.41 No No

/

(fwJ)2, -1.8 por/F

!,EI* I 1418* 10%

-'yes iM

,- A'L pcm lW(*Meas. Des,)/Des. =:2A7%

NIA No A Ref

1) r eslFTE-NAF-201-o0056s, fley 5 Z) Memoranldum from C.T. Snow Ito FJ. Lozito, dated June 27, 1980 3.) Westinghouse RepoIl WCAP-7905, Rev. 1 4.) ETE-NAF-2010-0068, Rev. 0

&) Catbulallon PM-1408, Rev. 0 Page 41 of 46

Serial No.11-087 Docket No. 50-280 Attachment Surry Power Station Unit 1 Cycle 24 Startup Physbcs Test Summary Sheet - Formal Tests (Page 2 of 6)

Design Dutaf Crhatla Acce!nnce Time of Prepared Measured Valuo Oesion Criterla Accepance fta Met Criteria Met Tost Remdewer (Ce)pe-(C8)6=' 13 9 74-&(Ce)ARO *29 PPm I4

-M A....

ppm Zc.no 3

ppm (from above)

WsA N(A (C)O-= -j.j=

29 ppm NO (C~

(j k pppp (ace 5

,cxC.

-t1 -7.50 76 pcmtm WA y

p==

pc/pprn Aac

.-oLc-.

p_

N4

-IA 1Meae. -Des,.=l-,pcm (ISAR )A Z1I-l

=

s W:A k-\\(Ma~

OesiApos=WA."64 (IB+/-Y 1

g 1

15%

1___

si WA II2 ~

Apan 100i4Meas, - OI.Ies.

j-,-_. %

No A i,-!o n' E W (Ii9R3)4=

6I+/- 2

+/--15%

V yes W

D"M pmn 1m~

%O4a.Dsie N/A12h WNA pCM 1 00lodeas. - DesyDes =..,%

N[A

___1Di/I_

M'_-

Refererncos 1.) ETE-NAF-2nl 0-0056, Rev. 0 2.) Memorandum from C.T. Snow to FJ. Lo2i*0, dated June 27, 1980 3,) Westinghouse Report WCAP.7905, Rev. 1 4.) ETE-NAF-2010-O056, Rev. 0 5.) Calbulation PM-1406, Rev. 0 Page 42 of 46

Serial No.11-087 Docket No. 50-280 Attachment Surry Power Station Unft 1 Cycte 24 Startup Pttys,,s Test Summary Sheet - Formal Tefts (Page 3 of 6)___

113=1n D ata~

I eliterra fteplence TIMo of Pleparel Disasired Value OWsin Crftwa*

Appevtmn Crftfti fiet

~CdtIv111ASM TeSt IRSVieer ftwer tL-Max RfW IM IUMnE~

TMui IWW 2A..)I

____ye WA__

%forI3.,

1 WA V/Ye

~~~~W IWAI1~C~~d)jW

-- Noa oW Hea Rim 03 bn~Fct~F

_Z___

CAgntrM MdW A IS15( #0,3(1-)) 1C(Z)[Ot 3,71 MA z~

a"puex~vIo~cineV1A ____________

A Factar=,,2,2mm 1.)

ETE-NUF-L1mitBIm

$ev.

0_

M~~u2.)

Mmoranduu froin C.Traz Snow~

Til

___________________27,_1__0

3. Wetngos Repoc 1CP7M R&A J1 ET-A-oIs

_s, 5eeeue

.) ETE-~n F%-210-005, Rev. 0-Page 43 of 46

Serial No.11-087 Docket No. 50-280 Attachment Sunry Power Statbon Unft 1 Cycle 24 Staitup Physics Test Summary Sheet - Formal Tests (Page 4 of 6)___

Dostgn Dam/i Measured Va~Cwteris Accepmmt lime of Preprirert M ue asDesgni Cdta~a AmoItw=c Ciftrta Met 1rtte7~a Vet Test RSaIIBwer

-&10% for 6 WO.9 1WF~+/-~LL.~kPIO.

IWfrR.4s WA IUA iI WA I PAH'(Ms

.8403(1-P))

1OLS 3.71 MA yeav T a W I t e F w r!

ýC a mP P a mJ~Cz O L R &7 1

O Iw Fmf faJoMA WA

!5 Ik MIA KW

~AQI~L~I I

I______

Nip__

Referamce 1..) ETE.NAF-201O.4JOA~ Rev. 0 2.) Memowandum frmmC.T, Snow bo E.J. Lnxzitadated1 June 27, IMS 3,) Wesgfrghmms Report WCAP-7908. Rmv 1 4.j ETE-NAF-2011"r46 RWv 0 5j) CaIv~d~on PM-14O6 Rev. 0 Page 44 of 46

Serial No.11-087 Docket No. 50-280 Attachment Surry Power Station Unit 1 Cycle 24 Startup Physics Test Summary Sheet - Fonnal Tests (Page 5 of 6)

Ia A ctutiv C rite r i P o w ere T im e o fJI P r e p a red__

I

+/-l0%for P,O.

IA I-/

e

%IOIFF.-ý ý-

3 f or Pi 09I t15%tor PC9 INIA No WA/

Kidajc r OUhalft Rise Htot Chamiil Factor, FAJ4(M

-_WA________________________0_03_73_

121ye WA I FNcs.5t1.0,WM-P2 [COWA 3.711 Y8 Peak F4(Z)01 CIhut j

WA jWA FactxL-IMh~um Maugki Io COLS Lim~it-

-N*

nMaumam PostWive Waore Ouadient Powe lilt n~S s1.02 NIA WA Reerenoces 1.) ETE-NAF-2M1-O056, Rev. 0 2.) Memorandum from C.T. Snow to EJ. Lozito. dated June 27,1980 3,) Wesdnghouse Report WCAP-7905, Rev, 1 4.) ETE-NAF-201"O066, Rev. 0 5.) Calculation PM.1406, Rev, 0 Page 45 of 46

Serial No.11-087 Docket No. 50-280 Attachment Surry Power Station Unit 1 Cycle 24 Staitup Physics Test Summary Sheet - Formal Tests (Page 6 of 6)

Design Date/

CrIt*ia Aoceptarb, Time of Preparerl Measured Value Design Criteria Azceptanca Criteria Mat Criteria Mat Test Reviewer WA Fj1,d 273000gpm [T.S.3.12.F.1]

N/Ayes 1/27/1o Referenwes 1.) ETE-NAF-2010-0056, Rev. 0 2.) Memorandum from C0T. Snow to E.J. Lozito, dated June 27, 1980

3) Westinghousa Reort WCAP-7905, Rev, 1 4.) ETE-NAF-2010-0066, Rev. 0 5.) Cae

,lation PM-1406, Revm 0 Page 46 of 46

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