ML17241A046

Surry, Unit 2, Submittal of Cycle 28 Startup Physics Tests Report

ML17241A046
Person / Time
Site:	Surry
Issue date:	08/24/2017
From:	Stanley B L Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation, Region 2 Administrator
References
Download: ML17241A046 (49)

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i. Dominion Energy Services, Inc. 5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com August 24, 2017 United States Nuclear Regulatory Commission Regional Administrator-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 28 STARTUP PHYSICS TESTS REPORT ;;iiliii" Energy. Serial No.: 17-330 NRA/GDM Docket No.: 50-281 License No.: DPR-37 As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 2 Cycle 28 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 28 on June 3, 2017. The results of the physics tests were within the applicable Technical Specifications limits. If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771. Sincerely, B. L. Stanley, Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None

.. cc: U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Ms. K. R. Cotton Gross NRG Project Manager -Surry U.S. Nuclear Regulatory Commission, One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 J. R. Hall NRG Project Manager-North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B-1A 11555 Rockville Pike Rockville, MD 20852-2738 NRG Senior Resident Inspector Surry Power Station Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Page 2 of 2

.. Enclosure Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 CYCLE 28 STARTUP PHYSICS TESTS REPORT August 2017 Virginia Electric and Power Company (Dominion Energy Virginia) Surry Power Station Unit 2 CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion Energy (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 ylaim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMP ANY MAKES NO WARRANTY OF MERCHANTABILI'LY 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 out of the use, authorized or unauthorized, of this report or the data, ' techniques, information, or conclusions in it. Page 1of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report TABLE OF CONTENTS Classification/Disclaimer ............................................................................................................... 1 Table of Contents ........................................................................................................................... 2 List of Tables .................................................................................................................................. 3 List of Figures ................................................................................................................................. 4 Pref ace ...................................... ***************************************************e11***************************************************5 Section 1 -Introduction and Summary ........................*.........*.......................*.......................... 6 Section 2 -Control Rod Drop Time Measurements ..........................................**..*.*...*.......... 14 Section 3 -Control Rod Bank Worth Measurements .................*.........*................................ 19 Section 4 -Boron Endpoint and Worth Measurements ...............................*..*..................... 24 Section 5 -Temperature Coefficient Measurement ............................................................... 27 Section 6 -Power Distribution Measurements .........*............................................................. 29 Section 7 --Conclusions ....................................... ..................................................................... 36 Section 8 --References ............................................................................................................... 38 Appendix -Startup Physics Test Summary Sheets ...................................................*............ 40 Page 2 of46 --------,

LIST OF TABLES Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Table 1.1 -Chronolog)'" of Tests .................................................................................................. 9 Table 2.1 -Hot Rod Drop Time Summary .............................................................................. 15 Table 3.1 -Control Rod Bank Worth Summary .....................................*.*............................. 21 Table 4.1 -Boron Endpoints Summary ................................................................................... 25 Table 4.2 -Boron Worth Coefficient ........................................................................................ 26 Table 5.1 -Isothermal Temperature Coefficient Summary ................................................... 28 Table 6.1 -Incore Flux Map Summary .................................................................................... 31 Table 6.2 -Comparison of Measured Power Distribution Parameters with their Core Operating Limits ..................................................................................................... 32 Table 7.1 -Startup Physics Testing Results Summary ........................................................... 37 Page 3 of46 LIST OF FIGURES Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Figure 1.1 -Core Loading Map **************************************************************************o**********************lO Figure 1.2 -Beginning of Cycle Fuel Assembly Burnups (GWD/MTU) ..*.....*...*.*..*.*..........*. 11 Figure 1.3 -Available Incore Moveable Detector Locations .....*............................................. 12 Figure 1.4 -Control Rod Locations ........................................................................................... 13 Figure 2.1 -Typical Rod Drop Trace ........................................................................................ 16 Figure 2.2 -Rod Drop Time -Hot Full Flow Conditions ................*........................*.............. 17 Figure 2.3 -Rod Drop Times Trending .................................................................................... 18 Figure 3.1 -Control Bank B Integral Rod Worth -HZP ..............*......................................... 22 Figure 3.2 -Control Bank B Differential Rod Worth -HZP .................................................. 23 Figure 6.1 -Assemblywise Power Distribution 28.81 % Power .............................................. 33 Figure 6.2 -Assemblywise Power Distribution 71.02% Power ........................................*..... 34 Figure 6.3 -Assemblywise Power Distribution 99.80% Power .......*...................................... 35 Page4 of46 PREFACE Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 2 Cycle 28 (S2C28) core could be operated safely, and makes an initial evaluation of the performance of the core.

• This report was performed in accordance with DNES-AA-NAF-NCD-5007, Rev. 3 [Ref. 12]. 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 S2C28 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 Energy's Nuclear Engineering and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits. Page 5 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SECTION 1 -INTRODUCTION AND SUMMARY On May 6, 2017, Unit No. 2 of Surry Power Station completed Cycle 27 and began refueling [Ref. l]. During this refueling, 89 of the 157 fuel assemblies in the core were replaced with 65 fresh Batch S 1/30 and Batch S2/30 assemblies, 8 twice-burned S2/26 assemblies last irradiated in Surry 2 Cycle 25, and 16 twice-burned Sl/28 assemblies last irradiated in Surry 1 Cycle 27 [Ref. 1]. The Cycle 28 core consists of 7 sub-batches of fuel: two fresh batches (Sl/30A and S2/30A), two burned batches (S2/29A and S2/29B), and three twice-burned batches (S2/26B, Sl/28B, and S2/28B). Like the previous cycle, S2C28 will have a full core of the 15xl5 Upgrade Fuel Design [Ref. l]. The Westinghouse Upgrade fuel includes three ZIRLO Intermediate Flow Mixing (IFM) grids for improved thermal-hydraulic performance, ZIRLO (I-spring) structural mid grids with balanced mixing vane pattern, "tube-in-tube" guide thimbles, and the use of optimized ZIRLO fuel clad that improves corrosion resistance and oxidation of the bottom portion of the fuel clad to improve debris resistance. The Upgrade fuel used for all batches except S2/26 includes the Westinghouse Robust Protective Grid (RPG) and modified Debris Filter Bottom Nozzle (mDFBN). Only batches Sl/30, S2/29, and S2/30 include the Westinghouse Integrated Top Nozzle (WIN) [Ref. 13]. This cycle uses Westinghouse's Integral Fuel Burnable Absorber (IFBA) fuel product. The IFBA design involves the application of a thin coating of ZrB2 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]. Cycle 28 loads two Secondary Source Assemblies (SSAs) in core locations H-04 and H-12. Each assembly consists of six source rods containing antimony and beryllium pellets encapsulated in Page 6 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report a double layer of stainless steel cladding. There are no thimble plugging, devices in S2C28. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 28 core. The S2C28 full core loading plan [Ref. 2] is given in Figure 1.1 and the beginning of cycle fuel assembly bumups [Ref. 18] are given in Figure 1.2. The incore moveable* detector locations used for the flux map analyses [Ref. 11] are identified in Figure 1.3. Figure 1.4 identifies the location and number of control rods in the Cycle 28 core [Ref. 1]. According to the Startup Physics logs, the Cycle 28 core achieved initial criticality on June 3, 2017 at 03:59 [Ref. 3]. Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. This cycle used the Reactivity Measurement and Analysis System (RMAS) to perform startup physics testing. Note that RMAS v.7 [Ref. 9] was used for S2C28 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 2.40 second* Technical Specification [Ref. 6] limit, as well as the Surry Unit 2 1.68 second administrative limit [Ref. 8]. Individual control rod bank worths were measured using the rod swap technique [Ref. 4]. 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. 10]. The sum of the individual measured control rod bank worths was within-2.3% of the design prediction. The reference bank (Control Bank B) worth was within -1.9% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within -5.l % of the design predictions. Control rod banks with design predictions less than 600 pcm (Control Bank A) were within 6 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, all rods out (ARO) and Reference Bank (B-bank) in, were within the design tolerances and the Technical Specification criterion [Ref. 6] that the overall core reactivity balance shall be within +/- 1 % Lik/k of Page 7 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report the design prediction. The boron worth coefficient measurement was within + 1.3% of the design prediction, which is within the design tolerance of+/- 10%. The measured isothermal temperature coefficient (ITC) for the ARO configuration was within +0.248 pcm/°F of the design prediction. This result is within the design tolerance of +/-2.0 pcm/°F. All criteria [Ref. 20] to perform the first flux map at up to 50% power were met. However, the first flux map was performed at approximately 30% power in anticipation of a required chemistry hold [Ref. 14]. The investigation summarized in Reference 19 concluded that the start order of the reactor coolant pumps (RCPs) could be a contributor to the larger than expected core tilts experienced at the beginning of Surry Unit 2 Cycle 27. The S2C28 initial start order sequence of the RCPs was C-B-A, and is consistent with the startup sequence recommended in Reference 19. Core power distributions were all within established design tolerances. The measured assembly power distributions were within +/-5.5% of the design predictions, where a 5.5% maximum difference occurred in the 28.81 % power map. The heat flux hot channel factors, FQ(z), and enthalpy rise hot channel factors, F:r, were within the limits of the COLR [Ref. 13]. The maximum positive incore quadrant power tilts ranged from 0.72% to 1.05% during the power ascension. All flux maps were within the maximum incore power tilt design tolerance of 2% (QPTR :'.S 1.02). The total RCS Flow was successfully verified as being greater than 273,000 gpm and greater than the limit in the COLR (274000 gpm), as required by Surry Technical Specifications [Ref. 6]. The total RCS Flow at nominal conditions was measured as 290,226 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 8 of46 Table 1.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 06/02/17 13:26 HSD 2-NPT-RX-O 14-0T0-1 Reactivity Computer Checkout 06/03/17 05:00 HZP 2-NPT-RX-008 Boron Endpoint -ARO 06/03/17 05:00 HZP 2-NPT-RX-008 Zero Power Testing Range 06/03/17 05:00 HZP 2-NPT-RX-008 Boron Worth Coefficient 06/03/17 10:00 HZP 2-NPT-RX-008 Temperature Coefficient -ARO 06/03/17 05:41 HZP 2-NPT-RX-008 BankB Worth 06/03/17 06:53 HZP 2-NPT-RX-008 Boron Endpoint -B in 06/03/17 09:35 HZP 2-NPT-RX-008 BankA Worth-Rod Swap 06/03/17 09:35 HZP 2-NPT-RX-008 Bank C Worth -Rod Swap 06/03/17 09:35 HZP 2-NPT-RX-008 Bank D Worth -Rod Swap 06/03/17 09:35 HZP 2-NPT-RX-008 Bank SA Worth -Rod Swap 06/03/17 09:35 HZP 2-NPT-RX-008 Bank SB Worth-Rod Swap 06/03/17 09:35 HZP 2-NPT-RX-008 Total Rod Worth 06/03/17 09:35 HZP 2-NPT-RX-008 Flux Map -less than 50% Power* 06/04/17 09:27 28.81% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008 & Power Range Calibration 2-NPT-RX-005 2-GEP-RX-001 Flux Map -65% -75% Power 06/05/17 02:14 71.02% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008 & Power Range Calibration 2-NPT-RX-005 2-GEP-RX-001 Flux Map -95% -100% Power 06/08/17 09:00 99.80% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008 & Power Range Calibration 2-NPT-RX-005 2-GEP-RX-001 RCS Flow Measurement 06/08/17 10:30 HFP 2-NPT-RX-009

• Results of zero power physics testing permitted the first flux map to be performed up to 50% power (versus 30% power if specified criteria were not met). The first flux map was performed below 30% power in anticipation of a required chemistry hold. Page 9 of 46 R llOR'l'll l 231 RCC 757 801 RO:: 660 916 z;;s 806 RCC ?GO 22, S<:l<.ll'T.ICllS: OEVICB DBS W::C-YUL!. LDICn'K sst-sccond<ley ROD 1"'CC11bl.y M 52X RCC 37X 811 821 842 RCC 9::19 748 ace 419 706 ?51 ?53 ace 416 704 RCC 925 '42 81-1 855 RCC SLX 818 42X Proparoo By: _.... --;;:::=._ aav!cwcd Hy:LJ.. S .. ?ouik Approved By: A. ff. >>icnoJson Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Figure 1.1 SURRY UNIT 2-CYCLE 28 CORE LOADING MAP SURRY UNIT 2 -CYCLE 28 CORE LOADING PLAN REVISION NO. 0 K J 234 RO:: 228 ?GJ Q03 RCC 819 8l2 ,19 RCC 8'8 741 714 RCC 729 "MO 854 RCC ?3'1 'Ill 834 RO:: as2 9lS 720 RCC 719 709 703 RCC 845 836 ?21 RCC 7l9 no 840 RCC 727 843 RCC 747 7U RCC 829 413 RCC 229 762 802 237 !>ate: fl t.;=116 IMC"°' 1'2..(/$ //(, D.sto: 17./'l.O(lfo ll 655 RCC 820 749 SS9 752 724 llCC '113 ?1S 857 705 RCC 702 722 ssa 756 754 RCC 810 656 Page 10 of 46 F Z38 llO:: Q()Q 1G1 RO:: 415 BlO RO:: 709 146 956 735 RCC $39 726 !I.CC 7?.l 8J3 RCC 112 ?ll RCC 717 837 RCC 8lS 728 73!> RCC 710 744 RCC 421) 826 !\CC BOS ?SB 233 K'l'IMIAP-201,,-0144, Rov. 0 1.ttaeh!Mne 1 PME l of 1 D c B A 2 227 822 -'6X RCC 850 817 40X RCC 5 732 8'14 813 230 RCC RCC G 7'G "14) 827 RCC ' 847 ?Ol 4l4 80? 236 RCC B 719 750 ?55 924 658 RCC 841 707 41? 804 240 RO:: !ICC 10 733 7-'S 831 764 RCC 11 725 846 815 232 RC:C 12 853 809 56X 1J 47X 14 225 15 !>cite' ...... l_J.. ... (

R 1 2 3 4 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Figure 1.2 SURRY UNIT 2 -CYCLE 28 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWD/MTU) p N M L K J H G F E D c B A I 42.571 32.051 42.611 I 42.511 31.821 42.so1 I MEASURED I I PREDICTED I I 41.631 23.181 0.001 0.001 0.001 22.661 42.101 I 41.511 22.671 0.001 0.001 0.001 22.681 41.521 I 39.491 0.001 0.001 0.001 21.661 0.001 0.001 0.001 39.491 I 39.441 0.001 0.001 0.001 2i.41I 0.001 0.001 0.001 39.4BI I 39.611 0.001 0.001 19.361 23.661 20.021 23.841 19.591 0.001 0.001 39.551 I 39.591 0.001 0.001 19.261 23.591 19.941 23.621 19.381 0.001 0.001 39.601 I 42.171 0.001 0.001 23.70119.281 0.001 23.301 O.OOl 19.221 23.BOI 0.001 0.001 41.721 I 41.521 0.001 0.001 23.931 19.191 0.001 23.381 0.001 19.191 23.971 0.001 0.001 41.511 I 22.821 0.001 19.321 19.281 23.141 0.001 23.781 0.001 23.241 19.321 19.231 0.001 22.821 I 22.761 0.001 19.311 19.151 23.341 0.001 23.831 0.001 23.361 19.lBI 19.231 0.001 22.681 1 2 3 4 7 I 42.801 0.001 0.001 23.711 0.001 0.001 23.341 23.941 23.231 0.001 0.001 23.611 0.001 0.001 42.531 I 42.521 0.001 0.001 23.661 0.001 0.001 23.491 23.911 23.311 0.001 0.001 23.631 0.001 0.001 42.541 10 11 12 13 14 15 I 32.291 0.001 21.891 20.561 23.331 23.751 23.741 0.001 23.771 24.051 23.421 19.981 21.561 0.001 32.00I I 31.891 0.001 21.481 19.981 23.491 23.731 23.711 0.001 23.701 23.731 23.481 19.981 21.481 0.001 31.871 I 42.561 0.001 0.001 24.021 0.001 0.001 23.301 24.231 23_301 0.001 0.001 23.611 0.001 0.001 42.621 I 42.541 0.001 0.001 23.651 0.001 0.001 23.301 23.911 23.491 0.001 0.001 23.611 0.001 0.001 42.521 I 22.801 0.001 19.561 19.221 23.301 0.001 23.881 0.001 23.271 19.351 19.501 0.001 22.811 I 22.701 0.001 19.231 19.191 23.351 0.001 23.831 0.001 23.341 19.221 19.311 0.001 22.761 I 41.301 0.001 0.001 23.78119.621 0.001 23.541 O.OOl 19.171 23.791 0.001 0.001 41.601 I 41.511 0.001 .. 0.001 23.971 19.211 0.001 23.381 0.001 19.111 23.931 0.001 0.001 41.521 R I 39.551 0.001 0.001 19.571 23.521 20.161 23.901 19.541 0.001 0.001 39.311 I 39.601 0.001 0.001 19.381 23.631 20.001 23.641 19.261 0.001 0.001 39.591 p I 39.SSI 0.001 0.001 0.001 21.391 0.001 0.001 0.001 39.411 I 39.481 0.001 0.001 0.001 2i.411 0.001 0.001 0.001 39.441 N I 41. 60 I 22. 73 I o. oo I o. oo I o. oo I 22. 63 I 41. 68 I I 41. 52 I 22. 70 I o. oo I 0.001 o. oo I 22. 66 I 41.51 I M L I 42.911 31.901 42.561 I 42.501 31.831 42.511 K J H G Page 11 of46 F E D c B A 10 11 12 13 14 15 Figure 1.3 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R p N M L K J H G F E D c B A MD MD 2 MD MD MD MD 3 MD MD MD 4 MD MD MD MD MD MD 5 MD MD MD 6 MD MD MD MD MD 7 MD* MD MD MD MD MD 8 MD MD MD MD 9 MD MD MD MD 10 MD MD MD MD 11 MD MD MD MD 12 MD MD 13 MD MD 14 MD 15 MD -Moveable Detector

• Detector in R8 was not available for power ascension maps. Page 12 of46 R p A D A N M L c SB B SA SA B SB c D = Control Battle D C = Control Battle C B = Control Battle B A = Control Battle A Figure 1.4 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 CONTROL ROD LOCATIONS K J H G 180° A D SA SA B D c SB SB c SB SB D c B SA SA A D Page 13 of46 F E D c B A B c SB D B A SA c D SA D B A SB B c A SB = Shutdown Bank SB SA = Shutdown Battle SA A 270° 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SECTION 2 -CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot shutdown (HSD) with three reactor coolant pumps in operation (full flow) and with Tave greater than or equal to 530°F per 2-NPT-RX-O 14-0TO-l. 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. l [Ref. 6] . . Surry Unit 2 Cycle 28 used the Rod Drop Measurement Instrument (RDMI) to gather and analyze the rod drop data [Ref. 7]. The rod drop times were measured by withdrawing all banks to their fully withdrawn position and dropping 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 a comma-separated value file. Further details about the RDMI can be found in Reference 7. Additional verification was performed for the rod drop in core location G-13 due to the bending and subsequent replacement of the control rod drive shaft for that location during the onload. Although the shape was not consistent with the shape in G-13 from S2C27, the shape was consistent with the shape in location F-06, which has shown acceptable performance. The drop time in G-13 was slightly slower seconds) than S2C27. All remaining criteria for G-13 were satisfactory [Ref. 14]. A typical rod drop trace for S2C28 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 2 Cycles 20-28. Technical Specification 3.12.C.l [Ref. 6] 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. 8] of 1.68 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region. The average rod drop time for S2C28 was the same as S2C27. Page 14 of46 Table 2.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2-CYCLE 28 STARTUP PHYSICS TESTS HOT ROD DROP TIME SUMMARY ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME G-13 1.45 sec. L-05 1.30 sec. 1.35 sec. Page 15 of46 Figure 2.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE S2C28 DROP DATA: G7 (SBB} Beginning of 5 Dashpot Entry (Extreme Drop in . . 1 4.5 * . . Voltage) .. 4 .. ' _____ .*. ____ . . ' t**-' *---I 3.5 +--------------+----------w * !' i I 3 --** 2* 5 , Initiation of 2 *' RodDrop Event Mark 0 1 Bottom of Dashpot ---------------1-1 Bounce Indicating Rod is NOT Stuck 2 nme (sec) Page 16 of46 3 4 R p 1.324 1.310 1.344 Figure 2.2 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS ROD DROP TIME -HOT FULL FLOW CONDITIONS N M L K J H G F E D C B A 1 1.338 1.322 1.332 2 1.338 1.344 3 1.336 1.314 1.352 1.358 4 1.304 1.342 5 1.324 1.336 1.342 1.430 1.330 1.420 6 1.342 1.360 1.358 1.344 7 1.338 1.332 1.360 8 1.346 1.356 1.340 1.324 9 1.338 1.360 1.348 1.382 1.330 1.362 10 1.328 1.344 11 1.324 1.322 1.346 1.340 12 1.324 1.446 13 1.392 1.316 1.360 14 15 I x.xxx 1--> Rod drop time to dashpot entry (sec.) Page 17 of46 2.50 2.40 2-30 2.20 2.10 2.00 _1.90 u CD .!!. CD E i=1.80 1.70 1.60 1.50 1.40 1.30 1.20 1.10 Figure 2.3 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2-CYCLE 28 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING Tlchnkal: pecificat on Limit, l2.4secor ds -Slowest Rod Time -Fastest RodTime -+-Average Time Adm in strative l mit,1.68 seconds .-ca-.a ---____ I ___ ---* ---i---* ---/ ./" /)k I.____ / 20 21 22 23 24 25 26 27 28 Cycle Page 18 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report 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. 4]. 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 28, Control Bank B was used as the reference bank. Surry 2 targeted a dilution rate around 1100 pcm/hr for the reference bank measurement. During a previous startup physics testing campaign, a control rod became stuck on the bottom eventually forcing a reactor trip to fix the problem. The 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. 10], 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 S2C28 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 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 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 Page 19 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report 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 fmal 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 -2.3% 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. Page20 of46 BANK B -Reference A c SA SB D Table 3.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH SUMMARY MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE(%) (PCM) (PCM) (M-P)/P X 100 1396 1424 -1.9% 357 363 -6 pcm* 770 807 -4.6% 950 943 +0.7% 921 971 -5.1% 1176 1196 -1.6% Total Bank Worth 5572 5705 -2.3% *Note: For bank worth < 600 pcm, worth difference= (M -P). Page 21of46 1600 ........ 1400 ,....... ,...__ 1200 i 1000 . :S 0 800 Ill I-** OI Cll 600 H 400 . 200 0 0 -Figure 3.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH -HZP ALL OTHER RODS WITHDRAWN l I I I --1--l i _,__ 'II

• I\\ *--* \\ -.. ___ --*-*-,__ I -). I \ I *-,_. J. I .\\ C--* \I \\ *-\l -,. ,_ ,_. I ' *-----* *-'i 11--,.._ I --M-o ----,....._ t--* " 1' r\\ p\ ,_ ;i. I *--e--\ I I r :I.. 1--" ""\, I , r '\. I ,, i I

• I -,; i .... 50 100 150 200 250 Bank (steps) Page 22 of46 12.0 10.0 ..... 8.0 -1.l Ill ...... B S! ii f..I & 6.0 'O 0 rl Ill :rJ ; J.-4 4.0 *<i 0 2.0 0.0 ,__.. ,__ r---Figure 3.2 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH -HZP ALL OTHER RODS WITHDRAWN l l

• 14< I' I I/ I°'" r 1\ I I ' -,_ t--'.. .,__ \ * **--,_ ,__ ., __ .. ' ------,_

• I I _,_ l"t l !'.,,. ,_ l "

• la --Pmdlctod I 1'""-l* ,... I " \ t \ !\ 1 11 j I I ' I/ I I j ! 11 ,.. __ -* 1/ J i I fj i"' , 0 50 100 150 200 250 Bank Position (steps) Page 23 of 46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SECTION 4 -BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power (HZP), 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 4.10.A [Ref. 6] 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. Page24 of46 Table 4.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS BORON ENDPOINTS SUMMARY Control Rod Measured Predicted Difference Configuration Endpoint Endpoint M-P (ppm) (ppm) (ppm) ARO 1632 1648 -16 B Bank In 1448 1442* +6

• 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. Page25 of46 Table 4.2 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2-CYCLE 28 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Difference (M-P) Boron Worth Boron Worth x 100 (pcm/ppm) (pcm/ppm) p (%) -7.59 -7.49 1.3 Page26 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SECTION 5 -TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the ARO condition is measured by controlling the RCS temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate by adjusting feed and letdown :flow rates, and monitoring the resulting reactivity changes on the reactivity computer. Reactivity was measured during the RCS heat up of 3.05°F, followed by the RCS cool down of 3.02°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 ITC 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 ITC value was within the design tolerance of +/-2 pcm/°F. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -1.394 pcm/ °F, a predicted Doppler temperature coefficient (DTC) of -1.82 pcm/°F, and a measurement uncertainty of +0.5 pcm/°F, is +0.926 pcm/°F. It thus satisfies the COLR criteria [Ref. 13] which indicates MTC at HZP be less than or equal to +6.0 pcm/°F. Page27 of46 BANK POSITION (STEPS) D/201 Table 5.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT SUMMARY TEMPERATURE BORON ISOTHERMAL TEMPERATURE COEFFICIENT RANGE(°F) PCM/°F) LOWER UPPER CONCENTRATION HEAT-COOL-AVG. j I DIFFER LIMIT LIMIT (ppm) UP DOWN MEAS I PRED (M-P) 546.47 549.57 1622.0 -1.421 -1.367 -1.394 I -1.642 0.248 I I Page 28 of 46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report 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 49 available locations monitored by the moveable detectors for Cycle 28 power ascension flux maps. As noted in Figure 1.3, one thimble location (R8) was determined to be unusable during the incore checkout and was not attempted during the power ascension flux maps. 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 Energy Virginia-modified version of the Combustion Engineering computer program, CEBRZ/CECOR [Ref. 15, Ref. 16]. CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core. The CECOR GUI (Ref. 17) was used as an interface to CEBRZ and CECOR. A list of the full-core flux maps [Ref. 11] 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 28.81 % power to verify the radial power distribution (RPD) predictions at low power and to ensure there is no evidence that supports the possibility of a core misload or dropped rod. Figure 6.1 shows the measured RPDs from this flux map. Flux Maps 2 and 3 were taken at 71.02%, and 99.80% 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, respectively. 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 +/-5.5% in the 28.81% power map, +/-3.6% in the 71.02% power map, and +/-3.1% in the 99.80% power map. The maximum positive incore quadrant power tilts for the three maps were 1.05%, 0.72%, and 0.86%, respectively. These power tilts are within the design tolerance of2%. Page29 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report The measured FQ(Z) and peaking factor values for the at-power flux maps were within the limits of the COLR [Ref. 13]. Flux Maps 1 through 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. 13]. It is therefore anticipated that the core will continue to operate safely throughout Cycle 28. Page 30 of46 Map Map Description No. Low Power 1 Int. Power 2 Table 6.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS INCORE FLUX MAP SUMMARY Burn up Bank Peak FQ(Z) Hot Hot(2) CoreFz Core Tilt (3) Axial No. Date MWD/ Power D Channel Factor (1) Channel Factor Max --Offset Of (%) -MTU Steps Axial FQ(Z) Axial (%) Thimbles Assy Point Assy Point Fz Max Loe 06/04/17 1.25 28.81 170 F-13126 2.308 F-13 1.552 29 1.379 1.0105 SW 2.178 49 06/05/17 12.8 71.02 197 F-13 26 1.996 F-13 1.493 21 1.229 1.0072 SW 4.387 49 Hot Full Power 3 06/08/17 124.5 99.80 229 F-13 26 1.880 F-13 1.463 29 1.181 1.0086 SW 2.334 49 NOTES: Hot spot locations are specified by giving assembly locations (e.g., H-8 is the core assembly) and core height (in the "Z" direction the core is divided into 61 axial points starting from the top of the core). These flux maps were used for power range detector calibration or were used to confirm existing calibrations. (1) FQ(Z) includes a total uncertainty of 8% (2) includes no uncertainty. (3) CORE TILT -defined as the average quadrant power tilt from CECOR. "Max" refers to the maximum positive core tilt (QPTR > 1.0000). Page 31 of46 Map No. 1 2 3 Table 6.2 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2 -CYCLE 28 STARTUP PHYSICS TESTS COMP ARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak FQ(Z) Hot Channel Factor Hot Channel Factor Meas. Limit Node Margin* Meas. Limit Margin* (%) (%) 2.308 5.000 26 53.8 1.552 1.984 21.8 1.996 3.520 26 43.3 1.493 1.777 16.0 -1.880 2.505 26 25.0 1.463 1.636 10.6 The measured FQ(Z) hot channel factors include 8% total uncertainty. Measured data includes no uncertainty.

• Margin(%)= lOO*(Limit -Meas.) I Limit Page 32 of46 R 1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report p N Figure 6.1 -ASSEMBL YWISE POWER DISTRIBUTION 28.81 % POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Delta % Delta = (M -A)xlOO/A M L K J H G / 0.261/ o.397/ 0.265/ I 0.261/ o.392/ 0.265/ I -0.13/ i.20/ 0.06/ F E / 0.209/ o.658/ i.019/ i.102/ i.011/ 0.660/ 0.209/ / 0.291/ o.664/ 1.090/ 1.114/ 1.005/ 0.660/ 0.290/ I -o.54/ -0.05/ -o.99/ -i.o3/ -0.13/ -0.05/ -o.5o/ D I o.359/ i.002/ i.265/ i.1011 i.200/ i.115/ i.250/ o.996/ o.363/ I o.363/ 1.011/ 1.210/ 1.195/ 1.206/ 1.106/ 1.269/ 1.005/ o.361/ I -1.05/ -o.9o/ -1.00/ -1.19/ -o.5o/ -o.9o/ -0.00/ -0.01\ o.44\ c / o.365/ i.002\ i.212/ i.313/ 1.158/ i.203\ i.141/ i.290/ 1.199/ o.99o/ o.36o/ I o.363/ i.006\ i.221/ i.325/ i.113\ i.225\ i.150/ i.313\ i.215\ i.oo4/ o.363\. J o.45\ -o.36\ -0.12\ -o.92\ -1.25/ -1.03\ -1.44/ -1.13/ -1.35\ -1.35/ -0.11\ B / 0.295/ 1.022/ 1.220/ 1.151\ 1.292/ 1.200/ 1.111/ 1.211/ 1.212/ 1.134/ 1.201\ 1.010\ 0.290\ I 0.292\ 1.011/ 1.221/ 1.151\ 1.306/ 1.301\ 1.139\ 1.299\ 1.300\ 1.156\ 1.225\ 1.011\ 0.294/ J o.97\ i.06/ -0.04/ 0.01\ -i.o9\ -1.42/ -1.95/ -2.10/ -2.12\ -1.93\ -1.96/ -0.12/ 1.39\ I o.669/ i.205/ 1.319\ i.211\ i.066\ i.230/ i.o49\ i.210/ i.051\ i.290/ i.320/ i.290\ o.677\ / o.665\ i.200\ 1.325/ i.301\ i.090\ i.256/ i.019/ i.256\ i.091/ i.312/ 1.336\ i.290/ 0.610/ J o.64/ o.43/ -o.46\ -2.30\ -2.21/ -2.06/ -2.02/ -3.03\ -3.68\ -1.69/ -o.57/ 0.01/ o.98/ A I o.269/ i.101/ i.211/ 1.173\ 1.295/ 1.240\ 1.019/ 0.963/ i.oo5/ i.225\ 1.303\ i.205\ i:221\ 1.119\ 0.215/ 1 / 0.260/ i.o96\ i.201\ i.114/ i.311/ i.261\ i.o39\ o.900\ i.o43\ i.263/ i.320/ i.190\ i.211\ i.102/ 0.210/ / o.49/ o.44/ 0.05/ -0.00/ -i.24/ -1.65\ -1.93/ -2.51/ -3.68/ -2.99\ -i.29/ i.23/ 0.05\ 1.55/ i.04/ J o.395\ i.124/ i.220\ i.211\ 1.145\ i.015/ o.910/ i.010/ o.964/ i.041\ i.130/ i.214/ i.231\ i.159\ o.405/ 0 J o.394\ 1.126/ 1.224/ 1.210\ 1.152/ 1.006/ o.992/ 1.041/ o.993/ 1.001\ 1.154\ 1.212\ 1.226\ 1.120\ o.395/ J 0.23/ -0.14/ 0.29/ 0.00/ -o.63\. -o.90\ -1.45/ -2.10/ -2.94/ -3.12\ -i.42\ 0.10/ o.9o\ 2.14\ 2.62\ J 0.211\ 1.100/ 1.221/ 1.196/ 1.315/ 1.252\ 1.030\ 0.912\ 1.014\ 1.229/ 1.294\ 1.114/ 1.209/ 1.114/ 0.214/ 9 J 0.269/ 1.100\ 1.209\ 1.100\ 1.310/ 1.261\ 1.042/ 0.901/ 1.039\ 1.261\ 1.312\ 1.116\ 1.203\ 1.091\ 0.260\ / 0.11\ 0.11/ o.90\ o.66/ -0.26/ -0.60/ -i.16/ -i.52/ -2.42/ -2.56/ -i.31/ -0.16/ o.53\ 1.53\ 2.01/ / 0.601/ 1.316/ 1.353\ 1.319\ 1.003\ 1.240\ 1.060\ 1.239\ 1.069\ 1.292/ 1.320\ 1.204/ 0.611\ 10 I o.669/ i.201\ 1.333/ i.309\ i.000/ i.254/ i.011/ i.256\ i.o9o\ i.306/ i.326\ i.201\ o.666\ / 1.75/ 2.21/ 1.47/ 0.14/ -o.47/ -i.12\ -0.02/ -1.33\ -i.89/ -i.10/ -o.45\ 0.23/ 0.10/ / o.3oo/ i.o39/ i.246/ i.116/ i.311/ i.303/ i.131/ i.3o4/ i.296\ i.144\ i.223/ i.016\ 0.294\ 11 J 0.293\ 1.015/ 1.222/ 1.153/ 1.291\ 1.296/ 1.131\ 1.306\ 1.301/ 1.151/ 1.221/ 1.012\ 0.292\ 12 13 14 15 / 2.31/ 2.35/ 1.94\ 1.96/ i.o5/ o.51/ -0.03/ -0.10/ -0.00/ -i.11/ 0.19/ o.35/ o.65\ J o.379\ i.025\ i.231\ 1.336\ i.101/ i.246/ i.193/ 1.348/ i.230\ i.031/ o.368/ I o.363/ i.002\ i.212/ i.310\ i.155\ i.222/ i.110\ t.324/ i.220/ i.oo5/ o.363/ I 4.32/ 2.26/ 2.01/ 2.01/ 2.24/ 1.98/ 1.98/ 1.84/ 1.51/ 2.50/ i.32/ I o.369/ 1.025/ 1.296/ 1.211/ 1.241/ 1.239/ 1.335/ 1.042/ o.373/ I o.36o/ i.003/ 1.266/ i.103/ i.203/ i.193/ i.216/ i.010/ o.362/ / 2.42/ 2.16/ 2.35/ 2.05/ 3.65/ 3.84/ 4.6o/ 3.12/ 3.10/ / 0.294/ o.676/ 1.111/ 1.151/ 1.140/ o.697/ o.3o3/ I 0.209/ o.658/ 1.002\ 1.112/ 1.0001 o.663/ 0.291/ / i.02/ 2.19\ 3.24\ 3.46\ 5.55\ 5.01\ 4.00\ I 0.210/ o.400\ 0.201\ / 0.265\ o.391\ 0.261/ / 4.85\ 4.23\ 5.20\ AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.6 STANDARD DEVIATION 1.188 Summary: Map No: 82-28-01 Date: 06/04/2017 Power: 28.81% Control Rod Position: Fo(Z) = 2.308 QPTR: 0.9926 0.9897 D Banlc at 170 Steps pN = 1.552 1.0105 1.0073 Ml Fz = 1.379 Axial Offset(%)= +2.178 Burnup = 1.25 MWD/MTU Page 33 of46 R 1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report p N Figure 6.2 -ASSEMBL YWISE POWER DISTRIBUTION 71.02% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value ;:: Measured, middle value = Analytical, bottom value = % Delta % Delta = (M -A)xlOO/A M L K J H G I 0.2061 o.4241 0.2031 I 0.2051 0.4201 0.2031 I o.341 o.961 0.101 F E I 0.2991 o.6721 i.1001 i.1561 i.o93I o.6631 0.2961 I o.3011 o.6731 i.1021 i.1591 i.0901 0.6101 0.2991 I -o.521 -0.111 -0.191 -0.251 -o.481 -o.981 -o.941 D I o.3611 o.9931 1.2401 1.1051 1.2111 1.1151 1.2361 o.9841 o.3611 I o.3111 1.0001 1.2531 1.1011 1.2011 1.1001 1.2461 o.9951 o.3101 I -2. 63 I -o. 73 I -o.42 I -0.20 I o.34 I -o. 45 I -o. 79 I -1.15 I -2.40 I c I o.3111 o.99ol 1.1921 1.2091 1.1531 1.2011 1.1391 1.2101 1.1111 o.9761 o.3671 I o.3711 o.9961 i.1911 i.2961 i.1611 i.2131 i.1401 i.2061 i.1921 o.9941 o.3721 I -0.111 -0.581 -0.391 -0.511 -0.681 -0.961 -0.801 -0.601 -1.271 -1.791 -1.441 B I o.3011 o.9991 i.1951 i.1401 i.2011 i.2011 i.1241 i.2121 i.2111 i.1261 i.1121 o.9921 o.3021 I o.3001 o.9991 i.1961 1.1431 1.2951 i.2911 i.1311 i.2901 i.2901 1.1421 1.1991 i.0041 o.3021 I 0.491 0.021 -0.131 0.461 -0.631 -1.271 -1.141 -1.391 -1.511 -1.441 -2.231 -1.151 -0.021 I 0.6111 1.2581 1.2911 1.2111 1.1211 1.2521 1.0001 1.2421 1.1031 1.2001 1.2921 1.2511 0.6021 I o.6731 i.2541 i.2941 i.2951 i.1341 i.2611 i.0911 i.2611 1.1341 i.2991 i.3031 i.2611 o.6771 I o.651 o.311 -0.201 -1.371 -i.131 -i.111 -i.021 -1.951 -2.121 -1.491 -0.001 -0.201 0.011 A I 0.2871 1.1131 1.2051 1.1631 1.2911 1.2601 1.0501 0.9991 1.0381 1.2441 1.2921 1.1791 1.2061 1.1301 0.2921 1 I 0.2051 i.1051 i.1911 i.1601 i.3001 i.2111 i.0611 i.0121 i.o64I i.2131 i.3011 i.1141 i.1991 i.1091 0.2061 I o.831 0.121 i.151 0.211 -o.661 -0.031 -i.001 -1.331 -2.421 -2.291 -1.171 o.461 o.591 1.931 2.201 I o.4231 1.1101 1.2241 1.2571 1.1451 1.0951 1.0101 1.0551 o.9991 1.0101 1.1371 1.2551 1.2301 1.1961 o.4301 0 I o.4201 i.1661 i.2201 i.2521 i.1411 i.0901 1.0151 i.0611 i.0111 i.0901 i.1401 1.2541 i.2211 i.1601 o.4211 I o.671 o.371 o.311 o.381 -0.161 -0.261 -0.581 -i.121 -1.731 -2.521 -0.971 0.051 o.761 2.381 2.121 I 0.2001 1.1161 1.2011 1.1031 1.3211 1.2141 1.0611 1.0051 1.0521 1.2591 1.2901 1.1611 1.1951 1.1111 0.2011 9 I 0.2061 i.1001 i.1911 i.1121 i.3051 i.2121 i.o64I i.0121 i.0611 i.2111 i.3001 i.1621 i.1921 i.1061 0.2051 I 0.031 0.151 0.031 o.971 i.251 0.111 -0.291 -o.631 -0.001 -o.941 -0.151 -0.111 0.201 o.961 0.101 I 0.6051 i.2n1 i.3151 i.3001 i.1351 i.2611 i.0051 i.2591 i.1251 i.2051 i.2901 i.2521 0.6121 10 I o.6761 i.2591 i.3011 i.2911 i.1331 i.2661 i.0911 i.2611 1.1351 i.2941 i.2951 i.2541 o.6741 I i.321 1.451 i.091 0.051 0.111 -o.361 -o.521 -o.661 -o.n1 -0.121 -o.371 -0.161 -0.261 I o.3061 1.0161 1.2091 1.1491 1.2951 1.2901 1.1211 1.2931 1.2901 1.1301 1.1931 o.9961 o.3001 11 I o.3021 1.0031 1.1901 1.1411 1.2001 1.2091 1.1361 1.2961 1.2961 1.1431 1.1961 1.0001 o.3011 12 13 14 15 I 1.331 i.261 o.941 o.681 o.511 0.001 -0.111 -0.211 -o.411 -i.131 -0.231 -o.421 -o.3ol J o.3101 i.0031 i.2011 i.291J i.1601 i.225J i.1131 i.310J i.2051 i.0091 o.3651 I o.3111 o.9931 i.1911 i.2041 i.1461 i.2101 i.1591 i.2951 i.1911 o.9961 0.3111 I 1.901 1.021 0.011 o.991 1.201 1.221 1.231 1.111 0.101 1.331 -1.531 I o.3731 i.0031 i.2601 i.1991 i.2401 i.2101 i.29ol i.0191 o.3781 I o.3691 o.9941 1.2441 1.1191 1.2051 1.1061 1.2531 o.9991 o.3111 I 1.141 o.9ol 1.261 1.741 2.091 2.661 2.991 1.981 1.011 I 0.2971 o.6791 i.1101 i.1011 1.1411 o.6961 o.3001 I 0.2991 o.6691 i.o96I i.1501 i.1011 o.6731 o.3001 I -o.591 1.471 2.041 2.541 3.651 3.371 2.791 I 0.2091 o.4311 o.2951 I 0.2031 o.4191 0.2051 I 2.011 2.051 3.561 AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.0 STANDARD DEVIATION 0. 7 8 6 Summary: Map No: S2-28-02 Date: 06/05/2017 Power: 71.02% Control Rod Position: F0(z) = 1.996 QPTR: 0.9967 0.9916 D Bank at 197 Steps pN = AH 1.493 1.0072 1.0045 Fz = 1.229 Axial Offset(%)= +4.387 Burnup = 12.8 MWD/MTU Page 34 of46 R 2 4 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report p N Figure 6.3 -ASSEMBL YWISE POWER DISTRIBUTION 99.80% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Delta % Delta = (M -A)xlOO/A M L K J H G I 0.2941 o.4311 o.2n1 I 0.2951 o.4331 0.2931 I -o.471 -o.351 -o.651 F E I 0.3021 0.6691 1.0931 1.1761 1.0851 0.6631 0.2991 I 0.3041 0.6721 1.0961 1.1801 1.0921 0.6691 0.3031 I -o.541 -o.301 -0.201 -o.311 -0.611 -o.961 -i.111 D I o.3661 o.9761 i.2231 i.1161 i.2031 i.1631 i.2091 o.9661 o.3661 I o.3761 o.9841 i.2291 i.1101 i.2021 i.1121 i.2231 o.9001 o.3741 I -2.641 -0.061 -o.511 -0.101 0.061 -0.191 -i.131 -i.301 -2.001 c I o.3731 o.9741 1.1101 1.2691 1.1481 1.1921 1.1311 1.2511 1.1511 o.9651 o.3111 I o.3761 o.9831 1.1191 1.2761 1.1551 1.2061 1.1431 1.2611 1.1741 o.9011 o.3761 I -0.791 -0.951 -0.741 -0.581 -0.611 -1.121 -1.051 -1.221 -1.481 -1.631 -1.291 B I o.3o31 o.9781 i.1101 i.1321 i.2061 i.2001 i.1311 i.2151 i.2111 i.1191 i.1611 o.9761 o.3011 I o.3o41 o.9841 i.1101 1.1381 i.2941 1.2981 i.1421 i.2921 i.2901 i.1311 i.1011 o.9881 o.3061 I -0.211 -o.651 -0.601 -o.561 -0.611 -0.141 -o.921 -i.291 -1.471 -1.561 -1.691 -i.221 -1.761 I o.6721 i.2211 i.2101 i.2061 i.11s1 i.2151 i.o99I i.2661 i.1621 i.2021 i.2121 i.2291 o.6761 I 0.6121 i.2301 i.2151 i.2951 i.1021 i.2041 i.1001 i.2041 i.1021 i.2901 i.2031 i.2361 o.6761 I -0.071 -0.251 -0.411 -0.731 -0.601 -0.731 -0.861 -1.411 -1.711 -1.231 -0.851 -0.551 -0.051 A I 0.2951 1.1011 i.1051 i.1541 1.2951 i.2011 i.0101 i.0261 i.o69I i.2111 i.2961 i.1691 i.1091 i.1131 0.2991 1 I 0.2941 i.o99I i.1021 i.1551 i.3011 i.2001 i.0041 i.o36I i.0011 i.2091 i.3011 i.1611 i.1091 i.1031 0.2961 I 0.331 0.141 0.211 -0.081 -0.451 -0.511 -0.581 -0.941 -1.621 -1.391 -0.841 0.181 0.011 0.931 1.071 I 0.4351 1.1891 1.2111 1.2451 1.1501 1.1141 1.0371 1.0831 1.0291 1.1011 1.1461 1.2431 1.2151 1.2121 0.4411 0 I o.4341 i.1011 i.2151 1.2451 i.1521 i.1141 i.0401 i.0911 i.o4ol i.1151 1.1531 1.2461 i.2161 i.1001 o.4341 I 0.261 0.171 -0.341 0.041 -0.151 -0.041 -0.311 -0.701 -1.061 -1.281 -0.621 -0.221 -0.121 1.981 1.641 I 0.2911 1.1091 1.1971 1.1161 1.3191 1.2941 1.0001 1.0321 1.0151 1.2051 1.2961 1.1531 1.1001 1.1041 0.2951 9 I 0.2951. 1.1021 1.1881 1.1661 1.3061 1.2891 1.0871 1.0361 1.0841 1.2881 1.3011 1.1571 1.1831 1.1001 0.2951 I 0.121 0.671 0.751 0.851 1.021 0.391 0.101 -0.371 -0.831 -0.201 -0.401 -0.321 -0.221 0.401 -0.031 I 0.6851 1.2601 1.2991 1.3111 1.1901 1.2881 1.1081 1.2801 1.1801 1.2891 1.2691 1.2241 0.6651 10 I o.6751 i.23s1 i.2011 i.2961 i.1011 i.2041 i.1001 i.2041 i.1021 1.2941 i.2151 i.2311 o.6721 I i.471 2.061 1.381 i.161 o.761 0.201 -0.041 -0.201 -0.201 -o.351 -o.491 -o.551 -i.031 I o.3111 i.0031 i.1951 i.1511 i.3011 i.2991 i.1411 i.2901 i.2921 i.1361 i.1111 o.9011 o.3021 11 I o.3osl o.9011 i.1001 i.1361 i.2001 i.2911 i.1411 i.2n1 i.29sl i.1301 i.1101 o.9841 o.3041 12 13 14 15 I i.021 1.581 i.211 1.331 i.011 o.641 -0.011 0.111 -0.211 -0.111 -0.091 -o.341 -o.s11 I o.3001 o.9921 i.1011 i.2021 i.1601 i.2161 1.1671 i.2921 i.1901 o.9931 o.3741 I o.3761 o.9801 i.1131 1.2661 1.1411 i.2031 1.1531 1.2751 i.1191 o.9831 o.3761 I 0.991 1.231 1.201 1.271 1.651 1.121 1.191 1.311 0.921 1.051 -0.541 I o.3101 o.99ol i.2311 i.1011 i.2201 i.2021 i.2601 i.0041 o.3021 I o.3741 o.9791 i.2221 i.1101 i.2011 i.1111 i.2291 o.9841 o.3761 I 1.191 1.111 1.201 1.451 1.551 2.141 3.131 2.041 1.551 I o.3031 o.6761 i.1011 i.2021 i.1211 o.6921 o.3121 I o.3031 o.6681 i.0911 i.1191 i.o9sl 0.6121 o.3041 I -0.101 1.261 1.511 1.951 2.091 2.981 2.5sl I 0.2941 o.4411 o.3021 I 0.2921 o.4331 o.2941 I o.841 1.061 2.111 AVERAGE ABSOLUTE PERCENT DIFFERENCE = 0.9 STANDARD DEVIATION 0.666 Map No: S2-28-03 Control Rod Position: D Bank at 229 Steps Summary: Date: 06/08/2017 Power: 99.80% Fo(Z) = 1.880 QPTR: __ o_.9_9_5_5 -+----0_.9_9_13_ F!:i = 1.463 1.0086 1.0046 Fz = 1.181 Burnup = 124.5 MWD/MTU Axial Offset(%)= +2.334 Page 35of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SECTION 7 -CONCLUSIONS Table 7 .1 summarizes the results associated with Surry Unit 2 Cycle 28 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, technical specification limits, or COLR limits. Based on the results associated with the S2C28 startup physics testing program, it is anticipated that the Surry 2 core will continue to operate safely throughout Cycle 28. Page 36 of46 Table 7.1 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SURRY UNIT 2-CYCLE 28 STARTUP PHYSICS TESTS STARTUP PHYSICS TESTING RESULTS SUMMARY Measured Predicted Diff (M-P) or Design Parameter (M) (P) (M-P)/P,% Tolerance Critical Boron Concentration 1632 1648 -16 +/-50 (HZP ARO), oom Critical Boron Concentration 1448 1442 6 +/-29 (HZP Ref Bank in), oom Isothermal Temp Coefficient -1.394 -1.642 0.248 +/-2 (HZP ARO}, ocm/F Differential Boron Worth -7.59 -7.49 1.3% +/-10% (HZP ARO), ocm/oom Reference Bank Worth 1396 1424 -1.9% +/-10% (B-bank, dilution), pcm A-bank Worth (Rod Swap), pcm 357 363 -6 +/-100 C-bank Worth (Rod Swap}, pcm 770 807 -4.6% +/-15% SA-bank Worth (Rod Swap), pcm 950 943 0.7% +/-15% SB-bank Worth (Rod Swap), pcm 921 971 -5.1% +/-15% D-bank Worth (Rod Swap}, pcm 1176 1196 -1.6% +/-15% Total Bank Worth, pcm 5572 5705 -2.3% +/-10% S2C28 Testing Time: 7.0 Hrs [criticality 06/03/2017 @03:59 to end of testing 06/03/2017@ 10:56] Recent Startups: S1 C28 testing time: 5.8 hrs S2C27 testing time: 7.6 hrs S1C27 testing time: 5.6 hrs S2C26 testing time: 7.2 hrs S1C26 testing time: 7.8 hrs S2C25 testing time: 6.1 hrs S1C25 testing time: 5.7 hrs S2C24 testing time: 7.1 hrs S1 C24 testing time: 7.0 hrs S2C23 testing time: 9.4 hrs S1 C23 testing time: 6.2 hrs Page 37 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report SECTION 8 -REFERENCES 1. W. A. Peterson, "Surry Unit 2, Cycle 28 Design Report," Engineering Technical Evaluation ETE-NAF-2017-0059, Rev. 0, May 2017. 2. B. R. Kinney, "Surry Unit 2 Cycle 28 Full Core Loading Plan," Engineering Technical Evaluation ETE-NAF-2016-0144, Rev. 0, January 2017. 3. B. R. Kinney, "Surry Unit 2 Cycle 28 Startup Physics Testing Logs and Results," Memorandum MEMO-NCD-20170017, Rev. 0, June 2017. 4. T. S. Psuik, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," Topical Report VEP-FRD-36-Rev. 0.3-A, February 2015 [Included in Technical Report NE-1378, Rev. 2 as Attachment B]. 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. Surry Units 1 and 2 Technical Specifications. 7. D. J. Agnew, "Rod Drop Text Computer Users Guide and SQA Paperwork," Engineering Technical Evaluation ETE-NAF-2014-0118, Rev. 0, April 2015. 8. B. J. Vitiello and G. L. Darden, "Implementation of the Westinghouse 15x15 Upgrade Fuel Design at Surry Units 1 and 2," Engineering Technical Evaluation ETE-NAF-2010-0080, Rev. 0, January 2011. 9. M. P. Shanahan, "Implementation of RMAS version 7 at Surry Units 1 and 2," Engineering Technical Evaluation ETE-NAF-2014-0021, Rev. 0, May 2014. 10. 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-2006-0046, Rev. 0, May 2006. 11. D. T. Smith et al, "Surry Unit 2 Cycle 28 Flux Map Analysis," Calculation PM-1890, Rev.O, and Addenda A-B, June 2017. 12. Nuclear Engineering Standard DNES-AA-NAF-NCD-5007, Rev. 3, "Startup Physics Tests Results Reporting," July 2016. 13. B. T. Miller, "Reload Safety Evaluation Surry Unit 2 Cycle 28 Pattern PRI," EV S2C28, Rev. 0, April 2017. 14. S. B. Rosenfelder, "Surry Unit 2 Cycle 28 Hot Rod Drops, Startup Physics Testing and Flux Map Post-Job Critique," MEMO-NCD-20170019, Rev. 0, June 2017. 15. C. J. Wells and J. G. Miller, "The CEBRZ Flux Map Data Processing Code for a Movable core Detector system," Engineering Technical Evaluation ETE-NAF-2011-0004, Rev. 0, March2011. Page 38 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report 16. A. M. Scharf, "The CECOR Flux Map Analysis Code Version 3.3 Additional Software Requirements and Design," Engineering Technical Evaluation ETE-NAF-2013-0088, Rev. 0, November 2013. 17. A. M. Scharf, "Qualification and Verification of the CECOR-GUI," Engineering Technical Evaluation ETE-NAF-2013-0081, Rev. 0, November 2013. 18. J. A. Cantrell, "Surry Unit 2, Cycle 28 TOTE, Core Follow, and Accounting Calculations," Calculation PM-1889, Rev. 0, May 2017. 19. A. K. Lafrance, "Evaluation of Surry Unit 2 Cycle 27 Incore Tilt," Engineering Technical Evaluation ETE-NAF-2016-0019, Rev. 0, April 2016. 20. T. S. Psuik, "Implementation of Changes to the Allowable Power Level for the Initial Startup Flux Map for Surry Units 1 and 2," Engineering Technical Evaluation ETE-NAF-2015-0007, Rev. 0, April 2015. Page 39 of46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report APPENDIX-STARTUP PHYSICS TEST SUMMARY SHEETS Page 4.0 of 46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report s¥rry Power S!aUon Unit 2 Cycle 28 Startup Physics T.:ist Summary Sheet* Fonnal Tests (Page 1 of 6) Measured Value ..._,_-"-_amps 7f. >'U-lfB',1Jicm {measured reactivity) P1"" 11.tl.Z!il -'!:{t. 601 pcm (predicted reactMty) %0 = {(pc* pt)lpt} x '100% %0 == -o, l/i 9£ 1-1. Design Criteria background < ZPTR < POAH backbround = l./. l/ 6: e.. '." I J amps POAM"' i lfCPo 4 pJ!pJI x 100% :> 4.0%1 The range ls set to the larger of the meailured orthe pre-cr1tlcal bench test I ! Prejritlcal Bench Test Results .J 11.o/-/Oopcm . Altowabl<i range -t I z.o I -l co pcm i Acceptance Criteria N/A .Date! Oesig11. Acceptance Time of Preparer/ Criteria Met Criteria Met Reviewer Test N/I\ No Vves 6/.Jln IJAfi/ No NIA /(L[< (a/"'0)1Nl.O"' pcm/'F (N. 1 * £ LJ-11. +/- 2 pcm/"F .... TjJAP.Q-I ! ' = I i 16REF,,,Z 1424 +/- 10% i pcm i100x(Meas.

• Des.)JDes."' ... 1.9 % References 1.} DNES-AA-NAF-NCD4015, Rev. 3 2.} Rev. 0 3.) gTE-NAF-2017-0058, Rev. 0 ' 1'1Ce XA{Cs)i;.'\ol :S: 1000 pcm [f.S. 4.10.A] a/SO S: a.wJlm <<T m'11! + a; a.,180:,,; 3.680 pcmf'F where: 6.0 pcmf"F .[COLR 3.4] (r,i.;'"!:<!)1; 0.5 pcmrF (a.r°0P)2; -1.82 pcm/"F NlA Page 41of46 ___..L Yes V Yes No Yes No V Yes __ No Ni A /(Lr/(

Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Surry Power Station Unit 2 Cycle 28 Startup Physics Test Summary Sheet-Formal Tests (Page 2 of 6) l Measured Value Design Criteria , (l1oi.i)a" * $'?C +/- 10% I 100x(Meas. -Des.)JOes. = -:(?. % References 1.)jDNES-AA-NAF-NCP-4015, Rev. 3 2.)fETE-NAF-2017-0059, Rev. 0 3.)jETE-NAF-2017--0058, Rev. 0 Acceptanca Criteria Date/ Design Acceptance Time of Preparer/ Criteria Met Criteria Met Reviewer Page 42 of 46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Surry Power Station Unit 2 Cycle 28 Startup Physics Test Summary Sheet-Formal Tests (Page 3 of 6) Measured Value Design Criteria q:;::' "" '""' *'.*>* *.,;; .:.;, ,,; "'-< *.:: ... *1'>":<.=* .. * .,, '-< -",; __ ,._ Map Power level (% Full Power) ...,;p. ;r/ Max Relative Assembly Power, %DfFF (M*P)/P +/-10% for P1 <!:0.9 %DIFF= %forPi;;;;0.9 +/-15% for P;<0.9 5:3 %forP1<0.9 {P1 = a$$Y po<<ver)1*2 Nuclear Enthalpy Rise Hot Channel Factor, FAH(N) Fti.H(N)= /,sS2-NIA Total Heat Flux Hot Channel Factor, FQ(Z) Peak F0(Z) Hot Channel Factor= .:2,13 0 8' NIA Maximum Positive lncore Quadrant Power Tilt Tilt= L,o/o.$'" :;; 1.021 References 1.) DNES-AA-NAF*NCD-4015, Rev. 3 2.) ETE-NAF-2017-0059, Rev. 0 3.) ETE-NAF-2017-0058, Rev. 0 Design Acceptance Date/ Preparer[ Acceptance Criteria Time of Criteria Met Criteria Met Test Reviewer ... "'" . ' " -"'" "'" "'Xi:i1;;t;}::;>;::;V;f; 6/1/17 /(11( .L_ves o9! "-1 NM& NIA No NIA --* / Yes Fi1H(N):;1.635(1+0.3(1-P)) {COLR 3.7] NIA --No ___L_ Yes Fo_{Z}so*K(Z) {COLR 3. 7] NIA --No L_ves N/A NIA No --Page 43 of 46 Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Surry Power Station Unit2 Cycle 28 Startup Physics Test Summary Sheet-Formal {Page 4 of G) Measured Value Date/ Design Acceptance Time of Preparer/ Criteria Met Criteria Met Reviewer Te$t Design Criteria Acceptance Criteria Map Power Level (% Full Power)= I l

• O"Z. rM_a_x_R_e_1_at_iv_e_A_ss __ e_m_b_ly __ ______________ _J.L_ Yes 0'1...l'-\ %01FF= 13.. % for Pi 2':0.9 S. 6 % for P1oc:0.9 +/-15% for P1<0.9 (Pi= assy power)1.Z Nuclear Rise Hot Channel Factor, FAH(N} F11H(N)'" \ .11, 93. ! Total HotChannel Factor, FQ(Z) Peak F 0(Z) Hot C factor= I. t:tq a Maximum Posl ive. lncore Quadrant Power Tilt NIA N/A References 1.) DNES-AA-NAF-NCD-4015, Rev. 3 2.) ETE-NAF-2017-0059, Rev. 0 3.) ETE-NAF-2017*0058, Rev. 0 NIA FLIH(Nr--1.635(1+0.3(1-P)) (COLR 3.7} F0(Z):>{2.5/P}*K(Z) [COLR 3.7J NIA Page 44 of46 No NIA 7 Yes NIA No _.L._ Yes NIA No _:L__Yes NIA No

, .. ' .** .... Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report ....... .Station Unit 2 *cycle 28 Startup Physics Test. Summary Sheet -formal Tests (Page 5 of6)_. *l ** . * . D

• A tan Data/ p f i . M: ; . ' .. "" , .. , .,. . ..,_,,. **:-; **;;;;;i '"'" ' .. /' " ,, ........... " *.* ... .-*"'*. v.-:* Map Pow-:irlavet (%.Full Max Relative Assembly f>cwer, %DIFF iM*P)/P ; I l%DlfF= 1 .. I % tor Pi *1 *---. I . /. . . ; . .E., 0 .% for P1.:0.9 +/-1.5% to: Pj<0.9 ... * ; (Pr *'assy ' ! -Nuclear Enthalpy Ri$eHotChannei Fact.er. Ft\H(N) ; .,., iFAH<Nt"' ' . . * *

• u .. i$J . .. :wA WA tiH 1+0.$(1-P.l} 3.7} .... **.* ' *** .. .. *. i._:;** ...* " ** VYas __ >>No* NIA *. "'.* .. i: .. * ';.. ** NIA ! __ No Total Heat Flu>< Hot f.Q(Zj , *' .. ' .. **:* : .* ,.. .., ............. ...... ...._ ...... _...,..... __________

• V'Yes Peak F 0(Z) Hot Cha,nnel .* . * * ;* * )!fA '.-" Maximum P.ositivelncore QmldrantPower Tilt Ti!t,. o .ct:oZ L-u s1.021 References t) Rev. 3 2.} ETE-NAF..:2017-0059; Rev. 0 3.) ETE-'MAF-2017-u058_,:Rev.O Fa(Z)s{2,5!P},K(Z) [COl.R3.7j NIA Page 45 of46 NIA '< **:.. A_:. * ... *, .;*' V Yes NIA No * .. *-** ii :1 " } .* ... ' l ,.

Serial No.17-330 Docket No. 50-281 S2C28 Startup Physics Tests Report Surry Power Station Unit2 Cyc1e*2a Startup Physics Test Summary Sheet-Formal Tests (Page.6 of6k l f I .* ....... **.' . * *-** *** :'"1 ' Measured Value * .

• _,.. *-,* ... Acceptanee Criteria -* --.,. * '1 * **': -* : *

• Design; Acceptance Dater Preparer/ Criteria Met Criteria Met Reviewer Froiai"'. . *NIA gpm References 1.) DNES*AA*NAF-NCD-4015, Rev. 3 2.) Rev. 0 3.) ETE-NAF-2017*0058, Rev. 0 . . . i ;:: 274000 gpm (COLR 3.8] ... Page 46 of46 --*Yes '-fsM * -!'[Q :. io *Q . :\ . ,! '.*.