Text

Re Cycle 27 Startup Physics Tests Report
	ML16112A251
Person / Time
Site:	Surry
Issue date:	03/07/2016
From:	Huber T; Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	16-071
	Download: ML16112A251 (50)
	v • d • e

Dominion Resources Services, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 March 7, 2016 United States Nuclear Regulatory Commission Serial No.: 16-071 Regional Administrator- Region II NLOS/GDM Marquis One Tower Docket No.: 50-281 245 Peachtree Center Ave., NE Suite 1200 License No.: DPR-37 Atlanta, Georgia 30303-1257 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 27 STARTUP PHYSICS TESTS REPORT As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 2 Cycle 27 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 27 on December 1, 2015. 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,

,--:--R~Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Ms. K. R. Cotton Gross NRC Project Manager- Surry U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.16-071 Docket No. 50-281 Enclosure SURRY UNIT 2 CYCLE 27 STARTUP PHYSICS TESTS REPORT February 2016 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit 2

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 avrulable, 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 from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure TABLE OF CONTENTS Classification/Disclaimer ...............................................................................................................1 Table of Contents ........*..................................................................................................................2 List of Tables .....................................................................................................................*............3 List of Figures .................................................................................................................................4.

Preface ............................................................................................................................................. 5 Section 1 - Introduction and Summary .....................................................................................6 Section 2 - Control Rod Drop Time Measurements ............................................................... 15 Section 3 - Control Rod Bank Worth Measurements ............................................................20 Section 4 - Boron Endpoint and Worth Measurements ........................................................25 Section 5 -Temperature Coefficient Measurement ...............................................................28 Section 6 - Power Distribution Measurements .......................................................................30 Section 7 - Conclusions .............................................................................................................38 Section 8 - References .................................................................................................. ~ ............ 40 Appendix - Startup Physics Test Summary Sheets ................................................................ 41 Page 2 of 47

Serial No.16-071

Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 ...........................................................39 Page 3 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 Figure 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 45.40% Power .............*................................34 Figure 6.2 - Assemblywise Power Distribution 71.14% Power ..............................................35 Figure 6.3 - Asseniblywise Power Distribution 73.14% Power ..............................................36 Figure 6.4 - Assemblywise Power Distribution 99.88% Power ..............................................37 Page 4 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure PREFACE This report presents the analysis*and evaluation of the physics tests that were performed to verify that the Surry Unit 2 Cycle 27 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. 2 [Ref. 12]. It is not the intent ofthis 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 2 Cycle 27 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 I 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.

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure SECTION 1-INTRODUCTION AND

SUMMARY

On October 19, 2015, Unit No. 2 of Surry Power Station completed Cycle 26 and began refueling [Ref. 1]. During this refueling, 64 of the 157 fuel assemblies in the core were replaced with fresh Batch S2/29 assemblies [Ref. 1]. The Cycle 27 core consists of 5 sub-batches of fuel:

two fresh batches (S2/29A and S2/29B), two once-burned batches (S2/28A and S2/28B), and one twice-burned batch (S2/27B). Like S2C26, S2C27 will have a full core of the 15x15 Upgrade Fuel Design [Ref. 1].

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 batches S2/28 and S2/29 includes Westinghouse's Robust Protective Grid (RPG) and modified Debris Filter Bottom Nozzle (mDFBN), unlike the Upgrade fuel used for batch S2/27. S2C27 will be the first Surry Unit 2 cycle to utilize the Westinghouse Integral Nozzle (WIN), top nozzle design to reduce the potential for spring screw failures in the top nozzle [Re£ 1].

This cycle uses Westinghouse's Integral Fuel Burnable Absorber (IFBA) fuel product.

The IFBA design involves the application of a thin (0.0003125 inch) 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 ':'oi~ 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].

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Cycle 27 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 a double layer of stainless steel cladding. There are no thimble plugging devices in S2C27. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 27 core.

Three reactor coolant pumps were replaced during the S2C26-S2C27 refueling outage.

Further information on this replacement can be found in Reference 13.

The S2C27 full core loading plan [Ref. 2] is given in Figure 1.1, and the beginning of cycle fuel assembly burnups 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 27 core [Ref. l].

According to the Startup Physics logs, the Cycle 27 core achieved initial criticality on December 1, 2015 at 04:35 [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 S2C27 Startup Physics Testing. The tests performed are the same as in previous cycles. A summary of the test results follows.

~ --- --*------ - -----------------------------------------------

After zero power physics testing, the reactor was shut down at 13 :00 on

,December 1, 2015 for maintenance. The unit returned to critical at 16:35 on December 10, 2015, and reached full power on December 18, 2015 at 05:00.

The measured drop time of each control rod was witqin the 2.40 seconds Technical Specification [Ref. 6] limit, as well as the Surry Unit 2 1.68 seconds 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. 1O]. The sum of the individual measured control rod bank worths was Page 7 of 47

Serial No.16-071 DocketNo. 50-281 S2C27 Startup Physics Tests Report Enclosure within -2.0% 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-5.2% of the design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within+ 16.8 pcm of the design prediction.

These results are within the design tolerances of +/- 15% for individual banks worth more than 600 pcm (+/-I 0% for the reference bank worth), +/-I 00 pcm for individual banks worth 600 pcm or less, and +/-I 0% 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% Afdk:

of the design prediction. The boron worth coefficient measurement was within +0.8% of the design prediction, which is within the design tolerance of +/-I 0%.

The measured isothermal temperature coefficient (ITC) for the ARO configuration was within +0.053 pcm!°F of the design prediction. This result is within the design tolerance of +/-2.0 pcm/°F.

The zero power physics testing results were within the criteria established in Reference

_ _ _ ______..O_pennitting_the__ firsLflux_map_to_b_e_p_erforme_d_Jip_to_ __5_0_%_p_o_w_er_(yer_s_u_s_3_.0%_p_Qwe_r_ if the_________

criteria were not met).

Core power distributions were all within established design tolerances. The measured assembly power distributions were within +/-8.0% of the design predictions, where an 8.0% -

maximum difference occurred in the 45.40% power map. The heat flux hot channel factors, FQ(Z), and enthalpy rise hot channel factors, F~, were within the limits of the COLR [Ref. 13].

None of the power ascension flux maps were within the maximum incore quadrant power tilt design tolerance of 2% (QPTR .:S 1.02). The maximum incore quadrant power tilts ranged from 2.45% to 3.44% during the power ascension. NAF performed an additional assessment to Page 8 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure confirm that the measured quadrant tilts were bounded by the current safety analysis. The larger than normal tilt is still under investigation at the time of this report [Ref. 18].

The total RCS Flow was successfully verified as being greater than 273,000 gpm and greater than the limit in the COLR (274,000 gpm), as required by Surry Technical Specifications

[Ref. 6]: The total RCS Flow at nominal conditions was measured as 289,584 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.

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Serial No.16-071 Docket No~ 50-281 S2C27 Startup Physics Tests Report Enclosure Table 1.1 SURRY UNIT 2 - CYCLE 27 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 11/30/15 17:45 HSD 2-NPT-RX-014 Reactivity Computer Checkout 12/01/15 05:45 HZP 2-NPT-RX-008 Boron Endpoint - ARO 12/01/15 05:45 *HZP 2-NPT-RX-008 Zero Power Testing Range 12/01/15 05:45 HZP 2-NPT-RX-008 Boron Worth Coefficient 12/01/15 10:20 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 12/01/15 05:48 HZP 2-NPT-RX-008 BankB Worth 12/01/15 07:15 HZP 2-NPT-RX-008 Boron Endpoint - B in 12/01/15 10:20 HZP 2-NPT-RX-008 Bank A Worth - Rod Swap 12/01/15 09:55 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap 12/01/15 09:55 HZP 2-NPT-RX-008 Bank D Worth- Rod Swap 12/01/15 09:55 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 12/01/15 09:55 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap 12/01/15 09:55 HZP 2-NPT-RX-008 Total Rod Worth 12/01/15 09:55 HZP 2-NPT-RX-008 Flux Map - less than 50% Power* 12/12/15 04:59 45.40% 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 12/13/15 14:49 71.14% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008

--- *--&-Pewer-Range-Galibration - - - - - - - - - - * - - - - - ----,-- - ----- - NPT-RX-005---

2-GEP.,.RX-001 Flux Map - 95% - 100% Power 12/21/15 08:36 99.88% 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 12/18/15 05:00 HFP 2-NPT-RX-009

Results ofzero power physics testing permitted the first flux map to be performed up to 50%

power (versus 30% power if specific criteria were not met).

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 1.1 SURRY UNIT 2 - CYCLE 27 CORE LOADING MAP ETE-NAF-2015-000S, Rev. 0 A.ttachment l PAGE l Of l VEP-NES-NAF R p M L K J H G F E D c B A l

49Y 656 47Y RCC RCC RCC 2 43Y 26Y 743 754 748 21Y 40Y RCC RCC 3 41Y 735 758 708 648 713 762 740 32Y RCC RCC SSS RCC RCC 4 34Y 750 701 531 607 617 604 640 706 756 39Y RCC RCC 5 44Y 738 716 646 624 723 644 720 626 645 710 733 42Y RCC RCC RCC RCC *Rec RCC RCC 6 25Y 764 642 621 731 612 652 605 726 623 636 760 28Y RCC RCC RCC RCC 7 SlY 747 705 601 718 611 654 729 657 610 724 613 703 744 45Y RCC RCC RCC RCC 8 658 755 632 520 630 653 727 625 732 650 637 619 634 751 660 RCC Rec RCC RCC 9 46Y 741 712 606 722 616 &61 725 659 615 719 608 715 746 SOY RCC RCC RCC RCC F.CC RCC RCC 10 27Y 759 639 622 730 614 651 602 72S 628 643 757 24Y RCC RCC 11 31Y 737 714 641 627 717 633 721 629 647 709 736 33Y RCC RCC $$9 RCC RCC 12 30Y 752 707 635 603 618 603 638 704 753 37Y INCORE DlWICE DESCRJ:PTIONS: RCC RCC 13

.Rec- PULL LENG'l'l;r CONTROL ROD 3BY 739 761 702 649 711 763 734 36Y SS~- Seocndar-; Source Assembl.y RCC RCC RCC 14 35Y 22Y 745 749 742 23:< 29Y 15

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 1.2 SURRY UNIT 2 - CYCLE 27 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWD/MTU)

R p N M L K J H G F E D c B A 1 I 42.991 22.701 42.981 I MEASURED I 1 I 42.84 I 22.67 I 42.031 I PREDICTED I 2 I 42.651 39.201 0.001 0.001 0.001 39.661 42.641 I 42. 70 I 39. 41 I o. oo I o. oo I o. oo I 39. 40 I 42. 711 I 40.201 0.001 0.001 0.001 19.191 0.001 0.001 0.001 40.331 I 40.481 0.001 0.001 0.001 10.951 0.001 0.001 0.001 40.431 4 I 41.141 0.001 0.001 19.551 23.761 23.981 23.881 19.141 0.001 0.001 41.141 4 I 41.lOI 0.001 0.001 19.161 23.721 23.861 23.891 19.201 0.001 0.001 41.181 I 40.571 0.001 0.001 20.941 24.011 0.001 19.661 0.001 24_221 20.371 0.001 0.001 40.361 I 40.651 0.001 0.001 20.371 23.991 0.001 19.471 0.001 23.971 20.301 0.001 0.001 40.681 I 39.231 0.001 19.381 23.761 0.001 23.371 21.641 23.831 0.001 23.821 19.291 0.001 39.181 I 39.381 0.001 19.211 23.981 0.001 23.471 21.471 23.441 0.001 23.961 19.201 0.001 39.401 7 I 43.111 0.001 0.001 24.111 0.001 23.741 23.121 0.001 22.611 23.3ol 0.001 23.911 0.001 0.001 42.661 I 42.W3I 0.001 0.001 23.881 0.001 23.461 22.571 0.001 22.651 23.461 0.001 23.871 0.001 0.001 42.811 8 I 22.741 0.001 19.501 23.871 19.681 21.991 0.001 23.00I 0.001 21.781 19.681 23.731 19.511 0.001 22.921 I 22.651 0.001 19.471 23.841 19.501 21.641 0.001 23.141 0.001 21.641 19.531 23.841 19.441 0.001 22.661 I 43.021 0.001 0.001 24.071 0.001 23.691 22.661 0.001 22.561 23.481 0.001 24.001 0.001 0.001 42.711 I 42.811 0.001 0.001 23.931 0.001 23.461 22.661 0.001 22.551 23.461 0.001 23.931 0.001 0.001 42.831 10 I 39.491 0.001 19.331 23.981 0.001 23.471 21.511 23.451 0.001 23.901 19.111 0.001 39.261 10 I 39.391 0.001 19.191 23.961 0.001 23.441 21.461 23.471 0.001 23.991 19.201 0.001 39.391 11 I 40.571 0.001 0.001 20.511 23.911 0.001 19.621 0.001 23.701 20.301 0.001 0.001 40.691 11 I 40.681 0.001 0.001 20.381 23.981 0.001 19.511 0.001 24.00I 20.371 0.001 0.001 40.651 12 I 41.131 0.001 0.001 19.231 23.851 23.711 24.121 19.131 0.001 0.001 41.141 12 I 41.201 0.001 0.001 19.211 23.841 23.851 23.781 19.161 0.001 0.001 41.121 13 I 40.281 0.001 0.001 0.001 18.941 0.001 0.001 0.001 40.551 13 I 40.451 0.001 0.001 0.001 18.911 0.001 0.001 0.001 40.461 14 I 42.481 39.081 0.001 0.001 0.001 39.181 42.451 14 I 42.n1 39.411 0.001 0.001 0.001 39.421 42.701

- -- --- --15 ---- - - ------------ - -=--==----=~====r~~~~,~~;;1-~;~~~1-------------- 15 1 42.831 22.661 42.841 Page 12 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 1.3 SURRY UNIT 2 - CYCLE 27 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R p N M L K J H G F E D c B A MD 2

MD 3

MD MD MD MD 4

MD MD MD 5

MD MD MD MD MD MD 6

MD MD MD 7

MD MD MD MD MD 8

MD MD MD MD MD MD 9

MD MD MD MD 10 MD MD MD MD 11 MD MD MD MD

- - --- -* --- -. . -* - -- - -- - - ----- -~--- --- - - - - ---- .. --- -- - -- --- ----12**----- ---- ---

MD MD MD MD 13 MD MD 14 MD MD 15 MD MD - Moveable Detector Page 13 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure IA SURRY UNIT 2 - CYCLE 27 CONTROL ROD LOCATIONS R p N M L K J H G F E D c B A 180° 1

A D A 2 SA SA 3 c B B c 4 SB SB 5

,A B D c D B A 6 SA SB SB SA 7 90° D c c D 270° 8 SA SB SB SA 9 A B D c D B A 10

- - -- - --*--*- - ---~ - ----- - - ---- - - - - ~*---* -- ------ - - - - - - ---- - - - - -

SB SB 11 c B B c 12 SA SA 13 A D A 14 15 D = Control Bank D SB = Shutdown Bank SB C = Control Bank C SA= Shutdown Bank SA B = Control Bank B A = Control Bank A Page 14 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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-014. This verified that the time to entry of a rod into the dashpot region was less thari or equal to the maximum allowed by Technical Specification 3.12.C.1 [Ref. 6].

Surry Unit 2 Cycle 27 used the Rod Drop Measurement Instrument (RDMI) instead of the rod drop test computer (RDTC) [Ref. 7]. The rod drop times were measured by withdrawing all banks to their *fully withdrawn position and dropping all 48 control rods by opening the reactor trip breakers. This allowed the rods to drop into the core as they would during a plant trip.

The current methodology acquires data using the secondary rod position indication (RPI)

coil terminals (/3 & /4) on the Computer Enhanced Rod Position Indication (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.

__.________ .h._typjc~l rod drop trace for S2C27 is shown in FiID!!:e 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 20-27. Technical Specification 3.12.C.1 [Ref. 6] specifies a maximum rod drop time to d?shpot entry of 2.4 seconds for all rods. These test results satisfied this TechnicatSpecifi9atio.n 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 rod drop times were slower than S2C26 by an average of 0.06 seconds, which is attributed to use of the new RDMI (data analyzed for previous cycles with RDMI also gave similar slower rod drop times [Ref. 14]).

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report

- Enclosure Table 2.1 SURRY UNIT 2- CYCLE 27 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME B-06 1.43 sec. K-04 1.31 sec 1.35 sec.

---------- ------------------~--------------

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 2.1 SURRY UNIT 2-CYCLE 27 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE 5

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Page 17 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 2.2 SURRY UNIT 2 - CYCLE 27 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

2 1.348 1.340 1.344 3

1.352 1.356 4

1.340 1.312 1.364 1.360 5

1.332 1.346 6

1326 1.336 1.342 1.350 1.426 1.326 1.432 7

1.344 1.352 1.340 1.356 8

1.330 1.332 1.328 1.368 9

1.360 1.338 1.334 1.336 10 1.348 1.330 1.348 1.350 1.372 1.342 1.366 11 1.346 1.362 12

- -- -- - -- - - - 1.340 _l.33_0 1.332 1.338 13 1.338 1.360 14 1.386 1.338 1.364 15 Ix.~ 1--> Rod drop time to dashpot entry (sec.)

Page 18 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 2.3 SURRY UNIT 2 - CYCLE 27 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 2:.50 Tee nfcal1Spec fication l!...i rrnit;.Z.4sec nnds 2.30 2.20 2.10 2.00

-+--Silowesl:RadTllll"le

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.____ ~

1.101 26 21 22 24 25 26 27 Cycle Page 19 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 re.active 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 27, Control Bank B was used as the reference bank. Surry 2 targeted a dilution rate of 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. 1O],

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 S2C27 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

____________ _A!t~r ~c:n~p~tio_~ ofth~!~~ere~~-e~~-!e~~~i_vity ~~-~ ~ea~1:1!~me!_lt, !]:i~ !~-~ct9!"_~~0Jant system temperature and boron concentration were stabilized with the reactor critical and the reference bank near its full ipsertion. Initial statepoint data* (core reactivity and moderator temperature) for the rod swap maneuver were next obtained with the reference bank at its fully inserted posi!ion 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 Page 20of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 Sumri:iary 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 refe~eJ:!C~ ban)c, +/- ! 5o/()_for_!e~j__Q~s of worth ~eater than 600 pcm, and +/-I 00 pcm for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was within -2.0% 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 21of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 3.1 SURRY UNIT 2- CYCLE 27 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM) (PCM) (M-P)/P X 100 B - Reference 1398.7 1426.3 -1.9%

A 218.9 202.1 +16.8 pcm*

c 872.7 919.8 -5.1%

D 941.4 960.8 -2.0%

SA 993.3 965.6 +2.9%

SB 1111.9 1173.4 -5.2%

Total Bank Worth 5536.9 5648.1 -2.0%

Note: For bank worth< 600 pcm, worth difference= (M- P).

Page 22 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 3.1 SURRY UNIT 2- CYCLE 27 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600 I I I I I I

L-*

- --- ,. I 1400 'r--....

...,,r-.... I"\

I\\

\

1200

\'

I ,\

\&

ip. 1000 ~\

!\'\

5M I ~Ila

(\

~ I l==J i~*

~ 800 ti A1

'\

m \""

r-l 41! ' ill k \,'

tn

~ 600 '\I

~

i I~

H

- --- -- --- -- -- -- - - *- - --- - -~'.IL - - -- - - - - _, .. -- - -

I \; '

,\.

t[\

400 I\\

1\\_

~\

I - I~

t 200

~I

' ..' II

'l ,,_

0 0 50 100 - 150 200 250

Sank Position (steps}

Page 23 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 3.2 SURRY UNIT 2- CYCLE 27 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12.0 l

ItI\\.

10.0

i ~

~

I\

1\ ~

~~

I-

....... ~~-

g. 8.0

,iJ

~

i:t 0

.....p, i

~-

\)1 J

I

ik I I

' *~ ~..._ .....-

~ ' ""' ...., -MaasUfiid 6.0 ...-~

.: \

'ti ,Iii"" ....... -p~

~ 1i.,

. J

~

0i:: I \

al k

al I

I~

I I l'I

- - -- - -~

I 4.0

rl Cl \ I I

i J I I I * -

2.0

_J - I

'}

I I r I

J/

0.0 j( l 0 50 100 150 200 250

Sa.pk Position (steps}

Page 24 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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.

Page 25of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 4.1 SURRY UNIT 2- CYCLE 27 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 1554.l 1578 -23.9 B Bank In 1370.1 1365.1 * +5.0

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 47

Serial No.16-071 DocketNo. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 4.2 SURRY UNIT 2 - CYCLE 27 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Percent Difference Measured Predicted Boron Worth Boron Worth (M-P) p x 100 (pcm/ppm) (pcm/ppm)

(%)

-7.60 -7.54 0.8

~------- - - - - - - - - - - - -------------- ---~ - -- --- -*- - - - -

Page 27 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure SECTION 5 -TEMPERATURE COEFFICIENT MEASUREMENT The 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 3.26 °F, followed by the RCS cool down of 2.91 °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 -2.412 pcm/ °F, a predicted doppler temperature coefficient (DTC) of -1.83 pcm/ °F, and a measurement uncertainty of +0.5 pcm/ °F, is -0.082 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.

Page 28 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 5.1 SURRY UNIT 2 - CYCLE 27 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

TEMPERATURE ISOTHERMAL TEMPERATURE COEFFICIENT BANK BORON RANGE(°F) (PCM/°F)

CONCENTRATION -- ----

POSITION (STEPS)

I LOWER UPPER (ppm)

HEAT- I COOL- I AVG. I I DIFFER LIMIT ! LIMIT UP I DOWN i MEAS i PRED (M-P)

I i I I I !

I I D/207 547.28 I 550.56 1547.3 -2.201 -2.624 -2.412 -2.465 I 0.053 I I I I I Page 29 of 47

Serial No.16-071

Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 Cycle 27 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-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 45.40% 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 through 4 were taken at 71.14%, 73.14%, and 99.88% power, respectively, with different control rod

- configurations. - Flux:- .maps--2 and-4 were taken to check -at-power design- predictions and -to-------- --

measure core power distributions at various operating conditions. Map 3 is a full core map used for the maximum allowable power calculation, and incore average quadrant tilt verification after a dc:iwn power. The RPDs for these maps are given in Figures 6.2 through 6.4.

The RPDs for the maps given in Figures 6.1, 6.2, 6.3, and 6.4 show that the measured relative assembly power values deviated from the design predictions by at most +/-8.0% in the 45.40% power map, +/-6.7% in the 71.14% power map, +/-6.3% in the 73.14% power map, and

+/-6.1% in the 99.88% power map. The maximum average quadrant power tilt for the four maps were +3.44%, +2.96%, +2.95% and +2.45%, respectively. These power tilts are not within the design tolerance of 2%. The current safety analysis was examined and it was confirmed the Page 30 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure measured tilt was bounded by the safety analysis. At the time of this report, this issue is still under investigation [Ref. 18] and being monitored [Ref. 19].

The measured FQ(z) and F~ peaking factor values for the at-power flux maps were within the limits of the COLR [Ref. 13]. Flux Maps 1 through 4 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 27.

Page 31of47

Serial No.16-071 DocketNo. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 6.1 SURRY UNIT 2 - CYCLE 27 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Peak FQ(z) Hot F!ii Hot (2) CoreFz Burnup Bank Core Tilt (3) Axial No.

Map Map Power Channel Factor (1) Channel Factor Max Date MWD/ D **-***************-i:~xiall Offset Of Description No.

MTU

(%)

Steps Assy P . ti FQ(z) Assy om I ..

~ ..AXia~********;- -Max I Loe (%) Thimbles Point z 1 I Low Power 1 12/12/15 7.0 45.40 177 E-121 26 I 2.134 D-1011.571 26 I1.268 1.03441I SE i 4.397 50 Int. Power (4) 2 12/13/15 34.9 71.14 191 E-12 I 30 I2.034 E-12 I 1.540 29 Ii 1.222 1.02961 SE 2.054 50 Int. Power (4) 3 12/16/15 115.0 73.14 197 E-12 I 30 I2.005 E-12 I u28 29 I1.210 1.02951 SE 2.506 50 Hot Full Power 4 12/21/15 262.3 99.88 227 E-12 I 30 11.909 E-12 , l.497 29 11.169 1.02451 SE 1.779 50 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). 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) F~ 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).

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

Page 32 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 6.2 SURRY UNIT 2- CYCLE 27 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak FQ(Z) Hot Channel Factor F~ Hot Channel Factor Map Meas. Limit Node Margin* Meas. Limit Margin*

No. (%) (%)

1 2.134 5.000 26 57.3 1.571 1.816 13.5 2 2.034 __3.514

,, 30 42.1

___ ,, ___ 1.540 1.695 9.1 3 2.005 3.418 30 41.3 1.528 1.686 9.4 4 1.909 2.503 30 23.7 1.497 1.561 4.1 The measured FQ(Z) hot channel factors include 8% total uncertainty. Measured F~ data includes no uncertainty.

Margin(%)= 1OO*(Limit- Meas.) I Limit Page 33 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 6.1 - ASSEMBL YWISE POWER DISTRIBUTION 45.40% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value == Analytical, bottom value = % Delta

% Delta = (M - A)xlOO/A R p N M L K J H G F E D c B A I 0.2411 o.4011 o.2441 1 I 0.2471 o.4101 0.2501 I -2.56J -2.08J -2.381 I 0.2641 o.4491 o.9021 o.9621 0.9121 o.4641 0.2101 I 0.2121 o.4621 o.9281 o.9981 o.9361 o.4651 0.2121 I -2.851 -2.121 -2.011 -3.621 -2.591 -o.311 -o.79J I o.3651 0.9121 i.1111 i.2401 1.2001 i.2401 i.1361 o.9971 o.3911 I o.3771 i.0041 i.1s11 i.2121 1.3321 i.2031 i.1s1J i.0011 o.3011 I -3.291 -3.191 -2.941 -2.5ol -3.011 -2.691 -1.831 -i.001 2.s11 I o.36sl o.9721 1.2461 i.3101 i.2111 i.2021 i.2221 1.3391 i.2111 i.0111 o.31s1 I o.3721 i.0041 i.2901 1.3621 i.2441 i.2201 i.2521 1.3681 i.2951 i.0001 o.3721 I -i.941 -3.111 -3.411 -3.241 -2.611 -2.111 -2.361 -2.091 -1.361 o.251 o.921 I 0.2011 o.9981 i.2401 i.2111 i.1s11 i.2191 i.3111 i.2411 i.1051 1.3371 i.3011 i.0101 0.2051 J o.203J i.0011 i.2921 i.3601 i.2061 i.2501 1.3491 i.21s1 i.2121 1.3621 i.2921 i.0001 0.2831 J -o.641 -0.001 -3.371 -6.131 -4.081 -3.071 -2.831 -2.671 -2.201 -1.831 1.191 i.021 o.s4J J o.4671 i.1501 1.3371 1.1631 i.os11 i.1os1 1.2251 i.1201 i.0161 i.2001 1.3741 i.1691 o.4751 I o.4101 i.1631 i.3111 i.2121 i.1os1 1.1471 i.2101 i.1541 i.1011 i.2111 i.3661 i.1561 o.4671 I -0.741 -1.101 -2.461 -4.0ll -4.361 -3.651 -3.581 -2.961 -2.831 -0.941 0.571 1.091 1.681 I 0.2491 o.9371 i.293J i.2421 i.2461 i.1181 i.1451 i.1231 i.1561 i.1321 i.2641 i.2601 i.2911 o.9591 0.2501 1 I 0.2511 o.9431 i.2921 i.2591 i.21s1 i.1521 i.1961 i.1621 i.1961 i.1511 i.2611 i.2501 i.2131 o.9331 0.2491 I -0.671 -o.681 o.os1 -1.341 -2.311 -2.951 -4.221 -3.351 -3.341 -1.631 -0.211 o.821 1.441 2'.781 3.651 I o.4091 0.9011 1.3061 1.2461 i.3431 i.244J i.1361 i.0161 i.1461 i.2591 i.3661 i.2821 i.3471 i.os11 o.4361 8 I o.4141 1.0031 1.3231 1.2601 1.3551 1.2671 1.1651 1.0981 1.16sl 1.2601 1.3561 1.2621 1.3211 1.0051 o.41s1 I -i.281 -1.641 -i.261 -i.o81 -0.921 -i.811 -2.461 -1.991 -i.6ol -o.691 0.111 1.591 1.541 5.211 5.161 I 0.2461 o.92ol i.2511 i.23s1 1.2451 i.1321 i.1161 i.1501 i.1921 1.1641 i.3001 1.2991 1.3331 o.9821 0.2641 9 J 0.2481 o.93ol i.2681 l.245J 1.2641 i.1491 i.1941 1.1621 1.1961 i.1531 i.2161 i.2601 i.2931 o.9441 0.2521 I -o.9ol -i.o61 -o.841 -o.831 -1.511 -1.471 -1.471 -i.031 -o.371 o.921 i.901 3.121 3.o91 3.991 4.651 I o.463J i.1401 1.3561 i.2001 i.o89I i.1311 i.2681 i.1511 i.1211 i.2511 1.4461 i.2131 o.4851 10 I o.4641 i.1501 1.3591 i.2061 i.1041 i.1521 i.269J i.1461 i.1051 i.2121 i.3711 i.1631 o.4101 I -0.321 -0.151 -0.251 -0.Sll -1.401 -1.301 -0.0SI 0.921 1.421 3.211 5.461 4.271 3.171 I 0.2811 l.OOOI 1.2861 1.3621 1.2111 1.2741 1.3571 1.2831 1.2451 1.4041 1.3551 1.0531 0.295J 11 J *0.2811 o.9981 1.2831 1.3551 i.2081 i.2121 1.3461 1.2561 i.2061 1.3611 i.2911 i.0061 0.2031 I 0.001 0.241 o._211 o.521 o.241 o.191 o.851 2.131 3.211 3.121 4.961 4.111 4.371 I o.3711 i.0041 i.2951 1.3761 i.2631 i.2511 i.2881 i.4211 i.3561 i.01s1 o.3891 12 I 0.3661 0.9981 1.2851 1.3621 1.2491 1.227J 1.2421 1.3621 1.2911 l.OOSI 0.3681 I 1.301 0.641 0.801 LOOI 1.091 2.481 3.711 4.751 5.061 7.0ll 5.831

-1. o.3.781 .i.010.1 .. i.1111 1.3131. 1.38.6.I .1.3351 1.233.I. i..061.1 ... 0.. 4011 13 I o.3741 o.9971 i.1s21 i.2011 i.3301 i.2111 i.1511 i.0061 o.3811 I i.021 i.261 1.691 2.531 4.241 5.031 1.101 6.091 6.111 I 0.2741 o.4751 o.9671 1.0361 o.9801 o.4921 0.2901 14 I 0.2691 o.4631 o.9341 o.9961 o.9281 o.4621 0.2121 I 1.831 2.541 3.511 4.os1 5.651 6.591 6.5ol I 0.2691 o.4311 0.2611 15 I 0.2491 o.4101 0.2411 I 8.051 5.081 s.52J AVERAGE ABSOLUTE PERCENT DIFFERENCE = 2.4 STANDARD DEVIATION l.756 Summary:

Map No: 82-27-01 Date: 12/12/2015 Power: 45.40%

Control Rod Position: Fo(Z) = 2.134 QPTR:~_0_.9_7_35~-+--~0._99_2_6~

D Bank at 177 Steps 0.9995 1.0344 F~ = 1.571 Fz = 1.268 Axial Offset(%)= +4.397 Bumup = 7.0 MWD/MTU Page 34of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 6.2 - ASSEMBL YWISE POWER DISTRIBUTION 71.14% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta = (M - A)xlOO/A R p N M L K J H G F E D c B A I 0.2521 o.4151 0.2551 1 I 0.2591 o.4291 0.2621 I -2.021 -3.371 -2.691 I 0.2101 o.4581 o.916J o.9971 o.925J o.4651 0.2151 2 J 0.2101 o.4711 o.9391 i.0241 o.9461 o.4741 0.2101 I -2.851 -2.701 -2.441 -2.691 -2.191 -1.811 -1.031

~----------------------------------------

I o.365J o.9641 i.1091 i.2361 i.2941 i.2491 1.1331 o.9931 o.3891 3 I 0.3011 o.9961 i.1411 i.2631 i.3241 i.2141 i.1411 o.9991 o.3861 I -4.241 -3.221 -2.851 -2.171 -2.26j -1.961 -l.25j -0.631 0.721 I o.3681 o.9641 i.2201 i.3001 i.1911 i.1001 i.2101 1.3391 i.2691 i.0031 o.3001 I o.3761 o.9961 i.2101 1.3431 i.2351 i.2201 i.2421 1.3491 i.2151 o.9981 o.3771 I -2.001 -3.171 -3.321 -3.201 -3.061 -3.261 -1.951 -0.721 -0.501 0.461 0.751 I 0.2011 o.9881 i.2361 1.2841 i.1611 i.2001 i.3011 i.2431 i.1941 1.3371 i.2011 i.0091 0.2091 5 I 0.2891 0.9991 1.2721 1.3441 1.2061 1.2561 1.3401 1.2721 1.2111 1.3461 1.2721 l.OOOI 0.2891 I -0.861 -1.lll -2.811 -4.44j -3.741 -3.851 -2.94J -2.28J -l.42J -0.65j 1.191 0.921 -0.05j J o.474J i.14oJ i.3221 i.169J i.o94J 1.1191 i.2301 1.1371 i.1011 i.2031 1.3551 i.151J o.4831 6 I o.4791 1.1531 1.3521 i.2111 i.1361 i.1511 i.2101 i.1641 i.1301 i.2101 L347J 1.1461 o.4751 I -0.941 -1.161 -2.221 -3.461 -3.671 -3.271 -2.501 -2.361 -2.711 -0.611 0.581 0.961 1.701 I 0.2611 o.9471 i.2031 i.2331 1.2431 i.1311 i.1611 i.1401 i.1111 i.1461 i.2621 i.2501 i.2001 o.9711 0.2691 7 I 0.2631 .* o.9531 i.2031 i.2501 i.2131 i.1621 i.2031 i.1691 i.2031 i.1601 i.2651 i.2411 i.2651 o.9441 0.2611

. I -0.901 -0.671 -0.031 -1.361 -2.321 -2.631 -3.481 -2.501 -2.181 -1.161 -0.241 0.731 1.181 2.901 3.211 I o.4261 -.i.0161 i.2901 L237J i.3211 1.2451 i.1481 i.0921 i.1621 i.2651 i.3541 1.2661 1.3301 i.0121 o.4501 0 I o.4341 1.0301 i.3101 i.2521 1.3471 i.2601 i.1121 i.1001 i.1121 i.2601 1.3471 i.2541 i.3211 i.0321 o.4341 I -1.921 -1.391 -1.501 -1.231 -1.481 -1.781 -2.081 -l.42J -0.891 -0.211 0.501 0.931 0.661 3.851 3.631 I 0.2511 .0_9321 i.2511 i.4291 i.2511 1.1461 i.1011 i.1621 i.2091 i.1691 i.2091 i.2131 i.3011 0.9001 0.2101 9 I 0.2611 o.9411 i.2621 i.2311 i.262J i.1591 i.2021 i.1691 i.2031 i.1621 i.2131 i.2501 i.2041 o.9541 0.2641 I -1.391 -0.941 -0.871 -0.681 -0.871 -1.llj -1.211 -0.611 0.541 0.611 1.281 1.821 1.811 2.711 2.151 I -o.4721 i.1421 i.3401 i.2031 i.1251 i.1411 i.2691 i.1691 i.1541 i.2431 i.3901 i.1031 o.4911 10 I o.4731 i.1411 1.3421 i.2061 1.1361 i.1621 i.2691 i.1561 i.1361 i.2111 1.3521 i.1531 o.4791 I -0.221 0.091 -0.141 -0.241 -o.94J -i.261 0.031 i.121 i.561 2.65J 2.021 2.611 2.531 I .0.2011 o.9951 i.2601 i.3471 i.2111 i.2121 i.345J i.2191 i.2441 i.4021 1.3261 i.o34I 0.2991 11 I *0.2011 o.9921 i.2651 1.3411 i.2001 i.2691 L337J 1.2551 i.2051 L345J i.2121 o.9981 0.2091 I 0.111 0.201 0.251 o.421 0.291 0.221 0.621 1.951 3.221 4.24J 4.211 3.6ol 3.431 I o.3741 o.9961 i.2111 1.3581 i.2511 i.2461 i.2161 i.4041 i.3301 i.o64I o.3891 12 I o.3711 o.9901 1.2671 1.3441 i.24ol i.2101 i.2331 1.3441 i.2121 o.9971 o.3731 I o.931 o.641 o.751 1.031 1.351 2.331 3.461 4.461 5.151 6.121 4.3oJ I 0 ..:i_82 j . _1. 0021 1.16'.IJ LJJ!J.I L373 l._L321 I .. 1_._2_nJ._l ._05_6J_o_._41.0.I _ _ _ _ _ _ _ _ _ __

13 I o.3791 o.99ol i.1421 i.2121 1.3241 i.2631 i.1421 o.9981 o.3861 I 0.001 i.201 1.641 2.441 3.741 4.561 6.111 5.021 6.201 I 0.2191 o.4831 o.9751 1.0641 o.9901 o.4991 0.2951 14 J 0.2161 o.4721 o.9441 i.0231 o.9391 o.4711 0.2101 I i.011 2.201 3.331 4.041 5.481 5.861 6.041 I 0.2111 o.4491 0.2121 15 I 0.2611 o.4291 0.2591 I 6 .121 4. 65 I 5 .121 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 2.1 STANDARD DEVIATION 1. 548 Summary:

Map No: S2-27-02 Date: 12/13/2015 Power: 71.14%

Control Rod Position: Fo(Z) = 2.034 QPTR: 0.9751 0.9950 D Bank at 191 Steps pNllll

= 1.540 1.0003 1.0296 Fz = 1.222 Axial Offset(%)= +2.054 Bumup = 34.9 MWD/MTU Page 35 of 47

Serial No,16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 6.3 -ASSEMBLYWISE POWER DISTRIBUTION 73.14% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta = (M - A)xlOO/A R p N M L K J H G F E D c B A I 0.2521 o.4181 0.2561 1 I 0.2591 o.4301 0.2621 I -2.631 -2.161 -2.331 I 0.2601 .o.4561 o.9111 i.0011 o.9231 o.4661 0.2141 I 0.2111 o.4691 o.9361 i.0201 o.9431 o.4721 0.2161 I -3.221 -2.061 -2.651 -2.661 -2.131 -i.331 -0.121 I o.3631 o.9541 i.1001 i.2261 i.2001 1.2441 i.1251 o.9841 o.3011 I o.3791 o.9001 1.1351 1.2591 i.3211 1.2691 1.1401 o.99ol o.3831 I -4.101 -3.401 -3.111 -2.641 -2.481 -2.011 -i.201 -o.651 i.111 I o.3651 o.9561 i.2191 1.2941 i.1961 i.1021 i.2161 1.3311 i.2591 o.9921 o.3761 4 I o.3741 o.9001 i.2631 1.3391 1.2341 i.2191 i.2411 1.3441 1.2671 o.9911 o.3751 I -2.451 -3.251 -3.491 -3.331 -3.111 -3.o61 -1.991 -o.961 -o.651 0.141 o.351 I 0.2041 o.9741 i.2211 i.2021 i.1651 i.2141 i.3051 i.2401 i.1961 1.3331 i.2131 o.9981 0.2091 I 0.2001 o.9911 i.2651 i.3421 i.2091 i.2611 1.3431 i.2111 i.2151 i.3431 i.2651 o.9921 0.2001 I -1.411 -i.121 -2.971 -4.451 -3.651 -3.701 -2.021 -2.291 -1.591 -0.101 o.671 o.581 0.211 I o.4731 i.1341 i.3101 i.1141 i.1131 i.1301 i.2411 1.1471 i.1241 i.2041 1.3471 i.1411 o.4001 I o.4771 1.1461 1.3471 i.2151 i.1531 i.1661 i.2101 i.1131 i.1551 i.2131 1.3431 i.1401 o.4741 I -o.841 -i.001 -2.131 -3.391 -3.461 -3.lOI -2.431 -2.221 -2.101 -0.111 0.211 o.641 i.201 I 0.2621 o.9471 i.2051 i.2351 i.2511 i.1421 i.1121 i.1511 i.1901 i.1561 i.2661 i.2411 i.2131 o.9621 0.2601 1 I 0.2641 o.9511 i.2191 i.2501 i.2101 i.1121 i.2131 i.1191 i.2131 i.1101 i.2101 i.2411 i.2611 o.9411 0.2621 I -0.021 -o.461 o.441 -1.191 -2.121 -2.521 -3.351 -2.341 -1.921 -i.211 -0.331 o.521 o.921 2.251 2.401 I o.4201 i.0221 i.2961 i.2391 1.3351 i.2551 i.1591 i.1041 i.1131 i.2111 1.3561 i.2651 i.3211 i.o73I o.4501 0 I o.4351 1.0341 1.3161 1.2521 1.3501 1.2151 1.1021 1.1101 1.1021 1.2761 1.3511 1.2541 1.3191 1.0361 o.4361 I -1.551 ~i.111 -1.501 -1.071 -1.101 -1.551 -1.941 -1.281 -0.761 -0.381 0.401 0.891 0.621 3.611 3.221 I 0.2501 --0.9291 i.2461 i.2201 i.2511 i.1511 i.1991 i.1141 i.2221 i.1001 i.2951 i.2131 i.3041 0.9101 0.2111 9 I 0.2611 o.9391 i.2501 i.2311 1.2671 i.1601 i.2121 i.1191 i.2131 i.112/ i.2101 i.250/ i.2001 o.9521 o.264/

I -1.161 -i.o3/ -o.981 -0.131 -0.00/ -o.941 -i.101 -o.45/ 0.111 o.68/ i.31/ 1.86/ i.091 2.101 2.01/

I o*.4691 i.1311 1.3341 i.2061 i.1441 i.1501 i.2191 i.1001 i.1121 i.241/ i.3891 i.119/ o.4921 10 I o.412/ 1.1351 1.3381 i.210/ i.1521 i.1121 i.2111 i.1661 i.1521 i.215/ 1.347/ i.146/ o.411/

I -o. 65 I -o.39 / -o.3o I -0.291 -o. 69 I -i.23 I 0.15 I i.221 i. 73 I 2. 63 I 3. 091 2.061 3 .23 I I . 0.2051 o.9841 i.2601 i.3431 i.2111 i.2001 i.3531 i.2061 i.2411 i.3971 i.3111 i.0261 0.2901 11 I 0.2061 o.9841 i.250/ 1.3381 i.2111 i.214/ 1.3411 i.260/ i.2091 1.3421 1.265/ o.9901 0.2001 I -0.261 0.031 0.141 o.391 o.491 o.491 0.011 2.051 3.121 4.091 4.121 3.631 3.511 J o.3731 o.9891 i.210/ 1.3571 i.2631 i.2491 i.215/ i.3911 i.3211 i.0511 o.3011 12 I o.3681 o.9831 i.2601 1.3401 i.2401 i.210/ 1.2331 1.3391 1.2651 o.9891 o.3711 I i.3ol o.611 o.831 1.261 1.851 2.581 3.411 4.341 4.011 6.291 4.191

__ I __ o._'.!!l.QLJl_._222J_1~1.2.?..LJ.3o3l_lJ.:u.J__.!._,_315J~LLM.4.I o.406.___ _ _ _ _ _ _ _ _ _ _ _ _ _ __

13 I o.3761 o.9021 1.1361 i.2611 i.3211 i.2501 1.1351 o.9901 o.3831 I i.021 i.331 i.861 2.011 3.961 4.511 5.001 5.441 5.931 I 0.2101 o.4021 o.9751 i.o69I o.9831 o.4951 0.2921 I 0.2141 o.4101 o.9411 i.021/ o.9361 o.4691 0.2111 I 1.461 2.611 3.581 4.05/ 5.061 5.531 5.451 I 0.2191 o.45ol 0.2121 15 I 0.2621 o.4301 0.2591 I 6.621 4.771 5.031 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 2.1 STANDARD DEVIATION 1.499 Summary:

Map No: 82-27-03 Date: 12/16/2015 Power: 71.14%

Control Rod Position: Fo(Z) = 2.005 QPTR: 0.9753 0.9939 D Bank at 197 Steps pNAll

= 1.528 1.0013 1.0295 Fz = 1.210 Axial Offset(%)= +2.506 Bumup = 115.0 MWD/MTU Page 36 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Figure 6.4 -ASSEMBLYWISE POWER DISTRIBUTION 99.88% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = %: Delta

% Delta = (M - A)xlOO/A R p N M L K J H G F E D c B A I 0.2621 o.4331 0.2651 l I 0.2601 o.4461 0.2111 I -2. 211 -2. 021 -2. 091 I 0.2121 o.4631 o.9261 i.0401 o.9351 o.4711 0.2111 2 I 0.2791 o.4741 o.9451 1.0631 o.9521 o.4771 0.2791 I -2.451 -2.261 -2.031 -2.161 -1.BOI -1.221 -0.641 I o.3671 o.9511 i.0901 i.2291 i.2051 i.2411 i.1211 o.9771 o.3911 3 I o.3001 o.9781 i.1261 i.2531 i.3121 i.2631 i.1311 0.9001 o.3841 I -3.541 -2.791 -2.441 -1.921 -2.061 -1.711 -0.091 -0.291 i.031 I o.3671 o.9511 i.2121 i.2021 i.1901 i.1691 i.2001 i.3101 i.2471 0.9001 o.3781 I o.3751 o.9791 1.2471 i.3191 i.2221 i.2061 i.2201 i.3231 i.2511 0.9011 o.3751 I -2.001 -2.011 -2.031 -2.791 -2.611 -3.041 -i.671 -o.421 -o.321 0.601 o.9ol I 0.2071 o.9671 i.2141 i.2661 i.1111 i.2271 i.2991 i.2551 i.1991 1.3171 i.2641 o.9891 0.2091 5 I 0.2901 o.9001 i.2491 i.3251 i.2091 i.2641 i.3311 i.2191 i.2141 1.3271 i.2491 o.9011 0.2901 I -i.001 -i.321 -2.781 -4.441 -3.171 -2.911 -2.371 -i.9ol -i.231 -o.741 i.161 0.011 -o.511 I o.4791 1.1271 1.3011 1.1791 1.1691 1.1481 1.2521 1.1631 1.1771 1.2051 1.3201 1.1391 o.4851 I o.4021 i.1381 1.3271 i.2141 i.2031 i.1101 i.2761 i.1041 i.2051 i.2131 i.3221 i.1321 o.4791*

I -o.671 -i.001 -1.981 -2.921 -2.021 -2.561 -1.851 -1.771 -2.301 -0.621 o.451 o.661 1.301 I 0.2121 o.9571 i.2111 i.2231 i.2551 i.1571 i.1061 i.1701 i.2051 i.1701 i.2601 i.2341 i.2651 o.9771 0.2791 7 I 0.2731 .. o.9601 1.2721 i.2371 i.2001 i.1031 i.2221 1.1931 i.2221 i.1011 i.2721 i.2201 i.2551 o.9511 o.2n1 I -o.411 -o.331 o.411 -i.101 -1.931 -2.201 -2.911 -1.951 -i.361 -o.961 -0.201 o.471 0.021 2.691 2.901 I o.4471 *1.0601 i.2001 i.2261 i.3211 i.2561 i.1141 i.1171 i.1071 i.2111 i.3411 i.2461 i.3091 i.1111 o.4671 0 I o.4511 -1.0101 1.3001 1.2391 1.3391 1.2141 1.1951 1.1301 1.1961 1.2151 1.3391 1.2401 1.3101 1.0121 o.4521 I -0.781 -0.891 -1.521 -1.051 -1.311 -1.451 -1.731 -1.161 -0.721 -0.301 0.151 0.471 -0.051 3.661 3.401 I 0.2691 -.o.9431 1.2451 i.2201 1.2681 i.1701 i.2071 i.1051 i.2261 i.1031 i.2091 i.2511 i.2091 o.9841 0.2011 9 I 0.2701 o.9481 i.2521 i.2251 i.2711 i.1001 i.2211 i.1921 i.2221 i.1031 i.2001 i.2371 i.2731 o.9611 0.2731 I -0.531 -0.551 -0.541 -0.391 -0.221 -0.811 -1.151 -0.571 0.331 0.031 0.741 1.111 1.231 2.431 2.931 I o.4771 i.1331 i.3101 i.2001 i.1951 i.1661 i.2741 i.1011 i.2101 i.2301 1.3521 i.1611 o.4961 10 I o.4771 i.1271 i.3101 i.2101 i.2031 i.1031 i.2751 i.1771 i.2031 i.2141 i.3261 i.1301 o.4021 I 0.051 0.561 0.021 -0.151 -0.681 -1.471 -0.091 0.871 1.281 1.961 1.951 1.981 2.811 I *0.2091 o.9771 i.2431 i.3201 i.2121 i.2111 1.3371 i.2041 i.2411 i.3111 i.2911 i.0001 o.2991 11 I 0.2001 o.9741 1.2431 i.3221 i.2111 i.2111 i.3291 1.2631 i.2091 i.3251 1.2481 o.9001 0.2901 I o.371 o.3ol 0.011 -0.141 0.111 0.011 o.581 1.631 2.671 3.471 3.411 2.9ol 3.o41 I o.3711 o.9771 1.2491 1.3301 i.2421 i.2291 1.2561 1.3701 i.3031 i.o37I o.3011 12 I o.37ol o.9741 1.2441 1.3201 1.2271 1.2051 1.2201 1.3191 1.2491 0.9001 o.3721 I 0.261 0.291 o.381 o.731 i.211 1.991 2.991 3.891 4.351 5.781 4.14i

__ L _o,=!_0_o1 __ 0~~8!.L_Ll43_L_l_.,1.~J 1.353J 1.3021 i.1nJ~J__,o'"'. ..e.40,,_,5'--!I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

13 I 0.3771 0.9721 1.1281 1.2611 1.3121 1.2521 1.1271 0.9791 0.3841 I o.711 o.931 i.301 2.111 3.131 4.031 5.651 5.161 5.411 I 0.2021 o.4851 o.9791 i.1011 o.99ol o.4991 0.2941 14 I 0.2111 o.4751 o.9511 i.0621 o.9451 o.4741 o.2791 I i.671 2.151 2.961 3.651 4.781 5.211 5.3ol I 0.2001 o.4651 0.2011 15 I o.2n1 o.4461 0.2601 I 6.131 4.321 4.681 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 1.8 STANDARD DEVIATION 1.414 Summary:

Map No: S2-27-04 Date: 12/21/2015 Power: 99.88%

Control Rod Position: Fo(Z) = 1.909 QPTR: 0.9789 0.9961 D Bank at 227 Steps FN &I

= 1.497 1.0005 1.0245 Fz = 1.169 Axial Offset(%)= +l.779 Burnup = 262.3 MWD/MTU Page 37 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure SECTION 7 - CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 2 Cycle 27 startup physics testing program. As noted herein, all test results were acceptable. The test results were within associated design tolerances, Technical Specifications limits, or COLR limits, except for the maximum positive incore quadrant power tilt exceeding the design criteria for all power ascension flux maps. Maximum incore quadrant power tilts ranged from 2.45% to 3.44% during the power ascension, exceeding the design criteria of 2%. It was confirmed that the measured tilt was bounded by the current safety analysis. As of the writing of this report, the larger than normal quadrant tilts remain under investigation and are being continuously monitored. Based on the results of the S2C27 startup physics testing program, it is anticipated that the Surry 2 core

will continue to operate-safely throughout Cycle 27.

Page 38of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure Table 7.1 SURRYUNIT2-CYCLE27 STARTUP PHYSICS TESTS STARTUP PHYSICS TESTING RESULTS

SUMMARY

Measured Predicted Diff (M-P) or Design (M) (P) (M-P)/P,% Tolerance Parameter Critical Boron Concentration 1554 1578 -24 +/-50 (HZP ARO), ppm Critical Boron Concentration 1370 1365 5 +/-29 (HZP Ref Bank in), ppm Isothermal Temp Coefficient -2.412 -2.465 +/-2 0.053 (HZP ARO), pcm/F Differential Boron Worth -7.60 -7.54 0.8% +/-10%

(HZP ARO), pcm/ppm Reference Bank Worth 1399 1426 -1.9% +/-10%

ffi-bank, dilution), pcm A-bank Worth (Rod Swap), pcm 219 202 17 +/-100 SA-bank Worth (Rod Swap), pcm 993 966 +2.9% +/-15%

C-b~ Worth (Rod Swap), pcm 873 920 -5.1% +/-15%

D-bank Worth (Rod Swap), pcm 941 961 -2.0% +/-15%

SB-bank Worth (Rod Swap), pcm 1112 1173 -5.2% +/-15%

Total Bank Worth, pcm 5537 5648 -2.0% +/-10%

S2C27 Testin2 Time: 7.6 Hrs

[criticality 12/01/2015@ 04:35 to end of testing 12/01/2015@ 12:08]

Recent Startups:

S 1C27 testing time: 5.6 hrs S2C26 testing time: 7.2 hrs S 1C26 testing time: - 7.8 hrs S2C25 testing time: 6.1 hrs SlC25 testing time: 5.7 hrs S2C24 testing time: 7.1 hrs S 1C24 testing time: 7.0 hrs S2C23 testing time: 9.4 hrs S 1C23 testing time: 6.2 hrs S2C22 testing time: 6.2 hrs SlC22 testing time: 8.0 hrs Page 39of47

Serial No.16-071 DocketNo. 50-281 S2C27 Startup Physics Tests Report Enclosure SECTION 8 - REFERENCES

1. M. M. Giffen, "Surry Unit 2, Cycle 27 Design Report," Engineering Technical Evaluation ETE-NAF-20150118, Rev. 0, November 2015.

2. B. R. Kinney, "Surry Unit 2 Cycle 27 Full Core Loading Plan," Engineering Technical Evaluation ETE-NAF-20150005, Rev. 0, May 2015.

3. B. R. Kinney, "Surry Unit 2 Cycle 27 Startup Physics Testing Logs and Results," Memorandum MEMO-NCD-20150034-0-0, Rev. 0, December 2015.

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.

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 I and 2 Technical Specifications.

7. D. J. Agnew, "Rod Drop Text Computer Users Gide and SQA Paperwork," Engineering Technical Evaluation ETE-NAF-2014-0118, Rev. 0, April 2015.

8. B. J. Vitiello & G. L. Darden, "Implementation of the Westinghouse 15x15 Upgrade Fuel Design at Surry Units I and 2," Engineering Technical Evaluation ETE-NAF-2010-0080, Rev. 0, January 2011.

9. M. P. Shanahan, "Implementation ofRMAS version 7 at Surry Unit I 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 0046, Rev. 0, April 2006.

11. M. M. Giffen et al., "Surry Unit 2 Cycle 27 Flux Map Analysis," Calculation PM-1767, Rev.a, and Addenda A-C, December 2015.

12. Nuclear Engineering Standard DNES-AA-NAF-NCD-5007, Rev. 2, "Startup Physics Tests Results Reporting."

13. 1'.( M .. Gatto et aL,-"Reloa<fSafet)/Evaluaffon Surry Unit 2 Cycli27Pattem HGG," EVAL-ENG-RSE-S2C27, Rev. 0 and Addenda, October 2015.

14. A. T. Folkening, "Surry Rod Drop Measurement Instrument (RDMI) Data Comparison & Analysis Report,"

AREVA Document No. 5-9228549-000, Feb 2015.

15. C. J. Wells and J. G. Miller, "The CEBRZ Flux Map Data Processing Code for a Movable In-core Detector System,"

Engineering Technical Evaluation f:TE-NAF-2011-0004, Rev. 0, March 2011.

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. Condition Report CRI021297, "Unit 2 Incore QPTR greater than nominal RSAC limit," 14 December 2015.

19. Condition Report CRI024733, "Tracking of S2C27 Incore Tilt for review at 11,000 MWD/MTU," 21January2016.

20. T. S. Psuik, "Implementation of Changes to the Allowable Power Level for the Initial Startup Flux Map for Surry Units I and 2," Engineering Technical Evaluation ETE-NAF-2015-0007, Rev. 0, April 2015.

Page 40 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure APPENDIX- STARTUP PHYSICS TEST

SUMMARY

SHEET Page 41of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure; Appendix

~

Surry Power StatioJi Uni~ 2 C*;cle 27 Startup Pltysics Test Summary Sheet~ Fama! Tests (Page 1of6)

Dato!

Acceptanco. Prepateri Criteria Net Re~*lewer OT'~,

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.:<..) E.TE-NAF-2015-0118, Rev. ()

~-) fTl5-Nil\F'*201~*O'l1 T, Rev. D Page 42 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure; Appendix I. .

Sury Povver Station Unit 2 Cyde 27 Start:..tp Physics Test Sunmary Sheet- FomaJ Tests (Page 2 of 6)

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Relen:moel! 1.) DNf.S*M*NAF*NCC:-40t6, Rev. 2 2.) ETE-NAF-2015-)118, Rev. c 3.) ETE~NAF-2015..iJ11i, Rev. C Page 43 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure; Appendix I

Surry Power S*taltlon UnitZ Crete _2.7 Startup Physics Test Summary Sheet- Formal Tests (Page 3. oi 6)

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3.) El&NlAF-2.015-0117 Rev. 0 Page 44 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure; Appendix Surry Power Stallion Unit 2 Cyc:le 27 Startup Physics Test Summary- Sheet.: Formal Tests {Paga4of6)

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Page 45 of 47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure; Appendix

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Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure; Appendix I

I I

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\References 1.) Dt:JES-AA-NAF-NC~015, Rev. 2 2.} ETE*NAF-20i~0118j, Rev. {1 3.}_ETE-NAF-2:!.Hl>-011~. Rev. O Page 47 of 47

Dominion Resources Services, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 March 7, 2016 United States Nuclear Regulatory Commission Serial No.: 16-071 Regional Administrator- Region II NLOS/GDM Marquis One Tower Docket No.: 50-281 245 Peachtree Center Ave., NE Suite 1200 License No.: DPR-37 Atlanta, Georgia 30303-1257 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 27 STARTUP PHYSICS TESTS REPORT As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 2 Cycle 27 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 27 on December 1, 2015. 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,

,--:--R~Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Ms. K. R. Cotton Gross NRC Project Manager- Surry U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.16-071 Docket No. 50-281 Enclosure SURRY UNIT 2 CYCLE 27 STARTUP PHYSICS TESTS REPORT February 2016 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit 2

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 avrulable, 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 from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

Page 1of47

Serial No.16-071 Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure TABLE OF CONTENTS Classification/Disclaimer ...............................................................................................................1 Table of Contents ........*..................................................................................................................2 List of Tables .....................................................................................................................*............3 List of Figures .................................................................................................................................4.

Preface ............................................................................................................................................. 5 Section 1 - Introduction and Summary .....................................................................................6 Section 2 - Control Rod Drop Time Measurements ............................................................... 15 Section 3 - Control Rod Bank Worth Measurements ............................................................20 Section 4 - Boron Endpoint and Worth Measurements ........................................................25 Section 5 -Temperature Coefficient Measurement ...............................................................28 Section 6 - Power Distribution Measurements .......................................................................30 Section 7 - Conclusions .............................................................................................................38 Section 8 - References .................................................................................................. ~ ............ 40 Appendix - Startup Physics Test Summary Sheets ................................................................ 41 Page 2 of 47

Serial No.16-071

Docket No. 50-281 S2C27 Startup Physics Tests Report Enclosure 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 ...........................................................39 Page 3 of 47