ML14238A004

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Cycle 26 Startup Physics Tests Report
ML14238A004
Person / Time
Site: Surry Dominion icon.png
Issue date: 08/11/2014
From: Blasioli P
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation, NRC/RGN-II
References
14-397
Download: ML14238A004 (48)
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Text

l!tominion Resources Services, Inc.

" ' Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060

  1. Dominioni August 11, 2014 United States Nuclear Regulatory Commission Serial No.: 14-397 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 26 STARTUP PHYSICS TESTS REPORT As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 2 Cycle 26 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 26 on May 20, 2014. The results of the physics tests were within the applicable Technical Specification limits.

If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.

Sincerely, P. A. Blasioli, Director In Charge Nuclear Support Services Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None

Serial No.14-397 Docket No. 50-281 S$2C26 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 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.14-397 Docket No. 50-281 Enclosure SURRY UNIT 2 CYCLE 26 STARTUP PHYSICS TESTS REPORT July 2014 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit 2

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

Page 1 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report TABLE OF CONTENTS Classification/Disclaim er .................................................. 1 Table of Contents ............................................................................................................................ 2 List of Tables .................................................................................................................................. 3 List of Figures ................................................................................................................................. 4 Preface ............................................................................................................................................. 5 Section I - Introduction and Sum m ary ................................................................................. 6 Section 2 - Control Rod Drop Tim e Measurem ents .......................................................... 14 Section 3 - Control Rod Bank Worth Measurements ........................................................ 19 Section 4 - Boron Endpoint and Worth Measurements ................................................... 24 Section 5 - Tem perature Coefficient Measurem ent .......................................................... 27 Section 6 - Power Distribution M easurem ents ................................................................. 29 Section 7 - Conclusions ....................................................................................................... 36 Section 8 - References ............................................................................................................... 38 Appendix - Startup Physics Test Sum m ary Sheets .......................................................... 39 Page 2 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report LIST OF TABLES Table 1.1 - Chronology 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 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report LIST OF FIGURES Figure 1.1 - Core Loading Map ............................................................................................ 10 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 29.80% Power ........................................ 33 Figure 6.2 - Assemblywise Power Distribution 71.10% Power .......................................... 34 Figure 6.3 - Assemblywise Power Distribution 99.87% Power ........................................ 35 Page 4 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 2, Cycle 26 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 [Ref. 17]. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard testing techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at Surry Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.

The Surry Unit 2, Cycle 26 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer/ reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations performed by Dominion's Nuclear Analysis and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits.

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Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report SECTION 1 - INTRODUCTION AND

SUMMARY

On April 20, 2014, Unit No. 2 of Surry Power Station completed Cycle 25 and began refueling [Ref. 1]. During this refueling, 61 of the 157 fuel assemblies in the core were replaced with 61 fresh Batch S2/28 assemblies. The Cycle 26 core consists of 6 sub-batches of fuel: two fresh batches (S2/28A and S2/28B), two once-burned batches (S2/27A and S2/27B), and two twice-burned batches (S2/26A and S2/26B). S2C26 is the first Surry cycle to load a full core of the 15x 15 Upgrade (Upgrade) Fuel Design [Ref. I].

The Westinghouse Upgrade fuel assembly design incorporates ZIRLO (I-spring) structural mid grids with balanced mixing vane pattern, ZIRLO Intermediate Flow Mixing (IFM) grids for improved thermal-hydraulic performance, "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 Surry 2 Batch 28 fuel is the first Unit 2 batch to utilize Westinghouse's Robust Protective Grid (RPG) and modified Debris Filter Bottom Nozzle (mDFBN). The RPGs were developed to mitigate grid failure mechanisms and the mDFBNs reduce the likelihood of debris bypass into the fuel bundles.

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 ZrB 2 on the fuel pellet surface during fabrication. Pellets with the IFBA coating are placed in specific symmetric patterns in each fresh assembly, typically affecting from 16 to 148 rods per assembly. The top and bottom 6 inches of the fuel pellet stack in the IFBA rods will contain pellets that have no IFBA coating, and have a hole in the center (annular). This additional void space helps accommodate the helium gas that accumulates from neutron absorption in ZrB2 . IFBA rods generate more internal gas during operation because neutron absorption in the ZrB 2 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].

Surry Unit 2 Cycle 26 implements the reinsertion of Secondary Source Assemblies (SSAs) to improve Source Range Detector indication. Cycle 26 loads SSAs in core locations Page 6 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report J-02 and G-14. Each assembly consists of six source rods containing antimony and beryllium pellets encapsulated in a double layer of stainless steel cladding. The SSAs are dimensionally similar to those loaded in prior Surry cycles, and are compatible with the 15 x 15 Upgrade Fuel Design. There are no thimble plugging devices in S2C26. The cycle design report [Ref. 13 provides a more detailed description of the Cycle 26 core.

The S2C26 full core loading plan [Ref. 8 and Ref. I I] is given in Figure 1.1 and the beginning of cycle fuel assembly bumups [Ref. 6] are given in Figure 1.2. The incore moveable detector locations used for the flux map analyses [Ref. 7] are identified in Figure 1.3. Figure 1.4 identifies the location and number of control rods in the Cycle 26 core [Ref. 1].

According to the Startup Physics logs, the Cycle 26 core achieved initial criticality on May 20, 2014 at 18:33 [Ref. 14]. 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.6 [Ref. 9] was used for S2C26 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. 4] limit, as well as the Surry Unit 2 1.68 second administrative limit

[Ref. 10].

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

For the purpose of this test, a bank was defined as 'fully inserted' when it was 2 steps off the bottom of the core [Ref. 13]. The sum of the individual measured control rod bank worths was within -4.6% of the design prediction. The reference bank (Control Bank B) worth was within

-3.5% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within -8.4% of their design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within -3 pcm of the design prediction.

These results are within the design tolerances of + 15% for individual banks worth more than 600 Page 7 of 45

Seria( No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report 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. 4] that the overall core reactivity balance shall be within + 1% Ak/k of the design prediction. The boron worth coefficient measurement was within -0.4% of the design prediction, which is within the design tolerance of + 10%.

The measured isothermal temperature coefficient (ITC) for the ARO configuration was within 0.190 pcrn/F of the design prediction. This result is within the design tolerance of +2.0 pcm/°F.

Core power distributions were within established design tolerances. The measured assembly power distributions were within +5.3% of the design predictions, where a -5.3%

maximum difference occurred in the 29.80% power map in assembly J10. The heat flux hot channel factors, FQ(Z), and enthalpy rise hot channel factors, FA, were within the limits of the COLR [Ref 8]. All flux maps were within the maximum incore power tilt design tolerance of 2% (QPTR < 1.02).

The total RCS Flow was successfully verified as being greater than 273,000 gpm and greater than the limit in the COLR (276,000 gpm), as required by Surry Technical Specifications

[Ref 4]. The total RCS Flow was measured as 294,349 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.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 1.1 SURRY UNIT 2 - CYCLE 26 CHRONOLOGY OF TESTS t 1e 1 Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 05/20/14 1013 HSD 2-NPT-RX-014 Reactivity Computer Checkout 05/20/14 2011 HZP 2-NPT-RX-008 Boron Endpoint - ARO 05/20/14 2154 HZP 2-NPT-RX-008 Zero Power Testing Range 05/20/14 2011 HZP 2-NPT-RX-008 Boron Worth Coefficient 05/20/14 2357 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 05/20/14 2045 HZP 2-NPT-RX-008 Bank B Worth 05/20/14 2155 HZP 2-NPT-RX-008 Boron Endpoint - B in 05/20/14 2357 HZP 2-NPT-RX-008 Bank A Worth- Rod Swap 05/21/14 0000 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap 05/21/14 0000 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap 05/21/14 0000 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 05/21/14 0000 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap 05/21/14 0000 HZP 2-NPT-RX-008 Total Rod Worth 05/21/14 0000 HZP 2-NPT-RX-008 Flux Map - less than 30% Power 05/21/14 1545 29.8% 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 05/22/14 2129 1 71.10% 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 05/27/14 0700 99.87% 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 05/23/14 1 1800 HFP 2-NPT-RX-009 Page 9 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 1.1 SURRY UNIT 2 - CYCLE 26 CORE LOADING MAP SURRY UNIT 2 - CYCLE 26 FULL CORE LOADING PLAN REVISION NO. 0

-TE-NAF-2013-011, Rev. 0 Attachment 1 PAGE 1 oa 1 V'TP-NES-.fAF R P 14 M I K a H a r E D C B A I- 1 2'?x I O0X 22X RCC SS9 RCC RCC 2 13x lox 649 651 632 08X l1X NORTH RCC RCC 3 44X 638 659 607 37Y 604 661 635 soX RCC RCC .ACC RCC 4 38X 647 614 45Y 12Y 38Y 13Y 51Y 602 641 41x RCC RCC 5 M6x 643 610 ley 28Y olY 619 04Y 25Y 20Y 611. 639 oiX RCC RCC R FtCC R RCC RCC 6 M4X 655 52Y 22Y 44Y 623 29Y 621 42Y 23Y 48Y 658 12X "CC RCC RCC RCC '1 21X 630 60L iiy 06y 62'7 55Y 57Y 54Y 629 D8Y 09y 613 644 25X RCC 2CC 2Cc RCC' 8 go, lax 650 39Y 36Y 617 40Y 53Y 625 60Y 35Y 618 41Y 30Y 653 19X RCC HCC RCC RcC. 9 28X 633 606 6Y. 037 624 58Y 56Y 59Y 626 02Y 10y 608 637 23X RCC CC RC RCC "CC RCC RCC 10 07X 660 49Y 76Y 31Y 628 43Y 622 33Y 21Y 47Y 656 15X RCC RCC 1.

059 636 615 iSY 24Y 05Y 620 07Y 27Y 17Y 63.6 642 02X 2CC 2CC ACC RCC 12 532 645 612 50Y 14Y 32Y 15y 46Y 605 646 55X ZiWORE DEVICE 021 CAIPUIO$: 2CC RC RCC.- FULL. LnEN2 CONMROIL ROD 45X 640 657 603 34Y 609 654 631 54X MS4- SecondaryS lource Asi.,nbgy RCC RCC SS8 RCC 14 04X 06X 634 652 648 09X 03X 15 L6X 28X Prepared Byt Z Date: to1 0// ConcurrenAce B

_ .y_ _ Date:_

A. b~. nlack Reviewed b~y: CA 5 b." __________

T. S. Psuik Approved lAJ beta: 0ho/Z%.3 Approved By: On-ý Dte-a: _______

A. H. Nicholson X. N. Lapfaoll Page 10 of 45

Serial No.14-397 Docket No. 50-281 82C26 Startup Physics Tests Report Figure 1.2 SURRY UNIT 2 - CYCLE 26 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWD/MTU)

R P N M L K J H G F E 0 C B A 1 42.79 28.491 43.101 IMASURED 1 42.83 28.49 42.911 PREDICTED 2 I 41.911 42.201 0.001 0.00 0.001 42.251 42.04 2 1 42.03 42.211 0.00 0.00 0.00 42.18 - 41.91 3 39.681 0.001 0.001 0.00 19,671 0.00 0.001 0.001 39.53 3 1 39. 77 0.001 0.00 0.001 19.581 0.00 0.00 0.001 39.56 4 I 39.581 0.001 0.001 22.541 23.341 19.54I 23.131 22.981 0.001 0.001 40.0sf 4 I 39.741 0,00 0.00 22.57 23.14 19.58 23.15 22.551 0.001 0.00 39.891 5 1 42.09 0.001 0.001 23.271 23.091 19.251 19.18 24.121 0.001 23.861 19.25 19.141 23.121 41.94 " 0.001 0.001 23.83 0.001 23.811 23.101 0.001 0.001 0.001 42.171 0.001 42.011 5 6 I 42.071 0.001 22.611 19.221 19.941 0.001 21.671 0.00) 19.821 19.191 22.751 0.00 42.061 6 I 42.14[ 0.001 22.551 19.171 19.761 0.001 21.73 0.00 19,7s1 19.191 22.571 0.00 42.191 7 1 42.79) 0.OO 0.001 23.151 23.821 0.001 23.591 23.551 23.631 0.001 23.961 23.321 0.00 0.001 43.021 7 I 42.971 0.001 0.001 23.171 23.851 0.001 23.641 23.661 23.381 0.00 23.841 23.151 0.00 0.001 42.891 8 I 28.431 0.00 19.58 19.661 0.001 21.741 23.341 0.001 23.42 21.88 0.001 19.541 19.63 0.00 28.43 8 I 28.471 0.00 19.54 19.541 0.001 21.711 23.391 0.001 23.39 21.711 0.001 19.571 19.57 0.00 28.47 9 1 42.88) 0.001 0.001 23.281 23.861 0.001 23.28 23.521 23.571 0.001 24.261 23.14( 0.001 0.001 42.951 9 I 42.891 0.001 0.001 23.151 23.841 0.001 23.381 23.661 23.641 0.001 23.85 23.171 0.001 0.00 42.97 10 I 42.151 0.001 22.671 19.17 19.861 0.001 21.811 0.00I 19.811 19.461 22.751 0.00! 42.711 10 1 42.19f 0.001 22.57[ 19.19 19.781 0.00 21.731 0.00 19.761 19.171 22.551 0.001 42.141 21 I 42.02 0.001 0.00 23.111 19.251 23.88 0.001 23.821 19.281 23.311 0.001 0001 41.921 11 1 42.011 0.001 0.001 23.10J 19.14 23.86! 0.001 23.831 19.181 23.09S 0.001 0.001 41.94 12 1 39.991 0.00 0.001 22.591 23.22 19.52 23.24J 22.571 0.00 0.001 39.781 12 i 39.891 0.00 00.00 22.551 23.15 19.55 23.14 22.571 0.001 O0.0 39.741 13 1 39.531 0.001 0.00 0.001 19.521 0.001 0.001 0.001 39.721 13 I 39.56f 0.001 0.00 0.001 19.55 0.00 08.0010.001 39.771 14 I 41.811 42.281 0.001 0.001 0.001 42.35 41.961 14 I 41.911 42.181 0.00 0.001 0.00 42.211 42.03 15 I 42.921 28.3Sf 43.06 15 42.91 28.49 42.83 Page IIof 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 1.3 SURRY UNIT 2 - CYCLE 26 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R P N M L K i H G F E D C B A I

MD 11 t-t-r 2

MD MD MD MD MD 3 MD MD 4

MD MD MD 5

IEMD MD I 1MD I_ MD MD MD 6

MD MD I MD MD MD MD MD 7 MD MD MD 8

_MD MD MD MD 9

MD MDMD M MD MD MD 10 MD MD If IiJ I _MDIMDI I K 11 12 MD MD MD MD MD MD 13 MD MD MD 14 MD MD MD MD MD

-MD I.- 15 MD - Moveable Detector Page 12 of 45

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report Figure 1.4 SURRY UNIT 2 - CYCLE 26 CONTROL ROD LOCATIONS R P N M L K J H G F E D C B A 180o 1

A D A 2

- 4- 4-1-1 A -4 1--4-A I-SA SA 3 SA SA C B B C 4 SB SB 5

A B D C D B A 6 SA SB SB SA 7 900 D C C D 2700 8 SA SB SB SA 9 A B D C D B A 10 B 1 D BA 11 C B B C 12

-t B B SA SA 13 A D A 14 A B AB 15 00 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 13 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report SECTION 2 - CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured in hot shutdown with three reactor coolant pumps in operation (full flow) and with Tare greater than or equal to 530 *F per 2-NPT-RX-0 14. This verified that the time to entry of a rod into the dashpot region was less than or equal to the maximum allowed by Technical Specification 3.12.C.I [Ref. 4].

Surry Unit 2 Cycle 26 used the rod drop test computer (RDTC) in conjunction with the Computer Enhanced Rod Position Indication (CERPI) system. The rod drop times were measured by withdrawing all banks to their fully withdrawn position and dropping all of the 48 control rods by opening the reactor trip breakers. This allowed the rods to drop into the core as they would during a plant trip.

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

A typical rod drop trace for S2C26 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 20-26. Technical Specification 3.12.C.1 [Ref. 4] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. These test results satisfied this Technical Specification limit as well as the administrative limit [Ref. 10] of 1.68 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region.

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Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 2.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-06 1.38 sec. L-05 1.25 sec 1.29 sec.

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Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 2.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE Graph of BIO Time Stamp or Rod Drop: Path of ASCII Rod Drop Daa Ffle:

Rod*"8 \Drop\ 0

.,1';.17 05-25 0' 0.2 . IX~O7 7s2'~.5~17.

OXtkI il? .~ eod fl1me 0)"Nfip~tude (V).'.,

jger~F~~63 _

Page 16 of 45

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report Figure 2.2 SURRY UNIT 2 - CYCLE 26 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 I1-I 1 I 2

1.28 1.27 1.30 1,28 3 1.27 4

1.28 1.26 1.29 1.29 5

_IJ71.25 K1_1.28 6

1.27 1.27 1.29 1.29 1.38 1.26 1.37 1.28 1.28 1.30 1.28 7 1.261 1.29 1.27 1.32 8 1 1.28 1.28 1.28 1.26 9 1.29 10 1.28 1.27 1.28 1.29 1.32 ~1.29 1.31 1.3112813 1.28-I I- 4 I 11 1.27 1.31 1.29 1.26 1.26 1.29 12 1.27 1.27 13 1.26 1.29 1.26 1.29 14 1.34 1.27 1.30 15

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

Page 17 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 2.3 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 2.510 Techni aiSpecificati n Limit, 2.4 seconds 2.44 2.3(0 2.20 2.10 2.O0

-- *- Slowest Rod Time

-N- Fastest Rod Time

,*,1.90 --- Average Time i*1.80 1.70 Ad inistrative Limit, 1.68 se onds 1.60 1.50

m m m m 1.40 1.30 1.20 1.10 20 21 22 23 24 25 26 Cycle Page 19 of 45

Serial No.14-397 Docket No. 50-281 S2C26 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. 2]. The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 26, Control Bank B was used as the reference bank. Surry 2 targeted a dilution rate of 960 pemlbr 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. 13],

concluding that the definition of fully inserted for control rod positions used in startup physics testing could be changed from 0 steps withdrawn to a range of 0 to 2 steps withdrawn. The S2C26 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

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

Test bank swaps proceed in sequential order from the bank with the smallest worth to the bank with the largest worth. The second test bank should have a predicted worth higher than the first bank in order to ensure the first bank will be moved fully out before the second bank is fully 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 Page 19 of 45

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report previous test bank was fully withdrawn and the current test bank was nearly inserted. The next step was to swap the rest of the test bank in by balancing the reactivity with the withdrawal of the reference bank, until the test bank was fully inserted and the reference bank was positioned such that the core was near the initial statepoint condition. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank.

The core reactivity, moderator temperature, and differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver was repeated for all test banks. Note that after the final test bank was fully inserted, the test bank was swapped with the reference bank until the reference bank was fully inserted and the last test bank was fully withdrawn. Here the final statepoint data for the rod swap maneuver was obtained (core reactivity and moderator temperature) in order to verify the reactivity drift was within procedural limitations for the rod swap test.

A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Summary Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance of + 10% for the reference bank, +15% for test banks of worth greater than 600 pcm, and +100 pem for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was within

-4.6% 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 20 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 3.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM) (PCM) (M-P)/P X 100 B'- Reference 1309 1357 -3.5%

A 200 203 -3 pcm*

C 845 905 -6.6%

D 1138 1188 -4.2%

SA 919 923 -0.5%

SB 1032 1127 -8.4%

Total Bank Worth 5443 5703 -4.6%

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

Page 21 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 3.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600 1400 1200 g 1000

.*800 ---- Measured Predicted U Bo0 600 400 200 0

0 50 100 150 200 250 Bank Position (steps)

Page 22 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 3.2 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12.0 10.0 8.0 0

-*-Meaured

.aJ 6.0 44 L Pedited 4.0 2.0 0.0 0 5o 100 150 200 250 Bank Position (steps)

Page 23 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report SECTION 4- BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position and moderator temperature, as necessary.

The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Summary Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.10.A [Ref. 4] regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

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

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

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

Page 24 of 45

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report Table 4.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

  • The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Summary Sheet in the Appendix.

Page 25 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 4.2 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

(pcm/ppm) (pcm/ppm) (M-P)/P x 100

-7.47 -7.50 -0.4%

Page 26 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report SECTION 5 - TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.

Reactivity was measured during the RCS heat up of 2.99 TF, followed by the RCS cool down of 3.01 '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/PF. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -2.005 pem /F, a predicted Doppler temperature coefficient (DTC) of -1.83 pem/ TF, and a measurement uncertainty of +0.5 pcm/lF, is +0.325 pcm/ F. It thus satisfies the COLR criteria [Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pcm/°F.

Page 27 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 5.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

Page 28 of 45

Serial No.14-397 Docket No. 50-281 S2C26 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 available locations monitored by the moveable detectors for Cycle 26 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 [Refs. 3, 15, 18]. 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. 16] was used as an interface to CEBRZ and CECOR.

A list of the full-core flux maps [Ref. 7] taken during the startup test program and the measured values of the important power distribution parameters are given in Table 6.1. A comparison of these measured values with their COLR limits is given in Table 6.2. Flux map 1 was taken at 29.80% 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 71.10% and 99.87% power, respectively, with different control rod configurations.

These flux maps were taken to check at-power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3.

The RPDs 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 -5.3% in the 29.80%

power map, -4.0% in the 71.10% power map, and +3.8% in the 99.87% power map. The maximum average quadrant power tilt for the three maps was +1.20% in the SE quadrant for the 29.80% power map. These power tilts are within the design tolerance of 2%.

Page 29 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report The measured FQ(Z) and F. peaking factor values for the at-power flux maps were within the limits of the COLR [Ref. 8]. Flux Maps 1, 2, and 3 were used for power range detector calibration or to confirm existing calibrations.

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

It is therefore anticipated that the core will continue to operate safely throughout Cycle 26.

Page 30 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 6.1 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Bank Peak FQ(Z) Hot F. Hot (2) Core Fz Core Tilt (3) Axial No.

Burua p Max Offset Of Mapmur Power BankChannel Factor (1) Channel Factor Map Date MWD/ D __ - Offset Thimbles Description No. MTU (0/ Steps Assy Axial FQ(Z) Ass, FN Axialnt Fj Max Loc (%)

_________ _____ ___ ____Point FQZ Isy F on Low Power I 05/21/14 1.3 29.80 175 C8 25 2.276 C8 1.527 26 1.387 1.0120 SE 6.973 50 Int. Power (4) 2 05/22/14 22.0 71.10 197 Fll 25 1.985 FI1 1.483 26 1.227 1.00831 SE 4.104 50 Hot Full Power 3 05/27/14 166.0 99.87 225 Fl11 30 1.871 FII 1.467 29 1.179 1.00851 SE 2.271 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). Flux Maps 1, 2, and 3 were used for power range detector calibration or were used to confirm existing calibrations.

(1) FQ(z) includes a total uncertainty of 8%.

(2) FN 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 31 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Table 6.2 SURRY UNIT 2 - CYCLE 26 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Map No. Peak FQ(Z) Hot FN Hot Channel Factor Channel Factor Meas. Limit Node Margin* Meas. ý Limit Margin*

(%) (%)

1 2.276 5.000 25 54.5 1.527 1.889 19.1 2 1.985 3.516 25 43.5 1.483 1.695 12.5 3 1.871 2.503 30 25.3 1.467 1.561 6.0 The measured FQ(Z) hot channel factors include 8% total uncertainty. Measured FN data include no uncertainty.

  • Margin (%) = 100*(Limit - Meas.) / Limit Page 32 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 6.1 - ASSEMBLYWISE POWER DISTRIBUTION 29.80% POWER Top value -Measured, middle value = Analytical, bottom value = % Delta I Delta = (M - AWxlO0/A R P N M b K J H 0 F R 0 C B A 0.236 0.370 0.2431 0.232 0.3591 0.238 1.931 3.121 2.121 I 0.2541 0.4291 0.9631 1.069 1.002 0.4431 0.2611 0.2541 0.425 0.9511 1.053 0.985 0.433 0.257

-0.161 0.69 . 1.261 1.46 1.691 2.39 .1.391 0.371 0.989 1.1771 1.254 1.337 1272 11981 1.010 0383 0.3741 0.991 15177 1.24i1 1.309 1.255 1.1871 1.003 0.371

-1.141 -0.831 0.001 1.091 2.131 1.331 0.911 0.711 1.601 1 0.3701 1.060 1.2231 2.2721 1.2461 1.376 1.249 1.2381 1.2861 1.2861 1.2481 1.2461 1.090 1.080 0.381j 0.375 I 0.3761 1.078 1.242 1.2811 1.239 1.349 1023 1.2B51 1.2461 1 .7 4 213 4

-1.491 -1.651 -1.531 -0.681 0.52 2.021 0.901 0.071 0.161 0.97 1.48 1 0.256 0.990 1.2241 1.236 1.324 1.180! 1.2581 1.186 1.346 1.2761 1.2466 1.021j 0.2621 5 0.258 1.005 1.2471 1.269 1.346j 1.190I 1.2631 1.1891 1.349 1.270 1.247 1.004 0.257 I -0.95 -1.46j -1.871 -2.601 -1.631 -0.82l -0.411 -0.271 -0.261 -0.74 1.52 1.72 1.99 I 0.4361 1.1851 1.2711 1.3101 1.1821 1.1621 1.1691 1.1751 1.2141 1.3551 1.3101 1.2151 0.4441 6 0,4361 1.1941 1.2901 1.3511 1.2161 1.1921 1.203 1.1931 1.2171 1.3501 1.2891 1.191 0.435I

-0.10 -0.751 -1.50 -3.02 -2.83 -2.501 -2.78 -1.52 -0.25 0.391 1.591 2.00 2.101 1.271 1.242J 1.1731 1.1641 1,1251 1.1321 1.137 1.184 1,203 1.278 1.2929 1.0161 0.2461 0.2441 1.0011 7 0.242 0.996 1.263 1.2511 1.1961 1.1951 1.164 2.165 1.169I 1.196 1.199 1.249 1.260 0,992 0.2391 0.66 0.52 0.60S -0.721 -1.941 -2.62 -3.36 -2.85 -2.761 -0.991 0.66 2.331 2.55 2.441 2.931 0.3741 8 1I0,3681 1.0021 1.07j 1.3461 1.3301 1.360f 1.3631 1,2521 1.2711 1.1801 1.209 1.1371 1.1711 1.1301 1.163 1.17431 1.1701 1..9 1.2071 12771 1.269 1.3591 1.3711 1.3901 1.3261 1.1141 1.0751 0.3801 0.3671 1 1.521 0.351

1.201 -0.231---. -1.931 -2.39 ... -2.93.. .. -2.83

.. .. .. -2.34

.. .. ..-1.51

.. .. .. .. .. 2.31

..0.59 .. .. ... 3.401

.. ..... 3.661

. . . . 3.501 0.2431 1.0071 1.279 1.244 1.171 1.1631 1.1301 1.1321 1.1331 1.1821 1.2041 1.275s 1.3031 1.0291 0.247 0.2401 0.998 1.268 1.248 1.195 1.196 1 .170 1.1661 1.1631 1.193 1.191 1.244 1.265 0.997 0.241 1.321 0.85 0.851 -0.291 -2.01 -2.73 -3.45 -2.881 -2.60 -0.89 1.08 2.50 2.99 3.16 2.35 1 0.4421 1.2161 1.2911 1.3331 1.1781 1.1311 1.1711 1.1721 1.2091 1.368f 1.330 1.228 0.446 10 1 0.436 1.1951 1.291j 1.3511 1.2181 1.1951 1.2041 1.1911 1.2141 1.3481 1.288 1.193 0.436 1 1.49 1.751 -0.031 -1.331 -3.25 -5.331 -2,731 -1.561 -0.411 1.511 3.29 2.951 2.35 1 0.2601 1.0121 1.2461 1.265s 1.3251 1.1601 1.2451 1.184f 1.3541 1.2911 1.285 1.0341 0.2651 11 1 0.2581 1.006 1.2491 1.272 1.351 1.192 1.264 1.187 1.345 1.2671 1.24S 1.0041 0.258 0.931 0.61 -0.211 -0.53 -1.92 -2.68 -1.54 -0.28 0.65 1.86 3.22 3.021 2.82 I 0.3741 1.0741 1.235 1.2671 1.2141 1.346 1.245 1.3051 1.2771 1.130 0.3851 12 0.3761 1.0811 1.248 1.287 a 1.2441 1.352 1.236 1.280 1.2411 1.0771 0,375 I------------------------.-.-----.-.------------------------------------------------------

-0.601 -0.641 -1.05 -1.53 -2.44 -0.45 0.751 1.94 2.89 4.961 2.731 0.3741 0.9921 1.1751 1.2441 1.3291 1.2661 1.2191 1.0291 0.390 13 0.3771 1.004 1.1881 1.252j 1.312 1.2471 1.1791 0.9971 0.374

-0.801 -1.21 -1.131 -0.621 1.31 1.551 3.381 3.24 4.251 I 0.250 0.4291 0.982f 1.057 0.964 0.4371 0.2631 14 10.257 0.432 0.9831 1.055 0.955 0.4261 0.25s1 1 -2.671 -0.681 -0.101 0.221 0.891 2.62 2.981 I 0.241[ 0.3621 0.2351 15 I 0.238f 0.359S 0.2331 I 1.191 0.731 0.891 AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.7 STANDARDDEVIATION = 1.073 Summary:

Map No: S2-26-01 Date: 05/21/2014 Power: 29.80%

Control Rod Position: F0 (Z) = 2.276 QPTR: 0.9890 1.0075 D Bank at 175 Steps FNH = 1.527 0.9915 1.0120 FzS==1.387 1.387 MWDAxial Offset (%) = +6.973 Burnup = 1.3 MWD/MTU Page 33 of 45

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report Figure 6.2 - ASSEMBLYWISE POWER DISTRIBUTION 71.10% POWER Top value - Measured, middle value = Analytical, bottom value -  % Delta

% Delta = (M - A)xlOO/A R P N 14 L K J H a F P 0 C B A 0.2541 0.393 0.2601 1 0.2511 0.380 0.257 1 1.071 1.32 1.01 1 0.2661 0.4431 0.9781 1.1041 1.0121 0.4531 0.2701 2 I 0.2661 0.442) 0.9721 1.0961 1.0051 0.4491 0.2691 I -0.171 0.331 0.631 0.731 0.661 0.931 0.371 0.3721 0.987? 1.1661 1.241 1.314 1.2511 1.1771 0.9991 0.3901 0.3851 0.993 1.1673 1.232 1.299 1.245 1.175 0.9981 0.3871

-3.49 -0.601 -0.051 0.71 1,12 0.48 0.15 0.13 0.70 I 0.384) 1.0561 1.216!1 1.255) 1.2281 1.3411 1.226 1.258 1.2221 1.076 0,389 4 0.386 1.067 1.221[ 1.259) 1.224) 1.3271 1.2231 1.2631 1.224 1.068 0.385

-0.63 -1.081 -0.401 -0.291I 0.31 1.091 0.271 -0.40? -0.20 0.78 1.09 0.2701 0.997 1,2111 1.222 1.3191 1.1811 1.2521 1.181 1.327! 1.2401 1.2441 1.0111 0.2681 0.269 0.999 1.2251 1.250 1.3341 1.1:81 1.256 1.187 1.336 1.251 1.2251 0.999 0.269) 0.24 -0.201 -1.151 -2.22 -1.13 -0.61 -0.31 -0.51 -0.66 -0.921 1.561 1.18 -0.22 I 0.454' I"1181 1.259) 1.3161 1.235' 1.186' 1.194 1"187! 1.243) 1.333 I1.276 I 1.192) 1.1781 0.457' 0.450 1.254 1.203 1.206 1.204)1 1.2551 1.337 1.250 6 0.451 1.179 1 1.2661 1.337 0.641 0.191 -0.571 -1.58 -1.SO -1.44 -1.021 -1.41) -0.921 -0.281 0.89? 1.161 1.66 I 0.2621 1.0201 1.266[ 1.2331 1.183 1.1871 1.1441 1.1461 1.141) 1.1881 1.1891 1.244) 1.2965 1.033 0.2651 7 I 0.2601 1.0121 1.2491 1.2321 1.192 1.2051 1.1711 1.169 1.1761 1.2061 1.191) 1.231 1.247 1.009 0.258 I 0.781 0.831 1.351 0.121 -0.79 -1.481 -2.27 -1.94 -2.94 -1.481 -0.14) 1.03 1.47 2.42 2.601 1 0.3971 1.1191 1.321) 1.3391 1.258 1.1971 1.1541 1.1461 1.1521 1.1901 1.258) 1.3461 1.331) 1.1541 0.4071 0.3961 1.1141 1.314 1.337 1.261 1.2101 1.1741 1.1681 1.1741 1.209 1.259 1.3341 1.3121 1.1131 0.395 0.251 0.441 0.51 0.13 -0.22 -1.11 -1.671 -1.851 -1.911 -1.581 -0.071 0.901 1.431 3.661 2.95 0.2601 1.0171 1.2501 1.230[ 1.189 1.1911 1.155) 1.152 1.1541 1.2091 1.1961 1.2401 1.269 1.0331 0.2591 0.2591 0.35! 1.0131 0.421 1.253) 0.36! 1.2291 0.11) 1.190

-0.11[ 1.206

-1.22 1.1761

-1.76 1.169

-1.49 1.171

-1.43 1.204 0.40 1.188 0.66 1.227 1.09 1.252 1.351 1.014 1.88 0.2601

-0.211 0.4541 1.1861 1.2631 1.3271 1.2351 1.1701 1.1921 1.197 1.261) 1.3471 1.2801 1.1931 0.4541 10 0.452 1.180 1.266) 1.337) 1.255 1.205 1.206 1.202) 1.253 1.335 1.2641 1.1791 0.4521 0.36 0.49 -0.20 -0.74) -1.57 -2.92 -1.18 -0.40) 0.631 0.89 1.26 1.191 0.401 I 0.2691 0.9971 1.2171 1.2381 1.3211 1.1751 1.2541 1.193) 1.358! 1.2611 1.2441 1.0141 0.273 11 I 0.269) 1.0001 1.2261 1.251) 1.3381 1.1891 1.256 1.186 1.333 1.249) 1.224 0.999 0.269 1 0.16 -0.281 -0.711 -1.041 -1.25 -1,21 -014 0.63 1.851 0.941 1.64 1.48 1.33 1 0.3801 1.0591 1.2111 1.2521 1.2171 1.332 1.2331 1.2811 1.2451 1.1031 0.3931 12 1 0.3861 1.065! 1.2251 1.2641 1.2201 1.3291 1.221) 1.2591 1.221 1.0661 0.386) 1 -1.481 -0.98! -1.12 -0.971 -0.931 0.201 1.021 1.79! 1.97 3.501 1.77) 1 0.3831 0.9861 1.165 1.2308 1.3121 1.2511 1.194I 1.0161 0.396 13 0.387 0.999) 1.175 1.242 1.301) 1.237 1.168 0.9931 0.385 1 -1.031 -1.291 -0.83 -0.31 0.83 1.16 2.251 2.281 2.83

[ 0.2581 0.4451 1.0031 1.101 0.981) 0.450) 0.2721 14 I 0.2691 0.449! 1.0031 1.097 0.975 0.443) 0.267 I -3.991 -0.811 -0.051 0.36 0.641 1.69 2.02 0.259 0.391 0.254 15 0.257 0.389 0.252 0.92 0.701 0.70)

AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.0 STANDARD DEVIATION = 0.785 Summary:

Map No: S2-26-02 Date: 05/22/2014 Power: 71.10%

Control Rod Position: F0 (Z) = 1.985 QPTR: 0.9942 1.0024 D Bank at 197 Steps F*N = 1.483 0.9950 1.0083 Fz Bp = 1.227 .22.0 Axial Offset (%) = +4.104 Burnup = 22.0 MWD/MTU Page 34 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report Figure 6.3 - ASSEMBLYWISE POWER DISTRIBUTION 99.87% POWER Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta - IM - A)xlOO/A R P N 2 E, K J H 0 G F B C B A I 0.2611 0.4061 0.2671 1 I 0.2591 0.400 0.264 i 0.81 1.52 1.21 I 0.2671 0.446 0.9781 1.129 1.0111 0.4551 0.2721 2 0.268 0.4451 0.9711 1.119 1.003 0.452 0.2711 I -0.25 0.261 0.681 0.931 0.771 0.741 0.271 I 0.3721 0.9701 1.148a 1.2301 1.3031 1.2401 1.1601 0.984 0.389 3 I 0.3841 0.9761 1.150 1.222 1.289 1.234 1,158 0.981 0.3861 I -3.231 -0.58 -0.15

..-----------------------------.----.--.--------------.-------------.......... 0.65 1.06 0.50 0.18 0.27 0.821 S0.381 1.0351 1.1981 1.2381 1.216 1.3301 1.219 1.2451 1.2061 1.0561 0.388 4 0.385 1.0471 1.2031 1.2441 1.217 1.3151 1.2161 1.2471 1.206 1.049 0.385 1 -1.081 -1.171 -0.381 -0.521 -0.101 1.141 0.271 -0.191 0.02 0.66 0.71!

1 0.2691 0.9721 1.1891 1.2131 1.314 1.1741 1.2571 1.1891 1.3291 1.2381 1.2221 0.9911 0.2701 5 1 0.2711 0.9821 1.206 1.2401 1.335 1.1961 1.262 1.1951 1.3351 1.2411 1.2061 0.9811 0.2701 I.........................................................................................................

-0.671 -0.991 -1.4 1 -2.191 -1.541 -1.82j -0.421 -0.471 -0.491 -0.231 1.291 0.991 -0.061 0.4541 1.1571 1.2391 1.3141 1.2861 1.2091 1.214 1.2131 1.2921 1.3341 1.258 1.1011 0.4591 6 0.4541 1.1611 1.2501 1.3371 1.306 1.2271 1.220 1.228 1.3061 1.3371 1.249: 1.1601 0.4531 I 0.071 -0.381 -0.901 -1.721 -1,511 -1.471 -0.52 -1.21 -1.061 -0.24 0.73 0.911 1.381 0.2691 1.0151 1.2461 1.2211 1.188 1.213! 1.1691 1.1671 1.1651 1.2141 1.197 1.2331 1.2501 1.0291 8.271 7 0.2671 1.0101 1.238 1.224 1.1991 1.229 1.1901 1.185 1.1951 1.230 1.1991 1.223! 1.2361 1.0071 0.265 0.621 0.501 0,64 -0.251 -0.891 -1.34 -1.75 -1.55 -2.541 -1.31 -0.201 0.801 1.131 2.201 2.241 I 0.4101 1.1431 1.3091 1.3251 1.2621 1.2121 1.1731 1.1691 1.1721 1.2091 1.2641 1.3301 1.3131 1.1631 0.4161 8 1 0.407 1.1371 1.302 1.3241 1.2611 1.224 1.1901 1.1871 1.189: 1.2231 1.266j 1.3221 1.300 1.135I 0.407 0.69 0.501 0.55 0.051 -0.371 -0.971 -1.391i 1.53 -1.46 -1.13 -0.16 0.59 0.98 2.51 .. 2.11 0.2671 1.0161 1.2471 1.2241 1.2021 1.219 1.179 1.1711 1.178 1.230 1.2021 1.2281 1.253 1.0271 0.269 9 0.2661 1.0111 1.241 1.2211 1.198 1.230 1.195 1.185 1.1901 1.228 1.1961 1.2191 1.240 1.0121 0.267 1 0.561 0.521 0.50 0.22 0311 -0.87 -1.37 -1.20 -1.001 0.8 0.46. 0.75 1.021 1.451 0.40 I 0.4571 1.1711 1.2491 1.3291 1.292 1.2011 1.2071 1.2221 1.3121 1.3461 1.2591 1.1731 0.4591 10 I 0.4541 1.161 1.2501 1.337 1.307 1.229 1.220 1.226 1.3051 1.3351 1.2491 1.161 0.4551 I. . . .0.71 0.84

-0.081 -0.58 -1.18

-2.29 -1.04 -0.301 0.56! 0.841 0.77j 1.02 0.93 0.2711 0.9801 1.1981 1.225 1.3221 1.18! 1.2:551 1.159 1:354 1.2581 1.2271 0.597 0.275I 11 0.271 0.982 1.2071 1.242 1.3371 1.1971 1.2631 1.194 1.333 1.239 1.205 0.982 0.271 I 0.06 1 -0.741 -1.34 -1.091 -1.101 -0.62 0.421 1.54 1.50 1.81 1.52 1.38 0.378! 1.08 1.1931 1.238 1.2131 1.3191 1.2251 1.2661 1.2301 1.0871 0.3941 12 I 0.385 1.049 1.2071 1.249 1.220 1.317 1.214 1.243 1.203! 1.0471 0.385!

-1.051 -1.18 -0.88 -0.57 0.15 0.95! 1.861 2.231 3.791 2.43!

1 0.382 0.9701 1.150l 1.2291 1.300 1.2431 1.1791 1.001 0.396j 13 I 0.386! 0.981 1.157 1.2311 1.290 1.226 1.151 0.961 0.384 I -1.031 -1.081 -0.641 -0.141 0.791 1.361 2.441 2.541 3.141 1 0.2621 0.449 1.003! 1.129 0.9871 0.455! 0.275 14 1 0.2711 0.4521 1.001 1.120 0.9741 0.446! 0.268 I -3.141 -0.56j 0.25 0.791 1.381 2.10! 2.52!

i 0.266! 0.404! 0.2631 15 I 0.264! 0.4001 0.259 1 0.771 0.991 1.36!

AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.0 STANDARD DEVIATION c 0.721 Summary:

Map No: S2-26-03 Date: 05/27/2014 Power: 99.87%

Control Rod Position: F0 (Z) = 1.871 QPTR: 0.9927 1.0024 D Bank at 225 Steps rN, = 1.467 0.9964 1.0085 Pz p ==1.179 166.0 MAxial Offset (%) = +2.271 Burnup = 166.0 MWD/MTU Page 35 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report SECTION 7 - CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 2 Cycle 26 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, Technical Specification limits, or COLR limits. It is anticipated, based on the results associated with the S2C26 startup physics testing program, that the Surry 2 core will continue to operate safely throughout Cycle 26.

Page 36 of 45

Serial No.14-397 Docket No. 50-281

$2C26 Startup Physics Tests Report Table 7.1 SURRY UNIT 2 - CYCLE 26 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 1602 1616 -14 +50 (HZP ARO), ppm 1602 161__4___

Critical Boron Concentration 1427 1421 6 -28 (HZP Ref Bank in), ppm Isothermal Temp Coefficient -2.005 -2.195 0.190 L2 (HZP ARO), pcm/F Differential Boron Worth -7.47 -7.50 -0.4% +/-10%

(HZP ARO), pcm/pm.

Reference Bank Worth 1309 1357 -3.5% :10%

(B-bank, dilution), pcme A-bank Worth (Rod Swap), pcm 200 203 -3 +/-100 C-bank Worth (Rod Swap), pcru 845 905 -6.6% +/-15%

SB-bank Worth (Rod Swap), pcm 1032 1127 -8.4% +/-15%

SA-bank Worth (Rod Swap), pcm 919 923 -0.5% +/--15%

D-bank Worth (Rod Swap), pcm 1138 1188 -4.2% +15%

Total Bank Worth, pcm 5443 5703 -4.6% +10%

S2C26 Testing Time: 7.2 hrs

[criticality 05/20/2014 @ 18:33 to end of testing 05/21/2014 @ 01:42]

Recent Startups:

S1C26 testing time: 7.8 hrs

$2C25 testing time: 6.1 hrs S IC25 testing time: 5.7 hrs S2C24 testing time: 7.1 hrs SI C24 testing time: 7.0 hrs

$2C23 testing time: 9.4 hrs SIC23 testing time: 6.2 hrs S2C22 testing time: 6.2 hrs S IC22 testing time: 8.0 hIs Page 37 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report SECTION 8 - REFERENCES

1. M. P. Shanahan, "Surry Unit 2, Cycle 26 Design Report", Engineering Technical Evaluation ETE-NAF-20140036, Rev. 0, May 2014.
2. R. W. Twitchell, "Control Rod Reactivity Worth Determination by the Rod Swap Technique,"

Topical Report VEP-FRD-36-Rev. 0.2-A, September 2004.

3. C. J. Wells and J. G. Miller, "The CEBRZ Flux Map Data Processing Code for a Movable In-core Detector System," Engineering Technical Evaluation ETE-NAF-2011-0004, Rev. 0, March 2011.
4. Surry Units 1 and 2 Technical Specifications.
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 I Cycle 2 1," Technical Report NE-1466, Rev. 0, January 2006.
6. J. A. Cantrell, "Surry Unit 2 Cycle 26 TOTE, Core Follow, and Accounting Calculations,"

Calculation PM-1655, Rev. 0, April 2014.

7. R. A. Hall et al, "Surry Unit 2 Cycle 26 Flux Map Analysis, "Calculation PM-1656, Rev. 0, and Addenda A - B, May 2014.
8. T. S. Psuik, C. D. Clemens, "Reload Safety Evaluation Surry 2 Cycle 26 Pattern EBA, "EVAL-ENG-RSE-S2C26, Rev. 0, March 2014.
9. S. B. Rosenfelder and S. S. Kere, "RMAS v6 Verification," Calculation PM-1075, Rev. 0, May, 2005.
10. B. J. Vitiello & 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.

It. B. R. Kinney, "Surry Unit 2 Cycle 26 Full Core Loading Plan," Engineering Technical Evaluation ETE-NAF-2013-01 10, Rev. 0, October 2013.

12. N. A. Yonker, "Validation of Rod Drop Test Computer for Hot Rod Drop Analysis," Calculation PM-1044, Rev. 0, November, 2004.
13. A. H. Nicholson, "Justification for Defining 0 to 2 Steps Withdrawn as Fully Inserted When Measuring Control and Shutdown Banks During the Surry Startup Physics Testing Program,"

Engineering Transmittal ET-NAF-06-0046, Rev. 0, April, 2006.

14. B. R. Kinney, "Surry Unit 2 Cycle 26 Startup Physics Testing Logs and Results," Memorandum MEMO-NCD-20140016, Rev. 0, May 2014.
15. J. G. Miller, "The CECOR Flux Map Analysis Code for a Movable In-core Detector System,"

Engineering Technical Evaluation ETE-NAF-20 11-0011, Rev 0, May 2011.

16. A. M. Scharf, "Qualification and Verification of the CECOR-GUI," Engineering Technical Evaluation ETE-NAF-2013-0081, Rev. 0, November 2013.
17. Nuclear Engineering Standard DNES-AA-NAF-NCD-5007, Rev. 1, "Startup Physics Tests Results Reporting."
18. 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.

Page 38 of 45

Serial No.14-397 Docket No. 50-281 S2C26 Startup Physics Tests Report APPENDIX - STARTUP PHYSICS TEST

SUMMARY

SHEETS Page 39 of 45

Serial No.14-397 Docket No. 50-281

  • Appendix Surry Power Station Unit 2 Cycle 26 Startup Physics Test Summary Sheet - Formal Tests (Page 1 of 6)

Measured Value Design Acceptance Date Preparer/

Design Criteria I Acceptance Criteria Criteria CCriteria Mat Reviewerl Met Test v r ZPTR-- - background < ZPTR < POAH V-/ Yes 13Rt1

  • ..*IO to background = . 1 >rio" amps NIA N/A -. 0: I I tJ 1.Kr10" amps POAH= 2..'9xiv amps No pc q IS TCpafekt ___

1 Pc=~~ ~ / JX, pcrl{(p.px100%<4.0%

- L' Yes Izen I (measured reactivity) The allowable range is set to the larger of .'*/'

p= C-0.o0p - 411. *" pcm the measured results or the pre-critical (predicted reactivity) bench test. N/A NIA 100%

- X 10.

pt)/pt)

&pc - pt/t ,_q, Pre-critical Benchpcm Test Results

&-20

%D = {(c-07

%D =-0.77 .- o. ' Allowable range . opcm (CS)M RO= G ppm (CS)ARo-- 1616 50 ppm A(Ca)MOI 5 1000 PCM Y Yes BAR BAO I[T.S. 4.10AJ 24t:

(Adj. To design conds.) .(C-)ARo=(OB)mAR, - (C)ARO = -- i ppm aCs* -7.430 pcrn/ppm - No No,.VVW M~ 2hW,5 :5 Rrn aTiISO=C OLO ______i.

jN 3

(XT"S)MAo = o~rIe 3.670 pcm/F m Yes Yes - Al 0

(aT A~o(aTsO)mo =.2 - 9- +/-+/-2 pcm/ F 3.7 cm" "Z

-Z.Oor pcm/°F where: (aMu"); 6.0 pcmr0F [COLR 3.4) No No (CLTISO)MARo - (aT[SO)ARO -0 120 pcm/rF (an. ) 0.5 porn/F (coroo)2; -1.83 pcm/PF linREFM-" i8RUF=2 1357

  • 10%-v Yes'zlp/' *e, I1_____ pcm 100x(Meas. - Des.)/Des. -  % ____ No A .i*s-s- j /tv References 1.) DNES-AA-NAF-NCD-4015, Rev. 0 2.) ETE-NAF-2014-0036, Rev. 0 3.) ETE-NAF-2014-0039, Rev. 0 4.) Calculation PM-1 652 Rev. 0 Page 40 of 45

Serial No.14-397 Docket No. 50-281 Appendix Surry Power Station Unit 2 Cycle 26 Startup Physics Test Summary Sheet - Formal Tests (Page 2 of 6)

'Design1 DeinAcceptanc Datel Dae/ Preparerd Measured Value Design Criteria Acceptance Criteria Criteria Arep Time ofPRevieer CriteMet Test Reviewer (Ca)Msa (Ce)a--'2 1435 +A(C)ARO + 28 ppm I'7,y '64/

b-7 , ppm A(CB)ARO= -11q ppm (from above) N/A Y N/A (CB)s= It*'I.. +/-28 ppm No

_(Ca)' - (C)13 Sr ppM I

____y________zzJs *,l1 *J____

CECS)M= CL3C -7.50 _0.75 pcnmppm NIA Y.I NA NIA 7

" 7,j *7 pcmippm 1AcaCB(OzC8)M-(aCG)=!.0.OS pcmnppm No IARS= (IARS)3= -2 03.1 _100 Opc (IA pcm~ N/ INIA Yesi I Io:oo 5"V'*l" A,/.rY

- pcm Meas. - Des.. = -2..9 pcm N/A No ____,V_

Ic RS= CIO RV =_- 1 0 /.*_T +/-15% Ye

  • L P/

t enl~

pcm 100x(Meas. - Des.)/Des. =

'~Oj~

+/-5%N/A

.4

. ." ' " .W... 6 M "S*i

  • "*I*"i N/__

"R* ' *" .. ' "

_No NA N

00 IsA(Is= 'J -3. 1 15% ,/ Yes N*" r *b 4SI K

_ Is.,?_ pcm 10Ox(Meas. - Des.)/Des. = -. Oi" % N!A No 0:00 VW Is*RS= ' (ISE;)* 12, 1:15% NIA Ye N/ 61/1V~ B$[L ji031 pcm 100x(Meas. - Des.)/Des. = -j&,Lq  % Nt__No o *4p'./

loPS=. (iR~S)3= .. 1. 2 -. +/-15% N-A YeS N/A O711.o JA 1 1 *..$,ji . pcmI 00x(Meas. - Des.)/Des.  % W-q_N_ _ _ No _ __

- "IjZ.. pcm 100x(Meas. - Des.)!Des. = :  %

Tu =%N/A ~ Yes No N/A ,04) 0O References 1.) DNES-AA-NAF-NCD-4015, Rev.0 2.) ETE-NAF-2014-0036, Rev. 0 3.) ET-NAF-2014-0039, Rev. 0 4.) Calculation PM-i1852 Rev. 0 Page 41 of 45

Serial No.14-397 Docket No. 50-281' Appendix Surry Power Station Unit 2 Cycle 26 Startup Physics Test Summary Sheet - Formal Tests (Page 3 of 6)

Design Acceptance Date/ Prepared Measured Value Design Criteria Acceptance Criter iteria Criteria Met Time of Reviewer Met Test Map Power Level (% Full Power) = 9. 2 /.%'

Max Relative Assembly Power. %DIFF (M-P)/P 1 *10% for P, ýO.9 Yes ~bu

%DlFF= %forPi >.s 115%forP,'<0.9 N/A No N/A /116Y*-5 9*t "  % for Pi'0.9 (P, assy power) 1 Nuclear Enthalpy Rise Hot Channel Factor, FAH(N)

FAH(N)s1i.56(1+0.3(1-P)) [COLR 3.71 NIA FMH(N)= 1* N/A No Total Heat Flux Hot Channel Factor, FQ(Z)

Peak Fo(Z) Hot Channel WA F 0 (Z)!59K(Z) lCOLR 3.7J N/ Yes INA Maximum Positive Incore Quadrant Power Tilt 1lt-/0 /2'0 s 1.021 No NA No Rodded Flux Map Criterion (If either criterion Is met, a rodded flux map S 30% powar with rods at the Insertion limit is nat required) 4 Max RPD %DiFF`1=-,ý.% I NA A N/2.% 4 /'.

for P> 0.9 Yes OR Synthesized FdH at poer limtin limiting power'4 A IN/A W F,*H S; 1.56(1+0.3(1-P)) [COLR 3.71]

NIA __

No References 1.) DNES-AA-NAF-NCD-4015, Rev. 0 2.) ETE-NAF-2014-0036. Rev. 0 3.) ETE-NAF-2014-0039, Rev. 0 4.) Calculation PM-1652 Rev. 0 Page 42 of 45

Sedal No.14-397 Docket No. 50-281 Appendix References 1.) DNES-AA-NAF-NCD-4015, Rev. 0 2.) ETE-NAF-2014-0036, Rev. 0 3.) ETE-NAF-2014-0039, Rev. 0 4.) Calculation PM-1 652 Rev. 0 Page 43 of 45

Serial No.14-397 Docket No. 50-281 Appendix Surry Power Station Unit 2 Cycle 26 Startup Physics Test Summary Sheet - Formal Tests (Page 5 of 6)

Ooig tosign D'ate/

Acceptance DTrn Preparerd alue Design Criteria Acceptance Critoria Cri riteria Met ofReviewer Nucloar EnthaIpy Rise Hot Channol Factor, FAH(N)

FAK(N)= t-1.) DN-S-AA-NAF-NCD-4015, Rev. 0 2.) ETE-NAF-2014-0036, Rev. 0 3.) ETE-NAF-2014-0039, Rev. 0 4.) Calculation PM-1652 Rev. 0 Page 44 of 45

Serial No.14-397 Docket No. 50-281' Appendix Surmy Power Station Unit 2 Cycle 26 Startup Physics Test Summary Sheet - Formal Tests (Page 6 of 6) 1.) DNES-AA-NAF-NCD-4015, R 2.) ETE-NAF-2014-0036, Rev. 0 3.) ETE-NAF-2014-0039, Rev. 0 4.) Calculation PM-1652 Rev, 0 Page 45 of 45

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