ML19071A109

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Unit, Cycle 29 Startup Physics Tests Report
ML19071A109
Person / Time
Site: Surry Dominion icon.png
Issue date: 03/05/2019
From: Stanley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation, Region 2 Administrator
References
19-094
Download: ML19071A109 (49)
v • d • e


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. Dominion Energy Services, Inc.

~ Dominion I~

5000 Dominion Boulevard, Glen Allen, VA 23060 DominionEnergy.com p, Energy March 5, 2019 .

  • United States Nuclear Regulatory Commission Serial No.: 19-094

~egional Administrator - Region II NRA/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 29 STARTUP PHYSICS TESTS REPORT As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 2 Cycle 29 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 29 on December 5, 2018. The results of the physics tests were within the applicable Technical Specifications limits.

If you have any questions or require additional information,

  • please contact Mr. Gary Miller at (804) 273-2771.

Sincerely, B. L. Stanley, Director Nuclear Regulatory Affairs Dominion Energy Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None

Serial No.19-094 Docket No. 50-281 S2C29 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 Mr. J. R. Hall NRC Project Manager- North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B-1A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.19-094 Docket No. 50-281 y

ENCLOSURE SURRY UNIT 2 CYCLE 29 STARTUP.PHYSICS TESTS REPORT February 2019 Virginia Electric and Power Company (Dominion Energy Virginia)

Surry Power Station Unit 2 Page 1 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure CLASSIFICATIONilllSCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion Energy (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMP ANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

Page 2 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure TABLE OF CONTENTS Classification/Disclaimer ............................................................................................................... 2 Table of Contents ...........................................................................................................................3 List of Tables ................................................................................................................................... 4 List of Figures .................................................................................................................................. 5 Preface ............................................................................................................................................. 6 Section I --Introduction and Summary ..................................................................................... 7 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 ............................................................................................................. 37 Section 8 -- References ............................................................................................................... 39 Appendix A -- RCP Startup Order ............................................................................................. 40 Appendix B - Startup Phyics Tests Summary Sheets ........................................................... 41 Page 3 of 47

Serial No.19-094 Docket No. 50-281 S2C29 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 En~points Summ.ary ................................................................................... 26 Table 4.2 - Boron Worth Coefficient ........................................... ,............................................ 27 Table 5.1 - Isothermal Temperature Coefficient Summary ................................................... 29 Table 6.1 - Incore Flux Map Summary ....................................................................................32 Table 6.2 - Comparison of Measured Power Distribution Parameters with their Core Operating Limits ...................................................................................................... 33 Table 7.1 - Startup Physics Testing Results Summary ........................................................... 38 Page 4 of47

Serial No.19-094 Docket No. 50-281 S2C29 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 26.94% Power .............................................. 34 Figure 6.2 - Assemblywise Power Distribution 70.57% Power ..............................................35 Figure 6.3 - Assemblywise Power Distribution 99.89% Power ..............................................36 Page 5 of 47

Serial No.19-094 Docket No. 50-281 S2C29 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 29 (S2C29) core could be operated safely, and makes an initial evaluation of the performance of the core. This report was performed in accordance with DNES-AA-NAF-NCD-5007, Rev. 3 [Ref. 12]. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard testing techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at Surry Power Station. Therefore, only a cursory discussion of thes.e 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 S2C29 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) _test results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer/ reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations _performed by Dominion Energy's Nuclear Engineering and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specifications and COLR Limits.

Per Surry Technical Specification 6.6.A [Ref. 6], "the report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program, and a comparison of these values with design predictions and specifications." Per UFSAR Section 3.6.1.l [Ref. 20],

"a detailed series of start-up physics tests are performed," followed by references to core power distribution measurements, i.e., flux maps. The S2C29 Startup Physics Tests Report includes, as required, a description of measured values and a comparison of these values to design predictions of the tests performed during startup testing and the initial power ascension flux maps performed thereafter.

Page 6 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure SECTION 1 - INTRODUCTION AND

SUMMARY

On October 27, 2018, Unit No. 2 of Surry Power Station completed Cycle 28 and began refueling [Ref. 1]. During this refueling," 84 of the 157 fuel assemblies in the core were replaced with 64 fresh Batch S2/31 assemblies and 20 twice-burned Batch S 1/29 assemblies last irradiated in Surry 1 Cycle 28 [Ref. 1]. The Cycle 29 core consists of 9 sub-batches of fuel: three fresh batches (S2/31 A, S2/31B and S2/3 l C), two once-burned batches (S l/30A and S2/30A), and four twice-burned batches (S1/29A, S1/29B, S1/29C and S2/29B). Like the previous cycle, S2C29 will have a full core of the 15xl5 Upgrade Fuel Design [Ref. 1]. One batch S2/30A assembly (Assembly 817 in Full-core location M-08) was reconstituted with a single stainless steel rod [Ref. 14].

The Westinghouse Upgrade fuel includes three ZIRLO Intermediate Flow Mixing (IFM) grids for improved thermal-hydraulic performance, ZIRLO (I-spring) structural mid grids with balanced mixing vane pattern, "tube-in-tube" guide thimbles, and the use of optimized ZIRLO fuel clad that improves corrosion resistance and oxidation of the bottom portion of the fuel clad to improve debris resistance. The Upgrade fuel used for all batches includes the Westinghouse Robust Protective Grid (RPG), modified Debris Filter Bottom Nozzle (mDFBN) and the Westinghouse Integrated Top Nozzle (WIN) [Ref. 13].

This cycle uses Westinghouse's Integral Fuel Burnable Absorber (IFBA) fuel product. The IFBA design involves the application of a thin coating of 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 p~r 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 ZrB 2* 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].

Cycle 29 loads two Secondary Source Assemblies (SSAs) in core locations H-04 and H-12 to improve Source Range Detector response. Each assembly consists of six source rods containing Page 7 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure antimony and beryllium pellets encapsulated in a double layer of stainless steel cladding. There are no thimble plugging devices in S2C29. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 29 core.

The S2C29 full core loading plan [Ref. 2] is given in Figure 1.1, and the beginning of cycle fuel assembly bumups [Ref. 18] are given in Figure 1.2. The in-core 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 29 core [Ref. 1].

According to the Startup Physics logs, the Cycle 29 core achieved initial criticality on December 5, 2018 at 11 :59 [Ref. 3]. Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. This cycle used the Reactivity Measurement and Analysis System (RMAS) to perform startup physics testing. Note that RMAS v.7 [Ref. 9] was used for S2C29 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 seconds Technical Specification [Ref. 6] limit, as well as the 1.68 seconds l 5xl 5 Upgrade Fuel administrative limit

[Ref. 8].

Individual control rod bank worths were measured using the rod swap technique [Ref. 4]. For the purpose of this test, a bank was defined as 'fully inserted' when it was 2 steps off the bottom of the core [Ref. 10]. The sum of the individual measured control rod bank worths was within -2.2% of the design prediction. The reference bank (Control Bank B) worth was within -1.7% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within -6.7% of the design predictions. Control rod banks with design predictions less than 600 pcm (Control Bank A) were within 18 pcm of the design prediction. These results are within the design tolerances of+/- 15%

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

Measured critical boron concentrations for two. control bank configurations, all rods out (ARO) and Reference Bank (B-bank) in, were within the design tolerances and the Technical Page 8 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Specification criterion [Ref. 6] that the overall core reactivity balance shall be within +/- 1% ~k/k of the design prediction. The boron worth coefficient measurement was within -1. 7% of the design prediction, which is within the design tolerance of+/- 10%.

The measured isothermal temperature coefficient (ITC) for the ARO configuration was within -0.189 pcm/°F of the design prediction. This result is within the design tolerance of +/-2.0 pcm/°F.

All zero power physics testing results met the tighter criteria permitting the first flux map analysis to be performed as high as 50% power (versus 30% power).

The Reactor Coolant Pump (RCP) start sequence is as follows: 'C' RCP started on 12/01/18 at 10:21, 'A' RCP started on 12/01/18 at 15:40, and 'B' RCP started on 12/03/18 at 09:47

[Appendix A].

Core power distributions were all within established design tolerances. The measured assembly power distributions were within +/-8.7% of the design predictions, where an 8.7% maximum difference occurred in the 26.94% 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]. The first power ascension flux map was not within the maximum incore quadrant power tilt design tolerance of 2%.

(QPTR < 1.02). NEF performed a review to confirm that the measured quadrant tilt for this map was bounded by the current safety analysis [Ref. 13]. The subsequent two power ascension flux maps had power tilts within this design tolerance, so no additional assessment was performed. The tilt is expected to remain within the design tolerance for the remainder of the cycle. The maximum positive in-core quadrant power tilts ranged from 2.87% to 1.57% during the power ascension.

The total RCS Flow was 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 290,012 gpm.

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

Page 9 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table I.I SURRY UNIT 2 - CYCLE 29 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 12/04/18 19:50 HSD 2-NPT-RX-014 Reactivity Computer Checkout 12/05/18

  • 13:21 HZP 2-NPT-RX-008 Boron Endpoint - ARO 12/05/18 13:21 HZP 2-NPT-RX-008 Zero Power Testing Range 12/05/18 13:21 HZP 2-NPT-RX-008 Boron Worth Coefficient 12/05/18 14:50 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 12/05/18 13:45 HZP 2-NPT-RX-008 BankB Worth 12/05/18 14:50 HZP 2-NPT-RX-008 Boron Endpoint - B in 12/05/18
  • 14:50 HZP 2-NPT-RX-008 Bank A Worth-Rod Swap 12/05/18 17:07 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap 12/05/18 17:07 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 12/05/18 17:07 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap 12/05/18 17:07 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap 12/05/18 17:07 HZP 2-NPT-RX-008 Total Rod Worth 12/05/18 17:07 HZP 2-NPT-RX-008 Flux Map - less than 50% Power* 12/06/18 15:51 26.94% 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 12/07/18 15:45 70.57% 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 12/11/18 09:52 99.89% 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 12/10/18 10:00 HFP 2-NPT-RX-009

  • Results of zero power physics testing permitted the first flux map to be performed up to 50%

power (versus 30% power if specified criteria were not met). The first flux map was performed below 30% power in anticipation of a required chemistry hold.

Page 10 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 1.1 SURRY UNIT 2 - CYCLE 29 CORE LOADING MAP SURRY UNIT 2 - CYCI,E 29 FULJ~ CORE LOADUlG l?.t.l\.N Re;VISJON NO. 0 R'I';1;-Nl!F-21)1Jl-(!065 Rll'\I'. 0 J\TTJ\C:ilC~Eti1' l l>AG& 1 OF l

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Page 11 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 1.2 SURRY UNIT 2- CYCLE 29 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 35.241 40.661 35.421 MEASURED I 1 I 35.311 41.061 35.271 PREDICIED I 2 I 40.471 24.731 0.001 0.00[ 0.001 24.801 40.551 2 I 40.511 24.941 0.001 0.001 0.001 24.871 40.511 3 41.291 a.oar o.op1 0.001 21.511 0.001 0.001 a.oat 41.591 3 41.411 0.001 0.001 a.oat 21.261 0.001 0.001 0.001 41.431 4 41.901 a.oat 0.001 19.821 19.531 20.551 19.681 19.901 0.001 0.001 41.641 4 41.481 0.001 0.001 19.861 l-9.511 20.271 19.541 19.901 0.001 0.001 41.461

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

41.601 0.001 0.001 23. 711 24.161 0.001 23.301 0.001 24.021 23.561 0.001 0.001 41.181 5 I 5 I 41.401 0.001 0.001 23.451 24.251 0.001 23.381 0.001 24.231 23.481 0.001 0.001 41.301 6 t 24. 771 0.001 19.941 24.191 o.op1 23.751 0.001 23.411 0.001 24.371 19.941 0.001 24.871 6 I 24.81[ 0.001 19.89! 24.21[ o.oo r 23.481 0.001 23.431 0.001 24.251 19.871 0.001 24.891 7

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

35.371 a.oar 0.001 19. 791 0.001 23.311 24.661 24.35[ 24.691 23.431 o.oor 19.511 0.001 0.001 35.271 7 35.241 0.001 0.001 19.531 0.001 23.421 2.4.641 24.621 24.651 23.471 0.001 19.501 0.001 0.001 35.261 8 41.361 0.001 21.521 20.181 23.611 0.001 24.521 21.491 24.521 a.oar 23.401 20.271 21.301 0.001 41.121 8 41.201 0.001 21.261 20.251 23.411 0.001 24.611 21.61 I 24.621 0.001 23.421 20.251 21.251 0.001 41.20 I 9 35.051 0.001 a.oar 19.451 a.001 23.891 24.371 24.731 24.551 23.461 0.001 19.451 0.001 a.001 35.701 35.241 a.001 0.001 19.511 a.oar 23.471 24.651 24.621 24.631 23.411 0.001 19.531 0.001 0.001 35.251 10 24.791 0.001 19.921 24.09f 0.001 23.501 a.oar 23.451 0.001 24.041 19.981 0.001 24.561 10 24.901 0.001 19.861 24.251 0.001 23.431 0.001 23.481 0.001 24.21[ 19.891 0.001 24.821 11

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I 41.131 0.001 a.oar 23.471 24.261 0.001 23.441 a.oar 24.331 23.461 0.001 0.001 41.22 I 11 I 41.301 0.001 0.001 23.491 24.231 0.001 23.371 a.oar 24.251 23.451 0.001 a.oar 41.401 12 41.521 a.oar 0.001 20.251 19.481 20.131 19.361 20.011 a.oat 0.001 41.371 12 41.461 a.oar a.oar 19.90 I 19.541 20.271 19.511 19.861 a.oar 0.001 41.481 13

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I 41.431 a.oar a.oar 0.001 21.231 0.001 0.001 a.oar 41.161 13 I 41.421 0.001 0.001 0.001 21.261 0.001 a.oar a.oar 41.411 14 40.541 24.781 0.001 a.oar 0.001 25.131 40.091 14 I 40.511 24.87} 0.001 a.oat 0.001 24.941 40.511 15 I 35.351 40.751 35.321 15

. I 35.251 41.0~l 35.301 R p N M. L K J H G F D C B A Page 12 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure-1.3 SURRY UNIT 2 - CYCLE 29 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 MD+ 8 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

+ * - Location not used for any map.

Page 13 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 1.4 SURRY UNIT 2 - CYCLE 29 CONTROL ROD LOCATIONS R p N M L K J H G F E D C B A 180° 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.19-094 Docket No. 50-281 S2C29 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 than or equal to the maximum allowed by Technical Specification 3.12.C. l [Ref. 6].

S2C29 used the Rod Drop Measurement Instrument (RDMI) to gather and analyze the rod drop data [Ref. 7]. The rod drop times were measured by withdrawing all banks to their f~lly 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 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.

A typical rod drop trace for S2C29 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 20-29. Technical Specification 3.12.C.1 [Ref. 6] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. These test results satisfied this Technical Specification limit as well as the administrative limit [Ref. 8] of 1.68 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region.

The average rod drop time of 1.36 seconds for S2C29 increased slightly from 1.35 seconds for S2C28.

Page 15 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 2.1 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD(S) AVERAGE TIME G-13 1.47 sec. L-O~/K-04 1.32 sec. 1.36 sec.

Page 16 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 2.1 SURRY UNIT 2- CYCLE 29 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE s

4.S .i

. Initiation of Rod

, . Entry {Extreme Drop in Voltage) l lM~

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t Bottom of Dash pot li Bounce Indicating I Rod is NOT Stuck I

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I 0 :z S2C29 Time (sec)

Page 17 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 2.2 -

SURRY UNIT 2 - CYCLE 29 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 2

1.356 1.344 1.350 3

1.346 1.352 4

1.342 1.322 1.370 1.360 5

1.322 1.354 6

1.330 1.348 1.344 1.350 1.428 1.332 1.430 7

1.344 1.370 1.380 1.354 8

1.338 1.342 1.340 1.380 9

1.358 1.364 1.370 1.334 10 1.358 1.332 1.362 1.354 1.374 1.346 1.374 11 1.344 1.368 12 1.338 1.342 1.342 1.352 13 1.340 1.466 14 1.388 1.340 1.364 15 I I~-=>

x.xxx Rod drop time to dashpot entry (sec.)

Page 18 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 2.3 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 2.50 Techn 1k:al Spe, 1ficatior Limit,~ .4 secOI ds 2.40 2.30 2.20 2.10 2.00

-slowest Rod Time

- Fastest Rod Time

....1.90 -Average Time u

QI

E.

QI E

i=1.80 1.70 Ad ninistra ive Lim t, 1.68 ! econds 1.60 1.50 l..--

L---'

1.40

  • ~

~ /

/

/i IL_ ___i1 1.30 I.__ ;~

r/

1.20 1.10 20 21 22 23 24 25 26 27 28 29 Cycle Page 19 of47

Serial No.19-094 Docket No. 50-281 S2C29 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 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 29, Control Bank B was used as the reference bank. Surry 2 targeted a dilution rate around 1100 pcm/hr for the reference bank measurement.

During a previous startup physics testing campaign, a control rod became stuck on the bottom eventually forcing a reactor trip to fix the problem. The solution to this issue for startup physics testing was to avoid requiring control rods to be manually inserted to O steps. To accomplish this, an evaluation of the startup physics testing process was performed [Ref. 10],

concluding that the definition of fully inserted for control rod positions used in startup physics testing could be changed from O steps withdrawn to a range of O to 2 steps withdrawn. The S2C29 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

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

Test bank swaps proceed in sequential order from the bank with the smallest worth to the bank with the largest worth. The second test bank should have a predicted worth higher than the first bank in order to ensure the first bank will be moved fully out before the second bank is fully inserted. The rod swap maneuver was performed by withdrawing the previous test bank (or reference bank for the first maneuver) several steps and then inserting the next test bank to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the previous test bank was fully withdrawn and the current test bank was nearly inserted. The next step was to swap the rest of the test bank in by balancing the reactivity with the withdrawal of Page 20 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure 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 Tests Summary Sheets provided in Appendix B, the individual measured bank worths for the control and shutdown banks were within the design tolerance of +/- 10% for the reference bank, +/- 15% for test banks of worth greater than 600 pcm, and +/- 100 pcm for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was within -2.2% of the design prediction.* This is well within the design tolerance of+/- 10% for the sum of the individual control rod bank worths.

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

Page 21 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 3.1 SURRY UNIT 2- CYCLE 29 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE(%)

BANK (PCM) (PCM) (M-P)/P X 100 B - Reference 1365 1389 -1.7%

A 276 258 18 pcm*

C 731 781 -6.4%

SA 1000 973 +2.7%

SB 998 1070 -6.7%

D 1085 1107 -1.9%

Total Bank Worth 5456 5578 -2.2%

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

Page 22 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 3.1 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600 I

l I

. I I I 1400 I

- a...-

- 0--

I l

f I

'I'-.. I

  • 1m
  • '-* - - i i

i I

I\\ \,

1200

........ '\ Rt -- -

\\ -*I- e-

' f I 5 1000 - - 1-

\

\~

I EJ -*1 '

J I- I

'.1-l5 i

\

\

~I

\

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~ 800

! \ fl\ *-* *-

! I

\ ""\

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l

.8

\ l \

\11 lo-600 ti \.,

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~ II 400

\

~

\ \.

-* i\,

r,..,*

200

'l~  !

)a j '\)a

~

  • . ~

0 -

0 50 100 150 200 . 250 Bank Position (iateps)

Page 23 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 3.2 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12.0 l l I i r

f I 10.0 . '-

I ~ *'

/ I 117 ii '"* \

I I

i

"'g, 8.0 /1 \\ I I

I

.p Ill

\ b i

...... l 1 3 *-

'I; i, "a I I

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iiti I

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~

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rl Cll

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~

r:i I \ - --

I 7 j I J I .*

r ~

2.0 .

I

  • I 1 r

IJ

/,(

0.0 0 50 100 150 200 250 Bank Position (steps)

Page 24 of47

Serial No.19-094 Docket No. 50-281 S2C29 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 Tests Summary Sheets provided in Appendix B, 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 Appendix B, the measured DBW was well within the design tolerance of +/-10%. In summary, the measured boron worth coefficient was satisfactory.

Page 25 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 4.1 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configurati.on (ppm) (ppm) (ppm)

ARO 1556 1545 +11 B Bank In 1376.6 1377* -0.4

  • 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 Tests Summary Sheet in AppendixB.

Page 26 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 4.2 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Difference Boron Worth Boron Worth (M-P)

(pcm/ppm) (pcm/ppm) X 100 p

(%)

-7.63 -7.76 -1.7 Page 27 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure SECTION 5 - TEMPERATURE COEFFICIENT MEASUREMENT The Isothermal Temperature Coefficient (ITC) at the ARO condition is measured by controlling the RCS temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate by adjusting feed and letdown flow rates, and monitoring the resulting reactivity changes on the reactivity computer.

Reactivity was measured during the RCS heat up of 3.41 °F, followed by the RCS cool down of 2.87 °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 Tests Summary Sheet provided in Appendix B, 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 -2.019 pcm/°F, a predicted doppler temperature coefficient (DTC) of -1.66 pcm/°F, and a measurement uncertainty of +0.5 pcm/°F, is +0.141 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.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 5.1 SURRY UNIT 2 - CYCLE 29 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

TEMPERATURE BORON ISOTHERMAL TEMPERATURE COEFFICIENT BANK POSITION -**-- RANGE.(°FL_. ._ coNCENTRAnoN 1*---*--..---*-*-*--...., ...- ..--*---*-*-............,.C,,..P_. .c

. . . Ml...°F)

(STEPS) LOWER UPPERI (ppm) HEAT- I COOL- I AVG. I l DIFFER UP DOWN MEAS I PRED i (M-P)

II .I I

' I I

D/207 546.29 I 549.73 1550.0 -2.154 Ii -1.883 I! -2.019 I II

-1.830 I I

-0.189 Page 29 of 47

Serial No.19-094 Docket No. 50-281 S2C29 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 49 available locations monitored by the moveable detectors for Cycle 29 power ascension flux maps. As noted in Figure 1.3, one thimble location (R8) was determined to be unusable during the incore checkout and was not attempted during the power ascension flux maps. For each traverse, the detector voltage output is continuously monitored on a recorder and scanned for 610 discrete axial points. Full core, three-dimensional power distributions are determined from this data using a Dominion-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 26.94% 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 70.57%, and 99.89% power, respectively, with different control rod configurations.

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

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

+/-8.7% in the 26.94% power map, +/-5.3% in the 70.57% power map, and +/-5.2% in the 99.89%

power map. The maximum positive incore quadrant power tilts for the three maps were 2.87%,

1.78%, and 1.57%, respectively. The tilt from the 26.94% power map was reviewed to confirm Page 30 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure that the 2.87% measured quadrant tilt was bounded by the C\UTent safety analysis [Ref. 13]. The remaining power tilts were within the design tolerance of 2%.

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 3 were used for power range detector calibration or to confirm existing calibrations.

Due to the reconstituted rod in Assembly 817 (full-core location M-08), a reduced F~

limit of 1.619 (1 % less than the nominal value of 1.635; at 100% power) was imposed. This is tracked in the monthly flux maps as "Fuel Type 2". Through the first three power ascension maps, the F~ has not been limiting in Assembly 817 for either maximum peaking or minimum margin to the limit. These are denoted in Table 6.2 with (M-08).

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 29.

Page 31 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 6.1 SURRY UNIT 2- CYCLE 29 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Peak Fq(Z) Hot F:H Hot (2) CoreFz Bumup Bank Core Tilt (3) Axial No.

Map Map Power Channel Factor (1) Channel Factor Max Date MWD/ D ****---***-*1 ******-**********- -*-**********.*-**1*********-************ Offset Of Description No. (%)

MTU .

Steps Assy iAxiali ip . ti Fq(Z) i om 1 A ssy  !

i pN

<'>H Axial I F Point I z I Max Loe (%) Thimbles Low Power 1 12/06/18 2.0 26.94 169 H-131 27 i

! 2.318 J-12 I u84 i 26 \ 1.377 1.02871 SW i

4.887 49 Int. Power (4) 2 12/07/18 17.0 70.57 197 1-12 I i 26 11.998 J-12 I u28 26 i 1.224 l.0178i SW 3.620 49 Hot Full Power 3 12/11/18 138.0 99.89 224 J-12 I 30 I1.392 J-12 I 1.497 30 I 1.183 l.OI5ii SW 1.615 49 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:H includes no uncertainty.

(3) CORE TILT- defmed as th.e 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.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 6.2 SURRY UNIT 2- CYCLE 29 STARTUP PHYSICS TESTS COMP ARISION 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 2.318 5.000 27 53.6 1.584 1.993 20.5 (M-08) NIA 1.546 1.974 21.7 2 1.998 3.543 26 43.6 1.528 1.779 14.1 (M-08) NIA 1.495 1.762 15.1 3 1.892 2.503 30 24.4 1.497 1.636 8.4 (M-08) NIA 1.470 1.620 9.2 The measured Fq(Z) hot channel factors include 8% total uncertainty. Measured F:H data includes no uncertainty.

(M-08) is the F~ data for Assembly 817 (reconstituted assembly) only.

  • Margin(%)= lOO*(Limit-Meas.) I Limit Page 33 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 6.1 - ASSEMBL YWISE POWER DISTRIBUTION 26.94% 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 0.2641 0.293 I 0.267 I I 0.2741 0.2991 0.2141 I -3.581 -1.9BI -2.591 I 0.2661 0.5551 0.9411 1.0141 0.9551 0.5681 0.2701 I 0.2761 0.5791 0.9801 1.0441 0.9831 0.5821 0.2771 I -3.711 -4.071 -3.931 -2.871 -2.881 -2.421 -2.6BI 0.3271 0.B771 1.0701 1.1871 1.2681 1.2151 1.0881 0.8851 0.3301 I 0.3341 0.9101 1.1171 1.2461 1.2971 1.2531 1.1221 0.9121 0.3341 I -2.011 -3.611 -4.1BI -4.761 -2.211 -3.051 -3.061 -2.981 -1.331 0.3271 0.9311 1.2551 1.2711 1.3001 1.2931 1.3251 1.2861 1.2571 0.9331 0.3261 I 0.3351 0.9591 1.2991 1.3271 1.3661 1.3671 1.3801 1.3321 1.2991 0.9571 0.3331 I -2.351 -2.941 -3.411 -4.191 -4.861 -5.381 -4.001 -3.481 -3.241 -2.561 -1.961 I 0.2701 0.9001 1.2681 1.1661 1.1781 1.1721 1.1121 1.1901 1.1871 1.1671 1.2711 0.8971 0.2681 I 0.2741 0.9181 1.3071 1.21n 1.2321 1.2351 1.1731 1.2411 1.2351 1.2141 1.3001 0.9101 0.2721 I -1.341 -1.921 -2.971 -4.201 -4.421 -5.121 -5.201 -4.0BI -3.901 -3.B81 -2.221 -1.481 -1.311 I 0.5821 1.1171 1.3131 1.1911 1.120 I 1.1111 1.0851 1.1331 1.1191 1.1991 1.3111 1.120 I 0.5951 6 I 0.5881 1.135 I 1.3461 1.2441 1.170 I 1.1711 1.158 I 1.173 I 1.16!11 1. 237 I 1. 3371 1.127 I 0.5841 I -1.031 -1.581 -2.481 -4.291 -4.271 -5.131 -6.Jll -3.371 -4.271 -3.041 -1.921 -0.651 1.92 I I 0.2781 0.9961 1.2671 1.3881 1.2271 1.1411 1.1081 1.129 I 1.1811 1.1461 1.2191 1.3661 1.269 I 1.0461 0.2911 7 I 0.278 I 0.9981 1.275 I 1.4061 1.2571 1.1791 1.1651 1.1641 1.1651 1.1761 1. 2481 1.3891 1.2661 0.9941 0.278 I I 0.141 -0.211 -0.611 -1.291 -2.371 -3.261 -4.85 I -2.981 1.341 -2.541 -2.321 -1.691 0.261 5.25 I 4.52 I I 0.3061 1.0691 1.341 I 1.4211 1.1831 1.1471 1.1391 1.1971 1.1391 1.1071 1.1661 1.405 I 1.3161 1.0781 0.3101 8 I 0.3031 1.0621 1.3251 1.4201 1.192 I 1.1661 1.1671 1.2251 1.1671 1.1661 1.192 I 1.420 I 1.3251 1.0621 0.3031 I 0.84 I 0.681 1.221 0.081 -0.741 -1.601 -2.411 -2.291 -2.391 -5.071 -2.191 -1.071 -0.681 1.51 I 2.321 I 0.2821 1.0101 1.2901 1.4061 1.2471 1.1741 1.1561 1.1481 1.1241 1.1601 1.2501 1.4091 1.2821 1.0111 o.2841 9 I 0.2781 0.9941 1.2661 1.3891 1.2481 1.1761 1.1651 1.1641 1.1651 1.1791 1.2571 1.4061 1.2751 0.9981 0.2781 I 1.341 1.661 1.911 1.191 -0.051 -0.211 -0.791 -1.401 -3.481 -1.601 -0.551 0.201 0.581 1.311 1.991 I 0.6011 1.1691 1.3731 1.2631 1.1871 1.1841 1.1691 1.1721 1.1731 1.2591 1.3701 1.1551 0.6011 10 I 0.5841 1.1271 1.3371 1.2371 1.1691 1.1731 1.1581 1.1711 1.1101 1.2441 1.3461 1.1341 0.5881 I 2.971 3.771 2.701 2.141 1.511 0.901 0.951 0.121 0.301 1.201 1.761 1.871 2.261 I 0.2821 0.9491 1.3511 1.2671 1.2781 1.2821 1.2201 1.2671 1.2501 1.2571 1.3541 0.9481 0.2821 11 I 0.2721 0.9101 1.3001 1.2141 1.2351 1.2411 1.1731 1.2351 1.2321 1.2161 1.3061 0.9171 0.2741 I 3.621 4.301 3.901 4.381 3.471 3.331 4.001 2.571 "1.451 3.401 3.651 3.361 3.101 I o.3591 i.0011 1.3591 1.3911 1.4431 1.4361 1.4281 1.3821 1.3601 1.0251 0.3611 12 l 0.3331 0.9571 1.299[ 1.3321 1.3801 1.367[ 1.3661 1.327[ 1.2991 0.9591 0.3351 I 7.681. 4.611 4.601 4.451 4.551 5.061 4.571 4.161 4.731 6.871 7.661 0.3501 0.9571 1.1801 1.326[ 1.391[ 1.326[ 1.1821 0.9591 0.355[

.13 I 0.3341 0.9121 1.1221 1.2531 1.2971 1.2461 1.1171 0.9101 0.3341 I 4.801 4.901 5.201 5.861 7.271 6.451 5.821 5.391 6.241 o.2941 0.6151 1.0471 1.120 I 1.065 I 0.620 I 0.293 I 14 I 0.2111 o.5821 0.9831 1.0441 0.9801 0.5791 0.2761 I 6.031 5.751 6.471 7.321 8.671 7.001 6.091 I 0.2961 0.3221 0.2971 15 I 0.2741 0.299 I 0.2741 I 8.171 7.781 B.341 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 3.2 STANDARD DEVIATION 1. 985 Summary:

Map No: S2-29-01 Date: 12/06/2018 Power: 26.94%

Control Rod Position: Fo(Z) = 2.318 QPTR: _ _0_.9_6_98_-+-_0._97_6_7_

D Bank at 169 Steps 1.0287 1.0249 F! = 1.584 Fz = 1.377 Axial Offset(%)= +4.887 Bumup = 2.0 MWD/MTU Page 34 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 6.2 - ASSEMBL YWISE POWER DISTRIBUTION 70.57% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value  % Delta

% Delta = (M - A)xlOO/A R p ]I[ !Ir L K J l! G F E D C A 0.2921 0.82BI 0.2951 1 0.29BI 0.8291 0 * .29BI

-1.991 -0.161 -0.951 0 * .2B3I D.5B8I 0.9B41 1.0921 0.9971 0.5971 0.2B71 0.2B91 0.59BI 1. ODB I L10BI 1. 0101 0.6011 0 * .2901

-2.211 -2.46*1 -2.891 -1.461 -1.241 -D.6BI -1.191 0.8411 D.B98I l..OB21 1.19BI 1.2?71 1.2261 1.1001 0.9001 0.3441 3 0.3451 0.9121 1.1121 1.2391 1.2911 1.2441 1.1151 o.913 I 0.3451

-1.171 -2.061 -2.651 -3.311 -l..051 -1.4BI -1. 361 -1.401 -0.361 0.3401 0.93B I 1.2521 1.26BI 1.2971 1.2BBI l..3171 l..2B31 1.2521 0.9421 0.3401 0.3451 0.9551 1.2741 1.8001 1. 8851 1.8821 1. 3471 1. 8041 1.2751 0.9541 0.8441

-1.521 -1.731 -1.741 -2.451 -2.B61 -3.2BI -2.241 -1.641 -1. B41 -1.291 -1.131 0.2B3I 0.9031 1.2541 1.1691 1.l.96.I 1.l.961 1.1291 1.2001 1.2021 l..1651 1.263 I 0.9031 0.2B21 5 O..:lB61 0. 9171 1.2BOI 1.2021 1.22BI 1.2251 1.1621 1.2811 1.2801 1..2001 1.2751 0.9111 0.2B41

-1.051 -1.541 -2.001 -2.791 -2.571 -2.841 -2.B21 -2.521 -2.251 -2.911 -0.981 -0.841 -0.731 0.6001 l..1111 l..2911 1.19BI l..1B91 l..14BI l..1231 1.1491 1.1951 1.2071 1.2911 1.1091 0.6001 6 0.6041 1.1.2a I 1.a181 1.2861 !L~!a1.I L1BOI 1.1591 1.1B2 I 1.2201 1.2811 1.8061 1.1171 0.6021

-0.6BI -1.031 -1. 711 -a.OSI -2.621 -2."lll -a.01.1 -2.771 -2.091 -1.951 -1.141 -0.671 -o.351 I o.8011 1.0191 1.2571 1.3551 1.2251 1.1641 1.1331 1.1291 l..12BI 1.1531 1.2141 1.3391 1.2491 1. 0211 0.3021 7 I 0.3011 1. 0201 1.2601 1.3661 1.24.21 1.1B61 1..1671 1.1621 1.1671 1.1B4I 1.2351 1.3521 1..2531 1.01BI 0.3011

-0.071 -l}.111 -0.231 -0.7BI -1. 401 -1. B91 -2.!131 -2.B41 -3.371 -2.601 -1.6B I -1. 001 -D.821 D.2BI 0.2BI I o.8a21 1.1221 1.8121 1.a7B I l..l.7B I 1.1561 1. l.461 1.l.931 1.l.341 1.1251 1.161.1 1.3731 1. 3161 1.1271 0.3341 B I o.aa21 1.1.201 1.3111 1.37BI 1.1761 1.1651 1.1641 1.2161 1.1641 1.1651 1.1761 L37BI 1.32.11 1.1201 o.a32l I 0.141 0.1BI 0.101 0.021 o.131 -0.771 -1.521 -1.931 -2.SBI -3.441 -1.271 -0.341 0.351 0.651 0.621 I 0.3021 1. 0241 1.2621 1.3621 1.2421 1.1B61 1.1631 1.1521 1.1491 1.l.B41 1.243 I 1.3741 1.2701 1. 0301 0.3051 9 I 0.3011 1. 01B I 1.253 I 1. 3521 1.2351 1.1B41 1.1671 1.1621 1.1671 1.1B61 1.24.21 1. 3661 1.2591 1.0201 0.3011 I 0.401 0.611 0.741 0. 761 0.601 0.191 -0.341 -O.B41 -1.541 -0.141 0.041 0.561 0.B41 0.921 1.201 0.6091 1.1261 1.3261 1.2491 1.2341 1.1901 1.1661 1.1B41 1.227 I 1.247 I 1.3351 1.1401 0.6121 10 0.6021 1.1171 1.3061 l.2311 1-.2201 1.1B21 1.1591 1.1BOI 1.2211 1.2361 1.3131 1.1231 0.6041 1.211 1. 731 1.561 1.461 1.l.51 0.701 0.571 0.841 0.511 0.931 1.6BI 1.521 1.391 0.2901 0.9331 1.3041 1.2311 1.25BI 1.25BI 1.l.B71 1.2451 1.2421 1.2191 1.3101 0.92BI 0.2921 H 0.2B41 0.9111 1.2751 1.1991 1.2301 1.2311 1..1621 1.2251 1.22BI 1..2021 1.2791 0.9171 0.2B61 1.941 2.371 2.2!11 2.701 2.301 2.221 2.l.41 1.671 1.151 1.3BI 2.391 2.301 2.021 0.3611 O.!IB11 1.3121 l.2441 1.3961 1.8761 1.3731 1.aaa1 1. a101 0.9!191 0.3631

0. 3441 0.9541 1.2751 1. 304 I 1.3471 1.aa21 1.3351 1. 3001 1.2741 0.9551 0.3451 4.!131 2.B61 2.911 8.041 a.651 3.291 2.B21 2.551 2.B41 4.561 5.2BI 0.3551 0.9411 1.153 I 1.2921 1. 3461 1.2B61 1.1501 0.9421 o.asa1 13 0.3451 0.9131 1.U51 l.244 I 1.2911 1.2391 1.1121 0.9121 0.8451 2.901 3.071 a.391 2.B71 4.291 2. 761 a. 431 3.241 3.B91 0.2971 0.6211 1. 0501 1.1561 1. 0561 0.6221 0.2991 14 D.2901 0.6011 1. 0111 1.l0B I 1. DOB I 0.59BI 0 * .2B91 2.291 a.401 3.911 4.351 4.761 4.021 a.541 0.3101 0.3441 o.a121 15 0.29BI 0.3291 0.29BI 4.161 4.461 4.551 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 1.9 STANDARD DEVIATION 1.240 Summary:

Map No: S2-29-02 Specificatl 2/07/2018 Power: 70.57%

Control Rod Position: Fo(Z) = 1.998 QPTR: 0.9819 0.9839 D Bank at 197 Steps F:H = 1.528 1.0178 1.0164 Fz = 1.224 Axial Offset(%)= +3.620 Burnup = 17.0 MWD/MTU Page 35 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Figure 6.3 -ASSEMBLYWISE POWER DISTRIBUTION 99.89% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Delta

. % Delta= (M ~ A)xlOO/A R p H H L K J B G F I: D C B A 0.3041 0.3411 o.a.061 1 0.3091 0.3451 C1 ..ao91

-1. "JOI -1. 061 -1.oa.1 0.2BBI 0.5911 0.9!!11 1.1211 1.0001 0.5971 0.2911 2 0.2951 0.6041 1.01.11 1.1a51 1.0131 Cl.EOE! 0.2951

-2.241 -2.1~1 -1.981 -1.251 -1.281 -1.561 -1.201 o.a.u1 0. 8851 1. 0751 1.1961 1.2"101 1.2181 1. 09a1 0.8961 O.a.461 3 0.3491 0. 9051 1.1011 1..2271 1.2eo1 1.'2a.:n 1.1041 0.9061 0.3491

-2.301 -2.2a1 -2.a81 -2.5.61 -O."l!!I -1.101 -1. 011 -1.0BI -0.961 o.34at 0.9261 1.2271 1.2521 1.2861 1.2811,1 1.a.091 1.278 I 1.2a.91 0.9a.a.1 o.a.441 4 0.3501 0.9461 1.2541 1.2B11 1..3111 1.3131 1.32BI 1.2B51 1.2541 0.9451 0.3481

-1.891 -2.101 -2.1a1 -2.261 -2.a.41 -2.281 -1.461 -0.551 -1.18 I -1.2a.1 -1.161 0.2881 0.8941 1.2311 1.15.BI 1.2011 1.2021 1.la.91 1.2111 1.2141 1.1"101 1.2a.a1 0.89a.l o.2831 5 0.2921 0.9091 1.25BI 1.1941 1.2a1l 1.2291 1.1641 1.2341 1.:rn31 1.1921 1.2541 0.9041 0.2901

-l..2BI -1.601 -2.141 -2.991 -2.451 -2.191 -2.111 -1.B41 -1.511 -1.B71 -1.261 -1.251 -2.491 0.6051 1.09BI 1.2"111 1.2041 1.2401 1.1"101 1.1461 1.1721 1.245.1 1.2151 1.278.I 1. 0951 0.6021 6 0.6091 1.1111 1.29a1 1.23B I 1.2691 1.1971 1.1121 1.1991 1.2661 1.2331 1.2671 1.1061 0.6071

-0."lOI -1.1a.1 -1."121 -2.761 -2.301 -2.2a.1 -2.241 -2.251 -1.851 -1.461 -1.111 -0.981 -0.901 I (1.3121 1.0201 1.2421 1.3341 1.2281 1.1841 1.1531 1.1461 1.1441 1.1"161 1.2221 1. 324 I 1.2331 1. 0141 o.3111 7 I 0.3121 1.0211 1.2461 1.3451 1.2441 1.2031 1.1611 1.1'131 1.1611 1.2011 1.2361 1,3331 1. 2401 1.[1191 o.3111 I -0.0!11 -0.131 -0.321 -0.801 -1.281 -1.611 -2.3!11 -2 .271 -3.101 -2.051 -1.28 I -0.111 -o.581 -0.461 -0.011 I 0.3471 1.1481 1.3011 1.35"11 1.178 I 1.l"lll 1.1631 1.2071 1.1521 1.1531 1.1671 1.35.21 1.2!171 1.1541 0.3481 8 I 0. 3471 1.1451 1.2971 1..3561 1.1171 1.1781 1.1151 1.223 I 1.1751 1.1181 1.1711 1.3561 1.2971 1.H.51 0.3461 I 0.121 0.251 0.281 0.041 0.111 -0.561 -1.041 -1. 341 -1. 92 I -2.151 -O.B41 -0.2!11 -0.031 0.771 0.621 o.3131 1.0251 1.2481 1.3411 1.2451 1.2061 1.1831 1.16!11 1.1681 1.2031 1.2451 1.3501 1.2511 1.02"11 0.3121 9 0.3121 1.0191 1.2391 1.3331 1.23BI 1.2011 1.1811 1.1131 1.1611 1.2031 1.2441 1.3451 1.2461 1.[1211 0.3121 0.391 0.5"11 0.691 0.601 0.561 0.431 0.141 -0.321 -1.121 0.041 0.101 0.361 0.3!11 0.561 -0.091 0.6131 1.1201 1.3oa.1 1.2491 1.2851 1.21"11 1.1B5I 1.2051 1.27BI 1.2481 1.3091 1.1221 0.6121 10 Cl.6071 1.1051 1.2871 1.2331 1.268 I 1.1991 1.1.,.21 1.1971 1.2691 1.23BI 1.2931 1.1111 Cl.6091 1.021 1.:141 1.211 1.331 1.321 1.541 1.091 0.661 0.691 o.B31 1.231 0.991 0.571 0.2!141 0.9201 1.2761 1.2161 1.2561 1.2621 1.1931 1.25.11 1.2481 1.2081 l.2Bll 0.9261 0.2961 11 0.29[)1 [).9041 1.2541 1.1921 1.2331 1.2341 1.1641 1.2291 1.2311 1.1941 1.25a I Cl.9091 Cl.2921 1.37 I 1."151 1. 141 2.041 2.061 2.291 2.451 1. 751 1.381 1.141 1."l!II 1.861 1.211 0.3601 o.9661 1.2831 1.a.181 1.3691 1.a.521 1.a.511 1.3101 1 . .2B21 0.9781 0.3681 12 0.34Bl o.9451 1.2541 1.2851 1.32BI 1.31a1 1.a171 1.2a21 1.2541 D.9461 0.3501 3.5.61 2.191 2.311 2.561 3.111 2.981 2.5"11 2.211 2.211 a.a8J 5 * .201 0.35."ll 0.9281 1.1351 1.2"131 1.3281 1.26BI 1.1321 0.9291 o.a.so1 13 Cl ..3491 0. ~Cl61 l..1041 1.*2a21 1.2791 1.2211 1.1Clll 0.9051 Cl.3491 2.aa.1 2.421 2."l!II 3.311 3.B41 a.a.al 2.191 2.621 3.0BI 0.2991 0.6241 1.04"11 1.1"181 1.0541 0.6251 0.3Cl31 14 Cl.2951 0.6061 1.0131 1.1351 1.0111 Cl.6041 Cl.2951 1.491 2.911 a..3.61 3.821 4.271 3.471 2.871 I o.a.191 0.35"11 0.3221 15 .I D.alDI D.3451 0.3091 I 2.821 3.621 4.1a.1 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 1. 6 STANDARD DEVIATION 1. 023 Summary:

Map No: S2-29-03 Date: 12/11/2018 Power: 99.89%

Control Rod Position: Fo(Z) = 1.892 QPTR: 0.9834 I 0.9865 D Bank at 224 Steps F:H = 1.497 1.0157 1.0144 Fz = 1.183 Axial Offset(%)=+ 1.615 Burnup = 138.0 MWD/MTU Page 36 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure SECTION 7 - CONCLUSIONS Table 7 .1 summarizes the results associated with Surry Unit 2 Cycle 29 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, Technical Specifications limits, or COLR limits. Based on the results associated with the S2C29 startup physics testing program, it is anticipated that the Surry 2 core will continue to operate safely throughout Cycle 29.

The reconstituted assembly in full-core location in M-08 is not leading the core m peaking or minimum margin to the limit and will continue to be monitored throughout Cycle 29.

Page 37 of47

  • Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure Table 7.1 SURRY UNIT 2- CYCLE 29 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 1556 1545 11 +/-39 (HZP ARO), ppm Critical Boron Concentration 1376.6 1377 -0.4 +/-28 (HZP Ref Bank in), oom Isothermal Temp Coefficient -2.019 -1.830 -0.189 +/-2 (HZP ARO), pcm/F Differential Boron Worth -7.63 -7.76 -1.7% +/-10%

(HZP ARO), pcm/ppm Reference Bank Worth 1365 1389 -1.7% +/-10%

(B-bank, dilution), pcm A-bank Worth (Rod Swap), pcm 276 258 18 +/-100 C-bank Worth (Rod Swap), pcm 731 781 -6.4% +/-15%

SA-bank Worth (Rod Swap), pcm 1000 973 2.7% +/-15%

SB-bank Worth (Rod Swap), pcm 998 1070 -6.7% +/-15%

D-bank Worth (Rod Swap), pcm 1085 1107 -1.9% +/-15%

Total Bank Worth, pcm 5456 5578 -2.2% +/-10%

S2C29 Testing Time: 6.5 Hrs

[criticality 12/05/2018@ 11 :59 to end of testing 12/05/2018 @ 18:27]

Recent Startups:

81 C29 testing time: 8.0 hrs S2C28 testing time: 7.0 hrs 81 C28 testing time: 5.8 hrs S2C27 testing time: 7.6 hrs S1C27 testing time: 5.6 hrs S2C26 testing time: 7.2 hrs 81 C26 testing time: *7.8 hrs Page 38 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure SECTION 8 - REFERENCES

l. J. A. Cantrell, "Surry Unit 2 Cycle 29 Design Report", Engineering Technical Evaluation ETE-NAF-2018-0123, Rev. 0, November 2018.
2. S. B. Rosenfelder, "Surry Unit 2 Cycle 29 Full Core Loading Plan", Engineering Technical Evaluation ETE-NAF-2018-0065, Rev. 0, May 2018.
3. S. B. Rosenfelder, "Surry Unit 2 Cycle 29 Startup Physics Testing Logs and Results", Memorandum MEMO-NCD-20180041, Rev. 0, December 2018.
4. T. S. Psuik, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," Topical Report VEP-FRD-36-Rev. 0.3-A, February 2015 [Included in Technical Report NE-1378, Rev. 2 as Attachment B].
5. R. W. Twitchell, "Operational Impact of the Implementation of Westinghouse Integral Fuel Burnable Absorber (IFBA) and the Removal of Flux Suppression Inserts (FSis) for Surry Unit 1 Cycle 21,"

Technical ReportNE-1466, Rev. 0, January 2006.

6. Surry Units 1 and 2 Technical Specifications.
7. D. J. Agnew, "Rod Drop Test Computer Users Guide and SQA Paperwork," Engineering Technical Evaluation ETE-NAF-2014-0118, Rev. 0, April 2015.
8. B. J. Vitiello and G. L. Darden, "Implementation of the Westinghouse 15x15 Upgrade Fuel Design at Surry Units 1 and 2, "Engineering Technical Evaluation ETE-NAF-2010-0080, Rev. 0, January 2011.
9. M. P. Shanahan, "Implementation of RMAS version 7 at Surry Units 1 and 2," Engineering Technical Evaluation ETE-NAF-2014-0021, Rev. 0, May 2014.
10. A. H. Nicholson, "Justification For Defining O To 2 Steps Withdrawn As Fully Inserted When Measuring Control And Shutdown Banks During The Surry Startup Physics Testing Program," Engineering Transmittal ET-NAF-2006-0046, Rev. 0, May 2006.
11. R. A. Hall et al, "Surry Unit 2 Cycle 29 Flux Map Analysis", Calculation PM-1994, Rev.O, and Addenda A-B, December 2018. * *
12. Nuclear Engineering Standard DNES-AA-NAF-NCD-5007, Rev. 3, "Startup Physics Tests Results Reporting", July 2016.
13. Thu Ho, "Reload Safety Evaluation Surry Unit 2 Cycle 29 Pattern SUP, EVAL-ENG-RSE-S2C29, Rev.

0, October 2018.

14. Thu Ho, "Reload Safety Evaluation Surry Unit 2 Cycle 29 Pattern SUP," EVAL-ENG-RSE-S2C29, Rev.

0, Add. A November 2018.

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 ETE-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. M. L. Provinsal, "Surry Unit 2 Cycle 29 TOTE, Core Follow, and Accounting Calculations", Calculation PM-1993, Rev. 0, December 2018.
19. T. S. Psuik, "Implementation of Changes to the Allowable Power Level for the Initial Startup Flux Map for Surry Units 1 and 2", Engineering Technical Evaluation ETE-NAF-2015-0007, Rev. 0, April 2015.
20. Surry Power Station Updated Final Safety Analysis Report.

Page 39 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure APPENDIX A - RCP STARTUP ORDER 12/1/2018 09:50 Initia!RCP Start:2-RC-P-lC itw2-0P-RC-001 0952 Load shed in ENABLE 0959 Bearing Lift Pump started. White !wit lit l O11 All personnel on station ii Containment for start of2~RC-P-1 C 1016 Engineering personnel are monitoring Vibes and prepared for start of2-RC-P-1 C 1021 Started 2-RC-P-lC. All parameters SAT.

1023 SecuredBearingLiftPump SPS Unit2 ControlRoomLog CASEY, SEAN 12/1/201812:21: C"RCS Loop flow indicators have been vented by l&C. HUMPHRIES, JOSHUA A 12/1/2018 14:57 2-RC-P-lA UPDA1E:

2-EP-BKR-25A3 is in TEST IAW 2-0P-RC-001.

1500 2-RC-P-lAl C'A" RCP Brg Liftpmnp) started.

1505 2-EP-BKR-25A3 closed in TEST.

1507 2-EP-BKR-25A3 opened in TEST.

1525 2-EP-BKR-25A3 racked to CONNECT.

1530 Ops on station in containment 1536 Eve1yone on stafun in containment 1540 Started 2-RC-P-lA.

1542 Secured 1-RC-P-lAl (A"RCP BrgLiftpump).

SPS Unit:2 ControlRoomLog FORD, WALTERJOE 12/3/2018 09:40 All PMTs required for 200"F Mode Change are comp~te. Pe!lllissi>n has been granted to rase RCS temperature>

200°F. Commence heatng up from 193 "F to > 200"F.

0947 Started B"RCP IAW 2-0P-RC-001. AllRCPs are nowrunnng.

0959 U2 has left Cold Shutdown and has entered Intennediate Shutdown. C111rentheatup rate is 34"F/Hr.

1039 Stabilized RCS temperature at 210°F for Engineering cross-cals.

1044 Engineering cross-cak are complete. Recommence heating up to 340-345"F.

SPS Unit2 Contro!RoomLog HUMPHRIES, JOSHUAA 12/3/2018 12:00': RCS temperature is 248"F and rising. Rate ofheatup i;; 30"F/Hi* (maximum attainable rate). HUMPHRIES, JOSHUA A Page 40 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure APPENDIX B- STARTUP PHYSICS TESTS

SUMMARY

SHEETS Page 41 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure; Appendix B Surry Power Station Unit 2 Cycle 29 Startup Physics Test Summary Sheet - Formal Tests (Page 1 of 6)

Datei D~ign Acceptance Prepared Measured Value Dosign Criteria Acceptance Criteria Criteria Met Criteria Mat Reviewer

~ c a l Bench Test Reevlts f'!,Z/

'.-le?" pcm No NIA NIA The allowable range Is set to the larger of the

%D =((pc* pt}!et} x 1 DO% measured results or tne P!e--<:rit1cal bench test

%D = .-o,Jt,.lfi /-/.'/ S"% Allowable rangeT/ZO /.... /()t:J pcm

<<r ~ <;t.r""o + (;I.TOOP aJ 50

,; 3.840 pcmrF / Yoo (al 0 ).ARO - /. f!..3 () +/- 2 pcmt F pcm/"F where: (czt.f""}; 6.0 pcm/"F [COLR 3.4] No No (ur""")1; 0.5 i;x:;ml"F.

IeREF,~\..

- 1lEF=2 1389 +/- 10%

i3~S pcm 100x(Meas_ -Des._)/Des_"' -/. 7-%

References 1.) DNES-M-NAF-NCD-401'5, Rev. 3 2.) ETE-NAF-2018-0123, Rev. 0 3.) ETE..NAF*201.8-0124, Rev. 0 Page 42 of47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure; Appendix B Suny Power station Unit 2 Cycle 29 Startup Physics Test Summary Sheet - Formal Tests (Page 2 of 6)

Date/

Mea$Ured Value Design Criteria Acceptance Criteria Design Acceptance Criteria Met: Criteria Met NIA NIA No References 1.) DNES-AA-NAF~NCD-4015, Rev. 3 2.) ETE-NAF-2018-0123, Rev. 0 3.) ETE-NAF-2018-0124, Rev. 0 Page 43 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure; Appendix B

~"1'1 ~Ct,1,1"\ e >>1 -=t . . . .

Surry Power Station Unit2 Cycle 29 Startup Physics Test Summary Sheet - Formal Tests (Page 3 of 6)

Da~/

Measured Value Design Criteria Accopta~e Criteria Design Acceptance Timeof Preparer/

Criteria Met Criteria Met Test Reviewer Map Power Level(% Full l>OMlr)"' Q.~ *CJ4 Max Retatlve Assembih, Power, %D1FF (M-P)JP l'-]Gjil [)A./

MO% for P1~.9 J~ :$' l

% DlFF= S , 7 o/,, for p* ~o. 9 :t15% for Pr:Q.9 NIA No NIA ~u-2 l

i .. '.3' % for I 1<0.9 {P1"' 8$$Y power)1-Nuclear Enthalpy Rise Hot Channel Factor, F.AH(N) if._ Yes F.l1H{N)= I* '5~4 NIA FAH(N)s1 .635(1+0.3(1-P)) [COLR 3.7] NIA No

  • Tottl Heat Flux Hot Channel Factor, FQ(Z)

Peak FQ(Z) Hot Channel Factop: *1_

  • 2d ~

I N(A Fo~Z} ICOLR 3.7] NIA V Yes No Maximum Positive lncpre Quadrant Power Tilt

'Yes NIA N/A

_L_No Refennces 1.) DNES-AA-NAF-NCD-4015, Rev. 3 2.) ETE-NAF-2018-0123, Rev. 0 3.) ETE-NAF-2018-0124, Rev. 0 Page 44 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure; Appendix B Surry Power Station Unit2 Cycle 29 Startup Physics Test Summary Sheet- Formal Tests (Page 4 of 6)

Date/

Design Acceptance Preparer/

Measured Value Design Criteria Acceptance Criteria Criteria Met Criteria Met Reviewer Map Power level {% Full Powel) - JO.(;/

1-Max-_Re_1_ativ_eAs_s_em_bly

__ Pow-.-e_r._%_0_1F_F_(M_..P_)IP_ _ _ _ _ _ --.-----------~-_,...:a..-...,.------i l?/9/Jg JJ¥./

+/-100.k for P1~.9 _ _ Yes /

%D1FF=. ', 1' S, % fur Pi20.9 ;i;15% for P1<0,9 N/A No WA tG':45' f' t, 3 *% for P1<0,9 (P1= a~y power)1.Z Nuclear Enthalpy Rise Hot Channel Factor, FAH(N}

FAH(N~ L SZR NFA Fh.H(Nr-,1.635(1+0.3{1-P)) [COLR 3.7] NIA

~Yes No Total Heat Flux Hot Channel Factor~ FQ(Z}

Peak FQ(Z) Hot Ctl?'nel NIA NIA Fa~2.5/P}*K{Z) [OOLR 3.7]

Factor:= t*1' Ii. No Maximum Positive lncore Quadrant-Power TiH Yes NIA NIA No References 1.) DNES-AA-NAF-NCD-4015, Rev. 3 2.) ETE-NAF~2018-0123. Rev. 0 3.) ETE-NAF-2018-0124, Rev. 0 Page 45 of 47

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure; Appendix B Suny Power Station Unit 2 Cyc1e 29 Startup Physics Te$t Summary Sheet- Formal Tesl.$ * (Page S of 6}

Measured Value Design Criteria Aeeeptanee Criteria Design Ac~ptance Preparer/

Criteria Met Criteria Met Reviewer Max Relative Assembly Power, %D1FF (M-P}/P

__L_ Yes *

%DlFF"" J../. 3 .. % for Pi.!;{).9 !ie15% for P1<0.9 NIA No NIA 5, a./ % for P<0.9 1

(Pi = assy power)1-2 Nuclear Enthalpy Rise Hot Channel FaotorJ FAH(N}

/ _ Yes l ?./,, pq NIA FAH(N)~1.635(1+0.3(1-P)) [COLR 3.7} NIA

_ _ No OJ~S".t..

Total Heat Rux Hot Channel Factor, FQ(Z)

Peak F<l(Z) Hot Ctiann; _L_ Yes NIA Fo(Z)s:{2.5/P}"1<(Z} [COLR 3.7J NIA Factor= /. FJ(f2... _ _ No Maxtmun-i Positive lncore Quadrant Power Tilt

_JC:_Ye5 NIA NIA No R~erences 1_) DNES-AA-NAF-NC0-4015, Rev. 3 2.) ETE-NAF-2018-0123, Rev. o 3.) Ere-NAF-2018-0'124, Rev. o Page 46 of 47

/

Serial No.19-094 Docket No. 50-281 S2C29 Startup Physics Tests Report Enclosure; Appendix B Surry Power Station Untt 2 Cycle 29 Startup Physics Test Summary Sheet ... Formal Tests (Page 6 of 6)

Date/

Measured Value Design Criteria Design AcceptariGe Prepared Acceptance Criteria Criteria Met Criteria Met T~e::' ' Reviewer

_L Yes NIA F1o131 ~ 274000 gpm {COLR 3.8] NIA gpm No References 1.} DNEs-AA-NAF-NCD-4015, Rev. 3 2.) ETE-NAF-2018-0123, Rev. 0 3.) ETE-NAF-2018-0124. Rev. o Page 47 of 47

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