ML15244B205

Virginia Electric and Power Company (Dominion) Surry Power Station Unit 1, Cycle 27 Startup Physics Tests Report

ML15244B205
Person / Time
Site:	Surry
Issue date:	08/24/2015
From:	Huber T Dominion, Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:	NRC/RGN-II
References
15-432
Download: ML15244B205 (49)

Text

', Dominion Resources Services, Inc.

Innsbrook Technical Center

1. D .ii *

'* 5000 Dominion Boulevard, 2SE, Glen.Allen, VA 23060 August 24, 2015 United States Nuclear Regulatory Commission Serial No.: 15-432 Regional Administrator- Region II NLOS/GDM Marquis One Tower Docket No.: 50-280 245 Peachtree Center Ave., NE License No.: DPR-32 Suite 1200 Atlanta, Georgia 30303-1257 VIRGINIA SURRY POWER ELECTRIC AND POWER STATION UNIT 1 COMPANY (DOMINION)

CYCLE 27 STARTUP PHYSICS TESTS REPORT As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 1 Cycle 27 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 27 on May 27, 2015. 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, T. R. Huber, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company

Enclosure:

Surry Unit I Cycle 27 Startup Physics Tests Report Commitments made in this letter: None LF94e~

kftJC

Serial No.15-432 Docket No. 50-280 S1C27 SPTR Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Ms. K. R. Cotton Gross NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager - North Anna U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.15-432 Docket No. 50-280 Enclosure SURRY UNIT I CYCLE 27 STARTUP PHYSICS TESTS REPORT August 2015 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit I

Serial No.15-432 Docket No. 50-280 CLAS SIFICATION/DIS CLAIMER 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, TH~E COMPANY MARES 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 46

Serial No.15-432 Docket No. 50-280 S1C27 SPTR TABLE OF CONTENTS Classification/Disclaimer................................................................................ 1 Table of Contents......................................................................................... 2 List of Tables.............................................................................................. 3 List of Figures............................................................................................. 4 Preface...................................................................................................... 5 Section 1 -- Introduction and Summary ............................................................. 6 Section 2 -- Control Rod Drop Time Measurements.............................................. 14 Section 3 - Control Rod Bank Worth Measurements ........................................... 19 Section 4 - Boron Endpoint and Worth Measurements......................................... 24 Section 5 -- Temperature Coefficient Measurement.............................................. 27 Section 6 -- Power Distribution Measurements ................................................... 29 Section 7-- Conclusions............................................................................... 36 Section 8 - References ................................................................................ 38 Appendix - Startup Physics Test Summary Sheets .............................................. 40 Page 2 of 46

Serial No.15-432 Docket No. 50-280 Sl1027 SPTR 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 46

Serial No.15-432 Docket No. 50-280 SiC027 SPTR 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 29.01% Power ................................. 33 Figure 6.2 - Assemblywise Power Distribution 70.45% Power ................................. 34 Figure 6.3 - Assemblywise Power Distribution 99.87% Power ................................. 35 Page 4 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 1 Cycle 27 core could be operated safely, and makes an initial evaluation of the performance of the core. This report was performed in accordance with DNES-AA-NAF-NCD-5007, Rev. 1 [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 1 Cycle 27 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer!/reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations performed by Dominion's Nuclear Analysis and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits.

Page 5 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR SECTION 1-m INTRODUCTION AND

SUMMARY

On April 19, 2015, Unit No. 1 of Surry Power Station completed Cycle 26 and began refueling [Ref. 1]. During this refueling, 65 of the 157 fuel assemblies in the core were replaced with fresh Batch S$1/29 assemblies [Ref. 8]. The Cycle 27 core consists of 8 sub-batches of fuel:

three fresh batches (S 1/29A, S1/29B and $1/29C), three once-burned batches ($1/28A, S1/28B and S1/28C), and two twice-burned batches (S1/27A and $1/27C). S1C27 will be the third Surry Unit 1 cycle to utilize the 15x15 Upgrade Fuel Design and contains only Upgrade fuel [Ref. 8].

The Westinghouse Upgrade fuel includes ZIRLO (I-spring) structural mid grids with balanced mixing vane pattern, three ZIRLO Intermediate Flow Mixing (IFM) grids, "tube-in-tube" guide thimbles, and the use of optimized ZIRLO fuel clad that improves corrosion resistance and oxidation of the bottom portion of the fuel clad to improve debris resistance. The Upgrade fuel used for batches S1/28 and S$1/29 includes Westinghouse's Robust Protective Grid (RPG) and modified Debris Filter Bottom Nozzle (mDFBN), relative to the Upgrade fuel used for batch S1/27. In addition, S1C27 will be the first Surry cycle to utilize the Westinghouse Integral Nozzle (WlN) top nozzle design [Ref. 8].

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 ZrB2 coating creates helium gas in addition to the fission gas created during irradiation of the fuel. Therefore, the initial pressure is set lower so the internal pressure early in lifetime may be lower [Ref. 5].

$1C27 also implements the reinsertion of Secondary Source Assemblies (SSAs) to improve Source Range detector indications. Cycle 27 loads two SSAs in core locations H04 and Page 6 of 46

Serial No.15-432 Docket No. 50-280 S10C27 SPTR H12. Each assembly consists of six source rods containing antimony and beryllium pellets encapsulated in a double layer of stainless steel cladding. There are no thimble plugging devices in Si1 C27. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 27 core.

Two of the three reactor coolant pumps were replaced during the S 1C26-S 1C27 refueling outage. Further information on this replacement can be found in Reference 20.

The S1 C27 full core loading plan [Ref. 8 and Ref. 11] is given in Figure 1.1 and the beginning of cycle fuel assembly burnups [Ref. 6] are given in Figure 1.2. The 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 27 core [Ref. 1].

According to the Startup Physics logs, the Cycle 27 core achieved initial criticality on May 27, 2015 at 00:21 [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.7 [Ref. 9] was used for

$1C27 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 1 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 -1.2% of the design prediction. The reference bank (Control Bank B) worth was within

-2.2% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within -3.5% of the design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within -6.8 pcm of the design prediction.

Page 7 of 46

Serial No.15-432 Docket No. 50-280

$1 C27 SPTR These results are within the design tolerances of + 15% for individual banks worth more than 600 pcm (+ 10% for the reference bank worth), +/- 100 pcm for individual banks worth 600 pcm or less, and +10% for the sum of the individual control rod bank worths.

Measured critical boron concentrations for two control bank configurations, all rods out (ARO) and Reference Bank (B-bank) in, were within the design tolerances and the Technical Specification criterion [Ref. 4] that the overall core reactivity balance shall be within + 1% Ak/k of the design prediction. The boron worth coefficient measurement was within +0.5% 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 pcrr/°F.

Core power distributions were within established design tolerances. The measured assembly power distributions were within +_4.7% of the design predictions, where a -4.7%

maximum difference occurred in the 70.45% power map. The heat flux hot channel factors, FQ(Z), and enthalpy rise hot channel factors, FN*, were within the limits of the COLR [Ref. 8].

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

< 1.02).

The total RCS Flow was successfully verified as being greater than 273,000 gpm and greater than the limit in the COLR (274000 gpm), as required by Surry Technical Specifications

[Ref 4]. RCS Flow was measured at various plant configurations in accordance with the RCS Loop Flows test plan [Ref. 18]. The total RCS Flow at nominal conditions was measured as 289,422 gpm.

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

Page 8 of 46

Serial No.15-432 Docket No. 50-280 S1027 SPTR Table 1.1 SURRY UNIT 1 - CYCLE 27 CHRONOLOGY OF TESTS Test jDate I 1 1 1Reference jTime Power Procedure Hot Rod Drop-Hot Full Flow 05/25/15 20:20 HSD 1-NPT-RX-0 14 Reactivity Computer Checkout 05/27/15 01:10 HZP 1-NPT-RX-008 Boron Endpoint - ARO 05/27/15 01:10 HZP 1-NPT-RX-008 Zero Power Testing Range 05/27/15 01:10 SHZP 1-NPT-RX-008 Boron Worth Coefficient 05/27/15 04:40 HZP 1-NPT-RX-008 Temperature Coefficient - ARO 05/27/15 01:50 HZP 1-NPT-RX-00 8 Bank B Worth 05/27/15 02:48 HZP 1-NPT-RX-008 Boron Endpoint - B in 05/27/15 04:40 HZP 1-NPT-RX-008 Bank A Worth -Rod Swap 05/27/15 04:45 HZP 1-NPT-RX-00 8 Bank C Worth -Rod Swap 05/27/15 04:45 HZP 1-NPT-RX-008 Bank SA Worth -Rod Swap 05/27/15 04:45 HZP 1-NPT-RX-008 Bank D Worth -Rod Swap 05/27/15 04:45 HZP 1-NPT-RX-008 Bank SB Worth -Rod Swap 05/27/15 04:45 HZP 1-NPT-RX-00 8 Total Rod Worth 05/27/15 04:45 HZP 1-NPT-RX-008 Flux Map - less than 50% Power 05/28/15 02:57 29.01% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT.-RX-005 1-GEP-RX-00 1 Flux Map - 65% - 75% Power 05/29/15 12:10 70.45% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-00 8

& Power Range Calibration 1-NPT-RX-005 1-GEP-RX-001 Flux Map - 95% - 100% Power 06/04/15 09:00 99.87% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT-RX-005 1-GEP-RX-001 RCS Flow Measurement 06/01/15 12:00 H{FP 1-NPT-RX-009 Page 9 of 46

Serial No.15-432 Docket No. 50-280 Si1027 SPTR Figure 1.1 SURRY UNIT 1 - CYCLE 27 CORE LOADING MAP SURRY UNIT 1 - CYCLE~ 27 FULL CORE LOADING PLAN REVISION NO. 0 VBP-555-5AP A S C 0 5 0 EC J S 0 90 2 1? 5 15

[146 145 Rco 5CC 5CC NO0TH 101 217 350 353 352 223 103 5CC- RCC 13 142 346 326 301 246 301 329 342 143 5CC RCC SS1O 5CC 8LCC 12

!41 360 334 230 202 257 205 231 340 362 144 5cc 5CC 11 105 348 337 216 253 "313 261 337 255 212 332 345 107 5CC 5CC 5C*C 5CC 5CC 5CC RCC 10 220 331 229 254 324 237 309 233 315 266 225 328 218 5*CC 5CC 5CC 5CC 9

152 350 206 204 319 236 242 212 243 239 322 208 304 354 167 5CC 5CC 5CC 5CC 8

270 155 354 247 250 264 310 210 324 209 322 263 259 245 361 156 5CC 5CC 5CC 5CC 151 353 303 205 315 240 244 211 245 235 316 201 302 356 148 222 338 225 250 320 234 311 238 323 251 227 339 221 5

165 34:7 330 2 4 248 3i4 262 321 252 21S 336 349 106 5CC 5CC 5511 5CC RCC 140 365 333 232 207 258 203 224 341 356 137 5IT*S CC 5CC IS*CORO D5E?1C5 5 3 5CC- 5050. 0.5507 057501 500 139 343 327 305 241 305 336 344 139 SSXX- COOS S 30500 AS59eM8tY 5CC 5cc 5CC 2

104 224 367 359 351 219 102 145 154 Pese  : s~,, oae <,A,((,,-- 1800 Concurrence By: ___________ Dato, I3S/*

A. 3. BlaCk Approved By; ooto: _____,.r-A. 5. Slicholeon 5. 5. LaPr d Page 10 of 46

Serial No.15-432 Docket No. 50-280 S1C27 SPTR Figure 1.2 SURRY UNIT 1 - CYCLE 27 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWD/MTU)

R P N N L K I N G F - E D C B A 1 I 40.611 40.971 40.641 I EASURED I 1 I 40.521 41.O1J 40.531 PREDICTED 2 I 35.08j 23.92f 0.001 0.00l 0.00l 23.991 34.891 2 I 35-191 24.151 0.001 0.001 0.001 24.141 35.181 3 I40.601 0.001 0.001 0.001 19.981 0.001 0.001 0.001 40.16I 3 I40.391 0.001 0.00] 0.001 19.911 0.001 0.001 0.001 40.381 4 F40.421 0.001 0.00? 23.111 23.95f 20.441 24.161 23.30f 0.001 0.00f 40.45j 4 I40.371 0.001 0.001 23.191 23.95l 20.39j 2395 23.19f 0.001 0.00i 40.391 5 35.461 0,001 0.0sf 22.41! 19.6Sf 0.001 20.941 0.001 19.791 22.461 0.001 0.00! 35.581 5 I35,58J 0.001 0.00? 22.701 19.771 0.001 20.851 0.00f 19.791 22.721 0.001 0.001 3559 6 I24.061 0.001 23.721 19.751 0.001 24.33! 0.001 24.141 0.001 19.771 23.111 0.001 24.321 6 I24.141 0.001 23.151 19.751 0.001 24.161 0.001 24.151 0.00? 19.731 23.151 0.001 24.141 7 I40.481 0o00 0.001 24.24f 0.001 24.181 19.94f 25.081 19.921 24.20j 0,001 23.831 0.001 0.001 40.531 7 I40.541 0.001 0.001 23.981 0.001 24.16? 19.881 24.571 19.911 24.171 0.00? 23.981 0.001 0.001 40.53f 8 I41.241 0.001 20.211 2054 20.971 0.001 24.501 0.001 24.35I 0.001 20.631 20.491 20.141 0o00i 40o911 8 I41.011l 0.001 19.891 2o.391 20.831 0.001 24.571 0.001 24.581 0.001 20.82! 20.401 19.891 0.001 41.011 9 I40-781 0.00? 0.00f 23.9Sf 0.00! 24.33l 19.9sf 24.53f 19.871 24.20f 0.001 24.19j 0.001 0.001 40.16f 9 I40.53f 0.001 0.001 23.98l 0.00[ 24.171 19.91? 24.571 15.881 24.16j 0-001 23.981 0.001 0.001 40.54[

10 'I24.21f 0.001 23.131 19.72j 0.00f 24.091 0.001 24.701 0.001 20.021 23.38f 0.001 24.13f 10 I24.14J 0.00? 23.151 19,73j 0.001 24.1sf 0.001 24.16f 0.001 19.7sf 23,151 0.001 24.141 11i 35.441 0.001 oCofl 22.561 20.02f 0.001 20.681 0.001 19.771 22.63? 0.001 0.001 35.511 11 I35.59l 0.001 0.001 22.671 19.781 0.00? 20.851 0.001 19.77j 22.671 0.001 0.001 35.59l 12 I 40.55j 0.00j 0.001 23.791 24.031 20.36f 23.97f 23.23j 0.001 0.001 40.361 12 I 40.391 0.001 0.0sf 23.191 23.95J 20.391 23.951 23.191 0.001 0.001 40.371 13 I 40.401 0.001 0.O01 0.o01 20.22j 0.00j 0.001 0.001 40.39? 13 I 40.391 0.001 0.001 0.001 19.911 0.00j 0.001 0.001 40.401 14 I 35.l0f 24.13l 0.00? 0.00l 0.001 23.95j 35.O9j 14 I 35.231 24.141 0.001 0.oof 0.00? 24.151 3S.221 15 I 40.591 40.831 40.541 15 I 40.53j 41.011 40.53f..... ......... . .....----

Page 11 of 46

Serial No.15-432 Docket No. 50-280 SI1027 SPTR Figure 1.3 SURRY UNIT 1 - CYCLE 27 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R P N M L K J H G F E D C B A 1

MD 2

MD 1--I -~ t ~ MD 3

MD MD MD MD MD

+ 4 MD MD MD MD_ MD MD M DI M DLI MD 5 MD MD MD 6

+ * +

____MD __ __ MD __MD __ __MD MD __

7 8

MD MD _MD __MD MD MD

_ MD _ MD MD _ __ MD 9

MD 10 MD MD MD

_I__IMDIIII MDIMDIIII] MD MD MD 11

-12 MD MD -MD

+ 13 MD MD 14 MD MD M J3 M MD M 15 MDj-MD - Moveable Detector

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

• -Location G7 Used as Calibration Thimble Due to Location J7 Being Unavailable Following Replacement Page 12 of 46

Serial No.15-432 Docket No. 50-280 Si C27 SPTR Figure 1.4 SURRY UNIT 1 - CYCLE 27 CONTROL ROD LOCATIONS R P N M L K J H G F E D C B A 1800 1

SB A D 1 A 2 1

• 4 1 -t------~

SA SA 3 SB 4 4 f I + + -t C B B C 4 C C

___ I A

B ISB[I (1 I I.~I D

C D

B A

5 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

___ ___ ___ ISB[II ___ I I ISBIT 11 C B B C 12 SA SA 13 A D A 14 SB - SBt-15 0o 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 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR 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 0 F per 1-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. 1 [Ref. 4].

Surry Unit 1 Cycle 27 is the first cycle to use the Rod Drop Measurement Instrument (RDMI) instead of the rod drop test computer (RDTC) [Ref. 12]. 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 a comma-separated value file.

Further details about the RDMI can be found in Reference 12.

A typical rod drop trace for S1C27 is shown in Figure 2.1. The measured drop time for each control rod is recorded on Figure 2.2. The slowest, fastest and average drop times are summarized in Table 2.1. Figure 2.3 shows slowest, fastest, and average drop times for Surry 1 cycles 18-27. Technical Specification 3.12.C.1 [Ref. 41 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.

The rod drop times were slightly slower than SLC26, by an average of 0.07 seconds, which is attributed to use of the new Rod Drop Measurement Instrument (data analyzed for previous cycles with RDMI also gave similar slower rod drop times [Ref. 19]).

Page 14 of 46

Serial No.15-432 Docket No. 50-280 S1C027 SPTR Table 2.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME P-08 1.45 sec. M-06 1.31 sec 1.36 sec.

Page 15 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Figure 2.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE I

S1C27 DROP DATA : G9 (SBB) 0 1 ~ 234 Time (S)

Page 16 of 46

Serial No.15-432 Docket No. 50-280 SI1027 SPTR Figure 2.2 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R P N M L K J H G F E D C B A 1

2 1.34 1.32 1.35 3

1.35 1.38 4

1.35 1.32 1.33 1.39

__I___1 1.331__11 __ [ 1 .3511__ 5 6

1.33 1.31 1.35 1.35 1.37 1.33 1.43 7

__ ___ 1.35 ___ __ 1.40 ___ 1.35 ___ __ __ 1.36___

8

___ 1.45 ___ __ __ 1.37 _ _ ___1.43 ___ __ __ 1.38 ___

9

______ 1.39 _ __ ___ 1.34 _ __ 1.37 ___ __ __ 1.36 __ __

1.34 1.37 10 1.35 1.34 1.36 1.37 1.35 11 1.32 1.33 12 1.33 1.32 1.35 1.40 13 1.37 1.37 14 1.37 1.33 1.38 I 4 I +

15

[-1 --- > Rod drop time to dashpot entry (sec.)

Page 17 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Figure 2.3 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 2.5 2.4 2.3 2.2 2.1

-- *-- Slowest Rod Time

-- Fastest Rod Time 1.9 -- Average Ti me 1.7 1.6 1.5 1.4 1.3 1.2 1.1 18 19 20 21 22 23 24 25 26 27 Cycle Page 18 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR SECTION 3-- CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worthis 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 detennine the differential and integral worth of the reference bank. For Cycle 27, Control Bank B was used as the reference bank. Surry 1 targeted a dilution rate of 1100 pcm/hr for the reference bank measurement.

During 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 Si1C27 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 Page 19 of 46

Serial No.15-432 Docket No. 50-280

$1027 SPTR balance the reactivity of the reference bank withdrawal. This sequence was repeated until the previous test bank was fully withdrawn and the current test bank was nearly inserted. The next step was to swap the rest of the test bank in by balancing the reactivity with the withdrawal of the reference bank, until the test bank was fully inserted and the reference bank was positioned such that the core was near the initial statepoint condition. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank.

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

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

-1.2% 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 20 of 46

Serial No.15-432 Docket No. 50-280 S10C27 SPTR Table 3.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM) (PCM) (M-P)/P X 100 B -Reference 1219.4 1247.0 -2.2%

A 250.8 257.6 -6.8 pcm*

C 908.6 908.2 +0.0%

SA 886.3 875.0 +1.3%

D 1044.5 1045.1 -0.1%

SB 1162.7 1204.8 -3.5%

Total Bank Worth 5472.3 5537.7 -1.2%

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

Page 21 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Figure 3.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1400 1200 1000 \\

00 00 -U- Prediklnd

@1

\\.

400 200 "IR

• ! tJl i,

51 ..

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

Page 22 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Figure 3.2 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 9.0 8.0 7.0 6.0 0.i 5.0 43

- +Measued 0.i ---U- Prdee A

4.0 3.0 2.0 1.0 0.0 0 50 100 150 200 250 Bank Position (steps)

Page 23 of 46

Serial No.15-432 Docket No. 50-280 S1C27 SPTR SECTION 4-- BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power (HZP), reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position and moderator temperature, as necessary.

The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Summary Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.1 0.A [Ref. 4] regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.

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

A summary of the measured and predicted DBW is shown in Table 4.2. As indicated in this table and in the Appendix, the measured DBW was well within the design tolerance of 10%. In summary, the measured boron worth coefficient was satisfactory.

_+

Page 24 of 46

Serial No.15-432 Docket No. 50-280 SI1027 SPTR Table 4.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 1472.4 1477.0 -4.6 B Bank In 1312.8 1308.4* +4.4

• 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 Test Summary Sheet in the Appendix.

Page 25 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Table 4.2 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

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

-7.64 -7.60 +0.5%

Page 26 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR SECTION 5-- TEMPERATURE COEFFICIENT MEASUREMENT The ITC at the ARO condition is measured by controlling the RCS temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate by adjusting feed and letdown flow rates, and monitoring the resulting reactivity changes on the reactivity computer.

Reactivity was measured during the RCS heat up of 3.04 °F, followed by the RCS cool down of 3.02 °F. Reactivity and temperature data were taken from the reactivity computer. Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature.

The predicted and measured ITC values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Summary Sheet given in the Appendix, the measured ITC value was within the design tolerance of +/-+2 pcm/°F. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -2.866 pcm/°0 F, a predicted doppler temperature coefficient (DTC) of -1.83 pcm/ °F, and a measurement uncertainty of +0.5 pcm/°0F, is -0.53 6 pcm/°0F. It thus satisfies the COLR criteria [Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pcm/°0F.

Page 27 of 46

Serial No.15-432 Docket No. 50-280 S1C27 SPTR Table 5.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

BAK TEMPERATURE BRNISOTHERMAL TEMPERATURE COEFFICIENT POSTINK RANGE (°)--CONCENTRATION -CO-(CP)__-DfE (TPOS)TO -LIMIT IULIMIT HEAT- iCO-AVG. iDFE LOWERS LIMI UPPERI (ppm) UP iDOWN MEAS -PRED (M-P)

D/206 544.62 547.73 1464 -3.214 i-2.517 -2.866 -3.055 i0.189 Page 28 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR 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 insfrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available locations monitored by the moveable detectors for Cycle 27 power ascension flux maps. For each traverse, the detector voltage output is continuously monitored on a recorder, and scanned for 610 discrete axial points. Full core, three-dimensional power distributions are detenmined from this data using a Dominion-modified version of the Combustion Engineering computer program, CEBRZ/CECOR [Ref. 3, Ref. 15]. CECOR couples the measured voltages with predetenmined 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 29.0 1% 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 70.45% 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 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

+/-4.1% in the 29.01% power map, +/-4.7% in the 70.45% power map and +/-4.3% in the 99.87%

power map. The maximum average quadrant power tilt for the three maps were +0.91%, +0.48%

and +/-0.49%, respectively. These power tilts are within the design tolerance of 2%.

Page 29 of 46

Serial No.15-432 Docket No. 50-280 S1C27 SPTR 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 27.

Page 30 of 46

Serial No.15-432 Docket No. 50-280 S1C27 SPTR Table 6.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

iaBurnu:PowrBn PoerBak Peak FQ(Z) Hot F* Hot (2) Core Fz Map Description Map No. Dt MTU W/() D Steps Channel Factor (I) Channel Assy Axi[FQ(Z Factor PoinMaxOfst Core Assy !F* Mao Tilt (3) Axial

)Tibe No.f Low Power 1 05/28/15 1.3 29.01 171 M-8 26 2.183 M-8 1.513 26 1.358 1.0091 SW 5.640 46 Int. Power (4) 2 05/29/15 24.8 70.45 197 D-8 I 25 1l.907 M-8 1.467 26 1.214 1.00481 SW 3.532 46 Hot Full Power 3 06/04/15 196.0 99.87 225 D-8 {29 11.826 D-8 1.447 29 1.172 1.05SW 1.661 46 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.

(I) FQ(Z) includes a total uncertainty of 8%.

(2) F* includes no uncertainty.

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

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

Page 31 of 46

Serial No.15-432 Docket No. 50-280 Si1027 SPTR Table 6.2 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak FQ(Z) Hot Channel Factor F* Hot Channel Factor Map Meas. Limit Node Margin* Meas. Limit Margin*

No. _ _ __ _ __ _ _ (%) _ __ (%)

1 2.183 5.000 26 _ 56.3 1.513 1.892 20.0 2 1.907 3.549 25 46.3 1.467 1.698 13.6 3 1.826 2.503 29 27.0 1.447 1.561 7.3 The measured FQ(Z) hot channel factors include 8% total uncertainty. Measured F* data includes no uncertainty.

• Margin (%) = 10*(Limit -Meas.) / Limit Page 32 of 46

Serial No.15-432 Docket No. 50-280 Si1027 SPTR Figure 6.1 -- ASSEMBLY WISE POWER DISTRIBUTION 29.01% POWER ASSEMBLY RELATIVE POWERFRACTIONS Top value = Measured, middle value = Analytical, bottom value = %Delta

% Delta = (H - A)xl0O/A R P N M L K J H 0 F E D C B A I 0.2431 0.2901 0.242[

1I 0.2401 0.289f 0.2391 I 1.211 0.281 1.17j I 0.303f 0.5701 0.9541 0.980f 0.947f 0.573f 0.3041 2I 0.302J 0.5651 0.9421 0.970! 0.93sf 0.563f 0.3011 I 0.41f 0.911 1.301 1.001 1.201 1.82! 0.921 I 0.364f 0.998! .11n2j 1.2411 1.2931 1.22sf 1.nol1 0.9981 0.364f 3 0.3651 0.9981 1.105! 1.2201 1.2731 l.214f 1.1031 0.9971 0.38Sf S-0.381 0.001 0.611 1.681 1.571 0.94f 0.621 0.091 -0.1sf I 0.3861 0.9641 1.2121 1.212! 1.217! 1.3381 1.226f 1.2151 1.2121 0.964! 0.384!

'0I 0.3671 0.9691 1.2181 1.2121 1.2101 1.319! 1.2181 1.2131 1.2181 0.969! 0.3671 I -0.14f -0.48j -0.92! -0.02! 0.58! 1.28! 0.s68 0.18! -0.471 -0.55! -0.73!

I0.303! 1.0081 1.217! 1.206! 1.257f 1.251! 1.341! 1.270f 1.304! 1.209! 1.215! 0.957f 0.297!

S I0.303! 1.006! 1.225! 1.225! 1.3071 1.265! l.337f 1.2701 1.308f 1.2241 1.223! 1.006f 0.303!

I 0.18! 0.16f -0.65! -1.55! -0.751 -1.081 0.32! -0.Olj -0.32f -1.25! -0.83! -0.90! -1.95!

Io.5661 1.1091 1.224! 1.323! 1.161f 1.2121 1.31sf 1.210f 1.1811 1.305! 1.217! 1.111l 0.569!

6 I0.572! 1.120] 1.228! l.318f 1.167f 1.214f 1.30sf 1.216! 1.167f 1.3161 1.226! 1.121! 0.574!

I-1.08! -1.03! -0.32! 0.40j -0.481 -0.14f 0.871 -0.52! -05 -0.861 -0.72! -0.88! -0.92!

I0.240! 0.93Sf 1.210! 1.2391 1.292f 1.2241 1.3221 1.184! 1.287! 1.203! 1.2691 1.227! 1.236! 0.954f 0.2431 7I0.244! 0.9561 1.240! 1.24sf 1.28Sf 1.223f 1.325! 1.193! 1.324! 1.220! 1.283f 1.237! 1.247! 0.962f 0.24Sf I-1.82f -1.77[ -2.40! -0.4sf 0.22f 0.08f -0.24! -0.76! -2.78! -1.39! -1.101 -0.83! -0.85! -0.83! -0.7sf I0.287! 0.579f 1.296! 1.384f 1.37sf 1.323! 1.193! 1.162! 1.169! 1.299! 1.348f 1.369! 1.2971 0-9761 0.290f 8I0.2951 0.9921 1.307! 1.381f 1.362f 1.318! 1.195! 1.176! 1.195! 1.318! 1.382! 1.381! 1.307f 0.992f 0.295f I-2.68l -1.30! -0.87! 0.25! 1.19! 0.37! -0.15! -1.15! -2.14! -1.48! -0.99! -0.8sf -0.76f -1.5sf -1.67!

I0.2441 0.962! 1.254! 1.248! 1.296! 1.227! 1.324! 1.180! 1.281! 1.216f 1.277! 1.230f 1.224f 0.940f 0.235!

9I0.245! 0.962! 1.247! 1.237! 1.283! 1.220! 1.324! 1.153f 1.32Sf 1.223f 1.289! 1.24sf 1.2411 0.956! 0.245!

I-0.351 0.03! 0.60f 0.91! 1.02! 0.97! 0.00! -1.13[ -3.33! -0.571 -0.96! -1.19f -1.341 -1.68! -4.10!

I0.983! 1.149f 1.246! 1.333f 1.173f 1.224! 1.39Sf 1.200f 1.152f 1.30sf 1.205! 1.102! 0.562!

10 I0.574! 1.121f 1.227! 1.31sf 1.167f 1.216! 1.30sf 1.2141 1.167f 1.31sf 1.22sf 1.120! 0.572!

I 1.02! 2.54f 1.58! 1.2sf 0.51f 0.65! -0.24f -1.1sf -1.31! -0.7Sf -1.96! -1.59s -1.74!

I0.309! 1.025! 1.243! l.246f 1.324f 1.281! 1.349! 1.263f 1.293! 1.23sf 1.216! 0.993! 0.299!

1ii 0.304! 1.006! 1.224! 1.226! 1.30sf 1.271! 1.337! 1.26Sf 1.307f 1.22sf 1.226! 1.008f 0.303!

I 1.62f 1.86! 1.5sf 1.61! 1.12f 0.82! 0.87! -0.12! -1.10! 1.05! -07 -1.29! -1.33!

I 0.369! 0.982f 1.235! 1.22sf 1.231! 1.335! 1.224! 1.224! 1.227! 0.963! 0.359!

12 I 0.367! 0-9701 1.219! 1.214! 1.21Sf 1.320! 1.211! 1.212! 1.218! 0.970! 0.367!

I 0.60! 1.2sf 1.31! 1.20! 1.05! 1.19! 1.08! 0.96! 0.78! -0.70! -2.23!

I 0.37Sf 1.010!1.1-17! 1.22sf 1.293f 1.246! 1.141! 1.016f 0.368f 13  ! 0.3651 0.998! 1.104! 1.2141 1.2731 1.221f 1.10Sf 0.998f 0.36sf I 1.47! 1.21! 1.20! 1.22f 1.5sf 2.08f 3.2sf 1.8Sf 0.76f I 0.304f 0.971! 0.948f 0.985! 0.571f 0.583f 0.30Sf 14 I 0.301f 0.563f 0.937f 0.970f 0.942! 0.56sf 0.302!

I 1.12f 1.3sf 1.17! 1.58! 3.07! 3.16! 2.33!

I 0.238! 0.293! 0.247!

iS I 0.240! 0.289! 0.40 I -0.89! 1.49! 2.89!

AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.1 STANDARD DEVIATION = 0.735 Summary:

Map No: S1-27-01 Date: 05/28/2015 Power: 29.01%

Control Rod Position: FQ(z) = 2.183 QPTR: 0.9982 0.9953 D Bank atl171 Steps EN = 1.513 1.0091 0.9974 Fz= 1.358 Burnu =13 MW/MTU Axial Offset (%) = +5.640 Page 33 of 46

Serial No.15-432 Docket No. 50-280 SI1027 SPTR Figure 6.2 -- ASSEMBLYWISE POWER DISTRIBUTION 70.45% POWER ASSEMBLy RELATIVE POWERFRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Delta

% Delta = (M - A)xl00/A R P N M L K J N G F E D C B A I 0.2631 0.31Sf 0.261f 1I 0.263f 0.31Sf 0.2621 I 0.041 -1.41f -0.2sf I 0.3161 0.55Sf 0.97Sf 1.02Sf 0.96Sf 0-587f 0.3161 2I 0.317f 0.557f 0.971f 1.02sf 0.9661 0.58Sf 0.3171 I -0.1sf 5.2Sf 0.43f -0.24f -0.13f 0.3Sf -0.36f I 5.36Sf 0.593f 1.1061 l.233f 1.26sf 1.211f 1.l01f 0.9921 0.36sf 3I 0.37sf 1.0001 1.10Sf 1.21Sf 1.2721 1.213f 1.1041 1.00sf 0.37sf I -2.2sf -0.6sf 0.nlf 1.1sf -0.33f -0.17f -0.31f -0.80f -2.52f I 0.377f 0.957f 1.19sf 1.194f 1.202f 1.31sf 1.208f 1.157f l.154f 0.962f 0.377f 4I 0.37Sf 5.96Sf 1.203f 1.19sf l1-17f l.254f 1.203f 1.20sf l.203f 5.56sf 5.37Sf I -0.501 -1.1sf -1.041 -0.3sf 0.44f l.24f 0.3Sf -0.21f -0.7sf -0.7sf -0.52f I 5.31Sf 1.004f l.194f 1.18sf 1.25f 1.243f 1.317f 1.25sf 1.29Sf l.194f l.207f 1.00sf 0.30Sf S I 0.317f 1.00Sf 1.20sf l.211f 1.297f l.252f 1.311f 1.25Sf 1.29sf 1.21sf l.206f 1.00Sf 0.3l7f I -0.36f -0.l1f -1.17f -2.53f -0.9sf -0.72f 0.4sf 0.1Sf -0.17f -1.3Sf 0.0sf -0.52f -2.9sf I 0.584f 1.103f 1.206f 1.31Sf 1.206f 1.213f l.304f 1.2131 1.21Sf 1.301f 1.207f l.liif 0.587f 6 I 0.551f 1.n14f 1.21sf 1.305f 1.206f 1.21sf 1.25Sf 1.212f l.206f l.303f 1.20sf 1.11Sf 0.593f I 14f 97f 36f 0.74f -0.03f s.24f 1.13f 0.12f 0.74f -0.1sf -0.07f -0.3sf -0.96f I0.259f 0.561f 1.20Sf 1.21sf 1.27Sf 1.222f 1.31sf 1.17sf 1.253f l.214f l.264f 1.21Sf 1.234f 0.574f 0-264f 7I0.26Sf 5.579f 1.231f 1.223f 1.27sf 1.217f 1.307f 1.17Sf 1.35Sf 1.214f 1.26Sf 1.216f 1.237f 0-954f 0.267f I-2.65f -1.57f -2.14f -0.34f 0.9sf 0.44f 0.19f -0.0sf -1.7sf 0.03f -0.07f 0.03f -0.26f -l.03f -1.16f I0.30sf 1.02Sf 1.280f 1.34sf 1.35sf 1.30Sf 1.185f 1.161f 1.172f 1.307f 1.334f 1.34sf 1.301f 1.04sf 0.32sf 0 .323f l.043f 1.256f 1.346f 1.330f 1.256f 1.151f 1.16Sf l.181f 1.296f 1.33sf 1.34sf 1.29Sf 1.043f 0.323f I-4.6sf -l.66f -l.22f 0.22f 1.53f 0.72f 0.32f -0.37f -0.7Sf 0.87f 0.2sf 0.llf 0.41f -0.27f -0.92f I0.262f ,0.97sf 1.237f 1.22Sf l.283f 1.22Sf 1.31sf 1.17Sf l.251f 1.226f 1.27sf 1.21sf 1.224f 0.96sf 0.254f 5I0.267f 0.954f 1.237f 1.216f 1.26Sf 1.21Sf 1.30Sf 1.15Sf l.307f 1.217f 1.27sf l.223f 1.231f 0.97sf 0.2866 I-l.77f -0.61f -0.Olf 0.7Sf 1-41f 0.51f 0.3sf -0.46f -2.0sf 0.74f -0.02f -0.3sf -0.57f -1.1sf -4.54f I0.596f 1.130f 1.221f 1.31sf 1.214f 1.21sf 1.29sf 1.20Sf 1.204f 1.3021 1.1921 1.10sf 0.97Sf 10 0 .593f 1.116f 1.20Sf 1.303f 1.206f 1.212f 1.28sf 1.21sf 1.20Sf 1.30Sf 1.21sf 1.11Sf 0.591f I 0.511 1.3sf 0.9Sf 1.12f 0.64f 0.46f 0.0Sf -0.41f -0.21f -0.24f -1.4sf -1.31f -1.96f I0.32sf 1.011f 1.21Sf 1.22Sf 1.30sf 1.265f 1.323f 1.25Sf l.252f 1.21sf l.201f 0.553f 0.313f 11l 0.31sf 1.00sfl1.207f 1.212f 1.29sf 1.257f 1.311f 1.252f l.257f l.212f 1.20Sf 1.50Sf10.317f 0 .52f 0.63f 0.77f 1.17f 0.57f 0.63f 0.5sf 0.22f -0.3sf 0.57f -0.61f -l.17f -1.3sf I 0.371f 0.972f 1.211f 1.20Sf l.213f 1.307f 1.21sf 1.213f 1.213f 0.96sf 0.36sf 12 I 5.37Sf 0.96Sf 1.20Sf 1.20sf 1.204f 1.25Sf 1.197f 1.19sf 1.203f 0.56sf 5.379f I -2.131 0.3sf 0.59f 0.7Sf 0.7sf 1.oif .nll 1.24f 0.57f -O~lif -2.53f I 0.38sf 1.003f 1.10sf l.221f l.286f 1.24sf 1.152f 1.02sf 0.352f 13 I 0.37sf 1.00sf 1.15Sf 1.2131 1.272f 1.21sf 1.10Sf 1.00sf 5.37sf1 -

I 0.17f 0.27f 0.4Sf 0.66f 1.0Sf 1.0sf 3.3sf 1.9sf 0.52f f 0.311f 0.587f 0.97sf l.037f 0.956f 0.602f 0.32Sf 14 I 0.317f 0.505f 0.56sf 1.02sf 0.9711 0.557f 0.317f S-2.0Sf 0.29f 0.4sf 0.8sf 1.56f 2.57f 2.31f I 0.25Sf 0.321f 0.267f 15 f 0-262f 0.31sf 0.263f S-2.1Sf 0.47f 1.3Sf AVERAGE ABSOLUTE PERCENT DIFFERENCE = 0.9 STANDARD5DEVIATION = 0.s814 Summary:

Map No: S1-27-02 Date: 05/29/20 15 Power: 70.45%

Control Rod Position: FQ(Z) = 1.907 QPTR: 0.9966 [ 0.9973 D Bank at 197 Steps F* = 1.467 1.0048 I 1.0013 Fz =1.214 Burnp =24.8 MWDMTU Axial Offset (%) = +3.532 Page 34 of 46

Serial No.15-432 Docket No. 50-280

$1027 SPTR Figure 6.3 -- AS SEMBLY WISE POWER DISTRIBUTION 99.87% POWER ASSEMBLY RELATIVE POWERFRACTIONS Top value = Measured, middle value = Analytical, bottom value = % Dlelta

% Delta = (M - A)XlOO/A R P N M L K J N G F E D C B A

[ 0.271j 0.3281 0.2701 1 I 0.271f 0.3311 0.2701 I 0.ioi -0.841 -0.181 I 0.3181 0.5901 0.0761 1.055! 0.967! 0.5861 0.317f 2I 0.3191 0.589! 0.0721 1.05sf 0.0681 0.5871 0.31Sf I -0.451 0.131 0.401 0.041 -0.081 -0.161 -0.191 I 0.367! 0.9771 1.0931 1.2211 1.264j 1.2051 1.0911 0.9801 0.3711 3 I 0.379j 0.9851 1.0951 1.2101 1.2621 1.20sf 1.0031 0.0851 0.3791 I -3.151 -0.85! -0.181 0.88f 0.121 0.02f -0.1Sf -0.511 -2.00!

I 0.3761 0.944! 1.176! 1.1811 1.191! 1.2951 1.2011 1.1891 1.1831 0.554f 0.379!

4 I 0.3801 0.9571 1.1881 1.1871 1.1901 1.2791 1.1951 1.1881 1.18Sf 0.9561 0.3791 I -1.071 -1.39j -i.00f -0.47j 0.061 1.261 0.501 0.091 -0.391 -0.25! -0.111 I 0.31Sf 0-983! 1-1771 1.180j 1.2851 1.2401 1.311! 1.266! 1.301! 1.19Sf 1.1941 0.987f 0.311f 5 I 0.3191 0.98Sf 1.1921 1.204j 1.2091 1.2591 1.306j 1.2631 1.3001 1.2031 1.191j 0.989f 0.319!

I -l.00f -0.61f -1.30! -2.011 -1.101 -1.511 0.411 0.21! 0.08j -0.561 0.2sf -0.22f -2.571 I 0.5831 1.0861 1.188f 1.3061 1.2551 1.22sf 1.3161 1.2301 1.2671 1.3051 1.198j 1.1021 0.5901 6 I 0.5931 1.1031 1.1981 1.3061 1.260f 1.2261 1.298f 1.2281 1.2591 1.3041 1.196!1i.1041 0.5941 I -1.62! -1.54f 851 -0.031 -0.381 -0.051 1.35! 0.151 0.601 0.0sf 0.131 -0.23! -0.621 I 0.2661 0.958! l.188f 1.204! 1.276f 1.234f 1.314f 1.1881 1.292! 1.229f 1.271! 1.2051 1.22Sf 0.976! 0.2721 7 I 0.2741 0.9801 1.2221 1.214f 1.2761 1.2321 1.3131 1.1881 1.3131 1.2301 1.2711 1.207! 1.2271 0.984f 0.2741 I -2.871 -2.201 -2.751 -0.84! -0.011 0.131 0.091 0.01! -1.61f -0.04! 0.031 0.16f -0.091 -0.81! -0.781 I 0.321f 1.052j 1.268! 1.3281 1-3381 1.3111 1.1931 l.176j 1.183j 1.3141 1.328! 1.332! 1.291! 1.063! 0.331!

8 0.3351 1.069! 1.2841 1.329! 1.324! 1.305! 1.190f 1.179! 1.190! 1.305! 1.324! 1.329! 1.284! 1.069! 0.335!

I -4.291 -l.60f -1.22j -0.05! 1.07! 0.49! 0.23f -0.24! -0.599! 0.71! 0.29j 0.20! 0.531 -0.60! -1.13!

I 0.2701 "0.9781 1.227! 1.21Sf 1.291f 1.2401 1.317! 1.186! 1.295! 1.235! 1.276! 1.211! 1.217! 0.970! 0.261!

91I0.2741 0.984! 1.227! 1.207! 1.271! 1.230! 1.313! 1.1881 1.313! 1.232! 1.276! 1.214! 1.222! 0.980! 0.273!

I -1.42! -0.59l -0.02! 0.71! 1.57! 0.82! 0.28! -0.21! -1.37! 0.27f -0.02! -0.27! -0.43! -1.06! -4.30!

I 0.598k l.118j 1.209! 1.319! 1.268! 1.233! 1.300! 1.223! 1.258! 1.307f 1.185! 1.093! 0.585!

10 I 0.594! 1.104! 1.197f 1.305! 1.260! 1.22sf 1.298! 1.226! 1.260j 1.306! 1.198! 1.103f 0-593j I 0.599! 1.27! 0.97f 1.10! 0.67! 0.401 0.13! -0.25! -0.13! 0.09! -1.10! -0.88f -1.38!

I 0.321! 0.9961 1.200! 1.218! 1.310f 1.270! 1.316! 1.262! 1.297! 1.220! 1.1901 0.982! 0.316!

1i I 0-319! 0.990! 1-192! 1.204! 1.300j 1.264! 1.307! 1.259! 1.299! 1.204! 1.192f 0.990! 0.319!

I 0-71l 0.62! 0.69! 1.19! 0.80f 0.51! 0.67! 0.24j -0.17f 1.37! -0.20] -079 -1.O0f I 0.3741 0.960! 1.199! 1.197! 1.204! 1.290f 1.202f l.201f 1.199f 0.9055 0.372!

12 I 0.380f 0.9571 1.1891 1.189! 1.19Sf 1.279! 1.190! 1.187! 1.18sf 0.957! 0.380!

I -1.s0f 0.34! 0.53l 0.64! 0-64f 0.88! 0.98! 1.14! 0.94f -0.23! -2.041 I 0-380f 0.98Sf 1.098! 1.212! 1.275! 1.229! 1.12sf 1.002! 0.382f 13 I 0-379! 0.985j 1.0941 1.205! 1.262! 1.211! 1.09sf 0.985! 0.379!

I 0.28! 0.26! 0.40j 0.59! 1.04! 1.93! 2.70f 1.73! 0-73[ -

I 0-313! 0-589! 0-972! 1-066! 0.991! 0.603! 0.325!

14 I 0-318j 0.988! 0.968! 1.055! 0.973! 0.589! 0.319f I -1.51f 0.17! o.4o! 1.09! 1.82! 2.41! 1.9Sf I 0.264f 0.333! 0.275!

15 I 0.27Sf 0.331f 0.271!

I -2.35j 0.67! 1.63!

AVERAGE ABSOLUTE PERCENT DIFFERENCE = 0. 8 STANDARD DEVIATION = 0. 783 Summary:

Map No: S 1-27-03 Date: 06/04/20 15 Power: 99.87%

Control Rod Position: FQ(Z) = 1.826 QPTR: 0.9942 0.9989 D Bank at 225 Steps F* = 1.447 1.0045 I 1.0023 Fz= 1.172 Burnp96.= MWDMTU Axial Offset (%) = +1.661 Page 35 of 46

Serial No.15-432 Docket No. 50-280 S1 C27 SPTR SECTION 7-- CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 1 Cycle 27 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 Si C27 startup physics testing program, that the Surry 1 core will continue to operate safely throughout Cycle 27.

Page 36 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Table 7.1 SURRY UNIT 1 - CYCLE 27 STARTUP PHYSICS TESTS STARTUP PHYSICS TESTING RESULTS

SUMMARY

Measured Predicted Diff (M-P) or Design Parameter (M) (P) (M-P)/P, % Tolerance Critical Boron Concentration 1472.4 1477.0 -4.6 +/-50 (HZP ARO), ppm Critical Boron Concentration 1312.8 1308.4 4.4 +/-26 (HZP Ref Bank in), ppm Isothermal Temp Coefficient -2.866 -3.055 0.189 +/-2 (HZP ARO), pcm/F Differential Boron Worth -7.64 -7.60 0.5% _+10%

(HZP ARO), pcm/ppm Reference Bank Worth 1219.4 1247.0 -2.2% +10%

(B-bank, dilution), pcm A-bank Worth (Rod Swap), pcm 250.8 257.6 -6.8 +100 SA-bank Worth (Rod Swap), pcm 886.3 875.0 1.3% +15%

C-bank Worth (Rod Swap), pcm 908.6 908.2 0.0% -+15%

D-bank Worth (Rod Swap), pcm 1044.5 1045.1 -0.1% +15%

SB-bank Worth (Rod Swap), pcm 1162.7 1204.8 -3.5% _+15%

Total Bank Worth, pcm 5472.3 5537.7 -1.2% _+10%

S1C27 Testing Time: 5.6 hrs

[criticality 5/27/2015 @ 00:21 to end of testing 5/27/2015 @ 05:59]

Recent Startups:

$2C26 testing time: 7.2 hrs

$1C26 testing time: 7.8 hrs

$2C25 testing time: 6.1 hrs

$1C25 testing time: 5.7 hrs

$2C24 testing time: 7.1 hrs

$1C24 testing time: 7.0 hrs

$2C23 testing time: 9.4 hrs S1C23 testing time: 6.2 hrs

$2C22 testing time: 6.2 hrs

$1C22 testing time: 8.0 hrs Page 37 of 46

Serial No.15-432 Docket No. 50-280 S1027 SPTR SECTION 8 - REFERENCES

1. K. L. Kennett, "Surry Unit 1, Cycle 27 Design Report", Engineering Technical Evaluation ETE-NAF-20 150044, Rev. 0, May 2015.

2. T. S. Psuik, "Control Rod Reactivity Worth Determination By The Rod Swap Technique,"

Topical Report VEP-FRD-36-Rev. 0.3-A, February 2015.

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-20 11-0004, Rev. 0, March 2011.

4. Surry Units 1 and 2 Technical Specifications.

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

6. C. M. Sweeney, "Surry Unit 1 Cycle 27 TOTE, Core Follow, and Accounting Calculations",

Calculation PM-1727, Rev. 0, June 2015.

7. M. M. Giffen et al., "Surry Unit 1 Cycle 27 Flux Map Analysis", Calculation PM-1728, Rev. 0, and Addenda A - B, May 2015.

8. C. L. Tiernan, "Reload Safety Evaluation Surry 1 Cycle 27 Pattern TRX," EVAL-ENG-RSE-51 C27, Rev. 0, April 2015.

9. M. P. Shanahan, "Implementation of RMAS version 7 at Surry Unit 1 and 2," Engineering Technical Evaluation ETE-NAF-2014-0021, Rev. 0, May 2014.

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.

11. T. S. Psuik, "Surry Unit 1 Cycle 27 Full Core Loading Plan", Engineering Technical Evaluation ETE-NAF-2014-0130, Rev. 0, March 2015.

12. D. J. Agnew, "Rod Drop Text Computer Users Guide and SQA Paperwork," Engineering Technical Evaluation ETE-NAF-2014-01 18, Rev. 0, April 2015.

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. T. S. Psuik, "Surry Unit 1 Cycle 27 Startup Physics Testing Logs and Results",

Memorandum MEMO-NCD-20150016, Rev. 0, May 2015.

Page 38 of 46

Serial No.15-432 Docket No. 50-280 S1027 SPTR

15. A. M. Scharf, "The CECOR Flux Map Analysis Code Version 3.3 Additional Software Requirements and Design", Engineering Technical Evaluation ETE-NAF-20 13-0088, Rev. 0, November 2013.

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. J.EF. Kloecker, et al., "Results from Test Plan of DC SU-14-01 164- RCS Loop Flows",

Engineering Technical Evaluation ETE-NAF-2015-0071, Rev. 0, June 2015.

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

Analysis Report", AREVA Document No. 51-9228549-000, Feb 2015.

20. D. Ingell et al., "Unit 1 RCP Replacement" Design Change SU-14-01 164, April 2015.

Page 39 of 46

Serial No.15-432 Docket No. 50-280 S$1027 SPTR APPENDIX - STARTUP PHYSICS TEST

SUMMARY

SHEETS Page 40 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Appendix Surry Power Station Unit I Cycle 27 Startup Physics Test Summary Sheet - Formal Tests (Page 1 of 6)

Measurd Value Design~ Criteria A44ceptanlce Cdd Crieria cepac Tno Cita Criteria Met Reviewer ZPTR= ~~~~background < ZPTR <POAH Ysrl:t 1f 6

iOr o badkgroLund *8ra ps N/AK

,..I.OiiIG:Z* amr p 7 POAH=I 2,.a t a"T. empR _N ps-. 6 /,5 ZJ */-NI~ pcm l{(po.- i'p,}Hx 100%<*4.0 %1 " es/*, iJ (meaured reactivity) The allowable nang. Ia set to the larger of (4A¶K g,= £ 9-'/ 6 p'7 the measured results or the pro-critical No I (predicted reaciviy) bencht tJt N/A NIA Pro-cri.tical Bench Test Results

%D= {(pc -.p 1Wp.t} x100% +/-1!D/..le0 Aiowablarng "t~-** acm (Cd)',*= I '72.. 'f ppm (Ce)A~o= 1477 50pp kzC. x (Cs)t.jtol *;1000 pcmn ,. Yes / yea C"/,IO.V 441//

(Adj. To design condi.) &(s*=C~~o C). *CB= 2 -7.530 p!rn/ppm G** No No tITo S 3,S70 pcr/°F #" Yes ... +/- Yea :r 0,

___-______*... pcnVeFi - where: (o*'); 6.0 pcmn9 F COLR3.4] No No l* =-leh== 2 4* N/A Ye N lf.

-,,l,'

Reforences 1.) DNE$-AA, NAF-NCD-4O15, Rev. 1I" 2.) ETE-NAF-2015-0044, Rev. 0 3.) ETE-NAF-.2015-0043, Rev. 0 Page 41 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Appendix Surry Power Station Unit 1 Cycle 27 Startujp Physics Test Summary Sheet - Formal Tests (Page 2 of 6)

Deign

• tne

• Poatr Measured Value Design Criteria Acceptance Criteria Critedia Ciei.e ie Me it eT est Reviewer (Cs~~~s-- ~(C,*)--- i313 +A(C,)t~

• 26 ppm t,/* *,/

3.ilZ ppm *C(n)A~o "-. ppm (from above) N/A N/A '"k (C,),=i$0O,,.1 *26 ppm No C) - fCs)B= *. ppm (czJCd'M -7.60 rnC-- N/A ee Np/Apm*$/'P *~(

l* *;A f cdp *r,-(iA,,)M ((~) 100e pciV N/A No A '!ot/N

• Lpcm Moea..- Ds.o= 43,, pcrn*N Is*-(Is"-- t%. O +/-:15% N/A WA '--

I (lc1 )3= ,C5.. ..... +/-: 16% N/A -- N/A

.12JLL..p<am 100x(Meas. - Dee,)/De.a = o*.~ i ,

• pcm !00x(Meas. - De..)/D = -,04  % N/ANo /Ay  ;/

Is*(Issls)*= la' +/- 15% N/A -

I i lIL.7 pam lO~x(Meaa..s Des.)/Des. =L  % N ,q$ '1r

!Io=(lt=. )

9 J""S7.t.....

1Q1% NA *Ys N/A

• 7.3, porn l00xfMeas. -Des.)IDes.=-I o.  % N !1"K.F References 1.) DNE8-AA*AF-NCD-4015, Rev. I 2.) ETE-NAF-2015-0044, Rev. 0 3.) ET-A-01-03 Rev. 0)

Page 42 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Appendix Surry Power Station Unit I Cycle 27 Startup Physics Test Summary Sheet - Formal Tests (Page 3 of 6)

References !.) DNES-MA-NAF-NCD-.4015, Rev. 1

- 2.) ETE-NAF-2015..0044, Rev. 0 3.) ETE-NAF-2016-0043, Rev. 0 Page 43 of 46

Serial No.15-432 Docket No. 50-280

$1027 SPTR Appendix 2.) ETE-NAF-2015-0044, Rev. 0 3.) ETE..NAF-2015-0043, Rev. 0 Page 44 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Appendix Surry Power Station Unit 1 Cycle 27 Startup Physics Test Summary Sheet - Formal Tests (Page 5 of 6)

Dign A~pac Datel Preparerl Measured Value Design Criteria. Acceptance Criteria Crieria Acdeptance tTime of Rvea Crieti Test Map Po~vr Lewd 1% Full Power) =*

• Max Rhlative Aasnmi Power, %DIFF4Ibl-P)IP

%DF= %r~

~ 1+/-i~t0%fP*. O.9 N/A'JNo Ne NL*clea Enthallpy Riue Hot Channel Factor, FMI*(N)

FAHJJ lN,"/IA Fa&H(N)*t51.56tO.3(1-Pfl (COLR 3.1') j N_____

Totanl Heat Flux Hol Channel Factor, FQ4ZJ PekF()I**Ca[FFZ)s{2.5/IF}K()IHCOLR 3.7] j .- Yes

• No Maximum Podltlve Inoou Quadraunt Power TIW

• VYes References 1.) DNES-AA-NAF-NCD-4015, Rev. 1 2.) ETE-NAF-2015-0044, Rev. 0 3.) ETE-NAF-2015-0043, Rev. 0 Page 45 of 46

Serial No.15-432 Docket No. 50-280

$1C27 SPTR Appendix Surry Power Station Unit 1 Cycle 27 Startup Physics Test ;ummiary Sheet - Formal Tests (Page 6 of 6)

Design . Mt TiefRe'vlaeMr CitCriteria uaiei m r Acceplance Criteria Measured Value - Design Crtteria Iet I Test I..I FTh*I p N/A

• 8~ 'qA*, 240gi A. _____________________ A. 4.-.

References 1.) DNES.AA-NAF-NCD-4015, Rev. I 2.) ETE-NAF-2015-0044, Rev. 0 3,) ETE-NAF-2015-0043, Rev. 0 Page 46 of 46