ML17044A011

From kanterella
Jump to navigation Jump to search
Cycle 28 Startup Physics Test Report
ML17044A011
Person / Time
Site: Surry Dominion icon.png
Issue date: 02/06/2017
From: Huber T
Dominion Resources Services
To:
Office of Nuclear Reactor Regulation, NRC/RGN-II
References
17-017
Download: ML17044A011 (49)
v • d • e


Text

. } .

Dominion Resources Services, Inc~

Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 February 6, 2017

  • United States Nuclear Regulatory Commission Serial No.: 17-017 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 ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNIT 1 CYCLE 28 STARTUP PHYSICS TESTS REPORT As required by Surry Power Station (Surry) Technical Specification 6.6.A.1, enclosed is the Surry Unit 1 Cycle 28 Startup Physics Tests Report. This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 28 on November 10, 2016. 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,

~~T. R. Huber, Director Nuclear Regulatory Affairs Dominion Resources Services, Inc. for Virginia Electric and Power Company

Enclosure:

Surry Unit 1 Cycle 28 Startup Physics Tests Report Commitments made in this letter: None

Serial No.17-017 Docket No. 50-280 Page 2of2 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 Ms. B. L. Mozafari NRC Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 H-12 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.17-017 Docket No. 50-280 Enclosure SURRY UNIT 1 CYCLE 28 STARTUP PHYSICS TESTS REPORT January 2017 Virginia Electric and Power Company (Dominion)

Surry Power Station Unit 1

Serial No.17-017 Docket No. 50-280 Enclosure CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report 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 1of46

Serial No.17-017 Docket No. 50-280 Enclosure TABLE OF CONTENTS Classification/Disclaimer ******<i!****~***************************************************************************************************l Table of Contents .......*...................................................................................................................2 List of Tables ..................................................................................................................................3 List of Figures .......*.................._....................................................................................................... 4 Preface .........................*...................................................................................................................5 Section 1 -- Introduction and Summary .....................................-................................................ 6 Section 2 -- Control Rod Drop Time Measurements ............................................................... 15 Section 3 - Control Rod Bank Worth Measurements ............................................................ 20 Section 4 - Boron Endpoint and Worth Measurements ..*.*............................*......................25 Section 5 -- Temperature Coefficient Measurement ...............................................................28 Section 6 -- Power Distribution Measurements **********~************************************************************30 Section 7 -- Conclusions .............................................................................................................37 Section 8 -- References ............................................................................................................... 39 Appendix - Startup Physics Test Summary Sheets ....*........................................................... 40 Page 2 of 46

Serial No.17-017

'.I Docket No. 50-280 Enclosure LIST OF TABLES Table 1.1 - Chronology- of Tests ********************************************************~***************************************10 Table 2.1 - Hot Rod Drop Time Summary ..................................................................... ~ ........ 16 Table 3.1 - Control Rod Bank Worth Summary .....................................................................22 Table 4.1 - Boron Endpoints Summary .............................................................*..................... 26 Table 4.2 - Boron Worth Coefficient ........................................................................................27 Table 5.1 - Isothermal Temperature Coefficient Summary...................................................29 Table 6.1 - Incore Flux Map Summary ..........*.......................................................................... 32 Table 6.2 - Comparison of Measured Power Distribution Parameters with their Core Operating Limits ............. ~*******~*******************************************************************************33 Table 7.1 - Startup Physics Testing Results Summary ........................................*..................38 Page 3of46

Serial No.17-017

. Docket No. 50-280 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 lncore 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 46.30% Power ..............................................34 Figure 6.2 - Assemblywise Power Distribution 70.04 % Power ..............................................35 Figure 6.3 - Assemblywise Power Distribution 99.80% Power ..............................................36 Page 4 of 46

Serial No.17-017 Docket No. 50-280 Enclosure PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 1 Cycle 28 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. 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 28 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test results, 3) acceptance criteria and whether it was met (if applicable),. 4) date and time of the test, and 5) preparer I reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations performed by Dominion's Nuclear Engineering and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specifications and COLR Limits.

Page 5of46

Serial No.17-017

"' . Docket No. 50-280 Enclosure SECTION 1 - INTRODUCTION AND

SUMMARY

On October 22, 2016, Unit No. 1 of Surry Power Station completed Cycle 27 and began 1

refueling [Ref. 1]. During this refueling, 64 of the 157 fuel assemblies in the core were replaced with fresh Batch Sl/30 assemblies [Ref. 8]. The Surry 1 Cycle 28 (S1C28) core consists of eight sub-batches of fuel: three fresh batches (Sl/30A, Sl/30B and Sl/30C), three once-burned batches (Sl/29A, Sl/29B and Sl/29C), and two twice-burned batches (Sl/28A and Sl/28C).

SlC28 utilizes the 15x15 Upgrade (Upgrade) Fuel Design for all but eight of the fuel assemblies.

The remaining eight assemblies are Lead Test Assemblies (LTAs) of the AREVA AGORA-SA-I (AGORA) design that are being loaded for their first cycle of irradiation [Ref. l].

Surry 1 batches 28, 29, 30A and 30B are of the Westinghouse Upgrade fuel design, which includes ZIRLO (I-spring) structural mid grids with balanced mixing vane pattern, three ZIRLO Intermediate Flow Mixing *(IFM) grids, "tube-in-tube" guide thimbles, 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, Robust Protective Grids (RPG) and

\ .

modified Debris Filter Bottom Nozzles (mDFBN). In addition, Sµrry 1 batches 29, 30A and 30B utilize the Westinghouse Integral Nozzle (WIN) top nozzle design [Ref. 8].

The fresh Upgrade fuel uses Westinghouse's Integral Fuel Burnable Absorber (IFBA) product as the burnable absorber. The IFBA design involves the application of a thin coating of ZrB2 on the fuel pellet surface during fabrication. Pellets with the IFBA coating are placed in specific symmetric patterns in each fresh assembly, typically affecting from 16 to 148 rods per assembly. The top and bottom 6 inches of the fuel pellet stack in the IFBA rods will contain pellets that have no IFBA coating, and have a hole in the center (annular). This additional void space helps accommodate the helium gas that accumulates from neutron absorption in ZrB 2 .

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. SJ.

Page 6of46

Serial No.17-017 Docket No. 50-280 Enclosure Surry 1 batch 30C is of the AREVA AGORA fuel design. The top grids of the assemblies are a High Thermal Performance (HTP) design fabricated from MS material. The mid-grids are AFA-3G vaned mixing grids, which are bimetallic grids utilizing MS strips and Inconel 718 springs. The mid-span mixing grids (MSMG) are MS vaned mixing grids placed on spans 3 through S on the assembly. The MSMG are similar to the IFM grids used in the other batches of this cycle and are located at approximately the same elevations as the IFMs. The bottom grid is an Inconel 718 HMP (High Mechanical Performance) grid. The fuel rod cladding is composed of MS material, and the guide tubes and instrument tubes are composed of Q12 (zirconium alloy) and are of the MONOBLOC design [Ref. 1].

The AREVA AGORA LTAs utilize gadolinia (Gd203) as a burnable poison integral to the fuel. Each LTA contains 28 gadolinia rods, twelve at 12% and sixteen at 6%, with 6-inch cutback regions at the top and bottom of the fuel. The cutback regions are the same enrichment as non-gadolinia rocis. The gadonlinia rods are subject to the S:l enrichment penalty (S%

reduction in U-23S for each weight percent of gadolinia) from the nominal enrichment.

Cycle 28 loads the secondary source assemblies (SSAs) in core locations H04 and H12 to improve Source Range Detector respons~. 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 S1C28 .. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 28 core.

The SI C28 full core loading plan [Ref. 8 and Ref. I i] is shown in Figure I. I, and the beginning of cycle fuel assembly burnups [Ref. 6] are showr,i in Figure I .2. The incore moveable detector locations used for the flux map analyses [Ref. 7] are identified in Figure 1.3. Figure I .4 identifies the location and number of control rods in the Cycle 28 core [Ref. I].

According to the Startup Physics logs, the Cycle 28 core achieved initial criticality on November 10, 2016 at lS:SO [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 Page 7 of 46

Serial No.17-017 Docket No. 50-280 Enclosure used for S 1C28 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 1.68 second 15x15 Upgrade Fuel administrative limit

[Ref. 1O]. All control rods are located in Upgrade fuel assemblies.

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 -1.9% of the design prediction. The referei{ce bank (Control Bank B) worth was within

-0.3% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within -3.6% of the design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within -6 pcm of the design prediction.

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

Measured critical boron concentrations for two control bank configurations, all rods out (ARO) and Reference Bank (B-bank) in, were within the design tolerances and the Technical Specification criterion [Ref. 4] that the overall core reactivity balance shall be within +/- 1% ~

of the design prediction. The boron worth coefficient measurement (the differential boron worth, DBW) was within+ 1.3% of the design prediction, which is within the design tolerance of+/- 10%.

The measured isothermal temperature coefficient (ITC) for the ARO configuration was within +0.293 pcm/°F of the design prediction. This result is within the design tolerance of +/-2.0 pcml°F [Ref. 14].

The zero power physics testing- results were all within the criteria established in Reference 18 permitting the first flux map to be performed up to 50% power (versus 30% power if the criteria were not met).

Page 8 of 46

\

Serial No.17-017 Docket No. 50-280 Enclosure Core power distributions were within established design tolerances. The measured assembly power distributions were within +/-5.3% of the design predictions, where a 5.3%

maximum difference occurred in the 99.80% 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. 8].

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

.:s 1.02).

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

[Ref. 4]. The total RCS Flow at nominal conditions was measured as 289,888 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 46

Serial No.17-017 Docket No. 50-280 Enclosure Table 1.1 SURRY UNIT 1-CYCLE28 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow11 11/09/16 21:49 HSD 1-NPT-RX-014 Reactivity Computer Checkout 11/10/16 16:30 HZP 1-NPT-RX-008 Boron Endpoint - ARO 11/10/16 16:30 HZP l-NPT-RX-008 Zero Power Testing Range 11/10/16 16:30 HZP 1-NPT-RX-008 Boron Worth Coefficient 11/10/16 21:35 HZP 1-NPT-RX-008 Temperature Coefficient - ARO 11/10/16 16:54 HZP 1-NPT-RX-008 BankB Worth 11/10/16 18:02 HZP 1-NPT-RX-008 Boron Endpoint - B in 11110/16 18:04 HZP 1-NPT-RX-008 Bank A Worth - Rod Swap 11/10/16 20:19 HZP 1-NPT-RX-008 Bank C Worth - Rod Swap 11/10/16 20:19 HZP 1-NPT-RX-008 Bank SA Worth- Rod Swap 11/10/16 20:19 HZP 1-NPT-RX-008 Bank D Worth - Rod Swap 11/10/16 20:19 HZP 1-NPT-RX-008 Bank SB Worth - Rod Swap 11/10/16 20:19 HZP 1-NPT-RX-008 Total Rod Worth 11/10/16 20:19 HZP 1-NPT-RX-008 Flux Map - less than 50% Power* 11/11/16 21:25 46.30% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT-RX-005 1-GEP-RX-001 Flux Map - 65% - 75% Power 11/12/16 11:02 70.04% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration 1-NPT-RX-005 1-GEP-RX-001 Flux Map - 95% - 100% Power 11/15/16 08:44 99.80% 1-NPT-RX-002 Peaking Factor Verification 1-NPT-RX-008

& Power Range Calibration l:.NPT-RX-005 1-GEP-RX-001 RCS Flow Measurement 11114/16 15:24 HFP 1-NPT-RX-009

  1. The time indicated is for the first rod drop, for all rods except N-07 (SA-B~). A second drop was performed on 11/10/16 at 02:12 for only SA-Bank.
  • 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).

Page 10 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 1.1 SURRY UNIT 1-CYCLE28 CORE LOADING MAP S!JR!n' UN'J.'l' 1 ~ CYCW:: 28 l:'(Jhf, CCll~ll! f,(')J\:fll:ltlQ !>Li\l\l R.WIS:i"ON NO. 0 WP-U~~l:Ai' l'. fi \: t> ll l' G li J l( J, M li  !' R 15 3Jll .24.7 2:M l

ooc llCC RaC l{

Hell  :>49 43? M6 434  :>>n U.t K<ll\tl'H !WC wee u

-~9 429 443 401 359 409 M?; .431 .. 252 W,:>; R;;;<; <>~l¢ nee t<.C'G Ii ll!i6 u:: 150 Bil lJl;. 30'1 3-0 lS!! 4!111 4:t?3 !tS~

~ W.:."C tl

~$,7 .1:rn 45J l()4 :rn~

"'~ )j;). )t;O~ ws JQ(, *M 4li> iMl 1-a'C ECC::  !'.CC ll't.'C llCC m:c i\l:."C lli 1H 4!iP 111~ ),;(\ 4!!11 3jiji lU l-19 4ll.2 n.i j~i4 ii.lit ll;\i u:c  !\CC lli.U )%,.~

z:n. ..t::lll 4tl~ Jill ,\.t.'t.l :ii.ii :i.ss 4£::1 .)GO :n1 At:l2 ;i:rn 41.i: J!;);) 2::2

~  !<\!'<; gcq w;x; 2~;{)1:

14$ ~o!l; 31.b io? 41l::l 3M .:,;>2 323 354 ;as .. s Nl 32'1 :lC!l ):t;! 4U

~ ROC ~ l1W 1

2lll {.36 410 327 AGG SH 162 454 .'UiO 31? MS ;16 458 4tll  :'110 i<ec 1U~C' ~ l'l:.'C R{..'t! noc R~

J; M:t n2 3H l4l 4(11 311.! uo HS 404 33) l5~ 44$ 34~

R<:-'l;: nee

'5 2iii:) ;i.m; 4.SU ltll ))1 NJ1 ;w; /1fH 1~2 J03 45'1 {l(I :isa

!!QC .Ree' SStl. :KCC RC<:'

4 t.51 420 4:f.1~ H1 JU. !i.l. :n11 )51 46(1 4::17 U!i~

J
~P~ .. :©W.J.t;.;.'J.L~~.. ~)~.:. Rf..'X: f,t.'C 3

1&.';z'*.. [.'t!J,,h ~ttftZfit l;"t.r!WV11 £.?Oft 253 42l 44~ 4{)(\ S1ll 4U 441. 4~4 ~!i!i:

~* t#X'!l11lAM :lt:l llf~Cf! Af.~fl,~t."f  !-\\.'!;' l\l:.'C F'-'C 2 241  :;~s 4.la !41 >!l5 :HS .24.2 n:; 24$ 211 A'IA p,.,,,,,..,,. ay,  ;:JC,, 5. ~~

1', 1L !'Mlii:

lll>t" 'Sf:t-."i lt(r J?e?:e: k.[ i {i!:>

l\'.W.i.'1'100 l'q1 ~ ~~ oata' [:{!s fll

~J:'4W'~1 ~vi~~

u.~

A.,, R. Nicho.l~O'~

H<>IW' S'}'4t. /It. Pirwrw....e (ly' ..,.,......,,_...;..-J..----

M~

JN!t.,, <tt, Lr' Page 11 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 1.2 SURRY UNIT 1 - CYCLE 28 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 34.771 39.661 34.721 I MEASURED I I 34.751 39.451 34.731 I PREDICTED f I 37.831 11.911 0.001 0.001 0.001 10.031 38.26f I 38.09f 17.85f a.oaf a.oaf a.oaf 17.86f 38.12f I 39.52f a.oaf a.oaf a.oaf 19.52f a.oaf a.oaf a.oaf 38.99f f 39.18f a.oaf* a.oaf a.oaf 19.36f a.oaf a.oaf 0.001 39.151 I 39.28f a.oaf 0.001 17.96f 20.501 21.91f 20.751 1?.85f 0.001 0.001 39.23f I 39.141 0.001 a.oaf 17.961 20.591 21.74f 20.611 17.901 a.oaf 0.001 39.171 I 38.991 0.001 a.oaf 22.011 21.861 0.001 21.721 a.oaf 21.761 21.591 0.001 0.001 39.591 I 38.921 a.oaf a.oaf 21.94f 21.661 a.oaf 21.791 0.001 21.67f 21.86f 0.001 0.001 39.38f f 18.16f O.OOl 17.79f 21.581 a.oaf 22.171 22.191 22.091 0.001 21.47118.091 O.OOl 17.861 I 17.851 0.001 17.941 21.651 0.001 22.041 21.92f 22.091 0.001 21.651 18.00I 0.001 17.851 I 34.751 0.001 0.001 20.491 0.001 22.031 18.451 0.001 18.361 21.841 0.001 20.511 0.001 0.001 34.97f f 34.73f 0.001 0.001 20.581 0.001 22.021 10.311 0.001 10.311 21.971 0.001 20.561 0.001 0.001 34.761 I 39.831 0.001 19.631 2i.011 21.901 2t.87f a.oaf 19.741 0.001 2t.02f 22.1of 21.96f 19.29f o.oof 39.37f I 39.36f o.oof 19.411 2i.101 2t.06I 2i.92f 0.001 19.741 a.oaf 2t.92f 21.061 2i.10f 19.41f 0.001 39.361 f 34.98f o.oof o.oof 20.54f o.oof 21.641 18.39f 0.001 18.23f 22.04f o.oof 2t.05f o.oof 0.001 34.621 I 34.76f o.oof o.oof 20.561 o.oof 21.97f 18.311 0.001 18.31f 22.021 o.oof 20.57f o.oof o.oof 34.741 10 I 17.73f o.oof 17.981 21.84f o.oof 22.131 22.021 22.20f o.oof 21.121 10.011 o.oof 17.79f 10 f 17.851 0.001 10.oof 21.65f o.oof *22.09f 21.921 22.04f o.oof 21.66f 17.941 0.001 17.85f 11 I 39.50f 0.001 o.oof 21.011 21.55f 0.001 21.791 o.oof 21.96f 22.031 o.oof o.oof 38.90f 11 f 39.38f o.oof o.oof 21.861 21.671 0.001 21.791 0.001 21.66f 21.94f o.oof o.oof 38.92f 12 I 39.481 0.001 0.001 17.861 2t.05f 21.661 20.561 10.211 0.001 o.oof 39.38f 12 I 39.17f 0.001 o.oof 17.901 20.61f 21.74f 20.591 17.96f o.oof o.oof 39.14f 13 I 38.921 o.oof 0.001 0.001 19.301 0.001 o.oof o.oof 39.17f 13 I 39.151 0.001 0.001 0.001 19.36f o.oof o.oof 0.001 39.18f 14 f 38.o9f 11.901 o.oof 0.001 0.001 17.98f 38.19f 14 I 38.llf 17.85f a.oaf a.oaf 0.001 17.85f 38.09f 15 I 34.581 39.88f 34.52f 15 I 34.73f 39.451 34.75f Page 12 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 1.3 SURRY UNIT 1 - CYCLE 28 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R p N M L K J H G F E D c B A MD 2

MD 3

MD MD MD MD

+ 4 MD MD MD 5

MD MD MD MD MD MD 6

MD MD MD

+ * + + 7 MD MD MD MD MD 8

MD MD MD MD MD MD 9

MD MD MD MD 10 MD MD MD MD 11 MD MD MD MD 12 MD MD MD MD

+ 13 MD MD 14 MD MD

"'\

15 MD MD - Moveable Detector

+ - Locations Not Used For Any Map

  • -*Location G7 Used as Calibration Thimble Due to Location J7 Being Unavailable Following Replacement Page 13 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 1.4 SURRY UNIT 1 - CYCLE 28 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 14of46

Serial No.17-017 Docket No. 50-280 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 1-NPT-RX-O 14. This verified that the time to entry of a rod into the dashpot region was less than or equfil to the maximum allowed by Technical Specification 3.12.C.1 [Ref. 4].

Surry Unit 1 Cycle 28 used the Rod Drop Measurement Instrument (RDMI) to gather and analyze the rod drop data [Ref. 12]. The methodology acquires data using the secondary RPI coil terminals (/3 & 14) on the Computer Enhanced Rod Position Indication (CERPI) racks for each rod. Data is immediately saved to a comma-separated value file.

It is noted that rods were dropped twice due to an issue with rod N-07 (SA-Bank); the first drop was for all rods except N-07 and the second drop was for only SA-Bank. Prior to the first drop, N-07 was noted ~o be on the bottom of the core due to a blown lift coil fuse. After this fuse was replaced, SA-Bank was dropped in order to obtain the drop time for N-07. For SA-Bank, the reported rod drop times for all rods, except N-07, were from the first drop as the second drop was for evaluation of N-07. For the other SA-Bank rods, it was noted that the second drop had a similar shape and time when compared to the first drop with an increased signal magnitude.

A typical rod drop trace for S 1C28 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 18-28. Technical Specification 3.12.C.1 [Ref. 4] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. It is noted that the AREVA fuel assemblies are not loaded in rodded core locations. These test results satisfied this Technical Specification limit, as well as the 15x15 Upgrade 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 fastest and average rod drop times did not change from S1C27 but the slowest rod time increased by 0.01 seconds.

Page 15 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Table 2.1 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD A VERAGE TIME P-08 1.46 sec. K-04 1.31 sec 1.36 sec.*

Page 16 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 2.1 SURRY UNIT 1-CYCLE28 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE DROP DATA : G9 (SBB) 5 4.5 4

3.5 3

2,S 2

C.i.5 Q)

Cl ro 0

1 0.5 -

0

-0.5

-1 I

I

-1.5 I

I I

-2 I

I

-2.5 --1 t*.

l --

0 1 2 3 4 S1C28 Time (Sec)

Page 17 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 2.2 SURRY UNIT I -CYCLE 28 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

1.34 1.33 1.35 3

1.34 1.36 4

1.35 1.31 1.34 1.39 5

1.35 1.35 6

1.34 1.34 1.34 1.35 1.36 1.35 1.44 7

1.33 1.36 1.34 1.34 8

1.46 1.37 1.42 1.37 1.37 1.34 1.37 9

1.36 10 1.36 1.33 1.34 1.34 1.37 1.36 1.37 11 1.35 1.36 12 1.32 1.34 1.34 1.40 13 1.36 1.36 14 1.39 1.34 1.40 15

~ ==> Rod drop time to dashpot entry (sec.)

Page 18 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 2.3 SURRY UNIT 1-CYCLE28 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 2.5 2.4 Tech

' "' ,J"""'

I on Lim i I 2.4 SE conds I Ii 2.3 II 2.2 I I II 2.1 I I I

I 2 I  !

I I I - Slowest Rod lime

...... 1.9 I I - - - Fastest Rod lime

--..**-- Average lime

~ I I

.!E... I 41 E

II I

I i= 1.8 I I I l~xlS Upgrade ~dminis1 ative I imit, 1. J8 seco 1ds 1.7 1.6

I

--r-r- --- --- --**-- *--

I I I 1.5 I I I ,.--

1.4 I

I

_1- I --..J'

/

..-- T 1.3 rI  !

__ .... ....., ~

r---~v .._____ ~/

-11 1.2 1~1 I 1.1 I

I 18 19 20 21 22 23 24 25 26 27 28 Cycle Page 19 of 46

Serial No.17-017 Docket No. 50-280 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. 2]. The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 28, 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 S 1C28 startup physics testing campaign used 2 steps withdrawn for all conditions requiring control rods to be manually fully inserted.

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

Test bank swaps proceed in sequential order from the bank with the smallest worth to the bank with the largest worth. The second test bank should have a predicted worth higher than the first bank in order to ensure the first bank will be moved fully out before the second bank is fully inserted. The rod swap maneuver was performed by withdrawing the previous test bank (or reference bank for the first maneuver) several steps and then inserting the next test bank to balance the reactivity of the bank withdrawal. This sequence was repeated until the previous test Page 20 of 46

Serial No.17-017 Docket No. 50-280 Enclosure 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 provided in Table 3 .1. As shown in this table and the Startup Physics Test Summary Sheets 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

-1.9% 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 46

Serial No.17-017 Docket No. 50-280 Enclosure Table 3.1 SURRY UNIT 1-CYCLE 28 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE(%)

BANK (PCM) (PCM) (M-P)/P X 100 B - Reference 1543.6 1549.0 -0.3%

A 338.4 343 .9 -6 pcm*

c 873.5 905.9 -3 .6%

SA 918.9 919.4 -0.1%

D 989.5 1018.5 -2.8%

SB 1120.5 1158.2 -3.3%

Total Bank Worth 5784.4 5894.9 -1.9%

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

Page 22 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 3.1 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1800 --*- - ----- --- - *---*-**

1600 L.11

-...._"'-.. I I'..

~

1400

~

\

\..\

\'

~

1200

"\\

\'~\

\ii

'.1-lS 1000 \

~ \II

--+-- Measured

\'

~ - Predicted

\'i

~ \

\.

~I..

\\

600 ~ '

l\i

\:: ..I\\.

~I\

400 I'\'

'I\\

'I'

~

I.

200 'l ~

~

'1.

~ ...

'I:--...

0 100 150 200

- 250 0 50 Bank Position (steps)

Page 23 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 3.2 SURRY UNIT I -CYCLE 28 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 14.0 II')

12.0 * \

It 1

10.0

  • 1 II.

Pi Q)

I~

.jJ Ill

\

a ti

~

~

Pi ~

8.0

~

.jJ

~

M \_

~ I * ~.

--+- Measured "d

0 er: I 1-

Predicted

~ ty 111-l ...... Lo.

r-i Id

.jJ 6.0 I I "" r.-::: ~ I.A ~

i:::

Q)

M

\

Q) \ \

~

~

i:i I I

  • 11.-

4.0 I '\

-} 1 j

1 I 2.0

)l I

I I JI 11 0.0 0 50 100 150 200 250 Bank Position (steps)

Page 24 of 46

Serial No.17-017 Docket No. 50-280 Enclosure SECTION 4 - BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical .at hot zero power (HZP), reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position and moderator temperature, as necessary.

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

Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, the value 'of the DBW over the range of boron endpoint concentr~tions 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 25of46

Serial No.17-017 Docket No. 50-280 Enclosure Table 4.1 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

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

ARO 1535.6 1546.0 -10.4 B Bank In 1336.0 1332.6* +3.4

  • 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 26 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Table 4.2 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

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

-7.73 -7.63 1.3%

Page 27 of 46

Serial No.17-017 Docket No. 50-280 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 3.00 °F, followed by the RCS cool down of 3.04 °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 iri 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 in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of +/-2 pcm/°F. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -2.325 pcm!°F, a predicted* doppler temperature coefficient (DTC) of -1.83 pcm/ °F, and a measurement uncertainty of +0.5 pcm/ °F, is 0.005 pcm/ °F. It thus satisfies the COLR criteria

[Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pcm/°F.

Page 28of46

Serial No.17-017 Docket No. 50-280 Enclosure Table 5.1 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

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

POSITION (STEPS)

LOWER UPPER LIMIT LIMIT CONCENTRATION (ppm)

HEAT- - COOL-UP T

DOWN MEAS A VG.

PRED

--~*------

DIFFER (M-P)

I D/200 546.17 549.21 1535.6 -2.522 -2.128 I -2.325 -2.619 0.293 I

Page 29 of 46

Serial No.17-017 Docket No. 50-280 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 that traverse fuel assembly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available locations monitored by the moveable detectors for Cycle 28 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. 3, Ref. 15]. CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core. The CECOR GUI (Ref. 16) was used as an interface to CEBRZ and CECOR.

A list of the full-core flux maps [Ref. 7] taken during the startup test program and the measured values of the important power distribution parameters are provided 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 46.30% 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 70.04% and 99.80% power, respectively, with different control rod configurations.

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

given in Figures 6.2 and 6.3.

The radial power distributions for the maps given in Figures 6.1, 6.2 and 6.3 show the measured relative assembly power values deviated from the design predictions by at most +/-4.1 %

in the 46.30% power map, +/-3.0% in the 70.04% power map, and +/-5.3%.in the 99.80% power map. The maximum average quadrant power tilts for the three maps were +0.78%, +0.54% and

+0.41 %, respectively. These power tilts are within the design tolerance of2%.

Page 30 of 46

Serial No.17-017 Docket No. 50-280 Enclosure 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 28.

Page 31 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Table 6.1 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

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

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

MTU

(%)

sy !Point Point! z I

Steps As iAxial FQ(z) Assyr;~- -~ia11-;:--- . Max Loe (%) Thimbles Low Power 1 11/11/16 4.5 46.30 185 N-10 I 25 2.092 N-10 11.539 25 11.265 1.00781 NE 4.339 45 Int. Power (4) 2 11/12/16 17.5 70.04 I

201 N-10 i 31 I 1.936 N-10 uo5 19 I1.199 l.0054i NE I

3.531 45 Hot Full Power 3 11/15/16 116.9 99.80 227 N-10 I 32 1.866 D-6 11.480 29 11.162 l.004li NE 0.990 45 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 of8%.

(2) F:ii 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 32of46

Serial No.17-017 Docket No. 50-280 Enclosure Table 6.2 SURRY UNIT 1 - CYCLE 28 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 2.092

- ..--*--*-H-*--HO **--*..---*--*--*--- _,,,,,_, ___ __,,

5.000

,,, ___ 25 58.2

- - - - - -- -1.539 1.898 18.9 2

1.936 3.569 31 45.8

-- 1.505 1.782 15.5 3 1.866 2.505 32 25.5 1.480 1.636 9.5 The measured Fq(Z) hot channel factors include 8% total uncertainty. Measured F~ data includes no uncertainty.

  • Margin (%) = 1OO*(Limit - Meas.) I Limit Page 33 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 6.1 -ASSEMBLYWISE POWER DISTRIBUTION 46.30% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value == Analytical, bottom value = % Delta i Delta = (M - A)xlOO/A R p N M L K J H G F E D c B A I 0.2621 0.2991 0.2601 1 I 0.2611 o.3001 0.2591 I o.371 -0.411 o.5ol I o.3491 0.1201 o.na1 0.9011 0.9211 0.1251 o.3521 I o.34BI 0.1101 o.9251 o.9011 o.9231 0.1101 o.34BI I 0.111 o.351 o.361 0.021 o.451 i.o41 i.241 I o.4231 i.0511 1.2561 1.2341 i.2311 i.2311 i.2651 i.o6al o.4241 I o.4201 1.0561 i.2531i.22511.2321 i.2251 i.2541 i.0511 o.4211 I o.651 0.011 0.21 o.731 o.371 o.461 o.a41 i.o91 o.731 I o.4321 i.o96I i.2901 1.3841 i.2311 1.1451 i.2421 1.4031 i.3201 1.1141 o.4311 I o.4211 i.0011 i.3001 i.3001 i.2311 i.1501 1.2371 1.3901 i.3021 i.0001 o.4201 I 2.521 o.a31 -0.151 -0.251 -o.471 -o.451 o.391 o.951 1.351 2.381 2.101 I o.35BI i.1021 i.3201 i.2611 i.2391 i.0021 i.0011 1.0201 1.2611 i.2001 1.3531 i.0051 o.3481 I o.3481 i.o59I i.3031 i.2601 i.2401 1.0291 i.o93I i.o3ol i.2491 i.2691 i.3021 1.0571 o.3441 I 2.051 4.101 1.201 -0.011 -0.741 -2.621 -1.051 -0.191 o.941 1.471 3.911 2.691 1.091 I 0.1301 i.2101 i.4091 i.2611 1.2411 i.1221 i.0011 i.1331 i.2631 i.2691 1.4231 i.2031 o.7331 I 0.1221 i.2611 1.3961 i.2521 i.2521 1.1371 i.1031 1.1361 i.2521 i.2521 1.3941 i.2601 0.1211 I i.161 1.341 o.911 0.101 -0.001 -1.361 -1.451 -0.201 o.9ol i.321 2.001 i.031 1.641 I 0.2621 o.9321 i.2331 i.2561 1.0361 1.1341 i.2191 i.1161 i.2201 i.1301 l.o4ol i.2651 i.2511 o.9461 0.2601 1 I 0.2621 o.9321 1.2381 1.2531 i.o3al i.1411 i.2321 1.1311 1.2321 1.1411 i.o37I i.2521 i.2301 o.9331 0.2641 I 0.031 0.001 -0.381 0.241 -0.211 -0.631 -1.071 -1.321 -0.991 -0.251 0.261 1.051 1.081 1.351 1.361 I o.3031 o.9141 i.2431 i.1901 i.1001 i.1011 i.1191 i.1051 i.1101 i.0001 i.o99I i.1901 i.2531 o.93ol o.3001 a I o.3041 o.9111 i.2491 i.1901 i.1051 i.1001 i.1331 i.1221 i.1331 i.1001 i.1051 i.1901 i.2491 o.9111 o.3041 I -0.311 -0.311 -0.511 0.041 -0.491 -0.641 -1.211 -1.531 -2.041 -1.811 -0.581 0.021 0.351 1.451 1.471 I 0.2651 o.9411 i.2501 i.2621 i.0401 i.1361 i.2191 i.1001 i.1911 i.1241 i.0251 1.2421 i.2331 o.9331 0.2661 9 I 0.2641 o.9331 i.2301 1.2531 i.0311 i.1421 i.2321 i.1311 i.2321 1.1411 i.0301 1.2531 i.2301 o.9321 0.2621 I 0.521 0.821 0.951 0.701 0.331 -0.531 -1.081 -2.051 -3.291 -1.461 -1.221 -0.861 -0.421 0.151 1.561 I o.7361 i.2911 1.4101 1.2551 i.2421 i.1211 i.0021 i.1101 i.2221 i.2311 1.3671 1.2471 0.1151 lo I 0.1211 i.2601 1.3941 i.2521 i.2521 1.1361 i.1031 i.1311 1.2521 i.2521 1.3961 1.2611 0.1221

  • I 2.111 2.901 i.101 0.211 -o.nl -0.021 -1.931 -2.381 -2.371 -i.211 -2.001 -1.0BI -0.901 I o.3511 i.0141 1.3111 i.2601 1.2401 i.0121 i.o63I i.0061 i.2131 i.2151 i.2911 i.o53I o.3451 11 I o.3441 i.0511 i.3021 1.2691 1.2491 i.0301 i.o93I i.0291 1.2481 i.2601 i.3031 i.o59I o.34al I 1.891 1.651 0.681 -0.061 -0.731 -1.741 -2.711 -2.261 -2.771 0.531 -0.481 -0.581 -0.761 I o.4231 i.0091 1.2961 i.3101 1.2141 1.1341 i.2291 1.3851 1.3061 i.o95I o.4231 12 I o.4201 i.0001 i.3021 1.3901 1.2371 i.1501 i.2311 i.3001 i.3001 i.0011 o.4211 I 0.611 0.111 -o.471 -0.901 -i.031 -1.391 -o.661 -0.251 o.461 0.141 o.401 I o.4201 1.0511 1.2441 i.2121 i.2211 i.2321 i.2151 i.0611 o.4241 13 I o.4211 1.0571 1.2541 i.2251 i.2321 1.2251 1.2531 i.o56I o.4201 I -0.201 -0.551 -0.831 -1.031 -0.421 0.561 1.781 1.081 0.991 I o.3461 0.1131 o.9161 o.9011 o.9441 0.1321 o.3531 14 I o.34BI 0.1101 o.9231 o.9011 o.9251 0.1101 o.3481 I -o.451 -0.14 -0.121 -0.031 2.021 i.901 i.311 I 0.2551 o.3011 0.2661 15 I 0.2591 o.3001 0.2611 I -1.471 0.231 i.101 AVERAGE ABSOLUTE PERCENT DIFFERENCE = 1.0 STANDARD DEVIATION 0. 807 Summary:

Map No: Sl-28-01 Date: 11111/2016 Power: 46.30%

Control Rod Position: Fo(Z) = 2.092 QPTR: 1.0004 1.0078 D Bank at 185 Steps pN = 1.539 0.9979 0.9939 Ml Fz = 1.265 Axial Offset(%)= +4.339 Bumup = 4.5 MWD/MTU Page 34 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 6.2 - ASSEMBL YWISE POWER DISTRIBUTION 70.04% 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 0.2131 o.3131 0.2101 I 0.2141 o.3101 0.2121 I -o.351 -1.661 -0.611 I o.3541 0.1241 o.9361 o.9331 o.9311 0.1221 o.3541 I o.3531 o.7241 o.9371 o.9401 o.9361 0.1231 o.3541 I 0.231 0.001 -0.121 -0.141 -o.521 -0.201 -0.031 I o.4241 t.0471 i.2301 i.2221 i.2221 1.2141 i.2301 i.o4BI o.4241 I o.4231 t.o45I i.2301 i.2191 i.2311 i.2191 i.2301 i.o46I o.4241 I 0.201 0.101 0.001 o.241 -0.111 -o.411 -0.021 0.211 -0.041 I 0.4311 1.0BOI 1.2831 1.3621 1.2211 1.1401 1.2271 1.3711 1.2861 1.0911 0.4311 4 I o.4241 i.0741 i.2191 t.3651 1.2211 i.1451 i.2201 1.3671 i.2001 i.0151 o.4241 I 1.651 0.581 0.301 -0.lBI -0.491 -0.471 -0.0BI 0.321 0.481 1.491 1.721 I o.3591 i.0151 i.2001 1.2451 t.2361 i.0121 i.0091 t.0331 1.2561 i.2591 i.3191 t.0671 o.3491 I o.3531 i.o4al i.2011 t.2541 t.2451 i.o35I i.0901 i.o35I 1.2461 i.2561 i.2001 i.o46I o.3491 I 1.721 2.611 0.551 -0.751 -0.731 -2.231 -0.851 -0.161 0.761 0.261 3.021 2.001 0.091 I o.7311 i.2521 1.3781 t.2541 i.2141 i.1301 i.1021 i.1521 i.3011 t.2651 t.3951 i.2621 o.7351 I 0.1211 1.2441 1.3121 1.2491 1.2011 1.1491 1.1121 l.14BI 1.2011 1.2491 1.3101 1.2431 0.1261 I 0.511 0.671 0.451 0.421 -0.551 -0.931 -0.931 0.351 2.041 1.261 1.791 1.541 1.221 I 0.2131 o.94ol i.2231 i.2431 i.0411 t.1491 i.2311 i.1301 t.2361 i.1501 i.0411 i.2561 t.2451 o.9541 0.2191 1 I 0.2141 o.9431 i.2301 i.2421 i.o43I i.1521 i.2391 i.1391 i.2391 1.1531 i.0421 i.2411 i.2301 o.9441 0.2161 I -0.401 -0.271 -0.571 0.041 -0.201 -0.281 -0.621 -0.751 -0.251 0.431 0.481 1.191 1.231 1.101 1.131 I o.3161 o.9441 i.2301 i.1041 1.1091 t.1141 i.1331 i.1201 i.1211 i.1031 1.1001 i.1911* 1.2621 o.9561 o.3231 a I o.3211 o.94BI i.2411 i.1041 1.1091 t.1161 i.1411 i.1301 i.1411 i.1161 i.1091 i.1041 i.2461 o.94BI 0.3211 I -1.661 -o.391 -0.101 0.031 0.031 -0.211 -o.741 -o.911 -i.221 -i.111 -0.091 o.611 1.311 o.B61 o.561 I 0.2161 o.9491 i.2301 i.2491 i.0441 i.1521 i.2321 i.1241 i.2151 1.1431 1.0361 1.2411 1.2331 o.9451 0.2131 9 I 0.2161 o.9441 i.2301 i.2411 i.0421 1.1531 i.2391 i.1391 i.2391 i.1521 i.o43I i.2421 i.2301 o.9431 0.2141 I 0.171 0.531 0.681 0.641 0.221 -0.111 -0.551 -1.291 -1.901 -0.BOI -0.691 -0.101 0.221 0.221 -0.201 I o.13al 1.2131 l.3B41 1.2541 1.2101 1.1451 1.0961 1.1311 1.2631 1.2411 1.3601 1.2391 0.1241 10 I 0.1261 i.2431 i.3101 i.2491 i.2011 t.14BI i.1121 t.1491 i.2011 i.2491 t.3721 t.2441 0.1211 I 1.651 2.431 1.021 0.361 -0.271 -0.251 -1.441 -1.531 -1.391 -0.671 -0.BBI -0.371 -0.351 I o.3541 i.o59I i.2011 l.25BI i.2401 i.0191 i.0611 i.0161 i.2221 i.2551 i.2191 i.0441 o.3521 11 I o.3491 i.o46I i.2001 1.2561 1.2461 i.o3sl i.o9BI i.o35I t.2461 1.2541 i.2011 i.o4BI o.3531 I 1.491 1.221 0.541 0.141 -0.461 -1.531 -2.BOI -1.861 -1.961 0.061 -0.161 -0.341 -0.371 I o.4211 i.0141 i.2141 1.3551 i.2061 t.1311 i.2231 1.3691 1.2861 i.o85I o.4201 12 I o.4241 i.0151 i.2901 1.3671 i.2201 t.1451 i.2211 1.3651 i.2191 i.0141 o.4241 I -0.651 -0.111 -0.441" -0.851 -1.781 -1.261 -0.361 0.261 0.571 1.021 -0.881 I o.4231 i.o39I i.2211 i.2061 i.2211 i.2211 t.2691 i.0611 o.4291 13 I o.4241 i.o46I i.2301 i.2191 i.2311 i.2191 i.2301 i.o45I o.4231 I -0.211 -o.651 -0.871 -1.051 -0.351 o.671 2.511 1.561 t.421 I o.3491 0.1111 o.9281 o.9391 o.95ol 0.1381 o.36ol 14 I o.3541 o.7231 o.9361 o.9391 o.9371 0.1241 o.3531 I -t.411 -0.821 -0.021 -0.021 1.341 2.001 1.881 I 0.2611 o.3111 0.2111 15 I 0.2121 o.3101 0.2141 I -i.121 -0.231 1.111 AVERAGE ABSOLUTE PERCENT DIFFERENCE= 0.8 STANDARD DEVIATION 0

  • 65 5 Summary:

Map No: Sl-28-02 Date: 11/12/2016 Power: 70.04%

Control Rod Position: F0 (z) = 1.936 QPTR: 0.9987 1.0054 D Bank at 201 Steps pNt.11 = 1.505 0.9979 0.9980 Fz = 1.199 Axial Offset(%)= +3.531 Bumup = 17.5 MWD/MTU Page 35 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Figure 6.3 - ASSEMBL YWISE POWER DISTRIBUTION 99.80% POWER ASSEMBLY RELATIVE POWER FRACTIONS Top value = Measured, middle value = Analytical, bottom value = %: Delta

% Delta = (M - A)xlOO/A R p N M L K J H G F E D c B A I 0.2131 o.3201 0.2121 1 I 0.2111 o.3101 0.2691 I o.791 3.011 1.041 I o.3451 0.1111 o.9291 o.9551 o.9311 0.1201 o.3491 I o.3471 0.1141 o.9311 o.9561 o.93ol o.7141 o.3471 I -o.691 -o.4ol -0.111 -0.101 0.101 0.901 0.621 I o.4221 i.0221 i.2151 i.2011 i.2161 i.2011 i.2251 i.o34I o.4261 I o.4161 i.0201 i.2221 i.2111 i.2291 i.2111 i.2221 i.0291 o.4171 I 1.511 -o.581 -0.571 -o.321 -i.021 -o.341 0.261 o.4BI 2.151 I o.4201 i.o56I i.2501 1.3431 i.2131 1.1351 i.2211 1.3591 i.2691 i.0121 o.4221 I o.4171 i.o5sl i.2661 1.3561 i.2241 i.1441 i.2251 i.35BI i.2611 i.o5sl o.4161 I o.731 -0.221 -1.251 -0.921 -o.s91 -0.811 -o.351 0.061 o.131 i.201 1.541 I o.35ol i.o5ol i.2611 i.2311 i.2421 i.0221 i.o95I 1.0361 i.2511 1.2441 i.2931 i.o4BI o.3551 I o.3461 i.0311 i.26BI i.2551 i.2561 i.0401 i.1051 1.0411 i.2511 i.2561 i.2671 i.0291 o.3431 I 1.161 1.881 -0.091 -1.411 -1.141 -1.781 -0.891 -0.501 0.031 -0.931 2.021 1.861 3.521 I o.71BI i.2301 1.3601 i.2541 i.3191 1.1611 1.1221 1.1101 1.3451 i.2651 1.3761 i.2441 0.1291 I 0.1101 i.2291 i.3631 i.2601 1.3291 i.1111 i.1281 i.1101 1.3301 i.2601 1.3611 i.2201 0.1111 I 0.001 0.121 -0.201 -0.511 -0.751 -0.861 -0.501 0.021 1.111 0.381 1.141 1.301 1.651 I 0.2131 o.9331 i.2111 1.2331 1.0431 1.1691 i.2541 i.1511 1.2551 i.1161 i.o4BI 1.2461 1.2331 o.9521 0.2781 1 I 0.2121 o.93BI 1.2231 1.2391 i.o48I 1.1141 i.2611 1.1591 i.2611 i.1151 i.o4BI i.2391 i.2231 o.9391 0.2741 I o.311 -0.531 -0.991 -0.471 -o.5ol -0.461 -0.571 -0.671 -0.451 0.001 0.001 o.561 o.841 1.411 1.461 I o.3311 o.96ol i.2211 i.1101 i.1101 i.1311 i.1541 i.1421 i.1401 i.1251 i.1121 i.1041 i.2501 o.9B3I o.3291 s I o.3221 o.9661 i.2451 1.1031 i.1161 1.1331 i.1601 i.1511 i.1601 i.1321 i.1161 i.1031 i.2451 o.9661 0.3221 I 2.691 -o.601 -1.931 -0.451 0.111 -0.101 -0.521 -0.021 -1.061 -0.651 -0.321 0.011 o.381 l.7BI 2.101 I 0.2761 o.94ol i.2221 1.2431 i.o5BI i.1111 i.2571 1.1461 i.2361 i.1601 i.o4ol i.2321 1.2231 o.94BI 0.2061 9 I 0.2141 o.9391 i.2231 1.2391 1.0481 1.1151 i.2611 1.1591 i.2611 i.1141 i.o4BI 1.2391 i.2231 o.93BI 0.2121 I o.641 0.011 -0.091 o.3ol o.9BI 0.101 -0.201 -1.151 -1.9sl -o.511 -0.111 -o.561 0.031 i.111 5.261 1 0.7231 1.2451 1.3711 1.2651 1.3311 1.1711 1.1151 1.1521 1.3091 1.2471 1.3411 1.2241 0.7211 lo I 0.1111 i.2201 i.3611 i.2601 1.3301 i.1101 i.1201 1.1711 1.3291 1.2591 1.3631 i.2291 0.1101 I o.861 i.411 0.111 o.441 0.061 0.101 -i.131 -1.611 -1.521 -o.951 -1.651 -o.391 o.411 I o.3461 i.0421 1.2151 i.2561 1.2541 i.0301 i.0031 i.0211 i.2201 i.2551 i.26sl i.o33I o.3471 11 I o.3431 i.0291 i.2611 1.2561 i.2511 i.0411 i.1051 i.0401 i.2561 1.2551 i.26sl i.0311 o.3461 I 0.941 1.241 0.651 -0.031 -0.221 -1.041 -2.011 -1.861 -2.BBI 0.001 -0.231 0.161 0.311 I o.4271 i.o65I i.26sl 1.3541 1.2101 1.1361 i.2201 1.3541 i.2121 1.0691 o.4291 12 I o.4161 i.o5sl i.2671 l.35BI i.2251 1.1441 i.2241 1.3561 i.2661 i.o5BI o.4111 I 2.661 0.681 0.111 -0.201 -1.261 -0.721 -0.291 -0.121 0.451 l.OOI 2.831 I o.4101 i.0321 i.2231 1.2101- i.2341 i.2241 i.2401 i.0411 o.4201 13 I o.4111 i.0291 i.2231 i.2111 i.2291 i.2111 i.2221 i.0201 o.4161 I o.351 o.321 0.041 -0.121 o.411 i.091 2.131 i.201 1.051 I o.3531 0.1101 o.9361 o.9681 o.9561 0.1301 o.3521 14 I o.3471 o.7141 o.93ol o.9561 o.9311 o.7141 o.3471 I 1.851 0.511 0.671 1.221 2.701 2.301 1.501 I 0.2111 o.3231 0.2101 15 I 0.2691 o.3101 0.2111 I 3 .10 I 1. 63 I 2. 58 I AVERAGE ABSOLUTE PERCENT DIFFERENCE= 0.9 STANDARD DEVIATION 0. 834 Summary:

Map No: 81-28-03 Date: 11/15/2016 Power: 99.80%

Control Rod Position: Fo(Z) = 1.866 QPTR: 0.9953 1.0041 D Bank at 227 Steps pN Ml

= 1.480 1.0015 0.9991 Fz = 1.162 Axial Offset(%)= +0.990 Bumup = 116.9 MWD/MTU Page 36 of 46

Serial No.17-017 Docket No. 50-280 Enclosure SECTION 7 - CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 1 Cycle 28 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, Technical Specification limits, or COLR limits. The AREVA AGORA LTAs show no signs of anomalous behavior and are performing as expected. It is anticipated, based on the results associated with the S 1C28 startup physics testing program, that the Surry 1 core will continue to operate safely throughout Cycle 28.

Page 37 of 46

Serial No.17-017 Docket No. 50-280 Enclosure Table 7.1 SURRY UNIT 1 - CYCLE 28 STARTUP PHYSICS TESTS STARTUP PHYSICS TESTING RESULTS

SUMMARY

Measured Predicted Diff (M-P) or Design Parameter (M) (P) (M-P)/P,% Tolerance Critical Boron Concentration 1535.6 1546.0 -10.4 +/-50 (HZP ARO), ppm Critical Boron Concentration 1336.0 1332.6 3.4 +/-30 (HZP Ref Bank in), ppm Isothermal Temp Coefficient -2.325 -2.619 0.293 +/-2 (HZP ARO), pcm/F Differential Boron Worth -7.73 -7.63 1.3% +/-10%

(HZP ARO), pcm/ppm Reference Bank Worth 1543.6 1549.0 -0.3% +/-10%

(B-bank, dilution), pcm A-bank Worth (Rod Swap), pcm 338.4 343.9 -6 +/-100 C-bank Worth (Rod Swap), pcm 873.5 905.9 -3.6% +/-15%

SA-bank Worth (Rod Swap), pcm 918.9 919.4 -0.1% +/-15%

D-bank Worth (Rod Swap), pcm 989.5 1018.5 -2.8% +/-15%

SB-bank Worth (Rod Swap), pcm 1120.5 1158.2 -3.3% +/-15%

Total Bank Worth, pcm 5784.4 5894.9 -1.9% +/-10%

S1C28 Testing Time: 5.8 hrs

[Criticality 11/10/2016@ 15:50 to end of testing 11/10/2016 @21 :37]

Recent Startups:

S2C27 testing time: 7.6 hrs S1 C27 testing time: 5.6 hrs S2C26 testing time: 7.2 hrs S1C26 testing time: 7.8 hrs S2C25 testing time: 6.1 hrs S1 C25 testing time: 5.7 hrs S2C24 testing time: 7.1 hrs S1C24 testing time: 7.0 hrs S2C23 testing time: 9.4 hrs S1 C23 testing time: 6.2 hrs S2C22 testing time: 6.2 hrs Page 38 of 46

Serial No.17-017 Docket No. 50-280 Enclosure SECTION 8 - REFERENCES

1. J.A. Cantrell, "Surry Unit 1, Cycle 28 Design Report", Engineering Technical Evaluation ETE-NAF-20160134, Rev. 0, October 2016.
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-2011-0004, Rev. 0, March 2011.
4. Surry Units 1 and 2 Technical Specifications.
5. R. W. Twitchell, "Operational Impact of the Implementation of Westinghouse Integral Fuel Burnable Absorber (IFBA) and the Removal of Flux Suppression Inserts (FSis) for Surry Unit 1 Cycle 21," Technical ReportNE-1466, Rev. 0, January 2006.
6. J. A. Cantrell, "Surry Unit 1, Cycle 28 TOTE, Core Follow, and Accounting Calculations", Calculation PM-1847, Rev. 0, November 2016.
7. D. B. Livingston et al, "Surry Unit 1 Cycle 28 Flux Map Analysis", Calculation PM-1848, Rev. 0, and Addenda A - B, November 2016.

, 8. C. L. Tieman and B. T. Miller, "Reload Safety Evaluation Surry 1 Cycle 28 Pattern APT," EVAL-ENG-RSE-SlC28, Rev. 0, October 2016.

9. M. P. Shanahan, "Implementation ofRMAS version 7 at Surry Unit 1 and 2," Engineering Technical Evaluation ETE-NAF-2014-0021, Rev. 0, May 2014.
10. 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.
11. T. S. Psuik, "Surry Unit 1 Cycle 28 Full Core Loading Plan", Engineering Technical Evaluation ETE-NAF-2016-0066, Rev. 0, June 2016.
12. D. J. Agnew, "Rod Drop Test Computer Users Guide and SQA Paperwork," Engineering Technical Evaluation ETE-NAF-2014-0118, 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 28 Startup Physics Testing Logs and Results", Memorandum MEMO-NCD-20150033, Rev. 0, November 2016.
15. A. M. Scharf, "The CECOR Flux Map Analysis Cqde Version 3 .3 Additional Software Requirements and Design", Engineering Technical Evaluation ETE-NAF-2013-0088, 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. 3, "Startup Physics Tests Results Reporting".
18. T. S. Psuik, "Implementation of Changes to the Allowable Power Level for the Initial Startup Flux Map for Surry Units 1 and 2", Engineering Technical Evaluation ETE-NAF-2015-0007, Rev. 0, April 2015.

Page 39 of 46

Serial No.17-017 Docket No. 50.;.280 Enclosure APPENDIX- STARTUP PHYSICS TEST

SUMMARY

SHEETS Page 40 of 46

Serial No.17-017 Docket No. 50-280 Enclosure; Appendix Surry Power Station Unit 1 Cycle 28 Startup Physics Test Summary Sheet- Formal Tests (Page 1of6)

Date{

Design Acceptance Preparer/

Measured Value Design Criteria Acceptance Criteria Crlterla Met Criteria Met Time of Reviewer ZPTR= background < ZPTR < POAH Yes

~c-7 to 11 o background = -" ' 0 3 0 e

"'°' - -II amps NIA N/A I ¢!- -:r- amps POAH= 'ii. S"fe - 7 amps No Po"' +~c'fO '""~ :~'~cm IHPc - Pt)/PiH X 100% :> 4.0%1 / Yes (measured reactivity) The allowable range Is set to the larger of Pt= -t~:zd/- ,~I?' pcm the measured results or the pre-critical No (predicted reactivity) bench test. NIA NIA D = {( _ )/ '} , Pre-jticaJ Bench Test Results pc PltP' x 1000'o,. i 01 IP 4(1$ - I o pcm

  • VaD = -o.ie; i'" ,/=- o .11-'f 'l. Allowable range +1u, /- 10 o pcm (CarAAo= 153~. t- ppm 2 (Ca)AR 0 = 1546 +/-50 ppm (Adj. To design conds.)

1 t.(Ca)AAo=(C 8 ) ARO - (Ca)AAo = - /D .'/ ppm o.C 6 =2 ~7.56 pCIT\/ppm

( 0. ISO)  :}- - 2

  • C,/ 9 +/- 2 pcm/4F pcm/"F T AAO No No NIA pcm References 1.) DNES-AA-NAF-NCD-4015, Rev. 2 2.) ETE*NAF-201 &-0134, Rev. 0 3.) ETE-NAF-201&-0133, Rev. 0 Page 41 of 46

0 Serial No. 17-01 7 Docket No. 50-280 Enclosure; Appendix

. Surry Power Station lJnii 1Cyde28Startup Physics Test Summary .Sheaf

  • Formal rests (Page 2 of S) ..

Measured Value Design ~nteria Acceptance C ~ i teria NiA ppm NIA NIA NIA NIA pcm r  :~*;~: :::1~'0.~~~~vs,r~~~~~*~1~5~Yii'f-*"'::::1e' ~: ,f!i~,~~'!1,t~,;t.!il'Tti>taNR~"il?!Vg_rtti,*:~oe1,s;waP£ :~;~1;,;r:~'i.ii 1rf~K r:J~$~~~.t~,;;;~r~~i;,\;£ .

lro1a1= ,,t= .; iut; (J 101 +/- 10% NIA __y_ Yes 5 Z~lj.!;I pcm 1OOx(Meas. - Des.)/Des. = -\ *'j  % No NIA References 1.} DNES*AA* NAF*NC0-4015, Rev. 2 2.) ETE*NAF-2016-0134 , Rev. 0

4. )f.}ETE-NAF-2016..0133, Rev. 0

\f.A<. ll/h//6

~Y\ Jf/10/lb Page 42 of 46

Serial No.17-017 Docket No. 50-280 Enclosure; Appendix Surry Power Station Unit 1 Cycle 28 Startup Physics Test Summary She~t - Formal Tests (Page 3 of 6)

Date/

Design AcGaptance Preparert Measured Value Design Criteria Acceptance Criteria Timo of Critorla Met Criteria, Met Reviewer

' Test

[; *~Jl& "'t':i>!. .. '.i!!i;~~,,~::;0 . ' i'J# ~ '!;oft" ',',., ,,._ ;i;M~,,~-- *. * ~MID,.Flu:i~kl~ ~~.w~~. *':l,:1_,~

. :::, .,qi}h', ~lfi;;, ~. \lt\""" El;,,Ve _$,Jf" /' 0;, "' ~¢'~ j ~,.,,:

i* **~- *~;;'_ ,-~. c Map Pa.ver Level (% full Power) "' L,j 6, 3

'411ll R:al*tl,,. A*.!ll)tnbly PoW<tt, %01FF (M.f'JIP

+/-10% for P1'.:!0. 9 . / Yes

%0ffF; 4.1  % rorPi >!OJ 215% fOf P,-<0.9 NIA

__ ___ No NIA

2. ~  %. for P,<O.9 (P1= assy power)'.2 KL/:.

Nuclea r Enthalpy:*Rfs&Hot Channel Factor, f'AH(N) lt/t1 /16 ii~

2P 2S

. / Yes FMl(N)" 1.53'1 NIA FAH(N).:> t.6:3.5(1+Q,3{1* P}) [COJ.R 3.7] NIA

_ _ No Total Hoa.t Fl1.1x Hot Channol Factor, FC:l(Z)

-~

Peak F0 (Z} Hot Channel NIA Fo(Z):s:S*K{Z} {COLR 3.71 NIA v Yll1i Factor.- 2. ,<) ~l Maxim um Posltive lncom Quadrant Power Till

-- No

./

Tilt"' 1. 00 7i s: 1.02' NIA Yes NJA

- - No References 1.) DNES-AA* NAF-NCD-4015, Rev. 2 2.) ETE-NAF-2016--0134, Rev, 0 3.) :ETE*NAF-2016-0133, Rev. 0 Page 43 of 46

Serial No.17-017 Docket No. 50-280 Enclosure; Appendix Surry Power Station Unit 1 Cycle 28. Startup Physlcs Test Summary Sheet - Formal Tests (Page 4 of 6)

Date!

Design Criteria Deitlgn Acceptance Time of Preparer/

Measured Value Accopta.nca Criteria Crite.rla Met Criteria Met Reviewer Test rlf; 1!i;~!~!~l!tliiiimlttll;;1ml!i~!e4!iff.1Hl~J.11il!~~wi\l~ffitil$,fUll1~liilliiliili'.11!1r:;~;jlWIJ* J!liixr~IJiif6~~:s!i~ow.e~p~l'l,S%'illgrilffilti1i~~f!,~ll~'l;;i~ilf,;;i~\f.!Jii~!lh'il!f'liili&.'f~l~iitiif!i~1~lJ: latlmWJilliilf IMap PO'IVflr Level(% FuH Power)

  • 10, c:>4 Max Rel.a ttn Assembly Pow11r, %PIF'F (lot.P)JP

../ Yc>s

,,,1t.{I& tfij>

_ _ No \\ O"t.

%0lFF"' °1>. Q  % for Pl 20.E  :!:15% for P1<Q.9 IA NJA J...O  % for Pr:O.& (P1 ,. assy powerJ'"I KL!<

Nuclear Enthalpy RIH Hot Channel Factor, FAH(N)

_L Ys NIA F~H(N)S1 .~l*0 .3(1..P)) (COt..R 3.,7) NIA No Peak F0 (Z) Hal. Chaonol . ~. Yo NIA NIA

.Foctor= \Al 6 No Mlll<lmuro PoslUv* lneor* Quad.rant Powe.r Tiit Tilt,. NIA NIA References 1.) DNES-M-NAF*NCD-401 5. Rev. 2 2.) ETE* NAF-2016-0134, Rev. 0 3.) ETE*NAF*2016-0133, Rev. 0 Page 44 of 46

Serial No.17-017 Docket No. 50-280 Enclosure; Appendix

~. . .. Surry*Power .Station)Jnit 1 Cyc1e*2a Startup Physics Test Summary Sheet- Formal Tests (Page 5 of 6)

    • ,
      .-..  ; Date/

Measured Value***"':' :  ::~*;. ** ,,. Design criteti~.. '). *' -., . :. *.. *), ; : >*Acc~p~n~~,.~~lteria Design Acceptance Time of Pr~parer/

.*, -="**** "
,*.:****-* .'.,.*. *;.;*-.; .... *******: Criteria Met Crifoi-iaMet Test Reviewer*

Map Power Level {% Full Power) =C\C\ .'()Cl Max Relative Assembly Power, *%DIFF (M*P)IP t10~ for P1 ~0.9 *. VYes-

' f'1<0.9 *.

%DIFF"_- __Ol_._£:t__% for Pi <::O.E +/-15% for

S. ~

% for P<0.9 I

(P1 ~ a~y power)'"

Nuclear Enthalpy Rise Hot Channel Factor, FAH(N)

__k'.'.'.:. Yes FO.H(N)=_l,__.----'L!'----~-- N/A FilH(N):S:1.635(1+0.3(1-P)f [COLR 3.7] N/A No Total Heat Flux Hot Channel Factor, FQ(Z)

Peak F0 (Z) Hot Chanp1;>I . . VYes

  • N/A Fa(Z):S{2.5/P}.K(Z) [COLR 3.7] NIA Factor-: I* &Coct> * ** No Maxim um Positive lncorc Quadrant Power Tilt . *~ .. :, . ..
~ . **; ........

Titr-_\_.~=--O_L\~\__ :s: 1.021 NIA NIA No References 1.) DNES-AA-NAF-NCD-4015, Rev. 2 2.) ETE-NAF-2016-0134, Rev. 0 3.) ETE-NAF-2016-0133, Rev. 0 Page 45 of 46

Serial No.17-017 Docket No. 50-280

  • Enclosure; Appendix Surry Power.Station Unit 1 C.ycle 28*Startup Physics Test Summary Sheet - Formal Tests (Page 6 of 6) ;

Date/

Measurei;l Value * ..

  • Design .Criteria'. Design ~cceptance Time*of.

i . . *.~~ **. * . ~ Crite'ria*Met t;:riteria Met

.,..,A .. * * --;,,..- **Yes \1)~1//t.

NIA F1o~; ~ 274009 gpm [COLR 3.8] '"' \ .....>4-1'°"~

__._*No References 1.) ONES-AA:NAF-NCD-4015, Rev. 2 2.) ETE-NAF-2016-0134, Re\/. 0 3.) ETE-NAF-2016-0133, Rev. 0 Page 46 of 46

Retrieved from "https://kanterella.com/w/index.php?title=ML17044A011&oldid=2510039"