ML20063J621

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Cycle 30 Startup Physics Tests Report
ML20063J621
Person / Time
Site: Surry Dominion icon.png
Issue date: 02/28/2020
From: Standley B
Dominion Energy Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation, NRC/RGN-II
References
20-067
Download: ML20063J621 (52)
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Text

Dominion Energy Services, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 ~ Dominion Dominion Energy.com  ;;iii" Energy February 28, 2020 United States Nuclear Regulatory Commission Serial No .: 20-067 Regional Administrator - Region II NRA/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 ENERGY VIRGINIA)

SURRY POWER STATION UNIT 1 CYCLE 30 STARTUP PHYSICS TESTS REPORT Enciosed is the Surry Unit 1 Cycle 30 Startup Physics Tests Report. The report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 30 on November 29, 2019. 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,

/3(5~

B. E. Standley, Director Nuclear Regulatory Affairs Domin ion Energy Services, Inc. for Virginia Electric and Power Company

Enclosure:

Surry Unit 1 Cycle 30 Startup Physics Tests Report Commitments made in this letter: None

Serial No.20-067 Docket No. 50-280 Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Mr. Vaughn Thomas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 04 F-12 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. G. Edward Miller NRC Senior Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.20-067 Docket No. 50-280 Enclosure SURRY UNIT 1 CYCLE 30 STARTUP PHYSICS TESTS REPORT February 2020 Virginia Electric and Power Company (Dominion Energy Virginia)

Surry Power Station Unit 1

Serial No.20-067 Docket No. 50-280 CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Dominion Energy (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.

Page 1 of 49

Serial No.20-067 Docket No. 50-280 TABLE OF CONTENTS CLASSIFICATION/DISCLAIMER ............................................................................................ 2 TABLE OF CONTENTS .............................................................................................................. 3 LIST OF TABLES ......................................................................................................................... 4 LIST OF FIGURES ....................................................................................................................... 5 PREFACE ....................................................................................................................................... 6 SECTION 1 - INTRODUCTION AND

SUMMARY

............................................................... 7 SECTION 2 - CONTROL ROD DROP TIME MEASUREMENTS ................................... 16 SECTION 3 -. CONTROL ROD BANK WORTH MEASUREMENTS .............................. 21 SECTION 4 - BORON ENDPOINT AND WORTH MEASUREMENTS .......................... 26 SECTION 5-TEMPERATURE COEFFICIENT MEASUREMENT ................................ 29 SECTION 6 - POWER DISTRIBUTION MEASUREMENTS ............................................ 31 SECTION 7 - CONCLUSIONS ............................................................................................... 38 SECTION 8 - REFERENCES .................................................................................................. 40 APPENDIX A-RCP STARTUP ORDER................................................................................ 41 APPENDIX B-STARTUP PHYSICS TEST

SUMMARY

SHEETS ................................... 44 Page 2 of 49

Serial No.20-067 Docket No. 50-280 LIST OF TABLES TABLE 1.1 - CHRONOLOGY OF TESTS ............................................................................. 11 TABLE 2.1 -HOT ROD DROP TIME

SUMMARY

............................................................. 17 TABLE 3.1 - CONTROL ROD BANK WORTH

SUMMARY

............................................. 23 TABLE 4.1 - BORON ENDPOINTS

SUMMARY

................................................................. 27 TABLE 4.2 - BORON WORTH COEFFICIENT .................................................................. 28 TABLE 5.1 -ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

................ 30 TABLE 6.1 - INCORE FLUX MAP

SUMMARY

.................................................................. 33 TABLE 6.2 - COMPARISON OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS ............................................34 TABLE 7.1 - STARTUP PHYSICS TESTING RESULTS

SUMMARY

.............................39 Page 3 of 49

Serial No.20-067 Docket No. 50-280 LIST OF FIGURES FIGURE 1.1 - CORE LOADING MAP .................................................................................... 12 FIGURE 1.2 - BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWD/MTU) .. 13 FIGURE 1.3 - AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS ............ 14 FIGURE 1.4 - CONTROL ROD LOCATIONS ...................................................................... 15 FIGURE 2.1 - ANNOTATED SAMPLE ROD DROP TRACE ............................................. 18 FIGURE 2.2 - ROD DROP TIME - HOT FULL FLOW CONDITIONS ............................. 19 FIGURE 2.3 - ROD DROP TIMES TRENDING .................................................................... 20 FIGURE 3.1 - CONTROL BANK B INTEGRAL ROD WORTH - HZP .............................24 FIGURE 3.2 - CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP .................... 25 FIGURE 6.1 - ASSEMBLYWISE POWER DISTRIBUTION 28.53% POWER ................ 35 FIGURE 6.2 - ASSEMBL YWISE POWER DISTRIBUTION 70.62 % POWER ................36 FIGURE 6.3 - ASSEMBLYWISE POWER DISTRIBUTION 99.93% POWER ................37 Page 4 of 49

Serial No.20-067 Docket No. 50-280 PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 1 Cycle 30 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-N CD-5 007, 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 30 startup physics tests results and evaluation sheets are included in Appendix B to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer/ reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations performed by Dominion Energy's Nuclear Engineering and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits.

Per Surry Technical Specifications 6.6.A [Ref. 4], "the report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program, and a comparison of these values with design predictions and specifications." Per UFSAR Section 3.6.1.1 [Ref. 19],

"a detailed series of start-up physics tests are performed", followed by references to core power distribution measurements, i.e., flux maps. The S 1C30 Startup Physics Tests Report includes, as required, a description of measured values and a comparison of these values to design predictions of all of the tests performed during startup testing and the initial power ascension flux maps performed thereafter.

Page 5 of 49

Serial No.20-067 Docket No. 50-280 SECTION 1 - INTRODUCTION AND

SUMMARY

On October 19, 2019, Unit No. 1 of Surry Power Station completed Cycle 29 and began refueling [Ref. 1]. During this refueling, 60 of the 157 fuel assemblies in the core were replaced with fresh Batch S 1/32A and S 1/32B assemblies [Ref. 8]. The Surry 1 Cycle 30 (S 1C30) core consists of 8 sub-batches of fuel: two fresh batches (Sl/32A and Sl/32B), three once-burned batches (Sl/31A, Sl/31B and S2/30B), and three twice-burned batches (Sl/30A, Sl/30C and S2/29B). S1C30 utilizes the 15x15 Upgrade (Upgrade) Fuel Design for all but 4 of the fuel assemblies (which make up batch S 1/30C). The remaining 4 assemblies are Lead Test Assemblies (LTAs) of the AREVA AGORA-5A-I (AGORA) design that are being loaded for their third cycle of irradiation [Ref. 1].

Fuel batches S 1/30A, S 1/3 lA, S 1/3 lB, S 1/32A, S 1/32B, S2/29B and S2/30B 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, these batches of the Upgrade fuel design 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 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 to accommodate higher lifetime pressure increase from the IFBA coating [Ref. 5].

Page 6 of 49

Serial No.20-067 Docket No. 50-280 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 AF A-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 5 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, 12 at 2% and 16 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 rods. The gadolinia rods are subject to the 5:1 enrichment penalty (5% reduction in U-235 for each weight percent of gadolinia) from the nominal enrichment.

Cycle 30 loads Secondary Source Assemblies (SSAs) in core locations H04 and H12 to improve Source Range Detector response. 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 SIC30. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 30 core.

The S 1C30 full core loading plan [Ref. 8 and Ref. 11] is given in Figure 1.1 and the beginning of cycle fuel assembly bumups [Ref. 6] are given in Figure 1.2. The incore moveable detector locations used for the flux map analyses [Ref. 7] are identified in Figure 1.3. Figure 1.4 identifies the location and number of control rods in the Cycle 30 core [Ref. 1].

According to the Startup Physics logs, the Cycle 30 core achieved initial criticality on November 29, 2019 at O1:20 [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.7.15.04 [Ref. 9]

Page 7 of 49

Serial No.20-067 Docket No. 50-280 was used for SIC30 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. 10]. No control rods are located in the four AGORA 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 3.5% lower than the design prediction. The reference bank (Control Bank B) worth was 3.5%

lower than its design prediction. Control rod banks with design predictions greater than 600 pcm were within +/-3.0% of the design predictions except C-bank. The measured worth for C-bank was 622 pcm which was 6.1 % below the design prediction. The larger percent difference is due to the relatively low worth of C-bank. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was 12 pcm below 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% ~k of the design prediction. The boron worth coefficient measurement (the differential boron worth, DBW) was 1.8% lower than the design prediction, which is within the design tolerance of+/- 10%.

The measured isothermal temperature coefficient (ITC) for the all-rods-out (ARO) configuration was 0.496 pcm/°F higher than the design prediction. This result is within the design tolerance of +/-2.0 pcm/°F [Ref. 14].

Core power distributions were within established design tolerances. The measured assembly power distributions were within the design tolerance of +/- 15% for assemblies with Page 8 of 49

Serial No.20-067 Docket No. 50-280 power <0.9 and +/-10% for assemblies with power ~0.9. A 3.8% maximum difference occurred in the 28.53% power map. The heat flux hot channel factors, FQ(Z), and enthalpy rise hot channel factors, F1i.r, 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 Reactor Coolant Pump (RCP) start sequence is as follows: 'C' RCP started on 11/19 at 16:48, 'A' RCP started on 11/22 at 14:38, and 'B' RCP started on 11/26 at 00:01 [Appendix A].

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

The 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 289,846 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 49

Serial No.20-067 Docket No. 50-280 Table 1.1 SURRY UNIT 1 - CYCLE 30 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 11/28/19 12:24 HSD 1-NPT-RX-014 Reactivity Computer Checkout 11/29/19 02:25 HZP 1-NPT-RX-008 Boron Endpoint - ARO 11/29/19 02:25 HZP 1-NPT-RX-008 Zero Power Testing Range 11/29/19 02:25 HZP 1-NPT-RX-008 Boron Worth Coefficient 11/29/19 06:45 HZP 1-NPT-RX-008 Temperature Coefficient - ARO 11/29/19 02:53 HZP 1-NPT-RX-008 BankB Worth 11/29/19 05:03 HZP 1-NPT-RX-008 Boron Endpoint - B in 11/29/19 06:45 HZP 1-NPT-RX-008 Bank A Worth - Rod Swap 11/29/19 07:35 HZP l-NPT-RX-008 Bank C Worth - Rod Swap 11/29/19 07:35 HZP 1-NPT-RX-008 Bank SA Worth - Rod Swap 11/29/19 07:35 HZP 1-NPT-RX-008 Bank D Worth - Rod Swap 11/29/19 07:35 HZP 1-NPT-RX-008 Bank SB Worth - Rod Swap 11/29/19 07:35 HZP 1-NPT-RX-008 Total Rod Worth 11/29/19 09:20 HZP 1-NPT-RX-008 Flux Map - less than 50% Power* 11/30/19 02:09 28.53% 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 12/01/19 07:05 70.62% l-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 12/05/19 13:13 99.93% 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 12/03/19 09:25 HFP 1-NPT-RX-009

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

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

Page 10 of 49

Serial No.20-067 Docket No. 50-280 Figure I.I SURRY UNIT 1 - CYCLE 30 CORE LOADING MAP SURRY UNIT l - CYCLE 30 ETB-NAF-2019-0027 REV. 0 FULL CORE LOADING PLAN ATTACHMENT l REVISION NO. 0 PAGE 1 OF 1 VEP-NES-NAF A . C D  ;; F G H J K L N p R 15 747 AG2 144 l

RCC RCC RCC 14 409 510 AA33 AM6 AA40 508 407 IIORTH RCC RCC 13 735 AA52 MOS AA16 530 AA14 AA06 AA43 140 RCC RCC SS10 RCC RCC 12 738 750 AA55 547 533 517 539 545 AA59 156 733 RCC RCC 11 410 AA41 AA58 551 505 AA18 531 AA19 501 554 AAS3 AA46 4(19 RCC RCC RCC RCC RCC RCC RCC 10 502 AAOB 543 504 AA28 561 AA29 562 AA26 514 546 AA07 513 RCC RCC RCC RCC 743 AA36 Ml3 538 Ml1 560 520 552 518 563 AA20 536 AA09 AA39 748 RCC RCC RCC RCC AG3 AM:! 532 524 529 M32 553 858 550 M3l 528 522 525 AA45 AG5 RCC RCC RCC RCC 745 AA37 AAlO 540 AA24 558 519 50 521 559 AA22 534 AAll AA38 742 RCC RCC RCC RCC RCC RCC RCC 511 AA04 544 506 AA27 564 AA30 557 AA25 503 542 M02 515 RCC RCC 405 AA44 AA60 556 509 AA21 526 M23 516 555 M56 AA5l 412 RCC RCC SS11 RCC RCC 737 752 M57 541 535 523 537 548 AA54 753 136 RCC RCC lNCORS OEVlCE DESCRIPTlONS: 739 AA49 AAOl Ml5 527 AA12 AA03 AA50 734 RCC - FULL LE NGTll CONTROL ROD RCC RCC RCC sst - SECQNOAAY SOOP.CE ASSEMl!LY 411 507 AA35 AA47 AA34 512 406 741 l\G6 746 Cate: ~z/ls/18) it! '2.:tl ,,

Date: -fh/i<t I I Date: "'4/t.z..,/l'f Date: '::f (z. '-1. ( T'\-

Page 11 of 49

Serial No.20-067 Docket No. 50-280 Figure 1.2 SURRY UNIT 1 - CYCLE 30 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (MWD/MTU)

R N M L K J H G F E D C B A

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  • 15 R p N M L K J H G F E D C B A Page 12 of 49

Serial No.20-067 Docket No. 50-280 Figure 1.3 SURRY UNIT I -CYCLE 30 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS R p N M L K J H G F E D C B A 0

MD 2

MD 3

MD MD MD MD

+ 4 MD MD MD 5

MD MD MD MD MD MD 6

MD MD MD

MD MD MD MD MD MD X

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

+

13 MD MD X

14 MD MD 15 MD MD - Moveable Detector

+ - Locations Not Used For Any Map x - Location Not Used For Flux Map 1

  • - Location Not Used For Flux Maps 2 and 3 o - Location Not Used For Flux Map 3 Page 13 of 49

Serial No.20-067 Docket No. 50-280 Figure 1.4 SURRY UNIT 1 - CYCLE 30 CONTROL ROD LOCATIONS R p N M L K J H G F E D C B A 180° 1

A D A 2 SA SA 3 C B B C 4 SB SB 5 A B D C D B A 6 SA SB SB SA 7 90° D C C D 270° 8 SA SB SB SA 9 A B D C D B A 10 SB SB 11 C B B C 12 SA SA 13 A D A 14 15 D = Control Bank D SB = Shutdown Bank SB C = Control Bank C SA = Shutdown Bank SA B = Control Bank B A = Control Bank A Page 14 of 49

Serial No.20-067 Docket No. 50-280 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-014. This verified that the time to entry of a rod into the dashpot region was less than or equal to the maximum allowed by Technical Specification 3.12.C.l [Ref. 4].

Surry Unit 1 Cycle 30 used the Rod Drop Measurement Instrument (RDMI) to gather and analyze the rod drop data. Secondary coil voltage data is acquired for each rod using the Computer Enhanced Rod Position Indication (CERPI) system. Data is immediately saved to a comma-separated value file. [Ref. 12, Section 1.0 and Section 2.8 of Att. B]

An annotated sample rod drop trace 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 18-30. Technical Specification 3.12.C.1 [Ref. 4] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. These test results satisfied this technical specification limit as well as the Westinghouse 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. Compared to the rod drop results from S 1C29, the fastest rod drop time increased by 0.04 seconds, the average rod drop time increased by 0.01 seconds, and the slowest rod time increased by 0.01 seconds. This is within the normal cycle to cycle variation.

Page 15 of 49

Serial No.20-067 Docket No. 50-280 Table 2.1 SURRY UNIT 1 - CYCLE 30 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME P-08 1.46 sec. H-02 1.33 sec 1.36 sec.

Page 16 of 49

Serial No.20-067 Docket No . 50-280 Figure 2.1 SURRY UNIT I -CYCLE 30 STARTUP PHYSICS TESTS ANNOTATED SAMPLE ROD DROP TRACE 5

1j I: ...

4.5 JI :

4 Initiation of Rod Drop Event Mark I i......

~

Beginning of

..... Dashpot Entry

. /"' (Extreme drop 3.5 /

in Voltage)

/ /

3 2.5

. I 2

I I

1.5 J I

- G l .

It I

  • Bottom of Dash pot I J ~ i' I

Bounce Indicating

~0.5 N' 'A>I' \A.I\/ I Rod is NOT Stuck

)

I 0

t:t t

"'(r I I\ r, ,. J 0 .

Q.

.> E ~

. w~u - .

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. I V I I

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I

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-1.5

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-2

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. I

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-3

  • I ii*

-3.5 1 *'

I I

-4

. I .~

I

. *I I I I

' I 0 l 2 3 4 T ime (sec)

- SIGNAL - TRIGGER ~ X RECOIL  !:! - OASHPOT

~- ACCEL Page 17 of 49

Serial No.20-067 Docket No. 50-280 Figure 2.2 SURRY UNIT 1 -CYCLE 30 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

1.356 1.328 1.348 2 1.356 1.356 3 1.368 1.330 1.332 1.406 4 1.336 1.350 5 1.336 1.340 1.338 1.356 1.356 1.342 1.444 6 1.338 1.376 1.356 1.350 7 1.458 1.376 1.438 1.374 8 1.382 1.350 1.374 1.366 9 1.358 1.354 1.346 1.388 1.364 1.354 1.384 10 1.336 1.348 11 1.338 1.338 1.346 1.400 12 1.374 1.372 13 1.398 1.332 1.404 14 15 I x.xx I===> Rod drop time to dashpot entry (sec.)

Page 18 of 49

Serial No.20-067 Docket No. 50-280 Figure 2.3 SURRY UNIT I -CYCLE 30 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 1 2.5 I Technical Specification Limit, 2.4 seconds I 2 .4 2.3 2.2 2.1 2 SIF Admin . Limit l I 1.93 seconds

'u 1.9

--- i--

II

\

~

~

\

1.8

' l 1.7 \1 Upgrade Admin. Limit 1.68 seconds 1.6 1.5

/-

1.4 1.3

-- L. -'

'/

/. ,~

/I

- - Slowest Rod Time

- - Ave ra ge Time

- - Fastest Ro d Tine 1.2

___.lV ~,

r ---.~

1.1 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Cycle 1

Step increase from Cycle 26 to Cycle 27 is concurrent with rod drop test computer change.

Page 19 of 49

Serial No.20-067 Docket No. 50-280 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 30, 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 O 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 O steps withdrawn to a range of O to 2 steps withdrawn. The S 1C30 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 bank was fully withdrawn and the current test bank was nearly inserted. The next step was to Page 20 of 49

Serial No.20-067 Docket No. 50-280 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 zero reactivity. 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 and moderator temperature 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 Appendix B, the individual measured bank worths for the control and shutdown banks were within the design tolerance of +/- 10% for the reference bank,

+/- 15% for test banks of worth greater than 600 pcm, and +/- 100 pcm for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was 3 .5% lower than 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 49

Serial No.20-067 Docket No. 50-280 Table 3.1 SURRY UNIT 1 -CYCLE 30 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)

BANK (PCM) (PCM) (M-P)/P X 100 B - Reference 1338 1386 -3.5%

A 287 299 -12 pcm*

C 622 662 -6.1%

SA 951 980 -3.0%

D 1033 1061 -2.7%

SB 1067 1100 -3.0%

Total Bank Worth 5298 5490** -3.5%

  • Note: For bank worth< 600 pcm, worth difference= (M - P).
    • Total bank worth is calculated using individual bank worth with higher precision than reported.

Page 22 of 49

Serial No.20-067 Docket No. 50-280 Figure 3.1 SURRY UNIT 1 - CYCLE 30 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600 1400 -- -~

~

'i-... .......... 11\.

1200 " I\. ...

"\ \

"i?1000 0

0..

\

~

\...

\

..c: ~ '\

' *\.,

.j..l

~

0 \

~ 800 -+- Measured

~ t II - Predicted rd ill ~

.-1

\

rd \ I

~ 600 t,\ \.. II QJ

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~

' "\.'*\.

H

\.....

400 \ ...

\. .

"~\

\ ~

r'\."

~

200 ~

0

~.-

  • 1111

'I ...._

0 50 100 150 200 250 Bank Pos i tion (steps}

Page 23 of 49

Serial No.20-067 Docket No. 50-280 Figure 3.2 SURRY UNIT I - CYCLE 30 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12.0 10.0 ff

    • ~

I I' "

11* \\

- 0..

a, 8.0 1

I

~

\

I

\.

.µ C/l

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..c: IJ '

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l II ~

' ...\-

.µ H ~ -+- Measured 0 6.0

~ "' - Predicted

'O 0

ii::

..., J * \

ro

  • .-I

.µ I I i:: / j \

a, 4.0 I I H

a, 4--1 4--1 I

  • .-I Cl

/ '

I I 2.0 f .l I I

I J.

I r

I l/

0.0 0

". 50 100 150 200 l

250 Bank Pos i tion (steps)

Page 24 of 49

Serial No.20-067 Docket No. 50-280 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 Appendix B, the measured critical boron endpoint values were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.10.A [Ref. 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 Appendix B, the measured DBW was well within the design tolerance of+/- 10%.

In summary, the measured boron worth coefficient was satisfactory.

Page 25 of 49

Serial No.20-067 Docket No. 50-280 Table 4.1 SURRY UNIT 1 - CYCLE 30 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

Measured Predicted Difference Control Rod Endpoint Endpoint M-P Confi uration Ill Ill ( m)

ARO 1588 1589 -1 B Bank In 1410 1407* 3

  • 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 Appendix B.

Page 26 of 49

Serial No.20-067 Docket No. 50-280 Table 4.2 SURRY UNIT I -CYCLE 30 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)

M-P IP x 100

-7.52 -7.66 -1.8%

Page 27 of 49

Serial No.20-067 Docket No. 50-280 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 3.66 °F, followed by the RCS cool down of 3 .34 °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 Appendix B, the measured ITC value was within the design tolerance of +/-2 pcrn/°F. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -1.771 pcm/ °F, a predicted doppler temperature coefficient (DTC) of -1.65 pcm/ °F, and a measurement uncertainty of +0.5 pcm/ °F, is -0.121 pcm/ °F. It thus satisfies the COLR criteria [Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pcrn/°F.

Page 28 of 49

Serial No.20-067 Docket No. 50-280 Table 5.1 SURRY UNIT 1 - CYCLE 30 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

TEMPERATURE ISOTHERMAL TEMPERATURE COEFFICIENT BANK BORON RANGE(°F) (PCM/OF2 POSITION CONCENTRATION *-*****----******

~ DIFFER LOWER j UPPER HEAT- COOL- ~~ AVG. ~'

(STEPS)

LIMIT Ii LIMIT (ppm)

UP DOWN i MEAS ~ PRED! ~

I (M-P) f  ! -1.771 i i D/199 546.13 I j

549.79 1576.7 -1.583 -1.958 I I' -2.267

!! 0.496 I I I Page 29 of 49

Serial No.20-067 Docket No. 50-280 SECTION 6 - POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the moveable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available locations monitored by the moveable detectors for Cycle 30 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 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 28.53% 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 70.62% and 99.93% 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

+/-3.8% in the 28.53% power map, +/-3.1 % in the 70.62% power map and +/-2.8% in the 99.93%

power map. The maximum positive quadrant power tilt for the three maps were 0.72%, 0.66%

and 0.76%, respectively. These power tilts are within the design tolerance of 2%.

Page 30 of 49

Serial No.20-067 Docket No. 50-280 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.

As a best practice, transient FQ(Z) margin is being monitored starting in Surry 1 Cycle 30 for flux maps at greater than 90% power. The FQ(Z) margin is compared with conservative screening values from the design report [Ref. 1]. The FQ(Z) margin for the 99.93% flux map exceeds the conservative screening value of 10.6% from the design report.

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 30.

Page 31 of 49

Serial No.20-067 Docket No. 50-280 Table 6.1 SURRY UNIT 1 - CYCLE 30 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

Peak Fo(z) Hot F! Hot (2) Core Fz Burnup Bank Core Tilt (3) Axial No.

Map Map Power Channel Factor (1) Channel Factor Max Date MWD/ D Offset Of Description No. (%) -]Axiali i MTU Steps Assy ip . t! Fo(z) Assy

, Olll I I Axia!J F! Point; z F I Max Loe (%) Thimbles Low Power 1 11/30/19 1.6 28.53 175 M-71 27 I2.250 M-7 1.550 26 1.360 1.0072 NW 7.387 44 Int. Power (4) 2 12/01/19 20.8 70.62 191 M-7 27 1.956 M-9 1.506 26 1.219 1.0066 SW 1.733 45 Hot Full Power 3 12/05/19 153.0 99.93 226 M-9 27 1.864 M-9 1.485 27 1.168 1.0076 SW 1.934 44 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) F 0 (z) includes a total uncertainty of 8%

(2) F! includes no uncertainty.

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

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

Page 32 of 49

Serial No.20-067 Docket No. 50-280 Table 6.2 SURRY UNIT 1 - CYCLE 30 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 2.250 5.000 27 55.0 1.550 1.986 22.0 2 1.956 3.540 27 44.8 1.506 1.779 15.4 3 1.864 2.502 27 25.5 1.485 1.635 9.2 The measured FQ(Z) hot channel factors include 8% total uncertainty. Measured F~ data includes no uncertainty.

  • Margin(%)= IOO*(Limit -Meas.)/ Limit Page 33 of 49

Serial No.20-067 Docket No. 50-280 Figure 6.1 ASSEMBL YWISE POWER DISTRIBUTION 28.53% 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

0. 2611 0. 2961 0 .2621
o. 260 I 0. 2861 0.260 I
0. 421 3. 531 0. 921
0. 2751 o. 610 I 1. 0481 1. 0681 1. 055 I 0. 622 I o. 280 I 0 .2761 0. 6131 1. 0531 1. 0711 1. 054 I 0. 615 I 0. 2781

-0. 411 -0. 491 -0. 471 -0.291 0. 071 1. 20 I 0.831

0. 2791 0. 8981 1.1571 1. 2691 1. 2221 1. 2771 1.1721 0. 9151 0. 2851
0. 2821 0. 9021 1.1621 1. 2781 1. 2421 1. 280 I 1.1661 0. 9081 0. 2851

-1.121 -0. 441 -0. 461 -o. 70 I -1. 60 I -0.271 0.501 0. 751 0. 061

0. 2891 0.5741 1. 1851 1. 3461 1. 3721 1. 2571 1. 3831 1. 364 I 1. 210 I 0. 5931 0. 2911 0.2831 0. 5691 1.1881 1. 350 I 1. 3821 1. 2691 1. 3841 1. 3551 1.1951 0. 5821 0. 2861
2. 041 0. 841 -0. 281 -0. 331 -0. 721 -0. 911 -0. 051 0. 631 1. 281 1. 841 1. 911
0. 2861 0. 9341 1. 2151 1. 2961 1. 244 I 1. 2761 1. 2251 1.2921 1. 2551 1. 3031 1. 2331 0. 9311 o. 290 I
0. 2781 0. 9081 1.1921 1. 2731 1. 2391 1. 287 I 1. 2311 1. 2881 1. 2421 1. 2791 1.1991 0. 9121 o. 280 I
2. 811 2. 851 1. 961 1. 791 0. 381 -0. 851 -o. 48 I 0. 311 1. 04 I 1. 851 2.831 2 .121 3. 631
0. 6341 1. 200 I 1. 3851 1. 265 I 1.1411 1.2141 1.1561 1. 2171 1.1471 1. 2611 1. 3791 1.1871 0. 6251 6 0. 6191 1.1731 1. 3581 1. 2421 1.128 I 1. 2081 1.1611 1. 2091 1.130 I 1. 24 61 1. 3621 1.1761 0. 6211
2. 351 2. 321 2.021 1. 851 1.141 0. 481 -0. 411 0. 691 1. 54 I 1.20 I 1. 231 0. 891 0. 691 I 0. 2691 1. 088 I 1. 3261 1. 4261 1. 3191 1. 230 I 1.2471 1. 3231 1. 24 o I 1. 223 I 1. 3051 1. 4051 1. 294 I 1. 0651 0. 2631 7 I 0. 2631 1. 0661 1. 2951 1. 400 I 1. 297 I 1. 2121 1. 2211 1. 3121 1. 2211 1. 214 I 1. 2991 1. 4031 1. 297 I 1. 067 I 0. 2641 I 2. 261 2.071 2. 371 1. 871 1. 661 1. 491 2 .121 0. 811 1. 531 0. 781 0. 471 0 .131 -0. 261 -0 .181 -0. 411 I 0. 2961 1.1041 1. 274 I 1. 328 I 1. 2621 1.1791 1. 3231 1. 2861 1. 3081 1.165 I 1. 240 I 1. 2991 1. 2391 1. 0791 0. 2881 8 I o. 290 I 1. 0861 1. 2631 1. 310 I 1. 24 61 1.1661 1. 3111 1. 2851 1.3111 1.1671 1. 24 61 1. 3111 1. 2631 1. 08 61 o. 290 I I 2. 041 1. 651 0. 911 1. 411 1. 311 1.131 0. 881 0.111 -0. 211 -0.131 -0. 481 -0. 90 I -1. 90 I -0. 641 -0. 741 I 0. 2691 1. 088 I 1. 3211 1. 4221 1. 3111 1. 2211 1. 2231 1. 300 I 1.190 I 1.1891 1. 2791 1. 3831 1. 278 I 1. 0571 O. 2611 9 I 0. 2641 1. 0671 1. 2971 1. 4021 1. 2991 1. 2131 1. 2211 1. 3121 1. 2211 1. 2121 1. 2971 1. 400 I 1. 295 I 1. 0661 0. 2631 I 1. 90 I 1. 981 1. 871 1. 451 0. 891 0. 631 0.171 -0. 931 -2.511 -1. 89 I -1. 381 -1. 231 -1. 30 I -0. 821 -0. 621
0. 6371 1. 2151 1. 3821 1. 2531 1.1331 1. 2131 1.1441 1.180 I 1.100 I 1. 2161 1. 3381 1.1581 0. 6191 10 0. 6211 1.1761 1. 3621 1. 2451 1.130 I 1. 2091 1.1611 1. 2081 1.128 I 1. 2421 1. 3581 1.1731 o. 620 I
2. 60 I 3.341 1. 50 I 0. 611 0. 261 0.301 -1.441 -2. 311 -2. 471 -2.071 -1.441 -1. 271 -0. 241
0. 2851 0. 9291 1. 207 I 1. 2731 1. 235 I 1.2741 1.1941 1. 2511 1.192 I 1. 2351 1.1681 0. 8931 0.2761 11 0. 2791 0. 9121 1.198 I 1. 2781 1. 2421 1. 2881 1. 2311 1. 2871 1. 239 I 1. 2731 1. 1921 0. 9081 0.2781 2 .321 1. 831 0. 791 -0. 421 -0. 591 -1.111 -3. 021 -2. 781 -3. 751 -2. 981 -2.051 -1. 65 I -0. 871
0. 2851 0. 5811 1.1881 1. 3441 1. 3681 1. 24 61 1. 354 I 1. 319 I 1.1611 0. 5571 0. 2781 12 0. 2851 0. 5811 1.195 I 1. 354 I 1. 384 I 1. 2691 1. 3821 1. 350 I 1.188 I 0. 5691 0. 2831

-0 .121 0. 081 -0. 571 -0. 771 -1.191 -1. 851 -2. 051 -2. 271 -2 .271 -2. 071 -1. 721 0.2831 0. 9011 1. 155 I 1.2661 1. 2261 1. 2631 1. 1531 0. 8881 0. 2771 13 O. 284 I 0. 9071 1.1661 1.2801 1. 2421 1. 278 I 1. 162 I 0. 9021 0. 2821

-0. 241 -0. 691 -0. 921 -1.121 -1. 291 -1.181 -0. 761 -1. 511 -1. 781

0. 2751 0. 6091 1. 0431 1. 0611 1. 0471 0. 6091 0. 2731 14 0.2781 0. 6151 1. 054 I 1. 0711 1. 0531 0. 613 I 0. 2761

-0. 981 -1. 031 -1. 081 -0. 921 -0. 521 -0. 69 I -1.111

0. 2561 0. 2831 0. 2581 15 0. 260 I 0. 2861 o. 260 I

-1. 611 -0. 951 -0.581 AVERAGE ABSOLUTE PERCENT DIFFERENCE 1. 2 ANALYTICAL AXIAL OFFSET= 9.394 %

STANDARD DEVIATION= 0.833 MEASURED AXIAL OFFSET= 7.387 %

Summary:

QPTR: _ _l_.0_07_2_-+-_l_.0_0_71_

1.0032 0.9825 Page 34 of 49

Serial No.20-067 Docket No. 50-280 Figure 6.2 ASSEMBL YWISE POWER DISTRIBUTION 70.62% 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

0. 2781 0. 3141 0. 2791
0. 2791 o. 310 I O.280 I

-0.271 1.341 -0.371

0. 2881 0. 6261 1. 0581 1. 094 I 1.0611 0. 634 I 0. 2921
0. 2921 O. 6331 1. 0671 1.107 I 1. 0681 0. 634 I 0. 2931

-1. 281 -1.111 -0. 891 -1.131 -0. 691 0. 01 I -0.191

0. 2951 0. 9011 1.145 I 1. 2561 1. 2121 1.2581 1.1571 0. 9151 0. 2961
0. 2981 0. 9121 1.1571 1. 2671 1. 2371 1. 268 I 1.160 I 0. 9161 0.3011

-1. 071 -1. 221 -1. 011 -0. 851 -2. 041 -0. 831 -0. 291 -0.111 -1. 771

0. 3011 0. 5841 1. 1621 1. 3131 1. 3421 1. 2361 1. 3511 1. 331 I 1.1891 0. 6031 0. 3041
0. 2991 0. 5861 1.1791 1. 3261 1. 3551 1. 250 I 1. 3571 1. 330 I 1.184 I 0. 5981 0. 3011
0. 721 -0. 311 -1.471 -0. 981 -0. 981 -1.111 -0. 431 0. OB I 0. 411 0. 771 0. 971
0. 2971 0. 9311 1.1881 1. 260 I 1. 2271 1. 260 I 1. 2131 1. 2761 1. 24 41 1. 2751 1. 2051 0. 9291 O. 300 I
0. 2931 0. 9151 1.1811 1. 260 I 1. 2331 1. 2751 1. 2211 1. 2751 1. 235 I 1. 264 I 1.1861 0. 9191 0. 2941
1. 431 1. 711 0. 611 -0. 041 -0. 461 -1.151 -0. 671 0.111 o. 70 I 0. 851 1. 621 1.131 2 .191
0. 6431 1.1751 1. 3421 1. 2431 1.1631 1. 2131 1.1541 1. 2221 1.183 I 1. 250 I 1. 3441 1.1711 o. 640 I
0. 6371 1. 164 I 1. 3321 1. 235 I 1.160 I 1.2121 1.1611 1.2131 1.162 I 1. 2381 1. 334 I 1.1661 0. 6381
0. 871 0. 971 0. 781 0. 691 0. 271 0. 051 -0. 611 0. 711 1. 781 0. 931 0. 771 0. 451 0. 291 I o. 2831 1. 084 I 1. 2881 1. 3821 1. 2951 1. 2271 1. 2381 1. 3111 1. 2391 1. 230 I 1. 2911 1. 3731 1. 2761 1. 075 I 0. 2821 7 I o. 2821 1. 0761 1. 2791 1. 370 I 1. 2831 1. 2151 1. 2191 1. 3011 1. 2181 1. 216 I 1. 284 I 1. 3721 1. 280 I 1. 077 I 0. 2821 I o. 531 0. 771 0. 741 0. 871 0. 951 0. 981 1. 571 0. 751 1. 761 1.13 I 0.531 0. 061 -0. 311 -0 .171 -0 .171
0. 3131 1.124 I 1. 2571 1. 2991 1. 250 I 1.1761 1.3121 1. 2771 1. 3011 1.170 I 1. 232 I 1. 2791 1. 2311 1.1131 0. 3121
0. 3121 1.1171 1. 2531 1. 2871 1. 2341 1.164 I 1.300 I 1. 2731 1. 300 I 1.164 I 1. 234 I 1. 287 I 1. 2531 1.1171 0. 3121 0 .181 0. 661 0. 341 0. 951 1. 321 1. 061 o. 90 I O. 30 I 0. 081 0. 48 I -0 .161 -0. 631 -1. 731 -0.351 -0 .141 I 0. 2851 1. 0911 1. 2991 1. 3891 1. 2961 1. 2261 1. 2261 1. 2951 1.1921 1. 2031 1. 2731 1. 3591 1. 2661 1. 070 I 0. 2841 9 I 0. 2821 1. 0771 1. 280 I 1. 3721 1. 2841 1. 2161 1. 2181 1. 300 I 1. 2191 1. 2151 1. 2831 1. 370 I 1. 2791 1. 0761 0. 2821 I 1.111 1. 341 1.521 1. 20 I 0. 951 0. 861 0. 681 -0. 421 -2.231 -0. 95 I -0. 761 -0. 781 -1. 00 I -0. 551 0. 791
0. 6521 1. 2021 1. 3551 1. 2481 1.1711 1. 230 I 1.1531 1.1931 1.1421 1. 2211 1. 3221 1.1531 0. 6321 10 0. 6381 1.1661 1. 334 I 1. 2381 1.1611 1.2121 1.160 I 1. 2121 1.160 I 1. 2351 1. 3321 1.164 I 0. 6371 2 .171 3 .131 1. 541 0. 811 0. 841 1. 491 -0. 641 -1. 561 -1. 58 I -1.121 -0. 781 -0. 931 -0. 821
o. 300 I 0. 9341 1.1971 1. 2651 1. 2371 1. 2721 1.1941 1. 2521 1. 202 I 1. 24 o I 1.167 I 0. 9051 o. 290 I 11 0. 2941 0. 9191 1.1861 1. 2631 1. 235 I 1. 2751 1. 2211 1. 2751 1. 233 I 1. 260 I 1.1811 0. 9151 0. 2931
1. 921 1. 681 0. 961 0 .131 0.131 -0.251 -2 .181 -1. 831 -2.531 -1.581 -1. 20 I -1.111 -0. 961
0. 2981 o. 600 I 1.1861 1. 3291 1. 350 I 1. 2371 1. 3421 1. 3111 1.165 I 0. 5761 0. 2941 12 0. 3011 0. 5971 1.1841 1. 330 I 1.3571 1.2491 1. 3551 1. 3261 1.1791 0. 5861 0. 2991

-1. oo I 0. 461 0.151 -0. 081 -0.50 I -0. 961 -0. 961 -1.111 -1.211 -1. 781 -1. 771

0. 3011 0. 9191 1.160 I 1. 2651 1. 2331 1. 2661 1.1611 0. 9081 0. 2951 13 o. 300 I 0. 9161 1.1591 1. 268 I 1. 2371 1. 2671 1.1571 0. 9121 0. 2981
0. 441 0. 351 0. 061 -0.251 -0.311 -0. 061 0. 331 -0. 471 -1. 021
0. 3011 0. 6351 1. 0661 1.1071 1. 0771 0. 636 I 0. 2911 14 0. 2931 0. 6341 1. 0681 1.1061 1. 0671 0. 632 I 0. 2921
2. 671 0.171 -0.181 0.111 0. 981 0. 61 I -0.181
0. 2741 0. 3091 0.2811 15 O. 280 I 0. 3091 0.2791

-2 .171 -0.031 0. 831 AVERAGE ABSOLUTE PERCENT DIFFERENCE 0.9 ANALYTICAL AXIAL OFFSET= 3.301 %

STANDARD DEVIATION= 0.610 MEASURED AXIAL OFFSET= 1.733 %

Summary:

QPTR: _ _0_.9_9_9_8-+---1_.0_03_3_

1.0066 0.9904 Page 35 of 49

Serial No.20-067 Docket No. 50-280 Figure 6.3 ASSEMBL YWISE POWER DISTRIBUTION 99.93% 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

0. 2871 0. 3221 0. 2881
o. 290 I 0. 3251 o. 290 I

-0. 931 -0. 961 -0. 661 0.2921 0. 6281 1. 0531 1.1261 1.0561 0. 634 I 0. 2961 0.2961 o. 6351 1. 0641 1. 137 I 1. 0641 0. 636 I 0. 2971

-1.321 -1.111 -1. 02 I -0. 981 -0. 731 -0.38 I -0. 471

0. 2991 0. 8891 1.1261 1. 2391 1. 2151 1. 2431 1.1371 0. 9011 o. 300 I 3 0.3031 0. 9011 1.1391 1. 2511 1. 230 I 1. 2521 1.1411 0. 9041 0. 3061

-1. 341 -1. 381 -1.151 -0. 961 -1. 211 -0. 70 I -0. 38 I -0.291 -1. 881

0. 3041 0.5851 1.1431 1. 290 I 1. 3231 1. 220 I 1. 3311 1. 3071 1.1671 0. 6041 0. 3081
0. 3031 o. 590 I 1.1611 1. 304 I 1. 3371 1. 2371 1. 3381 1. 308 I 1.1661 0. 6011 0. 3061
0. 381 -0.821 -1. 551 -1. 061 -1. 071 -1.411 -0. 531 -0. 05 I 0 .121 0. 421 0. 661
0. 2991 0. 9111 1.1611 1. 2411 1. 2311 1. 268 I 1. 2151 1. 278 I 1.2501 1. 260 I 1.1811 0. 9141 0. 3031 5 0. 2971 0. 9041 1.1631 1. 250 I 1. 240 I 1. 277 I 1. 2231 1. 2781 1. 2411 1. 254 I 1.167 I 0. 9071 0. 2981
0. 721 0. 771 -0.141 -0. 741 -0. 721 -0. 681 -0. 661 0. 021 0. 69 I 0. 491 1.171 o. 80 I 1. 561
0. 6421 1.150 I 1. 310 I 1. 2331 1. 2211 1. 234 I 1.1691 1. 2431 1. 2511 1. 2551 1. 320 I 1. 150 I 0. 6411 6 0. 6391 1.1451 1. 310 I 1. 2411 1. 2231 1. 234 I 1.1761 1. 234 I 1. 225 I 1. 2431 1. 3121 1.14 61 0. 6391
0. 491 O. 40 I -0.011 -0. 671 -0.151 -0. 041 -0. 581 0. 721 2.111 1. oo I O. 60 I 0.391 0. 381 I 0. 2941 1. 078 I 1. 2691 1. 3571 1. 2921 1. 2451 1. 250 I 1. 3161 1. 2481 1. 252 I 1. 294 I 1. 3531 1. 2591 1. 0711 0. 2921 7 I 0. 2921 1. 0711 1. 2621 1. 350 I 1. 2851 1. 2361 1. 234 I 1. 3081 1. 2331 1. 2371 1.2861" 1. 3511 1. 2631 1. 0721 0. 2931 I 0. 571 0. 631 0. 521 0. 531 0. 511 0. 731 1. 321 0. 611 1. 251 1. 24 I 0. 611 0.171 -0. 281 -0.111 -0. 30 I I 0.3271 1.155 I 1. 252 I 1. 2871 1. 2551 1.1921 1.3201 1. 2821 1. 3091 1.190 I 1. 237 I 1. 2691 1. 227 I 1.1441 0. 3271 8 I 0. 3271 1. 14 61 1. 2441 1. 2741 1. 235 I 1.180 I 1. 308 I 1. 2791 1. 308 I 1.100 I 1. 235 I 1. 2741 1. 2441 1.14 61 0. 3271 I 0.051 0. 751 0. 631 1. 021 1. 651 1. 051 0. 891 0. 271 0. 071 0. 86 I 0.131 -0. 421 -1. 40 I -0 .181 -0.081 I 0.2951 1. 0851 1. 2811 1. 3691 1. 3021 1. 2511 1. 2451 1. 304 I 1. 2081 1. 2311 1. 2791 1. 3421 1. 2521 1. 0671 0. 2931 9 I 0. 2921 1. 0721 1. 2631 1.3511 1. 2861 1. 2371 1. 2331 1. 3081 1. 234 I 1.2361 1. 2851 1. 350 I 1. 2621 1. 0711 0.2921 I 1.141 1.261 1. 40 I 1. 331 1. 251 1.151 0. 941 -0.30 I -2. 091 -0. 371 -0. 481 -0. 591 -0. 821 -0.391 0. 321
0. 6521 1.1761 1. 3321 1. 258 I 1. 2391 1.2591 1.170 I 1. 2181 1. 210 I 1. 230 I 1. 3011 1.1361 0. 6361 10 0. 6391 1.14 61 1. 3111 1. 2431 1. 224 I 1. 2341 1.1761 1. 2341 1. 2241 1. 2411 1. 310 I 1.1451 0. 6391
2. 011 2. 651 1. 571 1. 20 I 1. 221 2. 011 -0. 521 -1. 331 -1.171 -0. 921 -0. 691 -0. 791 -0. 441
0. 3031 o. 920 I 1.180 I 1. 2621 1. 2471 1. 27 61 1.194 I 1. 2571 1. 218 I 1. 230 I 1.1491 0. 8941 0. 2951 11 0. 2971 0. 9061 1.1671 1. 2531 1. 2411 1. 2781 1. 2231 1.2771 1. 240 I 1. 250 I 1. 1631 0. 9041 0. 2971
1. 951 1. 581 1.131 0. 731 0. 471 -0.151 -2. 40 I -1. 551 -1. 81 I -1. 621 -1. 20 I -1. 091 -0. 771
0. 3021 0. 6041 1.170 I 1. 3091 1. 330 I 1. 2251 1.3261 1. 294 I 1.14 91 0. 5791 0. 2991 12 0. 3051 o. 600 I 1.1651 1. 3071 1. 3381 1. 2371 1. 337 I 1. 3041 1.1611 o. 590 I 0. 3031

-0. 971 o. 64 I 0. 471 0 .141 -0.561 -0. 961 -0. 851 -0. 741 -1.061 -1. 861 -1. 451

0. 3071 0. 9091 1.1421 1. 2491 1. 2261 1. 2521 1.1461 0. 8981 0. 3011 13 0.3051 0. 9041 1.14i I 1. 2521 1. 230 I 1. 2511 1.1381 0. 9011 0. 3031
0. 581 0. 531 0.071 -0. 261 -0.301 0. 071 0. 731 -0. 291 -0. 781
0. 3041 O. 6381 1. 0621 1.1381 1. 0731 0. 639 I 0. 2961 14 0. 2961 0. 6361 1. 064 I 1.1371 1. 064 I 0. 635 I 0. 2961
2. 811 0. 281 -0 .151 0.121 0. 881 0. 69 I 0. 081
0. 2851 0. 3241 0.2921 15 o. 290 I 0.3251 O. 290 I

-1. 881 -0 .161 0. 721 AVERAGE ABSOLUTE PERCENT DIFFERENCE 0.8 ANALYTICAL AXIAL OFFSET= 1.402 %

STANDARD DEVIATION= 0.563 MEASURED AXIAL OFFSET= 1.934 %

Summary:

QPTR: _ _0_.9_9_74_---+-_l._00_2_6_

1.0076 0.9924 Page 36 of 49

Serial No.20-067 Docket No. 50-280 SECTION 7 - CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 1 Cycle 30 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, technical specification limits, or COLR limits. The AREYA AGORA LTAs show no signs of anomalous behavior and are performing as expected. It is anticipated, based on the results associated with the SIC30 startup physics testing program, that the Surry 1 core will continue to operate safely throughout Cycle 30.

Page 37 of 49

Serial No.20-067 Docket No. 50-280 Table 7.1 SURRY UNIT 1 - CYCLE 30 STARTUP PHYSICS TESTS STARTUP PHYSICS TESTING RESULTS

SUMMARY

Measured Predicted Diff (M-P) or Design (M) (P) (M-P)/P,% Tolerance Parameter Critical Boron Concentration 1588 1589 -1 +/-39 (HZP ARO), ppm Critical Boron Concentration 1410 1407 3 +/-28 (HZP Ref Bank in), ppm Isothermal Temp Coefficient -1.771 -2.267 0.496 +/-2 (HZP ARO), pcm/F Differential Boron Worth -7.52 -7.66 -1.8% +/-10%

(HZP ARO), pcm/ppm Reference Bank Worth 1338 1386 -3.5% +/-10%

(B-bank, dilution), pcm A-bank Worth (Rod Swap), pcm 287 299 -12 +/-100 C-bank Worth (Rod Swap), pcm 622 662 -6.1% +/-15%

SA-bank Worth (Rod Swap), pcm 951 980 -3.0% +/-15%

D-bank Worth (Rod Swap), pcm 1033 1061 -2.7% +/-15%

SB-bank Worth (Rod Swap), pcm 1067 1100 -3.0% +/-15%

Total Bank Worth, pcm 5298 5490* -3.5% +/-10%

S1C30 TestinQ Time: 8.0 hrs

[criticality 11/29/2019@ 01 :20 to end of testing 11/29/2019@ 09:19]

Last 5 Surry Startups:

S2C29 testing time: 6.5 hrs S1 C29 testing time: 8.0 hrs S2C28 testing time: 7.0 hrs S 1C28 testing time: 5.8 hrs S2C27 testinq time: 7.6 hrs

  • Total bank worth is calculated using individual bank worth with higher precision than reported.

Page 38 of 49

Serial No.20-067 Docket No. 50-280 SECTION 8 - REFERENCES I. P.H. Smith, "Surry Unit 1, Cycle 30 Design Report", Engineering Technical Evaluation ETE-NAF-20190119, Rev.

0, October 2019.

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 Report NE-1466, Rev. 0, January 2006.

6. M. R. Merholz & K. A. Twum, "Surry Unit 1, Cycle 30 TOTE, Core Follow, and Accounting Calculations",

Calculation PM-2058, Rev. 0, November 2019.

7. K. L. Kennett, "Surry Unit 1 Cycle 30 Flux Map Analysis", Calculation PM-2059, Rev. 0, and Addenda A - B, November & December 2019.
8. D. T. Smith, "Reload Safety Evaluation Surry 1 Cycle 30 Pattern APO," EVAL-ENG-RSE-S1C30, Rev. 0, October 2019.
9. B. R. Kinney, "Implementation ofRMAS version 7.15.04 and ANSI Standard Rod Swap Technique at Surry Units 1 and 2," Engineering Technical Evaluation ETE-NAF-2019-0103, Rev. 0, October 2019.
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. S. B. Rosenfelder, "Surry Unit 1 Cycle 30 Full Core Loading Plan (Revision O)", Engineering Technical Evaluation ETE-NAF-20190027, Rev. 0, AprilO 2019.
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 O To 2 Steps Withdrawn As Fully Inserted When Measuring Control And Shutdown Banks During The Surry Startup Physics Testing Program," Engineering Transmittal ET-NAF-06-0046, Rev. 0, April, 2006.
14. D. B. Livingston, "Surry Unit 1 Cycle 30 Startup Physics Testing Logs and Results", Memorandum MEMO-NCD-20190440, Rev. 0, December 2019.
15. S. R. Ehrensberger, "The CECOR Flux Map Analysis Code Version 3.4 Additional Software Requirements and Design", Engineering Technical Evaluation ETE-NAF-2018-0021, Rev. 0, March 2018.
16. S. R. Ehrensberger, "Implementation ofCECOR Software System Using CECOR v3.4 and CECOR-GUI vl.7",

Engineering Technical Evaluation ETE-NAF-2018-0034, Rev. 0, March 2018.

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.
19. Surry Units 1 and 2 Updated Final Safety Analysis Report, Revision 51.01.

Page 39 of 49

Serial No.20-067 Docket No. 50-280 APPENDIX A - RCP STARTUP ORDER 11/19/2019 03:27 Started 1-RC-P-lCl (C RCP Aux oil Pump) IAW l-OP-RC-001. White light (pressure) lit immediately.

0350 Cycled l-EP-BKR-15C3 in Test IAW l-OP-RC-001. All checks SAT. Secured 1-RC-P-lCl.

0416 1-EP-BKR-15C3 racked back to Disconnect. Awaiting installation of PRZR Safety Valve to remove breaker blocking device (T/0).

SPS Unit 1 Control Room Log HUMPHRIES, JOSHUA A 11/19/2019 11:19 Notified that 'B' PZR Safety Valve is installed. Verified TS 3.1.G remains met. Commenced PZR Fi Solid conditions IAW l-OP-RC-002. Pzr level is 57%, RWST level is 93.7%.

1-CH-311 previously closed. Opened 1-CH-MOV-1 311 and closed 1-CH-MOV-131 OA in preparati, for Hydrazine Addition to the PZR.

1131 Commenced 1 gal Hydrazine addition IAW 1-0P-CH-008.

Seal injection is in service \Vith the follmving flowrates:

A RCP: 8.1 gpm B RCP: 7 .9 gpm C RCP: 8.2 gpm 1204 Completed I gallon Hydrazine add to the PZR IAW 1-0P-CH-008 in preparation for filling th, PZR solid.

1205 Continuing to raise PZR level using the RWST. Pzr level is 74.3%, RWST level is 92.5%.

1209 1-CH-LCV-1 l 15A is in Divert. l-RC-FL-2 is bypassed.

1236 l-CH-LCV-ill5A is in AUTO IAW l-OP-CH-008. l-RC-FL-2 is in service.

1239 1-CH-311 is open, l-CH-MOV-1310A is open, 1-CH-MOV-1311 is closed.

1253 PZR level by 1-RC-LI-1460 (cold Cal Channel) is 102.5%. Continuing to fill the PZR solid.

1257 Unit 1 RCS is solid. PRZ level is 102.9% by 1-RC-LI-1460 (Cold Cal Channel). Level is rising in the PRT. Closed PZR PORV's and commenced raising RCS pressure to 100 psig. RWST Level is 91.0%.

1336 RCS pressure is stable at 105#. Pressure control band of 100-120#.

1456 l&C has vented 1-CH-PT-1156, -1155 , -1154.

Page 40 of 49

Serial No.20-067 Docket No. 50-280 1544 Completed venting all RCP seals IAW 1-0P-RC-003. Commence raising RCS pressure to 300#

1620 RCS pressure is 300# and stable. Pressure control band of 290-320#

1645 O-OP-EP-004 Completed; Load shed system s,;vitch placed in NORM ENABLE.

1648 Started 1-RC-P- lC for continuous operation.

SPS Unit 1 Control Room Log MAJOR, SHATEEK RAS ON 11/19/2019 11:45: I concur with TS assessment. LO TG, CLEON MAURICE 11/22/2019 02:28 A and B RCP Breaker cycling in ~EST IAW 1-0P-RC-001:

Started 1-RC-P- lBI (B RCP Aux oil Pump) IAW 1-0P-RC-001 Section 5.9. White light (pressure) lit inunediately.

0234 Cycled l-EP-BKR-15B3 in Test IAW 1-0P-RC-001. All checks SAT. Secured 1-RC-P-lBl.

0235 l-EP-BKR-15B3 remains racked to TEST due to personnel working nearby. Will rack to Connect when it ,vill not impact ongoing work. 1-0P-RC-001 Section 5.9 remains open at step 5.9.11 to rack breaker as desired.

0300 Racked l-EP-BKR-15A3 (A RCP Breaker) to Test. Started 1-RC-P-lAI (A RCP Aux oil Pump)

IAW 1-0 P-RC-001 Section 5.8. White light (pressure) lit immediately.

0305 Cycled l-EP-BKR-15A3 in Test IAW l-OP-RC-001. All checks SAT. Secured 1-RC-P-lAl.

0308 l -EP-BKR-15A3 racked back to Disconnect. Breaker block remains installed for T/0 l-RCA-0009A.

0328 l -EP-BKR-15B3 has been racked to Connect for future start.

SPS Unit 1 Control Room Log HUMPHRIES, JOSHUA A 11/22/2019 14:38 Started 1-RC-P- lA IAW l -OP-RC-001 and 1-GOP-1.7.

'A' RCP Vibrations are:

Shaft: 7mils/6mi.ls Frame: l .2mils/0.8mils SPS Unit I Control Room Log MAJOR, SHATEEK RAS ON Page 41 of 49

Serial No.20-067 Docket No. 50-280 11/26/2019 00:01 The Security Diesel is in service IAW O-OP-SE-002 section 6.1. Started 'B' RCP IAW 1-0P-RC-001.

Shaft Vibrations: 7.0 mils, Frame Vibrations: .5 mils 0023 Stabilizing RCS Temp at 190°F to support l-NPT-RX-012, WR RID Cross Calibration.

0042 RX Eng has completed data collection. Commenced RCS heatup. Heat up rate is approximately 20°F/hr 0056 Unit 1 RCS ('C' Hot Leg) has exceeded 200°F. Unit 1 is no,v in Intermediate Shutdov.n. Shutdo,vn margin remains 1560 ppm.

0142 RCS temperature is 225°F (by Thot on "C" Loop, highest indicated). Current heat-up rate is -37°FIHr.

0242 RCS temperature is 261 °F (by Thot on "C" Loop, highest indicated). CU1Tent heat-up rate is -32°FIHr.

SPS Unit 1 Control Room Log GRAY, ED Page 42 of 49

Serial No.20-067 Docket No. 50-280 APPENDIX B- STARTUP PHYSICS TEST

SUMMARY

SHEETS Page 43 of 49

Serial No.20-067 Docket No. 50-280 S~rry Power Station Unit 1 Cycle 30 stf ~1up Physics Test Su~mary Sheet* Formal Tests {Page 1 of 6)

Measured Value Design Criteria

.r, I

Acc~ptance Criteria i

Design Acceptance Criteria Met Criteria Met IJatel Time of I111 I Preparer/

Reviewer Zero Pi;wer Testing Range Detem/inafio__11_ ./

ZPTR= ckground < ZPTR < POAH i7 Yes ti f'llt/<"t It!- Cf to (lf- 7 Background* Z,C '": l amps (./v .~i..) NIA _ _ No NIA ~tb TSP ?14(

amps POAH= z, amps **

t":-:;.~:=-r:.:;;;~y----,------1--------~RtactivityComputer p.,...tU.>V? -!&, "f'--,,----*r-* Chec:ko'ut--------,--.,...--,-----------'

(measured reactivity)

PFdS.,t.f/-Y"i.ot.'

I{( c- pt}/pt}I x 100%S4.00%'  ;* Yes I

,,,~ lt1 "'(.IP I (predicted reactivity}

pcm Pre-crillcal Ben h Test Results -ny, /-too '*:..pcm

~

NIA

_ _ No NIA ()21CS' ~1<<

The allowable r nge Is set to Iha larger of the m~~sured

%D={(pc-p~x;oo%

%0 * -o,.., * - o,V1 01,o results or the p e-critlcal ench test.

Allowable rang Zo ~too pcm Irs/' (

Crlb(;:at Boron Conaentrallon

  • i./\RO

,(Ce)M1,IIO*

/!.Ta ppm (Ce)AR0=2 589 :I: 39 ppm or 300 pcm ..,.,.(,:,*.:, I l&,4 Ailf. 11/z.'i ftl 1 laCe ~.;~(Cs)Mol S 1000 pcm l(TS4.10A]

~ Yes I .,,,- Yes ltlt~l'f

,,ZrtS ~,

, 1*

(Adjust to design oondltfons) ll(C.,}ARO=(c,j)MARO * (Cs)Mo_* ~ ..  ;. ppm aC!!."fL*7.57 pcm/j)pm Nol No I lsother)nal Temperature Coefflc/e*

  • ARO I v<

t,,.._ _ _ _ _ _ _ _ _ _ _ _ _ _ _....,._ _ _ _ _ _ _ _ ___

{ar 180

)MARO" (ar 180

),.Ro =2 z. U'"'I :I: 2 pcm/'F

.ii 1.

0 T1sos;~M11m .. 0 /no+arooP ar190 :J. 3.85 pcm/'F

~Yes Yes

,,,1v,1,, ~I

- /,-, '1 t pcm/'F where: (aM"'"); !j 6 pcml"F {COLR 3.4] - - f!)z:p K.tti 0

(al lMARO-(al 0

JARo= Q*"f ' " ' ~m/'F (ar"""l'il 0.5pcm/'F _ No _No L (ar°Dl)~; -1.65 pcm/'F Control Bank 8 w~.~ Measuroment, Rod-SWj,p Reference Bank Ia R!P,M.,.

/ 13 8 pcm I a REF:21386 :I: 10%

100x(Meaq. - Des.)/Oes. = - 3. 5" r

.i... %

NIA 7 ° Yesl No NIA ,,,12.1/ll,~

a,<:03 ,...tf/.11**

References 1.) ONES-AA-NAF-NCD-4015 .--

2.) ETE-NAF-~19-0119 3.) ETE*NAF,19-0120 Page 44 of 49

Serial No.20-067 Docket No. 50-280 Surry Power Station Unlt 1 Cycle 30 Staaup Physics Test ~ummary Sheet~ Fonnal Tests (Page 2 of 6}

r.. : '

Measured Value Design Criteria { I A~ceptance Criteria I -Design IAcceptance Criteria Met Criteria Met ITl.;;w~f I Preparer/

Reviewer I'"------------1.:---.. .1---------Crl-U-ca-l!oron Concentration-':' Bank In (Cu) u =' 1408 + 4.\(Ce)ARO :I: 28 ppm / ** I

( Ce}M a = /o//O ppm t.(Cako= - I ppm (from-ab1'i1*e)  ; / Yes N/A

" ~ IfPt; 28 ppm ~~\,, \ No p~J, \

= ..3 HZP Borf.lri Worth Coefficient Mnsurement --

<<Ce -7.66 ::I: 0.77 pcm/ppm (o.Ca)M:  ?,!t"Z--

pcm/ppm tiaC 8=(aC )" * (aC 1) = 0' /'f pcm/ppm NIA y::1 NIA

..._____----------(,-A-R-8)3-=,1.-_____:1:_1_o_o_p_cm_:~  !

Control sa!,"i~rtl!Measuremanf, Rod Swap I I7  !- ---- - .

NIA pcm Mea$.

  • Des. = - / '2,-- pcm(;: *. ~ 0 A

--cz-z_ ~ """"'s.;"'c""""-.-"I.""'._ , ~

I n.s,.

C pcm I ~o~~=a~. -~:~s. = :_:~~ I  ;;;, % I ,\ NIA I I

> ~ 0 A I1~~ 1~

- ,-<-,-Ra-.-.-..-!--,9"""8\""o..---:1:-1s-%---.,:r l Shutdown B~.k SA Worlh MeasuremJ~t. Rod Swap

~

~

0 pcm SA J t -

100x(Mea .

  • Das.)/De!*=~ - 3,0 ~- %

'.l control Barik D Worth Measuram1111tJ!Rod swap NIA 0

'A I

~

{I O R8)",, \ /06, / :I: 15% 1i*: NIA pcm 100x{Mea~.

  • Des.)/Des. * -z,7 :,*.% 0 Shutdown 81~k SB Worlh Measuremef#, Rod Swap I

89 RS-

/Ot:.'1- I l(' - :I: 15%

?,. 0

'.1' 1_ I l **--~A 100X(Meas

  • Oas.}/Oes. = - '! NIA v~

pcm  % No

- J T,;ital Rod Worth, Rod Swap Ir....=

3

pcm--r--1-0(-~;v-(M~:-as~.~O~a!"'!s.~)/De,;--11.-=-~-3--,}--~.%

$"2.9~

10 I  ;\

1 NIA I:z__ ,e,.I-' NIA I  ?&k: I References 1.) DNe.S-AA-N F-NCD-4015 1*

2.) e.TE-NAF-2 9-0119 1

.1:*

~)ETE-NAF~T" .\

1-

t.j' Page 45 of 49

Serial No.20-067 Docket No. 50-280 Surry Power Stati,.:m Unit 1 Cycle 30 Startup Physics Test Summary Sheet* Formal Tests (Page3of6) uaw, De$1gn Aceeptanee Preparer/

Measure fValue  : Design Criteria Acceptance Crlterfa Tlmeof Criteria Met Criteria Met T,...t Reviewer

" WO Flux Map, Power :s 50%

Map Power I.eve! ( %FUR Power)"' 29. .r.;~ ,*

Max Relative Ass, 1mb4y Power, %D1FF (M*P)IP !i 11/JIJ/Jq fHS C\'SC

%01FF*  :::i:10% for P1 l!! 0.9 _L. Yes KL!<

.. 1,._ 'B

'2. (,.,

% ror Pia 0.9 fd:15% for P1< 0.9 NIA

-- No NIA

%for Pi< 0.9 {Pi"' as,y power)1' 2 Nuclear- Hot Channel Factor, FaH(N) i

>0 IJ5* -£_ Yes F6H(N}* NIA :AH(N) s 1.635*{1+0.s*c1 - P {COLR 3.7.21 NIA 

                                                      *.                                                                                                 No Peak To<<al Heat FIUx Hot Channel Factor, Fg(Z)         '

Fc(Z)* ~.'A'!: 0 NIA FQ(Z) s: 5.0 ~ K(z} {COLR3.7.1} NIA I _L. Yes No Maximum Poeltiv , lncore Quadrant Power TIit ' Tlltw J_tx}1~~ s 1.02' NIA _£_ Yes NIA vi No References 1.} DNES*AA-NAF-f,ICD-4015 2.) ETE-NAF-2019-p119 3.) ETE-NAF*201 S.0120 Page 46 of 49

Serial No. 20-067 Docket No. 50-280 I Surry Power Station Unit 1 Cycle 30 Startup Physics Test Summary Sheet - Formal Te,ts (Page 4 of 6) Date/ peslgn Acceptance Preparer/ Measured Value Design Criteria Acceptance Criteria Time of Crjterla Met Criteria Met Tae+ Reviewer MID i=Jux Map, 65% S Power S 75% i Map Power Level (% Full Power) = zo.,i :II I Max Relative Assembly Power, %D1FF (M-P)/P i I 

                                                     +/-10% for P1 :i: 0.9

%DIFF= 3.1 

                                                                                                                                   +Yes                      1,./,/10,.
2. r
                    % for Pl:i:0.9
                    %for Pl< 0.9
                                                     +/-15% for P;< 0.9

{P1= assy power)1*2 NIA _1_ No 

                                                                                                                                     *I
                                                                                                                                     'I NIA Olf~l.!O
                                                                                                                                                                           /<t.K. ii1 Nuclear Enthalpy Rise Hot Channel Factor, Ft..H(N)

F.t.H(N)= I. s-o, NIA FLlH(N) :s 1.635.{1 +0.3*(1

  • P)) [COLR3.7.2)
! ..,!L_Yes
                                                                                                                                     'I NIA      _ _ No Peak Total Heat Flux Hot Channel Factor, FQ{Z) 1.1:fs <;                                                                                                                              _L_     Yes F0 (Z)=                                                     NIA                           FQ(Z) :s {2.5 I P}
  • K(z) [COLR3.7.1] NIA No if Maximum Positive lncore Quadrant Power TIit *I I

Tilt= 1:00 a, S1.02 1 NIA 

                                                                                                                                    .Y I

Yes No NIA I References 1.) DNES-M-NAF-NCD-4015 2.) ETE-NAF-2019-0119 3.) ETE-NAF-2019-0120 I Page 47 of 49

Serial No. 20-067 Docket No. 50-280 

                                             .suny PowetStatlon Unit tCy,cla 30iStiu:tup'.Pl'ly~lcsT~tsuanmary:SJte~t - Formal !r8'ts (Page'5 of~)
~e!lsute~Value OesJ~incCrlterla Acce¢aryce t.riierta Design IAcceptance Cri.teriil M.et Criteria Milt I* -rlaftiT T_t~~of I Reviewer l"(epan[lr/
                                                                                           'MID"FTU:XMap; 95%'s:Po.wer.!!L100%
    • ,Ml!P PqWJtrLf}veH(%,FuRFoweft~= C\!l;'{~~q~

M!IX..R8l!i!t1V&.,A!!silin~Y.Po~r;.%01Ff.:(Wl'!}/P, 

 %0.IFF=                                                              :1:10%:for ~~ D.9                                                                    v""' Yes.

z.. C, /  %,f9tPi:1!,0.9 +/-.15%-'for'P(<:0.9. NIA *--.* No '.NIA :ti{s{:t<lf, 2.,'il' "'*  %!0rPl,<:0.9. (P,=assypower:)!,Z ~o. . tiiuci_ear'E~_alj)y'.Rlst1Hclt:Challnill* Factorl'liliH(N) 1 I'>>t#lt,,M; F,'AH(N)=- L ~~ ./ N/A FAJ-!(N)s 1.635*{1+0.3'{1

  • P)}

tcotRa:?*:2] NIA ' - *- Yes, No eealiTotal'.HeatFlu1tH.otCf11j1_ilMl,FactQr,F~(Zj Fg(Z)= l. $'lt.'1 ~;; V Yes NIA FQ(Z) S{2.51P.}.

  • K(z~* .[COL:R ;t7;13 NIA No lliiaii:im.uti;i,:Pos1t1'.re*.lnco@*:Q(i'1J1dhinf* POVl'iriTl!t boo,~ .,,

Tlii"' 0 .:J.v fc, (t.,1e) .~;;1:02r NIA 1* /yes: NiA 

          .        Ci.ct~% Nil&j 'beffit;.                                                                                                                         No Refereni:;es-1.)DNES,M,NAF"NC0'-40,t.5 2.);ETE,lliAF,20J\:l;o.H9 3.) ETE-NAF*201:9.-0120 Page 48 of 49

Serial No. 20-067 Docket No. 50-280 Surry Power Station Unit 1 Cycle 30 Startup Physics Test Summary Sheet* Formal Tests (Page 6 or 6) Measured Value Oalgn Critoria Acceptance Crltortl Do1i9n IAcc.ptanco Criteria Met Crltoril Mot 7 YOl F_. i1,it'CS.jS 99111 NIA F-.t27~gpm (COlR:3.83 NIA No RoC.NIICK 1.}D~CD--4015 2,) ETfHfAF-2019-0119 3.) ETE-NAF-2019-0120 Page 49 of 49}}

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