ML112370243
| ML112370243 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/24/2011 |
| From: | Funderburk C Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Region 2 Administrator |
| References | |
| 11-487 | |
| Download: ML112370243 (48) | |
Text
Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 2SE, Glen Allen, VA 23060 August 24, 2011 United States Nuclear Regulatory Commission Serial No.: 11-487 Regional Administrator- Region II NLOS/GDM Marquis One Tower Docket No.: 50-281 245 Peachtree Center Ave., NE Suite 1200 License No.: DPR-37 Atlanta, Georgia 30303-1257 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNIT 2 CYCLE 24 STARTUP PHYSICS TESTS REPORT As required by Surry Technical Specification 6.6.A.1, enclosed is the Virginia Electric and Power Company (Dominion) Engineering Technical Evaluation ETE-NAF-20110083, Rev. 0, "Surry Unit 2 Cycle 24 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed prior to and following initial criticality of Cycle 24 on June 15, 2011. The results of the physics tests were within the applicable Technical Specification limits.
If you have any questions or require additional information, please contact Mr. Gary Miller at (804) 273-2771.
Sincerely,
~lbUrk, Director Nuclear Licensing and Operations Support Dominion Resources Services, Inc. for Virginia Electric and Power Company Enclosure Commitments made in this letter: None
Serial No.11-487 Docket No. 50-281 Page 2 of 2 cc: U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 R. E. Martin NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station
ENCLOSURE ENGINEERING TECHNICAL EVALUATION ETE-NAF-2011-0083 REV. 0 SURRY UNIT 2 CYCLE 24 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES DOMINION GENERATION August, 2011 Prepared By:._-:..fi_V~:-LA_~--:::7.::::-::::-*
K. L. Kennett (NCD-2)
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~_H_.-I-N: : :,ich~: :",:=~:-: ~:-(N_C.L.D Date Approved By: _ _ __l_S_1l_Perv1_'S_0_r) _ ?/1\JU Date QA Category: Nuclear Safety Related Key Words: S2C24, SPTR Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 1 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
CLASSIFICATIONIDISCLAIMER 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 FORA 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 it~elf 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.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 2 of 46 ETE-NAF-20 11-0083, Rev. 0 Enclosure
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 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 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 3 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
LIST OF TABLES Table 1.1 - Chronology ofTests ; 10 Table 2.1 M 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 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 4 of 46 ETE-NAF-20 11-0083, Rev. 0 Enclosure
LIST OF FIGURES Figure 1.1 - Core Loading Map 11 Figure 1.2 - Beginning of Cycle Fuel Assembly Bumups (GWD/MTU) 12 Figure 1.3 - Available Incore Moveable Detector Locations .13 Figure 1.4 - Control Rod Locations 14 Figure 2.1 - Typical Rod Drop Trace , 17 Figure 2.2 - Rod Drop Time - Hot Full Flow Conditions .18 Figure 2.3 - Rod Drop Times Trending 19 Figure 3.1 - Control Bank B Integral Rod Worth - HZP 23 Figure 3.2 - Control Bank B Differential Rod Worth - HZP 24 Figure 6.1 _ Assemblywise Power Distribution, Map 01, 28.66% Power 34 Figure 6.2 - Assemblywise Power Distribution, Map 02,65.14% Power 35 Figure 6.3 - Assemblywise Power Distribution, Map 03, 99.81 % Power 36 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 5 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
PREFACE This report presents the analysis and evaluation of the physics tests that were performed to verify that the Surry Unit 2, Cycle 24 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard testing techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at Surry Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.
The Surry Unit 2, Cycle 24 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test results, 3) acceptance criteria and whether it was met (if applicable), 4) date and time of the test, and 5) preparer/ reviewer initials. These sheets provide a compact summary of the startup test results in a consistent format. The entries for the design values were based on calculations performed by Dominion's Nuclear Analysis and Fuel Group. The acceptance criteria are based on design tolerances or applicable Technical Specification and COLR Limits.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 60f46 ETE-NAF-2011-0083, Rev. 0 Enclosure
SECTION 1 - INTRODUCTION AND
SUMMARY
On April 16, 2011 at 18:49, Unit No.2 of Surry Power Station tripped offline due to loss of offsite power. Unit 2 completed Cycle 23 at that time and began its Refueling Outage
[Ref. 1]. During this refueling, 73 of the 157 fuel assemblies in the core were replaced with 9 twice burned assemblies from Batch S2/23 last irradiated during Surry 2 Cycle 22, 36 fresh Batch S2/26A assemblies, and 28 fresh Batch S2/26B assemblies. The Cycle 24 core consists of 9 sub-batches of fuel: two fresh batches (82/26A and S2/26B), three once-burned batches (S2/25A, 82/25B, and S2/25C), and four twice-burned batches (82/23B, S2/230, 82/24A, and S2/24D) [Ref. 1]. S2C24 will be the first cycle to utilize the 15x15 Upgrade (Upgrade) Fuel Design. Therefore, all fresh fuel is the Upgrade fuel product and all reuse fuel is the Surry Improved Fuel (SIF/P+Z2) [Ref. 1].
For both fuel types, all fuel rods are supported by five structural ZIRLO grids and two Inconel-718 grids spaced along the axial length of the 'assembly. These grids are attached to the guide tubes, which are fixed to the upper and lower nozzles and thus provide structural support for the assembly. The Upgrade fuel design is similar to and compatible with the SIF/P+Z2 design.
However, the Upgrade fuel also includes three additional ZIRLO Intermediate Flow Mixing (IFM) grids for improved thermal-hydraulic performance, ZIRLO (I-spring) structural mid grids with new balancing vane pattern, "tube-in-tube" guide thimbles, a shorter bottom end plug length, and the use of optimized ZIRLO fuel clad that improves corrosion resistance. The SIFIP+Z2 design includes debris resistant features that are part of Westinghouse's Performance+
design with ZIRLO cladding, intermediate structural grids, guide tubes, and instrumentation tubes [Ref. 1].
This cycle uses only Westinghouse's Integral Fuel Burnable Absorber (IFBA) fuel product. The IFBA design involves the application of a thin (0.0003125 inch) 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 SuiTy Unit 2 Cycle 24 Startup Physics Tests Report Page 7 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
generate more internal gas during operation because neutron absorption in the ZrB 2 coating creates helium gas in addition to the fission gas created during irradiation of the fuel. Therefore, the initial pressure is set lower so the internal pressure early in lifetime may be lower [Ref. 5].
Note that there are no thimble plugging devices or secondary sources inserted in Surry Unit 2 for this cycle. The cycle design report [Ref. 1] provides a more detailed description of the Cycle 24 core.
The S2C24 full core loading plan [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 available 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 24 core [Ref. 1].
According to the Startup Physics logs, the Cycle 24 core achieved initial criticality on June 15, 2011 at 14:42 [Ref. 14]. Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. This cycle used the FTI Reactivity Measurement and Analysis System (RMAS) to perform startup physics testing. Note that RMAS v.6 [Ref. 9] was used for S2C24 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 2.4 second Technical Specification [Ref. 4] limit, as well as the Surry Unit 2 1.68 second administrative limit
[Ref. 10].
Individual control rod bank worths were measured using the rod swap technique [Ref. 2).
For the purpose of this test, a bank was defined as 'fully inserted' when it was 2 steps off the bottom of the core [Ref. 13]. The sum of the individual measured control rod bank wortbs was within -3.8% of the design prediction. The reference bank (Control Bank B) worth was within
-2.9% of its design prediction. Control rod banks with design predictions greater than 600 pcm were within +/-6.3% of the design predictions. For individual banks worth 600 pcm or less (only Control Bank A fits this category), the difference was within 3.2 pem of the design prediction.
These results are within the design tolerances of +/-15% for individual banks worth more than 600 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 8 of46 ETE-NAF-20 11-0083, Rev. 0 Enclosure
pcm (+/- 10% for the reference bank worth), +/- I00 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, ARO and 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 was within +4.4% of 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 within -0.228 pcmfF of the design prediction. This result is within the design tolerance of +/-2.0 pcrnf'F.
Core power distributions were within established design tolerances. The measured assembly power distributions were within +/-4.40% of the design predictions, where a +4.40%
maximum difference occurred in the 28.7% power map in assembly B8. 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 ReS Flow was successfully verified as being greater than 273,000 gpm and greater than the limit in the COLR (276,000 gpm), as required by Surry Technical Specifications
[Ref. 4]. The total RCS Flow was measured as 295,495 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.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 9 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 1.1 SURRY UNIT 2 - CYCLE 24 CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 06/12/11 1837 HSD 2-NPT-RX-014 Reactivity Computer Checkout 06/15/11 1540 HZP 2-NPT-RX-008 Boron Endpoint - ARO 06/15/11 1540 HZP 2-NPT-RX-008 Zero Power Testing Range 06/15/11 1540 HZP 2-NPT-RX-008 Boron Worth Coefficient 06/15/11 1950 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 06/15/11 1614 HZP 2-NPT-RX-008 BankB Worth 06/15/11 1657 HZP 2-NPT-RX-008 Boron Endpoint - B in 06/15/11 1950 HZP 2-NPT-RX-008 Bank A Worth - Rod Swap 06/15/11 2015 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap 06/15/11 2015 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap 06/15/11 2015 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap 06/15/11 2015 HZP 2-NPT-RX-008 Bank sa Worth - Rod Swap 06/15/11 2015 HZP 2-NPT-RX-008 Total Rod Worth 06/15/11 2015 HZP 2-NPT-RX-008 Flux Map - less than 30% Power 06/17/11 0337 28.7% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008
& Power Range Calibration 2-NPT-RX-005 2-GEP-RX-001 Flux Map - 65% - 75% Power 06/18/11 0118 65.14% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008
& Power Range Calibration 2-NPT-RX-005 2-GEP-RX-00I Flux Map - 95% - 100% Power 07/05/11 0853 99.81% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-008
& Power Range Calibration 2-NPT-RX-005 2-GEP-RX-001 RCS Flow Measurement . 6/28/11 1444 HFP 2-NPT-RX-009 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 10 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 1.1 SURRY UNIT 2 - CYCLE 24
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Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 11 of46 ETE-NAF-20l1-0083, Rev. 0 Enclosure
Figure 1.2 SURRY UNIT 2 - CYCLE 24 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS (GWDIMTU)
R P N M L K H G F E o C 8 A 1 I 40.821 32.191 40.401 I MEASURED I 1 I 40.801 32.19/ 40.811 I PREDICTED I 2
I 41.061 21.121 0.001 0.001 0.001 21.591 40.651
2 I 40.851 21.171 0.001 0.001 0.001 21.241 40.811 j 40.721 0.00/ 0.001 0.001 21.851 0.001 0.001 0.001 40.831 I 40.511 O.OOf 0.001 0.001 21.711 0.001 0.001 0.001 40.501 4 140.901 0.001 0.001 18.401 21.661 20.591 21.881 18.411 0.001 0.001 40.551 4 I 40.691 0.00 0.001 18.271 21.661 20.491 21.641 18.231 0.001 0.001 40.541 I 40.741 0.001 0.001 22.311 22.711 0.001 22.091 0.001 22.64121.941 0.001 0.001 40 98
, 1 I 40.861 0.001 0.00 22.121 22.771 0.001 22.061 0.001 22.761 21.911 0.00 O.OOf 40.89 6 I 21.251 0.001 18.181 22.731 0.001 18.251 22.071 18.571 0.00\ 22.621 18.361 0.001 21.391 6 I 21.201 0.001 18.151 22.731 0.001 18.251 22.19\ 18.171 0.001 22,741 18.271 0.00/ 21.171 7 I 37.661 0.001 0.001 21.581 0.001 18.351 17.561 O.OOJ 17.131 18.321 0.001 21.711 0.001 0.001 37.601 7 I 37.401 0.001 0.001 21.721 0.001 18.241 17.171 0.001 17.181 18.221 0.001 21.721 0.001 0.001 37.241 8 I 32.431 0.00121.701 20.431 22.39122.171 0.00142.311 0.001 22.13121.981 20.651 21.561 0.001 32.411 8 1 32.301 0.001 21.711 20.571 21.981 22.181 0.DOI42.381 0.001 22.18 21.98 20.57 21.711
______________________________________________________ ___________________________ w 0.00 32.30 _
9 I 37.081 0.001 0.001 21,Q71 0.001 18.391 17.111 0.001 17.131 18.281 0.001 11.651 0.001 0,001 37,601 9 I 37.251 0.001 0.001 21.721 0.001 18.221 17.18 0.00 17.171 18.241 0.001 21.721 0.001 0,001 37,401 10 I 21.271 0.001 18.251 13.031 0.001 18.321 22.041 18.211 0.001 22.721 18.111 0.001 21.261 10 I 21.171 0.001 18.271 22.741 0.001 18.271 22.191 18.251 0.001 22.731 18.151 0.001 21.201 11 I 40.961 0.001 0.001 21.891 22.541 0.001 22.141 0.001 22.691 22.131 0.001 O.GOI 40.501 11 I 40.891 0.001 0.001 21.91 22.761 0.001 22.06 0.00 22.77 22.12 0,00 0.001 40.86 12 140.501 0.001 0.001 18.131 21.671 20.561 21.721 18.341 0.001 0,00140.871 12 I 40.541 0.001 0.001 18.231 21.641 20.491 21.661 18.271 0.001 0,001 40.691 13 I 40,691 0.001 0.001 0.001 21.511 0.001 0.001 0.001 41.081 13 140.501 0.001 0.001 0.001 21.711 0.001 0.001 0.00140.S11 14 1 40.861 21.261 0.001 0.001 0.001 21.081 40.881 14 1 40.811 21.241 0.001 0.001 0.001 21.171 40.851 15 1 40.561 32.371 40.891 15 I 40.801 32.191 40.791 R p N ~I L K H G F E o c B A Suny Unit 2 Cycle 24 Startup Physics Tests Report Page 12 of46 ETE-NAF-201l-0083, Rev. 0 Enclosure
Figure 1.3 SURRY UNIT 2 - CYCLE 24 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 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 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 13 of 46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 1.4 SURRY UNIT 2 - CYCLE 24 CONTROL ROD LOCATIONS R p N M L K ] H G F E D c B A 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 D C C D 270 0 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 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 14 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
SECTION 2 - CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured in hot shutdown with three reactor coolant pumps in operation (full flow) and with T ave greater than 530 OF per 2-NPT-RX-014.
This verified that the time to entry of a rod into the dashpot region was less than or equal to the maximum allowed by Technical Specification 3.12.C.l [Ref. 4].
Surry Unit 2 Cycle 24 used the rod drop test computer (RDTC) in conjunction with the Computer Enhanced Rod Position Indication (CERPI) system. The CERPI system equipment replaced the Individual Rod Position Indication (lRPI) system. The rod drop times were measured by withdrawing all banks to their fully withdrawn po.sition and dropping all of the 48 control rods by opening the reactor trip breakers. This allowed the rods to drop into the core as they would during a plant trip.
The current methodology acquires data using the secondary RPI coil terminals (/3 & /4) on the CERPI racks for each rod. Data is immediately saved to the rod drop test computer (RDTC) which computes the rod drop time automatically. Original data is also saved as an ASCII file and burned to a CD-R. Further details about the RDTC can be found in [Ref. 12].
A typical rod drop trace for S2C24 is shown in Figure 2.1. The measured drop time for each control rod is recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Figure 2.3 shows slowest, fastest, and average drop times for Surry 2 cycles 20-24. Technical Specification 3.12.C.l [Ref. 4] specifies a maximum rod drop time to dashpot entry of 2.4 seconds for all rods. These test results satisfied this technical specification limit as well as the administrative limit [Ref. 10] of 1.68 seconds. In addition, rod bounce was observed at the end of each trace demonstrating that no control rod stuck in the dashpot region.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 15 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 2.1 SURRY UNIT 2 ~ CYCLE 24 STARTUP PHYSICS TESTS HOT ROD DROP TIME
SUMMARY
ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-06 1.39 sec. p-g, L-5 1.25 sec 1.29 sec.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 16 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 2.1 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE
/
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Beginning of Dashpot Entry (Extreme drop in Voltage)
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 17 of46 ETE-NAF-2011-0083, Rev, 0 Enclosure
Figure 2.2 SURRY UNIT 2 - CYCLE 24 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
1.29 1.27 1.27 3
1.27 1.31 4
1.28 1.26 1.29 1.30 5
1.25 1.27 6
1.27 1.27 1.29 1.29 1.39 1.27 1.38 7
1.29 1.31 1.32 1.30 8
1.25 1.29 1.27 1.30 9
1.29 1.29 1.29 1.27 10 1.29 1.28 1.29 1.30 1.32 1.27 1.31 11 1.28 1.30 12 1.27 1.26 1.28 1.27 13 1.27 1.30 14 1.32 1.26 1.31 15 IX.xx I > Rod drop time to dashpot enlIy (sec.)
Suny Unit 2 Cycle 24 Startup Physics Tests Report Page 18 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 2.3 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS ROD DROP TIMES TRENDING 2.60 Technical Speclfi ation limit 2.4 2.40 2.20
...... Fastest RodTIme
_Slowest RodTime
~AverageTime 2.00
~
II>
"tl c:
o u
~ 1.80 CIJ E
1= ...................... ********** t\qr:nJtll~r~tiy~ Limit 1.68 ....*.................
1.60
.IL 1.40 1.20 1.00 20 21 22 23 24 Cycle Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 19 of46 ETE-NAF-2011-0083, Rev. 0 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 refen'ed 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 24, Control Bank B was used as the reference bank. Surry 2's dilution rate was around 1000 pcmlhr for the reference bank measurement.
During the NIC19 startup physics testing campaign, a control rod became stuck on the bottom eventually forcing a reactor trip, to fix the problem. A theorized potential cause of the stuck rod issue was the presence of debris near the upper core plate interfering with the rod grippers when the control rods were manually inserted to the fully inserted position of 0 steps withdrawn. A possible 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 S2C24 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 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 20 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
balance the reactivity of the reference bank withdrawal. This sequence was repeated until the previous test bank was fully withdrawn and the current test bank was nearly inserted. The next step was to swap the rest of the test bank in by balancing the reactivity with the withdrawal of the reference bank, until the test bank was fully inserted and the reference bank was positioned such that the core was near the initial statepoint condition. This measured critical position (MCP) of the reference bank with the test bank. fully inserted was used to determine the integral reactivity worth of the test bank.
The core reactivity, moderator temperature, and differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver was repeated for all test banks. Note that after the final test bank was fully inserted, the test bank was swapped with the reference bank until the reference bank was fully inserted and the last test bank was fully withdrawn. Here the [mal statepoint data for the rod swap maneuver was obtained (core reactivity and moderator temperature) in order to verify the reactivity drift was within procedural limitations for the rod swap test.
A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Summary Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance of +/- 10% for the reference bank, +/-15% for test banks of worth greater than 600 pcm, and +/- 100 pcm for test banks of worth less than or equal to 600 pcm. The sum of the individual measured rod bank worths was within -3.8 % of the design prediction. This is well within the design tolerance of +/-1O% for the sum of the individual control rod bank wortbs.
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.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 21 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 3.1 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
SUMMARY
MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)
BANK (PCM) (PCM) (M-P)/P X 100 B - Reference 1442.64 1486 -2.9 D 1008.6 1050.9 -4.0 C 763.8 815.2 -6.3 A 332.1 335.3 -1.0*
SB 988.2 1045.9 -5.5 SA 912.9 927.9 -1.6 Total Bank Worth 5448.3 5661.1 -3.8
- Note: For Bank A, (M-P) ::::: -3.2 pern.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 22 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 3.1 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1600
-- - ~
1400
~ r.
.\
\J 1\
1200 \iII
'II.
lo.\
\
- a1000
.\
u \'l.
.....PI ~
ill r\\
- It!
~.
\
-Measured
-Predicted
~.
\
~
\I!'-
Ilil
\ r.
~....
~
400 \ i\.
~ ...
~
~
200
.~
, \,
I' o 'il -
o 50 1QO 150 200 250 Sank position (steps)
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 23 of46 ETE-NAF-20ll-0083, Rev. 0 Enclosure
Figure 3.2 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 14.0
~ ....
12.0 1/ .1.
~
~
l
\
10.0 '\'
\\
\ iI 4 \
~I\
,~
\. .
'4l '-
--Measured
-Predicted
\' IW- -;;;;;:;;;-
-~
~:\
I\~
\
4.0 I
/
II 2.0 1J
'j b
I~
0.0 o 50 100 150 200 250 Bank Position (steps)
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 24 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
SECTION 4 - BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position and moderator temperature, as necessary.
The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Summary Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.1 a.A [Ref 4] regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.
Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.
A summary of the measured and predicted DBW is shown in Table 4.2. As indicated in this table and in the Appendix, the measured DBW was well within the design tolerance of
+/-10%. In summary, the measured boron worth coefficient was satisfactory.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 25 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 4.1 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm)
ARO 1588.3 1620 -31.7 B Bank In 1387.5 1390.3* -2.8
- 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.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 26 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 4.2 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)
(pcm/ppm) (pcm/ppm) (M-P)/P x 100
-7.18 -7.51 -4.39 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 27 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
SECTION 5 - TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.
Reactivity was measured during the RCS heat up of +3.51°F, followed by the RCS cool down of -3.15°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 isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Summary Sheet given in the Appendix, the measured isothennal temperature coefficient value was within the design tolerance of +/-2 pcmfF. The calculated moderator temperature coefficient (MTC), which is calculated using a measured ITC of -1.860 pcm! OF, a predicted DTC of -1.80 pcm! OF, and a measurement uncertainty of +0.5 pcm! OF, is +0.440 pcm! OF. It thus satisfies the COLR criteria
[Ref. 8] that indicates MTC at HZP be less than or equal to +6.0 pem!°P.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 28 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 5.1 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
TEMPERATURE ISOTHERMAL TEMPERA11JRE COEFFICIENT BANK BORON
~GEeF) tPCM/oF)
POSITION CONCENTRATION -
(STEPS) L0w;.~ UPPER (ppm)
HEAT- COOL- AVG. DIFFER LIMIT LIMIT UP DOWN MEAS PRED (M-P)
D1205 545.96 549.47 1581 -1.743 -1.977 -1.860 -1.632 -0.228 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 29 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
SECTION 6 - POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the moveable ineore 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 the ramp to full power flux maps for Cycle
- 24. 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, 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.
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 28.7% power to verify the radial power distribution (RPD) predictions at low power. Figure 6.1 shows the measured RPDs from this flux map. Flux maps 2 and 3 were taken at 65.14% and 99.81 % power, respectively, with different control rod configurations. These flux maps were taken to check at-power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3.
The radial power distributions for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured relative assembly power values deviated from the design predictions by at most
+4.4% in the 28.7% power map, -3.5% in the 65.14% power map, and -3.7% in the 99.81%
power map. The maximum average quadrant power tilts for the three power maps are +0.62 %
(1.0062), +0.45 % (1.0045), and +0.65% (1.0065), respectively. These power tilts are within the design tolerance of2% (1.02).
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 30 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
The measured FQ(z) and F:H 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 24.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 31 of 46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 6.1 SURRY UNIT 2 - CYCLE 24 STARTUP PHYSICS TESTS INCORE FLUX MAP
SUMMARY
Bum Peak FQ(Z) Hot F~ Hot (2) CoreFz No.
Bank Channel Factor (l) Core Tilt (3) Axial Of Map Map up Power Channel Factor Max Date D Offset Thimbles Description No. MWDI (%)
MTU Steps Assy Ax!al F (Z) Assy Pomt Q I F~ Axial Point Fz I Max Loc (%)
Low Power I 06/17/Il 2 28.66 168 DOS 30 /2.174 D05 1.521 30 1.328 1.00621 SE -0.005 50 Int.Power(4) 2 06/18/1 I 17 65.14 198 DOS 29 1.924 D05 1.477 26 1.208 1.00451 SE +3.010 50 Hot Full Power 3 07/05/1 I 381 99.81 224 DDS 31 1.836 D05 11.437 3D 1.167 1.00651 SE -0.212 50 NOTES: Hot spot locations are specified by giving assembly locations (e.g. H-8 is the center-of-core assembly) and core height (in the liZ" direction the core is divided into 61 axial points starting from the top of the core). Flux Maps 1,2, and 3 were used for power range detector calibration or were used to confirm existing calibrations.
(1) FQ(z) includes a total uncertainty of 8.00%
(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.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 32 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 6.2 SURRY UNIT 2 -CYCLE 24 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Map PeakFQ(Z) Hot F~ Hot Channel Factor Channel Factor No. Meas. Limit Node Margin;) Meas. Limit Margin;)
(%) (%)
1 2.174 5.000 30 56.5 1.521 1.894 19.69 2 1.924 3.838 29 49.9 1.477 1.723 14.28 3 1.836 2.505 31 26.7 1.437 1.561 7.94 The measured FQ(z) hot channel factors include 8.00% total uncertainty. Measured F~ data includes no uncertainty.
$ Margin (%) = 100*(Limit - Meas.) I Limit Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 33 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 6.1 - ASSEMBLYWISE POWER DISTRIBUTION, MAP 01, 28.66% POWER Top value = Measured, middle value = Analytical, bottom value = % Delta
% Delta = (M - A}xl00/A p N K H G D c 8 A I 0.2871 0.3181 0.2651 1 0.2661 0.3351 0.2651 I o.nl 0.811 0.181
-I -_0.3211 0.6501 1.002/ 1.()491 0.9991 0.6381 0.3191 I 0.320 0.6481 0.999 1.()441 0.999 0.648J 0.321
-0. ()4 I -1.611 -0.501 1 0.3661 I 0.401 1.0431
_ -_1.2281 0.33 0.331
0.491 1.2161 1.1261 1.2191 1.2271 1.0441 0.3731 I 0.369 1.0381 1.2261 1.2141 l.llll 1.2161 1.2291 1.0411 0.3701 I -0.811 0.461 0.17 0.141 1. JSI 0.211 -0.191 0.27 0.881 10.36610.90711.30511.36111.20311.27311.21011.3651 1.3051 0.9211 0.3761 I 0.3691 0.9081 1.2931 1.3601 1.2061 1.2671 1.2091 1.3651 1.2981 0.9111 0.3711
/
---0.3191 I
~
-0.71! -0.06 1.0301 1.2901 0.92
-_ 1.1831 0.091 -0.25 1.2191 1.2921 0.50 1.1681 0.061 -0.011 0.551 1.10 1.3111 1.2271 1.2111 1.3231 1.0661 0.3301 1.46 0.3231 1.0461 1.2981 1.1891 1.2281 1.)17/ 1.1771 1.3201 1.2321 1.1961 1.3021 1.0481 0.3241
--1 --0.6531
-1.121 -1.551 -0.581 -0.471 -0.721 -1.901 -0.741 1.2281 1.)681 1.2411 1.1241 1.2371 l.097 I 1.2351 1.1041 1.2401 1.3951 1.2641 0.6751
-0.691 -0.441 1.231 1.601 1.731 1.671 6 I 0.658 1.2391 1.3721 1.2331 1.1321 1.2521 l.1081 1.2531 1.1HI 1.2351 1.3721 1.2411 0.6621 1 -0.74 -0.90 -0.27 0.6) -0.74 -1.231 -0.951 -1.431 -2.681 0.41 1.66 1.83 2.02 1 0.2871 1.0161 1.2181 1.2121 1.3241 1.2471 1.0941 0.9981 1.0921 1.2441 1.3341 1.2501 1.2571 1.0521 0.3021 7 I 0.2881 1.024 1.231 1.216 1.325 1.2541 1.1081 1.0111 1.1091 1.2561 1.3251 1.2161 1.2321 1.0291 0.2941 1 -0.501 -0.741 -1.041 -0.291 -0.101 -0.56 -1.261 -1.28/ -1.55 -0.93 0.641 2.811 2.061 2.271 2.621 8 I 0. 351 1 1.0731 1.1281 1.2771 1.1841 1.1121 1.012 10.35111.06911.13411.27611.18611.10611.00310.6701 1.000/ 1.1051 1.19211.2981 1.1441 1.1201 0.3661 0.6771 1.012 1.111 1.184 1.2771 1.1281 1. 07) 1 0.351/
-I 0.2931
-0.08
_ 1.0241-0.361
---_ 1.2261-_ --_1.2071
..0.53 -0.08 0.201 -0.561 -0.931 -1.021 -1.151 -0.521 1.3001 1.2431 1.1011 1.0011 l.Og61 1.2521 1.3321 1.2341 1.2541 .1.055[ 0.3001 0.671 1.621 1.441 4.401 4.171 9 I 0.2941 1.0291 1.2331 1.2161 .1.3251 1.256 1.1091 1.0111 1.1081 1.2541 1.3241 1.216 1.231 1.024 0.288 I -0.511 -0.471 -0.561 -0.771 -1.881 -1.07 -0.71 -0.96 -1.11 -0.18 0.631 1.491 1.88 3.061 4.311 I 0.6571 1.2281 1.3601 1.2221 1.1211 1.2521 1.0991 1.2411 1.1241 1.2421 1.3931 1.2631 0.6761 10 1 0.6621 1.2411 1.3721 1.2351 1.1341 1.2531 1.10BI l.2521 1.1321 1.233 1.3721 1.2391 0.6581
-_/ . 0.3221 ...... _.. ---_ .......... _.. -- --- --- --- -- -- --_. -- ---- ---- --- - -- -- - -- .. _.. -_ ...... ----_...... _-- --_.... -.. _.. -- _.. ------ .........
-0.76l -1.051 -0.891 -1.051 -1.181 -0.061 -0.791 -0.911 -0.731 0.71 1.56 1.91 2.71 1.0411 1.2921 1.1901 1. 220 1 1. 304 1 1.1571 1.3031 1.2151 1.2001 1.3191 1.0671 0.3311 11 I 0.3241 1.0481 1.3021 1.1961 1.232 1.320 1.1771 1.3171 1.228 1.189 1.298 1.045 0.323 I -0.631 -0.681 -0.771 -0.541 -1.00J -1.231 -1.711 -1.031 -1.061 0.921 1.621 2.091 2.351 I 0.3731 0.9051 1.2861 1.3481 1.1841 1.2551 1.20)1 1.3641 1.3061 0.9281 0.3831 12 10.37110.91111.29811.36511.20911.26711.20611.3601 1.2931 0.9081 0.3691 1 0.601 -0.691 -0.951 -1.231 -2.041 -0.961 -0.281 0.301 1.00 2.251 3.751 I 0.3671 1.0301 1.215[ 1.2011 1.1131 1.2181 1.2411 1.0511 0.3751 13 10.37011.04211.229 1.21611.11111.21411.22611.03810.3691 I -0.841 -1.121 -1.161 -1.061 0.181 0.351 1.251 1.251 1.631
/ 0.3151 0.6421 0.9921 1.0411 1.0031 0.6551 0.3241 14 I 0.3211 0.648 1.0001 1.0451 0.9991 0.6481 0.3201 1.801
-- --------------- -0.941 -0.81 -0.351 0.391 1.011 1 0.2631 O. 33S I 0.2661 1.211 15 1 0.2651 0.3351 0.2661 I -0.731 -0.111 0.071 AVERAGE ABSOLUTE PERCENT DIFFERENCE 1.0 STANDARD DEVIATION 0.819 Summary:
Map No: S2-24-01 Date: 06117/2011 Power: 28.66%
Control Rod Position: FQ(z) = 2.174 QPTR:_0~.9;..;;9....;;.5.;;...5 -+----=1:..:....:.0...:..05::....:8=__._
D Bank at 168 Steps F~ = 1.521 0.9925 1.0062 Fz = 1.328 Bumup = 2 MWDIMTU Axial Offset (%) = -0.005 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 34 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 6.2 - A8SEMBLYWI8E POWER DISTRIBUTION, MAP 02, 65.14% POWER Top value = Measured, middle value = Analytical, bottom value % Delta
% Delta = (M - A)xlOO/A R p N ~l L K J
--I ---- -- -- -_H..... ---- - G_.... ---
0.2871 0.3671 0.2861 F E 0 C B A 1 I 0.2861 0.3651 0.2861 I 0.3271 0.6591 I
0.211 1.0241 0.451 1.1091
--1.0201
-0.161 0.6481 0.3261 2 r *0.328 0.6591 1.0241 1.1071 1.0241 0.6591 0.3291 I
I
-0.231 0.3651 1.0211 1.2051 1.2111 1.1301 0.02 -0.011 0.181
-0.351 -1.641 -0.921
_1.2121 1.2041 1.0241 0.3741 0.3741 1. 024 1 1. 207 1 1.2121 1.1211 1.2HI 1.2091 1.0261 0.3751
--I ----_-2.351 -0.27
-_ -_ -_-0.13
-0.111 0.761 -0.05
0.391----_ ....-0.201 -0.211 I 0.3721 0.8941 1.2641 1.3271 1".1921 1.2651 1.1951 1.BOI 1.2661 0.9071 0.3791 I 0.3751 0.8991 1.262 1.328 1.192 1.254 1.1941 1.3321 1.2661 0.9011 0.3761 I -0.831
-0.521 0.171 -0.061 -0.011 0.921 0.091 .0.151 0.031 0.641 0.911 10.32811.02111.2611 1.170f 1.21611.29511.16811.30111.21311.17911.28811.04410.3311 I 0.3311 1.0301 1.2~61 1.172 1.2201 1.3071 1.1701 l.3G91 1.2231 1.1781 1.2691 1.0311 0.3311 I -0.771 -0.891 -0.381 -0.141 -0.361 -0.911 -0.191 -0.621 -G.BOI 0.051 1.461 1.221 0.101
-I - ------------------------- --- --- _... - - -- ------- ---------- .. --- ----- - -----_ ... - ------ - ----- - -- - ---_ .. -- -- - --- --
0.66~1 1.2131 1.3351 1.2241 1.1731 1.2511 1.1081 1.2441 1.1471 1.2221 1.3511 1.2331 0.6811 6 0.6681 1.2171 1.3371 1.2241 1.178 1.2591 1.1141 1.2591 1.1801 1.2251 1.336 1.219 0. 671 1 I -0.261 -0.321 -0.161 0.041 -0.431 -0.631 -0.561 -1.221 -2.831 -0.251 1.091 1.181 1.42
0.30811.04311.22511.19911.31011.25611.11411.0211
------ 1.1101 1.24811.31311.22111.24311.07010.3211 7 1 0.l091 1.04511.22511.19911.31211.26111.12111.03011.12211.26211.3121 1.1991 1.22~1 1.0501 Cl.3151 I -Cl.HI -Cl.181 -0.041 -0.021 -0.151 -0.361 -Cl.581 -0.851 -1.061 -1.121 0.111 1.811 1.381 1.931 2.0ll I 0.3751 1.1301 1.1411 1.2621 1.1741 1.1151 1.0261 0.6981 1.0231 1.1071 1.1791 1.2731 1.14-11 1.1691 0.3911 8 I 0.380/ 1.1331 1.1351 1.2611 1.1761 1.1161 1.0301 0.7011 1.0301 1.1161 1.1761 1.2611 1.135 1.133 0.3801 I -1.441 -0.221 0.531 0.061 -0.141 -0.13 -0.421 -0.44 -0.70 -0.761 0.28 0.981 0.81 3.18 2.791
-10.31211.04511.22111.19811.31511.26111.1211 1.G261 1.12111.27011.32011.21111.23911.06510.3151 9 I 0.3151 1.0501 1.2261 1.1991 1.3121 1.2621 1.1221 1.0301 1.1111 1.2611 1.3121 1.1991 1.2251 1.0451 0.3091 1 -0.871 -0.461 -0.401 -0.121 0.241 -0.071
---------------------- --- -_ .. -- - - - ----- -- --- .. -- -.. -_ .. _-0.341
-0.12)
I 0.6651 1.2021 1.3291 1.2231 1.1761 1.2601 1.1111 1.2581 1.1811 1.2301 1.3521 1.2311 G.67i1 0.011 0.711 0.591 1.021 1.131 1.941 1.981 10 ) 0.6711 1.2191 1.3361 1.2251 1.180) 1.2591 1.1141 1.2591 1.1781 1.2241 1.3371 1.2171 0.6681 I -0.861 -1.371 -0.551 -0.201 -0.301
0.091 -0.26 I 0.3281 1.0221 1.2601 1.1721 1.2191 1.3041 1.1S81 1.3041 1.2241 1.1701 1.2771 1.0411 0.3341
-0.081 0.261 0.511 1.111 1.131 1.281 11 I 0.3311 1.0311 1.2691 1.1781 1.2231 1.3091 1.1701 1.3071 1.2201 1.1721 1.2661 1.0301 0.331
--1 --_-0.801 -0.841 -0.681 -0.541 -0.351 -0.391 -1.001 -0.251 0.34) -0.191 0.851 1.091 1.041
~
I 0.l751 0.8951 1.2581 1.3271 1.1941 1.2521 1.1931 1.3331 1.2681 0.9121 0.3821 12 I 0.3761 0.9011 1.2661 1.3321 1.1941 1.254[ 1.1921 1.328 1.2621 0.8991 0.3751 I
-0.251 -0.611 -0.601 -0.39 -0.031 -0.16[ 0.051 0.391 0.501 1.47 1.96 I 0.3731
--1.0181 1.2031 1.2101 1.1261 1.2131 1.2141 1.0301 0.3781 13 I 0.3751 1.0261 1.2091 1.2131 1.1211 1.2121 1.2071 1. Cl24 I 0.374) f
-0.671 -0.831 -0.541 -0.241
_- -- ---- 0.071
-_ ..... - - - _.. _.. --- -- ----... 0.41/
J 0.3181 0.6541 1.0191 1.1041 1.0191 0.661.1 0.3291
.. _-_ .. -_ ....0.591-... _----_O.SClI 1.071 14 I 0.3291 0.6591 1.024 1.1071 1.0241 0.6591 0.3281
_.. ---_ .. ---- - _.. _.. ----_ .. ------_ .. ----_O.BI I -3.491 -0.771 -0.471 -0.241 -0.531
--- .. -- --_ .. --0.391 0.2821 0. 363 1 0. 285 1 15 I 0.2861 0.365 0.286 I -1.241 -O.BI -0.431 AVERAGE ABSOLUTE PERCENT DIFFERENCE 0.7 STANDARD DEVIATION 0.633 Summary:
Map No: 82-24-02 Date: 06/18/2011 Power: 65.14%
Control Rod Position: FQ(z) = 1.924 QPTR:_O-,.9_9--,-,69_+--.,.1_.O-:-02-,-1_
D Bank at 198 Steps F~ = 1.477 0.9966 1.0045 Fz = 1.208 Bumup = 17 MWD/MTU Axial Offset (%) = +3.010 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 35 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Figure 6.3 - ASSEMBLYWISE POWER DISTRIBUTION, MAP 03,99.81 % POWER Top value = Measured, middle value = Analytical, bottom value % Delta
% Delta = (M - A)xlOO/A R p l K G F E o c 8 A I 0.2961 0.3741 0.2951 1 I 0.2971 0.3771 0.297
-0. ~81 I 0.3281 0.6581
[
-0.751 -0.79 1.0231 1.130/ 1.0181 0.6451 0.~271 I 0.3301 0.6591 1.0241 1.131 1.0241 0.659 O.Bll I -0. 521 -0.17 I -0.151 -0.10 -0.541 -2.151 -1.171 I 0.3681 0.9991 1.1871 1.2101 1.1271 1.212/ 1.1B91 1.0051 0.3751 I 0.3761 1.005/ 1.1911 1.2111 1.1201 1.2121 1.1931 1.0071 0.3771 I -2.10 I -0. 57 -0. 31 -0.10 0.60 -0.02 -0. 341 -0.171 -0.491 I 0.3711 0.8841 1.2361 1.2961 1.1821 1.2581 1.1881 1.3071 1.2471 0.B981 0.3791 4 I 0.3761 0.8921 1.2421 1.2991 1.1611 1.2411 1.1831 1. ~031 1.2451 O. B951 0.3771 1 -1.251 -0.B61 -0.50 -0.21 0.111 1.411 0.391 0.341 0.181 0.391 0.591 I 0.3291 0.9971 1.2361 1.1541 1.2131 1.3071 1.1711 1.3141 1.2161 1.1671 1.2601 1.0181 0.3291 I 0.3321 1.0101 1.2451 1.1601 1.2181 1.3151 1.171 1.3181 1.2211 1.1651 1.2481 1.0111 0.3131 1 -1.051 -1.321 -0.761 -0.501 -0.391 -0.641 -0.021 -0.33 -0.371 0.151 0.991 0.721 -1.081 I 0.6631 1.1911 1.3011 1.2201 1.2311 1.2651 1.1201 1.2611 1.2141 1.2221 1.3181 1.2111 0.6741 6 I 0.6671 1.2001 1.3071 1.2221 1.2361 1.2711 1.127 1.272 1.B81 1.223 1.306\ 1.2011 0.6701 I -0.671 -0.781 -0.461 -0.181 -0.421 -0.491 -0.641 -0.901 -1.97 -0.07! 0.92 0.791 0.63 I 0.3161 1.0371 1.2161 1.1841 1.3171 1.2701 1.1391 1.0511 1.1361 1.2651 1.3241 1.2081 1.B51 1.0571 0.3291 7 I 0.3201 1.0431 1.2231 1.1871 1.3201 1.2731 1.1431 1.0671 1.1431 1.274 1.3201 1.1871 1.2241 1.0481 0.3251 1 -1.141 -0.591 -0.571 -0.291 -0.23[ -0.261 -0.33 -0.55 -0.60 -0.701 0.301 1.771 0.901 0.851 1.151 I 0.3841 1.1481 1.1351 1.2461 1.1761 1.1291 1.066/ 0.7391 1.0641 1.1231 1.1811 1.2591 1.1371 1.1841 0.4001 8 I 0.392 1.154 1.131 1.2471 1.175 1.129 1.068 0.7401 1.0681 1.129 1.1751 1.2471 1.1311 1.1541 0.3921 I -2.031 -0.481 0.371 -0.07/ 0.081 -0.021 -0.201 -0.151 -0.331 -0.511 0.541 0.981 0.511 2.631 2.151 I 0.1211 1.0401 1.2161 1.1841 1.3231 1.275/ 1.1451 1.06BI 1.1481 1.2911 1.~331 1.2021 1.2361 1.0591 0.3241 9 I 0.3251 1.0481 1.2241 1.1871 1.3201 1.2741 1.1431 1.0671 1.1431 1.2731 1.3201 1.1871 1.2231 1.0431 0.~201 I -1.15/ -0.741 -0.631 -0.251 0.201 (l.071 (l.221 0.111 0.481 1.391 0.981 1.261 1.051 1.571 1.221 I 0.6621 1.1831 1.2981 1.2211 1.2371 1.277/ 1.128[ 1.2761 1.2461 1.2341 1.3311 1.2151 0.6721 10 10.67011.201 1.30611.223 1.238 1.272 1.12711.27111.23611.22211.30711.20010.6671 I -1.121 -1.541 -0.621 -0.141 -0.081 0.42 0.10 0.421 0.841 0.971 1.831 1.251 0.731 11 I 1
0.3291 0.3331
-1.241 0.9991 1.0111
-1.171 1.2381 1.2481
-0.791 1.1521 1.1651
-0.291 1.2191 1.221
-0.20 1.3141 1.318
-0.281 1.162/
1.171
-0.781 1.3171 1.315 0.181 1.2291 1.218 0.94 1.159/
1.160
-0.051 1.25BI 1.245 1.031 1.0231 1.0101 1.111 (l.B6f 0.3321 I.OBI I 0.3701 0.8871 1.2371 1.297/ 1.1801 1.2401 1.1641 1.3091 1.2491 0.9011 0.3861 12 1 0.3771 0.8951 1.24'51 1.3031 1.1831 1.2411 1.1811 1.2991 1.2421 0.B921 0.3761 I -1.731 -0.941 -0.611 -0.431 -0.281 -0.071 0.291 0.751 0.551 1.011 2.571 1 0.3731 0.9981 1.1851 1.20BI 1.1251 1.2141 1.2031 1.013/ 0.3791 13 I 0.3771 1.0071 1.1931 1.2121 1.120 1.2111 1.1911 1.0051 0.3761 I -1. 041 -0.941 -0.651 -0.311 0.451 0.221 0.981 0.781 0.731 1
0.3191 0.6531 1.0181 1.1281 1.0171 0.6611 0.3321 14 I 0.3311 0.659 1.024 1.131 1.024 0.659 0.3301
.. --- 0.3751
-- 0.2951 1 -3.711
--- ------ .. -- -0.901 -0.561 -0.281 -0.691
0.2921 0.361
-------------- 0.511 15 II 0.2971
-1.
0.3771 0.2971 80 1 -0.441 -0.691 AVERAGE ABSOLUTE PERCE~~ DIFFERENCE 0.7 STANDARD DEVIATION 0.581 Summary:
Map No: S2-24-03 Date: 07/05/2011 Power: 99.81%
Control Rod Position: FQ(z) = 1.836 QPTR:_0_.9_9_54_-t--_l_.0_0_19_ _
D Bank at 224 Steps F~ = 1.437 0.9962 1.0065 Fz= 1.167 Burnup = 381.0 MWD/MTU Axial Offset (%) = -0.212' Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 36 of46 ETE-NAF-20 11-0083, Rev. 0 Enclosure
SECTION 7 - CONCLUSIONS Table 7.1 summarizes the results associated with Surry Unit 2 Cycle 24 startup physics testing program. As noted herein, all test results were acceptable and within associated design tolerances, technical specification limits, or COLR limits. It is anticipated, based on the results associated with the S2C24 startup physics testing program, that the Surry 2 core will continue to operate safely throughout Cycle 24.
Suny Unit 2 Cycle 24 Startup Physics Tests Report Page 37 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Table 7.1 STARTUP PHYSICS TESTING RESULTS
SUMMARY
Measured Predicted Diff (M-P) or Design (M) (P) (M-P)/P,% Tolerance Parameter Critical Boron Concentration (HZP ARO), ppm 1588 1620 -32 +/-50 Critical Boron Concentration (HZP Ref Bank in), ppm 1387.5 1390.3 -2.8 +30 Isothermal Temp Coefficient (HZP ARO), pcm/F ~1.860 -1.632 -0.228 +/-2 Differential Boron Worth (HZP ARO), ocm/opm -7.18 -7.51 +4.4% +10%
Reference Bank Worth (B-bank, dilution), ocm 1443 1486 -2.9% +/-10%
D-bank Worth (Rod Swap), pem 1009 1051 -4.0% +/-15%
SB-bank Worth (Rod Swap), pcm 988 1046 -5.5% +/-15%
SA-bank Worth (Rod Swap), pem 913 928 -1.6% +/-15%
C-bank Worth (Rod Swap), pem 764 815 -6.3% +/-15%
Rod Worth ~ 600 pcm:
A-bank Worth (Rod Swap), pem 332 335 -3 +/-100 Total Bank Worth, pem 5448 5661 -3.8% +/-10%
S2C24 testing time: 7.1 hrs
[criticality 6/15/2011 @ 1442 to end of rod swap 6/15/2011 @ 2145]
Recent Startups:
S1 C24 testing time: 7.0 hrs S2C23 testing time: 9.4 hrs S1 C23 testing time: 6.2 hrs S2C22 testing time: 6.2 hrs S1C22 testing time: 8.0 hrs S2C21 testing time: 5.8 hrs S1 C21 testing time: 5.0 hrs Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 38 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
SECTION 8 - REFERENCES
- 1. D. T. Smith, "Surry Unit 2, Cycle 24 Design Report," Engineering Technical Evaluation ETE-NAF-2011-0055, Rev. 0, May, 2011.
- 2. R. W. Twitchell, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," Topical Report VEP-FRD-36-Rev. 0.2-A, September 2004.
- 3. J. G. Miller, "The CEBRZ Flux Map Data Processing Code for a Movable In-core Detector System," Technical Report NE-1581, Rev. 0, September 2009.
- 4. Surry Units 1 and 2 Technical Specifications, Sections 3.l2.C.l, 3.12.F.l, 4.1O.A.
- 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. B. R. Kinney, "Surry Unit 2 Cycle 24 Core Follow TOTE Calculations," Calculation PM-1438, Rev. 0, April, 2011.
- 7. D. T. Smith et aI, "Surry Unit 2 Cycle 24 Flux Map Analysis," Calculation PM-1439, Rev.
0, and Addenda A - B, June, 2011.
- 8. M. S. Lico / R. K. Fawls, "Reload Safety Evaluation Surry 2 Cycle 24 Pattern UPO,"
EVAL-ENG-RSE-S2C24, Rev. 0, March, 2011.
- 9. S. B. Rosenfelder and S. S. Kere, "RMAS v6 Verification," Calculation PM-1075, Rev. 0, May, 2005.
- 10. B. J. Vitiello, Reload Transition Safety Report (RTSR): Westinghouse 15x15 Upgrade Fuel Design Transition at Surry 1 and 2," Engineering Technical Evaluation ETE-NAF-2010-0079 Rev. 0, January 2011.
- 11. B. R. Kiillley, "Surry Unit 2 Cycle 24 Full Core Loading Plan," Engineering Technical Evaluation ETE-NAF-201O-00n, Rev. 0, November, 2010.
- 12. N. A. Yonker, "Validation of Rod Drop Test Computer for Hot Rod Drop Analysis,"
Calculation PM-1044, Rev. 0, November, 2004.
- 13. A. H. Nicholson, "Justification For Defining 0 To 2 Steps Withdrawn As Fully Inserted When Measuring Control And Shutdown Banks During The Surry Startup Physics Testing Program," Engineering Transmittal ET-NAF-06-0046, Rev. 0, April, 2006.
- 14. B. R. Kinney, "Surry Unit 2 Cycle 24 Startup Physics Testing Logs and Results",
Memorandum MEMO-NCD-20110046-0-0, June, 2011.
- 15. J. G. Miller, "The CECOR Flux Map Analysis Code for a Movable In-core Detector System," Technical Report NE-1582, Rev 0, September 2009.
Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 39 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
APPENDIX - STARTUP PHYSICS TEST
SUMMARY
SHEETS Suny Unit 2 Cycle 24 Startup Physics Tests Report Page 40 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Preparerl (Measured Value i\c(:o tance Criteria Re'!iewer lpTR=: _.J_ Yes
-to )( \o-'!
flM/1I URY N1A NJA fl 1 l( )O--:r No 1'S4D r
Pc:::: 55.4~) -qS.ll'7 p;ml I{(Pc- pJlpJl x 100% ~ 4.0 %3 u!t5/U (measured reactivity) The allowable range is set to the larger of the measured results or the pre-
--L Yes @
Pt= 55.2., -l/S.-=r:r pem. critical bench test. 1540 ~'1 (predicted reactivIty) NlA No NlA
%0 :::; ((PC - pt)/pt} x 100%
%0:::; o.~. ~/ - Q .ttz I-Pre-Qillcal Bench Tesl Results
+: - \
Allowable range em
-ti_ 12-3 pcm
'fW' (Cs>MAROo; \$'1~.' 3 ppm (Adj. To design conds.)
CkrJSO S f4.{"". otrmO<l + otr°Of' lJ/YSlll (aiS'1ARO =1 -l.l.. 31- +/- 2 pcmlF otrlSO S 3.70 pemiF ~ Yes _ J Yes ~ Sf.i pcmIF where: (a/,Cu",); 6.0 pemfF [COLR 3.4] No No (a.F'O)MAAO - (iXr1SO)ARO:::; -o.m pcmJF (lXl'mod)2; 0.5 pcmIF (a,-DOP)1; .1.80 pcmlF N/A References 1.) ETE-NAF-2.011-OO55. Rev. 0 2.} Memorandum from C.T. Snow to E.J. Lozito. dated June 27. 1980 3.) Westinghouse Report WCAP-7905. Rev. 1 4.) ETE-NAF*2011.Q037. Rev. 0 5.) Calculation PM-1435. Rev. 0 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 41 of 46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Surry Power Station Unit 2 Cycle 24 Startup Physics Test Summary Sheet - Formal Tests (Page 2of6)
Design Oatel Criteria Acceptance TIme of Preparerl Measured Value D~i n Criteria AI;ce ance Criteria Met Criteria Met Teat Reviewer (Cel""e= (Cs>a=' 1422+.6(Cn}AAO +/- 30 ppm
~IL..03w81L,7f...J;;~l.-- __ ppm ~(Ca)ARO= w;?>I.7 "ppm (from above)
(Gs)e= 1390.1 :l: 30- ppm NIA
-i- Yes NfA No (Cs)t.lB- (Cs)8 =- ~.~' ppm aCe :: 1 -7.51 +/- 0.75 pcmlppm NlA Ao:CB=(aCe.}M - (exCe)=O,B pcmlppm oS 32. f pcm NJA (IC~04= e 15'. 2- +/-15% .
263*g pcm 100x(Meas. - Des.)lDes. = -=..6...L % NJA lSARS: (ISARS)'= iJ.7. fj +/-15%
- 9,2.., pem 100x(Meas. - Des.)lDes. = ~ % NlA II)RS_ - (l oRS)4: 105"'0.9 +/-15%
to OR, G pcm 100x(Meas. - Des.)lDes. = -t{,O . % NlA IsaRS_ - (IS!! RS)4= 10 t.{S'. 9 +/-15%
t\ge.2. pem 10Ox(Meas. - Des.)lDes.: -s-.6' % NlA ITotaF (I1i>t.t= 566 (. t +/- 10%
- NJA
~Cj f./,R.3,. pcm 100x(Meas. - Des.)JOes. = -:U~ %
References i.) ETE-NAF-2011-0055. ReIJ. 0 2.} Memorandum from C.T, Snow to E.J. lozito, dated June 27. 1980 3,} Westinghouse Report WCAP-7905, Rev. 1 4.} ETE..NAF-2011*0037, ReIJ. 0 5.. } Calculalion PM-1435, Rev. 0 Suny Unit 2 Cycle 24 Startup Physics Tests Report Page 42 of46 ETE-NAF-2011-0083, Rev. 0 Enelosme
. Surry Power Station Unit 2 Cycle 24 ~p Physics Test Summary Sheet - Formal Tests o.llgn Critarra Met
- 10% for Pa :ao.9
%OIFP-: -y/r" ~ PI ~O.9 :t15~ for Pj <O.9 NlA . _ _ No HI"
% forP:<O.9 (P ,. aIUlYpower)'~.
NudeII' Enthalpy Rite Hot Cllannel rllCtor. PAH(N)
NIA F~H(~.${HO.3(1.p}) 1C0lR 3.7} NfA Yes No .
Total Htat flux Hot Ch<<M.1 F.etor; FQ(Z)
NlA F~Z)s5"K(Z} lCOlR 3.7J
. NlA
-LVes rlbA..1f Paak Fc{Z) Hot Ch~
Faclor- .2-, ZI <-f Minimum Matgln to COl.R llml.t- ...
st.;:, :i6" No S1.02~
NIA NJA
__ No
- S Roddtd Flux Map Criterion (If 11tMr ~on II m.t.lIl'od~ flux map s3O'X. pawl' with rode at th.IMltUOfdlmlt II not requftlil)
Max RPO %OJFF=" NlA ~ 2.0.3% N/A
~rh 4(/1 for P> 0.9 01:11 3t)t OR' Synlhel$i$l F<lIi lit NlA FAH ~1.56(1+0.3(1.P) lCOlR 3.7) NI" References 1.) ETE-NAF-2011-Q055. Rev. 0 .
2.) Memorandum from C.T. Snow to E.J.loZllo. dated June 27, 1980 3.) Westinghouse ReportWCAP.7905. Rev. 1 4.) ETE-NAF-2011-OO37. Rev. 0 5.} calculation PM-1435. Rev. 0 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 43 of46 ETE-NAF-2011-0083. Rev. 0 Enclosure
Suny Power Station Unit 2 Cycle 24 Startup Physics Test Summary Sheet - Formal Tests (Page4of 6)
Design Datil CriterIa' TIme of Met Tett Max Relatlvt ~Nnb
%DIFF= g, 1.... %fQr PI ~O.9 No NlA
. -3. %forP,<O,9 l,S NucltarEnthel RI8tliot Charmel Fa~r. FAH(N)
NlA F.6.H(N)S1 .56(1 +0.3(1-P>> [CO!.R 3.7}
NIA Lv" No-T~lliftt flux Hot Chln081 Factor, FQ )
NIA F<iZ)~.5IP}"K(Z) lCOLR 3. 7]
NlA.
LV&$
71'.7 t:
Peek Fr}l:) Hot ha~
FacIOI':> Z;<f . IoCOLRUmil,. No Malllmllm Posltlw lneore Qu.drart Powu tilt NIA NIA
. 1'Jt; No Referencas 1.) ETE-NAF-2011.o055, Rev. 0 2.} Memorandum trom C.T. Snow to E.J. lozito. dated June 27, 1980
~.rWestinghouse Report WCAP--7905, Rev. 1 4.) ETE-NAF-2Q11.{)037, Rev. 0 .
5.) Calculation PM-1435. Rev. 0 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 44 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Surry Power Station U;",i: 2 Cycle 24 Startup Physics Test Summary Sheet - Formal Tests (Page 5 of 6)
DesIgn DatoJ Criteria Time of Met Test
+/-10% fe' 1', <:0.9 / Yes
%DlfF= '2.. (" , % fo.Pi ~O.9 £:15% (or P;-<O.9 N1A NO NfA
- ~.J ' %10,1',<0.9 (?i=l!$sypower)l~
Nuclear Enthalpy Rise Hot Chantl91 FaclM. FAH(N FAH(fIi};>l.56(1+O.3(1.P)} \COLR 3.7]
NIA NlA Total Heat Flux Hot ChalWll Factor, fQ{2.)
FO(Z~.5JP}1<(Z} LCOLR :J.7I ~Yes NfA NlA Peak Fc!Z) HGtChanno).
Faclor- \. ~'1e MinlmLlrT1Ma, intoCOLRUll111;; z..G:.:li~ No Maximum Po~ili"" fncoco Quadrant PowerTilt
/ ' Yes No'A NlA
\.OCXo5 NO References 1.) ETE-NAF*2011-0055, Rev. 0 2.) Memorandum from C.T. Snow to E.J. Lozito. dated June 27. 1980 3.} Westinghouse Report WCAp-7905, Rev. 1 4.) ETE-NAF-2011-Q037, Rev. 0 5.) Calculation PM-1435, Rev. 0 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 45 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure
Surry Power S~.:;j.=,*, *.!.1;i 2 Cycle 24 Startup Physics Test Summary Sheet- Formal Tests (Page 6 of 6)
,:--.... ~---- .- ~--,....- -'." Design Datel i"---,
I Criteria Acceptance Time of Prepar<:rl i AcceptanCQ CrilQria Met Criteria Mot Test Reviewer
~ ..-
FIct4i ~ 276000 gpm [COLR 3.8] Yes t.11t/d NfA NJA Ii '/'1
?~~ ¥"" 7S. ~.\~
No References 1.) ETE-NAF.2011..Q055, Rev. 0 2.) Memorandum from CT Snow to E.J.lozito, dated June 27.1960 3.) Westinghouse ReportWCAP-7905. Rev, 1 4.) ETE-NAF-2011-o037. Rev. 0 5.) C~lcula~on PM-1435. Rev. 0 Surry Unit 2 Cycle 24 Startup Physics Tests Report Page 46 of46 ETE-NAF-2011-0083, Rev. 0 Enclosure