ML18151A976

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Cycle 14 Startup Physics Test Rept. W/960830 Ltr
ML18151A976
Person / Time
Site: Surry Dominion icon.png
Issue date: 08/13/1996
From: CLEMENS C D, LAWRENCE D C, PSNIK T S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: EBNETER S D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
96-420, NE-1082, NE-1082-R, NE-1082-R00, NUDOCS 9609100125
Download: ML18151A976 (59)
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{{#Wiki_filter:.I I .I I .I *1 I I I' I TECHNICAL REPORT NE-1082 -Rev. 0 *suRRY UNIT 2, CYCLE 14 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING AND SERVICES VIRGINIA POWER AUGUST 1996 PREPARED BY: t.JJ. C. D. Clemens APPROVED BY: _/~ -~dos~ ... QA Category: Nuclear Safety Related Keywords: SPS2, S2C14, Startup ~80 Date Bl if,~ Date Date I I I I ;I .I I I I I I ,. I I Ii ,1 I* :1 1:. CLASSIFICATION/DISCLAIMER The data, -techniques, information, and c<;mclusions in this report have been prepared solely for use by Virginia Electric and Power Company (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. NE-1082 S2C14 Startup Physics Tests Report Page 1 of 56 TABLE OF CONTENTS Classification/Disclaimer .............................. . Table of Contents .....................

  • ................. . List of Tables ......................................... . List of Figures ........................................ . Preface ................................................ . Section 1 Introduction and Summary ......... ........ . PAGE 1 2 3 4 5 7 Section 2 Control Rod Drop Time Measurements.........

16 Section 3 Control Rod Bank Worth Measurements ....... . Section 4 Boron Endpoint and Worth Measurements ..... . Section 5 Temperature Coefficient Measurement ....... . Section 6 Power Distribution Measurements ........... . Section 7 References ................................ . APPENDIX Startup Physics Test Results and Evaluation Sheets ....................... . NE-1082 S2C14 Startup Physics Tests Report Page 21 26 30 32 39 40 2 of 56 *I I I I I I I I .I* *1 I I I I I I* LIST OF TABLES TABLE TITLE PAGE 1. 1 Chronology of Tests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2.1 Hot Rod Drop Time Summary............................. 18 3.1 Control Rod Bank Worth Summary........................ 23 4.1 Boron Endpoints Summary~****************************** 28 5.1 Isothermal Temperature Coefficient Summary............ 31 6.1 Incore Flux Map Summary............................... 34 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits...................... 35 NE-1082 S2Cl4 Startup Physics Tests Report Page 3 of 56 LIST OF FIGURES FIGURE TITLE 1. 1 Core Loading Map ........................................ . 1.2 Beginning of Cycle Fuel Assembly Burnups ................ . 1. 3 Incore Thimble Locations ................................ . 1.4 Burnable Poison and Source Assembly Locations .......... . 1. 5 Control Rod Locations .................................... . 2. 1 Typica 1 Rod Drop Trace .................................. . 2.2 Rod Drop Time -Hot Full Flow Conditions ................ . 3.1 Bank B Integral Rod Worth -HZP ......................... . 3.2 Bank B Differential Rod Worth -HZP ...............

  • ...... . 4. 1 Boron Worth Coefficient

................................. . 6.1 Assemblywise Power Distribution -24% Power ............. . 6.2 Assemblywise Power Distribution -71% Power ...... , ...... . 6.3 Assemblywise Power Distribution -100% Power ............. . NE-1082 S2C14 Startup Physics Tests Report Page 4 PAGE 11 12 13 14 15 19 20 24 25 29 36 37 38 of 56 ,I ., I I 1* ,.1:* ,. I. I* I. ,I 1* .,~~ I ,I 1, *I I I I* ,1 I* ,I 'I I ,, ,, I I I I I, I I I I I ,, PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 14 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 test techniques and methods of data analysis were used. The test data, results, and evaluations, coupled with the deta1led startup procedures, are on file at the Surry Power Station. Therefore, only a cursoJ"y 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 2, Cycle 14 Startup Physics Test 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 conditions (design), 3) test conditions (actual), 4) t~st results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values at these design conditions for the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1* During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the NE-1082 S2Cl4 Startup Physics Tests Report Page 5 of 56 preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests. NE-1082 S2C14 Startup Physics Tests Report Page 6 of 56 II 1* I ,I 1* I I I, ,, 1 1 *1 I ,I 1* 1 1, 1* *I II I

,, ,1 ,, ,I 'I I ' 1. 'I I, ,. *1 I, *1 I 'I I I 1:. SECTION 1 INTRODUCTION AND

SUMMARY

On May 3, 1996 Surry Unit 2 shut down for its thirteenth refueling. During this shutdown, 69 of the 157 fuel assemblies in the core were replaced with 60 fresh assemblies, 1 once-burned assembly, and 8 twice-burned assemblies. The Cycle 14 core consists of eight sub-batches of fuel: two fresh batches (batches 16A and 16B); three once-burned batches, two from Cycle 13 (batches ISA and 15B) and one from Surry 1 Cycle 13 (batch Sl/lSA); and three twice-burned batches, two from Cycles 12 and 13 (batches 14A and 14B) and one from Cycles 11 and 12 (batch 13B). The core loading pattern and the design parameters for each sub-batch are shown in Figure 1.1. Beginning-of-cycle (BOC) fuel assembly burnups are given in Figure 1. 2. The incore thimble locations available

  • during startup physics testing are identified in Figure 1. 3. Figure 1.4 identifies the location and number of burnable poison rods and secondary source locations for Cycle 14, while Figure 1.5 identifies the control rod locations.

The Cycle 14 core achieved initial criticality at 1756 on June 5, 1996. Startup physics tests, with the exGeption of hot rod drops, were performed after criticality as outlined in Table 1.1. Hot rod drops were performed prior to criticality. A summary of the physics test results follows. 1. The measured drop time of each control rod was within the 2. 4 ---second limit of Technical Specification 3.12.C.1. NE-1082 S2C14 Startup Physics Tests Report Page 7 of 56

2. 3. 4. 5. The reference control rod bank was measured with the dilution method, and the result was within 0.7% of the design prediction.

Individual control rod bank worths were measured using the rod swap technique 2'3 and all results were within 4.0% of the design predictions. The sum of the individual measured control rod bank worths was within 1.4% of the design prediction. All results were within the design tolerance of +/-15% for individual bank worths (+/-10% for the rod swap reference bank worth) and the design tolerance of +/-10% for the sum of the individual control rod bank worths. Measured critical boron concentrations for two control bank configurations were within 19 ppm of the design predictions. The all-rods-out (ARO) result was within the 50 ppm design tolerance, and met the Technical Specification 4.10 .A criterion that the overall core reactivity balance shall be within +/-1% tk/k of the design prediction. The reference bank in critical boron concentration was within its design tolerance. The boron worth coefficient measurement was within 0.6% of the design prediction, which is within the design tolerance of +/-10%. The measured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within 0.92 pcm/°F of the design prediction. This result is within the design tolerance of +/-3 pc~/ °F. The measured ITC was -0. 6 7 pcm/ °F. When the Doppler temperature coefficient (-1.67 pcm/°F) and a 0.5 pcm/°F uncertainty are accounted for in the +6.0 pcm/°F MTG limit of the NE-1082 S2C14 Startup Physics Tests Report Page 8 of 56 I I I I, I I ',I .1,, I I I I .1. I ,I, I I I I .1 ,1 I \II I I *f .1: *1 I I I I I 1. *1 ,, I 1: 6. Core:;, Operating Limits Report (COLR) Section 2, 1, the MTC requirement is satisfied as long as the ITC is less positive than 3. 83 pcm/°F. Measured core power distributions were within established . acceptance criteria and COLR limits. The average . relative assembly power distribution measured/predicted percent difference was 2.1% or less for the three initial power ascension flux maps. The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of COLR Sections 2.3 and 2.4, respectively. Note that since there are no LOPAR assemblies in this cycle, the FdH limits for all assemblies are the same. 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 repor~.* NE-1082 S2Cl4 Startup Physics Tests Report Page 9 of 56 Table 1.1 SURRY 2 -CYCLE 14 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Test Date Time Power Hot Rod Drop -Hot Full Flow.*~ 6/04/9_6 0050 HSD Zero Power Testing Range ....... 6/05/96 2012 HZP Reactivity Computer Checkout ... 6/05/96 2054 HZP Boron Endpoint -ARO ........... 6/05/96 2250 HZP Boron Worth Coefficient -ARO .. 6/05/96 2250 HZP Temperature Coefficient -ARO .. 6/05/96 2351 HZP Bank B Worth ................... 6/06/96 0109 HZP Boron Endpoint -Bin .......... 6/06/96 0445 HZP Bank D Worth -Rod Swap ........ 6/06/96 0551 HZP Bank C Worth -Rod Swap ........ 6/06/96 0623 HZP Bank A Worth -Rod Swap ........ 6/06/96 0725 HZP Bank SB Worth -Rod Swap ....... 6/06/96 0810 HZP Bank SA Worth -Rod Swap ....... 6/06/96 0846 HZP Flux Map -24% Power ........... 6/08/96 0043 24.3% Peaking Factor Verification & Power Range Calibration Flux Map~ 71% Power ........... 6/09/96 0640 71.0% Peaking Factor Verification & Power Range Calibration Flux Map -100% Power ...... ~**** 6/13/96

  • 1000 100 .1% Peaking Factor Verification

& Power Range Calibration Reference Procedure 2-NPT-RX-014 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-008 2-NPT-RX-002 2-NPT-RX-008 2-NPT-RX-002 2-NPT-RX-008 2-NPT-RX-002 2-NPT-RX-008 NE-1082 S2C14 Startup Physics Tests Report Page 10 of 56 I, 1* I t* I 1* ,f; I 1* .,, , .. I I' I I I I I I !' I I I, I I ,, I I R p H " Figure 1.1 SURRY UNIT 2 -CYCLE 14 CORE LOADING KAP L K J H G I l3B I l4B I l3B I I 5VB I 4W5 1:;:I 6VZ I F E I 148 I 148 I l6B I 158 I 168 I 148 I l4B I I 5W8 I 5WO I 3Y3 I 5Xl I 3Y8 I 4W8 I 6W4 I D I 14A I 16A I 168 I 158 I l6B I 158 I 168 I 16A I 14A I I lWZ I OYl I 3Y5 I 4X9 I 5Yl I 4X7 I 4YO I OY8 I 1W6 I C I 14A I 14A I 168 I l5B I 16A I 15A I 16A I 158 I l6B I 14A I 14A I I ow*1 I ZWl I 4Yl I 5XZ I OY4 I oxz I lYZ I 3XO I 5Y6 I Oil9 I 1W9 I B I l4B I 16A I 168 I 15A I 16A I 15A I l5B I 15A I 16A I 15A I 168 I 16A I 148 I I 6W8 I 1Y8 I 4Y4 I OX4 I 1Y9 I OX5 I 3X6 *I 1X8 I 3Yl I lXl _ I 4YZ I 1Y4 I 6WZ I I 148 I 168 I 158 I 16A I 15A I 16A I 15A I 16A I 15A I 16A I 158 I 168 I 148 I I 4WO I 5YO I 5X3 I ZYO I 1X6 I ZY4 I 1X5 I lYO I OX7 I 3YZ I 3X4 I 3Y6 I 6W6 I A I BB I 168 I 158 I 16A I 15A I 16A I 15A I 158 I 15A I 16A I 15A I 16A I 158 I 168 I BB I I 3Y5 I 5Y7 I 3X7 I lYl I ZX3 I ZY6 I lXZ I 3X5 I 1X4 I OY3 I OX9 I OY7 I 4Xl I 3Y4 I 4V9 I I 148 I 158 I 168 I 15A I 158 I 15A I 158 ISl/lSAI 158 I 15A I 158 I 15A I 168 I 158 I 148 I I 3W4 I ZX9 I 4Y5 I OXl I SXS I 1X7 I sxo I OK8 I 4XO I ZX4 I 5X6 I 1X9 I 6YO I 3X8 I 4WZ I I BB I 168 I 158 I 16A I 15A I 16A I 15A I 158 I 15A I 16A I 15A I 16A I 158. I 168 I BB I I 4Y5 I SYS I 5X4 I ZYS I ZX7 I 1Y6 I ZXl I 4XZ I OX6 I ZY3 f ZX6 I 3YO I 4X3 I 4Y6 I SYS I I 148 I 168 I 158 I 16A I 15A I 16A I 15A I 16A I 15A I 16A I 158 I 168 I 148 I I 5W6 I 5Y9 I. 4X6 I ovz I ZX5 I OY9 I 1X3 I ZY7 I lXO I 1Y3 I 3X3 I 4Y9 I 4W7 I I 148 I 16A I 168 I 15A I 16A I 15A I 158 I 15A I 16A I 15A I 168 I 16A I 148 I I 6WO I OY5 I 5YZ I OX3 I 1Y7 I ZXO I 4X5 I ZXZ I OY6 I ZX8 I 5Y4 I lYS I SWl I I 14A I 14A I 168 I 158 I 16A I 15A I 16A I l5B I 168 I 14A I 14A I I ZW7 I 1W3 I 4Y3 I 4X4 I ZY8 I OX8 I ZYl I 4X8 I 4Y8 I OW8 I lWl I I 14A I 16A I 168 I l5B I 168 I 158 I 168 I 16A I 14A I I zwo I ZY9 I 3Y9 I 3X9 I 5Y3 I 3XZ I 5Y8 I zyz I ZW3 I 1--> BATCH I 1--> ASSEHBLY ID I __ I INITIAL ENRICHHENT CW/0 U-Z35J BURHUP AT BOC 14 CHWD/HTU) ASSEHBLY TYPE NUHBER OF ASSEHBLIES FUEL RODS PER ASSEHBLY I 148 I 148 I 168 I 158 I 168 I l4B I 148 I I 6W5 I 6Wl I 3Y7 .I 3Xl I 4Y7 I 6W3 I SWZ I Sl/15A 3.8Z ZZ59Z 15xl5 l Z04 I BB I 148 I BB I I 4YO. I 3W7 I 5YZ I FUEL ASSEHBLY DESIGN PARAHETERS-SUB-BATCH 138 14A 148 15A 158 4.00 3.81 4.01 3.81 4.01 39630 30496 35383 17303 15559 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 8 lZ zo Z8 Z8 ---204 204 204 Z04 204 16A 3.80 0 15Xl5 3Z 204 NE-1082 S2Cl4 Startup Physics Tests Report Page 168 4.01 0 15Xl5 Z8 204 11 of 56 1 z 3 4 5 6 7 8 9 10 11 12 13 14 15 R p Figure 1.2 SURRY UNIT 2 -CYCLE 14 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS N " L IC J H C I 5V8 I 4W5 I 6V2 I l,39.191 35.111 39.471 F E I 5W8 I 5WO I 3Y3 I 5Xl I 3Y8 I 4W8 I 6W4 I I 37.161 32.851 0.001 17.091 0.001 33.181 37.931 D l~l~l~l~l~l~l~l~l~I I 28.791 0.001 0.001 14.081 0.001 13.981 0.001 a.001 28.481 C I OWi I ZIil I 4Yl I 5X2 I OY4 I OX2 I 1Y2 I 3XO I 5Y6 I OW9 I 1W9 I I 28.651 33.711 0.001 15.921 0.001 17.921 0.001 16.301. 0.001 34.461 28.591 B *1 6W8 I 1Y8 . I 4Y4 I OX4 I 1Y9 I DX5 I 3X6 I 1X8 I 3Yl I lXl I 4Y2 I 1Y4 I 6W2 I I 38.IOI 0.001 0.001" 16.911 0.001 11.241 1s.s21 17.'!ll 0.001 11.041 0.001 0.001 36.861 I 4WO I SYD I 5X3 I 2YO I 1X6 I 2Y4 I 1X5 I IYO I OX7 I 3Y2 I 3X4 I 3Y6 I 6W6 I I 33.471 0.001 16.191 0.001 11.011 0.001 11.s11 0.001 17.141 0.001 16.041 0.001 33.261 A I 3V5 I 5Y7 I 3X7 I lYl I 2X3 I 2Y6 I 1X2 I 3X5 I 1X4 I OY3 I OX9 I OY7 I 4Xl I 3Y4 I 4V9 I I 39.691 0.001 13.971 0.001 11.211 0.001 17.451 15.641 11.101_ 0.001 J7.19I 0.001 13.971 0.001 39.301 I 3W4 I 2X9 I 4Y5 I DXI I 5X5 I IX7 I 5XO I OKS J 4XO I 2X4 I 5X6 I IX9 I 6YO I 3X8 I 4W2 I I 35.371 17.151 o.ool 17.371 15.471 17.701 15.601 22.591 15.891 17.611 15.591 17.241 0.001 17.0ll 35.291 I 4V5 I 5Y5 I 5X4 I 2Y5 I 2X7 I 1Y6 I 2Xl I 4X2 I OX6 I 2Y3 I 2X6 I 3YD I 4X3 I 4Y6 I 5V5 I I 39.801 0.001 13.951 0.001 11.221 0.001 17.621 15.641 11.111 0.001 17.481 0.001 13.981 0.001 39.681 I 5W6 I 5Y9 I 4X6 I DY2 I 2X5 I OY9 I 1X3 I 2Y7 I lXO I 1Y3 I 3X3 I 4Y9 I 4W7 I _I 33.331 0.001 16.251 0.001 16.751 0.001 17.521 _ o.oll'I 16.951 0.001 16.441 0.001 32.941 I 6WO I OY5 I 5Y2 I OX3 I 1Y7 I 2XO I 4X5 I 2X2 I OY6 I 2X8 I 5Y4 I 1Y5 I 5Wl I I 37.491 0.001 0.001 16.891 0.001 17.391 15.681 17.321 0.001 17.231 0.001 0.001 37_.781 I 2W7 I 1W3 I 4Y3 I 4X4 I 2Y8 I OX8 I 2Yl -I 4X8 I 4Y8 I OW8 I IWI I I 28.991 34.611 0.001 16.311 0.001 17.381 0.001 16.351 0.001 33.861 28.321 I 2WO I 2Y9 I 3Y9 I 3X9 I 5Y3 I 3X2 I 5Y8 I 2Y2 I 2W3 I I 28.571 O.DDI O.OOI 14.201 O.OOI 14.051 O.DDI O.OOI 28.921 I 6W5 I 6Wl I 3Y7 I 3Xl I 4Y7 I 6W3 I 5W2 I . I 38.061 33.~21 0.001 17.071 0.001 33.201 37.231 I 4VO I 3W7 I 5V2 1* I 39.681 35.251 40.241 I 1--> ASSEHBLY ID I 1--> ASSEHBLY BURNUP CGWD/HTU) I __ I NE-1082 S2C14 Startup Physics Tests Report Page 12 of 56 ,I 1-I ,, l 1: 2 3 I 4 5 ,-6 7 .I 8 9 I 10 11 :1 12 ,, 13 14 I 15 I 1* -l I I I I I *1 I I I 1. I I I I .J I. I I I I I R p N " Figure 1.3 SURRY UNIT 2 -CYCLE 14 INCORE THIMBLE LOCATIONS L I{ J H G I I

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  • I I I I I I I I I I I I IITI IITI IITI I I I IITI I IITIITI I l __ l __ l __ l __ l __ l __ l __ l __ l __ l __ l __ l __ l __ l __ 1_-__ I I I I I I I I I I I I I I I I I I I I I I IT I I I I IT I IT I I I I I IT I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I I IITI I I IITI I I I IITI IITI 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1_._1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I I I I IHI I IITI IITIITI I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I IITI I I IHI I I I IITIITI 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I " I I I I I --1 I I I I IT I I IT I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I IT I I I I IT I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I. I I IT -Incore Thimble I IT I I I 111: -Unavailable Location I __ I __ I __ I NE-1082 S2C14 Startup Physics Tests Report Page 13 of 56 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 Figure 1.4 SURRY UNIT 2 -CYCLE 14 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R p N H L I( J H C F E D C B A I I I I I ---:-__ , __ , __ , __ I ____ _ I I I 4P I I 4P I I I I IBP451 I IBP455 I I I __ 1 __ 1 __ 1 __ , __ ,~_1 __ 1 __ 1 __ I I 4P I 16P I I ZOP I I 16P I 4P I I I IBP445 IBPCOO?I IBP4BO I IBPC008IBP446 I I __ 1 __ 1 __ , __ 1 __ 1 __ 1~_1 __ 1 __ 1~_1 __ I I I 16P I I zop I I 20P I I 16P I I I I I IBP465 I IBP4BS I IBP486 I IBP466 I I I __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ I I 4P I 16P I I 20P I I ZDP I I ZOP I I 16P I 4P I I I SS4 I BP449 I BP461 I I BP493 I I BP467 I I BP494 I I BP462 I BP450 I I l __ l __ l __ l~_l __ l __ l __ l~_I __ I __ I __ I __ I __ I I I 16P I I 20P I I ZOP I I ZOP I I 20P I I 16P I I I IBPCDlll IBP497 I IBP473 I IBP474 I IBP49B I IBPCOlZI I __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1~_1 __ 1 __ 1~_1 __ 1 __ 1 __ I I 4P I I ZDP I I ZDP I I BP I I ZDP I I 20P I I 4P I I I IBP45B I IBP489 I IBP477 I IBPCOOll IBP478 I IBP490 I IBP45Z I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I ZOP I I zop I I 8P I I BP I I ZOP I I ZOP I I I I I IBP481 I IBP469 I IBPC0031 IBPCOD41 IBP470 I IBP482 I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ ._1 I I 4P I I ZDP I I ZOP I
  • I 8P I I 20P I I 20P I I 4P I I I SS3 IBP454 I IBP487 I IBP475 I IBPCOOZI IBP476 I IBP48B I IBP456 I SSS I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1~_1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I 16P I I ZDP I I ZDP I I ZDP I I ZOP I I 16P I I I IBPCDD91 IBP495 I IBP471 I IBP472 I IBP496 I IBPCOlOI I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I 4P I lbP I I ZOP I I ZOP I I ZOP I I 16P I 4P I I I IBP447 IBP459 I IBP491 I IBP46B I IBP492 I IBP460 IBP44B I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I 16P I I ZOP I I ZOP I I 16P I I I I I IBP463 I IBP4B3 I IBP484 I IBP464 I I I l __ l __ ._l __ l __ l __ l __ l~_I __ I __ I __ I __ I I I 4P I 16P I I ZDP I I 16P I 4P I I I IBP443 IBPCDDSI IBP479 I IBPCOD6IBP444 I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ , __ 1 __ 1 __ 1 4P -4 BURNABLE POISON ROD CLUSTER BP -B BURNABLE POISON ROD CLUSTER 16P -16 BURNABLE POISON ROD CLUSTER 20P -20 BURNABLE POISON ROD CLUSTER SSx -SECONDARY SOURCE XXP -I OF BP RODS I I I 4P I I 4P I I I I I IBP457 I IBP453 I I I l __ l __ l __ l __ l~_I __ I __ I I I I I I I I I I __ I __ I __ I BPMII, SSW -BP ASSEHBLY ID, SECONDARY SOURCE ID NE-1082 S2C14 Startup Physics Tests Report Page 14 of 56 I 1* I I 11 2 3 ,I 4 5 I 6 7 I 8 I 9 10 I. 11 12, *., 13 14 I 15 I. .I ,I 1* I I .,

I I I I, I I I ,I *,. I I I I I I I R p N H Figure 1.5 SURRY UNIT 2 -CYCLE 14 CONTROL ROD LOCATIONS L K J H 180° I G I I I I F E ____ I __ I __ I __ I ___ _ 0 I I A I I o I I A I I _1_1_1_1_1_1_1_1_ C N-41 I I I I SA I I SA I I I

  • I N-43 __ 1_1_1_1_1_1_1_1_1_1_

B I I c I I B I I I I B I I c I I _I_I_I_I_I_I_I_I_I_I_I_I_ I I I I SB I I I I I I SB I I I I 1_1_1_1_1_1_1_1_1_1_1_1_1_1 IAI IBI IOI ICI IDI IBI IAI A _1_1_1_1_1_1_1_1_1_1_1_1_1_1_ I I I SA I I I I SB I I SB I I I I SA I I I 1_1_1_1_1_1_1_1_1_1_1_1_,_,_,_, I I D I I I I c I I I I c I I I I D I I 1_1_1_1_1_1_1_1_1_,_,_,_,_,_1_1 I I I SA I I I I SB I I SB I . I I I SA I I I 1_1_1_1_1_1_1_1_1_1_1_1_1_1_1_1 Absorber Material Ag-In-Cd Function IAI IBI IOI ICI IDI IBI IAI 1_1_1_1_1_1_1_1_1_,_,_,_1_1 I I I I SB I .1 I I I I SB I I I I I_I_I_I_I_I_I_I_I_I_I_I_I_I I I c I I B I I I I B I I c I I 1_1_1_1_1_1_1_1_1_1_1_1 I I I I SA I

  • I SA I I I I N-44 I __ I __ I __ I __ I __ I __ I __ I __ I __ I N-42 I I A I I D I I A I I I_I_I_I_I_I_I_I I I I I I_I_I_I I 00 Number of Clusters Control Bank D Control Bank C Control Bank B Control Bank A Shutdown Bank SB Shutdown Bank SA 8 8 8 8 8 8 -270° NE-1082 S2Cl4 Startup Physics Tests Report Page 15 of 56 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tave of 547+/-5°F) in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.12.C.1.

During this test, the RCS pressure varied between 2246 psia and 2249 psia, the RCS flow was 100%, and the RCS Tave varied between 544.9°F and 545.7°F. The rod drop times were measured by withdrawing a bank to its fully withdrawn position and tripping all eight control rods within the bank by opening the reactor trip breakers. This allowed the rods to drop into the car~ as they would during a plant trip. The Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded for each rod in the bank to determine each rod's drop time. repeated for each bank. This procedure was As shown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the increase in IRPI coil voltage when the reactor trip breakers are opened. As the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil voltage. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing. NE-1082 S2C14 Startup Physics Tests Report Page 16 of 56 I 'I, I I I I 1: ,,-1 ,I I I I I I I' I I ,, I I I I I I I I I I I I I I I I I I I The measured drop times for each control rod are recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 seconds with the RCS at hot, full flow conditions. The test results satisfy this limit. In addition, rod bounce was observed at the end of each trace which demonstrated that no control rod stuck in the dashpot region. NE-1082 S2C14 Startup Physics Tests Report Page 17 of 56 L Table 2.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-06 1.43 sec. M-06 1.25 sec. 1.30 sec. NE-1082 S2C14 Startup Physics Tests Report Page 18 of 56 I 1* I I I I *1 I. I I I I .I I :1. I .1 I I I I I ,I. I I I I I I I I I I I I ,. I Figure 2.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE BEGINNING Of' DASHPOT (beginning of first downturn in trace) INITIATJ:ON Of' ROD DROP EVENT MARX I ROD DROP TIME __ .;._ __ _ TIME J NE-l082 S2C14 Startup Physics Tests Report BOT'l'OM OF DASHPOT (beginning of first upturn" in trace) I Page STATIONARY GRIPPER* COIL VOLTAGE TRACE 60Hz IRPI PRIMARY COIL VOLTAGE-TRACE 60Hz TRACE 19 of 56 R Figure 2.2 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS ROD DROP TIME -HOT FULL FLOW CONDITIONS p N " l K J H G F E I I I I I 1 __ 1 __ 1 __ 1 1---1--1 I I l--~1--1 I I l. 27 I I l. 30 I I 1. 28 I I D __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ I I I I I I I I I I I I I I 1.za I I 1.32 I I I I C __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ I I I I I I I I I I I I I I 1. 29 I I 1. 29 I I I I 1. 28 I I 1. 30 I I B __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ I I I I I I I I I I I I I I I I I I 1.21 I I I I I I 1.32 I I I I l __ l __ 'l __ 1 __ 1-__ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I 11.261 11.251 ll.301 ll.311 11.431 11.291 ll.351 A __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ I I I I I I I I I I I I I I I I I I I 1. 29 I I I I 1. 32 I I 1. 33 I I I I 1. 29 I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I I I I I 1.21 I I I I 1.33 I I I I 1.32 I I I I 1.30 I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I I I I I I I.:Sl I I I I 1.31 I I 1.30 I I I I 1.26 I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I I 1.29 I I 1.31 I I 1.30 I I 1.33 I I 1.33 I I 1.21 I I 1.29 I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I I I I I l. 26 I I I I I I l. 29 I I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I I 1.30 I I 1.2a I I I I 1.29 I I 1.32 I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I I I I 11.291 11.291 I I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I I I 1.32 I I 1.26 I I 1.31 I I 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 __ 1 I I I I I I I I 1 __ 1 __ 1 __ 1 I I I X.XX 1--> ROD DROP TIHE TO DASHPOT ENTRY (SEC) I __ I NE-1082 S2C14 Startup Physics Tests Report Page 20 of 56 I I I ,I 11 z 3 ,I 4 5 ,-6 7 I 8 9 I 10 I 11 12 I 13 14 I 15 I I ,,, I I ,, I - I I I I I ,, I I I I I I I I I ,, t I I SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 2 J 3* 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 th~ reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 14, Control Bank B was used as the reference bank. After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position with all other banks fully withdrawn and recording the core reactivity and moderator temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps and then one of the other control rod banks (i.e. a test bank) was inserted to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical or near the initial statepoint reactivity. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to NE-1082 S2Cl4 Startup Physics Tests Report Page 21 of 56 determine the integral reactivity worth of the test bank. The core reactivity, moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver then was repeated in reverse such that the reference bank again was fully inserted with the test bank fully withdrawn from the core. This rod swap process was then repeated for each of the other control and shutdown banks. A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, all of the individual measured bank worths for the control and shutdown banks were within the design tolerance (+/-10% for the reference bank, +/-15% for test banks worth greater than 600 pcm, and +/-100 pcm for test banks worth less than or equal to 600 pcm). The sum of the individual measured rod bank worths was within 1. 4% of the design prediction. This is well within the design tolerance of +/-10% for the sum of the individual control rod bank worths. The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory. NE-1082 S2Cl4 Startup Physics Tests Report Page 22 of 56 I I I I I I ;1 I I I I. I I I I. I I I I I I I I, I I, I I I I I I* I. I. ,. I Table 3.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

MEASURED 'PREDICTED PERCENT DIFFERENCE WORTH WORTH (%) BANK (PCM) (PCM) (M-P)/P X 100. B-Reference Bank 1435.1 1425.0 0.7 D 1158. 3 1173.8 -1. 3 C 759.5 767.9 -1.1 A 250.2 258.8 -3.3* SB 1152.5 1169. 8 -1.5 SA 1093. 9 1139. 9 -4.0 Total Worth 5849.5 .5935.2 -1.4

  • Difference is less than 100 pcm. NE-1082 S2C14 Startup Physics Tests Report Page 23 of 56 1400 1200 z 1000 0 ci5 5 B -:E (.) C. 800 0 :::c ..J 600 C!) w I-z 400 200 0 Figure 3.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS BANK B INTEGRAL ROD WORTH -HZP ALL OTHER RODS WITHDRAWN

,-I I ' " \. ' ' * , II , .. , -, * ' " \. ' * ' , I ' ' * ' I I\. ' ' ' 1* '

  • I\. 1,
  • I\. ' " I ' " 1, ' ' II. I, " ... 0 40 80 120 160 200 B BANK POSITION (5 STEPS/ DIVISION)

Predicted Measured

  • NE-1082 S2C14 Startup Physics Tests Report Page 24 of 56 I I I I I I I I. I I. I I I I I I I I I I I I I I I I I. I I I I I I Figure 3.2 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS
  • BANK B DIFFERENTIAL ROD WORTH -HZP ALL OTHER RODS WITHDRAWN Predicted I I I 12 ...
  • I Measured j \
  • I , .. 1. 1. 10 \ 1 I 1 * -z \ 0 ci5 > 0 8 -Ill \ I ' \ * (.) Cl. IC) r.... f'\~ , , ... N .._;.. '~ Lo,_ .... ' J:
  • 6 Ill ' I * *
  • _J <( j::: z w 0:: w u. u. 0 4 .* . 2 l ' ,. I 'I' ,.,,. I I 0 .... ,'I I 0 40 80 120 160 200 B BANK POSITION (5 STEPS/ DIVISION)

NE-1082 S2C14 Startup Physics Tests Report Page 25 of 56 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, if necessary. The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The all-rods-out (ARO) endpoint comparison to the predicted value met the requirements of Technical Specification 4.10 .A 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, NE-1082 S2Cl4 Startup Physics Tests Report Page 26 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I the value of the DBW over the range of boron endpoint concentr.ations was obtained. A plot of the boron concentration versus inserted control rod worth is shown in Figure 4.1. As indicated in this figure and in the Appendix, the measured DBW was -7.03 pcm/ppm. This is within 0.6% of the predicted value of -6.99 pcm/ppm and is well within the design tolerance of +/-10%. In summary, the measured boron worth coefficient was satisfactory. NE-1082 S2Cl4 Startup Physics Tests Report Page 27 of 56 .* :1 I ! Table 4.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

Measured Predicted Control Rod Endpoint Endpoint Configuration (ppm) (ppm) ARO 1967 1986 B Bank In 1763 1763* Difference M-P (ppm) -19 0

  • 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 Results and Evaluation Sheet in the Appendix.

NE-1082 S2Cl4 Startup Physics Tests Report Page 28 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I :? 0 e:. I > j::: 0 a:: I I 1* I I I I I Figure 4.1 ,SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT

  • * . Measured DBW= -7.03 pcm/ppm . . 1200 ---+--!..,-.

-.J-----4----+----+------jt----t---i . * . . '* . . 1000 -------+------+-_.:*~. --+------t------t----i------r----;

  • . . . ' . * . BOO +-------1-----+-----+--....l',-,----,----t------t-----t-------j . *. . * . . . 600 +------+----+----+------if--....!.'-c-:,~-t-------t-----t------1 . * . . * . . . . 400 -l------1------l------l------,----t-----<:-, ---;r-----i------'t
  • . .. . * .
  • 200 J__----1----~-----+-----lf------+-------t---:..-.

--i-------t

  • . . * . * *, 0 -l------1------l-----+---~----+------+-----+-~-~~

1750 1780 1810 1840 1870 1900 1930 1960 BORON CONCENTRATION (PPM) NE-1082 S2C14 Startup Physics Tests Report Page 29 of 56

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 through varying the steam generator blowdown flow, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.

sequence includes a cooldown followed by a heatup. This test Reactivity was measured during an RCS cooldown of 3.1°F and an RCS heatup of 3.6°F. Reactivity and temperature data, was taken from the reactivity -computer and strip chart recorders. Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which . plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured ITC. 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 Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of +/-3 pcm/°F. Accounting for the Doppler temperature coefficient (-1.67 pcm/°F) and a 0.5 pcm/°F uncertainty, the moderator temperature coefficient was 1.50 pcm/°F, which meets the requirement of Core Operating Limits Report Section 2.1. In summary, the measured result was satisfactory. NE-1082 S2Cl4 Startup Physics Tests Report Page 30 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I BANK POSITION 219 Table 5.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/ F) TEMPERATURE BORON RANGE CONCENTRATION C/D H/U AVE. DIFFER. ( F) (ppm) MEAS. PRED. (M-P) 543.1 to 1966 -0.65 -0.69 -0.67 -1.59 0.92 546.8 NE-1082 S2C14 Startup Physics Tests Report Page 31 of 56 SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles depicted in Figure 1.3. For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using the CECOR code 4* CECOR couples the measured voltages with predetermined analytic signal-to-power conversions, pin-to-box factors, and average coupling coefficients in order to determine the power distribution for the whole core. A list of the full-core flux maps 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 Technical Specification limits is given in Table 6.2. Flux map 1 was taken at approximately 24% 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 through 3 were taken near 71% and 100% 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 through 6.3. These figures show that the average relative assembly power distribution measured/predicted percent difference was NE-1082 S2Cl4 Startup Physics Tests Report Page 32 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 2.1% or less for the three maps. The measured F-Q(Z) and F-DH(N) peaking factor values for all flux maps were within the limits of the Core Operating Limits Report (COLR) Sections 2.3 and 2.4, respectively. Flux maps 1 and 2 were used to recalibrate the power range excore detectors. A power range detector calibration based on flux map 3 verified the existing calibration was satisfactory. In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR limits. It is therefore anticipated that the core will continue to operate as designed throughout Cycle 14. NE~l082 S2Cl4 Startup Physics Tests Report Page 33 of 56 3 HAP DESCRIPTION TABLE 6.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

I I I l I 2 I I I I I BURN! I F-Q(Zl HOT F-DH(Nl HOT I CORE FCZ) POWER I I I IHAPI UP I !BANK CHANNEL FACTOR CHHL.FACTOR I HAX TILT I AXIAL! HO.I IND. I DATE HWD/IPWRI D !_________ I I I OFF I OF I I I HTU ICZllSTEPSIASSV I AXIAL I -AccS,-,,S,..,V-1,......,,F--::cDH-C,.,.H,.,.llAXJALI FCZll HAX !LOCI SET ITHIHI I I I I I I I POINT I F-QCZl I I IPOINTI I I I CZ> IBLES) -,,,.,,.,,.---,----'-'---'--'-'--1--1--1---'--' J __ I __ I _J_l __ l_l LESS THH 307. PWR I l I 6-08-961 4 I 241 151 I L 5 I 33 I Z.291 I HlO I 1.528 I 31 )l.39611.0121 SW) -6.621 '+2 I BTWN 657. ANO 757. I 2 I 6-09-961 19 I 71) 184 I HlD I 30 I 1.970 I DlD I 1.479 I 30 )l.258)1.0031 SWI -D.411 43 I GRT THAN 957. PWR I 3 I 6-13-961 155 )lODI 226 I DID I 41 I 1.857 I DlO I 1.451 I 30 )l.193)1.0021 SE) 0.501 43 I ______ 1_1 ___ 1 __ 1_1 __ , __ 1 __ 1 ___ 1 __ 1 1 __ 1 __ 1 __ ,_J __ l_l NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEHBLY LOCATIONS CE.G. HOB IS THE CENTER-OF-CORE ASSEHBLVl, AND CORE HEIGHT CIN THE "Z" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROH THE TOP OF THE CORE l. . I. F-QCZl INCLUDES A TOTAL UNCERTAINTY OF 1.08. 2. POWER TILT -DEFINED AS THE AVERAGE QUADRANT POWER TILT FROH CECOR. 3. EACH HAP WAS USED TO PERFORH A PEAKING FACTOR VERIFICATION AND A POWER RANGE EXCORE DETECTOR CALIBRATION. THE FLUX HAP 3 CALIBRATION VERIFIED THE EXISTING CALIBRATION. NE-1082 S2C14 Startup Physics Tests Report Page 34 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I Table 6.2 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS TESTS COMPARISON OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS PEAK F-Q(Z) HOT F-Q(Z) HOT F-DH(N) *HOT CHANNEL FACTOR* CHANNEL FACTOR** CHANNEL FACTOR/I (AT NODE OF MINIMUM MARGIN) MAP MEAS LIMIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN NO. 1 2 3 (%) (%) 2.291 4.640 33 2.291 4.640 33 50.6 1.528 1. 914 20.2 1.970 3.260 30 1.965 3.220 25 39.0 1.479 1.696 12.8 1.857 2.320 41 1.839 2.279 24 19.3 1,451 1.560 7.0 _.:

  • The Technical Specification's limit for the heat flux hot chann~l factor, F-Q( Z), is a function of core height and power level. The values for F-Q(Z) listed are the maximum value of F-Q(Z) in the core. The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(Z). ** The value for F-Q(Z) listed above is the value at the plane of minimum margin. The minimum margin values listed are the minimum percent.difference between the measured values of F-Q(Z) and the Technical Specification's limit at that node for each map. The measured F-Q(Z) hot channel factors include 8% total uncertainty.

fl Since all fuel assemblies in the core are SIF fuel (i.e. there are no lopar assemblies), the FdH(N) limit for all assemblies is the same. NE-1082 S2Cl4 Sfartup Physics Tests Report Page 35 of 56 .:.i. ,-'l R p Figure 6.1 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS ASSEHBLYWISE POWER DISTRIBUTION 24% POWER TESTS N " PREDICTED

  • NEASURED .PCT DIFFERENCE.

L K J N C D.227 0.277 0.227

  • D.231. 0.283. 0.232. 1.8. 2.1. 2.3. F E 0.290 0.520 0.974 0.847. 0.974. 0.520. 0.290 *
  • 0.296. 0.528. 0.990. 0.867. 0.997. 0.546. 0.298. 2.1
  • 1.6. 1.6. 2.4. 2.4. 4.9. 2.6. D C PREDICTED NEASURED .PCT DIFFERENCE.

0.340 0.996 1.186 1.306 1.225. 1.307 1.188 0.997 0.340 . 0.355. 1.020 . 1.206. 1.322. 1.238. 1.326. 1.211 . 1.011 . 0.347. 4.5. 2.4 . 1.6. 1.2. 1.1 . 1.4. 2.0. 1.4. 2.0. 0.342 0.629 1.224 1.402 1.288 1.326 1.291 1.403 l.225 0.630 0.343 . 0.351 . 0.646. 1.259. 1.423. 1.298. 1.331 . 1.300. 1.429. 1.233. 0.628. 0.339. 2.5. 2.7. 2.8. 1.5. 0.8. 0.4. 0.7. 1.9. 0.6. -0.3. -1.1 . B 0.292 1.002 1.229 1.327 1.271 1.309 1.097 1.312 1.272 1.328 1.230 1.003 0.292

  • 0.299. 1.026. 1.258. 1.372. 1.284. 1.308. 1.088. 1.300. 1.266. 1.318. 1.212. 0.988. 0.292. 2.7. 2.5. 2.3. 3.4 . 1.0. -0.l * -0.9. -0.9. -0.5. -0.8. -1.5. -1.4. 0.1
  • 0.522 1.190 1.405 1.272 1.221 1.230 1.281 1.229 1.:21 1.273 1.406 1.192 0.522 . 0.538. 1.222. 1.420. 1.250. 1.212. 1.213. 1.244. 1.189. 1.193. 1.243. 1.371. 1.172. 0.521 . 3.1
  • 2.7. 1.1. -1.7. -0.8. -1.4. -2.9. -3.3. -2.3. -2.4. -2.5. -1.7. -0.2. A 0.228 0.978 1.310 1.291. 1.311 1.232. 1.300 1.236 1.292 1.230 1.314 1.293. 1.311 0.978 0.228 . 0.237. 1.016. 1.367. 1.309. 1.298. 1.216. 1.276. 1.189. 1.201. 1.170 . 1.263. 1.238. 1.294. 0.994. 0.232. 3.9
  • 3.9. 4.4. 1.4. -1.0 * -1.3. -1.8. -3.8. -7.l. -4.8. -3.9. -4.3. -1.4. 1.6. 1.6. 0.278 0.850 1.229 1.329. 1.100 1.283. 1.238 1.180 1.237 1.283 1.100 1.328. 1.229 0.849 0.278 . 0.289 . 0.882. 1.266. 1.343. 1.071 . 1.261. 1.208. 1.136. 1.171. 1.204. 1.056. 1.296. 1.225. 0.869. 0.282. 3.7. 3.8. 3.0. 1.1. -2.6. -1.7. -2.4. -3.7. -5.4. -6.2. -3.9. -2.4. -0.3. 2.4. 1.5. 0.228 0.978 1.311 1.294. 1.314 1.231
  • 1.293 1.238 1.300 1.232 1.311 1.291
  • 1.310 0.977 0.228 . 0.236
  • 1.012. 1.354. 1.321 .*l.326. 1.219. 1.261. 1.196. 1.242. 1.150
  • 1.266. 1.275. 1.308. 0.984. 0.224. 3.6 . 3.5. 3.2. 2.1. 0.9. -1.0. -2.5. -3.3. -4.5. -6.6. ~3.4. -1.3. -0.2. 0.7. -1.7. 0.523 1.192 1.407. 1.274 1.221. 1.229 1.282 1.231 1.221 1.272 1.405. 1.190 0.522 . 0.543. 1.245. 1.449. 1.300
  • 1.213. 1.187. 1.247. 1.192. 1.175. 1.247. 1.419. 1.195. 0.528. 4.0. 4.5. 3.D. 2.0. -0.6. -3.4. -2.8. -3.2. -3.8. -2.0. 1.0. 0.4. 1.2. D.292 1.003 1.230 1.329 1.272 1.312 l.098 1.309 1.271 1.327 1.229 1.002 0.292
  • 0.303. 1.041. 1.275. 1.389. 1.285. 1.299. l.085. 1.285. 1.235. 1.302. 1.228. 1.002. 0.293. 3.8. 3.8. 3.6. 4.5. 1.0. -1.0. -1.2. -1.8. -2.9. -1.9. -0.l. 0.0. 0.4. 0.343 0.630 1.226 1.404 1.291 1.326 1.289 1.402 1.224 0.629 0.342 . 0.352. 0.648. 1.258. 1.418. 1.283. 1.323. 1.288. 1.401
  • 1.223. 0.638. 0.341. 2.7. 3.0. 2.6. 1.0. -0.6. -0.2. -0.l . -0.l. -0.l
  • 1.5. -0.4. 0.340 0.997 1.188 1.307 1.225 1.306 1.186 0.996 0.340 . 0.348. 1.017. 1.202. 1.315. 1.237. 1.329. 1.223. 1.011. 0.345. 2.4. 2.0 . 1.2. 0.6. 0.9. 1.7. 3.1 . 1.5. 1.4. STANDARD DEVIATION . =l.387 HAP NO: S2-14-0l CONTROL ROD POSITIONS:

D BANK AT 151 STEPS . 0.291 0.520 D.975 0.847 0.974 0.520 0.290 * ,0.299. 0.527. D.986. 0.862. l.009. 0.536. 0.296. 2.8. 1.4. 1.2. 1.8. 3.6. 3.1

  • 2.0. 0.227 0.277 0.227
  • 0.230. 0.283. 0.235. 1.4 . 2.0 . 3.3. SUHl'1ARY DATE: 6/08/96 F-QCZ) = 2.291 F-DHCNJ = 1.528 FCZJ = 1.396 POWER: 24.3% QPTR: NW 1.0092 SW 1.0116 NE 0.9888 SE 0.9905 BURNUP = 4.0 HWD/HTU A.O. = -6.620% NE-1082 S2C14 Startup Physics Tests Report Page AVERAGE .PCT DIFFERENCE.

= 2.1 36 of 56 I I I I I i 3 I I 6 I I 9 I I I 13 I I I I I I I I I I I I I I I I I I I I I I I I I R p Figure 6.2 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS ASSEMBLYWISE POWER DISTRIBUTION 717. POWER TESTS H H PREDICTED

  • HEASURED
  • PCT DIFFERENCE.

L K J H C 0.254 0.315 0.254 . 0.256. D.319. 0.258. 0.8. 1.1. 1.5. F E 0.307 0.543 1.018 0.930 1.018 0.543 0.307

  • 0.310. 0.547. 1.025. 0.942. 1.035. 0.568. 0.313. 0.9. 0.7. 0.7. 1.2. 1.6. 4.6. 2.0. D C PREDICTED
  • HEASURED .pCT DIFFERENCE
  • 0.357 1.001 1.174 1.302 1.226 1.302 1.175 1.002 0.357
  • 0.362. 1.012. 1.182. 1.309. 1.228. 1.313. 1.188. 1.008. 0.359. 1.4. 1.1. 0.7. 0.5. 0.2. 0.8. 1.1
  • 0.6. 0.3. 0.359 0.643 1.204 1.369 1.257 1.300 1.259 1.370 1.205 0.644 0.360 . 0.360 . 0.648. 1.222. 1.378. 1.264. 1.312. 1.266. 1.377. 1.204. 0.643. 0.358. 0.2. 0.7. 1.5; 0.6. 0.5. 0.9. 0.5. 0.5. -0.l * -0.2. -0.5. B 0.308 1.006 1.208 1.306 1.255 1.287 1.076 1.290 1.256 1.307 1.209 1.007 0.308 . 0.308. l.006. 1.206. 1.304. 1.255. 1.288. 1.074. 1.290. 1.258. 1.292. 1.207. 0.999. 0.300. o.o. 0.0. -0.l. -0.2. 0.0. 0.0. -0.2. -0.1. 0.2. -1.2. -0.2. -0.7. -2.7. 0.545 1.177 1.371 1.256 1.271 1.219 1.258 1.218 1.271 1.257 1.372 1.178-. 0.545 . 0.546. 1.177. 1.365. 1.239. 1.265. 1.214. 1.239. 1.208. 1.288. 1.248. 1.355. 1.169. 0.547. 0.2. o.o * -o.5. -1.4. -o.4. -o.3. -1.6. -o.8. 1.4 * -o.7. -1.3. -o.7. o.3. A 0.255 1.021 1.305 1.259 1.289 1.220 1.281 1.211 1.274 1.219 1.292 1.261 1.305 1.021 0.255 . 0.257. 1.028. 1.312. 1.257. 1.280. 1.216. 1.288. 1.194. 1.235. 1.200
  • 1.269. 1.221. 1.297. 1.047. 0.261
  • 0.8. 0.7. 0.6. -0.2. -0.7. -0.3. 0.5. -1.4. -3.0. -1.5. -1.8. -3.2. -0.6. 2.5. 2.3. 0.316 0.933 1.229 1.302 1.077 1.259 1.212 1.158 1.212 1.259 1.077 1.302 1.229 0.933 0.316
  • 0.319. 0.944. 1.236. 1.301. 1.066. 1.252. 1.205. l.14D. 1.180. 1.225. 1.059. 1.285. 1.226. 0.952. 0.320 . 1.0. 1.2. 0.6. -0.l. -1.l. -0.6. -0.6. -1.5. -2.6. -2.7. -1.7. -1.3. -0.2. 2.0. 1.3. 0.255 1.021 1.305 1.261 1.292 1.219 1.275 1.213 1.282 1.220 1.289 1.259 1.305 1.021 0.255 . 0.257. 1.031. 1.317. 1.266. 1.284. 1.213. 1.264. 1.194. 1.240. 1.181
  • 1.274. 1.261. 1.310. 1.028. 0.249. 1.0. 1.0. 0.9. 0.4. -0.6. -0.5. -0.9. -1.6 .. -3.3. -3.2. -1.2. 0.1 . 0.4. 0.7. -2.4. 0.545 1.178 1.373 1.257 1.271 1.218 1.259 1.219 1.271 1.256 1.371 1.177 0.545 . 0.553. 1.199. 1.389. 1.270. 1.272. 1.207. 1.251. 1.199. 1.247. 1.254. 1.406. 1.190. 0.548. 1.4. 1.8. 1.2. l.O. O.l. -0.9. -0.6. -1.6. -1.8. -0.2. 2.5. 1.1.. 0.5. 0.308 1.007 1.209 1.307 1.256 1.291 1.076 1.288 1.255 1.306 1.208 1.006 0.308 . 0.312. 1.019. 1.231. 1.353. 1.266. 1.289. 1.095. 1.280. 1.222. 1.303. 1.217. 1.011. 0.310 . 1.2. 1.2. 1.8. 3.5. 0.8. -0.2. 1.8. -0.7. -2.6. -0.3. 0.8. 0.5. 0.5. 0.360 0.644 1.205 1.370 1.259 1.300 1.258 1.369 1.204 0.643 0.360 . 0.350. 0.650. 1.221 . 1.369. 1.231. 1.298. 1.260. 1.370
  • 1.206. 0.641 . 0.352. -2.7. 1.0. 1.3. -0.1 . -2.3. -0.l. 0.1. 0.1 . 0.2. -0.4. -2.l. 0.357 1.002 1.175 1.303 1.226 1.302 1.174 1.001 0.357 . 0.360. 1.010. 1.175. 1.295. 1.229. 1.318. 1.208. 1.015. 0.360. 0.8. 0.8. 0.0. -0.6. 0.2. 1.2. 2.9. 1.4. 0.7. STANDARD DEVIATION

=0.863 HAP NO: S2-14-02 CONTROL ROD POSITIONS: D BANK AT 184 STEPS 0.307 0'.543 1.019 0.931 l.018 0.543 0.307 . 0.313. 0.544. 1.016. 0.937. 1.036. 0.555. 0.312. 2.0. 0.1. -0.2. 0.7. 1.8. 2.3. 1.7. 0.254 0.315 0.254

  • 0.249. 0.316. 0.258 * -2.l . 0.3
  • 1.5 .

SUMMARY

DATE: 6/09/96 F-Q(Z) = 1.970 F-DH(N) = 1.479 F!Z) = 1.258 POWER: 70.98% QPTR: NW 1. 0010 SW 1. 0034 NE 0.9973 SE 0.9984 BURNUP = 19 HWD/HTU A.O. = -0.406% NE-1082 S2Cl4 Startup Physics Tests Report Page AVERAGE .PCT DIFFERENCE

  • = 1.0 37 of 56 2 4 5 6. 7 8 9 10 11 12 13 14 15 R p Figure 6.3 SURRY UNIT 2 -CYCLE 14 STARTUP PHYSICS ASSEMBLYWISE POWER OISTRIBUTION 1007. POWER TESTS H PREDICTED 11EASURED 11
  • PCT DIFFERENCE.

L K J H G 0.265 0.335 0.265

  • 0.265. 0.336. 0.268. 0.1
  • 0.3
  • 1.1 . F E 0.306 0.544 1.031 0.991. 1.031
  • 0.544. 0.307 *
  • 0.307. 0.544. 1.031. 0.993. 1.045. 0.573. 0.315. 0.3. 0.1. 0.0. 0.1 . 1.3. 5.4. 2.9. D C PREDICTED HEASURED .PCT DIFFERENCE.

0.356 0.980 I.ISi 1.291 1.225 1.291 1.152 0.981 0.356 . 0.370 . 0.985 . 1.152 . 1-.289 . 1.216 . 1.298 . 1.169

  • 0.995
  • 0.369 . 4.1. 0.5. 0.1. -0.2. -0.8. 0.6. 1.5. 1.4. 3.7. 0.358 0.638 1.179 1.346 1.241 1.289 1.243 1.3.47 1.179 0.638 0.358 . 0.358. 0.640. 1.177. 1.346. 1.241 . 1.290. 1.248. 1.357. 1.183. 0.640. 0.358. 0.1. 0.4. -0.2. 0.0. 0.0. 0.1 . 0.4. 0.7. 0.4. 0.4. 0.0. B 0.308 0.984 1.182 1.295 1.257 1.289 1.076 1.292 1.258 1.296 1.183 0.985 0.308 . 0.308 . 0.984. 1.181 . 1.301 . 1.257. 1.291 . 1.079. 1.294 . 1.260. 1.285. 1.178, 0.982. 0.311. 0.0 . o.o. -0.l. 0.5. 0.0. 0.1. 0.3. 0.1. 0.1. -0.8. -0.4. -0.3. 1.1. 0.546 1.154 1.348 1.258 1.343 1.235 1.266 1.234 1.343 1.259 1.348 1.155 0.546
  • 0.546. 1.153, 1.337. 1.225. 1.334. 1.239. 1.276. 1.231. 1.349. 1.249. 1.331 . 1.149. 0.550. 0.1 . -0.l. -0.8. -2.6. -0.7. 0.3. 0.8. -0.2. 0.4. -0.8. -1.2. -0.5. 0.7. A 0.266 1.033 1.293 1.243 1.290 1.236. 1.296 1.222 1.289 1.235. 1.293 1.244. 1.294 1.033. 0.266 . . 0.266. 1.037. 1.300. 1.237. 1.274. 1.231. 1.309. 1.218. 1.261 . 1.220. 1.272. 1,206. 1.286. 1.053. 0.270. 0.3. 0.4. 0.6. -0.5. -1.2. -0.4. 1.0 . -0.3. -2.2. -1.2. -1.6. -3.l. -0.6. 2.0. 1.7. I I I I I I 3 I I 6 I 0.336 0.993 1.227 1.290. I.078 1.267. 1.223 1.170 1.222 1.267. 1.078 1.290. 1.227 0.993. 0.336. I . 0.336. 0.995. 1.229. 1.285. 1.063. 1.259. 1.219. 1.161 . 1.205. 1.247. 1.065. 1.277. 1.224. 1.004. 0.339. 0.2. 0.2. 0.1. -0.4. -1.4. -0.6. -0.4. --0.7. --1.4. -1.6. -1,2. -1.0. -0.2. I.I. 0.9. 0.266 1.033 1.294 1.244 1.293 1.235 1.290 1.223 1.296 1.236. 1.290 1.243 1.293 1.033 0.266 . 0.266. 1.034. 1.295. 1.246. 1.297. 1.229. 1.276. 1.212. 1.283. 1.210. 1.281 . 1.248. 1.302. 1.043. 0.264. 0.2 . 0.1 . 0.1 . 0.1 , 0.3 * -0.5 . -1.l * -0.9 . -1.0 . -2.1 *. -0.7
  • 0.4 . 0.7
  • 1.0 * -0.7 . 0.546 1.155 1.349 1.259 1.343 1.234 1.266 1.235 1.3.44 1.258 1.348 1.154 0.546
  • 0.546. 1.154. 1.356. 1.269. 1.336. 1.202. 1.255. 1.222. 1.322. 1.258. 1.383. 1.173. 0.557. 0.1 . -0.l. 0.5. 0.8. -0.5. -2.6. -0.8. -1.l. -1.6. 0.0. 2.6. 1.7. 2.1. 0.308 0.985 1.183 1.296 1.258 1.292 1.077 1.289 1.257 1.295 1.182 0.984 0.308 . 0.309. 0.991. 1.199. 1.332. 1.262. 1.281 . 1.093. 1.278. 1.215. 1.290. 1.198. 0.998. 0.313. 0.4. 0.6. 1.3. 2.8. 0.3. -0.9. 1.5. -0.8. -3.3. -0.4. 1.3, 1.4. 1.7. 0.358 0.638 1.179 1.347 1.243 1.289 1.241 1.3.46 1.179 0.638 0.358 . 0.359. 0.645. 1.192. 1.343. 1.214. 1.286. 1.240. 1.3.44. 1.185. 0.651. 0.359. 0.3. 1.1. 1.1 . -0.3. -2.3. -0.2. -0.l * :0.2. 0.5. 2.1. 0.4. 0.356 0.981 l.152 1.291 l.225 1.291 1.151 0.980 0.356
  • 0.359. 0.988. l.151. 1.283. l.227. 1.304. 1.180. 0.995. 0.362. 0.8 . 0.7 . -0.l * -0.6 . 0.1
  • 1.0 . 2.5
  • 1.5
  • 1.8
  • STANDARD DEVIATION

=0.891 MAP NO: S2-14-03 CONTROL ROD POSITIONS: D BANK AT 226 STEPS 0.307 0.544 1.031 0.991 1.031 0.544 0.306 . 0.313. 0.545. 1.030. 0.996. 1.047. 0.555. 0.312. 2.0

  • 0.2 . -0.l , 0.5
  • 1.5 . 2.0
  • 1.7 . 0.265 0.335 0.265 . 0.265. 0.336. 0.268. -0.2. 0.5. 1.3.

SUMMARY

DATE: 6/13/96 F-Q(Z) :: 1.857 F-DH(N) :: 1.451 FIZ) :: 1.193 BURNUP :: 155 MWD/MTU POWER: 100.08% QPTR: NW O. 9988 NE 0.9995 SW 1. 0001 SE 1. 0016 A.O. == 0.502% NE-1082 S2C14 Startup Physics Tests Report Page AVERAGE . PCT DIFFERENCE. = 0.9 38 of 56 I 10 13 I I I I I I I I I I I I I I I I I I I I I I I SECTION 7 REFERENCES

1. T. S. Psuik, "Surry Unit 2, Cycle 14 Design Report", Technical Report NE-1074, Revision O, May, 1996. 2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980. J 3. 'Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of Startup Physics Test Program -Inspector Followup Item 280, 281/88-29-01 11 , Serial No. 89-541, December 8, 1989. 4. T. W. Schleicher, "Reactor Power Distribution Analysis Using a Moveable In-Core Detector *system and the TIP/CECOR Computer Code Package", VEP-NAF-2, November, 1991. 5. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, 4.10.A, and 5.3.A.6.b.
6. "Core Operating Limits Report Surry 2 Cycle 14 Pattern AL, Revision 0 11 , April, 1996. NE-1082 S2C14 Startup Physics Tests Report Page 39 of 56 ** ! ' *-*I APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-1082 S2Cl4 Startup Physics Tests Report Page 40 of 56 I I I I I I I I I I I I I I I I I I I I 1--*} I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET . I Test

Description:

Zero Power Testing Range Determination Reference Proc No 1 Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps} RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Design) CB: 227 CC:

  • CD:
  • Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature

(°F): SL<<,. l, Test Power Level (% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Actual) CB: 227 CC: ~:l-7 CD: II~ Below Nuclear Heating Datemme Test Performed: ,Jrs-}q& ~l:l Reactivity Computer Initial -'I Flux Background Reading o.95x. lO amps IV Test Results Flux Reading At _.., . Point Of Nuclear Heating 3.S"~ IO amps -S -'i Zero Power Testing Range . , ""' ,o to 10 -1..lD amps Reference Not Applicable V FSARffech Spec Not Applicable Acceptance Criteria Reference Not Appli_cable Design Tolerance is met** . ~YES __ NO Acceptance Criteria is met** : v YES NO VI

  • At The Just Critical Position Comments ** Design Tolerance and Acceptance Criteria are met if ZPTR is below the Point of Nuclear Heating and above background.

Prepared By:~ Q). Reviewed By: / -NE-1082 S2C14 Startup Physics Tests Report Page 41 of 56 -*-------*-----~--. SURRY POWER STATION UNIT 2 CYCLE 14 STARTU~ PHYSICS T.EST RESULTS AND EVALUATION SHEET . I Test

Description:

Reactivity Computer Checkout Reference Pree No / Section: 2-NPT-RX-008

  • Sequence Step No: II Bank Positions (Steps) RCS Temperature

(°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 227 SDB: 227 CA: 227 Other (specify): (Design) CB: 227 CC:

  • CD:
  • Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature

(°F): S"~,. 3 Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: 227 Other (specify): (Actual) CB: 227 CC: ;;>:>'i CD: II t Below Nuclear Heating Datemme Test Performed: CJ>/5 /9& ~5"4 Measured Parameter Pc= Measured Reactivity using p-computer (Description) Pt= Predicted Reactivity IV Test Results Measured Value Pc= -..i.H, +41 ' . Pt= --'+1*, , 4-48 %0= -3. (., .,.,~ 1 -.:::l * \ '7 a Design Value %0= {(pc -pJ/pJ X 100% S 4.0 o/o Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/Tech Spec Not Applicable . Acceptance Criteria Reference Not Applicable Design Tolerance is met . ~YES __ -NO Acceptance Criteria is met : .,/ YES NO VI

  • At The Just Critical Position Comments The allowable range will be set based on the above results, as well as results from the benchmark test. Allowable Range = -'-IG,. , -\-'V} Prepared*By: 7>. Reviewed By:7/. -~ NE-1082 S2C14 Startup Physics Tests Report Page 42 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron.Concentration -ARO Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: . 227 Other (specify): (Design) CB: 227 CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): 54Co.9 Test Power Level (% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Actual) CB: 227 CC: 227 CD: 227 Below Nuclear Heating Datemme Test Performed: ta/s /c,<o JJ:so Measured Parameter (C 8)M ARO; Critical Boron Concentration -ARO (Description) .IV Test Results Measured Value (Ce)MARo= 1'Hot ppm .. (Design Conditions) Design Value C 8= 1986 +/- 50 ppm (Design Conditions) Reference Technical Report NE-1074, Rev. 0 V FSAR/Tech Spec lcxC 8 x C 8°1 1000 pcm Acceptance Criteria Reference Technical Specification 4.10.A Design Tolerance is met . _f_ YES NO . --Acceptance Criteria is met : ./ YES NO VI Comments aC 8 = -6.96 pcm/ppm Ce°= l(Ca)MARo-C 8 1; C 8 is design value Prepared By:~~~ Reviewed By: {J)//, .{;/ /Lr-.n

  • V I
  • T
  • NE-1082 S2C14 Startup Physics Tests Report Page 43 of 56 SURRY POWER STATION UNIT 2 CYCLE 14 STARTU~ PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Isothermal Temperature Coefficient -ARO* Reference Proc No I Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature {°F): 547 Test Power Level {o/o F.P.): 0 Conditions SDA: 227 SDB: 227 CA: 227 Other (specify): (Design) CB: 227 CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps} RCS Temperature (°F}: Slt(o.~ Test Power Level(% F.P.): 0 Conditions SDA: 227 SDB: 227 CA: 227 Other (specify): (Actual) CB: 227 CC: 227 CD: .?..\9 Below Nuclear Heating Datemme Test Performed: {g /5 /°l(p J3c; SI Measured Parameter (ex ISO) , T ARO* Isothermal Temperature (Description) Coefficient -ARO IV Test Measured Value (ex ISO) _ -o.<o, pcmt°F .T ARO -Results (Ce= lC)G,(p ppm) . Design Value (Actual Conditions} (exTiso)ARo = -1.S'l :1:3.0 pcmfF (Ce= IC\ (o(p ppm) Design Value (Design Conditions} (ex ISO) _ T ARO--1.40:1:3.0 pcmfF (Ce= 1986 ppm) Reference Technical Report NE-1074,Rev. 0 V FSAR/COLR ex/j 0 s 3.83* pcmfF Acceptance ex/0 P = -1.67 pcmfF Criteria Reference COLR 2.1.1, Technical Report NE-1074, Rev. O Design Tolerance is met ./ YES __ NO Acceptance Criteria is met : ./ YES NO VI Comments *Uncertainty on ixT MOD= 0.5 pcmPF (

Reference:

memorandum from C.T. Snow to E.J. Lozito dated June 27, 1980.) Prepar:ed By: ~Q.=)t\_&..e~ Reviewed By: Jfi. ~/,I --* I I I --NE-1082 S2Cl4 Startup Physics Tests Report Page 44 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration -B Bank In Reference Pree No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 227 SDB: 227 CA: 227 Other (specify): (Design) CB: 0 CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): 54, .. 0 Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA:. 227 Other (specify): (Actual) CB: 0 CC: 227 CD: 227 Below Nuclear Heating Datemme Test Performed: <.o/ li, {9(o 04:,4<.; Measured Parameter (Ce)Me; Critical Boron Concentration, (Description) B Bank In IV Test Results Measured Value (Ce)Me= \tlo3 ppm . (Design Conditions) -Design Value Ce= 1782+aCe Pnw +/- (10 + 142.5/laCel> ppm (Design Conditions) Ce= l1Co3 +/- 30 ppm Reference Technical Report NE-1074, Rev. 0 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met ./ YES __ NO Acceptance Criteria is met : J YES NO VI Comments aC 8 = -6.99 pcm/ppm a Ce Prev = M . (Ca) ARO -1986 ppm Prepared By: ~0 Reviewed By: c}j(((-rff~ 7 NE-1082 S2C14 Startup Physics Tests Report Page 45 of 56 ~-------------- SURRY POWER STATION UNIT 2 CYCLE 14

  • STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank B Worth Measurement, Rod Swap Ref. Bank Reference Pree No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions {Steps) RCS Temperature {°F): 547 Test Power Level {% F.P.): 0 Conditions SDA: 227 SOB: 227 CA:. 227 Other {specify): {Design) CB: moving .CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions {Steps) RCS Temperature (°F): . 'S'-\1 .. ;).. Test Power Level (% F.P.): 0 Conditions SDA: 227 SOB: 227 CA:. 227 Other (specify): (Actual) CB: moving CC: 227 CD: 227 Below Nuclear Heating Datemme Test Performed: lD Ito lct<P 01 ~O°t ,. Measured Parameter I REF. B I Integral Worth Of Control Bank B, {Description) All Other Rods Out IV Test Measured Value I REF_ B -\4:,S. l pcm Results Design Value 1 8 REF= 1425 :1: 143 pcm (Design Conditions) Reference Technical Report NE-1074, Rev. 0 If Design Tolerance is exceeded, SNSOC shall V FSAR/Tech Spec evaluate impact of test result on safety analysis. Acceptance SNSOC may specify that additional testing Criteria be performed. Reference VEP-FRD-36A Design Tolerance is met . _:L_ YES __ NO Acceptance Criteria is met : ___£ YES __ NO VI Comments Prepared By: A4L:~~ Reviewed By: ~.

  • I NE-1082 S2Cl4 Startup Physics Tests Report Page *46 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Boron Worth Coefficient Measurement Reference Proc No I Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): 54~~ Test Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Actual) CB: moving CC: 227 CD: 227 Below Nuclear Heating Datemme Test Performed: ~Is'°'~ ;;J:l". so ., Measured Parameter aC 8; Boron Worth Coefficient (Description) IV Test Results Measured Value aC 8= -,.03 pcm/ppm . <>:-.,. Design Value aC 8= -6.99 :1: 0.70 pcm/ppm (Design Conditions) Reference Technical Report NE-1074, Rev. 0 V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met . * ./ YES __ NO . --:T YES Acceptance Criteria is met : NO VI Comments -** I Prepared By:~~ "--A--~ Reviewed By: Z!Hct!JL I ( l 1v* V. NE-1082 S2G14 Startup Physics Tests Report Page 47 of 56 .. ,* .. SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank D Worth Measurement, Rod Swap Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps} RCS Temperature (°F}: 547 Test

  • Power Level(% F.P.}: 0 Conditions SDA: 227 SOB: 227 CA:. 227 Other (specify): (Design) CB: moving CC: 227 CD: moving Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (uF}: 54'*, Test Power Level (% F.P.}: 0 Conditions SDA: 227 SOB: 227 CA:. 227 Other (specify}: (Actual) CB: moving CC: 227 CD: moving Below Nuclear Heating Datemme Test Performed:

';,t,, , oss;{ Measured Parameter 1 0 Rs; Integral Worth of Control Bank D, (Description) Rod Swap IV Measured Valu~ I RS_ D -I f5'ir, 3 (Adjusted Measured Critical Test Reference Bank Position = ,, 'Z-steps) Results Design Value (Actual Conditions) lls= ff "73_ 1 (Adjusted Measured Critical Reference Bank Position = "7-steps) Design Value (Design Conditions) 1 0 Rs= 1149 +/- 172 pcm (Critical Reference Bank Position = 181 steps) Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis. Acceptance SNSOC may specify that additional testing Criteria be performed. Reference VEP-FRD-36A Design Tolerance is met . _,,._YES __ NO . Acceptance Criteria is met : .,, YES NO VI Comments Prepared By: .4~-{/~ Reviewed By: JJ. P NE-1082 S2C14 Startup Physics Tests Report Page 48 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank C Worth Measurement, Rod Swap Reference Pree No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 227 SDB: 227 CA:. 227 Other (specify): (Design) CB: moving CC: moving CD: 227 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): S'4',-4l Test Power Level (% F.P .): 0 Conditions SDA: 227 SDB: 227 CA:. 227 Other (specify): (Actual) CB: moving CC: moving CD: 227 Below Nuclear Heating Datemme Test Performed: ';, /'iG. J O"'Z-3 ~,:=-Measured Parameter le RS; Integral Worth of Control Bank C, {Description) Rod Swap IV Measured Value I RS_ C -7s<i. s {Adjusted Measured Critical .Test Reference Bank Position= 10~ steps) Results Design Value {Actual Conditions) I RS_ ,, 7. "I (Adjusted Measured Critical C -Reference Bank Position = 1"' steps) Design Value (Design Conditions) t/5= 775 +/- 116 pcm (Critical Reference Bank Position= 122 steps) Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis. Acceptance SNSOC may specify that additional testing Criteria be performed. Reference VEP-FRD-36A Design Tolerance is met . v YES __ NO Acceptance Criteria is met : VYES NO VI Comments Reviewed By: bJ, p~ NE-1082 S2C14 Startup Physics Tests Report Page 49 of 56 ... - SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank A Worth Measurement, Rod Swap Reference Pree No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions {Steps) RCS Temperature (°F): 547 -Test Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 Ck. moving Other (specify): {Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Bank Positions {Steps) RCS Temperat_ure (°F): S'f7. / Test Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 Ck. moving Other {specify): {Actual) CB: moving CC: 227 CD: 227 Below. Nuclear Heating Datemme Test Performed: '/r..h, I . o7Z.$ Measured Parameter l/5; Integral Worth of Control Bank A, (Description) Rod Swap . IV Measured Value I RS_ A -z Sc:>. z {Adjusted Measured Critical Test Reference Bank Position = , o steps) Results Design Value {Actual Conditions) 1/S= ?-~1.'i5 . (Adjusted Measured Critical Reference Bank Position = Co steps) Design Value {Design Conditions) 1/s= 268 +/- 100 pcm (Critical Refe*rence Bank Position= 72 steps) Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A FSARffech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis. Acceptance SNSOC may specify that additional testing Criteria be performed. Reference VEP-FRD-36A Design Tolerance is met . ~YES __ NO Acceptance Criteria is met : VYES NO VI *comments Rev*1ewed By*. ~. ?. !~ Prepared By: ,4:d: v144 c_ NE-1082 S2Cl4 Startup Physics Tests Report Page 50 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B Worth Measurement, Rod Swap Reference Pree No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 227 SOB: moving Ck 227 other (specify): (Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating 111 Bank Positions (Steps) RCS Temperature (°F): S'4'--'l Test Power Level (% F .P .): 0 Conditions SDA: 227 SOB: moving CA: 227 other (specify): (Actual) CB: moving CC: 227 CD: 227 Below Nuclear Heating Datemme Test Performed: '/r,.jc,r;,) OHO Measured Parameter lseRs; Integral Worth of Shutdown Bank 8, (Description) Rod Swap IV Measured Value lse RS= // 5".2.5' (Adjusted Measured Critical Test IC.I l'"° Reference Bank Position = eps) Results Design Value (Actual Conditions) Isa RS= 11,<}. l (Adjusted Measured Critical ,,, i.M*~ Reference Bank Position= J.',C"""'steps) Design Value (Design Conditions} lse RS= 1190 +/- 179 pcm (Critical Reference Bank Position= 182 steps) Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis. Acceptance SNSOC may specify that additional testing Criteria be performed. Reference VEP-FRD-36A Design Tolerance is met ~YES __ NO Acceptance Criteria is met . .... YES NO VI Comments Prepared By: ~-t/~ Reviewed By: ...2. NE-1082 S2C14 Startup Physics Tests Report Page 51 of 56 . '

  • I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank A Worth Measurement, Rod Swap Reference Proc No / Section: 2-NPT-RX-008-Sequence Step No: II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: moving SOB: 227 CA:. 227 Other (specify): (Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Ba_nk Positions (Steps) RCS Temperature (°F): 54'.'j Test Power Level(% F.P.): O Conditions SDA:. moving SOB: 227 CA:. 227 Other (specify): -(Actual) CB: moving CC: 227 CD: 227 Below Nuclear Heating Daternme Test Performed: r;, /ti:., /t:it>' oi<<o Measured Parameter ISA Rs; Integral Worth of Shutdown Bank A, (Description) Rod Swap IV Measured Value I RS_ SA -/o9 .;.i (Adjusted Measured Critical Test Reference Bank Position = IS'/ steps) Results Design Value. (Actual Conditions) ISA Rs= II 3 c,. er (Adjusted Measured Critical Reference Bank Position = /SI steps) Design Value (Design Conditions) ISA Rs= 1034 +/- 155 pcm (Critical Reference Bank Position= 172 steps) Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A FSAR!Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis. Acceptance SNSOC may specify that additional testing Criteria be performed. Reference VEP-FRD-36A Design Tolerance is met . _.,_ YES __ NO . Acceptance Criteria is met : .,, YES NO VI Comments t/<<14 *-;l-** 2.I,,) Prepared By: Reviewed Hy: *---"/ <./ NE-1082 S2Cl4 Startup Physics Tests Report Page 52 of 56 I I I I I I I I I I I I I I I I I I I I I I I I I I I I 'I I I I I I I I *I I

  • SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth, Rod Swap Reference Pree No I Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) Res* Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: moving SDB: moving CA:. moving Other (specify): (Design) CB: moving CC: moving CD: moving Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): S47.-Z.. Test Power Level(% F.P;): 0 Conditions SDA: moving SDB: moving CA:. moving Other (specify): (Actual) CB: moving CC: moving CD: moving Below Nuclear Heating Datemme Test Performed: C /r, /c,fe. ' 01 ot:t Measured Parameter lro1a1: Integral Worth of AU Banks, (Description) Rod Swap IV Measured Value Ir~=-S*'f. s pcm . ' . , I Test ! Results Design Value (Actual Conditions) lro1a1= sci 3 s. 7.. pcm . 'i Design Value \ ~-r.;o. (Design Conditions) l;-0131= 5919 +/- 592 pcm Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis. Acceptance Additional testing must be performed. Criteria Reference VEP-FRD-3SA Design Tolerance is met _LYES __ NO Acceptance Criteria is met : .,,, YES NO VI Comments -* Prepared By: 4~ t.1. (;( Reviewed By: -~~2.( NE-1082 S2C14 Startup Physics Tests Report Page 53 of 56 SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST.RESULTS AND EVALUATION SHEET . I Test

Description:

MID Flux Map -At Power Reference Proc No / Section: 2-NPT-RX-008 ,002 Sequence Step No: II Bank Positions {Steps) RCS Temperature {"'F): T REF= 1 Test Power Level(% F.P.): s 30 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): {Design) CB: 227 CC:

  • CD:
  • Must have 38 thimbles**

Ill BankPositions (Steps) RCS Temperature (°F}: Trc.f Test Power Level(% F.P.): ;24-. "3 % Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Actual) .CB: 227 CC: :2.~'1 CD: 15' i Datemme Test Performed: to/~j9G, ,oo'-1-3 4,.:2. Thi r')'} 6 \ es Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FAH(N) Factor F 0 (Z) Power lilt Test Measured -"1, 1 "h:..-P '!: 0. G\O I. '5~<g ;J. ;;291 4.'I "'"' p,40.qo l,Olll, Results Value Design Value :t:10% for P 1 :i:0.9 (Design :t:15% for P 1<0.9 N/A NIA 1.0203 Conditions) (P 1 = assy power) Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 V FSAR/COLR None F"1H(N)s1.56(1+0.3(1-P)) Fo(Z)s4.64"K(Z) None Acceptance Criteria Reference None COLR2.4 COLR2.3 None Design Tolerance is met . _:f_ YES __ NO Acceptance Criteria is met : ....:L_ YES NO . VI

  • As required Comments -Must have at least 16 thimbles for quarter core maps for multi-point calibrations P.repared By: 'D. ~* Reviewed By~ C2!/,4i' NE-1082 S2C14 Startup Physics Tests Report Page 54 of 56 I I I I I I I I I I 1* I I I I I I I I I I I I I I I I I I I I I I I I I I I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP.PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/0 Flux Map -At Power Reference Proc No I Section: 2-NPT-RX-008 ,002

  • Sequence Step No: II Bank Positions (Steps) RCS Temperature

("'F): T REF+/- 1 Test Power Level (% F.P.):65 s P s 75 Conditions SDA: 22.7 SDB: 227 CA:. 227 Other (specify): (Design) CB: 22.7 CC: 227 CD:

  • Must have 38 thimbles-Ill Bank Positions (Steps) RCS Temperature

(°F): Test Power Level (% F.P.): 7 0* j{ J Conditions SDA: 22.7 SDB: 227 CA:. 227 Other (specify):

  • * (Actual) CB: 22.7 CC: 227 CD: J/'/ '/J -rt,-_Jft,}

Date/Time Test Performed: ~/?/?I / () "'(;, Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%D1FF Channel Factor Channel Quadrant IV (Description) (M-P)/P F.:\H(N) Factor F 0 (Z) Power Tift Test Measured ,_,., f,1" p ~"* /, '{7? /,770 /. t'D:J y'° Results Value 6/. I" 1,,,, P tC ,. ,~ Design Value :t:10% for P1 ~0.9 (Design :1:15% for P 1<0.9 NIA NIA :s: 1.0202 Conditions) cP1 = assy power) Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 V FSAR/COLR None FAH(N):s:1.56(1+o.3(1-P)) Fa(Z):s:2.32/P"K(Z) None Acceptance Criteria Reference None COLR 2.4 COLR2.3 None Design Tolerance is met . _JL YES __ NO . Acceptance Criteria is met : r/ YES NO VI

  • As required Comments ** Must have at least 16 thimbles for quarter core maps for multi-point calibrations Prepared By: cftf:*
  • Reviewed By: ~-#(~ NE-1082 S2C14 Startup Physics Tests Report Page 55 of 56 SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

M/D Flux Map -At Power Reference Pree No /. Section: 2-NPT-RX-008 ,002 Sequence Step No: II Bank Positions (Steps) RCS Temperature (uF): T REF+/- 1 Test Power Level(% F.P.):95 .s: P .s; 100 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Design) CB: 227 CC: 227 CD:

  • Must have 38 thimbles**

111 Bank Positions (Steps) RCS Temperature (°F):

  • s,3 Test "2.2(.o Power Level(% F.P.): \CO. rj'c) S 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): (Actual) CB: 227 CC: 227 CD: Date/Time Tes Performed:

1.r:, ,3)c,<o toeP Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FAH(N) Factor Fa(Z) Power Tilt Test Measured .... 3. '3 p ?'0.1 \.'c,S1 \,CC'-t Results Value "5.4io f LD.&l. (.Lf'5 I , . ea; <..a tJ.,,:, b.Lj fo Design Value :10% for Pi :.!:0.9 . ..., (Design :15% for P 1<0.9 NIA N/A s 1.0202 Conditions) (Pi = assy power) Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 V FSAR/COLR None F !J.H(N)s1 .56(1+0.3(1-P)) Fa(Z)s2.32/P.K(Z) None Acceptance Criteria Reference None COLR2.4 COLR2.3 None Design Tolerance is met. _L.YES __ NO ' Acceptance Criteria is met : __LYES NO VI

  • As required Comments ** Must have at least 16 thimbles for quarter core maps for multi-point calibrations r 11 -Prepared By: '. tt!la,~1-r11 Reviewed By: 1<<<<4 M -C/ --NE-1082 S2C14 Startup Physics Tests Report Page 56 of 56 I I 1* Ii I I I I I I I I I I I I I I I

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