ML20082P660
| ML20082P660 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/05/1991 |
| From: | Banning P, Laroe C, Psuik T VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153C722 | List: |
| References | |
| NE-852, NE-852-R, NE-852-R00, NUDOCS 9109100434 | |
| Download: ML20082P660 (72) | |
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TECl!NICAL REPORT NE 852 Rev. O I I SURRY UNIT 2, CYCLE 11 STARTUP PilYSICS TCJT REPORT I I NUCLEAR ANALYSIS AND FUEL I NUCLEAR ENGINEERING SERVICES VIRGINIA POWEk AUGUST 1991 y I ) I PREPARED BY: O T. S. Psulk 9'/dN9/ Date REVIEWED BY: 7 / C. d LaRoe Date REVIEWED BY: m fe 1/$w%_ 1l P. D. Banning D Rtvitvto Bv Cn L E d re gt.
, ee, _
APPROVED BY:. IT l D. Duadesz ,f D6te'f/ QA Category: Nuclear Safety Related x., _ e.. g 2c 11.. St. , t, I e
CLASSIFICATION / DISCLAIMER I-The data, technaques, information, and conclusions 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 ,I 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 FITNLSS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BS DEEMED TO ARISE FI!0M COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusiens in it. By making this report available, the Company does not authorize its uss by others, and any such use is expressly forbidden e.: cept 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 even shall the Company be liable, under any legal theory whatsoever (whetner contract, tort, warranty, or strict or absolute l i a bility '. for any property damage, mental or physical injury or death, loss of use of property, or other damage res"Iting from or arising out of the use, authorized or unauthorized, of this report or the data, I techniques, inf or. nation, or conc lin .ons in it. I I I I x8-ee2 82cu 8-~ x- e- 1 - " u
) - f L I ms em 1x-miemm em,x i I I I I l I l l l r l xt.e,z zc11 s m m , 1. m s., _ e.s. - 21 l l -- - -
. TABLE OF CONTENTS s PAGE Classification / Disclaimer............ .. . ....... ..... 1 Table of Contents............................. ....... 3 List of Tables......... ..... . . .... ...... ......... 4 List of Figures. .......... .......... ... ........... 5 Preface. . .................... ....................... 7 Section 1 Introduction and Summary................... 9 I Section 2 Control Rod Drop Tims Measurements..... .. 21 Sectjon 3 Control Rod Bank Worth Measurements. ...... 27 Section 4 Boron Endpoint and Worth Measurements. . . .. 33 Section 5 Temperature Coefficient Measurement........ 37 Section 6 Power Distribution M.asurements... .... .. 41 Sectit.i 7 Startup Physics Testing Results With F6 In The Core. , .......,. ... ... 49 Section 8 References... ,. .. .. . .... ... ...... 53 APPENDIX Startup Physics Tests Results and Evaluation Sheets. .. ......... . . 55 I ... I I I NE-852 S2C11 Startup Test Report Page 3 of 71
l LIST OF TABLES TABLE TITLE PAGE 1.1 Chronclogy of Tests................ .. ........... ... 14 f 2.1 llot Rui Drop Time Summa ry . . . . . . . . . . . . . . . . . ....... ... 23 3.1 Control Rod Bank Worth Summary........................ 30 4.1 Boron Endpoints Summary..................... ...... .. 35 5.1 Isothermal Temperature Coef ficient Summary. . ......... 39 6.1 Incore Flux Map Summary............. . ..... ....... . 43 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specification Limits. ... ....... 44 7.1 S2C11 Startup Physics Testing Results Comparison Measured Vs. Predicted With F6 In ... . . ... .. ... 51 NE-852 S2C11 Startup Test Report Page 4 of 71
LIST OF FIGURES L FIGURE TITLE PAGE 1.1 Core Loading Map. . ........... ...... ...... .. ... 15 1.2 Beginning of Cycle F ml Assembly Burnups. . ....... ..... 16 1.3 Incore Movable Detector Locations........... . ... ... .. 17 1.4 Burnable Poison and Source Assembly Locations. . . . . . . 18 1.5 Control Rod Locations................... . .. .. . ...... 19 2.1 Typical Rod Drop Trace..... . .... ... . .. ... . ... 24 2.2 Rod Drop Time - Hot Full Flow Conditions. ....... . . . 25 3.1 Bank B Integral Rod n' orth - HZP. . . .. .... .... . ... 31 4 3.2 Bank B Differential Rod Worth - HZP. ..... ............. 32 4.1 Boron Worth Coefficient................. ..... ... ..... 36 6.1 Assemblywise Power Distribution - 32% Power.. ... ....... 45 6.2 Assemblywise Power Distribution - 29*. Power....,. . ... 46 Assemblywise Po.er Distribution - 68* Power. 47 I 6.3 . ... . . o.4 Assemblywl Power Distributien - 100% Power. . . .. 48 i NE-852 S2C11 Startup Test Report Page 5 of 71
i i i THIS PAGE INTENTIONALLY BLANK NE-852 S2C11 Startup Test Report Page 6 of 71
b PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 11 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, together with the detailed startup procedures, are on r file at the 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, e comparison of the test results with design i predictions, and an evaluation of the results. The Surry 2, Cycle 11 Startup Physics Tests Results and Evaluation l Sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) tast identification, 2) test conditions (design), 3) test conditions (accual), 4) test 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 of the measured parameters were completed p.2cr to the startup physics testing. The entries for the design values I were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group! During the tests, the data sheecs were used as guidelines both to verify that the proper test conc nions were met and to iacilitate the preliminary comparison between NE-852 52C11 Startup Test Report Page 7 of 71 l-
l l measured and predicted test results, thus enabling a quick identification of possible probleins occuring during the tests. l 1 NE-852 S2C11 Startup Test Report Page 8 of 71
s SECTION 1 L INTRODUCTION AND
SUMMARY
On March 30, 1991 Unit No. 2 of the Surry Power Station shutdown for its tenth refueling. During this shutdown, 81 of the 157 fuel assemblies in the core were replaced with 64 fresh fuel, one once-burned, 8 l twice-burned, and 8 thrice burned assemblies. The eleventh t.ycle core l consists of 11 sub-batches of fuel: two fresh batches (batches 13A and 13B); four once burned batches, threr from Cycle 10 (batches 12A, 128, and 12C) and one from Surry 1 Cycle 6 (batch SI/8B); six twice-burned batches, two from Surry 2 Cycles 9 and 10 (batches 11A and 11B), two from Surry 1 Cycle 6 and Surry 2 Cycle 10 (batches S1/8A and S1/8B), one from Surry 2 Cycles 7 and 8 (batch 9A), and one f rom Surry 2 Cycles 6 and 7 I (batch 8); and one thrice-burned batch from Surry 2 Cycles 7, 8, and 9 (batch 9A) . Note that batch 9A is listed as both a twice and thrice burned _ batch. Eight batch 9A assemblies were from Surry 2 Cycles 7, 8, and 9, and four came from Surry 2 Cycles 7 and 8. Also note that batch SI/8B is listed as both a once and twice burned batch. One assembly came from e Surry 1 Cycle 6, and four came from Surry 1 Cycle 6 and Surry 2 Cycle 10. The core ioading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The incore movable det ector locations are identified in Figure 1.3. Figure 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 11, and Figure 1.5 identifies the location and number of control rods in the Cycle 11 core. x,. 8 s 2 S2cu Sta,t , 1.s o .p m eage e of 71 l l _
On June 5, 1991 at *730, che eleventh cycle core achieved initial criticality. Following criticality, startup physics tests were performed i as outlined in Table 1.1. During the ascension to full power, the first flux map taken (at about 30* power) indicated that control rod F6 (D-bank) was possibly inserted in the core. Soon after it was confirmed that F6 was inserted, the plant was shutdown for repairs, to determine the extent of the damage, and to investigate the cause. Upon pulling the pressure vessel head and doing various tests and inspections, it is believed that the gripper on F6 had come undone during the hot rod drop test 2 It was determined that no significant damage had been done, and the unit could resume operation. I The design values on the Startup Physics Test Results and Evaluation Sheets in the Appendix are based on an ARO core. Since control rod F6 was in the core during startup physics testing, the design predictions for the startup were recalculated in the presence of F6 to be compared to tne measured results' . The F6-in predictions were done assuming no knowledge of the off-nominal conditions other than the fact that control rod F6 was inserted. This report includes a comparison of the measured values to the original predicted values, as well as a comparison of the measured values to the recalculated predicted values (in the presence of E6). A summary of the results of these test follows:
- 1. Since the unit was shut down and the pressure vessel head removed, the hot rod drop test was done a second time after the repair of control rod F6. The measured drop time et each control rod, for NE-852 S2C11 Startup Test Report Page 10 of 71
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both hot rod drop tests, was within the 2.4 second limit of L Technics 1 Specification 3.12,C.1. J
- 2. The reference control red bank was measured with the dilution method, and the results were within 2.9% of the design predictions. Individual control rod bank worths were measured using the rod swar technique" and the results were within 11*. of the design predictions. The sum of the individual measured control rod bank worths was within 4.4% of the design prediction.
These results are within the design tolerance of 115% for individual bank worths ( 10% for the rod swap reference bank worth) and the design tole.rance of 10 *. for the sum of the individual control rod bank worths. The measured bank worths, when compared to the predictions in the presence of F6, were within 6.7*. of the predicted values (0.5% for the reference bank) with the sum of the bank worths coming within 2.5*. of the design prediction. These results were also within the design tolerances I stated above. I 3. Measured critical boron concentrations for the two control bank configurations were within 4 ppm of the design predictions. These results were within the design tolerances and also met the Technical Specification 4.10 criterion that the overall core reactivit; balance shall be within 1 *. Ak/k of the design prediction. The measured critical borons, when compared to the predictions in the presence of F6, were within 14 ppm of the predicted values. These boron endpoints also met the design tolerances and Technical Specification 4.10. NE-852 S2C11 Startup Test Report Page 11 of 71
- 4. The boron worth coef ficient measurement was within 2.8% of the design prediction, which is within the design tolerance of 110%.
r The boron worth coef ficient measurement, when compared to the L prediction in the preser.co of F6, is within 2.2%. This is also within the design tolerance of 110%. I
- 5. The measured isothermal temperature coefficient (ITC) for the all-rods out configuration was within 0.51 pcm/'F ot the design prediction. This result is within the design tolerance of 13 pcm/*F. The measured ITC of -0.53 pcm/'F meets the Technical Specification 3.1.E.1 criterion that the moderator temperaturn coefficient (MTC) be less than or equal to +3.0 pcm/'F. The measured ITC is withir' O.70 pcm/'F of the design prediction (in the presence of F6), which is also within the design tolerance of +3 pcm/'F. When the Doppler temperature coef ficient and a 1.0 pcm/'F uncertainty are accounted for in the MTC limit, the MTC requirement is satisfied as long as the ITC is less than or equal to +0.82 pcm/'F.
- 6. The measured core power distribution for the first flux map taken i
at 32% power was within 8.0% of the design prediction. The power distribution did not meet the design tolerance for quadrar.t power tilt, and indicated that control rod F6 was possibly fully inserted in the core. Core power distributions for at power conditions, af ter the withdrawal of control rod F6, were within the established design tolerances. Generally, the measured core
,. power distribution was within 1.8% of the design predictions.
The heat flux bot channel factors, F-Q(T), and enthalpy rise hot NE-852 S2C11 Startup Test Report Page 12 of 71
channel factors, F-Dil(M), were within the limits of Technical s Specifications Section 3.12,B.1, respectively, r L 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. I I I I I I I I I I NE-852 S2C11 Startup Test Report Page 13 of 71
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Table 1.1 SURRY 2 - CYCLE 11 STARTUP PllYSICS TESTS CilRONOLOGY OF TESTS Reference Test Date Time Power Procedure , Hot Rod Drop - flot Full Flow 6/1/91 1015 ilSD 2-NPT-RX-007 Zero Power Testing Range 6/5/91 1953 HZP 2-PT-28.11 Reactivity Computer Checkout 6/5/91 2030 HZP 2-PT-28.11 Boron Endpoint - ARO 6/6/91 0152 Il2P 2-PT-28.11 Temperature Coefficient - ARO 6/6/91 0200 HZP 2-PT-28.11 Bank B Worth 6/6/91 0242 HZP 2-PT-28.11 Boron Endpoint - B in 6/6/91 0242 HZP 2-PT-28.11 Bank D Worth - Rod Swap 6/6/91 0730 !!ZP 2-PT-28.11 Bank C Worth - Rod Swap 6/6/91 1213 ilZP 2-PT-28.11 Bank A Worth - Rod Swap 6/6/91 1318 ll2P 2-PT-28.11 Bank SB Worth - Rod Swap 6/6/91 1355 HZP 2-PT-28.11 Bank SA Worth - Rod Swap 6/6/91 1429 ilZP 2-PT-20.11 Flux Map - 32% Power 6/8/91 0712 37% 2-NPT-RX-002 Hot Rod Drop - Hot Full Flow 7/3/91 0230 llSD 2-NPT-RX-007 Flux Map - 29% Power 7/4/91 1130 29% 2-NPT-RX-002 Flux Map - 68* Power 7/5/91 0430 68% 2-NPT-RX-002 Flux Map - HFP 7/23/91 1200 100% 2-NPT-RX-002 6. NE-852 S2C11 Startup rest Report Page 14 of 71
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- Figure 1.4 SURRY UNIT 2 - CYCLE 11 g BURNABLE POISON AND SOURCE ASSEMBLY LOCATI0dS l-4 R P m n L R J H G F l D C 6 & 1 i i ~l I i l l 1 l _ __ I I i I i i i SP i l se I i l I ( llPth% j llP967 ) l l 2 l I. .I l_ _l l _ . l .. l l SP l LIP l l 109 l l 47P l SP 1 l l 1sPart ispe94 I ISPle6 I ltpe9% 18P019 i I a i I I l i I I l 20p i inPtt6 1 i l l 16P~l i Impea6 6 l~ i 46p I ISPeap i l I l 28P l itPitt i I I t l 1 I 4 f ._w l l _.__ ,1 i __ _ t i I I I I I I aP t top i l toe i i isP l l rop l I top I aP i i i 554 ISPett Isplie i ISP!Ie 1 itetet i ItPltt i 16P179 IEPese 1 i s I 1 l I i 11P 1 ISPtst i I l_1 1 20P i l_ _l l 20P i l __ I l ISP l i l FOP 4
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P Figuro 1.5 7 H SURRY UNIT 2 - CYCLE 11 CONTROL R0D LOCATIONS
- R P N N L K J H C F f D C B A
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- SECTION 2 9 CONTROL RCD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tavg above 54715'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.I. Since the pressure vessel head was removed after the initial rod drop tents, the hot rod drop tests had to be performed a second time. A brief description of the test is given below, and the rod drop times from both tests are given in Figure 2.2. The rod drop times were measured by withdrawing a rod bank to its fully withdrawn position, and removing the movable gripper coil fuse and stationary gripper coil fuse for the pirticular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The stationary gripper coil voltage and the Individual Rod Position Indication (IRPI) primary coil voltage signala were recorded to determine the rod drop time. This procedure was repeated for each control rod. I As shown on the sample rod drop truce in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary gripper coil fuse is removed. As the rod drops, a voltage is induced in the IRPI primary coll. 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. This voltage reaches a minimum when the rod NE-852 S2C11 Startup Test Report Page 21 of 71
4 1 I- reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing. i The measured drop times for each control rod, for each test, 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 i
i 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. l j floth rod drop tests satisfied this limit. !I !I lI il 'I i I I g 2.e,z zc11 etm,1.,s r x,_ eage = of u
~
j Table 2.1 SURRY UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS Il0T ROD DROP TIME
SUMMARY
)
ROD DROP TIME TO DASilPOT ENTRY (FIRST ROD DROP TEST) SLOWEST ROD FASTEST ROD AVERAGE TIME K-06 1.34 sec. P-06 1.23 sec. 1.29 sec. I ROD DROP TIME TO DASilPOT ENTRY lp (SECOND ROD DROP TEST) SLOWEST ROD FASTEST ROD AVERAGE TIME F-06 1.38 sec. P-06sk 1.24 sec. 1.28 sec.
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I I I s I SE-852 S2C11 St.rtup Test Rep.rt P.ge 23 .f 71 L_- _ _ _ _ _ _ _ _
Figure 2.1 N SURRY UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE O E su .w& :f tg e,
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NE-852 S2C11 Startuo Test Report Page 24 of 71
l Figure 2.2 SURRY UNIT 2 - CfCLE 11 STAD/IUP PHYSICS TESTS I ROD DROP TIME - HGT FULL FLOW CONDITIONS e P N M L W J H G F f C C S a i l i i I I I I I I I I I I I I t.26 i I 4.27 I I 4.24 I l 1 I 1.25 l I 1.27 1 1 1.25 4 1 2 I 1 1 I l l l 1 I I I I 4.26 I i 1.50 t i I I I I I l i 1.27 I i 1.31 l l t l 5 l I i i l _.., I I i l I i i 1.29 4 1 1.24 4 I I I t.as Q l 4.12 i l i i 1.26 I i 1.26 I t i 1 a.27 4 1 1.31 I l 4 I i 1.. I I I I l _,,,,,, ] I I I I i 1.2h i l l l l 1.29 1 i i l I I I 1 i i 1 1 1.21 1 I I l l l 1.29 I I I i % 1 1 i l I I 1 ! I I I I l__ _ I I t.21 l l 4.ga e l g.5g ( l g.33 l l 3,g9 l l 4.50 l l 1.11 1 4 1.24 I i 1.24 4 1 1.29 1 1 1.31 1 l 1.34 I i 1.25 I i 1,32 1 6 I I l i 1 l l__ l l I i i 1 1 i 1.27 I I I i i I 1.34 I I 4.st i I I I I 1 i 1.ta I I I i 1.26 I I I i 1.24 I i 1.34 1 1 l i 1.27 1 I I i i l i l 1 1 1 I I l_ 1, I I I I I I i 1.29 I l i i 1.54 I I I I L.34 1 1 l i 1.12 I I i i 1.29 4 6 1 1 1.27 I l l I 1.30 l I 6 I i 1.26 I I I I I I I i i I I I i i l I I I I I i 1.2a l I i i 1.29 I i n.as a l i i 1.27 I i i 1 1.29 1 4 1.29 i l i i 1.27 1 9 1 1 l l i 1.27 l l 1 1 I i 1 1 1. I I I I i 1 1 I I l_1 l L 26 l i 1.52 4 1 1.51 I i 1.36 4 1 1.12 l l 1.29 l l 1.21 l 1 1.24 i l 1.24 1 1 1.28 i i 1.26 l t 1.36 1 1 1.27 i i 1.26 1 10 l i i I I l l I I I I l 1 1 1 I I I i 1.21 1 I I I I i 1.58 t I i i l i l i 1.25 l l I i 1 1 1.29 1 1 I 1 11 1 1 i l i l 1 1 i l i l I l i i 1.26 I i 1.21 1 1 1 I l.32 l i 1.28 I I I i 1.2* 1 1 1.26 I I I I t.27 6 l 1.27 I i 12 I I I I I i i 1 1 I I I I I I I i 1.26 1 I t.28 I I I I i l 1 1 1.26 I i 1.34 I l i i 13 i l i l i I l _ _1 i l i t 1,29 I I 1.29 1 I t.27 I I I i 1.29 1 1 1.26 i i 1.28 I i 14 I' I i .. I I I l __ I I I I I I I i i I 15 I l I I I a.sA t =*
- ROO DROP f1ME TO 045HPOT Enfev (SEC). FtWST ff si i X.11 i I l--> ROD DROP t tME 10 DASHPOf f utRY (SEC). SECOND IE$1 I
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~
T111S PAGE INTENTIONALLY BLANK I I I I I I I E I i NE-852 S2C11 Startup Test Report Page .' 6 of 71
u
~
r SECT 10h 3 l CONTROL ROD BANK tiORTl! HEASUREMENTS Control rod bank worths were measured for the conte.1 and shutdown banks using the rod swap technique" The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereaf ter 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 bann movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 11, 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 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. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral react ivity worth of the test bank. g NE.e 2 s2C11 tartup rest eepo,t eage 2, of 21
I ~ The core reactivit y , moderator temperature, and the dif ferential 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 5 5 bank again was near full insertion 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 tabl% and the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the individual measured bank worchs for the control and shutdown banks were within the design tolerance (!!0% for the reference bank and 115% or 100 pcm, which over is greater, for the test I banks). The sum of the individual measured rod bank worths was within 4.4% of the design prediction. This is well within the dasign tolerance of 110% for the sum of the individual cont rol rod bank worths . Note that during this test the control rod F6 was inserted in the core. Thus, all bank worths calculated during the startup test sequence were calt'ulated in the presence of F6. This meant that measured bank worths in the presence of F6 were compared to predicted bank worths with all rods out. Therefore, the design predictions for the control banks were recalculated in the presence of F6 in order to consistently compare results. These results are also summarized in Table 3.1. The measured results, when compared to the recalculated bank worths with F6 in, also met their respective design tolerances (listed above). The total bank worth was within 2.5% of the design prediction. This is well within the design tolerance of t10% for the sum of the individual control rod bank orths 2e of ,1 g xt.es2 2c11 sta, tup Test eeport eage
--+ - _ - _ _ _ _ _ _ _ _ _ _ . ._
[ The integral and dif ferential reactivity wortt the teference bank (Coritrol tank B) are shown in Figures 3.1 c* '.P. respectively. In these plots, the measured data is in the of F6 and the ( predicted values are with all rods out. The da.. n predictions and the { neasured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisf actory. [ l I 5 t i NE 852 S2C11 Startup Test Report Page 29 of 71
~
Table 3.1 I SURRY UNV 2 - CYC1.E 11 STARTUP PilYSICS TESTS CONTROL ROD BANK WORTil
SUMMARY
I MEASURED VS, PREDICTED I PERCENT DIFFERENCE I MEASURED PREDICTED WORTil WORT}l (%) BANK (PCH) (PCM) (M -)/P X 100 I B-Reference Bank D C 1375.2 934.1 841.6 1337.0 1050.1 934.2 2.9
-11.0
-9.9 A 248.3 235.8 5.3*
SB 1058.1 1157.4 -8.6 SA 1022,7 1015.3 0.7 Total Worth 5480.0 5729.8 -4,4 I I MEASURED VS. PREDICTED (WITH F6 STUCK IN) I MEASURED WORTH PREDICTED WORTH PERCENT DIFFERENCE (%) I BANK B-Reference nu k D (PCM) 1375.2 934.1 (PCM) 1368.0 924.5 (M-P)/P X 100 0.5 1.0 I C A SB 841.6 248.3 1058.1 901.7 254.7 1103.8
-6.7
-2.5*
-471 1 -
oA 1022.7 1070.6 -4.5 Total Worth 5480.0 5623.3 -2.5 I *The difference is less than 100 pcm. lI <I I. NE-852 S2C11 Startup Test Report Page 30 of 71 m
r Figure 3.1 l SURRY UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS BANK B INTEGRAL R0D WORTil - HZP f ALL OTilER RODS WITilDRAVN NOTE The measured data is in the presence of F6. I 1.400 m i,4 ; O ,,. . r r 7-~~- " l _ _
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4 O IIIIIi i IiiiIiiiIIIIIIi i !IIIIIi1iIIIIIIIIIIII O 10 25 40 55 70 85 100 120 140 160 180 200 220 BANK POSITIONS (steps) i I NE-852 S2C11 Startup Test Report Page 31 of 71
i E l l TIgure 3.2 I Sl!RRY UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS BANK B DIFTERENTIAL ROD WORTil - flZP ALL OTl!ER RODS WITilDRAWN NOTE: The measured data is in the presence of F6. I I !
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. HHiH HHt H t H 0 10 25 40 55 70 85 100 120 140 160 180 200 220 1 BANK PDSm0NS (steps)
I I 1 s L
E SECTION 4 I
!!ORON ENDPOINT AND WORTil MEASUREMENTS lioron Endpoint I With the reactor critical at hot zero power, reactor coolant system (RC3) 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 I 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. Note that since F6 was fully inserted in the core during this test, the critical boron endpoint was measured in the presence ot' F6. As shown in this table and in the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the measurco critical boron endpoint values were within their respective design tolerances and met the requirements of Technical Specification Section 4.10 regarding core reactivity balance. Since F6 was in the core during the boron endpoints measurement, the design predictions were recalculated in the presence of F6 to show that the results are acceptable. The results of these comparisons are also given in Table 4.1. These comparisons show that these boron endpoints also meet their respective design tolerances and the requirements of Technical Specification 4.10. In summary, the boron endpoint results were satisfactory. NE-852 S2Cll Startup Test Report Page 33 of 71
I I I I Boron Vorth Coefficient I The measured boron endpoint values provide stable statepoint data from which the baron worth coefficient or differential boren wotth (DBW) was det ermined. 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 baron endpoint. concentrations 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 -7.51 pcm/ ppm. This is within 2.8% of the predicted value of -7.31 pcm/ ppm and is well within the design tolerance of ilot. Note that since F6 was in the core, the DBW was measured in the presence of F6. To show that the test was acceptable, the predicted DbW was recalculated in the presence of F6. This predicted value was found to be -7.35 pcm/ ppm, which is within 2.2* of the measured value. In summary, the measured boron worth coefficient was satisfactory. I I I I I
<I I
g xx.ss2 2c,1 sta, tup Test x.po,, eage 3. of 71
E I Table 4.1 I SURRY UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS BORON ENDPOINTS
SUMMARY
- I I
MEASURED vs. PREDICTED I Measured Predicted Difference ig Control Rod Endpoint Endpoint H-P g Configuration (ppm) (ppm) (ppm) ARO 1926 1930 4 8 Bank in 1743 1743* 0 i il HEASURED vs. PREDICTED (IN Tile PRESENCE C F6) Heasured Predicted Difference lg Control Rod Endpoint Endpoint H-P
- g Configuration (ppm) (ppm) (ppm)
- ARO 1926 1912 +14 B Bank In 1743 1740* +3 I
- 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 l Sheets in the Appendix.
!I !I 1 I 4 9
J Figure 4.1 l l SURRY UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS BORON VORTli COEFFICIENT I i Measured DBW = -7.51 pcm/ ppm 1,400- - - --- ------1--- - - - - - - 1,200- - - - - , - ---
-<~~-+---r-- L-~<---+---+-- -i 1,000- - - - - + - = I g------<---~~.--.-<---+--+- i
^
I l E a u O $QQ- .
-s l o 600- - - - - - - - - - - ~ ~ -- L- a- -- - - - * - -
e La w 400- t - --- -+= + - - < l- -*--
- + - - - + - -i l !
4 i 200- * -
*--e----<+--- --< - -i, 0 , n , i i , , i i- i 1740 1760 1780 1800 1820 1840 1860 1880 1900 1920 1940 BORON CONCENTRATION (ppm) l NE-852 52C11 Startup Test Report Page 36 of 71
l SECTION $ l f TEMPERATURL COEFFICIENT MEASUREMENT E l The isothermal temperature coefficient (!TC) at the a l l - rod s - ou t condition is measured by controll'.ng 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. This test sequence includes a cooldown iallowed by a heatup. Reactivity was measured during the RCS cooldown of approximately 5.4'F and the RCS heatup of approximately 5.0*F. Reactivity and temperature data was taken from the reactivity computer and strip chart recorders. Using the statepoint method, the teeperature coef ficient 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 S lE ITC. I l lI The predicted and measured isothermal temperature coef ficient values are compared in Table 5.1. As can be seen f rom this summary and from the Startup Physics Test kesults and Evaluation Sheet given in the Appendix. I the measured isothermal temperature coefficient value was within the design tolerance of 13 pcm/'F and met the requirements of Technical Specification 3.1.E.1. Due to the presence of F6 in the core during the ITC measurement, the ITC prediction was recalculated in the presence of g xE.e52 S2c11 5ta, top Test xepo,< rag. >> e< 21
I E F6 to be compared to the measured value. This comparison is also given in Table 5.1. As can be seen from this summary, the measured ITC was within the design tolerance of 3 pcm/'T and met the requirements of j B Technical Specification 3.1.E.1. In summary, the sneasured result was satisfactory. I 5 I I I l i I lI s R E 1 I I I I g xx.s,2 2cu sta,t ,1os o , ort ease 3e of u
I l Table 5.1 [ 4 SURRY UNIT 2 - CYCL.E 11 STARTUP PilYSICS TESTS ISOTilERMAE TEMPERATURE COEFFICIENT
SUMMARY
i MEASURED vs. PREDICTED CORE CONDITIONS ISOTilERMAL 1EMPERATURE COEFTtCIENT j (PCM/'F) BANK TEMPERATURE BORON l , POSITION RANGE CONCENTRATION C/D ll/U AVE. LIFFER. ('F) (ppm) Mf a' " " F.D . (M-P) 541.9 D/225 to 19?6 -0.46 -0.60 -0.53 - .04 0.51 547.3 MEASURED vs, PREDICTED (IN Tile PRESENCE OF F6) CORE CONDITIONS ISOTilERMAE TEMPERATURE COEF} !CIENT (PCM/'F)
-8 BANK TEMPERATURE BORON POSITION RANGE CONCENTRATION C/D 11/U AVE. DIFFER.
('F) (ppm) MEAS. PRED. (M-P) 541.9 D/225 to 1926 -0.46 -0.60 -0.53 -1.23 0.70 547.3 NE-852 S2C11 Startup Test Report Page 39 of 71
Tills PAGE INTENTIONALLY BLANK NE-852 S2C11 Startup Test Report Page 40 of 71
I
^
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 in 48 core locations (see Figure 1.3). For each traverse, the detector voltage output is continuously monitored on a strip chart record e r , and scanned for 61 discrete axial points by the PRODAC P-250 process co;puter. Fal) core, three-dimensional power distributions ar.; determined f rom this data using the Westii.,, house computer program, INCORE'. INCOVE couples the measured voltages with predetermined ana) ic power-to-flux stics in order to determine the power distribution for the whole core. A list of the full-core flux maps taken during the rtartup test program and the measured values of the important power distribution parameters is given in Table 6.1. A comparison of these measured values with their Technical Specification limit s is given in Table 6.2. Note that there were two flux maps taken at about 30% power, as part of the startup physics test. The first flux map was taken at 3?.; power, and indicated that control red F6 was possibly fully inserted in the core. As a result of the control rod F6 insertion, the design tolerance for quadrant power tilt was not met for this map. The second flux map was takan at 29% power af ter the removal of control nd F6. The radial power distribution (RPD) for each of these maps is given in Figures 6.1 and 6.2. Flux raps 3 and 4 were taken at 68% and 100% power, respectively, with dif ferent control rod configurations. These flux maps were taken to check at power design predictions and to .neasure core power distrib'itions at i l NE-852 S2C11 Startup Test Report Pdge 41 of 71
I various operating conditions.
~
The radial power distributions for these maps are given in Figures 6.3 and 6.4 These tigures show that the measured r ' tive assembly power values were generally within 1.8*. of the predicted values (The measured relat ive assembly power values were within Further, the measured I 8 . 0 *. for the first flux map taken at 327. power). f F-Q(T) and F-DH(M) peaking factor values for the at power flux maps were within the limits of Technical Specifications 3.1:'.B. l . In conclusion, the power distribution measurement result s were
;I considereu a be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the Technical Specification limits, with the exception of the first map with control rod F6 fully inserted as noted above. It is therefore anticipated that the core will continue to operate safely throughout Cycle 11.
I il I lI I I g xs. m esu tart 1est xep.,t rage 2 of 71
~ TAB 11 6.1 L SURRY UNIT 2 - CYCLE 11 STARTUP PHYSICS TFSTS INCORE FLUX MAP
SUMMARY
p u a I i i i l i st*NI I i 6
# Otts Hot a i i f.lenMI Hot i e I COPt titi i Powtp i i i
i I l i I i i i 1 l 1 Illj i ARI&L ) NO,1 I N&P INa#l i UP l llaus 1 (H&MN(( $ &(IOR l (mt .f 4CIUR NAR
..._I I
l I De f I 08 1 1 DitCRIPfl0N lNO.1 D&It i kw0/IPwel 0 l l l l l lMfullZaltitPSl&5%vlPIN}5584Ll l&i$T IPlNif-DH4 Nil &Ejell $ (/ )1 M&E ikKl Lil IIHlN1 l i I l l l l l lPOINilF *0t t i i i l IPOINil l l l (23 Ittill l , e. ~ . ,.,llm,,!wlv,i,,ml ,l
, l ,.,,,=lm.!m01 i.... l1 i i.,u la.r.l iw T,.l l i.o,bvl
, i o. ~ .
lT,l.,....,il
, , .... 1 i., l Wl ,l ,.,,, i N 1 .,s.ii. l.ii..iu .i ., . , $ l I l a t Powi k IHof futt PowtN l
1 5 i F 44 ,il l_I I 661441 le i4 1 7 75 911 664 ligel fe,t1i Jt6) 11 l_1 fill tal l_l_l 30 1 3.9e 7 1 08 01 til 1.416 1 it il fillt.9 eel twl l.6&l 64 I Onl 36 l 1.646 8 Ji*l GN1 1.397 1 1Si ll.f I tbil.6tti til f.961 e7 I l l_I_1 1 l_l _1 _ I I I NO f( S t Hut t>0f 400&fl0M1 API $PICIFlf D SV CIVING &$$tMlt V 10tallDN1 14.0. M*$ l$ IHl (I N fi k Of -((W( 4 %',t M B L V ) , f Ot t owl 0 S t IME Pl4 L tX &Il(No I M I*)f t 0 t v Its "V" tot *0lmalt wi f M fit ilVt Ntit a pows of fJti pool L t i f t Pt 0 4 16*0ut.H D AND IHf *3* (00NOlM&f t IW $1Lhelt 0 IN & $lNIL &B N&tef D). IN THE *E* Dipt t flDN lit (Out 15 Diviotp INTO 64 &II AL POINIS SI ARilNC. $ PON IHf 10P (I D( ((M'f. , l . F 04 f 1 IN(t uot 5 & 10f al UME D f &lNIV 0F 1,4% I l.01. F. POWt R lit f - QuaDWANT SMh8t h lit t 45 luf lW O BV bt INCort Corit . NE-852 S2C11 Startui :ast Report Page 43 of 71
Table 6 2 I SURRY UNIT 2 - CYCLE 11 STARTUP PilYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITil TilEIR TECIINICAL SPECIFICATION LlHITS I I PEAE F-Q(T) 1107 l F-Q(T) HOT F-Dil( M ) 110T CllANNEL FACT 0F# CilANNEL FACTOR ** CilANNEL FACTOR I MAP MEAS 1,1MIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN NO. (%) (*) 1 2.299 4.634 30 2.299 4.634 30 50.4 1.572 1.868 15.8 2 2.218 4.634 30 2.218 4.634 30 52.1 1.460 1.882 22.4 3 1.947 3.418 30 1.947 3.418 30 43.0 1.416 1.700 16.7 4 1.846 2.320 36 1.816 2.283 24 20.4 1.397 1.550 9.9
- The Techniccl Specification's limit for the heat flux hot channel I factor, F-Q(T), is a function of core heignt.
F-Q(T) listed above is the maximum value of F-Q(T) in the core. The Technical Specification's limit listed above is evaluated at The value for the plane of maximum F-Q(T). I- ** The value for F-Q(T) listed above is the value at the plane of minimum margin. The minimum margin values listed above are the minimum percent dif ference between ,ne measured values of F-Q(T) I and the Technical Specification's limit at that node for each map. The measured F-Q(T) hot channel factors include 8'. total uncortainty. I I I
t L-
-~
Plgure 6.1 I SURRY UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMALYWISE POWER DISTRIBUTION 32% POWE5(
* > N N 4 J N c f ( 0 t 4 a Ppt 0lC fl 0 . . 9.24 0.11 0,te l'p10lC f t D .
4.*4 . 9.31 . 4.2) .
- 44Upl 0 I
1
. nt 4%u6( D .
.PCI bif t t Pt'TE . . 1.1 . 9.4 . -1.5 . ..PCI L '81kt Ntt .
. 8.f 7 . L 47 . l.91 9.A6 . 1.0% 0.44 . 9.f 4 .
0.10 . 0.46 . l.92 . 0.44 . l.St 4.4% 6.26 . t 9.4 . l . 3 . - 9. 3 . e.1 . l . 9 . -l . t . 6. 6 . I . 0.56 1,44 . 4.2% . 1.27 . 1.24 . 1. 29 . 1.27 . l.07 . 6.16 . e.39 . l.It . 1.2% . l.26 . I.!! 4.e 6.9 . 0.2 . al.6 . l.F . l.it . 1.1% . 0.9F . 9.15 F.9 . +9.4 . *9.4 . *9.0 . 1
. 9.54 . 0.47 . l.th 4.11 . l.FF 0.97 1.f8 . 1.14 . 4.28 . 0.64 . 4.14 .
I e.t1
. c.11 . 0.92
- 9. 5 . E.9 . 3.2 . 0.5 . +2.3 1.e4 1.26 . 1.27 . l.it 1,59 . 1,34 . l.24 . 0.94 1 10 . l.21 1.f4 . 1.t1 1.1#
1.2%
. l.86 . l.It . 0.77 . 0.31 .
l.6 . -9.1 . 14.6 +14.4 . 11.4 1.22 1.30 1.29 . 1.02 0.91 . 1.9% l.94 . 9.** 9.74
. l.28 10.1 1.9% 0.t?
4 4.50 . 1.16 . l.29 4.29 . % I II.9 !!.9 f6 f.7 . O.9 . -2.6 . -5.6 14.6 . 26.8 .-19.3 . 16.4 . 19.6 6.2 4.47 1.ft . l.15 . 1.18 . 4.14 1.20 1.t9 . l.21 1.16 1.22 1. S6 1.26 0.47 4.t! . 1.49 . l.42 1.24 . 1.1% l.14 . 1.16 9.95 . *.67 . 0.92 1.16 1.15 0.44 6 12.1 . 12.9 . 6.4 . 2.7 . 4.6 . -4. 5 . 9. 4 25.6 42.3 l4.7 .*lt.9 19.6 *F.0 I 9.24 1.04 0.28 . 1 17 . 1.4r 18.2 . it.7 1.28 11.6
. 4.t?
1.16 . 1.21 . 1.!! . 1.f7 6.6 . l.14 . 1.29 l.9 . 6.9 l.29 . 1.78 . l.12
- l . 6 . 4. 3 . I b .6 . 21. 2 e.it 9.44 1.73 . 0.9F . . 27 . l.29 . 1.28 . 1.14 . l.79 . 4.10 . 1.ta . 4.94 . 1.t4 . e.64 1.28 . 1.25 . 1.24 . l.28 1.17 . 1.1% . 0.95 . 9.99 3.12 . 4.lf . 0.96 0 lt .
tI.4 *lt.6 . 4.9 1.01
+ F.n 0.f4 6.4 .
0.31 P e.16 4.99 1.34 . l.44 1.38 . 1.32 . I.t* . 4.17 1.tv . 1.17 , 1.1% 0.47 1.14 . 4.44 0.34 . a 14.1 . 17.4 . 4.4 . 6.6 . 2.1 . f.6 -4.4 . *n.1 . 4.0 . 9.5 . 9.9 . 10.7 . 4.2 -6.6 1.7 0.24 L.8! . 1.27 . 1.27 1.f4 . l.it 4.t9 . l.27 1.19 . 1.28 . 1.t% . l.lf 1.24 8.6% 0.24 . 3.78 1.16 1.40 . 1.36 . l.11 . 1.tn 1.33 1. ' l.2% l.13 . 1.14 . 1,74 1.22 1<01 . 0.f4 9
. 18.! . 15.0 . 19.2 F4. 6.9 4.0 . 0.6 . e . - 3.1 . - 6. 0 . 4 6. 7 . l . 6 . - 4. 7 +3.7 8.8 0.47 . 1.tl 1.34 . l.21 1.1% 4.79 1.28 . 1.?t 1.1% . 1.24 . 1 34 1.t6 9.47
- 12
. 1 44 1.48 . 2.at . 1.22 . 1.fr . 1.3t . 1.20 1.16 1.14 . l.37 1.21 0.44 to
. !!.7 12.6 . 10.5 9.8 6.6 8.4 1.1 . 0.6 . 0.4 . 19 1.8 . 1.8 0.6 8.t1 1.01 . 1.!F . 1.29 8.tt . l.2% . 1.28 . l . 2% - 1.22 4.29 1.t? l.0% 0.27 e.54 1.19 . l.41 1.42 . 1.18 8.32 . 1.is . 1.54 1.24 8.16 . 3.15 1.08 . 0.28 11 15.8 . 11.4 12.1 10.8 . 4.4 S.2 . F.4 . 4.6 . l.6 6. F . 4.8 . 3.2 . 2.1 o.54 . 0.89 l.76 . 1.33 1.?9 0.48 1,29 4.3% . 1.78 . 0.64 . 9.34 8.39 4.81 1.41 4.*4 1.3F 1.04 . l.56 1,42 . 1.3% 9. 94 0.3% . 12
. 1%.9 . 11.0 9.9 . 1.8 6.6 7.4 . 6.4 4.4 . 6,9 . 6.5 f.9 4.1F 1.07 . 1.f4 . l.38 4.26 . 1.59 . 1.tf . 1 06 . 4. 36 S.42 . 1.21 . l.48 . 1.5J . l.37 . 1.41 . 1.57 . 1.14 . 4 . 14 . 13 1%.9 15.1 . 10.8 . 6.1 4.4 4.8 7.% 7.0 . %0
. 8.28 9.44 . 4.06 . 0.91 . 1.0% 0.44 0.to .
. 9.32 . 9.54 . 1.17 . 1.01 . 4 16 . 4.42 . 6.34 . 14
. ?,.4 . 11.3 . 19.4 10.6 . 18.2 8.4 . 1.1 .
516MD&9D 0.tt . 4.12 . 4.f4 . . A Vl W A GE . Dt viat I DN . 9.27 . 9.3% . 6.27 . PCT D!f f l RI NCE . Ib
. *6.146 10.4 10.% 10.5 a 6.9 S(ww1 A py MAP NO: 52 11 01 DATE: 06/08/91 POWERI 52X CONTPOL ROD POSIT 10NSI F-QtT) = 2.299 QPTRI D BAM AT lu STEPS F-DHIFil
- 1.672 NW 1.021 l NE 4.871 i
FtZ) = 1.3b6 SW 1.057 i SE 1.022 SURNUP e 0. 0 Mt. 'MTU A.O. 8 -1.268% NE-SS2 S2C11 Startup Test Report Page 45 of 71
0 L
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Flgure 6.2 f SURRY UNIT 2 - CYCLE 11 STARTUP PHYSICS TESTS - ASSEMBLYWISE POWER DISTFIBUTION 297, POWER e P a a I g J N C F i 0 C 6 & PM0ltif 0 . 0.f4 . 0.51 . 0.14 Wt blC fl 0 . ni asunt 0 . 9.f4 9.11 . 3.75 . , NE &Lurt D . 1 I PCT DIFilPtNCE. . f.4 f.3 . f.9 . .PCf OlfffPENCf. 9.t? . 4.4F . 1.08 . 0.04 . 1.06 . 0.44 . 9 74 . 9.28.9.46 1.07.0.87.4.06.9.49 0.29 . t
. l.! . 4.8 . 4.0 . *l.t . 11. 1.4 . 1.9 .
I 4............................................................... 9.h I.94 . 4.2% 1.!? . 3.24 . 1.79 . l.ft . 4.07 . 8.16 9.16 . 1.04 . l.21 . l.16 . l.it . 1.19 . 1.10 1.40 . 6.14 1
. 0.9 0 . 8 . - l . 2 . - l . ! . - 1. 8 . 6.2 . 2.t . 1.4 . 4.2 .
0.14 0.4F . l.t6 . l.55 . 4.!F . 0.97 1.28 . '. 54 8.lt . 0.64 . o.34 . I . 0.34 . 9.66 . l.74 . l.51 8.99 . 4.29 . 1.57 . 1.28 . 9.44 . 9.14 . 1.2F
- 1.1 . -4.1 . *l.1 . +4.8 . 4.5 . 4.9 8.6 0.6 0.3 . -9.1 . *l.1 6.!? 1.04 1.76 i FF . 1.ft . 3.74 1.t? 8.26 . 1.!? . 1.10 . l.28 8.0% 0.2P 9.76 . 1.03 1.25 . 1.26 1.21 1.27 1.14 1.26 . 1.22 . 4.26 . l.it . l.08 9.16 %
b.0 0.8 . 0.4 . a l . 6 . 3.1 . - 3. 7 . - 4. 0 I
-l.4 4.F l.S . f.! . a.6 . +0.F 0.47 1.t% . 4.11 1.14 . l.14 . 1.ft . 1.29 . 1.ft . 4.16 1.22 . 1.36 8.76 . 6.4F 8.49 . 1.51 1.$5 . 1.71 . 1.44 . 1.10 . 1.79 4 13 . l.13 1.49 . l.11 . 4.11 . t At . 4 6.0 5.0 . 1.4 0.4 . 9.2 . 8.6 . 0.0 . *2.1 l.t 2.4 S.4 **.9 . -4.4 I 0.f4 4.04 . 1.f4 4.27 . l.14 1.21 1.79 . 1.78 . 3 12 1.!! . 4.7% . 4.28 . l.28 . l.45 0.t4 .
9.t% 1.99 . l.14 . 3.11 . 4.26 . l.29 8.f4 . 4.tb . 1.26 . 1.18 . 4 ft . l.22 1.f4 1.00 . 9.t! . F 4.0 4.F . 4.9 1.3 . 1.6 . 0.4 . 0.9 . af.! . 4.F , al.t 1.9 -4.5 . - 5.1 . 3.4 . +2.8 .
. c.10 . 0.68 . l.23 s.9F l.tF . l.29 . 4.it , l.18 . 1.t9 . l.30 . 4.24 . 4.94 . l.74 0.44 . 9.11 .
S. 5t . 0.91 . l .76 . 1,91 . 1. 51 . l .17 1.17 . 4. 8 6 1.t? . 8.t? . 1.26 . 0.94 . 4.18 . 0.64 . 0.10 8 I 4.6 . 0.F4 . 1.02 0.7% 4.3 . 4.7 . 4.7 l 06 1.27 1,29 . 1.31 3.1 . f.5 . l.0 . 2.2 . -1.9 . l.7 . +1.F .
. 2F 1.24 4.19 . 1.79 1.27 . 1.t9 1.3 8 . l . tn . l . 34 . 1.(9 4.t9 1.tl 3.16 . 4.t8 1.t8 . 1.01 . 9.!!
1.!! 4.25 . 4.0 . -F.9 . -0.6 . al.9 . l.24 . l.78 9.0% . 6.tt . 4
. 4.4 . f8 4.7 3.4 L.4 . 4.2 . 3.4 I%. 0.2 0.8 0.4 . 9.1 -2.4 . -1.2 . 2.5 I . . .. .....
0.47 0.4s 0.6 1.76 1.24 0.F 1.34 1.5% l.t 1.28 . 1.8% . 4.te 1.tb f.F . 1.48 . l.74 f.9 .
!.f4 1.31 1.te 4.It 3.1 . l.7 . l.2 . 9.6 . 9.7 . l.9 1.1% . 1.!! . 1.34 . 1.26 4.16 . 1.22 . 4.3F 0.4
. 4.47 l . t F . 0.4 7 0.9 19 4.27 . 1.0% l.tF . 1.50 . 1.ft . l 25 . l.78 . L.tb l.it 1 29 1.t? 4.04 0.27 .
4.27 8.13 . 1 2F . l.34 . 4 28 8.f4 . 4.2F . 4.t? . 1.06 . 8.tF I 1.0% . 1.t? . 1.19 !!
. -0.1 . 0.1 0.4 0. 2 . 4.4 . 4.9 . 1.t . l.9 2.1 . l.6 . 9.1 . 4.0 . 9.4 .
0.34 4.49 1. 2 8 . 1. 3 % . l . t9 4.94 1.19 4.3% 1.28 0.84 . 6.14 0.54 . 0.49 . 4.27 l.36 . 1.34 . 4.00 4.30 . 1.16 4.tF . 0.sa 0.3% . It 0.6 . 0.9 . 0.8 . 0.6 . 1.4 . 1.2 . 1.2 0.5 . 0.5 . 0.4 . l.9 I . .... ........................... ............. ...................... .....
. 0.37 . 1.0F
. 0.5F . 1.07 . 1.29 4.4 . 8.t . 9.8 .
!.28 . 1.38 . 4.26 . l.it . 1.2F 1 12 . l .t6 . 4.24 l.4 0.8 0.F . 0,5 1,06 . 9.16 1.27 . 1.06 . 0.M .
0.4 . 0.6 . 13 4.05 0.44 . 0.78 I 0.f4 . 4.48 . 1.06 . 0.91 0.14 0.49 . 3 12 . 0.92 . 4.04 4.44 0.78 . 14
. 9.2 . 2.3 . 5.3 . 4 2 l.0 -0.7 0.3 STANDARD 4.24 . 4.32 . 9.24 . Avt P ACE' .
IdvlafloM . 6.t6 . 4.13 , 4.24 . .. PCT Olf f t PE NCf. 16 I al.4st . nt t.6 . 1.t
- 1.6 i puMMARY MAP NO. 52 11-02 DATE: 07/04/91 power: 29%
CONTROL ROD POSITIONS: F-QlTI a 2.018 QPTR: D BANK AT 163 STEPS F DHIMI a 1. 4 V. NW 0.997 l NE 0.987 1. FlZ) = 1.416 SW 1.015 i SE 1.001
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BURNUP a 26.0 ftWD/ftTU F.0. s -3.421% NE-852 S2C11 Startup Test Report Page 46 of 71
Figure 6.3 SURRY UNIT 2 CYCL.E 11 STARTUP PHYSICS TESTS ASSEMBLYVISE POVER DISTRIBUTION 68% POVER v P u a i s J H & $ l D ( $ & l'Wi t t . fl 0 0.76 0.1% 0. 7 Put git fi h 4.16 . 8.14 0 t6 af e%Upl D 1 e6 4Mwl D . F.6 . 2.9 . f# 1 Die f f pl eot t .
.f'(1 DifflFiteCf. -l.b
. 0.19 0.49 1.07 . 0.9% . l.09 . 0.40 . 4 19
. 0.10 . 0.49 1.07 0.44 1.04 0.40 0.10 . .
l.6 . 0.4 0.6 . 1.7 . 0.7 . 0.7 0.4 9.17 1.0% 4.14 4.28 . 1.7% 1.79 . 1.76 . l.06 . L 7.4 0.18 . 1.04 . 1.21 l.16 . 4.f$ . 1.19 1.16 . 4.07 0 44 . 1 f.6 0.1 0.6 . 9.1 . *0.t 0.8 . 0.1 0.4 0.7 0.44 . 0.00 1.21 1.1% . 1.F% . 0.90 1.76 . 1.11 . 1.26 . 0.49 0 16 0.90 . l.76 . 1.11 . l.f4 . 0.64 0.14
- 0.16 0.44 . 1.12 1.10 1.ft
. 1.8 . -0.0 . +4.5 -e 4 , 0.t . 0.1 0.3 . 0.0 . 0.0 0.2 1.0 .
0.29 1.04 . 1.11 1.1% 1.19 8.ft . 1.7% . 1.11 1.10 1.F7 1.14 4.04 0.19 SJ9 . 1.04 4.21 1.7% 4.19 1.75 . 1.th 4.25 1.!! . 1.17 . l.it . 1.01 0.19 %
-0.0 0.e -la 0.t -0.1 4 0.4 +0.4 0.1 . 0.6 . 8.6 1.6 l.4 . 1.6 .
............. ................ ... ...... ............. ............. ...... .....+ ...
. 0 A9 1.24 . 1.11 . 4.19 i '4. 1.14 l.76 1.l9 4.14 1.70 1.12 1.tb ca9 0.49 8.14 8.11 1 49 , l.17 8.49 1.F6 1.19 . 4.16 i 10 1.11 litt 9.40 6
+0.1 0.1 1.0 t,4 0.0 +0 0 0.8 . 0.7 . 0.6 . 0.4 . 0.2 . 4,6 . . .t.t 0.77 1.00 19' ..1.76 . 1.F5 . 4.18 1.77 . 1.t6 1.10 1.19 1.25 ....l.16 1.10 1.07 0.16 .
4.17 . 1.09 4.2% . l.77 . l.19 . I.f9 l.76 4 10 . l.it , l.F1 . 1.f4 . 4.14 4.01 0.7% 7 1.6 0.1 . 0.4 0,7 0.1 4.4 0.t . 0.6 0.6 . 0.i . +l.6 l.9 1.7 1.6 .
. 8.1% . 0.9% 4.1% . 0.98 . l.tn . l.tf . 1.26 . 4.86 . 1- l.77 . 1.7% . 0.99 . 1.th . 0.9% 0.14 .
0.16 . 0.9% . l.it . 0.90 . l.14 . l.t7 1.18 . l.46 . 1.77 t8 .. 4.77 . l.7% . 0.96 . 4.11 . 0.91 0.14 4
. 1.1 0.7 +0.6 . 0.t . -0.7 0.4 1.6 . l.1 . 0.4 . 0.2 , 0.( ta 1.2 -1.4 1.*
9.t6 1.07 8.78 4.t6 1.!! 1.19 1.77 1.7% 1.77 . l.19 . l.7% . 4.26 1.18 8.0* 6 F7 0,t1 4.07 1.fi i 16 1.74 . l.19 1.27 1.ib 1.74 . l.19 . 4.t1 1.rt 4.77 1.07 0.t6 4
. l.% . 0.2 . *0.4 . 0.0 1.0 0.8 0.5 . 4.1 0.6 0.1 0.1 . 0.6 . l.1 1.0 1.P
. 9 /9 1.F4 1.11 4.89 1.87 1.19 !.i6 1.at 1.17 1.19 1.11 1.tb 0.40 0.49 4.14 1.17 1.il 1,44 . 4.14 1.27 f.49 1.44 . 1.tl 1.11 1.14 0.te 10
+0.4 . *f,4 0.1 1.1 0,6 0.1 0.6 . 0.% . 9.% 1.7 la 1.8 0.5 9.f9 . l.0% 1.t* 1. 7 1.)0 1.75 , 4.7% 4 11 . l.10 . 1.F6 . 1.f4 4.0% 0.ts 0.f9 1.04 1 1% . 4.24 . l.20 1.21 . 4.17 1 24 . 4,10 1.19 . 1.2% l.04 0.t9 ll 0.2 -0.F 0.1 1.2 -0 0 . 0.6 . l.F 0.4 . 0.4 . t.1 0.7 0.7 . -0.2 .
9.16 0.90 4.7% 1.12 1.16 . 0.99 8.r6 1.11 8.f4 0.64 0.1%
- 0. 16 . 0.90 4.t6 1.lt . 1.2% , 0.99 8.t1 . 1.12 1.41 . 0.64 0.1% 1.'
0.0 BA 1.1 -0.% l.! . 8.1 . 1.1 . 0.4 . 0.6 . 0.2 . l.6 0.M l.06 4.76 . l.10 l.t6 . 1.10 . l.2% 1.06 . 6. 14 0.14 4.00 1.16 . 1.28 . l.fi 1.F9 1.ft . 1.0% 0.17 . 11
. 1.0 f.0 . 8.1 . -1.6 +0 4 0.6 ~0.7 0.6 -0.9
. .............. ..,4.. ............. ..... ...... .
0 F9 0.40 1.40 0.97 1.09 0.50 0.t9 0.10 . 0.60 . 1.04 0.96 1.09 0.50 . 8.19 14 f.) . 0.7 . l % . 0.9 *0.1 -0.h. 0.4 Ef ehDaarD a . 2 7 . 9.16 . 0. 7 7 . AVIWAGC tie v 4 4110es 8.!? . 8.1% 0.17 ..P(1 Olf f f Pt Nr{ , 1% 0.877 l.6 . l.1 +0.1
- 8.1
),1{tM A R Y MAP N01 52 11-01 DAftr 07/06/91 POWERI 68X CONTROL ROD POSITIONS: F-QtT) = 1.947 G*TRI D BANK At 182 Sites F DHIN)
- 1.416 Nw 0.997 l NE 4.997 1
tizl = 1.271 sw 1.oos I st 1. o n llVRNur
- 45 Hw0/N19 A.O. s 1.876%
NE-852 S2C11 Startup Test Report Page 47 of 71
Figure 6.4 SURRY UNIT 2 CYCLE 11 STARTUP PHYSICS Tf.STS ASSEMBLYWISE POWER DISTRIBt' TION 100% POWER 4 P N N L F J H C I I D t I & Pkl Dit tl 0
- 8.f4 4.37 . 6.it . PPI Dit tl D .
9t &4ukl 0 . p.ta . 0.17 9 te . . M AEs4 0 . !
..P(f Dif f l kt hKl . 0.4 0.3 1.0 . .PCI Dif f i ki W(1.
0.30 0.Se 1.00 . 0.98 . l.10 . 0.40 . 0.50 . 4.10 0.40 . 1.04 0.94 . 1.14 0.nl 0.3I . t f.6 . 0.6 . 0.6 0.9 . 0.4 . l.8 . f.7 0 34 . 1.04 . l.73 1.f7 8.16 1 28 8.t4 4.0 6 . 6 . 14 .
. 0.39 1.04 1 11 . 4.26 . 1.f4 1.24 1.2% l.07 . 0.40 1 1.0 . 0.2 l.% 0.6 . 4.4 0.0 . 0.4 . f.1 . e.l 0.36 0.64 B.tt . 1.19 . l.tn 0 99 4 26 . 1.38 3.21 0.64 0.16 0.17 0.87 1.20 . 1.EA . l.7% . 1.00 . 1.26 . 1.11 . 1.24 0.69 0. 16 4
. 2.5 . 0.2 2.8 . 4.0 0.1 0.8 . 0.0 . -0.1 . 0.6 . 4.9 8.1 .
0.19 1.01 1.11 1.Pt . 1.49 . l.it . 4.26 1.23 1.21 . 1.tn . 1.23 3 04 0 t9 0.39 l.03 1.!! 1.21 . 1.19 8.11 8.t1 1.24 1.21 . 1,76 1.14 1.01 0.10 4
-l.0 . 0.8 . 4. 0.6 . -0 6 . 0.7 1.0 . 0.9 0.6 0.0 1.6 . 0.1 . 4.t
. 0.40 . l.t3 1.19 1.20 8.20 . 3.19 1.26 3.70 . 84t! 1.70 1.10 L.11 0.4 0.49 l.22 . 1.18 8.89 . 4.te 1.10 4.tF l.t! . 1.ft i.!! . 1.t9 4.!! 9.60 6
~1.9 . 1.0 0.7 -0.P . 0.1 . 1.0 0.8 . 0.6 . 0.7 0.4 -1.0 1.3 -0.7 6.18 1.09 1.18 . 1.1% . 4.!! 8.70 1.27 1.75 1.29 . l.ft 1.73 1.16 8.17 1.06 . 0.f7 0.t9 . 1.09 8.26 . 3.f4 . 1.ft . 1.ft 1.20 . 1.26 . 1. 29 . l.11 . 4.24 1.!? 1.74 . 1.06 9.27 7 t.9 . 0.1 . al.0 1.0 l.0 0.4 . 1.4 . 0.4 0.t 6.7 . 1.1 . 2.8 . .I 1.4 -1.0 .
8.17 . 0.98 1 16 0.99 8.75 . l.26 . 1.2% . i.16 . 3.16 1.16 1.24 . 0. 99 . 1.76 . 0.90 . 0.17 . 4.16 4.99 . 1.f4 0.99 . 1. f t . l.27 1.77 . 1.14 1.te . l.28 . 1.f7 . 0.94 1.73 . 0.9F 0.56 8 2.4 . 0.8 . 1.2 0.% - 0. F . 6.$ . l.n 3.8 . 1.0 8.0 . l.1 . 1.4 l.1 -l.3 .
................6
.0.76 l.84 . l.27 I.it . 3.11 . l.20 1.11 . 1.f4 . 1.t6 . 4.te . 1.25 . 3.16 4.27 1.10 0.18 4 0.29 . 1.00 1.75 . 1.2% 1.26 1.11 1.27 4.26 4.t9 1.11 . 1.t4 4.fi . 1.t7 1.09 0.f4 . 9 2.9 0.2 . 1.4 . 0.5 . I.7 0.7 0.1 . 1.5 . l7 4.7 L.! . -0.5 -0.1 0.t 0.6 0.60 8.71 . l.21 8.70 1.10 l.it 1.26 1.19 4.10 8.10 . 1.29 8.11 0.40 q 0.69 1.20 8.t9 1.tl 3.11 1.20 1.27 1.t1 1.t! . 1.11 1.11 1.26 0.41 10
*t.t . 2.6 -0.6 0.9 0.6 0. 3 . 0.6 . l.2 l.2 1.1 15 1.8 f.0 0.t9 1.04 . 1.23 4.2% . 1.20 . L.!! 1.26 . 3.11 1.70 1.7% 1.ft 1.04 0.29 0.tv 4.01 1.t! t.*S 3.10 8.t3 1.t6 . 1.f4 I tt 1.26 . 1.74 4.05 0.50 . 11 0.4 0.4 . 0.4 0.4 -0.5 0.0 . 0.6 . 0.6 0.9 . 4.1 . 1.4 . I8 f.4 8.16 0.49 l.i. 1.10 1.?6 0.99 4.16 1.10 . 1.21 0. 6A 4.16 .
0.57 0.90 ' 75 1.t9 1.16 0.99 1.76 1.50 1.f4 0 69 0.36 it 6.s 0.s e. e.s 1.6 s.7 { . l.6 . .4 -0.0 0.8 , e.t
. 0.38 1. 0% 1. f 4 1.28 . l.t7 1.ta 1.24 . 1.0% . 9. na 4.39 1.07 1.74 1.27 . 1.25 . I t1 . l.22 . l.04 . 4.39 . 13 1.5 1.4 . 0.2 1.0 . -l.2 1.2 . 1.5 0.0 1.7 0.30 0.60 1.11 1.00 1.10 0.68 0.30 .
0.50 . 0.6L , 1.52 1.00 1. 04 . 0. 60 . 0. t9 . 14
. l.4 1.1 1.3 . -0.6 4.5 -l.3 . 1.1 SIANDARD 0.f4 . 6.14 0.26 . .
A vi p ACT +
. Dt vlell DN 4.29 0.54 . 6.26 . .PCI Olf F E RI MCI . IS
. *0.766 1.5 0.1 1.6 = 1.0
$(mW1ARY MAP Nos 52 11 04 DAff! 07/23/91 POWERI 100%
CONTROL ROD Pos!TIONSI F-Qtil s 1.846 QPTRI D BANK AT 209 STEM F DHlH) s 1.391 NW 0 . 9 He l NE 1.001 1 FlZ1 8 1.215 LW 1.001 l SE 1.00h BURNUP s $48 NWD/MTU A.O.
- 2.8607, t
NE-852 S2C11 Startup Test Report Page 48 of 71
m s ~ SECTION 7 r L STARTUP MlYSICS TESTING RESUI.TS WITH F6 IN Tile CORE I Upon analyzing the first flux map taken as part of the startup physics test for Surry 2 Cycle 11 and other related information, it was discovered that the control rod F6 was fully inserted in the core during the entire startup physics testing program. Thus, the measured values were actually measured in the presence of F6. These results when compared to the predicted values met all their respective design tolerances and utisfied their acceptance criteria. Since F6 was actually in the core during the startup testing sequence, it was necessary to revise the predictions to I reflect the presence of F6 (Reference 3). The measured data was then compared to these revised predictions, and the results are summarized in Table 7.1. The results of startup testing improved when these comparisons were made, and all tests met their respective design tolerances and acceptance criteria (these comparisons wers made in the a;,propriate sections of this startup report). Since the design tolerances and acceptance criteria were met with the revised predictions. it bas been , shown *. hat the Surry 2 Cycle 11 core has been modelled correctly. Since the neasured values met the acceptance criteria when compared to the predictions in the presence of F6, i'. is not expected that the ar ceptance criteria would not bo met if startup testing was done over and the measured values were compared to the original predictions. The results of tnis comparison show that the core was modelled correctly, and there is confidence in the model to accurately predict any other physical NE-852 S2C11 Startup Test Report page 49 of 71
l I parameter of the core throughout cycle 11. Since the results of startup t e s t ing and the results of the revised predictions met their design tolerances and acceptance criteria, it was decided that a second startup test .as not necessary, with the exception of hot rod drops and the 30*. power flux map. In conclusion, the rer.ults of the comparison of the measured values to the revised predictions show that the core behaved as predicted. I I I I I I I I I_ M
- i. . . . . . . . .
t s Table 7.1 S2011 STARTUP PilYSICS TESTING RESUI,TS COMPARISON ~ ME URED VS. PREDICTED VITil F6 IN
' \
Design Parameter Measured Predicted Difference Tolerance Critical Boron Concentration 1926 1912 +14 +/- 36 (llZP. All rods out), ppm Critical Boron Concentration 1743 1740 +3 +/- 29 (reference bank in), ppm Isothermal Tempurature Coef. -0.53 -1.23 +0.70 +/- 3.0 (HZP, All rods out), pcm/'f lB Dif f erent tal Boron Worth -7.51 -7.35 - 2 . 2 *. +/- 10*. (llZP All rods out), pcm/ ppm Reference Bank Worth 1375 1368 + 0 . 5 *. +/- 10 '. i (B bank, dilution) pcm U bank Worth 934 925 + 1: 07. +/- 157, (Rod Swap), pcm C-bank Worth 842 902 -6.7% +/- 157. (Rod Swap), pcm A-bank Worth 248 255 -7 pcm +/- 100 (Rod Swap), pcm pcm SB-bank Worth 1058 1104 - 4 . 1 ', +/- 15% (Rod Swap), pcm SA-bank Worth 1023 1071 -4.5% 4/- 15 *, (Rod Swap), pcm Total Bank Worth, pcm 5480 5623 -2.5% +/- 10% Notes: The predicted reference bank in critical boron was adjusted by the dif ference of the measured and predicted unrodded critical boron. The D-bank rod swap worths and the total bank worths do not include control rod F6. The sum of the individual bank worths iaay not equal the total bank worth due to roundoff. NE-852 S2C11 Startup Test Report Page 51 of 71
I L Tills PAGE INTENTIONALLY li!ANK I I I l l I I I i 1 1 NE-852 S2Cll Startup Test Report Page 52 of 71
g" SECTION 8 I REFERENCES
- 1. P. D. Banning, "Surry Unit 2, Cycle 11 Design Report".
Technical Report NE-837, Revision 0, Virginia Power, 'iny, 1991.
- 2. T. J. O'Connor," Unlatched Control Rod Event Review, Surry Unit 2 June 9, 1991", 91-07-SPd (Interim Report), July,1991.
I 3. A. H. Nicholson,"Surry Unit 2 Cycle 11 Startup Physics Testing Preparations", Calculational Note PM-381, Revision 0, Addendum 3, Virginia Power, June, 1991. J. . T. E. Ross, W. C. Bock. " Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1"80.
- 3. 'd . Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 1967.
I 6. Surry Unit I and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, and 4.10. I I I I I I I
'I ~
l , I "-" 8 c " 8 " < "e '- "-- " t- 8: " >' i ._
Tills PAGE INTENT 10N ALLI ';K NE-852 52C11 Startup Test Report Page 54 of 71
k B I ' 'rENDIX I STARTUP PilYSICS TESTS RESULTS AND EVALUATION SilEETS I I . I I I I I I I I I I g xr..e,2 2cu e _ ,1. - e., _ ro. ,s ->1
I 1 SURRY POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST Rt.SULTS AND EVALUATION SHEET I Test Descr:ption: Reactivity Computer Checkout Sequence Step No: Reference l Proc So /! action: 2 PT-28.11 II Bank Positions (Steps) RCS Teeperature ('T): $47 Test _
- Power Level (i T.P. ): O Conditions! SDA: '25
. SDB: 22$ CA: 225 Other (specify):
(Design) CB: . 25 CC: 225 CD:
- Below Nuclear Heating III I Bank Positions (Steps) RCS Temperature ('F): id 7 I' Test Conditions SDA: 225 SDB: 225 CA: 225 Power Level (1 F.P.): O Other (Specify):
(Actual) CB: 225 CC: 225 CD: /01 < Below Nuclear Heating I I Date/ Time Test Performed: 20;30 G/f/e/ Measured Parameter pe = Meas. Reactivty using p computer IV (Description) pt = Predicted Reectivity pc = $,C -28 I
~ n' '3 '
Measured Value pg= M.3
/.T b ~ 2. 7% '
Test ID = Results Design Value I (Actual Conditions) Design Value 1D = ((pe-pg)/pt) x 100% 1 4.0% (Design Conditions) 1D = ((pep g)/p g) x 1001 1 4.0% 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 VI 90 I Acceptance Criteria is met . _/,,,,_Y ES Comments ; -
- At The Range Allowable Just Critical 2 -2.0 Position ( ro + 36. 0 Prepared By: S.k _
Reviewed By: ,,a,,,,,S_ W* mM I g 2.es2 2c u S m ,t , 1. m e ,o,, Page se eu
B SURRY POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
- Test
Description:
Critical Boron Concentration - ARO
-I Reference Proc No /Section: 2-PT-28,11 Sequence Step No:
I Bank Positions (Steps) l RCS Teeperature ('F): 547 Test Power Level (% F.P ): 0 j, 2cnditionsi SDA: 225 SDB: 225 CA: 225 lCther(specify): (Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heatizg
'7I '
Bank Positions (Steps) RCS Teeperature ('F): f*/ 7. O f.st Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actual) CB; 225 CC: 225 CD: 225 Below Nuclear lleating Date/ Time Test Porformed: G/(,f g Offt Mens Parneeter 3 I IV (Description) (CB ) AR0; ri
...sl Boron Conc - ARO Measured Value (Cg ) arf' !
Test I- Results Design Value l(ActualCond) CB" [330*-- f Design Valne (Design Ccad) CB = 1930 1 36 ppe Re'eren e Tectiical Neporc NE-637, Rev. 0 I I D V ; FSA9/Tecb 9pec aC3xCB 5 IMO M Acceptance; - - Criteria j Reference Technical Sp m .fication 4.10.A Design Tolerance is est : __#YES NO Acceptance Criteria is met .,,hdES NO VI Coeeants aC B '7 U Pen /ppe D M CB = l(CB) ARO - CB l; CB--ls det.ign val.3 , scrusi conditions.
! ,,. ,a red , ,. % s 't , . . - , , . p. ua~,
l l 8
,t-s52 y 2C11 st.rt.p rest eepo,e enge s, oi > >
I j SURRY POWER STATION UNIT 2 CYCLE 11 g j STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET i
]. Test escr:F lon: Isothermal Teeperature Coefficient ARO R e f e renc.e, Proc No ! Sect an: 2 .T-28.11 Sequence Step No:
II Banx Positions (Steps) RCS Temperature ('P): 547 Test , Power Level (*. T.P. ): 0 { 2cnditionsi SDA: 225 SDB: 225 CA: 225 Other { Qecity):
- (Design) l CB
- 225 CC: 225 CD: 223 Belo., Nuclear Heattag III Bank Positions (Steps) l RCS Teeperature ('F): f n. f Test Conditions Power Level (7. F.P. ): 0 SDA: 225 SDB: ?25 CA: 225 Other (Specify):
!I (Actual) CB: 225 CC: 225 CD: Below Nuclear Heating Date/ Time Test Performed: ll &/C/91 010o j Meas Parameter ISO IV j (Description) (a T )ARO Isothermal Teep Coef f ARO Test ISO Measured Value .lu Results (a T )ARO " !8 J Pca/'T (CB *If2(PPe) Design Value g3o (Actual Cond) (a 7 )ARO * -/. 0a/ Pca/'T (CB */f2( ppa) ISO (a T )ARO a 1.00 2 3.0 pee /'T Design Value (Desagn Cond) (Cg: 1930 ppe) l Reference Technical Report NE-837, Rev. 0 Y Acceptance ISf Dop = -1. 68 pen / *T l TSAR / Tech Spec aT s 3.82 pee /'T aT Criteria -
, Reference TS 3.1.E. Technical Report NE-837, Rev. 0 l Design Tolerance is set : /YES . N0 VI Acceptance Criteria is set : M S N0
{ Cossents
- Uncertainty on aTMOD = 0.5 pea /'T (
Reference:
sesorandus from C. T. Snow to E. . Lozito dated June 27, 1980s. 8 1 Prepared By: h. . h41tA Reviewed By: > g st-832 s2C11 Startug Test Report ease s8 or 71 4 L
SURRY POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION' SHEET I Test
Description:
Cntl Bank B Vorth Meas.. Rod Swan Ref. Bank Reference ? roc No /Section: 2-PT 28.ll Sequence Steo No: II ! Bank Positions (Steps) ' RCS Teeperature ('T): 547 Test Power Level (% F.P.): O Conditionsi SDA: 225 SDB: 225 CA: 225 , Other (specify): (Design) l CB: Moving CC: 225 CD: 225 j Below Nuclear tienting III lBankPositions(Steps) l RCS Temperature ('F): 5~V4,f Test Power Level (1 F.P.): O Conditions SDA: 225 SDB: ?25 C.1: 225 other (Specify): (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Perfors.-4: t /6 /9/ O 2. 4/ Z REF
%sured Parameter 1 3 ; Integral Worth of Catl Bank b, (Description) All Other Rods Out IV r Test l hasured Value REF 1
B I 3 I T'1 Fw Results Design Valus REF (Actual Conditions) I B
" IMI f*
Design Value REF (D oign Conditions) I B
- 1337 1 13' PCs Reference Technical Report NE-837, Rev. O If Design Tolerance is exceeded, SNSOC shall e..iuate impact of test result V FSAR/ Tech Spec on safety analysis. SNSOC may specify Acceptance
- bat additional testing be performed.
Criteria Deference VEP-FRD-36A _ i I Das gn Tolerance is set : I YES _ NO VI Acceptance Criteria is met L YES _.NO Comments Prepared By: $1/ TI hMA Reviewed By: NE-852 52Cll Startup Test heport Page 59 of 71
I-SURRY POWER STATION UNIT 2 CYCLE 11. STARTUP PHYSICS TEST REdULTS AND ZYALUATION SHEET I Test
Description:
Critical Boron Concentration - 3 !ank In I Reference l Froc No /Section: 2-PT-28.ll Sequence Step No:
. . II Bank Positions (Steps) lRCSTemperature('F): 547
, Test Power Level (*. F.P. ): 0 l_ Conditionst SDA: 225 SDB: 225 CA: 225 Other (specify): (Design) l CB: O CC: 225 CD: 225 Below Nuclear Heattog III lBankPositions(Steps) RCS Temperature ('F): ( 4 (, . 5" Test ' Power Level (7, F r.J: 0 I Conditions (Actus1) SDA: 225 SDB: 225 CA: 225 CB: O CC: 225 CD: 225 Other (Specify): Below Nuclear Heating Date/ Time Test Performed: (, /4 /9/ Of' ') 02% j l Meas raraeeter 3 I IV j (Description) I (CB )B; Critical Boron Conc - B Bank In
! Measured Value Il4 3 I Test Results Design Value (CBB*
)M PP*
(Actual Cond) Cg= il N 3 ". [ $ P r &
, Design Value
' Prev (Design Cond) t (10 + 133. 7/ laC 3l) ppm CB = 1747 + AC3 l Reference l Technical Report NE-837, Rev. O V FSAR/ Tech Spec Not !pplicable I Acceptance Criteria t Reference lNot Applicable I Design o lerance is set Acceptance "riteria is met
/YES
.f._YES.,__NO
,_NO 4 VI Consents oC3 = -7.31 pcm/ppe Prev M AC B = (CB ) ARO - 1930 _: l9M -(1 So 5 - 4 p/ m I
I Prepared Ly: N' N' I Reviewed By: A i N I I I "'-"' "2 " "'"""" '"' "" " """
SURRY POVER STATION UNIT 2 CYCLE 11. STARTUP PP'"ICS TEST PESULTS AND EVALUATION SHEET I I Reference ! Test D sett,,. ton: HZP Boron Worth Ccef ficent Measurement Prec Nc /Section: 2 PT-28.11 Sequence Ste> No: Bank Positions (Steps) I, RCS Temperature ('T): 547 iI II Test Power Level (% T.P. ): 0 Conditionsi SDA: 225 SDB: 225 CA: 225 Other (specify): (Design) i CB: Moving CC: 225 CD: 225 Below Nuclear Heating I. !!! { Bank Positions (Steps) RCS Temperature ('T): f ys. L' Ter*. Power Level (% T.P.): 0 I Conditions (Actual) SDA: 225 SDB: 225 CA: 225 CB: Moving CC: 225 CD: 225 Other (Specify): Below Nuclear Heating g Date/ Time Test Performed: E & 4 hi % + s o 1 4 2. % Measured Parameter IV (Description) aC B , Boron Werth Coetficient I Results Measured Value aCB* ~ 7 TI F"/rfe Design Value (Actual Conditions) aCB = -7.31 2 0.73 pcm/ppe Design Value (Design Conditions) oCg = -7,31 1 0.73 pcm/ ppm l Reference Technical Report NE-837 Rev. 0
, FSAR/ Tech Spec Not Applicable V ,
I Acceptance Criteria Reference Not Applic ble l VI Comments Design Tolerance is met Acceptance Criteria is met
/
_jYES NO _,__YES _ N0
'I J Prepared By: ji/. ((- " Reviewed By: 'I I ,
eage >1 of >1 g xc.e,2 2c11 etnrtu, 1. t Re,o,t
I - SURRY POVER STATION UNIT 2 CYCLE 11_ STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET E : ' Test Descitption: Cnt! Bank D Wortn Measurement-Roc S ap L Reference Proc No /Section: 2-PT-28.11 Sequence Steo No:
' Bank Posittens (Steps) lRCSTemperature('T):
I Conditionsi II Test - SDA: 225 3DB: 225 CA: 225 Power Lsvtl (% F.P.. Other (specify): 547 O (Design) l CB: Moving CC: 225 CD: Moving Below i,uclear Heating II III Bank Positions (Steps) lRCSTemperature('P): 547,3 Test Power Level (1 F.P.): 0 j Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify): m (Actual) CB: Moving CC: 225 CD: Moving Below Nuclear Heating Date/ Time Test Performed: I i o / co lm c73o Meas Parameter RS (Description) ID ; Int W tch of Cntl Bank D-Rod Swap IV gg (Adj. Meas. Crit. Ref Bank I Test Results
- Measured Value Design Value I
D RS
*MI Position = n o steps)
( Adj. Meas. Crit. Ref Bank (Actual Cond) ID =teso,t P sition = t30 steps) _I R$ Design Value ID = 1048 2 157 pcs (Critical Ref Bank (Design Cond) Position = 158 steps)
! Reference Technicaa Report NE-837 Rev. O, VEP-TRD-36A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on I Acceptance Criteria ;
V FSAR/ Tech Spec safety analysis. SNSOC may specify that additional testing be performed. l Reference VEP-FRD-36A esign Tolerance is set : Z YES NO VI ..:ceptance Criteria is met __,f,YES __, NO I Comments Prepared By: d3 Th~~ L Reviewed By: M O' J
)
NE-i32 S2C11 Startup Test Report Page 62 of 71
.. - . . . . . ~ . - . ,
SURRY' POWER STATION UNIT 2 CYCLE ~11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SNEET
^. . . .
l Test-
Description:
.Catl Bank C Worth Measurement
- Rod Swap-Reference -Proc No /Section: 2 PT 28.11 Sequence Step No:
!! ' Bank Positions (Steps) lRCSTemperature('F): S t.7 Test Power Level (t F.P. ): 0 Conoitions! SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design)' l - CB: Moving CC: Moving CD: 225 Below Nuclear Heating III- kBankPositions(Steps) lRCSTemperature('F): s-+ 7 s Test : Power Level (% F.P.); O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):
.( Actual) CB: Moving CC: Moving CD: 225 Below Nuclear Heating Date/ Time Test Performed:
, a/ohl 1213 Meas Parameter RS (Description) I C ; Int Worth of Cnti Bank C-Rod Swap r < IV g3 (Adj. Meas. Crit. Ref Bank Test' Measured Value I C
- Ohl - (, Position = in steps)
Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) IC = 9 34. 2 Position = ilq steps) i RS
= Design Value IC = 920 t 138 pce (Critical Ref Bank (Design.Cond) Position = 135 steps) l' f Reference Technical Report . NE-837, Rev. O , VEP-FRD-36A I
If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec- safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria - Reference VEP FRD-36A Design Tolerance is set : ,,f,'_YES _ NO VI Acceptance Criteria is met _YES ,N0 Comments Prepared By: m1e S b~U Reviewed By: > r NE-852 S2C11 Startup Test Report Page 63 of 71 O .. , . - . - _ . . - .- _ - . - . . -
SURRY POWE( STATION UNIT 2 CYCLE 11 - STARTUP PHYSICS TEST PESULTS AND EVALUATION SHEET
- [ Test 2escription: Catl Bank A Worth Measureeent-Rod Swap Reference ;
Proc No /Section: 2 PT-28.11 Sequence Step No: AI ' Bank Positions (Steps) : RCS Temperature ('F): 547 Test , Power Level ( F.P.): O Conditionsi SDA: 225 SDB: 225 CA: Moving l Other (specify): g (Design) l CB: Moving CC: 225 CD: 225 l Below Nuclear Heating ig III Bank Positions (Steps) lRCSTempera*.ure('F): s* l. 5 Test Psver Level ( F.P.): 0 I Conditions (Actual) SDA: 225 SDB: 225 CA: Moving Other (Specify): CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed: 'I a /u Rt 1316 1 (g Meas Parameter g3 lg (Description) 14 ; Int Worth of Catl Bank A - Rod Swap I IV g3 ( Adj. Meas. Crit. Ref Bank j Tese Measured Value Ig = ;<.4 6 3 Position = r6 steps) m Resutes Design Value g3 (Adj. Meas. Crit. Ref Bank (Actual Cond) IA = O '35 6 Position = 56 steps) RS Design Value IA = 243 2 100 pcm (Critical Ref Bank (Design Cond) Position = 60 steps) Reference Technical Report NE-837, Rev. O, VEP-FRD-36A I - If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on I V Acceptance Criteria FSAR/ Tech >e c safety analysis. SNSOC may specify that additional testing be performed. Reference VEP-FRD-36A Design Tolerance is eet 4 YES N0 VI Acceptance Criteria is se_t n YES _ N0 Coements - I Prepared By: uIk 2S+' Reviewed By: I g d #
-I xe-s,2 22c11 e ge e. of z:
g tartup T.st eepo,t L
SURRY POWER STATION UNIT 2 CYCLE 11 - STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I fTestDescription: Shutdown Bank B Worth Meas. - Rod Swap Reference j Proc No /Section: 2 PT-28.11 Sequence Stsp No: I II Test Bank Fositions (Steps) Conditions: SDA: 225 SDB:hoving CA: 225 lRCSTemperature('T):
, Power Level (t P.P. ): O Other (specify):
547 (Design) l CB: Moving CC: 225 CD: 225 Below Nuclear Hesting III Bank Positions (Steps) lECSTemperature('F): s*t 7J Test Power Level (! T.P.): O Conditions SDA: 225 SDB: Moving CA: 225 Other (Specify): (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear ;feating I Date/ Time Test Performed: colU)R\ 13'3S" i t
; Meas Parameter ' RS I IV (Description) j ISB; Int Worth of Shutdown Bank B-Rod Swap (Adj. Meas. Crit. Ref Bank g3 I Test Results haasured Value Design Value ISB RS
= JC56. ) Position m is c steps)
(Adj. Mess. Crit, Ref Bank ( Actual Cond) I SB = Position = iSc steps) i t G "19 RS Design Value I SB = 1146 1 172 pcm (Critical Ref Bt.nk (Design Cond) ; Position = 177 steps) Reference Technical Report NE-837 Rev. O, VEP-FRL-36A I I If Design Tolerance is exe.eeded, SNSOC shall evaluate impact of test result on I V Acceptance Criteria FSAR/ Tech Spec safety analycis. SNSOC may specify that additional testing be performed. Reference VEP-FRD-36A i Design Tolerance is not : ,, YES _,,,,NO ! VI Acceptance Criteria is met .,,-(,Y ES _,, ,,,N0 Comments Prepared By: D [4*% Reviewed By: #
,I
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SURRY POWER STATION UNIT 2 CYCLE 11-STARTU' PHYSICS TEST RESULTS AND EVALUATION SHEET I. , Test
Description:
Shutdown Bank A Worth Meas. Rod Swap Reference l Proc No /Section: 2-PT-28.11 Sequence Step No: II Bank Positions (Steps) !RCSTemperacure('T): 547 Test , Power Level (% T.P. ): O Conditions SDA: Moving SDB: 225 CA: 225 l Other (specify): (Design) CB: Moving CC: 225 CD: 225 lBelovNuclearHeating III lBankPositions(Steps) l RCS Temperatur F): % 1. f. Test Power Level (1 T,P.): 0 Conditions SDA: Moving SDB: 225 CA: 225 Other (Specify): I (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating g Date/ Time Test. Performed: E -luDI I42P _ Meas Parameter 3 I (Description) ! g; Int Worth of Shatdown Bank A-Red Swap IV (Adj. Meas. Crit. Ref Bank RS I Test Results Measured Value Destru Value ISA = 8 col RS Position = > steps) (Adj. Maas. Crit. Ref Bank (Actual Cond) ISA = iois 3 Position = y steps) RS Design Value 133 = 1011 t 152 pcm (Critical Ref Bank (Design Cond) Position = 151 steps) I Reference Technical Report NE- U 7 Rev. O, VEP-TRD-36A If Design Tolerance is e xceeded , SNSOC shall ev.iluate impact of test result on I V Acceptance Criteria FSAR/ Tech Spec safety analysis. SNSOC may specify that additional testing be performed. Reference VEP-FRD-36A Design Tolerane.e is met : y_,,YES ,,.__NO VI Acceptance Criteria is met s YES , _,NO Comments s Prepared By: 3be Reviewed By: # b i 1 1 NE-852 S2C11 Startup Test Report Page 66 of 71 I
4 s SURRY POWER STATION UNIT 2 CYCLE 11^ r STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET t I Test
Description:
Total Rod Worth - Rod Swap Reference Proc No /Section: 2 PT 28.11 Sequence Step No: l II Bank Positions (Steps) lRCSTemperature('f): S47 Test , Power Level (t F.P.): O Conditions t SDA:Movir.g SDB: Moving CA: Moving Other (specify): (Design) lCB: Moving CC: Moving CD:Hoving Below Nuclear Heocing III lBankPositions(Steps) lRCSTemperature('F): SW ( Test Power Level (! F.P. ): 0 Conditions lSDA:MoJingSDB:MovingCA: Moving Other (Specify): I (Actual) lCB:tioving CC: Moving CD: Moving Below Nuclear Heating Date/ Time Test Performed: co 10 I 4 t 0 2.H 2. Meas Parameter (Description) ITotal; Int Vorth of All Banks - Rod Swap IV Test Measured Value ITotal
- Results Design Valus (Actual Cond) ITotal "
\ Design Value ITotal = 570S 2 571 pen.
(Design Cond) Reference Technical Report NE-837, Rev. O, VEP-FRD-36A lB If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. I Criteria Reference VEP-FRD-36A Design Tolerance is met : L YES _ NO VI Acceptance Criteria is set A YES N0 Comments , 2 Prepared By: N
-* Reviewed By: /
'D NE-852 S2C11 Startup Test Report Page 67 of 71
q y . SdRRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESITLTS AND EVALUATION SHEET Test Descri:tton: M/D Tlux Map - Low power inference i Proc No / Section: 2 PT-25.2, 2-0P-57 Sequence Steo No: II Bank Positions (Steps) l RCS Temperature ('T):T g t1 Test
'coditionsi Power Level (! T.P.): <. d SDA: 225 SDB: 225 CA: 225 Other (spsesfy)
(Design) j CB : 225 CC :
- CD:
- Must have 2 38 thieble III , Bank Positions (Steps) l RCS Temperature ('T): Tu,xf Test , Power Level (; F.P.): gj,7 7' Conditional SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) l CB : 225 CC . ;z.2.5" CD: /4 /. Diste/ Time Test Performed: 6-$-9/ 1.* /.2. A. .~1. IV
} MAX.REL NUC ENTHAL. TOTALHEATiQUADRANT Mess Parametert ASSY PWR RISE HOT FLUX HOT POWER TILT l (Description) : DIFF CHAN FACT CHAN FACT (IucoRE)
(M P)/P F dH(N) F-Q(T) j W Ye foA Measured Value #~'i E l=7
- f. 435 I o &'5 Test ~ W X #'# 2.2.71 Results . . P= c.91 Design Value j y ['t ' jj (Design Conds)pt s + a.. . ewa l NA NA 5 1.0227 WCAP-7905 WCAP-7905 Reference REY.1 NONE NONE i
REY 1 V [ FSAR/ Tech Speci NONE Acceptance NONE Criteria Reference NONE TS 3.12.B TS 3.12.8 NONE Design Tolorence is set YES .X HO Acceptanca Criteria is set X,.TES HC VI Consents
- as Required MAP
.T Es% L rs s Yb /cA T*Cbb - 8 4 ^! K A7 f-f gg ~7: I W putty pysspcorcg dh o L Rob Prepared By: O2 12[gh Reviewed By: / E' fr I
I NE-852 S2C11 Startup Test Report Page 68 of 71 l
t . l i SURRY POWER STATION UNIT 2 CYCLE 11 STAR rUP PHYSICS TEST RESULTS AND EVALUATION SFEET
- Test Desc:-iption: M/D Flux Mao- At Power Reference i Proc No / Section: 0 PT 25 :, OP-57 Sequence Step No:
;I Bant Positions (Steps)
Test RCS Temperature I'F):Tggy 21 Conditionsi Power Level (1 F.P. ): k -o .So E SDA: 225 SDB: 225 CA: 225 Other (specify) (Destgn) l CB 225 CC : 225 CD:
- Mttet have 2 38 chimbles i
III ant Positions (Steps) B Test l RCS Temperature ('F):'Trep ~ ' Y
! ' Power Laval (:. F.P. ): t e . (, %.3 Conditionst SDA: 225 SDB: 225 CA: 225 Other (Spectfy):
(Actual) l CB : 225 CC . 225 CD: pfug g Date/ Time Test Pen.:ermed: A\ 7f4%l U*.N w
- V Meas Parameter MAX. REL l WC ENTHAL TOTAL HEATI QUADRANT ASSY PVR l RISE HOT l FLUX HOT POVER TILT (Desertpston)
- DIFT lCRANFACTlCHANFACT (M-P)/P ; F-dH(N) F-Q(T) {
w on - C. %
'_ Haasured Value w d o.'
Test 52k t .56 22 I 6' ** Results , qt .9 QM Dastan Value (Design Conds) ;ie..r=. . lygg;'-ll l gg. 'IBO ' i NA NA l , S ' . %24 l..C:f?.7 7 WCAP-7905 Reference jWCAP-7905 l REV.1 NONE NONE REV.1 V i N . o..u..i&;5 ::r'"" FSAR/ Tech Spec: NONE Acceptance l Jg',"*Ef ' "'5 NONE Criteria Reference NONE TS 3,12.B TS 3.12.3 NONE
/ i Design Tolerance is sat : NO Acenptance Critaria is set : YES ,,,,,,,,NO VI Consents
- As Required .'
ll - Prepared By: _ g [ Il4/ Weviewed By: 1/ l NE-852 S2C11 Startup Test Repo:t Page e9 of 71
f SURRY POWER STATION UNIT 2 CYCLE 11 STARTUP PHYSICS TE3T RESULTS AND EVALUATIDN SHEET Test Oescription: M/D Flux Map-At Powar Reference i Proc No / Section: 2-PT-28.2, 2-OP 57 Sequence Step No: i II Banc Pcsitions (Steps) RCS Temperature ('F):T Test RE 21 Conditions Power Level (% F.P.): -$0 SDA: 225 SD3: 225 CA: 225 Other (specify): (Design) l CB 225 CC : 225 CD:
- Must have 2 38 thieblos III : B Test [ ank Pesitions (Steps) RCS Temperature ('F): 7,~y : /
~ Power Level (% F.P.): G 1,8 %
Conditionsu SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actual) CB : 225 CC : 225 CD: 4 Date/ Time Test Performed: IM91 nVM MAX. REL NUCENTRALlTOTALHEAT IV i Mess Paraseter ASSY PVR QUADRANT RISE HOT FLUX HOT l(Description) % DIFF CHAN FACT CHAN FACT POWER TILT (M-P)/P F-dH(N) F-Q(T) ; W1 r o.1 Test Measured Value ag g f,f gg g ") g.77 % laJfL pM Results __ Design Value e sa e- *
- e.. ._
(Design Conds) @ E=Y NA NA 5 1.0216 WCAP-7905 Reference WCAP-7905 REY.1 NONE NONE REV.1 1 V FSAR/ Tech Spec. NONE 0 " *' ' " " NONE Acceptance Criteria Reference NONE TS 3.12.B TS 3.12.B Nf.Kil
/
Design Tolerance is set : /' NO Acceptance Criteria is met - YES . ,_NO VI Comeants
- As Required I
!?
Prepared By: [/ _ Reviewed By. d1)' d_
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NE-852 S2C11 Startup Test Report "R" l
f SURPV POWER STATION UNIT 2 CYCLE il STARTUP Pn .!CS TEST RESULTS AND EVALUATION SHEET I Test
Description:
M/D Flux Map - HTP ARO, Ec. Xe Reference i Proc No / Section: 2 PT-28.2, 2-OP $7 Sequence Step No: II ' Bank Positions (Steps) I I Test RCS Teeperature ('F):T Power Level (; F.P.):95 REF: $ tl Conditions: SDA: 225 SDB: 225 CA: 225 (Design) l Other (specifr): Eq. Xe. CB : 225 CC : 225 CD:
- Must have k 38 thiebles III l RCS Temperaturet 'T): f*"77e /
Test !BanzPositions(Steps) Conditionsi SDA: 225 SDB: 225 CA: 225 Power Level (; T.P.):fco$ other (Specify): (Actual) l CB : 225 CC : 225 CD: pg g Date/ Ties Test Per'orsed: _ ~7bE/ /7 C I MAX. REL I IV Meas Parameter {(Dascription) ASSY PWR
- DIFF (M-P)/P NUC ENTHALITOTAL HEAT l QUADRANT ___
RISE HUT ! FLUX HOT (POWER TILT CHAN TACT ICHAN TACT l T-dH(N) , T-Q(T) j IJ TE M Hessured Value whv ~7e&i
;;,, -% ., i.s s3 i .s% asM Design Value ij (Design Conds) se. . .g ;; a e.eNA
....,.8 NA , s 1.0216
'WCAP-7905 3 Reference REV.1 NONE lWCAP-7905 NONE ; REV.1 V ' '"'
FSAR/ Tech Spec. NONE '""*"' Acceptance NONE Criteria Reference NONE TS 3.12.B TS 3.12.8 NONE
/
I VI Design Tolerance is set Acceptance Criteria is est YES S HO NO I Coseents
- As Required kl n //
[ Prepared by: [ __ Reviewed By: - ' I
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i . I 1 ME-852 S2C11 Startup Test Report Page 71 MM I- __ _ _ _ _ _ _ _ _ - - - - - - - - " ' " ' ^ - - - - - __}}