ML18139A785
ML18139A785 | |
Person / Time | |
---|---|
Site: | Surry |
Issue date: | 10/31/1980 |
From: | Leberstein J, Ross T VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
Shared Package | |
ML18139A784 | List: |
References | |
VEP-FRD-37, NUDOCS 8011040014 | |
Download: ML18139A785 (73) | |
Text
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- I VEP-FRD-37 I
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., Vepco I
I I SURRY UNIT 2, CYCLE 5 I STARTu*p PHYSICS TEST
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Docket# ~o- ~s,
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DEADLINE RETURN DATE Date 1012.91g~f Dssumeirt:i I 'B~~U~TQRJ D9.;C§ f~
I REG.UI.ATORY .DOCKET .Flt[ COPY I RECORDS FACILITY BRANCH*
.I J.
- FUEL RESOURCES DEPARTMENT
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- VI RGlNI A ELECTRIC POWER COMPANY 8 0 11 0 4* 0 tJl'f -~*
I VEP-FRD-37 I
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I SURRY UNIT 2, CYCLE 5 STARTUP PHYSICS TEST REPORT I BY I J. H. LEBERSTIEN T. K. ROSS I
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Approved: Nuclear Fuel Operation Group I Fuel Resources Department Virginia Electric and Power Company Richmond, Virginia I Group October, 1980 I REGULATORY .DOCKET fill COP1.
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I CLASSIFICATION/DISCLAIMER The data, .techniques, information, and conclusions in this report have been I prepared solely for use by the Virginia Electric and Power Company (the Company),
I and they may not be appropriate for use in situations other than those for which they were specifically prepared. The Company therefore makes no claim or I warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY I OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE I 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 I 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 I such written approval shall itself be deemed to incorporate the disclaimers of I liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, I warranty, or strict or absolute liabiiity), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting I from or arising out of the use, authorized or unauthorized, of thi~ report or
~ the data, techniques, information, or conclusions in it.
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,I . ACKNOWLEDGEMENTS I The authors would like to acknowledge the cooperation of the Surry Power Station personnel in performing the tests documented in this report.
I Special thanks are due Messrs. L. J, Curfman, J. I. Kelly, D. Padula, and I' R. H. Blount, Also,. the authors would like to express their gratitude to Dr. E. J. Lozito for his aid and guidance in preparing this report, We would I like to thank Ms. C. E. Bullock for her patience and accurate typing of the text.
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.I TABLE OF CONTENTS I SECTION TITLE Classification/Disclaimer PAGE NO.
i I Acknowledgements ii List of Tables iv I List of Figures
- V I 1 Preface Introduction and Summary vi 1
I 2 Control Rod Drop Time Measurements 8 3 Reactor Coolant System Flow Measurement 13 I 4 Control Rod Bank Worth Measurements . 15 I 5 6
Boron Endpoint and Worth Measurements Temperature Coefficient Measurements 20 24 I 7 Power Distribution Measurements 28 8 References 42 I APPENDIX Startup Physics Test Results and Evaluation Sheets . . . . * * . . * * . . . . .. . .
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I I LIST OF TABLES I TABLE TITLE PAGE NO.
1.1 Chronology of Tests ** 3 I 2.1 Hot Rod Drop Time Summary. 10 1* 3.1 Reactor Coolant System Flow Measurement Summary . 14 4.1 Control Rod Bank Worth Summary 17 I 5.1 Boron Endpoints Summary * * * *
- 22 6.1 Isothermal Temperature Coefficient Summary 25 I 7.1 Incore Flux Map Summary . * * . * * . . * * , 30 I 7.2 Comparison of Measured Power Distribution Parameters With Their Technical Specifications Limit . . * , . , 31 I
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I I LIST OF FIGURES FIGURE TITLE PAGE NO.
I 1.1 Core Loading Map * . * * .. .... .... 4 I 1.2 Assembly ID's and Incore Instrumentation Locations Burnable Poison and Source Assembly Locations 5
6 1.3 I 1.4 Control Rod Locations 7 11 I 2.1 2.2 Typical Rod Drop Trace Rod Drop Time - Hot*Full Flow Conditions. 12 I' 4.1 Bank B Integral Rod Worth - HZP ..** 18 4.2 Bank B Differential Rod Worth - HZP 19 I 5.1 Boron Worth Coefficient . . . * . * *.* 23 Isothermal Temperature Coefficient - HZP, ARO ... . 26 I 6.1 6.2 Isothermal Temperature Coefficient - HZP, B-Bank In 27 I 7.1 Assemblywise Power Distribution - HZP, ARO * * . 32 33 7.2 Assemblywise Power Distribution - HZP, B-Bank In I 7.3 Assemblywise Power Distribution - D-Bank At 1'06 Steps 34 7.4 35 I 7.5 Assemblywise Power _Distribution .,. . I/E Cal. - Flux ijap Assemblywise Power Distribution - I/E Cal, - Flux Map 36.
I 7.6 Assemblywise Power Distribution - I/E Cal. - Flux }!ap 37 7.7 Assemblywise Power Distribution.,... I/E Cal~ - Flux ijap 38 I 7.8 Assemblywise Power Distribution.,... I/E Cal, ~ Flux Map 39.
I 7.9 7.10 Assemblywise Power Distribution - I/E Cal~ - Flu~ Map Assemblywise Power Distribution.,... HFP, Eq, Xenon. , , , .
40 41 I
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I I PREFACE I The .purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 5 I core could be operated safely, and to make an initial evaluation of the expected performance of the core. It is not the intent of this report to discuss the I particular methods of testing or to present the detailed data taken. Standard I test techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at I the Surry Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented includes a brief summary of I each test, a comparison of the test results with design predictions, and an I evaluation of the results.
The Surry 2, Cycle 5 Startup Physics Tests Results and Evaluation I Sheets have been included as an appendix to provide additional information on I the startup test results. Each data sheet provides the following information:
- 1) test identification, 2) test conditions (design), 3) test conditions (actual),
I 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 I format. The design test conditions and design values of the measured parameters I were completed prior to startup physics testing. The entries for the design values were based oµ calculations performed by Vepco's Nuclear Fuel Engineering I 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 preliminary compari-son between measured and predicted test results, thus enabling a quick identi-fication of possible problems occurring during the tests. The appendix to this report contains the final completed and approved version of the Startup Physics Tests Results and Evaluation Sheets.
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I Section 1 I
I INTRODUCTION AND
SUMMARY
I On February 4, 1979, Unit No. 2 of the Surry Power Station was shut-down for its fourth refueling and a steam generator replacement outage. During I this shutdown, 64 of the 157 fuel assemblies in the core were replaced with fresh fuel assemblies. The second cycle core consists of six batches of fuel:
I two once-burned batches from Cycle 4 (Batches 6Al and 6B), one tw:,ice-buined I batch that is carried over from Cycles 3 and 4 (Batch 5A), one~thrice-burned batch that is carried over from Cycles 2, 3 and 4 (Batch 4B2), and two fresh I batches (Batches 7A and 7B). The core loading pattern and the design parameters for each batch are shown in Figure 1.1. The core location of each fuel assembly I is identified in Figure 1.2 together with the incore instrumentation locations.
I Figure 1.3 identifies the location and number of burnable poison rods in the Cycle 5 core. Figure 1.4 identifies the location and number of control rods in I the Cycle 5 core.
On August 14, 1980, at 1208, the fifth cycle core achieved initial I criticality. Following criticality, startup physics tests were performed as I outlined in Table 1.1.
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A summary of the results of these tests follows:
~e drop time of each control rod was confirmed to be within I the 1.8 second limit of the Technical Specifications.
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- 2. The reactor coolant system flow rate was confirmed to be greater I than the minimum limit specified in the Final Safety Analysis I 3.
Report.
3 Individual control rod bank worths for all control rod banks were I measured using the rod swap technique 4
and were .. *found *to be. within
- 13. 2% of thia design predictions. The sum of. the individual c0ntrol .rod
- I bank worths was measured to be.within 3.8% of the design prediction.
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I I These results are within the design tolerance of +15% for indi-vidual bank worths (+10% for the rod swap reference bank worth)
I and the design tolerance of +10% for the sum of the individual I 4.
control rod bank worths.
Critical boron concentrations for two control bank configurations I were measured to be within 43 ppm of the design predictions.
These results are within the design tolerances and also met the I accident analysis acceptance criterion.
I 5. The boron worth coefficient was measured to be within 5.9% of the design prediction, which is within the design tolerance of I +10% and met the accident analysis acceptance criterion.
- 6. Isothermal temperature coefficients for two control bank config-I urations were measured to be within 0.6 pcm/°F of the design I predictions.
8 These results are within the design tolerance of
+3 pcm/ F and also met the accident analysis acceptance criterion.
I 7. Core power distributions for various HZP and at-power conditions were generally within 6% of the predicted power distributions.
I For all maps, the hot channel factors were measured to be within I the limits of the Technical Specifications. Generally, all measurement parameters met their respective design value tolerances.
I All measurement parameters met their respective accident analysis acceptance criteria.
I In summ~ry, all startup physics test results were acceptable.
I Detailed results, .together with specific design tolerances and acceptance criteria for each measurement,* are presented in the appropriate sections of I this report.
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I I Table 1.1 SURRY UNIT 2 - BOL CYCLE 5 PHYSICS TESTS I CHRONOLOGY OF TESTS
-1 Test Date Time Power Reference Procedure I Hot Rod Drops-Hot Full Flow Reactivity Computer Checkout 8-8-80 8-15-80 1748 0040 HSD HZP PT-7.0 PT28.ll(B)
Boron Endpoint - ARO 8-15-80 0358 HZP PT28.ll(C)
I Temperature Coefficient - ARO Flux Map - ARO 8-15-80 8-15-80 0825 1154 HZP HZP PT28.ll(D)
OP-57/PT28.2 Bank :B Worth 8-15-'80 1820 HZP PT28. ll (E)
I Boron Endpoint - B Iri Temperature Coefficient - B Ir.
Flux Map-B In 8-16-80 8-16-80 8-16-80 0428 0601 0842 HZP HZP HZP PT28.ll(C)
PT28.ll(D)
OP-57/PT28.2 Bank D Worth - Rod Swap 8-16-80 1616 HZP PT28. ll (F)
I Bank C Worth - Rod Swap Bank A Worth - Rod Swap 8-16-80 8-16-80 1744 1759 HZP HZP PT28. ll (F)
PT28.ll(F)
Bank SB Worth - Rod Swap 8-16-80 1941 HZP PT28.ll(F)
I Bank SA Worth - Rod Swap Flux Map*,,,_. *D at 106 Steps 8-16-80 8-18-80 2206_
1108 HZP
."'5%
PT28.ll(F)
OP-57/PT28.2 Flux Map - I/E Calibration 8-20-80 1221 "-'42% OP-57/PT28.2 I Flux Map - I/E Calibration Flux Map - I/E Calibration Flux Map - I/E Calibration 8-21-80 8-21-80 8-26-80 0233 2307 1538
'v5 0%
'v61%
"'71%
OP-57/PT28.2 OP-57/PT28.2 OP-57/PT28.2 I Flux Map - I/E Calibration RCS Flow Measurement Flux Map - HFP, Eq. Xenon 9-1-80 9-12-80 9-12/80 1054 1040 1422
'v89%
rvl00%
",100%
OP-57/PT28.2 ST-52 OP-57/PT28.2 I
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I Figure 1.1 I SURRY UNIT 2 - CYCLE 5 CORE LOADING HAP
,I p *N I ~i M L K J l:i G F E D C B A 7B 16Al I I I I I I ( l~ri~Sj O O 16 .18 j
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\ 7B 1-- - 6 j , - - J02 Kll f 1'!03 - 112 - C04 Fll . G02 I - 1 1 6Al I 7B 16.391 o.o I14.12 6BI. 7B 0.0 i
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1 o.o 22.23 ;...- - - - - - - - - - 14
- 1' 1i1:"11J O:~ 1 1t*:.io i-------
I ~Batch
/ 4"- Burnup 3 (10 HWD/HTU)
F09 *K09
~ Previous Location I (Cycles 2,3 or 4)
FUEL ASSB-IBLY DESIGN PARAMETERS oaLcn I Initial Enrichment (w/o U235) 4B2 3.10 3.11 5 6Al 2.91 6B 3.20 7A 3.13 7B 3.41 I I Burnup At BOC-5 (HWD/MTU)
Assembly Type Number Of Assemblies 28,803 17Xl7 1
22,296 15Xl5 16,033 15Xl5 12,008 lSXlS 0
15Xl5 j
0 15Xl5 24 20 48 12 52 I Fuel Rods per Assembly I I
264 204 204 204 204 I! 204 I --- - .
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I Figure 1.2 SURRY UNIT 2 - CYCLES I ~
ASSEMBLY ID's AJ.'o!D INCOF.E INSTRUMENTATION LOCATIONS
-~oo I, pp ~
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T K JT
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I ~ Fuel Assembly I.D. Number l____::f-Indicates Location and Type of Incore Instrumentation I 8 - M/D Q-I @) -
T/C Buth M/D and T/C I 5 I
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Figure 1.3 I SURRY UNIT 2 - CYCLE 5 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS I I. R P N M L K J H. G F E *o C B A I- I 11 I II* I I I I I I 1
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PS 12 12 I
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I.T 2 I I J I 8 16 l ss I 16 8 I I I I
3 I ! I I I I 112 I 116 I I 16 12 l I l l 8 12
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- PS - Primary Source I SS - Secondary Source
- - Depleted Burnable Poison 48 Depleted Burnable Poison Rods I " 688 Fresh Burnable Poison Rods I 6 I
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I Figure 1.4 I .* SURRY ~IT 2 - CYCLE 5 CONTROL ROD LOCATIONS I . RP N :1 L K..J HG I
Ft I. I DCB I
I I I A
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I . 101 0 101 I 2 I . I I I & & I I I
fT I I l 1.01 l 0 I 181 101 1
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8 10H- 6 I
1* l I&! I II lwl !91 l I Mi I l I I
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i iyl l~i l&I I I l&I I I I I I . I . I I I I I I. SA 1 i'
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101 181 101 181 !GI 181 101j-I I ]:J I I I 191 I I I I l"o/1 I I 1--ll I L_I 181 181 I I 181 181 J I '
I I I I l&I /&I Ii II I 101 GI 101 I I I 15 I Function Number of Clusters I Control Bank D Control Bank C Control Bank B Control Bank A 8
8 8
8 Shutdown Bank SB 8 I Shutdown Bank SA 8 I
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I Section 2 I CONTROL ROD DROP TIME MEASUREMENTS I The drop time of each control rod was measured at cold and at hot RCS' I conditions in order to confirm satisfactory operation and to verify that the rod drop times were less than the maximum allowed by the Technical Specifica-I tions. The hot control rod drop time measurements were run with the RCS at hot, full flow conditions (~547°F, ~2235 psig) and are described below.
I The rod drop time measurements were performed by first withdrawing a I rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod. This allows the I rod to drop into the core as it would in a normal plant trip. The data recorded during this test are, the stationary gripper coil voltage, the LVDT (Linear I Variable Differential Transformer) primary coil voltage and a 60Hz timing trace which I are recorded via a visicorder. The rod drop time to the dashpot entry and to the bottom of the dashpot are determined from this data. Figure 2.1 provides an I example of the data that is recorded during a rod drop time measurement.
As shown in Figure 2.1, the initiation of the rod drop is indicated by I the decay of the stationary gripper coil voltage when the stationary gripper
~ coil fuse is removed. A voltage is then induced in the LVDT primary coil as the rod drops. The magnitude of this voltage is a function of the rod velocity.
I When the rod enters the dashpot section of its guide tube, the velocity slows causing a*voltage decrease in the LVDT coil. The LVDT voltage then reaches a I minimum as the rod reaches the bottom of the dashpot. Subsequent variations in
~ the trace are caused by the rod bouncing. This procedure was repeated for each control rod.
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I I The measured drop times for each control ro*d: are recorded *on Figure 2. 2.
The slowest, fastest and average drop times are summarized in Table 2.1.
I Technical Specification 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 1.8 seconds with the RCS at I hot, full flow conditions. All test results met this limit.
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I I Table 2.1 I SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST HOT ROD DROP TIME
SUMMARY
I ROD DROP TIME TO DASHPOT ENTRY I
Average I Slowest Rod Fastest Rod Time I E-11, 1.29 sec. J-9, 1.14 sec. 1.22 sec.
I I ROD DROP TIME TO BOTTOM OF DASHPOT I Slowest Rod Fastest Rod Average Time I E-11, 1.83 sec. G-9, 1.68 sec. 1.76 sec.
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- - - - -* - - - - - - - - - - - *- - -* SURRY UNIT 2 -
Figure 2.1 CYCLE 5 DOL PHYSICS 'l'ES'l' TYPIC/\L ROD DROP 'fHJ\CE
~-- ,~ =t=,~=~~;c~C:::~:.:l:~~t:~1;:r* I
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1
I Figure 2.2 I SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST ROD DROP TIME - ROT FULL FLOW CONDITIONS I
R P N M L K. J H G F E D C B A I I - I --+--l t----t--1~, I _ I ___,I_ _,_____
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D Rod Drop Time to Dashpot Entry (sec.)
Rod Drop Time to Bottom of Dashpot (sec.)
1 I
I 12 I
I I Section 3 I REACTOR COOL.ANT SYSTEM FLOW MEASUREMENT I The reactor coolant flow rate is measured in order to verify that the minimum flow rate requirement is satisfied. The RCS flow rate is determined I using the calorimetric measurement technique. Precision calorimetric data I (i.e., feedwater temperature, feedwater flow, and steam pressure) are obtained in order to accurately determine the secondary-side heat rate. The primary-side I enthalpy rise is determined from the RCS pressure and the temperature increase associated with each RCS loop. The flow for each RCS loop is determined by I establishing a primary-side to secondary-side heat balance. Steam generator I blowdown heat loss, system heat losses, and the power produced by the reactor coolant pumps are taken into account in the heat balance. A reactor coolant I flow measurement was performed at 100% power. This data was analyzed using the RXFLOW5 computer code. A sunnnary of the results for this test is given in I Table 3.1. As shown by this table, the test results demonstrated that the RCS I flow limit was met.
I I
I I
I I
I 13
Table 3.1 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST REACTOR COOLANT SYSTEM FLOW MEASUREMENT
SUMMARY
. Percent Loop A Loop B Loop C Total Flow Minimum Flow Power Flow ( gpm) Flow (gpm) Flow ( gpm) (gpm) Limit* (gpm) 100% 100,665 97,854 100,030 298,549 265,500
- k FSAR Section 4.1.3; Letter from C. M. Stallings (Vepco) to H. R. Denton (NRC) dated May 31, 1979 (Serial No. 388); Letter from C. M. Stallings (Vepco) to E. G. Case (NRC) dated November 16, 1977 (Serial No. 516).
I I Section 4 I CONTROL ROD BANK WORTH MEASUREMENTS I Control rod bank worth measurements were obtained for all control and shutdown banks using the rod swap technique. The first step in the rod swap I procedure was to dilute the most reactive control rod bank (hereafter referred to as the reference bank) into the core and measure its reactivity worth using conventional test techniques. The reactivity changes resulting from the 6
reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference I bank (Control Bank B). At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were I stabilized such that the reactor was critical with the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by I moving the reference bank to its fully inserted position and recording the core I reactivity and moderator temperature. At this point, a rod swap maneuver was performed by withdrawing the reference bank while one of the other control rod I banks (i.e., a test bank) was inserted. The core was kept nominally critical throughout this rod swap and the maneuver was continued until the test bank was I fully inserted and the reference bank was at the position at which the core was I just critical. This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest and was I used to determine the integral reactivity worth of the test bank. Statepoint data (core reactivity, moderator temperature, and the differential worth of I the reference bank) were recorded with the reference bank at the MCP. The rod swap maneuver was then performed in reverse order such that the reference bank I once again was near full insertion and the test bank was once again fully withdrawn I from the core. The rod swap process was then repeated for all of the other control rod banks (control and shutdown).
I 15
I I A summary of the results for these tests is given in Table 4.1. As I shown by this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for all of the I control and shutdown banks were within the design tolerance (+10% for the I reference bank and +15%. for the test banks). The sum of the individual control rod bank worths was measured to be within 3.8% of the design prediction. This I is well within the design tolerance of +10% for the sum of the individual control rod bank worths.
I The integral and differential reactivity worth of the reference bank
~ (Control Bank B) are shown in Figures 4.1 and 4.2, respectively. The design predictions and the measured data are plotted together in order to illustrate I their agreement. In sunnnary, all measured rod worth values were satisfactory.
I I
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- I*'
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I I 16
I I Table 4.1 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I CONTROL ROD BANK WORTH
SUMMARY
I I
MEASURED PREDICTED PERCENT DIFFERENCE BANK WORTH WORTH (M"""~) x 100 (PCM) (PCM) p B-Reference Bank 1284 1225 +4.8 D 1218 1214 +o.3 C 849 850 +0.1 A . 6-50 574 +13 .2 SB 952 969 -1.8 I SA 1159 1059 +9.4 Total Worth 6112 5891 +3.8 I
1*
I I
I I 17
I FJGURE 4.1 SURRY UNIT 2 CYCLE 5 BOL PHYSICS TEST I BANK B INTEGRAL ROD NORTH HZP I* B BANK*HJTH ALL OTHER BANKS OUT PREOJCTEO
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I FIGURE 4.2 I SURRY UNIT 2 BANK B DIFFERENTIAL ROD WORTH CYCLE 5 BOL PHYSICS TEST HZP I S SANK WJTH ALL OTHER BANK5 CUT PREOJCTEO ME/15UREO I
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1280 1300 1320 1340 1360 1380 1400 1420 1440 BORON CONCENTRATION lPPMl
I Section 6 I TEMPERATURE COEFFICIENT MEASUREMENTS The isothermal temperature coefficient measurements were accomplished I by controlling the RCS heat gains/losses with the steam dump valves to the
.I condenser, establishing a constant and uniform heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer. These I measurements were performed at very low power levels in order to minimize the
'i effects of non-uniform nuclear heating, thus, the moderator and fuel were approximately at the same temperature (between 543-549 °F) during these measure-
- 1. ments. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level was maintained constant or slightly increasing during these I measurements.
Isothermal temperature coefficient measurements were performed at I various control rod configurations. For each rod configuration, reactivity I measurem.ents were taken during both RCS heatup and cooldown ramps during which the RCS temperature varied approximately 6°F. Reactivity was determined using I the reactivity computer and was plotted against the RCS temperature on an x-y I recorder. The temperature coefficient was then determined from the slope qf the plotted lines. The x-y recorder plots of reactivity change vs. RCS temperature I for each measurement are shown in Figures 6.1 and 6.2.
The predicted and measured isothermal temperature coefficient values I are compared in Table 6.1. As can be seen from this summary and from the I Startup Physics Test Results and Evaluation Sheets given in the Appendix, all
., measured isothermal temperature coefficient values were within the design tolerance of +3 pcm/°F and met the accident analysis acceptance criterion.
all measured results were satisfactory.
In summary,
,I I 24
Table 6.1 SURRY UNIT 2 - *cYCLE 5 BOL PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
BANK POSITION TEMPERATURE BORON ISOTHERMAL TEMPERATURE COEFFICIENT (STEPS) RANGE CONCENTRATION (PCM/°F)
(OF) (PPM)
. B. HEATUP COOLDOWN AVERAGE PREDICTED DIFFERENCE D (M-P)
N U1 228 209 543-549 14'*4 -2.24 -2.76 -2.50 -3.05 +0.55 21 228 543-549 1303 -5.61 -5.17 -5.39 -5.61 +0.22
I I Figure 6.1 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ISOTHERMAL TEMPERATURE COEFFICIENT I HZP, ARO I
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I I 26
I I Figure 6.2 SURRY UNIT 2 - CYCLES BOL PHYSICS TEST I ISOTHERMAL TEMPERATURE COEFFICIENT I HZP 1 B-BANK IN I
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I 1°F/inch HORTZONTAL SCALE I TEMPERATURE (°F)
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I 27
I I Section 7 I POWER DISTRIBUTION MEASUREMENTS I The core power distributions were measured using the incore movable detector flux mapping system. This system consists of five fission detectors I which traverse fuel assembly instrumentation thimbles in 50 core locations (see Figure 1.2). For each traverse, the detector output is continuously I monitored on a strip chart recorder. The output is also scanned for 61 discrete I axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are then determined by analyzing this data using the Westing-I house computer program, INCORE. 7 INCORE couples the measured flux map data I with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.
I A list of all the flux maps taken during the test program together with a list of the measured values of the important power distribution parame-I ters is given in Table 7.1. The measured power distribution parameter values I are compared with their Technical Specifications limits in Table 7.2.
Maps 1 and 2 were taken at zero power.
Flux These flux maps serve as base case I design checks. Figures 7.1 and 7.2 show the resulting radial power distributions associated with these flux maps. The results of Flux Map 1 indicated a quadrant I power tilt ratio of slightly greater than 2%. However, during this map, the I flux level was low and there was a significant amount of flux drift. It is believed that this contributed to the high tilt indication. Subsequent flux I map results confirmed that the quadrant power tilt ratio was less than 2%.
Flux Maps 4 through 13 were taken over a wide range of power levels and control I rod configurations. These flux maps were taken to check the at-power design predictions and to measure core power distributions at various operating conditions. These maps also provide incore/excore calibration data for the 28
I I nuclear instrumentation system. The radial power distributions for these maps I are given in Figures 7.3 through 7.10. These figures show that the measured relative assembly power values are generally within 6% of the predicted values.
I In conclusion, all power distribution measurement results were considered to be acceptalbe with respect to the design tolerances, the accident I analysis acceptance criteria and the Technical Specification limits. It is I therefore anticipated that the core will continue to operate safely throughout Cycle 5.
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I I
I I
I 29
- - - - - - - *- - - .. - - - - .. - 'l'al>le 7.1 SURRY UNI'l' 2 - CYCLE 5 IIOL PHYSICS TES'J'S INCOllE FLUX MAP SUMMAIIY FT 110'1' -
MAP BANK POSI'flON Q F~II HOT CORE Fz DESCRIPTION MAP PWR (S'l'EPS)
NO. (%) CHANNEL FACTOR* CHANNEL FAC'fOJlH MAX F + QPTRx AXIAL NO.
xy OFFSET OF AXIAL FT N AXIAL (%) tl!Il!BLES n D ASSY. PIN POIN'1' Q ASSY. PIN FAIi POINT Fz Flux Map - ARO l 0 228 216 F06 LK 13 2.48 1106 DE 1.46 14 1.64 1.44 1.023 +35. r2 42 Flux Map - n In 2 0 33/34 228 1109 HG 13 2.lll GOS Ill 1.81 13 1.44 1. 76 1.006 +21.60 50 Flux Map 4XlC ..,5 228 106/107 Kl4 LM 44 2.42 DOS HG 1.55 43 1.51 1.53 -23.87 1,019 47 Flux Map - 5 43 228 170 B06 DE 33 1.99 B06 DE 1.45 32 1.30 1.41 1.011 - .-2.49 50 I/E Calibration Flux Map - 6 50 228 183/184 B06 DE 23 1.91 B06 DE 1.43 23 1.28 1.39 1.009 +3.87 47 I/E Calibration Flux Map - 7 61 228 190 B06 DE 24 1.85 D07 Ill 1.42 23 1.25 1.38 1.008 +2.49 49
'I/E Calibration Flux Map - 9++ 58 228 171 B06 DE 32 1.93 D07 Ill 1.43 32 1.29 1.39 1.011 -1.97 48 1/E Calibration w Flux Map - 11+1+ 71 228 185 B06 DE 33 1.84 B06 DE 1.41 0 33 1.24 1.37 1.005 -1.20 46 1/E Calibration Hux Map - 12 88 228 190 Kl4 KL 23 1. 79 D07 111 1.40 23 1.23 1.34 1.008 +1.26 48 1/E Calibration Flux Map - HFP, 13 100 228 215 ll06 DE 3/i 1.72 D07 Ill 1.39 23 1.17 1.35 1.005 +1.13 49 Eq. Xenon Notes: Hot spot locations are specified by giving assembly locations {e.g. 11-8 is the center-of-core assel)lbly location), followed by the pin location (aenoted by the "Y" coordinate with the fifteen rows of *fuel rods lettered A through k nnd the "x"* coordinate designated in a similar manner). In the "Z" direction the core is divided into 61 axial points starting from the top of the core.
- -FQT includes a total uncertainty of 1.08.
- N FAil includes_ a measurement uncertainty of 1.04
+F is evaluated at the midplane of the core.
xy xQPTR - Quadrant Power Tilt Ratio. This value is the maximum QlfR of the upper and lower halves of the core.
xxMap 3 was aborted,
++Map 8 was a quarter core M/D flux map.
+++Map 10 was a quarter core M/D flux map.
Table 7 .2 SURRY UNIT 2 '- CYCLE 5 BOL PHYSICS TESTS COMPARISON OF MEASURED POWER DISTRIBU'J:ION l'AllAMETERS WI'l'll 'l'l!ElR TECHNICAL SPECIFICATIONS LIMIT T a N N ILOCA ,N ILOCA FQ Hot Channel Factor Fllll Hot Channel Factorb Fl\11 ASSY !lot Channel Factorb FMl ROD Hot Channel Factorb Minimum Margin Mar~in Margin Margin Map Measured Limit (%) Measured Limit (%) Measured Limit (%) Measured Limit (%)
5 1. 99 4.36 54.5 l.45 1. 73 16.2 1.29 3.43 62.4 1. 46 3.61 59.6 6 1. 91 _ 4.27 55.3 1.43 1. 71 16.4 1.28 2.95 56.6 1.43 3.10 53.9 7 1. 85 3.51 47 .2 1.42 1. 67 15.0 1.27 2. ,,2 47.5 1.42 2.54 44.1 9c 1. 93 3.76 47.9 1.43 1.68 14.9 1.28 2.53 1,9. 4 1.43 2.65 46.0 lld 1. 84 3.07 39.4 1.41 *1.64 l/i.O 1.27 2.08 38.9 1.42 2.18 34.9 12 1. 79 2.43 26.3 1.l,O 1.59 ll.9 1.27 1.68 24.4 1.39 1. 76 21.0 13 1. 72 2.18 20.4 1.39 1.55 10.3 1.28 l.l,8 13.5 1.39 1.55 10.3 a The Technical Specifications limit for the heat flux hot channel factor, Factor, FT, is a function of core height, The value for FT listed above is the maximum value of FT in the core. The Technical Specifigations limit listed above is evaluated at the r2ane of maximum FT. The minimum margin Salues listed above are the minimum percent difference between the measured values of Fq(Z) and th~ Technical Specifications limit for each map. All measured F6 hot channel factors include 8% total uncertainty.
b ,,N l
- The measured values for the enthalpy rise hot channel factors, ~Lill' 1*Lill ASS). and FLIU ROD , include 4% measurement uncertainty.
cMap 8 was a quarter core M/D flux map.
d Hap 10 was a quarter core M/D flux map.
I Figure 7.1 I SURRY UNIT 2 CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I HZP, ARO I R F' H M L K J H G E D C B A PREDICTED
- 0.40 0.73 0.40 PP.ED!CTED I MEASURED
- F'CT DIFFEREIICE.
0.39 0.?4
- 0.41
- 0.7S
- 0.40 *
. 2.~. 2.3. 0.7.
l.06 l.13 1.06 0.94
- 0.40
- 0.95 . 1.07, l,14
- l.07. 0.93 . 0.19 .
2.5. 0.3. 1.1
- l.2
- 0.2 * -1.q. 0.1 .
0.39 11EASL1REO
.PCT DlFFf~EHCE.
I o.52 1.01 1.11 1.22 1.~o 1.22
- 0.54 . 1.03. 1.18 . 1.22
- 1.21
- 1.22 . 1.1q ,
2.4
- 2.5
- 1.2 . 0.2.
1.11 0.5
- o.3
- o.~ .
1.01 o.s2 l.03. 0.54 ,
1.1. 3.2 .
3 o.52 a.es 1.14 1.18 1.21 1.10 1.21 1.1~ 1.14 a.ea . o.s2 I 0.39
- o.5o
- o.aa. 1.11. 1.11 . 1.19. 1.oa . 1.22 . 1.21 .
. -5.l , -0.1 , 2.2. -0.l * -l.7. -1.4; 0.6. 2.9, 1.01 l,14 1.23 1.01 1.02 1.20 l.02 1.01 1.11. o.?o . o.55 .
2.6 . 2.7 .* 5.5 ,
1.23 1.14
- 0.37
- 0.96
- l.13. 1.24 . l.00 . 0.97 . 1.16
- 1.02 , 1.03. l.iS
- 1.16
- 1.06 . 0.43 .
1.01 0.3?
5
. -5.l . -5.l . -1.1
- 0.7, -1.3 . -5.0 . -3.3. -0.4 . 2.3. 1.8 . 2,7 , 6.6 . 10.3.
I
- 0.94
- 1.17. 1.18 . 1.01
- 1.23 . l.El . 1.11 , l,Zl
- 1.23 , 1.01 . 1.18 , 1.17. 0.9, .
- 0.94 . 1.17 , 1.17 . 0.99. l.~O , 1.16 . 1.07 , 1.17, 1.21. 1.03 . l.CO . 1.24 . 1.02.
. -0.2 . -0.3 . -0.5. -1.5. -2.4. -3.5 . -2.9. -3.l * -1.2 . E.l . 2.4 . 6.3 . 6.0 .
6 0.40 1.06 1.22 1.21 1.02 1.21 1.09 1.15 1.09 1.21 1.02 1.21 1.22 1.06 0.40 I
- 0.41 . 1.10 , 1.27, 1.21 . 0.99. 1.17. 1.06
- l,li . 1.06 , 1.21 . 1.08
- 1.24 . 1.27. 1.12 , 0.42 ,
- 2.a. 3.3 . 4.l . o.3 . -3.s . -3.o . -2.3 * -2.s . -2.a
- o.,
- 5.o . 2.a . 4.4 . 5.3. 5.3 .
.
- 0,73. 1.13. 1.20 . 1.10. 1.20. 1.11. 1.15. 0,87. 1.15. l.ll. l.ZO . 1.10
- 1.20 , 1.13, 0.73.
, 0.75. 1.16 . 1.23, 1.09 . 1.15. 1.07, 1.13 . 0.86
- 1.15 . 1.14. 1.22 . 1.13. 1.24
- 1.18. 0.77.
7 8
- 2.7 . 2.6
- 2.0 . -0.3 . -4.6 * -3.1 * -2.3. -1.4 . -o.o . 2.8
- l.l . 2.8 , 3.3. 4.4
- 5.0
- I 0.40 1.06 1.22 1.21 1.02 1.21 1.0? 1.15 1.09 1.21 . 1.02 1.21
, 0.41
- 1.09 . 1.24 . 1.19. 1.01 . 1.11. 1.02
- 1.14 . 1.10 . 1.11. 1.01 . 1.22
- 1.24 . 1.10 . o.~2 *
. 2.8. 2.2
- 1.6 . -1.3 . -1.3. -3.4, -5.7. -l,3. 1.0 * ~2-7 J -1.0 . 0.5. 2.2
- 3.2
- 3.3
- 1.22 1.06 0.40 9
. 0.94. 1.17. 1.18 . 1.01. 1.23. 1.21 . 1.11 . 1.21 . 1.23 . 1.01 . 1.18 . 1,17 . 0.94.
I . 0.97. 1.19, 1.14 . 0.98. 1.18, 1.14 . 1.06. 1.18 . 1.21 . 0.99. 1.16
- 1.17. 0,96
- 3.2. 1.6 . -3.o . -3.o . -4.2 . -5.8 . -4.l * -2.0 . -1.7. -1.a . -1.1
- o.4 . 1.8 .
0.39 1.01 1.14 1.23 1.01 1.02 1.20 1.02 1.01 1.23
. 0.41 , l.06
- 1.13 . 1.17. 0,97. 0.99, 1.14. 0.99. 1.00. 1.22
- 1.16 . 1.05. 0,41 .
1.14 1.01 0.39 10 11
. 5.5. 5.5. -1.0 * -5.3. -3.7. -3.7. -5.5. -3.3. -0.5 . -1.3
- 1.3. 4.2. 4,7.
I o.52 a.as 1.14 1.18 1.21 1.10 1.21 1.1a
- o.55. o.89. 1.oa. 1.16
- 1.21. 1.01. 1.1a. 1.11. 1.13. o.92
- 0.57.
- 5.5. 1.J. -5.3. -1.1. -0.1 . -2.1. -2.s. -o.8. -1.0
- 5.o. 9,1
- 1.14 o.a8 o.sz 12
- 0.52. 1.01 , 1.17. 1.22 , 1.20
- 1.22 - 1.17. 1.01
- 0.52
- I
- 0.55
- 0.96
- 1.18. 1.22*. 1.20 , l,25. 1.24. 0.99. 0.57.
.... ,-:-~ .~::.:.:~:\: .. \~;:. :~ ::.;.:-~:~; ;:/:~. :-.-}: r.-~:;~:~.: .. !:~.:
- 0;39. 0.94 . 1.06
- 1.13. 1.06
- o. 14. 0.39.
- 0.41
- 0.99. 1.09. 1.16
- 1.12. 1.00. 0.41
- 13 14
- 5.5, 5,4. 2.8. 3.1. 5.l. 5,7. 5,7.
I STAUOARO DEVIATION
=2.036 0.40 0.73. 0.40
- 0.42
- 0.77. 0.42.
- s.J. s.4. s.a.
AVERAGE
.PCT DIFFERENCE.
- 2,8 15 I MAP NO: S2-5-l DATE: 8/15/80 POWER == 0%
I CONTROL ROD POSITIONS:
D BANK AT 216 STEPS FT= 2.476 Q
N FAH = 1. 462 QPTR:
NW 0.982 I F = 1. 644 z NE* 1.023 A. 0, = +35.921 SW 0.984 I BURNUP == 0 MWD/MTU SE - 1.011 I 32
I Figure 7 .2 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION I HZP , B-BAi.'lK IN I R p H PREDICTED M K J
- 0. 46 H
0 . 86 G
- 0. 46 E D C PREDICTED B
MEASURED , 0.46
- 0.86 , 0.46 , 11EASUPED I ,PCT DIFFEREtlCE, 0.37 0.95
, o.s, o.s
- 0.2 *
. . . . . . ... . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~
l.16 1.2?
, 0.37 , o.,s
- l.16 , 1.29 . 1.16 , 0.94. 0.37 ,
0.2 , 0.3. -o.o . -0.2. :0,3 * -0.4 . 0.7 .
1.16 0.95 0.37
.PCT DIFFERENCE
- I 0.46 0.46 0.86 l,Ol l.22 l,30
, 0,46
- 0.86
- 1.01 , l.22
- 1,28. 1,21, l.Ol
- 0.87. 0.47 .
0.2 , 0.3 . 0.3 * -0,0 , -1,0 . -0,7 . -0.l . l.O . 2,3.
0.74 0.90 0.63 1.14 l.16 1,22 1.14 l.Ot 0.63 0.86 0.10 0.46 0,74 0.46 I
, 0.47, 0.75 , 0.89 , 0.62 . 1.12 . 1.15 . 1.13
- 0.63 . 0.90 . 0.76
- 0.48, 4
. 2.1 . 0.2 * -0.2 * -1.6 , -1.4, -1.4, -0.6 , -0.l , 0.6 . 1.5 , 4.9 ,
0.37 0.86 0.90 l,04 0.92 l.ll 1.39 l.11 0.92 1.04 0.90 0.86 0.37
- o.Ja
- o.a,. o.o,
- 1.01
- o.9o
- 1.01. 1.35 . 1.oa. o.91 . 1.oJ
- o.91 . 0.,1
- o.fto . 5
- 3.5
- 3.3 . -o.5 . -2.6 * -~.4 * -3.4 * -2.9 * -2.2 * -1.6 . -o.a. 1.7. 6.2
- 10.1
- I 0.46
, 0.95, 1.01 . 0.63 , 0.92 . 1,39, l.49. 1.41 , l.49 , l.39. 0.92 . 0.63 , l.01 . 0.95 *
- 0.98 , 1.05. 0.63, 0.90 , 1.35. 1.44 , 1.36 , l.ft4 . 1.33 , 0.92 . 0.64 , 1.06 . 1.02
- 3.5. 3.4. -0.7. -3.0 , -3.0 , -3.4. -3.6 , -3.6 , -4,0 . -0.8
- 1.0
- S,l
- 8.2 .
1.16 1.22 1.14 1.11 1.49 1.45 1.57 1.45 1.49 1.11 1.14 1.22 1.16 0.46 ,
I 0.49 , l,21
- 1.27, 1.15. 1.07, 1.45 , 1.40 , l.SJ . 1.40 , 1.44, l.O?
- 1.16 , 1.28 . 1.23 . 0.49
- 6,9 , 4.6 , 3.5 . 0.7, -3.2 , -3.0 , -2.9. -3.1, -3.0 , -3.4. -1.3
- 2.2 . 4.8 . 6.2 , 6.6,
- 0.86
- 1.29, 1.30 . 1.16 , 1.39, 1,41, 1.57 , 1.21
- 1.57 , 1.41 , 1,39. 1.16 . 1.30
- 1.29 '. 0.86 ,
0.91 , 1.35. 1.35 , 1,17, 1.34, 1.37, 1.53, 1.18 . 1.53. 1.37. l.36 . 1.2~ , 1.36 , l.38 , 0.?4.
6.9
- s.o : 4.o
- o.6 . -3.3. -2.a. -2.a. -Z.4 . -2.a. -3.l . -1.0 . 1.3 . 4.8 . ,.,
- 9.4
- I 0.46 1,16 l,22 1.14 1.11 1.49 1.45 1.57 1.45
, 0.49 , l,22 , 1.27. 1.15 . 1.09 . 1.45. 1.38 . 1.53, 1.41 . 1.44 , 1.09. 1,17. 1,£8. 1.25 , o.sz ,
- 6.9. 5.o . 4.o
- o.5 . -1.a . -z.9. -4.3 . -z.a . -z.1 * -3.3 . -1.a . 3.1 . 4.8
- a.o . 12.s
- 1.49 0.95 1.01 0.63 0.92 l,39 1.49 1.41 1.49 1.39 1.11 0,92 1.14 0.63 l.22 1.01 l.16 0.95 0.46 I
. o.9a
- 1.05
- o.64. o.9o
- 1.35
- 1.,.2 . 1.34. 1.43 . 1.36 . o.92
- o.64. 1.os
- 1.00
- 10 3.9, 3.7, 0.3. -Z.2. -3.l . -4.7. -5.3, -4.0 , -z.z . -0.4 . 1.6 , 3.7 , 6.2
- 0.37 0.86 0.90 1.04 0.92 1.11 1.39 1.11 0.92 1.04 0.90 0.86 0;37
- o.38. o.89. 0,90
- 1.01
- 0.90
- 1.05
- 1.2a. 1.0,
- o.90 . 1.os. Q,92
- o.9o
- o.39. 11 3.9, 3.8. 0.8. -3.0 , -3.2 * -5.l, -7.6 * -5.9 * -Z.7. 0,6 , Z.8 . 4.7, 6,l
- I 0.46 0.74 0.90 0.63 l,14 l.16
- 0.47. 0.75 , 0,87, 0.62, l.10
- 1.11 , 1.10
- 0.63. ~.90
- 0.77, 0.49 ,
3.8 , l,l , *-3.0 , -Z.9, -3,2 , -4.9, -3.6 , -1.3, 0.6 , 3.4, 6.5 ,
1.14 0.63 0.90 0.74 0.46
, 0.46 , 0.86 , 1.01 , 1.22. l.30 , 1.22 , l,01
- 0.86
- 0.46 ,
I
, 0.48. 0.93, 1.04, 1.16. 1.26
- 1.22 , l.02, 0.87, 0.48, 13
. 6.o . a.1
- 2.8 * -3.1 * -l.l * -0.2
- 0;9
- l.6
- 4.6
- 0.37 0.95 1.16 1.29 1.16 0.95 0.37
, 0.40, l.01 , 1,10, 1.30 , 1.18, 0.96 , 0.37, 14
, 8.2 , 6.9 , 1.5
- 0.6
- 1.6 , 1,6 , 0.9 ,
I STANDARO DEVIATION
=2.311 0.46 0.66
, 0.48, 0.69, 0.47,
, 4.8, 3.S, 2.2 ,
0.46 AVERAGE
,PCT DIFFEREIICE,
- 3,0 15 I MAP NO: S2-5-2 CONTROL ROD POSITIONS:
DATE: 8/16/80 FT= 2.809 POWER QPTR:
- e 0%
Q I D BANK AT 228 STEPS N
Ft.H = 1. 806 NW 0.991 B BANK AT 34/33 STEPS F = 1. 440 NE 1. 006 I z A. 0. = +21. 595 SW 0.997 I BURNUP :e O MWD/MTU SE - 1.006 I 33
I Figure 7.3 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST 11 I
ASSEMBLYWISE POWER DISTRIBUTION D-BANK AT 106 STEPS I
I R p H P~EOICTEO HEASUREO H L K J 0,37 II 0.63
- 0.37, O.o3. 0.37.
s 0.37 0 C PREDICTED t1E.4SU1lEO 9 A
.PCT DIFFEREtlCE, 0.5. -o.o , 1.5 , ,PCT DIFFEREIICE.
I o.42 o.97 1.00 o.~o 1.00 o.97
- 0.43. 0.?6 , l.00
- 0.87 , 1.02 . 1.00
- 0.44 .
1.4 , *l,2 , -C,6 * -1,l , 1.3 , 3,1
- 3.7.
o.42 0.58 1.09 1.23 1.22 1.16 1.22 1.23 1.09 0.58 I
- o.se
- l.Z
- 1.10 . 1.22
- 1.21
- 1.15 . 1.22
- 1.25
- 1.12
- o.,o .
1.2 * -0.3. -1.2 . -1.l
- 0.3. 1.9
- J.l
- 4.5.
o.se o.96 1.23 1.23 1.24 1.11
- 1.24 1.23 1.23 o.9& o.sa
- 0.59 , 0.97. 1.24 , 1 .* 2
- 1.22 , 1.10
- 1.24 . 1.24 , 1.,6 , 1.01 . 0.61
- 4 1.1. 1.J
- 1.0 * -o.6 . -1.4. -1.0 * -o.J
- 0.1. 2.e . 4.9 . 6.3 .
I 0.42 l.09 1.23 1.27 0.99 I.02 I.21 1.02 0.99 1.27
- 0.43
- 1.11 , 1.24 , 1.27. 0,98 , 0.99 , 1.18 , l.00 , 0.99 , 1.29 . I.Jl , 1.10 , 0.43 .
2.1
- 2,0
- 0,7 , -0,4. -1,3 * -2.8 * -3.l . -1.9 * -0,2 , 1.2 , 7.0
- 8,1 , 3.I ,
1.23 l,09 0.42 s
I 0.97 l,23 1 .* 3 0.99 , 1.01 1.15 , 1.10 , 1.15, 1.01 . 0.99 1.23 , 1.23 0.97 .
, 0.99, 1.25
- 1.23 . 0.97 , 0.98 . 1.10 , 1.04
- 1.12 , 0.98 , 1.01 . 1.28 , 1.28 , 1.00 . 6 2.1
- 2.l
- 0.4 . -1.9 . -2.8 . -4.0 * -s.o * -2.7 * -2.8
- 1.6 , 3.9
- 4.4 . 3.2 ,
0,37 1.00 1,22 1.2~ 1.02 1.15 1.06 1.15 1.06 1.15 1.02 1.24 1.22 , 1.00 0.37 .
o.3? . 1.04 . 1.24 . 1.,3 . o.oa
- 1.11
- 1.,2 , 1.11 . l.D4
- 1.12 . 1.01 . 1.26 . 1.2s . 1.04 . o.Js .
I 6.8 . 3.5 . 2.0 * -0.7 . -4.1 . *3.8 . -3.6 * -3.3 . -1.6 . -2.5 . -I.O , 1.7 . 2.6 . 3.4 . 3.9 .
i *o: 6; * * *;: ;o ***i: i6 * * *i: ii* **i: ii .. *i: ia ***i: is** *;: ~; ***i: is* **i: ia ***i:; i .. *i: ii* * *i: i6 * * *a: 90 * * *.;: 6; *
- o.67. o.94 . 1.1, . 1.09 . 1.1q . 1.a4 . 1.11 . o.e5 . 1.11 . 1.os , 1.1a . 1.1J . 1.1s
- o.94 . c.68
- ai 6.6
- 4.0 . 2.1 * -i.1 . -~.J * -5.4 . -3.3 , -2.7. -J.6 * -4.6 . -3.2 . 1.3 . 1.1 . 4.1 . a.o
- I 0.)7 1.00 1.22 1.24 1.02 1.15 l.06 1.15 l.06 1.15 l.U2 0.19 . 1.04
- 1,25 . l.Zl
- 0.96 . 1.~9 . 1,02 , 1.10 . 1.02 , l.O~
- 0,98 . l.Z4 . I.ZS , 1.00 . 0,41 .
6.8 . J.9 . 2.4 . -2.s . -,.z . -5.5 * -4.o * -4.0 * -'+.4 . -s.:; * -3.9 . o .. z . 2.1 . 7,3 . lJ.J
- 0.97 1.23 l.ZJ 0.?9 1.01 1,15 l.IO 1,15 1.01 0.?9 I.24 l.~2 , 1.00 . 0.37 ,
l.ZJ , l.23 0.97 .
, 1.00 . l,Z6
- l,ZO , 0.13 , 0.1~
- 1.10 , I.04 . J,09 , 0.?7. 0.97 . I.Z3 . 1.:6 , I.04 ,
I 2.6 . 2.5 , -2.l . -5.6 , -5.I , -4.3. -5.0 , -5.l * -4.0 * *l,S , -0.l
- Z.6
- 6.6 ,
0.42 1.09 l.Z3 1.27 0.99 1,02 1.21
- 1,02 , 0.99 2.s
- 2.s . -2.1 . -s.1 . -J.7. -3.9 . -,.o * -s.2 . -3.l . o.a . z.4
- 4.s . ,.1 .
1.27 . 1,23. l,09
- 0.42 .
- 0,43
- 1.12 . 1.:0 . l.21 , o. 0 S
- o.~a , 1.14 , O.?i , 0.96 . l.Z3
- l.Z6 . 1.14
- 0.45 , 11 I o.sa o.96 1.23 1.23 1.z1 1.11 1.24 1.23
. 0.59 . 0,91 . I.16 , l.?O
- 1.21
- 1.07. I.ZO
- 1.22 . l.c3
- 0.99 . 0,62
- 2.5 . -5.l , -5.1 . -2.7. -2.0 * -4.) , -3.5 . -0.5 ,
. o.5a . 1.09. 1.2J
- 1.22
- 1.16
- 1.22 . 1.23 . 1.0,
- o.s8 .
1.23 0.6 ,
o.?6 2.7 .
o.58 .
7,5
- 12
- 0.62
- 1.1a
- 1.21
- 1.1a
- 1.12
- 1.:2 . 1.24
- 1.11 . 0.60 . 13 I 1.a
- 1.a
- J.4 * -3,l * -4.o * -o.o
- 1.5 . 1.4
- 4.4
- 0.42 0.97 1.00 0.90 1.00 0.97
- 0.45
- 1-04
- 1.03 , 0.91 , 1.03 , 1.00 , 0.43
- 1.1. 7.6
- 2.4. 1.1
- 2.6
- 2.s
- 1.2
- 0.42
-** -~- -
14 I STAHOARO OEYIATIOH
=2.195 0.37 7.3 0.63 0.39, 0.67 S.8 ,
0.37 0.!8 3,5
- AVERAGE
.PCT DIHEREHCE.
- 3.2 15 I MAP NO: S2-5-4 DATE: 8/18/80 POWER == 5%
CONTROL ROD POSITIONS: FT= 2.415 QPTR:
I D BANK AT 107/106 STEPS Q
N F t:.H = 1.545 NW 0.986 I F z
= 1.512 A. 0. = -23.873 NE SW 1.019 0.992 I BURNUP == 0 MWD/HTU SE - 1.003 I 34
I Figure 7.4 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION I I/E CALIBRATION - FLUX MAP I R p N PREDICTED
- M L K
- *0.41 H
0.72 G
0.41 E D C P~EDICTED B A MEASURED
- 0.40 . 0.71 , 0.41
- MEASURED l *.
I ,PCT DIFFERENCE.
0.42 0.95
- -1.l , -1.4. O.l.
1.03 1.04 l.03 0.95 0.42
- 0.41
- 0.94. 1.02 . 1.02 . 1.03. 0.97. 0.42 .
- -2.4. -1.7. -1.5. -1.9 . 0.1 , l.8 . 1.0 .
- PCT DIFFEREllCE.
I
- 0.56
, 0.56 . 1.04 . 1.17. 1.20 . 1.18. 1.20 . 1.17. 1.04 . 0.56 *
- 0.55 . l.03. 1.16 , 1.17. 1.15 , 1.18
- 1.17. 1.04. 0.56 .
- -2.2 * -0.8 . -0.7 . -2.0 . -2.1 . -1.2
- 0.7. 0.3. -0.1
- 0.93. 1.17 1.18 1.20 . 1.10 1.20 . 1.18 1.17 0.93 0.56 3
. 0.56
- 0.92. 1.17. 1.17 . 1.17. l.06 . 1.18. 1.18. 1.17. 0.?4 , 0.59 . 4.
I 0.42
. -0.5 , -0.9. 0.1 * -1.5 * -3.l . -4.0 . -2.2 . -0.6 , 0.1 . 1.5 . 3.9 .
1.04 1.17 1.24 1.01 l.03 1.20 1.03 1.01 1.24 1.17 1.04
- 0.42
- 1.05. 1.16 . 1.22 . 0.99. 0.99. 1,15 . 1.00 . 0.99 . 1,22 . l,22. l.lD . 0.44.
. 0.9 . 0.9 . -0.7. -2.l . -2.l . -3.9. -4.0 . -2.9. -2.3. -1.8 . 4.8 . 6.0 . 5.9 .
0.42 5
I 0.41
. 0.95. 1.17. 1.18. 1.01 . 1.14, 1.18 . 1.11 , 1.18. 1.14 . 1.01 . 1,18. 1.17 , 0.95 .
- 0.96 . 1.18. l,18 . 1.00
- 1.11 , 1.14. 1.00. 1.15. 1.10 . 1.01 . 1.21 . 1.23 . 1.02 .
1.1
- 1.1 . -o.6 . -1.s . -2.5 . -2.9. -3.o . -2.4. -3.7 . -o.3 . 2.4. 5.6 . 6.9 .
1.03 1.20 1.20 1.03 1.18 1.09 1.16 1.09 1,18 1,03 1.20 1.20 1.03 0.41 6
0.42 . 1.04 . 1.21
- 1.19. 1.00
- 1.15 . l.07 , 1.14 . l.08. 1.15
- 1.03. 1.23. 1.24 . 1.10 . 0.43. 1.
I 3.1 . 1.0 , 0.8 . -1.2 . -3.l , -2.3. -1.4 , -1.6 , -1.0 . -2.3. -0.7. 2.2 , 3.5 . 6.6 , 5.~ ,
0.72 . 1.04 , 1.18. 1.10. 1.20 . 1.11 . 1.16 , 0.89 , 1.16 , 1.11. 1.20 , 1.10 . 1.18 . 1.04 , 0.72 ,
0.74 . 1.05 . 1.17
- 1.08 . 1.15 , 1.08 . 1.15
- 0.89 . 1.14 . 1.08 . 1.19 . 1.12 . 1.20
- 1.06 . 0.75 .
3.1. o.8. -a.a. -2.1 . -4.4. -3.2 . -1.1 * -0.1. -1.5 * -2.5 . -1.2 . 1.8 . 1.9 . 2.4 . s.o
- a*
I
- 0.41 , 1.03 . 1.20 . 1.20 . 1.03. 1.18 . 1.09 . 1.16
- 1.09 . 1.18. 1.03 . 1.20 . 1.20 . 1.03 , 0,41.
0.42 , 1.06
- 1.22 , l,19 . 1.00
- 1.13. 1.04. 1.13. 1.07 , l.J5. 1.01 . 1.20 . 1.22 . 1.07. 0.43.
3.1 . 2.3. 1.8 . -1.3 . -3.4 . -4.0 . -4.5, -2.3. -1.3. -2.4. -2.0
- 0.1 . 1.6 . 3.7. 5,9.
0.95 1.17 l,18 1.01 1.14 1.18 1.11 1.18 1.14 1.01 1.18 1.17 Q.95
, 1.00
- 1.22. 1.19. 0.98. 1.10 , 1.12 . 1.07 , 1.15. 1.12 , 1.00 , 1,18 . 1.18 , 0.99, 10' I
- 4.7. 4.6 , 0.2 . -3.2 , -4.0 , -4.5. -3.4. -2.5. -2.2 , -1.2 . -0.5, 1.6 , 4.1 .
, 0.42 , 1.04 . 1.17, 1.24 . 1.01
- 1.03 , 1.20 , 1.03, 1.01 . 1.24. 1.17, 1.04 . 0.42 .
- 0.43. 1.07. 1.17. 1.20 , 0.99. 1.00 , 1.16 . 1.00
- 0.99 . 1.24. 1.18 . 1.06
- 0.43 .
J,Q
- 2.? . 0.3. -3.2 , -2.6 , -2,7 , -3.5. -3.6 * -2.8. -o.o , 1.0
- 2.1 , 3.4 ,
ll I 0.56 0.93 l,17 l,18 1.20 , 1.10 1.20 1,16. 1.17 0.93 0.56
, 0.57. 0.92 , 1.13, l.17 , 1.20
- l.08. 1.16. l,l?. 1.18, 0.95 , 0.58 ,
- 1.3. -o.5. -3.2 * -1.1. -o.5. -2.5. -1.9. 0.2 , o.8. 2.0
- 2.a *
, 0.56 , 1.04. 1.17, 1.20 . 1,18, 1.20 . 1.17, l.04 , 0.56 .
12
, 0.58, l,06
- 1.18. 1.18 , 1.14. 1.21 , 1.21, 1.07, 0.58, 13 I
- 1.?. 2.1. 1.s. -1.9. -3.o
- o.6
- 3.4. 2.9. 2.4 *
- o.42. o.95. 1.03. 1.04. 1.03. o.?s. o.42 *
, 0.43. 0,99, 1.05 , 1.04. 1.06
- 0,98, 0,43 *
- 2.7, 3.5, 1.1 . 0.6
- 2.0 , 2.9, 3.5.
14 I STAHDARO DEVIATION
=l.462 0.41 0.72 0.41
, 0.43 . 0.74. 0.42,
, 4.4 , 3.7
- 2,6 ,
AVERAGE
.PCT DIFFERENCE.
- 2.3 15 I MAP NO: S2-5-5 CONTROL ROD POSITIONS:
DATE: 8/20/80 FT=l.985 POWER"' 43%
QPTR:
Q I D BANK AT 170 STEPS N F tiH - 1.-446 NW 0.989 F = 1.299 NE 1.011 I z A. 0. = -2.494 SW 0.997 I BURNUP"' 10 MWD/MTU SE - 1. 003 I 35
I Figure 7.5 I SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I I/E CALIBRATION - FLUX MAP I R p H PREDICTED M K J 0.41 H
0.72 G
0.41 D C PREDICTED 8 A MUSUPEO
- 0.42
- 0.73
- 0.42
- MEASURED I .PCT DIFFERENCE, 0,42 1.6 . 1.3 . 1.s
- 0.95 . 1.04 1.06 1.04 0.95 0.42
- 0.41. 0.95
- l.04 , l.05 , l.04 , 0.96
- 0.42 *
. -1.1 . 0.4 ** -0.l * -0.7, 0.3 . l.l . 1.2 .
,PCT DIFFEP.EHCE, I 0.56 0.56 1.03 1,16 1.20 l.18 l,ZO 1.11 1.03 O.S6
, O.S6 . l.03. 1.17, 1.20 . 1.15. 1.18 . l.lb , l.C4 . 0,57 *
, *l.O , O.l
- 0.7 , -0.l , -2.3 , *l.3 * -0.2 , 0.5 , 1.4 ,
0.92 l.16 1.18 1.20 l.10 l,20 , l.18 l.16 0.92 O.S6
- o.57. o.92 . 1.11. 1.11. 1.19. 1.oa. 1.1a
- 1.16 . 1.16
- o.93 . o.ss . 4 I 0.42 l.O , -0.2. 0.4, *0.6 * -1.~. -1.6 * -2.0 . -1.6 . -0.3 . l.l . 3.2 .
1.03 1.16 1.24 1.02 l.03 1.20 1.03 1.0[ 1.24 1.16 1.03 0.42
- 0.43 , 1.06 , 1.16 , 1.21
- 1,00 , 1.01 , 1.18 , 1.01 , 0.99 , 1.22 , l.JQ
- 1.07. 0.44 .
2.6 , 2.6 , -o.s. -2,7, -l.8, -2.0 * -2.0 , -2.5 , -2.6 , -1.7 . 2,2 , 4.l , 5.3 ,
5 I 0.41 0.95 1.16 1.18 1.02 1.16 1.18 1.11 1.18 1.16 1.02 l,18 1.16
- 0.98. l.~9. 1.18. 0.99 . 1.13. 1.16
- l.09 , l.15 . l.ll , 1.01 . 1.20 , 1.21 . 1.00 .
2.7. 2,6 , -0.4 , -z.s , -2.7 , -2.2 , -2.l , -2,Q , -4.6 , -0.8. 1.4 , 4.1 , 5.7, 1.04 1.20 1.20 l.03 1.18 1.09 1.16 1.0? 1.18 1.03 1.20 1.20 0.95 1.04 0.41 0.42 , l.06 , 1.22
- 1.20
- 1.00 . l.15. 1.07. 1.13. 1.06 , l,14 . l.03 . l.[3 . l.24 , l.10 . 0.44 , 7 I 2.9. 1.9. 2.2 . -0.4. -2.9 . -2.b , -2,l , -2.2 . -2,5 , -3.3 . -0.2
- 2.2 , 3.3. 5.7 . 6.2
- 0.72 1.06 1.18 1.10 l.20 1.11 1.16 0.89 1.16 l.ll 1.20 l.10 1.18 1.06 o.74 . 1.01. 1.19. 1.09. 1.16 , 1.os. 1.14. a.ea . 1.15. 1.10
- 1.21
- 1.12
- 1.*o . 1.11 . o.78
- 2.7, 1.4 , 0.4, -0.7. -,.2 * -2.4 * -2.l , -1.5 . -1,2 * -1.1 . 0.7, 1.9, 1.9 . 4.7, 7.2
- 0.72 8
I 0.41 1.04 1.20 1.20 1.03 1.18 1.09 1.16 1.09 l.18 1.03 1.20 1.20 2.9 , l.9, !*3 , -0.5. -1.4, -2.1 , -2.l , -0.8, -0.3 , -0.9 , -0.4 , 0.8, l.4 . 4.4 , 7,5, 0.95 1.16 1.18 1.02 1.16 1.18 l.ll 1.18 , l,16 1.02 1.18 1.16 l.04 0,95 0,41 0,42 , l.O~
- 1.21 , l.l?, l,02 , 1.16 , 1.07 , l,15 , l.09 . l.17 . 1.03 , 1.21 , 1,22
- 1.08. 0.44 , 9
. 0.97 , 1.19. 1.18. 0.99
- 1.13 , l,15 . 1.08. l.16 , 1.14 , 1.01
- I.la. 1.18. 0,98 . 10
- I 2.5 , Z.5. -0.4. -2,7. *2.7 , -2.4 * -2.5. -1,7 ~-l.b . -0.?. 0.1
- 1.3. 3.0 .
0.42 1.03 1,16 1.24 1.02 l.03 1.20 I.OJ 1.02 1.24 1.16 1.03
, 0.42
- 1.05. 1.15. 1.19. 0,99. 1.01 , 1.15 , 1.00 , l.CO , 1.22 , l,17
- l.06 , 0.43 ,
1.7 . 1.7. -0.9 . -4.4 . *2,4 , -2.l , -3,8 , -3.0 , -1.i * -1.3
- 1.0
- 2,6
- 3,1
- 0,42 ll I 0.56 0.92 1.16 1.18 1.20 1.10 1.20 1.18 1.16 0.92
- 0.57. 0.91 . 1.11 , I.lb
- 1.20 . l.07. 1.13 , l.18
- 1.17. 0.94 . 0.58.
0.56 l.O * *l,l , -4.4 , *l,5 , *0,4 * -2,4 * *l.4 , 0,3 , 0.5
- 2.3
- 4.0
- 0.56 1.03 1.16 1.20 1.18 1.20 1.16 1.03 0.56
).2
, 0.57. 1.04
- 1.17. l,18 , 1.15 . 1.21
- l.20 , L.06
- 0.58 ,
I 13 l.l , 1.2
- 0.8 , -1.4. -2.2. l.l
- 3.3 , 2.9. 3.l *
, 0,42 , 0,95 l,04 , 1.06 1,04 0.95 0.42
, 0.42
- 0.98. 1.06
- 1.07. l,06 , 0.98 , 0.43. 14.
1,2
- 3.3. 2.5. l.3. 2.5 , 3,1
- 3.3.
I STA!lO~RO DEVIATIO!l
=l. 427 0.41 0.72 0.41
, 0.44 , 0.76
- 0.42 ,
6.0 , 4,7. 3.0
- AVERAGE
.PCT DIFFEREHCE.
= 2.0 15 I MAP NO: S2-5-6 CONTROL ROD POSITIONS:
DATE: 8/21/80 FT = 1. 909 POWER= 50%
QPTR:
Q I D BANK AT 184/183 STEPS N
F~H = 1. 426 NW 0.994 F = 1.281 NE 1.000 I z A. 0. = +3.873 SW 0.997 I BURNUP = 25 MWD/MTU SE - 1.009 I 36
I Figure 7.6 I SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I I/E CALIBRATION - FLUX MAP I p H PREDICTED H L K 0.41 H
0.73 G
0.41 u
PllECICTED H.EASUREO , 0.41 , 0,73. 0.41
- t1EASUREO I
,FCT DIFFERENCE. * -o.a. -o.a. -0.2 * ,PCT DIFFEREHCE
- o.41 o.95 1.04 1.os 1.u .. *** o.95 o.41
- o.41 . o.9,, . 1.0::s
- 1.00
- 1.04
- o.. 95 . 0.42 .
- -0.2 * -1.0 . -1.5 * -1.1. -o.a . o.4 . o.7.
I 0.56 l.OZ l,16 l.20 1.18 1.20 l,16 l.02
, 0.56
- l.03 . 1.15 , 1.18, 1.15 , 1.18, 1.15
- 1.03 , 0.56 ,
, -0.l , 0.4, -0.2 . -1.3 , -2.7, -1.6 . -0.3 , 0.4 . l.3 .
0.56
- 0.56 , 0,91 , l.lS , l.la , 1.20 , 1,10
- 1.20
- 1.18 . l.15
- 0.9l . 0.56 ,
3
, 0.56 . 0.91 , 1.16 , l,17. 1.18 , 1.08 . 1.18 , 1.16 , 1.15 , 0,92 , 0.57 , 4 I 0.41 0,6 , -0.2 , 0.2 . -0,9 . -1.7 , -2,l * -1.9 , -1,2 , -0.2 , 0.3 , 3.0 ,
1.02 1.15 1.24 1.02 1.03 1.20 1.03 1.02 1.24 , 1.15
, 0.42 , 1.04 , 1.15 , 1.21 , l.00 , 1.02 , 1.18. 1.01 , l.00 , 1.22 , 1.17 , 1.06 . 0.44 .
1.2 . 1.2 * -a.a. -2.5 * -1.s . -1.4 . -i.7. -1.a . -l.9. -L.4 ~. l.6
- 3.9 . s.7 .
1.02 , 0.41 5
I 0.41 o.95 1.04 1.16 1.20 1.1a 1.20 1.02 1.03 1.1a l,19 1.19 1.09 1.11 1.16 1.19 1.09 1.1a 1.19 1.02 1.03 1.1a . 1.16 . o.95
. 0.96 , 1.17 , 1.17, l,00 , 1.16 , 1.17 , 1.10 , 1.17 ~ 1,15 , l.Ol , l,19 ,-1,20 , 1.00 ,
1.2 . 1.1 . -o.a . -1.9 . -1.9. -1.2 * -1.4 . -1.1 . -3.o . -o.4 . 1.~ . J.6
- s.o .
1.20 1.20 1.04 0.41
, 0.43 , 1.06 , 1.21 . 1.19 . 1.01 , l,17 . 1.08, 1.15 , 1.08 , 1.17 , 1.04 . 1.22 , 1.23 . 1.08 . 0.43 . 7 I 2.a
- 1.0 . 0.1 . -a.a . -2.::s * -1.6 * -o.6 . -o.9 . -o.9 . -1.1. o.5 . z.z . 2.6
- J.o . J.5
- 0.73 1.08 1.18 1.10 1.20 1.11 1.16 0.89 1.16 1.11 1.20 1.10 1.18
. 0.75 , l,09. 1.18 , l.09 , 1.17, l,09 , 1.15 , 0.89 , 1.16 , l.ll , l.~l , 1.12 . 1.:0 , 1.10 . 0.77 ,
1.08 , 0.73 2,7 . 0.9 . -0.2 , -1.0 * -2.7 . -1.7. -0.5 , -0.2 , -0.l , -0.2
- 1.0 . l.7 , 1.6 , 2.0 . 4.3 ,
I 0,41 1.04 1.20 l.ZO 1,03 1.19 l.O? 1,16 l.09 1.19 l,C3 l.ZO l.ZO
- 0,43 , 1.C6 , 1.21 , l.19 . 1.02 , 1.17 , 1.07, l,16 , l.09 , 1.18 . l.03. l.ZO . 1.21 , 1.08 . 0.44.,
z.a . 1.a
- 1.2 . -o.4 . -1.1 * -1.1 . -1.1 * -o.3
- o.4 * -o.3 * -o.3 . o.3 . t.4 . 3,4
- 6.1*.
, 0.95 1.16 1.18 1.02 l.18 1.19 , l.ll 1.19 , 1.18 1.02 1.18 l.04 1,1? , 0.95 ,
0.41
. 0.97 , 1,19 , 1.18 , l.00 , 1.15 . l,16 , 1.09 , 1.17 , 1.17, 1.01 . 1.17 . 1.17 , 0.98 . *10 I 2.a . ~.1 . -0.1 . -2.2 * -2.2 . -z.o . -2.1 . -1.1 * -1.0 * -o.a . -o.4
- 1.~
- z.9 .
0,41 1.02 l.15 , l.24 l.02 l.03 l.20 l.03 l.O:? , l.24 l.15 l.OZ ** 0.41
- o.~2
- 1.04 . 1.1s,. 1.19
- 0,99
- 1.01
- 1.1s . 1.01
- 1.01 . 1.22
- 1.16 . 1.04
- o.42
- ll 2.0 , 2.0 . -0.5 , -3.7, -2.3 * -2.2 , -3.7 . -2.6 * -1.l * **l.l , 0.6 . l.9 , 2,5 ,
I 0.56 0,91 1.15 l,18 1.20 1.10 1.20 1.18 l.15 0.91
, 0.56
- 0,91
- 1.11 , 1.16 , l,18 , 1.07, 1.16 , 1.18 , l,16 , 0.93 , 0,57 ,
l,3 * -o.7 * -,.7. -1.e * -1.2 * -2.a. -1.5
- 0.4
- o.6 . 2.1
- 2.e.
0.56 0.56 1.02 1.16 1.20 1.1e 1.20 . 1.16 1.02 o.5~
I
, 0,57 , l,05 , 1.17 , l,17. l.15
- 1.20 , 1.19 , l.05 , 0.57, 13 2,0 , 2,6 , l,l , -2,2 , -3.0 , O.l.. 2,7. 2.7
- 2.5
- 0.41 0.95 l.04 1.08 1.04 0.9~ 0.41
, 0,43 , 0.99, l,06 , 1.08, 1.05 , 0.97, 0.43 , , 14 2.a . 4.o
- 1.a
- 0.2
- o.a
- 2.0 . 2.9
- I STMIOARO DEVIATION
=l,191 0.41 5.4 .
0.73
, 0,44 , 0.76 3.6 0,41*,.
0.42
- l. l AVERAGE
,PCT DIFFERENCE,
= l, 7 15 I MAP NO: S2-5-7 DATE: 8/21/80 POWER "' 61%
CONTROL ROD POSITIONS: FT = 1.854 QPTR:
I D BANK AT 190 STEPS Q
N F.tiH = 1.416 NW 0.993 I Fz = 1. 252 A. 0. = +2.493 NE SW 1.000 0.999 I BURNUP "' 30 MWD /MTU SE - 1.008 I 37
I Figure 7.7 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION I I/E CALIBRATION - FLUX MAP I R p PREDICTED MEASURED H L K 0.41 H
0.72 G
0.41
, 0.40 , 0.7l , 0.41 ,
0 C PP.EOICTEO tlEASUREO B
,!'CT DIFFERENCE. , -1.4. -l.4. -0.4 , .PCT OIFFEREHCE, I 0.42 0.95 l.04 l.05 1.04 0.95 0.42
- 0.4Z . 0.94. 1.02
- l.03 , l.03 . 0.96
- 0.42 *
- -0.4 * -1.5 , -1.8 , -2.0 , -0.7 , l,O , l.O ,
0.56 1.03 l.16 1.20 l.18 1.20 1.16 1.03 0,56 I 0.56
. o.s1.
, 0.56 , 1.04
- 1.16 . 1.18. l.15 . l.18. 1.17. 1.04 , 0.57 ,
- -o.3
- 0.2 * -o.5. -1.a. -2.7. -1.b
- o.J . o.6 . 1.1
- 0.92 1.16 l,18 l.20 l.10 1.20 1.18 1.16 0.92 0.56 o.92
- 1.11. 1.11
- 1.11. 1.01 . 1.18
- 1.18 . 1.11 . o.94
- o.sa
- 3 4"
0.1. -o.J
- o.z . -1.z * -2.5 * -3.3 .--z.2 * -o.s. o.6 . 1.6
- 3.6 .
I 0,42 1.03 l.16 l.Z~ 1.01 1.03 1,20 1.03 1.01 1.24 1.16 l.OJ
, 0.42 . 1.05 , 1.15, 1.21 , 0,99 , 1.01 , 1.17, 1.01 . l,00 , 1.24 , 1.20 , 1.08 , 0.44 .
1.6 , l,6 . -0.9 * -2.7 . -2.l . -2.4. -2.9 . -2.6 * -1.6 * -0.4 , 3.0 . 4., . 6.2 .
0.42 5_
I 0.95 1.16 1.18 l.Ol l.lS 1.18 l.ll l.18 l.15 l.Ol 1.18 l.16 0.95
, 0.97 , l.18 . 1.17, 0,98 , l.12
- 1.15 , 1.08
- 1.15
- 1.11 . 1.01 , l.Zl , l.:c . 1.00 , 6 l.4
- 1.4. -1.l . -3.0 . -2.7. -2.Z , -2.5. -2.5 . -3.9 , -0.0 . 2.3 , 4.4 . 5.6 ,
0,41 l.04 l.20 l.ZO 1.03 1.18 1.09 1,16 1,09 1.18 l.03 1.20 1.20 1.04 O.~l
- 0.42
- 1.05 . 1.21 , 1.19
- 1.00
- 1.15
- 1.07. 1.14 , 1.07. l.l5 . 1.04 . 1,24 , 1.23 . 1.08 , 0.4Z .
I 2.6 , 1,6 , 1.2 . -0.9 , -3.5 * -z.6 , -1.5 * -1.6 * -1.3 . -2,l . 0.4. 2.7 , 2,9 . 4,3 . J.7 ,
0.72 1.05 1.18 1.10 1.20 1.11 1.16 0.89 1.16 l.ll 1.20 1.10 1.18 1.05 0.72
- 0.1~ . 1.06 . 1.11 . 1.09
- 1.16 . 1.08 . ,.14
- o.a9
- 1.15 . 1.10
- 1.21 . 1.1J . 1.to . 1.01 . o.,s . 8 Z.5 , 1.7 . 1.1 . -0.9 , -3.7. -Z.6 , -1.3 . -0.7, -0.S * -0.7. 0.9 . Z.2 . 1.9 . 1.9. 4.5
- I 0.41
. o.*z ,
l.04 1.2~ 1.20 l.03 1.18 1.09 l,l6 l.09 l.18 1.03 1.20 1.20 l.04 1.06 . l.Z3 . 1.20 , 1.01 , 1,15 , 1.07. 1.16 . 1.09. 1.17, 1.03 , 1.21 , l.ZZ . l,07 . 0.44 .
2.6 , Z.5. Z.3 . -o.4 * -1.9. -2.6 * *1,4
- 0.0 * -o.z * -1.l , -0.6
- 0.8 . 1.7 . J.6 , 6.4 ,
o.os l,16 1.18 1.01 l.15 1.18 1.11 1.18 l.15 1.01 1.18 1.16 0.?5 0.41
- o.98
- 1.20 . 1.1a
- o.9? . t.12
- 1.1J . 1.oa . 1.11
- 1.13
- 1.01 . 1.1a . 1.18 . o.98
- 10 ~
I 3.5 , J.4 . O.l . -Z.6 . -Z.7. -4.3 * -Z.6 , -l.6 , -l.5 . -1.B . 0.1 , 1.6 , 3.4
- 0.4Z 1.03 1.16 l.Z4 l.Ol 1.03 l,ZO l.03 l,01 1.24 1.16 l,03
, 0.43. l.06 , l.16 , 1.20 . 0,99 . 1.01 . 1.15 . 1.00 , l.00 , 1.23 . 1.18 , l.06
- 0.43 ,
2.4 , 2.4 . -0.3 , -J.7, -2.3 . -2.3 . -3.9 . -Z.9. -1,6 , -0.8 . l.Z . 2.7, 3.3 ,
0.42 11.
I 0.56 0.92 1.16 1.18 1.20 1.10 1.ZO 1.18 1.16 0.92 0.56
- o.57. o.92
- 1.12
- 1.16 . 1.11
- 1.01
- 1.19 . 1.19 , 1.1a . o.95
- o.sa.
l.3 , -0.6 , -3.7. -1.6 , -0.?, -2,7, -l.3 , 0.6 , l,0 , 2,7. 3.8.
, 0.56 , 1.03 . l.16 , 1.20 , l,18 , l,20 . l.16 , l.03 , 0.56 ,
lZ
, 0.58. l.07 , l.18 , :.17. l.15 , 1.20
- 1.21
- 1.07. 0.58 ,
I 2.5
- 3.6
- l.7 * -1.9, -2.9 , 0.4. 3.6 , 3.5
- 3.3 .
o.~2
- o.95 1.04 1.05 1.04 o.95 o.42
, 0.43, 0,99 , 1.05 , 1.05 , 1.04
- 0.97, 0.43 ,
3.6
- 4.2 , 1.5 , o.o , 0.7. 2.3
- 3.8 ,
I STAHOAP.O OEVIATIOH
- 1.319 0,41 0.72 0,41
- 0.43, 0.74 , 0.41 *
, 4,8. 3,2
- 0.8,
.I.VERAGE
,PCT OIFFEREHCE,
= 2.0 15 I MAP NO: S2-5-9 DATE: 8/24/80 POWER = 58%
CONTROL ROD POSITIONS: FT = 1.933 QPTR:
Q I D BANK AT 171 STEPS N
Ft,H = 1.429 NW 0.985
= 1. 291 NE 1.004 I F z
A. o. = -1. 970 SW 1.000 I BURl.UP = 65 MWD/MTU SE - 1.0ll I 38
I Figure 7.8 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION - FLUX MAP I
I H P'REDICTEO MEASURED n L J 0.41 11 0.73 0.41
- 0.41
- 0.73. 0.41
- r PREDICTED MEASURED
" A l
- PCT DIFFERENCE.
- 0.4. 0.3. 0.4 * .PCT DIFFEREUCE
- I 0.41 0.95 1.04 1.07 1.04 0.95 0.41
. 0.41
- 0.95
- 1.03. 1.0*
- 1.04. 0.95 . 0.42 .
- -0.1 . -o.z * -0.9. -1.3. -0.6
- 0.3 . 0.9.
2 0.56 1.02 l.16 l.ZO 1.18 1.20 1.16 1.02 0.56 I 0.56
. 0.56
- 1.02
- 1.16
- 1.19. 1.15. 1.18 . 1.16 , 1.04 . 0.57 .
- -0.2 . -0.2 * -o.z * -0.7 . -2.7. -1.2 . 0.5 . l.l . l.9
- 0.92 1.16 1.18 1.20 1.10 1.20 1.18 1.16 0.92
- 0.56 . 0.91 . 1.13
- 1.16
- 1.18. 1.08
- 1.19 . 1.18 . 1.16 . 0.93 . 0.58
- 0.56
- 1.0 * -0.6 . -2.l * -l.5 . -l.3 . -1.6 * -1.l
- 0.6 . 0.7. 1.2 . 3.3
- I 0.41 1.02 1.16 1.24 1.02 1.03 1.20 1.03 1.02 1.24 1.16 1.02
. 0.42
- 1.04
- 1.15
- l.ZO
- l.00
- 1.02
- 1.18. 1.02 . 1.01
- 1.23
- 1.18. 1.07 . o.,4
- 1.a. 1.0 * -o.9 . -3.l * -1.9. -1.0 . -1.2 * -1.2 . -1.1 * -o.7
- 1.7 . 4.1
- 6.1
- 0.41 0.95 1.16 1.18 l.02 1.18 1.19 1.11 1.19
- 1.18 1.02 1.18 1.16 0.?5 I o.41
- 0.96 . 1.17
- l.17 . 1.00 . l.16
- 1.18 . l.10 . l.16 . l.14. l.Ol. 1.19. l.21
- l.00
- l.5 . 1.5 * -o.5 . -1.1 * -1.6 * -o.a. -1.1 * -1.a . -3.3 * -1.0
- o.9 . 4.1 . s.1
- 1.04 1.zo 1.20 1.03 1.19 1.09 1.16 1.0, 1.19 1.03 1.20 1.20 1.04
- 0.42
- 1.05
- 1.21 . 1.19 . 1.01
- 1.17. 1.09 . 1.15
- 1.08 . 1.16
- 1.00
- 1.21 . 1.23 . 1.08 . 0.43.
o.41 7
2.1
- 1.1
- o.9 . -o.6 . -2.2 * -1.3 . -o.z . -o.a * -1.2 . -2.0 . -2.1 . 0.1 . z.3 . 3.5 . 3.2 .
I O.i3 1.07 1.18 1.10 1.20 l.ll 1.16 0,89 1.16 1.11 l."O 1.10 1.13 1.07
- o.;s . 1.oa . 1.1? . 1.09
- 1.11 . 1.10 . 1.16 . o.a9
- 1.16 . 1.11 . 1.1, . 1.11 . 1.20 . 1.01 . o.76 .
l.?
- 0.1
- 0.2 * -0.1 * -z.5 . -1.l. -0.1. Q.l. -o.o. -o.z . -o.5 . o.7. 1.1 . 1.a . 4.o .
0,73 0,41 1.04 l.ZO l.ZO 1.03 1.19 1.09 1.16 1.09 1.19 l.~3 1.20 l.:o 1.04 O.~l .
I
- 0.42 . l.C6 * !.21
- 1.20 . 1.03 . 1.17
- 1.08 . 1.16 . 1.10 , 1.19 . 1.03 . l.ZO . l.Zl
- 1.07 . 0.44.
2.1 . 1.4 . 1.0 * -0.2 * -o.4 . -1.3 . -1.3
- o.z . o.9. -o.~ . -o.z . o.4
- 1.2
- 3.o
- s.7.
0.95 1.16 1.18 1.02 1.18 1.19 l.ll 1.19 1.18 l.C2 l.18 l.16
- 0.97. 1.18 . 1.17. 1.00 . 1.15 . 1.17 . 1.09 . 1.18 . 1.17 . l.01
- 1.18 . 1.17
- 0.97 .
0.95 10 l.9
- l.9 . -o.3. -2.1 * -z.o . -l.6 . -l.6 . -~.s . -o.a . -o.a . -0.1
- 1.0
- 2.4 .
I !I 0.41 1.02 1.16 l.Z4 l.02 1.03 1.:0 1.03 1.02 1.24 l.16 1.02
- 0.42
- 1.04
- 1.15
- l.19
- 0.99
- 1.01
- 1.16
- 0.99 . 1.00 . 1.22
- l.17. l.05
- 0.43.
1.a. 1.e * -a.a. -4.l . -2.4 * -l.9 . -3.3 . -3.a * -2.0 . -l.4 . o.9. 2.l
- z.7.
0.41 ll I
0.56 0.92 1.16 1.18 1.20 1.10 1.20 1.18 1.16 0.9Z 0.56
- O.S7 . 0.91 , 1.11 , 1.15
- l.18
- 1.07 . 1.18
- 1.18 . 1.17
- 0.94
- 0.58
- 12.
1.e * -o.s . -4.l . -z.o * -1.z * -2.1. -1.1. o.6 . *a.a. 2.4 . l.6 *
- 0.56
- l.02 . 1.16
- l.ZO
- 1.18 . 1.20 , 1.16
- 1.02 . 0.56 *
- 0.57
- 1.06
- 1.17. 1.17. 1.15
- 1.20 . 1.18
- 1.05
- 0.57.
I 2.S
- 3.3. l.4. -2.2 . -3.0 . 0.1
- 2.3
- 2,4
- 3.1
- 0.41 0.95 1.04 1.07 1.04 0.95 0.41
, 0.43. 0.99
- 1.06
- 1.06
- 1.06
- 0.97 . 0.42 *
- 3.3
- 4.4
- 1.9. 0.4. 1.3. 2.1 , 2.3
- 14
- o:;.i***o:1;***0:;.i****************
I ST At/DARO AVERAGE OEVIATIOH *
- 0.44. 0.76. 0.42 , .PCT DIFFEREflCE
- 15
- 1.z34
- S.6 . 4.0 . 1.7. : l.6 I MAP NO: S2-5-ll DATE: 8/26/80 FT = 1.842 POWER ::: 71%
CONTROL ROD POSITIONS: QPTR:
Q I D BANK AT 185 STEPS FtH N
= 1. 410 NW 0.996 F = 1.239 NE 1.004 I z A. o. = -1.195 SW 0.995 I BURNUP ::: 90 MWD /MTU SE - 1. 005 I 39
I Figure 7.9 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION I I/E CALIBRATION - FLUX MAP R p tl L u A I
H K J H PREDICTED 0.42 0.74 0.42 PREDICTED NEAS!.mED , 0.42 , 0.74 , 0,42 , NEASURED
,PCT DIFFEREtlCE, . -0.1 . -0.2 , -0.1 , .PCT OIFFEF.EIICE.
I 0.42 0.94 l.04 l.07 1.04 0.?4 0.4Z
, 0.42, 0.?4 . 1.03. 1.07, 1.04 , 0.94 . 0.42 ,
, -0,8. -0,3 , -0.2 . -0.4 . -0.l , -0.3 , -0.3 .
0.56 l,OZ 1.14 1.19 1.18 1.19 1.14 l.OZ 0.56
- O.S6 . 1.01 , 1.14 . 1.18 . 1.17 . 1.18 , l,14 , l,01 . 0.56 ,
I 0.56
, -0.8 , -0.5 , -0.2 , -0.4 , -0.7. -0.8 , -0.7 . -0.5, -0.3 ,
0.9Z 1,15 1.17 l.19. 1.10 1.19 l.17 1,15 0.92 0,56
, 0.56 , 0.91 , l.14 , 1.16 , l,18 , l.09 , 1.18 , 1.16 , 1.14 . 0.92 , 0.58 , 4 O.l * -0.9 , -0.7. -l.2 , -o.~. -l.l , -1.l * -1.l , -0.6 . O,l . Z.l ,
I , 0.42 , l,02 , 1.15 l.24 l.OZ , 1.04 , 1.20 1.04 1.02 1.24 1.15 1.02 0.42
, 0,42 , 1.03 . l,14
- 1,20 , 1.01 , 1.03
- 1.19 . l,02 . l.Ol . l.22
- l.l~ . 1.05 , 0.44 ,
0,9. 0,8 , -1.0 , -Z.8 . -1,7, -1.2 , -1.J . -1.4 , -1.6 . -1.3 , l.Z , 3.4 . 5.1 .
5' i
, 0.94 . l.14, 1.17 . 1.02 . 1.18 . 1,19 . l,12 . 1.19
- 1.18 . 1.02 . 1.17 , 1.14 . 0.94 , I I , 0.95 , 1.15 . 1.16 , l.Ol
- 1.17. 1.18 . l.ll
- l.18
- 1.16
- 1.02 , 1.18 . I.la . 0.95 ,
o.6
- o.6 . -o.8 * -1.4 . -1.6 * -1.0 . -1.z * -o.9 . -Z.3. -o.4
- o.? . 2.9. 4.1
- 0.42 , 1.04 1.19
- 1.19 1.04 1.19 , 1.10 1.17 1.10 1.19 1.04 1.19 1.19 1.04 0,43 . l.04 . 1.19 , 1.18 . 1.02 . 1.18 , 1.10 . 1.17. 1.11 . 1.18 . 1.04 . 1.21 . 1.£1 . l.07. 0.43 .
0.42 6/
1.6
- o.6 . o.z . -o.7 * -1.9 . -1.1 * -a.1 * -o.z
- o.5. -a.5
- o.4
- 1.a . z.o . z.1 . Z.6 .
I 0.74 . 1.07. 1.18 . 1.10 , l.ZO , 1.12 , l,17 . 0.91 . !.17 . 1,12
- l.tO , 1.10 . l.!8 . l.07
- 0.74 .
0.75 . 1.08 , 1.18 , l,09 . 1.17, 1.10 . l.17, 0.91 . l,18 . 1.12 , 1.:1 . l.lZ . 1.19 . 1.09 . 0.77 .
1.5. o.s . -1.0 . -0.9, -z.s. -1.4. 0.1. 0.6 . o.s . 0.3 . 0.5 . 1.4 . 1.2 . 1.8 . 4.0 .
0.42 . 1.0*
- 1.11 1.19 l,04 1.1? . 1.10 1.17 1.10 1.19 1.n~ 1.19 1.19 1.04 0.42 I 0,43 , l.05 . l.20 , l.19
- 1.03 . l.17 , 1.08
- 1.17 . 1.10 . l.l~ . l.04 . l.ZO . l.ZO . 1.07 . 0.45 .
l.6 , 1.2 . l.O * -0.3. -0.9 . -1.5 , -1.6 . -0.3 . 0.4 . -o.: . -0.Z . 0.3 . 1.0 . Z.9 . 5.9 *
. 0.94 , 1.14 . 1.17 . l.OZ . l.la . 1.19. l.lZ . 1.19 , l.lD . l.CZ . 1.17 . 1.14 . 0.?4 .
. o.96 . 1.11 . 1.11 . 1.00 . 1.lb . 1.11 . 1.10 . 1.18 . 1.1a . 1.02 . 1.11 . 1.1s . o.q6
- 10 z.o
- z.o . -a.4. -Z.l . -z.3. -1.a . -1.1 . -o.,. -o.6 . -o.6 . -o.3 . o.s . 1., .
I , 0.42 , 1.02 l.lS l,24 l.OZ . 1.04 1.20 l.04 1.0. 1.24 l,15 1.oc
, 0.42 . l,03 , 1.14. 1.19, l.00 , l.02 , 1.16 . l.OZ , l.Ol . 1.23 . 1.16 , 1.03 . 0.43 ,
1,2 , l,Z , -1.l . -4.0 * -2.6 , -2,l * -3.l , -z.z , -1.0 , -0,7 , 0.6 . 1.3 , l.S ,
0.42 ll o.56 o.92 1.1s 1.11 1.19 1.10 1.1, 1.11 1.1s o.,~ o.56 I , 0.57 , 0,91 . l,10 , 1.14 , 1.17, l.07 , 1.18 , 1.18 , 1.16 , 0.93 . 0.57 ,
0.3 . -1.3. -4.0 * -C.4 . -1.8 . -Z.9 , -1.3 , 0.4 , 0.7 , 1.8 ,
. 0.56 , l,02. 1.14 . 1.19 . 1,18. 1.19, l.14 , I.OZ . 0.56 ,
, 0,57 , l.05, 1.16 , 1.16 . 1.14 , 1.19 , 1.17, l.04 , 0.58.
l.8 ,
12*
13!
I
, 1.9, 3.5. l,l * -2.6 . -3.Z , -o.o , 2.6 , Z.S
- 2,0 ,
I 0,42 0.94 1.04 1.07 1.04 0.94 0,42
- o.43. o.9e
- 1.04
- 1.01 . 1.04
- o.,~
- o.43 *
- 3.s. 3.7. 0.1.-0.3. o.7. 1.a. 2.8.
14 STANDARD , 0.42 , 0.74
- 0.42 . AVERAGE I DEVIATION
- l.091
, , 0.44, 0,76 , 0,43 .
3.5 , 2,5 , 1,0 .
,PCT OIFFEREIICE.
= l.4 I MAP NO: S2-5-12 CONTROL ROD POSITIONS:
DATE: 9/1/80 FT = 1. 790 POWER::: 88%
QPTR:
Q I D BANK AT 190 STEPS N
F llli = 1.398 NW 0.996 Fz = 1.234 NE 1.005 I A. O. = +1.257 SW 0.991 I BURNUP ::: 175 MWD/MTU SE - 1. 008 40 I
I Figure 7.10 SURRY UNIT 2 - CYCLE 5 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION I HFP, EQ. XENON I ? N PREDICTED t":CASU~ED i'1 L K J 0.43 H
0.75 G
0.43
- 0.43
- 0.75
- 0.42
- 0 C i=REDICTED ME~SU:t:!J 6
.PCT O!FFE~ENCE. O.l
- O.l * -0.4 . .PCT DIFFERENCE.
I o.42 o.93 i.o4 l.ll i.o4 o.93
- 0.41
- 0.93. l.04
- l.10
- l.03 . 0.92 . 0.41
- o.~2
- -0.2 * -0.6 * -0.7 * -0.8 * -1.0 * -1., * -0.7 .
0.56 l.Ol l.14 l.18 l.18 l.15 l.14 l.Ol 0.56 I 0.56
- 0.56
- 1.01
- l.13 . 1.17
- l.16 . l.16 . l.l~ . l.00 . 0.:, .
. -o.z * -0.1 * -o.3 * -o.a . -1.6 * -1.4 . -1.1 . -o.6 . 0.1 .
0.91 1.14 l.16 1.19 1.09 l.19 l.16 1.14 0.91
. 0.56 , 0.90 . l.13
- l.15. 1.17. 1.03
- 1.17. l.15 . l.13 . 0.9l , 0.57 .
0.56 4
0.4 . -o.5 . -o.4. -1.1 * -l.3 * -1.5 . -1.4 * -o.9 . -o.4
- o.z
- 2.7
- I 0.42 l.Ol l,14 l,23 l.03 1.04 1.20 l.04 l.03 l.Z3 l.14 l.01
. 0.4Z . l.02 . 1.13 . l.20 . 1.01 . l.02 . I.IS . l.02 . I.Cl . 1.:1 . 1.:3 . 1.05 . 0.~4 .
0.9 . 0.9 . -0.7 . -2.J . -1.4 . -1.5 * -1.5 . -1.5 . -1.6 . -l.l . 0.9. 4,0 . 6.D .
0.42 0.93 l.14 1.16 1.03 1.23 1.:1 l.l2 1.21 l.23 l.03 1.16 l.14 0.93 I 0.43
. 0.94 , l,14 . 1.15. 1.02 , l.Zl . l.19
- l.ll
- l.19 . l.19 , l.C2 . l.17 , 1.17 . 0.96 .
Q.3
- 1.04 0.3 . -0.6 . -0.6 . -1~1 . -l.O * -l.2 * -1.2
- l.!8 1.19 l.04 1.21 l.!l l.!S l.ll
-z.s .
1.=1
-0.5 .
l.C4 0.3 .
l.l?
J.4 .
l.lS
. 0.43 . 1.05 . l.13 . l.18 . l.02 . 1.19 . l.11 . 1.17 . l.ll . l.1~ . ~.04 . l.Zl . l.:o . 1.08 . 0.44 .
S.3 .
l.C4 0.43 0
7 1.a . o.s . -o.z . -o.7 . -1.6 . -o.9 . -0.2 . -o.4 . -o.z . -1.2 . o.~ . . . , . 1.s l.l . z.7 .
I 0.7S l.ll l.18 1.09 l.ZO l.lZ 1.:a 0.11 l.lS 1.1: 1.:0 1.:9 !.la
. 0.76 . l.ll . l.!3 . l.:s . 1.17 . 1.11 . 1.13 . 0.92 . !.!S . l.lZ . 1.:0 . l.:l . 1.19 , l.lZ . 0.78 .
1.a . o.6 . 0.3 . -o.a . -1.& . -1.J . -0.1 . a.z . 0.1 . -0.1 . o.; . 1.~ . c.7 . !.4 . ~.0 .
l.ll 0.75 e
0.43 :.c.; . 1.:.a . 1.19 . 1.c!+ 1.:.1 . 1.1e 1.11 ~ ... , 1.04 l.l? !..:..s 1.0~ o.-+3 I
1 ~, *
. o . .:.3 . l.;;:> . :.:a,,!_.:.:? . 1.04 . 1.19 . l.-cq . l.!3 . 1.:1 . 1 . .:0 . :..:3 . :.:a . !.la . 1.07 . :)..:.5 .
1.s . !.~ . 1.5 . a.1 . -o.3 . -1.: . -l.6 . -o.3 . o.4 . -1.b . -o.~ . -o.b . a.3 . :.7 . b.J .
0.?3 l.14 1.16 l.CJ l.2l 1.21 1.12 l.Zl 1.23 l.03 l.l6 l.14 0.93
. 0.16 . 1.1& . 1.16 . l.01 . 1.~o . 1.1s . 1.10 . :.19 . 1.:2 . 1.c: . 1.:~ . 1.13 . a.;; . :c 2.s . z.s . 0.1 . -1.1. -1.7 . -1.a . -2.0 . -a.1 . -o.; . -o.a . -r.z . -0.1 .
I 1.1 .
0.42 l.01 1.14 l.~3 1.03 l.04 1.20 l.C4 1.03 1.23 1.14 l.Ct 0.~2
. o.~3 . 1.J3 . :.:4 . 1.10 . 1.on . 1.02 . 1.1s . l.c: . :.J2 . 1.~z . 1.1s . 1.c~ . o.4~ .
2.3 . 2.l * -o.z . -3.5 . -2.3 . -%.3 . -3.6 . -Z.l . -~.3 . -J.6 . C.5 . l.Z . 1.3
- I a.so
. o.s1.
o.91 l.!4 1.16 1.19 1.09 1.1? 1.16 1.14 o.;1 o.91 . 1.10
- 1.14 . 1.11 . 1.06 . 1.1a . 1.11. 1.:s . o.93 . o.57 .
2.2 . -0.l * -3.5 . -2.l . -l.6 , -2.7. -0.9 . l.O
- l.2
- 2.5 . l.d *
. 0.56 , l,Ol
- l,l4. 1.18
- l.18, 1.18 . l.14 , l.Ol . 0.56 .
o.so
- 0.57. l.04
- l.15 , l.16
- l.15 , 1.19. l.17 . l.C4 . 0.57 . l3 I 2.9
- 3.7. l.3 * -2.a * -2.4. o.4 . 3.o . 3.l
- z.s .
0.42 0.93 l.04 l.ll l.04 0.93 0.42
, 0.43 , 0.97
- l.06 , l.ll
- l.05 . 0.95 , 0.43 .
3.7 , 4.l . l.6
- O.l , 0.6 . 2.0 . 3.2
=l.226
- 4.4. 2.9. 0.6 . = l.4 I MAP NO: S2-5-13 DATE: 9/12/80 N
POWER ::: 100%
CONTROL ROD POSITIONS: Ft.H = 1.387 QPTR:
I D BANK AT 215 STEPS FT Q = 1. 716 NW 0.9946 F = 1.171 1. 0019 I A.
z
I I Section 8 I REFERENCES I 1. M. C. Cheok, R. T. Robins, and S. A. Ahmed, "Surry Unit 2, Cycle 5, Design Report," NFE Technical Report No. 107, Vepco, December, 1979.
I 2. Surry Power Station Units 1 and 2 Technical Specifications.
- 3. Surry Power Station Units 1 and 2 Final Safety Analysis Report.
I 4. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36, May, 1980.
I 5. *T. J. Kunsitis, "RXFLOW, A Computer Program to Calculate Reactor Flow and Thermal Output," NFO-CCR-8, Vepco, December, 1979.
I 6. "Technical Manual for Westinghouse Solid State Reactivity Computer,"
Westinghouse Electric Corporation.
- 7. W. Leggett, and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 1967.
I I
I I
I I
I I
I I
I 42
I I
I I
.1 APPENDIX I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS I
I I
I I
I I
I I
I I
I 11
SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUL 3 1 1980 I Test
Description:
Reactivity Computer Checkout erence Procedure Number/ Section:PT28.111~PP* B Sequence Step.Nu:nber:
II *Bank.Positions (steps) RCS Te:c:iperature (°F): 547 SDA: 228 SDB: 228 CA: 228 ~o~er Level (% F.?.): 0 l~itions (Design) CB : 228 cc : 228 CD:
- Other (specify):
Below Nuclear Beating
- ;, r r-{ , i ior:
Ill Bank Positions (steps) RCS Terenerature (°F) : S'f-7
'Test Po-wer L~vel (:Z F .P.): 0 caiditions SDA:2.28 SDB: 2c.8 CA: 22.8 Other (specify):
Sct:ual) a:22.g CC:2. 2. 8 CD: /lf-'f-6e:low Nv~ear He.a.i:h-,8 I Date/Time Test Pe~!or.z?ed.:
8 / /~ - IS" / 80 2..39--S - OO'r-0 I IV
- Me.asilred P ar2.l!le"t.er (description)
Pc = Measured Reactivity using p_:-computer Pt* Inferred Reacti~-ity from reactor period I He.asured Value Pc = +*2 3.c.
+
pt = 2 2. *.5"
+ 3. /
-2.S,O
-c.S,O
+1-3-5
+"f-3.8
-0.7 i-, S"""
-+.s: 6'"
+fz.S-. S"
,3,5
-r 3, 2
-~o.o
-~o.s-
~;~ = o.o -2.2. - 0.2 l est e.sults
~e:sigu Value (ActuzJ.. Conditions) I Pc -Pt j:it I < .04 ..
I Design Value I~ .04 I
(Desig.i. Condi~ions)
I Pc - Pt Pt Refere:1ce WCAP 7905, Rev. 1, Table 3.6 V
ept2.nce FSAR/Tech Spec riteria
' Reference Not Applicable Desi£!! Tolerance is met : R' :""ES D !W Acceptance Cri ter::..a :Ls met: ;Et YES O NO I
Con:pleted ~a 1 ua tea* 11
...,y: ___ 7 ::4w
.....__i:.-0=.=.__._~--=-=->==----
.I A.l Revie~ed By: __ C:-=-_-_:J'_._'_~_,~~---------
lfr'O Engineer
SUR.RY POwER STATION mniz 2 CYCLE 5 STARTUP 1* STAR fUP PHYSICS TESTS RESULTS M""D EVALUATION SHEET JUL 3 1 1980 Fl I Test
Description:
control Bank B Worth ~asurenent teference Procedure Number/ Section: PT28.ll/App * .E Sequence Step Nm::ber: //
II Bank Positions (steps) RCS Temperatu~e (°F): 547 Cest SDA: 228 SDB: 228 CA: 228 Power Level (% F .P.): O
~<,dit:i,ons esign) CB : Moving CC : 228 CD: 228 Other (specify):
Below Nuclear Heating I III Test:
Bank Positions (steps) RCS Te~per2.ture (OF): S4Ca,Z r Power Level (% F .P.* ) : o.o
~onditions . SDA: 2 Z.B SDB:Z.Z.8 CA:U.S Other (specify):
lctual) CB: M O"INC:i CC: 22.8 CD:ZZ.8 Date/Time Test 8/1S/80*
I Per for.med: s~o 133'/ co1-1p1..~ 162.0 Measured Parameter IIV (description) Integral Worth of Control Bank B I Measured Value I;2.. 8 4 PC/P7 t l est ultS Design Value (Actual Conditions)
/Z,z.5 +/- I Z3 [)C,M I Design Value (Design Conditions) 1225 +/- 12 3 pcm I Reference VEP-FFD-1,E'E: 107 ; \'E?-??.:r-36 ; Letter ::rom Hr. W. ,..; .
Tnoffi:l.s (Vepco) to !>~r.E-:. ?... Senton (NRC) ci::.ted June 25, 1980 (Serial No. 569)
~cceptance FSAR/Tech Spec *Not Applicable lriteria
.Reference Not Applicable Design Tolerance is met . : {gJ . YES D HO Acceptance Criteria is met: 0 YESONO I
-** yr,, /
Co~pleted Evaluated B y ~ , /J
. 1 (l / /
Revic,;.:ed By: C . ~, . .d~iJ I A.2 NFO Engineer
.,:i::..
I STAR ruP PHYSICS TESTS RESULTS .M""D EVALUATION SHEET
.FINAL RFSl JI T~
JUL 3 1 1980 I* Test
Description:
Control Bank D Worth Measurement - Rod Swap ference Procedure NU!:lber / Section: PT28.ll/App. F Sequence Step Number: 1:5 rI st Bank Positions (steps) RCS Te~perature (°F): 547 Po~er Level (% F.P.):o SDA: 22B SD:S: 228 CA: 228 nlions CE : Moving CC : 228 CD: Moving Other (specify):
D *gn)
Below Nuclear Heating t II est onditions SDA: 22B Bank Positions (steps)
SDB: 228 CA: ZU3 RCS Terr.per2.ture (OF): s1c.:.. 4 'f" Power Level(% F.F.):o Other (specify) :
CB: MO\/INY CC: ZW CD: ,-.ov,l'Ju Alual)
Date/Time Test I PerfoTI!led:
Measured Parameter I (description) Integral Worth of Control B;:a..nk D - Rod Swap
.I ~ie2.sured Value
- Cesig:i. Value (Ac: tU2.l Condi ti.ans)
J 2. 14 I Design Value (Design Conditions) 1209:: 181 pen (Critical Re.fe:cenc::: B2.r.L Position = 216 ste?s)
~?-Fri:-NFE 18/ ; \..=.F-FF.Z.--36 ; iR.i:.-:.e.:- z=o;:: !.....=. '..: . *,.
'Iho;;;.es (Vepco) to ~'.:::.H. ?.. :::e~t.cn (~RC) c:c.ted J:.:.-ie 26, Reference 1980 (Se::-ial No. 559) ; .Me::s.o=-a..'1t...T.1 =:-o::i Mz. T .. K. P.:,ss to C":". ~ J. Lozito c.a~eC July l, 1980.
.cceptance FSAR/Tech Spec Not Applicable
- ,iteria Reference Not Applicable
-Ji---}-----1--------~--
- JZl. YES O NO
!rrts VI Design Toler2.nc:e is met Acceptance Criteria is met: rg) YES D NO I-I Evaluated s;,~ ~/
~
I Revie..,cd By: C. ,_1. z:.~..,.-0-~~1/
- ,;Fa .E.n~inecr
SURRY POWER STATION UNIT 2 CYCLE .5 STARTUP
.I STAR rw PHYSICS TESTS RESULTS .Ahl) EVALUATION SHEET JUL 3 1 1980 flNAL
-* RESULTS I Test
Description:
Control Bank C Worth Measurement - Rod Swap lerence Procedure Nur:iber I Section: PT28.ll/App. F Sequence Step Number: 10 II Bank Positions (steps) RCS Teu::perature (OF): 547 I t SDA: 228 SDB:228 CA:228 Power Level (% F.P.): 0 Clditions esign) CB : Moving cc :Moving CD :228 Other (specify):
Below' Nuclear Heating
-I III Bank Positions (steps) RCS T e.n?.p era t ur e (°F) : S45, Co "/:'
Test. Power Level (% F .P.* ): 0
- lditions SDA: z.-z..8 SDB: Z.Z.8 CA: Z.Z8 Other (specify):
ctual) CB : ,-.., ~ ""'6 CC: MO'l/1"',(:; CD: U.6 .
BtrUMJ Nl.)C.Lt!A~ HEPtTJI.J6 I
~
Date/Time Test B/tc./~
PerfarI!!ed:
1113 I IV Maasured Para.meter (description) Integral Warth of Control Bank C - Rod Swap I Neasured Value B4r ?:J--. ( ADJU,Slc() M=rl .sue.ro c.Zmc.Ac.. faj I rto>-1 : J4C.:. STc.PS)'
lest
?,esults Design 1.'alue (Actual Cm::.ditions) I 'I-BSD I 28 ?"-"'I ( At).)()$i'c0 1--1cf1:s~f!£D c.Jli~ICAL. fb~mON = /4{.,, s~
f I Design Value (Design Con:iitions) 851 +/- 128 pcm (Critical Ref e:::: c:cE r:~:-.;.!:
Position = '160 s ~e:-*~ ::
I "'0w*!'.,.:-:~:i= ~ 107 ; *vE?-::"?..:-35
'!11=::-.as (Ve?CO} to !-:=.E.
Ce:i-;:::i L-e-:-:.e= ==::=-.
(::?.:)
~.=. \i. ...
&tee J*.!..-;e 26,
- Reference 1920 (Se:=i.a::.. No. s*c) 0-. ;
r **
,.~ .......... -ar..:.~-- .:. ___ '-'-. ... K. F:oss to Dr. -- Lo=~~o ~~~e= Julv -* ' :!.9£0
- V 1e~t2.n 7e ri teri2._
FSAR/Tech ..Spec Not Applicable Reference Not Applicable Desi.'?;!l Toler2n'ce is met :~ 'YES0 HO VI Acceptance Criteria is met: 0. YES 0 NO fen~s I --*-
I I Cc~pletedBd.J 9,M~
le. '- Ens;:i eer A,4 Evaluated
SURRY POWER STATION UNIT 1... CYCLE ..2.. STARTUP I STARrUP PHYSICS TESTS RESULTS AND EVALUATION SHEET JUL 3 1 1S3J FINAL RESULTS Test
Description:
Control Bank A Worth* Measurement - Rod Swap nc Procedure NUI!lber I Section: PT28.ll/App. F Sequence Step Number: /7 Bank Positions (steps) RCS Temperature (OF): 547 iol gn)
SD.A: 228 CB : Moving SDB: 228 cc : 228 CA:Moving CD:228 Power Level (% F .P.): 0 0th.er (specify):
Below Nuclear Heating I :Bank Positions (steps) RCS Tei:q>er2.ture (OF): s4s.s or st Po..-er Level ( .lo, F .P.* ): 0
!I SDA: 2'2..8 CB: M.ovtJ.J6 SDB: 2.2.8 CC: 'Z.2.8 CA:
cn:zze f--.0\/IN6 Other (specify):
~ NC.X:.LE:13,e ;IEA,1}.16
- 1 Date/Tilne Test Performed:
a(l~jBo J7So I Measured Para.meter (description) Integral Worth of Control Bank A - Rod Swap I Measured Value b50 f,c.1-i ( ~ tJjLJ ~ i21' i--i cf:!> u eE1) cz., r.:!h<. ~sir1cr-.J: 1/4 5rt:Ps)
- s I . Design Value (Actual Conditions) ( A D.Ju.s1EO M£rr:1.)e.ea cemc.A-L fc,5/r/CN I14 ~T?P5 i 5t1 +/- /00
~
== /
I Design Value (Design Conditions) 578 +/- 100 pcm ( Cri tic:a1
~
r,!
~
erer.c::: .:iE:"".:.:
I Posi<:ion 121 Si::.?S,'
V::?-: FD-!,FE 107 ; . ** .:..?-F:"..:-36 ; :.o:-:.-:e= ---- ..... *. -**
-:"nor..as (Ve?CO) u, !-'.r.E. ?.* r:"=;-,:.~~ ~~~:.:; ..:.::, -.:::....: ""**-.e ,~,
Reference --=- ~*-
1980 (Se::ial }lo. 569) '* r,'~ ....
~. L°'.::i. ":.O -== te.:. :".!l ~*
. .: r o i *.'-. - . K. ?..:>SS to Dr. E. - ' 1920.
tale te a FSAR/Tech Spec Not Applicable I
Reference*
Design Tolerance is met I : rn. Y1:s o NO Not Applicable Acceptance Criteria is raet :@ YES0 KO
~s1 I - .
A.5
- SURRY POwu. S'I8.TION UNIT 2 CYCLE 5 STARTUP STA.1ITUP PHYSICS TESTS RESULTS .Ahl) EVALUATIO'N SHEET JUL 3 1 \980 FJNAL RESULTS I Test
Description:
Shutdown Bank B Worth Measurement - Rod Swap Ee nee Procedure !-lumber I. Section: PT28.ll/.App. F Sequence .Step *Number:
IB Bank Positions (steps) st I
- id ions De~ign)
SDA: 228 CB : Moving SDB:Moving cc : 228 CA: 228 CD: 228 RCS Tempe.:-a ture (°F): 547 Po..ier Level ("'
Other (specify):
Below Nuclear Heating
, F.P.): 0 Ill Bank Positions (steps) RCS Te~perature (°F): 545-S t)F Power Level. (% F .P.* ): c, n's t tions SDA:ZZ8 SDB: J-.4o'l1iJ6 CA: Z?.8 Other (specify):
Act.-ual) CB: MO\JJ/116 CC: Z.28 CD: zzs -
Z , ~ N r.x.u:A-~ tt EJ4TJIJ 6 Date/Time Test e;1,/eo Performed: l?o8 I Measured Parameter (description) Integral Worth of Shutdown Bank B - Rod Swap I Measured Value \
952. ~ ( AOJu~reo HEAs0£EO C../llilcAL ?o~ me,../ = I 63 s~,.:
lt e.lts Design Value (ActU.2.l Conditions) q~q t MEf'6(.)fU!) CJZ,IHcAi. fo!, JrJ i:w .- It., 3 jJ!?.S)
/45 A:M (Ao.lr..>5Tm Design Value (Design Conditions) '9 78 +/- 147 pcm (Critical F.i:.f ere::-.ce. .::a r!::
I '\rc.?-F;':.D-'.l?E lOi ; '\=.:-':F.:r-30 ; i..e-:-:.e~ =r~~
Positicr.. =- 17~ steps~
!-'....=. w. "*
~c:::-.as (Vep=o) to !-'.=. P.. ?** Cen~on {:;'2*::) c.a -:.ec:. Jc.."le 2 6, I' Reference 1980 (Se:::ial !lo. 569) ; ~mc~a..-id.~~ :ro::-, !-~.
to D:::. ~
J. Lc::i'to ..=~:==d J...:l*: l, l9SO.
~- 1'.. Ross
-v *Not Applicable
.c.1~tan e. FSAR/Tech Spec 7
1.ter1.a I Reference Not Applicable Jvr
-.ents Design Tolerance is met Acceptance Criteria is met: 00 YES ONO
- IB!-YESO 1:10 1-I Completed q J. Q ~
T t ~P*ineer A.6
SURRY POWER STATION UNIT 2 CYLE 5 STARTUP ST.AR.TUP PHYSICS TESTS RESULTS Ai.'\"D EVALUATION SHEET JUL 3 1 1980 I Test
Description:
Shutdown Bank A Worth. z.leasurenent - Rod Swap Procedure Number/ Section: PT28.ll/App. F Sequence Step Number:
erence /9 rlt . .
II ditions esign)
Bank Positions (steps)
SDA: Moving CB : Moving SDB: 228 CC : 228 CA: 228 CD: 228 RCS Temperature (°F): 547 Power Level (% F.P.): O Other (specify):
Below Nuclear Heating III Bank Positions (steps) RCS Te~per2.ture ( 0 F): 5"'1S.G. "f' Test. Power Level (% F .P.* ): o.t:>
SDA: Mov,A/6 SDB: z.z.e, CA: ZU3 Other (specify):
- ,-*di tions ctual) CB:,-.,ov,A.>6 CC: ZZ8 CD: Z.2..8 I Date/T:i.lne Test Perforned:
8/!c./ea 1945 I IV Measured Parameter (description) Integral Worth of* Shutdown Bank A - P.od swap
.I Measured Value
.I est
?._ ults Design Value (Actual Conditions)
Design Value (Design Conditions) 1055 +/- 15 8 pcm (Critical Refere~ce :ank Pos*iticn = 189 steps;.
I Reference
- v~P-.:'F~~;::. ... JI Tno:=-.as
- *\~?-Fi.U-36 ; Le'C~
- :-- .::-or;:!'"~. ~. ;,: ..
(Ve;:co) to ~!'°.H. ?... D:ntc:. ~!!?.Ci c.1ted .Ju:1e 26,
~980 (Se=ia~ No. SE9j ; t-~e::1ora.."1C.u..~ ==-:;:: !-"~. ':. 1:.. k:,ss I FSAR/Tech Spec to D=. ~- J. I..o=it~ C..:~ed :ulv l, 19SC.
Not Applicable Reference Not Applicable Design Tolerance is niet . : ~ YES D HO Acceptance Criteria is met : ~ YES O NO I
'I A. 7
. . siJt~Y -I*mrn: ST1~1'IO:f Ul;.i'I i:_ CYCl.2 5... S1:AR11JP I STARTL1' PliYSlCS TESTS KESULTS AKO .!:.'VALUATION SHEET FINAL RESULTS JUL 3 1 1980
-Ir .
Test
Description:
Total Rod Worth - Rod Swap
'!.ifrence Procedure Huobcr I Section: NA Sequence Step Number: NA
- 11*
B~nk Positions (steps) RCS Te-r::perature ( 6 F): 547 Po*wer Le'.~el (% F.P.): O
'.litions
- sign)
SDA:Moving CB : Moving SDB:Moving cc :Moving CA:Moving CD:Moving Other (specify):
Ilelo-.* Nuclear Heating
,I III Test Bank Positions (steps) RCS Te=.perature (Of): .o~
Power Level (% F.P.): 0 SDA: Movin ~ SDB: MoviV'I~ CA: Mo\fir.~ Other (specify):
,~;~)s CB: MoviY\!)
C:: Movi~j CD: Mov_iY\<:;
Below Nvc..lea..r HtW:.1~
<t,/ts--1" /80 I Date/Time Test Perfor.:::r:c.: /?,39 - /9'1-~ .
!-~easured Paral:!.<2.ter I IV (description) ~otal '
Integral Worth of All Rod Banks - Rod Swap I }ieasured Value I
Total = ~II 2. ff!AY'l kt
- ts Le sign "vc.lue
(.!.ctu.2.l Conclitic:is) -Total =
T S-8'1/ -
-r- S8'? pc..m I' Design Value (Desib11 Conci.itions)
~Total = 5896 +/- 590 T pcm 1* -- I VS?-:"?.:-~.;::: 107 ; \.:..?-Fr.::-36 ; Let.:e-!" i=o:. ~-=. ,.
'::-ior.-..:.s (Ve_;:,:::o) tc !".: .H. !"... Den 't.CZ"'1 (!*:~::). c.a te C J~e .c, Ref ere.nee ,..~.....,...-a:-~**- ~--- ,. __
If-__;~;:.=...:~.:.....::..:.....=:.::...::.0::_::=..;.:.=....=..:;.:~~.,;;-~*;:.;""~---~---~~~------=-*-
I lSEC- (S:=ial. No . 56?) ;
to D:.
-* J. Loz.i~ C2. ~e:: ""~l*.* ~ ,c:--
~
K. ?.:::>SS
\'
cptm1ce FSAR/Te.:h J__
1 :::-i~erln N_O_t_Ap_p_licable
-:11.**.t------;'----i:-:e_r_e_r_t_.r_,_(_:P_._____l,_ _N_o_t_A_.p_p_1__i_*c-ab--le_ _ _ _ _ _ _ _ _ _ _ _ _ __
l, *
~
D~si;n Tol£-r.::ince is ,::-c:t : ~ *::rs O HO l,ccc:;:: t.:::.;, cc. Cz-i t c r i2 is ,.let: )'8:: Y::S 1J i*iCl I
I l',::: - J f( ~
I A.8
__ C.J ,.-1' r?
Lr~..;. _ _
I - . - - - --- - - - - - - - - - - - - -- -
I - . SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP ItfWAES1:?t~( JUL 3 1 1980
- I STARTUP PHYS
'l'est
Description:
Critical -Boron Concentration - ARO JIVT~~TION SHEET eference Procedure Ntll!lber / Section: PT28.ll/ App . C Sequence Step Nt!l!lber: 7 I II Test nditions SDA:
CB .
Bank Positions (steps) 228 228 SDB:
cc . 228 228 CA: 228 CD: 228 RCS Te::::perat:ure (°F): 547 Po1,;1er Level (Z F.P.):O Other (specify): .....
(Design) Below Nuclear Heating -
I- III Bank :Positions (steps) RCS Te.:c::pe:r-at:ure (OF): S'f,.
Po'wer Level (::: F.?.):0
~
Test c2.8 2e.8 *other (specify):
tnditions (Actual)
SDA: 2.2.8 CE: 2.2.8 SDB:
CC:2,2.8 CA.:
CD:228 Be.low Nuu~a_r He.a.:ti'-ri~
,I Date/Time Tes-c Perfon:i.ed:
8fs-/ao 031--0 .
I IV Measured Para.meter (description) (CB) ARO Critical Eoron Concentration - ARO I Measured Value
- H (CB)ARO= /1--37 pprn lest Design Value CB=
=tesults (Ac.tu.al Conditions)
/ 3 9Lf + - 5"0 ppm I Design V2.lue (Design Conditions) CB= 1394 + 50 ppm I
Reference VEP-FRD-:NFE 107 I_
V FSAR/Tech Spec ac B X CB .£_ 15 i 1,15 pcm
'eptanc.e rit.er:ta FS.AR Section 14.2.5
-I Reference
,nnn~nts VI Design Tolerance. is met . :
- Accept2.nce Cr:!..te.ria is met:
l YES O HO YE.SO NO uc = -8.6 pcrn/ppn for preliminary an2lysis. -
I B
°'~e = - t:t *./1 p~/ppM for .fina) ~a.ly~is .
..I .
Evaluateq By:
I A,9 Reviewed By: ----'C_. _J_,_k_, __,:,-____
SUP.RY PO"WER STATION UNIT .1 CYE:LE 2. STARTUP I- ST.ARTUP PHYSICS TESTS RESULTS Ah"D EVALUATION SHEET 'JUL 3 1 1980
-I I FINAi RJ:"~111 T~
Test
Description:
Critical Boron Concentration - B f)ank In
~ference Procedure NUI:J.ber / Section: PT28.ll/App. C Sequence Step Number: /Z I I! I Bank Positions (steps) RCS Temperature (°F): 547 Test SDA: 228 SDB: 228 CA: 228 Power Level (i~ F .P.): 0 fnditions Design) CB : 0 cc : 228 CD: 228 Other (specify):
Below Nuclear Heating I III Test-.
Bank Positions (steps) RCS Ten::per2.t:ure (OF) : 5"¥-S. CJ Power Level (%. F .P.* ) :O
'nditions SDA: 22.~ SDB:22.~ CA: c.e.8 Other (specify):
(Actual) CB:0 CC: c:.2.i CD: 2.2.8 -.
Bel ow fJ., cJ e.a.A"" Hea.tihj
_8/t(p/80 I Date/Time Test Perfonied: 0'/--17 Measured Parameter I IV (description) (CB)B; Critical Boron Concentration - B Bank In I Heasured Value (C"Q)M
., B
= /2?0 ppm I Test esults Design Value (Actu.21 Conditions)
'"'B =
1301 + c.3 pp'<<)
I Design Value (D~sign Conditions) CB = 1258+[(CB)~0-1394] +/- [10+122.s/Jo.c B
!] P?T'i I
I V Reference I VEP-FRD-NFE 107 FSAR/Tech Spec *a. X CB 2 15,115 pcrc
.cceptance CB Criteria
,-~ents Reference FSAR Section 14.2.5 I
Design Tolerance is met :*~-YES 0 HO VI Acceptance Criteria is met :R YES-0 NO a.cB = -8.6 pc~/pprn for prelimir.ury ~nalysis.
I o<.c.B = -CJ.II ptM!p fYY\ ttir tino...l 0-,V\ a....1y :s;5.
Cci:.pleteo Evaluated By:
I A.10
*::; uRRY POWtR ::;TATION UNIT :L CYCLE -' !:iTAKTUr'
.I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET t" 11\. I /\ I n r- rq II T 0 JUL' 3 1 1980 j Ii '111 -u_ I \ L v U l.. I v Ir efercnce Test
Description:
Procedure Number/ Section:
HZP Boron Worth Coefficient*
NA Sequence Step Number: NA Bank Positions (steps) RCS Temperature (°F): 547 SDA: 228 SDB: 228 CA: 228 Po-1er Level (i: F .*P.) : 0 onditions Other (specify):
<l:~gn) CB : Moving CC : 228 *CD: 228 Below Nuclear Heating ID Bank Positions (steps) RCS Ten:per2.ture (°F): 5'f-7 I
_ 'Test Po"Wer Level (7. F .? * ) : 0 rtutl)
- cncii ti.C':!S SDA: 22.i CE: Movi"r'!,?J SDB: 2.c.8 CC: 22.8 CA:
CD:2a8 2.c.8 .
Other (specify):
Dat:_e/Ti.me Test: gj,s-- 16/80 I Performed:
Measured Parameter 03'1-S- - 0~/ 7
( description) a.Si, Boron Worth. Coefficient Irv Measured Value ac =.
-.: .
- 9.-/ I p~m /ppm I Design Value I B
(Actual Conditions) ac B
=
- 8.~o .+ - 0.8(c pc.,m I PPM t
Design Value I (Design Conditions) acB = -8.60 +/- 0.86 per.:.
- p~m I Reference VEP-FRD-NFE 107 I Reference FSAR Section 14.2.5 lvr O::ll!!e!l.tS.
Design Tole.ranee is met . : ~,YES O:No
- Acceptap.ce Criteria is met: ,E::'rr*s O NO I
I b:M~::\:<:py....!'\('Q.1,~
I Completed Evaluated By:
Reviewed By:
C-:J ~'1'..A_;
- G NFO En 0 ine("r I A,11
- ,uJ:UI.Y J:'UWJ::K ::iTATlUN UNlT "L. CYCLE .'.> ::i1AKlUJ:'
- 1. STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 111\1 f\ 1 r"\11'"9 II 1("\
JUL 3 1 1980
. J JA \lr\L. !\C...)U LI v .
Test
Description:
Isothermal Temperature Coefficient~ ARO Procedure N=bcr / Section! PT28.ll/ App. D . Sequence Step NUI:J.ber: B ltII SDA: 228 Bank Positions (steps)
SDB: 228 CA: 228 RCS Temperature (°F):
Po~er Level (! F.P.): 0 547
- onditions
. CB : . 228 cc: 228 CD: 228 Other (specify):
resign) Below Nucle~r Beating III Bank Positions (steps) RCS Temperature (°F): S"\3 - s4 Co 1 Test.
ditions (Actual)
SDA: 22.8.
CE: 2.28 SDB: Z..28.
CC: Z28 CA: 22.8 CD: Z.c,C/
Po~e.r Level (k F.P.): o Other (specify):
I...
Date/Time Test 8/IS /eo Perfonne:d.: o rSS- 0825 Measured Pa:=Emeter (description) (a ) Isothermal Te.=iperature Coefficient - ?_~o Trso ARo
}.ie.asured Vtlue aT =
ISO - 2,50 ~ F Te.st Design Value (Act1.:.2.l Conditions) lI C!
'T'
-rso
=
-3.05 ~rF Design Value
= -3. 69 +/- .3. 0 I pcm/"'F (C =139~ ppr,)
(I (Design Cond:..~ior.s) T B ISO I Reference E-;,-fi'J)-11:?E 107 I V ceptance Criteria FSA?/Tech Spec a TISO I Reference TS 3.1, VEP-~NFE 107 I VI
.o *..!!:!e.nts Design Tolerance is 1:1et Acceptance Criteria is r;:ie.t: l)l' Y~S0 NO
- ~
- 1..!:.S D HO
¥ Uncertainty on C!T -:;:- 0. 5 pcm/OF (Re ferenc~: r.emorandum froIP I * ~OD C. T. Snow to E. J. Lozito dated June 27, 1980)
/07 U516N Vl/1..J.1c, {te..Tt)fr<- ~pmow5 Ex.~f):)LtrT£D F/2.DM 'Dfn11 1N NF£ Tc--ct+N,u.L ';
I
- 5vfZP-'/ C, Cvc..LE 5 ~~/ G,.V .k!!"Fb~,
Evaluated I
I A.12
. SURRY POw"ER ST.A.TION UNIT 1. CYLE ~ ST.ART@
I. STARI!P.' prtNALTS R~';::u Af,'I) EVALUATION SF.EET JUL 3 1 \980
\L0 LTS I Test
Description:
. Isothermal Temperature Coefficient - B Bank In
,,D Procedure Number I Section: PT2.8. li/ App. D Sequence Step Number:
er2.nce /3 Ilt II ditions esign)
SDA: 22~
CB : 0 Bank Positio1:2s (steps)
SDB: 228 cc : 228 CA: 228 CD: 228 RCS Terr.peratu:re (°F): 547 Power Level ('" F.P.):O Other (specify):
,~
- Below Nuclear Heating I III Test:
l Bank Positions (steps) RCS Te.!I!.p era tur e (OF): 51-(:,
Po1.-1er Level (% F .P.. ): 0 8,ditions SDA: 22.f SDB: 22.~ cA: ccS' Other (specify):
ctual) CB: 2.1 CC: 22;:i CD:22.~
f3e{ow AJ vc...l ear He.a.+/-i~--
8f~/8o I Date/Time Test Perforl!led: 01/,St - OW J I IV Measured Parameter
( des cripticn) (a.Trs~) B Isothermal Temperature Coefficient - B Bank In I Heasured Value a.
TISO
= - S-,., 3? pe,rn /°F (c8 = /303 ppm) le.st l:::,ults Desig;:: Value (ActU2.l Conditions) aT.
=
.. 0 / :t 3.o pc.,m /op (c 6 :J3o3 p,orn)'
I I Design Value (Design Conditions) a = -6.17 - 3.0 pcm /or:-. ( CB = 1258 p;:,~.)
Trso I Re.fe.rence VEP-FRD-NF::: 107 I
-I- - ' t .
V
~,e~t2.n~e riteri2.
FSAR/Tech Spec a Tiso
..:S.. 0.53pcm,"'
Op a
a T1100 Toop
=o.
Trso
=-1 97pcm
-a OF Toop-
- op 1
<3 oPCIP 1 Reference TS 3.1, VEP-FRD-luE 107
- 1
- VI
. Design Tolerance is met : R-r.'ES D NO fe.n_ts -::
Acceptance Criteria is met : g(YES ONO Un cc rte. in ty en a.,, ~ 0.5 p .....~ P1,,o~ r ( Pe fe rer, ce:: rn:~ nor <'"l n :i um from
-~-*
- 1*:0D -
I c. T. Sno~. .,, to E- J_. w::ito. -dat~d June 27, 1980)
-1 Evaleated By:
I A.13 Reviewed By:
I SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP JUL 3 1 1980
- - - , - - ~ . , . . . . . . . . . . . . . ~ ~ ~ - - - - -
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
-1 I. Test Z, ARO erence Procedure Number/ Section: PT28.2, OP-57 "Sequence St:ep Number: / ()
II Bank Positions (steps) RCS Temperature (°F): TRef r ..
SDA: 228 SDB: 228 CA: 228 Po~er Level (Z F.P.): '\-0
- l~itions fflesign) CE : 228 cc: 228 CD: 228. Other (specify):
Must have> 40 thimbles III Bank Positions (steps) RCS Temperature (°F): -.SY1° F Test ?o;.;er Level (7. F .P.): ..... ~ '7 0 Other (specify):
1 ditions ctual)
SDB: 1..2lr CC: 1:l..~
CA: :2..:2.~
CD: "2..1 l:. 41- n:. . . ble...S I Date/Ti!lle Te.::-t Perfonned:
~R~ _NUCLEAR I IV Me.a.sured Parameter (description) ENTHALPY RISE ROT CHANNEL FACTOR FQ, TO~.L EE.AT FLu..Z HOT QUADR.~~T POHER TILT CE...t..NNEI.. :FACTOR RATIO (QPTR.;
I Measured value
~.o 7o -fo,. ~-" ~ 1.02 IO.::i7o fa..- ~s:o.\-l3 l.L/Co2 /.022 !
l
<>sr ults I)esiE::l ve..'.i..ut::
(Actual-Cond~tions) t I~ lo. +o- P.*z -~
+/-.1s'Z-for r.-~.q L- 1.0=-
I Design Value (DeEign Conditions) ilOI for 11 1
.!.
- 9 il.5: !or i i < .9 *rNt.~ --=-
' l .~0 ;,-(1~'. 2(1-~))
\.- .. : [} ,~
_T '~) < 4. 36 X K (Z) I 1-
< 1.02 I (? :1. - A.arr,. ?v::.)
i I
1
-:.P- 7Cr-,-:-
Re£erence II ?*.s *.-. :..
Rev. 1 NONE V
None NA NA
~=~=:~:
.---~c;.--G.
- FSAR/Tech Spec .NA TS 3.12 ~nC o.e~cra~du=. 1 from E. J. Lozl~O to Refer~ce None TS 3.l2 'r. A. Peebl1:::s d.otc~ TS 3.l2 July 15, 1~80. 1 Design Tole.:::-~ce is me:: : D YES 0 HO S,_e Cc=~-:7 &J..:.,"
Acceptance Criteria. is met:: 0 YES D NO I
Evelt12ted 3y:
Revie;.:ed By :
I A.14 l\FO Enginee:-
.I SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP JUL 3 1 1980
. STARTIJP PHYSICS TEST RESULTS .AND EVALUATION SHEET C'll\l/\1 nc01 11 TC.
J u ~' \L. 1\1-VUI- i--0 I Test
Description:
M/D nux Map - BZP, B-Bank In rence Procedure Number / Section: PT28.2, OP-57 Sequence Step Number: 14 I.1 Bank Positions (steps) TR; ttions SDA: 228 CE :*o SD:B: 228 cc .. 228 CA.: 228 CD: 2)8 RCS Temperature (°F):
Pov er Levtl (% F. P.) : '\.Q ,e Other (specify):
-I sign)
- Must have> 40 thimbles III :Bank Positions (steps) RCS Temperature (°F): --SL/7 °F Te.st Po-..er Level (% F.P.):-.0°70 1:~) SDA: 1.1 '2
~: ~'-1/3~
SDB: 1.2i CC: ?..2.~
CA.: '2..'2. $?'
CD: '1..°22 Other (specify):
S0 T~.~ble..S I Date/Time Test Pe::-for.::cd:
iln.l~o 0,13 -- ..
- Eh, I-IV Measured Para:!leter (description)
MAX. REL. ASSY Pw"?... ~-DTu-"T.
(~
NUCLEAR EN'l1ll,.J.PY RISE HOT CHANNEL
~Q* TOTAL HEAT FLUX ROT CF..PJilE.L FACTOR RATIO (O?TR)
QUA.DP..Al\T POi,ER TILT t'
. FACTOR I Measured Value f'or l"l..Sbr r..* a o.q </
Bi-9: 0.$2. 1. ioeo J... ~o '7 /.00(:,2_
Jest..llts I . .
I
. Design V2lue (Actual Conditions)
Design Value I +/-io"%.
iJSh hr-r.
Tor
~C:: !.,,r l' 1
P>
- -. ~ I P.*L.~
!_
- 9 NA Nt I
I -/ Jo~ . . .:...
(Design Co::::idi ti.ens) NA ..., ....... 0..::
~ : fer l'i < .9 I Re:fe.re!:lce Cl' i - Aa:rry. Pvr.)
WCJ...?-7905 ~*7t:J..:P- 79 :, :
- v Re.v. l I NONE !;ON~ Re\- . -
leptance FSAR/Tech Spe C None. NA" .NA I NA
- iteria I
I Reference*
I None *TS 3.12 TS 3.12 I TS 3.11
,~:s VI Design Tolera.nce :is .::i.et A_ccepta.nce Criteria is me=: IB.l YESO NO
- ~-ITS0 HO I
I Evaluated By: -'o~.....* .ti.. &2,c::'Y-yt~
~:::...:.._~...c::::c=..J~-""""=-_,__-
Revi eimd By: (. :f ~..;--.,J I A.15
_ . : : _ ~_ _ _=-.::.;:::..._~--,---
NF O Engineer
SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP
, STARTUP J=1Tf\{s TEST RESULTS AND EVALUATION SHEET JUL 3 l 19 BO
-
- Al RJ:"~111 TC
- ---&...1'\,J I I Test
Description:
M/D Flwc Map - At Po-wer, NI Calib.
1 erence Procedure Number/ Section: PT28.1, OP-57 Sequence 5-tep Number: 44 II :Bank Positions (steps) RCS Temperature (OF): TRef
~est
- lditions SDA: 228 SDB: 228 CA: 228 'Po'wer Level o: :F. l" * ) : ...,40 esign) CB : 228 cc :* 228 CD: Above Otbe.r (specify):
Insertion Limits Must have > 40 thimbles I III Test:
- Onditions SDA:228 Bank :Positions (steps)
SDB: 228 CA: 22.~
RCS Temperature .(OF): ~ef+/-l*
Po-wer Level (7. :F.:P.):
Other (specify):
'f-3 CE:2.28 cc:2.a8 /70 lctual) CD:
s-o t:h irnb\e.s Dat.e/T:b.e Tesr: 2./20/80. ...
I PerforI!led: 0'121- /2.c..l Measured Pa:.:-2'.!!)eter MAX. R.EL. ASSY ~. NUCLEAR FQ, I TOL.U. 1IT.A.T .QUADRA.1\T FLUX BOT IIV (description)
,~~Dux.
ENTilAI.PY RISE HOT CHA..1-"'NEL F.ACTOR POWER TILT CF.J._""lliEI. FACTOR RATIO(OPTI:
6 /1 o/o ~-~ ~1. oz I Measured value 5".1?o I J
fa-!: ::a,'H / 0 l/-~ lo'1?S /,0/01
~
lest ults Design Value (Act't!.21 Cond~!:ic~s) 1+/- to% for f;
+/-1s-'fo +t,r- P; ~. ~
-;,,e; I NA. NA I
~loo?..
I Design Value (De.sign Condit:ions)
- ,ic: for P 1
~
- il.5% for Pi <
- 9
.9 NA NA
-< l. 02 0'1 * .ury. h-r.)
I P" e. f e:;:e:n c::.
WCAP-7905 Rev. 1 NOKE NON.t.
WCJ.2*- 79 C*.:
!<Ev. '
I V
,cceptance FSAR/Tech Spec None .FN ti.H -
< 1.55(1+.2(1-p)) F~(Z)*.::_ 4.36 ~ K(Z) NA lriter:la IS J.12 and ~t~ocandc::::i froQ E. J. Lozito co Reference
!. A. Peebles dateC July 15. l9SG.
. Design Tole~2:1ce is met . : )3:.1::s D HO Acceptance Criteria is me.:: fil:°YES 0 NO i,e.n_ts I -
I Evaluated By:
I A.16
*--*--*-**- - *- --*----- -.:,uiU\.i -.[Ut',.C..1'1. .:lJ..t'..J..LU11 U!\.LJ.- L 1.,i1.,.1..,.c. ..J .:JJ.~.I.U.C I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET t:"11\ I/\ I Mir-1'1 I! -:-r-.
JUL *3 1 1980
_. _u 'JJ-\1.. f\I.:.0 UL j ~
'Iest
Description:
M/D Flux Map - At Power, IU Calib.
Procedure Number / Section: PT28.2, OP-57 Sequence Step Number: 4S
~III SD.A.: 228 Bank Positions (steps)
SDB: 228 CA: 228 RCS Temperature (°F): TRef.
"Po..ier Level (.! F .l'.) : "'.50
- Onditions sign) CB : 228 cc: 228 CD: Above Other (specify):
. In~,ertioI: Limits Must have> 40 thimbles III Bank Positions (steps) RCS Temperature (°F):i,~~ :t l J Test tlitions (Actual)
SDA: 2~~
CB: 226 SDB: 2. '2.8
- CC: 2'2.8 CA: '2 28 CD: 183.//6 'i l'o'Wer- Level (% :F .P.): SO .
Other (specify):
-I I
Dat.e/Time Te£~ (f8/2. I /f3:1:y Performed: 00 '3:. I_ 0 e..i~
Measured Paxa:oet.er MAX. REL.. ASSY ~ -E, NUCLEAR F6,* FLUX TOT.AL EElJ QUADRANT (description) !'WR. i Diil'. ENT!~ UPY RISE EDT ROT PO~*.ER TIL'I tv (~~~)
-1,.S."'?S:Or P::.\,10 CE..ANNEL FACTOR CH..A..NNEL FACTOR RATIO(QPT?-.
Measured Value 1,909 \.oo<;l~
fl, o,t..tt; ITest 'Desig-:i v ci. ue *
- 1
+7,S )"ct" (Actu.2.l Conditions) NA ~ 1.02.
Design Value I (Design Conditions)
(l'i
- Any. Pv:.)
NA. < 1.02
. '*'C"P-7-9i*=
I Reference WCJ..?-7905 Rev. l I
,, .l""-
?~-"*. =-
v !
I I I NA
- I ept:ance Criteria FSAR/Tech Spec None I i:;
r~H ~ 1.ssc1+.2(1-?)) Q -
?
FT(Z) < __ le, p
X X.(Z)l 1
' TS I Reference None TS 3.12 I
3.!2 and oe=:=oranduc fro~~- J. Lozi[o to T. A. Peebles carec July 15, 1SBO.
TS 3.l2 Design Tolerz..nce is met : Il:g ::ES D HO Accept:a.nce Criteria is ::::iet:: ~YE.SD NO I
i - -- r*.. .. r-Evaluated By: b- 'M V,0..9-,. ~l'.:h..,~.
- Revie..;ed By:-:- r /( ,+Z-u . c.
NFO Engineer I: A.17
SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP
.I STARTUP "PHYSICS TEST RESULTS AND EVALUATION SHEET JUL 3 1 1980
[""1\\.11\ 1 DC~I 11 T~
i jj \,I/ .a... I\L-'-"--'
1 Test
Description:
M/D Flux Map - At Po.;,er, NI Calib.
e rence Procedure NUI:lber I Section.: 1'T28.2, OP-57 Sequence Step NUI:Jber: 4-fo II :Bank Positions (steps) T P.CS Te.Dperature (OF): . Ref liticns
( sign)
SDA: 228 CE :2is SDB:
cc 228
- 228 -
CA: 228 CD: Above
- Insertion Limits Po,.,,er Level (! F.1'.): '\,60 Other (specify):
Hust have > 4*0 thimbles I III Te.st Eank. l'ositioI!.S (steps) . RCS T e!:!p era t: ur e. (Of): T\"')-
Po-wer Level (7. F.:P.): 61
+/-l
- ili"tions
( tual)
SD.A:<- '<-2>
q.: 1.2..~
SDB: 'l. "2. 2, CC: 'L'2..3 CA.: 2._2.8.
CD: 190 Other (spec.ify):
Y9 t~~""~\es og/2,i IB6 ..
I Date/Ti:me Test J:'erfor.ned:
'2.\01 - c. ?:,07 Me.2Sured ::?ar2!l!eter ASSY %, NUCLEAR .?Q. I I IV (description)
MbX. REL.
1i;~ DI=:.
~'TB...A...Ll'Y RISE BOT CEAN"NEL "FACTOR TOTAL EEA.T FLUX ROT I
QUADR.Al~T ro:rrn TIL':
CE.l~-Nil. "FACTOR RATIO (QPTR; I :He.as-cred valu.~
+.S,o H,,l S-e.(
~~
~ =.
P-:..
l,oo O,l;'i 1,Y lb l,65Lf \, 00~ L/
I l t \0%. s:o , t> l Jr ts Desig::i vc..l ue (Actuzl Conditions) t 15 °/c,
~
<;o"(" ?.c.o.~
o.9 N'.tl. NJ.* L. l , 0*'2..
I Design Value (Des:i.g::i Ccnd..:i.tiou.s) tlO! :fer ?' 1 il..5: for
.!.
- 9
- P 1 < .9 NA NA I~ l.O:
(Pi - ~*Y* :Fv..)*
I I
Iv Refe.:r-ence l wLl.P-7905.
Rev. 1 NOl-t"i: NO~i.:2
\~?Ci~-7?*:.:.
F-.e *.-. -
cceptznc.e FSAR,/Tech Spec None ~ F:H ~ l. 5 5 ( 1+
- 2 (l-p) ) F~(Z) -< 2.18 p
. "!Z)
X .. , NA fteria 1 TS 3.12 anc c,c::ioca~e= I r
Refer~c.e I
Desi~ Tole.r2=1.ce :i..s :;:::ie,:
None
=El ~so NO TS 3.l2
.from ::. J. Lozi:o to
!. A. Peebl~s date~
July 15, 1960 .
7S 3.1:
VI Accept:2.nce Cri.t:eria is met:: W YES0 NO T*t.s I .
I
! I Completed* B)d J. (1Lng*v' )./1,L"'rr~ Evaluated By:
. -.. I Ies;/ eer Revie,;..*ed By:
I -.
A.18 NFO J::ngineer-
SURRY PO"l-.7ER STATION UNIT 2 CYCLE 5 STARTUP
.I STARTUP PHYSICS TEST RESULTS P.ND EVALUATION SHEET JUL 3 1.\SBO
,, .... i.,,- ---* .. ---
I Test*Description: M/r V1~l\kp _KJ:i~-JJ~1n! ~ Calih.
P,ef ere.nee Procedure 'NUI:1ber I Section: PT28.2, OP-57 Sequence Step Number: 47 II Bank Po-si tions (steps) RCS Temperature (OF): TR e ...~-
Test SDA: 228 SDB: 228 CA: 228 Po-wer Level (: F.:P.): 1\,70 lnditio-:is Design) CB : 228 cc . 228 CD: _* Above
. Other (specify):
Insertion Limits Must have~ 40 thimbles I
~Dditions III Test SD.A..: 2.22
- Bank Positions (steps)
SDB: 2.28 CA: 22.8 RCS Te11:perature (OF):
l'o-wer Level (7. F.P.):
Other (specify):
'Ref :t I 7/
I.Actual) ~:B: 228 CC: ?28 CD: /~S "LJ-6 t1) *1Mb/~
Date/Time 'Iest 8/~/ao * ..
I Performed:
JS38- /757 Me.asured "Par2::ieter ~t....""'{. REL. ASSY ~ , NUCLEAR F~? TOT.AI. EAT QUADP-6.NT I IV (description) PWR. ~ DIIT.
e1; ENTHALPY RISE HOT GaA..NNEL FACTOR FLUX ROT
~"lliEL FACTOR PO:l:C:R TILT RATIO(QPTI, r
S.J 'Jo J P6 _, =1.00 I Measured Value
,., % J PB-6" =.lf-lJ- /o'/-/0 ,
- 8'fc. I.005" 2..
I+. q, Ai ~
fuits 'Ies~ 1'esi~ value
(.A.c'tt*:,., Conc:i-.:ions)
-10 0 )
+/- 15"%) P,*~. "f
- '1 ,.,
!.\A NA L... 1.0.::
.. ilC: for ? 1 !.. .9 I Desig:i Value (Desi.g:1 Conditions) :.U: !c-:: l'1 < .9 Cl' 1
- J.uy. ?-.-:.)
F'=- NA -< l. o::
I ltef e.:-e=ice WCAP-7905 Rev. l IIt,~~:_. ~...--
-:.o,,
7-=- -,=
J' -.
NOkt. NOIE ...
- *I -
I Acceptance V
FSAR/Tech Spec
- . None f ;,,.,. ~ 1.5.5( 1+. 2(1-p)) . FT(Z) ; 1..:.J& x K(Z)
Q . - p I
NA
- ICriter~a TS J.!2 and ~enora~d""'I frot:.i :. .. J. Lo:::.to to Refere..""1ce None TS 3.12 !. A. Peebles catec TS 3.12 July 15, 1980.
Desi~ Toler2.nce is met * :2(YES D 1W VI Acceptc:..!lce Cri-z:eria is met:: .S:,YES 0 NO
- 0 c:::! en ts .
I -
I - .
I Co~pleteci Evaluated By:
I A.19
SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP I. STARTUP PCTif)\ psT RESULTS AND EVALUATION SHEET JUL 3 1 1980
, f'"\r-nl II --r,,
1 u '.inL J \C~UL i ~
I Test Descript:ion: H/D Flux Map - At Power , NI Calib.
'Refe-rence Procedure NUI!lbe:r I Section: PT28.2, OP-57 Sequence Step N=ber: 48 II Bank J?osi tions (steps) RCS Tempe-rature (°F): TP.ef 1'est SDA:228 SDB: 228 CA: 228 Po...,e:::: Level (Z F.P.):""90 lnditious Other (specify):
Design) CB : 228 cc : 228 CD: Above Insertion Limits Must have > 40 thimbles I
RCS Temperature (OF): °TieJt I III Te.st Conditions SDA: 2.~'8 Bank Positions (steps)
SDB: 2.c.8 C..A..: 228 Po...,er Level (i: F.P~):
Other (specify):
~~
/
'Actual) CE: 2. 2.8 CC: 228 CD:/ CjO 4-J) i:h;mbleo Date/Tfu.e Test 1 /1/ 8.o .
I .
Performe~:
Meas.urerl Pa= aE e. t er
/OS'f - /332..
MAX. REL. ASSY F;!
lill, 1'.uC'"LEA.R F'T', TOTAL EEA.7 Q'JJ..DRA,\"'..
Q.FLUX liOT I (description)
(r1;f DIIT *. EIT'.d.A.LPY RISE E.OT ?OlJER TIL':"
IV
. 1 CR...;Nl.tL FACTOR G1-~\'"NEL FACTO:i:{. R!,TIO (Q?TI;:
L/-. / ?o J P6 _,: .18 I Measured Value 5,CJ ?o I ..:..,on.
1 PA-., = .1-5 pi ~
- c; I I 1>318 / o 7CJO
/. 0075° fuits Test: Iies::..g:r V<UUE:
(Act::.2..2. Conditions)
. .!.. ,* 10 )
+/-. ISf.:,J pI. .: :_ , I C
NJ. l.",.
J.1....-..
LJ,02.
. :.l.O! fo:: "1 !. .5 .
I Design Value (De.sig::i Conditions) :..:....:s:: !c=
1
]4
(?i
- JJ.a;. P-..-:.)
< *9 l\.n N..!,. -< 1. 02 I. WCJ...P- 7 9 05 I ....... -
1**--:..-=o-7ar,: --
I Re:ferEnce Rev. 1 I NO}~
I NG:~ : --= ,*. ::..
i i'
,. V cceptance FSAR,/Tech Spec None f~H j_ 1.55(1+.2(1-P)) FT(Z)' 2.18
- K(Z)
Q - p I NA Criteria I .. I" ,.n ,oO ceamoO,,
I i
I Refere..:ice frn:: E. J. !..c:i:c co -. : ,__
None TS 3.12 ~- A. Peehles d::i:cc! 7S _j. ---
.. July 15, 1g130
- I VI Desi£!:. Toler2.nce is net Accept:2J.Jce Criteria is ~et::
=A~.:.S 0
'A YES D EO NO Co=ents I -
I -
I Co:::Dletec Evaluated By:
Revie ..... ed By:
_"'_er_.!"'~* ~/~---=*
K....::
I A.20
~rn E:1ginee:-
_I SURRY POWER STATION UNIT 2 CYCLE 5 STARTUP STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUL 3 1 1980 i <.)
7est
Description:
Flm:: Map - HFP, ARO, Eq. Xe. Map ence Procedure Number/ Section: PT28.2, OP-57 Sequence Step Number: 4,q Eank Positions (steps) RCS Temperature (°F) :* TRef
.st SDA:223 SDB: 228 CA: 228 Fove.r Level (! F .P. )-: 100
,1tions
.
- ign) C:B : 228 cc: 228 CD: Above Other (specify): Equil. Xenon Inserti'on Limits Must have> 40 thimbles Ea.nk Positions (steps) RCS Te.Eperature (°F):T*.fF+/-I
'Po'w'er Level (% 'F.i?.): /oO SDA: 2.'l.l/ CA.: '2..'2. ~ Other* (specify):
CB:"')..2~ CD: 2.JS Y q T~ ,*""h/e.5 I Date/Time Ter.r
- Performed:
Me2SUI"ed Pa:.:2!!e.ter MAX. REL._ ASSY Jt:1°ci3: NUCLEA...-q, F'.J;, TOTAL EE.AT 1
QU,'.DR..',!'iT l (description) 11;/) DIIT.
S.3% 1P5 _" ;, -~~
ENTrl.£...1.PY '
C:BANNEL FACTOR RISE HOT I.('. FLUX B.OT CRJ..NNEL FACTOR! RATIO(O?TR'.
PO:*:£?, TIL7 I Measured Value C~7::i 1 PQ.-s L . '-)i.{
J. 3~7 1.7/(=, l1.00S.3 I
I . ~ r r, I
~
ts i) esign ~ 2....:.. U:
(AC 't 1:.2.l Cm:1di t:i.ons)
!_ /Cl /~
--t" 15 !,
't"='r
--+er ~ L i- ;,
.9 NA K!~.
1~
j
/. :1-_
I Design value (Desig-;::i Couc.i t:ions)
~o:
~:
!or for
- r 1 r1
~ .9
< *9 NA NA I~ l.02
. (1'1
- J..asy. ?=.)
I I
- I Refe-r-e::ice.
WCA?-7905 Rev. l NONE NOl:I.
I;*, c;.::- -
! :*= *:. -
I 7 s c=
I Iv
- ceptance FSAR/Tech Spec None Jl
- C AH ~ 1.55(1*.2(1-P)) ~ F~(Z) -
,: 2.18 p
X K(Z)
NA lite.ria Re.£ ere.nee TS J.12 .and :oe:::ura:'\cc::::
f:-oe: E. J. Lo=l:-.o to I ..,..~
Nor1e TS 3.12 :. A. Pe~blcs dateC J'"ly 15, 19SO.
... .::, .:; * .l.-
Design Tole:-2nce is me.t : i8i -:=.S 0 NO VI T*ts Accept2..:J.ce Criteria is r:et: 19 YES0 NO
- 1 Evaluated By:
Reviewed By:
NFO Engine£"r A.21
.Slifi"!.Y rm:rn. SL\TIO:~ u~a~: ;2_ CYCL:S ~ ~';:]J,.:rur STJ>Jt~fU:f> l'HYSICS n.:~;rs RES1JL1'S Alm EVALU/1TlON SHEET JUL 3 1 1980 FINA[ RESULTS.
I Test De scrip tJ.on: RCS Flow Measurement .
[ e:.nce: Procedure !*lu,-:,ber / *section: ST-52 Se::qucnce Ste.p Number: -5'0 II Bc:.nl: Position~ (s tcps) .. RCS Ten:pcra ture (dF): TRef SDA:228 SDB:228 CA:228 Pm-ier Level (7. F.P.):100
~,ticms Jesign) en :228 cc :228 CD:Above Other (specify):
Insertion Limits tLfo~ ih:,e3..ee! Heet:j: *. h ::n\L 9/18/80 tr Test Bank Positions (steps) RCS Te!!'.peraturc (°F) :TR.eF":!:. I Power Level (% F.P.): 100
- iltions SD.P.: '2.:2..8 SDB: 1.""2 <a CA: 1."'l. ~ Other (specify):
~- ual) CE: 2.1<a CC: 11~ CD: '1..IS Date/Time Test 9 I 11. I So Pcrf~rn.ed: .O'it/0 - /OL/0 I Hecsu!."ed Parair.eter (description) FTOTAL RCS '
Total RCS Flow Rate IV I 2-Icc.si..rred V2.lue FTOTAL
= 193) 5yq 5f rr-.
RCS It
-**i 't- Co I.:e:sigu V2.lu~
(Actual Ccnditicns) Not Applicable I
I Design Vah.1e (Design Con:ii tic=.s) Not Applicable
.I l I~e.ferenc.:e Not Applicable L I l - -n.s ltan~e V t2r1a FSAR/Tech Spec FTOTAL RCS
/1. 02 .:'... 265 '500 gpm
-*--- r~AR ~ection 4.1.j; Let~er :re= C. H. ~t~.L 1ngs l*epco) --*
-, to H. R. Denton (!;;:'.C) cated ~lay 31, 1979 (S.,,::-ial ,;o. 383);
I P'"e.ft2rence ~*
Letter from C. ., . Stallings (Vepco) to E.. G. Case: (1";:C) dated Nove~ber 16. 19i7 (SC?,i"1 Nn. 516)
~Cs I Desif.11 Tc*lcr.:c.r,ce is wet : l8i YES D ;;o Acccet_~_.r:_:~_~_~_c_¥_~_i_t_e__r_i_2~i-s~~-*~_t_=_~~-1-*~_s_o~_~_;c_J~~~~~~~~~~~~~---~~~~~~~~~
II I- I .
I_ ~C'c:p11.'t('.(;* J;yd, ~
- 1~~t
-~- . -
l:\.*.:~ 1. :..:;4 t ~J ~J:
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