ML20011D446
| ML20011D446 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/08/1989 |
| From: | Dziadosz D, Ford C, Nicholson A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18151A668 | List: |
| References | |
| NE-757, NE-757-R, NE-757-R00, NUDOCS 8912270240 | |
| Download: ML20011D446 (60) | |
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_o . - 'r :n, +y , 3 % t, ,, . n ~ :s . i ' F VIRGINIA POWER t' 5 I ( i. e > ?.' TECilNICAL REPORT NE-757 - Rev._0 SURRY UNIT 2, CYCLE 10 .STARTUP PilYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER DECEMBER 1989 PREPARED BY: O t Undw CAM A 11. Nicholson Date REVIEWED BY: hI ~8 7 C. A. Ford Date APPROVED BY: k D. Dz 6dosz Date QA Category: Nuclear Safety Related Keywords: 52C10, Startup CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Elcetric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever.' express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARD!lTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report availabic, +he Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liabic, under any Icgal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it. l l l NE-757 S2C10 Startup Physics Tests Report Page 1 of 58 '/(f TABLE OF CONTENTS 5 \' PAGE 1 Classification / Disclaimer............................... Table of Contents....................................... 2-List of Tab 1cs..................................'........ 3 ~ List'of F1gures......................................... 4 Preface................................................. 5 Section11- Introduct ion and Summary . . . . . . . . . . . . . . . . . . . 7 -Section 2 Control Rod Drop Time Measurements......... 16 Section 3 Control Rod Bank Worth Measurements........ 21 ~Section 4 Boron Endpoint and Worth Measurements...... 26 Section 5 Temperature Coefficient Measurements....... 30 Section 6- Power Distribution Heasurements............ 33 Section 7 References................................. 40 APPENDIX Startup Physics Tests Results and Evaluation Sheets........................ 41 NE-757 S2C10 Startup Physics Tests Report Page 2 of 58 i-s ^r \ l' LIST OF TABLES-TABLE' TITLE PAGE
- 1. '1 Chionology of Tests................................... 10 2.1 Hot Rod Drop Time Summary............................. 18 3.1 Control Rod Bank Worth Summary........................ 23 4.1 Boron Endpoints Summary............................... 28 5.1 Isothermal Temperature Coefficient Summary............ 32 6 .1 - Incore Flux Hap Summary............................... 35 6 .' 2 Comparison of Measured Power Distribution Parameters With Their Technical fpecifications Limits............ 36 NE-757 S2C10 Startup Physics Tests Report Page 3 of 58
4 i LIST OF FIGURES FIGURE TITLE PAGE '1.1~ Core Loading Map......................................... 11 1.2 Beginning of Cycle Fuel' Assembly Burnups................. 12 1.3 Incore Movable Detector Locations........................ 13 l'4- . Burnable Poison and Source Assembly Locations............ 14 1.5 Control Rod Locations.................................... 15 2.1 Typical Rod Drop Trace................................... 19-2.2 Rod Drop Time - Hot Full Flow Conditions................. 20 ~3.1 Bank B Integral Rod Worth - HZP.......................... 24 '3.2 Bank B Differential Rod Worth - HZP...................... 25 /4.1 Boron Worth Coefficient.................................. 29 6.1- Assemblywise Power Distribution - 30% Power.............. 37 u 6.2 Assemblywise Power Distribution - 64% Power.............. 38 6.3 Assemblywise Power Distribution - 100% Power............. 39 + l NE-757 S2C10 Startup Physics Tests Report Page 4 of 58 s k PREFACE This report presents the analysis and evaluation of the physics tests which were portormed to verify that the Surry 2, Cycle 10 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard test techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at the Surry Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results w.ith design predictions, and an evaluation of- the results. The Surry 2 Cycle 10 Startup Physics Tests Results and Evaluation Sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values of the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Groupl . 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 comparison between NE-757 S2C10 Startup Physics Tests Report Page 5 of 58 --y . - . . - . .. , ,,x-
- a. , ,,
t 7 m , . measured and predicted test results, thus enabling a quick identification of possibic problems occ-ring during the tests. .,.r' s-51-; NE-757 S2C10 Startup Physics Tests Report Page 6 of 58 SECTION 1-INTRODUCTION AND
SUMMARY
On September 10, 1968 Unit No. 2 of the Surry Power Station shutdown for its ninth refueling. During this shutdown, 77 of the 157 fuel assemblics in the core were replaced with 52 fresh fuel assemblies, 17 once burned fuel assemblics, and 8 twice burned fuel assemblies. The tenth cycle core consists of 10 sub-batches of fuel: five once-burned batches, two from Cycle 9 (batches 11A and 11B), two from Surry Unit 1 Cycle 6 (batches S1/8A and S1/8B), and one from Surry Unit 1 Cycle 8 (batch S1/10); two twice burned batches, one from Cycles 8 and 9 (batch 10), and one from Cycles 7 and 8 (batch 9A); and three fresh batches (batches 12A, 12B, and 12C). Fourteen of the batch S1/8A and S1/8B assemblies' are reconstituted, containing a total of 26 solid zircaloy rods. The three fresh batches are of the Surry Improved Fuel (SIF)
-product design. The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The incore movable detector locations are identified in Figure 1.3. Figure 1.4 identifies thet location and number of burnable poison rods and source assemblics for Cycle 10, and Figure 1.5 identifies the location and number of control rods in the Cycle 10 core.
On September 16,1989 at 19:59, the tenth cycle core achieved initial criticality. Following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the results of these tests follows:
i
'NE-757 S2C10 Startup Physics Tests Report Page 7 of 58
ii 1.. The measured drop time of each control rod was within the 2.4 second limit of Technical Specification 3.12.C.1.
- 2. Individual control rod bank worths were measured using the rod 2
swap technique ,6 and the results were within 8.2% of the design predictions. The sum of the individual measured control rod bank worths was within 0.7% of the design prediction. These'results are within the design tolerance of il5% for individual bank worths (110% for the rod' swap reference bank worth) and the design tolerance of'110% for the sum of the individual control rod bank worths,
- 3. Measured critical boron concentrations for two control bank configurations were within 36 ppm of the design predictions.
These results were within the design tolerances and also met the accident analysis acceptance criterion.
- 4. The boron worth coefficient measurement was within 3.5% of the design prediction, which is within the design tolerance of 10%.
- 5. The measured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within 0.78 pcm/'F of the design prediction. This result is within the design tolerance of 13 pcm/'F, and also meets the accident analysis acceptance criterion.
- 6. Core power distributions for at power conditions were within established design tolerances. Generally, the measured core hE-757 S2C10 Startup Physics Tests Report Page 8 of 58
t-power distribution was. within- 4.57. of. the predicted power distribution. The heat flux hot channel factors, F-Q(T), and enthalpy. rise hot' channel factors, F-dH(M), were ' within the limits of their respective Technical Specifications.
In' summary, all startup physics test results were acceptabic.
Detailed results, specific design tolerances and acceptance criteria .for each measurement are presented in the following sections of this report.
\
NE-757 S2C10 Startup Physics Tests Report Page 9 of 58
Table 1.1 i SURRY 2 - CYCLE 10 STARTUP PHYSICS TESTS
!> CilRON0 LOGY OF TESTS
- i. Reference I Test Date Time Powe" Procedure i llot Rod Drop Timing Test 9/14/89 1842 HSD 2-PT-7.2
- Zero Power Testing Range 9/16/89 2232 Il2P 2-PT-28,11 L< Reactivity Computer Checkout 9/17/89- 0251 IlZP 2-PT-28.11 Boron Endpoint - ARO 9/17/89 0557 HZP 2-PT-28.11 Temperature Coefficient - ARO 9/17/89 0715 HZP 2-PT-28.11 ;
Bank B Worth 9/17/89 1124 HZP 2-PT-28.11 Boron Endpoint - B in 9/17/89 1330 llZP 2-PT-28,11 Bank.D Worth - Rod Swap 9/17/89 1420 HZP 2-PT-28.11 ,
Bank C Worth - Rod Swap 9/17/89 1459 HZP 2-PT-28.11 Bank A Worth - Rod Swap 9/17/89 1547 HZP 2-PT-28.11 Bank SB Worth - Rod Swap 9/17/89 1725 ll2P 2-PT-28.11 Bank SA Worth - Rod Swap 9/17/89 1808 IlZP 2-PT-28.11 Flux Map - 30% Power 9/20/89 0739 30% '2-PT-28.2 Flux Map - 70% Power 10/02/89 0727 64% 2-PT-28.2 Plux Map - 1/2 Calibration 10/02/89 0957 64% 2-PT-28.2 Flux Map - I/E Calibration 10/02/89 1350 64% 2-PT-28.2 Flux Map - I/E Calibration 10/03/89 0947 61% 2-PT-28.2 Flux Map - HFP 10/09/89 1638 100% 2-PT-28.2 NE-757 S2C10 Startup Physics Tests Report Page 10 of 58
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NE-757 S2C10 Startup Physics Tests Report else 12 of 58
Figure 1.3 l- SURRY UNIT 2 - CYCLE 10
!, INCORE MnVABLE DETECTOR LOCATIONS f R P M M L E J M C f f D C $ A r i i i i I l MD I i 1 i
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i NE-757 S2C10 Startup Physics Tests Report Page 13 of 58 j
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[ Figure 1.4 SURRY UNIT 2 - CYCLE 10 p BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS C.
R P N M L E J H C F E D C B A I i l i i i i
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l l 1 I i i I l- 1 1 20pm I i 20Pe I i 1 2 1 I l 1 1 1 l 1 I i i l i i i i i i l i 20Pe l 16P l l 16P l l 16P l 20Pe i i 3 L. 8 1 l t i i l I i l i l i I i i i i i i a 1 i i l 1 16P 1 1 16P i op i 16P l 1 16P 1 1 1 4 I i I i l i l i l i l i l 1 1 i i l i i l i i 1 1 i l I 70Pe i 16p I . I I i l i 1 1 16p i 20pm I l 6 1 1 1 1 1 1 I I I 1 1 I i 1 I I i 1 I i i l i I i i i i L
1 1 16p i l 1 i IFP l l 17P 1 1 $$4 l l 16P l 1 6 I I l l l t i I i i I f I I l i i i i l I l i i i i i l l 1 1 I 20P= 1 1 16P 1 1 17P l l 4Pe I l ITP l l 16P l 20Pe l I 7 l l l l l l l l l l l l- l--l l l l l l 16P 1 4P i l I spe i 4p i 4Pe i i I 4P l 16P l I i 8 I I I i 1 1 l l I i 1 I I I I i 1 1 I l i I i l 1 i i I i 1 1 l 20P= I i 16P 1 1 17P l 1 4Pe i 17P 1 1 16P I il 20Pe I sss I 7 1 1 I I I i 1 1 I I l l 1 l l '
4 i i i i i i l I I i i I i i i 16P 1 I 553 I i 17P 1 1 17P l l l l 16P i l 6 I I I I I I I I l t i i i i l i i l i i i i i l i l i 1 20Pe 1 16P l l l l l l l 16P l 20Pm l l $
l 1 I I I I I I I i i I I I I I I i l i l i I i 1 i i i 16P 1 1 16P 1 4P 1 16P 1 1 16P l l I 4 i i l I I I I I I I I 1 i i 1 i 1 i 1 i i i l l 20Pe i 16P 1 1 16P I i 16P 1 20Pe i t 3 ,
I t i l _t I l i I I I I I i 1 1 I i 4P - 4 TURNABLE Pol $ON ROD CLUSTER I l i 20Pe l i 20Pe i l l 14 16P
- 16 suRNeeLE P0150N R00 CLUSita 1 l i i i i l i IFP
- 17 $URNASLE P0! SON ROD CLUSTER 1 l l 4 4Pe
- 4 DEPLETED SURNASLE P0!$0N ROD CLUSTER l l i i 15 FDPS
- 20 DEPLETED SURNASLE P0l$DN POD CLUSTER l 1 1 1 SSm SECONDARY SOURCE NE-757 S2C10 Startup Physics Tests Report Page 14 of 58
l i
Figute 1.5 SURRY UNIT 2 - CYCLE 10 CONTROL ROD LOCATIONS R P N M L K J H G F E D C B A 130' i Loop C i i l l Loop B 1 Outlet I i l i Inlet i l lA 1 lD l lA l l 2 '
I I I I i l i I N-41 l l l l sA I I sA i l l I N-43 s I l l I I i i l_l i I ic l ls l l l le l lc l l 4 i l i I ~1 I I I I I I I I 1 I I I I sa l l sr 1 I se i I so 1 I I I s ]
I I I i l I I i l I I I l l l
lA I Ie l lD 1 Ic I lD l le l lA 1 6 i Loop c l l l l l l l l l l l l l l Loop e l Inlet i l I sa I i sr i I so l I so i 1 sr I i sA 1 l l Outlet 7 )
l I I l I l l I I I i l i I I I i 90'- 1 lD l l l lc l l l lc l l l lD l l + 270' 8 l l 1 1 I I I I I I l. I I I I I I l I I SA i i sr l l 0s 1 I ss l I se I I SA i 1 1 9 I I I I i 1 1 1 1 I I I I l l l lA 1 1a l iD 1 1c I ID i ie l lA I lo i l I i l l I I I I I I I I I l I I I sa l I sP l l se I i sa l I l l 11 1 I I I I i 1 1 1I 1 l l l l lc 1 ie l I 3 Ie I ic I i 12 I I I I I I i I i l i I I I I I sa l I sA l l l l 15 N-44 l l 1 1 1 l l I I I N-42 I IA I iD l IA I i 14 I I I I l l l l ;
I I I I - 15 Loop A l l l l Loop A Absorber Outlet Inlet Material i As*In-Cd O' Function Number of Clusters Control Bank D 8 control Bank C 8 Control Bank B 8 ,
Control Bank A 8 shutdown Bank ss 8 shutdown Bank sA 8 sP tspero Rod Locational 8.
.NE-757 S2C10 Startup Physics Tests Report Page 15 of 58
L SEC" ION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions in order to verify that the time from initiation of the rod drop to the entry of the rod-into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.12.C.1. The hot control rod drop time measurements were run with the L
RCS at hot full flow conditions (547'F, 2235 psig) and are described t below.
The rod drop times were measured by withdrawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The data recorded during this test are the stationary gripper coil voltage, the LVDT (Linear Variable Differential Transformer) primary coil voltage, and a 60 !!z timing trace which 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 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 r
by the decay of the stationary gripper coil voltage when the stationary 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. When the rod enters the dashpot section of its guide tube, the velocity slows causing a voltage decrease in the LVDT coil. The LVDT NE-757 S2C10 Startup Physics Tests Report Page 16 of 58
.- <--m p--
.s voltage then reaches a minimum as the rod reaches the bottom of the dashpot.- Subsequent variations in the trace are caused by the rod j v .
bouncing.. . This procedure was repeated for each control rod..
r The measured drop times for each control rod are recorded on Figure i 2.2. The slowest, fastest, and average drop times are summarized in Table i
'i 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time - .
- from. loss ' of stationary gripper coil voltage to dashpot entry of 2.4
- seconds with'the RCS at hot, full
- flow conditions. These test results !
sa'tisfied this limit. f P
3 F
?
t
.. i k
i P
t'
't
/ }
t b
i NE-757 S2C10 Startup Physics Tests Report Page 17 of 58
,. - ,. . . . . . - ~ , - ., - , . . - - - - - . .. . - , ,
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Tab!? 2.1 ;
f SURRY UNIT 2 - CYCLE 10 STARTUP PilYSICS TESTS ,
!!0T ROD DROP TIME
SUMMARY
ROD DROP TIME TO DASilPOT ENTRY t
SLOWEST ROD FASTEST ROD AVERAGE TIME t K-06 1.22 sec. M-12 1.11 sec. 1.17 sec.
ROD DROP TIME TO BOTTOM OF DASilPOT ,
SLOWEST ROD FASTEST ROD AVERAGE TIME !
M-06 1.91 sec. P-06 1.64 sec. 1,77 sec. i l
t v
I
'NE-757 S2C10 Startup Physics Tests Report Page 18 of 58 e
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SE-757 S2C10 Startup Physics Tests Report Page 19 of 58
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Figure 2.2 SURRY UNIT 2 - CYCLE 10 STARTUP PilYSICS TESTS ROD DROP TIME - Il0T FULL FLOW CONDITIONS R P N M L E J H C F t D C 8 A 1 6 l l i 1 1 I i i 1 1 1_ ,
I i 1.16 I i 1.16 1 1 1.19 8 1 1 1 1.71 1 1 1.a9 1 l 3.69 l l t 1 1 1 1 1 1 I I I I i 1.15 I i 1.16 I i i i 1 i 1 1.76 I i 1.79 1 1 1 1 3 1 I i 1 1 I I ll I t.ta 1 1 1.t= l l l l 1.16 l t 4.ta i 1 i 1.74 1 1 1.77 l 1 l l 1.78 l l 1.75 1 1 6 1 1 I i 1 i i i l 1 i l i I, i 1.85 I l i i 1 I a 14 1 l 1 1 1 1 1 1 3.79 l 1 1 1 1 1 1.61 l l l l 5 i i l 1 1 I I I I I I I i l 1.15 l l 1.20 1 1 IZIl 1I 1 1.35 I i 1.20 l l 1.46 l l 1,38 1 1 1.64 i l 1.91 I i 1.80 l i 1.76 l l 1.43 I l 1.76 1 l 1.75 l 6 1 l I 1 l l l 1 1 I l l i i i l 1.1b l i I i 1.13 l l 1.16 i i i 1.44 i i l i i l 1.73 I l 1 l 1.6a i i 1.72 i L i i 1.77 I i 1 7 l 1 i i l I i I i 1 'l I I l 1 1 I a.20 1 4 1 1 1.17 I l I i 4.20 1 i i I 4.20 4 I i 1.76 l 1 1 1 1,67 I I I i 1.66 I i l i 1.63 1 8 i l i l i l i l i i l i l 1 I i 1 1.37 I I i i 1.17 1 1.16 1 I i i 1.13 1 l l l l 1.e4 I l t i 1.70 1 1,66 l l l l 1.75 i 1 ll 9 I I I i i l i I I I lI 1 1 1 1.14 1 1 1.la i 1.19 8 1 3.17 i i 1.16 I i 4.13 l l 3.16 l 1 1.74 i i 1.64 i , 1.60 l l 1.41 1 1 3 65 l l 1.76 1 l 1.69 1 le 1 l 4 i l l 1 I i I i l 1 I I l i i 1.th l I I I I i 1.16 I I i l i i i 1 1.77 I 1 1 I i i 1.79 I i I i 11 1 1 1 1 l l I I i 1 1 1 1 I i i 1.11 I i 1.16 I I I i 1.17 l l 1.lo i i 1 l 1.69 l 1 1.79 1 l l l 1.70 l l 1.75 l l 12
! I l_1 i l i l i l 1 i i i I i 1.17 I i 1.17 i l
I i l 1 1.80 t i 1.79 l l 13 I I I l 1 1 1 I i l 1.2e 1 i 1.17 I l 1.70 l l 1.77 I i 1.83 1 1.76 i 14 i l i i l I l l 1 I I I I l 1 1 15 1 1 I I I T E l**) rod DPop 11MC to DASHPoi ENTRY ($(C)
I v,vy l- > 900 Deop tint to sotton or Dasupot (stt 1 I l
NE-757 S2010 Startup Physics Tests Report Page 20 of 58
U, r
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SECTION 3 i
CONTROL ROD BANK WORTil HEASUREMENTS I Control rod bank worths were measured for the control and shutdown banks using the rod swap technique2 ,6 The initial step of the rod swap L procedure was to dilute the predicted 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 1
changes resulting from the reference bank movements were . recorded continuously by the reactivity computer3 and were used to determine the differential and integral worth of the reference bank. For Cycle 10, Control Bank B was used as the reference bank.
After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position and recording the core reactivity and moderator.
temperature. At this point, a rod swap maneuver was performed by C
withdrcwing the reference bank while one of the other control rod banks (i.e., a test bank) was inserted. The core was kept nominally critical
- throughout this rod swap and the seguence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical. This measured critical position (MCP) of the h
reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank. The core reactivity, NE-757 S2C10 Startup Physics Tests Report Page 21 of 58
m- ,
moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver was then repeated in reverse order such that the reference bank was once again near full insertion with the test bank fully withdrawn from the core.= This rod swap process was then repeated for each of the other control and shutdown banks.
A summary of the test results is given in Table 3.1. As shown by this table and the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the ' individual measured bank worths for the control and shutdown banks were within the design tolerance (110% for the reference bank, 15% for each test bank worth greater than 600 pcm, and 1100 pcm for each test bank worth of less than 600 pcm). The sum of the individual measured rod bank worths was within 0.7% of the design prediction. This is well within the design tolerance of 110% for the sum of the individual control rod bank worths.
The integral and differentia 1' reactivity worths of the reference bank (Control Bank B) are shown ir. Figures 3.1 and 3.2, respectively.
l The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.
i i
i NE-757 S2010 Startup Physics Tests Report Page 22 of 58
. . . . . . .y Table 3.1 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
SUMMARY
MEASURED PREDICTED WORTH PERCENT DIFFERENCE WORTH (7.)
BANK (PCM) (PCM) (M-P)/P X 100 B-Reference Bank 1347.9 1364.0 D
1154.6
-1.2 C 1118.0 3.3 781.4 739.8 A 5.6 331.1 360.6 SB -8.2
- 1054.2 989.7 SA 1018.7 6.5 Total Worth 1078.3 -5.5 5687.9 5650.4 0.7
- Difference is less than 100 pcm.
NE-757.
S2C10 Startup Physics Tests Report Page 23 of 5A
5?M ,
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l:1 Table 3.1 h- i SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS :
il CONTROL ROD BANK WORTH
SUMMARY
l'
.j t
E' i I MEASURED ~ PREDICTED PERCENT DIFFERENCE WORTH WORTH (%)~
BANK (PCM) :(PCM) '(M-P)/P X 100 B-Reference Bank 1347.9 1364.0 -1.2 D 1154.6 1118.0 3.3 g- C 781.4 739.8 5.6
[ A 331 ~.1 360.6 -8.2
- t SB 1054.2 989.7 6.5
~SA 1018.7 1078.3 -5.5 Total Worth -5687.9 5650.4 0.7 l'
- Difference'is less than 100 pcm.
r s
- NE-757 S2C10 Startup Physics Tests Report Page 23 of 58
r.
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i SECTION 4 .
i BORON ENDPOINT AND WORTil MEASUREMENTS Boron Endpoint ;
With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured s critical boron concentration values were made to account for off-nominal ,
control rod position and moderator temperature, if necessary. ,
The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Tests Results and Evaluation ;
Sheets given in the Appendix, the measured critical boron endpoint values 1
i were within their respective design tolerances and met the accident l
In summary, the boron endpoint results analysis acceptance criterion. ,
were satisfactory.
l l
Boron Worth Coefficient l
The measured boron endpoint values provide stable statepoint data
. from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod' worth present in the core at the time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.
NE-757 S2C10 Startup Physics Tests Report Page 26 of 58
m , , ,
r r ~
2 A plot of the boron concentration versus inserted control rod worth is shown in Figure 4.1. As indicated in this figure and in the Appendix, the DBW measured was -8.07 pcm/ppe. This is within 3.3% of the predicted
- c. ,
value of -7.80 pcm/ ppm and is well within~the design tolerance of 110%'.
g The measurement' result ~also met the accident. analysis; acceptance L,
-: criterion. In - summary, the measured boron worth coefficient .was satisfactory.
i 1:
l' 1
NE-757 'S2010'Startup Physics Tests Report Page 27 of 58
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Table 4.1 SURRY UNIT 2 - CYCLE 10 STARTUP PilYSICS TESTS BORON ENDPOINTS
SUMMARY
t Measured Predicted Difference l Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm) 4 ARO 1581 1617 -36 B Bank In 1414 1405* +9
- The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted i values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheets in the Appendix, l
l l
i NE-757 S2C10 Startup Physics Tests Report Page 28 of 58 i L i
Figure 4.I' SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT i Measured DBW = -8.07 pcm/ ppm 1
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- l. .NE-757. S2C10 Startup Physics Tests Report Page 29 of 58
Pi ,
SECTION 5 -
TEMPERATURE COEFFICIENT MEASUREMENTS The isothermal temperature coefficient (ITC) measurement was
- accomplished by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser and/or the steam generator blowdown, establishing a constant and uniform heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer. This measurement was performed at a very low power level in order to minimize the effects of non-uniform nuclear heating, thus the moderator and fuel were at approximately the same temperature during the ,
measurement. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer 1cvel was held constant or slightly increasing during the measurement.
Reactivity was measured during both the RCS cooldown and heatup while l
the RCS temperature varied by approximately 5'F. Reactivity and i temperature data were taken from the reactivity computer and strip chart recorders. Using the statepoint method, the temperature coefficient was
. determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the applicability of using the statepoint method to calculate the measured ITC.
The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the
.NE-757 S2C10 Startup Physics Tests Report Page 30 of 58
Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of.13 pcm/'T and met the accident analysis acceptance criterion, in summary, the measured temperature coefficient was satisfactory.
NE-757 S2C10 Startup Physics Tests Report Page 31 of 58
Tabic 5.1 SURRY UNIT 2 - CYCLE 10 STARTUP PilVSICS TESTS ISOTIIERMAL TEMPERATURE COEFFICIENT
SUMMARY
ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/'F)
BANK TEMPERATURE BORON COOL HEAT AVE. DIFF.
POSITION RANGE CONCENTRATION DOWN UP MEAS. PRED. (M-P)
(steps) ('F) (ppm)
D 542.5 215/216 to 1580 -3.50 -3.44 -3.47 -4.25 +0.78 547.5 l
NE-757 S2C10 Startup Physics Tests Report Page 32 of 58
l-SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations (sco Figure 1.3). For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using the Westinghouse computer program, INCORE4 . INCORE couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.
A list of the full-core flux maps taken during the startup test program and the measured values of the important power distribution parameters is given in Table 6.1. The measured power distribution parameter values are compared with their Technical Specifications limits in Table 6.2. Flux Map 1 was taken at 30% power to verify the radial power distribution (RPD) predictions at low power. Figure 6.1 si.ows the measured RPDs from this flux map. Flux maps 2 and 6 were taken at 64%
and 100% power 1cvels with different control rod configurations. These flux maps were taken to check at power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3.
These figures show that the measured relative assembly power values were generally within 4.5% of the predicted values. Further, the measured NE-757 S2C10 Startup Physics Tests Report Page 33 of 58
f i
F-Q(T) and T-DH(N) peaking factor values for the at power flux maps were within the respective Technical Specification limits.
In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the Technical Specification limits. It is therefore anticipated that the core will continue to operate safely throughout Cycle 10.
NE-757 S2C10 Startup Physics Tests Report Page 34 of 58 L......
h-l TABLE 6.1 SURRY UNIT 2 - CYCLE 10 STARTUP PilYSICS TESTS INCORE FLUX MAP
SUMMARY
l 4 i l l l i 1 4 i i i l i l i 1 1 SUPNI i l F-O(1) HOT 1 F e dH( h ) H01 l CORE F(l) l t l l l l MAP QMAPI l UP l l$ANK 1 CHANN[L F AC10R I CHNL.F AC10R I MAM i GPIR l AX1ALl NO.1 1 DESCRIPTION (NO.! Daft i Nif0/IPWR1 D 1 .
1 -._.l___ l 1 0FF 1 0F l l 1 l l M1U l(2)l$1tP$lA$$vlPINlAtl4Ll IA$$VlPINif*ckHullAXIAll FL231 MAN lLOCl SET 11HIMl l l l l l l l l lPOIN11F*0(i) l I I IPOINil j l I (2) llit$1 l L ON PD.L R lT! 9.,0..,l , lmi 1.. ir$h,l 3. l ,.,03 l mlwl 1.5, ! si l i.3,4li:mlml -0..Alvl 10PTR V!RIFICA1104 1 2 110 02+891 115 1 641 180 i Hill DCI 24 1 2.006 1 Jill DMI 1.467 1 12 11.27841.010) St l 1.961 42 l lH01 FULL POWLR l 6110 09 89131511000 207 i F 91 AMI 33 l 1.860 l F 91 AMI 1.474 1 33 13.21481.6181 Stl -1.!!! 43 1 1 lI l lI l !_i i I_l I l l 1 l_l l_l N0f t $ 3 HOT $P01 10CA110NS APE $PECIFIED BY CIVING A$$EMBLY LOCATIONS (E.C. H-8 !$ THE CENTER OF+ CORE A$$tM8 lyt, FOLLOWID BY THE PIN 10CA110N (Df MOTED BY THE *Y" C00RDINATE WITH THE $EVENittN ROWS OF FUEL ROD $ .
ttit(Pt0 A THROUGH R AND 1H[ "X" COORDINATE DE$1GNAf tD IN A $1 MIL AR MANN[R).
IN THE "2" CIREC110N 1HC C0pt l$ DIVIDED INTO 61 Akl AL PolN1$ $1&R1]NG FROM THE TOP OF THE CORE.
- 3. F-Oti) INCLUDES A TOT AL UNCERT AINTT OF 82.
- 2. FdH(N) INCLUDES A TOTAL UNCERT AINiv 0F 42,
- 3. OPTR - GUADRANT POWER TILi CATIO.
4 MAPS 3 AND 4 WERE QUARitR-CORE FLUM MAPS T AKEN FOR INCORE/ Ext 0RE CAL!bRAi!DN. II/E CAllBRAi!ON)
MAP b WAS A QUARi[R CORC FLUX MAP 1 AKEN OUTSIDE OF THE PHYSICS it$1 PROGRAM 10 MC A$URE AX1AL OFF$tt.
l NE"757 .S2C10 Startup Physics Tests Report Page 35 of 58
n Tabic 6.2 SURRY UNIT 2 - CYCLE 10 STARTUP Pl!YSICS TESTS COMPARISION OF MEASURED P0k'ER DISTRIBUTION PARAMETERS WITil TilEIR TECilNICAL SPECIFICATION LIMITS F-Q(T) 110T F-dll(N) Il0T CllANNEL FACTOR
- CllANNEL FACTOR MAP NO. MEAS LIMIT M.A.RGIN MEAS LIMIT MARGIN
(%) (%)
1 2.203 4.640 52.0 1.524 1.876 18.8 2 2.006 3.566 43.8 1.467 1.717 14.6 6 1.840 2.320 20.6 1.474 1.550 4.9
- The Technical Specification's limit for the heat flux hot channel factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q(T) in the core.
The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T). The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each map. The measured F-Q(T) hot channel factors include 8% total uncertainty.
i NE-757 S2C10 Startup Physics Tests Report Page 36 of 58
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............ ..'. .............. ....'2............. .. -t'.L............... *...............
dst GtJ))d3N33'.
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- l 26
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- 4*tb
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- 0
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0 t9
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1*t *
.....,.............,.............'6 2*2
- t*L
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- SIVNOV50
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- =1*169
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.. .. .... . . ............. . .'L.. ....... . ..
SOHWVMA WYJ N08 SE 10-01 QY138 6/30/96 JcM3Wt 20%
30N1801 800 d0SIII0NSI J-O)1( m 3*Z0S Bd188 Q SYNM VI 199 S13dS J-PH)H( s I*529 NM O*69ZS l N3 0*6642 l
J)2( a I'tLb ~
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M gurc 6.2 SURRY UNIT 2 - CYCLE 10 STARTUP PilYSICS TESTS i i
ASSEMBLYWISE POWER DISTRIBUTION.- s 1
64% POWER-
'/ ,
R P N M L K J H G F [ D C $ A t
. PHEDICTED . . 0.31 . 0.46 . 0.31 . . PREDICTED .
. MEASURED . . 0.31 . 0.45 . 0.30 . . MEASUNED . 1
. PCT DIFFERENCE. . -2.3 . -2.4 . *2.5 . . PCT DIFFERENCE.
. 0.39 . 0.62 . 1.12 . 0.99 . 1.12 . 0.61 . 0.39 .
0.34 0.61 . 1.09 . 0.97 . 1.09 . 0.60 . 0.38 . 2
. 2.7 . -2.3 - 2. 3 . -2. 4 . 2.5 . - 2.7 . -1.2 .
. 0.39 1.10 1.23 . 1.19 . 1.26 . 3.19 . 1.23 . 1.30 . 0.39 .
. 0.38 1.07 , 1.19 3.17 , 1.23 . 1.18 . 1.22 . 3.10 . 0.39 . 3
. 2. 8 . -3.3 . - 3.9 . - 1. 5 . 2. 0 . - 1. 3 . - l .1 +0.2 . 1.1 .
0.39 . 0.69 1.25 . 1.29 1.28 1.16 . 1.24 . 1.29 . 1.25 . 0.69 . 0.39 .
. 0.38 . 0.67 1.21 . 1.27 . 1.28 . 3.16 . 1.27 . 1.29 . 1.24 . 0.68 . 0.39 . 4
. 2.7 -2.6 . 3.3 . *1.4 - 0 .1 . - 0.4 . - 0. 5 . 0.3 . -0.6 . -1.0 . -0.1 .
. 0.39 . 1.10. 1.25 . 1.25 . 1.23 . 1.01 . 1.23 1.01 . 1.23 . 1.25 . 1.24 1.10 . 0.39 .
. 0.38 . 1.10 . l.22 . 1.24 1.22 . 1.03 . 1.25 . 1.02 . 1,42 . 1.23 . 1.21 . 1.09 . 0.39 . 5
. -2 7 . 0.6 . -2.0 . 1.3 . -0.9 . 1.6 . 1.7 1.3 . 0.1 . - 1. 2 . -2. 7 . -0. 7 . 1.5 .
0.62 . 1.23 . 1.29 .'l.24 1.16 . 1.21 . 1.22 . 1.20 . 1.15 . 1.23 . 1,29 . 1.23 . 0.62 .
0.62'. 1.21 . 1.27 1.21 . 1.16 1.25 . 3.26 1.22 . 1.15 . 1.22 . 1.27 . 1.22 . 0.62 . 6
. -0.5 . -2.4 . 1.7 -2.2 . -0.0 . 2.9 . 3.4 1.9 . 0.2 . - 0. 7 . - 1.6 . -0.7 . 0.3 .
1.21 . 3.17 . 1.25 . 1.13 . 1.2e . 1.01 1.27
. 0.31 . 1.12 . 1.19 . 1.28 . 1.01 1.19 . 1.11 . 0.31 .
. 0.31 . 1.11 . 1.19 . 1.27 1.00 . 1.22 . 1.21 . 1.28 . 1.15 . 1.21 . 1.01 . 1.27 1.19 , 1.11 . 0.31 . 7
. -0.6 . -0.6 . -0.5 . -1.1 . +1.5-. 0.7 . 3.7 . 2.9 . 1.3 . 1.4 0.8 . -0.4 0.3 . 0.4 . 0.4 .
. 0.46 . 0.99 . 1.26 . 1.16 . 1.23 . 1.22 . 1.25 . 1.15 . 1.24 1.21 . 1.23 . 1.16 . 1.26 . 0.99 . 0.46 .
0.46 . 0.98 . 1.25 1.17 . 1.24 , 1.24 . 1.29 . 1.19 . 1.28 . 1.24 1.25 . 1.16 . 1.27 . 1.00 . 0.46 . 8
. -0.7 . *0.8 . +0.6 . 0.6 . 0.2 . 2.0 . 3.7 . 3.4 . 3.0 . 2.6 . 1.8 . 0.1 0.8 . 1.5 . 0.8 .
0.31 . 1.12 . 1.19 . l.28. 1.01 . 1.20 . 1.13 1.24 . 1.13 . 1.20 . 1.01 . 1.28 . 1.19 . 1.12 . 0.31 .
. 0.30 . 1.09 . 3.16 . 1.28 . 1.04 1.22 1.15 1.2* 1.19 . 1.23 1.03 . 1.20 . 1.20 . 1.13 . 0.31 . 9
. -3.5.. -2.1 . -2.2 . 4.3 . 3.3 . 2.2 . 23. 4 4.9 . 3.1 1.9 . 4.1 . 0.9 . 1.2 . 0.8 .
. 0.61 . 1.23 . 1.29 . 1.23 . 1.15 . 1.19 . 1.21 . 1.19 . 1.15 . 1.23 1.29 1.23 . 0.61 .
0.59 . 1.18 . 1.28. 1.25 1.17 . 1.22 1.25 . 1.23 . 1.18 . 1.24 . 1.29 . 1.23 . 0.62 . 10
. -3.9 . 43.9 . 0.7 . I.8 . 1.9 . 2.2 3.0 . 3.6 . 2.6 . 1.1 . -0.3 . 0.1 . 0.5 .
l' . 0.39 . l.10 . 1.25 . 1.25 . 1.23 . 1.01 . 1.23 . 1.00 . 1.23 . 1.25 . 1.25 . 1.10 . 0.39 .
. 0.38 1.08 . 1.23 . 1.24 1.24 . 1.03 1.25 . 1.03 1.26 . 1.25 . 1.25 . 1.10 . 0.39 . 11
. -1.9 . -1.9 . -1.3 . -0.4 . 0.7 2.1 . 2.0 . 2.7 . 2.8 . 0.2 0.3 . 0.5 . 0.5 .
. 0.39 . 0.69 . 1.24 . 1.29 . 1.27 1.16 . 1.27 . 1,29 . 1.24 . 0.69 . 0.39 .
. 0.39 . 0.69 1.24 1.28 . 1.30 . 1.18 . 1.29 1.29 . 1.25 . 0.70 . 0.39 12
. 0.1 . -0.2 . -0.5 0.5 . 2.0 . 2.0 . 1.2 . 0.5 . 0.6 . 1.1 . 0.7 .
. 0.39 . 1.10 . 1.23 . 1.19 1.25 1.19 1.23 . 1.10 0.39 .
. 0.38 . 1.06 . 1.19 . 1.23 . 1.28 . 1.17 . 1.20 . 1.09 . 4.39 . 13
. *1.6 -3.3 . -3.3 . 3.7 - 1.9 . - 1. 7 . - 1. 8 . - 0. 6 . 1.0 .
. 0.39 . 0.61 . 1.!! 0.99 . 1.11 . 0.61 0.39 .
. 0.37. 0.61 . 1.15 . 1.02 . 1.09 . 0.60 . 0.38 . 14
. -3.5 . -0.5 . 3.6 . 3.3 . -1.6 . -1.7 -1.8 .
. STANDARD . 0.31 0.46 0.31 . . AVERAGE .
. DEVIATION . . 0.32 . 0.48 . 0.32 . PCT DIFFERENCE. 15
. *l.152 . . 3.5 . 3.4 . 3.5 = 1.7 .
SUMMARY
MAP NO: S2-10-02 DATE: 10/02/89 POWER: 64)
CONTROL ROD POSITIONS: F-QtT) s 2.006 QPTR:
D BANK AT 180 STEPS f-dHIN) a 1.467 HW 0.9917 l NE 0.9969 i
F(Z) s 1.278 LW 1.0018 l SE 1.0096 BURNUP = 115 MWD /MTU A.O. s -1.961%
NE-757 S2C10 Startup Physics Tests Report Page 38 of 58
ers ,-e- ,
7 e
i lt F Figure 6.3 SURRY UNIT 2 - CYCLE 10 STARTUP PilYSICS TESTS 4 ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R P N M .I E J H C F E D C 8 A PREDICTED . . 0.32 . 0.48 . 0.32 . . PREDICTED .
. MC ASURE D . . 0.32 . 0.47 . 0.32 . . MEASURCD . 1
. PCT DIFFERENCE. . *2.5 -2.5 . -1.9 . . PCT DIFFERENCE.
. 0.39 . 0.62 . 3.12 . 1.03 . 1.12 . 0.61 . 0.39 .
. 4.39 . 0.61 . 1.09 . 1.00 . 1.10 . 0.60 . 0.39 . 2 ,
. -0.8 -2.5 . -2.5 . -2.5 . -2.1 . -2.0 . -0.3 .
. 0.39 1.07 1.21 . 1.18 1.25 . 1.18 1.20 . 1.07 . 0.39 .
0.39 . 1.05 . 1.15 . 1.16 . 1.22 . 1.16 . 1.18 . 1.07 . 0.40 . 3
-1.2 . -2.7 -4.5.. 2.0 . -2.3 -1.8 , -!.6 . 0.1 . 2.3 .
. 0.39 0.69 1.22. 1.27 . 1.26 1.16 . 1.26 . 1.27 . 1.22 . 0.69 . 0.39
. 0.39 0.67., 1.17 . 1.24 . 1.26 . 1.14 . 1.24 1.25 . 1.21 . 0.68 . 0.39 4
. -0.9 - 2. 5 . 3. 8 . - 2. 0 . - 0. 5 . - 1.1 . - 1. 5 . - 1. 2 . - 0. 7 . -0. 3 . 0.2 .
. 0.39 1. 0 7 ~ 1.22 . 1.24 . 1.t4 . 1.02 . 1.24 . 1.02 . 1.24 . 1.24 . 1.22 . 1.07 0.39 .
. 0.39 . 1.06 1.19 1.23 . 1.23 . 1.03 . 1.25 . 1.02 . 1.23 . 1.23 . 1.19 . 1.06 . 0.39 . 5-
. 0. 8 . - 1. 8 . - 2.3 . 2. 0 . - 1.1 . 1.4 . 1.0 . 0.3 . 0.4 . -0.8 . 2.4 . -0.8 . 1. 2 . .
. 0.62 . 3.21 a 1.27 .1.24 1.21 . 1.73 . 1.23 1.22 . 3.20 1.24 1.27 . 1.20 . 0.62 . -
. 0.61 . 1.20 . 1.26 . 1.23 . 1.22 . 1.26 . 1.26 . 1.24 1.21 . 1.23 . 1.25 . 1.19 . 0.62 . 6
. 2. % . - 0. 8 . - 1. 2 -1.0 . 0.5 , 2.8 . 2.8 . 2.2 . 0.6 . *0.7 . -1.6 . 0.8 . 0.2 .
. 0.32 . 1.12 . 3.18 . 1.27 . 1.02 . 1.22 , 1.18 . 1.26 . 1.15 . 1.21 . 1.02 . 1.26 . 1.18 1.12 . 0.32 .
. 0.32 . 1.10 . 1.16 . 1.25 . 1.02 . 1.24.. 1.23 . 1.30 . 3.19 . 1.24 . 1.02 . 1.25 . 3.18 . 1.11 . 0.32 . 7
. -2,4 -2.3 . 2.3 . -1.1 . -0.5 . 1.6 . 4.2 . 3.5 . 3.1 . .t.4 . 0.7 . -1.0 . -0.4 . -0.6 . -0.1 .
. 0.48 . 1.03 . 1.25. 1.16 . 1.24 1.23 . .l.26 . 1.16 . 1.25 . 1.22 . 1.23 1.15 . 1.25 . 1.03 . 0.48 .
. 0.47 , 1.01 . 1.23 , 1.14 . 1.24 . 1.25 . 1.31 . 1.21 . 1.30 . 1.26 . 1.26 . 1.14 . 1.25 . 1.04 . 0.48 . 8
. -2.4 . 2.4 . +2.3 . -l.2 . -0.1 . 1.6 . 4.4 . 4.1 . 3.5 . 3.3 1.9 . -1.0 . 0.0 . 0.7 . 0.7 .
. 0.32 . 1.12 . 1.18 . 1.26 . 1.02 . 1.22 . 1.15 . 1.25 . 1.15 . 1.21 . 1.02 1.26 . 1.18 . 1.12 . 0.32 .
. 0.32 . 1.09 1.15 . 1.24 . 1.02 . 1.22 . 4.17 . 1.30 . 1.20 . 1.25 . 1.04 1.25 . 1.19 . 1 14 0.33 . 9
. "2.5 . -2.4 -2.5 . -1.7 . -0.1 . 0.7 . 1.7 . 3.3 . 4.0 . 2.8 . 1.7 . -1.2 . 0.4 1.3 . 1.5 .
. V.61 . 1.20 . 1.27 . 1.24 . 1.20 . 1.21 . 1.22 . 1.21 . 1.20 . 1.24 . 1.27. 1.20 . 0.62 .
. 0.60 1.17 . 1.24 . 1.22 . 3.21 . 1.24 . 1.25 . 1.25 . 1.23 . 1.25 . 1.26 . 1.20 . 0.62 . 10
. -2.7 . 2.7 -2.2 . -1.3 . 0.5 1.7 . 2.6 . 3.0 . 2.5 . 1. 0 . - 1. 0 . - 0. 2 . 1.0 .
. 0.39 1.07 . 1.22 . 1.24 . 1.24 . 1.02 . 1.23 . 1.02 . 1.24 1.24 1.22 . 1.07 . 0.39
. 0.38 . 1.06 . 1.20 . 1.22 . 1.23 . 1.03 . 1.26 . 1.04 . 1.26 . 3 25 . 1.22 . 1.08 . 0.39 . 11 '
. -1.3 . -1.4 -1.4 . 1.4 0.2 . 1.2 2.0 . 2.3 2.2 . 1.1 . 0.6 . 0.6 . ,1.0 .
. 0.39 . 0.69 1.22 . 1.27 . 1.26 . 1.15 . 1.26 . 1.27 . 1.22 0.69 . 0.39 .
. 0.39 0.68 . 1.20 . 1.26 . 1.26 . 3.16 1.27 . 1.27 . 1.23 . 0.70 . 0.39 . 12 0.0 . 0.6 -1.4 . -0.8 . -0.1 . 1.0 . 1.0 . 0.5 . 0.9 . 1.4 1.1 .
0.39 . 1.07 1.20 . 1.38 . 1.25 . 1.18 . 1.20 . 1.07 0.39
. 0.39 . 1.07 . 1.20 . 1.17 . 1.25 . 1.16 . 1.18 . 1.07 0.39 , 13
. -0.1 . 0.2 . -0.3 . -0.4 -0.4 . -1.7 . -1.8 -0.5 . 1.3 .
0.39 . 0.62 . 1.12 . 1.03 . 1.12 . 0.61 . 0.39 .
- 9.39 0.62 . 1.16 . 1.06 . 1.10 . 0.60 . 0.38 . 14 0.2 1.3 . 3.4 3.2 . -1.7 . -1.8 . -1.8 .
. DEVIAT10N 0.33 . 0.50 . 0.33 . . PCT DIFFERENCE. 15
. al.050 . 3.4 3.3 . 3.4 = 1.6 SLPW1ARY NAP NO: 52-10-06 DATE: 10/09/89 POWER: 100%
CONTROL ROD POSITIONS: F-QlTI s 1.840 QPTR:
D BANK AT 207 STEPS F-dHIN) a 1.474 NW 0.9925 l NE 0.9989 l
F(Z) a 1.214 SW 0.9990 l SE 1.0096 BURNUP = 315 MWD /NTU A.O. s -1.212%
NE-757 S2C10 Startup Physics Tests Report Page 39 of 58
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i,;
h t L' - REFERENCES. i s '. _ -
, ild 'Db A. Trace', "Surry Unit2, Cycle 10' Design Report,"
[F * .' .
. Technical Report;NE-657., Rev.ision.1.,; Virginia l t ; Electric and PowerLCompany . August, 1989. -jj 2r-T.:Ki Ross, W'. C.' Beck, " Control Rod Reactivity Worth Determination- '-I
[f.7 m
. By The Rod Swap Technique," VEP-FRD-36A, December,: 1980.
3', "Technica'1. ManualLfor; West'inghouse~ Solid- State Reactivity Computer," d 77
' ' ~
0 : Westinghouse ~ Electric Corporation.
i ;
't LW.?Leggett'and'L.~ Eisenhart, "The:1NCORE Code,".WCAP-7149, j
' December , :1967 ~.
- 5. Surry Power! Station 1-Technical Specifications,. Sections =3 12.C.1, ,
= 3.'12. B ,1, L a nd . 3.1. E . I '. y
~ ^
4 6;--Letterefrom.W.'L. Stewart (VP) to USNRC, " Modification of Startup;
"" lPLysics1 Test'. Program - Inspector Fo11owup. Item 280;281/88-29-01",.
-dated December.8..1989.
4 r^ d 4
r
)
4
+
i 1 't i P 5 n
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, NE-757 S2C10_Startup Physics Tests Report Page 40 of 58
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APPENDIX STARTUP PllYSICS TESTS RESULTS AND EVALUATION SilEETS u
NE-757 S2C10 Startup Physics Tests Report Page 41 of 58
y .. .
J 2-PTo38.11 l ATTACHMENT 1 l PACE 1 0F 19 SURRI POWER STATION UNIT 2 CYCLE it STARTUP PHYSICS TEST RESULTS AND ETALVATION SNEET i-I Test
Description:
Reactivity Computer Checkout Reference Proc No /Section: 2-PT-28.11 l
Seiruence Step No: 3 II Bank Positions (Steps) RCS Temperature ('F): 547 Test Conditions Power Level (x F.P.): 0 !
SDA: 225 SDB: 225 CA: 225 other (specify):
(Design) CB: 225 CC: 225 CD: E Below Nuclear Heating I III Bank Positions (Steps) RCS Temperature (8F):.SW. 3 Test Conditions Power Level (X F.P.): O
.SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) CB: 225 CC: 225 CD : /90 below Nuclear Heating Date/ Time Test Performed:
9//7/87 C '2.3 O Measured Parameter pe = Meas. Reactivty using p computer IV (Description) pt = Inferred React from react period
- pc = 9S - 9.7 Measured Value pt *
- Y Ya 8 ~N8 Test xD =
Results /./ll ~ 3. 3 7 If Design Value (Actual Conditions) XD = ((p, pt)/ pts x 100% $ 4.0%
Design Value (Design Conditions)
XD-= ((pe pt 'Pt) 3 x 100% 5 4.0X i
Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : _f._YES _ NO VI- Acceptance Criteria is met : E._YES NO Comments a At The Just Critical Position Allowable Range = 2 - 4.9 -ys n
Completed By: Evaluated By: e/ # -
Test Erigrineer ppr va y : -M-NAF Engineer NE-757 S2C10 startup Physics Tests Report Page 42 of 58
2 - h'-a .11
$tcacanant .
-Pago 2 of 15-WIN Sif C : G3 SURRY POWER STATION UNIT 2 CYCLE IC STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - ARO Reference Proc No /Section: 2-PT-28.11- Sequence Step No: 4 II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating III. Bank Positions (Steps) RCS Temperature ('F): 545a Test ~ Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225. CA: 225 Other (Specify):
(Actual) CB: 225 CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:
9/0 M c542 Meas Parameter 3 IV (Description) (CB ) AR0; Critical Boron Conc - ARO g
Measured Value (CB ) ARO
- I53I PPM Test Results Design Value (Actual Cond) CB= g(on 150 Ppm Design Value (Design Cond) CB = 1617 2 50 ppe Reference NE Technical Report No. 657, Rev. 1 V FSAR/ Tech Spec aCBxCB s 15,115 pcm Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met : / YES _ NO Acceptance Criteria is met : J YES NO VI Comments aCB = -7.80 pcm/ ppm for preliminary analysis "Cc : - LCO pc e l ppm 4 El one.W 5.
Completed By: ..bi b v Evaluated By: bb '
est Engineer Approva :t- 4 NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 43 of 58
Attacament 1 Pogo 4.cf 19 SEP G : E SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Isothermal Temperature Coefficient - ARO Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 5 II Bank Positions (Steps) RCS Temperature ('F): 547
' Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225- Other (specify):
(Design) CB: 225. CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): trvr Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) CB: 225 CC: 225 CD:2sr/2:4 Below Nuclear Heating Date/ Time Test Performed:
'l 5 cl o (, o 's Meas Parameter g3o IV (Description) (a T )ARO Isothermal Temp Coeff - ARO Test Measured Value (m )ARO = - 3. O Pcm/'F (CB = ICI ppa)
Results Design Value (Actual Cond) s,,
(* Iso)ARO T 2. f pea /'T (CB = IS~IOPPa)
ISO (a T )ARO = -3.88 1 3.0 pca/'T Design Value (Design Cond) (CB = 1617 ppe)
Reference NE Technical Report No. 657, Rev.1 Acceptance FSAR/ Tech Spec a 5 0.79*pcm/'F a Dop = -1.71 pcm/'F Criteria Reference TS 3.1.E. NE Technical Report No. 657, Rev. 1 Design Tolerance is met : / ES Y _,__NO VI Acceptance Criteria is met : /YES _,_ NO Comments
- Uncertainty en aTMOD = 0.5 pcm/*F (
Reference:
memorandum from C. T. Snow to E. J. Lozito dated June 27, 1980).
p '
A7 /
Completed By: / Evaluated By: L Test Engineer Approva y: 6-W-NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 44 of 58 J
- SoPTo28.11-ATTACHMENT 1 PAGE 5 or 19 f
SEP0 : 1989 SURRY' POWER STATION UNIT 1 CYCLE 18 STARTVP PHYSICS TEST RESULTS AND ETALVATION SNEET I Test
Description:
Catl Bank B Worth Meas. , Rod Swap Ref. Bank Reference Proc No /Section: 2-PT-28.11- Searuence Step No: 6 II Bank Positions (Steps) RCS Temperature ('F): 547 Test. Power L.evel (X F.P.): 0 Conditions SDA: 225- SDB: 225 CA: 225 Other (specify):
(Design) CB: Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F): $%. O Test. -
Power Level (x F.P..): O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:
9b7/?9 07!Iit REF Measured Parameter I g ; Integral Worth of Cnti Bank B, (Description) All Other Rods Out IV Test Measured Value I = /.5W 7,#7 g M Results Design Value REF (Actual Conditions) I g a M6W M6 %
Design _Value REF (Design Conditions) I g = 1364 2 136 pcm Reference NE Technical Report No. 657, Rev. O If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result V FSAR/ Tech Spec on safety analysis. SNSOC may specify Acceptance that additional testing be performed.
Criteria Rsference 7EP-FRD-36A Design Tolerance is. net : ES NO VI Acceptance Criteria is met : _ YES _ N0 Comments Comple'ted B Evaluated By L ' Te'st F,nipneer
/ (.) "**1;;;"':ti;": M['i' NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 45 of 58
2 -P'6'-2 3.11 atwr.asnt A Page 6 or 1 i: h $EP 0 : M9 SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I . Test
Description:
Critical Boron Concentration - B Bank In Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 7 II Bank Positions (Steps) RCS Temperature ('F): 547 Test -
Power Level (* F.P. ): O Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: O CC: 225_ CD: 225 Balow Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 5%.4 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) CB: 0 CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:
Ci b7 N*t I"LioO i
-Meas Parameter y IV (Description) (CB )D; Critical Boron Conc - B Bank In Measured Value (CBD* INb hM Results Design Value (Actual Cond) CB= 1405 1 77 Pem Design Value pg,y (Design Cond) CB = 1441 + ACB 1 (10 + 136.4/laCBl)PP8 Reference NE Technical Report No. 657 Rev. 1 V
-FSAR/TechSpecl_aCBxCg 5 15.115 pcs Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met : YES N0 Acceptance Criteria is met : YES N0 VI Comments oCB = -7.80 pcm/ ppm for preliminary analysis Prev M AC B = (C B) ARO - 1617 c(0 : - LO'"7 pc.e /99m be bdMWM Completed By N. k- -o -
Evaluated By: bb 4 Kest Engineer Recommended for Approval By f.d#O ,
/
NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 46 of 58 m
O 3 PTo38.11 ATTACHMENT 1 Le PAGE 3 OT 19 F I N ) A L. EP 0 5 G89 SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SNEET '
l '
j 1; I Test
Description:
HZP Boron Worth Coefficent Measurement Reference Proc No /Section: 2-PT-28.11 {
Sequence Step No: 4 l II Bank Positions (Steps) RCS Temperature (8F): 547 Test Power Level (x F.P.): 0 2 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Disign) CB: Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F): 5%5.3 Test Power Level (X F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating-Date/ Time Test Performed:
Cl /t7 N9 } C50 4 3 Measured Parameter IV (Description) aCB , Boron Worth Coefficient l: Measured Value Test aCa= - % .0 7 9 m /pem Results Design Value (Actual Conditions) aC =
- 7.%O 1 O .~'7% Pc- /Pem l Design Value (Design Conditions) aCg = -7.80 2 0.78 pen /ppe Reference NE Technical Report No. 657. Rev. 0 FSAR/ Tech Spec aCgxCg 5 15,115 pcm V
Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met : YES ,,,,,,N0 VI Acceptance Criteria is set : V YES ,NO Comments i
Completed By: '
Evaluated By: ~
Tyst Engineer Recommended for Approval By:- ~
NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 47 of 58
~.- ., , . _ _
i .- .
2 PT-28.11 j ATTACHMENT 1
. PAGE 7 0F 19 SEP 0 3 'lii SURR[POWERSTATIONUN!?2 CYCLE 10 4 ;
STARTVP PHYSICS TEST RESULTS AND EVALUA720N $NEET l
l I Test
Description:
Catl Bank D Worth Measurement-Rod Swap Referen'ce Proc No /Section: 2-PT-28.11 Sequence Step No: 9 l
II Bank Positions (Steps) RCS Temperature (*F): 547 i Test j Conditions Power Level (X F.P.): 0 -
SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: Moving CC: 225 CD: Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (ep) gyg,9 '
Test Conditions Power Level (X F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) CB: Moving CC: 225 CD: Moving Below Nuclear Heating Date/ Time Test Performed:
9/t?/rf /3:30 -
Mens Parameter RS (Description)
ID ; Int North of Cnti Bank D-Rod Swap
. IV (Adj. Mees. Crit. Ref Bank RS Test. Measured Value I D = //f7 Position = /8/ steps) '
Results Design Value (Adj. Meas. Crit. Ref Bank RS (Actual Cond) I D = /// /6B Position = /8/ steps) '
Design Value RS IIIS ,
ID = MeE 2 M f'pca-(Critical Ref Bank /
(Design Cond) hpg((If Position = 179 steps)
Reference NE Technical Report No. 657, Rev. O, VEP-FRD-36A, NFO TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V TSAR / Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.
Criteria Reference VEP-FRD-36A Design Tolerance is met : YES ,,_ NO VI Acceptance Criteria is met : YES N0 Comments Completed By: b wu est Engineer Evaluated Byt
- 6 NAF Eng:neer NE-757- S2C10 Startup Physics Tests Report Page 48 of 58
3-PT-28,11 ATTACHMENT T PAGE 8 0F 19 SURRY PONER STATION UNIT 1 CYCLE 10 SEP 0 5 E9 l
STARTUP PHYSICS TEST RESULTS AND EVALUATION SNEET i'
I Test
Description:
Cntl Bank C Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 10 I
II lBankPositions(Steps) RCS Temperature (*F): 5847 Test Power Level (x F.P.): 0 Conditions SDA: 225 .SDB: 225 CA: 225 other (specify):
(Design) -CB: Moving CC: Moving CD: 225 .Below Nuclear Heating
-III- Bank Positions (Steps) RCS Temperature (87): A(,f 7 /
Test Power Level (x F.P.): 0 Conditions .SDA: 225 SDB: 225 CA: 225 Other (Specify):
.(Actual) CB: Moving CC: Moving CD: 225 Below Nuclear Heating Date/ Time Test Performed:
9/n/01 M .'2 s' ' .
Meas Parameter RS (Description). IC ; Int Worth of Catl Bank C Rod Swap
.. IV g .- ( Adj . Meas. Crit. Ref Bank L Test- Measured Value I = 78/# Position = /2.3 steps)
- C Results Design Value ( Adj. Meas. Crit. Ref Bank
!^
(Actual Cond)- I C
= N N /// Position = /23 steps) j Design Value RS Y ,
I C = 799- 2 ttf pca (Critical Ref Bank /
(Design Cond)- Position = 125 steps) g g,g I\ l Reference NE Technical Report No. 657, Rev. O, VEP-FRD-36A, NF0-TI-2.2A If Design Tolerance is exceeded, SNSOC .
shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC cay specify that Acceptance additional testing be performed.
Criteria Reference VEP-FRD-36A Design Tolerance is met : i NO VI Acceptance Criteria is met : YES NO Comments Completed By
- Evaluated By-jTestEngineer -
pprova y : A NAF Engineer NE-757 S2C10 startup Physics Tests Report Page 49 of 58
v PT-28.11 ATTACHMENT 1 PAGE 9 OF 19
.l SEP 0 5 *M SURRY' POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SMEET
)
I Test
Description:
Cnti Bank A Worth Measurement-Rod Swap Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 11 II Bank Positions (Steps) RCS Temperature ' ('F): 547 Test -
Power Level (X F.P.): 0 Conditions SDA: 225 SDB: 225 CA: Moving Other (specify):
(Design) CB: Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F): .SV(:3, L
- Test Power Level (X F.P. ): 0 Conditions SDA: 225 SDB: 225 CA: Moving Other (Specify):
3 (Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:
9//7//9 - /f//7 -
Meas Parameter RS (Description) I4; Int Worth of Cnti Bank A - Rod Swap IV (Adj. Meas. Crit. Ref Bank
- RS l*
I' Test Results Measured Value Ig =33/ Position = /*/ steps) /
Design Value (Adj. Meas. Crit. Ref Bank' RS
- l. (Actual Cond) Ig = 3 5 /f /00 Position = 7 f steps) '
Design Value RS 3 Ig = 962 t 100 pcm (Critical Ref Bank . /
(Design Cond) ggg -Position = 84 steps)
Reference NE Technical Report No. 657, Rev. O, VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAK/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.
Criteria Reference VEP-FRD-36A Design Tolerance is met : [ YES _,,,,,hD VI Acceptance Criteria is met : / YES _ N0 Comments i- < _
Completed By: ,0 I , ' ' Evaluated By:
M est Eng1heer pp va y :
NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 50 of 58
V. .
3-PT-28.11 ATTACHMENT 1 PAGE 10 0F 19-SEP 0 5 1553 SURRY' POWER blATION UNIT 1 CYCLE 18 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I~
. Test'
Description:
Shutdown Bank 8 Worth Meas. - Rod Swap
' Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 12 I
II Bank Positions (Steps) -RCS Temperature ('F): 547
-Test 1 Conditions SDA: 225 SDB: Moving CA: 225 Power Level (X F.P.): 0 Other (specify):
j (Design) CB: Moving CC: 225 CD: 225 i
Below Nuclear Heating :
.III Bank Positions (Steps) RCS. Temperature (*F): 5 % ~1
' Test Conditions SDA: 225 SDB: Moving CA: 225 Power Level (X F.P.): 0 i Other (Specify):
(Actual) CB: Moving CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed:-
9[tl[%9 lb'S 7 Mens Parameter RS (Description)
Igg; Int North of Shutdown Bank B-Rod Swap j -
IV Test RS (Adj. Meas. Crit. Ref Bank Measured Value I gg = . t059 Position = l(et -l steps)
Results Design Value gg (Adj. Meas. Crit. Ref Bank (Actual Cond) I gg =
990 : 14cl Position = i(cq st.ps) 999 t
l RS Design Value I gg = M 2 M pea (Critical Ref Bank -
(Design Cond)=
qqJ %t Position = 160 steps)
Reference NE Technical Report No. 657, Rev. O, VEP-FRD-36A.
NF0-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.
- Criteria Reference VEP-FRD-36A Design Tolerance is met VI Acceptance Criteria is met
- IYES NO Coements
- d YES NO Completed By: \ . .
Evaluated By: b MestEngineer
~
Recoemended for Approval By L g<[
NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 51 of S8
__ - . . . _ . . . _ . _ . ~ . _ _ . . _ _ . . . _
PT-28.11 ATTACHMENT 1 PACE 11 0F 19
-SURA 1/ POWER STATION UNIT 2 CYCLC 10
'STARTUP PHYSICS TEST RESULTS AND ETALVATION SMEET I Test
Description:
Shutdown Bank A Werth Meas. - Rod Swap Reference Proc No /Section: 2-PT 28.11 Sequence Step No: 13 II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Le' vel (X F.P.): O Conditions SDA: Moving SDB: 225 CA: 225 Other (specify):
(Design)- CB: Moving CC: 225 CD: 225 Below Nuclear Heating III lBankPositions(Steps) RCS Temperature (eF): f/$ 7 ' '
Test Power Level (X F.P.): 0 Conditions SDA: Moving SDB: 225 CA: 225 Other (Specify):
(Actual) CB: Moving- CC: 225 CD: 225 Below Nuclear Neating Date/ Time Test Performed:
3/o M nuco Meas Parameter RS (Description) Igg; Int North of Shutdown Bank A-Rod Swap IV gg ( Adj . Meas. Crit. Ref Bank Test Measured Value I gg a /C/9 p Position = /78 steps) #
Results Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) ISA =/d /6"L Position = /yg steps) #
~
RS Design Value . Igg
- MM 2 W+ pea (Critical Ref Bank e (Design Cond) g,g Sl Position = 172 steps)
Reference NE Technical Report No. 657, Rev. O, VEP-FRD 36A, NFO-TI-2.2A l If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.
Criteria Reference VEP-FRD-36A Design Tolerance is met : /YES NO VI- Acceptance Criteria is met i /YES NO Comments
\
Completed By: (C k Evaluated ByL <
est Engineer
"":;;:::t !; , (Lwud-NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 52 of 58
2-PT*28.11 ATTACHMENT 1
~
PAGE 12 0F 19 N
SURR1f POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SNEET 1 Test'
Description:
Total Rod Worth - Rod Swap Reference Proc No /Section: 2-PT-28.11 Sequence Step No ll.
II Bank Positions (Steps) RCS Temperature (*F): 547 Test. Power Level (X F.P.): O Conditions SDA: Moving SDB: Moving CA: Moving Other (specify):
(Design) CB: Moving CC: Moving CD Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (OF): 545.7 Test. Power Level (X F.P. ):' O Conditions SDA: Moving SDB: Moving CA: Moving Other (Specify):
(Actual) CB: Moving CC: Moving CD: Moving Below Nuclear Heating Date/ Time Test Performed:
9/o/ta 7wi Mens Parameter (Description) ITotal; Int Worth-of All Banks - Rod Swap IV
. . Test Measured Value ITotal - 5(o %
Results Design Value (Actual Cond) ITotal * '~
Design Value I #
- O PC" (Design Cond) Total
,g
- 665h 6%
Reference NE Technical Report No. 657,' Rev. O, VEP-FRD-36A, NF0-TI-2.2A If Design Tolerance .is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spee safety analysis. SNSOC may specify that Acceptance additional testing be perforsed.
. Criteria Reference VEP-FRD-36A Design Tolerance is set i d YES ___ N0 VI Acceptan:e Criteria is set V YES _ NO Coseents Completed By: LC - - Evaluated By: Nb' -
7ept Engineer
~ Recommended for N<
Approval By g ' NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 53 of 58
2-PT-26.11 ATTACRMENT 1 PACE:13 OF 19 m
"* ,) .sB9 SURRY PONER STATION UNIT 2 CYCLE 10 STARTUp PHYSICS TEST RESVLTS AND EVALUATION SHEET I Test Desertption: M/D Flux Map - Low power Reference-i Proc No / Section: 2-PT-28.2, 2-OP-57 Sequence Step No 41 II. Bank Positions (Steps) RCS Temperature ('F): TREF *1 Test Power Level (% F.P.): <30 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify)'
(Design) l CB : 225 CC : s CD: s Must have 2 38 thimbles III Bank Positions (Steps) RCS Temperature (*F): TaF A
Test Conditions Power Level (% F.P.): 3e?,
SDA: 225 SDB: 225 CA: 225 other (Specify):
(Actual) CB': 225 CC : 7.25 CD: 16 6 g 4 Date/ Time Test Performed g _ g-
'1/2.chr? c'N l
, MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) % DIFF' CHANFACTlCHANFACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR
~4. *E Measured Value ,' f,62q 2 ,2 c 3 /,o ;y Test g p,.4 e,q
-Results Design Value (Design Conds) !,hk!d![ NA NA S 1.020 NCAP-7905 I WCAP-7905 Reference REY.1 NONE REY.1 f NONE i
V "* "*"' ***"***
FSAR/ Tech Spec NONE NA Acceptance Criteria
. Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met :
YES _ N0 Acceptance Criteria is met : 7,_YES N0 VI Comments s As Required 3
Completed By: u9 k > Evaluated By:
'#est Engineer
""::::"':t !; 4 e s B /
NAF Eng~aneer NE-757 S2C10 Startup Physics Tests Report Page 54 of 58
2-PT 28.11
+ >
ATTAC)DIENT 1 PAGE 15 0F 19
- k. .,
SURRY PONER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SNEET 1~ Test Descr16 tion: M/D Flux Mep-At Power Reference Proc No / Section: 2-PT-28.2. 2 0P-57 Sequence Step No: 44 II Bank Positions (Steps) I RCS Temperature (8F):T AI Test , Power Level (% F.P.): -REF 70 Conditional SDA: 225 SDB: 225 CA: 225 l Other (specify):
(Design) I CB : 225. CC : 225 CD:
- l Must have 2 38 thimbles
-III lBankPositions(Steps) lRCSTemperature('F): *T~g p Test Conditiona,l SDA: 225 SDB: 225 CA: 225 Power Level (x F.P. ): M%
. Other (Specify):
(Actual) l CB 225 CC : 225 CD: Igo l 97 ggy l_Date/TimeTestPerformed:
ic/z /Sc) 0621 MAP cz- to-oz
! MAX. REL NUC ENTHAL TOTAL HEATI QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT' POWER TILT (Description) % DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-QCT) QPTR 4.i i, F.R. P; %. O A Measured Value 3.9 y. 1/K"7 Test 2,ooro J. 00%
p p,.4 o,cg Results Design Value
- "S**"
3 gg gigt ;
(Design Conds)
NA NA $ 1.02 WCAP-7905 NCAP-7905 Reference REV.1 NONE NONE l REV.1 V FSAR/ Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is set Acceptance Criteria is met
[YES NO L YES No VI Comments
- As Rep ired Completed By: Ib- - > -
Evaluated By: 5.M ,k est E w eer Recommended for Approval By - ((NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 55 of 58
2-PT-28.ll ATTACHMENT 1 PAGE 16 0F 19 SURRY POWER STATION UNIT 2 CYCLE 10
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
$ I Test
Description:
M/D Flux Map-At Power,NI Calibration Reference -
Proc No / Section: 2-PT-28.2, 2-OP-57 Sequence Step Noi 45 II Bank Positions (Steps) RCS Temperature'('F): TREF *i Test Power Level (% F.P.): - 70 Conditionsi' SDA: 225 SDB: 225 CA: 225 ' Other (specify): a (Design) I CB : 225 CC : 225 CD: ss ,
III lBankPositions(Steps) RCS Temperature (8F) TggF Test , Power Level (% F.P.): M */,
Conditions SDA: 225 SDB: 225 CA: 225 other (Specify):
(Actual) [ CB : 225 CC : 225 CD: 17 0 QL.; ARTE.R. GRE. M AP 21 TNf M86.ES
' Date/ Time Test Performed:
p\ A P - 02.- 1C - C3
- I o / z. / B*i 0:i 2.c i
l MAX,REL NUC ENTHALITOTAL HEATI QUADRANT ,
'IV Mens Parameter ASSY PWR RISE HOT FLUX HOT l POWER TILT (Description) % DIFF CHAN FACT CHAN FACT l RATIO
. . (M-P)/P F-dH(N) F-QCT) j QPTR Measured Value QA g4 g4 g Results Design Value (Design Conds) ,,,,,,,,d...,
fe'O U:.' .' NA NA 5 1.02 WCAP-7905 {WCAP-7905 Reference REV.1 NONE NONE REY.1 i
" ~
V FSAR/ Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met : /YES NO Acceptance Criteria is met : /,,_YES _ NO VI Comments s Must have at least 38 thimbles for a full-core flux map, or at least 16 thimbles for a quarter-core flux map.
su As Required ,
Completed By: N -
Evaluated By: b M- = - -
res Eng meer Recommended for #
Approval By : fd "
NAF Engineer NE-757 S2C10 Startup Physics Tests Report Page 56 of 58
_y _. _ _.
i -
2-?To23.1i ATTACm!ENT 1 PAGE 17 0F 19 p
IU . .3
! SURRY POWER STATION UNIT 2 CYCLE 10 p STARTVP PNYSICS TEST RESULTS AND EVALUATION SHEET
- 6 ""
I Test
Description:
M/D Flux Map-At Power.NI Calibration i
Reference Proc No / Section: 2-PT-28.2, 2-0P-57 Sequence Step No: !. 6 l.
H II Bank Positions (Steps) l 'RCS Temperature ('F):T #1 L Test REF L Conditions , Power Level (% F.P.): - 70 SDA: 225 SDB: 225 CA: 225 j Other (specify):
- l (Design) 1 CB : 225 CC : 225 CD: **
a >
i III lBankPositions(Steps) RCS Temperstwe( 8F): "T g,gp Test Conditions, Power Level (% F.P.): (o g SDA: 225 SD8: 225 CA: 225 other (Specify):
L (Actual) CB : 225 CC . 225 CD: 19 0 ouAeTr2 0;.ee. gap Date/ Time Test Performed: '
to/2./gq 13 6- MAP M -IC - o4 4 i .
j MAX. REL NUC ENTHALITOTAL HEATI QUADRANT IV } Meas Parameter ASSY PWR l
(Dest;ription)
RISE HOT I FLUX HOT IPOWER TILT
% DIFF CHAN FACT CHAN FACT ' RATIO
. (M-P)/P F-dM(N) F-Q(T)
QPTR -
1 l Measured Value g g4 Results l Design Value ;;g;;pt;;
- (Design Conds) '
"i'""' NA NA i 5 1.02 WCAP-7905 lWCAP-7905
, ' Reference REV.1 NONE NONE lREV.1 V FSAR/ Tech Spec.
e'.mi.n n... ..n. rlive.w. . .,i/,
NONE NA Acceptance ,
Criteria Reference l NONE TS 3.12 TS 3.12 {TS3.12 l
Design Tolerance is met : / YES NO Acceptance Criteria is met : /YES NO VI Comments s Must have at least 3B thimbles for a full core flux asp, or at least 16 thimbles for a quarter core flux map.
- As Required Completed By. .W -
Evaluated By: Y m%
Recommended for Approval By : "
NAF / Engineer NE-757 S2C10 Startup Physics Tests Report Page 57 of 58
0 2-PT-28.11 ATTACHMENT'1 l -. PACE 18 0F-19 l
W. .. 3 SURRY POWER-STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description + M/D Flux Map - HFP, ARD, Eq. Xe Reference ! Proc No /-Section: 2-PT-28.2, 2-0P-57 Sequence Step No: 47 II Bank Positions (Steps) RCS Temperature (8F): TREF *1 Test ; Power Level i% F.P.):95 2 5 Conditionsi SDA: 225 SDB: 225 CA: 225 j Other (specify): Eq. Xe.
(Design) l CB : 225 CC : 225 CD:
- lMusthave238 thimbles III Bank Positions (Stet.s) RCS Temperature ('F): 'TA.aF Test , Power Level (X F.P.):-- gco'7, Conditionst SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) _l CB : 225 CC : 225 CD: 2.0 / q Date/ Time Test Performed:
to(9ls9 t f t 2,*/ d 52-/O-c(,
i MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameteir ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) % DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) DQ(T) QPTR
- M .S*4 Measured Valse O'9 g,q 7q I,gq o j.OIO Results "'
Design Value ;gg; ;;
(Design Conds) 'S * =-
REV.1 NONE NONE REV.1 I
V lFSAR/TechSpec NONE NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Toleran e is met :
- YES NO Acceptance Criteria is met -
/ YES N0 VI Comments a As Required Completed By: b u -
Evaluated By: U T>st Engineer Recommended for -1 Approval By : , 've l
1
-NE-757 S2C10 Startup Physics Tests Report Page 58 of 58