ML20083C995
| ML20083C995 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/08/1995 |
| From: | Clemens C, Lawrence D, Trace D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18151A903 | List: |
| References | |
| NE-1023, NUDOCS 9505230209 | |
| Download: ML20083C995 (58) | |
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I TECHNICAL REPORT NE-1023 - Rev. O I ~ I SURRY UNIT 2, CYCLE 13 STARTUP PHYSICS TESTS REPORT I NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER I APRIL 1995 I PREPAREDBY:d C. D SClemens f Date f l , REVIEWED BY: f/0/98- ! D. A. Trace Date REVIEWED BY: ._ , , //Ik [ j D. C. Lawrence Date V 7I I APPROVED BY: D. Dziadol/z U Date ' I QA Category: Nuclear Safety Related 4 g ) I I
L r I L CLASSIFICAT10h/ DISCLAIMER , 1 F L The data, techniques, information, and conclusions in this report have l [ been prepared solely fo.. use by Virginia Electric and Power Company (the j l Company), and they may not be appropriate for use in situations other than I those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING [ OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it. 4 E -- --------
i Oi 5' l TABLE OF CONTENTS l l 4 PAGE Classification / Disclaimer............................... 1 Table of Contents....................................... 2 _ List of Tables.......................................... 3 i List of Figures......................................... 4 i Preface................................................. 5 l Section 1 Introduction and Summary................... 7 ) Section 2 Control Rod Drop Time Measurements......... 16 Section 3 Control Rod Bank Worth Measurements........ 21 ) I Section 4 Doron Endpoint and Worth Measurements...... 26 ; I Section 5 Temperature Coefficient Measurement........ 30 l l l Section 6 Power Distribution Measurements............ 32 1 Section 7 References................................. 39 j 1 APPENDIX Startup Physics Test Results and Evaluation Sheets........................ 40 I I I I II l i l' NE-1023 S2C13 Startup Physics Tests Report Page 2 of 56 s-3
L LIST OF TABLES u TABL5 TITLE PAGE F l l
. l 1.1 Chrnr. ology of Tests................................... 10 i L 2.1 Ilo t Rod Drop T i m e Su m ma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18
~ 3.1 Control Rod Bank Worth Summary........................ 23 L 4.1 Boron Endpoints Summary............................... 28 5.1 Isothermal Temperature Coef ficient Summary. . . . . . . . . . . . 31 6.1 Incore Flux Map Summary............................... 34 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits...................... 35 I I k I NE-1023 S2C13 Startup Physics Tests Report Page 3 of 56
O, U LIST OF FIGURES FIGURE TITLE PAGE 1.1 Core Loading Map......................................... 11 1.2 Beginning of Cycle Fuel Assembly Burnups . . . . . . . . . . . . . . . . . 12 1.3 Incore Thimble Locations................................. 13 1.4 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 l l 1 3.1 Bank B Integral Rod Worth - HZP.......................... 24 ; 3.2 Bank B Differential Rod Worth - HZP...................... 25 l l 4.1 Boron Worth Coefficient.................................. 29 I 6.1 Assemblywise Power Distribution - 30% Power.............. 36 6.2 Assemblywise Power Distribution - 69% Power.............. 37 l
'6.3 Assemblywise Power Distribution - 97% Power.............. 38 I
I I I I NE-1023 S2C13 Startup Physics Tests Report Page 4 of 56 si
r f-t PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 13 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard test techniques and methods of data analysis were used. The test data, results, and evaluations, coupled with the detailed startup procedures, are on file at the Surry Power Station. Therefore, only a cursory f discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results. The Surry 2, Cycle 13 Startup Physics Test Results and Evaluation Sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) 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 at these design conditions for the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group . 1 During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the NE-1023 S2C13 Startup Physics Tests Report Page 5 of 56
O O I preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests. I I I I I I: I I I I I I I t NE-1023 S2C13 Startup Physics Tests Report Page 6 of 56 a iii
I ; I SECTION 1 I INTRODUCTION AND
SUMMARY
I On February 3,1995 Surry Unit 2 shut down for its twelfth refueling. During this shutdown, 77 of the 157 fuel assemblies in the core were replaced with 56 fresh assemblics and 21 twice-burned assemblies. The Cycle 13 core consists of eight sub-batches of fuel: two fresh batches (batches 15A and 15B); two once-burned batches from Cycle 12 (batches 14A and 14B); and four twice-burned batches, one from Surry 1 Cycles 11 and 12 (batch S1/13D), one from Surry 1 Cycles 7 and 8 (batch S1/9A), one from Surry 2 Cycles 11 and 12 (batch 13A), and one from Surry 2 Cycles 7 and 8 (batch 9A). The core loading pattern and the design parameters for each sub-batch are shown in Figure 1.1. Beginning-of-cycle (BOC) fuel assembly burnups are given in Figure 1.2. The incore thimble locations available during startup physics testing are identified in Figure 1.3. Figure 1.4 identifies the location and number of burnable poison rods and secondary source locations for Cycle 13, while Figure 1.5 identifies the control rod locations. The Cycle 13 core achieved initial criticality at 2250 on March 19, 1995. Following criticality, startup physics tests, except hot rod drops which were performed prior to criticality, were performed ac outlined in Table 1.1. A summary of the physics test results follows.
- 1. The measured drop time of each control rod was within the 2.4
,I l second limit of Technical Specification 3.12.C.1. I NE-1023 S2C13 Startup Physics Tests Report Page 7 of 56
l 0: O) I!
- 2. The reference control rod bank was measured with the dilution method, and the result was within 3.4% of the design prediction. E' l Individual control rod bank worths were measured using the rod swap technique 84 8 and all results were within 4.4% of the design
]
predictions. The sum of the individual measured control rod bank worths was within 1.0% of the design prediction. All results were within the design tolerance of 115% for individual bank worths 1 ( 10% for the rod swap reference bank worth) and the design am g, tolerance of 110% for the sum of the individual control rod bank , 1 worths. l
- 3. Measured critical boron concentrations for two control bank configurations were within 24 ppm of the design predictions. The all-rods-out ( ARO) result was within the 50 ppm design tolerance, and met the Technical Specification 4.10.A criterion that the overall core reactivity balance shall be within 11% Ak/k of the design prediction. The reference bank in critical boron concentration was within its design tolerance.
- 4. The boron worth coefficient measurement was within 1.8% of the I
design prediction, which is within the design tolerance of 110%.
- 5. The measured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within 0.71 pcm/'F of the design prediction. This result is within the design tolerance of 13 pcm/'F. The measured ITC was -3.94 pcm/'F. When the Doppler temperature coefficient (-1.71 pcm/'F) and a 0.5 pcm/'F !
uncertainty are accounted for in the +3.0 pcm/'F MTC limit of the l NE-1023 S2C13 Startup Physics Tests Report Page 8 of 56 Bl 3, l
t. L I L Core Operating Limits Report (COLR) Section 2.1, the MTC - requirement is satisfied as long as the ITC is less positive than 0.79 pcm/'F. L
- 6. Measured core power distributions were within established acceptance criteria and COLR limits. The average relative assembly power distribution measured / predicted percent difference L was 2.07, or less for the three initial power ascension flux maps.
The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of COLR Sections 2.3 and 2.4, respectively. In summary, all startup physics test results were acceptable. Detailed results, specific design tolerances and acceptance criteria for [ each measurement are presented in the following sections of this report. s I ( NE-1023 S2Cl3 Startup Physics Tests Report Page 9 of 56
~ - ~ ~
C 0-I Table 1.1 SURRY 2 - CYCLE 13 STARTUP PilYSICS TESTS CilRON0 LOGY OF TESTS I Reference I Test Date Time Power Procedure E Hot Rod Drop - Ilot Full Flow... 3/19/95 0449 HSD 2-NPT-RX-014 5 Zero Power Testing Rango....... 3/20/95 0009 ilZP 2-NPT-RX-008 Reactivity Computer Checkout. . . 3/20/95 0057 HZP 2-NPT-RX-008 E Boron Endpoint - AR0........... 3/20/95 0320 HZP 2-NPT-RX-008- g Boron Worth Coef ficient - ARO. . 3/20/95 0742 HZP 2-NPT-RX-008 Temperature Coef ficient - ARO. . 3/20/95 0358 HZP 2-NPT-RX-008 Bank B Worth................... 3/20/95 0742 HZP 2-NPT-RX-008 Boron Endpoint - B in.......... 3/20/95 0742 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap........ 3/20/95 1557 HZP 2-NPT-RX-008 Bank C Worth - Rod Swap........ 3/20/95 1728 HZP 2-NPT-RX-008 Bank A Worth - Rexi Swap. . . . . . . . 3/20/95 1825 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap....... 3/20/95 1912 HZP 2-NPT-RX-008 Bank SA Worth - Rod Swap....... 3/20/95 1945 HZP 2-NPT-RX-008 . Flux Hap - 30% Power........... 3/21/95 0825 29.6% 2-NPT-RX-002 . Peaking Factor Verification 2-NPT-RX-005
& Power Range Calibration Flux Hap - 69% Power........... 3/23/95 0122 69.4% 2-NPT-RX-002 Peaking Factor Verification 2-NPT-RX-005
& Power Range Calibration Flux Hap - 97% Power. . . . . . . . . . . 3/28/95 1600 97.4% 2-NPT-RX-002 ;
Peaking Factor Verification 2-NPT-RX-005
& Power Range Calibration I
I I I Il l 1 Il NE-1023 S2C13 Startup Physics Tests Report Page i 1 10 of 56 iiis
t t F*igure 1.1 / SURRY UNIT 2 - CYCLE 13 CORE LOADING MAP R P N M L x J H G F E D C a & I 9A l Isa 1 9A 1 I las i Ive i eR2 1 1 I SA l 14e i Isa I tes l 15s I tes 1 9A i 1 4R4 I sus 1 3x2 l Sv7 l 3x9 l 6wl l 4k2 l 2 I 11A i 14A i 155 1 14s i 15s 1 14s l 15s 1 14A l lia l I 3vz l rus i 3x5 I sur 1 3x6 i rue 3va 1 3 I
.................................. 1 3x1.....1 6v5 .......... ........1 .............
t I lia 151/13s1 15s 1 I4s i 15A 1 lea i t ha 1 les I 1 54 151/1581 lia 1 1 Iv6 1 5H6 1 5x2 I sw9 1 ex5 1 ews I las 1 4w6 1 3xe i ont i eva 1 4 i
.................................................... ... ................................. \
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..........................i.3x4 ............1 .......
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.............................................................-- i sus 1 5x6 I she 1 l 94 1 15s l 14e i 15A i 14A 1 I5A i 14e i 14A 1 les 1 15A i 144 1 15A i 14n i 15s I 9A 1 tw4 i ex6 i Swt i rul i sw9 i txt I rwa 7
............................I l 6Re 14xs i Swl I txs
................................................ i ext i 6we i 5x4 I sR4 l I 15A I tes i 15s 1 14A l 15A i 14A i 14A ISI/9A i 14A i 14 l 15A i 14A i 15e i les I lsA l l rw,A I ext t tv2 I out I sus I rwe i lx9 l Iwl I lus 1 105 I ow9 2x, i sw4 i ryo 1 a
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........................................- __ ...............................__ _=.
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I 9A 1 154 I 9A 1 i FR9 1 ev3 i IR9 1 15 l 1 .) sATCH I 1 .) ASSEMBLY ID 1 1 FtKL ASSEMBLY DESIGN PARAfETERS Sun-sAIDH 9A 14A 148 15A 15s # SI/9A SI/lis I SA INITIAL INRICHMENT 3.59 4.os 3.59 3.s1 3.s1 4.et 3.at 4.el (w/0 U 235) suRNUP Af 80C 13 r$rts 14312 33771 54475 21515 23647 0 e inwD/Miul ASSIMsLY IYPE 15 15 15x15 15x15 15xl5 15x15 15x15 15x15 15x15 MuMatR Dr ASSI.MsLit$ 4 4 16 12 32 16 !s la FUEL PODS PER ASSEMsLY re4 Fe4 Fe4 r$4 re4 Fe4 2e4 2e4 NE-1023 S2C13 Startup Physics Tests Report Page 11 of 56
u> i n a, 1 I Figure 1.2 l l SURRY UNIT 2 - CYCLE 13 l BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS l R P N N L x J H C F E D C B a I tus I tva i ser i a 1 1 54.721 32.141 54.4al I 4e4 1 6ws I sur i sw? I sus I 6wa 1 *N I r 1 32.774 24.rel e.sel 22.911 e. eel. 25.111 52.521 1 I svr i rus I sus I sur i 3xt i 6Ws i 3x6 1 rue i sva 1 3
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l two I sem i Ext i sw9 I exs I aus I tra 1 nw6 I suo i 4HI l ove 1 4 35.151 54.691 e. col r2.761 e. eel 24.esi s.ee e. col 34.568 ss.961
.......1 .................................................l.23.744 ..................................
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.......1.17.9tl ..................................................................................
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.....................................................................1 ......
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I l.-> asMMaLY auRMUP (CwD/MfU) i I I I I I I E NE-1023 S2C13 Startup Physics Tests Report Page 12 of 56 su
I Figure 1.3 ! I I SURRY UNIT 2 - CYCLE 13 INCORE THIMBLE LOCATIONS 1 l i I I l R P N M L E J H G F E D C B A i l
- I l l If i l i I i l i 1 e 1 i i 1 IT
- 1 1 I I
/ l i I I i =1 8 I 11 1 l If 1 l l If l II l l 11 If 1 3 i 1 1 1 1 l l l ll l l 1 1 i i l I .I 11 11 l l i I I It ' i 1 If i 1 If 11 11 1 1 4 ! ! 1 1 I l l l 1 l 11 1 I I I a i 1 I =ll l :l l' I i 1 i l i If 1 i II l If i 11 ll If I If I I If i 5 i 1 1 i l l ll ll l l l l 1 1 1 1 1 I I I I i 1 i II l 11 IT 1 IT l .I I l l 6 1 l I i 11 1 1 ! I l I l i l I I i i i i i i } l 1. I li l l l fi l If IT l l 11 1 1 7 i ' I l l I l i n I l l I 1 e I I i !I l' I i i l i l l If I I If I 1 If I l' I l l IT 1 If It i 8 l i ' l 1 1 1
! ! 1 l l l 1 h 1 1 I I i l l l 1 Il 11 l If I If I l 1 IT l 9 1 1 I l 1 1 1 l l ll 1 -1 l l l h I I I If i 1 'l ti i i II 1 IT ll Is I I i 1 1 1 1 I
! 1 1 1 1 h I i ' I l l 1 i If 11 IT I IT IT l 1 1 11 1 1 l 1 1 I I l 1 1 1 1 i l I i 1 l l ! l II 1 1 I If 1 1 1 1 It i If 12 l l 1 l I l 1 1 i I 1 1 I e1 1 l l 1 1 1 If 1 If 1 I i 13 1 1 -1 1 I l l i l l l l l l 1 11 ., 1 IT l l 14 I ll 1 i i l 11 1 1 IT - Incore Th!able i It 11 1 1 15 m - Unavailable Location l 11 l l / I NE-1023 S2C13 Startup Physics Tests Report Page 13 of 56
n u O I Figure 1.4 SURRY UNIT 2 - CYCLE 13 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R P N M L K J H C F E D C B A I 1 1 1 l 1 *P 1 18P354 1 4P 1 l
,sessa i 1
I 1 I 2 I 1 1 1 1 l l 1 1 tsp 1 I toe l l 20P i i l 4 i IBP3ro I itPS% i lsPM9 l l 1 3 1 1 l i I i l 1 I l-1 l 8 top i i top i i rep 1 1 teP l ll l l 1 ISP371 1 IBP346 i ISP345 I (BP%s l l 4 i l I i l i i i l 1 1 l 1 1 top 1 I top i i top i i rep l l rop 11 i sse 1 InP372 1 ISP353 l IBP3:a 1 isP344 l l BPM 7 5 l i 1 1 I I I i 1 1 1 l l teP i i top I i rep l l top 1 i r$P 1 1 20P -1 I lbp373 I isP347 l&P329 I (SP327 1 l&P343 1 ISPM6 , l, 6 1 1 I I I I i 1 I I i i I I I I *P l 1 20P i I t9P l l 1 l 20P i 1 20P l ll 4P i l (BPhl l ISP346 1 IBP330 I i 1 lBP326 l lBP342 l 16P355 7 l l l,oP ' l,.rl l l l l l,oP l !.P 1 I lBP337 ISP131 1 I i 1 l lBP325 l lBP335 i 8 I I I i i l i 1 1 1 I I I l *P l ll rop I i rop l l l 1 rop i ll zoP i n *P 1 ss3 isP357 l lBP349 I IBP332 l l 1 ISP324 l l SP341 l l$P359 i $$5 :l 9 I I I I I I I i 1 1 1 1 I I I i top i i top i i top i 11 rop 1 j 20P l 20P 1 isP374 l lap 350 l 16P333 i i SP323 l lBP340 ISP%5 l ll 10 I I 1 I l i 1 ! I I i l i l t I i top i i teP i i top i top 1 I r0P 1 l li i I l Bears l lBP351 l IsP322 IsP339 l lBP%4 1 I l. I1 1 i l 1 1 i l 1 1 1 1 I I I i 1 top i i 20P 1 11 20P 1 i FOP l l 1 1 1 is9376 l lBP352 I IBP33a i IsP%3 1 I i 12 4 I I I I l i I l 1 l 1 4 l 1 1 29P 1 1 29P 1 1 20P l l l i I inP377 i IBP334 1 laPur i i 13 1 I I I I I I I I i i i i 4P 1 1 4P i i 1 I i I (BP360 1 ISP356 l l l 14 ! I i 1 1 1 I I I i 1 6 1 l 6P - 4 BURNABLE Po! SON ROD CLU$ffR 1 1 1 1 15 POP - 20 BURNABLE P01$0N ROD CLUSTER l l l 1 $$m - SECONDARY SOURCE 1 I xxP - 9 0F BP RODS BPoet, $50 - BP ASSEMBLY ID, SECONDARY SOURCE ID I I I E NE-1023 S2C13 Startup Physics Tests Report Pages 14 of 56 m
~ , Figure 1.5 - SURRY UNIT 2 - CYCLE 13 CONTROL ROD LOCATIONS R P N H L K J H C F E D C 8 A 180* 1 Loop C l l l l Loop B 1 Outlet l l l l Inlet
- N-41
*\ 1 l
l l*l l l sA 1 l" lI sA ll' l l l l J l N-43 3 ^ l i I i 1 1 1 I I I l lC l lB l l l l8 l lC l l 4 - l l l l 1 I i 1 1 1 1 I l l l l 1 sa l I i i i I sa 1 1 i i s l I I I I l I l i 1 1 1 1 I IA I Ie 1 iD l lC l lD I IB l lA l 6 Loop C l l 1 I I I I I I I I I l l Loop a i Inlet 1 I I sA I i l l sa 1 i sa 1 i l i sA 1 l 1 outlet 7 L \l i I i 1 1 1 1 1 I I I I I i 1/ va*- %I io I i i IC i 1 l lC i 1 l 10 l 1 - 270* 8 1 1 1 I I I I I I I I l l I I l
- l l l SA 1 l l l se I i se 1 l l l sA l i 1 9 i l l I I I I i i i I I I I I I IA I Ia 1 io l lC l l0 l ls 1 1A i 19 I i 1 1 1 1 I l 1 1 I I l 1 1 1 1 I sa l l l l l l ss i l l l 11 1 I I l l I I i 1 1 1 1 1 1 1 1C 1 ie i I i 1e l lC 1 1 12 I I I I I I I I I i 1 1 1 l l l sA I I sA i l l 1 , 13 H-44 i l i i l l l l l l N-42 i iA l lD l lA l l 14 1 1 l l I I l l I Absorber Material Loop A Outlet
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%Loop Inlet A
15 Ag-In-Cd O' I Function Number of Clusters Control Bank D 8 Control Bank C 8 Control Bank 8 8 Control Bank A 8 shutdown Bank sB 8 shuidown 8ank $A 8 NE-1023 S2C13 Startup Physics Tests Report Page 15 of 56 -
O O I SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full- flow reactor coolant system (RCS) conditions (Tavg of 54715'F) in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the maximum e '. lowed by Technical Specification 3.12.C.1. This test was performed at approximately 2247 psia. The rod drop times were measured by withdrawing a bank to its fully withdrawn position and tripping all eight control rods within the bank by opening the reactor trip breakers. This alle,wed the rods to drop into E the core as they would during a plant trip. The stationary gripper coil voltage and the Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded for each rod in the bank to determine each I I rod's drop time. This procedure was repeated for each bank. l As shown on the sample rod drop trace in Figure 2.1, the initiation I! 1 of the rod drop is indicated by the decay of the stationary gripper coil l 5 voltage when the stationary gripper coil fuse is removed. As the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters i the dashpot reginn of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod , reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing. I I NE-1023 S2C13 Startup Physics Tests Report Page 16 of 56 su
w. P. L r The measured drop times for each control rod are recorded on Figure 2.2. The slowest, fastest, and average drpp times are summarized in Table 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 seconds with the RCS at hot,' full flow conditions. The test results k satisfy this limit. E C C E [ [ [ [ NE-1023 S2C13 Startup Physics Tests Report Page 17 of 56
O O l-Table 2.1 l SURRY UNIT 2 - CYCLE 13 STARTUP PilYSICS TESTS Il0T ROD DROP TIME
SUMMARY
I ROD DROP TIME TO DASHPOT ENTRY I SLOWEST ROD FASTEST ROD AVERAGE TIME
\
F-06 1.40 sec. L-05 1.22 sec. 1.28 sec. \ .. I I ' I li l' I I I I NE-1023 S2C13 Startup Physics Tests Report Page 18 of 56 a E
L l l W Figure 2.1 I SURRY UNIT 2 - CYCLE 13 STARTUP PHYSICS TESTS L. TYPICAL ROD DROP TRACE 1 1 l Eh MOh lg g g org ,g ,,,g m G Mrut (BegermeQ Firm. % m% Upasa m Tra m N/ %" {."."." ^.".". .
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NE-1023 S2C13 Startup Physics Tests Report Page 19 of 56
n. u O I-Figure 2.2 SURRY UNIT 2 - CYCLE 13 STARTUP PilYSICS TESTS ROD DROP TIME - 110T FULL FLOW CONDITIONS R P N N L E J H C F E D C B A I I I i 1 1 1 1 1 1 l 1 1 I I I i 1 i i i i i 1 1.27 1 1 1.r6 I i 1.27 1 1 2 1 1 1 1 I I I l 1 1 1 I i i i i l i i 1 1 1 1.r6 l l 1.38 i i i I 3 1 1 I i i I i i l I , I I i i i i l i 1 i l i l l l 1.28 I i 1.25 I I I i 1.27 1 1 1.ra i 1 4 , 1 I i l i l I 1 1 I i 1 1 1 1 i l 1 i i 1 1 1 1 1 1 1 1 1 1.22 I i a l l 1.ra i i l 1 5 i i 1 i l 1 i n i 1 1 i i t i I I I i l 1 1 i i 1 1 I i 1.ra 1 1 1.26 1 1 1.31 i i 1.31 1 1.4e 1 1 1.27 L 11.321 6 1 I i i i l i I i 1 I l 1 , I 1 i i i 1 1 I h i I I i 1 1 1.27 1 1 1 1 1.re i 11 1.3e I I i 1.26 I ' 7 1 1 I I I I i i u i i 1 1 1 1 1 1 I i I I i 1. 1 ii ! l l 1.r3 i i l i 1.ra 1 1 1 1 1.5e I a.31 . a l 1. I I I i i l I l 1 1 i i i i l i i H I > 1 1 1 1.27 l l l l 1.5e l l 1.2a i 1.27 l 9 1 1 1 1 1 1 i i l 1 1 1 i i l i a l i 1 1.27 l l 1.r? l 1 1.31 1 1 1.5e 1 1.32 1 1.27 1.31 to l i l l 1 l 1 1 I h , i 1 1 l i I i 1 li l 11 I l 1 l l 1.26 l l l l 1 1.27 ' I I 11 i l i l i 1 l 1 i l l 1 l l t 1 I I i j i 1.27 l l 1.25 l 1 , t . ra 1 1.27 1: I tr l I I i 1 l l ll l' 1 I i l 1 1 1 l l l l 1.ra I i 1.ra l I 13 l l l l l l l l I I I I I 1 1 1.31 1 1 1.26 l 1.26 I I 14 1 1 l l i l i I l 1 1 1 l 1 1 1 15 I I i 1 l i i 1 x.xx l--> rod Duop 11410 D4$HPOI (NTRY ($(C) i I l II l li Bl li NE-1023 S2C13 Startup Physics Tests Heport Page 20 of 56 a er
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CQ SECTION 3 CONTROL ROD BANK WORTH NEASURENENTS , Control rod bank-worths were measured for the control'and shutdown banks using the rod swap technique e8 8 The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 13, 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 wfth all other banks fully withdrawn and recording the core reactivity and moderator temperature. From this point, a rod swap 4 maneuver was performed by withdrawing the reference bank several steps and then one of the ;other control rod banks (i.e. a test bank) was inserted to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical or near the initial statepoint reactivity. This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to NE-1023 S2C13 Startup Physics Tests Report Page 21 of 56
O O I determine the integral reactivity worth of the test bank. The core reactivity, moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver then was repeated in reverse such that the reference bank again was fully inserted with the test bank fully withdrawn from the core. This rod swap process was then repeated for each of the other control and shutdown banks. A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, all of the individual measured bank worths for the control and shutdown banks were within the design tolerance (110% for the reference bank, 115% for test banks worth greater than 600 pcm, and 1100 pcm for test banks worth less than or equal to 600 pcm). The sum of the individual measured rod bank worths was within 1.0% of the design prediction. This is well within the design tolerance of fl0% for the sum - of the individual control rod bank worths.
~
The integral and dif ferential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the reasured rod worth values were satisfactory. I I I I-NE-1023 S2C13 Startup Physics Tests Report Page 22 of 56 a as
-Y r-L k, Table 3.1 e SURRY UNIT 2 - CYCLE.13 STARTUP PHYSICS' TESTS l
CONTROL ROD BANK WORTH
SUMMARY
I MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH (%) BANK (PCM) .(PCM) (M-P)/P X 100 B-Referene.e Bank 1382.0 1336.0 3.4 D 1187.0 1203.4 -1.4 C 767.0 801.9 -4.4 A 333.0 341.8 -2.6* SB 1133.0 1145.6 -1.1 SA 1084.0 1116.4 -2.9 Total Worth 5886.0 5945.1 -1.0
- Difference is less than 100 pcm.
NE-1023 S2C13 Startup Physics Tests Report Page 23 of 56
01 m, i Figure 3.1 3i SURRY UNIT 2 - CYCLE 13 STARTUP PHYSICS TESTS El l BANK B INTEGRAL ROD WORTH HZP l ALL OTHER RODS WH HDRAWN , 1400 ' b- Predicted w ' Ni T s Measured s, 1200 \ . ! ____. "1 1 1 l _\ I
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O 40 80 120 160 200 ' R 3ANK POSITION (5 STEPS / DIVISION) al NE-1023 S2C13 Startup Physics Tests Report Page 24 of 56
k Figure 3.2 SURRY UNIT 2 - CYCLE 13 STARTUP PHfSICS TESTS BANK B DIFFERENTIAL ROD WORTH - HZP l ALL OTHEP.iiVDS WITHDRAWN 12 Predicted s ""
. Measured E -----
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NE-1023 S2C13 Startup Physics Tests Report Page 25 of 56
C-0 I SECTION 4 BORON ENDPOINT AND WORTl! MEASUREMENTS , Horon Endpoint g. 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 I at or very near a selected endpoint position. Adjustments to the measured critical boroa 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 Ctartup Physics Test Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values ~ were within their respective design tolerances. The all-rods-out (ARO) endpoint comparison to the predicted value met the requirements of Technical Specification 4.10. A regarding core reactivity balance. In summary, the boron endpoint results were satisfactory. I Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, I NE-1023 S2C13 Startup Physics Tests Report Page 26 of 56 E er
=
f' l-the value of the DBW over the range of boron endpoint concentrations was obtained. A plot of the boron concentration versus inserted control rod w: orth . is shown in Figure 4.1. As indicated in this figure and in the Appendix, the measured DBW was -7.47 pcm/ppe. This is within 1.8% of the predicted value of -7.34 pcm/ppe and is well within -the design tolerance of 210%. In summary, the measured boron worth coefficient was satisfactory. ( NE-1023 S2C13 Startup Physics Tests Report Page 27 of 56 1 1
C I f Table 4.1 SURRY UNIT 2 - CYCLE 13 STARTUP PilYSICS TESTS BORON ENDPOINTS
SUMMARY
I i g: Heasured Predicted Difference W Control Rod Endpoint Endpoint H-P Configuration (ppe) (ppm) (ppa) g, g; ARO 1679 1703 -24 B Bank In 1494 1497* -3
- The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as showh in the boron endpoint Startup Physics Test Results and Evaluation Sheet in the Appendix.
I I I I. I-f I l I-l l I NE-1023 S2C13 Startup Physics Tests Report Page 28 of 56 t
=s
? .x L F 1 Figure 4.1 1 SURRY UNIT 2 - CYCLE 13 STARTUP PHYSICS TESTS BORON WORTH COEF71CIENT t : L Measured DBW = -7.47 pcm/ ppm
" 00 g
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m \ g 0- % 1480 1500 1520 1540 1560 1580 1600 1620 1640 1660 1680 BORON CONCENTRATION (PPM)
~
NE-1023 S2C13 Startup Physics Tests Report Page 29 of 56
Oi O' i SECTION 5 Ej g, l TEMPERATURE COEFFICIENT MEASUREMENT El q' l l The issthermal temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature through varying the steam generator blowdown flow, lll l establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer. This test sequence includes a cooldown followed by a heatup. Reactivity was measured during an RCS cooldown of 3.5'F and an RCS heatup of 3.2*F. Reactivity and temperature data was taken from the - reactivity computer and strip chart recorders. Using the statepoint , method, the temperature coef ficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statopoint method in calculating the measured ITC. The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from chis summary and from the Startup Physics Test Results and Evaluation .9heet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of 13 pcm/'F. Accounting for the Doppler temperature coefficient (-1.71 pcm/'F) and a 0.5 pcm/'F uncertainty, the moderator temperature coefficient was -1.73 pcm/'F, which meets the requirement of Core Operating Limits Report Section 2.1. In summary, the measured result a El ' war. aatisfactory. I l NE-1023 S2C13 Startup Physics Tests Report Page 30 of 56 EI m'
l Table 5.1 SURRY UNIT 2 - CYCLE 13 STARTUP PilYSICS TESTS ISOTIIERHAL TEMPERATURE COEFFICIENT
SUMMARY
CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/0F) BANK
- TEMPERATURE BORON POSITION RANGE CONCENTRATION C/D ll/U AVE. DIFFER.
(*F) (ppm) MEAS. PRED. (M-P) D/227 542.8 l & to 1680 -4.43 -3.44 -3.94 -4.65 0.71 D/217 547.1 L
- The cooldown ITC wa. mea.ured with D-bank at 227 W steps. The heatup ITC was measured with D-bank at 217 steps.
l I 1 l I l I - l I h
. .... - . ..F . ... . .... R.F... .... .. . . . .
E a I SECTION 6 POWER DISTRIBUTION MEASUREMENTS I I The core power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles depicted in Figure 1.3. For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using the CECOR code". CECOR couples the measured voltages with predetermined analytic signal-to power conversions, pin-to-box factors, and average " coupling coef ficients in order to determine the puer distribution for l the whole core. A list of the full-core flux maps taken during the startup test program and the measured values of the important power distribution parameters are given in Table 6.1. A comparison of these measured values a with their Technical Specification limits is given in Table 6.2. Flux map 1 was taken at approximately 30% power to verify the radial power distribution (RPD) predictions at low power. Figure 6.1 shows the measured RPDs from this flux map. Flux maps 2 through 3 were taken near 69% and 97% power, respectively, with different control rod configurations. These flux maps were taken to check at power design ( predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 through 6.3. These figures show that the average relative assembly power distribution measured / predicted percent difference was NE-1023 S2C13 Startup Physics Tests Report Page 32 of 56 a
=<
'h i
2.07. or less for the three maps. The measured F-Q(Z) and F-DH(N) peaking factor values for. all flux maps were within the Ifmits of the Core Operating Limits Report (COLR) Sections 2.3 and 2.4, respectively. Flux maps 1 and 2 were used to recalibrate the power range excore detectors. A power range detector calibration based on flux map 3 verified the existing calibration was satisfactory. In conclusion, the power distribution measurement results were considered to be acceptable with respect to the desigr. tolerances, the accident analysis acceptance criteria, and the COLR limits. It is therefore anticipated that the core will continue to operate as designed throughout Cycle 13. l 1 i [ [ [
, NE-1023 S2C13 Startup Physics Tests Report Page 33 of 56
Fl. L W TABLE 6.1 SURRY UNIT 2 - CYCLE 13 STARTUP PilYSICS TESTS l INCORE FLUX MAP
SUMMARY
l I n i i i I l l 1 i l 2 l l l I I ll 3 l l l BURN l l l F-Q(2) HOT F DH(M) HOT l CORE F(2) l POWER l l l 1 MAP l MAP l l UP l ISANK l CHA89tL F ACTOR CNNL. FACTOR l MAX l Titi l AXIAll NO.i 1 DFSCRIPI!ON lNO.1 DATE l MWD /IPWR'I D l l l l OFF l OF i 1 l l l MTU l(2) Sf f PS t AS$Y I AXIAL i ASSV F-DH(N)l AMI All F(lill MAX (LOC l SET lfHIMl i l l l l POINI l F-Q(2) . lPOINfl l l (X) 18tESl l LisS IHN 382 PWW l Y i 3*23*95 2 l 153 M13 31 l 2.314 Mll l 1.495 32 11.425 1 -9.45 l sfWN 65% AND 75% l 2 l 3+23*951 29 l 69l IFF l Cl4 . 32 1 1.997 l HIS I 1.435 l 31 11.276l1.886l SEl -4.611 44 l l C#f THAN 95% PWR l 3 l 3-28-951 186 l 91l 225 i He31 32 1 1.841 l Dil I !.411 1 32 11.196l1.006l SEl -1.30l 44 l l 1l l ll i l l l l l 1 i l_ _ I ll N0lfS H0f SPOT LOCA!!ONS ARE $P(CIFlf D BY CIVING ASSEMBLY LOCATI0sti (E.G. Hoe IS THE CEMIER-OF-CORE ASSEMBLY), AND COPE HEICHI (IN ItE "2" BIRECIl0N IHE CORE IS DIVIDED INTO 61 AXtAL POINTS SIARTING FROM IIE TOP OF THE CORC3.
- 1. F-Q(2) INCLUDES A 10f AL UNCERTAINTY OF 1.08.
- 2. POWER TILT - DEFINED AS f 6E AVERACE QUADRANT POWER T!LT FROM CECOR.
- 3. F ACH MAP WAS USE D 10 PERF0k11 A PEAXING FACTOR VERIFICAf!ON AND A POWER RANCE EXCORE DE1ECIL9f CallSRAll0N. IFE FLUX MAP 3 CALinRAf!ON VtRIF110 THE EXISIING CAL ISNAf!UN.
I I I I I I I I NE-1023 S2C13 Startup Physics Tests Report Page 34 of 56 a
=
L I' Table 6.2 r SURRY UNIT 2 - CYCLE 13 STARTUP PHYSICS TE3TS COMPARISON OF MEASURED POWER DISTRIBUTION PARAMETERS WITil TilEIR CORE OPERATING LIMITS l PEAK F-Q(Z) I!OT F-Q(Z) Il0T F-DH(N) Il0T CilANNEL FACTOR
- CilANNEL FACTOR ** CilANNEL FACTOR (AT NODE OF MINIMUM MARGIN)
MAP MEAS LIMIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN NO. (%) (%) 1 2.314 4.640 31 2.314 4.640 31 50.1 1.495 1.889 20.9 2 1.997 3.344 32 1.995 3.335 30 40.2 1.435 1.703 15.7 3 1.841 2.382 32 1.841 2.382 32 22.7 1.411 1.572 10.2
- The Technical Specification's limit for the heat flux hot channel factor, F-Q(Z), is a funct ion of core height and power level.
The values for F-Q(Z) listed are the maximum value of F-Q(Z) in the core. The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(Z).
** The value for F-Q(Z) listed above is the value at the plane of minimum margin. The minimum margin values listed are the minimum percent difference between the measured values of F-Q(Z) and the Technical Specification's limit at that node for each map.
The measured F-Q(Z) hot channel factors include 8% total uncertainty. s NE-1023 S2C13 Startup Physics Tests Report Page 35 of 56 . '
111, sus 1 1 I lll1 F1gtore 6.1 SURRY UNIT 2 - CYCLE 13 STARTUP P11YSICS TESTS I. 1 ASSEMBLYWISE POWER DISTRIBUTION 30% POWER R P N M 1 K J H C F E D C 4 A
. PRf Dicit 0 . . 0.269 . 4.334 . 0.269 . PRf DIClLD .
. ME ASURf D . . 9.267 . 4.332 . 4.269 . . MEASURfD . 1
. PCT DIFF E RE NCE. . -0.6 . -0.5 . 0.0 . . PCT DIFF2RE NCE. :
0.258 . 0.641 . 1.120 0.497 . 1.120 . 0.642 . 9.259 .
. 9.257 . 0.637 . 1.112 . 0.890 . 1.122 . 0.657 . 9.261 . 2
. -0.6 . -0.6 . -0.7 . -0.8 . 0.2 . 2.3 . 1.0 .
. 9.298 . 0.741 . 1.210 . 1.218 . 1.306 . 1.270 . 1.211 . 0.782 . 0.294 .
- 0. 295 . 0. F 77 . 1. 20 2 . 1. 269 . 3. 296 . I . 2 75 . 1. 23 4 . 0. 74I 0.300 3
. ~0.8 . -0.5 . 0.1 . *0.1 . -0.6 . *0.2 . 9.2 . 0.0 . 8.1 .
. 0.298 . 0.654 1.237 . 1.306 1.307 . 1.2a9 .1.304 . 1.306 . 1.239 0.655 . 4.294 .
. 0.298 . 0.653 , 1.233 . 1.297 . 1.294 . 1.216 . 1.298 . 1.303 . 1.250 . 0.645 . 0.292 . 4
. 0.2 . -0.1 . -0.4 . -0.7 -1.0 . -1.0 -0.7 . -0.2 . -0.7 -1.5 . -2.1 .
. 0.254 . 0.780 . 1.239 1.314 . 1.245 . 1.269 . 1.247 . 1.270 . l.244 . 1.316 . 1.241 . 0.741 . 9.258 .
. 0.260 . 0.783 . 1.241 . 1.320 . 1.273 . 1.249 . l.263 . 1.250 . 1.272 . 1.300 . 1.208 . 0.760 . 0.245 . 5
. 0.7 . 0.4 9.2 . 0.5 . =0.9 . 1.6 . -1.9 . -I.5 . -1.1 . -1.2 . -2.6 . -2.6 . -5.1 . .
0.640 . l.209 1.306 . 4.286 1.170 . 1.242 . l.235 . l.245 . 1.172 . l.284 . 1.304 . 1.212 . 0.641 .
. 0.646 . 1.214 . 1.306 . l.272 . 1.144 . 1.209 . 1.193 . l.213 . 1.253 . 1.262 . 1.274 1.184 . 0.632 . 6
. 1.0 0.7 . -0.1 . -1.1 . -1.9 . -2.6 . -3.4 . -2.5 . -1.4 . -2.0 . -2.7 . -2.3 . -1.4 .
. 0.264 . 1.117 . 1.277 . 1.307 . l.270 . 1.244 . 1.245 . l.243 . 1.249 . 1.245 . l.272 . 1.309 . 1.279 . 1.118 . 0.265 .
. 0.269 1.133 1.295 . 1.308 . 1.251 . 1.216 . 1.199 1.201 1.204 . 1.210 . 1.237 . 1.261 . 1.250 . 1.122 . 0.264 7
. 1.7 . l.4 1.4 . 0.0 . -1.4 . =2.2 . - 3. 7 . -3.4 . -3.6 . -2.8 . -2.8 . *3.7 . -2.2 . 0.4 -0.1 .
. 0.333 . 0.895 . 1.304 . 1.288 . 1.286 . 1 . 2 34 . 1.238 1.040 . 1.249 . 1.239 . 1.290 . 1.290 . 1.306 . 0.096 . 0.333 .
. 0.34l . 0.910 . 1.322 . 1.290 . 1.252 . 1.210 . 1.207 1.012 . 1.211 . 1.199 , 1.257 . 1.257 . 4.266 . 0.886 . 0.327 . 8
. 2.5 . l.7 . 1.4 . 0,2 -2.6 . -l.9 . -2.5 . -2.7 . -3.1 . -3.3 . -2.5 . 2.6 . -3.0 . -1.2 . -1.8 .
. 0.264 . 1.117 . 1.217 . 1.307 . 1.269 . l.241 . 1.243 1.243 . 1.251 . 1.244 . 1.213 . 1.310 l.279 . 3.119 . 0.265 .
. 0.271 . 3.143 . 1.306 . f.330 . 1.286 1.234 . 1.238 . 1.217 . 1.218 . 1.210 . 1.252 . 1.296 . 1.263 . 1.107 . 9.247 . 9
. 2.4 . 2.3 . 2. 3 , 1.4 . 3.3 -0.5 . -2.0 -2.1 . *2.7 . -3.0 . -1.6 . -1.1 . - 1. 2 . -1.1 . -6.5 .
. 0.640 . l.209 . 1.306 . l.285 . 1.169 1.243 . 1.235 . 1.244 . 3.173 . 3.209 . 1.309 1.212 . 0.641 .
. 0.661 . 1.256 1.347 . 1.319 . 1.172 . 1.209 1.220 . 1.229 . 3.156 . 1.289 . 1.320 . 1.216 . 0.649 . 10
. 3.2 . 3.9 . 3.1 . 2.7 . 0.2 . -2.7 . *l.3 . -1.2 . -1.4 . 9.1 . 0.9 . 0.3 . 1. 3 .
. 0.254 . 0.780 1.234 . 1.314 . 1.284 1.269 . 1.247 . 1.210 . 1.286 . 1.316 . 1.241 . 0.781 . 9.258 .
. 9.267 . 0.810 . 1.291 . 1.347 . 1.318 . 1.281 . 1.297 . 1.217 . 1.291 . 1.344 . 1.263 . 0.790 . 0.262 . Il 3.6 3.9 . 4.2 . 5.6 . 2.6 . 1.0 . 0.8 . 0.5 . 0.4 . 2.1 . 1.4 . 1.1 . 1.2 .
. 0.298 . 0.654 1.237 1.305 . 1.307 . 1.289 1.304 . 1.307 . 1.239 0.655 . 9.298 .
. 6.306 . 0.641 . 1.298 . 1.545 3.347 . 1.318 . 1.334 . 1.332 . 1.268 . 0.678 . 0.302 . 12
. 3.0 . 4.1 . 4.3 . 3.4 . 3.0 . 2.2 . 2.0 . 1.9 . 2.4 . 3.5 . 1.3 . .
9.298 . 0.788 . 1.210 . 1.218 . 1.306 . 1.278 . 1.241 . 0.782 . 0.294 .
. 0.310 . 0.812 . 1.252 . 1.318 . 1.344 1.319 . 1.24% . 0.803 . 0.307 . 13
. 4.1 . 4.0 . 3.5 . 3.2 . 3.0 . 3.2 . 2.7 . 2.7 . 3.1 .
. 0.258 . 0.641 . 1.120 0.497 . 3.120 . 0.642 . 0.259 .
. 4.271 . 0.664 . 1.155 . 0.926 . 1.180 . 0.667 . 0.267 . 14
. 4.7 . 3.5 . 3.2 . 3.3 . 5.3 . 4.0 . 3.3 .
. STANO&R0 . . 9.269 8.354 . 0.269 . . AvtPAGE .
. DE VI AllDN . . 9.273 . 4.345 . 0.202 . . PCT DIFFE RENCE. 15
. =1.341 . . 1.6 . 3.4 . 4.9 . .
- 2.0 .
SLRW1ARY NAP NOR $2-13-01 DATE: 3/21/95 POWERI 29.6% CONTROL ROD POSITIONS: F-QtZ) = 2.314 QPTRI D BANK AT 153 STEPS F-DHIN) = 1.495 MW 8.9919 HE e.9842 F(Z) = 1.425 SW 1.0188 l SE 1.0051 BURNUP = 1.5 MWD /NTU A.0. s -9.449% NE-1023 S2C13 Startup Physics Tests Report Page 36 of 56 lll'
=,
s Figure 6.2 g SURRY UNIT 2 - CYCLE 13 STARTUP Pl!YSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 69% POWER R P W 4 1 E J N G F E D C 8 A
. PRfDICllD . .sy* 0.370 . 0.P95 . PREDICTED .
. NE ASURf D . . 9.t94 . 0.373 . 4.297 . MEASURED . 1 i
. PCT DIFFERENCE. -0.1 . 0.3 . 0.9 . . PCT DIFF8_RENCE. l
................ ......................................................... ................ l
. 0.277 . 0.664 . 1.147 . 0.952 . 1.147 . 0.664 . 0.277 . l
. 9.274 . 0.660 . 3.145 . 0.955 . 1.159 . 0.642 . 9.282 . 2 I
. -0.8 . *0.5 . -0.2 . 4.3 . 1.0 . 2.0 . 2.0 .
. 8.317 . 0. F91. 3.194 .1.267 .1. r90 . 1.267 .1.198 . 0. F97 . 0.35 F .
. 0.317 . 0.788 . 3.190 . 1.261 . 1.286 . 1.216 . 1.236 . 0.807 . 0.318 . 3
. -l.6 -1.0 . -0.F . -0.4 . -e.3 . 0.7 . 1.6 . 1.3 . 4.4 .
. 0.317 . 0.670 .1.214 . 1.F80 . 1.F74 . 4.46k . 1.274 .1.280 . 1.219 . 0.671 . 0.317 .
. 4.315 . 0.664 . l.203 . 4.271 . 1.269 . l.266 . 1.284 . 1.305 . 1.233 . 0.647 . 0.313 . 4
. -0. F . -0.9 . -1.2 . -0.7 . -0.4 . 0.3 . 0.8 . 1.9 . 1.1 . -0.5 . -1.3 .
0.276 . 0.796 1.219 .1.t93 . 1.263 . 1.250 .1.257 .1.251 . 1.264 . 1.294 .1.220 . 0.796 . 0.276 .
. 9.275 . 0.792 . 1.214 . 1.299 . 1. tS6 1. 24 2 . 1. 252 . 1. 253 . 1. 2 77 . 1. 304 . 1.196 . 0. 781 . 0. 263 . 5
. -0.4 -0.5 . -0.4 . 0.5 . -0.5 . -0.6 . -0.5 . 0.2 . 1.0 . 1.1 . -2.0 . -1.9 . -4.9
. 0.663 . 1.197 . 1.208 1.264 3.197 . 1.F33 . 1.229 . 1.235 . 1.194 . 1.265 . 1.201 . 1.197 . 0.663 .
. 0.661 . 1.192 . 1.264 . 1.237 . 3.184 . 1.214 . 1.204 . 1.229 1.208 . 1.265 . 1.765 . 1.101 . 0.654 . - 6
. -0.2 . -0.4 . -1.0 . -2.1 . -1.1 . -1.2 . -1.6 . -0.5 . 0.8 . 0.0 . -1.3 . -1 3 . -1.1 .
. 0.290 . 1.144 . 1.266 l. 74 1.250 . 1.235 . 1.249 . 1.253 . 1.252 . l.235 . 1.252 . I.275 . 1.267 . 1.145 . 0.790 .
. 4.290 . 3.146 . 4.210 . 1.263 . 1.227 . 1.217 . 1.231 . 1.235 . 1.232 . 1.228 . 1.243 . 4.254 . 1.254 . 1.146 . 0.289 . 7
. 0.0 . 4.1 . 0.3 . -0.9 . -1.8 . -1.5 . -1.5 . -1.5 . -1.6 . -0.6 . -0.7 . -1.7 . -1.0 . 0.0 . -0.4 0.349 . 0.950 . 1.209 1.262 . 1.257 . l.228 . 1.249 . 1.065 . 1.259 . 1.233 . 1.259 . 1.163 . l.290 . 0.951 . 0.569
, 0.367 0.9 54 . 1.249 . 1.254 . 1.221 . I.709 . 3.232 . 1.052 . 1.246 1.223 . 1.252 . 1.253 . 1.276 . 0.942 . 0.362 . 8
. -0.6 . 0.4 . -0.1 . 0.9 . -2.9 . -1.6 . -1.4 . -1.2 . -1.0 -0.7 . -0.6 . -0.0 . 1.4 . -1.0 . -1.9 .
. 9.290 . l.144 . 1.766 . l.274 . 1. 250 . l . 232 . 1. 24 7 . 1. 253 . I . 254 . 1. 238 . 1. 252 . l . 275 . 1. 267 . 1.145 . 8. t90
. 9.290 . 1.147 1.268 , 1.276 . 1.256 . l.225 . 1.232 . 1.241 . 1.247 1.223 . 1.250 . 1.279 . l.26F . 1.141 . 0.271 . 9
. 0.0 . 0.2 . 4.2 0.1 . 0.5 . +0.6 . 1.3 . -I.0 . -0.6 -1,3 . -0.2 . 0.3 . 0.0 . -0.4 . -6.7 .
. 0.663 . 1.197 . 1.280 . 1.t64 . 1.197 . 1.234 . 1.229 1.254 . l.199 . 1.266 . 1.208 . 1.194 . 0.663 .
. 0.665 . 1.202 . 1.t91 . 1.274 . 1.194 . 1.209 1.214 . 1.230 1.198 . 1.276 . 1.104 . 1.214 . 0.679 . 10 0.3 . 0.5 . 4.4 . 1.2 . 3.1 . -r.) . -0.9 . -0.4 0.1 . 0.9 2.1 . 1.4 . 2.4 .
I . 9. 2 76 . 0. 796 . 1. 219 . 1. t9 3 . 1. 763 . 1. 250 . ! . 25 7 . 1. 251 . 1. 264 1.t94
. 4.210 . 0.802 . 1.240 . 1.33 5 . 1.277 .1.250 . 1.258 .1.2h2 . l .r64 . 1.314 . 1.243 . 0.804 . 0.282 .
. 0.6 . 0.0 . 1.7 . 3.2 .
1.1 . 0.0 . 0.0 . 8.1 . 4.1 . 1.6 . 1.220 . 0.796 . 0.276 . 1.9 . 1.5 . 1.9 11
. 0.317 . 0.670 . 1.214 . 1.2 79 . 1.774 l.762 . 1.274 . 1.280 . 1.219 . 0.671 . 0.357 .
0.314 0. 680 . 4. 24 2 . 1. t96 . 1. 266 . 4. 2 71 . 1. 283 . 1. 249 . 1. 236 , 0.648 . 0.310 . 12
-1.0 . 1.5 . 1.9 . 1.3 . 0.9 . 0.7 . 0.7 . 0.7 . 1.4 . 2.6 . 0.2 .
1
. 0.317 . 0.797 . 1.197 . 1.267 . l.290 . 1.267 . 1.194 . 0.797 . 0.317 .
. 8.321 . 0.408 . 1.240 . 1.280 1.306 . 1.285 . I.206 . 0.406 . 0.323 . 13
. 1.4 . 4.4 . 1.1 . 1.0 . 1.2 . 1.4 0.7 . 1.1 . 1.8 .
I .. .. .......... ........................................................
. 0.277 . 0.664 . 1.147 . 0.952 . 1.147 . 0.664 . 4.277 .
. 0.271 . 0.670 . 1.157 . 0.969 . 1.183 . 0.676 . 4.281 .
. 0.0 . 0.9 . 0.9 . 1.8 . 3.2 . 1.0 . 1.4 .
14 STANDARD . 8. t95 . 0. 370 . 9.195 . . AVERAGE . I
. DE VI AllDN . . 9.2&& . 0.374 . 4.303 . .PCI OlfFEptMCE. 15
. =0.845 . . -2.4 . 1.1 . 2.7 . .
- 1.0 .
St#W4ARY I MAP NO: $2-13-02 DATER 3/23/95 POWER: 69.38% CONTROL RCD POSITIONSI F-Q(Z) = 1.997 QPTR: D BANK AT 177 STEPS F-DHIN) = 1.435 NW 0.9921 NE 0.9986 F(Z) = 1.276 SW 1.0054 l SE 1.0059 BURNUP a 20 HWO/MTU A.O. s -4.6057 I NE-1023 S2C13 Startup Physics Tests Report Page 37 of 56
p: J; y ta l Figure 6.3 I SURRY UNIT 2 - CYCLE 13 STARTUP PilYSICS TESTS I 1 ASSEMBLYWISE POWER DISTRIBUTION i 97% POWER R P N M L 0 J H G F E D C 8 A l
. PREDICi[0 . . 4.389 . 0.394 . 0.309 . . Mit DICIED .
. MEAsuRfD . . 0.310 . 0.397 . 4.383 . . MF&SUNE.0 . 1
. PCT Of f f E RE NCE . . 0.4 . 0.8 . 1.4 . JCT DIFFERENCE.
. ............ . ......................................................... ................ 1
. 9. 280 . 0.MF . 1.159 . l .021 . 1.159 . 0.MF . 0. 280 . l l
. 4.279 . 0. M 6 . 1.161 . I.028 . 1.177 . 0.698 . 9.2A8 . 2
. -0.6 . -0. 2 . 0.2 . 0.7 . 1.6 . 3.7 . 2.6 . I
......................................................................... i
. 0.318 . 0.790 . l.877 . l.2 % . 1.784 . 1.2 % . 1.177 . 0.790 . 0.314 . 1
. 0.357 . 0.742 . 1.171 . 1.2 % . 1.293 . 1.270 . 1.198 . 0.803 . 0.326 . 3 i
. - 0. 3 . 1.0 . - 0. 5 . 0.0 . 0.5 . 3.1 . 1.8 . 1.7 . 2.3 . l
........................................................................................ l
. 0.318 . 0.M5 . 1.194 . 1.257 . l.7% . l.746 l .7% . 1. 258 . 1.194 . 0.M5 . 4.118 .
. 0.315 . 0.657 . 1. l FF . I.248 . 3.252 . l .752 . 1.FM . 1.274 . 1.209 0.Ma . 0.314 . 4 :
. -1.0 . -l.2 . -1.8 . -0. 7 . -0.2 . 0.5 . 1.0 . 1.6 . 1.3 . 0.5 . -0.2 .
4.280 . 0.709 . l.195 . 1.276 . l.263 . l.245 . l.244 1.246 . 1.263 . 1.277 . 3.195 . 0.709 . 4.240 1
. 0.217 . 0. 701 . 1.186 . l .275 . 1.F% . 1.240 . 1.244 1.253 . 1.277 . l.294 . 1.187 . 0.703 . 0.272 . 5
. -1.0 . -0.9 . -0.4 . -0.8 -0.5 . -0.4 . 0.0 . 0.6 . 1.1 . 1.1 . -0.6 . -0.4 . -2. 7 . l
................ ........................................................................................ j
. 0 . M6 1.176 1.258 . l.264 . 1.273 . 1.245 . l.230 1.247 . 1.274 I.764 . 1.758 1.177 . 0.M6 i
. 0.659 1.163 . 1.243 . 1.2 % . l .760 . 3.236 .1.219 . I.212 . 1.290 . 1.269 . l .254 . 1.169 . 0.M4 . 6 '
. -1.0 . -1.8 . -1.2 . -1,6 -1.0 . -0.T . -0.9 . 0.4 1.2 . 0.4 . -0.6 . -0.6 . -0.3 .
. 0.304 . l.157 . 1.255 . 1.254 . 1.246 . l.747 . 4.260 . l.261 . 1.262 , 1.247 . 1.746 . 1.254 . 1.255 . 1.157 . 0.304 1 0.301 1.146 I.741 . 1.236 . 1.223 1.232 . I.253 . 1.257 . 1.268 . 1.254 1.244 1.235 . 1.244 1.1% . 0.304 7
-0.9 . -1.0 . -1.0 . -1.4 . -1.4 . - 1. 2 . -0.5 . -0.4 . 0.5 . 0.6 . -0.1 . -1.5 . -0.4 . 0.6 . 0.0 .
. 0.393 . 1.020 . 1. 28 7 . 1. 2% . l . 7% . 1.230 l .247 . 1.082 . 1.fM . 1.233 . l.245 . 1.247 . 1.288 . 1.020 . 0.393 .
. 4.398 . 1.011 . 1.214 . 1.227 . 1.7 % . 1.211 . 1.245 . 1.0FF . 1.268 . 1.240 . 1.2% . 1.239 1.268 . l.605 . 0.386 . 8
. = 0. 6 . -0.0 . -1.0 . -1.5 . -3.1 . -l.6 . -1.0 . *0.5 . 9.1 . 0.6 . 0.0 -0.7 . -l.6 . -1.4 . 1.8 . i
. 0.304 . 1.157 . 1.255 . 1. 253 . 1. F45 . 1.244 . 1.254 . 1.261 . 1.264 1.249 1.247 . 1.2 % . 1.2 % . 3.157 . 0.304 .
0.302 1.149 1.247 . 1.245 . 1.239 . 1.232 . 1.241 . 4.?S2 . 1.260 1.234 . 1.tSO . 1.760 1. F% . 1.154 . 0.288 . 9
. -0.6 . -0.6 . -0.0 . -0.6 . -0.4 . 1.0 . -4.3 . -0.7 . 0.2 . -0.9 . 9.2 . 0.5 . 0.0 . 0.3 . -S.I .
. 0.M6 1.176 1.254 . l.263 . 1.272 . 1.246 . 1.230 . I.2 % . 1.274 1.265 . 1.F59 1.177 . 0. M 6 .
. 0.M3 1.173 1.261 . 1.269 1.264 . 1.215 . 1.219 . 1. 741 . 1. 272 . 1. 282 . 1. taa . 1.19 7 . 0.6% . Id
-0.4 . -0.2 . 0.2 . 0.5 . *0.6 . -2.5 . -0.9 . -0.4 -0.2 . 1.4 2.3 . 1.F . 3.0 .
. 0.700 . 0.789 . 1.195 . l.276 . l.262 . 1.f45 . 1.244 1.245 . 1.263 . 1.277 . 1.195 . 0.789 . 0.280 .
. 0.?00 . 0. F91 . l .209 .1.381 . 1.264 .1.237 . 1.245 . 1.242 1.253 .1.316 .1.227 . 4.407 . 0.74F . 11
. 0.0 . 0.4 . 1.2 . 2.7 . 0.5 . -0.6 . 8.1 . -0.2 . -0.6 . 3.1 . F.F . 2.2 . 2.6 .
. 0.318 . 0.M5 . 1.194 . 1.257 . 1.2% . 1.2% . 1.2% . 1. 258 . 1.194 . 0.M5 . 0.318 .
. 0. 317 . 0. 672 . 1. 210 . 1. F62 . 1. 24 7 . l . 2% . 1. F% . 1. 263 . 1. 217 . 0. 688 . 0. 325 . 12
. -0.4 . 1.4 . 1.3 . 0.4 -0.6 . 0.0 . 0.2 . 0.4 . l.9 . 3.4 . 2.0 .
. 0.310 . 0.790 . 1.177 . 1.7 % . 1.288 . 1.2 % . 3.177 . 0.790 . 0.314 .
. 0.321 . 0.F96 1.180 .1.2% .1.F92 . l.263 .1.180 . 0.800 . 0.375 . 13
. 0.9 . 0.4 . 4.3 . 0.0 . 0.5 . 0.6 . 0.3 . 1.2 . 2.2 .
. 0.280 . 0.MF . 1.159 . 1.02) . 1.159 . 0.667 . 0.280 .
. 4. 282 . 0.M4 . 1.154 . 1.027 . 1.179 . 0.674 . 9. 284 . 14
. 0.6 . 4.2 . -0.1 . 0.6 . 1.8 . 1.0 . 1.1 .
$fANDARD . . 0.309 . 0.394 . 0.309 . . AVidACC .
. IEVIAllON . . 9.299 . 8.394 . 6.313 . .PCI DIFFEREMCE. 15
. 0.054 . . -3.0 . 0.1 . l.3 . . = 1.0 .
SUMMARY
MAP N05 $2-13-03 OATE: 3/28/95 POWERI 97.38% CONTROL R00 POSITIONSI F-Q(Z) s 1.841 QPTRE D BANK AT 225 STEPS F DHIN) = 1.411 MW 0.9919 NE 1.0041 F(Z) a 1.196 E v.9915 l SE 1.0064 BURNUP = 186 HWO/MTU A.O.= *1.299% NE-1023 S2C13 Startup Physics Tests Report Page 38 of 56 a aims
SECTION 7 r-( REFERENCES
- 1. R. F. Villaflor, "Surry Unit 2, Cycle 13 Design Report",
(' Technical Report NE-1012, Revision 0, March, 1995.
- 2. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Determination
[ By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
- 3. Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C.
( "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of Startup Physics Test Program - Inspector Followup Item 280, 281/88-29-01", Serial No. 89-541, December 8, 1989.
- 4. T. W. Schleicher, " Reactor Power Distribution Analysis Using a Moveable In-Core Detector System and the TIP/CECOR Computer Code Package", VEP-NAF-2, November, 1991.
- 5. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, 4.10.A and 5.3.A.6 b.
- 6. " Core Operating Limits Report Surry 2 Cycle 13 Pattern UG, Revision 0", February, 1995.
[ 4 ( [
- NE-1023 S2C13 Startup Physics Tests Report Page 39 of 56
_ . . . - - _. .. _ . . . _ _ = _ . . ._ S
~;
1 l I I APPENDIX STARTUP Pl!YSICS TEST RESULTS. , AND EVALUATION S!!EETS l l I: I 1 I I l ~ l i I , I I I I I
"~
NE-1023 S2C13 Startup Physics Tests Report Page 40 of 56
r L r f SURRYPOWERSTATION UNIT 2 CYCLE 13
- s. . . .
STARTUP PHYSICS .. . TEST RESULTS AND EVALUATION SHEET I Test Desedption: Zero Power Tesdng Range De- E=^!on ( Reference ProcNo/Section: 2-NPT-RX-008 ' Sequence Step No: 1
)
II BankPositions(Steps) RCS Tampa-('F): 547 Test ( Conditions PowerLevel(% F.P.): O (Design) SDA: 227 SDB: 227 CA:227 Other(M)* p CB: 227 CC:
- CD:
- BelowNuclearHeating i
III Bank Positions (Steps) RCS Temperature (SF): 5v(,,(, Test Power Level (% F.P.): O Conditions Other(spe@): SDA: 227 SDB: 227 CA:227 (Actual) CB: 227 CC: 2.27 CD: / 52 BelowNuclear Heating . Date/ Time Test Performed: S/2.hs ooro9 4 Reactivity Computer Initial Flux - ( IV Background Reading /, 3 I ( ) 0 ,,, ,9 L Test Results Flux Reading At ( Point ofNuclear Heating 2.h /o 7amps Zero Power ' a , g. Testing Range I(10 to 10X/0 amps Reference Not Applicable V FSAR/ Tech Spec NotApplicable Acceptance Criteda Reference Not Applicable Design Tolerance is met ** : / YES NO Acceptance Criteriais met ** : V YES NO - ( VI Comments
- At'Ihe Just Critical Position
*
- Design Tolerance and Acceptance Criteria are met ifZPTR
( is below the Point ofNuclear Heating and above backgmund. [ Prepttred By: /#A O-Reviewed By: M OMN J' NE-1023 S2C13 Startup Physics Tests Report Page 41 of 56
E
=
I SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l l I Test
Description:
Reactivity Computer Checkout Reference ProcNo / Section: 2-NPT-RX-008 Sequence Step No: II BankPositions (Steps) RCS Temperature (0F): 547 Test Power Level (% F.P.): O Conditions CA:227 Other(specify): SDA: 227 SDB: 227 (Design) BelowNuclearHeating CB: 227 CC:
- CD: *.
III Test BankPositions (Steps) RCS Temperate (CF): PowerLevel(% F.P.): O
.rys.ol l
Conditions Other(specify): E SDA: 227 SDB: 227 CA:227 (Actual) CB: 227 CC: 2.17 CD: 64, BelowNuclear Heating 5 Date/Iune Test Performed: g 3/zo/ss, 0 0:57 Measured Parameter p,= Measured Reactivity using p-computer g (Description) p, = Predicted Reactivity 3i IV ! Test B Results P." + Jo 50 ~ 42 0 Eli Measured Value p = , sv. t o - 4Z. c 6 l
%D = - o , c, - /, 5 2.
Design Value %D = {(p,- pi)/ p,} x 100% s 4.0% Reference WCAP 7905, Rev.1, Table 3.6 l l V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable . l Design Tolerance is met Acceptance Criteriais met :
- / YES
/ YES NO NO
, l VI Comments
- At The Just Critical Position -
The allowable range will be set based on the above results, as well as the results from the benchmark test. Allowable Range = + .co . , - 42 Preppred By: MV G1 Reviewed By:
. v h*
1 NE-1023 S2C13 Startup Physics Tests Report Page 42 of 56
h, SURRY POWER STATION UNIT 2 CYCLE 13 l STAR'IUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - ARO Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: g II BankPositions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): (Design) CB: 227 CC: 227 CD: 227 BelowNuclear Heating j III Bank Positions (Steps) RCS Temperature (OF): sw. 3 j Test Power Level (% F.P.): 0
'g Conditions SDA: 227 SDB: 227 CA:227 Other(specify):
E (Actual) CB: 227 CC: 227 CD:227 BelowNuclear Heating Date/I~nne Test Perfonned: 3/2e[95 03: 20 I IV Measured Parameter (Description) (C3)"no ; Critical Boron Concentration- ARO Test 'I Results Measured Value (Design Conditions) /(,7i (C)3 Mao = I Design Value (Design Conditions) C3= 1703
- 50 ppm Reference Technical ReportNE-1012, Rev. 0 V FSAR/ Tech Spec cC3x C D 3 s 1000 pcm ,
Acceptance j Criteria Reference Technical Specification 4.10.A Design Tolerance is met : / YES NO l VI Acceptance Criteriais met : / YES NO Comments eC3= -7.27 pcm/ ppm l C3D =l(C )3 Mao - C 3l: C 3is design value
-l Prepa. red By:'
Reviewed By: /M. . M.g//m - ( - I NE-1023 S2C13 Startup Physics Tests Report Page 43 of 56
E-( SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l.
. I TestI>escription:IsothennalTemperature CoefEcient- ARO Reference Proc No / Section: 2-NPT.RX-008 .
Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test PowerLevel(% F.P.): O Conditions (Design) SDA: 227 CB: 227 SDB: 227 CC: 227 CA: 227 CD: 227 Other(specify): BelowNuclear Heating l III Test Bank Positions (Steps) RCS Temperature (0F):59:t.8 -ent Power Level (% F.P.): O l Conditions Other(specify): SDA: 227 SDB: 227 CA:22 BelowNuclear Heating g (Actual) CB: 227 CC: 227 CD: $]2 b[o ,,, Date/Iune Test Performed: g 3/,o /*15 oE 58 5 Measured Parameter IV (Description) (ar" )ao ; Isothermal Temperature Coeff- ARO Test Results Measured Value (ar ** )ao " -3 H PcmFF (Cn "l/'80 Ppm) Design Value (Actual Conditions) (er " )ao = -4,(p5 pcmFF (C =1680 3 ppm) Design Value (Design Conditions) (ar** )ao = -4.43
- 3.0 pcmFF l.
(Cs = 1703 ppm) Reference Technical ReportNE-1012, Rev. 0 , V FSAR/COLR ar tS s 0.79* pcmFF ar P = -1.71 pcmFF g Acceptance Criteria Reference COLR 2.1.1, Technical Report NE-1012, Rev. O DesignTolerance is met : v' YES NO , Acceptance Criteriais met : / YES NO VI E Comments
- Uncertainty on eTuoo = 0.5 pcmFF (
Reference:
memorandum from a C. T. Snow to E. J. Lozito dated June 27,1980). A Preppred By: O h] Reviewed By: e_ NE-1023 S2C13 Startup Physics Tests Report Page 44 of 56
E [ SURRYPOWEk STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RES,ULTS AND EVALUATION SHEET r I Test
Description:
Control Bank B Worth Measurement, Rod Swap Ref. Bank L Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 [ Test Conditions Power Level (% F.P.): O SDA: 227 SDB: 227 CA: 227 Other(specify): (Design) CB: moving CC: 227 BelowNuclear Heating [ CD: 227 III Bank Positions (Steps) RCS Temperature ( F): 5%,7 p Test PowerLevel(% F.P.): O L Conditions SDA: 227 SDB: 227 CA: 227 Other(sppeify): (Actual) CB: moving CC: 227 CD: 227 BelowNuclear Heating Date/ Time Test Performed: 3 /~zol'15 0142. Measured Parameter (Description) I,5 ; Integral Worth of Control Bank B, IV All Other Rods Out Test Results Measurer'.Value I," = I M Design Value (Desiga Conditions) I,5 = 1336
- 134 pcm Reference Technical Report NE-1012, Rev. O V FSAR/reen Spec If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis.
Criteria SNSOC may specify that additional testing be . performed. Reference VEP-FRD-36A Design Tolerance is met : V YES NO VI Acceptance Criteriais met : v YES NO [ Comments Prepped By:MMb Reviewed By: _ 2 E
~
NE-1023 S2C13 Startup Physics Tests Report Page 45 of 56
O m I ( - SURRYPOWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l I Test
Description:
Critical Baron Concentration - B Bank In Reference ProcNo / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Tempe:ature (CF): 547 Test Power Level (% F.P.): O Conditions SDA: 227 Other(specW)* SDB: 227 CA: 227 l (Design) CB: BelowNuclearHeating 0 CC: 227 CD: 227 l III BankPositions (Steps) RCS Temperature ( F): 54<,3 Test Power Level (% F.P.): 0 Conditions SDA: 227 Other(specW): SDB: 227 CA: 227 3, (Actual) CB: O CC: 227 CD: 227 BelowNuclear Heating 5 Date/I"une Test Performed: sluh5 own ! Measured Parameter (Description) g (Cs)"a ; Critical Boron Concentration, B Bank In E IV - l Test I Results Measured Value (Design Conditions) (C3 )"3 = 14 % l Design Value . (Design Conditions) ' C3 = 1521 + AC 3P" * (10 + 133.6/leCaD Ppm E C3 = I4M ppm : 28 5 Reference Technical Report NE-1012, Rev. O V FSAR/ Tech Spec Not Applicable Acceptance , Criteria Reference Design Tolerance is met : Not Applicable J YES NO
, l VI Acceptance Criteriais met :
aCa = -7.34 pcm/ ppm v YES NO l' Comments ACa" = (Cs)%o - 1703 ppm l Prepared By: MM Reviewed By: ei,
-Y B.
NE-1023 S2C13 Startup Physics Tests Report Page 46 of 56
L i r L r L jt SURRY POWER STATION UNIT 2 CYCLE 13 L STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET F I Test
Description:
HZP Boron Worth CoefHelent Measurement Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: p II BankPositions (Steps) RCS Temperature (CF): 547 L Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): [ (Design) CB: moving CC: 227 CD: 227 BelowNuclearHeating l III Bank Positions (Steps) RCS Temperature ( F): sw, p Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): (Actual) CB: moving CC: 227 CD: 227 BelowNuclear Heating Daterrime Test Performed: 5/zo/4r o > v 2. Measured Parameter l (Description) aC ; Boron Worth Coefficient IV Test Results Measured Value aC, = - 7,4r7 pom/g+ Design Value (Design Conditions) aC3= -7.34
- 0.73 pcm/ ppm Reference Technical Report NE-1012, Rev. 0 V FSAR/ Tech Spec Not Applicab!c .
Acceptance Criteria Reference Not Applicable Design Tolerance is met : /XES NO Acceptance Criteriais met : / YES NO VI { Comments Prepgred By: 5/f/9f , Reviewed By. h 4"#- W% C . 1 ---_-2'"2' """ " "'
O o ( SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I' Test
Description:
Control Bank D Worth Measurement, Rod Swap , Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): g (Design) CB: moving CC: 227 CD: moving BelowNuclear Heating III Bank Positions (Steps) RCS Temperature (OF):(% 3 Test Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): E (Actual) CB: moving CC: 227 CD: moving BelowNuclear Heating 3 Date/ rime Test Performed: 3 3/30/4r /.G 7 E Measured Parameter Iou ; Integral Worth of Control Bank D, (Description) Rod Swap IV Test Measured Value Iou = //87 (Adjusted Measured Critical Results Reference Bank Position = l'16 steps) Design Value Iou = 1203,41/B0 (Adjusted Measured Critical (Actual Conditions) Reference Bank Position = 176 steps) Design Value Iou = 1195
- 179 pcm (Design Conditions)
Reference . (Critical Reference Bank Position = 194 steps) Technical Report NE-1012, Rev. O, VEP-FRD-36A l V FSAP/rech Spec If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis. ' Criteria SNSOC may specify that additional testing be performed. Reference VEP-FRD-36A Design Tolerance is met : /YES NO VI Acceptance Criteriais met : g YES NO g Comments E Preppred By: ' 8 V h Reviewed By: 2% A h -VV sisi NE-1023 S2C13 Startup Physics Tests Report Page 48 of 56
L r I ( SURRY POWER STATION UNIT 2 CYCLE 13 c STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET L . . . . . . . . . .. . . . . . . . . .. . . . . .. . . . . . . . ... I Test
Description:
Control Bank C Worth Measurement, Rod Swap [ Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (OF): 547 F Test ' Power Level (% F.P.): 0 Conditions Other(specify): SDA: 227 SDB: 227 CA: 227 - (Design) CB: moving CC: moving CD:227 BelowNuclear Heating b III Bank Positions (Steps) RCS Temperature ( F): fn Test Power Level (% F.P.): O Conditions Other(specify): SDA: 227 SDB: 227 CA: 227 (Actual) CB: moving CC: moving CD:227 Below Nuclear Heating Date/I"une Test Performed: 3/u/fr 1726 Measured Parameter Ic"; Integral Wodh of Control Bank C, (Description) Rod Swap IV Test Measured Value Icu= 76 7 (Adjusted Measured Critical Results Reference BaMosMon = W steps) [ Design Value Ic" = 90Mr120 (Adjusted Measured Critical (Actual Conditions) Reference Bank Position = //G steps) l Design Value Ieu = 791
- 119 pcm (Design Conditions) (Critical Reference Bank Position = 131 steps)
Reference Technical Report NE-1012, Rev. O, VEP.FRD-36A l l V Acceptance FSAR/rech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.
- Criteria SNSOC may specify that additional testing be performed. '
Reference VEP-FRD-36A Design Tolerance is met : / YES NO ' VI Acceptance Criteria is met : ,_ V YES NO Comments o /") n n Prepared By: f Reviewed By:7% (.Me.#L Fz#ps-l NE-1023 S2C13 Startup Physics Tests Report Page 49 of 56
O, O; 5 ( SURRY POWER STATION UNIT 2 CYCLE 13 , I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
.l I Test
Description:
Control Bank A Worth Measurement, Rod Swap Reference Proc No / Section: 2.NPT-RX-008 Sequence Step No:_ g II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 227 SDB: 227 CA: moving Other (specify): < (Design) CB: moving CC: 227 CD: 227 BelowNuclear Heating III Test Bank Positions (Steps) RCS Temperature ( F): 6t/j,g I' ' Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA: moving Other (specify): (Actual) CB: moving CC: 227 CD: 227 BelowNuclear Heating Date/ rime Test Performed: 3/20/9f /6 2f 1 Measured Parameter (Description) IxM ; Integral Worth of Control Bank A, Rod Swap l l IV l Test Measured Value IxM = ~3 '33 (Adjusted Measured Critical Results Reference Bank Position = 7/ ste.ps) Design Value Ixu = W/ S f/p (Adjusted Measured Critical Reference Bank Position = 7/ steps) g (Actual Conditions) Design Value Iru = 350
- 100 pcm (Design Conditions) (Critical Reference Bank Position = 80 steps)
Reference Technical Report NE-1012, Rev. O, VEP-FRD-36A V FSAR/rech Spec If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis, g Criteria SNSOC may specify that additional testing be g performed. ' Reference VEP-FRD-36A Design Tolerance is met : , [ YES NO ' VI Comments Acceptance Criteria is met : / YES NO l A A nA Prepared By:
/ Vi W ~l/lfff Reviewed By: Wal MFT>/6 g
p NE-1023 S2C13 Startup Physics Tests Report Page 50 of 56
'( SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Desc'ription: Shutdown Bank B Worth Measurement, Rod Swap Reference Proc No / Section: 2-NPT-RX.008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (O ):F 547 Test Power Level (% F.P.): O Conditions SDA: 227 Other(specify): SDB: moving CA: 227 (Design) BelowNuclear Heating CB: moving CC: 227 CD: 227 III Bank Positions (Steps) RCS Temperature (0F): TW,,9 Test Power Level (% F.P.): O Conditions Other(specify): SDA: 227 SDB: moving CA: 227 (Actual) CB: moving CC: 227 CD:227 BelowNuclear Heating Date/ Tin;e Te,st Performed: 3/za/W /7/2 Measured Parameter Iss" ; Integral Worth of Shutdown Bank B, (Description) Rod Swap IV Test Measured Value Isa" = l/33 (Adjusted Measured Critical Results Reference Bank Position = IM steps) Design Value Issu = INMtDZ(Adjusted Measured Critical ) (Actual Conditions) Reference Bank Position = llA steps) Design Value Issu = 1146
- 172 pem (Design Conditions) (Critical Reference Bank Position = 186 steps) l Reference Technical Report NE-1012, Rev. O, VEP-FRD-36A V FSAR/rech Spec -
If Design Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis.
- Criteria SNSOC may specify that additional testing be performed. '
Reference VEP- -36A , Design Tolerance is met : [YES NO
- l ~VI Acceptance Criteriais met : / YES NO Comments
,n a - 6 Prepped By:
g v-4 y i D f Reviewed 2 By &.2 bA 7/r J// NE-1023 S2C13 Startup Physics Tests Report Page 51 of 56
5 ( SURRY POWER STATION UNIT 2 CYCLE 13 g STAR'IUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Shutdown Bank A Worth Measurement, Rod Swap Reference ProcNo / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA: moving SDB: 227 CA: 227 Other(specih): g (Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating m III Bank Positions (Steps) RCS Temperature ( F): 646,4 Test
- Power Level (% F.P.): 0 Conditions CA: 227 Other(speci&):
SDA: moving SDB: 227 (Actual) CB. noving CC: 227 CD: 227 BelowNuclear Heating l, Datfe/ u/u Time Testmr Performed: l Measured Parameter 154" ; Integral Worth of Shutdown Bank A, IV (Description) Rod Swap l Measured Value 134" = /O O T (Adjusted Measured Critical Test Results Design Value Reference Bank Position =H,I steps) IsxM = 1//4M 167(Adjusted Measured Critical l (Actual Conditions) Reference Bank Positica = 14 mps) Design Value Isx" = 1103
- 165 pcm (Design Conditions) (Critical Reference Bank Position = 179 steps)
Reference Technical Report NE-1012, Rev. O, VEP FRD-36A V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall l1 Acceptance evaluate impact of test result on safety analysis. l Criteria SNSOC may specify that additional testing be l performed. Reference VEP-FRD-36A
- //YES Design Tolerance is met NO VI Acceptance Criteriais met : / YES NO Comments
.- /1 Af1 l 1 Prepped By:
r
k Reviewed By ah J 3/ .
y i I NE-1023 S2C13 Startup Physics Tests Report Page 52 of 56
( SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ' I Test
Description:
Total Rod Worth, Rod Swap Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No: II Bank Positions (Steps) RCS Temperature (CF): 547 Test l Conditions (Design) SDA: moving SDB: moving CA: moving CB: moving CC: moving CD: moving Power Level (% F.P.): 0 Other(specify): BelowNuclear Heating l III Test Bank Positions (Steps) RCS Temperature ( F): 594,7 Power Level (% F.P.): 0 I Conditions (Actual) SDA: moving SDB: moving CA: moving CB: moving CC: moving CD: moving Other(specify): BelowNuclear Heating .g Date/ rime Test Performed: m 3/2o/g 07 v 2 I IV Measured Parameter (Description) 1,w; 7 Integral Worth of All Banks, Rod Swap I Test Results Measured Value Ir w " T 9 0 6 Design Value Ir.w " IT O'II I N l - (Actual Conditions) Design Value Ir.w = 5920
- 592 pcm l (Design Conditions) -
Reference Technical Report NE-1012, Rev. O, VEP-F 36A V FSAR/ Tech Spec IfDesign Tolerance is exceeded, SNSOC shall Acceptance evaluate impact of test result on safety analysis. - g Criteria Additional testing must be performed. Reference VEP-FRD-36A Design Tolerance is met : / EYES NO " 'E VI ^CCeptance Criteria is met : s Comments V YES _ _ NO
- A -
Prepared By: Iv[& Reviewed By. d.d$.e44,.'y%g NE-1023 S2C13 Startup Physics Tests Report Page 53 of 56
E' 5' ATt'ACHmEtJT ~7 1 SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l-l I Test
Description:
M/D Flto: Map - At Power l-Reference Pnc No / Section: 2-NPT-PX-008,002 Sequence Step No: II Test Conditions Bank Positions (Steps) SDA: 227
. RCS Temperature (CF): Tu* I Power Level ("A F.P.): s30 Other(specify):
l SDB: 227 CA: 227 , (Design) CB: 227 CC:
- CD:
- Must have a 38 thimbles ** g III Bank Positions (Steps)
Test RCS Temperature ( F): T n g. g Conditions Power Level (*4 F.P.): 2 9. G g SDA: 227 SDB: 227 CA: 227 Other(specify): (Actual) CB: 227 CC: 227 CD: 1 s .3 ' g DaterI"une Test Performed: 44 Wm ble s '
'S/2.i/4s o B 2.5 '
Max. Relative Nuclear Enthalpy Rise TotalHeat Flux Maximum ll Measured Assembly Hot Channel Hot Positive B Parameter Power Factor yy (Description) % DIFF FAH(N) Channel Factor Incore g F(Z) n Quadrant (M P)/P Power Tilt
?
Results Mea.sured value 1A9L L3i4 1, q g Design Value
- 10% for P a0.9 N/A i
N/A s1.0204 (Design Conds)
- 15% for P.<0.9 g,- assy pwr)
Reference WCAP- 7905 None None WCAP.7905 Rev.1 Rev.I V FSAR/COLR None Fo(Z)s4.64*pZ) FAH(N) 1.56(1+0.3(1 P)) None Acceptance , Criteria Reference Noue COLR 2.4 l COLR2.3 None Design Toleranceis met : M XES No li ' g Acceptance Criteriais met : DYES NO Comments
- As required . .
l
*
- Must have at least 16 thimbles for quarter core maps for multi-point calibrations g)
. 5 Prepped By: DJf1 /2 6t[%
Reviewed By: d>Not_ O j E. NE-1023 S2C13 Startup Physics Tests Report Page 54 of 56 i
e L e L F. SURRY POWER STATION UNIT 2 CYCLE 13 . STAR'IUP PHYSICS TEST RESULTS AND EVALUATION SHEET r L I Test
Description:
M/D Flux Map - At Power Reference Proc No / Section: 2-NPT-RX-008,002 Sequence StepNo: [ II Test Bank Positions (Steps) M n" RCS Temperature (9F): Trs* 1 Power Level (% F.P.): 65sPs75 Conditions SDA: 227 SDB: 227 CA: 2h7 Other(specW): (Design) CB: 227 CC: 227 CD:
- Must have a 38 thimbles" r III Bank Positions (Steps RCS Temperature (CF): Atwhc L Test t 81 7 PowerLevel(% F.P.): ci.ssh Conditions CA: 227 Other(specW):
. SDA: 227 SDB: 227
[ (Actual) CB:227 CC: 227 CD: nl .
'N Utab\es-K I
Date/ rime Test Performed: [ b/24/T O I Z-2., Max.Reladve Nuclear Enthalpy Rise TotalHeat Flux Maximum Measured Assembly Hot Channel Hot Posidve Parameter Power Factor ChannelFactor Incore (Description) % DIFF, FAH(N) Fo(Z) Quadrant gy (M PyP PowerTilt Test Results Meamed value 3 2.foPt.4
- c. n /ca.i (d M lR91 g,eesq
- m; ]y,y.
h Design Value (Design Conds)
*10% fw F=0S i
- 15% rw F,<os N/A N/A s1.0204 (F - assy pwr)
Reference WCAP- 7905 None None WCAP-7905 Rev.1 Rev.1 [ V Acceptance FSAR/COLR None F AH(N)x1.56(1+0.3(1 F)) FgZis2.32/F
- K(z) None Criteria Reference None COLR 2.4 COLR2.3 None b '
Design Toleranceis met : NO Acceptance Criteriais met : NO { Comments
- As required
" 1pust havf at least 16 thimbles for quarter core maps
[ fd zgultfpoint calibrations c 3 m , Prepped By: {W // //d Reviewed [ .g w -- - ~ NE-1023 S2013 Startup Physics Tests Report Page 55 of 56 )
. ,,.. J
E em SURRY POWER STATION UNIT 2 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l I Test
Description:
M/D Flux Map - At Power l Reference Proc No / Section: 2-NPT-RX-008,002 Sequence Step No: 1 l II Bank Positions (Steps) RCS Temperature (OF):Tn r* 1 Test Power Level (% F.P.): 95sPs100 Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): g (Design) CB:227 CC: 227 CD:
- Must have a 38 thimbles" III Bank Positions (Steps) RCS Temperature (OF): NMNw Test Power Level (% F.P.): 97,32),
Conditions SDA: 227 SDB: 227 CA: 227 Other(specify): (Actua0 CB: 227 CC: 227 CD:Z2 f_ DateHime Test Performed:
. h?)9i~ /46n Max. Relative Neelear Enthalpy Rise TotalHeat Flux Maximum Measured Assembly Hot Channel Hot Positive Parameter Power Factor ChannelFactor Incore IV @c5dPtion) */. M RHM Fo@ Qua h t i (M P)/P Power Tilt E' Test g Results Measured value -3.1fo /207 /
- D'/
-gis r <o.9 /. W/ / 8Y/ O.6Y&
Design Value
- 10% for P. =0.9 N/A N/A s1.0204 (Design Conds)
- 15% for P.<0.9 (P. = assy pwT) ,
Reference WCAP- 7905 None None WCAP-7905 " Rev.I Rev.I V FSAR/COLR None F AH(N)st.56(1+03(1 P)) Fe(Z)s232/P
- K(Z) None l Acceptance Criteria Reference None COLR 2.4 COLR 2.3 None
//
Design Tolerance is met :
/IS NO q Acceptance Criteriais met : /YES NO Comments
- As required l
"M have p least 16 thimbles for quarter core maps f fnulti- pintcalibrations _
Prepared By: v -///7d k Reviewed Byc td __ N I
~
_E NE-1023 S2C13 Startup Physics Tests Report Page 56 of 56}}