ML20239A430
| ML20239A430 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/31/1987 |
| From: | Rogers P, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-525, VP-NOS-34, NUDOCS 8709170337 | |
| Download: ML20239A430 (58) | |
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North Anna Unit 1, Cycle 7 Startup Physics Tests Report Nuclear Operations Department V!RGINIA POWER G709170337 870911
- VP-NOS-34 l
l NORTH ANNA UNIT 1, CYCLE 7 STARTUP PHYSICS TESTS REPORT by P. S. Rogers
~l 1
l Reviewed By: Approved By: C. i C. A. Ford, Staff Engineer C. T. Snow, Supervisor Nuclear Fuel Operation Nuclear Fuel Operation Operations and Maintenance Support Subsection Nuclear Operations Department ( Virginia Electric _and Power Company Richmond, Va. August, 1987
- - - - _ - - _ - - - _ _ _ _ _ _ _ _ _ _ _ . ___________7_ _ __ _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _. __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by the Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company i therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE I 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 . 1 Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided j herein. In no event shall the Company Se liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute
.. lability), -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.
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1 TABLE OF CONTENTS SECTION TITLE PAGE NO. Classification / Disclaimer.................. i List of Tab 1es............................. 111 l l l List of F1gures............................ iv I Preface.................................... v 1 I>troduction and Summary................... 1 2 Control Rod Drop Time Measurements......... 9 1 3 ,' Control Rod Bank Worth Measurements........ 14 4 Boron Endpoint and Worth Measurements...... 19 5 Temperature Coefficient Measurement........ 23 6 Power Distribution Measurements............ 25 l l 7 References........ . ...... .............. 34 l APPENDIX Startup Physics Tests Results and j l Evaluation Sheets.... ... .... .. ......... 35 l 11
1 LIST OF TABLES l TABLE TITLE PAGE NO. 1.1 Chronology of Tests................................ 3 1 2.1 Hot Rod Drop Time Summary.......................... 11 3.1 Control Rod Bank Worth Summary..................... 16 l l 4.1 Boron Endpoints Summary............................ 21 l 1 5.1 Isothermal Temperature Coefficient Summary......... 24 { ( 6.1 Incore Flux Map Summary............................ 27 j i 6.2 Comparison of Measured Power Distribution Para- ) meters With Their Technical Specifications Limits. . . 28 4 l 111 l
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i LIST OF FIGURES 4, I FIGURE TITLE PAGE NO. i J 3 t I 1.1 Core Loading Map...... ....................... .......... 4 s 1.2 Beginning of Cycle Fuel Assembly Burnups................. 5 i e 1.3 Incore Instrumentation Locations......................... 6 1 1.4 Burr.able Poison and Source Assembly Locations............ 7 1.5 Control Rod Locations.................................... 8 1 2.1 Typical Rod Drop Trace................................... 12 2.2 Rod Drop Time - Hot Full Flow Conditions....... ......... 13 3.1 Bank B Integral Rod Worth - HZP........... ............. 17 l 3.2 Bank B Differential Rod Worth - HZP...................... 18 4.1 Boron Worth Coefficient.................................. 22 1 6.1 Assemblywise Power Distribution - 26% Power.............. 29 ; 6.2 Assemblywise Power Distribution - 49% Power.............. 30 a j 6.3 Assemblywise Power Distribution - 51% Power.............. 31 ! 6.4 Assemblywise Power Distribution - 85% Power.............. 32 l l 6.5 Assemblywise Power Dis tribution - KFP. . . . . . . . . . . . . . . . . . . . 33 1 1 1 i i l, l I I i i 4
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4 PREFACE 1 II The purpose of this report is to present the analysis and evaluation l or the physics tests which were performed to verify that the North Anna 1, Cycle 7 core could be operated safely, and to make an initial evaluation of the performance of the core. It is not the intent of this report to i 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 North Anna Power Station. Therefore, only j 1 a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparision of : the test results with design predictions, and an evaluation of the results, j The North Anna 1, Cycle 7 Startup Physics Tests Results and Evaluation l Sheets have been 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 I conditions (actual), 4) test results, 5) acceptance criteria, and 6) 4 i comments concerning the test. These sheets provide a compact summary of , i the startup test results in a consistent format. The design test i conditions and design values of the measured parameters were completed ! prior to the startup physics testing. The entries for the design values l l were based on the calculations performed by Virginia Electric and Power j Company's Nuclear Engineering Group *, During the tests, the data sheets l were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliminary comparison between measured and a l' predicted test results, thus enabling a quick identification of possible l problems occuring during the tests. The Appendix to this report contains i the final completed and approved version of the Startup Physics Tests j Results and Evaluation Sheets. I v l l
-l l
SECTION i INTRODUCTION AND
SUMMARY
On April 19, 1987 Unit No. 1 of the North Anna Power Station was shutdown for its sixth refueling. During this shutdown, 64 of the 157 fuel assemblics in the core were replaced with fresh fuel assemblies. The seventh cycle core consists of 9 sub-batches of fuel: three once-burned batches, two from Cycle 6 (batches 8A and 8B) and one from Cycle 4 (batch 6A6); three. twice burned batches, two from Cycles 5 and 6 (batch 7A2 and \ N2/5B), and one frco North Anna 2 Cycles 3 and 4 (batch N2/5A4); one thrice-burned batch from Cycles 4, 5, and 6 (batch 6A5), and two fresh batches (batches 9A and 9B). The core loading pattern and the design parameter.? for each batch are shown in Figure 1.1. Fuel assembly burnups arn given in Figure 1.2. The incore instrumentation locations are identified in Figure 1.3. Figure 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 7, and Figure 1.5 identifies the location and number of control rods in the Cycle 7 core. On June 29, 1987 at 0308, the seventh 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:
- 1. The drop time of each control rod was confirmed to be within the 2.2 second limit of the North Anna Technical Specifications . 8
- 2. Individual control rod bank worths for the control rod banks were
- ueasured using the rod swap technique8 and were found to be within 6.9% of the design predictions. The sum of the individual control rod bank worths was measured to be within 1.5% of the design prediction. These results are within the design tolerance of il5%
1
l for individual bank worths (t10% for the rod swap reference bank 1 worth) and the design tolerance of 10% for the sum of the individual control rod bank worths.
- 3. Critical boron concentrations for two control bank configurations were measured to be within 26 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 was measured to be within 0.3% of the design prediction, which is within the design tolerance of 10%
and met the accident analysis criterion. l S. The isothermal temperature coefficient for the all-rods-out configuration was measured to be within 0.5 pcm/'F of the design l l \ prediction. This result is within the design tolerance of 3 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 power distribution was within 5.1% of the predicted power distribution.
The measured parameters were within the limits of the Technical Specifications and met their respective accident analysis acceptance criteria. I In summary, the startup physics test results were acceptable. Detailed results, together with specific design tolerances and a;ceptance criteria for each measurement, are presented in the appropriate sections of this report. l l 2
Table 1.1 NORTH ANNA 1 - CYCLE 7 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure l Hot Rod Drop - Hot Full Flow 06/28/87 1600 HSD 1-PT-17.2 ! Reactivity Computer Checkout
~
06/29/87 0450 HZP 1-PT-94.0 Baron Endpoint-ARO 06/29/87 0849 HZP 1-PI-94.0 ' Temperature Coefficient-ARO 06/29/87 0900 HZP 1-PT-94.0 Bank B Worth 06/29/87 1043 HZP 1-PT-94.0 , Boron Endpoint-B In 06/29/87 1528 HZP 1-FT-94.0 i Bank D Worth - Rod Swap 06/29/87 1534 HZP 1-PT-94.0 Bank C Worth - Rod Swap 06/29/87 1613 HZP 1-PT-94.0 Bank A Worth - Rod Swap 06/29/87 1653 HZP 1-PT-94.0 Bank SB Worth - Rod Swap 06/29/87 1717 HZP 1-PT-94.0 ; Bank dA Worth - Rod Swap 06/29/87 1745 HZP 1-PT-94.0 l i Flux Map - 30% Power 07/01/87 1757 26% 1-PT-21.1 Flux Map - Delta I Target 07/06/87 0600 49% 1-PT-21.1 Flux Map - Fxy Verification 07/07/87 1358 51% 1-PT-21.1 Flux Map - I/E Calibration 07/13/87 0430 85% 1-PT-21.2 l Flux Map - I/E Calibration 07/13/87 0930 85% 1-PT-21.2 l Flux Map - I/E Calibration 07/13/87 1544 85% 1-PT-21.2 ' Flux Map - RFP 07/14/87 0730 98% 1-FT-21.1 3
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Figure 1.1 i NORTH ANNA UNIT 1 - CYCLE 7 CORE LOADING MAP l A P H H L K J H G F E O C 8 A . l ' TA2 fA5 TA2 G25 F23 G22 1 N2/5A 8A ~95~~~ ~BB~~~ 98 8A 7A2 i 301 H12 J51 H49 J42 Hl4 C04 2 j N2/58 9A 98 88 9i 88 "D8 9A N2/58 i
$5 B JIS J37 H39 Adl H55 J44 J06 560 3
~E27T3 6A 98 88 9A ~II'~~ 9A 88 98 8A N2/58 558 Hot J62 H48 J01 H35- J35 H30 J54i H04 S63 4 !
7A2 9A 98- 6A 9A 8A 88 l 8A 9A 8A "f5~~~ 9A FA2 J28 J53 Hof H43 H28 J26 H23 G40 G59 JOS H21 J49,]Jio 5 8A 98 ~II~~~ 9A 6A5 ~ 9A 8A 9A 6A5 9A 88 . 98 8A H16 J38 H29 JI7 F66 J13 H2C J02 F52 J29 H45 J50 H19 6
~7A F"~ 98 88 9A 8A 9A N2/50 9A 7A2 9A 8A 9A 88 98 TA2 l C27 J39 H54 J14 H03 J03 S61 J31 GIF J11 H08 J12 H40 J47 G46 7
( 6A5 88 98 88 88 8A 9A 6A6 9A 8A 88 88 ~f6~~~ 738 . 6AS l F30 H52 J48 H42 H34 H02 J24 F29 JO9 H06 H36 H44 J60 H50 F64 8 FA2 ' 98 88 9A J10 8A 9A J23 W 9A 7A2 9A J16 8A Hl? 9A J04 88 98 J46 7A2 G28 J45 H38 H24 G56 J21 G37 H56 G02 9 8A ~8~ 9 88 9A 6AS 9A 8A 9A 6A5 9A 88 98 8A HIS JS9 H47 JOS 707 J30 HtC J25 F35 J20 H31 J57 H22 10 4 T 7f3 TA~ 98 8A 9A 8A 88 ~51 ~ 9A 8A 98 9A /A2 S48 J32 J41 H25 Ji9 H27 H41 Hl3 J33 H05 J40 J27 G37 11 N2/58 8A ~IE~~~ 88 9A 68 9A 88 ~98 8A Nd/58 562 Hit J68 H32 J07 H33 J36 i'46 J56 H09 559 12 H2/iB 9A 98 88 98 88 98 9A N2/$8 . S57 J34 J55 H53 AH2 H37 J43 J22 S65 13 7AF 8A 98 88 98 8A 7A2 G47 H18 J58 HS1 J52 H26 019 14
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l FUEL ASSEMBLY DESION PARAMETIES l l SUB* BATCH .I-N2/5A N2/5B 6AS 6A6 7A2 8A I 8B 9A 9B INITIAL ENRICKTENT (V/O U235) 3.59 3.59 3.59 3.59 3.60 3.60 3.80 3,79 3,99 BURNUP AT BOC 7 (MVD/NTU) 28814 26250 36868 '17122 25353 20083 18595 0 0 ASSEMBLY TYPE 17X17 17X17 17X17 17X17 17X17 17X17 17X17 17X17 17X17 NUMBER OF ASSEMBLIES 2 9 8 1 17 28 28 36 28 FUEL RODS PER ASSEMBLY 264 264 264 264 265 264 264 264 264 4
Figure 1.2 NORTH ANNA UNIT 1 - CYCLE 7 BEGINNING OF CYCLE FUEL ASSEMBLY BURUNUPS R P N M L M J H 0 f E D C 8 A C25 I F23 , C22 23752 31178 i 23403 , 1 S01 , H 12 T~ H49 J42 Hl4 004 l 29188 - 20811 0 ' 1T651 0 21186 2T8511 ? l 564 J15 J31 H39 i AN I TI J44 J 04- ,10-1 26351 0 0 20177 ' O 20074 0 J 26581 3 78~ H01 J62 H48 J01 H35 J35 1830 J54 ~ Tif $63 26494 18880 0 18850 0 16557 0 18689 0 19172 26481 is W~ J28 J53 HO F J08 TI C 75 7 ~HC : J26 TC 7C J18 G40 21808 0 - 0 18642 0 2n291 16234 20304 0 18823 0 0 28 tis 2 5
~iilI~ 38- H29 Js1 566 J13 H2O J02 852 J29 1114 5 J 54F Hl9 20598 0 18492 0 43198 0 20582 0 42703 0 19002 0 20824 6 cri 7TV ~ T55's J14 li01~ J03 7C J31 Gli Jll Hoo J12 Hl4 0 ~J4T G46 4 23124 0 20435 0 19967 0 24409 0 25037 0 20257. 0 20161 0 234401 7 f30 H52 7iE~ H42 HC H02 J24 TI JO9 H06 H36 TiiiTe~ J60 H50 7644 30839 19781 0 16330 16602 206f8 0 17122 0 71039 16374 16041 0 19553 305481 8 G}8 23895 Ji45 ~Ii]8 J10 HC J23 W~ J21 G39 ~C J Hi7 J04 3 56 J44 CO2 0 19980 0 19993 0 24371 0 24474 0 20128, a *0304 0 23917 9 Ht5 J59 454 1 ~N5~ F07 J30 H10 TI TT~ J20 H31 Jil H22 21104 0 18549 0 42820 0 20863 0 42821 0 18377 0 20804 to 7C JW~ J41 - H25 Ji9 H27 H'i l Hl3 J33 H05 J40 7/ ~ C37 1 28447 0 0 19112. : 0 19599 16354 20024 0 19264 0 A 28013 11 1
~T C Hit J6) H32 J07 H33 J36 H46 ~,ITI HU9 $59 26203 19047 0 18301 0 16443 0 19012 0 18807 26504 12 TT~ J34 J55 Hs3 AHJ H3r T~ J22 565 ?
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.=> A$$(HOLY 10 1 23T74 30839 23485 15
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Figure 1.3 NORTH ANNA UNIT 1 - CYCLE 7 INCORE INSTRUMENTATION LOCATIONS C O C 8 A R P N M L K J H F E 1 MO TC TC TC MD 2 M0 M6 MO TC TC TC 3 1 TC TC MO I MO MO TC 4 TC M0 MO MO MO MO TC M0 TC TC M0 TC TC $ j M6~ 6 TC TC 1 MO TC MO l l M0 TC MD MO 1 7 TC TC MO MO 70~ MO MO 1 TC TC TC TC MO TC TC MO TC 6 MO TC TC
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MO TC MO TC M0 TC MD I 9' 1 MO HD PO TC TC MO TC 10 TC
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MO M0 IC 11 TC MO TC } TC MO MO M0 TC TC TC M0 TC 12 MO MS MO tc TC , 13
~~ . M0 14 TC MO TC M0 - Movable Detector 15 TC - Thermocouple MO (C TC l
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NOB 1H YNNV ON11 l - D A313 L BnBNV813 dOISON YNO S00833 VSS3W81A l~ODV1lONS W d N M 1 M 0- H D J 3 0 D G~ Y t t 2 SStf 2 t 904 L2d LLd { l2d sod f - 694 nod 694 69d q 4 694 G 904 694 694 494 194 god G 9 62d 19d 12d 8RJ 49d 13d 9 L SSlt 69d t2d 694 82d 19d 1 9 iLd 404 494 194 904- LLd 9 6 194 42d L9d 82d tad 6 60 l2d 494 12d l2d 69d 83d 10 li 9Od L9d 894 19d 694 904 LL iZ L94 19d nod 696 694 42 tf 9Od L2J ILJ L2d 904 tt lb l SSIG lh 1 ~ l lG lG W d N M 7 M 'l H -D J 3 0 0 S Y 70d f -- 71 03d73130 8nuNV073 d01 SON H00 olnS13W 90d -- 0 03d73130 anWNV073 d01 SON 800 010913W led -- 12 0nBNV073 d0lSON W00 070913W 59d -- 19 anaNV973 JGISON W00 olnS13B LLd -- ll BnBNV073 d01 SON W00 0lnS13W SS -- S300N0V8A S00803 1 4
1 Figure 1.5 { 1 l NORTH ANNA UNIT 1 - CYCLE 7 I i CONTROL ROD LOCATIONS { l l I R F N M L K J H C F E D C B A 180* I loop C l Loop B 1 Outlet l inlet _ . ,. i _ A D A 2 a!-41 l bA SA SP N-43 3
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l C 8 B C 4 l SP SB SP SB 5 l A P G C ( 0 B I A 6 Loop C Loop B inlet $A SB S8 SD SA -l Outlet 7
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9 0' - ~'~lD C C D - 270' 8 l l ~~ l SA SP S8 $8 SA 9 l A B D C D 8 A 10 S8 l SF SB SP 11 ) C B 6 C 12 1 SP SA SA i 13 N-44 ._ __ N-42 A D A 14 Loop A 4 N Loop A 15 Ab so rbe r Outlet inlet Ma te a l a l l , A.g-le-C# O' I Function Humber of Citister s Control Bank O 8 Control Bank C 8 Control Bartk 8 8: Cont ro l Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 SP ( Spa re Rod Locations) 8 8 l
SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS 1 I The drop time of each control rod was measured 6c hot full-flow RCS l condit!ons in order to confirm satisfactory operatica and to verify that i the rod drop times were less than the maximum allowed by the Technical j l l Specifications. The het control red drop time measurements were run with j the RCS at hot, full flow conditions ( 547*F, 2235 psig) and are described 1 below. l The rod drop time measurements were performed by first withdrawing a rM bank to its f ully withdrawn posttion, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod. This I allows the rod to drop into the core as it would in a normal plant trip. l The data recorded during this test are the stationary gripper coil voltage, ) 1 the LVDT (Linear Variable Differential Transformer) primary coil voltage, l and a 60 Hz timing trace which are recorded via a visicorder. The rod drop l cime to the dashpot entry and to the bottom of the dashpot are determined ! from this data. Figure 2.1 provides on examplo of the data that is recorded during a rod drop timn measurement. I As shown in Figure 2.1, the initiatien of the rod drop is indicated ( by the decay of the stationary gripper coil voltage when the stationary i i 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 'he t rod ( i velocity. When the rod enters the dashpot section of its guide tube, the l 1 velocity slows causing a voltage decrease in the LVOT coil. The LVDT voltage then reaches a miniaum as the rod reaches the bottom of the 9 i
dashpot, Subsequent variations in the trace are caused by the rod ) bouncing. This procedure was repeated for each control rod. l I The measured drop times for each contro) rod are recorded on Figure 2.2. The slowest, festest, and average drop times are summarized in Table 2.1. Technical Specification 3.1.3.4 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.2 seconds with the RCS at hot, full flow conditions. The test results met this limit. 10
Table 2.1 NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS HOT ROD DROP TIME
SUMMARY
.l l
ROD DROP TIME TO DASHPOT' ENTRY SLOWEST ROD FASTEST R0D AVERAGE TIME l B-06 1.80 sec'.' .C-09 1.48 sec. 1.59 sec.
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ROD DROP TIME TO BOTTOM OF DASHPOT SLOWEST ROD FASTEST R0D AVERAGE TIME ~ B-06 2.51 sec. C-09 2.05 sec. 2.25 sec. l l' l I i 11
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. Figure 2.1 ;
NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE l 17 " ' sar.
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1 l 1 Figure 2.2 NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS ROD DROP TIME - HOT ' FULL FLOW CONDITIONS l R P N N L' K J H c F E D' C 8 A I
-- .t 1.55 TF 1.59 l f 2 2.27 2.12 2.21 2 l l
1.57 1.57 3 - 2.24 2.24 3 l 1.56 1.52 TW TT l 4 2.25 2.20 2.25 2.22 4 J ar- Tr 2.19 1 5 2.30 5 q 1.50 TT 1.60 1.56 T'.C i.6o 1.80 l 6 2.19 2.29 2.26 2.25 2.26 2.28 2.51 6 f T"W t.51 TT TW
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I
. 1 SECTION 3 CONTROL R0D BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtained for the control and l shutdown banks using the rod swap technique. The first step in the rod l swap procedure was to dilute the most reactive control rod bank (hereafter referred to as the reference bank) into the core and measure its reactivity l l
worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by l
- the reactivity computer' and were used to determine the differential and integral worth of the reference bank (Control Bank B).
At the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were l stabilized such that the reactor was critical with the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by 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 withdrawing 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 maneuver was continued until the test bank was fully inserted and the reference bank was at the position at which the core was just critical. This measured critical position (MCP) of the reference bank with the test bank fully inserted is the major parameter of interest and was usod to determine the integral reactivity worth of the test bank. Statepoint data (core reactivity, moderator temperature, and the differential worth of the reference bank) were recorded with the reference bank at the MCP. The rod 14
1 swap maneuver was then performed in reverse order such that the reference bank coce again was near full insertion and the test bank was once again fully withdrawn from the core. The rod swap process was then repeated for all of the other control rod banks (control and shutdown). 1 A summary of the results for these tests is given in Table 3.1. As shown by this table and the Startup Physics Tests Results and Evaluation , 1 Sheets given in the Appendix, the individual measured bank worths for the l control and shutdown banks were within the design tolerance ( 10% for the reference bank and 15% for the test banks). The sum of the individual l rod bank worths was measured to be within 1.5% of the design prediction. This is well within the design tolerance of 10% for the sum of the individual control rod bank worths. l The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The l design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were l satisfactory. j l l l 15
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i Table 3.1 ! NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS l l CONTROL ROD BANK WORTH
SUMMARY
li MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH ( *. ) BANK (PCM) (PCM) (M-P)/P X 100 i i B-Reference Bank 1323 1338 -1.1 i l D 766 807 -5.1 ; i C 766 780 -1.8 l A 343 321 6.9 ! SB 902 930 -3.0 ! SA 1054 1056 -0.2 Total Worth 5154 5232 -1.5 l l l l 16
F10URE 3.1 NORTH ANNA 1 - CYCLE 7 80L PHYSICS TEST BANK B INTEGRAL ROD WORTH - HZP .. BANK 8 WITH ALL OTHER RODS OUT
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FIGURE 3.2
- CYCLE 7 BOL PHYSICS TEST NORTH ANNA 1 BANK.B DIFFERENTIAL R00 WORTH - HZP BANK B WITH ALL OTHER R0DS OUT
-- PRE 0!CIE0 ,
- MEASURED o
t ev
~ -
-f-i l
l i i i
, - li 6
1 i i t i , ! - ir "i t i ! l ! i 6 , j t ! ! t I ' O'[ i ! ! l O ! ! ! u i i 6 e i i i I . e 2 i I i ; a i 1 g- - i "m ! ! / I l ' ,
~
~P f
s i l j Lu ,
- ! i i i
H I I i E s I 1 C ' m\ No a ' = t , go e t i 3 i/ 4 R I 1 ue 1 i i w , i i l t > i ! x i i i 1 l i i i t i i X ! i
* ' 8! l O i l I r1 I s i I 4 '! = 'n '
F- o .j i 'L g o. ! i 1 i i i i i f i 1 1 i i x 4 i l
! i
@ l f I t $t 3: > n' Ii !, n !. a >
i i .= i . ; i I ~.k 1 ! J - I. l' e C ! i l . k l a <, 1 s i so e i e
\
i l Z . ,r ,
, , i ll.,,l ,
_ \t i
% / l l i' tu , ! , i W ! t i
l ll- o _ i1 .! i l tl
-o i l i
n '
. in a y 9 CQ '
i I t ' i
'i u
GRID t RAIION,I ' i _.MPem- ' r _-- - 5-9 '/ N ^ q % f _,, - # I/ Q ~% ,
% m._
,, * #~
, y "
g r Tm^ Q _
% ,,,' ~%m t M. l l O / i \
O ,, k7N t I ! i I
. , , i ,
i, s; , 0 40 80 120 160 200 2iB BANK POSITION (STEPS) 18 i - - - -__
SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system baron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. The { critical boron concentration was then measured. If necessary, an 5 adjustment to the measured critical boron concentration was made to account for off-nominal core conditions (rod position and moderator temperature). 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 were within their respective design tolerances. The measured values met the accident analysis acceptance criterion. In summary, the boron endpoint results were satisfactory, i Boron Worth Coefficient , , , i I The measured boron endpoint values provide stable ststcpoipe data ' m f rom w'aich the boron worth coefficient was determined. A plce of the buron, concentration as a function of integrated reactivity can be constructed . by relating each endpoint concentration to the integrated red worth present in the core et the time of t.he endpoint nicasuremiat. Tho value of th6 boron s
/ h-( g' g
iJ
) $ >'
1:: ;
}
' ~
coefficient, over the range cf boron endpoint concentrations, is obtained directly from this plot. Tha boron worth plot is shown in Figure 4.1. As indicated in this figure and in the Appendix, the boron worth coefficient of reactivity was measured to be -7.27 pcm/ ppm. The measured boron worth coefficient is within 0.3% of the predicted value of -7.25 pcm/ ppm and is well within the design tolerance of 10%. The measurement result also met the accident analysis acceptance criterion. In summary, the measured boron worth was satisfactory. Y k 20
? [ 4
'.l' V
9 ' Table 4.1 l NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
( Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm) ARO 1969 1995 -26 , B Bank In 1787 1785'r 2
- The predicted endpoint for the B Bank in configuration has been adjusted for the dif ference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the baron endpoint Startup Physics Test Results and Evaluation Sheets in the Appendix.
4
)
+
21
m . p p
/
m c p 7 2 7 T = S B E 0 C 6 T S C I S T Y N H E \ P I C \ L I O F ST
\
B F NE E EM N 4 1
. 7 O RU C S
\
A E E E M
\
R L H U C T N T
\
G l o I Y R P F C O D N WE _ N C s x\ _ 1 O N R A O N B \ N A h H
\
T N R O N - N x y 0 0 0 0 0 0 0 0 0 0 4 0 6 2 0 0 2 2 1 1 8 4 {oL *[ >~CEbg J uw i
SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient measurement at the all-rods-out l l condition was accomplished by controlling the RCS heat gains / losses with l the steam dump valves to the condenser, 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 approximately at the same temperature (between 544 and 548 F) during these measurements. Reactivity measurements were taken during both RCS heatup and cooldown ramps during which the RCS temperature varied approximately 3.0*F. Reactivity was determined using the reactivity stripchart recorder and temperature was recorded on the average RCS temperature stripchart. The temperature coefficient was then determined from the change in these parameters. The change in reactivity divided by the change in temperature yields the isothermal temperature coefficent. The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of 3 pcm/*F and met the accident analysis acceptance criterion. In summary, the measured result was satisfactory. 23
l t t i Table 5.1 ! l NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS 1 ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
f, ISOTHERMAL TEMPERATURE COEFFICIENT f BANK TEMPERATURE BORON (PCM/ F) ! POSITION RANGE CONCENTRATION j ( F) (ppm) COOL DIFFER. j HEATUP D0VN AVER. PRED. (M-P) j j 544.7 [ eD/208 to 1965 -0.11 -0.89 -0.49 -0.96 0.47 ! 548.0 l 1 l E. l 1 d ( l I I 24 i ; i i
SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the incore ' movable detector flux mapping system. This system consists of five fission detectors which traverse fuel assembly instrumentation thimbles in 50 core , locations (see Figure 1.3). For each, traverse, the detector output is continuously monitored on a strip chart recorder. The output is also scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are then determined by analyzing this data using the Westinghouse computs.r program, INCORE'. INCORE couples the measured flux map data 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 test program together with a list of the measured values of the important power , distribution parameters is given in Table- 6.1. The measured power l distritiution parameter values are compared with their . Technical Specifications limits in Table 6.2. Flux Map 1 was taken at 26*; power. This flux map served as the base case design check. Figure 6.1 shows the resulting radial power distribution associated with this flux map. Map 1 did, however, indicate a Fxy (RTP) violation. As a result of this Fxy (RTP) violation and a similar violation at 50*. power, additional flux maps were taken in accordance with Technical Specification 4.2.2.2. However, 1 at no time did the measured Fxy value exceed the power-dependent limit 'of Fxy (L). Flux maps 2 through 7 were taken over a wide range of power levels i and control rod configurations. These flux maps were taken to check the y at power design predictions and to measure core power. distributions at 3 25' i w-______-__--_.-_--______--_-____-_-----___ _ _ - _ _ _ . _ _ _ _ _ _ __ __ _-- - . _ _ - _ - _ . _ _ _ - - _ - - _ - _ -
t, l 4 ( 1 various operating conditions. These maps also provide a cross-calibration between the incore and excore nuclear instrumentation systems. 'The radial I power distributions for these maps are given in Figures 6.2 thru 6.5. { These figures show that the measured relative assembly power values are generally within 5.2?. of the predicted values. Further, the. measured F-Q(T) and F-4H(N) peaking factor values for the at power flux maps were witnin the Technical Specification limits, 1 j In conclusion, the power distribution measurement results .were. j 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 7. l i 1 [ 26 _-_-_=____-_:__-_a
llIlIliIIi1I1IIli MS OFIE 8 1 4 4 9 NOHL 3 4 4 4 3 TB IlllIIII1i111!1!1 l AFT) t XOS( A FE% 4 6 5 0 8 2 1 3
-2 9 6 3
0 2 5
)
Y L B M E - llIlllI_IIIIII1Ill 3 R T P C O L lIlIlI111l1l1 WWWWE S S S S N 5 8 0 6 5 S SS AD E ER O O R Q X 0 0 1 0 0 R C N A 0 0 0 0 0 OL O M CE E I 1 1 1 1 1 U H T iI]llII!!I111l1I1 FF T A _
- 2) 0 3 3 8 7 O T _
YX 5 1 3 6 f F N - XA 6'4 7 7 5 5 RO O E _ (M . E M _ F 1 1 1 1 1 TS P U illliIIl1l111I1i1
)
NW O R - 1 6 8 3 3 EO T T _
) Z 3 1 0 3 3 CR S Z ( 3 3 3 2 2 E N
( FX EM R A lIlTI" AN F 1 1 i111I1l1 2 9 9 9 7 1 1 1 EN H HE TE sNRO T)M
.T I
R A E _ O tI 2 2 2 2 3 aEER L _ C XO VNF C _ AP 8EN U _ llIIllII1I111Ili1 SAG N _
) H MN M 8 6 3 2 8 I E
( 1 8 9 1 9 .EiRT l R _ S TR H 5 4 4 4 3 O T OO D G. TAR LA C S HT - 1 1 1 1 1 EHIT X E C f (1MS E T )A l iI
/ _
MF S C I S ( HL DN
- H i1_iIII1IIIlI N
I P lll11I1i1I1i1 Y M M M M O N 3 N N 3 3 N N 3 1 SWSS N OEAN IT TANO T I E R O C Y FC S 1 1 1 1 1 ANIP IN _ H Y S L L L L N CI _ P R A ODDL 3 . R A ilIIlliIiIiliIill LREA 0 3 O . P M ) OTt 0 F U M T 7 8 5 4 6 YOAX 1 T U 8 0 0 9 8 LCNA 1 N R S Q( 1 1 1 8 8 B G X E 1 A R - . . . M I1 X K
. T P 1 O F 2 2 2 E"Y S 6 5 A
- 6 S A TT 1 1 S" E 0 5 T M OC lIIl1IlilI1Il S DO 0 E 7 HA lT AE T 1 S _ L X F AN 1 8 9 9 7 lien 1 P B E U ) II 2 2 2 2 3 GTTI F A A L L TL XO N A O F M T C F (E AP IYND O Y QN lIIiIIIiIIIll VBIE Y E C E - N N M M M M O I DD T Y R R O C FA C H I P _N N N N N llll1I1l1I1I1 GDRI YTOI EOV N I A T N O I I
. O C
1 N Y 3 3 3 3 1 BOCD T A T R . I S 1 i 1 1 1 N R T A E) _ A S L L L L N DE S E R R TN _ N A E D "X I C E RO N IlIIIlliiliiiIiIi I{ N C T AI A S F E U N L UT K P 8 9 3 8 8 INER U I QA H NDE 8 7 8 0 2 COlOt L T R T A T 1 1 1 2 2 EIIC A L EB R B S Pi T A R Rf O IllIlll SADE O T E EL N R) W% _i1I1I1I1I1 6 9 _ 2 4 5 8 9 1 5 8 EOAT CNH T O W WA T O C P( _ RL A P 6 1!lIllli1i1I1I1I1 N / A RN A E 4 7 3 3 5 N O S T D/ RPDU 1 3 7 5 8 SIHI E S N N1 UUWT 1 1 NPCT D E A A( B MM O UC U D R IEOE L U D 5N 1ljIIlIl1i1I1I1l1 TiRR i C L A O 7 7 7 7 7 ATHI N C U SI 8 8 8 8 8 C TD I N Q PT E - - - - - OY I AA T 1 6 7 3 4 ) - MR A 1 1 L B A "Z T( ) B D - - - - - T D D" Y R Xl 7 7 7 7 7 OEE Q X T Ul PWRE - ( P LA SOEH F F Q FC 1ljIIlI_i1i1I1I1l1 P AO MN lI1IIllii1II1!lij
. 1 2 3 4 7 TLT OOEN HFLI LTT 1
2 3 4 N : O S I E T T T N E A O O G C ) N I R l 4 T A f ( PP A T i AI E R . MR W I E L C O V A S P A C E T Y D W L X E P O E - / F L D F I H lllIillIIiIIl!III Illl
Table 6.2 NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS MAP F-Q(T) HOT F-DH(M) HOT 2 NO. F(XY) MAX CHANNEL FACTOR 1 CHANNEL FACTOR MEAS LIMIT MARGIN MEAS LIMIT MARGIN MEAS AXIAL LIMIT I MARGIN (%) ('.' ) POINT (?.) 1 2.19 4.19 47.8 1.52 1.82 16.5 1.65 2.11 36 1.86 12.7 2 4.27 50.5 1.49 1,72 13.4 1.75 1.88 3 2.11 4.19 50.1 10 6.9 1.49 1.71 12.9 1.71 10 1.88 9.0 4 1.89 2.52 24.7 1.41 1.56
~
9.6 1.54 27 1,67 7.8 7 1.89 2.19 13.8 1.40 1.50 6.7 1.57 10 1.65 5.1 1 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 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 vclues listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each raap. All measured F-Q(T) hot channel factors include 5% measurement uncertainty and 3*. engineering uncertainty. 2 All measured F(XY) MAX values include 5*. measurement uncertainty and 3?. engineering uncertainty. 28
t l
.l l
ll Figure 6.1 1 1 NORTH ANNA UNIT 1 -- CYCLE 7 STARTUP PHYSICS TESTS 1 ASSEMBLYWISE POWER DISTRIBUTION 26% POWER R P M M L K J H 0 F E. O C 8' A l**'hkkbibiib.' l'bl5i'l'b[55','b55' *k(bIbidb'l P
. MLASURt0 . . 0.33 0.33 0.32 MEASURE 0 i
. . 1 l
.PCF OlFFERENCE. . S.4 S.O . 3.0 .PCF OtrFERENCE. '
..;.;;.,3.;;.;.;.;;..6'h6',im'"b'4i'b'ii"
. 0.37 . 0.60 . 1.13 . 0.90 . 1.12 . 0.53 , 0.35 . 2
. 5.5 . -4 1 , 0. 8 . 0.4 0.7 0.5 . 0.5 .
. 0.38 , 1.11 . 1.29 . 1.22 . 1,32 . 1.22 1,29 . 1.11 . 0.38 1.23 1.19 S.5 . S.S . 4.1 . 2.9 . -3.0 . -1.8 . 1.29 . 1.12 . 0.39 .
. 0.41 . 1.l? 1.28 . 1.20 3
- 05. 0.5 0.5 .
J
55h*l'b'i9'[*I55i.'iE*5'il$b*i5h*'i,5b'l'Iho*l'I$5*'bl79'l*bl59
. 0.40 . 0.8) . 1.30 1.29 . 1.33 . 1.27 . 1.32 1.26 . 1.23 . 0.77 . 0.40 . 4
. 2.9 . 2.7 . *7.. 0.9 . -1.9 . -2.0 . *2,9 . -1,6 . -1.6 . 1.6 . 4.4 .
. 0.3S . ......................................................................
1.11 . 1.2S . 1.14 1.22 . 1.17 ...... .......
.. 0.35 . 1.12 . 1.26 . 1.15 . 1.22 . 1.17 1.22 . 1.17 , 1.22 1.23 . 1.17 1.22.. 1.14 1.14 . 1.25 .'t.11 0.35 0.3
. l.23 1.16 . 0.36 . S 0.4 . 0.4 . 0.3 . 0.1 . -0.7 0.8 . *0.3 . -0.1 . *0.2 . -1.6 . 4.4 . 4.5 .
............................ .. 4. .............. .....n...... ............................
. 0.63 . 1,29 . 1.28 . 1.22 0.77 . 1.22 . 1.13 . 1.22 . 0.77 1.22 . 1.28 . l.29 . 0.63 .
0.63 . 1.29 . l.28 . 1.22 . 0.77 . 1.22 1.13 . 1.22 0.77 . 1.22 . 1.26 . 1.35 . 0.66 . 6
. *0.1 . *0.2 . *0.0 . 0.0 . 0.0 . *0.3 . *0.2 . 0.4 0.0 . -0.1 . -1.6 . 45.
..... .. ............. 4.5 .
. 0.31 1.12 . 1.22 . .........................................
1.36 . 1.18 , 1.21 . 1.04 .......................................... 1.22 . 1.04 . 1.21 . 1.18 . 1.36 1.22 . 1.12 . 0.31 . 0.31 1.09 . 1.20 , 1.34 l.17 1.2% . 1.04 1.22 . 1. 04 .. 1.22 . 1.18 . 1.32
-0.8 . -2.4 =2.3 1.21 . 1.11 . 0.31 . 7
-1.4 . -0.3 +0.3 . -0.4 *0.1 . 0. 3 . 0. S . 0.6 . -2.8 . -0.9 . 0.9 . 0.8 .
i . 'b$ii'l'blhb*1 0.30 . 0.88 , 1,295E
. 1,29 'il5b'$'i
. 1.25hi'*'i'iE
. 1.13 . *Ildl*i 1.21 I6' *iil*5'Ilib'l'i25'5*il5b'*i[$U'*
1.17 . 1.21 6.12 . 1.21 l.26 bub'l'h$55'. 1.31 . 0.89 . 0.31 l . -4.1 -2.5 . -2.6 . -0.4 . 1.5 . 1.0 . -0.2 . 8 0.2 . -0.S . -0.6 -1.5 . *2.8 . -1,1 -1.2 . 0 0.31 . ............................................................................................. 1.12 1.22 , 1.36 1.18 1.21 . I,04 1.22 . 1.04 1.28 1.18 . 1.36 , 1.22 . 1.12 . 0.31 6.
. 0.31 1.09 . 1.19 . 1.35 . 1.20 . 1.22 . 1.01 1.21 1.03 1.20
*1.0 . *2.6 . -2.6 . -0.5 . . 1,16 . 1.33 . 1.21 1.11 . 0.31 9 1.6 . 0.2 . -2.4 a0.9 . -0.8 . -1.0 . *1.4 . 61.8' -0.9 . *0.9 . 0.8 .
0.63 . 1.29 . 1.28 ..................................................................... 1.22 0.77 . 1.22 . 1.13 . 1.22 . 0.77 1,22 1.28 . 1.29 . 0.63 . .... .. 0.62 1.27 1,29 . 1.24 . 0.77 1.21 1.13 . 1.21 . 0.76 , 1.21 t 1.28 . 0.63 . 0.7 . 1.27 10
*1.2 -1.2 . 1.6 . 0.1 -1.1 . -0.4 . ab.6 . *0.9 . *1.1 -0.2 +J.8 i
. *C.8 .
- 0. 3 S ., 1.11 1.25 . 1.14 1.22 1.17 ........
. 0.36 . 1.14 . 1.28 . 1.16 2.5 2.S . 2.0 . 1.4 . *0.9 . 1.16 1.21 . . 1.22 . 1.18 . 1.23 . 1.15 . 1.28 , 1.14 . 0.37 ..
1.23 . 1.l? . l.22 . 1.14 . 1.25 . 1.11 . 0.3S 11 3.0 . *0.9 . 0.7 . 0.5 . 0.7 . 1.8 . 2.4 . S.6
. 0.39 0.79 . 1.25 ................... ...........................................
1.28 . 1.36 . 1.29 . 1.36 . 1.28 . 1.25 . 0.79 . 0.39 . 0.48 0.82 . 1.27 . f.27 . 1.35 . 1.28 . 1.35 . 1.27 . 1.26 . 0.81 . 0.40 6.1 12
. 3.7 . 1.1 . =0.2 . *0.9 . a0.8 . -0.7 . 0.3 . 0. 6 . 2.8 4.0 .
0.38 . 1.11 . 1.29 . 1.22 . 1.32 . 1.22 . ..................... 1.29 . 1.11 . 0.36 O.4l . 1.19 . 1.32 . 1.20 , 1.31 . 1.22 1.29 . 1.12 . 0.40 6.4 13
. 6.7 . 2.7 . -1.6 . -0.6 . -0.4 0.2 . 0.5 . 3.8
' . *0.
6.7 3 7 . 0. 1.10 6 7 ...b'$$'l'bldi'.'1lli'.**bl9hil$h'**b*55S'b!5$*'***'** 0.90 1.11 , 0.63 . 0.34 , 14
. 6.8 . -l.8 . *0.1 . -0.2 0.4 . 1.1 .
Ot vl A F10N , 0.33 . 0.31 . 0.31
=1.703
. PCT OlFTERENCE.
. . 7.0 , 1.6 . 1.7 . . = 1.7 .
SUMMARY
MAP NO: N1 1 DATE3 7/ 1/07 POWER: 26% CONTROL ROD POSITIONS: F=Q(T) = 2.187 QPTR: D BANK AT 188 STEPS F-DH(M) = 1.518 NW 1.001 NE 0.995 F(Z) = 1.331 SW 1.005 SE 0.999 F( XY ) = 1.649 BURNUP = 14 MWD /MTU A.O = 8.54(%i 29
t
.' / .
1 1 ll 1 i 1 4
-z Figure 6.2 - ]
i i NORTH ANNA ' UNIT 1 - CYCLE 7. STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTR.lBUTION s I 49.0% POWER 1 A P N h L K J H G F E D C 8 A j
................ .l
. PR(DICfE0 ,
, 0.31 . 0.31 . 0.31 . . PRiotCTto . 'l MEASURED .
, 0.33 0.33 . 0.33 . . MEASURto . 1 9 5.1 . 4.7 . 3.5 .
. 1
. PCT DIFFERENCE. . .PC7 DIFFERENCC.
................ l
..... . . ...... ......, ............. ...... ..................... j
. 0.35' 0.64 . 1.11 . 0.89 1.11 . 0.64 . 0.35 2 3 0.37 . 0.61 . 1.12 . 0.89 . 1.'12 , 0.65 . 0.36 I
. 5.1 . -4.8 0.3 -0.3 . 0.8 1.8 . 2.5 .
....... ............. .................... .................... l 0.39 . l.11 . 1.28 1.21 . 1.30 , 1.21 1.28 . 1.11 . 0,39 . -
. 0.40 . 1.14 . 1.27 . 1.15 . 1.24 . 1.19 . 1.28 . 1.13 . 0.41 . 3
. 2.6 . 2. 3 . -0. 5 . -4. 8 . -4. 8 . - 1. 4 . 0.3 . 1.4 . 3.3 .
. 0.39 . 0.79 . 1.25 . 1.27 . e.35 . 1.29 . 1.35 .. 1.25 1.27.. 1,25 . 0.79 . 0.39 .
. 0.40 0.81 . 1.27 . 1.27 . 1.28 . 1.23 . 1.31 , 1.24 . 0.80 . 0.41 . 4
. 2.6 . 1.6 . 1.8 0. 4 . -4. 7 . -4. 7 . 2. 9 . - 1. 6 . =0.1 . < 0. 6 . 3.5 .
. 0,35 . l.11 . 1.25 . 7.14 . 1.22 1.18 . 1.23 . 1.18 . 1.72 . 1.14 . 1.25 . 1.11 . 0.35 . 'S
. 0.36 . 1.12 1.25 . 1.14 . 1.2l . 1.17 . 1.23 . t.18 . 1.21 . 1.14
- 22 . 1.15 . 0.37 .
. 03. 0.3 . -0.1 . -0.2 . 0.2 . 0.'4 . -0.4 . 0.2 , *0.4 . -0.6 . -2.3 . 37. 3.7 .
............... .................................. ......................... 4...............
l
. l.64 . 1.28 . 1.27 . 1.22 . 0.7' . l.23 . 1.14 . 1.23 . 0.77 . 1.22 . 1.27 1.24 . 0.77 , 1.21 . 1.24 . 1.29 .'O.66
. 1.28 . 0.64 . 6 1.27 . 1.22 . A.77 . 1.22 . 1.14
. 0.64 . 1.28
. 0.4 . 0,3 -0.0 . *0.3 , -0.2 . -0.1 . 0.2 . 0.e 0.1 . 0.6 2.0 . 0.9 . 3.7 . ]
............................................... .....,,...... .................................. ....... l
.0.32 . 1.11 '1.21 . 1.35 . 1.18 , 1.22 1.05 . 1.24 . 1.05 1.22 , 1.18 . 1.35 . 1.21 . 1.11 . 0.32 i 0.30 . 1.08 . 1.17 . 1.33 . 1.18 . 1.22 . 1.05 . l.24 1.06 . 1.24 .'1.18 . 1.33 . 1.20 , 1.11 . 0.32 , '
7
- 1. 0 .
. -3.3 . 3.3 . -3.3 . 1.2 -0.1 -0.0 . -0.1 0.2 0.8 . 1.1 . C.3 -1.7 . -0.7 . -0.2 .
'bl52*bl59' *$$55* il59'!'il25'*,'iI$','ili2'$l'.55'*'i.52.***i li***i55*l*I29' *I ib'*.*bI59' *bl}i*
0.30 . 0.86 1.26 . 1.29 . 1.25 . 1.15 . 1.23 . 1.19 . 1.22 . 1,13 . 1.22 1.27 . 1.30 . 0.89 . 0.32 . 8
-3.3 -3.4 . -3.3 -0.1 . 1.5 1.1 , 0.3 0.5 . 0.0 . -0.0 . -1.0 . -1.7 . -0.7 . -0.5 , 0.8 .
O.32 . 1.11 . 1.21 1.35 . 1.18 . 1.22 1.05 . 1.24 . 1,05 1.22 . 1.18 1.35 . 1.21 , 1.11 . 0.32 0.31 . 1.09 , 1.18 1 34 . 1.20 , 1.22 . 1.03 . 1.22 . 1.05 . 1.22 . 1.18 , 1.34 . 1.22 . 1.12 . 0.32 . 9
-1.6 . =2.5 , -2.6 . 0.5 . 1.) . 0.1 . -2.7 . -1,1 =0.3 . 0.5 . =0.2 . -0.3 . 0.8 0.8 . 1.8 .
0.64 . 1.28 1.27 1.22 . 0.77 , 1.23 . t.14 . 1.23 . 0.77 . 1.22 . 1.27 1.28 . 0,64 .
. 0.63 1.25 . 1.28 . 1.24 0.77 . 1.22 . 1.14 1.22 . 0.77 . 1.22 . 1.28 . 1.30 . 0.65 . 10 l . 1.9 . 1.9 . 0.4 1.7 0.1 . =0.8 . =0.3 . =0.3 . -0.6 . -0.3 0.9 . 1.7 2.6 ,
I ......................................... ...... .................................. .......
. 0.35 1.11 . 1.25 . 1.14 . 1.22 . 1.18 . 1.23 1.18 , 1.22 . 1.14 1.25 . 1.11 . 0.35 .
l . 0.36 . 1.13 . 1.27 , 1.16 , 1.21 1.17 . 1.23 . 1.18 . 1.21 . 1.15 . 1.27 . 1.14 . 0.37 . 11 l . l.5 . 1.5 . 1.6 . 1.8 -0.4 . -0.6 -0.4 . 0.1 . -0.3 . 0.7 . 2.2 . 2.6 . 3.6 . i . .......................................................................... .............. l . 0.39 , 0.79 1.25 1.27 , 1.35 . 1.29 . 1.35 . 1,27 . 1.25 . 0.79 . 0.39 f t . 0.41 0.82 , 1.27 , 1.28 . 1.34 . 1.28 . 1.33 . 1.26 1.25 . 0.81 . 0.41 . 12 i 5.0 . 3.4 1.8 . 0.6 . =0.5 . -0.4 . -0.9 4 =0.7 . 0.1 . 2.6 . 3.6 . i . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . l 0.39 . 1.11 . 1.28 . 1.21 . 1.30 . 1.21 . 1.28 1.11 . 0.39 .
. O.41 . 1.17 . 1.31 . 1.19 1,29 . 1.20 1.27 1.11 . 0.41 . 13 5.2 . 5.3 , 2.4 . 1.4 . 0.8 . -1.1 . -0.6 . 0.3 . 3.4
***'bli$'l'blAk*'Ilii'l'bl59'5lii*'bl65*b$$5'.*'*****
0.63 . 0.35 . 14
. 0.37 . 0.67 . 1.09 . 0.88 . 1.10 i
. L3 5.3 -2.3 -0.6 . -0.9 . =0.5 -1.7 . t
.kikkbkkb$ bh5.'b$5','bhi**'*"*** '1hEkkbC'
, O(VIAfl0N . 0.33 . 0.12 . 0.32 . ..PC7 Diff(R(NCE.
=1.502 . . 5,3 . 1.0 0.9 . .
= 1.6 .
SUMMARY
MAP.NO: N1 2 DATE: 7/ 6/87 POWER: 49% CONTROL ROD POSITIONS: F-Q(T) = 2.108 QPTR3 D BANK AT 179 STEPS F-DH(M) = 1.486 NW 0.991 NE 0.996 , F(Z) = 1 316 SW 1.008 SE 1.005 l t l F(XY) = 1.753 r l BURNUP = 37 MWD /MTU A.0 = 2.06(%) t 30 L
1 Figure' 6.3 : NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS l a ASSEMBLYWISE POWER DISTRIBUTION ! 1 i
' 51.0% POWER !
R P N M L K J H C F E 0 C 8 A j t
**hktbICfE0'
. *b$$h' 'O 3E 'b 3h [ "PEkbibikb** j
. MEASUREO , . 0.33 . 0.33 . 0.33 . . MEA $URED , 1 !
, PCT DIFFERENCE. 4.8 . 4.4 . 2.6 . . PCT OlFFERENCE, i
....... . . ..., ..................... ............................ ... ............ [
, 0.36 . 0.64 l.12 0.90 . 1.12 . 0.64 0.36 .
. 0.37. 0.62 . 1.12 . 0.90 . 1.12 . 0.64 . 0.36 . 2
. 4.1 . -3.6 . 0.7 . 0.3 . 0.6 . 0.3 . 1.9 . '
0.39 , ,11 . 1.27 , 1.23 . 1.30 . 1.21
.........I..........................................
. . 1.27 . 1.11 . 0.39
. 0.40 . 1.12 . 1.25 . 1.19 . 1.28 . 1.20 . 1.27 . 1.12 . 0.41 . $
. 1.4 . 1.1 . -1.7 . -1.9 . *l.9 . -l.0 . -0 1 . 1.2 . 36.
. 0.40 . 0.79 . 1.24 1.26 . 1.34 . 1.28 1.34 .-1.26 , l.24 . 0.79 . 0.40 .
. 0.40 . 0.80 , 1.26 . 1.27 . 1.33 . 1.27 . l.32.. 1.26 . 1.25 . 0.8) . 0.41 . 4
. 1.9 . 1.1 . 1.3 . 0.5 . -0.8 . 0.9 . -1.3 , -0.4 . 0.9 . 1.7 . 3.9 .
. 0.36 . 1.11 . 1. 24 .. 1.14 . 1.22 . 1.18 . l.23 1.18 . 1.22 . 1.14 . 1.24 . 1.11 . 0.36 .
. 0.36 . 1. I'l . 1.24 , 1.14 1.22 . 1.18 . 1.23 . 1.18 . 1.22 . 1.14 . l.24 l.16 . 0.37 5
. *0.0 . *0.0'. 0.3 . -0.3 . 0.0 . 0. 2 -. 0.2 . 0.0 . 0.1 . 0.1 . =0.3 . 4.2 . 4.2 .
....... .........s... .......................................................................
. 0.64 . 1.28 1.27 t.22 . 0.78 . 1.23 . 1.14 1.23 . 0.78 . 1.22 . 1.27 . 1.28 . 0.64 .
. 0.64 . 1.28 . 1.27 . 1.22 . 0.78 . 1.23 1.15 . 1,23 . 0.78 . 1.21 . 1.24 . 1.28 . 0.67 . 6
. 0.0 =0.0 . 0.1 . 0.1 0.3 . 0.2 0.3 . 0.4 . 0.4 . -0.7 . 1.8 . 0.5 . 4.2 .
. 0.32 . 1.12 . l.21 . 1.34 . 1.18 . 1.22 . 1.05 . 1.24 . l.05 . 1.22 . 1.18 . 1.34 1.21 . 1.12 . 0.32 .
, .31 . 1.07 1.16 . 1.32 1.17 . 1.22 . 1.05 . 1.24 . 1.06 . 1.23 . 1.17 . 1.30 . 1.19 . 1.10 . 0.32 7
. 0.3.9 . 3.9 -3.9 . al 7 . 0.6 . -0.4 . ~0.1 . 0.1 0.4 . 0.7 . -0.6 .. -3.1 . -l.8 . -1.0 , 0. 7 .
. 0.32 . 0.90 . 1.30 . 1,29 . 1.23 . 1.13 1.22 . 1.18 . 1.22 . 1,13 . 1.23 . 1.29 . 1.30 . 0.90 . 0.32 .
. 0.31 . 0.86 . 1.25 . 1.28 1.25 . 1.14 1.23 . 1.19 1.22 . 1.13 . 1.21 . 1.25 . 1.28 . 0.89 . 0.32 . 8
. -3.9 . -3.9 . -3.9 . -0.6 . 1,1 . 0.8 0.2 . 0.6 . -0.2 -0.3 . -1.9 . 3.1 . -1.3 . -1.2 0.3
. U 32 1.12 . 1.21 1.34 1.18 . 1.22 . 1.05 . 1.24 . 1.05 . 1.22 . 1.18 . 1.34 . 1.2% . 1.12 0.32
. 0.31 , 1.08 . 1.17 . 1.33 . 1.19 . 1.23 . 1.04 . 1.23 . 1.05 . 1.21 . 1.17 . 1.33 1.21 . 1.12 . 0.32 9.
. -2,1 . 3.0 . 3.1 . -0.9 1.2 . 0.2 . -1.8 . *0.4 -0.5 . -0.7 . -0.8 . -1,3 . 0.2 . 0.2 . 1.6 .
... ..... 1................. ..................... ........... ............................ ............
. 0.64 1.28 . 1.27 . 1.22 0.78 . 1.23 . 1.14 . 1.23 0.78 1.22 1.27 1.28 . 0.64 .
. 0.62 . 1.25 . 1.27 . 1.24 . 0.78 . 1.22 1.14 . 1.22 . 0.77 , 1.21 . 1.28 , 1.29 . 0.66 . 10 4
. -2,3 2.3 . 0.4 1.9 . 0.7 . 0.5 0.1 . -0.6 . 0.7 . -0.6 . 0.8 . 1.4 . 2.5 .
l
. 0.36 1.11 . 1.24 . 1.14 1.22 1.18 . 1.23 . 1.18 . 1.22 1.14 1.24 . 1.11 0.36 .
l (
. 0.36 . 1.13 . 1.27 2.0 . 2.0 . l.9 .
1.16 . 1.21 . 1.17 . 1.23 . 1.18 . 1.22 . 1.15 . 1.27 . 1.14 . 0.37 1.9 . -G.2 . -0.5 . -0.3 , -0.1 . -0.1 . 0.6 . 2,1 . 2.5 . 11 3.7 . 1 1 . 0.40 . 0.79 , 1.24 . 1.26 1.34 . 1.28 . l.34 . 1.26 . 1.24 . 0.79 . 0.40 . l . 0.s.1 . 0.83 . 1.26 . 1.27 1.33 1.27 1.32 . 1.25 . I.24 . 0.82 . 0.41 . IP i . 6.3 . 4.1 . 1.8 . 0.4 . 0.8 . 0.8 . -1.3 . -0.8 . -0.0 . 2.8 . 3,6 . 0.39 , 1.11 . 1.27 '.21 . 1.30 1.21 . 1.27 , 1.11 . 0.39 .
. 0.42 . 1.16 . 1.31 . 1.19 . 1.29 . 1.20 . 1.27 1.11 0.h1 . 13 6.2 6.2 . 2.7 . -1.8 . -0.7 . -0.9 . -0.2 -0.2 . 3.4 ,
. 0.36 . 0.64 1.12 . 0.90 . 1.12 . 0.64 . 0.36 .
. 0.38 . 0.67 . 1.13 . 0.91 . 1.11 0.64 . 0.35 . 14 l . 6.2 . 5.6 . 1.1 1.0 . -0.7 . -0.0 . =2.3 .
...g.. ......... ...... ..... ...
. DEVIAllON . . 0.33 . 0.33 . 0.33 . .rC7 DIFFERENCE 4
. al.516 . . 4.5 . 3.1 . 2.0 . . = 1.5 .
SUMMARY
MAP NO: N1 3 DATE: 7/ 7/87 POWER: 51% CONTROL ROD POSITIONS: F-Q(T) = 2.105 QPTR: D BANK AT 183 STEPS F-OH( M ) = 1.1493 NW 0.995 NE 0.997 F(Z) = 1.308 SW 1.010 SE 0.'998 F(XY) = 1.713 BURNUP = 73 MWO/MTV A.0 = 2.31(%) 31 1 I
4 . p 1 s l i i e Figure 6.4 NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS TESTS I 1 ASSFMBLYWISE POWER. DISTRIBUTION 85.0% POWER R P N M L .k- J H .0 F t D C 8 A
.PRibibiib. 'bl3k'l'bl3S'.'bl3E"' lPRibibik6*'l
. MIA5UR(0 . . 0.34 . 0.35 . 0.34 . . MEASURE 0 . 1.
,PC7 GiFFERENCE. . 0.0 . 0.2 . 0.0 .PL7 OlFFER!hCE.
.. . . .. .g . . . ;. ; . . .g.gg. . g ; g e . .g.gg. . .g. g p .....u....
i
' . 0.38 . 0.63 . 1.11 . 0.93 . 1.12 . 0.65 , 0.37 . 2 i
. 2.6 . 2.6 . -1.2 . -1.5 . 0.8.. 0.1 . 0.5 .
'.'blEi'l'II0h'.'1.24.I!b5'l'lbb'l"i59
. 0.41 . 1,10 1.17 . 1.26 . 1,18 '5bb'*55El5b9l555
. 1.24 . 1.09 . 0.41 . 3
. 1.4 . l.0 . -0.6 . -1.8 . -1.8 . -l.3 . -0.5 . 0.0 . 0.9 . i
...... ....................................................................... l
. 0.41 . 0. 80 . 1.21 . 1.24 . 1.31 . 1.27 . 1,38 . 1.24 . 1.25 0.80 . 0.48 . J
. 0.41 . 0.8D . 1.23 . 1.25 . 1.30 1.26 . 1,29 , 1.23 . 1.21 . 0.80 . 0.41 .
. 1.3 0.8 . 0.9 . 0.5 . 0.8 . -0.8 . -1.5 . =1.1 . *0.5 . *0,2 . 1.5 .
4 )t 0.37 1.09 . 1.22 . 1.13 . 1.21 . 1.18 . 1.23 . l.18 . 1.21 . 1.13 . 1.22 . 1.09 . 0.37 . 'l l
. 0.37 . 1.09 . 1.22 . 1.13 . 1.22 . 1.18 1.23 , l.17 . 1.21 . 1.13 . 1.20 , 1.12. 0.37 . S. !
. 0.1 . 0.1 . 0.1 . 0.1 , 0.3 . 0.2 . 0.1 . -0.2 . 0.5 . -0.6 . 1.3 . 2.0 . 2.0 . l
. 0.6S . 1.25 . 1.24 . 1.22 . 0.82 . 1.24 1.15 .. 1.24 . 0.82 . 1.22 . 1.24 . 1.25 . 0.65 . !
. 0.65 . L *S 1.24 . 1.22 . 0.83 . 1.25 . 1.16 1.25 . 0.83 . 1.21 . 1.23 . 1.25 . 0.66 . 6 j
. 0.3 . u.3 . 0.3 . 0.3 . 0.4 . 0.4 0.6 . 0. 7 . 0.2 . -0.5 . -1.1 . -0.6 . 2.0 . (
........ ............................. ................. ................................................. 1
. 0.34 l.13 . 1.23 1.32 . 1.18 , 1.24 . l.07 , 1.24 . 1.07 l.24 1.18 . 1.32 1.20 1.13 . 0.34 . 1 0.34 1.12 . 1.18 . 1.31 . 1.18 , 1.24 1.08 . 1.25 . 1.08 . 1.25 . 1.18 . 1.30 . 1.19 . l.13 . 0.34 , 7 j
. 0.4 . 1.1 . -l.0 . 0.4 . 0.4 . 0.2 . 0.1 . 0.5 . 0.8 l.0 . 0.3 . -1.2 . -0.5 . -0.3 . 0.9 .
. 0.35 . D.94 . 1,29 . 1.27 . 1.23 . 1.15 . 1.23 1.19 . 1.21 . 1.15 . 1.23 . 1.27 1.29 . 0.94 . 0.3S .
0.34 . 0.93 . 1.27 . 1.27 l'.25 . 1.16 . 1.23 . 1.20 .. 1.23 . 1.14 . 1.22 . 1.25 . 1.28 . 0.94 . 0.35 . 8 1 2.7 . -1.2 . =1.3 . 0.2 1.7 . 1.1 . 0.0 . 0.4 . -0.3 -0.3 . -1.1 . -1,2 . -0.5 -0.4 . 0.8 ,
. 0.34 1.13 . 1.20 1.32 . 1.18 1.24 . l.07 . 3.24 . 1.07 1.24 . 1.18 . 1,32 1.20 1.13 . 0.34 0.34 . 1.11 . l.18 . 1.32 1,6 . -1.6 1.20 . 1.25 . 1.06 1.24 . 1.07 , 1.23 . 1.16 . 1.30 , 1.20 . 1.13 . 0.35 .
9
. -0.4 0.1 . 1.7 0.7 . -1.3 . -0.6 -0.9 . 1.0 . -1.4 -1.5 . -0.1., 0.4 . 1.3 .
. 0. 6% ., 1.25 . 1.24 . 1.22 0.82 . 1.24 . 1.15 1.24 . 0.82 . 1.22 1.24 1.25. 0.65 .
. 0.65 . l.24 . 1.25 . 1.24 . 0.83 . l.24
. =0.4 0.8 ,
1.15 . l.23 . 0.81 . I . '19 . 1.22 . 1.2S . 0.66 . 10
-0.S . 1.5 . 0.5 . 0 4 . 0.0 . 1.0 . -1.9 . -2,2 . -1.5 . 0.1 . 1.6 .
. 0.37 1.09 . 1.22 1.13 . 1.21 . 1.18 . 1.23 . 1.18 . 1.21 . 1.13 . l.22 , 1.09 , 0.37 .
- 0. 3 7 .. 1.11 . 1.23 . 1.14 . 1.26 . 1.18 . 1.23 . 1.18 . 1.19 , 1.13 . 1.22 . 1.10 , 0.37 .. 01
. 1.2 . 1.2 . 1.1 . 0.8 . 0.4 . =0.2 -0.1 . -0.2 . -1.7 . .0.6 0.7 .' 1.0 . 2.0 .
.... . ........................ 4....................... ...................................
0.41 . 0.80 . 1.25 . 1.24 . 1.31 . 1. 2 7 . l.31 . 1.24 . l.21 , 0,80 . C.41 j
. 0,41 . 0.8) . 1.22 . 1.24 . 1.31 . 1.26 . 1.30 . 1,22 . 1.21 , 0.81 . 0.41 i f.9 , 12 j
. 1.9 . 0.8 . 0.1 . 0.5 -0.4 . *0.8 . =1.3 . -3.4 l.8 . 1.8 . '
G.41 . 1.09 1.24 . l.20 , 1.29 1.20 , 1.24 . 1.09 . 0.41 . i
. 0.42 . l.13 . 1.26 . 1.18 . 1.28 . 1.19 1.24 1.09 . 0.41 . 13 l
. 3.1 . 3.4 . l.4 . -1.3 . -0.8 . =0.8 . *0.2 .. 0.2 . 1.8 . j
.. ... ........... .............................. .......... . i 0.37 . 0.65 . 1.13 . 0.94 . 1.13 , 0.6S . 0.37 .
0.38 . 0.67 1.13 . 0.94 . 1.12 . L.65 . 0.36 . 14 3.4 . 2.6 . =0.2 . -0.1 . -0.7 . 0.2 *0.9 . STANDARD
. . 0.34 0.15 0.34 AVCRACC D(VIAil0N .
. 0.35 . 0.35 . O.34 .
.PC7 OlFFERENCE.
. =0.731 . . 1.5 0.9 0.3 , = 0.9 .
SUMMARY
MAP NO: N1 4 DATE: 7/13/87 POWER: 85% l CONTROL ROD POSITIONS: F-Q(7) = 1.894 QPTR: D BANK AT 208 STEPS F-DH(H) = 1.412 NW 1.000 NE 1.001 F(Z) = 1.233 SW 1.006 SE 0.953 F(XY) = 1.538 l BURNUP u 153 MW/MTU A.0 = -0.29(%) 32 i
Figure 6.5 NORTH ANNA UNIT 1 - CYCLE 7 STARTUP PHYSICS T,ESTS ASSEMBLYWISE POWER DISTRIBUTION HFP R P N M $. K J H O F E O C 8 .A PRC01C1(D . ................ MfA5UR(0 . 0.35 . 0.36 . O.35 . PRE 01Cffo .
. 0.36 . 0.37 . 0.35 .
( .
. PCT Otff(RENCE. . NCAsunto
. %.6 . 2.6 . 1.8 . .PC7 OlFIERENCE.
. 1 0.37 . 0.65 . 1.13 . 0.95 . 1.13 0.6% , 0.37 .
0.38 . 0.63 . s.13 . 0.95 1.13 0.66 . 0.37 3.8 . -3.1 . -0.2 . -0.2 . 0.1 . 0.8 1.5 . 2 0.41 . 1.08 . 1.24 1.19 . 1.2S 1.19 ........................
, 1.24 1.08 0.41
. 0.41 . 1.10 . 1.22 . 1.17 .
1.1 . -1.3 . -1.5 . -1.6 . =0.6 . 0.A . 1.10 .'J.42 . 1.26 . 1.18 . 1,24
, 1.4 . .
1.1 . 2.3 . 3
.. 0.41 0.41 .. 0.80 0.80 .. 1.22 1.21 .. 1.241.23 . 1.31 . 1.26 . 1.31 1,23 . 1.21 . 0.80 . 0.41 l.30 , 1.25 . 1.29 1.23
. 1.5 . 0.8 . 1.2 . 0.4 -0.6 . -0.6 . 0.9 . =0.4 . 0.
1.21 . 0.80 . 0.42 . 4
. ..................................................................<.5.
0.37 1.09 . 1.21 1.13 1.21 1.18 1.23 1.18 . 1.21 1.13 . 0.8 . 1.21 2.9 . 0.37 1.08 . 1.21 1.14 . . 1.09 . 0.37
-0. 7 . -0. 7 . -0.1 , 0.3 . 1.22 . 1.18 . 1.24 . 1.18 . 1.2? . 1.13 1.20 . 1.13 0,38 S
0.3 . 0.5 . 0.5 . 0.4 0.5 . 0.2 . -0.8 3.5 . 4.5 . 0.6S . 1,24 . 1.23 1.22 0.84 1.25 . 1.16 . 1.25 . 0.84 1.22 . 1.23 ................ 1.24 0.6S . 0.65 . 1.24
-0.0 . =0.0 . 1.24 0.6 . . 1.24 . C.85 . 1.25 . 1.16 . 1.26 . 0.85 .. 1.21 1.22 . 1.25 . 0.68 ,
1.8 . 1.1 . 0.5 . 0.5 . 0.9 . 0.6 . -0.3 . -1.4 6
.........................................................o d.9 . 3.5 .
. 0.35 1.13 . 1.19 . 1.31 . 1.16 1.24 . 1.08 . 1.25 . 1.08............................................
1.24 - 1.18 . 1.31 1.19 . 1.13 . 0.35 .
. 0.35 . 1.12 1.14 . 1.30 . 1.19. 1.25 . 1.08 , 1.25
. 1.09 . 1.26 . 1.lt . 1.28 . 1.18 . 1.12 . 0.3S .
0.1 . -1.2 . -1.1 -0.6 . 0.R 0.6 . 0.3 . 7
- 0. 3 , 1.2 0.2 . -1.9 1.28 . 1.26 . 1.23 1,.1$ . 1.24 1.19 . 1.24 . 1.15 . 1.23 . 1.26-1,3 . -0.9 . 0.0 .
... 0.8 .
. U.36 . 0.96 0.34 . 0,94 1.27 , 1.26 . 1.2S 1.17 . 1.24 1.20 1.28 0.96 . 0.36 .
. -3.3
-1.4 . -1.4 0.1 . 1.6 1.2 . 0.5 . 0.6 . -0.
1.23 . 1.15 . 1.21 . 1.24 1. 2 7 . 0. 95 . P. 36 8
..0.35 . 1.13 . 1.19 . 1.31 1.18 1.24 5 . -0.$ . =%.3 . -1.9 . -1,3 . 0.9 0.0 .
0.34 1.09 . 1.15 1.31 l.20 e 1.25 1.08 . 1,25 . 1,08 . 1.24 . 1.18 . 1.31 1.19 . 1.13 . 0.35 . 1.04 . 1.24 1.08 . 1.24 . 1.17 . 1.30 . 1.19. 1.13 . 0.35 .
-3.3 . -3.3 -3.3 . 0.1 . 1.7 0 5 . -2.0 . -0.7 . -0.5 . 0.7 9
.......................... ...........................................,4-0.8 . -0.9 . 0.1 0.2 . 1.2 .
. 0.55 . 1.24 1.23 . 1.22 . 0.84 1.25 . 1.16 . 1.25 . 0.84 , 1.22 . 1.23
. 0. 6 3 . 1.20 , 1.26 . .24 1.24 . 0.65
. -3.3 . 3.3 . 1.9 . '1.9 . 0.6% 0.S .. 1.22 *2.0 .. 1.150.7 .. 1.23
=1 . 0.83 1.20 . 1.23 . 1.25 . 0.67 10
. -1.4 . 0.1 .
. 0.37 l.05 . 1.21 1.13 . 1.21 1.18 1.23 2.
1.18 1.3
. 1.21 1.2 . 2.1 .
0.38 . 1.13 1.24 1.15 . 1.21 1.16 1.22 1.13 . 1.21 . 1.09 . p.37 .
. 43. 4.3 . 2. 7 .
- 1. 3 . n o . L , = 1. 4
. 1.16 . 1.20 , 1.13 . 1.23 . 1.11 . 0.38 11
-i.e . 1
. 0.41 . 0.80 1.28 . 1.23 . 1.31 1.26 l.31
. -1.4 . 0.1 1.8 . 2.0 . 3.0 .
4 .......................................
. 0.43 . 0.82 1.22 . %.24 . 1.29 1.24 1.28 , 1.22 1.23 . 1.21 . 0.80 . 0.41 .
. 4.3 . 2.8 . 1.3 . 0.3 . 1.4 . -1.$ 1.20 . 0.92 . 0.42 . 12
-1.7 . 1.4 . -0.3 . 2.6 . 2.8 .
. 0.41 1.08 1.24 . 1.19 , 1.28 ...................................
1.19 . l.24
. 0.42 . 1.10 . 1.23 . 1.17 1.27 1.08 . 0.41 .
4.3 . 1.18 . 1.23 . 1.09 . O.42
......... l.3 ...
. =0.7... . -1.5... -0.9 . =1.1 . -0.6 . 0.1 . 2.7 .
13
. 0.38 . 0.67 1.13 . 0 96 , 1.12 . 0.5) 0.36 .
2.7 2.8 0.3 . 14 0.3 . *0.9 . *0.4 . -1.$ .
. OtvlAfl0N .
. 0.36 U.36 . 0.35 .
. s1.0$0 .
. 2.7 . 1.7 W.6 . . PCT 01FFERENCC.
..... .......... .
- 1.3 .
SUMMARY
MAP NO: N1 7- 7 CATE: 7/14/87 POWER: 98% CONTROL ROD POSITIONS: F-Q(T) = 1.886 QPTR: O BANK AT 228 STEPS F-DH(M) = 1.398 NW 0.998 NE 1.005
.......... .... ....~
r!Z) = 1.233 SW 1.004 . sg o,gg3 r(XY) a 1.567 BURNUP = 1.85 MWD /VTU A.0 = -2.56(%) 33
SECTION 7 REFERENCES
- 1. C. B. LaRoe, S. M. Bowman, " North Anna Unit 1, Cycle 7 Design Report,"
NE Technical Report No. 576, Virginia Electric and Power Cotapany, May 1987.
- 2. North Anna Unit 1 Technical Specifications, Sections 3.1.3.4, 3/4.2.
- 3. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A December, 1980.
- 4. " Technical Manual for Westinghouse Solid State Reactivity Computer,"
Westinghouse Electric Co poration.
- 5. W. Leggett and L. Eisenhart. "The INCCRE Code," WCAP-7149, December, 19o7.
34
l l APPENDIX 1 STARTUP PHYSICS TESTS RESULTS AND EVALUATION SHEETS l 35
'bORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP' PHYSICS TEST RESULTS AND EVALUATION SHEET {
i I Test
Description:
Reactivity Computer Checkout ~ Reference j Proc No /Section: 1-PT-94.0 Sequence Step No: 3 II ' Bank Positions (Steps) RCS Temperature (*F): 347 ;j Test Power Level--(*.' F.P.): 0 1 Conditions SDA: 228 . SDB: 228' Ca: 228 Other (specify): (Design) CB: 228 CC: 228 CD:
- Below Nuclear Heating III Bank Positions (Steps) 'fRCSTemperature<(*F): 5%
Test Power Lava l (*.' F.P. ) : O Conditions SDAi 228 SDB: 228 CA: 128 Cther (Specify): ' (Actual) CB: 228 -CC: 328 CD:moviq Below Nuclear Heating l Date/ Time Test Performed; G - 2.1 - 8 7 [om a Neasured Parameter pc = Meas. Reactivty using p-computer i IV (Description) pe = Inferred React from reaft period l 1 pc" ~ N' # U-Measured Value p = ~47 o (f 7. o l Test %D = l . o (,*/, 2.17. I Results Design Value j l (Actual Conditions) ?.D = ((pc"Pt )/Pt] x 100*.' 5 4.0.. q Design Value (Design Conditions) *D
= ((pc"Pt)/Pt] x 100*. 5 4.0% l Reference WCAP 7905, Rev. 1, Table 3.6 l V FSAM/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable ,
i Design Tolerance is met : l YES _.N0 VI j Acceptance Criteria is met : _X.YES NO Comments I* At The Just Critical Position j Allowable Range,= 47 Completed By: Evaluated By: C K I , N < Q .c c
' Test 'En"gitteer s i
$a y: C-NFO Engineer
]
4 4 1 A.1 4
l s 5 NORTH ANNA POWER CTATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ' Test Description. Critical Boron Concentration - ARO Reference Proc No /Section: 1-PT-94.0 Sequence Step No: Y II I Dank Positions (Steps) ECS Temperature (*?): 547 Test Power Level (*. F.P.): O Conditions SDA: 228 SDB: 228 CA: 22,4 Other (specify).: (Design) CB: 228 CC: 228 CD: 228. Below Nuclear Keating l III Batik Positions (Steps)' RCS Temperature (*F):S+7. 2. ! Test - Power Level (% F.P.): 0 l Conditions SCA: 228 SDB: 228 CA: 228 Other (Specify): 1 (Actual) CB: 228 CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: . , 6-2.9-77 / o e't9 ' l Meas Parameter IV (Description) (C)Af0;CriticalBoronConc-ARO g Measured Value b (CB )A 0
- ff" -
Test j Results - Design Value (Actual Cond) CB= 1, 9 9 5- f 5't ([> m peaign value l (Design Cond) <0B =1995 t 50 ppm Reference NE Technical Report No. 576 V FSAR/ Tech Spec a C xC B5 24,000 pcm i B Acceptance Criteria Reference UFSAR Section 15.2.4 Design Tolerance is met :_#YES ___NO l Acceptance Criteria is ret : # YES NO VI Comments a C B
#c e* ~7' 2'7 f **/N" -
b 'hI Completed By: m- Evaluated By: - Test Engineer l Recommended for Approval,By : j NTO Engineer A.2
NORTH ANNA POWER STATION ' UNIT 1 CYCLE 7 STARTUP PHYS!CS TEST RESUt.TS AND EVALUATION SHEET I Test
Description:
Isothermal Temperature Coefficient - ARO Reference Proc No /Section: 1-PT-94.0 Sequence Step No: S II Bank Positions (Steps) RCS Temperature (*F): 347 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F): 547. 2. Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): CB: 228
}ctual) CC: 228 CD : 2. o ? Below Nuclear Heating Date/ Time Test Performed:
lo 2A-87 /O900 } Meas Parameter IV (Description) 0 (a 73ARO Isothermal Temp Coeff - ARO Wst Measured Value (aIS0)APO * ~ ' Pcm/'F (CB = 9 W Ppm) Results Design Value IS (Actual Cond) (a ;.0) ARO = -0 A pcm/ F (Cg =1906 ppm) (" ISO)ARO T = -0.67 2 3.0 pcm/'F Design Value (Design Cond) (CB = 1995 ppm) Reference NE Technical Report No. 576 7SO V FSAR/ Tech Spec a g 3,77*pcm/*F a Dop = -1.73 pcm/*F Acceptance Criteria Reference TS 3.1.1.4, NE Technical Report No. 576 Design Tolerance is met : /YES NO VI Acceptance Criteria is met : / YES NO Comments
- Positive a T Tech Spec approved for North Anna Unit 1 g
on 12-20-85. Uncertainty on a = 0.5 pcm/*F Tg (Reference memorandum from C.T. Snow to E.J. Lozito, June 27, 1980)
- N, Completed By: '
~
Evaluated By: - UN Test Engineer to B : C-A,3 NFO Engineer
l NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Catl Bank B Worth Meas., Rod Swap Ref. Bank l Reference- -Proc No /Section: 1-PT-94.0 Sequence Step No: 6 l II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F):5 M.'t j Test Power Level (% F.P.): 0 ' Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): ) (Actual) CB: Moving CC:'228 CD: 228 Below Nuclear Heating ) Date/ Time Test Performed: (r'29-59 / / O'+3 1 Measured Parameter IR ; Integral Worth of Cntl Bank B, (Description) All Other Rods Out ' IV Test Measured Value IR = l3 23 pcm Results Design Value (Actual Conditions) IR , l3 3 y i 13(p peM Design Value (Design Conditions) IR = 1338.t 134 pcm l Reference NE Technical Report No. 576 ! If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result FSAR/ Tech Spec on safety analysis. SNSOC may specify V that additional testing be performed. Acceptance Criteria
,,' Reference VEP-FRD-36A VI Design Tolerance is met Acceptance Criteria is met
- /S NO
- ES NO Comments Completed By: "/ #lbL Test Engineer Evaluated By:
/ wer .u *-
rova y: C. A.4 STO Engineer
i{ NORTH ANNA POWER STATION UNIT 1 CYCLE 7 i STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - B Bank In Reference j Proc No /Section: 1-PT-94.0 Sequence Step No: 7 ]{ II Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (f. F.P.): 0 . Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): l (Design) CB: o CC: 228 CD: 228 Below Nuclear Heating ! III Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (f. F.P.): 0 Conditions SDA: 228 SDB:-228 CA: 228 Other (Specify): (Actual) CB: 0 .CC: 228 CD: 228: Below Nuclear Heating Date/ Time Test Performed: lo - 2 9 - S 7 /)S2%
' Meas Parameter IV (Description) (C ) ; Critical Boron Conc - B Bank In I
.8 Measured Value (CB )
- ffi^
Results Design Value (Actual Cond) CB" ff
- Design Value (Design Cond) C B=1811+ACf#"# t(10 + 133.8/la C B I) Ppm Reference NE Technical Report No-. 576 V FSAR/ Tech Spec a xC Bs 24,000 pcm C
B 1 i Acceptance i Criteria Reference UFSAR Section 15.2.4 Design Tolerance is met : / YES NO Acceptanc.e Criteria is met : M ES NO VI Comments a C B AC
"" = (C B)A 0 - 1995 m . .w ,p u 4 Completed By: b f Y--
Evaluated By: f - Test Engineer Recommended for A E# V81 Y ' ' 'j f , P
^*5 NFO Engineer
r NORTH ANNA POWER STATION UNIT 1 CYCLE '7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
HZP Boron Worth Coefficent Measurement Reference l Proc No /Section: 1-PT-94.0 Sequence Step No: 4/- II Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (% F.P.): 0 , Jonditions SDA: 228 SDB: 228 CA: 228 Other (specify): ! (Design) CB: Moving CC: 228 CD: 228 Below Nuclear' Heating III Bank Positions (Steps) RCS Temperature (*F): 5N7. 2. Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: Moving CC: 228 .CD: 228 Below Nuclear Heating Date/ Time Test Performed: (c - 2 'l - f 7 / 07Mt Measured' Parameter l 1 IV (Description) a Boron Worth Coefficient C l B 4 Measured Value a =
-7'27 C
B f C# /7 Results Design Value : (Actual Conditions) a C B Design Value (Design Conditions) a C
~
B Reference NE Technical Report No. 576 FSAR/ Tech Spec a xC B5 24,000 pcm C B V Acceptance Criteria Reference UFSAR Section 13.2.4 i Design Tolerance is met : __ YES _NO VI Acceptance Criteria is met : #YES NO Comments Completed By: - Evaluated By: - Test ' Engineer ' Recommended for Approval By:] Ch L NFO Engineer A,6 l _
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l I Test
Description:
Cnti Bank D Worth Measurement-Rod Swap Referencej Proc No /Section: 1-PT-94.0 Sequence Step No: 9 II l Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (*. F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: Moving CC: 228 CD: Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F): 6'f f . 3 l Test Power Level (*. F.P.): 0 l Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): ) (Actual) CB: Moving CC: 228 CD: Moving Below Nuclear Heating 1 l Date/ Time Test Performed: l 6-29-97 / 1531 i Meas Parameter l (Description) I ; Int Worth of Cnti Bank D-Rod Swap 1 IV (Adj. Meas. Crit. Ref Bank Test Measured Value Position = l2.4 steps) Results IE3= 766 fem ( Design Value (Adj. Meas. Crit. Ref Bank j (Actual Cond) I RS,gc71 g 7,l pe,h Position = 12'f steps) 1 l Design Value I E8= 800 t 120 pcm (Critical Ref Bank (Design Cond) Position = 130 steps) Reference NE Technical Report No. 576, VEP-FRD-36A, l SFO-TI-2.2A If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/ Tech Spac safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria -- Reference VEP-FRD-36A
! Design Tolerance is met : S NO VI Acceptance Criteria is met : _.__. YE S NO Comments 1
Completed By: - ' Evaluated By- h )T't c _ Test Engineer
- Recommended for Approval By
gj NFO Engineer l l A.7 l
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Cnti Bank C Worth Measurement-Rod Swap Reference l Proc No /Section: 1-PT-94.0 Sequence Step No:lo II ! Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB: Moving CC: Moving CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('F):5'47.5~ Test Power Level (% F.P.): O Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): . (Actual) CB: Moving CC: Moving CD: 228 Below Nuclear Heating Date/ Time Test Performed: b - 2 '7- 5' 7 //M 3 Meas Parameter (Description) I ; Int Worth of Cntl Bank C-Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value Position = 12,2_ steps) Results IRS = 76 L fcm - Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) IRS = '/ fD ll7pe m Position = l 2 Lsteps) Design Value I RS= 775 t 116 pcm (Critical Ref Bank (Design Cond) Position = 127 steps) Reference NE Technical Report No. 576, VEP-FRD-36A, NFO-TI-2.2A If Design Tolerance is exceeded, SNSOC V shall evaluate impact of test result on FSAR/ Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. ./ l Reference VEP-FRD-36A Design Tolerance is met : S NO VI Acceptance Criteria is met : __ YES NO Comments l Completed By: Evaluated By: ' - Test fngineer Recommended for Approval By : j , 1 NFO Engineer j l A.8 1 i __--_-__--_-a
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ' Test
Description:
Cnti Bank A Worth Measurement-Rod Swap Reference Proc No /Section: 1-PT-94.0 Sequence. Step No:Jf. J II -Bank Positions (Steps) RCS Temperature (*F): 547 j Test Powe r Level (*. F.P. ): 0 j Conditions SDA: 228 SDB: 228 CA: Moving Other (specify): ; (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F): 5V7. (o i Test Power Level (% F.P.): O Conditions SDA: 228- SDB: 228 CA: Moving Other (Specify): (Actual) CB: Moving CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: G-29-77 //6.73 Meas Parameter (Description) IRS; g Int Worth of Cnti Bank A - Rod-Swap-IV (Adj. Meas. Crit. Ref Bank j Test Measured Value IR=3 A 3 fcm Position = 7 7 steps) Results Design Value (Adj. Meas. Crit. Ref' Bank ' l(ActualCond) IRA "32I
##D f em Position = 77 steps)
Design Value I RS= g 328 i 100 pcm,(Critical Ref Bank (Design Cond) Position = 80 steps) Reference NE Technical Report No. 576, VEP-FRD-36A, NFO-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
.,'Re f e r ence VEP-FRD-36A ;
Design Tolerance is met :
# YES NO VI -Acceptance Criteria is met : # YES NO Comments Completed By- f-Test En'gineer Evaluated By: f' A-Recommended for Approval By : j- [;t-)
NFO-Engineer A.9
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Shutdown Bank B Worth Meas. - Rod Swap Reference Proc No /Section: 1-PT-94.0 Sequence Step No:12. II Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (* F.P. ): 0 Conditions SDA: 228 SDB: Moving CA: 228 Other (specify): (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature (*F):f'ff. I Test Power Level (*. F.P ): 0 Conditions SDA: 228 SDB: Moving CA: 228 Other (Specify): (Actual) CB: Moving.CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: lo -2 9 -V7 /I7I7 Meas Parameter (Description) I ; Int Worth of Shutdown Bank B-Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value I Position = lYlsteps)
= 9 0 2. f c m Results Design Value (Adj. Meas. Crit. Ref Bank (Actual Cond) I = 9 DIlW CmPosition P = /Yl steps)
Design Value I = 931 140 pcm (Critical Ref Bank (Design Cond) Position = 147 steps) Reference NE Technical Report No. 376, 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. e -- Criteria f Referer.ce r VEP FRD-36A / Design Toleranck is met : _id3S NO VI Acceptance Criteria is met : WES NO Comments
/
i I ' Comotered By: / /' ' Evalu ced By: - 1 Test Engineer ' ( Recoce. ended for
>gts:tLd' ,
, / /1.pprava1 By : C. .
.u_.
s .[ 1
} y ,7
[ NFO En2ineer , s j l '/ A.1(k ! n , ,
^
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I ' TesP.
Description:
Shutdown Bank A Worth Meas. - Rod Swap Reference Proc No /Section: 1-PT-94.0 Sequence Step No: 13 II Bank Positions (Steps) RCS Temperature (*F): 547 Test Conditions SDA: Moving SDB: 228 CA: 228 Power Level (% F.P.): O (Design) CB: Moving CC: 228 CD: 228 Other (specify): Below Nuclear Heating III Bank Positions (Steps) .RCS Temperature (*F): f'f 7,'i Test Conditions SDA: Moving SDB: 228 CA: 228 Fower Level (% F.P.): O (Actual) CB: Moving CC: 228 CD: 228 Other (Specify): Below Nuclear Heating Date/TimeTestferformed: (c -2 c1 - % 7 / / 7'+5" Meas Parameter (Description) I ; Int Worth of Shutdown Bank A-Rod Swap IV (Adj. Meas. Crit. Ref Bank Test Measured Value I
=/O Q cm Position = l(cYstcps)
Results Design Value (Adj. Meas. Crit. Re f E .nk (Actual Cond) I = 105'b t 157pcm Position = / V,Asteps) Design Value I = 1057 138 pcm (Critical Ref Bank (Design Cond) Posi'. ion = 165 steps) Reference NE Technical Report No. 576, VEP-FRD-36A, NTO-TI-2.2A If Lesign Tolerance is exceeded, SNSOC V FSAR/ Tech Spec shall evaluate impact of test result on Acceptance safety analysis. SN500 may specify that Criteria additional te. sting be performed. Reference VEP-FRD-36A Design Tolerance is met . ._1dT.,S NO VI Acceptance Criteria is met Comments : _ ::fES ___NO Completed By: l// ' + Evaluated By: - - Test Ehgineer recommended for Approval By : C j- C STO Engineer A.ll
s
~
/
( .s > t NORTH ANNS: POWER STATION UNil' 1 CYCLE 'I STARTUP FYlYSICS TEST RESUl TS AND EVALUATir.N 6HET I tsst De^cript:lon: Total Ref Yorti. - Rod Swap Reference l Proa Nd /Sqct. ion: 1-PT-94.J , Secaence Step No:13 II > B r k Pot.Ltions (dteps) RCS Tce.gerature ("F): % ;' Test 5
-- Powe r 1. eve l (f. f. P. ) : 0 ConditionsISDA:MNir.h 3DB. Moving CA:Mov{agl Othe; ;specify): .
(Design) j CB: Moving C'.: Moving CD:Movingj Bej:w Nuclear' Jp ting III BanL ?c 4tfons (S t ep:-) i PC1, Tempe ature ( *F) : TW5. 't Test Poect Leve! (f. F.P.): 0 Condicians SDA:novi v,SDB: Moving CA: Moving Other (Srweify): (Actual) CB:McVi $ CC:N.,ving CD:.Yoving Be .2w Nuc bar C,cating Gate, ce Test Perforued: . s (, - i-97 })o+3 Meas ' irweter (Der, iption) ITotal; Int W rth of All 'e ks - Rod Swap . IV Test Moarured Valae Results - ITotal
- E W fO*
Design Valre (Act'ual Con 11 ITotal = 5 ?._ 3 2. di 52.3 fum Design Valsa ITotal = 32F> t 323 pcm (3esign Cond) Reference I NE Technical Rep 6tv No. $76 '/EP-FRD T6A,
- lNFO-TI-3.2A I
!f Design Tolerance ls bxceeded; SNSOC V
W.11 ovaluate_ impa!:t of tes2 result on FSAR/ Tech $pec safety analys .s . . GNSOC may specify that Acceptance add:.tional tascing be perfarmed. Criteria - Reference VEP FRD 36A Design Tolerance is uit VI
- __.EIES _ NO Acceptance Criteria is met : M ES NO Comments
[ ei[ > ' Completed By: -
#fdb 7' n ..
. Evaluatad By:
I l Test Engineer Recommended for Approval By : C u.rf ! t N'F0 Engineer , A,12 1-
q l-yg ggy
*j9 <
i' , e+ y NORTH ANNA POWEN STATION U$1T 1 CYCLE 7 STARTUP PHYSICS TEST. RESULTS AND EVALUATION SHEET
, I j Test Description t!/D Flux Map - Low' power Re ference - [ Proc; No ./ Sectiori: 1-PT-21.1 Sequence Step No: #/
- II '
Bank: Posit 1/5s '(? teps) ] RCS Temperature (*F):T II REF
.- Test Concitions: SSA: 226 SC3: 225- CA: 228 fPowerLevel(%F.P.): <50 (Design)
Other (specify) c CW . 22: CC . 226 CD:
- Must have 2 38 thimbles lIf Bank Posicfons (Steps) RCS Temperature (*F): TREF Test . - -
Conditiens Power Level (% F.P.): 2. 6. 5~
' SDA: 228 SDG: 228 CA: 228 Other (Specify):
( Ac t e.a) ) CB : 228" CC : d28 CD: lSS 3,g 4 Date/Th o Test;' 7 /s/87 Perforeed: ;757 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV RADIAL Meas Pa ameterj-ASSY PWR RISE HOT FLUX HOT, POWER TILT (Description)-)
- DIFF PEAKING CHAN FACT CHAN FACT RATIO FACTOR j (M-P)/P F-dH(N) F-Q(T) QPTR F-XY G.7 % G<ros P -. {
Measured Value " I.517 2. I 5' 7 1.005- l' b d Test b'"*M'b
~
Results o','{ 3 . Design Value a *
- a "
(Design Conds) I.N..'.C's NA NA 51.02 NA
~. WC AP - 7905 Reference WCAP-7905 i
REV.1 NONE NONE REV.1 l NONE V FSAR/ Tech Spec NONE i""*"""" 4'"" Acceptance - NA **
-}
Criteria Reference NONE TS 3.2.3 l TS 3.2.2 TS 3.2.4 TS 4.2.2 e Design Tolerance is met : / YES - NO Acceptance Criteria is met : YES Z NO # VI Cuments
- As Required
** 5 1.71 rodded, s 1.64 unrodded from 15% to 36% and'60% to 85%, -
5 L 62 unrodded from 36% tc 60%, excepting top and bottom 15*. and grid locations. l: Completed By: - '1 Test Er.gineer Evaluated By: 'h I r va y : [. hTO Engineer
#~ Th e +e s t res u;lts - cu e acceff ale os ludi coJ*A byAl4,A%
Powe< Sh+% b.e v;&%, b. e < + s4 , T 7 - 7I 3 .
' A. 3
[ __ -
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description : M/D Flux Map - At Power Reference Proc No / Section: 1-PT-21.1 Sequence Step No: 4 3 II Bank Positions (Steps) RCS Temperature (*F):T II Test REF Conditions Power Level (% F.P.): ~50 SDA: 228 SDB: 228 CA: 228 Other (specify) (Design) CB : 228 CC : 228 CD:
- Must have 2 38 chimbles III Bank Positions (Steps) RCS Temperature (*F): Teen Test Conditions Power Level (% F.P.): 49.0 SDA: 228 SDB: 228 CA: 228 Other (Specify):
(Actual) CB : 228 CC': 228 CD: 17 9 4 / thimbles Date/ Time Test: Performed: 7/0/F7 ocoo MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RADIAL RISE HOT FLUX HOT POWER TILT (Description) % DIFF CHAN FACT CHAN FACT RATIO PEAKING FACTOR (M-P)/P F-dH(N) F-Q(T) QPTR F-XY L3% bP,3 t 5 Measured Value I' ' 7 Test * ) 476 2.Iof /,007 l.763 Results %3% b[%'7 (rodd ech Design Value l ,'* l" l, " l (Design Conds) u, "=.
- NA NA $1.02 NA WCAP-7905 Reference WCAP-7905 REV.1 NONE NONE REV.1 NONE V
,gm....m FSAR/ Tech Spec NONE i"' * " " "
hI,h' sam Acceptance NA ** Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 TS 4.2.2 Design Tolerance is met : _,YES NO Acceptance Criteria is met : __ YES / NO #
.. yr Comments
- As Required
$ 1.71* rodded, 5 1.64 unrodded from 15% to 36% and 60% to 85%,
$ 1.62 unrodded from 36% to 60%, excepting top and bottom 15%
and grid locations. Completed By: f/ dbl Test fngineer Evaluated By: ea s1 Recommended for Approval By : C- . h70 Engineer TLe tes+ results a re etecepM ie. a s iwdice W b y A/o <+L Anu fo w ee Sin % bevia% oct A/.. 87-720. A.14
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description : M/D Flux Map - NI Calibration Reference Proc No / Section: 1-PT-22.2 Sequence Step No: 4 Y II Bank Positions (Steps) RCS Temperature (*F): TREF *1 Test Conditions Power Level (% F.P.): 5 85 SDA: 228 SDB: 228 CA: 228 other (specify): ** (Design) CB : 228 CC : 228 CD:
- III Bank Positions (Steps) RCS Temperature (*F): Tee, Test Conditions Power Level (% F.P.): Fr. o SDA: 228 SDB: 228 CA: 228 Other (Specify):
(Actual) CB : 228 CC : 228 CD: Zog 4'f t h .% b le s Date/ Time Test: 7/13 /F7 Performed: o 4f.S o MAX REL NUC ENTRAL TOTAL HEAT QUADRANT RADIAL IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT PEAKING (Description) *'. DIFF CHAN FACT CHAN FACT RATIO l FACTOR l (M-P)/P F-dH(N) F-Q(T) QPTR F-XY 3.4 */. fw Pus Measured Value * '" 3 l,'f12. / , S' '? 4 l.OOG l,537 Test 3M* f'du* Results * '# Design Value ' 'C
, ',' '. l l (Design Conds) < '. " ar a> NA NA 51.02 NA VCAP-7905 WCAP-7905 t Reference REV.1 NONE NONE REV.1 NONE V FSAR/ Tech Spec NONE 'b'"'**'
Acceptance NA *** Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 TS 4.2.2 Design Tolerance is met : __/_ S__ NO Acceptance Criteria is met : YES NO VI Comments
- As Required
** Must have at least 38 thimbles for a full-core flux map, or at least 16 chimbles for a quarter-core flux map.
1.71 rodded, s 1.64 unrodded from 15% to 36% and 60% to 85%, 5 1.62 unrodded from 36% to 60%, excepting top and bottom 15% and grid locations. Completed By: Evaluated By: - Test Engineer Recommended for Approval By : C v'-1 NTO Engineer __ A.15
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description : M/D Flux Map - NI Calibration Reference Proc No / Section: 1-PT-22.2 Sequence Step No: %5~ II Bank Positions (Steps) RCS Temperature (*F):T Test REF t1 Conditions SDA: 228 SDB: 228 CA: 228 Power Level-(% F.P.): 5 85 (Design) Other (specify): ** CB : 228 CC : 228 CD:
- III Bank Positions (Steps) RCS Temperature (*F): T~t tf Test Conditions SDA: 228 SDB: 228 CA: 228 Power Level (% F.P.): 75.0 (Actual) Other (Specify):
CB : 228 CC : 228 CD: 195 gl #9;wn Date/ Time Test: 7/I3l87 Performed: O '13 o Gua r k'- CoM Rux AA*f MAX. REL IV NUC Moss Parameter ASSY PWR RISEENTRAL HOT TOTAL HEAT QUADRANTRADIAL FLUX HOT l (Description) % DIFF CHAN FACT POWER TILT PEAKING CHAN FACT RATIO FACTOR (M P)/P F-dH(N) F-Q(T) QPTR F-XY I.4% W Pps, Measured Value = o. w 1 Test Pu M M g d i M f Results " # Design Value l " l" ',' l l l (Design Conds) ". "- w NA NA 51.02 NA WCAP-7905 Reference REV.1 NONE WCAP-7905 SONE REV.1 NONE V FSAR/ Tech Spec Acceptance NONE
'b '"" ' * *' ***
NA Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 TS 4.2.2 Design Tolerance is met : S NO Acceptance Criteria is met : _ YES VI _NO Comments
- As Required
** Must have at least at
***5 least 16 thimbles for a quarter-core flux map.38 thimbles for a full-co 1.71 rodded, s 1.64 unrodded from 15% to 36% and 60% to 85%,
5 1.62 and unrodded grid from 36% to 60%, excepting top and bottom 15% locations. Completed By: Test Engineer Evaluated By: - Recommended for 4 Approval By :_ 6. d-1 STO Engineer Tkese pocome+e<5 ore not ver;Oe.l ust,,g a p or+vd ce , e rop ob fatuJ 4- Nr calibrah. A.16
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET j I Test Description : M/D Flux Map - NI Calibration i Reference Proc No / Section: 1-PT-22.2 Sequence Step No: W, II Bank Positions (Steps) RCS Temperature (*F):T II REF Test Conditions Power Level (% F.P.): 5 85 SDA: 228 SDB: 228 CA: 228 Other (specify): ** (Design) CB : 228 CC : 228 CD:
- i III Bank Positions (Steps) RCS Temperature (*F): Tgyc Test Power Level (% F.P.): gs, o {
Conditions SDA: 228, SDB: 228 CA: 228 Other (Specify): (Actual) CB : 228 CC : 228 CD : 22.5" 2; n; w ,3 Date/ Time Test: 7/n/77 Q ud +ee- coM Flux Afeg Performed: 15'M MAX. REL NUC ENTHAL TOTAL HEAT QUADKANT IV Meas Parameter ASSY PWR RISE HOT RADIAL FLUX HOT, POWER TILT (Description) % DIFF CHAN FACT CHAN FACT RATIO PEAKINO FACTOR (M-P)/P F-dH(N) F-Q(T) QPTR F-AT I4*/. % Pgz. Test Measured Value ,,g hp [ A//}1 A d 1 i
= o,3c Results ,
Design Value l ,7 l"l' j ll (Design Conds) e. " + + NA NA $1.02 NA WCAP-7905 Reference WCAP-7905 REV.1 NONE NONE REV.1 NONE V FSAR/ Tech Spec NONE 4'" "'*" Acceptance NA *** Criteria Reference NONE TS 3.2.3 TS 3.2.2
. TS 3.2.4 TS 4.2.2 Design Tolerance is met : YES NO Acceptance Criteria is met : /YES NO VI Comments
- As Required
** Must have at least 38 thimbles for a full-core flux map, or
***5 at least 16 thimbles for a quarter-core flux map.
1.71 rodded, s 1.64 unrodded from 15% to 36% and 60% to 85%, sand 1.62 unrodded from 36% to 60%, excepting top and bottom 15% grid locations, Completed By: ' VI Test Engineer Evaluated By: f* 0 Recommended for Approval By : C d.1 g NFO Engineer Thes e fo ra we + cts a re as+ veriDed usisy a p,+;o f. c.o r e map obtaNetc for A/I ca li b re +im . A .17
NORTH ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Description : M/D Flux Map - EFP, ARO Reference _ Proc No / Section: 1-PT-21.1 Sequence Step No: 47 II Bank Positions (Steps) RCS Temperature (*F): TREF *1 Test Power Level (% F.P.): 95 5 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): (Design) CB : 228 CC : 228 CD:
- Must have 2 38 thimbles III Bank Positions (Steps) RCS Temperature (*F): Terr Test Power Level (% F.P.): 97 3 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):
(Actual) CB : 228 CC : 228 CD: 22.7 3 9 g,a fe3 Date/ Time Test: 7//Y/77 Performed: 0730 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT RADIAL IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT PEAKING (Description) % DIFF CHAN FACT CHAN FACT RATIO FACTOR (M-P)/P F-dH(N) F-Q(T) QPTR F-XY
- 4. 3 */. f e .-
Measured Value 6"" l.3 9 8 l.7FG l.005' l. S (, 7 Test 9. '3 % f. - Results p,y , o ,3, Design t,alue ,, (Design Conds) c e,34..y. g, ,, ,wa
,,, NA NA 51.02 NA WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REV.1 NONE V FSAR/ Tech Spec NONE -' b" " '"" NA **
Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 T6 4.2.2 Design Tolerance is met : ! YES NO Acceptance Criteria is met : __/YES _ _.N0 VI Comments
- As Required
** 5 1.71 redded, 5 1.64 unrodded from 15% to 36% and 60% to 85%,
5 1.62 unrodded from 36% to 60%, excepting top and bottom 15% and grid locations. f I Completed By: ' Evaluated By: Test Engineer Recommended for j-Approval By : hTO Engineer A.18 - - -- I
,l .. . . . .. . .. . .. .. .. . . . . . . :- ... _ .. . . . . VIHOINIAJLECTHIC AND POWEH COh!PANY
' n te n non a, Vi nc ia:A 20261 W. L. STH WART YtCE ISBEHlD8NT Nt-clean Ore MATIONS September 11, 1987 United States Nuclear Regulatory Commission Serial No. 87-525 Attention: Document Control Desk NOD:CAF Washington, D.C. 20555 . Docket No. 50-338 License No. NPF-4 Centlemen:
1 VIRGINIA ELECTRIC AND POWER COMPANY I NOR7H ANNA POWER STATION UNIT 1 CYCLE 7 STARTUP PHYSICS TESTS REPORT For your information, enclosed is one copy of the Virginia Electric and Power Company Topical Report VP-NOS-34, " North Anna Unit 1, Cycic 7 Startup Physics Tests Report." Should you have any questions, please contact us. 1 Very truly yours, W. L. Stewart i Enclosure cc: U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, GA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector : North Anna Power Station ! ZEL6 i- I( L__-- _ -- - - _ - - - _ - - - - - _ - . - - _ - - _ - _ - .
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