ML20149H894: Difference between revisions
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| number = ML20149H894 | | number = ML20149H894 | ||
| issue date = 12/31/1994 | | issue date = 12/31/1994 | ||
| title = Cycle 11 Startup Physics Tests Rept. W/ | | title = Cycle 11 Startup Physics Tests Rept. W/ | ||
| author name = Main A, Miller W, Nicholson A | | author name = Main A, Miller W, Nicholson A | ||
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | ||
| Line 11: | Line 11: | ||
| contact person = | | contact person = | ||
| document report number = 94-719, NE-1000, NE-1000-R, NE-1000-R00, NUDOCS 9412300246 | | document report number = 94-719, NE-1000, NE-1000-R, NE-1000-R00, NUDOCS 9412300246 | ||
| title reference date = 12-27-1994 | |||
| document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST REPORT | | document type = TECHNICAL SPECIFICATIONS & TEST REPORTS, TEST REPORT | ||
| page count = 60 | | page count = 60 | ||
Latest revision as of 14:13, 11 December 2021
| ML20149H894 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1994 |
| From: | Main A, Miller W, Nicholson A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-719, NE-1000, NE-1000-R, NE-1000-R00, NUDOCS 9412300246 | |
| Download: ML20149H894 (60) | |
Text
{{#Wiki_filter:1 7 VINGINIA ELECTHIC AND POWER COMPANY Iticnwoxo, Vino NIA 23861 December 27, 1994 i l l United States Nuclear Regulatory Commission Serial No. 94-719 - Attention: Document Control Desk NL&P/GSS RO Washington, D.C. 20555 Docket Nos. 50-338 Ucense Nos. NPF-4 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 f,XfdE 11 STARTUP PHYSICS TESTS REPORT As required by North Anna Technical Specification 6.9.1, enclosed are five copies of the Virginia Electric and Power Company Technical Report NE-1000, " North Anna Unit 1, Cycle 11 Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after initial criticality of Cycle 11 on October 8. 1994. The results of the physics tests were within required design tolerances and applicable Technical Specification limits. Very truly yours, M. L. Bowling, Manager Nuclear Licensing and Programs Enclosures cc: U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station 9412300246 941209 - PDR ADOCK 03000338 P PDR l1 -
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g g g 'g e g i'% orth anna Unit 1 Cycle 11 J. . .= :_ =:: StartuP Physics: Tests Report Nuclear Analysis and Fuel Nuclear Engineering Services December,1994
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VTRGINIA POWER
t
. 4 TECHNICAL REPORT NE-1000 - REV. 0 NORTH ANNA UNIT 1, CYCLE 11 STARTUP PHYSICS TESTS REPORT l
l l NUCLEAR ANALYSIS AND FUEL l NUCLEAR ENGINEERING SERVICES VIRGINIA POWER DECEMBER 1994 l PREPARED BY: < - IA - @~7 '9Y W. S. MILLER Date REVIEWED BY: d 1 D d i d FJ A. H. Nicholson Dr.te REVIEWED BY: /E-84Y
'd. P. Main Dute APPROVED BY:
/2/y/y D. Dziadosz U Date QA Category: Nuclear Safety Related Keywords: NIC11, Stgrtup
L CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which thez 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 l 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 l 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. NE-1000 N1C11 Startup Physics Tests Report Page 1 of 57 E - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
i . t TABLE OF CONTENTS PAGE Cla ss ificat ion / Dis claimer. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Ta b l e o f C o n t e n t s . .,. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 List of Tab 1es.......................................... . 3 List of Figures......................................... 4 Preface................................................. 5 Section 1 Introduction and Summary................... 7-Section 2 Control Rod Drop Time Measurements......... 17 Section 3 Control Rod Bank Worth Measurements........ 22 Section 4 Boron Endpoint and Worth Heasurements...... 27 Section 5 Temperature Coefficient Measurement........ 31 Section 6 Power Distribution Measurements............ 33 Section 7 References................................. 40 APPENDIX Startup Physics Test Results and Evaluation Sheets........................ 41 NE-1000 N1C11 Startup Physics Tests Report Page 2 of 57
S LIST OF TABLES TABLE TITLE PAGE 1.1 Chronology of Tests................................... 11 2.1 Ho t R od D r op Kf m e S u m m a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 3.1 Control Rod Bank Worth Summa ry. . . . . . . . . . . . . . . . . . . . . . . . 24 4.1 Boron Endpoints Summary............................... 29 5.1 Isothermal Temperature Coefficient Summary............ 32 6.1 Inco re Flux Map Summa ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35
, y.
6.2 Comparison of Measured Power Distribution Parameters \ With Their Core Operating Limits...................... '36
\
\
\
NE-1000 N1C11 Startup Physics Tests Report Page 3 of 57
t LIST OF FIGURES FIGURE TITLE PAGE 1.1 Core Loading Map......................................... 12 1.2 Beginning of Qycle Fuel Assembly Burnups . . . . . . . . . . . . . . . . . 13 1.3 Available Incore Moveable Detector Locations............. 14 1.4 Assembly Insert Locations................................ 15 1.5 Control Rod Locations.................................... 16 2.1 Typical Rod Drop Trace................................... 20 2.2 Rod Drop Time - Hot Full Flow Conditions................. 21 3.1 Control Bank B Integral Rod Worth - HZP.................. 25 3.2 Control Bank B Dif ferential Rod Worth - HZP. . . . . . . . . . . . . . 26 4.1 Boron Worth Coefficient.................................. 30 6.1 Assemblywise Power Distribution - 30% Power.............. 37 6.2 Assemblywise Power Distribution - 74% Power.............. 38 6.3 Assemblywise Power Distribution - 100% Power............. 39 NE-1000 NIC11 Startup Physics Tests Report Page 4 of 57
t v PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the North Anna 1, Cycle 11 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard l testing 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 a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results. The North Anna 1, Cycle 11 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values (at design conditions) of the measured parameters were completed prior to the startup physics testing. The entries for the design value.. were based on the calculations performed i by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1. During the tests, the data sheets were used as guidelines both l l to verify that the proper test conditions were met and to facilitate the NE-1000 NIC11 Startup Physics Tests Report Page 5 of 57
4 l preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests.
=
f NE-1000 NIC11 Startup Physics Tests Report Page 6 of 57
SECTION 1 INTRODUCTION AND
SUMMARY
On September 9,,1994 Unit No. 1 of the North Anna Power Station shutdown for its tenth refueling. During this shutdown, 81 of the 157 fuel assemblies in the core were replaced with 64 fresh fuel assemblies, 1 once-burned fuel assembly, and 16 twice-burned fuel assemblies. The eleventh cycle core consists of 10 sub-batches of fuel: four once-burned batches, three from Cycle 10 (batches N2/11A, 12A, and 12B) and one from North Anna 2 Cycle 8 (batch N2/10B);- four twice-burned batches, one from Cycles 7 and 8 (batch 9A), two from Cycles 8 and 9 (batches N2/9B and 10B), and one from Cycles 9 and 10 (batch 11A); and two fresh batches (batches 13A and 13B). Batches N1/11, N1/12. N2/10, and N2/11 have top and bottom grids of Inconel-718 while the inner six grids are made of Zircaloy-4. Batch N1/13 has top and bottom grids of Inconel-718, six inner grids made of ZIRLO (ZIRLO provides improved corrosion resistance and dimensional stability under irradiation relative to 71rcaloy-4 components), and one Inconel-718 protective grid placed below the fuel and above the bottom nozzle for debris resistance. All other batches are composed of 8 Inconel-718 grids. Cycle 11, similar to Cyc1c 10, incorporated the burnable poison rod design made of B 4 C in Alumina, which is available in various enrichments of B 4C. There are no thimble plugging devices inserted in N1C11. Twenty-four peripheral assemblies have baffle clips mounted on them to NE-1000 NIC11 Startup Physics Tests Report Page 7 of 57
help protect against baffle jetting degradation. Reference 1 provides a more detailed description of the Cycle 11 core. The core loading pattern and the desigo parameters for each sub-batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2. The available incore moveable detector locations used for the BOC flux map analyses are idengified in Figure 1.3. Figure 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 11, and Figure 1.5 Jdentifies the location and number of control rods in the Cycle 11 core. On October 8, 1994 at 2225, the Cycle 11 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 i follows:
- 1. The measured drop time of each control rod was within the 2.7 second limit of Technical Specification 3.1.3.4.
- 2. Individual control rod bank worths were measured using. the rod swap technique *** and the results were within 4.6% of the design predictions. .The sum of the individual measured control rod bank worths was within 1.9% of the design prediction. These results are within the design tolerance of 115% for individual bank worths (110% for the rod sw. p reference bank worth) and the design tolerance of 110% for the sum of the individual control rod bank worths.
- 3. Measured critical boron concentrations for two control bank configurations were within 7 ppm of the design predictions. These NE-1000 NIC11 Startup Physics Tests Report P(ige 8 of 57
results were within the design tolerances and also met the Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 1% Ak/k of the design prediction.
- 4. The boron wofth coefficient measurement was within 1.0% of the design prediction, which is within the design tolerance of :510%.
- 5. The measured isothermal temperature coefficient (ITC) for the all-rods-out (AR0) configuration was within 0.74 pcm/'F of the l
design prediction. This result is within the design tolerance of 3 pcm/'F. The measured ITC of -2.87 pcm/'F meets the Core Operating Limits Report (COLR) 2.1.1 criterion that the moderator temperature coefficient (MTC) be less than or equal to +6.0 pcm/'F. When the Doppler temperature coefficient and a 0.5 pcm/'F uncertainty are accounted for in the MTC limit, the MTC requirement is satisfied as long as the ITC is less than or equal to +3.75 pcm/'F.
- 6. Mode 1 (see Reference 4) core power distributions were within established design tolerances. Generally, the measured core power distribution was within 1.3% of the design predictions.
The heat flux hot cham 31 factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of COLR Sections 2.5.1 and 2.6, respectively. l NE-1000 N1C11 Startup Physics Tests Report Page 9 of 57
4 In summary, all startup physics test results were acceptable. Detailed results, specific design tolerances and acceptance criteria for-each measurement are presented in the following sections of this report. i NE-1000 NIC11 Startup Physics Tests Report Page 10 of 57
4 Table 1.1 NORTH ANNA 1 - CYCLE 11 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test
- Date Time Power Procedure Hot Rod Drep - Hot Full Flow 10/08/94 0549 HSD 1-PT-17.2 '
Zero Power Testing Range 10/08/94 2354 HZP 1-PT-94.0 Reactivity Computer Checkout 10/09/94 0057 HZP 1-PT-94.0 Temperature Coefficient - ARO 10/09/94 0512 HZP 1-PT-94.0 Boron Endpoint - ARO 10/09/94 0515 HZP 1-PT-94.0 Bank B Worth 10/09/94 0649 HZP 1-PT-94.0 Boron Endpoint - B in 10/09/94 1000 HZP 1-PT-94.0 Bank D Worth - Rod Swap 10/09/94 1047 HZP 1-PT-94.0 Bank C Worth - Rod Swap 10/09/94 1140 HZP 1-PT-94.0 Bank A Worth - Rod Swap 10/09/94 1210 HZP 1-PT-94.0 Bank SB Worth - Rod Swap 10/09/94 1233 HZP 1-PT-94.0 Bank SA Worth - Rod Swap 10/09/94 1309 HZP 1-PT-94.0 Flux Map - 30% Power 10/10/94 1048 30% 1-PT-21.1 Peaking Factor Verification 1-PT-21.2
& Power Range Calibration 1-PT-22.4 Flux Map - 74% Power 10/12/94 1641 74% 1-PT-21.1 Peaking Factor Verification 1-PT-21.2
& Power Range Calibration 1-PT-22.4 Flux Map - 100% Power 10/31/94 1148 100% 1-PT-21.1 Peaking Factor Verification 1-PT-21.2
& Power Range Calibration
- 1-PT-22.4
- Power range calibration calculation was performed which verified that the existing calibration was satisfactory.
I NE-1000 NIC11 Startup Physics Tests Report Page 11 of
l - d Figure 1.1 NORTil ANNA UNIT 1 - CYCLE 11 CORE LOADING HAP M C F E O C s A a P N N L a J 1 11A i 12A sta l 3 i 1A6 l es9 , 2A7 1 I I _;I I In2/11al 9a i 13e i tZs i 13a l Sa IM2/ttal 2 l eL6 l J22 l 5C1 l es3 1I 6C2 1I J34 -1i eL4 l1 I I I .I tsa i los l ( tes i 13s i 136 1 12s i 13a l 12s I tas : 4c7 I asa 3 I s6e 1 4c4 1 Sca1 i sat 1I set i 12s1 I Iace l I i 1 tsa 1 ala, h les i I tes i 12a i nsa 1 als i 13A i sla i tsa i tra sc6 I 1:5 ,1 ase 1 6 I R47 1 2:3 I scs 1 3s9 li sce 1 I Ist I ioc2 I Iss3 l 1 i I i I .I IN2/ttAl 13a i 13s 1 12s j ISA i 12A j 134 4 12A i 13A i 12s i 13a i 15s (N2/11al 5 i eL3 I sc3 I ses lI saa II ac9 i 1 ist 1 l 2c7i I ist iI 2c5 1 I 5:e iI Sco i 2c9 Ii ett 1I 1 1 l .I i *a i ass I 12s 4 134 l 12A I isA i Ze i 13A i 12A I asa i 12s I asa l 9A i 6 l JZ7 i Sc9 1 3s4 1 2C3 i Zse i oc6-1 l_f 586 1 1CFI l es3I l IC3 I1 3:3 ii SC9 1l J32 l 1 l 1 (_
-l 1 1 i 13A 1 32A I asa i 12e i 13s I laa i 1 tia i tsa i its I asa i 12A i sia i tZs i Za i als . ect i est 1 2c2 l sat i isee i i144 1I 7 i 1At i 4c6 I sat iI ocs Ii es6 lI its i iess i isat i eso I , I i l i
i I i tra i 12s i 134 1 12A I ecs asa i 12s i its tw2/ teal als J 12s i 13a i 12A i 13e i 12s 6 nta 1 a i ts? I so$ Ix I tot I sat I est 1 Y32 i1 Zs6l I tal Ii eca Ii oss Ii sc4 L eso l.I est II I l I l _I i i l tsa i stA I i Ata i 138 l als i 134 t 124 1 13a i 12s i 12s i als i 13A i sta i 134 l 12s 9 i 1A1 i sc7 ll 464 iI act i 186 Ii 2ct ii saa Ii est i isaa i l_tct i 2s4 i Ic6 1 I i ssel 11 Sc3 1 l .l oA6 Il I i l_ l19A JiaI iassecsi i12s 482i I13A sca i1ala 2s2 i 13A I teai i12s es6i i13A Ic4 i1sta cari i134 ece1i alssat ii 13a ecs i1J2f, 9A ii 18 I l l 1 l i I i~~ 1I I I i l_ IM2/ttal'lls i tsa i als i tsa i 12A 1 13A i 12a i 134 l 12s i 138 l t3s IM2/ del 11 i ets I oc2 I 6ct I l$ss I Iac9 1i 1s4 iI tco Il isa 1i 2c6 il esa ii scs Ii sca ii els 1l 1 I i l~les i 12A i 136 1 als 1 13A i 12A i 13A i 12s I las i 12a a les i 12 I ns9 i osa 1 3c7 I1 2s9I 1 2c4I I las l. I oc7 I14s9 Ii sc2 1i Iso Il s52 11 I ll i los I tas i 13s I its I als i 32s i 13s i 13s in2/9s I 13 i a64 i sce i see iI ss9 ii sc! l i3s? I i6ce 1i 4cs ll X44 l4 i l 1 lN2/11Al 94 l 13a i 12s I ass 1 9A lM2/11A1 14 i OL1 8 Joe 1 4c3 l 2as I1 3c6 Il JIS Ii eL7 1l 1 I l i i ita i lla I tia l 15 i 1*=> sATCH I 1 A2 l es4 l e43 1 l l l l l 1.-> AS$tMSLY 10 6 i FtKL AS$fMsLY DESIGN PARAMFfERS Sus-sAlcH IOs 114 12A 12s 13A 13s N2/9s M2/tes N2/ala 94 4.eo65 4.e036 4.2s52 4.ees2 4.ro97 JMIflat ENRICHMENT 4.0o57 4.2e51 4.st$5 3.7944 4. Boo? (W/0 U-2351 26e92 22ss5 0 0 36315 21397 26e53 39t22 36795 Sara 3 sURNUP Af s0C 11 (MWD /Miul 17s17 17m17 17al? 17ml? 17 17 17st? ASSEMalY TYPE 17m17 17st? 17 17 17ml? 7 a 24 36 !s 36 NUMsER OF ASSEMlLIES 1 1 a a 264 264 264 264 264 264 FUEL RODS PER aSSEMsLY 2H 26 264 26 NE-1000 N1C11 Startup Physics Tests Report Page 12 of 57
l l . Figure 1.2 NORTH ANNA UNIT 1 - CYCLE 11 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R P N N L K J H C F E D C 8 & l 1A6 i est i 2A7 l 1 3a1638 2677sl 39eest 1 I I l I l eL6 l s22 i Sc1 i esa i 6c2 1 J34 i eL4 I i 2655el 186721 el to76sl el 392471 26%41 2 1 i 1 I I I I i b see 1 4c4 i Sca i Sal i 4c1 1 2ar i sce i 4c7 4 m5a ' l 361391 el el 2332sl el 243768 el el 364e51 3 l l l _ _l 1 1 1 1 I I l a47 1 ras 1 3c5 1 3s3 I sce I las i ec2 i 5s3 I sc6 1 las . I au i 1 379058 2591st el 2545al el 2M 271 el 251 %I el 260111 359451 4 I I I i 1 1 1 1 I I l I l ets l 6c3 i Sc3 i Saa 1 ac9 l1 1 1 2c7 1 152 I tc5 I see 1 4ce i 2c9 i eL2 l l 26s691 el el 206478 el 25775l el 25%91 el 21eul el el 256341 5 l 1 1 1 1 I l l 1 I l_t ! I I J27 i Sc9 i ss6 l 2c3 1 2se i sca i sse i act i oss l Ac3 1 3s3 i sc9 I J32 I l 391511 el 253381 el 257s11 el 249538 el 26e17) el 25512l el 3a4741 6 l i l l l l l l 1 I l l l l l 1A1 l 4c4 1 3s4 i Oc5 i es6 l ICS l 4ss a 552 1 6a4 l eC1 l es2 1 2C2 1 3s2 i SCs i 1A8 1 i I 3a92el el 239741 el 263561 el 194441 197e44 2 ele 61 el 2636el el 237641 el 382 cal 7 l t I i l i I l l i I I I i l i i i ist i 1s5 i Sci i ts! I ocs 1 5:1 1 4s1 1 v32 1 2s6 1 ts5 i sca i oss i 4c4 1 4se i est I i 267371 214531 el 259371 of 25e391 2e8231 233971 201628 24a718 el 259478 el 216a68 264451 a i i i l I i l ___. _1 1 I i 1 .I l __ I I i 1A3 i sc7 1 4s4 I ac2 1 1s6 1 2c1 I asa I es7 8 3ae l Ica 1 2s4 i ac6 1 5s4 i Sc3 l eA6 4 i sa7901 el 232328 el 253451 el 264 %I 19a761 1955el el 252571 el 245761 el 391%i 9 I i I I 1 I I I I I i l i I I I I Jia 1 =c9 i est I aca i tat i 2ca i nse I act i est I ac4 15s1 1 4c5 l Jza i l 39M91 el 247181 el 267511 el 2473el el 26s15l el 249331 el 3a7941 le i 1 1 I I l I I i i i l i I I sta 1 4c2 1 6c1 1 5s5 I oc, i 164 l 2ce i Isa i 2c6 3 4sa i sc5 I sca I sts i I 26e231 el el 216671 el 2570sl el 263291 el 2147sl el el 262538 11 l i 1 1 1 I I l i l I i i l i s59 I osa 1 sc7 I ts9 8 2c4 l las I sc1 8 4s9 l Sc2 I las I ast I i 36%el 267a61 el 25e131 el 268251 el 256641 el 261651 372541 12 I I I 1 1 1 1 I I I I I I a64 i Sc4 I sce 1 5s, I sc2 1 3a7 1 ace i sca I x64 I l 371531 el el 241eal el 233121 el el 363351 13 4 I I i 1 l I 1.__ _ I I l ell l Je6 1 4c3 l 2s4 1 3C6 l J15 l eL7 l l 257241 39s421 el te9961 el 392311 256e71 14 I I I I I i 1 1 i lat i es* I eAs l l l--> AsstMsLY 10 1 3asa51 257421 39e331 15 l l--> ASSEMsLY sURMUP (MWO/MTU) l 4 l l ~~ l 1
~~
NE-1000 NIC11 Startup Physics Tests Report Page 13 of 57
Figure 1.3 NORTH ANNA UNIT 1 - CYCLE 11 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS E J M C F E D C B A R P N M L I I i 1 1 1 Mo 1 i 1 1 1 I l 1 i i l i 1 aa i l 1 1 1 I I I Mo 1 1 2 1% ! i l i l i I I I I I as i 1 1 I I I I Mo I i i Mo i Mo I i i i MD I 3 I I I I I i 1 1 I I I I i i l I I i l I I l i 1 no 1 4 I i i Mo I i Mo l 1 1 1 I i i I I I I i l i I I I l l l 1 1 a l i i i i i l 1 I Mo I ] Mo I i l i Mo l MD I l Mo l 5 1 1 Mo i i ! I I I I I I I I I I I l i I I I i i l i i sa l i 1 I l i 1 No I i i Mo 1 I Mo 1 I I i 6 i I 1 I I I I I i i I I I i 1 1 1 1 I i 1 1 I I I i l i 1 1 I I i l l l Mo I I l l Mo I ! Mo I i i Mo i 1 Mo 1 I 7 I I I I I I I i 1 l_1 1 I I i I i I i i == 1 1 I I I I i 1 1 1 I i i Mo i I Mo I l Mo I i i i 1 Mo 1 I I Mo I Mo 1 I a i i i I i i l I I I I I I I I I I i i i i i i i i aa a i i l i I I I I I I I Mo I I l i Mo i Mo I I I i i Mo I 9 I i i i i I I I i l i I l i I I I l 6 1 i i i l i I a 1 1 I l l Mo I i I l Mo I i l i i Mo i I Mo i 18 1 1 1 I I i i i i l 1 1 I i l 1 I i l i i i l i I I I I I Mo l Mo i I I I 11 i 1 I I Mo 1 I I Mo 1 1 I i 1 l t i I I I l i I I i i i l I l 8 l I l i I I Mo I I i i Mo 1 1 1 1 I Mo l MD 1 12
- l. t l t I I i i l I i l I i i i l i i l i i i i l i Mo I no i l i 13 1 I i 1 I I I I I I I I I I i 1 1 i Mo 1 I I I Mo 1 1 1 14 I I t I I i l 1 Mo Moveable Detector I i l i a
- Not Available For Maa 1 1 Mo 1 l i 15 as - Locations Not Avallable For i l i I Flux Mapping System For Cycle 11 NE-1000 NIC11 Startup Physics Tests Report Pige t 14 of 57
, y -
Figure 1.4 NORTH ANNA UNIT 1 - CYCLE 11 ASSEMBLY INSERT LOCATIONS R P N M L K J H C F E D C 5 A 1 i i l ~ l VSDA 1 VSDA I VSDA i 1 l l I I I I I 2P l i 2P l l l l VSDA i 1 SP3338 I 89534) i VSDA I 2 m i I I I i l I I I i w I tap 1 1 2cP l 16P l p 1 j
- i i sP M 51 SP3491 1 BP3218 SP3508 SPM74 1 3 I i I i i i l i l 1 I I lop i i 24P 1 5519 1 24P 1 I 20P l I l' i l ! EP3578 1 $P3091 1 8P3141 l SPM41 l l 4 1 1 _1 l 'I I l i 1 i l i 1 1 6P i Zop i i 24P l 1 24P i i 24P 1 I top 1 4P l l l VSDA I BP%61 SP3541 1 8P3418 i BP3111 1 SP3421 1 BP3591 BP %81 VSDA 1 5 1 1 1 1 I i i l i I t 1 1 1 l l tap i l 24P i l 24P 1 I 24P l l 24P 1 1 18P l 4 l l BP3561 i SP3431 1 BP3258 8 893261 l BP3441 l BP3511 1 6 1 I t I i i i l 1 I I I I I I I 2P l I 24P I I 24P l l *P 1 1 24P 1 1 24P 1 1 2P i l l VSDA I BP3391 1 8P3128 i BP3318 i BP3051 l BP3271 i SP313l l 893351 VSDA 1 7 1 1 I I I I i 1, 1 I I I i i i l 1 1 I top i 1 24P i t *P 1 4 4P 1 1 24P 1 i ZoP 1 I I l vsoA i 1 BP3221 1 8P3141 l SP3061 i BP3071 1 BP3151 i BP3248 i VSDA l 8 1 1 i 1 l I t i I I I I I I I l 1 1 2P 1 1 24P l 8 24P 1 1 4P l 1 24P 1 1 24P l 1 2P l l 1 VSDA I BP3401 1 8P3161 i BP3321 1 BP3081 1 SP3281 l BP3174 1 SP3 MI VSDA l 9 1 1 1 1 1 1 1 1 I I I I l l I 1 l l tap l 1 24P i i 24P 1 I 24P 1 1 24P 1 1 lap 1 1 l l BP3551 I ap3458 i BP3291 i BPsiol 1 SP3461 I sP3521 I to 1 1 1 1 1 1 I I I I I i i I i 1 p i 20p I 1 24P l 1 24p i 1 24p i i top I w I I I VSDA I BP3711 aP M 31 i BP3471 1 SP318) 1 SP3481 1 BP3621 SP369) VSDA i 11 1 I l i i t t I I i i i I l i i i top I 1 24P i S$20 l 24P l i 20P l l l l t i *Pu4l l SP3191 l 893201 i SP%11 l l 12 I I l I i t i 1 I I i I i i w I nap i i 2oP i i lap i e I i l i BP372) SP354l i SP3231 1 SP3531 ap37el I is l I I l i I I t i I I I i 2P l i 2P 1 l l l V50A 1 l BP3371 l BP3381 1 VSDA i 14 l 2P - 2 suRNAsLE POISON R0o CtuSTER I 1 I l l l l l 4P - 4 suRNABLE PO! SON R00 CLUSTER l l l l 1 6P - 6 sUPNASLE POISON R00 CLUSTER 1 VSDA I VSDA l VSDA i 15 l l&P
- 18 SURNASLE POISON ROD CLUSitR I l l 1 20p - 20 BURNASLE POISON ROD CLUSTER 24P
- 24 BURNA8tE POISON ROD CLUSTER
$5mm a SECONDARY SOURCE VSDA
- VIBRATION SUPPRESSION DAMPING ASSEMBLY 4 xmP er SSnu 1 - 0 0F BP RODS or SECONDARY SOURCE ID c l
lBPest or VSDAl
- BP ASSENSLY ID or VSDA l I I
~ '
NE-1000 N1C11 Startup Physics Tests Report Page 15 of 57 - L______________________________._______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _ __
Figure 1.5 NORTH ANNA UNIT 1 - CYCLE 11 CONTROL R0D LOCATIONS R P N N L K J H G F E D C B A 180* I .. Loop C l l l l Loop B 1 Outist l l l l Inlet N-41 l
.5! l
!^ll sA l!" !l sA l!^ ! 'd l l l l N-43 3
I I I I I I I I I 1 l lC l l8 l l l lB l 1C l l 4 I I I I I I I l i I I I l i I l sa i l i l i i so i I l l 5 I I I I .I I l l 1 l i I I I IA i lB i iD I lC l lD l l8 l lA i 6 Loop C I I I l l l I I I I i l I I Loop B Inlet l l l sA 1 l l l sa I i so i I I i SA 1 1 I outlet 7 ii I I I I l I l i I I I I I I I/ 90 - El lD 1 l l lC i i l lC l l l lD 1 1/- 270* 8 I I I I I I I I I I I I I I I i 1 1 I sA i l l I s81 i sB l l l l sA 1 I l 9 I I I I i 1 1 I I I I I I I I i 1A i lB l lD l lC l 1D I IB I IA l 10 I I I I l l I 1 I I I I I I I I I I s8 i i l i i i sa 1 i I i 11 1 I I I I I I I I I I I l i I lC l l8 1 1 1 Ia l lC l l 12 1 1 I I I I I I I I 1 1 1 I I I sA I l sA i l I i 13 N-44 1 I I I I I I l l 1 N-42 I IA I ID l lA I i 14 l I I I i 1 I i Loop A
/ l i
l 1 I 1 l I
\
Loop A 15 Absorber Outlet Inlet Material I Ag-In-Cd 0* Function Number of Clusters Control Bank D 8 Control Bank C 8 Called Control Bank 8 8 North Control Bank A 8 shutdown Bank s8 8 shutdown Bank sA 8 NE-1000 N1C11 Startup Physics Tests Report Page 16 of 57
SECTION 2 CONTROL F0D DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant systen (RCS) conditions.in order to verify that the time from initiation of the rod drop to the entry of the rod into 'the dashpot was less than or equal to the maximum allowed by Technical Specification 3.1.3.4 The control rod drop times were measured in Mode 3" with the RCS Tavg above 500'F and all reactor coolant pumps operating. The rod drop times were measured by withdrawing a rod bank 229 steps and then removing the moveable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The stationary gripper coil voltage and the Individual Rod Position l Indication (IRPI) primary coil voltage signals were recorded to determine the rod drop time. This procedure was repeated for each control rod. As shown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary gripper coil fuse is removed. As the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing.
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NE-1000 NIC11 Startup Physics Tests Report Page 17 of 57
The measured drop times for each control rod are recorded on Figure 2.2. The slowest, fastest, 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 2.7 seconds with the RCS at hot, full flow conditions. These test results satisfied this limit. NE-1000 NIC11 Startup Physics Tests Report Page 18 of 57
Table 2.1 NORTil ANNA UNIT 1 - CYCLE 11 STARTUP PilYSICS TESTS IlOT ROD DROP TIME
SUMMARY
ROD DROP TIME TO DASIIPOT ENTRY
=
SLOWEST R0D FASTEST ROD AVERAGE TIME B-06 2.04 sec. C-09 1.58 sec. 1.77 sec. i l
~~ ~~
NE-1000 N1C11 Startup Physics Tests Report Pgge 19 of 57
Figure 2.1 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE-
=
Beginning Of Dashoot Bottom Of Dashoot Initiation Of Rod (Beginning Of First (Beginning Of First Drop Event Mark Downtum in Trace) Upturn in Trace)
/ \ / .
Vlll,V:,V:l,V::,{ Stationary Grioper Coil Voltage Trace
-: Rod Drop Time :
AAAAAAAAA A VVVVVVVV V x P
- VVVVVVV Vvv yn geTae SAAAAAA/ AAAAAAAAAAAAAAAAAAAAA AAAAAA AAAAAAAA vvvvvvvvuvvvvvvvvvvvvvvvvvvvevvvyvavvvvvvy, 60Hz Trace
.... y. .mu
___ ~ One Cycle ROD DROP TIME MEASUREMENT NE-1000 NIC11 Startup Physics Tests Report Page 20 of 57
9 Figure 2.2 NORTil ANNA UNIT 1 - CYCLE 11 STARTUP Pl!YSICS TESTS ROD DROP TIME - liOT FULL FLOW CONDITIONS R P N N L K J H G F E D C 8 A I i i i i l I i 1 I l i i l i i i l i a l I i 1.79 I i 1.67 I i 1.74 I I 2 9 I I I I l l 1 I i 1 1 i l i i i i l i I I i 1.72 I i 1.76 I I I i 3 I I I I i 1 i l i l i i i l l I i 1 i l i i l l 1.78 l l 1.70 l l l l 1.40 l l 1.76 l l 6 1 1 1 l 1 1 I I i 1 i i l 1 I i i i i I i i i e i i 1 i i i 1 76 i i 1 i i 1 1.76 I I I l 5 1 I l l t i I i 1 l i l i I I i 1 1 1 4 i i i l i l 1 1 1 1.68 i ! 1.s1 I i 1.73 1 I 1.74 l l 1.76 1 1 1.7s 1 I 2.e4 1 6 I i l 1 1 i l i i i i 1 1 1 1 I i i 1 1 1 1 I I I i 1 1 1 l I I I 1.76 1 1 I i 1.69 i i 1.74 I l I i 1.77 1 1 1 7 1 I I i i 1 i i i l I i l i i l i I I I I I I I I I i l I i i i l i 1.as i i l l 1.76 I I i i 1.73 1 1 1 1 1.93 I i a i l i i i 1 i I I i l i l i l I l i I I I I i l i l i I I i l i l i I i 1.as i e 1 i 1.69 i i 1.70 1 I i l 1.54 l l l 9 I i 1 I I i i l i 1 1 1 1 I i 1 l l 1 i l i i l I i i i i l i 1 1 1.74 I i 1.83 I i 1.75 1 1 1.83 I i 1.7a 1 1 1.79 I i 1.70 l le I l l l I l l l l l l 1 1 1 4 1 I l i l i i l l i i l l l l I ! l 1.85 I I 1 l t i 1.77 l l l l 11 l l t i I I I i i l I i l I I i i i i l i i i i i i i 1 1.70 1 l 1.83 l l l l 1.72 l l 1.76 1 1 12 i l l l 1 I i 1 I I I i i i I 4 i i i i l I i i l i 1.72 l i 1.74 1 1 l l 13 I I I I l I l 1 1 I i 1 i i i i i l 1 1 1.99 I I 1.7s I i 1.44 I l is
! 1 I I l 1 1 1 i i i l I i l i 15 i 1 1 i l I l X.XM l--> R00 DROP TIE TO DASHP07 ENTRY (SEC)
I 1 o NE-1000 NIC11 Startup Physics Tests Report P(1ge 21 of 57
s I SECTION 3 CONTROL R0D BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod snap technique **'. 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 11, Control Bank B was used as the reference bank. After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully inserted position with all other banks fully withdrawn and recording the core reactivity and moderator temperature. From this point, a rod swap maneuver was performed by withdrawing the teference bank several steps and then inserting one of the other control rod bsnks (i.e. , a test bank) 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 condition. This measured critical position (MCP) of the ( I reference bank with the test bank fully inserted was used to determine l NE-1000 NIC11 Startup Physics Tests Report P4ge 22 of 57
the integral reactivity worth of the test bank. The core reactivity, l moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver i l then was repeated in reverse such that the reference bank again was near l l full insertion with the test bank fully withdrawn from the core. This rod swap process was, then repeated for each of the other control and shutdown banks. , A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control
~
and shutdown banks were within the design tolerance ( 10% for the - - reference bank, 15% for test banks of worth greater than 600 pcm, and 100 pcm for test banks of worth less than or equal to 600 pcm.) The sum of the individual measured rod bank worths was within 1.% cf the design prediction. This is well within the design tolerance of 10% 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 measured rod worth values were satisfactory. NE-1000 NIC11 Startup Physics Tests Report Page 23 of 57
Table 3.1 NORTil ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
SUMMARY
l I i 1 l MEASURED PREDICTED PERCENT DIFFERENCE
- WORTH WORTH (%)
BANK (PCM) (PCM) (M-P)/P ,X 100 I B-Reference Bank 1250.0 1310.0 -4.6 ! D 978.0 '1003.7 -2.6 C 823.0 812.8 1.3 A 266.0 263.2 1.1
- I SB 1089.0 1076.9 1.1 SA 937.0 980.3 -4.4 Total Worth 5343.0 5446.9 -1.9
- Difference is less than 100 pcm.
l l l l l l l l NE-1000 NIC11 Startup Physics Tests Report Page 24 of 57
p v ,c Figure 3.1 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL R0D WORTH - HZP ALL OTHER RODS WITHDRAWN
. _ . _ . _ . _% , l .
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+- ,,si 0 40 80 120 160 200 B&NK POSITION (5 STEPS / DIVISION)
NE-1000 N1C11 Startup Physics Tests Report Page 25 of 57
]
4 Figure 3.2 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 12 ,,,,,,, ,,, ,,, , , , , , , , , , , , , , ,,,, , , ,,,, i 1 ! ! ! t i i ! ! ! ! ! i i i i ! i ! . 1 i ! ' i ! l ! l ! Iiii1 i i i i i i ee i6 i t i i i 1 { i i i jiiie 1 I i i I i} i t i .iii eiiittt i! !!iii f! i i i i i ! # !I i t! ! I III i li 1 ! Iti1 I tI i! ! I i i i i i i ! i i i I i.- IIi i iiii iI I i i I ' I I I Ii1 i i ' I i l 1i i i i! I i iiil ieiI i i I i i l I i l i ,il i ) Ii i i i t i i i l i iiil i i f l1 10 i t i i 1 l ! I I I i t[ Nii1 ! ! I I i i eii l i i i ' I i ! t I ' i
,, , , , g y3 , , , , , , , , ; , , , , , , ,
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,,,,
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i ili i i.i # 1 i i ii,ivi6 #N iiii i iiit i l i i ji > i i i i i l i i i i l l I i i i i !l $ iil\l i I p . , . ,J .,, i i i . . : ! ii iii! isii%i i i i
$ i f i i i ! f I j 4 i i i i Iii i i l ii ! l ( i I hI i \l i i i 1 ';;! i i e ' i l! i ' i i i ! ! !il Ii! I i ! !!t i\ l1i i p i i , , i ,
gli i i i ! i i , i ! i! ai! i i i
- i 43 !! !!
Z r ! , i i $ ff i i r i i r i ! i i t i i i ! i i ! it i i i +i (!ii! i S$ ' ' ' 1 i i /t i i 11 : !i! i i ' i i tii! IiI' t i tiiii g i 4 t ;i t i i i i i > i i i i i i> t i - i iii ie i i i _ i , i i i fiiiiiii e i i i , , . , i i , , i i . . i iii \,iii C eit s i - i /* ! i i i! , i t i , t lii >
!! !: , i!, i\' i ! i i i i i i i fii1 t ii i i i i i i iii i i i !# i i i j\iit e i i i e i j i,) iii i i i eiI e i . i 6i i i !ie i ) i .\ i i j i i e i (f !! i .>i .
!iie i i i !!!i! i i ti! !i # it! !
I g! :/ ;}{ t ii i i 6 ' i i i i i !I i l I i i 1 i i IQ! i
, i .
, i , ii . , i , i , ,iiii i i i i i ii ii1,i
, i i , . , , , . , , , i ii , , , s , iigii 2 , , j , , , , , ,,,,, , , , 3 , ; , 3 ;g 3 ,
4 i : /~ 61 ' i i 4 l l !) I il i ! . I i i ! l i ! \l ! i i : i * ' 'i
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& , i . . . 1i ...I . . 6 , . i l!. i l l . 4 e i e ii i i iii{1 0 40 80 120 160 200 BANK POSITION (5 STEPS / DIVISION)
NE-1000 N1C11 Startup Physics Tests Report Page 26 of 57
4
, 5 ,
a SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint I With the reactor' critical at hot zero power, reactor coolant system-(RCS) boron concentrations were measured at. selected' rod ' bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position and moderator temperature, if necessary. The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Results and Evaluation 1 Sheets given in the Appendix, the measured critical boron endpoint values were within their respective ' design tolerances. The ARO endpoint i comparison to the predicted value met the requirements of Technical Specification 4.1.1.1.2 regardin'g core reactivity balance. In summary, the boron endpoint results were satisfactory. 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, NE-1000 N1C11 Startup Physics Tests Report Page 27 of 57
the value of the DBW over the range of boron endpoint concentrations was obtained. A plot of the boron concentration versus inserted control rod worth is shown in Figure 4.1. As indicated-in this figure and in the Appendix, , the measured DBW was -6.72 pcm/ ppa. This is within 1.0% of the predicted vslue of -6.79 pcm/ ppg and is well within the design tolerance of 110%. In summary, the measured baron worth coefficient was satisfactory.
.I e
E t NE-1000 N1C11 Startup Physics Tests Report Page 28 of 57
Table 4.1 : NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) , (ppm) ARO 1984 1983 1 B Bank In 1798 1791* 7
- The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation i Sheet in the Appendix.
I 1 I, I NE-1000 N1C11 Startup Physics Tests Report Page 29 of 57
Figure 4.1 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured DBW = -6.72 pcm/ ppm 1300 G., g 1200 '., 1100 . 1000 900 .
~
800 . c 4 . MM b - > 600 . 9 : . us . . 500 '.. 400 300 . 200 , 100 .
. w
. , ., . I. . . .I .. ... "...
1900 1920 1940 1960 1980 2000 1780 1800 1820 1840 1860 1880 BORON CONCENTRATION (PPM) P(ige 30 of 57 NE-1000 N1C11 Startup Physics Tests Report
~
SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC) at the all-rods-out condition is measured' by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity t 1 i changes on the reactivity computer. Reactivity was measured during the RCS cooldown of 3.4'F and RCS heatup o f 3.1'F. Reactivity and temperature data were taken from the reactivity computer and strip chart recorders. Using the statepoint method, the i temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint 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 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. The moderator temperature coefficient was determined to be -1.12 pcm/'F wich met the requirements of COLR Section 2.1.1. In summary, the measured result was satisfactory. l NE-1000 NIC11 Startup Physics Tests Report Page 31 of 57
Table 5.1 , NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
ISOTHERMAL TEMPERATURE COEFFICIENT BANK TEMPERATURE BORON (PCM/'F) POSITION RANGE CONCENTRATION (ppm) AVE. DIFFER. (STEPS) ('F) MEAS. PRED. (M-P) C/D H/U 544.4 to 1984 -2.50 -3.23 -2.87 -3.61 0.74 D/212 547.8 NE-1000 N1C11 Startup Physics Tests Report Page 32 of 57 il
t SECTION 6 POWER DISTRIBUTION NEASUREMENTS The core power distributions were measured using the moveable incore i detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows th.e available locations
#s monitored by the moveable detectors for the ramp to full power flux maps l
~
l for Cycle 11. For each traverse, the detector voltage output is l 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 l a Virginia Power modified version of the Combustion Engineering computer program, CECOR'. CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core. A list of the full-core flux maps taken during the startup test C ' program and the measured values of the important power distribution parameters are given in Table 6.1. A comparison of these measured values with their COLR limits is given in Table 6.2. Flux map I was taken at i 30% power to verify the radial power distribution (RPD) oredictions at low power. Figure 6.1 shows the measured RPDs from this flux map. Flux maps 2 and 3 were *sken at 74% and 100% power, respectively, with r. dif ferent control rod configura ions. These flux maps were taken to check at power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3. The radial power distributions NE-1000 NIC11 Startup Physics Tests Report Page 33 of 57
for the maps given in Figures 6.1, 6.2, and 6.3 show that the measured relative assembly power values were generally within 1.37. of the predicted values. Further, the measured F-Q(Z) and F-DH(N) peaking factor values , for the at power flux maps were within the limits of COLR Sections 2.5.1 and 2.6, respectively. Flux maps 1, 2, and 3 were used to perform power range detector calibrations (flux map 3 verified that the existing I calibration was satisfactory, thus no adjustments to the power range detector calibration were required). In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR. It is therefore anticipated that the core will continue to operate safely throughout Cycle 11. NE-1000 N1C11 Startup Physics Tests Report Page 34 of 57 /,
< s TABLE 6.1 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PilYSICS TESTS INCORE FLUX HAP
SUMMARY
l i i 8 i i I (18 I l I i l l l 1 1 6 suRNI 1 i F-Otz) NOT ] F-CH(M) H0il CORE F(2) l (2) l l l l MAP lMAPI l UP l 18AM I CHANHEL FACTOR I CNNL.FACTOH1 MAX l CORE TILil AX!Atl M0.1 l DESCRIPTION lMO I DATE I MWD /IPWRI O I I I l 1 0FF l OF l l l l l MTU l(2)lSTEPSIASSYlAXIAll IASSYlF-OHtN)lAXIALI F(2)l. MAX (LOC) SET liMINI l l J l J l l IPOINilF-Q(2) l l lPOINil l l l (2) ISLESl
!L.Pe.eR lP.F.V. (3) l rli.1.-,.! . lml 1, lwl 3, l ,.m lwl 1.5,, l 3. l1.41,li mH-is.3,htl l 2 110-!!-941 37 I 741 179 i C141 35 1 2.011 i Nc61 1.434 1 35 11.2988L.co71 NW1 -7.551 45 I l HOT FULL power l 3118-31-94) 764 intel 225 i Noel 37 1 1.833 1 N061 1.3% 1 36 11.20811.8041 NW1 -3.531 45 1 1 1l I l_f lI I l__ l I i 1 l _I l_1 NOTEst Hof SPOT LOCAf t0NS ARE SPECIFIED BY GIVING ASSEMBLY LOCAi!ONS (E.O. H 8 IS THE CENTER-OF-CORE ASSEMBLY)
AND CORE HEIGHT (IN THE "2" OIRECTION THE CORE IS OlvlDED INTO 61 AXI AL POIMTS STARTING FROM THE TOP OF THE CORE). (1) F-0(2) INCLUDES A TOTAL UNCERIAINTY OF 1.05 X 1.05. (2) CORE TILT - DEFINED AS THE AVERAGE QUADRANT POWER TILT FROM CECOR. (3) P.F.W. PEAKING FACTOR VERIFICATION. (4) MAPS 1, 2. ANO 3 WERE USED FOR POWER RANGE DETECTOR CALIBRATIONS. THE CALIBRAi!ON FOR FLUX MAP 3 YERIFIED THE ACCEPTA81LITY OF THE EXISTING CALIBRATION. l I NE-1000 NIC11 Startup Physics Tests Report Page 35 of 57
Table 6.2 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS PEAK F-Q(Z) HOT F-Q(Z) HOT F-DH(N) HOT CHANNEL FACTOR ** CHANNEL FACTOR CHANNEL FACTOR * (AT N0DE OF MINIMUM MARGIN) MAP NO. MEAS. LIMIT NODE MEAS. LIMIT NODE MARGIN MEAS. LIMIT MARGIN (%) (%) 4.380 2.297 4.380 36 47.6 1.525 1.804 15.5 1 2.297 37 2.011 2.959 35 2.011 2.959 35 32.0 1.434 1.606 10.7 2 1.833 2.190 37 1.833 2.190 37 16.3 1.394 1.490 6.4 3
- The Core Operating Limit for the heat flux hot channel factor, F-Q(Z), is a function of core height and power level. The value for F-Q(Z) listed above is the maximum value of F-Q(Z) in the core. The COLR 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 above are the minimum percent difference between the measured values of F-Q(Z) and the COLR limit for each map.
The measured F-Q(Z) hot channel factors include 8.15% total uncertainty. NE-1000 NIC11 Startup Physics Tests Report Page 36 of 57 -
Figure 6.1 NORTl! ANNA UNIT 1 - CYCLE 11 STARTUP PliYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 30% POWER R P N M L K J M C F E D C 8 A
. PREDICTED . . 9.253 . 8.326 . 8.2 % . . PREDICfED .
. HE ASIDtED . . 8.252 . 6.321 . e.253 . . NEASURED . 1
. PCT DIFFERENCE. . -0.6 . -1.6 . -0.9 . . PCT DIFFERENCE.
9.382 . 0.501 . 1.957 8.425 1.869 . 0.543 . 8.343 . g . 0.333 . 0.588 . 1.954 . 8.420 . 1.868 . 0.494 . 0.378 . 2
. e.1 . e.e . -0.3 . -0.5 . -8.8 . 0.9 . -1.3 .
. 0.411 . 1.220 . 1.357 . 1.211 . 1.273 . 1.216 . 1.360 . 1.219 . 0.481 .
. 0.407 . 1.224 . 1.359 . 1.2e9 1.264 1.2sa . 1.347 . 1.202 . 0.349 3
. -1.1 . 0.3 0.2 . -0.2 . -0.7 . -0. 7 . -0.9 . -1.4 -2.6 .
e.396 . 0.875 .1.361 . 1.296 .1.213 1.154 1.215 . 1.294 . 1. % I . 0.874 . 0.413 .
. 0.407 . 0.886 1.373 . 1.383 . 1.214 1.146 . 1.208 . 1.290 . 1.342 . 0.853 . 0.399 4
. 2.4 . 1.3 . 0.9 . 0.5 0.1 -1.0 . -0.5 . -0.6 -1.4 -2.9 . -3.4
. 0.3a1 . 1.212 . 1.357 . 1.309 . 1.287 . 1.1 % . 1.1 % l.1 % . 1.207 . 1.312 . 1.366 . 1.225 . 0.384 .
. 0.394 . 1.261 . 1.344 1.328 . 1.220 . 1.144 . 1.162 . 1.139 . 1.203 . 1.297 . 1.318 . 1.188 . 8.371 . 5
. 3.4 . 4.0 2.0 . 1.5 . 1.1 . 1.1 . 4.5 . 0.3 . -0.4 . -1.1 . -4.1 . -3.7 . *3.4 .
. 0.581 . 1.3 % . 1.296 . 1.206 . 0.949 . 1.148 . 1.170 1.139 . 0.948 . 1.207 . 1.299 . 1.359 . 0.500 .
0.518 . 1.384 . 1.312 . 1.264 . 0.984 . 1.170 . 1.192 . 1.159 0.971 1.186 1.252 . 1.314 . 8.491 . 6 1.9 . 2.1 1.2 -0.1 1.5 . 2.6 . 1.4 . l.7 . 0.3 . -1.7 . -3.6 . -3.3 . -2.0 .
. 0.255 1.064 . 1.212 . 1.210 . 1.130 1.131 1.216 . 1.217 . 1.207 . 1.127 . 1.138 1.211 . 1.209 . 1.054 . 9.251 .
. 0.258 1.079 . 1.227 . 1.221 . 1.137 . 1.158 . 1.285 . 1.259 . 1.255 . 1.136 . 1.108 1.151 1.170 . 1.054 . 9.253 . 7
. 1.2 . 1.3 . 1.2 . 0.4 . 0.6 . 2.4 . 5.7 . 3.5 . 3.9 . 0.4 . al.9 . -5.0 . -3.2 . e.4 0.2 .
. 0.325 8.821 . l.264 . 1.154 . 1.148 1.154 . 1.199 1.224 . 1.203 . 1.1 % 1.149 . 1.155 . 1.264 . 0.822 . e.325 .
. 0.324 0.430 1.273 . 1.157 . 1.141 . 1.171 . 1.233 . 1.252 . 1.224 1.164 . 1.131 . 1.!!6 . 1.214 . 0.823 . 8.324 8
. 0.9 1.1 0.4 8.3 . -9.6 . 1.5 . 2.8 . 2.3 . 1. 7 . 0.7 . -1.6 . 3.3 . -4.3 . 0.2 . -0.4
. 0.253 . 1.053 . 1.208 . 1.210 . 1.129 1.125 1.205 . 1.217 1.216 . 3.132 . 1.131 . 1.211 . 1.213 . 1.066 . 9.255 .
. 9.254 . 1.059 . 1.211 . 1.215 . 1.134 1.139 . 1.225 . 1.230 . 1.217 . 1.101 . 1.109 . 1.183 . 1.182 . 1.044 . 9.244 . 9
. 0.6 0.5 . 4.3 . 0.4 . 0.5 . 1.2 . 1.6 . 1.1 . 0.8 -2.7 . -1.9 . 2.5 . -2.5 . -1.7 . -2.4 .
0.586 . 1.354 . 1.294 . 1.286 , 0.968 . 1.139 1.170 . 1.141 . 0.970 1.206 . 1.296 1.356 . 0.501 .
. 0.501 . 1.154 . 1.306 . 1.219 . 8.979 . 3.156 . 1.174 . 1.1 % . 0.9 % . 3 192 . 1.278 . 1.333 . 0.490 . le
. 9.2 . 0.4 . 0.6 . 1.9 . 1.2 . 1.4 . 0.3 . -0.4 -1.4 -1.2 . -1.4 . -1.7 . -2.2 .
. 0.344 1.225 . 1. % 5 . 1.311 1.207 . 1.135 . 1.156 . 1.1 % . 1.267 . 1.310 1.357 . I.213 . 0.341 .
0.345 . 1.231 . 1.378 . 1.3 % . 1.214 . 1.137 . 1.144 . 1.127 . 1.192 . 1.310 . 1.152 . 1.201 . 0.376 . II
. 0.4 . S.5 . 1.0 . 1.9 . 0.9 8.2 . -1.0 . -0.4 . -1.3 . 0.0 . -0.4 . -1.0 . -1.3 .
. 0.413 . e.478 . 1.%8 . 1.297 . 1.214 1.154 . 1.213 . 1.297 1.%2 8.876 0.394 .
. 0.418 . 0.886 . 1.374 . 1.302 . 1.295 . 1.153 . 1.248 . 1.287 . 1.360 . 8.887 . 4.397 . 12
. 1.2 . 1.0 . 1.0 . 0.4 . -0.7 . -0.5 . -0.4 -0.8 . -0.1 . 1.3 . 4. 3 .
. 4.491 . 1.219 . 1. % 8 . 1.216 . 1.273 . 1.211 . 1.358 . 1.221 . 0.411 .
. 9.404 . 1.224 . 1. % 5 . 1.216 . 1.276 . 1.216 . 1.341 . 1.214 . 8.412 . 13
. 0.8 . 0.6 . 0.4 . 0.0 . 0.3 . 4.4 . -1.2 . -0.6 . 9.2 .
. e.343 . 0.543 . 1.069 0.825 . 1.057 . 0.501 . 4.342 .
. 0.349 . 0.585 . 1.649 . 0.835 . 1.097 . 0.504 . 6.382 . 14
. 1.5 . e.3 . e.e . 1.3 . 3.8 . 0.8 . -e.2 .
. STANDARD . . 9.256 . 8.326 . e.253 . . AvtRAGE .
. DEvlafl0M . . 8.244 . 4.327 . 9.261 . . PCT DIFFERENCE. 15
=l.154 . . -4.5 . e.5 . 3.0 . .
- 1.3 .
SUMMARY
MAP NO: N1-11-01 DATE: 10/ W 94 POWER: 30% CONTROL ROD POSITIONS: F-QtZ) = 2.297 CORE TILT: D BANK AT 124 STEPS F-DH(N) = 1.525 NW 1.011 l NE 0.989 l FlZ) = 1.419 SW 1.006 l SE 0.993 BURNUP = 4 MWD /NTU A.O. m -13.39%
~~
NE-1000 N1C11 Startup Physics Tests Report P(ige 37 of 57
emii .iti 4mmir ir
- s Figure 6.2 NORTH ANNA UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 74% POWER R P M M L K J H C F E D C 8 A
. PREDICTED . . 9.205 . 0.378 . e.287 . PREDICTED .
. ME ASURE D . . e.279 . e.361 . 0.201 . . MEASURED . }
. PCT O!FFERENCE. . -2.1 . -4.3 . -2.1 . . PCT DIFFERENCE.
. e.345 . 0.513 .1.107 . e.957 .1.114 . 0.515 . e.385 .
% . 0.342 . 0.549 1.092 . 0.939 . 1.103 . 0.511 . e.382 . 2
. -0.6 . -0.9 . -1.4 -1.9 . 1.3 . -0.9 . -0.7 .
. 4.409 1.166 . 1.366 . 1.287 . 1.286 . 1.213 . 1.308 . 1.165 . 6.394 .
. 0.464 1.16e .1.298 .1.195 .1.265 .1.201.1.382 .1.157 . 8.394 . 3
. -1.3 . -0.5 . -0.6 . -1.0 . -1.6 . -0.9 . -0.5 . -0.7 . -1.0 .
e.394 . 0.848 . 1.291 . 1.250 . 1.185 . 1.147 . 3.186 . 1.251 . 1.289 0.850 . e.410 . 4
. 0.403 . e.853 . 1.288 1.249 . 1.18e . 1.131 . 1.182 . 1.215 . 1.279 . e.832 . 0.398 .
. 2.2 . 0.6 . -e.2 . -0.1 . -0.4 . -1.5 . -0.4 0.3 . -0.4 . -2.2 . -2.9 0.384 . 1.16e .1.287 .1.271 . 1.te3 . 1.134 . 1.146 .1.134 .1.283 .1.272 .1.293 .1.17e , e.386 .
. e.394 . 1.208 . 1.387 . 1.280 1.212 . 1.147 . 1.155 . 1.145 .1.204 .1.268 .1.246 .1.13e . 0.367 . 5 2.7 . 3.4 . 1. 5 . e.8 . e.7 8.8 . e.8 . e.7 . 0.1 . -1.0 . - 3. 7 . * - 3. 4 -4.8 .
. 0.514 . 1.346 . 1.251 . 1.202 . 1.089 1.165 . 1.178 . 1.164 1.088 . 1.203 . 1.253 . 1.307 . 0.513 .
1.197 . 1.213 . 1.189 1.992 . 1.188 , 1.216 . 1.269 . 0.5e2 . 6
. 0.519 . 1.324 . 1.265 . 1.216 . 1.106
. 0.9 . 1.4 . 1.2 . 1.2 . 1.6 . 2.8 . 3.0 . 2.2 . 0.4 1.2 . -2.9 . =2.9 . 2.1 .
. e.287 1.117 . 1.216 . 1.184 1.133 . 1.156 . 1.234 . 1.227 . 1.226 . 1.152 . 1.133 . 1.184 . 1.205 . 1.164 . 4.284
. 9.286 1.115 . 1.284 . 1.191 . 1.147 . 1.187 . 1.340 . 1.274 . 1.278 1.168 .1.12e . 1.137 . 1.173 .1.100 . e.282 . 7
. -0.3 . -0.2 . -0.1 . o.6 1.2 . 2.6 . 5.3 3.9 . 4.3 . 1.4 . -1.1 . -3.9 . 2.7 . -0.3 . -e.0 .
0.378 0.955 . 1.202 1.143 . 1.139 . 1.163 . 1.210 . 1.232 . 1.213 . 1.165 . 1.140 . 1.144 . 1.283 . 0.955 . e.378 .
. e . 3 75 . 0. 94 7 . 1. 264 . 1.143 1.144 . 1.187 . 1.244 1.267 . 1.244 . 1.184 . 1.134 . 1.118 . 1.239 . 0.939 . e.370 . 8
. -0.7 . -0.8 -1.4 . 8.0 . 0.4 . 2.1 . 3.2 . 2.9 . 2.5 . 1.6 . -0.5 . -2,3 . -3.4 -1.6 . -2.1 .
. e.284 . 1.104 1.204 . 1.184 . 1.132 . 1.151 . 1.225 . 1.227 . 1.234 1.157 . 1.134 . 1.184 . 1.211 . 1.!!7 . 0.287 . 9
. e . 242 . 1. 09 7 . 1.19 7 . 1.18 7 . 1.149 3.172 1.252 . 1.249 . 1.249 . 1.152 1 128 . 1.172 . 1.192 . 1.18 8 . e . 271 .
. -0.7 -0.7 . -0.6 . e.3 . 1.5 . 1.8 . 2. 2 . 1.8 . 1.1 . -0.5 . -0.5 . -1.1 . -1.6 . -1.5 . -5.5 .
. 0.513 . 1.306 . 1. 252 . 1. 20 2 . 1. 08 7 . 1.163 . 1.17e . 1.166 . 1. 849 . 1. 20 2 . 1. 251 . 1. 306 . 0. 514 .
. 0.518 . 1.299 . 1. 256 . 1.216 . 1.10e . 1.188 , 1 189 . 1.169 . 1.081 . 1 202 . 1. 250 . 1.30 2 . 0.528 . le
-0.6 . 0.6 . 0.4 1.1 . 1.2 2.1 . 0.9 . 0.3 . -0.8 . 0.0 . -0.1 . -0.3 . 1.2 .
0.386 . 1.169 . 1.293 . 1.272 . 1.203 . 1.137 . 1.146 . 1.138 . 1.293 . 1 272 . 1.288 1.16e . 6.184
. 4.385 . 1.17e . 1.341 . 1.290 . 1.211 1.139 . 1.138 . 1.132 . 1.191 . 1.205 . 1.298 . 1.162 . 0.345 . 11
. 0.2 . 0.6 o.6 . 1.5 . 0.7 . 9.2 . -0.7 . -0.5 . -1.0 . 1.0 . 0.0 . 0.2 . 0.5 .
. . ........ .s .......................................................................................
. 0.41s . 0.850 . 1.289 1. 251 . 1.186 . 1.147 . 1.185 . 1. 25e . 1. 291 . 0. 849 e.394 .
. 4.411 . e.854 1.295 . 1.249 1.171 . 1.135 . 1.179 . 1.246 . 1.300 . 0.878 . 4.392 . 12 0.2 . e.4 . e.4 . -0.2 . -1.3 . -1.0 -0.5 . -0.4 . 9.7 . 2.5 . -0.6 .
. 4.398 . 1.165 . 1. 308 . 1.213 . 1.286 . 1. 28 7 . 1.386 . 1.166 . e . 4 09 .
. 8.399 . 1.164 . 1.301 . 1.197 . 1.265 . 1.293 . 1.297 . 1 168 . e.414 . 13
. e.2 . -0.1 . -0.6 . -1.3 . -1.7 . -0.3 . -0.7 . 0,2 . 1.2 .
. e.345 . 0.515 . 1.11e . e.957 . 1.187 . 9.513 . 0.385 .
. 8.184 . e.510 . 1.e99 . e.949 . 1.128 . 0.516 . e.386 . 14
. -0.3 . -1.0 . -1.8 . -0.8 . 1.9 . 0.5 . 0.3 .
. STANDARD . . e.287 . e.370 . 0.285 . . SVERAf4 .
. DEV!8tt0M . . e.263 . e.371 . e.287 . . PCT DIFFERENCE. 15
. = 1. 24 3 . . 0.5 . -1.9 . e.9 . .
= 1.3 .
SUMMARY
MAP N01 N1-11 02 DATE: 10/1'/94 POWER: 74% CONTROL R00 POSITIONS: F-Q(Z) = 2.011 CORE TILT: D BANK AT 179 STEPS F-DH(N) a 1.434 NW 1.007 l NE 0.992 i F(Z) = 1.290 SW 1.002 l SE 0.999 BURNUP = 37 MWD /MTU A.D. s -7.55% NE-1000 N1C11 Startup Physics Tests Report P(ige 38 of 57 - - - -
h
+ .
l . Figure 6.3 l i NORTl! ANNA UNIT 1 - CYCLE 11 STARTUP PilYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R P N M L E J H C F E D C S a
. PitEDICTED . . 0.295 . 0.397 . 4.298 . . PREDICTED .
ME ASURf D . . 9.291 . e.391 . 9.294 . 0(ASURED . 1
.. PCT DIFFERENCE. . -1.4 -1.5 . 1.3 . . PCT O!FFERENCE.
. 0.344 . 0.519 1.189 . 1.004 . 1.120 . 0.521 . 0.347 9 . e.342 . 4.513 . 1.093 . 0.986 . 1.106 . 0.517 . e.346 . 2
. -1.1 . -1.2 . -1.4 . -1.7 . 1.3 . -0.4 . -0.4 .
. e . 419 . 1.141 . 1. 285 . 1.193 . 1. 289 . 1.19 7 . 1. 287 . 1.139 . e .4 00 .
. e.410 . 1.129 . 1.273 .1.177 . 1.256 .1.184 . "1.282 .1.137 . 8.403 . 3
. 0.8 . -1.s . -1.4 . -1.3 . -2.5 . al.1 . -0.4 -0.2 . e.9 . -
. 4.396 0.840 . 1.271 . 1.230 1.144 . 1.140 .1.145 . 1.230 . 1.270 . 0.642 . e.411 . y
. e.399 . 0.839 . l.252 . 1.223 . 1.140 1.133 1.183 . 1.232 . 1.265 . 0.427 . 0.401 . 4
. 0.9 . -0.1 . -l.4 -0.5 . -0.3 . -0.6 . -0.2 . e.2 . -0.4 . -1.8 . -2.5 .
\ ................................ ........................................................................ 1.135 . 1.264 e.346 1. 257 . 1.219 . 1.141 . 1.153 . 1.141 . 1.219 . 1.257 . 1. 273 . 1.144 . e.384 .
. 0.391 . 1.154 . 1.278 . 1.268 . 1.228 . 1.156 . 1.164 . 1.151 . 1.224 1.255 .1.225 .1.11e e.342 . 5
. 1.2 . l.6 . 0.8 . e.9 . e.8 . 1.3 . 1.0 . 8.9 . 0.5 . -0.2 . -3.7 . -3.0 . -1.5 .
. 4.520 , 1.205 . 1.234 . 1.218 . 1.152 . 1.185 . 1.174 . 1.184 . 1.151 1.218 . 1.232 . 1.285 . 0.519 .
. 0.522 . 1.295 . 1.236 1.218 . 1.169 1.218 . 1.203 . 1.211 . 1.161 . 1.209 . 1.196 . 1.249 . 4.509 6 i
. 4.4 . e.8 . 0.5 . 0.0 . 1.5 . 2.7 . 2.5 . 2.3 . e.9 . -0.8 . 2.4 . -2.s . -2.0 .
l ............................... ........................................................................................ e . 294 . 1.12e . 1.1% 1.183 1.137 . 1.178 1.227 . 1.212 . 1.228 . 1.174 . 1.136 . 1.182 . 1.191 . 1.186 0.295 .
. 6.296 . 1. !!7 . 1.201 . 1.187 . 1.146 . 1.208 . 1.295 . 1.259 . 1.276 . 1.195 1.127 . 1.134 1.154 . 1.094 . e.292 . 7
. *0.5 . -0.2 9.4 e.3 . 0.4 . 2.5 . 5.6 . 3.9 4.6 . lea . -0.8 . -4.1 . -3.1 . 1.1 . -1.0 .
. 8.397 . 1.002 . 1.245 1.134 . 1.147 1.162 . 1.19a . 1. 217 . 1.20s . 1.163 . 1.148 . 1.134 . 1.286 . 1.002 . 0.397 .
. 6.393 . e.986 1.259 1.133 . 1.150 . 1.184 . 1.235 . 1.251 . 1.232 . 1.19e . 1.144 . 1.11e . 1.234 1.001. e.394 4
. -1.2 . -1.3 . -2.0 . -0.4 . 8.3 . 1.9 . 3.1 . 2.4 . 2.1 . 2.4 -0.3 . -2.4 -4.0 . 4.0 . -0.8 .
. e.295 . 1.106 1.191 . 1.182 . 1.136 1.173 . 1.218 . 1.212 . 1.224 . 1.178 . 1.134 . 1.183 . 1.196 . 1.12e . 0. 298 .
. e.290 1.049 1.171 . 1.181 1.159 1.194 . 1.242 . 1.232 1.240 1.172 . 1.133 . 1.170 . 1.178 . 1.112 . 0.289 . 9
. -1.5 . -1,6 . -147 . -0.1 . 2.0 . 1.8 . 2.s . 1.6 . 1.0 . -0.6 . -0.4 -1.1 . -1.5 . -0.7 . -3.0 .
. 0. 519 . 1. 285 . 1.231 . 1.214 . 1.15e . 1.144 1.174 1.186 . 1.152 . 1.219 . l.231 . 1.245 . 0.528 .
. 0.504 1.250 . 1.226 . 1.233 . 1.166 . 1.200 . 1.142 . 1.184 . 1.149 1.222 .1.238 .1.284 . e.526 . le
. -2.1 -2.8 . -0.3 . 1.2 . 1.3 . 1.3 . e.7 . 6.2 -0.3 . e.2 . -0.1 . -0.1 . 1.0 .
. 4.344 . 1.144 1.273 . 1.257 . 1.219 . 1.141 . 1.153 . 1.141 . 1.219 . 1.257 . 1.264 . 1.135 . 6.346 .
. e.345 . 1.135 . 1.270 . 1.282 .1.231 . 1.144 1.145 . 1.135 . 1.207 . 1.277 . 1.284 . 1.145 . e.349 11
. -1.2 . -0.4 . e.4 1.9 . 1.6 . 0.3 . -0.6 -0.5 . -1.0 . 1.6 . 1.3 . e.8 . 0.9 .
. 4.411 . 0.841 . 1.278 . l.230 . 1.185 . 1.140 . 1.144 1.238 . 1.271 . 0.841 . e.396 .
. 0.426 . 0.444 . 1.281 . 1.233 . 1.177 , 1.129 1.!?5 . 1.222 . 1.242 . 0.869 . 4.445 . 12
. 2.1 . 0.4 . 0.9 . 8.3 . -0.6 . -1.0 . -0.4 . -0.6 . 0.9 . 3.4 . 2.2 .
0.400 . 1.139 . 1.247 . 1.197 . 1.289 1.19 3 . 1. 285 . 1.141 . e . 410 . 0.402 . 1.144 . 1.266 . 1.187 . 1.265 . 1.182 . 1.264 . 1.139 . 0.416 . 13
. 0.6 . 0.4 . -0.1 . -4.s . -1.4 . =0.9 . -1.6 . -e.1 . 1.4 .
0.347 . e.521.1.120 .1.004 . 1.109 . 0.519 . 8.346
. e. 587 . 0.519 . 3.111 . 0.997 . 1.!!9 . 0.517 0.344 . 14 8.0 . -0.4 *0.8 . -0.7 . 0.9 . -0.4 -0.2 .
l . 1
. STANDA20 . . e.294 . e.397 . 9.295 . . AVERACZ .
. DEVIATION . . e.292 0.395 . 0.296 . . PCT 01FTERENCE. 15
. =1.009 . . 1.9 -e.7 6.5 . = 1.2 .
SUMMARY
MAP NO: N1-11-03 DATE: 10/t1/94 POWER: 100% CONTROL RCD POSITIONS: F-Q(Z) a 1.833 CORE TILT . D BANK AT 225 STEPS F-DH(N) = 1.394 NW 1.004 l NE 0.995 i F(Z) = 1.208 SW 1.001 1 SE 1.000 BURNUP s 7 M MWD /MTU A.O. = -3.53% NE-1000 N1C11 Startup Physics Tests Report Page 39 of 57
SECTION 7 REFERENCES
- 1. P. D. Banning, " North Anna Unit 1, Cycle 11 Design Report",
Technical Report NE-997, Revision 0, Virginia Power, October,1994.
- 2. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Determinati
By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
- 3. T. W. Schleicher, "The Virginia Power CECOR Code Package", Technical Report NE-831, Revision 2, Virginia Power, March, 1994.
- 4. North Anna Unit 1 Technical Specifications, Sections 1.19, 3.1.3.4, 3.2.2, 3.2.3, 3.1.1.4, 4.1.1.1.2, and 4.2.2.2 and Core Operating Limits Report (COLR) for North Anna 1, Cycle 11 Pattern BW, Revision 0 (September, 1994) Sections 2.1.1, 2.5.1, and 2.6.
- 5. 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.
- 6. R. F. Villaflor, " North Anna Unit 1, Cycle 11 TOTE Calculations",
PM-553 Revision 0, October, 1994.
- 7. R. A. Hall, et al, " North Anna 1, Cycle 11 Flux Map Analysis",
PM-560, Revision 0, and Addenda A and B, October-November, 1994. NE-1000 NIC11 Startup Physics Tests Report Page 40 of 57
l O APPENDIX STARTUP PilYSICS TEST RESULTS AND EVALUATION SHEETS l l NE-1000 NIC11 Startup Physics Tests Report Pege 41 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE I1 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 3 I Test
Description:
Zero Power Testing Range Determination Reference Proc No / Section: 1 PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature (0F): 547 Test Power Level (% F.P.): O Conditions Other(specify): SDA: 225 SDB: 225 CA: 225 (Design) Below Nuclear Heating CB: 225' CC:
- CD: .
III Bank Positions (Steps) RCS Temperature'(0F): 5%.O Test Power L.evel(% F.P.): 0 Conditions Other (specify): SDA: 225' SDB: 225 CA: 225 Below Nuclear Heating (Actua0 CB: 225 CC: 323 CD: cl5 DaterTime Test Perfonned: tolSM4 33* 5 4 Reactivity Computer Initial Flux IV Background Reading IM X to amps Test Results Flux Reading At Point ofNuclear Heating to8'x to'7 amps Zero Power -3 amps
-3 to 10 x 10 Testing Range r x 10 Reference Not Applicable V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met" : / YES NO Acceptance Criteriais met" : v/ YES - NO VI
- At The Just Critical Position Comments
" Design Tolerance and Acceptance Criteria are met if ZPTR is below the Point of Nuclear Heating and above background.
Prepared By: d% do. O - . Reviewed By: , 8-NE-1000 NIC11 Startup Physics Tests Report Page 42 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE II STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Reactivity Computer Checkout Reference P'r oc No / Section: 1-PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): (Design) CB: 223' CC:
- CD: . Below Nuclear Heating III Bank Positions (Steps) RCS Temperat' u re ( F): 5% 3 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Acnul) CB: 225 CC: 215 CD: 98 Below Nuclear Heating Date/ Time Test Performed:
/ c/9/M Co:57 Measured Parameter p,= Measured Reactivity using p-computer (Description) p, = Predicted Reactivity IV Test Results Pe " * *O Measured Value p, = +47 Y2
%D = *t.z2%
Design Value %D = ((p, - p,)/ p, } x 100% s 4.0% Reference WCAP 7905, Rev.1, Table 3.6 V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference . Not Applicable Design Tolerance is met : V YES NO Acceptance Criteria is met : / YES NO VI Comments
- At ne 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 = 12 fM Prepared By: fw 8. Reviewed By: k k I NE-1000 NIC11 Startup Physics Tests Report Page 43 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE I1 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Baron Concentration - ARO Reference Proc No / Section: 1-PT-94.0 Sequence Step No: 11 Bank Positions (Steps) RCS Tempemture ( F): 547 Test Power Level (% F.P.): 0 Conditions Other (specify): SDA: 225 SDB: 225 CA: 225 (Design) Below Nuclear Heating CB: 225 ' CC: 225 CD: 225 III Bank Positions (Steps) RCS Temperature ( F): 545.(o I Test Power Level (% F.P.): 0 Conditions Other(specify): SDA: 225 SDB: 225 CA: 225 (Acmal) Below Nuclear Heating CB: 225 CC: 225 CD: 225 i Date/ Time Test Performed: I
@[9 f99 050 l5 Measured Parameter l (Description) (Cs)"tgo ; Critical Baron Concentration - ARO IV Test Measured Value Results (Design Conditions) (Cs)"4xo = )Cl34 ppm Design Value (Design Conditions) C. = 1983
- 50 ppm Reference Technical Report NE 997, Rev. O V FSAIUTech Spec aC x C,0 s 1000 pcm Acceptance Criteria Reference Technical Specification 4.1.1.1.2 Design Tolemnce is met : / YES NO Acceptance Criteria is met : / YES NO VI .
Comments aC, = -6.71 pcm/ ppm C. = l(Cs)"xxo - Cal; C, is design value Prepared By: d%d Reviewed By: 0 k~d NE-1000 N1C11 Startup Physics Tests Report Page 44 of 57 _
l l NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EW\LUATION SHEET I Test
Description:
Isothermal Tempemture Coefficient - ARO Reference , Proc No / Section: 1 PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225, SDB: 225 CA: 225 Other (specify): (Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating l III Bank Positions (Steps) RCS Tempemture ( F): 59'i.8" Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): (AC"22II CB: 225 CC: 225 CD: 2l3 Bel w Nuclear Heating . Date! Time Test Performed: tolc1h4 05: 19. Measured Parameter IV (Description) (e r" ),no ; Isothermal Tempemture Coeff- ARO Test Results Measured Value (ar "%o = - 2X7 pcm/*F (C = R34 ppm) Design Value (Actual Conditions) (ar "%o = -3.to l pcm/ FC (C, = RS4 ppm) Design Value (Design Conditions) (ar"%o = -3.62
- 3.0 pcm/*F (C, = 1983 ppm)
Reference Technical Report NE-997, Rev. 0 V 5 s 3.75* pcm/*F FSAR/COLR ar ar ' = -1.75 pcmFF Acceptance Criteria Reference COLR 2.1.1, Technical Report NE-997, Rev. 0 Design Tolemnce is met : / YES NO l Acceptance Critetiais met : / YES NO VI Comments
- Uncertainty on aTuco = 0.5 pcm/ F (
Reference:
memorandum from C. T. Snow to E. J. Lozito dated June 27,1980). Prepared By: dO Reviewed By: , lN NE-1000 NIC11 Startup Physics Tests Report Page 45 of 57
- l. _
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS T1!ST RESULTS AND EVALUATION SHEET I Test
Description:
Control Bank B Wotth Measurement. Rod Swap Ref. Bank Reference Proc No / Section: 1 PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions CA: 225 Other(specify): SDA: 225 SDB: 225 (Design) Below Nuclear Heating CB: movihg CC: 225 CD: 225 III Bank Positions (Steps) RCS Temperature (oF): fwW Test Power Level (% F.P.): 0 Conditions Other(specify): SDA: 225 SDB: 225 CA: 225 (Acmal) Below Nuclear Heating CB: moving CC: 225 CD: 225 Date.' Time Test Performed:
/o/9/9y 070o Measured Parameter (Description) I," ; Integral Worth of Control Bank B, IV All Other Rods Out Test Measure'd Value I," = / 7. IO Design Value (Design Conditions) I,5 = 1310
- 131 pcm Reference Technical Report NE-997, Rev. 0 V FSAR/ Tech 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 Tolemace is met : / YES NO VI Acceptance Criteria is met : / YES NO Comments
.1 _o Prepared By: /e/ y Reviewed By2e d-n
(; sp, NE-1000 N1C11 Startup Physics Tests Report Page 46 of 57 .
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STAREJP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - B Bank In Reference Proc No / Section: 1-PT-94.0 Sequence Step No: l l II Bank Positions (Steps) RCS Temperature t F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): l (Design) CB: 0' CC: 225 CD: 225 Below Nuclear Heating l III Bank Positions (Steps) RCS Temperature ( F): 99y,3 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): (Acmal) CB: 0 CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performed: to/4/O+ 070 v i Measured Parameter i (Description) (Cs)", ; Critical Baron Concentration. Bank B In i IV Test Results Measured Value (Design Conditions) (Cs)", = /7f8 Design Value (Design Conditions) C, = 1790 + AC * * (10 + 131.0/laCal) ppm C, = 17#// ppm i Reference Technical Report NE-997, Rev. O V FSAR/rech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : [ YES NO Acceptance Criteria is met : / YES NO VI Comments sC, = -6.79 pcm/ ppm AC,* = (C,)%o - 1983 ppm A ii A Prepared By: Reviewed By[We'- u - v q NE-1000 N1C11 Seartup Physics Tests Report Page 47 of 57 I
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l Test
Description:
HZP Boron Worth Coefficient Measurement .. Reference Proc No / Section: 1 PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions Other (specify): SDA: 225 SDB: 225 CA: 225 (Design) Below Nuclear Heating CB: moving CC: 225 CD: 225 III Bank Positions (Steps) RCS Temperature (0F): 5 45,3 Test Power Level (% F.P.): 0 Conditions Other(specify): SDA: 225- SDB: 225 CA: 225 (Actual) Below Nuclear Heating CB: moving CC: 225 CD: 225 Date/Thne Test Performed: w 19/sa 07w Measured Parameter (Description) aCs ; Boron Worth Coefficient IV Test Results aC, = - 6.7 7 Measured Value Design Value (Design Conditions) aCs = -6.79
- 0.68 pcmippm Reference TechnicalReportNE-997 Rev.0 V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : / ESY NO Acceptance Criteria is met : / YES NO VI Comments Prepared By:
i- -. Reviewed By: IN A h NE-1000 NIC11 Startup Physics Tests Report Page 48 of 57 . . .
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET -. I Test
Description:
Control Bank D Worth Measurement. Rod Swap Reference Proc No / Section: 1-PT-94.0 Secuence Step No: II Bank Positions (Steps) RCS Temperature FF): 547 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): (Design) CB: moving CC: 225 CD: moving Below Nuclear Heating III Bank Positions (Steps) RCS Tempemture ( F): fv5 r Test Power Level (% F.P ): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): ' I^' CB: moving CC: 225 CD: moving Below Nuclear Heating Date/ Time Test Performed:
/0[4/ff 0700 .
Measured Parameter lo" ; Integral Worth of Contro! Bank D, (Description) Rod Swap IV Test Measured Value Io" = O6 '(Adjusted Measured Critical Reference Bank Position = 154 steps) Results Design Value Io" = 1003. 7 (Adjusted Measured Critical (Actual Conditions) Reference Bank Position = 15'9 steps) Design Value Iou = 1001
- 150 pcm (Design Conditions) (Critical Reference Bank Position = 159 steps)
Reference Technical Report NE-997, Rev. O. VEP FRD-36A V FSAR/fech 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 Criteria is met : / YES NO Comments A ti 0 /2 Prepared By: o I - Reviewed By: /M M- ' l 4 NE-1000 NIC11 Startup Physics Tests Report Page 49 of 57
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Description:
Control Bank C Worth Measurement. Rod Swap Reference , Proc No / Section: 1 PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Tempenture (0F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 Other (specify): CA: 225 (Design) CB: movitig CC: moving CD:225 Below Nuclear Heating III Bank Positions (Steps) RCS Tempemture ( F): 5vcs-Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other(specify): (AC*2AI CB: moving CC: moving CD:225 Below Nuclear Heating Date/ Time Teyt Performed: lol9j'fY 0700 Measured Parameter Ic" ; Integral Worth of Control Bank C, (Description) Rod Swap IV Test Measured Value Ice = Q Z 3 '(Adjusted Measured Critical Results Reference Bank Position = By steps) Design Value Ic" = @16 '(Adjusted Measured Critical (Acmal Conditions) Reference Bank Position = / 3 Y steps) Design Value Ic" = 812
- 122 pcm (Design Conditions) (Critical Reference Bank Position = 132 steps)
Reference Technical Report NE-997, Rev. O, VEP FRD-36A V FSAR/ Tech 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 : / YES NO Comments
. . A M1 Prepared By: Reviewed By: / /2
/' Y d' NE-1000 NIC11 Startup Physics Tests Report Page 50 of 57 _ __
NORTH ANNA POWER STATION UNIT 1 CYCLE 1I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Control Bank A Worth Measurement. Rod Swap Reference , Proc No / Section: 1-PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature toF): 547 Test Power Level (% F.P.): 0 ' Conditions SDA: 225 SDB: 225 CA: moving Other (specify): (Design) CB: moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( F): 5'vt.r Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: movine Other (specify):
~
(Acmal) CB: moving CC: 225 CD: 225 Below Nuclear Heating Date! Time Test Performed: lO/4/9y 67oo Measured Parameter I 4"8 ; Integral Wotth of Control Bank A. _ (Description) Rod Swap IV Test Measured Value I4"5 = 7 GG (Adjusted Measured Critical . I Results Reference Bank Position = 66 steps) Design Value 14R3 m a2(,3.2 [ Adjusted Measured Critical (Actual Conditions) Reference Bank Position = 68' steps) Design Value I 4"8 = 269
- 100 pcm -
(Design Conditions) (Critical Reference Bank Position = 73 steps) l 1 Technical Report NE-997, Rev. O. VEP FRD 36A Reference V FSAR/ Tech 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 perfonned. Reference VEP FRD-36A ':r Design Tolerance is met : / ESJ NO VI Acceptance Criteria is met : f YES NO Comments
/7 -/7 Prepared By: / Reviewed By: /4/
p 3 NE-1000 N1C11 Startup Physics Tests Report Page 51 of 57
l NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Shutdown Bank B Worth Measurement. Rod Swap Reference , Proc No / Section: 1-PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature t F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: moving CA: 225 Other (specify): (Design) CB: moving CC: 225 Below Nuclear Heating CD: 225 III Bank Positions (Steps) RCS Temperathre ( F): or, r ; Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: moving CA: 225 Other (specify): > IAC**O CB: moving CC: 225 CD: 225 Below Nuclear Heating l Date/ ime Test Performed: ' se A)'44 0700 Measured Parameter Iss" ; Integral Worth of Shutdown Bank B, , (Description) Rod Swap , IV Test Measured Value Is " = /06 9 (Adjusted Measured Critical : Results Reference Bank Position = 179 steps) Design Value Is," = /O'7(o.9(' djustedA Measured Critical (Actual Conditions) Reference Bank Position = l 19 steps) Design Value Is," = 1077
- 162 pcm (Design Conditions) (Critical Reference Bank Position = 171 steps)
Reference Technical Report NE-997, Rev. O. VEP FRD-36A
)
V FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall .l 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 : BYES NO i VI Acceptance Criteriais met : / YES NO Comments
,e n 0 Prepared By: l -
Reviewed By: XdM j'- y c:r NE-1000 NIC11 Startup Physics Tests Report Page 52 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET r I Test
Description:
Shutdown Bank A Worth Measurement. Rod Swap Reference , Proc No / Section: 1-PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature (oF): 547 Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: 225 CA: 225 Other (specify):
~
(Design) CB: moving CC: 225 Below Nuclest Heating , CD: 225 III Bank Positions (Steps) RCS Temperature ( F): Syr,f Test Power Level (% F.P.): 0 ndm, ons Other (specify): SDA: moving SDB: 225
~
CA: 225 (AC CB: moving CC: 225 CD: 225 Below Nuclear Heating Date/Tjme Test Performed: 10/ 4 /4 4 0700 , Measured Parameter 1s4"8 ; Integral Worth of Shutdown Bank A, l (Description) Rod Swap j IV Test Measured Value Is4"= 9 3~7 '(Adjusted Measured Critical Reference Bank Position = IW steps) Results , Design Value Isins . c7gg, g '(Adjusted Measured Critical (Actual Conditions) Reference Bank Position = / f 2 steps) Design Value Is4"8 " 981
- 147Pcm :
(Design Conditions) (Critical Reference Bank Position = 156 steps) Reference Technical Report NE-997, Rev. O, VEP FRD-36A V FSARfrech 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 l VI Acceptance Criteria is met : t/YES NO l Comments 40 in /] , Prepared By: Reviewed By: Id./b
/
i NE-1000 NIC11 Startup Physics Tests Report Page 53 of 57
T NORTH ANNA POWER STATICN UNIT 1 CYCLE 11
' STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
I Test
Description:
Total Rod Worth.' Rod Swap Reference , Proc No / Section: 1-PT-94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 Conditions SDA: moving SDB: moving CA: moving Other(specify): (Dutgn) CB: moving CC: moving CD: moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( F): 6W# Test Power Level (% F.P.): 0 Conditions SDA: moving. SDB: moving CA: moving Other (specify): i (Actual) CB: moving CC: moving CD: moving Below Nuclear Heating : Date/ Time Test Performed: 0 20 a 10/9l4Y Measured Parameter Ir ; integral Worth of All Banks. (Description) Rod Swap IV , Measured Value Test Ir w " 6 3 e./ 3 ' Results Design Value Ir = $N r.,t 4 g ' 4 (Actual Conditions) Design Value Iru = 5450
- 545 pcm ,
(Design Conditions) Reference Technical Report NE-997, Rev. O. VEP FRD-36A V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall Acca-'ance evaluate impact of test result on safety analysis. Criteria Additional testing must be performed. Reference VEP FRD-36A
, Design Tolerance is met : [YES NO VI Acceptance Criteria is met : V YES NO Comments
_n li /i s Prepared By: Reviewed By: //M
, <o -
p-NE-1000 N1C11 Startup Physics Tests Report Page 54 of 57 ,
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
M/D Flux Map - At Power Reference , Proc No / Section: 1-PT-94.0,1 PT-21.1,1 PT-21.2 Sequence Step No: II Bank Positions (Steps) RCS Temperature (0F): Tu* 1 Test Power Level (% F.P.): s30
)
i Conditions SDA: 225 SDB: 225 CA: 225 Other(specify): (Design) CB: 225
- CD: . Must have a 38 thimbles" .
QC: III Back Positions (Steps) RCS Temperature (0F): 74,p ~ Test Power Level (% F.P.): ; p, .7 /, Conditions SDA: 225 SDB: 225 CA: 225 Other(spe:W): (Actual) - CB: 225 CC: , ,fCD: /z<y Date/ Time Test Performed: N, ,""- g
/0/M/W /0l'YE Max. Relative Nuclear E.nthalpy Rise TotalHeat Flux Maximum Measured Assembly Hot Channel Hot Possible Parameter Power Factor ChannelFac:or Incore (Description) % DIFF F.iH(N) Fg(Z) Quadrant gy Power Tilt (M P)/P i Tat !'
M'"dVAl"' M 97 Results [- Arg y Desip Value
- 10% for F.=0 9 N/A N/A s1.0203 l (Desip Conds)
- 15% for P"0 i 9 -
(P, = assy pwr) Reference' WCAP- 7905 None None WCAP-7905 Rev.I Rev.I ! V FSAR/COLR None F AH(N)s!.49(1+0J(1.P)) F@s4J8'KfZ) None Acceptance ; Reference Nane COLR 2.6 COLR 2.5.1 None Cdteda Design Tolerance is met : / YES NO Acceptance Criteria is met : / YES NO I Comments.
- As required l
" Must have at least 16 thimbles for quarter core maps i for multi-point calibrations Prepared By [N Reviewed By:
<r
( < r b- , l NE-1000 N1C11 Startup Physics Tests Report Pags 55 of 57 I 4
NORTH ANNA POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SEEET I Test Desedption: M/D Flux Map - At Power Reference , Proc No / Section: t-PT-94.0,1-PT-21.1,1-PT-21.2 Secuence Step No: l II Bank Positions (Steps) RCS Te:npemture ( F): Tu= 1 i Test Powe Level (% F.P.): 65sPs75 Conditions SDA: 225 SDB: 225 CA: 225 06e(specify): j (Design) Must have 2 38 thimbles == CB:225 CC: 225 CD: . ; III Bank Positions (Steps) RCS Temperature (CF): "Fr-4 , Test Powe Level (% F.P.): M.c2 Conditions SDA: m SDB: 225 CA: 225 O&c(specify): ; (Acmal) CB:225 CC: 225 CD: no ' a.s h@s Date/TimeTest Pe:fonned: . eojsalvt IM48 Max. Reladve Nuc!sar F.ntnaipy PJse TotalHeat Flux Maxunum i gw Assembly . Not Qanne! Hot Possfole ! Parameter Power Fac:or QannelFac:or Incore (Description) % DIFF FAH(N) Fq(Z) IV (M-PyP Quadrant PowerTilt M**'"d V*l"*
- ts ,[ 1 3
1.4 M - Ot t w Design Value
- 10% the F.d3 N/A N/A s 1.0201 (Design Conds)
- 15% ibr 7,43 (P. = assy pwr)
Reference WCAP- 7905 None None WCAP 7905 Rev.( Rev.1 I V FSAR/COLR None F AH00sl.49(!+0.3(1-P)) F4Z)s2.19/P
- L2) None Acc-ptance COM Crite:ia Reference None COL W .1 None i
Design Tolerance is met : V YES NO ! Acceptance Crite:iais met : V. YES NO VI i i Comments
- As regsd l
** Must have at least 16 thimbles for quatte core maps for multi-point calibrations Pwed By: Reviewed By: -
D. 8 ==J ; l I I NE-1000 N1011 Startup Physics rests Report Page 56 of 57 ! i
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NORTH ANNA POWER STATION UNIT 1 CYCLE I1 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Desedpcion: M/D Flux Map - At Power Re:~erence Proc No / Section: 1 PT 94.0,1 PT 21.1.1 PT 21.2 Sequence Step No: 37 II Back Positions (Steps) RCS Temperamre ( F):Tna* 1 1 Test Power Level (% F.P.): 95sPs100 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): (Design) C3:225 CC: 225 CD: . Must have a 38 thimbles *" III Bank Positions (Steps) RCS Temperature (CF): Tw Test Power Level (% F'.P.): /co.o Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): (Acmal) CC: 225 CD: ZY
. C3: 225 9's- ,4g Date/ Time Test Performed: 7G5.6 - o/~ru '
to/gifqq a. gr Max. Relative Nuc!est F.nthalpy Rise Total Hest Flux Maximum Mensured Assemoly Hot Channe! Hot Possible Parameter Power Fac.or Channel Fac or Incore (Desenpuon) % DIFF FAH(N) F,(Z) Quadrant N (M-P)/P Power Tilt R ts M M V868 ,,,( g: f, gcfy f,g33 fogy Desip Value a io% br 7,20.9 N/A N/A s1.0201 (Desip Conds)
- 13% for P.*0 9 (P, = assy pwr)
! neference WCAP. 7905 None None' WCAP 7905 Rev.1 Rev.1 l V FSAFJCCLR None F AHO41.49(14.3(1 F)) F4Z)a.2.19/P a KfZ) None Acceptance , Cdteria Reference None COLR 2.5 COLR 2.5.1 None Design Tolerance is met : X YES NO Acceptance Criteriais met : X YES NO Comments
- As required i " Must have at least 16 thimbles for quarter core maps
- for multi-point cahirations
~
Prepared By: Reviewed By: N/kT d o/ NE-1000 NIC11 Startup Physics Tests Report Page 57 of 57
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