ML18151A930
| ML18151A930 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/19/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18151A931 | List: |
| References | |
| 89-711, NUDOCS 8910260310 | |
| Download: ML18151A930 (61) | |
Text
{{#Wiki_filter:e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 19, 1989 United States Nuclear Regulatory Commission Serial No*. 89-711 Attention: Document Control Desk NUCGL:vlh Washington, D. C. 20555 Docket No. 50-280 License No. DPR-32 Gentlemen: VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION *UNIT NO. *1 CYCLE 1*0A STARTUP PHYSICS TESTS REPORT Virginia Electric and Power Company submitted the Surry Unit 1 Cycle 1 O Startup Physics Tests He.port by .an ..0ctober2B.,. lBB8JetteL(SeriaL.No_ ...BB.-:649.)~.,.Durjng . .Cycle
- 1 O,.there were .indications of fuel failure in the core . .During a mid-cycle .fuel inspection in September* 1988, a single failed fuel assembly-was iocated *and replaced. The balance of Cycle *1 O is designated as Cycle 1 OA due-to iheiuel assembly replacement.
For your information, enclosed are five *(5) copies of the Virginia-Electric and Power Company Technical Report NE-751,-.Hev. 0, entitled .Surry Unit 1, Cycle 1OA Startup Physics Tests Report." This report summarizes the results of the physics testing
*program performed *after initial criticality of .Cycle "'1 OA*on July 5, 1989. The results of the physics tests were within required design tolerances and applicable Technical Specification .limits.
Very tr.ulyyours,.
*. -. ) ; \ . : *.--.<. _).
W. L. Stewart
*senior Vice *president - -Power -Enclosure
- cc:
- U. S. Nuclear Regulatory Commission Region II
.* 101 Marietta Street, N, W.
Suite 2900 Atl_anta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 8910260310 891019
~DR ADOCK 05000280 PNU
1.~
-NOTICE-
>THE ATI ACHED FILES ARE OFFICIAL . RE-
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- OF THE RECORDS & REPORTS
.:MANAGEMENT BRANCH. ,THEY HAVE BEEN
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' **JiY*
-NOTICE-
- TECH~'ICAL REPORT NE-7 51 - Rev. 0 SURRY UNIT 1, CYCLE lOA STARTUP PHYSICS TEST REPORT
\UCLEAR ANALYSIS AND FUEL POWER ENGINEERING SERVICES VIRGINIA POWER OCTOBER, 1989 PREPARED BY: ~~42/z..C.G /q/.{/69 N. S. Pierce Date I,
'./)
./"';-
,-c/1, REVIEWED BY: ~~ -. *-t..('
D. A. Trace APPROVED BY: ~*vr~,, D. Dziadosz Date QA Category: Nuclear Safety Related Keywords: SlClOA, Startup
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 they have. been specifically _prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY '.1AKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to . this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever ( whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it .
- ~E-751 SlClOA Startup Test Report Page 1 of 58
- TABLE OF CONTENTS
. PAGE Classification/Disclaimer............................... 1 Table of Contents ........................ ; .'........... . . 2.
List of Tables... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 List of Figures......................................... 4 Preface ................................................... * .5 Section 1 Introduction and Summary ....... *****:* .. :*. 7 Section 2 Control Rod Drop Time Measurements......... 16 Sec.cion 3 Control Rod Bank Worth Measurements........ 21 Section 4 Boron Endpoint and Worth Measurements.... . . 26
- Section .5 Temperature Coefficient Measurement........ 30 Section 6 Power Distribution Measurements.......... . . 33 Section 7 References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 APPENDIX Startup Physics Tests Results and Evaluation Sheets........................ 41
- NE-7.51 SlClOA Startup Test Report Page 2 of .58
l. LIST OF TABLES TABLE TITLE PAGE
- 1. 1 Chronology of Tests .................................. . 10 2.1 Hot Rod Drop Time Summary ............................ . 18 3.1 Control Rod Bank Worth Summary ........ , .............. . 23 4.1 Boron Endpoints Summary .............................. . 28 5.1 Isothermal Temperature Coefficient Summary ........... .
6.1 Incore Flux Map Summary .............................. . 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specifications Limits ........... . 36
- NE-751 SlClOA Startup Test Report Page 3 of 58
- LIST OF FIGURES FIGURE TITLE PAGE 1.1 Core Loading Map ......... ;............................... 11
- 1. 2. Beginning of Cycle Fuel Assembly Burnups................. 12
- 1. 3 Incore Instrumeritation Locations ...... ~.................. 13
- 1. 4 Burnable Poison and Source Assembly Locations............ 14 1 :) Control Rod Locations.................................... 15 2.1 Typical Rod Drop Trace ..... :............................. 19 2.2 Rod Drop Time - Hot Full Flow Conditions................. 20 3.1 Bank B Integral Rod Worth - HZP .. : . ... .. . . . . . .. . . . .. .. . . . 24 3.2 Bank B Differential Rod Worth - HZP. .. .. .. . ......... .. . . . 25
.';.. 1 Boron Worth Coefficient..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 6.1 Assemblywise Power Distribution - 26% Power.............. 37 6.2 Assemblywise Power Distribution - 65% Power.............. 38 6.3 Assemblywise Power Distribution - 100% Power............. 39
- \E-751 SlClOA Startup Test R~port Page 4 of 58
- PREFACE The purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the Surry Unit 1, Cycle
- lGA 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 discuss the particular methods of testin.g or to present the detailed data taken. Standard *test techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at the Surry Power Station.
Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation
- of the results.
The Surry 1, Cycle lOA Startup Physics Tests Results and Evaluation
,. Sl:eets 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 conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values of the measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1
- During the tests, the data sheets were used as guidelines both to verify that the proper test conditions were met and to facilitate the preliminary comparison between NE-751 SlClOA Startup Test Report Page 5 of 58
- measured and predicted test results, thus enabling a quick identification of p6ssible probl~ms o~curin~ during the tests .
- NE-751 SlClOA Startup Test Report Page 6 of 58
SECTION 1 INTRODUCTION AND
SUMMARY
On September 14, 1988, Unit 1 of the Surry Power Station was shutdown for maintenance. During Cycle 10, there were indications of fuel failure in the core. During the outage, a'single failed assembly was located and replaced. The remaining assemblies were then moved back into the core. Since a full-core off load took place, startup physics testing was required. Due to a change in the Cycle 10 core loading, the balance of the cycle will be referred to as Cycle lOA. The Cycle lOA core consists of 19 subba tches of fuel; eight once-burned batches, one from Cycle 6
- (batch 8B7), three irom Cycle. 7 (batches 9A5, 9B5 and 9B7) and four from Cycle 9
£com Cycles (batches llAl, 11A2, 11B2, 11B3); four twice burned batches, one 6 and 7 (batch 8B3), two from Cycles 7 and 9 (batch 9B4 and 9A4), and one from Cycles 8 and 9 (batch 10A3); four thrice burned batches, one from Cycles 6, 8 and 9 (batch 8B4) and three from Cycles 7, 8, and 9 (batches 9A3,_9B3 and S2/9B2); and three fresh batches (batches 12A, 12B2 and S2/12Al). The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given_ in Figure 1. 2. The incore 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 lOA, and Figure 1.5 identifies the location and number of control rods in the Cycle lOA core . ~E-751 S1C10A Startup Test Report Page 7 of 58
j
- On July 5, 1989 at: 0647, t:he Cycle lOA core achieved criticality.
Following criticality, *st:artup 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 2.4 second limit of Surry Technical Specification 3.12.C.1.
- 2. Individual control rod bank worths for the control rod banks were measured using the rod swap technique 2 and were found to be within 7.3% of the design predictions. The sum of the individual control rod bank worths was measured to be within' 2.5% of the design prediction. These results are within the design t:olerance of
+/-15% for individual bank worths (+/-10% for the rod swap reference bank 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 24 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 4.6% of the design prediction, which is within the design tolerance of +/-10%.
- 5. The isothermal temperature coefficient for the all-rods-out configuration was measured to be within 1.96 pcm/°F of t:he design prediction. This result is within the design tolerance of +/-3
\E-751 SlClOA Startup Test Report Page 8 of 58
- pcm/ °F, and also Specification 3.1.E.l.
meets the requirements of Technical
- 6. Core power distributions for at-power conditions were within established design tolerances. Generally, the measured core power distribution was within 7.3% of the predicted power distribution. The heat flux hot cµannel factors and enthalpy rise hot channel factors, F-Q(T) and F-DH(N) respectively, were within the limits of the Technical Specification 3.12.B.1.
In summary, the startup physics test results were acceptable. Detailed results, together with specific d~sign tolerances and acceptance
- criteria for each measurement, are presented in the appropriate sections of this report .
- NE-751 SlClOA Startup Test Report Page 9 of 58
- Table 1.1 SURRY 1 - CYCLE lOA STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Te.st Date Time Power Procedure Hot Rod Drop Timing Test 7/4/89 0100 HSD l-PT-7.2 Zero Power Testing Range 7/5/89 0850 HZP l-PT-28 .11 Re.activity Computer Checkout 7/5/89 1004 HZP l-PT-,28.11 Boron Endpoint - ARO 7/5/89 1529 HZP l-PT-28.11 Temperature Coeffi~ient - ARO 7/5/89 . 1950 HZP l-PT-28.11 Bank B Worth 7/5/89 2119 HZP l-PT-28.11 Boron Endpoint - B in 7/6/89 0310 HZP l-PT-28.11 Bank D Worth - Rod Swap 7/6/89 0424 HZP l-PT-28.11 Bank C Worth - Rod Swap 7/6/89 0915 HZP l-PT-28.11 Bank A Worth - Rod Swap 7/6/89 1002 HZP l-PT-28.11 Bank SB Worth - Rod Swap 7/6/89 1111 HZP 1-PT-28.11 Bank SA Worth - Rod Swap 7/6/89 1254 HZP l-PT-28.11 Flux Map - Power Distribution 7/7/89 1929 26% 1-PT-28.2 Verification l-OP-57 Flux Map - Hot Channel Factor 7/8/89 1846 65% 1-PT-28.2 Verification 1-0P-57 Flux Map - I/E Calibracion 7/8/89 2224 65% 1-PT-28.2 1-0P-57 Flux Map - I/E Calibration 7/8/89 2357 65% l-PT-28.2 1-0P-57 Flux Map -- HFP ARO equilibrium 7/19/89 0929 100% l-PT-28.2 1-0P-57
~E-751 SlClOA Startup Test Report Page 10 of 58
I
- SURRY UNIT 1 - CYCLE lOA CORE LOADING MAP Figure 1.1 R p N H K J H F E D A I 9A !DA 9A I 2D2 I 2E2 I 2D4 I
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- I 4G6 I DF4 I IF2 I OD2 I OG3 I 2F7 I !GS I 307 I DF7 I 2F3 I 2UD I 3CO I 6
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- _ 1 _ _ 1 I_ _ I R p N H J H G F E D C A FUEL ASSEH8LY DESIGN PARANETERS SUB-BATCH 85 ,9A 98 S2/9B !DA llA llB 12A 12B S2/l 2A INITIAL ENRICHHENT 3.40 3.59 3.61 3.60 3.60 3.60 3 *. 80 3.80 3.99 3.78 (W/0 U-235)
BURNUP AT BOC JOA 20643 32202 22506 34706 33690 21697 21070 2098 2078 0 ( HWD/HTU l ASSEMBLY TYPE 15Xl5 lSXIS 15Xl5 15Xl5 15Xl5 15Xl5 lSXlS lSXlS lSX!S !5Xl5 NUHBER OF ASSEHBLIES 14 14 12 2 12 28 27* 24 23 I I RODS PER ASSEHBLY 204 204 204 204 204 204 204 204 204 204
- NE-751 SlClOA Startup Test Report Page 11 of 58
- SURRY UNIT 1 - CYCLE lOA BEGINNING OF CYCLE FUEL ASSEMBLY BURUNUPS Figure 1.2 R p N H K J H G F E D C A 2D2 2E2 2D4 I I 349731 311321 349401
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NE- 7 51 SlClOA Startup Test Report Page 12 of 58
- SURRY UNIT 1 - CYCLE lOA INCORE INSTRUMENTATION LOCATIONS Figure 1. 3 R p H H K J H G F E D C B A HD I I TC I I
- - ~ - - - - - - - - 1 _ _ 1_ _ _ __
I I HD I I I I .1 I I TC I I 2 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ I HD I I I HD I HD I I I I HD I I TC I I I TC .I TC I I I I TC I 3 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ I I I HD I I I I I I I I I I I I TC I I I TC I I I I I I 4 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ I I HD I I HD I I I I I I HD I HD I I HD I I I TC I I TC I I I I I I TC I TC I I TC I 5 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1_ _ 1 _ _ 1 _ _ 1 I I I I 110 I I I I I HD I I I I I I I I I TC I I I TC I I TC I I I I I 6 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1_ _ 1_ _ 1 _ _ 1 _ _ I I I HD I I I I HD I I I I I HD I I HD I I I I I TC I I I I TC I I TC I I I TC I I TC I I 7 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 I HD I I HD I I HD I I I I I HD I I I HD I HD I I I TC I I TC I I TC I I I I I TC I I I TC I TC I I 8
, _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 I I I I I HD I I I I HD I HD I I I I I HD I I I I I I TC I I _ I I TC I TC I I I I I TC I 9
, _ . _ , _ _ , _ _ , _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 I I HD I I I I HD I I I I I HD I I HD I I I TC I I I I TC I I I I I TC I I TC I lO 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 I I I I HD I I I HD I I HD I HD I I I I I I I I TC I I I TC I I TC I TC I I I I 11 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1_ _ , _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 I HD I I I I HD I I I I I HD I HD I I TC I I I I TC I I I I I TC I TC I 12
. 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ , _ _ , _ _ 1 _ _ 1_ _ 1 _ _ 1 I I I I I I I HD I I I I I I I I I I TC I I I 13
, _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ _ 1 _ _ 1 _ _ 1_ _ 1_ _ 1 I HD I I I I HD I I I I TC I I I I TC I I I 14 I _ _ I _ _ I _ _ I _ _ I _ _ I_ _ I _ _ I
' I HD I I I I TC I I I 15 I _ _ I_ _ I _ _ I HD - Movable Detector TC - Ther*ocouple
~E-751 SlClOA Startup Test Report Page 13 of 58
f
- SURRY UNIT 1 - CYCLE lOA BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS Figure 1. 4 R p N H K J H G F E D C B A I
I I I I _ _ _ _ _ 1 _ _ 1 _ _ 1 _ . _ 1 _ _ _ __ I I I I I I I 3P I I 3P I I I 2 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ I I I I I I I I I I I I 4P I 16P I I SSl I I 16P I 4P I I 3 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ I I I I I I I I I I I I I I I 16P I I 20P I I 20P I I 16P I I I 4 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ I I I I I I I I I I I I I I I I 4P I 16P I I 4P I I 4P I I 4P I I 16P I 4P I I 5 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 I I I I I I I I I I I ! I I I I 16P I I 4P I I 20P I I 20P I .I 4P I I !SP I I 6 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ I I I I I I I I I I I I I I I I 3P I I 20P I I 20P I I I I 20P I 20P* I 20P I I 3P I I 7 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1_ _ 1 _ _ 1_ _ 1_ _ 1_ _ 1 I I I I I I I I I I . I I I I I I I I I 4P I I SS7 I I I I 4P I I I I I 8 1 _ _ .1 _ _ 1 _ _ 1 _ _ 1 _ _._1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 I I I I I I I I I I I I I I I I I I 3P I I 20P I I 20P I I I I 20P I I 20P I I 3P I I 9 1_ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 _ _ 1_ _ 1 I I I I - I I I I I I I I I I I I 16P I I 4P I I 20P I I 20P I I 4P I I 16P I I Io 1 _ _ 1_ _ 1 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 _ _ 1_ _ 1_ _ 1_ _ 1 _ _ 1_ _ 1 I I I I I I I I I I I I I I I I 4P
- I 16P I I 4P I I 4P I I 4P I I 16P I 4P I I 11 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 I I I I I I I I I I I I I I I 16P I I 20P I I 20P I I 16P I I I 12 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1 I I I I I I I I I I I I 4P I 16P I I SS2 I I 16P I 4P I I 13 I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I_ _ I _ _ I _ _ . I I I I I I I I I I I I 3P I I 3P I I I 14 1 _ _ 1 _ _ 1 _ _ 1 _ _ 1_ _ 1 _ _ 1 _ _ 1 I I I I I I I I 15 I _ _ I_ _ I_ _ I 3P -- 3 BURNABLE POISON ROD CLUSTER 4P -- 4 BURNABLE POISON ROD CLUSTER ISP -- 15 BURNABLE POISON ROD CLUSTER 16P -- 16 BURNABLE POISON ROD CLUSTER 20P -- 20 BURNABLE POISON ROD CLUSTER 20P* 20 DEPLETED BURNABLE POISON ROD CLUSTER SSX -- SECONDARY SOURCE NE-751 SlClOA Startup Test Report Page 14 of 58
Figure 1. 5
. SURRY UNIT 1 - CYCLE lOA CONTROL ROD LOCATIONS R p N H L K J H G F E D C B A 1:80 D I
Loop C I I I I Loop B 1 Outlet I I I I Inlet
............ I I.A I __ I_D_l--1 A I I / 2
~_l_l_l_l_l_i_l<<'.:._
N-41 I *I I I SA I I SA I I I I N-43 3 __I_I_I_I_I_I_I_I_I_I_ I I C I I B I I I I B I I c I I 4 _I_I_I_I_I_I_I_I_I_I_I_I_ I I* I I SB I I SP I I SP I I SB I I I I 5 1_1 __ 1_1_1_1_1 __ 1__ 1_1_1_1_1 __ 1 IAI IBI IDI ICI IDI IBI IAI 6 Loop C __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I __ I__ Loop B Inlet I I I* SA I I SP I I SB I I SB I I SP I I SA I I I Outlet 7
'\...I I I I I I I I I I I I_I_I 1* IA 90 °- ')t.i I D I I I I c I I I I c I I I I D I r"- 270 ° 8 I_I_I_I_I_I_I_I_I_I_I_I_I_I_I_I I I I SA I I SP I I SB I I SB I I SP I I SA I I J 9 1_1_1_1_1_1_1_1_1_1_1_1_1_1_1_1 IAI IBI IOI ICI IDI IBI IAI 10 1_1_1_1_1_1_1_1_1_1_1_1_1_1 I I I I SB I I SP. I I SP I I SB I I I I 11 1_1_1_1_1_1_1_1_1_1_1_1_1_1 I I c I I B I I I I B I I c I I 12 I_I_I_I_I_I_I_I_I_I_I_I I I . I I SA I I SA I I I I 13 N-44 I __ I __ I __ I_-_I __ I __ I __ I __ I __ I N-42 I I A I I D I I A I I 14 J_1_1_1_1_1_1_L
~ I I I I "\. 15 Loop A I I I I Loop A Absorber Outlet -- -- -- Inlet Material Ag-In-Cd Function Number of Clusters Control Bank D 8 Control Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 SP (Spare Rod Locations) 8
~E-751 SlClOA Startup Test Report Page 15 of 58
- SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow RCS conditions in order to confirm satisfactory operation and to verify that the time from initiation of.the rod drop to the entry of the dashpot be less than the maximum allowed by the Technical Specification 3.12.C.l.
The hot control rod drop time measurements were run with the RCS at hot, full flow conditions (547°F, 2235 psig). The rod drop time measurements were performed by first withdrawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod. This allows the rod to drop into the core as it would in a normal plant trip. The data recorded during this test are the stationary gripper coil voltage and the LVDT (Linear Variable Differential Transformer) primary coil voltage.* The rod drop time is determined from this data. Figure 2.1 provides an example of the data that is recorded during a rod drop time measurement. As shown in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary coil fuse is removed. A voltage is then induced in the LVDT primary coil as the rod drops. The magnitude of this voltage is a function of the rod velocity. When the rod enters the dashpot section of its guide tube, the velocity slows causing a voltage decrease in the LVDT coil. The LVDT voltage then reaches a minimum as the rod reaches the bottom of the NE-751 S1C10A Startup Test Report Page 16 of 58
dashpot. Subsequent variations in the trace are caused by the rod bouncing. This procedure was repeated for each control rod. 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 3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 seconds with the RCS at hot, full flow conditions. The test results met this limit. NE-751 SlClOA Startup Test Report Page 17 of 58
- Table 2.1 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS HOT ROD DROP TIME
SUMMARY
ROD DROP TIME TO DAS HP OT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME K-04,H-06, F-14,B-08 1. 25 sec. G-07,F-02
- 1.17 sec . 1. 20 sec.
- ROD DROP TIME TO BOTTOM OF DASHPOT SLOWEST ROD FASTEST ROD . AVERAGE TIME
- B-08 1. 8 7 sec . P-10 1. 74 sec. 1.80 sec.
- \E-751 S1C10A Startup Test Report Page 18 of 58
z M
- FIGURE 2.1
.....,I \Jl TYPICAL ROD DROP TRACE 51ATION~R'f GRIPPER COIL \Jol&L!~---- BOTTOM ~ l>A~" 10T l ENlR'C' INTO DN:.11 fOT 4
~s"
.4 1MT "TO ROD goTTOH TIH DROP TIME m 0,..S" POT 0
t-t,
\Jl 00
- SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS Figure 2. 2 R p H H G F E D C A I 1 I I 1 I I_ _ I_ _ I _ _ I
---1,---,-1-.1'""'9-1 I 1. 19 I 1--,--1....,,1""7-, -
1 1. 77 I I 1. 81 I I i. 79 I 2 _ _ _ _ l _ _ l _ _ l _ _ l _ _ l _ _ l _ _ __ I I 1. 20 I I 1. 20 I I I I 1. 80 I I 1. 78 I I 3 _ _ _ _ _ _ I _ _ I_ _ J_ _ I _ _ I _ _ I _ _ I _ _ I _ _ I I 1. 20 I I 1.17 I I I .I 1. 20 I I 1.19 1 I I I 1. 75 1 1 1. 77 I I I I 1. 79 I I 1. 77 I I 4 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ I I I 1.19 I I I I I I 1. 20 I I I 1* I I I I. 78 I I I I I I 1. 80 1 I I I 5 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I 1. 18 I I 1. 19 I I 1. 19 I I I. 17 I I 1. 19 I I I. 19 I I 1. :3 I 11.781 11.811 11.771 11.791 11.861 11.781 il.861 6 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ I I 1. 18 I I I I 1.19 I I 1.17 I I I I 1.19 I I I I l!.801 I I 11.841 11.751 I I 11.811 I I 7 l __ l__ l __ l __ l __ l . I_ _ I_ _ I_ _ I _ _ I _ _ I _ _ I _ _ I _ _ I_ _ I I I 1. 24 I I I I 1. 20 I I I I 1. 22 I I I I 1. 25 I I I 11.821 I I 11.821 I I 11.801 I I 11.871 I 8 l __ l__ l __ l__ l __ l __ l__ l__ l __ l __ l __ l __ l__ l __ l__ l I I 11.221 I I 11.201 11.211 I* I 11.181 I I I I I 1. 80 I I I I 1. 78 I I 1. 83 I I I I 1. 76 I I 1 9 I . I__ I__ I__ I__ I__ I__ I
- I__ I__ I__ I__ I__ I__ I__ I I 1.19 I I 1.19 I I 1. 20 I I 1. 21 I I 1. 22 I I I. 20 I I 1. 20 I 11.741 11.791 11.821 11.801 11.861 11.811 11.851 10 I _ _ I _ _ I _ _ I _ _ I _ _ I_ _ I _ _ I _ _ I _ _ I _ _ I_ _ I _ _ I 'I I I I I 1. 18 I I I I I I 1. 20 I I I I I I I I 1. 78 I I I I I I 1. 77 I I I I 11 I _ _ I _ _ I _ _ I _ _ I _ _ I_ _ I_ _ I_ _ I _ _ I _ _ I I__ I__ I I 11.191 11.181 I I 11.201 11.221 I I 11.791 11.801 I I 11.791 11.811 I 12 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I 1.18 I I 1. 20 I I I I I I I I 1. 76 I I 1. 80 I I I I 13 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I. 22 I I I. 20 I I 1. 25 I I I 11.821 11.821 11.861 I 14 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I I I I I 15 I _ _ I_ _ I_ _ I 1~1--> ROD DROP TIHE TO DASHPOT EHTRY CSECJ I X.XX 1--> ROD DROP TIME TO BOTTOM OF DASHPOT CSECJ I I
\E-751 SlClOA Startup Test Report Page 20 of 58
- SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worth measurements were obtaiD~d for the control and shutdown banks using the rod swap technique 2
- The first step in the rod 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 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 (Control Bank B) .
- At the measurement, completion the reactor of the coolant reference system bank reactivity temperature concentration were stabilized such that the reactor was critical with the and worth boron 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 (HCP) of the reference bank with the test bank fully inserted is the major
- parameter of interest and was used to determine the integral reactivity worth of the test bank. _ Statepoint data (core reactivity, moderator
~E-751 SlClOA Startup Test Report Page 21 of 58
temperature, and the differential worth of the reference bank) were recorded with the reference bank at the HCP. The rod swap maneuvei was then performed in reverse order such that the reference bank once 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 the other control rod banks (control and shutdown). 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 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 and +/-15% for the test banks). The sum of the individual I_ rod bank worths was measured to be within 2.5% of 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 differential reactivity worths of the reference bank (Control ~ank 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 .
~E-751 SlClOA Startup Test Report Page 22 of 58
Table 3.1 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
SUMMARY
MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH (%) BANK (PCM) (PCM) (M-P)/P X 100 B-Reference Bank 1271. 6 1271 0.05 D 1153. 7 1089.6 5.88 C 916.8 854.7 7:27 A 331. 1 353.4 -6.31 SB 1068.9 1017.3 5.07 SA 953.3 971. 2 -1. 84 Total Worth 5695.4 5557.2 2.49 ~E-751 SlClOA Startup Test Report Page 23 of 58
Figure* 3.1 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS BANK B INTEGRAL ROD WORTH - HZP BANK B WITH. ALL OTHER RODS OUT 2400 MEASURED I I I I I PREDICTED I I ' I I I. I I 2000 I I I I j I I! I I I I I I I I I I I I I I I I I' I I I I I I I I I I I I I I ! I i I I I I I I I ' I: I I i I I , I I I I I I I I I : I I I I I
'I .~ I I I I! I! I i ' I I I I I i j I I I I I I I I I I I 2 1600 ! I I I I I I ! I ! i I I u
r, I i' I/ I I I I I I I
, I I
I I I I I I I I i Ii I I I I I I I I I ! I I I I
! I I I I I I I f- ,I I I I I I I er: 1 11 1 1
'H--i-+f-"'":+-,.-""'=~i-"i: -+.+-t--i--f---H-H+-H-++-H-+H++-H-+H-++H+-H-++H+-H ! I I i I 0 -1 200 ! I I id'
- ,,~: t I I i ! I :
I ; s I I I _-...;.i,. i
- I I I I I I I I I i I I I I I I I I I, I I I "Cl!' I
- l. t I I I , I I I I I ~ " I I I I I I I I I I
! Ii l *H1' ! I I I! I \ :'!::* I I E.00 I' I
,, I "i IL I ' I I I I I I I I I! i I I
'I I I
' I I I I I I I I i I ! I i ! I I I I I I*
I I I I! I I! I I ' I
! ! i I I '
I I I I I I I I I I I I I 400 I j I I
'/ I i I I I I t I I I I! I I '
I I I I I I ' I I I I I I ~II
! ! I I
- i I I'
I I I I i '"""'" I! I I I I I I I I ! I I I I I 1 ! Ii I I I I I I ..c I i I I I I I I I I i I I I I I I : " " ~.... 11,... 0 I'
.4,,\ !
120 160 2cc STEPS //1TrlDRAWN (STEPS)
- NE- 7,51 SlClOA Startup Test Report Page 24 of 58
- *suRRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS BANK B DIFFERENTIAL ROD WORTH - HZP Figure 3.2 BANK B WITH ALL OTHER RODS OUT 12 MEASURED I
I I I I I I I I
'TlI i
i ! I I II I I j j I I I I I I I I I I I I I I : I I I I I 11 I PREDICTED I I I 1,: I I I I I I! !' I I I ! l ' I I I ! I I
*10 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 i I I I I I I' i I I I I I
' I I I I I 11 i I I I I I I I I I I I I I I I, 1,1 I I I CL I 1-,, I w I I I i I I I ,,
.,, I l'l'I.
I I en I I I
~ 8- I I I I I I I l I !' I I I i I ' I I I I 2 I I I I I I I I , I I I I I I u I I I I I I I Q_ I I I i I I I I
,._,.. I I l I I I I Ii T i,*t 1 ll- I
,- I I I I 11 T I I i I
'I ' ! I I I!
1 I I I i I I I I I I I I *1 I U::: r ! I I I I I I I 11 0 0 I I , .j I Ii I
,,i I I I s i I I I I
~:J II
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_J I I I I I I j\
<( I i I I -) I I I I I : I I I f- 11 z 'I 'I I
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I' I i I I i I I w 4 I '. I I ii., I I I I I I 1 i I \' I 0::: I ii j I I I I
/" I I
I I I I I I ! w ' I 111 ' .,I LL I I LL i I D
,,I I I
1,." i I ' I I I I I I I
? I
i' I I I: I I I I I I ~ I'
'Ii i I I I i I -{I, I I I I 1*1 I I I I" ) I I I I I ,i
! i *~,I I I I I I I ! I i I I ! 1 I
)
' I 1, I I I I i .,..,, I I I
, 'I I I I I I I I I I
I 11 I I I 1 I I I I i I I I I I i I I I I I I I I ! 0 ~. I'
'-' ..10 80 120 160 200 S1EPS \NITHDRAWN (STEPS~: C *
- NE-751 SlClOA Startup Test Report Page 25 of 58
- . SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpojnt With the reactor critical at hot zero power, reactor coolant system boron concentrations were measured at selected rod bank configurations to enable a direct: comparison of measured boron endpoints wit:h design predictions. For each measurement, the RCS condit:ions were st:abilized with the control banks at or very near a selected endpoint position. The critical boron concent:ration was then measured. If necessary, an 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. 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 . A plot of the boron concentratibn as a function *of integrated reactivity can be constructed by relating each endpoint concentration to the integrated rod worth present in the core at the time NE-751 S1Cl0A St:artup Test Report Page 26 of 58
- of the endpoint measurement. The value of the boron coefficient, over the range of boron endpoint concentrations, is obtained directly from this
- plot.
The b~ron worth piot is shown in Figure 4.1. As indicated in this figure and in -the Appendix, the boron worth coefficient was measured to be -7.52 pcm/ppm. The measured boron worth coefficient is within 4.6% of the predicted value of -7.88 pcm/ppm and is within the design tolerance of +/-10%. In summary, the measured boron worth was satisfactory.
~E-751 SlClOA Startup Test Report Page 27 of 58
l Table 4.1 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
I I
'.1easured Predicted Difference Control Rod Endpoint: Endpoint I '.1-P Configuration (ppm) (ppm) (ppm)
ARO 1427 1451 -24 B Bank In 1258 1266 7
-8
- The predicted endpoint for the B Bank in configuration has been 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 Sheets in the Appendix .
\E-751 S1C10A Startup Test Report Page '.:8 of 58
- SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS Figure 4.1 BORON WORTH COEFFICIENT Measured Diffeeential Boron Worth= -7.52 pcm/ppm ENDPOINT 1400 I I I*'
MEASUREMENTS
- 200 I'\.' r , ,
I I I I 2 1000 I I '\.II 1 u I t I I 1, Q_
'--" I, I I f-800 f-u
<(
w I I Ct'. 600 I ' " 400 200 *
- p::::::i::+=µ:::;:::,++-;_.;.,~ . -+++-H-+++-H-+++-H-t+t-H+t-t-t-rld-t-tti-t::tt::t:J:::i:1
'I i , I 1320 1360 . 1400 1440 2*~)C?ON CONCENTRATION (PPM)
- NE-751 S1Cl0A Startup Test Report Page 29 of 58
- SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The* isothermal temperature coefficient ( ITC) measurement at the all-rods- out condition is accomplished by controlling the RCS heat gains/losses with the steam dump valves to the condenser, and/or st~am generator blowdown, establishing a constant and uniform heatup/cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer. This measurement was performed at a very low power level in order to minimize the effects of non-uniform nuclear heating, thus, the moderator and fuel were approximately at the same temperature (between 543°F and 547°F) during these measurements.
Reactivity measurements were taken during the 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.
\E-751 SlClOA Startup Test Report Page 30 of 58
design tolerance of +/-3 pcm/ °F and met the requirements of Technical Specification 3.1.E.l. In summary, the measured result was satisfactory . NE-751 SlClOA Startup Test Report Page 31 of 58
Table 5 .1 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
ISOTHERMAL TEMPERATURE COEFFICIENT BANK TJ;:MPERATURE BORON (PCM/°F) POSITION RANGE CONCENTRATION ( OF) (ppm) COOL HEAT
- DIFFER.
DOWN UP MEAS. PRED. (M-P) 546.5 D/219 to 1425 -3.50 --- -3.61 -5.57 1. 96 543.5 543.4 D/219 to 1425 --- -3.65 -3.61 -5.57 1. 96 546.0
** D/219 546.2 to 543.2 1425
*=AVERAGE OF THREE MEASUREMENTS
-3.67 --- -3.61 -5.57 1. 96 NE-751 SlClOA Startup Test Report Page 32 of 58
- 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 44 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 computer program, INCORE 3
- INCORE couples the measured flux map data wi.th 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 distribution parameter values are compared with their Technical Specifications limits in Table 6.2. Flux Map 10 was taken at 26% power and served as the base case design check. Flux maps 11 and 16 were taken a.t different power levels and control rod configurations. These flux maps were taken to check the at-power design predictions and to measure core power distributions at various operating conditions. The radial power distributions for the full-core maps are given in Figures 6.1, 6.2 and
- 6.3. These figures show that the measured relative assembly power values are generally within 7.3% of the predicted values.
NE-751 SlClOA Startup Test Report Page 33 of 58
'* In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the Technical Specification limits. It is therefore anticipated that the core will continue to operate safely:throughout Cycle lOA . NE-751 SlClOA Startup Test Report Page 34 of 58
- TABLE 6.1 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS INCORE FLUX MAP
SUMMARY
I I I I I I l 2 I I I I I I I - I I BURN( I I F-QCTJ HOT F-DHCNJ HOT I CORE FCZJ I 3 I I I I HAP (HAPI I UP I IBANK I CHANNEL FACTOR CHHL.FACTOR I HAX I ClPTR f AXIALI HO. ( I DESCRIPTION (HO. I DATE I HWD/IPWRI D I I I I I OFF I OF I I I I I HTU IC%J(STEPS1ASSYIPINIAXIALI IASSYIPIHIF-DHCHJIAXIALI FCZJI HAX ILOCI SET ITHIHI I I I I I I I I IPOIHTIF-CCTJ I I I IPOIHTI I I I C%J IBLESI l _ _ _ _ _ _ _ l _ l _ _ _ l _ _ l _ l _ _ l_l..:_I _ _ I _ _ I _ I _ I _ _ _ I _ _ I _ _ I _ I _ I _ _ I _ I ILOW POWER I 101 7°07-8911850 I 261 133 I Ll3J IHI 35 I 2.118 J Ll31 IHI l.549 I 36 Jl.333Jl.006J SEJ-13.381 44 I raTPR 1/ERIFICATIOH I 111 7-08-8911900 I 651 154 I K 61 DEi 34 I l.984 I H 51 DEi l.470 I 33 ll.296Jl.0081 SWJ -7.951 44 I JHOT FULL POWER I 161 7-19-8912102 JIOOJ 195 I E 81 HII 35 I 1.792 I E 81 HII l.442 I 34 ll.203Jl.OlOI SEJ -3.301 44 I I l_l ___ l __ l_l __ l_l_l __ l _ _ l_l_l ___ l __ l __ l __ l_l __ l_l NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIIIIHG ASSEHBLY LOCATIONS (E.G. H-8 IS THE CENTER-OF-CORE ASSEHBLY), FOLLOWED BY THE PIH LOCATION (DENOTED BY THE "Y" COORDINATE WITH THE SEVENTEEN ROWS OF FUEL RODS LETTERED A THROUGH RAND THE '"X" COORDINATE DESIGNATED IHA SIHILAR HANNER!. IN THE '"Z" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROH THE TOP OF THE CORE. I. F-Q(T) INCLUDES A TOTAL UNCERTAINTY OF 1.08;
- 2. FDHCNJ INCLUDES A TOTAL UNCERTAINTY OF 4%.
- 3. QPTR - QUADRANT POWER TILT RATIO.
- 4. HAPS 12-15 WERE QUARTER-CORE FLUX HAPS TAKEN FOR !NCORE/EXCORE CALIBRATION. CI/E CALIBRATION)
\IE-751 SlClOA Startup Test Report Page 35 of 58
- Table 6.2 SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TE_STS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS F-Q(T) HOT . F-DH(N) HOT CHANNEL FACTOR* CHANNEL FACTOR MAP NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN
(%) (%) 10 2.12 4.64 54.4 1. 55 1. 90 18.4 11 1. 98 3.57 44.7 1. 47 1. 71 14.0 16 1. 79 2.32 22.3 1.44 1. 55 7.1
- 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* value of F-Q(T) in the core.
The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T). The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each
!Tlcip. The measured F-Q(T) hot channel factors include 8% total uncertainty . \E-751 SlClOA Startup Test Report Page 36 of 58
- SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION Figure 6 .1 26% POWER R p K J H G F E D C B A PREllICTED 0.25 0.29 0.25 PREDICTED HEASUREO . 0.27 . 0.31 . 0.27 . MEASURED
. PCT DIFFERENCE. 6.4 . 5.8 . 5.3 . .PCT DIFFERENCE.
0.33 0.65 1.08 0.82. 1.05 0.66 0.33
. 0.36 . 0.64 . 1.08 . 0.82 . 1.10 . 0.68 . 0.35 . 2 7.4 . -O.l . 0.1 . -0.4 . 1.7 . 3.3 . 5.1 .
0.36 1.12 1.23 1.20 1.24 1.20 1.23 1.11 0.35
. 0.38 . 1.15 . 1.23 . 1.18 . 1.18 . 1.17 . 1.28 . 1.18 . 0.38 . 3 6.4 . 2.8 . -0.7 . -0.9 . -5.l . -2.3 . 3.3 . 6.1 . 7.9 .
0.36 0.80 1.27 1.24 1.28 1.33 1.27 1.23 1.26 0.78 0.35
. 0.37. 0.82. 1.27. 1.23 . 1.25. 1.28. 1.19. 1.21 . 1.27. 0.80 . 0.37 .
2.0 . 1.7 . -0.6 . -0.4 . -2.4 . -3.6 . -6.0 . -1.4 . 1.4 . 2.3 . 5.2 . 0.34 1.13 1.28 1.24 1.19 1.30 1.29 .* 1.25. 1.17 . 1.22 1.25. 1.11 0.33 .
. 0.33 . 1.11 . 1.28 . 1.25 . 1.20 . 1.32 . 1.21 . 1.32 . 1.18 . 1.21 . 1.24 . 1.15 . 0.36 . 5
. -1.4 . -1.4 . -O.l . 1.1 .. 0.6 . 1.3 . -6.0 . 2.6 . 0.6 . -1.0 . *0.9 *. 3.9 . 8.6 .
0.66 1.25 1.24 1.19 1.13 1.18 1.20 1.17 1.11 1.17 1.22 1.23 0.65
. 0.66 . 1.24 . 1.25 . 1.21 . 1.14 . 1.19 . 1.22 . 1.20 . 1.12 . 1.16. 1.20 . 1.23 . 0.66 . 6
. -1.2 . -1.2 . 0.2 . 1.4 . 1.4 . 1.2 . 1.3 . 2.4 . 1.4 . -0.2 . -1.4 . -O.l . 1.3 .
0.25 1.09 1.21 1.28 1.30 1.18 1.00 1.23 0.99 1.16 1.22 1.26 1.20 1.09 0.25
. 0.27. 1.10 . 1.20 . 1.27. 1.30 . 1.19 . 1.02. 1.25. 1.01 . 1.19. 1.23. 1.23. 1.15. 1.03. 0.24. 7 4.9. 0.3. -1.2. -0.8. 0.2. 0.6. l.3. 1.3. 2.5. 2.4 . 0.5 .. -2.3. -3.7. -5.3. -4.4 .
..o: 30 ... o: 84 ... i: 26 ... i: 34 ... i: 29 ... i: 20 ... i: 23.:. i: 24.:. i: 23.:. i: i 9.: ,* i: 29 ... i: 32 ... i: 24 ... o: 83 ... o: 29 ..
. 0.31 . 0.84. 1.23. 1.33. 1.28. 1.20 . 1.25. 1.27. 1.26. 1.22. 1.29. 1.28. 1.19. 0.81 . 0.29. 8 4.6 . 0.4 . -2.2. -1.2. -0.8. -0.l . 1.3. 2.8. 2.3. 2.2. 0.3. *-3.2. -3.9. *2.4 . O.l .
0.26 1.10 1.21 1.28 1.30 1.17. 1.00 . 1.23. 1.00. l.17. 1.29. 1.27 1.20 1.08 0.25
. 0.27. 1.10 . 1.18. 1.27. 1.29. 1.16. 0.97. 1.25. 1.03. 1.17. 1.30 . 1.26. 1.19. 1.10 . 0.27 . 9 4.9. 0.1 . -2.5. -1.3. -0.2. -1.0 ~ -2.5. 1.6. 3.3. -o.o . 0.7. -0.8. -0.8. 1.4. 5.4 .
0.66 1.25 1.24 1.19 1.12 1.18 1.21 1.18. 1.12. 1.18 1.24 1.24 0.66
. 0.65 . 1.21 . 1.22 . 1.18 . 1.11 . 1.15 . 1.21 . 1.20 . 1.13 . 1.19 . 1.25 . 1.27 . 0.68 . 10
. -2.6. -2.7. -1.3. -0.2. -1.3 . -2.3. 0.2. l.~. 0.5. 0.5. 1.3. 2.2. 3.5.
0.34 1.12 1.26 1.23 1.18 1.29 1.30 1.30. 1.19 1.24 1.28 1.12 0.34
. 0.35 . 1.17 . 1.29 . 1.22 . 1.16 . 1.27 . 1.29 . 1.31 . 1.20 . 1.25 . 1.32 . 1.18 . 0.35 . 11 4.3 . 4.3 . 2.2 . -0.4 . -1.7 . -1.7 . -0.2
- 0.4 . 0.5 . 0.9 . 3.6 . 5.2 . 5.3 .
0.36 0.79 1.26 1.23 1.28 1.34 1.29 1.25 1.28 0.81 0.36
. 0.40 . 0.84 . 1.25 . 1.21 . 1.25. 1.33 . 1.25 . 1.23 . 1.30 . 0.86 . 0.39 . 12
. 11.3 . 6.7 . -0.5 . -1.9 . -2.5 . -1.2 . -0.9. -1.1 . 1.2. 5.6 . 8.3 .
0.35 1.11 1.24 1.21 1.26 1.21 1.26 1.13 0.36
. 0.39 . 1.20 . 1.27 . 1.18 . 1.19 . 1.15 . 1.21*. 1.13 . 0.39 . 13 9.5 . 7.7 . 2.5 . -2.8 * -5.l . -5.4 . -4.0 . -0.0 . 6.9 .
0.33 0.66 1.11 0.84 1.10 ~.66 0.34
. 0.35 . 0.70 . 1.16 . 0.51 . 1.02. 0.63 . 0.33 . 14 7.7 . 6.6 . 4.6 . -3.0 . -6.9 . -5.4 . -3.7 .
STANDARD 0.26 0.30 0.26 AVERAGE DEVIATION . 0.27. 0.30. 0.24. .PCT DIFFERENCE . 15
=2.351 4.5. -0.3 . -7.4 . = 2.6 SUHHARY HAP HO: Sl-10-10 DATE: 7/7/89 POWER: 25.7%
COHTROL ROD POSITIONS: F-Q(TJ 2.118 QPTR: D BANK AT 133 STEPS F-DH(HJ 1.549 NW l. 000 HE 0.991 FCZJ 1.333 SW l. 003 SE 1.006 BURHUP l, 850 HWD/HTU A.O. = -l3.3n7. NE-751 SlClOA Startup Test Report Page 37 of 58
I
- SURRY UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS Figure 6.2 ASS.EMBLYWISE POWER DISTRIBUTION 65% POWER R p H 11 K J H G F E D C B A PREDICTED 0.28 0.33 0.28 PREDICTED MEASURED 0.28 0.33 0.28 t1EASURED
. PCT DIFFEREHCE. -0.5 -0.8 -0.4 .PCT DIFFERENCE .
0.35 0-:67 l..10 0.89 l.ll 0.68 0.35 0.37 0.66 l.08 0.86 .l.09 0.68 0.35 2 5.8 -0.6 . -1.9 . -2.6 * -l.7 . -0.2 l.5 0.37 1.10 1.21 1.19 1.25. 1.19 1.21 1.10 0.37 0.39 1.12 1.19 1.17 1.19 . 1.15 l.21 1.13 0.38 3 5.0 1.9 -1.l -1.3 -4.8 . --3.4 -0.2 2.4 4.1 0.37 0.81 1.24 1.21 1.25 1.31 l..24 1.21 1.23 0.79 0.37 0.38 0.82 . 1.23 . 1.21 . 1.21 . 1.26. 1.17
- 1.20
- 1.24 . D.80 . 0.37 4 1.5 l.2 . -0.8 . -0.6 * *2.5 . -3.6 . -5.-5 * -0.9 . 0.6 . l.l . 2.0 0.35 1.11 1.24 l.22 1.19 1.28. 1.27 1.28 1.18 1.21 1.23 1.10 0.35 0.35 1.09. . 1.24 . 1.24
- 1.20
- 1.31 . 1.20 . L3D . 1.19 ** 1.20 . *1:z:z . 1.11
- 0.36 5
-1.3 -1.3 . 0.1 . 1.:z . o.9 . 1.-9 .-~5.5 . -,:,3*. -*o.fl * ~o.6 . --0.1 . 1.0 . 2,6 0.68 1.22 1.21 1.19 1.17 1.18 1.20 1.17 1.16 1.17 1.20 1.21 0.67 0.67 1.20 1.22 1.21 1.19 1.20 1.23 1.20 1.18 1.17 1.19 1.19 0.66 6
*L4 . *-1.4 . 0,5 . 2.1 .* 2.0 .. 1.8 . 1.9 . 2.1 . l.3 . . O.l ; o0.9 * -1.4 . -1.9 0.28 1.11 1.20 . 1.25 1,28 1.18 1.03 1.25 1.01 1.17 1.21 1.23 1.19 1.11 0.28 0.28 l.lO .* 1.18 . 1.24 1 . .30 1.20 l.04 1.27 1.04 1.20 1.22 1.22 1.14 l.05 0.26 7 0.2 *LZ *l.7 . *0.5 l.'3 1.5 1.*9 2.0 2.7 2.6 l.l *l.5 -4.l *6.0 *5.7 0.33 0.89 1.25 1.31 1.27
- 1.20 1.25 1.26 1.25 . 1.20 1.27 1.30 1.25 0.89 0_33 o.33
- o.88 . *i;-23
- 1:*30 * *1.7a . 1.22
- 1.21 . L3l> .*1:29 . *i:*n . 1:n .* 1:n . 1:1'9 . *0:115 . l>*.-:sz *8
-0.l * *l.5 . *2.2 . -0.6 . 0.6. l.l . 2.0. 3.1 . 3 . ( . 3.1
- 1.4 * *2.8 . *4.3 . -4.7 . -3.l 0.211 . 1.12 1.20 1.25 1.28 1.18 1.02 1.25 1.02 1.18 1.27 1.24 1.19 1.11 0.211 0.28. 1.10 1.18 1.24 1.29 1.18 l.OZ 1.29 1.06 1.19 1.30 1.23 1.17 1.09 0.28 9 0.2 . -~l..l . *l.8 . -0 * .3 * . 1.0
- 0.5 * **O.l
- 2.6
- 3.8 . .1.7 . l . 7 . *1.0 . *2.0 * *1.5
- 0 * .5 0.68 1.22 1.21 l.18 1.17 1.18 1.20 1.18 1.17 1.18 1.21 1.21 . 0.68 0.67: 1.20 1.21
- 1.19 1:11 .l.18 l.2.3 1.21 *1.19 1.20 1.22 l.23 . 0.68 10
*l.4 -l.5 -0.2 0.7 0.0 0.0 1.7 2.5 2.0 1.4 1.1 1.0_. l.O 0.35 1.10 1.23 1.21 1.18 1.28 1.27 1.28 1.19 1.22 1.24 1.11 0.35 0.36 1.13 . 1.25 . 1.22 . 1.18. 1.28. 1.29. 1.31
- l.21 . l.24 . 1.27 . 1.13 0.36 11 2.9
- 2.9 . l.8 . 0.3 . *0.2 . 0.3 . l.5 . 1.8 . l.8
- l.8 . 2.~ . 2.4 l.7 0.37 0.79 1.22 1.21 1.24 1.31 l.25 1.22 1.24 0.82 0.37 0.39 0.83
- 1.23
- 1.20
- l.23
- 1.32
- 1.25
- 1.22 . 1.26 . 0.85 0.38 12 7.3
- 4.6
- D.4 * *0.4 . *0.7
- D.5
- D.3
- 0.0
- 1.6
- 3.11
- 3.2 0.37 1.09
- 1.21
- 1.20
- 1.25 l.20 1.22 1.11 . 0.37 0.39 1.14 . 1.23 .* 1.19
- 1.20 . 1.14
- 1.11!
- L11 . ll.39 13 5.8. 4.4. 1.11. *l.O. *4.0 . *4.9. *3.2 .. *0.0 . 3.7 0.34 0.67 1.12 0.89 1.11 0.68 D.35
- 0.36 0. 70 1.ll 0.116 1. Olo 0.64 0 .34 14 4.4 . 3.2
- 0.9. *4.1 * *6.6 . *4.9 * -2.8 .
STANDARD 0.28 0.33 0.28 AVERAGE
*DEVIATION 0.28 '0.32 0.26 :PCT DIFFERENCE. 15
=l. 603 0.8 *2.4 *7.1 = 2.0
.SUl111ARY HAP ND: S1*lO-ll DATE: 7/8/89 POWER: 64.6%
COHTROL'ROD .. POSlTlONS: *rocCT) = l:984 . QPTR: D BAt<< AT .154 STEPS F*DH(Nl = 1.470 NW l.002 t NE 0.988 I FCZJ = l.296 .,..SW--1-.D,,..D,.,8-l-
..S.,..E,.......,l,..._-0-u-2 BURHUP = 1,900 11WD/11TU A.O.= -7.9507. ~E-751 S1Cl0A Startup Test Report Page 38 .of 58
Figure 6. 3 SURRY ,UNIT 1 - CYCLE lOA STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R p N H K J H G F E D C B A PREDICTED 0.29 0.35 0.29 PREDICTED HEASURED . 0.29 . 0.36 . 0.29 . HEASURED
.PCT DIFFERENCE. 1.8 . 1.6 . 0.7 . .PCT DIFFERENCE.
0.36 0.67 1.10 0.92 1.11 0.69 0.36
. 0.36 . 0.67 . 1.09 . 0.91 . 1.09 . 0.68 . 0.36 .
0.8 . O.l . -0.5 . -0.9 . -1.l . -1.0 . -0.l . 0.38 1.10 1.21 1.16 1.22 1.16 1.21 1.09 0.38
. 0.38 . 1.09 . 1.20 .- 1.15 . 1.17 . 1.13 . 1.20 . 1.10 . 0.38 . 3 0.4. -1.0. -1.0. -0.5. -3.4. -2.9. -1.0 . 0.4. 1.3.
0.38 0.82 1.25 1.19 1.26 1.27 1.25 1.19 1.24 0.80 0.38
. 0.38 . 0.81 . 1.22 . 1.18 . 1.24 . 1.24 . 1.20 . 1.16 . 1.22 . 0.79 . 0.37 .
. -1.l . -1.l . -2.1 . -1.2 . -1.5 . -2.4 . -4.l . -2.l . -1.2 . -0.9 . -o.5 .
0.36 1.10 1.25 1.21 1.19 1.26 1.25 1.26 1.18 1.19 1.23 1.08 0.35
. 0.35 . 1.08 . 1.24 . 1.21 . 1.19 . 1.30 . 1.20 . 1.28 . 1.19 . 1.17 . 1.20 . 1.07 . 0.35 . 5
. -2.2 . -2.2 . -0.9 . -0.3 . -0.3 . 2.5 . -4.l . 2.3 . 0.1 . -1.7 . -2.3 . -1.-3 . -0.2 .
0.69 1.22 1.19 1.19 1.23 1.23 1.19 1.22 1.23 1.18 1.17 1.18 0.67
. 0.67. 1.20 . 1.19. 1.21 . 1.25. 1.26. 1.22. 1.25. 1.24. 1.17. 1.15. 1.16 . 0.66. 6
. -1.7 . -1.7 . -0.2 . 1.6 . 1.5 . 2.5 . 2.5 . 2.2 . 1.3 . -0.5 . -1.8 . -1.5 . -1.3 .
0.29 1.11 1.17 1.26 1.26 1.23 1.03 1.22 1.02 1.22 .l.21 1.24 1.15 1.09 0.29
. 0.30 . 1.11 . 1.15 . 1.26 . 1.28 . 1.25 . 1.05 . 1.25 . 1.05 . 1.26 . 1.23 . 1.23 . 1.13 . 1.07 . 0.28 . 7 1.6. 0.1 . -1.0 . o.3. 1.2. 1.8. 2.5. 2.6. 3.4. 3.3. 1.5. -1.1 . -1.5. -2.2. -1.8 .
0.35 0.93 1.22 1.27 1.25 1.19 1.22 1.21 . 1.22 1.18 1.26 1.26 1.21 0.92 0.35
. 0.36 . 0.93 . 1.22 . 1.27 . 1.26 . 1.20 . 1.25 . 1.26 . 1.27 . 1.23 . 1.28 . 1.25 . 1.19 . 0.91 . 0.35 . 8 1.3 . 0.2 . o.3 . 0.2 . o.6 . 1.1 . 2.6 . 4.1 . 4.2 . 4.2 . 2.1 . -1.3 . -1.5 . -1.1 . 0.1 .
0.29 1.11 1.17 1.26 1.26 1.22 1.02 1.22 1.03 1.22 1.26 1.25 1.16 1.10 0.29
. 0.30 . 1.11 . 1.16. 1.26. 1.27. 1.23. 1.02. 1.26. 1.08. 1.25. 1.28. 1.25. 1.15. 1.10 . 0.30
- 9 l.[. . -0.l . -1.l . -0.2 . 0.5 . 0.5 . 0.4 . 3.6 . 5.0 . 2.4 *- 2.1 . -0.2 . -0.4 . 0.5 . 2.5 .
0.69 1.22 1.19 1.19 1.23 1.22 1.19 1.23 1.23 1.19 1.19 1.21 0.68
. 0.67 . 1.19 . 1.17 . 1.19 . 1.23 . 1.23 . 1.22 . 1.27 . 1.26 . 1.20 . 1.20 . 1.22 . 0.69 . 10
. -2.7 . -2.8 . -1.4 . -0.4 . -0.2 . 0.6 . 2.4 . 3.4 . 2.3 . 1.0 . 0.6 . 0.6 . 0.8 .
0.36 1.10 1.24" 1.20 1.19 1.26 1.25 1.26 1.19 1.20 1.24 1.10 0.36
. 0.36. 1.10 . 1.24 . 1.18. 1.18. 1.26. 1.27. 1.30 . 1.22. 1.21 . 1.25 . 1.11 . 0.36. 11 0.3 . 0.3 . --0.3 . -1.2 . -0.8 . 0.5 . 1.8 . 2.5 . 2.4 . 0.5 . 0.7 . l.l . 1.0 .
0.38 0.81 1.24 1.19 1.26 1.27 1.26 1.19 1.25. 0.82 0.38
. 0. 39 . O. 82 . l. 22 . l. 17 . l. 24
- l. 211
- l. 27 . l. 20 . l. 25 . O. 83 . O. 39 . 12 3.3. 1.6. -1.2. -1.2. -0.11. 0.6. 0.9. 0.2. 0.4. 1.0 . 1.6.
0.38 1.09 1.21 1.17 1.22 1.17 1.22 1.10 0.38
. 0.38 . 1.09 . 1.20 . 1.15 . 1.19 . 1.13 . 1.19 . 1.09 . 0.39 . 13 1.5 . -0.2 . -0.7 . -1.2 * -2.2 . -2.7 . -2.4 . -1.0 . 1.2 .
0.35 0.68 1.11 0.93 1.11 0.68 0.36
. 0.35 . 0.69 . 1.15
- 0.92 . 1.07 . 0.66. 0.35 . 14
. -0.2 . 1.1 . 2.8 . -0.9 . -3.l . -2.7 . -2.3 .
STANDARD 0.29 0.35 0.29 AIIERAGE DEIIIATION . 0.30 . 0.35 . 0.28 . .PCT DIFFERENCE . 15 al. 062 2.8 . 0.4 . -3.l . 1.5 SUHHARY HAP NO: Sl-10-16 DATE: 7/19/89 POWER: 100% CONTROL ROD POSITIONS: F-Q( Tl l. 792 OPTR: D BANK AT 195 STEPS F-DHCNl l.442 NW l. 000 NE 0.987 FCZJ l. 203 SW l. 003 SE l. 01 O BURNUP 2,102 HWD/HTU A.O. a -3.298%
\'E-751 SlClOA Startup Test Report Page 39 of 58
- SECTION 7 REFERENCES
- 1. D. A. Trace, "Surry Unit 1, Cycle lOA Design Report,"
Technical Report NE-676, Revision 1, Virginia Electric and Power Company, J~ne, 1989.
- 2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
- 3. W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 19 6 7 .
- 4. Surry Technical Specifications, Sections 3.12.C.1 3.12.B.1. and 3.1.E.l.
~E-751 S1Cl0A Startup Test Report Page 40 of 58
APPENDIX STARTUP PHYSICS TESTS RESULTS AND EVALUATION SHEETS \S-751 SlClOA Starcup Test Report Page 41 of 58
1 l-PT-28.1 Attacblllen Page 1 of SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Descripti_on: Reactivity Computer Checkout Reference Pree No /Section: l-PT-28.11 Sequence Step No: J
. II I 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:
- Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( 0 F): S'14l\,g Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) I CB: 225 CC: 225 CD: tSa Below Nuclear Heating Date/Time Test Performed:
\DC Measured Parameter Pc = Meas. Reactivty using p-computer . * --~:~::J/"
IV (Description) Pt= Inferred React from react period.
... .le- q \. - --:i...r .
- c; = -r-Measured Value Pt = ~ \\\ -"3-LS-0 4,()
Test w = Results Design Value (Actual_ Conditions) I>esi:gll(Vame-;.j:--*:,,, . . (Design Conditions) %D = {(pc-Pt)fpt} X 100% S 4.0% Reference WCAP 7905, Rev. 1, Table 3.6
-----------------*_:/<;}ff' V FSAR/Tech Spec Not Applicable ....,',i,: .......
Acceptance 1------------+--------------------c.-.* :;*Ji:. Criteria Reference Not Applicable Design Tolerance is met * ....!:ftS _NO VI Acceptance Criteria is met : _LYES _NO Comments . :,1;-c~1.i.~.,.': At The Just Critical Positi~n . -~*-.J:~}6~,
.. ***-~:**.-
Allowable Range = +/- ~ 0 _._ -r:-.-:: -"." , Prepared B y ~ , \ . l - 3 : ~ Reviewed By: e,;f:/~e:ear:: e
*. NE-751 SlClOA Startup Test Report Page 42 of 58
l-PT-28.11 Attachment 1 Page 2 of 18 JUN Z 9 1S89
;==-' _,-J A:-L SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND- EVALUATION SHEET I Test
Description:
Critical Boron Concentration - ARO Reference ?roe ~o /Section: l-PT-28.11 Sequence Step No: -+ II Bank Positions (Steps) I RCS Temperature (OF): 547 Test I Power Level ( ";; F. p.): 0 Conditionsj SDA: 225 SDB: 225 CA: 225 Other (specify): (Design) [ CB: 225 CC: 225 CD: 225 Below Nuclear Heating I I III Bank Pas it ions (Steps) RCS Temperature (on: ~'-1(:,.i.{ T.est i Power Level (% F. p'): 0 I Conditions1 SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actual) ! CB: 225 CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed: jeas Parameter M IV (Description) (CB) ARO; Critical Boron Cone - ARO C>DM I' Test Results Design Value (Actual Cond) Design Value (Design Cond) CB =1451 +/- 50 ppm Referenc& NE Technical Report No. 676, Rev. 1
*--~~~
V 1--F_s_A_R_I_T_e_c_h_S_p_e_c--+~a_c_B~x~c_B_~~1_s_,_1_1_5_p_c_m_ _ _ _ _ _ _~~~~ .:"~~- Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met ./YES _S'O Acceptance Criteria is met /YES _S'O
.VI Comments aCB = -7.88 pcm/ppm for preliminary analysis Prepared By: \}:Jel.,/ S:{ ~ Reviewed By: S.;Y/./~
- NE-751 SlClOA Startup Test Report Page 43 of 58
1- PT-28 .11 Attachment 1 Page 3 of 18
- SURRY POWER STATION UNIT 1 CYCLE l~A STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JIJ~ 2 9 1989 I Test
Description:
Isothermal Tempera~ure Coefficient - ARO Reference ?roe No /Section: l-PT-28.11 Sequence Step No: 5 II Bank Posi~ions (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 I
. I III Bank Positions (Steps) RCS Temperature ( 0 F): ,61..\G.,r Test I Power Level(% F.P.): O Conditionsj SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) I CB: 225 CC: 225 CD: 'a\~ Below Nuclear Heating Date/Time Test Performed:
"1-5 -:n °i \C\ s-o Meas Parameter\ ISO
.IV (Description) j (a T )ARO Isothermal Temp Coeff - ARO lSO "
Test Measured Value I' -~
,- T 1 ARO Results Design Value (Actual Cond)
ISO (a T )ARO= -5.32 +/- 3.0 pcm/°F Design Value (Design Cond) (CB= 1451 ppm) Reference NE Technical Report No. 676, Rev. 1 V ISO * . Dop Acceptance FSAR/Tech Spec a T ~ 0.77 pcm/°F a T = -1.73 pcm/°F Criteria Reference TS 3.1, NE Tech Report No. 676, Rev. 1 Design Tolerance is met LJEs NO VI Acceptance Criteria is met LYES _NO Comments
- Uncertainty on aTMOD = 0.5 pcm/°F (
Reference:
memorandum from__,.. C. T. Snow"to E. . J. Lozito dated June 27, 1980).
- 0. LL Prepared By\, ,;.W ;L Reviewed By:
I Page 44 of 58 NE-7Sl S1C10A Startup Test Report
l-PT-28.1 J Attacbmen* Page 4 of
- SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Cntl Bank B Wo~th Meas.,Rod Swap Ref. Bank Reference Proc No /Section: l-PT-28.11 Sequence Step No:~ II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (%F.P.): 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (specify): (Design) CB:Moving CC: 225 CD: 225 Below Nuclear Heating III Banlc Positions (Steps) RCS Temper*ature ( OF) : ~I{~ ,S Test Power Level (% F.P.): 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (Specify): (Actual) CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed: 7/> Bf 2/.'/f REF Measured Paraaeter I B ; Integral Worth of Cntl Bank B, (Description) All Other Rods Out TV
- REF Test Measured Value I B = /2 71. ~
Results Design Value (Actual Conditions) REF I B =
.:"i~
/27/
-----=---------------** ~~iJff;\
Design Value . REF (Design Conditions) I B = 1271 +/- 127 pcm RefereJICa\1:?. * -~-; ':: NDTedm:lcal Report;'.* No,. 676:* *!.~ If Design Tolerance is exceeded, S shall evaluate impact of test result V FSAR/Tech Spec on safety analysis. SNSOC aay specify Acceptance that additional testing be performed. Criteria Reference VEP-FRD-36A Design Tolerance is aet VI Acceptance Criteria is met Comments Prepared By: Reviewed By:
- NE-751 S1C10A Startup Test Report . Page 45 of 58
l-PT-28.11 Attachment I Page 5 of 1s* JUN 2 9 i989 SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND. EVALUATION SHEET I Test
Description:
Critical Boron Concentration - B Bank In Reference Proc No /Section: l-PT-28.11 Sequence Step No: 7 II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Con d.itionsl
. 1 SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 0 CC: 225 CD: 225 Below Nuclear Heating I III Bank Positions (Steps) RCS Temperature C°F) :54-5", / Test , Power Level (% F.P.): 0 Conditions I SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actual) I CB: 0 CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed: i 7-&,-~'1 0"310 I Meas Parameter M IV (Description) (CB)D; Critical Boron Cone - B Bank In Measured '.'::i l 11<>* Test Results Design Value -~ .. "'.' ' *. (Actual Cond) Design Value Prev (Design Cond) CB = 1290 + flCB +/- ( 10 + 127'. 1/ I aCB I )ppm Reference NE Technical Report No. 676, Rev. 1 Acce~tance .._F_s_A_R_I_T_e_c_h_s_p_e_c-+_a_c_8_x_c_B_~_1_s_,1_1s_p_c_m-------------=-'~{~it; Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met v'yES _NO Acceptance Criteria is met </YES _NO VI Comments aCB = -7.88 pcm/ppm for prelimina~y analysis Prev M 6CB = (CB)ARO - 1451
- (J_'._<1 -= - 7' e;-z. p~?"" ( ;; ,v.m__)
Prepared By: Reviewed By: NE-75i S1C10A Startup Test Report Page 46 of 58
l-PT-28. ll Attachment Page 6 of I
*suRRY POWER STATION UNIT' 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
HZP Boron Worth Coefficent.Measurement Reference Proc No /Section: 1-PT-28.11 Sequence Step No: 7 II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F;P.): 0 Conditions (Design) SDA: 225 SDB: 225 CB:Moving CC: 225 CA: 225 CD: 225
*I Other (specify):
Below Nuclear Heating I III Bank Positions (Steps) RCS Temperature ( °F): ~~. / Test Power Level(% F.P.): 0 Conditions! SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actual) CB:Moving CC: 225 CD: 225 Below Nuclear Heating I Date/Time Test Performed: I 7 / rat ~CJ 031 b Measured Parameter IV (Description) aCB, Boron. Worth Coefficient Measureii. Value Test Results Design Value _<_A_c_t_u_a_1_c_o_n_d_1_*t_1_*o_n_s_)___ a_cB_=__ -_'_*~-~_=_o_._'_~__f_(.._>fi__P_,..,____. ::.xi~f)jl,.. Design Value (Design Conditions) aCB = -7.88 +/- 0.79 pea/ppm FSAR/Tech Spec aCB x CBS 15,115 pcm V f-----------+-------------------.. . ). -:f* ~-~* Acceptance Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met /YES _NO VI Acceptance Criteria *is met 7YEs _NO Comments Prepared By: Reviewed By: NE-751 S1Cl0A Startup Test Report Page 47 of 58
l-PT-28. U Attachment Page 7 of JUN 2 .. .*~
.~. .....
SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test
Description:
Cntl Bank D Worth Measurement-Rod Swap Reference I Proc No /Sect~on: 1-PT-28.11 Sequence Step No: 9 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:Moving CC: 225 CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( or) : 5"~5". q Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify) : (Actual) CB:Moving CC: 225 CD:Moving Below Nuclear Heating
~
I Date/Time Test Performed: Meas Parameter RS (Description) In; Int Worth of Cntl Bank D-Rod Swap IV RS (A,:li.- Meas. Grit. Ref Bank Test He.~sured Value I ... u
= //53,7oc~~ P.:,sition = l'r<? steps)
Results ' . -* -:,*. ,I Design Value RS (Adj. Hess. Crit. Ref Bank.-- ___;:.~ .* *-_,Jt * (Actual Cond) In = 1oi"t,lo .!"/i,3p,iJ>osition =/Cf~ steps) -.~;fit)P:;: RS Design Value In= 1085 +/- 163 pcm (Critical Ref Ban1t. (Design Cond) Position = 185 stel)!l_)*i',
. NllfTicmdcal'.'.ieport Na~. 676t VEP--FR!~lil NFCrTI,-2. 2A If Design Tolerance ~s exceeded, SNSOC
...*.*.:/.
shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that* Acceptance additional testing be performed. Criteria Reference VEP-FRD-36A VI Design Tolerance is met Acceptance Criteria is met vn:s 7YEs _NO _NO Comments
- Prepared By:* (v {,/ ~ / / . <;"' c-,,,4 Reviewed By: ......... /1'(-~
NE-751 S1C10A Startup Test Report Page 48 of 58
l.:.PT-28.11 Attachment Page 8 of SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP*PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Cntl Bank C Worth Measurement-Rod Swap Re-ference Pree No /Section: l-PT-28.11 Sequence Step No: 10 II Bank Positions (Step~) RCS Temperature (°F): 547 Test Power Level(% F.P.):_O Conditions SDA: 225 SDB: 225 CA: 225 Other (specify) : (Design) CB:Moving CC:Moving CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( 0F): 5"4,. (p Test I Power Level(% F.P.): 0 Conditions! SDA: 225 SDB: 225
- CA: 225 Other (Specify) :
(Actual) j CB:M6ving CC:Moving CD: 225 Below Nuclear Heating Date/Time Test Performed: 7/<P/'i-'7 O°lt S Meas Parameter RS (Description) Ic; Int Worth of Cntl Bank C-Rod Swap IV (Adj ~~~~~ c~~t. P-~~ E~nk Test -Measured Value icRs = 'iii.<?' :-r ... Po~ i 't. i nn = ' 1,.. 1 c: r. "'""" r-,) Results
*£.*.-
Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond)
- Ic = ~5'-f.7
-+/- l'Z.
r c..., Position = 11of steps) RS Design Value Ic = 844 +/- 127 pcm (Critical (Design Cond) Position Reference, NE". Technical Repo~ No. 676, VEP-FRi>- NFO-TI-2. 2A
--------------+------------------------**:~~~g If Design Tolerance is exceeded, SNSOC shall ~valuat~ impa~t of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed.
Criteria
. Reference VEP-FRD-36A Design Tolerance is met I YES _NO VI Acceptance Criteria is met J YES _NO Comments Prepared By: Reviewed By:
--1*
/
NE-751 S1Cl0A Startup Test Report Page 49 of .58
l-PT-28.11 Attachment Page 9 of
- SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
* '**I
._iwai"""
~, "
I Test
Description:
Cntl Bank A Wor~h Measurem~nt*Rod Swap Reference Pree No /Section: l-PT-28.11 Sequence Step No: 11 II Bank Positions (Steps) RCS Temperature (°F): 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): :,</~.6 Test Power Level(% F.P.): 0 Conditions SDA: 225 SDB: .225 CA:Moving Other (Specify): (Actual) CB:Moving CC: 225 CD: 225 Below Nuclear Beating Date/Time Test Performed: 7/ ~ /<c~ 1007--- Meas fl_arameter RS (Description) IA; Int Worth of Cntl Bank A - Rod Swap 1v RS (Adj. Meas. Crit Test *I Measuretl Value IA - 331.1 pc:wi Position = :-r. ~.- 0 :;:-~) Results Design Value RS (Adj. Meas. Crit. Ref Bank*.:- -~.-:4t~i; (Actual Cond) IA = 3'53.!.{f'-.,..., Position= ?D steps) **'*}~'.,;*Js:*
"! 100 RS Design Value IA = 355 +/- 100 pcm (Critical (Design Cond) Position Reference;..*__. fflT&clmica~ RepozF-lb-.;,, 678;! *VEY- .
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 Reference VEP-FRD-36A Design Tolerance is met / YES _NO VI Acceptance Criteria is met j YES _NO Comments Prepared By: Reviewed By:
- NE-751 S1C10A Startup Test Report Page 50 of 58
l - l-PT-28.11 Attachment Page 10 of
- SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET JUN 2 :;
J;IJ:1 I Test
Description:
Shutdown Bank B Worth Meas. - Rod Swap Reference Pree No /Section: 1-PT-28.11 Sequence Step No: 12
. II Bank Positions (Steps) RCS Temperature (°F): 547 Test- Power Level(% F.P.): 0 Conditions SDA: 225 SDB:Moving CA: 225 Other (specify):
(Design) CB:Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( °F): 5"-15. 2. Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB:Moving CA: 225 Other (Specify) : (Actual) CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Performed: 7/4,/~ ///I I Meas Parameter RS (Description) *IsB; Int Worth of Shutdown Bank B-Rod Swap IV Test Measured Value
-- IOI&, 'i'.9 ,,...,
=-feirc-:3-rc..,
CAd*. J Meas. Crit. Ref Bank_ Position = I a"'5 steps) Results ~1." Design Value RS . (Adj. Meas. Crit. Ref B~~~?~~~ (Actual Cond) IsB =~ IOl1,3pc"" I5~ c,.. Position= *
,a..-
IS ;;, ste,__'-f;.i )J~L:. r--.r.: * . .*< *"-' RS
*~4".~~t:**
Design Value IsB = 1026 +/- 154 pcm (Critical Ref Banh~'?;~\\~~(: (Design Cond) Position = 172 st_
- _,:*. _.:. .. *
...,.. ,..*{11..tvm- *'""
' . . ~ ... . .
If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety ~nalysis. SNSOC may specify that
-Acceptance additional testing beperformed.
Criteria Reference VEP-FRD-36A Design.Tolerance is met LYES _NO VI Acceptance Criteria is met LYES _NO Comments Prepared By: Reviewed By: NE-751 S1Cl0A Startup Test Report Page 51 of 58
l-PT-28.1 Attacbmen* Page 11
- o SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Shutdown Bank A Worth Meas. - Rod Swap
- Reference Pree No /Section: 1-PT-28.11 Sequence Step No: 13
. II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (% F.P.): 0 Conditions I SDA:Moving SDB: 225 CA: 225 Other (specify):
(Design) CB:Moving CC: 225
- CD: 225 Below Nuclear Heating III I Bank Positions (Steps) RCS Temperature (°F): S-L/5.~'F Test Power Level (% F.P.}: 0 Conditions SDA:Moving SDB: 225 CA: 225 Other (Specify):
(Actual) CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test. Performed: Meas Parameter RS (Description) IsA; Int Worth of Shutdown Bank A-Rod Swap. IV -(~~~j. ~~=:;. ~~it. R~f Bank Test Measured Value '}S 3,::, ."" .. *. ?-:-~i+;fon .,.,. .:: steps) Results - --~..;~;.~*:*~- Design Value Rs q 7 'Z.. (Adj. Meas. Crit. Ref Banb'fi:~~\-;f f'CM * ******~** (Actual Cond) IsA =-+ /~lP c.wi Position = 14'7 steps-)\*~,:-;,,_~*~'!'.(*
- '"'* -j~~~~~-*
RS Design Value IsA = 971 +/- 146 pcm (Critical Ref Bank,,.** :.;:,,'.~:?fl?'* (Design Cond) Position.. = 164 st If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that Acceptance additional testing be performed. Criteria Reference VEP-FRD-36A Design Tolerance is met ./ YES -~O VI Acceptance Criteria is met .:; YES _NO Comments
/1/l !?tw' Prepared By: Reviewed By:
NE-751 S1C10A Startup Test Report Page 52 of 58
l-PT-28. L Attachment Page 12 01 SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSIC~ TEST RESULTS AND EVALUATION SHEET I Test
Description:
Total Rrid W~rth - Rod Swap Reference Proc No /Section: 1-PT-28.11 Sequence Step No: 13 II Bank Positions (Steps) RCS Temperature ( o F): 547 Test Power Level (i. F.P.): 0 Conditions SDA:Moving SDB:Moving CA:Moving Other (specify): (Design) CB:Moving CC:Moving CD:Hoving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( °F): 5'-15.5 Test Power Level (i. F.P.): 0 Conditions.SDA:~oving SDB:Moving CA:Moving Other (Specify) : (Actual) j CB:Moving CC:Moving CD:Moving Below Nuclear Heating Date/Time Test Performed: 2-/ ( Meas Parameter (Description) !Total; Int Worth of All Banks - Rod Swap IV 1'~,;,t. ~easured Value 1Total = 5(;95,<-/ f<-"-. Results (Design Cond) 1Total =
,S,7. 'L ,.,,..,
~ 55~ CM f-'-:-:-:-:-.:-:-:-:-:-:-:--------------'------------*---_**~
1Total = 5555 +/- 556 pc11 :2 If Design Tolerance is exceeded, shall evaluate iapact of test result on V FSAR/Tech Spec safety analysis. SNSOC aay specify that Acceptance addit1onal testing be performed. Criteria Reference VEP-FRD-36A Design Tolerance is met : - ,/ YES _NO VI Acceptance Criteria is met : 7YES _NO Comments Prepared By: Reviewed By: NE-751 SlClOA Startup Test Report Page 53 of 58
l-PT-28.11* Attachment Page 13 of
- SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVA_LUATION SHEET I Test Descriptiqn: M/D Flux Map - Low power
- Reference Proc No/ Section: 1-PT-28.2, 1-0P-57 Sequence Step No: 41 II Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): <30 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify)
(Design) CB : 225 cc : 225 CD:
- Must have~ 38 thimbles III Bank Positions (Steps) RCS Temperature( °F): S'<E;°"'.?:>
Test Power Level (% F. P.): ~'5.1 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actuap C-B : 225 cc : 225 CD: \:.,3 I NUC ENTHAL TOTAL HEAT QUADRANT . IV Meas Parameter RISE HOT FLUX HOT POWER TIL~ct' *>'>f( (Description) CHAN FACT CHAN FACT RATIO. -**-f:t-!f-'-. (M-P)/P , F-dH(N) F-Q(T) QPTR Measured Value Test Results Design Value (Design Conds) NA NA J.sa.JSU*.JCl*Pll . ~I) S *.MIP
- ll(Q V FSAR/Tech Spec NONE NA Acceptancel---------------+-----------+----~-----+----------+----------'""'"""..-
Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met : _=::::-YJS NO Acceptance Criteria is met : _LYES _-_NO VI Comments
- As Required
**The design value of QPTR i:,; the sum of the . 003 design , ___ , -
prediction tilt' and the 1.02. uncertainty identified iIJ,~~-?5 WCAP-7905. * ** (\
- LJ &µPJ Prepared By: ~1-~n.
\ I Reviewed By:
r \ NE-751 S1Cl0A Startup Test Report Page 54 of 58
l-PT-28 .11 Attachment Page 14 of
- SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET T
I Test D~scri6tion: ~/D Flux ~ap-At Power,NI Calibration
- teference 1 ?roe No / Section: l-PT-28.2, l-OP-57 Sequence Step :,;o: 44 II Bank Positions (Steps) RCS Temperature l °F):TREF +/-1 Test Power Level(: F.P.): - 70 Conditionsi SDA: 225 SDB: 225 CA: 225 Other (specify):*
(Design,) ! CB : 225 cc : 225 CD: ** III Bank Positions (Steps) RCS Temoerature(°F): -S-~S" Test Power Level (~ F. P.): ~ '\ i(o Conditions/ SDA: 225 SOB: 225 CA: 225 Other (Specify): (Actual) CB : 225 cc : 225 CD: \ 'S"L\ Date/Time Test: \-~-~'; Performed: \°'6 L\ b I I MAX. REL NUC ENTHALITOTAL HEAT! QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) i. DIFF CHAN FACT CHAN FACT RATIO (M-P)/P -** ..
.J:"-,Hl'OJ) / -J:"-n(T)
"' ... ., QPTR
~0,'-1 LI
~14.i ,.cl.\;" \ ,oc,S-,
Measured Value \,Y'l6 l-9~Y
<-6,90 Test
~1;;2 ~44 -IJ ~~
Results Design Value t 101. tor *1 l O. t t Ul for Pi < 1.t (Design Conds) (Pl* Aaay. fn,) NA NA !, 1. 02
- L:~~(::-*f4::~.~ f ~*.i__.):Tllfer I
F.1.1Sl.SJl1+.JO*Pll r~Ul s z.WP
- lUl V FSAR/Tech Spec NONE NA Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met _L!Es _S'O Acceptance Criteria is met .,.LYES _S'O VI Comments
- Must have at least 38 thimbles for a full-core flux map, or at least 16 thi,bles for a.quarter-core flux map.
** As Required
'l
~
I f: I Prepared By:\ I(~. *~J::::c6 ('\ I I Reviewed By: I i II I I I/ ( 6:1,...,,t> ' "I.}./"'.'--
\
\
Page 55 of 58
- NE-751 S1C10A Startup Test Report
l-PT-28.1 Attachmen Page 15 o
- I SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test
Description:
~/D Flux Map-At ~ower,~I Calibration*
~eference ! ?=oc ~o / Section: l-PT-28:2, l-OP-57 Sequence Ste~ No: 45 II Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test Power Level(% F.P.): - 70 Conditionsi SDA: 225 SDB: 225 CA: 225 Other (specify): -
(Design) I CB : 225 CC : 225 CD:** III Bank Positions (Steps) RCS Temperature(°F): :S-~ Test ' Power Level(% F.P.): ~S-,'.2 Conditionsj SDA: 225 SDB: 225 CA: 225 1 Other (Specify): (Actual) j CB : 225 cc 225 CD: \()~ Date/Time Test: 1 -"'6 -~ S Perrormeci: Jct~l..\ I I
- I MAX. REL NUC ENTHALITOTAL HEATI QUADRANT IV Meas Parameter ASSY PWR RISE HOT I FLUX HOT !POWER TILT (Description) % DIFF CHAN FACT jCHAN FACT I RATIO (M-P)/P F~dH(N) II F-Q(T) 0P'f'R
"! c.c::i o Measured Value P't 1 **Mj-S:61.
.::.. o.9 I:)
Test Results
~ ,c ~.lc,6"-'\
Design Value t 11'1 r. p~ I I.I t U1: - '1 .. ,., (Design Conds) CPt * - * '-*> NA NA :5 1.02
~~~5:* -., ;~. ,' ;, : ,: ;~~-- ~':.~-~~~'::.*
V FSAR/Tech Spec NONE ,:.U.ssu*.J(M>I I'~ 11
- a.w.
- aca, NA Acceptancel--------~~-----+------4------+-----~
Criteria Reference NONE TS 3.12 I TS 3.12 TS 3.12 Design Tolerance is met 6~_~0 Acceptance Criteria is met _../TI:_ESS -*~o VI Comments * ~ust have at least 38 thimples for a full-core flux map, or at least lp thlmbles for a quarter-core flux map.
** As Required
*-*--**-*-------------------- ----------~--
.,,.--. 1 r
- rI .___.,...,\y I
I '. Prepared ByK;...,;,.._.,~0-J~\~,\~J~......cO'~l....._=-~- Reviewed By: NE-751 S1C10A Startup Test Report Page 56 of 58
l-PT-28. L Attachment Page 16 oi-.
.,,: .; I **
SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Oescripti.on: j/D Flux Map-At Power ,NI Calibration
- =leference ?roe No/ Section: l-PT-28.2, l-OP-57 Sequence Step No: 46 II Bank Positions (Steps) RCS Temperature (°F):TREF_+/-l Test i Power Level c: F.P.): - 70 Conditions1 SDA: 225 SDB: 225 CA: 225 Other (spe~ify): *
(Design) I CB : 225 CC: 225 CD:** III Bank Positions (Steps) RCS Temperature( 0 F): 56 ,S-Test Power Level (% F.P.): ~ *1 Conditions SDA: 225 SDB: 225 cA: 22s Other (Specify) : (Actual) CB : 225 CC: 225 CD: \3o Date/Time Test: 1-"3 -'3;1 Performed:
'J. 3-S- 7 MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) % DIFF *CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR
?. e..GD i Measured Value G"l 11.~-6.1~
1,4'5'! I \.e:oo_:__ I Test
.c.o.C\O 2-0~5 I Q\,)CHiet<otE?
lil"3iO.:fl ,+3.,t Results Design Value I 111 f.w ft I l.t I I.SI r. It c o:t (Design Conds) (Pt*._.-.) T r:.UJ5(1+.J(l*Pll PQ(ll S Z.:WP
- I( II V FSAR/Tech Spec NONE NA Acceptancei--~~~~~~-+-~~~~-+-~~~~~-+-~~~~-+-~~~~~
Criteria. Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met Acceptance Criteria is met VI Comments
- Must have at least 38 thimples for a full-core flux map, or at least 16 thi~bles for a quarter-core flux map.
** As Required Prepared
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By'}...__di
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li). Reviewed By: I NE-751 S1Cl0A Startup Test Report Page 57 of 58
l-PT-28.1 Attachmen Page 17" c JUN 2 13 ~~- SURRY POWER STATION UNIT 1 CYCLE lOA STARTUP PHYSICS TEST RESULTS AND EVALUATION S.HEET Test D~scription: M/D Flux Map - HFP, ARO, Eq. Xe
~eference Proc No/ Section: l-PT-28.2, l-OP-57 Sequence Step No: 47
- I Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Test ,,------------------------------, Power Leiel (% F.P.):95 +/- 5 Conditions 1' SDA: 225 SDB: 225 CA: 225 Other (specify): Eq. Xe.
(Design) CB : 225 cc : 225 CD:
- Must have~ 38 thimbles III I Bank Positions (Steps) RCS Temperature( °F): '5"1 l\
Test .......-----------------------------< Power Level (% F. P.): \CO '?e. Conditions I SDA: 225 SDB: 225 CA: 225 Other (Specify): (Actual) j CB : 225 cc : 225 CD: \Cl s Date/Time Test: l-1q-~9 Performed: \05q MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT (Description) % DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR
----+---------~t--*------------1----------------
~-O"c ~' .ir:t oc-c.,.,.,~ ..
~I ~ O, qz "' \ I
\ ..-1 q *~ ~,- r;;\i ., ~~:>
3.3 ,,. "'~<1=\ Measured Value Ol Test Results (2 .o,or:i*** Design Value t 111 ,,_,,a *. , .' *.. '/F*i~ *: .. t: 1S1, , _ Pt CI.I (Design Conda) c*, *-* --> NA NA S 1.02.:-.* *.: - _...,.,* . .a~o;~~-*
.r~ *-.:S..,
,I. -. . . .Jll-f')t -'* ~.l.9"aUII V FSAR/Tecb Spec NONE Acceptance Criteria Reference NONE TS 3.12 TS 3.12 TS 3.12 Design Tolerance is met ~ NO Acceptance Criteria is met _YES _NO VI Comments As Required I*
Prepared Reviewed By: I
- I
\/I NE-751 S1C10A Startup Test Report Page 58 of}}