ML18151A636
| ML18151A636 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/18/1991 |
| From: | Dziadosz D, Mcelroy J, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-128, NE-819, NE-819-R, NE-819-R00, NUDOCS 9103200372 | |
| Download: ML18151A636 (62) | |
Text
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- VIRGINIA ELECTRIC AND PowER CoMPAXY
- RICHMOND, YIRGINIA 23261 March 14, 1991 United States Nuclear Regulatory Commission Serial No.91-128 Attention: Document Control Desk NURBP RO Washington, D. c: 20555 Docket No. 50-280 Licen~e No.* DPR-32 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1
- CYCLE 11 STARTUP PHYSICS REPORT As required by Surry Technical Specification 6.6.A. 1 ,enclosed are five (5) copies of .
the Virginia Electric and Power Comp*any Technical Report NE-819 "Surry Unit 1, **
- Cycle 1'1 Startup Physics Report." This report summarizes the results of the physics testing program performed after initial criticality .of Cycle 11 on December 17, 1990.
The results of the physics tests were within required design tolerances and applicable Technical Specification limits.
Very truly yours,
/(/0~
Jr-w. L. Stewart
? Senior Vice President "'. Nuclear Attachment cc: U: S. Nuclear Regulatory,Comm:ssion Region II
- 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident lnspecto( ,.
Surry Power Station 9103200372 910218 PDR ADOCK 05000280 P PDR
-NOTICE-THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION &
REPORTS MANAGEMENT BRANCH.
THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RE-CORDS & ARCHIVES SERVICES SEC-TION P1-22 WHITE FUNT. PLEASE DO NOT SEND DOCUMENTS CHARGEQ OUT THROUGH .THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE RE-FERRED TO FILE PERSONNEL.
-NOTICE-
TECHNICAL REPORT NE-819 - Rev. 0 I
I SURRY UNIT 1, CYCLE 11 STARTUP PHYSICS TEST REPORT 1-I
-1 NUCLEAR.ANALYSIS AND.FUEL NUCLEAR ENGINEERING SERVICES I VIRGINIA POWER FEBRUARY 1991 I
I' BY,Jr?.rtl~ 2-/~r~(
I .PREPARED D. McElroy Date REVIEWED BY:+/-?.Q:>~. 2 hR fqt P. D. Banning iTatT" REVIEWED Bs:;;l;(J , ~'
J
- -'=----'
W. Henderson J-&-9/
Date I I' APPROVED BY,b-~ 2-)sj, 1 D. D iadosz Date I
QA Category: Nuclear Safety Related I Keywords: SlCll, Startup
I 1 CLASSIFICATION/DISCLAIMER I
The data, techniques, information, and conclusions in this report have I been prepared solely for use by Virginia Electric and Power Company (the I; Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company I therefore makes no claim or warranty whatsoever, express or implied, as to thei.r accuracy, usefulness, or applicability. In particular, THE I COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL .ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING I
,,. 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 I use is expressly forbidden except with the*prior written approval of the Company. Any such written approval shall itself be deemed to incorporate I' the disclaimers of. liability and disclaimers of warranties provided I herein. In no event shall the Company be liable, under any legal theory
,, whatsoever (whether contract, tort, warranty, or strict or absolute liability), for ahy 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,
'I techniques, information, or conclusions in it.
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I) NE-819 SlCll Startup Test Report Page 1 of 59
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 Section 3 Control Rod Bank Worth Measurements ....... . 21 Section 4 Boron*Endpoint an~ Worth Measurements...... 26 Section 5 Temperature boefficient Measur~ment ....... : 30 Section 6 Power Distribution Measurements ... *........ . 32 Section 7 References .. _........... ; .................. . 40 APPENDIX Startup Physics Tests Results and Evaluation Sheets ....................... . 41 l'l I
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LIST OF TABLES
- 1 I:
TABLE TITLE PAGE
- 1. 1 2.1 Chronology of Tests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Hot Rod Drop Time Summary.............................
10 18 I
3.1
- 4. 1 Control Rod Bank Worth Summary........................
Boron* Endpoints Summary. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .
23 28 I
5.1 Isothermal Temperature Coefficient Summary............ 31 ,t 6.1 Incore Flux Map Summary ............ ~.................. 34 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specification Limits............. 35 I
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.,. FIGURE TITLE LIST OF FIGURES PAGE.
II 1. 1 1.2 Core Loading Map. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Beginning of Cycle Fuel Assembly Burnups.................
11 12
- I 1:3 1.4 Incore Movable Detector Locations........................
Burnable Poison and Source Assembly Locations............
13 14 I 1. 5 Control Rod Locations ......................... *...... . . . . . 15
/I 2 .1 2.2 Typical Rod Drop Trace .... , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Rod Drop Time - Hot Full Flow Conditions.................
19 20 I/ 3.1 3.2 Bank D Integral Rod Worth - HZP..........................
Bank D Differential Rod Worth - HZP ..................... .
24 25
- I\ 4.1 Boron Worth Coefficient ................................. . 29 6.1 Assemblywise Power Distribution - 27% Power .............. 36
- 1 6.2 Assemblywise Power Distribution - 61% Power .............. 37 I 6.3 6.4 Assemblywise Power Distribution Assemblywise Power Distribution -
88% Power ..............
100% Power .............
38 39 I
II
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- 1 PREFACE I* This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 1, Cycle 11 core could be I operated safely, and makes an initial evaluation of the performance of
- I the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard test I, techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on
- 1 file at the Surry Power Station. Therefore, only a cursory discussion I) 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 I predictions, and an evaluation of the results.
The Surry 1, Cycle 11 Startup Physics Tests Results and Evaluation I 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 I conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of I the startup test results in a consistent format. The design test I conditions and design values of the measured parameters were completed
,, prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1
- During the tests, the data I sheets were used as guidelines both to verify that the proper test I* conditions were met and to facilitate the preliminary comparison between I NE-819 S1Cll Startup Test Report Page 5 of 59
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I measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests.
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,. SECTION 1 1 INTRODUCTION AND
SUMMARY
- 1. On October 6, 1990 Unit No. 1 of the Surry Power Station shutdown 1, for its eleventh refueling. During this shutdown, 55 of the 157 fuel
,., assemblies in the core were replaced with 52 fresh fuel and 3 twice-burned assemblies. The eleventh cycle core consists of 11 sub-batches of fuel:
/I two fresh batches (batches 13A and 13B); three once-burned batches, all three from Surry 1 Cycle 10/lOA (batches 12A, 12B, and S2/12A); seven
- 1. twice-burned batches, one from Surry 1 Cycles 6 and 10/lOA (batch BB),
- I; one from Surry 1 Cycles 7 and 9 (batch 9A), one from Surry 1 Cycles 8 and 9 (batch lOA), two from Surry 1 Cycle_s 7 and 10/lOA (batches 9A and 9B),
a: and two from Surry 1 Cycles 9 and 10/lOA (batches llA and llB); and one thrice-burned batch from Surry 1 Cycles 8, 9, and 10/lOA (batch lOA).
I The core loading pattern and the design parameters for each batch are I shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2.
incore movable detector locations are identified in Figure 1.3.
The Figure
'I 1.4 identifies the location and number of burnable poison rods and source assemblies for Cycle 11, and Figure 1.5 identifies the location and number of control rods in the Cycle 11 core.
I On December 17, 1990 at 2347, the eleventh cycle core achieved initial criticality. Following criticality, startup physics tests were I
,, performed as outlined in Table 1.1.
tests follows:
A summary of the results of these I NE-819 SlCll Startup Test Report Page 7 of 59
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- 1. The measured drop time of each control rod was within the 2.4
,I second limit of Technical Specification 3.12.C.1. ,
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- 2. Individual control rod bank worths were measured using the rod ;I swap technique 2 and the results were within 2.8% of the design predictions. The sum of the individual measured control rod bank worths was within 0.1% of the design prediction. These results 11:,
are within the design tolerance 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. I
- 3. Measured critical boron concentrations for. two control bank \l configurations were within 24.0 ppm of the design predictions.
These results we~e within the design tolerances and also met the I'.
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Technical Specification 4. 10 criterion that the overall core reactivity balance shall be within +/-1% Ak/k of the design prediction.
- 4. The boron worth coefficient measurement was within 3.3% of the 1:
design prediction, which is within the design tolerance of +/-10%.
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- 5. The measured isothermal temperature coefficient (ITC) all-rods-out configuration was within 1.07 pcm/°F of the design for the I
prediction. This result is within the design tolerance of +/-3 I pcm/ °F. The measured ITC of -4. 32 pcm/ °F meets the Technical Specification 3. 1. E. 1 criterion that the moderator temperature
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coefficient (MTC) be less than or equal to +3.0 pcm/°F. When the NE-819 SlCll Startup Test Report Page 8 of 59 .*,
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Doppler temperature coefficient and a 1.0 pcm/°F uncertainty are
- accounted for in the MTC limit, the MTC requirement is sa~isfied as long as the ITC is less than or equal to +0.78 pcm/°F ..
1 I/ 6. Core power distributions for at-power conditions were within established design tolerances. Generally, the measured core 1 power distribution was within 2~ 1% of the design predictions.
The heat flux hot channel factors, F-Q(T), and enthalpy rise hot I channel factors, F-DH(M), were within the limits of Technical Specifications Section 3.12.B.1, respectively.
1 t In summary, all startup physics test results* were acceptable.
Detailed results, specific design ~oierances and acceptance criteria for I each measurement are presented in the following se.ctions of this report~
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I' Table 1.1 I SURRY 1 - CYCLE 11 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS I
Test Date Time Power Reference Procedure
,I Hot Rod Drop - Hot Full Flow Zero Power Testing Range Reactivity Computer Checkout 12/16/90 12/18/90 12/18/90 0250 0204 0221 HSD HZP HZP 1-PT-7.2 1-PT-28 .11 1-PT-28 .11 1:
Boron Endpoint - ARO Temperature Coefficient - ARO Bank D Worth Boron Endpoint - -D in 12/18/90 12/1,8/90 12/18/90 12/18/90 0554 0759 0941 0941 HZP HZP HZP HZP 1-PT-28 .11 1-PT-28.11 1-PT-28 .11 1-PT-28; 11 I
Bank C Worth - Rod Swap Bank B Worth - Rod Swap Bank A Worth - Rod Swap 12/18/90 12/18/90 12/18/90 1437 1532 1632 HZP HZP HZP 1-PT-28.11 1-PT..:28 ._11 1-PT-28.11 I'
Bank SB Worth - Rod Swap Bank SA Worth - Rod Swap Flux Map - 21% Power 12/18/90 12/18/90 12/20/90
- 1714
. 1859 0819 HZP HZP 2.7%
1-PT-28.11
. 1-PT-28 .11 1-PT-28.2
\I Flux Map - 61% Power 12/21/90 0700 61% 1-PT-28.2 I
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Flux Map - I/E Calibration 12/21/90 1200 62% 1-PT-28.2 Flux Map* - I/E Calibration 12/21/90 1600 59% 1-PT-28.2 Flux Map - HFP 12/26/90 1200 100% 1-PT-28.2 I*
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,~
,~ Figure 1.1 SURRY UNIT 1 - CYCLE 11
- coRE LOADING KAP
- 1-~
.H p R A B C D E F G J K L
" N 118 98 I 118 I I 3F5 I 5D8 I 3F3 I 15
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I_ _ I 1--> BATCH 1--> ASSEHBLY ID I 3F9 I OD2 I 4F2 I 1_ _ 1_ _ 1_ _ 1 1
FUEL ASSEHBLY DESIGN PARAHETERS SUB-BATCH S2/12A 88 9A 98 lOA llA 118 12A 128 13A 138 I INITIAL ENRICHMENT CW/0 U-235)
BURNUP AT BOC 11 CHWD(HTUJ 3.79 17616 3.40 29262 3.59 33859 3.61 34088 3.60 36640 3.60 35348 3.80 36543 3.80 19469 3.99 19050 3.80 0
4.01 0
ASSEHBLY .TYPE 15xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 NUHBER OF ASSEHBLIES l 12 3 7 5' 8 22 24 23 24 28 FUEL RQ_DS PER ASSEHBL 1 204 204 204 204 204 204 204 204 204 204 204 t
I NE-819 S1Cll Startup Test Report Page 11 of 59
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Figure 1.2 SURRY UNIT 1 - CYCLE 11 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS p R A B C 0 E F G H J K L
" H 3F5 508 3F3 I 15
.I 392411 347881 394091
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NE-819 SlCll Startup Test Report Page 12 of 59 I
I ti Figure 1.3 I. SURRY UNIT 1 - CYCLE 11 INCORE MOVABLE DETECTOR LOCATIONS 1 R p H H L K I
J I
H I
G I
F E D C B A I I I HD I I 1
---,---l _ _ l_ _ l_ _ l_ _~ - -
1 I I I I I I I I I HD I I 2
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I I I I .I I I I I I I HD I I I HD I HD I I I I HD I 3
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I I I I I I I I I I I I I I I HD I I I I I I I I I 4
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I I I I I I I I I I I I I I I I HD I I HD I I HD I I I I HD I HD I I HD I 5 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 HD I I I HD I I HD I I I I *1 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 I I I HD I I I I HD I I HD I I I HD I I HD I I 7 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 HD I I HD I I HD I I I I I HD I I I HD I HD 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 I I I HD I I I I HD I HD I *1 I I I HD 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 HD I* I I *I HD I I I I t HD I I HD I 10
- t.
1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I . I I I I *1 . I I I I I I I I I I I I HD I I I HD I I HD I HD I I I I 11 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 HD I I I I HD . I I I I I HD I HD 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 I I I HD I I HD I I I 13 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I I *1 I I I HD I I I I HD I I I 14 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I HD - Hovable Detector I HD I I I 15 I_ _ I_ _ I _ _ I I
I
- I I
I NE-819 SlCll Startup Test Report Page 13 of 59
1*
Figure 1.4 I
SURRY UNIT 1 - CYCLE 11 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS I A B C D E F G H J K L H H p R I I I I
. I I I
I I
I BP I I
I I
I I
,---I _ _ I _ _ I _ _ I _ _---,-__
I I BP I.
_ _ 1_ _ 1_ _ 1_*_1 _ _ 1_ _ 1_ _ 1_ _ 1_ _
I I I I I I
I I
I I 15 14 I I
I I SP I 16P I I 20P I I 16P I
_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _
I I I I I I I I SP I I
I I I 13
,1:
I I I 12P I I ss2. I 4P I I I 12P I I I 12
_ _ l_ _ l_ _ l _ _ l_ _ l_ _ l_ _ l _ _ l_ _ l_ _ l_~I _ _ I_ _
I I
I I
I SP -I 12P I
I I
I 16P I
I I
I 20P I
I I
I 16P I
I 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_-_1 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I
I I
I 16P I
I I
I 16P I
I I,
I 4P I
I I
I 4P I
I I
I 16P I
I 12P I
I I
I I
SP I 16P I
I I
I
- I I
I I
11 10
,I
_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_*_1 _ _ 1_ _ 1_ _
I I
I I BP I
I I
I
' I I
I I 4P I
I I
I 16P I
I I
I 4P I
I I
I I
I I
I BP I
I I
I 9 I,
,~
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 I 20P I 4P I 20P I I 16P I I 16P I I 20P I 4P I 20P I I I B 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 BP I I I I 4P I I 16P I I 4P I I SS7 I I BP
- I I 7 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 16P I I 4P I I 4P I I 16P I I 16P I I 6 I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I _ _ I_ _ I _ _ I I
I I I I SP I 12P I I I I 16P I I I I I 20P I I I I 16P I 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_._ _ 1 I I I 12P I SP I I I I 5 .1, I I I I I I I I I I I I I I I 12P I I I 4P I ss1 I I 12P I I I 4 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 SP I 16P I I 20P I I 16P I SP I I 3 I_ _ I_ _ I_ _ I_ _ I _ _ I_ _ I_ _ I_ _ I_ _ I I I I I I I I I 4P - 4 BURNABLE POISON ROD CLUSTER I I I BP I I BP I I I 2 SP - 5 BURNABLE POISON ROD CLUSTER 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1~_1 _ _ 1 8P - B BURNABLE POISON ROD CLUSTER I I I I 12P - 12 BURNABLE POISON ROD CLUSTER I I I I l 16P - 16 BURNABLE POISON ROD CLUSTER I _ _ I_ _ I _ _ I 20P - 20 BURNABLE POISON ROD CLUSTER 1:
SSxx - SECONDARY SOURCE
~,:
I I
I NE-819 S1Cll Startup Test Report Page 14 of 59 I
I
,~ Figure 1.5 SURRY UNIT 1 - CYCLE. 11 CONTROL ROD LOCATIONS 1 R p N H L K J H G F E D C B A
'*1/
180° I
- Loop c I. I I I Loop B 1*
Outlet I __ I __ I __ I Inlet I I A I I D I I A I I 2
_1_1_1_1_1_*_1_.1_1_
N-41 I I I I SA I I SA I I SP I I N-43 *3
__I_I_I_I_I_I_I_I_I_I_
1( I I
_1_1_1_1_1_1_1~1_1_1_1_1_._
l_l_l_l_l_l_*_I_I_I_I_I_I_I_I I
I SP I I
I I I 4
5 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 1** Inlet I
. 90°- I I 1* SA I I* I I SB I I SB I I SP I l _ l _ l _ l _ l _ l _ l _ l _ f _ ._ I _ I _ I _ I _ I _ I _ I I D I I I I c I I I I c I I I SA I I I D I I I Outlet I - 270° 7
8 I _ .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 1_1_1_1_1_1_1_*_1 ___ 1_*_1_1_1_.1_1_1_*1 IA I I.BI ID I' IC-I I SB I ID I I I I SA I IB I- '*IA I I I 9 10 l_l_l--=---1_1_-_ I _ I _ I _ I _ I _ I _ '_ I _ I _ I I I I I I SB I I_I_I_I_I_I_I_I_I_I_I_I_I_I I IC I IB I I
1_1_1_1_1_1_1_1_1_1_*_1_1 I
I I SP I I IB I I . SB I IC I I SP I I
I 11 12 I I SP I
- I SA I I SA I I I I 13 I N-44 I __ I __ I __ I __ I __ I _ I __ I __ I __ I N-42 I I A I I_I_I_I_I_I_I_I I
I D I I I I A I I
I 14 15 Loop A I __ I __ I __ I Loop A Absorber Outlet Inlet
,'. Material Ag-In-Cd Function I0 o
Number of Clusters t Control Bank D Control Bank C Control Bank B Control Bank A Shutdown Bank SB 8
8 8
8 8
I Shutdown Bank SA SP (Spare Rod Locations) 8 8
I I
1~
I NE-819 S1Cll Startup Test Report Page 15 o_f 59
I
- t. SECTION 2 I'
CONTROL ROD DROP TIME MEASUREMENTS 1
I The drop time of each control. rod was measured at hot full -flow reactor coolant system (RCS) conditions (Tavg above 547+/-5°F) in order to I 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 I Technical Specification 3.12.C.1.
1\ The rod drop times were measured by withdrawing a rod bank to its
,,, fully withdrawn position, and removing the movable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be
- 1. dropped. This all~wed the rod to drop into the core as it would during a plant trip. The stationary gripper coil voltage and the Individual Rod I Position Indication (IRPI) priinary coil voltage *signals were recorded to determine the the rod drop time. This procedure was repeated for each I/ control rod.
I 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
- I: this voltage is a function of control *rod velocity. As the rod enters I 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 I
,. reaches the bottom of the dashpot.
are caused by rod bouncing.
Subsequent variations in the trace I NE-819 SlCll Startup Test Report Page 16 of 59
I 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 h *.
- 1... s *~* t* ion 2 ...
1 :..'r,ec,.nlca pec;.,~.1.ca .. *,, l"*,,
...;._L.,*,,.,.1 spec1'f'1es a maximum
- rod d rop t*1me from loss of stationary gripper coil voltage to dashpot entry of 2. 4 seconds with the RCS at hot, full flow conditions. These test results satisfied this limit.
/I
,f
\
I.
I' t:
.I)
- I I
I f
NE-819 S1Cll Startup Test Report Page 17 of 59
I
,, Table 2.1 I SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS HOT ROD DROP TIME
SUMMARY
- 1
,, ROD DROP TIME TO DASHPOT ENTRY I' SLOWEST ROD FASTEST ROD AVERAGE TIME I, B-06 . 1.38 sec. K-04 1.21 sec. 1.30 sec.
1 f,
I I
I
'I, I.
I I
I NE-819 SlCll Startup Test Report Page 18 of 59
___ I
sutrLI am, oaor TaACI BEGINNING or DASIIPOT tbeginnlnq of firet ,downtua:n in ta:ace)
CJ) rt Pl 11 rt c
'd
>-3
(!)
INITIATION OF ROD DROP IVENT MARK
' I I BOTl'OH OF DASHPOT (beqlnning of first upturn in ta:ace)
STATIONARY GRIPPER en c:::
i-<
c:::
- z:
H COIL VOLTAGE TRACE >-3 1:/l rt
>-3 I-'
~
(!)
ROD DROP TIME i-< I
'd "ti 0 H C"l 11 C"l i-<
rt > C"l t""< t""< "'j t-*
- ,::, tr:! OQ g I-'
I-'
=11 CD t:::i cn
- ,::, >-3 o>
"ti:,::,
N I-'
>-3 >-3
- ,::, c:::
>"ti C"l "ti 60Hz IRPI PRIMARY tr:! ::i::
COIL VOLTAGE TRACE i-<
en H
C"l 60Hz TRACE (if used) en
~
Pl >-3
()Q tr:!
(t) en TIME >-3 en .
I-'
I.O 0
Mi U1 I.O
-I Figure 2.2 SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS
,, R p N H I
L K I 1.29 I I
I J
I I
I H
I 1.31 I I
I
_ _ _ _ _ 1_ _ 1_ _ 1_ _ 1_ _~ - -
1 I I G
_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _
I I
I F
I 1.31 I E
I D C B A 1
z I I I I I I I I I I I I I I I 1.34 I I 1.33 I I 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 1. 29 I I 1. 21 I I I I 1. 21 I I 1. 29 I I
_ _ 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 1.26 I I I I I I 1.28 I I 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 1. 30 I I 1. 26 I I 1. 31 I I 1.31 I I 1. 29 I I 1. 25 I I 1. 38 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 I I I 1.30 I I I I 1.31 I I 1.29 I I I I 1.32 I I I 7 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 1.32 I I I I 1.30 I I I I 1.34 I I I I 1.35 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 I 1.33 I I I I 1.28 I I 1.32 I I I I 1.33 I 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 1.28 I I 1.26 I I 1.31 I I 1.32 I I 1.32 I I 1.2s I I 1.35 I JO 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 1. 21 I I I I I I l. 30 I I 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 1. 21 I I 1. 27 I I I I 1. 26 I I 1. 31 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 I I 1.28 I I 1.32 I I I I l3 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I I I I I I I 1.37 I I 1.31 I I 1.37 I I 14 I
1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I I I I I 15 I_ _ I_ _ I_ _ I I I I I X.XX 1--> ROD DROP TIHE TO DASHPOT ENTRY CSECl I_ _ I l
I::
I' I
I NE-819 S1Cll Startup Test Report Page 20 of 59
I I SECTION 3 I
CONTROL ROD BANK WORTH MEASUREMENTS I
,, Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 2
- The initial step of the rod swap I method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its I
,, reactivity worth using conventional test changes resulting from the reference techniques.
bank movements continuously by the reactivity computer and were used to determine the The reactivity were recorded
'I. differential and integral worth of the reference bank. For Cycle 11, Control Bank D was used as the reference bank.
I After the completion of the reference bank reactivity worth
'I measurement, the reactor coolant system temperature concentration were stabilized with the reactor just critical and the and boron I reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by moving the reference bank to its fully 1: inserted position and recording the core reactivity and moderator t temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps and then one of the other I control rod banks (i.e., a test reactivity of the reference bank withdrawal.
bank) was inserted to balance This sequence was repeated the I until the test bank was fully inserted and the reference bank was positioned such that the core was just critical. This measured critical I position (MCP) of the reference bank with the test bank fully inserted II was used to determine the integral reactivity worth of the test bank.
I NE-819 SlCll Startup Test Report Page 21 of 59
i I I The core reactivity, mcideraior temperature, and the differential worth I
of the reference bank were recorded with the.reference bank at the MCP.
The rod swap maneuver then was repeated in reverse such that the reference I
I bank again was near full insertion with the test bank fully withdrawn from the core. This rod swap process was then repeated for each of the other control and shutdown banks.
A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Tests Results and Evaluation Sheets I
given in the Appendix, the individual nieasured bank worths for the control_
and shutdown banks were within the design tolerance (+/-10% for the I
reference bank and +/-15% or 100 pcm, which ever is greater, for the test
- 1.*
banks). The sum of the individual measured rod bank worths was within 0.1%
of the design prediction. This is well within the design tol~rance of I:
+/-10% for the sum of the individual control rod bank worths.
The integral and differential reactivity worths of the reference
.I bank (Control Bank D) 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.
were satisfactory.
In summary, the measured rod worth values t
I I
I I
NE-819 SlCll Startup Test Report Page 22 of 59
I I. Table 3.1 I SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
SUMMARY
I
,. MEASURED WORTH PREDICTEI)
WORTH PERCENT DIFFERENCE
(%)
I BANK (PCM) (PCM) (M-P)/P X 100
,. D-Reference Bank C
B A
SB 1183. 7 710.0 1082 .1 518.5 770 .3 1194.0 724.2 1075.2 504.4 788.4
- -0. 9
-2.0 0.6 2.8
-2.3 1 SA Total Worth 1189 .4 5454.0 1163 .0 5449.2 2.3 0.1
- I
- I I
I I
I I-I I NE-819 SlCll Startup Test Report Page 23 of 59
I Figure 3.1 I SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS BANK D INTEGRAL ROD WORTH - HZP
,f ALL OTHER RODS WITHDRAWN 1,200 1,100
'I I
- e u
a..
1,000 900 800
- I:
I-c::
a 3:
700 t 600
....J c:: 500
{!)
c::
l.&J I-z 400 300 I*
200 100 I
I I
I NE-819 SlCll Startup Test Report Page 24 of 59 I
I I Figure 3.2 I SURRY UNIT 1 - CYCLE 11 STARTUP.PHYSICS TESTS BANK D DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN I
I 9.00 8.50 I 8.00 ci_"7.50
~7.00 I (/)
,s.so
- e u 6.00 1: ~5.50
~ 5.00
~4.50 I ~ 4.00
_J
~3.50 I ~ 3.00 LLJ O! 2.50 LLJ 1..&.. 2.00 I I.&..
c 1.50 1.00 I 0.50 0.00 0 S 15 25 JS 45 55 65 75 BS 95 105 115 125 135 145 155 165 175 185 105 205 215 225 I BANK POSITION (STEPS) t I
I I
I I NE-819 S1Cll Startup Test Report Page 25 of 59
I SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint
,, (RCS)
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 I with design predictions. For each critical bo*ron concentration I 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.
in this table and in the Startup Physics Tests Results and Evaluation As shown Sheets given in the Appendix, the measured critical boron endpoint values I were within their respective design tolerances and met the requirements of Technical Specification Section. 4.10 regarding I
core reactivity I balance. In summary, the boron endpoint results were satisfactory.
I Boron Worth Coefficient
,I The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW)
I was determined. By relating each endpoint concentration to the integrated I rod worth present in the core at the time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was I obtained.
I NE-819 SlCll Startup Test Report Page 26 of 59
I A plot of the boron concentration versus inserted control rod worth I
is shown in Figure 4.1. As indicated in this figure and in the Appendix, the DBW measured was -8 .16 pcm/ppm. This is within 3. 3% of the pr'edicted I
value of -7.90 pcm/ppm and is well within the design tolerance of +/-10%.
I
.In summary, the measured boron worth coefficient was satisfactory.
I
- 1 I
I I
NE-819 SlCll Startup Test Report Page 27 of 59 I
I I Table 4.1 I \
SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
I I Measured Predicted Difference Control Rod Endpoint Endpoint M-P I Configuration (ppm) (ppm) (ppm)
I ARO D Bank In 1499 1354 1523 1348*
-24
+6 I - '
I I
The predicted endpoint for the D Bank In configuration was I 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 Sheets in the Appendix.
I I
I I
I I
I I NE-819 S1Cll Startup Test Report Page 28 of 59
I Figure 4.1 l'I SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS.
I BORON WORTH COEFFICIENT Measured DBW = -8.16 pcm/ppm .,
1,300
. 1,200 ******...1...........1.. *........1...........1...........1...........1.......... l.......... 1.......... 1...........1.......... 1.......... 1.......... 1.......... 1.......... 1.......... 1
! i i i i ! ! I I I I I I I I I 1,100 1,000 *........1....... *...:...... ..!...........1...........!...........!.*.........L.. . . ..1......... 1...........1. ...... J. . . . . 1.......... 1.......... L. . . . .1.......... 1 . I
- 900
. -.J. -.. J. _._ :* *- * * * -* :**- . .L_ .J_ . .J_.J.*_...J. . .__ i._____i*.*. . . .t. _._.L. . .l. . . I
- e u
c.. 800 _.1
>- 700 I-i'.=
u
-ct w
D:
600 500 ::::::!::::::. ::L::::::i : = .: i: =: T~~~*i:=~~-+~-* t~~~-* i=:~~:=i*
- i . i* J * '. i i I i .
- J I* i i i I i i
- :*: : i::::::C:::: !::::::: i::::::::i*
I 400 300 ... *.....1.......... .1 ...........1...........1...........!...........I.......... I. *. . . .!...........!........... =.......... ! . . ...1..........1. . . . . 1. . . . . l. . . . ..J I 200 100 . ..J. - . Ji. --.l. ._.J___-.LJ_.J. . . Li . J_ _ l_.__...l. . -*. l. . . .L. . L..__:
~
..1......
~ ~ j ~ ~ ~ ~ ~ 1 ~. ~ ~
I 0+----i--+--+--+--+--~-4--+--~-4--4--~-4--+-~~~
1J50 1J60 1370 1380 1390 1400 1410 1420 1430 14-4<1 1450 1-460 1470 1480 H90 1500 1510 BORON CONCENTRATION (PPM) I I
I
- 1 I
NE-819
- S1Cll Startup Test Report Page 29 of 59 I
I I SECTION 5 I
TEMPERATURE COEFFICIENT MEASUREMENT I
The isothermal temperature coefficient (ITC) at the all-rods-out I condition is measured by controlling the reactor coolant system (RCS)
I temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity I changes on the reactivity computer. This test sequence includes a
- I cooldown followed oy a heatup.
I Reactivity was 3.0°F and the RCS measured during the RCS cooldown of approximately heatup of approximately 4.8°F. Reactivity and I temperature data was taken from the reactivity computer and strip chart recorders. Using the statepoint method, the temperature-coefficient was I determined by dividing the change in reactivity by the change in RCS I temperature. An X-Y plotter, which plotted reactivity temperature, confirmed the statepoint method in calculating the measured versus I ITC.
I The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the I Startup Physics Test Results and Evaluation Sheet given in the Appendix, I the measured isothermal temperature coefficient value was within the design tolerance of +/-3 pcm/ °F and met the requirements of Technical I Specification 3.1.E.1. In summary, the mea~ured result was satisfactory.
I I NE-819 S1Cll Startup Test Report Page 30 of 59
I Table 5.1 II SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
I I
ISOTHERMAL TEMPERATURE COEFFICIENT I
BANK POSITION TEMPERATURE RANGE (OF)
BORON CONCENTRATION (ppm) C/D H/U (PCM/°F)
AVE. DIFFER.
I MEAS. PRED. (M-P)
I 542.2 D/216 to 547.0 1498 -4.67
-3.96 -4.32 -5.39 -1. 07 I
1, I
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I Page 31
- of 59 NE-819 S1Cil Startup Test Report I
I I
,. SECTION 6 POWER DISTRIBUTION MEASUREMENTS
-I The core power distributions were measured using the movable incore I detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles I in 48 core locations (see Figure 1.3). For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and I scanned for 61 discrete axial points by the PRODAC P-250 process computer.
I Full core, three-dimensional power distributions are determined from this data using the Westinghouse computer program, INCORE 3
- INCORE couples I the measured voltages with predetermined analytic power-to-flux ratios I in order to determine the power distribution for the whole core.
A list of the full-core flux maps taken during the startup test I program and the measured values of the important power distribution parameters is given in Table 6.1. A comparison of these measured values I with their Technical Specification limits is given in Table 6.2. Flux I Map 1 was taken at 27% power to verify the radial power distribution (RPD) predictions at low power. Figure 6.1 shows the measured RPbs from this I_ flux map. Flux maps 2, 5 and 6 were taken at 61%, 88%, and 100% power I levels with different control rod configurations. These flux maps were taken to check at-power design predictions and to measure core power I distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2, 6.3 and 6.4. These I figures show that the measured relative assembly power values were I generally within 2.2% of the predicted values. Further, the measured I NE-819 SlCll Startup Test Report Page 32 of 59
I F-Q(T) and F-DH(M) peaking fact9r values for the at-power flux maps were I within the limits of Technical Specifications 3.lj.B.1.
In conclusion, the power distribution measurement results were I
considered to be acceptable with respect to the design tolerances, the I.
accident analysis acceptance criteria, and the Technical Specification limits. It is therefore anticipated that the core will continue to I operate safely throughout Cycle 11.
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NE-819 S1Cll Startup Test Report Page 33 of 59 I
I I TABLE 6.1 SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS INCORE FLUX MAP
SUMMARY
I I I I
I HAP I
I I IHAPI I
BURNI UP I I
I
!BANK I I
I F-QCTl HOT CHANNEL FACTOR 1 I I F-DHCHl HOT I CHNL.FACTOR CORE FCZl HAX QPTR 2 I I I I
I AXIAL! NO.I I
I I I* DESCRIPTION I
I I_ _ _ _ _ _ I_I
)LOW POWER INO.I DATE I
I I
I l )12-20-90)
I HWD/IPWRI D I HTU_ICZllSTEPSIASSYIPINIAXIALI I I I I I
IPOINTIF-QCTl I I I I
IPOINTI I
I l _ _ l_l _ _ l _ l _ l _ _ l_ _ l _ l _ l _ _ l_ _ l_ _ l _ l _ l _ _ l _ l I
I OFF I OF I IASSYIPINIF-DHCHllAXIALI FCZll HAX ILOCI SET ITHIHI I CZl IBLESI 21 271 176 I G 21 EDI 26 I 2.214 IF 3) CL) 1.502 I 25 )1.362)1.0131 NW) 5.52) 48 I
)QPTR VERIFICATION I 2 112-21-90) 15 I 61) 202 I J 2) KDI 22 I 1.873 IF 31 CLI 1.427 I 22 )1.216)1.006) NWI 4.80) 44 I I IQPTR VERIFICATION I 5 )12-23-90) 53 I 881 223 I J 31 LEI 35 I 1.799 I J 3) LEI 1.412 I 32 )1.166)1.005) NWI 0.63) 45 I
)HOT FULL POWER I
I 6 )12-26-90) 165 1100) 224 I J 31 LEI 36 I 1.770 I B 91 DK) 1.403 I 34 )1.169)1.0011 NWI -1.09) 47 I I_I l _ _ l_l _ _ l _ l _ l _ _ l_ _ l _ l _ l _ _ l _ _ l _ _ l _ _ l_l _ _ l _ l I NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEHBLY LOCATIONS CE.G. H-8 IS THE CENTER-OF-CORE ASSEHBLY),
FOLLOWED BY THE PIN LOCATION (DENOTED BY THE "Y" COORDINATE WITH THE SEVENTEEN ROWS OF FUEL RODS LETTERED A THROUGH RAND THE "X" COORDINATE DESIGNATED IN A SIHILAR HANNER).
IN THE "Z" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROH THE TOP OF THE CORE.
I
- 1. F-Q(Tl INCLUDES A TOTAL UNCERTAINTY OF 1.05 X 1.03.
- 2. QPTR - QUADRANT POWER TILT RATIO.
- 3. HAPS 3 AND 4 WERE QUARTER-CORE FLUX HAPS TAKEN FOR INCORE/EXCORE CALIBRATION. CI/E CALIBRATION)
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I I NE-819 SlCll Startup Test Report Page 34 of 59
I Table 6.2. I SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS I
I MAP PEAK F-Q(T) HOT CHANNEL FACTOR*
F-Q(T) HOT CHANNEL FACTOR**
F-DH(M) HOT CHANNEL FACTOR I NO. MEAS LIMIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN
(%) I 1 2.214 4.594 26 2.214 4.570 24 51.5 1.502 1. 889
- 20.5 2
5 6
1.873 1.799
- 1. 770 3.746 2.636 2.320 22 35 36 1.872 0 .858
- 1. 770 3.7~4 1.136 2.320 21 36 1
49.8 24.5 23.7 1.427 1.412 1.403
- 1. 732 1.606 1.550 17.6 12.1*
9.5 I
I
- The Technical Specification's limit for the heat flux hot channel factor, F-Q(T), is a function of* car~ height. The value for F-Q(T) listed abo-ve is the maximum value of F-Q(T) in the core. I.
The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T).
The value for F-Q(T) listed above is the value at the plane of m1n1mum margin.
- The minimum margin values listed above are the I
minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each map. I The measured F-Q(T) hot channel factors include 8% total uncertainty.
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NE-819 SlCll Startup Test Report Page 35 of 59 I
!1 I Figure 6.1 SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 27% POWER I R p N_
PREDICTED *
" K J 0.30 H
0.34 G
0.30 F E .D C PREDICTED B A HEASURED . 0.33. 0.37. 0.33. HEASURED 1 I . PCT DIFFERENCE.
0.34 0.80 9.9. 9.7. 8.6 .
1.22 1.04 1.22 0.79 3.0 . 2.1 . 3.6 . 3.9 . 5.6 . 6.6 . 6.0 .
0.34
. 0.35 .. 0.82 . 1.27 . 1.08 . 1.29 . 0.85 . 0.36 .
.PCT DIFFERENCE.
2 I 0.36 1.17 1.29 1.34 1.30 1.33 1.27 1.15
. 0.37. 1.18. 1.30. 1.36. 1.30. 1.36. 1.36. 1.21. 0.37.
2.6 . 0.9 . 0.8 . 1.7 . -0.l . 2.4 . 6.6 . 5.6 . 4.9
- 0.35 3
0.35 0.60 1.19 1-03 1.29 1.31 1.28 1.01 1.16 0.59 0.34 I . 0.36. 0.61. 1.19; 1.04. 1.32. 1.33. 1.28. 1.02. 1.19. 0.60. 0.35. 4 2.7. 1.6. -0.3. 1~7. 2.3. 1.6. -0.4. 1.1. 2.7. 3.2. 3.7.
0.35 1.17 1.19 0.93 1.22 *0.96 1.28 0.95 1.21 0.91 1.17 1.16 0.35
. 0.36. 1.20. 1.20. 0.95. 1.25. 1.00. 1.32. 0.97. 1.21. 0.92. 1.20. 1.20 . 0.36. 5 2.6 . 2.5 . 1.2 . 1.9 . 1.8 . *3.9 . 3.3 . 1.3 . 0.5
- 1.3 . 2.7 . 3.1 . 3.2
- I ........................ -. ................................................................... .
0.81 1.29 1.03 1.23 1.20. 1.22 1.27 1.21 1.19 1.20
. o.s3. 1.33. 1.05. 1.22. 1.21. 1.24. 1.30. 1.22. 1.1s. 1.2r. 1.03. 1.31 . 0.81 .
1.02 3.1 . 3.0 . 1.6 . -0.4 . 0.9 ,* 1.6 . 2.0 . 0.4 . -0.8 . 0.7 . 0.8 . 0.6
- 0.5 .
1.30 0.81 6
0.31 1.24 1.35 1.30 0.97 1.23 0.98 1.23 0.98 1.22 0.96 i.30 1.36 1.24 0.31 I . 0.32. 1.27. 1.39. 1.31 . 0.95. 1.20. 0.97. 1.23. 0.97. 1.20. 0.94. 1.28. 1.33. 1.22. 0.30 .
3.1 . 2.5. 3,0. 0.4. -1.9. -1.8. -1.2. -o.o. -0.9. -1.7. -1.6. -1.7. -1.6. -1.7. -1.0.
0.35 1.06 1.31 1.32 1.29 1.29 1.24 0.97 1.24 1.28 1.29. 1.33
. 0.36. 1.08. 1.32. 1.33. 1.26. 1.27. 1.22. 0.96. 1.21. 1.24. 1.26. 1.30. 1.29. 1.05. 0.34.
1.32 1.05 0.34 7_
8 I 3.0 . 2.1. 0.7. 0.4. -2.0. -1.0. -1.5. ~1.6. -2.2. -3.0. -2.5. -2.l. -2.2. -0.2. -0.0 .
0.32 1.24 1.35 1.30 0.96 1.23 0.98' 1.23 0.98 1.23 0.97 1.31 1.35
. 0.33 . 1.25 . 1.33 . 1.29 . 0.98 . 1.22 . 0.95 . 1.20 . 0.96 . 1.20 . 0.96
- 1.31
- 1.35 . 1.23 . 0.30 .
3.1 . 0.5. -0.9. -0.2. 1.7. -0.8. -3.4. -2.6. -2.3. -2.2. -1.l. 0.5. -0.5. 4 . 0.6.
1.24 0.30 9
I 0.80 1.29 1.03 1.22 1.20 1.22 1.28 1.22 1.20 1.23 1.03
. 0.79. 1.26. 1.03. 1.24. 1.19. 1.18. 1.25. 1.20 . 1.18. 1.22. 1.06. 1.30 . 0.80 .
. -2.2. -2.3. -0.2. 1.3. -1.1. -3.2. -2.2. -1.8. -2.l . -0.5. 2.1. 0.7. -1.0.
1.29
. 0.35. 1.16 1.18 0.93. 1.22 0.96 1.28 0.96 1.23 0.93 1.18 1.16 0.80 0.35 10
, 0.35. 1.16. 1.18. 0.93. 1.22. 0.95. 1.27. 0.95. 1.21. 0.92. 1.20. 1.18. 0.35. 11 I 0.4. 0.4. 0.3. 0.2. -0.5. -1.0. -1.l. -1.2. -1.4. -1.5. 1.1. l.8. 0.5.
0.34 0.60 1;13 1.02 1.29 1.32 1.30 1.03 1.19
. 0.35. 0.61 . 1.18. 1.03. 1.31. 1.32. 1.27. 1.00. 1.17. 0.62. 0.35.
3.2. 2.0. 0.1 . 1.0. 1.1. -0.3. -2.2. -3.0. -1.5. 1.5. 3.0 .
0.61 0.34 12 I 0.36 1.17 1.29 1.34 1.31
. 0.36 . 1.19 . 1.31 . 1.35 . 1.29 .
2.3 . 1.5 . 1.6 . 0.2 . -1.4, 1.35 1.29 1.17 0.36 1.29 . 1.23 . 1.15. 0.37.
-3.9 . -5.0 . -2.4 . 2.2 .
13 0.34 0.80 1.23 1.05 1.23 0.81 0.35 I STANDARD DEVIATION
. 0.35. 0.82. 1.25. 1.03.
1.5. 2.1. 1.3. -2.0.
0.30 0.34 1.17. 0.76. 0.33.
-5.1. -5.3. -5.0.
0.30
. 0.31. 0.34. 0.29.
AVERAGE
.PCT DIFFERENCE.
14 15
~1. 736 2.8. -0.5. -5.5. ~ 2.1
.I SUHHARY.
HAP NO: Sl-11-01 DATE: 12/20/90 POWER: 27%
I CONTROL ROD POSITIONS: F-QCT) = 2.214 QPTR:
D BANK AT 176 STEPS F-DHCH> = 1.502 NW 1.013 NE 1.004 I FCZ)
BURNUP =
= 1.362 2.0 HWD/HTU SW 0.998 A.O. = 5.5161.
SE 0.985 I
NE-819 S1Cll Startup Test Report Page 36 of 59
I Figure 6.2 I SURRY UNIT' 1 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 61% POWER I
R p N PREDICTED H K J 0.32 H
0.36 G
0.32 F E D C PREDICTED B A I
HEASURED* . 0.33. 0.38. 0.33: HEASURED 1
.PCT DIFFERENCE.
0.35 0.80 3.5. 3.4. 3.6.
1.21 1.07 1.21 0.79
- 0.36. 0.83. 1.24. 1.09. 1.24. 0.83. 0.36.
1.4. 3.4. 2.1. 1.6. 2.3. 3.8. 2.7.
0.35
.PCT DIFFERENCE.
2 I
0.37 1.16 1.26 1.31 1.27 1.30 1.25 1.15
- 0.38. 1.17. 1.28. 1.34. 1.26. 1.31. 1.29. 1.17. 0.37.
1.2. 0.6. 2.0 . 2.7. -0.5. 0.8. 3.8. 2.1. 0.9.
0.37 3 I 0.36 0.62 1.18 1.03 1.27 1.28 1.27 1.02 1.11* 0.61 0.36 0.36
. 0.37. 0.63. 1.19. 1.04. 1.30 . 1.29. 1.25. 1.03. 1.18. 0.61. 0.36.
1.4. 0.7. 0.1 . 1.4. 1.8. 1.0. -1.2. 0.6. 0.6. 0.5. 0.3.
1.15 1.18 0.95 1.23 0.97 1.26 0.97 1.22 0.94 1.17
. 0.36. 1.17. 1.18. 0.95. 1.25. 1.00. 1.30. 0.99. 1.24. 0.94. 1.17. 1.15. 0.36.
1.15 0.36 4
5, I
. -0.0. 1.0. 0.2. 0.7. 0.9. 2.3. 2.8. 2.5. 1;1. 0.7. 0.2. -0.0. -0.l .
0.80 1.26 1.03 1.23 1.25 1.23 1.27 1.23 1.25 1.22 1.03
. 0.80. 1.26. 1.03. 1.23. 1.26. 1.26. 1.30. 1.25. 1.25. 1.23. 1.03. 1.26. 0,80 .
0.0. -0.0. 0.1. -0.2. 0.5. 1.7. 2.7. 1.3. 0.6. 0.8. 0.4. -0.5. -1.2 .
1.27 0.81 6 I 0.32 1.22 1.31 1.28 0.97 1.24 1.00 1.23 1.00 1.24 0.97 1.28 1.32 1.23 0.32
. 0.33. 1.23. 1.32. 1.28. 0.97. 1.23. 1.00. 1.24. 0.99. 1.24. 0.98 ~ 1.29. 1.31, 1.20. 0.31.
1.4. 0.9. 0.3. -o.o. -0.9. -0.8. -0.2. 0.6. -0.3. 0.4. 0.9. 0.4. -0.8. -2.2. -2.3.
0.37 1.08 1.28 1.29. 1.27 1.28 1.24 0.99 1.24 1.28 1.27 l.2f
. 0.38. 1.09. 1.29. 1.29. 1~26. 1.28. 1.24. 0.98. 1.24. 1.29. 1.27, 1.29. 1.27. 1.06. 0.36.
1.28 1.08 0.37 7
8 I
1.3. 1.1. 1.3. 0.5. -0.8. -0.2. -0.5. -0.8. -0.3. 0.5. 0.5. o.o. -0.6. -1.8. -2.7.
0.34 1.23 1.31 1.27 0.97 1.24 1.00 1.24 1.00 1.24 0.98 1.28 1.31
. 0.34. 1.24. 1.32. 1.28*. 0.99. 1.25. 0.99. 1.22. 0.99. 1.24 ~ 0.98. 1.29. 1.31 . 1.21. 0.30.
1.4. 1.0. 0.7. 0.7. 1.4. 0.6. -0.6. -0.9. -0.7. -0.2. 0.4. 0.2. -0.l. -1.3. -2.5.
1.22 0.31 9
I 0.80 1.25 1.03 1.23 1.25 1.24 1.27 1.24 1.25 1.24 1.03
. 0.80. 1.25. 1.03. 1.24. 1.26. 1.21. 1.25. 1.23. 1.25. 1.23. 1.04. 1.26. 0.79 .
. -0.l. -0.l. 0.4. 0.7. 0.6. -2.1. -1.7. -0.6. -0.5: -0.3. 0.4. 0.1 . -0.7.
0.36 1.15 1.17 0.94 1.23 0.97 1.26 0.97 1.24 0.95 1.18 1.26 1.15 0.80 0.36 10 I
. 0.36. 1.14. 1.17. 0.94. 1.23. 0.97. 1.24. 0.97. 1.24. 0.93. 1.18. 1.16. 0.36 . 11
. -0.5. -0.5. -0.4. -0.4. 0.1: -0.7. -1.9. -0.5. 0.7. -1.3. 0.1 . 0.7. -0.5.
0.36 0.6Z. 1.18 1.02 1.27 1.29 1.27 1.03 1.18
. 0.36. 0.61. 1.17. 1.03. 1.28. 1.28. 1.27. 1.02. 1.18. 0.64. 0.37
- 0.63 0.36 12 I
. -0.8. -0.7. -0.4. 0.3. 0.5. -0.3. -0.5. -0.6. -O.l . 1.6. 2.0.
0.37 1.16 1.26 1.31 1.27 1.31 1.26 1.16
. 0.37. 1.16. 1.26. 1.32. 1.27. 1.29. 1.24. 1.16. 0.38 .
. -0.2. 0.4. 0.6. 0.6. 0.0. -1.6. -1.6. -0.0. 2.0.
0.37 13 I 0.35 0.80 1.22 1.08 1.22 0.80 0.36 STANDARD DEVIATION .
. 0.35. 0.81. 1.24. 1.07. 1.18. 0.78. 0.36.
0.4. 1.1. 1.4. -0.9. -3.3. -2.6. -1.4.
0.32 0.37 0.32
, 0.33. 0.36. 0.31.
AVERAGE
.PCT DIFFERENCE.
14 15 I
=0.921 2.0. -0.3. -3.9. = 1.0 SUHHARY I
HAP NO: Sl-11-02 DATE: 12/21/90 POWER: 61%
CONTROL ROD POSITIONS: F-Q(TJ = 1.873 QPTR: I D BANK AT 202 STEPS F-DH<HJ = 1.427 NW 1. 006 NE 1. 001 FCZJ BURNUP
= 1.216
15 HWD/HTU SW A.O.
0.999 4.795%
SE 0.994 I I
NE-819 SlCll Startup Test Report Page 37 of 59 I
I I Figure 6.3 I SURRY.UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 8.8% POWER I R p N PREDICTED
- M L K J 0.32 H
0.37 G
0.32 F E D C PREDICTED B A I
MEASURED
- 0.34. 0.39. 0.33. MEASURED l
0.35 0.79 1.20 1.08 1.20 0.79 0.35
. 0.36 . 0.82. 1.24. 1.11 . 1.23. 0.81
- 0.36. 2 0.9. 3.0. 2.7. 2.6. 2.3. 2.0. 0.9.
I 0.38 1.15 1.24 1.29 1.26 1.29 1.23 1.14
. 0.38. 1.13. 1.25. 1.33. 1.27. 1.31. 1.26. 1.14. 0.37.
0.5 . -1.0 . 0.7 . 2.7 . 1.0 . 1.2
- 2.0
- 0.3 . -0.8
- 0.37 3
0.36 0.63 1.18 1.03 1.27 1.27 1.26 1.02 1.17 0.61 0.36 I 0.36
. 0.37 . 0.63 . 1.16 . 1.03 . 1.29 . 1.29 . 1.27
- 1.03 . 1.17 . 0.61
- 0.36 .
0.9. -0.2. -1.8. 0.5. 1.7. 1.5. *0.7. 1.2. 0.3. -0.0. -0.l.
1.14 1.17 0.95 1.24 0.98 1.26 0.98 1.23 0;95
. 0.36. 1.16. 1.17. 0.96. 1.25. 1.00. 1.28. 1.00. 1.24. 0.95. 1.17. 1.14. 0.37.
1.16 1.14 0.36 4
5 I
. -0.3. 2.3. 0.0. 1.3. 0.4. 1.3. 1.9. 1.5. 0.7. 0.9. 0.2. 0.3. 0.5.
0.79 1.24 1.03 1.24 1.28 1.25 1.28 1.25 1.28 1.23 1.03 1.25 0.80
. 0.79 . 1.23 . 1.03
- 1.24 . 1.29
- 1.27 . 1.31 . 1.26 . 1.28 . 1.23 . 1.02 . 1.24 . 0.79 . 6
. -0.3. -0.3. 0.3. -0.3. 0.6. 1.4. 2.2. 1.2. 0.1. 0.2. -0.2. -0.8. -1.0.
I 0.33 1.21 1.30 1.27 0.98 1.25 1.01 1.24 1.01 1.25 0.98 1.0. o.4. -0.1. -o.7. -1.8. -0.8. o.6. 1.2. o.7. o.4. -o.5. -1.4. -1.5. -2.3. -2'.5.
0.38 1;09 1.26 1.28 1.26 1.29 1.25 1.00 1.25 1.29 1.27 1.28
. 0.33. 1.22. 1.29. 1.26. 0.97. 1.24. 1.02. 1.26. 1.02. 1.26. 0,98. 1.26. 1.28. 1.19. 0.32.
1.28 1.30 1.26 1.22 0.33 1.09. 0.37 7
.I
. 0.38 . 1.10 . 1.27 . 1.27 . 1.24 . 1.28 . 1.26 . 1.00 . 1.25 . 1.29 . 1.26 . 1.27 . 1.25 . 1.07 -. 0.37
- 8 I 0.9. 0.6. 0.6. -0.3. -2.2. -0.6. 0.4. 0.4. 0.1 . 0.1. -0.6. -1.l. -1.0. -1.6. -1.8 .
0.34 1.21. 1.29 1.27 0.98 1.25 1.01 1.24 1.01 1.25 0.99 1.28 i.30 1.21
. o.35 . 1.22 -. 1.29 . 1.27 . o.99 . 1.25 . 1.00 . 1.24 . 1.oi' . 1.24 . o.99 . 1.28 . 1.30 . 1-.20 . o.31 .
1.0 . 0.1. -0.3. -0.2. I.I. -0.3. -0.9. -0.2. 0.1. -0.8. -0.l. 0.4. 0.1. -0.5. -1.1.
0.32 9
I 0.80 1.23 1.03 1.24 1.28 1.25 1.28 1.25 1.28 1.24
. 0.78. 1.22. 1.03. 1.25. 1.29. 1.24. 1.27. 1.25. 1.28. 1.25. 1.04. 1.25. 0.79.
. -1.4. -1.4. 0.1. 1.2. 0.3. -0.9. -0.5. -0.3. -O.l
- 0.4. 1.0. 0.7. 0.1 .
1.03 1.24 0.79 ~
10 0.36 1.13 1.17 0.95 1.24 0.98 1.26 0.98 1.24 0.95 1.17 1.13 0.36 I . 0.36. 1.13. 1.17. 0.96. 1.24. 0.98. 1.25. 0.98. 1.24. 0.96. 1.19. 1.15. 0.36.
0.1. 0.0. 0.3. 0.7. o.o . -0.6. -0.6. -0.4. 0.1. 1.0. 1.3. 1.0. 0.3.
0.36 0.62 1.17 1.02 1.27 1.28 1.27 1.03 1.18
- 0.37. 0.63. 1.18. 1.03. 1.26. 1.27. 1.26. 1.02. 1.18. 0.64. 0.37.
0.63 0.36 11 12 1.5. 1.2. 0.7. 0.2. -0.3. -0.5. -1.l. -0.9. 0.2. 1.6. 1.7.
I 0.37 1.14 1.24 1.29 1.26 1.29 1.24
. 0.38. 1.15. 1.24. 1.29: 1.25. 1.27. 1.20. 1.13. 0.38.
- '1.3. 1.1 . 0.4. -0.4. -0.8. -2.0. -3.0. -1.2. 1.7.
1.15 0.38 13 I
0.35 0.79 1.21 1.09 1.21 0.80 0.36
. 0.36. 0.80. 1.21. 1.08. 1.18. 0.77. 0.35. 14 1.1 . 0.9 . 0.1 . -1.0 . -2.2. -2.7. -3.l
- STANDARD 0.32 0.37 0.32 AVERAGE DEVIATION
- 0.33. 0.37 . 0.32 . .PCT DIFFERENCE. 15 I =0.839 0.6. -0.5. -2.3.
SUHHARY
= 1.0 I HAP NO: Sl-11-05 CONTROL ROD POSITIONS:
DATE: 12/23/90 F-QCTJ = 1.799 POWER: 88%
QPTR:
D BANK AT 223 STEPS F-DHCH) = 1.412 NW 1.005 NE 1.001 I FCZ)
BURNUP
= 1.H,6
= 53 MWD/HTU SW O.998 A.O.= 0.634%
SE 0.996 I
I NE-819 S1Cll Startup Test Report Page 38 of 59
I Figure 6.4 I
SURRY UNIT 1 - CYCLE 11 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 1007. POWER I
R p N M .l K J H G F E D C s* It 1*
PREDICTED 0.33 0.38 0.33 PREDICTED
- MEASURED . 0.34. 0.39. 0.34. MEASURED 1
.PCT DIFFERENCE.
0.36 0.79
- 4.0. 4.0. 3.3.
1.20 1.06, 1.20 0.79
. 0.36. 0.80. 1.21 . 1.10. 1.22. 0.61. 0.36.
1.2. 1.3. 1.4. 1.4. 1.7. 2.2. 1.4.
0.35
.PCT DIFFERENCE.
2 I
0.36 1,14 1.23 1.29 1.25 1.26 1.23
- 0.36. *1.13. 1.23. 1.30. 1.24. 1.29. 1.25. 1.14. 0.36.
0.8. -0.7. -0.2. 1.0. -0.6. 0.2. 2.2. 1.0. 0.2.
1.13 0.36 3 I 0.37 0.63 1.18 1.03 1.27 1.27 1.26 1.03 1.17 0.62 0.36 0.36
. 0.37. 0.63. 1.16. 1.03. 1.26. 1.26. 1.25. 1.03. 1.17. 0.62. 0.37.
0.1. -0.2. 71.6. 0.1. o.7. *o.3. -1.1 . o.9. o.4. o.3. o.5.
1.13 1.17 0.96 1.24 0.99 1.26 0.96 1.24 0.95
- 0.36. 1.13. 1.17. 0.96. 1.25. 1.00. 1.29. 1.00 . 1.24. 0.96. 1.17. 1.14. 0.37.
1.16 1.13 0.37 4
5 I
. -0.5. -0.5. -0.3. 0.8. 0.3. 1.5. 2.0. 1.4. 0.5. 0.7. 0.1. 0.7. 1.5.
I 0.79 1.23 1.03 1.24 1.29 1.26 1.28 1.25 1.28 1.23 1.03 1.24 0.60
. 0.79 . 1.22 . 1.03 . 1.24 . 1.30 . 1.27 . 1.31 . 1.27 . 1.29 . 1.23 . 1.03 . 1.24 . 0.60 . 6
. -0.6. -0.6. -0.1. -O.l . 0.6. 1.5. 2.2. 1.1 . 0.1 . 0.1. -0.1. -0.4. -0.4; 0.33 1.21 1.29 1.27 0:99 1.26 1.02 1.25. 1.02. 1.26. 0.99. 1.26. 1.30. 1.21. 0.33
. 0.33. 1.21. 1.26. 1.26. 0.97. 1.25. 1.02. 1.26. 1.02. 1.26. 0.98. 1.26. 1.28. 1.16. 0.32. 7 1.8. 0.2. -0.6. -o:6. -1.4. -0.7. 0.5. 1.2. 0.6. 0.1. -0.4. -0.9. -1.6. -2.2. -2.2.
0.38 1.09 1.25 l.~8 1.26 1.29 1.25 1.01. 1.25. 1.29 1.27. 1.26 1.26. 1.09. 0.38
- O* 39 . 1. l O
- 1. 26 . 1. 27 . 1. 24 . 1. 28 . l. 26 . 1. 0 l
- 1. 25 . 1. 29 . l. 26 . l. 26 . 1. 24 . l. l O
- 0. 40 . 8 1.8. 0.6.
- 0.3. -0.4. -1.8. -0.4 ** 0.3. 0.3. -0.0 .
1.21 1.29 1.27 0.99 1.26 1.02
. 0.35. 1.21. 1.26. 1.27. 1.00. 1.26. 1.01. 1.24. 1.02.
1.8. 0.3. -0.4. 0.0. 1.4. -0.l * -1.l. -0.3. 0.0.
1.25 1.02
-0.2. -0.5. -1.3. -1.7. 0.9. 5.1:
0.35 1.26 0.99 1.27 1.29
-0.6. -O.l. -0.l. -0.4. 3.3. 6.6.
1.20 .. 0.32 1.25. 0.99. 1.27. 1.29. 1.24. 0.35. 9 I
. 0.79. 1.23. 1.03. 1.24. 1.29. 1.26. 1.28. 1.26. 1.29. 1.25. 1.03. 1.23. 0.79 .
. 0.78. 1.21. 1.03. t.25. 1.29. 1.24. 1.26. 1.25. 1.29. 1.25. 1.04. 1.24. 0.60.
. -1.3. -1.3. 0.1. 1.2. 0.2. -1.0. -0.5. -0.l. 0.0. 0.3. 0.9. 0.6. 1.1.
0.36 1.13 1.17 0.95 1.24 0.99 1.26 0.99 1.24 0.96 1.17 1.13 0.36 10 I
. 0.36 ~ 1.13. 1.17. 0.96. 1.24 . 0.96. 1.26. 0.99. 1.25. 0.96. 1.19. 1.14. 0.36.
I 11 0.0. 0.0. 0.1. 0.3. -0.3. -0.6. -0.4. 0.0 . 0.4. 0.6. 1.3. 1.3. 0.6.
0.36 0.62 1.17 1.02 1.27 1.27 1.27 1.03 1.17 0.63 0.36
. 0.37. 0.63. 1.17. 1.02. 1.26. 1.27. 1.26. 1.02. 1.18. 0.65. 0.37. 12 1.3. 0.9. 0.3. -0.l . -0.4. -0.6. -0.8. -0.6. 0.6. 2.3. 1.5.
0.36 1.14 1.23 1.29 1.25 1.29 1.23
. 0.36. 1.15. 1.24. 1.28. 1.24. 1.26. 1.20. 1.14. 0.39.
1.5. 1.6. 0.7 .* -0.7. -1.2. -2;2. -2.4. -0.3. *2.1 .
1.14 0.38 13 I 0.35 0.79 1.20 1.09 1.20 0.79 0.36 STANDARD DEVIATION .
- 0.36. 0.80 . 1.21. 1.07. 1.16. 0.77. 0.35.
1.6. 1.5. 0.4. -1.3. -3.l. -2.8. -2.3.
0.33 0.36
. 0.33. 0.37. 0.32.
0.33 AVERAGE
.PCT DIFFERENCE .
14 15 I
I.
=l.087 1,4. -0.5. -3.4. = 1.0
SUMMARY
HAP NO: Sl-11-06 CONTROL ROD POSITIONS:
DATE: 12/26/90 F-QCT> = 1. 770 POWER: 1007.
QPTR: 1*
D BANK AT 224 STEPS F-DHCH) = 1.403 NW 1. 001 NE 1. 001 FCZ)
BURNUP
= 1.169
= 165 HWD/MTU SW 0.999 A.O. = -1.0877.
SE 0.999 I I
NE-819 SlCll Startup Test Report Page 39 of 59 I
I I SECTION 7 I REFERENCES I 1. A. H. Nicholson and T. S. Psuik, "Surry Unit 1, Cycle 11 Design Report," Technical Report NE-814, Revision O, Virginia Power, December, 1990.
I 2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
I 3. W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 1967.
I 4. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, and *4.10.
I I
I I
I I
I I
I I
I 40 of 59 I NE-819 SlCll Startup Test Report Page
I I
I I APPENDIX I .STARTUP PHYSICS TESTS RESULTS AND EVALUATION SHEETS I
I I
I I
I I
I I
I I
I I
I NE-819 S1Cll Startup Test Report Page 41 of 59
I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
I Reference Test
Description:
Reactivity Computer Checkout Pree ~o /Section: 1-PT-28.11 Sequence Step No: b I
i II Test I
iI Bank Positions (Steps) RCS Temperature (°F): 547 Power Level (% F. p.): 0 I
Conditions1 SDA: 225 SOB: 225 CA: 225 Other (specify):
I I
(Design) I CB: 225 CC: 225 CD:
- Below Nuclear Heating I
III Test Bank Pas it ions (Steps) RCS Temperature (°F): 5<./":J.
Power Level (% F.P.): 0 I
Conditions SDA: 225 SOB: 225 . CA: 225 Other (Specify):
(Actual) CB: 225 CC: 225 CD: /72, Below Nuclear Heating i
I Date/Time Test Performed: I i ,211r1~ ') - 022..,
IV Measured Parameter (Description)
Pc = Meas. Reactivty using p-computer Pt = Predicted Reactivity I
- -~y. .:, ., .,
Measured Value Pc =
- '(7. 0
-f
-f r,,/.
'(5"* y (l
,, I Pt =
Test Results
%D = f },f
,, -I/*~ I Design Value (Actual Conditions)
Design Value i..D = {(pc-Pt)/pt} X
- 100% $ 4, 0%
I (Design Conditions)
Reference i..D = {(pC-pt)fpt}
WCAP 7905, Rev. 1' Table 3.6 X 100% .S: 4.0%
I V
Acceptance Criteria FSAR/Tech Spec Not Applicable I
Reference Design Tolerance is met Not Applicable
- -VYES _NO I
Acceptance Criteria is met : _LYES VI
- NO Comments
- At The Just Critical Position I.
Allowable Range=+/- - cf'(* ,l -f 'It:::, /
I Prepared By: Reviewed By:
I I
NE-819 S1Cll Startup Test Report Page 42 of 59
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATIO~ SHEET I I Reference Test
Description:
Critical Boron Concentration - ARO Pree No /Section: l-PT-28.11 Sequence Step No:
I II Test Bank Positions (Steps)
+
Conditions, SDA: 225 SDB: 225 CA: 225 RCS Temperature (°F): 547 Power Level c: F.P.): 0 Other (specify):
I (Design) !
III i CB: 225 CC: 225 CD: 225 Bank Positions. (Steps)*
Below Nuclear Heating RCS Temperature ( °F): 5'44. \
./
I ----------------------------1 Test Power Level(% F.P.): 0 I Conditions (Actual) j
~I SDA: 225 CB: 225 SDB: 225 CA: 225 CC: 225 CD: 225 Other (Specify):
Below Nuclear Heating I Date/Time Test Performed:
i/,-s /CiO 05: 54 J 1- IV Meas Parameter-(Description)
I I
M (CB) ARO; Cri~ical Boron Cone - ARO
/
I 1 Test Results
- Measured Value Design Value
/
1- (Actual Cond)
Design Value
_ (Design Cond) CB= 1523 +/- 50 ppm 1 Reference Technical Report NE-814, Rev. 0 I V I FSAR/Tech Spec aCB x C~ 1000 pcm ~
Acceptancei-----------------------------------------------------------------------------------
Criteria j Reference Technical Specification 4.10.A I Design Tolerance is met Acceptance Criteria is met
.JYES _NO JYES _NO I VI Comments I aCB = -7. 86 pcm/ppm .1 I D CB= ICCa) ARO M
CBI; CB is design value at actual conditions.
I Prepared By: ~ - - . , { - ~-<<-t.>Reviewed By: ~*~
I I
I NE-819 S1Cll Startup Test Report Page 43 of 59
I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
I Re f erence Test
Description:
Isothermal Temperature Coefficient - ARO*
Proe Io N ,'S ection: 1- PT-28.11 Sequence Step No:
I II Test Bank Positions (Steps) RCS Temperature (°F): 547 Power Level (% F.P.): 0 I
Conditions I SDA: 225 SDB: 225. CA: 225 Other (specify):
(Design)
III I CB: 225 CC: 225 CD: 225 Bank Positions (Steps)
Below Nuclear Heating RCS Temperature (°F): 5"'/~
I Test Power Level (% F.P.): 0 Conditions (Actual)
SDA: 225 CB: 225 SDB: 225
- CA: 225 CC: 225 CD: ;;_/b Other (Specify):
Below Nuclear Heating I
Date/Time Test Performed:
12../;.rho 07.S-9 I
- 11eas Parameter IV (Description)
ISO (a T )ARO Isothermal Temp Coeff - ARO I ISO Test Results Measured Value Design Value (a T )ARO = - .,r: 3 2-.pcm/°F (CB =/¥9d'ppm)
I ISO
= l'f~ ppm)
(Actual Cond) (a T )ARO ISO
= - 5. 3'1 pcm/°F (CB I
(a T )ARO = -5.15 +/- 3.0 pcm/°F Design Value (Design Cond) (CB = 1523 ppm) I V
Reference Technical Report NE-814, Rev.
ISO Dop 0
I Acceptance FSAR/Tech Spec a T ~ 0.78 *pcm/ 0 F a T = -1.72 pcm/°F Criteria
- Reference TS 3.1.E, Technical Report NE-814, Rev. 0 I VI Design Tolerance is met Acceptance Criteria is met
- ~-NO
/.
S _NO
- 1 Comments
- Uncertainty on aTMOD = 0.5 pcm/°F (
Reference:
memorandum from C. T. Snow to E. J. Lozito dated June 27, 1980).
I Prepared Reviewed By, ~ID.~
I I
I NE-819 S1Cll Startup Test Report Page 44 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference Test
Description:
Cntl Bank D Worth ~eas.,Rod Swap Ref. Bank Pree No /Section: 1-PT-28.11 Sequence Step No:
I II Test Conditions Bank Positions (Steps) RCS Temperature (OF): 547 Power Level(% F.P.): 0 SDA: 225 SDB: 225 CA: 225 Other (specify):
I (Design)
III CB: 225 CC: 225 Bank Positions (Steps)
CD:Moving Below Nuclear Heating RCS Temperature (°F): 5~.<..
Test Power Level .(% F. P.): 0 I Conditions (Actual)
SDA: 225 CB: 225 SDB: 225 CC: 225 CA: 225 CD:Moving Other (Specify):
Below Nuclear Heating I Date/Time Test Performed:
1'2..fa.a I ~o O 9"+/
I Measured P~rameter (Description)
REF I D ; Integral Worth of Cntl Bank D, All Other Rods Out IV.
I Test Results Measured Value REF I D = IL 83.1 PCJ'Y'l I Design Value (Actual Conditions)
REF I D = I \ 9 "+ :t- I \ q pc.n--,
Design Value REF I (Design Conditions)
Reference I D = 1194 +/- 119 pcm Technical Report NE-814, Rev. o:
I If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result V FSAR/Tech Spec on safety analysis. SNSOC may specify I Acceptance Criteria Reference that additional testing be performed *.
VEP-FRD-36A I VI Design Tolerance is met Acceptance Criteria is met
- _LYES
- ..L.YES
-_so NO Comments I
I Prepared By:. ?.µ~j Reviewed B y ~ ~
I I
I NE-819 S1Cll Startup Test Report Page 45 of 59
SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
I Reference Test
Description:
Critical Boron Concentration - D Bank In Pree No /Section: l-PT-28 .11 Sequence Step No:
I
. II Test Bank Positions (Steps) RCS Temperature (°F): 547 Power Level (% F.P.): 0 I
Conditions SDA: 225 SOB: 225 CA: 225 Other (specify):
(Design)
III CB: 225 CC: 225 Bank Positions (Steps)
CD: 0 Below Nuclear Heating Res* Temperature (°F): ~~5.4 I
Test Conditions (Actual)
SDA: 225 CB: 225 SDB: 225 CC: 225 CA: 225 CD: 0 Power Level(% F.P.): 0 Other (Specify):
Below Nuclear He~ting I
Date/Time Test Performed:
I~ /18 /9_0 0~4\ - -
I IV Meas Parameter (Description)
M (CB)D; Critical Boron Cone - D Bank In I Test Results Measured Value Design Value M
(CB)D = 135~ ppn1 I 1348 ~ ;1,5 Pfr'Y'l (Ac;:tual Cond)
Design Value CB =
Prev
- I (Design Cond) CB= 1372 + ~CB +/- (10 + 119.4/laCBI )ppm Reference Technical Report SE-814, Rev. 0 I V
Acceptance Criteria I
FSAR/Tech_Spec Reference
~ct Applicable Not Applicable I
Design Tolerance is met Acceptance Criteria is met
- ~YES_ NO
- .L_YES _NO I
VI Comments aCB = -7.94 pcm/ppm Prev I
M
= (CB)ARO - 1523 = 1"1G9 - 15Z3: -.=2.4 ppl'Y'l
~CB I
Prepared By, Q..\._ I P ~ .Reviewed By~u I I
I NE-819 S1Cll Startup Test Report Page 46 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I :teference Test
Description:
HZP Boron Worth Coefficent Measurement Pree No /Section: l-PT-28.11 Sequence Stec So:
I :r Test Conditions Bank Positions (Steps)
SDA: 225 SDB: 225 CA: 225 RCS Temperature (°F)i 547 Power Level (% F. P.): 0 Other (specify):
I (Design)
III CB: 225 CC: 225 Bank Positions (Steps)
CD:Moving - Below Nuclear Heating RCS Temperature (°F): S'~'5.4 Test Power Level(% F.P.): 0 I Conditions (Actual)
I SDA: 225 CB: 225 SDB: 225 CC: 225 CA: 225 CD:Moving Other (Specify):
Below Nuclear Heating I Date/Time Test Performed:
,-:z./18 / 9o oq~I Measured Parameter I IV (Descr~ption) aCB, Boron Worth Coefficient I Test Measured Value.* aCB = - 8.\Gi p c.xn/p-prn Results -
Design Value I (Actual Conditions) aCB = -7.90 +/- 0.79 pcm/ppm -
Design Value I (Design Conditions)
Reference aCB = -7.90 +/- 0.79 pcm/ppm Technical Report NE-814, Rev. a I
I V
Acceptance Criteria FSAR/Tech Spec Reference Not Applicable Not Applicable I VI Design Tolerance is met Acceptance Criteria is met
..L.YES _NO
...::!.....YES _NO Comments I
I Prepared By: 90:W:1~9:a '1). :f.>~ Reviewed By:
I I
I I
NE-819 S1Cll Startup Test Report Page 47 of 59 I
I SURRY POWER STATION UNIT 1 CYCLE 11 I
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
Reference Test
Description:
Cntl Bank C Worth Measurement-Rod Swap Pree No /Section: 1-PT-28 .11 Sequence Step No:
I II Test Bank Positions (Steps) RCS Temperature (°F): 547 Power Level (% F .P.): 0 I
Conditions SDA: 225 SOB: 225 CA: 225 Other (specify):
(Design). CB: 225 CC:Moving.CD:Moving Below Nuclear'Heating I
III Bank Positions (Steps) RCS Temperature (°F): ~%
Test Conditions (Actual)
SDA: 225 CB: 225 SOB: 2i5 CA: 225 CC:Moving CD:Moving Power Level (1. F.P.): 0 Other (Specify):
Below Nuclear Heating I
Date/Time Test Performed:
,;) /1B/'lo 14-31
- I I
Meas Parameter (Description) I I
RS Ic i Int Worth of Cntl. Bank C-Rod Swap I IV I IcRS = .(Adj. Meas. Crit. Ref Bank Test Results Measured Value I '710 Position =/"3(.p steps) I Design Value RS (Adj. Meas. Crit. Ref Bank (Actual Cond) Ic = 7;i~. .:2. Position = 13G, steps)
I RS
= 725 +/- 109 pcm (Critical Ref Bank r
Design Value (Design Cond)
Ic Position = 145 steps) I Reference Technical Report NE-814, Rev. 0, VEP-FRD-36 A 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 : ...L.,YES _NO I
VI Comments Acceptance Criteria i~ met : ...L_YES _NO I
I Prepared Reviewed I
I NE-819 S1Cll Startup Test Report Page 48 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference Test
Description:
Cntl Bank B Worth Measurement-Rod Swap Pree No /Section: l-PT-28 .11 Sequence Step No:
I II Test Bank Positions (Steps) RCS Temperature (OF): 547 Power Level (I F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
I (Design)
III CB:Moving CC: 225 CD:Moving Bank Pas i tioris (Steps)
Below Nuclear.Heating RCS Temperature (°F): t;;'ll 1./, fo I Test Conditions (Actual)
SDA: 225 SOB: 225 CB:Moving CC: 225 CA: 225 CD:Moving Power Level (t F.P.): 0 Other (Specify):
Below Nuclear Heating I Date/Time Test Performed:
1~l1'6£qo ;s-; ~
I Meas Parameter (Description)
RS Is ; Int \forth of Cntl Bank B-Rod Swap IV (Adj. Meas. Crit. Ref Bank I Test Results Measured Value RS Is =foS,,I Position = '2.,.oo steps)
Design Value RS
_ (Adj. Meas. Grit. Ref Bank I (Actual Cond) Is RS
= /6 75,'2.
~ I"/
Position= Zoo steps)
Design Value Is= 1079 +/- 162 pcm (Critical Ref Bank I (Design Cond) Position= 199 steps)
Reference Technical Report NE-814, Rev. 0. VEP-FRD-36 A I If Design Tolerance is exceeded, SNSOC I V Acceptance FSAR/Tech Spec shall evaluate impact of test result on safety analysis. SNSOC may specify that additional testing be performed..
Criteria I Reference VEP~FRD-36A Design Tolerance is met : ./YES -*_so
_0Es _so I VI Comments Acceptance Criteria is met :
I Prepared B y ? ~ ~ - ~ Reviewed By:
I I
I NE-819 SlCll Startup Test Report Page* 49 of 59
I SURRY POWER STATION UNIT 1 CYCLE 11 I
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Cntl Bank A Worth Measurement-Rod Swap I
Reference Pree No /Section: 1-PT-28.11 Sequence Step No:
II Test Bank Positions (Steps) RCS Temperature (°F): 547 Power Level(: F.P.): 0 I
Conditions SDA: 225 SDB: 225 CA:Moving Other (specify):
(Oesign) CB: 225 CC: 225 CD:Moving Below Nuclear Heating I III Bank Positions (Steps) RCS Temperature (°F): i;" <<, ' 2..
Test Conditions (Actual)
SDA: 225 CB: 225 SDB: 225 CC: 225 CA:Moving CD:Moving Power Level(% F.P.): 0 Other (Specify):
Below Nuclear Heating I
Date/Time Test Performed:
,i.-10-<:;o /G: 3.;l.
I I
Meas Parameter i RS (Description) I IA ; Int Worth of Cntl Bank A - Rod Swap I
I IV Test Results Measured Value RS IA = 518.5 (Adj. Meas. Crit. Ref Bank Position =10 7 steps) I Design Value _ (Adj .. Meas. Crit. Ref Bank (Actual Cond)
RS IA 4 , '1'"
= ~()/l>D
~ ,.,,,,._
. Position = lo 7steps)
I RS Design Value (Design Cond) I I
IA = 503 +/- 100 pcm (Critical Ref Bank Position = 112 steps) I Reference Technical Report NE-814, Rev. 0 VEP-FRD-36 A I
I If Design Tolerance is exceeded, SNSOC V
Acceptance FSAR/Tech Spec shall evaluate impact of test result on safety analysis. SNSOC may specify that additional testing be performed.
I Criteria Reference VEP-FRD-36A I Design Tolerance is met : ..........YES _No*
VI Comments Acceptance Criteria is met : ......-YES -~O I
I Reviewed By:
I I
NE-819 S1Cll Startup Test Report Page 50 of. 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I ! Test
Description:
Shutdown Bank B Worth Meas. - Rod S~ap Reference 1. ?roe No /Section: l-PT-iB.11
- Sequence Ste~ No:
I I II Test Bank Positions (Steps)
Conditions I SDA: 225 SDB:Moving CA: 225 RCS Temperature (°F): 54 i Power Level (% F.P.): 0 Other (specify):
I (Design) iI CB: 225 III CC: 225 I Bank Positions (Steps)
CD:Moving .Below Nuclear Heating RCS Temperature (°F): S""Cf,-~.(o Test I Power Level(% F.P.): 0 I I 1
- Conditions SDA: 225 SDB:Hoving CA: 225 (Actual)
- CB: 225 CC: 225. CD:Moving Other (Specify):
Below Nuclear Heating I Date/Time Test Performed:
,~-18-~o /7.'/~
Meas Parameter I (Description)
RS IsBi Int Worth of Shutdown Bank B-Rod Swap
,-,o.~
IV RS (Adj. Meas. Cr.it. Ref Bank I Test Results Measured Value Design Value IsB =~!6- Position = l'f, steps)
(Adj. Meas. Grit. Ref Bank (Actual Cond)
RS _ 71i, 'r Position = I 'fl:, steps)
I IsB RS
- :t: (I 'o Design Value IsB = 789 +/- 118 pcm (Critical Ref Bank I (Design Cond)
Reference Position= 155 steps)
Technical Report NE-814, Rev. 0, VEP-FRD-36 A I If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on I V Acceptance Criteria FSAR/Tech Spec safety analysis. SNSOC may specify that additional testing be performed.
I Reference VEP-FRD-36A Design Tolerance is met : */YEs _NO VI Acceptance Criteria is met : ~YES _NO*
I Comments I . ?~d-~
Prepared Bt; ~ Reviewed By:
I I
Page 51 of 59 I NE-819 S1Cll Startup Test Report
I SURRY POWER STATION UNIT 1 CYCLE 11 I
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test
Description:
Shutdown Bank A Worth Meas. - Rod Swap I
Reference I Pree No /Section: l-PT-28.11 Sequence Step No:
I 1*
II RCS Temperature (°F): 547 Test. I Bank Positions (Steps) Power Level(% F.P.): o*
I Conditions I SDA:Moving SOB: 225 CA: 225 (Design) I I
I CB: 225 CC: 225 CD:Moving Other (specify):
Below Nuclear Heating I III Bank Positions (Steps) RCS Temperature (°F): ~ , . 3 Test Conditions SDA:Moving SOB: 225 CA: 225 (Actual) CB: 225 CC: 225 CD:Moving Power Leve 1 ( % F. P. ) : 0 Other (Specify):
Below *Nuclear Heating I
Date/Time Test Performed:
(d-l til 'lo /g:s1 I
Meas Parameter
- (Description)
RS IsA; Int Worth of Shutdown Bank A-Rod Swap I
IV Test Results Measured Value RS IsA = tl~T,'-f (Adj. ~eas. Crit. Ref Bank Position = ~steps) I Design Value. /6 3 (Adj. ~eas. Crit. Ref Bank (Actual Cond)
RS IsA = I +/- 17¢ Position =do}Ssteps) I RS Design Value (Design Cond)
IsA = 1169 +/- 175 pcm (Critical Ref Bank
- Position = 215 steps) I Reference. Technical Report NE-814, Rev. o, VEP-FRD-36 A I
If Design Tolerance is exceeded, SNSOC V
Acceptance FSAR/Tech Spec.
shall evaluate impact of test result on safety analysis. SNSOC may specify that 1.
additional testing be performed.
c,rit~ria Reference VEP-FRD-36A I Design Tolerance is met : 6ES
- NO VI Comments Acceptance Criteria is met : VYES
- NO I
I Prepared By: , ~ - a ~/~ Reviewed I
I NE-819 S1Cll Startup Test Report Page 52 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference Test
Description:
Total Rod Worth - Rod Swap Proc ~o /Section: l-PT-28.11 Sequence Step No:
I II Test Bank Positions (Steps) RCS Temperature (°F): 547 Power Level (% F.P.): 0 Conditions SDA:Moving SDB:Moving CA:Moving Other (specify):
I (Design)
III CB:Moving CC:Moving CD:Moving Bank Positions (Steps)
Below Nuclear Heating RCS Temperature (°F): .5'16 Test Power Level (% F.P.): 0 I Conditions SDA:Moving SDB:Moving CA:Moving (Actual) CB:Moving CC:Moving CD:Moving Other (Specify):
Below Nuclear Heating I Date/Time Test Performed:
!d-/18(90 /"6;.59 I
I Meas Parameter (Description) i 1rotal; Int Worth of All Banks - Rod Swap IV I I Test Results Measured Value Design Value I
I I
1Total = 5L/6L/
I
= 5'119 . .;2 I (Actual Cond)
Des_ 5n Value i
i 1rotal 2. S"'-1~
(Design Cond) I 1rotal = 5459 +/- 546 pcm I Reference i
' Technical Report NE-814, Rev. 0' VEP-FRD-36 A I If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on V FSAR/Tech Spec safety analysis. SNSOC may specify that I Acceptance Criteria additional testing *be performed*.
Reference I VEP-FRD-36A I Design Tolerance is met : Vy'ES
.* "YES - NO
~o VI Comments Acceptance Criteria is met I
I Prepared By:
-;;?_
Reviewed B y : ~ d'-
. ~ 4 I
I Page 53 of 59 I NE-819 SlCll Startup Test Report
I SURRY POWER STATION UNIT 1 CYCLE 11 I
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
M/D Flux Map - Low power I
Reference Pree No/ Section: 1-PT-:28.2, 1-0P-57 Sequence Step No:
II Test Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Power Level(% F~P.): <30 I
Conditions SDA: 225 SDB: 225 CA: 225 Other ( specify)
(Design) CB: 225 CC:
- CD:
- Must have~ 38 thimbles I III Bank Positions (Steps) RCS Te~perature( °F): ,v555e~
Test Conditions Power Level Cio F.P.J: Q,,,,c I SDA: 225 SDB: 225 CA: 225 Other (Specify):
(Actual) cc : 2aS
""" ~"'"" 'o \ C. ~
CB : 225 CD: \ , ,
I Date/Time Test Performed:
,~ .. ".lo ... qri/ 0~~9 I
I IV Meas Parameter CDescription)
MAX. REL ASSY PWR
% DIFF NUC ENTHAL TOTAL HEAT QUADRANT RISE HOT CHAN FACT CHAN FACT FLUX HOT POWf;R TILT RATIO I
(M-P)/P a.11~.~ "s,a F-dH(N) F-Q(T)
QPTR t.o~a u I
I Measured Value 'a,~\l\ \.Cl4!4 L Test 1,13"=> SO ft 1'111-... l,C\.30 Results
.t. 10% for i'i i_1):9 Design Value .t. HI" for Pi < o:s (Design Conds) (P 1
F..i.,,tS.1.M(t+.311-P})
T I V I FSAR/Tech Spec NONE F (Z) 0
_s,.su KIZ)
NONE Acceptance Criteria I Reference NONE TS 3.12.B 'TS 3.12.B NONE I
Design Tolerance is met Acceptance Criteria is met
- _:LYES _NO
- LYES _NO I
VI Comments
- As Required '
I I
Prepared By~.~;l:!..,M,.\ _ _. Reviewed By, ~ I I
NE-819 S1Cll Startup Test Report Page 54 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference Test
Description:
M/D Flux Map-At Power Pree ~a/ Section: l-PT-28.2,. l-OP-57 Sequence Step No:
II Bank Positions (Steps) RCS temperature (°F):TREF +/-1 Test Power Level(% F.P.): - 50 Conditions (Design)
I SDA: 225 . _SOB : 225 CB Z25 CC: 225 CA: 225 CD:
- Other (specify)
Must have~ 38 thimbles III Bank ~ositions_ (Steps) RCS Temperature(°F):
Test Power Level (t F.P.):
I Conditions (Actual)
SDA: 225 *soB: 225 CB : .225 cc : 225 CA: 225 CD:
Other (Specify) :
I I Date/Time Test Performed:
I MAX. REL NUC ENTHAL TOTAL HEATI QUADRANT I IV Meas Parameter (Description)
ASSY PWR
- i. DIFF RISE HOT
'CHAN Fl~CT FLUX HOT POWER TILT Cfr~ FACT RATIO (M-P)/{ rpuc o F Q(T) .QPTR I
I Test Results Measured Value
\ ~r--
~
.t, 1°" IOI 2, 0.11 1
Design Value
.t, 115"f0r C 0.11 (Design Conds) (P;
- A-,. Pwr.l NA I I I ~ 1.02 I Reference WCAP-7905 REV.l NONE NONE jwcAP-7905 I REV.l I
I- V FSAR/Tech Spec NONE N
F~1,5S{1 +.3(1-P))
FQ(Z) :S. 4.54 I K(Z)
ForP ~0.15 FQ(Z)S)!.32/P r K(Z)
ForP > 0.15 -
NONE Acceptance I Criteria Reference NONE TS 3.12.B TS 3.12.B NONE I Design Tolerance is met Acceptance Criteria is met
- _YES_.NO
- _YES _NO VI I Comments
- As Required I
Prepared By: Reviewed By:
I I
NE-819 S1Cll Startup Test Report Page 55 of 59 I
I
-SURRY POWER STATION UNIT 1 CYCLE 11 I
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
Reference Test
Description:
~/D Flux Map-At Power Pree No/ Section: l-PT-28.2, 1-0P-57 Sequence Step No:
I II Test Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Power Level(% F.P.): - 70 I
Conditions SDA: 225 SOB: 225 CA: 225 Other (specify):
(Design) I CB : 225 cc : 225 CD:
- Must have~ 38 thimbles .I III I Bank Positions (Steps) RCS Temperature(°F):
Test Conditions I SDA: 225 SOB: 225 CA: 225 Power Level(? F.P.):
Other (Specify) :
"o* 7 I
(Actual) CB : 225 cc : 225 CD: 2 o'2.. ~f~J~
I i!
Date/Time Test Performed:
rz /.,_,. /; .a .t:J7:o~
I
! I IV Meas Parameter (Description)
MAX. REL ASSY PWR
% DIFF NUC ENTHALITOTAL HEAT QUADRANT RISE HOT CHAN FACT CHAN FACT FLUX HOT POWER TILT RATIO I
(M-P)/P F-dH(N) F-Q(T) QPTR L*..iw I
Measured Value 3.(o , ,'-\ca 4 ,.~,3 Test Results Design Value
(~-\ ~
J:.1°"10rP 1 ~0.11 l,O\ \1$
I J:. 15" IOr P.I < 0.11 (Design Conds) NA NA S 1.02 (P 1*Aay,Pwr.l WCAP-7905 WCAP-7905 I
Reference REV. l NONE NONE* REV .1 V
I N F,>>tS.1.55{1 + .3(1 .Pl)
T F o!ZI.S.2,:12/P r KIZ)
-1 Acceptance I FSAR/Tech Spec NONE NONE Criteria Reference* NONE TS 3.12.B TS 3.12.B NONE Design Tolerance is met : 7!ES _NO VI Acceptance Criteria is met : _YES
- NO Comments
- As Required I Prepared B ~ J \ << , els -' Reviewed By:
I I
NE-819 S1Cll Startup Test Report Page 56 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference Test
Description:
M/D Flux Map-At Power,NI Calibration Pree No/ Section: l-PT-28.2, l-OP-57 Sequence Step No:
I II Test Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Power Level (1. F.P.): - 70 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):*
I (Design) CB: 225 cc: 225 CD: **
~~/'
III Bank Positions (Steps) RCS Temperature(°F):
I Test Conditions SDA: 225 SOB: 225 cc: 225 CA: 225 Pow~r Level (% F.P.): <.:Z...o Other (Specify):
~
-,-l:_,. *(..Q.
. (Actual) CB: 225 CD: I 'f I 2..~~
I .. Date/Time Test Performed:
- 12. (21 / , o 12.:*6a I IV (Description)
MAX. REL Meas Parameter I ASSY PWR
% DIFF NUC ENTHAL TOTAL HEAT QUADRANT RISE HOT FLUX HOT POWER TILT CHAN FACT CHAN FACT RATIO (H*P)/P F*dH(N) F-Q(T) QPTR I JJ IA- IA Measured Value ,-.J N (/t- Cl, OL I Test Results Design Value
( &le.. "1A.,)
~10StorP ~o.ll 1
~ 15" for Pl C 0.11 (Design Conds) NA 1.02 I (Pi
- Aay.
WCAP-7905 Pwr.t NA ~
WCAP-7905 Reference REV. l NONE NONE REV .1 I V FSAR/Tech Spec NONE N
F~U5(t +.3(i.P)>
T F (Z).s,Z.3Z/P
- K(Z) 0 NONE Acceptance I Criteria Reference NONE TS 3.12.B TS 3.12.B NONE I Design Tolerance is met Acceptance Criteria is met
- -~YES _NO
- _YES _NO I VI Comments
- Must have at least 38 thimbles for a full-core flux map, or at least 16 thimbles for a quarter-core flux map.
- As Required I -
I Prepared By ~~ M::1 _, Reviewed By: 1ff~---.
I Page 57 of 59 I NE-819 S1Cll Startup Test Report
I SURRY POWER STATION UNIT 1 CYCLE 11 I
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Iese
Description:
~/D Flux Map-At Power,~I Calibration I
Reference ?=oc ~o I Section: l-PT-28.2, l-OP-57 Sequence Step No:
II Test
\
I I
Bank Positions (Steps)
, ~~~~~~~~~~~~~~~
RC.S Temperature ( 0 F) :TREF +/-1 Power Level Ci. F.P.): - 70 I
1 Conditions1 SDA: 225 SDB: 225 CA: 225 *
(Design) I CB : 225 CC: 225 CD:**
\
I Other (specify):
I III 1 Bank Positions (Steps) RCS Temperature( 0 F): .57'/
Test Conditions (Actual)
SDA: 225 CB : 225 SDB: 225 cc : 225 CA: 225 Power Level (% F. P.): S'f.~
Other (Specify) :
~~ ~-fh(6\
. ,I , J. n I CD: 2// J(A~
I Date/Time Test Performed: .~21 I I /'L.. /z.1 / ro /fot.oo IV I MAX. REL NUC Meas Parameter! ASSY PWR ENTHALITOTAL HEAT! QUADRANT RISE HOT FLUX HOT POWER TILT I (Description) I % DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR I
Measured Value Test Results
- _ 1o,,i,1or,'i ~0.1
,AJ ~ 1o1(,4... I Design Value :. I"' larPi < 0.1 (Design Conds) (Pi
Reference I REV .1 NONE NONE REV .1 N
II T I
V I FSAR/Tech Spec NONE F~1.55(1 + .3/1.P)} FQ(Z)g_:12/P K K(Z)
NONE Accepcancei-----~~~~~--~~~~-+-~~~-
Criteria
Design Tolerance is mec : ~S
/
NO I
Acceptance Criteria is met : LYES _NO VI Comments
- Must have at least 38 thimbles for a full-core flux map, or at least 16 thimbles for a quarter-core flux map.
I
- As Required ~
I Prepared Reviewed By: £~ I I
NE-819 S1Cll Startup Test Report Page 58 of 59 I
I I SURRY POWER STATION UNIT 1 CYCLE 11 STARTUP PHYSICS TEST RESULTS AND ,EVALUATION SHEET I I
'Reference Test
Description:
zi/0 Flux Map - HFP, ARO, Eq. Xe Pree No/ Section: l-PT-28.2, 1-0P-Si Sequence Step No:
I II Test:
Bank Positions (Steps) RCS Temperature (°F):TREF +/-1 Power Level (% F.P.):95 +/- 5 I Conditions (Design)
I SDA: 225 CB : 225 SDB: 225 cc : 225 CA: 225 CD:
- Other (specify) : Eq. Xe.
Must: have~ 38 thimbles III Bank Positions (Steps) RCS Temperat:ure(°F): S7'1 Test: Power Level (% F.P.): (00 I Conditions (Actual)
- SDA: 225 CB : 225 SOB: 225 cc : 225 CA: 225.
CD: Z"2.'(
Other (Specify): E.t x.... .
'17 7k,.., u..5 I Date/Time Test Performed:
11..hc.,/q.a IJ:oo -
I MAX. REL NUC ENTHALITOTAL HEAT QUADRANT I IV Meas Parameter (Description)
ASSY PWR
- DIFF RISE HOT CHAN FACT CHAN FACT FLUX HOT POWER TILT RATIO (M-P)/P F*dH(N) F-Q(T) QPTR
'I ).-'.r"'~ 1.11~1 /, 770 q.'( (Z-1t1 c.*~)
Measured Value i *"B (A-'l) ~
I Test:
Results Design Value
+/- IO'JI, IOr Pl~ 0.11
.:,1WIOrP cO,II 1
(Design Conds) NA 1.02
,I (Pi
F ~1.55(1 +,3(t-"))
T FcfZl,S,2.32/P ll K(ZI NONE Acceptance I Criteria Reference NONE TS 3.12.B TS 3.12.B NONE I Design Tolerance is met : ~ s _NO VI Acceptance Criteria is met : _YES
- NO I Comments
- As Required
'I Prepared By:
- Reviewed Byq ll,\, U, 1 J.._,
(
I I
NE-819 S1Cll Startup Test Report Page 59 of 59 I