ML18151A667
| ML18151A667 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/15/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18151A668 | List: |
| References | |
| 89-838, NUDOCS 8912270232 | |
| Download: ML18151A667 (61) | |
Text
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l e VIRGINIA ELECTRIC AND POWER COMPAl\'Y RICHMOND, VIRGINIA 23261
. December 15, 1989 United States Nuclear Regulatory Commission Serial No.89-838 Attention: Document Control Desk NO/CGL:vlh Washington, D. C. 20555 Docket No. 50-281 License No. DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TESTS REPORT As* required by Surry Technical Specification 6.6.A.1, enclosed are five (5) copies of the Virginia Electric and Power Company Technical Report NE-757 "Surry Unit 2, Cycle 1O Startup Physics Tests Report." This report summarizes the results of the physics testing program performed after initial criticality of Cycle 10 on September 16,
- 1989. The results of the physics tests were within required design tolerances and applicable Technical Specification limits.
Very truly yours,
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\ I
\-.._ . . ...... \, ,\. -
W. L. Stewart Senior Vice President - Nuclear Attachments cc: U. S, Nuclear Regulatory Commission Region II
- 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station
//
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9c 2?70?~0 P~]2;r i=' ~ / T I.~ ' { ~ 1.' ,' '
- TECHNICAL REPORT NE-757 - Rev. 0 SURRY UNIT 2, CYCLE 10 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER DECEMBER 1989
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PREPARED BY: \~£2w*~ - lL, tj_.__.~ 1-:..171~
A. H. Nicholson Date REVIEll'ED BY: /2-"'i -8 r C. A. Ford Date APPROVED BY,])])~~ 12/t/r(r D. Dzfuosz Date QA Category: Nuclear Safety Related Key~ords: S2Cl0, Startup
CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclus io11s 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 MAKES NO wARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, 1,.*ith 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 disclair.,ers cf liability and disclaimers of ,,arranties provided herein. In no event shall the Company be liable, under any legal theory 1,;hatsoever (whetber contract, . tort, warranty, or strict or absolute liability), for a~v property damage, merital or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized er unauthorized, of this report or the data,
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techniques, ir.for~at:on, or conclusions in 1 ....
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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 Red Drop Time Measurements......... 16
';r Section 3 Control Rod- Bank Worth Measurements........ 21 Section 4 Boron Endpoint and worth Measurements. . . . . . 26 Section 5 Temperatu"e Coefficient Measurements....... 30 Section 6 Pc~er Distrib~ticn Measurements............ )3 Section 7 References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 APPE~DIX Startup Physics Tests Results and Evaluatio~ Sheetj,............ *. . . . . . . ... 41
- Page ::! cf SE
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 Sbmmary... .* . . . . . . . . . . . . . . . . . . . 23
- 4. 1 Boron Endpoints Summary ........................._. . . . . . 28 5.1 Isothermal Temperature Coefficient Summary .... ,....... 32 6.1 Incore Flux ~ap Summary............................... ~5 6.2 Comparison of Measured Power Distribution Parameters
~ith Their Technical Specifications Limits............ 36
\*:--:-- C'"'""'"r' :::::: .... *
- *FIGURE TITLE LIST OF FIGURES PAGE
- 1. 1 Core Loading Map .. : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 1.2 Beginning of Cycle Fuel Assembly Burnups....... .. .. . . . . . . 12 1.3 Incore Movable Detector Locations........................ 13 1.4 Burnable Poison and Source Assembly Locations ...... .-..... 14 1.5 Control Rod Locations.................................... 15 2.1 Typical Rod Drop Trace................................... 19 2.2 Rod Drop Time - Hot Full Flow Conditions .......... ,...... 20 3.1 Bank B Integral Rod Worth - HZP.......................... 24 3.2 Bank B Differential Rod Worth - HZP...................... 25 4 .1 Boron v.*orr:h *coefficient .....-................... .'......... 29 6.1 Assembly.,'ise Po.,'er Distribution - 30~~ Power. . . .. . . 37 6.2 A/s s emb 1yw is e Po.,'er Distribution - 64~., Power. .. 38 6.3 Assembly.,*ise Pm.-er Distribution - 1 OO~o Power. .... 39
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- ' PREFACE This report presents the analysis and evaluation of the physics tests which were performed to verify that the Sutry 2, Cycle 10 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to pre~ent the detailed data taken. Standard t~st 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 2, Cycle 10 Startup Physics Tests Results and Evaluation Sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), :3) test conditions (actuE.:), 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 ~alues of the measured parameters were complet~d prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Corrpary's \uc!eer A~a!ysis and Fuel Group 1 . During the tests, the data sheets 1,;ere usec as guidelines both to verify that the proper test conditions were ~et a~~ to facilitate the preliminary comparison between 5 of 5~
- ' measured and predicted test results, thus enabling a quick identification of possible problems occuring during the tests .
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1 SECTION 1 INTRODUCTION AND
SUMMARY
On September 10, 1988 Unit No. 2 of the Surry Power Station shutdown for its ninth refueling. )Ju ring this shutdown, 77 of the 15 7 fuel assemblies in the core were replaced with 52 fresh fuel assemblies, 17 once burned fuel assemblies, and 8 twice burned fuel' assemblies. The tenth cycle core consists of 10 sub-batches of fuel: five once-burned batches, two from Cycle 9 (batches llA and llB), two from Surry Unit- 1 Cycle 6 (batches Sl/8A and Sl/8B), and one. from Surry Unit 1 Cycle 8 (bat.ch Sl/10); two twice burned batches, one from Cycles 8 and 9 (batch 10), and one from Cycles 7 and S (batch 9A); and three fresh bat.ches (batches 12A, 12B, and 12C). fourteen of the batch SI/SA and Sl/8B assemblies are reconstituted, containing a total of 26 solid zircaloy rods. The three fresh bat.ch es are of the Surry Improved fuel . ( SIF) product design. The core }oading pattern and the design parameters for each bat.ch are shown in figure 1.1. fuel assembly burnups are given in figure 1. 2. The incore movable detector* locations are identified in Figure 1.3. figure l.~ identifies the location and number of burnable ppison rods and source assemblies for Cycle 10, and Figure 1.5 identifies the location and number of control rods in the Cycle 10 core.
On Sept.ember 16, 1989 at 19:59, the tenth cycle core achieved initial c~i:icality. Fc2low~:~ c~itica1i:y, start.up physics tes:s we~e ~e~~ormed
- E.s cu:. l ineC follo\,:s:
- - - -: - C
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...:.. . -".. A sur:irrary of the results of t~ese tests
- 1. The measured drop time of each control rod was within the 2. 4 second limit of Technical Specification 3.12.C.l.
- 2. Individual control rod bank worths were measured using the rod swap technique 2 , 6 and the results were within 8.2% of the design predictions. The sum of the individual measured control rod bank worths was within 0.7: of the design prediction. These results aie 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 1,.-orths.
- 3. ~easured critical boron concentrations* for two control bank
- configurations were \..'ithin 36 ppm of the design predictions.
These results were ~ithin the design tolerances and also met the accident analysis acceptance criterion.
- 4. The boron ~orth coefficient measurement was within 3.S: of the desiin prediction, ~hich is ~ithin the design tolerance of +/-10:.
- 5. The measured isothermal temperature coefficient (ITC) for the all-rods-out configuration was within o:78 pcm/°F of the design prediction. This result is within the design tolerance of +/-3 pcm,'°F, and also meets the accident analysis acceptan_ce criterior: .
- 6. Ccr(: po1-*er dis;t::ricutior:s established ces ign for to} e:rar.ces.
"C" ~
et-.power conditions Generally, the 1-*ere 1-*i::r.:::
measured core
power distribution was within 4.5% of the predicted power distri.bution. The heat flux hot channel factors, F-Q(T), and enthalpy rise hot channel factors; F-dH(M), were within the limits of their respective Technical Specifications.
In summary, all startup physics test results were acceptable.
Detailed results, specific design tolerances and acceptance criteria for each measurement are presented in the following sections of this report.
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Table 1.1 SURRY 2 - CYCLE 10 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop Timing Test 9/14/89 1842 HSD 2-PT-7.2*
Zero Power Testing Range 9/16/89 2232 HZP 2-PT-28.11 Reactivity Computer Checkout 9/17/89 0251 HZP 2-PT-28.11
~
- , Boron Endpoint - ARJ 9/17/89 0557 HZP 2-PT-28.11 Temperature Coefficient - ARO 9/17/89 0715 HZP 2-PT-28.11 Bank B \.1orth 9/17/89 1124 HZP. 2-PT-28 .11 Boron Endpoint - B in 9/17/89 1330 HZP 2-PT-28.11 Bank D 1,,*orth - Rod s,..;ap 9/17/89 1420 H".,P L,. 2-PT-28 .11 Bank C \.,"orth - Rod S1.*ap 9/17/89 1459 HZP 2-PT-28 .11 Bank A Worth - Rod S1.*ap 9/17/89 1.547 HZP 2-PT-28.11 Bank SB Worth - Rod Swap 9/17/89 1725 HZP 2-PT-28 .11 Bank SA 1,,*orth - Rod S1.*_ap, 9/17/89 1808 HZP 2-PT-28.11 Flux Map - 30'.'~ Po1.*er 9/20/89 0739 30% 2-PT-28.2 Flux Map - --~I U ,o Po1.*er 10/02/89 0727 0 6.:.. o 2-PT-28.2 Flux Map - I/E Calibration 10/02/89 0957 61. ~o 2-PT-28.2 Flux Map - I/E Calibration 10/02/89 1350 64~o 2-PT-28.2 Flux Map - 1/E Calibration 10/03/89 0947 6 l~o 2-PT-28.2 Flux Map - HFP 10/09/89 1638 100% 2-PT-28.2
t Figure 1. 1 SURRY UNIT 2 - CYCLE 10 CORE LOADING MAP R p H J H G F E D C B A lD Sl/8BI 10 I I SS9 I DCl I 3S5 I 1
_____ I__ I __ I__ I I ID Sl/8AI 12B I llB I 12B I Sl/8AI 10 I 1S2 I lB8 I 2U9 I 3T7 I 4Ul I DB2 I lS4 I 2
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Figure 1. 2
' R p H H SURRY UNIT 2 - CYCLE 10 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS K J H G F E D C B A 5S9 OCl 3S5 I I 347251 148281 346721
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r-.,... ... _.
Figure 1. 3 SURRY UNIT 2 - CYCLE 10 INCORE-MOVABLE DETECTOR LOCATIONS R. p N 11 K J H G F E 0 C B A I I I 110 I 1
_ _ _ _ _ I _ _ _ _ I _ _ _ _ _ __
I I I I I I I I 110 I I 2
_ _ I _ _ I _ _ I _ _ I_ _ I_ _ I _ _ I _ _ I _ _
I I I I I I I I I I I 110 I I I 110 I 110 I I I I 110 I 3
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_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1- I _ _ I _ _ I_ _
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_ _ 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 I HD I I HD I HD I I I I JJ 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 l1D I I I I HD I I *I I_ I HD I 110 I lZ 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 HD I I I l3 I I* I ! I I I I I I I I I 1--1 I I i HD ! I I HD I I I 14 I _ _ _ _ _ _ I _ _ I _ _ I _ _ I_ _ I HD - Hovable Detec-:::ir I I I I I 11C I I I 15 1_ _ 1_ _ , _ _ 1
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'~ Figure 1.4 SURRY UNIT 2 - CYCLE 10 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS R p N K J H G F E D C B A I
I I I I
' I I I I 1 I ZOP* I I 2DP* I I I 2
_ _ l_ _ , _ _ ,_ _ I_ _ I_ _ ,_ _ ,_ _ ,_ _
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17P - 17 BURNABLE POISON ROD CLUSlfP I I I I
.. p. - . " DEPLETED BU,'NU'.E POIS_ON PO,* CLUSff*. I I I I 15 20P* - 20 DEPLETED BURNAB,E POISON POD CLUSTER I_ _ I _ _ I_ _ I
_ss, - SECONDARY SOUPCE
- R Tes:s -
Figure 1.5 SURRY UNIT 2 - CYCLE 10 CONTROL ROD LOCATIONS R p N H L K J H G F E D C B A 180° I
Loop C I I I I Loop B l Outlet I __ I __ I __ I Inlet I I A I I D I I A I I 2
_I_I_I_I_I_I_I_I_
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 I_I_I_I_I_I_I_I I_I_I_I_I_I 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- l __ l __ l _ l _ ! _ I _ I _ I _ I __ I __ I __ I _ I _ I _ I 90°- I I D I -I I I c I I I I c I I I I D I I - 270° 8 1_1_1_1_,_,_,_1_1_1_1_1_1_1_1_1 I I I SA I I SP I I SB I I SB I I SP I I SA I I I 9 1_1_1_1_1_1_1_1_1_1_1_1_1_1_1_1 IAI !Bl !DI ICI IDI IBI IAI 10 I __ L 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 11 I_I_I_I_I_I - l_l_l_l_l_l_l_l 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 i4 I_-_ I _ I _ I _ I _ I _ -_ I _ I I I I I 15 Looo A I __ I __ I __ I Loop A Absorber Outiet Inlet Haterial I Ag-In-Cd 00 Function Nu~ber 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
- 1. : - - - '.'" - ~ ~ =: . ,* .................. -
SECTION 2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at. hot full-flow reactor coolant system (RCS) conditions in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was liss than or equal to the maximum allowed by Techn~cal Specification 3.12.C.1. The hot control rod drop time measurements were run with the RCS at hot full floi..* conditions (547°F, 2235 psig) and are described be loi..*.
The rod drop times were ~easured by withdrawing a rod bank to it~
fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The data recorded during this test are the stationary gripper coil voltage, the LVDT (Linear Variable Differential Transformer) primary coil voltage, and a 60 Hz timing trace which are recorded via a (isicorder. The rod drop time to the dashpot entry and to the bottom of the dashpot are ~etermined 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 dro?s. :he rra£nitude of this voltage is a function c~ the ro~
veloci:v. ~hen xhe rod enters the dashpot section of its guide tube, the
\*elocitY sloi..'s causing a voltage decrease in the LVDT coil. The LVDT Page 1: of S8
t voltage then reaches a minimum as the rod reaches dashpot. Subsequent variations in the trace a*re the bottom of the 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.l specifies a maximum rod drop time from loss of stationary gripper coil vo)tage to dashpot entry of 2.4 seconds with the RCS at hot, full flow conditiohs. These test result~
satisfied this limit.
Table 2.1 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS HOT ROD DROP TIME
SUMMARY
ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE* TIME K-06 1.22 sec. 11-12 1.11 sec. 1. 17 sec.
ROD DROP TIME TO BOTTOM OF DASHPOT SLO~EST ROD FASTEST ROD AVERAGE TIME M-06 l . 91 sec. P-06 1. 64 sec . 1. 77 sec.
- ,*;-_-;c-* C ....., ,.... ~ r
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'J TYPICAi. ROI> DROP TRACI!
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Figure 2.2 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS ROD DROP ,TIME - HOT FULL FLOW CONDITIONS R p N H J H G F E D C B A I
I I I I
_ _ _ _ _ I_ _ I_ _ I _ _ I I l. 16 I I l. 18 I 1--=-1."""1c:-9--,-I- -
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_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _
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- _ _ I _ _ I _ _ I . I _ _ I _ _ I_ _ I_ _ I_ _ I _ _ I_ _ I _ _ I _ _
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_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _
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I Y.Y\ i--' ROD DROP TJHE TO BOTTOH OF DASHPOi (SEC)
I I
- (: ~: ~ . : -* - ..- : ~ '", C: . ,.
'* SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 2
- 6 . The initial step of the rod swap procedure was to dilute the predicted 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 3 and were used to determine the differential a_nd integral i..*ort!l of the reference bank. For Cycle 10, Control Bank B was used as the reference bank.
After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration i..*ere stabilized i..*ith the reactor just critical and the reference bank near full inseition. Initial statepoint data for-the rod swap maneu\*er i..*ere 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 sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the This meesured critical position (~:::?) of the
- refeT~~2e be:-:K w1:~ t~e test bank fully inserted was used to deterffii~e tr,0 i:-:te~:-al reec:'.i\*ity i..*orth of the test bank. The core*reactivity.
f m6derator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver was then repeated in reverse order such that the reference bank was once again near full insertion with the test bank fully withdrawn from the core. This rod s1.1ap 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 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, +/-15: for each test bank worth greater than 600 pcm, and
+/-100 pcm for each test bank worth of less than 600 pcm). The sum of the individual measured rod bank worths was within 0. 7% of .the design prediction. This is well within the design tolerance of +/-10% for the sum o~.the individual control rod bank worths.
The integral and differential reacti\'ity worths of the reference bank (Control Bank E) are shO\,:n 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 .
- \ ~
,':) I S2C1C ~:2r:~~ ?hys~cs Tests Reoort of ="
I Table 3.1 SURRY UNtT 2 - CYCLE 10 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 1347.9 1364.0 -1. 2 D 1154. 6 1118.0 3.3 C 781. 4 739.8 5.6 A 331.1 360.6 -8.2
~ Difference is less than 100 pc~.
~3 c: *
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~.,..,
S:ar:~~ Phvs~cs ~ests Report Page
I Figure 3.2 SURRY UNIT 2 CYCLE 10 STARTUP PHYSICS TESTS BANK B DIFFERENTIAL ROD WORTH HZP ALL OTHER RODS WITHDRAWN i 11 21 *. 00 00 i:.***. *,* * * *. :* :::::~:: ***:*** . *:** :::::::::::::: ::::::::~: ::;.::;:~::;:::::;_*::;:: . . ::1::;:~::1::~:* :
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0 8 16 24 J2 '4-0 ~ 56 64 72 80 88 96 1oe 132 H4 156 16B 180 192 216 22e BANK POSITION (STEPS)
- ~:2~:~? Fhysics Tests Eeport Page ...,
_:)
- of
SECTION 4.
Ii BORON ENDPOINT AND WORTH MEASUREMENTS i
Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron. concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration \*alues were made to account for off-nominal control rod position and moderator temperature, if necessary.
The results of these measurements are given in Table 4.1. As shown in this ta.ble and in the Startup Physics Tests Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values 1,.*ere 1,.*ithin the::- respective design_ tolerances and 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. By relating each endpoint concentration to the integrated rod ""'*or:b presc:-.:- ::! t.lit cc:-E: a: the t.ime o: the endpoin:. measuremen:.,
- the val~e of the DE~ over the ra~ge of boron endpoint concentra:ions w~c c::ita ir:cc.
A plot of the boron concentration versus inserted control rod worth is shown in Figure 4.1. As indicated in this figure and in the Appendix, the DBW measured was -8.07 pcm/ppm. This is within 3.3% of the predicted value of -7.80 pcm/ppm and is well within the design tolerance of +/-10%.
The - measurement result also met the accident analysis .acceptance criterion. In summary, the measured boron worth coefficient was satisfactory .
- \*:-
' - -. -*:: -. of SE
Table 4.1 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
Measured Predictec;i
- Difference Control Rod Endpoin:t Endpoint M-P Configuration (ppm) (ppm) (ppm)
ARO 1581 1617 -36 B Bank In 1414 1405* +9
- The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and* predic.ted values of the endpoint taken at the ARO configuration as shown in the bore~ endpoint Startup Physics Test Results and Evaluation Sheets in the Appendix.
\:- - - :- -
I Figure 4.1.
SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT
~
i' I Measured DBW = -8.07 pcm/ppm
.1,500 .......:........ _.......... ******** ..................:' ........ :............................i******** r.. ******r********i ........ r****** ... ******** r................. ********r**.. *** ~
1;400 *******.******************.******** ********,-*******,********.*********:********:"********t******,*********:"*******1********:-********1********1********t******1********;********
1,300 *************** ***************** ********:*** ******-********r********;***************************\*****'*************-********1********-~********r********i********.. ********1********
1,200 *******>********t*********t
- ********l********".*********f*********l********(*********l********<*********l*********:.********l*********)********(*********l*********:.,,,., *** 1 ********
1,100 *******>********(*********I********(***
- l*********",o********C*********)********(*********l***oo***(**"*****l*****oo**:***"****l******00*)********(*** 0 0 ****1* 00
. .. .. .. ******:0********I********
I : : : .
'i' 1,000 :
' ... -~ .. ** *' *. ~* ........ !**** .... ~**. *** *' * . ' .. * -> ** ** ** ** ~* **** ** **> * '" ** ~* ...... **~* ..... **~*' *** * *** ~' * .. * *' * °? *** *** ~' ******* *r******* *~* ********~ *** ** ***~********I' ...... .
u .
CL 900 ...... *. ........ *......... .* ........ * ................ *. ............... *. ........ .*......... .* ................... .. .
800 .......................... :........ :. ....... . .. ...... . ........ :- .... .... . ..... : ........ ;................. ;.................
._.. ~
._.. 700 * * * * * * -~ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .;. ******** .;.. . . * ** * ... * * ** * * * * ... *
- ************ .;.. . . . . . . . . . . . . . . . . . .;. . . . . . . . . ,j . . . . . . . . . . . . . . . . . . . .;.. . . . . . . . ** . . . . . . . . . . . . . . . . . . . . ; . . . . . . . .
u
<{ 600 ....... * ............... , .. :********* .............. * ........ *.........:,., ..... * ........ :**" .* .... , ... :-*******:***************************:********:""" .. * ........ *....... .
w . . ..
c::: 500 ******- ***************************-******** . ********-*****************-********-*****************-****** .. ********-*****************-********-*****************-*****************
400 '
- * * - * * ', * ** ********* * ** ** *, * *** - *, ***** * ** ** ** ** - * * ** ** ,,;,,, *****.,. ,,,,,,,,.;.,,,,u,.i,.,,,,,,.;;,.,,,,,,,,;,,,,, ***
- ooo,,;.,,,,,.,..;.,,,,, ,,,.;.,,,,,,,,, ****** ,,.;.,,,,,,,, : *. ** ****
300 ****** - *************************** - **************** w:. ******* -.~ ******* ,..;. ****** **':"*'"'; ........ ~ ***************** ..;. ********~*.
- ** ..;. ******** ':"*******-~*-******~**** **** ; ********
200 ...... * ........................... * ................ * ........ *........ * ........ * ....... *........ * ........ :*.* ...... * ........ *:............ *: ........ *: ........ *: ........ * ....... .
. . : : . : : : I : : . . : .
100 ..*... .c .................. :........ .:. ........ ********-'"********!********-'"********~*******.; ........ .:. ........ :********-'"********'******** ........ .:. .... .
~ 1 L O+-_....._..____.___,_-+--+-...----+--~--+-----+--+----+---+-..........-f---+-~...---+---..
1'400 1420 14-4-0 1460 1480 1500 1 S20 1540 1!>60 1580 1600 BORON CONCENTRATION (PPM)
- ':c. of SE
SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENTS The isothermal temperature coefficient (I7C) measurement was accomplished by controlling the reactor coolant system (RCS) temperature with the ste~m dump valves to the condenser and/or the steam 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 minimizi the effects of .non-uniform nuclear heating, thus the moderator and fuel were at approximately the same temperature during the measurement. To eliminate the boron reactivity effect of outflow from the pressurizer, the pressurizer level i.as held constant or slightly increasing during the measurement.
Reactivity was rreasured during both the RCS cooldown and heatup while the RCS temperature varied by approximately S°F. Reactivity and temperature data were taken from the reactivity computer and strip chart recorders. Csing the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature,. confirmed the applicability of using the statepoint method to calculate the measured ITC .
1ne
=reci~c:e~
C: - - **
e~~ measured isothermal tern~erature coe~~icient ve2ues As can be seen from this summary and from the
I
?
Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured isothermal temperature coefficient value was within the design .tolerance of +/-3 pcm/°F and met the accid~nt analysis acceptance
~
criterion. In summary, th~ measured temperature coefficient was i satisfactory.
j I
i
Table 5.1 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/°F)
BA\'K TD PER,\ TLRE BORD\ COOL HEAT AVE. DIFF.
POSITIO~ RANGE CO\'CE!'-."TRA TIO\' DOWN UP MEAS. PRED. (M-P)
(steps) ( OF) (ppm)
D 542.5 215/216 to 1.580 -3.50 -3.44 -3.47 -4.25 +0.78 5.'..7.5
- \
. - - -. - C:. ' ' ** ,* - ,... C ~ ( ::° **.~ ?:: ~r_,
I
-' SECTION 6 POWER DISTRIBUTION MEASUREMENTS The co_re power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations (see Figure 1.3)._ For e_ach traverse, the detector voltage out:put is continuously moni t,ored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimerisional power distributiGns are determined from this data using the Westinghouse computer program, I\CORE 4 . I\CORE couples the measured voltages with predetermined analytic ratios in order to determine the po\o:er distribution for the whole core.
A list of the, full-core flux .maps taken during the startup test program and the measured \*alues of the important power distribution parameters is gi,;en in Table 6.1. The measured power distribution parameter {a1ues are compared with their Technical Specifications limits in Table 6.2. Flux ~ap 1 was taken at 36\ power to verify the radial power distribution (RPD) predictions at low power. Figure 6 .1 shows the measured RPDs frpm this flux map. Flux maps 2 and 6 were taken at 64~
and 100% power levels with different control rod configurations. These flux maps were taken to check at-power design predictions and to measure core pOl,'er distributions at various operating conditions. The radia 1
- ,01.;er d
- s::rii:utic:'.5 ::er t:--.ese m3~s are gi\*en i:-. Figures 6. 2 a:-::: t. 3 .
- These figures show t~a: the measured relative asse~bly power values were ge:-,erall\* i,;it~.i:-: -.:~, c: the p!'edic:ec values. Further, the measu!'ec
F-Q(T) and F-DH(N) peaking factor values for the at-power flux maps were within the respective Technical Specification limits.
In conclusion, the power distribution measurement results were considered to be acceptabl~ with respect to the design tolerances, the accident analysis acceptance criteria, and the Technical Specification limits. It is therefore anticipated that the core v.ill continue to operate safely throughout Cycle 10 .
- ' ** (. ** I.. * ;. :: : s :- r., :*
I TABLE 6.1 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS INCORE FLUX MAP
SUMMARY
I I I I .1 I I I I I I I BURHI I F-C(Tl HOT I F-dH(Hl HOT CORE FCZ) 2 I I I I HAP IHAPJ UP I IBANK CHANNEL FACTOR I CHNL.FACTOR HAX CPTR I AXIAL! NO.I I DESCRlPTION IHO. I DATE HWD/IPWRI D I I I I I OFF I OF I I I I HTU IC%llSTEPSIASSYIPIHIAXIALI IASSYIPINIF-dH(NllAX!ALI F(Zll HAX )LOCI SET ITHH1l I I I I I I I IPOIHTJF-CCTl I I I IPOIHTI I I I C%J IBLESI I _______ I_I ___ I . I_I __ I_I_I
- I ___ I _ I _ I ___ I __ I __ I _ l _ l _ _ l __ l ILOW POWEP I 1 I 9-20-B91 I 301 166 Hl3I DCI 34 I 2.203 I El21 GHI 1.524 I 31 11.374)1.0151 SEI -0.881 42 I IOPTP VEPFICATJOH I 2 llO-GZ-891 115 I 6sl 180 I Hl31 DCI 24 I 2.006 I Jl21 OHi 1.467 I 32 ll.27811.0101 SEI -1.961 42 I IHOT FULL POWER I 6 ll0-09-891 315 llOOI 207 IF 91 AHi 33 I 1.840 IF 91 AHi 1.474 I 33 ll.21411.0101 SEI -1.Zll 41 I I l _ l _ _ _ l _ _ 1_:._1 _ _ I _ I _ I _ _ I _ _ _ I _ I _ I _ _ _ I _ _ I _ _ I _ _ I _ I _ _ I _ I HOTES: HOT SPOT LOCATIONS APE SPECIFIED BY GIVING ASSEHBLY LOCATIONS (E.G. H-8 IS THE CENTER-OF-CORE ASSENBLY),
FOLLOWED BY THE PIH LOCATION IDEHOTED BY THE "Y" COORDINATE WITH THE SEVENTEEN ROWS OF FUEL RODS LETTEPED .A THROUGH R AHO THE "X" COORDINATE DESIGNATED IN A SHIILAR HANH[R).
IH THE "Z* DIPECTIOH.THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROM THE TOP OF THE CORE.
- l. F-O(Tl INCLUDES A TOTAL UNCERTAINTY OF 8%.
- 2. FdHCH1 INCLUDES A TOTAL UNCERTAINTY OF 4%.
- 3. ~PTR - QUADRANT POWER TILT RATIO.
,. HAPS 3 ANc, WERE QUARTER-CORE FLU~ HAPS TAKEN FOR IHCOR'E/EXCORE CALIBRATION. 11/E CALIBRATIOHJ.
HAP 5 WAS .A OUARTEP.-CORE FLUX HAP TAKEN OUTSIDE OF THE PHYSICS TEST PROGRAM TO HEASURE AXIAL OFFSET .
- C- '. ~- **- . ;, ~:: s
t Table 6.2 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS COHPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR TECHNICAL SPECIFICATION LIMITS F-Q(T) HOT F-dH(N) HOT CHANNEL FACTOR* CHANNEL FACTOR MAP
~o. MEAS LIMIT MARGIN MEAS LIMIT MARGIN 0~) (%)
1 2.203 4.640 52.0 1.524 1. 876 18.8 2 2.006 3.566 43.8 1. 467 1. 717 14.6 6 1.840 2.320 20.6 1. 4 74 1. 550 4.9
~ The Technical Specificat{on'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 bet1.'een the measured values of F-Q(T) and the Technical Specification's limii for each map. The measured F-Q(T) hot channel factors include 8% total unce:-t.a int.y.
\"...
- - -' - =C*
Figure 6.1 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 30i. POWER R p H H J H G F E D C B A PREDICTED 0.30 0.43 0.30 PREDICTED HEASURED . 0.29 . 0.42 . 0.29 . HEASURED
- PCT DIFFERENCE. . -4.2 . -4.2 . -1.7 .
- PCT DIFFEREHCE.
0.38 0.62 1.13 0.98 1.13 0.61 0.38
. 0.37 . 0.59, 1.09. 0.94. 1.10. 0.60 . 0.38. 2
. -2.0 . -4.2, -4.2. -4.2. -2.7. -1.9. -0.6.
0.38 1.14 1.28 1.22 1.29 1.22 1.27 1.13 0.38
. 0.38 . l."10 . 1.22 . I.I~ . 1.24 . 1.18 . 1.25 . 1.13 . 0.39 . 3
. -2.4 . :3.4 . -4.7 . -3.5. -3.9 . -2.8. -2.0 . -0.4 . 1.6 ,
0.38 ._O.b9 1.29 1.33 1.31 1.18 1.30 1.32 1.28 0.69 0.38
. 0.38. 0.67. 1:24 .. 1.29. 1.28 . 1.15. 1.27. 1.30. 1.27. 0.68. 0.38 . 4
. -2.1 . -3.2 . -4.2 . -2.8. -2.0 . -2.5. -2.7. -1.9. -1.0 . -o.4 . o.8 .
0.38 1.14 1.29 1.27 1.23 0.99 1.22 0.99 1.22 1.26 1.28 1.13 0.38
. 0.38 . I.II . 1.25 . 1.23 . 1.20 . 0.99 .* 1.22. 0.98. 1.21 . 1.25. 1.26 . 1.13 . 0.39 . 5
. -2.0 . -2.7 . -3.5 . -3.l . -2 . * . 0.0 . 0.1 . -0.2. -0.7. -1.0 . -1.8 . 0.5 . 2.9 .
0.62 1.28 1.33 1.23 1.12 1.18 1.19 1.17 -1.11 1.22 1.32 1.27 0.61
. 0.60. 1.2,. 1.29*. 1.19. l.l_l . 1.21 . 1.22. 1.19. 1.11. 1.21 . 1.30. 1.27. 0.62. 6
. -2.7. -3.4 . -3.2 . -3.4 . -1.3. 2.0 . 2.6. 2.1 . 0.4 . -0.5 . -1.2 *. 0.3 . 1.8 .
0.30 1.14 1.22 1.31 0.99 l.18 1.12 1.20 1.08 1.16 0.98 1.29 1.21 1.12 0.29
. 0.29 . 1.11 . 1.19. 1.28 . 0.97 . 1.18. 1,16. 1.23 . 1.11 . 1.19. 0.99. 1.29 . 1.21 . 1.13 . 0.30 . 7
. -2.8 . -2.7 . -2.7, *2.6 . -2.6 . 0.0 . 3.6. 3.2 . 2.9. 2.7. 1.3. -0.6. 0.4 . 0.8 . 1.3.
0.43 0.98 1.24 :.lb 1.22 1.19 1.20 1.09 1.18 1.17 1.20 1.17 1.28 0.97 0.43
. 0.42 . 0.95 . 1.2b. 1.17 . 1.20 . 1.20 . 1.24 . 1.14 . 1.23. 1.22. 1.24 . 1.16 . 1.28 ~ 0.99. 0.44 . 8
. -2.8 . -2.8 . -:.7 . -0.9 . -1.0 . l.l . 3.7 . 3.9 . 4.0 . 4.3. 2.8. -0.4 . 0.2 . 1.8. 2.4 .
0.30 1.13 1.22 ].30 0.99 1.17 1.08 1.19 1.08 1.16 0.98 1.30 1.21 1.13 0.29
. 0.29 . 1.10 . 1.1* . 1.30 . I.OJ . 1.18. 1.10 ; i.23. 1.13. 1.20 . 1.01 . 1.29 . 1.22 . 1.15 . 0.31 . 9
. -2.l . -2.5 . -2.6. -0.4 . 2.3 . 1.2. 1.9. 3.8. 4.6. 3.5. 2.7. -0.2 . 0.8 . 2.3. 3.6.
0.61 1.27 1.3: 1.22 l.11 1.16 1.17 1.16 1.10 1.22 1.32 1.27* 0.61
. 0.59 . 1.24 . 1.31 . 1.23 . l.t2 . 1.19. 1.21 . 1.20 . 1.13. 1.24 . 1.31 . 1.28 . 0.62 . 10
. -2.5 . -2.5 . -0.6 . 0.8 . 1.1 . 1.9. 2.9. 3.5. 2.9. 1.6 . -0.1 . 0.7 . 2.0 .
0.38 1.13 1.29 1.26 1.22 0.98 1.20 0.98 1.21 1.26 1.28 1.13 0.38
. 0.36 . 1.13 . l.27 . 1.24 . 1.22 . I.OD . 1.24 . I.OD . 1.24 . 1.28 . 1.30 . I.I* . 0.38 . 11
. -O.b. -C.b. *l.O. -1.5. -O.I . 2.3. 2.6. 2.7. 2.6; 1.6. 1.4. 1.4. 1.7.
0.35 0.69 1.28 1.32 1.30 1.16 '1.29 1.31 1.28 0.68 0.38
. 0.39 . 0.b9 . 1.26 . 1.30 . t.33. 1.20 . 1.31 . 1.33. 1.30 . 0.70 . 0.39 . 12 I.* 0.2 . -1.6 . -1.b. 2.7 . 2.7 . 1.5. I.I . 1.6 . 2.3 . 1.9 .
C.38 1.13 1.27 1.21 1.28 1.21 1.26 1.12 0.38
. 0.39 . 1.14 . 1.28. 1.26. 1.31 . 1:20 . 1.25. 1.13. 0.39 . 13 1.2 . I.I . 1.2. 3.8 . 2.6 . -0.8 . -0.9. 0.4 . 2.2 .
0.38 0.60 1.12 0.97 1.12 0.60 0.38
. 0.38 . 0.62 . 1.16 . 1.00 . 1.11 . 0.60 . 0.37 . 14 I.I . 2.2 . 3.7 . 3.6 . -0.7 . -0.9 . -1.0 .
STANDARD 0.29 0.43 0.29 AVERAGE DE\ilATJOs . 0.30 . 0.45. D,30 . .PCT DIFFERENCE. 1S
=l.196 3.7 . 3.6 . 3.7 . 2. l SUHHARY HAP NO: s2-10-01 DATE: 9/20/89 POWER: 30%
CONTROL ROD POSITIONS: F-Q(TJ = 2.203 QPTR:
D BANI: t.., 1 bb STEPS F-dH(N) = 1.52-i NW 0.9825 NE 0.9<?72 F( Zl 1. 37'< SW 1.0052 SE 1.0151 BURNUP = 2 HWD/HTU A.O. = - 0. 863:,
I Figure 6.2 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSIGS TESTS ASSEMBLYWISE POWER DISTRIBUTION 64% POWER R p N H J H G F E D C B A PREDICTED 0.31 0.46 0.31 PREDICTED MEASURED . 0.31 . 0.45. 0.30 . MEASURED
0.39 0.62 1.12 0.99 1.12 0.61 0.39
. 0.38. 0.61 . 1.09. 0.97. 1.09. 0.60 . 0.38 .
. -2.7. *2.3. -2.3. -2.4 . -2.5. -2.7. -1.2 .
. 0.39 J.JO J.23 1.19 1.26 1.19 1.23 1.10 0.39
. 0.38 . l.07. 1.19. 1.17 . 1.23. 1.18 . 1.22. 1.10 . 0.39. 3
. -2.8 . -3.3 . *3.9. -).5 . -2.0 . -1.3. -1.l . -0.2. 1.1 .
0.39 0.69 1.25 - 1.29 1.28 1.16 1.28 1.29 1.25 0.69 0.39
. 0.38 . 0.67 . 1.21 . 1.27. 1.28. 1.16. 1.27. 1.29. 1.24. 0.68 . 0.39. 4
. -2.7 . *2.6 . *3.3. -I.* . *O.l . -0.4 . -0.5 . 0.3. -0.6 . -1.0 . -O.l .
I 0.39 1.10 1.25 1.25 1.23 1.01 1.23 1.01 1.23 1.25 1.24
. 0.38 . 1.10 . 1.22 . 1.24 . 1.22 . 1.03 . 1.25 . I.OZ . 1.23. 1.23 . 1.21 . 1.09. 0.39 .
. -Z.7 . -0.6 . *2.0 . -1.3. -0.9 . 1.6. 1.7 .. 1.3 . O.l . -1.2 . -Z.7 . -0.7 . 1.5 .
1.10 0.39 0.62 1.23 l.z* 1.24 I.lb 1.21 1.22 1.20 1.15 1.23 1.29 1.23 0.62
. 0.62 . 1.21 . 1.27 , l.ZJ. I.lb . 1.25 . 1.26 . 1.22 . 1.15. 1.22 . 1.27 . 1.22. 0~62 . 6
. -0.5 . -2.4 . -1.7. -2.2 . -0.0 . 2:9. 3.4 . 1.9 . 0.2. -0.7 . -1.6. -0.7. 0.3.
o.31 1.12 1.1° ,.n 1.01 1.21 1.11 1.25 1.13 1.20 1.01 1.21 1.19 1.11 o.31
. 0.31 . 1.11 . 1.19 . 1.27 . 1.00 . 1.22 . 1.21 . 1.28 . 1.15. 1.21 . 1.01 . 1.27. 1.19. 1.11 . 0.31 . 7
. -0.6 . -0.6 . -0.5. -1.1 . -1.5 . 0.7 . 3.7. 2.9. 1.3. 1.4*. 0.8 . *0.4 . 0.3 . -0.4 . 0.4 .
0.46 0.99 1.26 I.lo 1.23 1.22 1.25 1.15 1.24 1.21 1.23 1.16 1.26 0.99 0.46
. 0.46 . 0.98 . 1.25 . 1.17 . l.24 . 1.24 . 1.29. 1.19 . J.28 . 1.24 . 1.25 . 1.)6. 1.27. 1.00 . 0.46 . 8
. -0.7 . -0.8 . -0.6 . 0.6 . 0.2 . 2.0 . 3.7. 3.4 . 3.0 . 2.6 . 1.8 . 0.1 . 0.8. 1.5 . 0.8 .
. 0.31 1.12 1.19. 1.28 l.Ol 1.20 1.13 1.24 1.13 1.20 ).01 1.28 1.19 1.12 0.31
. 0.30 . 1.09 . 1.16 . 1.28 . I.Os . 1.2::
- 1.15 . 1.29 . 1.19 . 1.23 . 1.03 . 1.28 . 1.20 . 1.13 . 0.31 . 9
. -3.5 . -2.1 . -2.2 . 0.3. 3.3. 2.2 . 2.3. 4.3. 4.9 . 3.l . l.9. 0.1 . 0.9. 1.2. 0.8 .
0.6] 1.23 J.2G l.23 1.15 J.)9 1.2) ).)9 ).)5 1.23 1.29 1.23 0.6)
. 0.59 . 1.18. 1.28 . 1.25. 1.17 . 1.22 . 1.25. 1.23 . 1.18 . 1.24 . 1.29 . 1.23 . 0.62 . 10
. -3.9. -3.9. -0.7. 1.8. 1.9. 2.2. 3.0. 3.6. 2.6. l . l . -C.3. O.l. 0.5.
0.39 1.10 I.ZS I.ZS 1.23 . I.OJ 1.23 1.00 1.23 1.25 1.25 I.JO 0.39
. 0.38. I.De. 1.23. l.2*. 1.2* *. i.03. *1.z5. l.0.3. 1.26. f.25. l.25. l.10. 0.39. 11
. -1.9 . -1.9 . *i.3 . -0.* . D.7 . 2.1 . 2.0 . 2.7 . Z-8. 0.2 . D.3. 0.5. 0.5.
0.3° C.69 1.24 l.:'9 J.27 l.16 l.27 1.29 1.24 0.69 0.39
. 0.39 . 0.69 . 1.24 . 1.28 . 1.30 . 1.18 .* 1.29 . 1.29 . 1.25 . 0.70 . 0.39. 12 0.1 . -o.: . -0.5 , -o.s . 2.0 . 2.0 . l.2 . 0.5 . 0.6 . 1.1 . 0.7 .
o.39 1.10 1.23 1.19 1.25 1.19 1.23 1.(0 o.39
. 0.38 . 1.06. 1.19 . 1.23. 1.28 . 1.17 . 1.20 . 1.09. 0.39. 13
-1.6 . -3.3. *3.3 . 3.7 . l.9 . -).7 . -1.8. -0.6 . 1.0 .
0.39 0.61 1.11 0.99 l.ll 0.61 0.39
. 0.37 . 0.61 . 1.15 . 1.02 . l.09 . 0.60 . 0.38 . 14
. -3.3 . -0.5 . 3.6 . 3.3 . -l.6 . - l J . -1.8 .
STANjJAP[, 0.31 0.46 0.31 AVERAGE DEVlA1JON . 0.32 . 0.48 . 0.32 . .PCT DIFFERENCE. 15
=!.152 3.5. 3.4 . 3.5. 1. 7 SUHHARY HAP NO: s2-10-02 DATE: 10/02/89 POWER: 64%
CONTROL ROD POSITIONS: F-Q(Tl = 2.006 QPTR:
D BANK AT 160 STEPS F-dHO;J l.4e7 NW 0."917 NE 0.99e9
- F(ZJ BURl'<UP
= 1.278 115 HWD/HTU SW 1.0018 A.O. = -1. 961;:
I.
Figure 6.3 SURRY UNIT 2 - CYCLE 10 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION lOOi. POWER R p N 11 *J H G F E D C B A PREDICTED 0.32 0.48 0.32 PREDICTED MEASURED . 0.32. 0.47. 0.32. MEASURED
0.39 0.62 1.12 1.03 1.12 0.61 0.39
. 0.39. 0.61 . 1.09. 1.00 . 1.10 . 0.60. 0.39. 2
. -0.8 . -2.5 . -2.5 . -2.5 . -2.1 . -2.0 . -0.3 .
0.39 1.07 1.21 1.18 1.25 1.18 1.20 1.07 0.39
. 0.39 . 1.05, 1.15 . 1.16. 1.22 . 1.16. 1.18. 1.07. 0.40 . 3
. -1.2 . -2.7. -4.5. -2.0 . -2.3 . -1.8 . -1.6. 0.1 . 2.3.
0.39 0.69 1.22. 1.27 1.26 1.16 1.26 1.27 1.22 0.69 0.39
. 0.39 . 0.67'. 1.17. 1.24 . 1.26 . 1.14 . 1.24 . 1.25. 1.21 . 0.68. 0.39. 4
. -0.9 . -2.5 . -3.8. *2.0 . -0.5 . -1.l . -1.5 . -1.2. -0.7. -0.3. 0.2.
0.39 1.07 1.22 1.24 1.24 1.02 1.24 1.02 1.24 1.24 1.22 1.07 0.39
. 0.39 . l.Oo . 1.19 . -1.21 . 1.23 . 1.03 . 1.25 . 1.02 . 1.23 . 1.23 . 1.19 . 1.06 . o .. 39 . 5
. -0.8 . -1.8 . -2.3 . -2.0 . -1.l . 1.4. *l.O . 0.3 . -0.4 . -0,8. -2.4 . -0.8 . 1.2.
0.62 1.21 1.27 1.24 1.21 1.23 1.23 1.22 1.20 1.24 1.27 J.20 0.62
. 0.61 . 1.20 . 1.26 . l.~3 . 1.22. 1.26. 1.26 . 1.2~ . 1.21 . 1.23. 1.25 . 1.19. 0.62. 6
. -2.3 . -0.8 . -1.2 . -1.0 . 0.5. 2.8. 2.8 . 2.2. 0.6. -0.7. -J.6. -0.8. 0.2.
0.32 1.12 1.18 1.27 1.02 1.22 1.18 1.26 1.15 1.21 1.02 1.26 1.18 1.12 0.32
. D.32 . 1.10 . I.lo . 1.25 . 1.02 . 1.24 . 1.23. 1.30 . 1.19 . 1.24 . 1.02. 1.25 . 1.18. 1.11 . 0.32 . 7
. -2.4 . -2.3 . -2.3 . -1.l . -0.5. 1.6. 4.2 . 3.5 . 3.1 . 2.4 . 0.7. -1.0 . -0.4 . -0.6. -0.l .
0.48 1.03 1.25 1.16* 1.24 . 1.23 1.26 1.16 1.25 1.22 1.23 1.15 1.25 1.03 0.48
. 0.47 . 1.01 . 1.23 . 1.14 . 1.24 .. 1.25. 1.31 . 1.21 . 1.30 . 1.26 . 1.26. 1.14 . 1.25 . l.04 . 0.48. 8
. -2.4 . -2.4 . -2.3 . -1.2 . -0.l . 1.6. 4.4 . 4.1 . 3.5 . 3:3 . 1.9. -1.0 . 0.0 . 0.7. 0.7.
0.32 1.12 1.18* 1.20 1.02 1.22 1.15 1.25 1.15 1.21 1.02 1.26 1.18 1.12 0.32
. 0.32 . 1.09 . 1.15 . 1.24 . 1.02 . 1.22 . 1.17. 1.30 . 1.20 . 1.25. l.04. 1.25. 1.19 . 1.14 . 0.33 . 9
. -2.5 . -2.4 . -2.5 . -1.7 . -0.l . 0.7 . 1.7 . 3.3. 4.0 . 2.8. 1.7. -1.Z. 0.4 . 1.3 . 1.5.
0.61 1.20 1.27 1.24 1.20 1.21 1.22 1.21 1.20 1.24 1.27 1.20 0.62
. 0.60 . 1.17 . 1.24 . 1.22 . 1.21 . 1.24 . 1.25 . 1.25 . 1.23. 1.25 . 1.26 . 1.20 . 0.62 . 10
. -2.7 . -2.7 . -2.2 . -1.3. 0.5 . 1.7 . 2.6 . 3.0 . 2.5 . 1.0 . -1.0 . -0.2 . l.0 .
0.39 I .07 1.22 1.24 1.2* 1.02 1.23 I.OZ 1.24 1.24 1.22 1.07 0.39
. 0.36 . I.Cc . 1.20 . 1.22 . 1.23 . 1.03 . 1.26 . 1.04 . 1.26. 1.25 . 1.22 . 1.08 . 0.39. 11
. -1.3*. -J., . -1.4 . -1.4 . -0.2. 1.2. 2.0. *2 .. 3. 2.2. 1.2. 0.6. 0.6. 1.0.
0.39 0.69 1.22 1.27 1.26 1.15 1.26 1.27 1.22 0.69 0.39
. 0.3C . 0.60 . 1.20 . 1.26 . 1.26 . 1.16 . 1.27 . 1.27. 1.23. 0.70 . 0.39 . 12 0.0 . -0.b . -1.4 . -0.8 . -O.l . 1.0 . 1.0 . 0.5 . 0.9 . l.4 . 1.1 .
o.39 1.01 1.20 1.18 1.25 1.1a 1.20 1.01 *o.39
. 0.39 . 1.07. 1.20 . 1.17 . 1.25 . 1.16. 1.18. 1.07. 0.39. 13
. -0*.1. -0.2. -0.3. -0.4. -0.4. -1.7. -l.8. -o.s. 1.3.
0.39 0.62 1.12 1.03 1.12 0.61 . 0.39
. 0.39 . 0.62. 1.16 . 1.06 . 1.10 . 0.60 . 0.38 . 14
. -o. 2 . 1. 3 . 3. 4 . . 3. 2 . -1. 7 . -1. 8. . -1. e ..
ST A~DAPC* 0.32 0;48 0.32 AVERAGE DEVI Ai JON . 0.33. 0.50 . 0.33 . .PCT DIFFERENCE. 15
=l. 050 3.4 . 3.3 . 3.4 . 1.6 SUHHARY HAP ND: S2-l0~06 DATE: 10/09/89 POWER: 100::
CONTROL ROD POSITIONS: F-Q(Tl = l.840 QPTR:
D BANK AT 207 STEPS F -dH ( f'i) = 1.474 NW 0.9925 NE 0. 9'l89-
- C, r.'
F ( Z)
BURNUP
- -- .. *: ~*
=
1.214 315 HWD/HTU SW 0.9990 A.O. = -1.212%
SE 1.009D r -
'I I
SECTIO\ 7 REFERENCES 1.. D. A. Trace, "Surry Cnit 2, Cycle 10 Design Report-,"
Technical Report NE-657, Revision 1, Virginia Electric and Power Co~pany, August, 1989.
- 2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
- 3. "Tech~ical ~anual for*hestinghouse Solid State Reactivity Computer,"
hestinghouse Electric Corporation.
- 4. \.,". Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 19 6 7.
- 5. Surry Power Station Technical Specifications, Sections 3.12.C.l,
- 3. 12. E. 1 , and 3. 1. E. 1 .
- 6. Letter from\,. L. SLe~ar:. (\'P) to l"S\RC, "~edification of Starti.:p 11 Physics Test Program - Inspector Followup Item 280,281/88-29-01 ,
daLed December 8, 1989 .
APPENDIX STARTUP PHYSICS TESTS RESULTS AND EVALUATION SHEETS
- i::-
.\._
- **~ *-
C: -
~ r
- , Page -;
2-PT-28.11
' SVP.RY POWDl STATION UNIT Z CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EYALUATION SHEET ATTACHM!:NT*l PAC£ 1 OF 19 S:? C ; .::9 I Test
Description:
Reactivity Coaputer Checkout Reference Proc No /Section: 2-PT-28.11
- Sequence Step No: 3
. II I Bank Positions (Steps) RCS Teaperature (Of): 547
. Test ..-----------------~~~~------~ Power Level CX f.P.): O Conditions 1 SDA: 225 SOB: 225 CA: 225 Other (specify> :
(Design) / CB: 225 CC: 225 CD:
- Below Nuclear Heating I
III Bank Positions (Steps) RCS Teaperature (Of) :->Y'1, 3 Test Power Level CX f.P.): 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (Specify):
__(_A_c_t_u_a_1_)__~__c_B__ :_2_2_5______c_c_:__2_2_5___c_o_:__/~--o__~I Below Nuclear Heating Date/Tiae Test Perforaed:
l 9/1?/sr I Measured Paraaeter Pc= Meas. Reactivty using p*coaputer IV (Description) Pt= Inferred React fro* react period*
1.
Measured Value*
Test XD = - 3. 37 4 Results
_Design Value (Actual Conditions)
Design Value (Design Conditions)
.i Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/Tech Spec Not Applicable Acceptance.~--~----------------------------------------------------------
Criteria I Reference Not Applicable Design Tolerance is aet ~YES _NO VI Acceptance Criteria is .*et ..LYES _NO Comments
- At The Just Critical Position Allowable Range Completed By: Evaluated By: ~;,<<
Recoa1111ended for Approval By :
NAF Engineer Cr,-.. ,. '" *-- - ..... ,
~-?*..*-~~.l.i.
~t
. .;..icru;it!n ~
Page J oi lS SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - ARO
- Reference Pro~ No /Secti6n: 2-PT-28.11 Sequence Step No: 4 II Bank Pas it ions (Steps) RCS Tempe-ra ture (OF): 547 Test I Power Level (% F.P.): 0 Conditionsi SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ( 0 F): 54S.9 Test Power Level (% F.P.): 0 Conditions) SDA: 225 SDB: 225 CA: 225 Other (Specify):
Actual
- CB: 225 cc:. 225 CD: 225 Below Nuclear Heat in g Date/Time Test Performed:
qf,,~ 6S4~
Meas Parameter l'1 IV (Description) (CB) ARO; Critical Boron Cone - ARO i
Measured \'alue Test Results Design Value (Actual Cond.)
Design Vafoe (Design Cond) CB= 1617 +/- 50 ppm Reference NE Technical Report No. 657, Rev. 1 V FSAR/Tech S~ec aCB x CBS 15,il5 pcm Acceptance~.~~~~~~~~~-,--~~~~~~~~~~~~~~~~'---~-'
Criteria Reference UFSAR Section 14.2.5 Design Tolerance is -et ./ YES _NO Acceptance Criteria is met JYES _NO VI Comments !
I ac 8 = -7.80, pcm/ppm for preliminary analysis v'..(G: - ~.Cl. P'.M /P~"" ~ t,"-CJ Ow'\.C..~ ~\ s.
rr'* , .* ~
1.
Coitpleted By:"-, I_)'. ~-,,l-_.., Evaluat.ed By:
lest Engineer Recommended for ~/ , ,7 / #
Approva 1 By :c7 ~*'/'i/..:,,f'*
1-iAF Enginee:-
2-PT-2!:l * .i.. ...
Attacru.ient l Page 4 of 19 SEP ~ ~ 1:5.;;
SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET t
I Test
Description:
Isothermal Temperature Coefficient - ARO Reference Pree No /Section: 2-PT-28.11 Sequence Step No: !i II Bank Positions (Steps) RCS Temperature (OF): 547 Test Power Level (I F.P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating III _Bank Positions (Steps) RCS Temperature ( 0 F): ~'+f;"
Test Power Level (I F. P.): 0 Conditions SDA: 225 SDB: 225 CA: 225 Other (Specify)_:
(Actual) CB: 225 CC: 225 CD:21~/Z.1<.. Below Nuclear Heating Date/Time Test Performed:
I '1-17-?SC/
I 0 (, 03 Meas Parameter ISO IV (Description) (a T )ARO Isothermal Temp Coeff - ARO ISO Test Measured Value ( a T ) ARO = -3.'+7 pcm/°F (CB = JS°S'Oppm)
Results Design Value ISO I (Actual Cond) (a T )ARO = -'f.2S- pcm/°F (CB = /S'"iOppm)
I i
ISO Design Value I (a T )ARO = -3.88 +/- 3.0 pcc/°F (Design Cond) I. (CB= 1617 ppm)
Reference ~E Technical Report No. 657, Rev. 1
\' I i ISO +. Doo Acceptance: FSAR/Tech Spec a T S 0.79 'pcm/°F a r' = -1.71 pcm/°F Criteria Reference TS 3.1.E, NE Technical Report ~o. 657, Rev. 1 Design Tolerance is *met _: 6ts _NO VI Acceptance Criteria is met : _./"_YYES _NO Comments 1*
- Uncertainty on aTMOD = 0.5 pcm/°F (
Reference:
memorandum from C. T. Snow to E. J. Lozito dated June 27, 1980).
I Completed By: Evaluated By:
':"est Eng:.:;eer.
Recommended for Approval By
!',;AF Engineer of 58
2-PT-28.11
_ATTACHMENT l PAGE 5 OF 19 SEP O 3 :989 SURRY.POWER STATION UNIT Z CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test De~cription: Cntl Bank B Worth_Meas.,Rod Swap Ref. Bank Referem:e Proc No /Section: 2-PT-28.11 Sequence Step No: 6 II. Bank Position* CStepsl RCS Teaperature (OF): 547 Test Power Level ex F.P.>: 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (specify):
(Design) I CB:1'1oving CC: 225 CD: 225 Below Nuclear.Heating III Bank Positions (Steps) RCS Teaperature (OF): .SV6,0 Test Power Level ex F.P...>: 0 Conditions SDA: 225 SOB: 225 CA: 225 Other (Specify):
(Actual) I CB:1'1oving CC: 225 CD: 225 Below Nuclear Heating Date/Ti.lie Test Perforaed:
9/;J/?1 07.'19 I.
Measured Paraaeter I I REF ; Integral Worth of Cntl Bank B; 8
(Description)
IV I All Other Rods Out REF Test Measured Value I B =
,* Design Value REF I (Actual Conditions) I B = /36'1--= /36 ~
Des ~gn Va.lue REF (Design Conditions) I 8 = 136~ ~ 136 pea Reference NE Technical Report No. 657, Rev. 0 If Design Tolerance is exceeded, SNSOC shall evaluate iapact of' test result V FSAR/Tech Spec on safety analysis. SNSOC aay specify i
Acceptance, that add~tional testing be perforaed.
1 Criteria Reference VEP-FRD*36A Design Tolerance is aet _NO VI Acceptance Criteria ~s aet _NO Co1naents
\.
~ ~'.
Co11pleted *Evaluated B y ~ ( * -,Ajt, Reco11aended for Approval By d .n / _
--zv,:,--,,1 NAF "Engineer_
.\ ::. - ,'::; i
2-n-2t:1.1.:.
,;. t. *~a..;c,.:i~n t
?age *6 o::: ,;.
SEP G SURRY POWER STATION UN'!T 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I
- Test
Description:
Critical Boron Concent~ation - B Bank In Reference Proc No /Section: 2-PT-28.11 Sequence Step No: 7 II Bank Positions (Steps) RCS Temperature (°F): 547 Te.st Power Level (t F.P.): 0 i
Conditions 1 SDA: 225 SDB: 225 CA: 225 \ Other (specify):
(Design) I CB: 0 CC: 225 CD: 225 I- Below .Nuclear Heating III Bank Posit ions (Steps) RCS Temperature ( 0 F): Sl.{<t,.Y Test Power Level(% r:P:): O Conditions I SDA: 225 SDB: 225 CA: 225 1 Other (Specify):
(Actual) CB: 0 CC: 225 CD: 225 Below Nuclear H~ating Date/Time Test Performed:
c.,/11 R°1 12:00 Meas Parameter ?1
- IV (Description) (CB)D; Critical Boron Cone - B Bank In
' Measured Value Test Results Design Value (Actual Cond) IYOS + pp('("\
Design Value Prev (Design Cond) c8 = 1441 + 6C 8 +/- (10 + 136.4/jaC 8 j)pp*
Reference NE Technical Report No. 6~7, Rev. l V FSAR/Tech Spec aCB x Cg S 15,115 pcm Acceptance-.~~~~~~~~~~~~~~~~~~~~~~~~~~~~-
Criteria Reference UFSAR Section 14.2.5 Design Tolerance is met YES _NO Acceptance Criteria is met _YES _NO VI Comments ac 8 = -7.80 pcm/ppm for preliminary analysis Prev !'1 6CB = (CB)ARO - 1617
~t~= -~~0"7 f)t.W'I/P~M ~ ~~r'\U-[ 0.(\4~S.iS
. . :\
Completed ByL '..l"" ~.~_)
- Evaluated By: ~L~ u.:J.J~
~est Engineer 1.*:- - - : : -
- '-* ..) '
2-PT-28.ll ATTACHMENT l PAGE 3 OF 19 SEP O 5 1~a9 SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET.
I Test
Description:
HZP Boron Worth C~efficent Neasureaent Referem:e Proc: No /Section: 2-PT-28.11 Sequence Step No: 4 II I Bank Positions (Steps) RCS Teaperature (OF): 5~7 Test * ~:~~~~~~~~~~~~~~--, Power Level(~ F.P.): 0 Conditions/I SDA: 225 SOB: 225 CA: 225 Other Cspec: ify) :
(Design) I CB:Moving CC: 225 CD: 225. Below Nuclear H~ating III -1 Bank Positions (Steps) RCS Teaperature COf): S'iS' .. 1)
Test ~-~~~~~~~~~~~~~~----- Power Level CX F.P.): 0 Conditions! SDA: 225 SOB: 225 CA: 225 Other (Specify) :
(Actual) I CB:Moving CC: 225 CD: 225 Below Nuclear Heating Date/Tiae Test Perforaed:
0,/1,('iC.. OS~Y*~
I Measured Paraaeter 1*
- IV (Description) ac 8 , Boron Worth Coefficient Measured Value Test Results Design Value (Actual Conditions)
Design Value (Design Conditions) ac 8 = -7.80 ! 0.78 pea/pp*
Reference* I NE Technical Report No. 657, Rev. 0 V i FSARITech Spec I aCB x Cs $ 15, 1 15 pea Ac:c:eptanc:el Criteria Reference
- _UFSAR Sect ion 1 ~ . 2. 5 Design Tolerance is aet : )YES _NO VI Acceptance Criteria is aet : 2YES._NO Comaents Completed By: Evaluated By: futv:~ ~ -
Recou,ended for ~ ../ ~~ / /I Approval B y : ~ l/./ ,
NAF Engineer S:ar:~p ?hysics ;ests Report Page ., of Sf
2-PT-28.11 ATTACHMENT l PAGE 7 OF 19 SE? O .i '.;53.
SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSiCS TEST RESULTS AND £VALUATION.SHEET I Test
Description:
Cntl Bank D Worth l'feasureaent*Rod Swap Referen*ce Proc No /Section: 2-PT.-28.11 Sequence Step No: 9 I II Bank Position* (Steps)
I RCS Teaperature (OF): 547 Test Power Level CX F.P.): 0 I SCA: 22S SOB: 225 CA: 225 Other (specify):
i Conditions (Design) CB:Moving CC: 22S CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Temperature COF): s:YSi9 /
t Test Conditions .SCA: 22S SOB: 22S CA: 225 Power Level CX F.P.): 0 Other (Specify):
.(Actual) CB:Hoving CC: 22S CD:Moving1 Below Nuclear Hea~ing l Date/T~e Test Performed:
9/17/t f /3.' 3 6
' IV Test Meas Paraaeter (Description)
Measured Value RS Io ; Int Worth of Cntl Bank D-Rod Swap I RS. = /!S'S-D (Adj. l'feas. Crit. Ref Bank Position = /8/ steps)* /
Results I Design Value (Adj. Meas. Crit. R~f Bank
- RS /
(Actual Cond) Io = /!/l!/6'8 Position =/t?/ steps)
RS Design Value
- Io= (Critical Ref Bank (Design Cond) * ~osition = 179 steps)
Reference *1 NE Technical Report No. 657, Rev. 0, VEP-FRD-36A, I NFO-TI-2.2A
- If Design Tolerance is exceeded, SNSOC shall evaluate iapact of test result on V FSAR/Tech Spec safety analysis. SNSOC aay specify that Acceptance additional testing be perforaed.
Criteria Reference VEP-FRD-36A Desigri.Tolerance is aet .LYES _NO VI Acceptance Criteria is aet /_'YES _NO Co1aaents, I
(
Co111pleted By:\, ; ,' ,\ \ II -
~__ '
_.,, Evaluated B y ~ ~
1
~est En gineer I Reco111aended for ~ -.........1 1 .,* , (';'--
Approval By : ~ 1'- ~
NAF' Engineer
2-PT-28.1 l AT'.I'ACKMENT l PAGE 8 OF 19 SEP O J 1sa9.
SUllRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET.
I Test
Description:
Cntl Bank C Worth Neasure*ent*Rod Swap Refererrce Proc No /Section: 2-PT-28.11 Sequence Step No: 10 II Bank Positions CStep1) RCS Te*perature COf): S'41 Test Power Level (X F.P.): 0 Conditions SDA: 22S SDB: 22S CA: 22S Other (specify):
(Design) CB:Moving CC:Moving CD: Z25 Below Nuclear Heating III Bank Positions <Steps> RCS Teaperature (OF): S'Yb,7 ./
Test Power Level C:C F.P.): 0 Conditions SDA: 225 SOB: 22S CA: 22S Other CSpedfy):
CActual) CB:Moving CC:Moving CD: 225 Below Nuclear Heating Date/Tiae Test Perforaed:
9/17/!9 /~.' i. '> ,,.
Meas Paraaeter RS (Description)
- Ic i Int Worth of Cntl Bank C-Rod Swap IV I RS *(Adj. Meas. Crit. Ref Bank Test Measured Value j Ic = 7g/, '-I Position =/:2.3 steps) /
Results i Design Value RS ,.,,r D -f . ( Adj . Meas. Crit. Ref Bank /
! ( Actual Cond) Ic = 7 - Ill Position = /23 steps)
RS : 31 , /
- Design Value Ic = ~ ~ ~ p c * (Critical Ref Bank i (Design Cond) B~-1.7*c,?/ t\\ Position= 12S steps)
Reference NE Technical Report No. 657, Rev. 0, VEP-FRD-36A, HFO-TI -2. 2A
.If Design Tolerance is exceeded, SNSOC I shall evaluate impact of test result on V
- FSAR/Tech Spec I safety analysis. SNSOC may specify that Acceptance! additional testing be perforaed.
Cri.*te. ria r------------------------1------------------------------------------------------------------
Reference
- I VEP-FRD-36A Design Tolerance is aet ~-NO VI Acceptance Criteria is aet _YES _NO Coa11ents Co111pleted By~!\\~~) *,
\Test Engineer
< Evaluated By~,_.,/011/!
I Rec:o,wmended for ,/1 ~ -..... l l ,* t I Approval By fuk:- ~ ~ ' - " ' -
NAF Engineer
- ;age .:.9 of SE
.2-PT-28. ll ATTACHMENT .1 PAGE 9 OF 19
- SEP O S a89 SURRY POWER STATION UNIT Z CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I . Test
Description:
Cntl Bank A Worth Measureaent-Rod Swap Referem:e Proc No /Section: 2-PT-28.11 Sequence Step No: ll.
II Bank Positions (Steps) RCS Teaperature (OF): 5q7 Test Power Level (X F.P.): 0
- conditions I SDA: 225 SOB: 225 CA:Moving Other (specify):
(Design) CB:Moving CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps} RCS Teaperature COF): .sY6, 2- **
Test Power Level CX F.P.): 0 Conditions SDA: 225 SOB: 225 CA:Moving Other (Specify):
(Actual) CB:11oving CC: 225 *co: 225 Below Nuclear Heating Date/Tiae Test Perforaed:
9/;7/?9 1s:17 ,
Meas Paraaeter RS (Description) IA ; Int Worth of Cntl Bank A - Rod Swap IV (Adj. Meas. Cr~t. Ref Bank Test Measured Value Position = 7'-/ steps) /
Results.
I Design Value RS (Adj. Meas. Crit. Ref Bank I (Actual Cond) IA = .3 6 / +/- /00
- Position = 7~ steps) i RS °311 I Design Value IA = ~ t 100 pea (Critical Ref Bank /
I (Design Cond)
I 66! 1 7s::.rf Position= 84 steps)
J NE Technical Report No. 657, Rev. 0, VEP-FRD-36A, j NFO-TI-2.2A I If Design Tolerance is exceeded, SNSOC I I shall evaluate iapact of test result on V i FSAR/Tech Spec
- 1' safety analysis. SNSOC aay specify that Acceptance I additional testing be performed.
Criteria I Reference VEP-FRD-36A I Design Tolerance is met* .Z.Es _NO VI 1Acceptance Criteria is **t LYES _NO Coaaents
\ .. \ *.~ ..
Co11pleted B y : , . _ _ ; 1 , ~ * ~ Evaluated By:
9est Engineer I Reco11111ended for
- r---J r-, , * , 0 Approval By : ~:::s;\.......- r ..... ~~
NAF Engineer
- ?age 50 of 58
., 2..;PT-28, ll ATTACHMENT l
' PAGE _10 OF 19 I
ReferNTce suu~* POWEil STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET Test Descriptiori: Shutdown Bank B Worth Meas. - Rod Swap Proc No /Section: 2-PT-28 .11 SEP O ,3 :S:9
- Sequence Step No: 12 II I Bank Positions (Steps) RCS Teaperature (OF): 5q7 Test ! - - - - - - - - - - - - - - - Power Level (~ F.P.): 0 Condit ions I SDA: 225 SDB:Moving CA: 225 Other (specify) :
(Design) j CB:Moving CC: 22S CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Teaperature COF): SC.,"'. i Test Power Level (X F.P.): 0 Conditions! SDA: 225 SDB:Moving CA: 225 Other (Specify):
(Actual) I CB:Noving CC: 225 CD: 22S Below Nucle&r Heating I
Date/Tiae Test Perforaed:
Cl. f ,, I ~9 11o*.. ?.,
_Meas Para.aeter RS (Description) I 58 ; Int Worth of Shutdown Bank 8-Rod Swap IV RS (Adj. Meas. Crit. Ref Bank Test Measured Value Isa = 1051...\ Position = l(t~ steps)
Results. I_
Design Value RS (Adj. Meas. Crit. Ref Bank
.( Actual Cond) IsB = c,qo:: IY~ - Position = 1(&'1 steps>
RS q99_
Design Value IsB = ~ !: 1--$8 pc* (Critical Ref Bank ,, .
I (Design Cond) '1""(7>-tl~ 1'-\q Position= 160 step~)
\ Reference NE Technical Report No. 657, Rev. 0, VEP-FRD-36A, I
l NFO-.TI-2 .2A If Design Tolerance is exceeded, SNSOC shallevaluate illpact of test result on V FSAR/Tech Spec safety analysis. SNSOC **Y specify that Acceptance additional testing be perforaed.
Criteria Reference VEP-FRD-36A Design Tolerance is *et ./YES _NO VI Acceptance Criteria is aet ~YES _NO Co111111ents Completed Evaluated By: Bw~~'--
,,-,---7 C Reconended for /_::--/~ ;1(7;;""'~~
Approval By r.__,D:::[.....u ,, I
. ~ F Engineer
\E-75; S2ClG S:ar:~? ?hysics Tests Report Page :1 of 51.3
2-PT-28. U I ATTACHMENT 1 PACE 11 OF 19 SE? O *.-:~
SUllRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
}
I Test
Description:
Shutdown Bank A Worth Neas. -_ Rod Swap Referem:e Proc No /Section: 2-PT-28.11 Sequence Step No: 13 II Bank Positions (Steps) RCS Telliperatur* (OF): 51f7 Test Power Level ex F.P.>: 0 Conditions SDA:Noving SOB: 225 CA: 225 Other (specify):
(Design) CB:P1oving . CC: 225 CD: 225 Below Nuclear Heating III Bank Positions (Steps) RCS Teaperature (OF): 5','Si 7 /
Teat Pow~r Level ex F.P.>: 0 Conditions SDA:Noving SOB: 225 CA: 225 Other (Specify):
(Actual) CB:P1oving CC: 225 CD: 225 Below Nuclear Heating Date/Time Test Perf~raed:
~ /17 /~c... 11c;7.<.c, 11eas Paraaeter CDescription)
I. IsA; I
RS Int Worth of Shutdown Bank A-Rod Swap IV RS . (Adj. Neas. Crit. Ref Bank
/
- Test Measured Value IsA = /0/9 f'V"'" Position =/.S-8 steps)
Results Design Value RS (Adj. Neas. Crit. Ref Bank
/
/ CActual c'ond) Is A =/018:. /6"'2.. Position =; S-8 steps)
RS ICl.3 1
Design Value IsA = ~ t '"5-7'" pc* (Critical Ref Bank II (Design Cond) (JOJ--)7.cfl \bl Position= 172 steps)
! Reference NE Technical Report No. 657, Rev .. 0, VEP-FRD-36A,
! NFO-TI-2.2A
/
If Design Tolerance is exceeded,* SNSOC shall evaluate illpact of test.result on V FSAR/Tech Spe*c safety analysis. SNSOC aay specify that Acceptance: additional testing be perforaed. _
Criteria I Refere::ice VEP-FRD-36A Design Tolerance is aet ./YES _NO VI Acceptance Criteria is aet _L'.'.'YES _NO Co11aents
/
Col'lpleted By:
Recoa11ended for Approval By : 4,[;'{. li;9J c -
NAF Engineer
\ ....... - ---
, - S2Cl0 Startup Physics Tests Repo~t ?age 52 of 58
2-PT*.28, 11 AnACHMENT 1 PACE 12 OF 19 SURRY POWER STATION UNIT 2 CYCLE 10 STARTlTP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test
Description:
Total*Rod Wor~h - Rod Swap Referem:e I Proc No /Section: 2-PT-28. 11 Sequence Step No: 14 I
II Bank Positions (Steps) RCS* Teaperatur* (OF): 5q7 Test Power Level (X F.P.): 0 Conditions SDA:Moving SDB:Moving CA:Moving Other (specify):
(Design) CB:Moving CC:l'loving CD:Moving Below Nuclear Heating III Bank Positions (Steps) RCS Teap~rature (OF): SYS.7 Test ~. ------------------------------~ Power Level C~ F.P.): 0
. I Conditions,SDA:Moving SDB:Moving A:Moving c_ Other (Specify):
(Actual) CB:Moving CC:l'loving CD:l'loving B~low Nuclear Heating I
- 1
- Date/Tiae Test Perforaed:
C?/i1/9:,9 "l~\9 I
Meas Paraaeter I (Description) !Total; Int Worth of All Banks* Rod Swap IV Test I .Measured Value Results Design Value j
1 (
I Actual Cond) 1Total = seoso + seos
[ Desigr1 Value
/
(Design Cond)
Reference NE Technical Report No. 657, Rev ..0, VEP*FRD*36A, NFO*TI-2. 2A tf Design Tolerance is exceeded, SNSOC shall evaluate iapact of test result on V f'SAR/Tech Spec safety analysis. SNSOC aay specify that Acceptance: additional testing be perforaed.
Criteria I. Reference VEP*F'RD*36A Design Tolerance is aet J YES _NO VI Acceptance Criteria is aet ...::LYES _NO Co1111nents Coapleted By: i,
! \
-i il~l.\
\;~
- . *L.
- Evaluated By:
~efo't.Engineer
. Recoaaended. for ~ - ; J Approval By r µ,,-
r:v:71 /J
_, /,Y../
.__.,...... NAF Engineer
\'t:" - "';-: - ~::18 S:art~o Physics Tescs Recort Page of ~b
.'\ . . . . . . . -1.
2-n-20.li.
A.T'!ACHMEi*IT l
?AGE lJ OF 19
....... J : ;~as -
SUJUlY POWER STATION UNIT 2 CYCLE 10 .,_.
STARTt!J' PHYSICS TEST RESULTS AND EVALUATION SHEET I :Test
Description:
11/D Flux Map - Low power Reference ?roe: No/ Section: 2-PT-28.2, 2-0P-57 Secru,enc:e Step Ho:l-1 II Bank Positions <Steps) RCS Teaperature {Of):TREF ~,
Test Power.Level Cr. F.P.): <30 Conditions1 SDA: 22S SDB: 225 CA: 22S Other (specify)
(Design) CB : 225 cc :
- CD:
- Must have~ 38 thimbles III Bank Positions (Steps) *r RCS Temperature COF) : ~eF i - - - - - - - - - - - - - - - - Power Level CX F. P. ) : 3070 Test -
Cond:i.tions 1 SDA: 225 SOB: 225 CA: 22S I Other (Specify):
(Actual) I CB : 22S cc : 22..5' CD: /1.:,(.:,
Date/Time Test Perforaed:
1
'4 2 'T't-\- 1,\1\ d L:S MM"::. 'S."'2.-10 --o(
'1 hci~ 0'141 MAX. REL NUC ENTHALITOTAL HEAT' QUADRANT IV 11eas Paraaeter ASSY PWR RISE HOT j FLUX HOT POWER TILT (Description) X DIFF CHAN FACT CHAN FACT I RATIO (M*P).IP F*clHCN) F-~CT) QPTR I
Test 11easured Value 2-20'3 I /.0 IS° Results I~
Design Value (Design Conds) NA NA 1.020 WCAP-790S _WCAP-7905
. Reference I REV. 1 NONE NONE I REV. 1 I
FSAR/Tech Spec I NONE . I'-1.*1t* ... ,.,,.
I . : T .
V I 1
1 '*'_
11
,- ..... * ,u, I NA Acceptance...--------.,;_ : _ _..;...._...:.;.
1-. _ _ _ _ _ _...._____________
Criteria I Reference NONE ! TS 3. 12 TS 3. 12 TS 3. 12
' Design Tolerance is aet ./YES _NO Acceptance Criteria is aet 7YEs _No
- As Re(fliired Co11pleted By:\,
1---..,
I i l I\?, f\ln:'s o'l Evaluated. By:
1)es't Engl.lleer
.Recoaaended f o r ~ ~
~
Approval By :
NA Engl.lleer .
\E-757. S2C:0 5:3::~~ ?~ysics Tests Report Page )- of SE
I 2-P'!'-28.11 ATTACHMENT l PAGE 15 OF 19
- I Reference SURRY *POWER STATION UNIT 2 CYCLE io STARTUP PHYSICS TEST. RESULTS AND EVALUATION SHEET Test Descri6tion: M/0 Flux Map-At Power Proc No/ Section: 2-PT-28.2, 2-0P-57 Sequen~e Step N~:44 II Bank Positions (Steps) RCS Temp~rature C°F):TREF !1 Test Power Level CX F.P.): - 70 Conditions, SCA: 225 SDB: 225 CA: 225 Other C specify):
I
( o*esign) CB : 225 CC : 225 CD: z Must have~ 38 thimbles III Bank Positions (Steps) RCS Teaperature( OF): 'Re..=
Test Power Level CX F. P. ) : fo'f'r...,
Conditionsi SDA: 225 SOB: 225 CA: 22S Other CSpecify):
(Actual) ' CB : 22S CC : 225 CD: 1£1,u
'f 2. T rt I t"'18L£. S Date/Tiae Test Perforaed:
M.AP -s2. 02.
. , c /7- /E9 05'2.t
, MAX. REL NUC ENTHALITOTAL HEATI QUADRANT i
IV 1 Meas Paraaeter! ASSY PWR RISE HOT FLUX HOT :POWER TILT (Description) I* X DIFF CHAN FACT CHAN FACT ' RATIO I (11-P)/P F*dHCN)
F-QCT) QPTR
. -f.'i 1.. '
I~ P;2.o.4 I Measured Value I_ 3.'1'1- . I. l.j.(: 7 2.000 /.00'1~
Test Results 1 ~ Pi'"- o.'1 I Design Value I "
I 1
,a fn
."1"-*,-* 1
- I*1 t( 'I.I
- ' I (Design Concls) NA I HA ~ 1.02 iwcAP-7905
I iWCAP.,7905 Reference REV. 1 NONE NONE REV. 1
.. i, i *1 *
, .-,.u, , *. ,n*P*
- 1 r1rusa.ll.n'
- 1eu 1
V *FSAR/Tech Spec: i NOHE i. *
- 1 NA 1
Acceptance'.*
Criteria I I Reference NOHE TS 3. 12 TS 3. 12 TS 3. 12 I
Demign Tolerance is aet Acceptance Criteria is *et VI Coa11ents z As Required Coapletecl By: Evaluated By: S70...*~
Recoaaended !or Approval By * : (O~f NAF Engineer t:" - - - S2Cl0 Start~p Physics Tests Report Page 55 of 58
.\ - - I::; I
l cl v 2*?'!'*28.11 A T!ACID-!ENT 1 PAGE 16 OF 19
- SE? .~. . ::53
' SURRY POWER STATION UNIT 2 CYCLE io STARTUP PHYSICS TEST RESULTS AND EVALUATION SHtET
.I Test Desc:~ipti~n: M/0 Flux Map-At Power.NI Calibration Reference Proc: No/ Section: 2-PT-28.2, 2-0P*S7 Sequence Step No:u5 II Bank Positions (Steps) RCS Temperature C°F):TREF ! i Test Power Level (~ F,P.): - 70 Conditions 1 SDA: 22S SOB: 22S CA: 225 Other <specify): *
(Design) ! ca : 22s cc : 225 CD: z:.
III Bank Positions (Steps) RCS Teaperature( OF): l~E.I=
Test I I Power Level CY. F.P.): <<o'fo/0 Conciitions1 SDA: 225. SDB: 225 CA: 225 i _Other CSpec: ify) :
(Actual) CB : 225 CC : 225 CD: I "10 . Q\..:A'<'Tc.Z.. Uo<E. 1,..iPR 2 l T"HrJ.1BL-2;;
Date/Time Test Perforaed:
1-,,\~P ......;i-Z..-1G**C3 Io I z.: /Sc; i MAX. REL I NUC ENTHALITOTAL HEATI .QUADRANT IV Meas Para111eter1 ASSY ?WR RISE HOT ! FLUX HOT !POWER TILT (Description) I. ~ DIFF .. CHAN FACT. , CHAN FACT i
- RATIO I
CM*P)/P I *F*dHCN) . F*QCT) QPTR I I Measured Value1 t-JA NA N A.
Test I Results I I Design Value I *,.. ,_ ,. 1 ,., I (Design Conds), '"*,u* *- *~ .... ,
._.-.., NA NA ~ i .02
\WCAP-7905 :wcAP*79os Reference ' REV. i NONE NONE REV. i V FSAR/Tech Spec::
NONE I **-, ...11*. 11,.,,, I ,,11,111.-
' * "'" I NA 1
Acceptance Criteria Reference I NONE TS 3. 12 TS 3. 12 TS 3. 12 II
/, .
~~ -_NO Design Tolerance is aet : NO Ac:c:eptance Criteria is aet :
VI Coaaent;s z Must have at least 38 thiables for a full-core flux **P, or at least 16 thi..ables for a quarter-core flux map.
zz As Required
. /) .
Co*pleted By: Evaluated By: *S.771. .*~
Rec:0111aended for fC~/
Approval By :
NAF Engineer
\E-75; S2C10 Startuo Physics Tests Report Page 56 of 58
.I ;, , . 2-?T-23. :~
A7iACfillENT PAGE li OF :9
-~-
- SURRl' POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Te~t Descri~tioti: M/D Flux Map-At Power.NI Calibration Reference Proc No ,*section: 2*PT*2S.2, 2-0P-57 Seq~ence Step No: ~6 II Bank Positions (Steps)
- I RCS Temperature (OF):TREF :1 Test - - - - - - - - - - - - - - - - Power Level(X F.P.): - 70.
Conditions_ 1 SDA: 225 SOB: 225 CA: 225 Other (specify): z CDesign) CB : 225. CC : 225 CD: **
III Bank Positions (Steps) RCS Teaperataxe( :>f): T1tE.F Test Power L.evel CY. F. P . ) : ~*"lo Conditionsi SOA:. 225 SOB: 225 CA: 22S Other CSpecify) :
.(Actual) ! i:B : 225 tc : 225 CD: 1'10 QuARTe.e G.:.-.<E MA.P Date/Time Test Perforaed:
2l 'lHt~8L..£S 1319 M~P ~2..- re- o+
11AX. REL i NUC ENTHALITOTAL HEATI QUADRANT IV I Neas Paraaeter1 ASSY PWR RISE HOT I FLUX HOT :POWER TILT (Description) r. Dif'F' I CHAN FACT icHAH FACT RATIO I
I I
Cl1*P)/P F-clHCH) F-QCT) QPTR i - ! i i
11easured Value I1 i Test N.A N~ "-i I\ NA Results I
Design Value 1 *1 1'"U** t w*l , (
1 1 1,.,
.I (Design Conds) " 1
- _ _ ....,_,
I I NA I NA ~ i. 02 Reference IWCAP-7905
- REV. i 1*
NONE*
.I NONE iWCAP-7905 REV. 1 I
I II . r I ,lil:U.UC1*.Ht*PII* I ,,,ua.u.,,,,
' ,*111, 1 V FSAR/Tech Spec1 NOflE NA Acceptance.
Criteria !
i Reference NONE TS 3 .12 TS 3. 12 TS 3 .12 Design Tol~rance is aet VYES _NO Acceptance Criteria*is aet /YES _NO
- . Must have at least 38 thimbles for a full-core flux 11ap, or at least 16 thiables for a quarter-core flux map.
- As Required Evaluated By:
Recoaaended for
~pproval By :
\E-757 S2Cl0 Startup Physics Tests Report Page 57 of 58
2-PT-28.ll
- ,l' ' ATTACHMENT l f PAGE 18 OF 19
",*- -:i .
~~* "" -,.I IJ~W SURRY POWER STATION UNIT 2 CYCLE 10 STARTUP PHYSICS
. . TEST RESULTS AND EVALUATION SHEET I Test
Description:
M/D Flux Map - HFP, ARO; Eq. Xe Reference Proc No/ Section: 2-PT-28.2, 2*0P~S7 Sequence Step No:47 II Bank Positions (Steps) RCS Teaperature (OF).:TREF !1 Test Power Level (~ F.P.):95 ~ 5 Conditions1 SCA: 225 SOB: 22S CA: 225 Other (specify): Eq. Xe.
(Design) i CB : 22S cc : 22S CD: z Hust have~ 38 thiables a
III Bank Positions CSteps) 'Res Teaperature(OF): ,.~~
Test Power Level C~ F.P.): 100?0 Conditions, SDA: 22S SDB: 22S CA: 225 Other (Specify):
(Actual) I
- CB : 22S cc : 22S CD: 2.07
. '-t ( 'l"'H-\1"\~~':,
Date/Time Test Performed:
ro(qlg'l \-+:2.7 IV
. I MAX.
Paraaeter1 ASSY REL PWR I
NUC ENTHALiTOTAL HEATI QUADRANT RISE HOT FLUX HOT POWER TILT
' Meas i
I (Description) I*
~ DIFF CHAN FACT CHAN FACT RATIO
- 1 I
I i I
CH-P)/P F-dHCN) F-QCT) QP'.l"R i
I
- 1 Measured , *~'"-10 /.O l 0 Test Results Design vaiue *1 *I .
1D '1 I,.,
. -tw ,, f I ,I CDesign Conds) "1 * - * .__, NA NA ~ 1.02 lwCAP-7905 I lwCAP-7905 Reference ' REV. 1 I
NOHE NONE REV. 1 V , FSAR/Tech Spec!
I NONE .I **-**-*"*...... i *:*-*- * ... ; NA Acceptance.-------------------------------------------------------------------------------------
Criteria '1 Reference *NONE TS 3. 12 TS 3. 12 TS 3 .12 I*
I Design Toleran~e is aet ~YES _NO j Acceptance Criteria is aet ...::::..n:s _NO 11: As Required Coopleted BY, q \£), \,l .,
st Engl.lleer
~ .~ Evaluated By:
Reco11aended for Approval By
\E-757 S2Cl0 Startup Physics Tests Report
- Page 58 of 58