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Cycle 14 Startup Physics Test Rept. W/960830 Ltr
	ML18151A976
Person / Time
Site:	Surry
Issue date:	08/13/1996
From:	Clemens C, Lawrence D, Psnik T; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Ebneter S; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	96-420, NE-1082, NE-1082-R, NE-1082-R00, NUDOCS 9609100125
	Download: ML18151A976 (59)
	v • d • e

.I I TECHNICAL REPORT NE-1082 - Rev. 0

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suRRY UNIT 2, CYCLE 14 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING AND SERVICES VIRGINIA POWER AUGUST 1996 I

.I PREPARED BY: t.JJ. ~ ~80 C. D. Clemens Date Bl if,~

Date

1 APPROVED BY: _ / ~ - ~~

~ d o s ~... Date I

I QA Category: Nuclear Safety Related Keywords: SPS2, S2C14, Startup I'

I

I I CLASSIFICATION/DISCLAIMER I

The data, -techniques, information, and c<;mclusions 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 their accuracy, usefulness, or applicability. In particular, THE I COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR I PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, I 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 herein.

whatsoever liability and disclaimers of warranties provided In no event shall the Company be liable, under any legal theory (whether contract, tort, warranty, or strict or absolute I liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out I of the use, authorized or unauthorized, of this report or the data, Ii techniques, information, or conclusions in* it.

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I TABLE OF CONTENTS I

I PAGE Classification/Disclaimer .............................. . 1 Table of Contents ..................... *................. . 2 List of Tables ......................................... . 3 List of Figures ........................................ . 4 Preface ................................................ . 5 I Section 1 Section 2 Introduction and Summary ......... ~ ........ .

Control Rod Drop Time Measurements......... 16 7

I Section 3 Control Rod Bank Worth Measurements ....... . 21 Section 4 Boron Endpoint and Worth Measurements ..... . 26 Section 5 Temperature Coefficient Measurement ....... . 30 Section 6 Power Distribution Measurements ........... . 32 Section 7 References ................................ . 39 APPENDIX Startup Physics Test Results and Evaluation Sheets ....................... . 40 I

NE-1082 S2C14 Startup Physics Tests Report Page 2 of 56 I

I LIST OF TABLES

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TABLE TITLE PAGE

1. 1 Chronology of Tests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2.1 Hot Rod Drop Time Summary............................. 18 3.1 Control Rod Bank Worth Summary........................ 23 4.1 Boron Endpoints Summary~****************************** 28 5.1 Isothermal Temperature Coefficient Summary............ 31 6.1 Incore Flux Map Summary............................... 34 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits...................... 35

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NE-1082 S2Cl4 Startup Physics Tests Report Page 3 of 56

,I LIST OF FIGURES I

FIGURE TITLE PAGE I

1. 1 1.2 Core Loading Map ........................................ .

Beginning of Cycle Fuel Assembly Burnups ................ .

11 12 1*

1. 3 Incore Thimble Locations ................................ . 13 ,.1:*

1.4

1. 5 Burnable Poison and Source Assembly Locations .......... .

Control Rod Locations .................................... .

14 15

2. 1 Typica 1 Rod Drop Trace .................................. . 19 2.2 Rod Drop Time - Hot Full Flow Conditions ................ . 20 I.

3.1 3.2 Bank B Integral Rod Worth - HZP ......................... .

Bank B Differential Rod Worth - HZP ............... *...... .

24 25 I*

4. 1 Boron Worth Coefficient ................................. . 29 I.

6.1 6.2 Assemblywise Power Distribution - 24% Power ............. .

Assemblywise Power Distribution - 71% Power ...... , ...... .

36 37

,I 6.3 Assemblywise Power Distribution -100% Power ............. . 38 1*

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,1 I* PREFACE

,I This report presents the analysis and evaluation of the physics tests which were performed to verify that the Surry 2, Cycle 14 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 techniques and methods of data analysis were used. The test data, results, and evaluations, coupled with the deta1led startup procedures, are on file at the Surry Power Station. Therefore, only a cursoJ"y I discussion of these items is included in this report. The ... analyses presented include a brief summary of each test, a comparison of the test I results with design predictions, and an evaluation of the results.

The Surry 2, Cycle 14 Startup Physics Test Results and Evaluation I Sheets are included as an appendix to provide additional information on I the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test I, conditions (actual), 4) t~st results, 5) acceptance criteria, and 6)

I comments concerning the test.

the startup test results in These sheets provide a compact summary of a consistent format. The design test I conditions and design values at these design conditions for the measured parameters were completed prior to the startup physics testing. The I entries for the design values were based on the calculations performed I by Virginia Group 1

Electric and Power Company's Nuclear Analysis and During the tests, the data sheets were used as guidelines both Fuel I

to verify that the proper test conditions were met and to facilitate the NE-1082 S2Cl4 Startup Physics Tests Report Page 5 of 56

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preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the I

tests. ,I 1*

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,, SECTION 1

,I INTRODUCTION AND

SUMMARY

'I On May 3, 1996 Surry Unit 2 shut down for its thirteenth refueling.

I During this shutdown, 69 of the 157 fuel assemblies in the core were replaced with 60 fresh assemblies, 1 once-burned assembly, and 8 twice-burned assemblies. The Cycle 14 core consists of eight sub-batches of fuel: two fresh batches (batches 16A and 16B); three once-burned

1. batches, two from Cycle 13 (batches ISA and 15B) and one from Surry 1 Cycle 13 (batch Sl/lSA); and three twice-burned batches, two from Cycles

'I 12 and 13 (batches 14A and 14B) and one from Cycles 11 and 12 (batch 13B).

I, The core loading pattern and the design parameters for each sub-batch are

,. shown in Figure 1.1.

given in Figure 1. 2.

Beginning-of-cycle (BOC) fuel assembly burnups are The incore thimble locations available

during

1 startup physics testing are identified in Figure 1. 3. Figure identifies the location and number of burnable poison rods and secondary 1.4 I, source locations for Cycle 14, while Figure 1.5 identifies the control rod locations.

1 The Cycle 14 core achieved initial criticality at 1756 on June 5, 1996. Startup physics tests, with the exGeption of hot rod drops, were I performed after criticality as outlined in Table 1.1. Hot rod drops were

'I performed prior to criticality.

follows.

A summary of the physics test results I 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. The reference control rod bank was measured with the dilution I

method, and the result was within 0.7% of the design prediction. I Individual control rod bank worths were measured using the rod swap technique 2 ' 3 and all results were within 4.0% of the design I,

predictions. The sum of the individual measured control rod bank worths was within 1.4% of the design prediction. All results were I

within the design tolerance of +/-15% for individual bank worths I

(+/-10% for the rod swap reference bank worth) and the design tolerance of +/-10% for the sum of the individual control rod bank

',I worths.

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3. Measured critical boron concentrations for two configurations were within 19 ppm of the design predictions.

control bank The I

all-rods-out (ARO) result was within the 50 ppm design tolerance, I and met the Technical Specification 4.10 .A criterion that the overall core reactivity balance shall be within +/-1% tk/k of the I design prediction. The reference bank concentration was within its design tolerance.

in critical boron I

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4. The boron worth coefficient measurement was within 0.6% of the design prediction, which is within the design tolerance of +/-10%. I

5. The measured isothermal temperature coefficient (ITC) for the ,I, all-rods-out configuration was within 0.92 pcm/°F of the design prediction. This result is within the design tolerance of +/-3 I

pc~/ °F.

temperature The measured ITC was -0. 6 7 pcm/ °F.

coefficient (-1.67 pcm/°F) and When the Doppler a 0.5 pcm/°F I

uncertainty are accounted for in the +6.0 pcm/°F MTG limit of the I NE-1082 S2C14 Startup Physics Tests Report Page 8 of 56 I

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,1 Core:;, Operating Limits Report (COLR) Section 2, 1, the MTC I requirement is satisfied as long as the ITC is less positive than

3. 83 pcm/°F.

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6. Measured core power distributions were within established I . acceptance criteria and COLR limits. The average . relative I assembly power distribution measured/predicted percent difference was 2.1% or less for the three initial power ascension flux maps.

f The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N), were within the limits of COLR Sections

.1: 2.3 and 2.4, respectively. Note that since there are no LOPAR

1 assemblies in this cycle, the FdH limits for all assemblies are the same.

I In summary, all startup physics test results were acceptable.

I Detailed results, specific design tolerances and acceptance criteria for each measurement are presented in the following sections of this repor~.*

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Table 1.1 SURRY 2 - CYCLE 14 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS I,

Reference 1*

Test Date Time Power Procedure Hot Rod Drop - Hot Full Flow.*~

Zero Power Testing Range .......

Reactivity Computer Checkout ...

6/04/9_6 6/05/96 6/05/96 0050 2012 2054 HSD 2-NPT-RX-014 HZP 2-NPT-RX-008 HZP 2-NPT-RX-008 I

Boron Endpoint - ARO ...........

Boron Worth Coefficient - ARO ..

Temperature Coefficient - ARO ..

6/05/96 6/05/96 6/05/96 2250 2250 2351 HZP 2-NPT-RX-008 HZP 2-NPT-RX-008 HZP 2-NPT-RX-008 t*

Bank B Worth ...................

Boron Endpoint - Bin ..........

Bank D Worth - Rod Swap ........

6/06/96 6/06/96 6/06/96 0109 0445 0551 HZP 2-NPT-RX-008 HZP 2-NPT-RX-008 HZP 2-NPT-RX-008 I

Bank C Worth - Rod Swap ........ 6/06/96 0623 HZP 2-NPT-RX-008 Bank A Worth - Rod Swap ........

Bank SB Worth - Rod Swap .......

6/06/96 6/06/96 0725 0810 HZP HZP 2-NPT-RX-008 2-NPT-RX-008 1*

Bank SA Worth - Rod Swap .......

Flux Map - 24% Power ...........

Peaking Factor Verification 6/06/96 6/08/96 0846 0043 HZP 2-NPT-RX-008 24.3% 2-NPT-RX-002 2-NPT-RX-008

,f;

& Power Range Calibration Flux Map~ 71% Power ........... 6/09/96 0640 71.0% 2-NPT-RX-002 Peaking Factor Verification

& Power Range Calibration Flux Map -100% Power ...... ~**** 6/13/96

1000 2-NPT-RX-008 100 .1% 2-NPT-RX-002 I

Peaking Factor Verification

& Power Range Calibration 2-NPT-RX-008 1*

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Figure 1.1 SURRY UNIT 2 - CYCLE 14 CORE LOADING KAP I R p H

" L K J H G F E D C B A I I 148 I 5W8 I 148 I 5WO I l3B I 5VB I l6B I 3Y3 I l4B I l3B I 4W5 1:;:I 6VZ I 158 I 5Xl I 168 I 3Y8 I

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ZZ59Z 39630 30496 35383 17303 15559 0 0 I

ASSEHBLY TYPE 15xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5 15Xl5

,, NUHBER OF ASSEHBLIES FUEL RODS PER ASSEHBLY Z04 l 8 204 lZ 204 zo 204 Z8 Z04 Z8 204 3Z 204 Z8 204 I

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,I Figure 1.2 1-I R p N SURRY UNIT 2 - CYCLE 14 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS L IC J H C F E D C B A I 5W8 I 5V8 I 4W5 I 6V2 I l,39.191 35.111 39.471 I 5WO I 3Y3 I 5Xl I 3Y8 I 4W8 I 6W4 I l

2 1:

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.I I 33.471 0.001 16.191 0.001 11.011 0.001 11.s11 0.001 17.141 0.001 16.041 0.001 33.261 I 3V5 I 5Y7 I 3X7 I lYl I 2X3 I 2Y6 I 1X2 I 3X5 I 1X4 I OY3 I OX9 I OY7 I 4Xl I 3Y4 I 4V9 I 7 I 39.691 0.001 13.971 0.001 11.211 0.001 17.451 15.641 11.101_ 0.001 J7.19I 0.001 13.971 0.001 39.301 I 3W4 I 2X9 I 4Y5 I DXI I 5X5 I IX7 I 5XO I OKS J 4XO I 2X4 I 5X6 I IX9 I 6YO I 3X8 I 4W2 I 8 I 35.371 17.151 o.ool 17.371 15.471 17.701 15.601 22.591 15.891 17.611 15.591 17.241 0.001 17.0ll 35.291 I 4V5 I 5Y5 I 5X4 I 2Y5 I 2X7 I 1Y6 I 2Xl I 4X2 I OX6 I 2Y3 I 2X6 I 3YD I 4X3 I 4Y6 I 5V5 I I 39.801 0.001 13.951 0.001 11.221 0.001 17.621 15.641 11.111 0.001 17.481 0.001 13.981 0.001 39.681 I 5W6 I 5Y9 I 4X6 I DY2 I 2X5 I OY9 I 1X3 I 2Y7 I lXO I 1Y3 I 3X3 I 4Y9 I 4W7 I 9

10 I

_I 33.331 0.001 16.251 0.001 16.751 0.001 17.521 _ o.oll'I 16.951 0.001 16.441 0.001 32.941

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11 12 13 14 I 38.061 33.~21 0.001 17.071 0.001 33.201 37.231 I 4VO I 3W7 I 5V2 1*

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1 Figure 1.3 I SURRY UNIT 2 - CYCLE 14 INCORE THIMBLE LOCATIONS I R p N

" L I{ J H G F E D C B A I

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I Figure 1.4 1*

SURRY UNIT 2 - CYCLE 14 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS I

R p N H L I( J H C F E D C B A I

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8 I

I 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ ._1 I I 4P I I ZDP I I ZOP I

I 8P I I 20P I I 20P I I 4P I I I SS3 IBP454 I IBP487 I IBP475 I IBPCOOZI IBP476 I IBP48B I IBP456 I SSS I 9 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1~_1 _ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I 16P I I ZDP I I ZDP I I ZDP I I ZOP I I 16P I I I IBPCDD91 IBP495 I IBP471 I IBP472 I IBP496 I IBPCOlOI I 10 I.

1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I 4P I lbP I I ZOP I I ZOP I I ZOP I I 16P I 4P I I I IBP447 IBP459 I IBP491 I IBP46B I IBP492 I IBP460 IBP44B I I 11 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I 16P I I ZOP I I ZOP I I 16P I I I I I l _ _ l__

I I

IBP463 I I 4P I 16P I IBP443 IBPCDDSI IBP4B3 I I ZDP I IBP479 I IBP484 I 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ , _ _ 1_ _ 1_ _ 1 IBP464 I

._l _ _ l _ _ l _ _ l _ _ l ~ _ I _ _ I _ _ I_ _ I _ _ I I 16P I 4P I IBPCOD6IBP444 I I

I I

I 12, 13 I I I 4P I I 4P I I I 4P BP 4 BURNABLE POISON ROD CLUSTER B BURNABLE POISON ROD CLUSTER I I IBP457 I I I I_ _ I_ _ I_ _ I IBP453 I l _ _ l _ _ l _ _ l _ _ l ~ _ I _ _ I_ _ I I I I I

I I

I I 14 15 I

16P - 16 BURNABLE POISON ROD CLUSTER 20P SSx 20 BURNABLE POISON ROD CLUSTER SECONDARY SOURCE I.

XXP BPMII, SSW

- I OF BP RODS

- BP ASSEHBLY ID, SECONDARY SOURCE ID

.I

,I 1*

I I

NE-1082 S2C14 Startup Physics Tests Report Page 14 of 56

I I

Figure 1.5 I SURRY UNIT 2 - CYCLE 14 CONTROL ROD LOCATIONS I,

R p N H L K J H G F E 0 C B A I 180° I

I I I I 1 I N-41 I I

I

____ I __ I __ I __ I _ _ __

I A I

_1_1_1_1_1_1_1_1_

I I o I I SA I I A I I SA I I I

I

I N-43 2

3

_ _ 1_1_1_1_1_1_1_1_1_1_

I I I

I I c I I I SB I I B I

_I_I_I_I_I_I_I_I_I_I_I_I_

I I

I I B I I

I c I I SB I I I

I I 4

5 1_1_1_1_1_1_1_1_1_1_1_1_1_1

,I I IAI I

IBI I SA I I IOI

_1_1_1_1_1_1_1_1_1_1_1_1_1_1_

I ICI I SB I IDI I SB I I IBI I I SA I IAI I I 6

7

,. 1_1_1_1_1_1_1_1_1_1_1_1_,_,_,_,

I I D I I I I c I 1_1_1_1_1_1_1_1_1_,_,_,_,_,_1_1 I I I SA I I I 1_1_1_1_1_1_1_1_1_1_1_1_1_1_1_1 I

I SB I I I c I I SB I .I I

I I

I SA I I D I I

I I

- 270° 8 9

IAI IBI IOI ICI IDI IBI IAI 10 I 1_1_1_1_1_1_1_1_1_,_,_,_1_1 I I I I SB I .1 I_I_I_I_I_I_I_I_I_I_I_I_I_I I I c I I B I I

I I

I B I I SB I I c I I I I

I 11 12 1_1_1_1_1_1_1_1_1_1_1_1 I N-44 I I I I SA I

I SA I I I I __ I __ I __ I __ I __ I __ I __ I __ I __ I I I A I I D I I A I I I

N-42 13 14 I_I_I_I_I_I_I_I I Absorber Material I I I_I_I_I I

I I 15 Ag-In-Cd 00 I Function Number of Clusters I Control Bank D Control Bank C Control Bank B 8

8 8

Control Bank A 8 I Shutdown Bank SB Shutdown Bank SA 8

8 I

NE-1082 S2Cl4 Startup Physics Tests Report Page 15 of 56

I

'I, SECTION 2 I

CONTROL ROD DROP TIME MEASUREMENTS I

The drop time of each control rod was measured at hot full-flow I

reactor coolant system (RCS) conditions (Tave of 547+/-5°F) in order to verify that the time from initiation of the rod drop to the entry of the I rod into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.12.C.1. During this test, the RCS pressure 1:

varied between 2246 psia and 2249 psia, the RCS flow was 100%, and the ,,-

RCS Tave varied between 544.9°F and 545.7°F.

The rod drop times were measured by withdrawing a bank to its fully 1 withdrawn position and tripping all eight control rods within the bank by opening the reactor trip breakers. This allowed the rods to drop into

,I the car~ as they would during a plant trip. The Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded for each rod I

in the bank to determine each rod's drop time. This procedure was I repeated for each bank.

As shown on the sample rod drop trace in Figure 2.1, the initiation I

of the rod drop is indicated by the increase in IRPI coil voltage when the reactor trip breakers are opened. As the rod drops, a voltage is I

induced in the IRPI primary coil. The magnitude of this voltage is a I function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the I'

IRPI coil voltage. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused I

I by rod bouncing.

NE-1082 S2C14 Startup Physics Tests Report Page 16 of 56

I I The measured drop times for each control rod are recorded on Figure I 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification 3.12.C.1 specifies a maximum rod drop time I from loss of stationary gripper coil voltage to dashpot entry of 2.4 I seconds with the RCS at hot, satisfy this limit.

full flow conditions. The test results In addition, rod bounce was observed at the end of I each trace which demonstrated that no control rod stuck in the dashpot region.

I I

I NE-1082 S2C14 Startup Physics Tests Report Page 17 of 56

I 1*

Table 2.1 SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS HOT ROD DROP TIME

SUMMARY

I I

ROD DROP TIME TO DASHPOT ENTRY I I

SLOWEST ROD FASTEST ROD AVERAGE TIME

1 F-06 1.43 sec. M-06 1.25 sec. 1.30 sec.

I.

I I

.I I

1.

I

.1 I

NE-1082 S2C14 Startup Physics Tests Report Page 18 of 56 I

I I

Figure 2.1 I SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE

,I.

I I

I BEGINNING Of' DASHPOT (beginning of first downturn in trace)

I INITIATJ:ON Of' ROD DROP BOT'l'OM OF DASHPOT (beginning of first upturn" in trace)

I EVENT MARX J I I STATIONARY GRIPPER*

COIL VOLTAGE TRACE I ROD DROP TIME _ _.;.__ __

I I

60Hz IRPI PRIMARY I COIL VOLTAGE-TRACE 60Hz TRACE TIME I

I I

I NE-l082 S2C14 Startup Physics Tests Report Page 19 of 56

I Figure 2.2 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS I

R p N l F

,I

" K J H G E D C B A 1---1--1 I

I I l. 27 I I

1_ _ 1_ _ 1_ _ 1 I

I I

I l. 30 I I

I l--~1--1 I 1. 28 I I 11 z

_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _

I I

I I 1.za I I I I 1.32 I

_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _

I I I

I I

I I 3

,I I I I I I I I I I I I I I I 1. 29 I I 1. 29 I I I I 1. 28 I I 1. 30 I I 4

_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _

I I I I I I I I I I I I I I I I I I 1.21 I I I I I I 1.32 I I I I 5 l__ l__ ' l _ _ 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 11.261 11.251 ll.301 ll.311 11.431 11.291 ll.351 6

_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _

I I

I I 1. 29 I I I I

I I

I I I 1. 32 I I I I 1. 33 I 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I

I I I I 1.21 I I

I I

I 1.33 I I I I

I I

I I 1.32 I I

I I

I 1. 29 I I

I I

I I 1.30 I I

I I

I 7

8 I

1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I

I I

I I.:Sl I I

I I

I 1.31 I I

I I

I I 1.30 I 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 1.26 I I

I I

I 9 I I 1.29 I I 1.31 I I 1.30 I I 1.33 I I 1.33 I I 1.21 I I 1.29 I 10 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I

I I

I I I l. 26 I I I I

I I

1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I

I I

I l. 29 I I

I I

I I 11 I I I 1.30 I I 1.2a I I I I 1.29 I I 1.32 I I 12 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I

I I

11.291 I

I I

I 11.291 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I

I I

I I 13 I I

I I 1.32 I I 1.26 I I 1.31 I I 14 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1_ _ 1 I I I I I I I I 15 1_ _ 1_ _ 1_ _ 1 I I I X.XX 1--> ROD DROP TIHE TO DASHPOT ENTRY (SEC)

I_ _ I I

I I

I NE-1082 S2C14 Startup Physics Tests Report Page 20 of 56 I

- ~

I I

SECTION 3 I

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 J 3

The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter I referred reactivity to as the reference bank) worth using conventional test into the core techniques.

and measured The its reactivity I changes resulting from the reference bank movements were recorded continuously by th~ reactivity computer and were used to determine the I differential and integral worth of the reference bank. For Cycle 14, I Control Bank B was used as the reference bank.

After the completion of the reference bank reactivity worth I measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the I reference bank near full insertion. Initial statepoint data for the rod I swap maneuver were obtained by moving the reference bank to its fully inserted position with all other banks fully withdrawn and recording the I core reactivity and moderator temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps I

,, and then one of the other control rod banks (i.e. a inserted to balance the reactivity of the reference bank withdrawal.

sequence was repeated until the test bank was test bank) fully inserted and the was This t reference bank was positioned such that the core was just critical or near the initial statepoint reactivity. This measured critical position (MCP)

I of the reference bank with the test bank fully inserted was used to I NE-1082 S2Cl4 Startup Physics Tests Report Page 21 of 56

I determine the integral reactivity worth of the test bank. The core I

reactivity, moderator temperature, and the differential worth of the I reference bank were recorded with the reference bank at the MCP. The rod swap maneuver then was repeated in reverse such that the reference bank I

again was fully inserted with the test bank fully withdrawn from the core.

This rod swap process was then repeated for each of the other control and I

shutdown banks. I A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets

1 given in the Appendix, all of the individual measured bank worths for the control and shutdown banks were within the design tolerance (+/-10% for the I

reference bank, +/-15% for test banks worth greater than 600 pcm, and +/-100 I

pcm for test banks worth less than or equal to 600 pcm). The sum of the individual measured rod bank worths was within 1. 4% of the design I prediction. This is well within the design tolerance of +/-10% for the sum of the individual control rod bank worths.

I.

The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively.

I The design predictions and the measured data are plotted together in order I to illustrate their agreement. In summary, the measured rod worth values were satisfactory.

I I.

I I

I NE-1082 S2Cl4 Startup Physics Tests Report Page 22 of 56 I

I I Table 3.1 I SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH

SUMMARY

I, I MEASURED WORTH

'PREDICTED WORTH PERCENT DIFFERENCE

(%)

BANK (PCM) (PCM) (M-P)/P X 100.

I, B-Reference Bank D

1435.1 1158. 3 1425.0 1173.8 0.7

-1. 3 C 759.5 767.9 -1.1 I A SB SA 250.2 1152.5 1093. 9 258.8 1169. 8 1139. 9

-3.3*

-1.5

-4.0 I Total Worth 5849.5 .5935.2 -1.4 I

Difference is less than 100 pcm.

I I

I*

I.

I NE-1082 S2C14 Startup Physics Tests Report Page 23 of 56

I Figure 3.1 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS BANK B INTEGRAL ROD WORTH - HZP I

ALL OTHER RODS WITHDRAWN Predicted 1400 I I

'" Measured

\.

1200 II

. ,, I z 1000

- , I 0 * '

ci5 5

B " \. I

E '

(.)

~

C.

0 800 I

I

c

~ *

~..J I I\.

~ 600 C!)

w I-z 1* '

' I\.

400 1,

I.

I\.

I I

200

" 1, I.

' II.

I, "

I 0

0 40 80 120 B BANK POSITION (5 STEPS/ DIVISION) 160 200 I I

NE-1082 S2C14 Startup Physics Tests Report Page 24 of 56 I

I I

Figure 3.2 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS BANK B DIFFERENTIAL ROD WORTH - HZP I ALL OTHER RODS WITHDRAWN Predicted I

I 12 I

I I Measured I I j \

I

1. 1.

10

\

1 I I -z 0

1

\

ci5 Ill

\

I >

-0 8 I

~

(.)

\

r....

I Cl.

IC)

N f'\~

'~ Lo,_ ....

J:

~

I ~

_J 6

Ill I

<(

I j:::

zw w

0::

I.

u.

0 4 I

I 2 l I ,.

'I' I

,.,,. I I

I

.... ,'I I 0

0 40 80 120 160 200 B BANK POSITION (5 STEPS/ DIVISION)

I I NE-1082 S2C14 Startup Physics Tests Report Page 25 of 56

I I

SECTION 4 I

BORON ENDPOINT AND WORTH MEASUREMENTS I

Boron Endpoint I With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank I

configurations to enable a direct comparison of measured boron endpoints I

with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks I at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal I

control rod position and moderator temperature, if necessary. I The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Results and Evaluation I

Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances. The all-rods-out (ARO)

I endpoint comparison to the predicted value met the requirements of I Technical Specification 4.10 .A regarding core reactivity balance.

summary, the boron endpoint results were satisfactory.

In I

I Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data I

from which the boron worth coefficient or differential boron worth (DBW)

I was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, I NE-1082 S2Cl4 Startup Physics Tests Report Page 26 of 56 I

I I the value of the DBW over the range of boron endpoint concentr.ations was I obtained.

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, I the measured DBW was -7.03 pcm/ppm. This is within 0.6% of the predicted value of -6.99 pcm/ppm and is well within the design tolerance of +/-10%.

I In summary, the measured boron worth coefficient was satisfactory.

I I

.*:1 I I I

I I

I NE-1082 S2Cl4 Startup Physics Tests Report Page 27 of 56

I Table 4.1 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS BORON ENDPOINTS

SUMMARY

I I

Control Rod Measured Endpoint Predicted Endpoint Difference M-P I

Configuration (ppm) (ppm) (ppm)

ARO 1967 1986 -19 I

B Bank In 1763 1763* 0 I

The predicted endpoint for the B adjusted for the difference between Bank In configuration was the measured and predicted I

values of the endpoint taken at the in the boron endpoint Startup Physics Sheet in the Appendix.

ARO configuration as shown Test Results and Evaluation I I

I I

NE-1082 S2Cl4 Startup Physics Tests Report Page 28 of 56 I

I I

Figure 4.1 I ,SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT I

I Measured DBW= -7.03 pcm/ppm I

I **

I 1200 ---+--!..,-..- . J - - - - - - - + - - - - + - - - - - - j t - - - - t - - - i I 1000

+------+-_.:*~.--+------t------t----i------r----;

I :?

0 e:.

~

BOO

+-------1-----+-----+--....l',-,----,----t------t-----t-------j I j:::

0

~

a:: 600

+------+----+----+------if--....!.'-c-:,~-t-------t-----t------1 I * ....

400 -l------1------l------l------,----t-----<:-,---;r-----i------'t I *... .

1* 200 J__----1----~-----+-----lf------+-------t---:..-. * --i-------t I 0 -l------1------l-----+---~----+------+-----+-~-~~

1750 1780 1810 1840 1870 1900 1930 1960 I BORON CONCENTRATION (PPM)

I I

I NE-1082 S2C14 Startup Physics Tests Report Page 29 of 56

I SECTION 5 I

I TEMPERATURE COEFFICIENT MEASUREMENT I

The isothermal

temperature coefficient (ITC) at the all-rods-out condition is measured by controlling the reactor coolant system (RCS)

I temperature through varying the steam generator blowdown flow, I establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer. This test I

sequence includes a cooldown followed by a heatup.

Reactivity was measured during an RCS cooldown of 3.1°F and an RCS I

heatup of 3.6°F. Reactivity and temperature data, was taken from the I reactivity -computer and strip chart recorders. Using the statepoint method, the temperature coefficient was determined by dividing the change I in reactivity by the change in RCS temperature. An X-Y plotter, which

. plotted reactivity versus temperature, confirmed the statepoint method I

in calculating the measured ITC.

The predicted and measured isothermal temperature coefficient values I

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, the measured isothermal temperature coefficient value was within the I

design tolerance of +/-3 pcm/°F. Accounting for the Doppler temperature coefficient (-1.67 pcm/°F) and a 0.5 pcm/°F uncertainty, the moderator I

temperature coefficient was 1.50 pcm/°F, which meets the requirement of I Core Operating Limits Report Section 2.1. In summary, the measured result was satisfactory.

I I

NE-1082 S2Cl4 Startup Physics Tests Report Page 30 of 56 I

I I Table 5.1 I SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT

SUMMARY

I I CORE CONDITIONS ISOTHERMAL TEMPERATURE COEFFICIENT (PCM/ F)

I BANK POSITION TEMPERATURE RANGE BORON CONCENTRATION C/D H/U AVE. DIFFER.

( F) (ppm) MEAS. PRED. (M-P)

I 219 543.1 to 1966 -0.65 -0.69 -0.67 -1.59 0.92 546.8 I

I I

I NE-1082 S2C14 Startup Physics Tests Report Page 31 of 56

I SECTION 6 I

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 I chamber detectors which traverse fuel assembly instrumentation thimbles depicted in Figure 1.3. For each traverse, the detector voltage output I is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, I

three-dimensional power distributions are determined from this data using I

the CECOR code 4

CECOR couples the measured voltages with predetermined analytic signal-to-power conversions, pin-to-box factors, and average I coupling coefficients in order to determine the power distribution for the whole core.

I 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 are given in Table 6.1. A comparison of these measured values I with their Technical Specification limits is given in Table 6.2. Flux map 1 was taken at approximately 24% power to verify the radial power I

distribution (RPD) predictions at measured RPDs from this flux map.

low power. Figure 6. 1 shows the Flux maps 2 through 3 were taken near I

71% and 100% power, respectively, with different control rod I configurations. These flux maps were taken to check at-power design predictions and to measure core power distributions at various operating I

conditions. The radial power distributions for these maps are given in I

Figures 6.2 through 6.3. These figures show that the average relative assembly power distribution measured/predicted percent difference was I NE-1082 S2Cl4 Startup Physics Tests Report Page 32 of 56 I

I I 2.1% or less for the three maps. The measured F-Q(Z) and F-DH(N) peaking I factor values for all flux maps were within the limits of the Core Operating Limits Report (COLR) Sections 2.3 and 2.4, respectively. Flux I maps 1 and 2 were used to recalibrate the power range excore detectors.

I A power range detector calibration based on flux existing calibration was satisfactory.

map 3 verified the I In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the I accident analysis acceptance criteria, and the COLR limits. It is I therefore anticipated that the core will continue to operate as designed throughout Cycle 14.

I I

I NE~l082 S2Cl4 Startup Physics Tests Report Page 33 of 56

I TABLE 6.1 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS INCORE FLUX MAP

SUMMARY

I I

I I I l I 2 I I I I

3 I I BURN! I F-Q(Zl HOT F-DH(Nl HOT I CORE FCZ) POWER I I I HAP DESCRIPTION IHAPI IND. I I

I I

I DATE I

UP I !BANK CHANNEL FACTOR HWD/IPWRI D ! _ _ _ _ _ _ _ _ _

HTU ICZllSTEPSIASSV I AXIAL I I I

-,,,.,,.,,.---,----'-'---'--'-'--1--1--1---'--'

I I POINT I F-QCZl I CHHL.FACTOR I I

HAX I

TILT I AXIAL! HO.I I OFF I OF I

-AccS,-,,S,..,V-1,......,,F--::cDH-C,.,.H,.,.llAXJALI FCZll HAX !LOCI SET ITHIHI I IPOINTI I I I CZ> IBLES)

J_ _ I_ _ I _ J _ l _ _ l _ l I

LESS THH 307. PWR I l I 6-08-961 4 I 241 151 I L 5 I 33 I Z.291 I HlO I 1.528 I 31 )l.39611.0121 SW) -6.621 '+2 I BTWN 657. ANO 757. I 2 I 6-09-961 19 I 71) 184 I HlD I 30 GRT THAN 957. PWR I 3 I 6-13-961 155 )lODI 226 I DID I 41

_ _ _ _ _ _ 1_1 _ _ _ 1_ _ 1_1 _ _ , _ _ 1_ _ 1_ _ _ 1_ _ 1 I 1.970 I DlD I 1.857 I DlO I 1.479 I 30 )l.258)1.0031 SWI -D.411 43 I I 1.451 I 30 )l.193)1.0021 SE) 1_ _ 1_ _ 1_ _ ,_J __ 0.501 43 I l_l I NOTES: HOT SPOT LOCATIONS ARE SPECIFIED BY GIVING ASSEHBLY LOCATIONS CE.G. HOB IS THE CENTER-OF-CORE ASSEHBLVl, AND CORE HEIGHT CIN THE "Z" DIRECTION THE CORE IS DIVIDED INTO 61 AXIAL POINTS STARTING FROH THE TOP OF THE CORE l. . I I. F-QCZl INCLUDES A TOTAL UNCERTAINTY OF 1.08.

2. POWER TILT - DEFINED AS THE AVERAGE QUADRANT POWER TILT FROH CECOR.

3. EACH HAP WAS USED TO PERFORH A PEAKING FACTOR VERIFICATION AND A POWER RANGE EXCORE DETECTOR CALIBRATION. THE FLUX HAP 3 I

CALIBRATION VERIFIED THE EXISTING CALIBRATION.

I I

I NE-1082 S2C14 Startup Physics Tests Report Page 34 of 56 I

I I Table 6.2 I SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS COMPARISON OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS I

I PEAK F-Q(Z) HOT F-Q(Z) HOT F-DH(N) *HOT I CHANNEL FACTOR* CHANNEL FACTOR**

(AT NODE OF MINIMUM MARGIN)

CHANNEL FACTOR/I MAP MEAS LIMIT NODE MEAS LIMIT NODE MARGIN MEAS LIMIT MARGIN I NO.

1 2.291 4.640 33 2.291 4.640 33

(%)

50.6 1.528 1. 914

(%)

20.2 2 1.970 3.260 30 1.965 3.220 25 39.0 1.479 1.696 12.8 I 3 1.857 2.320 41 1.839 2.279 24 19.3 1,451 1.560 _.:

7.0

The Technical Specification's limit for the heat flux hot chann~l .:.i.

I factor, F-Q( Z), is a function of core height and power level.

The values for F-Q(Z) listed are the maximum value of F-Q(Z) in the core. The Technical Specification's limit listed above is

,-'l evaluated at the plane of maximum F-Q(Z).

I ** The value for F-Q(Z) listed above is the value at the plane of minimum margin. The minimum margin values listed are the minimum I percent.difference between the measured values of F-Q(Z) and the Technical Specification's limit at that node for each map.

The measured F-Q(Z) hot channel factors include 8% total I uncertainty.

fl Since all fuel assemblies in the core are SIF fuel (i.e. there I are no lopar assemblies), the FdH(N) limit for all assemblies is the same.

I I

I I NE-1082 S2Cl4 Sfartup Physics Tests Report Page 35 of 56

I Figure 6.1 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS ASSEHBLYWISE POWER DISTRIBUTION I

24% POWER R p N

" L K J N C F E D C B A I PREDICTED

PREDICTED I

D.227 0.277 0.227 NEASURED

D.231. 0.283. 0.232. NEASURED

.PCT DIFFERENCE. 1.8. 2.1. 2.3. .PCT DIFFERENCE.

0.290 0.520 0.974 0.847. 0.974. 0.520. 0.290 *

0.296. 0.528. 0.990. 0.867. 0.997. 0.546. 0.298.

0.340 2.1

0.996 1.6.

1.186 1.6.

1.6.

1.306 1.2.

2.4.

1.1 .

2.4.

1.225. 1.307 1.4.

4.9.

1.188 2.0.

2.6.

0.997

. 0.355. 1.020 . 1.206. 1.322. 1.238. 1.326. 1.211 . 1.011 . 0.347.

4.5. 2.4 . 1.4.

0.340 2.0.

i3 0.292 0.342 1.002 0.629 1.229 1.224 1.327 1.402 1.271 1.288 0.8.

1.309 1.326 0.4.

1.097 1.291 0.7.

1.312 1.403 1.9.

1.272 l.225

. 0.351 . 0.646. 1.259. 1.423. 1.298. 1.331 . 1.300. 1.429. 1.233. 0.628. 0.339.

2.5. 2.7. 2.8. 1.5.

0.630 0.343 0.6. -0.3. -1.1 .

1.328 1.230 1.003 0.292 I

I

0.299. 1.026. 1.258. 1.372. 1.284. 1.308. 1.088. 1.300. 1.266. 1.318. 1.212. 0.988. 0.292.

2.7. 2.5. 2.3. 3.4 . 1.0. -0.l * -0.9. -0.9. -0.5. -0.8. -1.5. -1.4. 0.1

0.522 1.190 1.405 1.272 1.221 1.230 1.281 1.229 1.:21 1.273 1.406 1.192 0.522

. 0.538. 1.222. 1.420. 1.250. 1.212. 1.213. 1.244. 1.189. 1.193. 1.243. 1.371. 1.172. 0.521 . 6 3.1

2.7. 1.1. -1.7. -0.8. -1.4. -2.9. -3.3. -2.3. -2.4. -2.5. -1.7. -0.2.

0.228 0.978 3.9.

1.310 4.4.

1.291. 1.311 1.232. 1.300 1.236 1.292 1.230 1.4. -1.0 * -1.3. -1.8. -3.8. -7.l. -4.8. -3.9. -4.3. -1.4.

1.314 1.293. 1.311

. 0.237. 1.016. 1.367. 1.309. 1.298. 1.216. 1.276. 1.189. 1.201. 1.170 . 1.263. 1.238. 1.294. 0.994. 0.232.

3.9

0.978 1.6.

0.228 1.6.

I 0.278 0.850 1.229 1.329. 1.100 1.283. 1.238 1.180 1.237 1.283 1.100 1.328. 1.229 0.849 0.278

. 0.289 . 0.882. 1.266. 1.343. 1.071 . 1.261. 1.208. 1.136. 1.171. 1.204. 1.056. 1.296. 1.225. 0.869. 0.282.

3.7.

0.228 3.8.

0.978 3.0.

1.311 1.1. -2.6. -1.7. -2.4. -3.7. -5.4. -6.2. -3.9. -2.4. -0.3.

1.294. 1.314 1.231

1.293 1.238 1.300 1.232 1.311 1.291

1.310

. 0.236

1.012. 1.354. 1.321 .*l.326. 1.219. 1.261. 1.196. 1.242. 1.150

1.266. 1.275. 1.308. 0.984. 0.224.

2.4.

0.977 1.5.

0.228 I9 3.6 . 3.5. 3.2. 2.1. 0.9. -1.0. -2.5. -3.3. -4.5. -6.6. ~3.4. -1.3. -0.2. 0.7. -1.7.

0.523 1.192 1.407. 1.274 3.D.

1.221. 1.229 1.282 1.231 2.0. -0.6. -3.4. -2.8. -3.2. -3.8. -2.0.

1.221 1.272 1.405. 1.190

. 0.543. 1.245. 1.449. 1.300

1.213. 1.187. 1.247. 1.192. 1.175. 1.247. 1.419. 1.195. 0.528.

4.0. 4.5. 1.0. 0.4.

0.522 1.2.

I D.292 1.003 3.8.

0.343 1.230 3.6.

0.630 1.329 4.5.

1.226 1.272 1.312 l.098 1.309 1.271 1.0. -1.0. -1.2. -1.8. -2.9. -1.9. -0.l.

1.404 1.291 1.326 1.289 1.402 1.327 1.224 1.229

0.303. 1.041. 1.275. 1.389. 1.285. 1.299. l.085. 1.285. 1.235. 1.302. 1.228. 1.002. 0.293.

3.8.

0.629 1.002 0.0.

0.342 0.292 0.4. I

. 0.352. 0.648. 1.258. 1.418. 1.283. 1.323. 1.288. 1.401

1.223. 0.638. 0.341.

2.7. 3.0.

0.340 2.6.

0.997 1.0. -0.6. -0.2. -0.l . -0.l. -0.l

1.188 1.307 1.225 1.306 1.186

. 0.348. 1.017. 1.202. 1.315. 1.237. 1.329. 1.223. 1.011. 0.345.

2.4. 2.0 . 1.2. 0.6. 0.9. 1.7. 3.1 .

0.996 1.5.

1.5. -0.4.

0.340 1.4.

I 13 STANDARD

. 0.291 0.520 D.975 0.847 0.974 0.520

,0.299. 0.527. D.986. 0.862. l.009. 0.536. 0.296.

2.8. 1.4. 1.2. 1.8. 3.6. 3.1

0.290 2.0. I 0.227 0.277 0.227 AVERAGE I

DEVIATION .

0.230. 0.283. 0.235. .PCT DIFFERENCE.

=l.387 1.4 . 2.0 . 3.3. = 2.1 SUHl'1ARY HAP NO: S2-14-0l CONTROL ROD POSITIONS:

DATE:

F-QCZ) 6/08/96

= 2.291 POWER:

QPTR:

24.3%

I D BANK AT 151 STEPS F-DHCNJ = 1.528 FCZJ = 1.396 NW SW 1.0092 1.0116 NE SE 0.9888 0.9905 I

A.O.

BURNUP 4.0 HWD/HTU -6.620%

I NE-1082 S2C14 Startup Physics Tests Report Page 36 of 56 I

I I Figure 6.2 I SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 717. POWER I R p H H L K J H C F E D C B A I

PREDICTED

0.254 0.315 0.254 PREDICTED

HEASURED . 0.256. D.319. 0.258. HEASURED

PCT DIFFERENCE. 0.8. 1.1. 1.5. .pCT DIFFERENCE

0.307 0.543 1.018 0.930 1.018 0.543 0.307

0.310. 0.547. 1.025. 0.942. 1.035. 0.568. 0.313. 2 I 0.357 0.9.

1.001 0.7.

1.174 0.7.

0.7.

1.302 0.5.

1.2.

1.226 0.2.

1.6.

1.302 0.8.

4.6.

1.175

0.362. 1.012. 1.182. 1.309. 1.228. 1.313. 1.188. 1.008. 0.359.

1.4. 1.1. 1.1

2.0.

1.002 0.6.

0.357 0.3.

I 0.308 0.359 1.006 0.643 1.208 1.204 1.306 1.369 0.6.

1.255 1.257 0.5.

1.287 1.300 0.9.

1.076 1.259 0.5.

1.290 1.370 1.205

. 0.360 . 0.648. 1.222. 1.378. 1.264. 1.312. 1.266. 1.377. 1.204. 0.643. 0.358.

0.2. 0.7. 1.5; 0.644 0.5. -0.l * -0.2. -0.5.

1.256 1.307 1.209 0.360 1.007 0.308 4

I

. 0.308. l.006. 1.206. 1.304. 1.255. 1.288. 1.074. 1.290. 1.258. 1.292. 1.207. 0.999. 0.300. 5 o.o. 0.0. -0.l. -0.2. 0.0. 0.0. -0.2. -0.1. 0.2. -1.2. -0.2. -0.7. -2.7.

0.545 1.177 1.371 1.256 1.271 1.219 1.258 1.218 1.271 1.257 1.372 1.178-. 0.545

. 0.546. 1.177. 1.365. 1.239. 1.265. 1.214. 1.239. 1.208. 1.288. 1.248. 1.355. 1.169. 0.547. 6.

0.2. o.o * -o.5. -1.4. -o.4. -o.3. -1.6. -o.8. 1.4 * -o.7. -1.3. -o.7. o.3.

I 0.255 0.8.

1.021 0.7.

1.305 1.259 1.289 0.6. -0.2. -0.7. -0.3.

1.220 1.281 1.211 1.274 1.219 1.292 1.261

. 0.257. 1.028. 1.312. 1.257. 1.280. 1.216. 1.288. 1.194. 1.235. 1.200

1.269. 1.221. 1.297. 1.047. 0.261

0.5. -1.4. -3.0. -1.5. -1.8. -3.2. -0.6.

1.305 1.021 2.5.

0.255 2.3.

7 0.316 0.933 1.229 1.302 1.077 1.259 1.212 1.158 1.212 1.259 1.077 1.302 1.229 0.933 0.316 I

0.319. 0.944. 1.236. 1.301. 1.066. 1.252. 1.205. l.14D. 1.180. 1.225. 1.059. 1.285. 1.226. 0.952. 0.320 .

1.0.

0.255 1.2.

1.021 0.6. -0.l. -1.l. -0.6. -0.6. -1.5. -2.6. -2.7. -1.7. -1.3. -0.2.

1.305 1.261 1.292 1.219 1.275 1.213 1.282 1.220 1.289 1.259

. 0.257. 1.031. 1.317. 1.266. 1.284. 1.213. 1.264. 1.194. 1.240. 1.181

1.274. 1.261. 1.310. 1.028. 0.249.

1.305 2.0.

1.021 1.3.

0.255 8

9 I

1.0. 1.0. 0.9. 0.4. -0.6. -0.5. -0.9. -1.6 .. -3.3. -3.2. -1.2. 0.1 . 0.4. 0.7. -2.4.

0.545 1.178 1.373 1.257 1.271 1.218 1.259 1.219 1.271 1.256 1.371 1.177 0.545

. 0.553. 1.199. 1.389. 1.270. 1.272. 1.207. 1.251. 1.199. 1.247. 1.254. 1.406. 1.190. 0.548. 10 1.4. 1.8. 1.2. l.O. O.l. -0.9. -0.6. -1.6. -1.8. -0.2. 2.5. 1.1.. 0.5.

I 0.308 1.007 0.360 1.209 1.8.

0.644 1.307 3.5.

1.205 1.256 1.291 0.8. -0.2.

1.370 1.259 1.076 1.288 1.255 1.8. -0.7. -2.6. -0.3.

1.300 1.258 1.369 1.306

. 0.312. 1.019. 1.231. 1.353. 1.266. 1.289. 1.095. 1.280. 1.222. 1.303. 1.217. 1.011. 0.310 .

1.2. 1.2.

1.204 1.208 0.8.

0.643 1.006 0.5.

0.360 0.308 0.5.

11

. 0.350. 0.650. 1.221 . 1.369. 1.231. 1.298. 1.260. 1.370

1.206. 0.641 . 0.352. 12 I -2.7. 1.0.

0.357 1.3. -0.1 . -2.3. -0.l.

1.002 0.8.

1.175 1.303 0.0. -0.6.

1.226 0.2.

0.1.

1.302 1.2.

0.1 .

1.174

. 0.360. 1.010. 1.175. 1.295. 1.229. 1.318. 1.208. 1.015. 0.360.

0.8. 2.9.

0.2. -0.4. -2.l.

1.001 1.4.

0.357 0.7.

13 I 0.307 0'.543 1.019 0.931 l.018 0.543

. 0.313. 0.544. 1.016. 0.937. 1.036. 0.555. 0.312.

2.0. 0.1. -0.2. 0.7. 1.8. 2.3.

0.307 1.7.

14 STANDARD 0.254 0.315 0.254 AVERAGE I DEVIATION

=0.863

0.249. 0.316. 0.258 *

-2.l .

SUMMARY

0.3

1.5 .

.PCT DIFFERENCE *

= 1.0 15 I HAP NO: S2-14-02 CONTROL ROD POSITIONS:

DATE:

F-Q(Z) 6/09/96

= 1.970 POWER: 70.98%

QPTR:

I D BANK AT 184 STEPS F-DH(N) = 1.479 F!Z) = 1.258 NW SW

1. 0010

1. 0034 NE SE 0.9973 0.9984

A.O.

I BURNUP 19 HWD/HTU -0.406%

I NE-1082 S2Cl4 Startup Physics Tests Report Page 37 of 56

I Figure 6.3 I

SURRY UNIT 2 - CYCLE 14 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER OISTRIBUTION I

1007. POWER R p H 11 L K J H G F E D C B A I

PREDICTED 11EASURED

PCT DIFFERENCE.

0.306 0.544 0.265 0.1

1.031 0.335 0.3

0.265

0.265. 0.336. 0.268.

1.1 .

0.991. 1.031

0.544. 0.307

PREDICTED HEASURED

.PCT DIFFERENCE. I

0.307. 0.544. 1.031. 0.993. 1.045. 0.573. 0.315.

0.356 4.1.

0.3.

0.980 0.5.

0.1.

I.ISi 0.0.

1.291 0.1. -0.2. -0.8.

0.1 .

1.225 1.3.

1.291 0.6.

5.4.

1.152 1.5.

2.9.

0.981 1.4.

0.356

. 0.370 . 0.985 . 1.152 . 1-.289 . 1.216 . 1.298 . 1.169

0.995

0.369 .

3.7.

I 3

0.358 0.638 1.179 1.346 1.241 1.289 1.243 1.3.47 1.179

. 0.358. 0.640. 1.177. 1.346. 1.241 . 1.290. 1.248. 1.357. 1.183. 0.640. 0.358.

0.1. 0.4. -0.2. 0.0. 0.0. 0.1 . 0.4. 0.7. 0.4.

0.638 0.4.

0.358 0.0. I 0.308 0.984 1.182 1.295 1.257 1.289 1.076 1.292 1.258 1.296 1.183 0.985 0.308

. 0.308 . 0.984. 1.181 . 1.301 . 1.257. 1.291 . 1.079. 1.294 . 1.260. 1.285. 1.178, 0.982. 0.311.

0.0 .

0.546 o.o. -0.l. 0.5.

1.154 1.348 1.258 0.0.

1.343 0.1.

1.235 0.3.

1.266 0.1.

1.234 0.1. -0.8. -0.4. -0.3.

1.343 1.259 1.348

0.546. 1.153, 1.337. 1.225. 1.334. 1.239. 1.276. 1.231. 1.349. 1.249. 1.331 . 1.149. 0.550.

1.155 1.1.

0.546 I

6 0.1 . -0.l. -0.8. -2.6. -0.7. 0.3. 0.8. -0.2. 0.4. -0.8. -1.2. -0.5. 0.7.

0.266 1.033 1.293 1.243 1.290 1.236. 1.296 1.222 1.289 1.235. 1.293 1.244. 1.294

. 0.266. 1.037. 1.300. 1.237. 1.274. 1.231. 1.309. 1.218. 1.261 . 1.220. 1.272. 1,206. 1.286. 1.053. 0.270.

1.033. 0.266 .

I 0.3.

0.336 0.4.

0.993 0.6. -0.5. -1.2. -0.4.

1.227 1.290. I.078 1.0 . -0.3. -2.2. -1.2. -1.6. -3.l. -0.6.

1.267. 1.223 1.170 1.222 1.267. 1.078 1.290. 1.227

. 0.336. 0.995. 1.229. 1.285. 1.063. 1.259. 1.219. 1.161 . 1.205. 1.247. 1.065. 1.277. 1.224. 1.004. 0.339.

0.2. 0.2. 0.1. -0.4. -1.4. -0.6. -0.4. - -0.7. --1.4. -1.6. -1,2. -1.0. -0.2.

2.0. 1.7.

0.993. 0.336.

I.I. 0.9.

I 0.266 1.033 1.294 1.244 1.293 1.235 1.290 1.223 1.296 1.236. 1.290 1.243 1.293 1.033 0.266

. 0.266. 1.034. 1.295. 1.246. 1.297. 1.229. 1.276. 1.212. 1.283. 1.210. 1.281 . 1.248. 1.302. 1.043. 0.264.

0.2 . 0.1 .

0.546 0.1 . -0.l.

0.1 .

1.155 0.1 ,

1.349 0.5.

0.3 * -0.5 . -1.l * -0.9 . -1.0 . -2.1 *. -0.7

1.259 1.343 1.234 1.266 0.8. -0.5. -2.6. -0.8. -1.l. -1.6.

1.235 1.3.44 1.258

0.546. 1.154. 1.356. 1.269. 1.336. 1.202. 1.255. 1.222. 1.322. 1.258. 1.383. 1.173. 0.557.

0.0.

0.4 .

1.348 2.6.

0.7

1.154 1.7.

1.0 * -0.7 .

0.546 2.1.

I 10 0.308 0.985 1.183 1.296 1.258 1.292 1.077 1.289 1.257 1.295 1.182 0.984 0.308

. 0.309. 0.991. 1.199. 1.332. 1.262. 1.281 . 1.093. 1.278. 1.215. 1.290. 1.198. 0.998. 0.313.

0.4. 0.6. 1.3. 2.8. 0.3. -0.9. 1.5. -0.8. -3.3. -0.4. 1.3, 1.4. 1.7.

0.358 0.638 1.179 1.347 1.243 1.289 1.241 1.3.46 1.179 0.638 0.358

. 0.359. 0.645. 1.192. 1.343. 1.214. 1.286. 1.240. 1.3.44. 1.185. 0.651. 0.359.

0.3. 1.1. 1.1 . -0.3. -2.3. -0.2. -0.l * :0.2. 0.5. 2.1. 0.4.

0.356 0.981 l.152 1.291 l.225 1.291 1.151 0.980 0.356

0.359. 0.988. l.151. 1.283. l.227. 1.304. 1.180. 0.995. 0.362. 13 0.8 . 0.7 . -0.l * -0.6 . 0.1

1.0 . 2.5

1.5

1.8

0.307 0.544 1.031 0.991 1.031 0.544 0.306

. 0.313. 0.545. 1.030. 0.996. 1.047. 0.555. 0.312.

2.0

0.2 . -0.l , 0.5

1.5 . 2.0

1.7 .

STANDARD 0.265 0.335 0.265 AVERAGE DEVIATION . 0.265. 0.336. 0.268. . PCT DIFFERENCE.

=0.891 -0.2. 0.5. 1.3. = 0.9

SUMMARY

MAP NO: S2-14-03 CONTROL ROD POSITIONS:

DATE:

F-Q(Z) 6/13/96

1.857 POWER: 100.08%

QPTR:

I D BANK AT 226 STEPS F-DH(N) :: 1.451 FIZ) :: 1.193 NW SW O. 9988

1. 0001 NE SE 0.9995

1. 0016 I

BURNUP :: 155 MWD/MTU A.O. == 0.502%

I NE-1082 S2C14 Startup Physics Tests Report Page 38 of 56 I

I I SECTION 7 I REFERENCES I 1. T. S. Psuik, "Surry Unit 2, Cycle 14 Design Report",

Technical Report NE-1074, Revision O, May, 1996.

I 2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.

I J

3. 'Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of Startup Physics Test Program - Inspector I Followup Item 280, 281/88-29-01 11 , Serial No.89-541, December 8, 1989.

4. T. W. Schleicher, "Reactor Power Distribution Analysis Using a I Moveable In-Core Detector *system and the TIP/CECOR Computer Code Package", VEP-NAF-2, November, 1991.

5. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, I 3.12.B.1, 3.12.C.1, 4.10.A, and 5.3.A.6.b.

-*I

6. "Core Operating Limits Report Surry 2 Cycle 14 Pattern AL, I Revision 0 11 , April, 1996.

I I

I NE-1082 S2C14 Startup Physics Tests Report Page 39 of 56

I I

I APPENDIX I

STARTUP PHYSICS TEST RESULTS I

AND EVALUATION SHEETS I

I I

NE-1082 S2Cl4 Startup Physics Tests Report Page 40 of 56 I

--*}

SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Zero Power Testing Range Determination I Reference II Proc No 1 Section:

Bank Positions (Steps}

2-NPT-RX-008 RCS Sequence Step No:

Temperature (°F): 547 Test Power Level(% F.P.): O I Conditions SDA: 227 SOB: 227 CA: 227 (Design) CB: 227 CC:

CD:

Other (specify):

Below Nuclear Heating I Ill Test Bank Positions (Steps) RCS Temperature (°F): SL<<,. l, Power Level (% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify):

I (Actual) CB: 227 CC: ~:l-7 Datemme Test Performed:

CD: II~ Below Nuclear Heating

,Jrs-}q& ~l:l I Reactivity Computer Initial

-'I I IV Flux Background Reading o.95x. lO amps Test I Results Flux Reading At Point Of Nuclear Heating 3.S"~ IO amps I

Zero Power Testing Range .," ' ,o-S to 10 -1..lD

-'i amps I Reference Not Applicable I V Acceptance FSARffech Spec Not Applicable I Criteria Reference Not Appli_cable Design Tolerance is met** . ~YES _ _ NO I VI Acceptance Criteria is met** :

At The Just Critical Position v YES NO I Comments ** Design Tolerance and Acceptance Criteria are met if ZPTR is below the Point of Nuclear Heating and above background.

I Prepared B y : ~ Q). ~ Reviewed By: / ~-~

I I NE-1082 S2C14 Startup Physics Tests Report Page 41 of 56

I I

SURRY POWER STATION UNIT 2 CYCLE 14 STARTU~ PHYSICS T.EST RESULTS AND EVALUATION SHEET

. I I

Reference Test

Description:

Reactivity Computer Checkout Pree No / Section: 2-NPT-RX-008

Sequence Step No: I II Bank Positions (Steps) RCS Temperature (°F): 547 Test Conditions SDA: 227 SDB: 227 CA: 227 Power Level(% F.P.): 0 Other (specify):

I (Design) CB: 227 CC:

CD:

Below Nuclear Heating Ill Test Bank Positions (Steps) RCS Temperature (°F):

Power Level (% F.P.): O S"~,. 3 I Conditions SDA: 227 SDB: 227 CA: 227 (Actual) CB: 227 CC: ;;>:>'i CD: II t Other (specify):

Below Nuclear Heating I Datemme Test Performed:

CJ>/5 /9& ~5"4 I Measured Parameter Pc= Measured Reactivity using p-computer (Description) Pt= Predicted Reactivity I

. IV Test Results Measured Value Pc= -..i.H,

+41 I

. Pt= --'+1 *, , 4-48

%0= - 3. (., .,.,~ 1 - .:::l * \ '7 a I Design Value %0= {(pc - pJ/pJ X 100% 4.0 o/o S

I Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/Tech Spec Not Applicable I

. Acceptance Criteria Reference Not Applicable I

__ - NO Design Tolerance is met Acceptance Criteria is met :

. ~YES

.,/

YES NO I VI

At The Just Critical Position Comments The allowable range will be set based on the above results, as well as results from the benchmark test.

I Allowable Range = - '-IG,. , -\-'V}

Prepared*By: ~ 7>. ~ Reviewed By:7/. - ~

I I

NE-1082 S2C14 Startup Physics Tests Report Page 42 of 56 I

I I

SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron.Concentration -ARO I Reference II Proc No / Section:

Bank Positions (Steps) 2-NPT-RX-008 Sequence Step No:

RCS Temperature (°F): 547 Power Level(% F.P.): 0 I Test Conditions SDA: 227 SOB: 227 CA: . 227 Other (specify):

Below Nuclear Heating (Design) CB: 227 CC: 227 CD: 227 I Ill Test Bank Positions (Steps) RCS Temperature (°F): 54Co.9 Power Level (% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify):

I (Actual) CB: 227 CC: 227 CD: 227 Datemme Test Performed:

Below Nuclear Heating ta/s /c,<o JJ:so I (C8)MARO; Critical Boron Concentration - ARO Measured Parameter I .IV (Description)

Test I Results Measured Value (Design Conditions)

(Ce)MARo= 1'Hot ppm I

Design Value C8 = 1986 +/- 50 ppm I (Design Conditions)

I V Reference FSAR/Tech Spec Technical Report NE-1074, Rev. 0 lcxC 8 x C8 °1 ~ 1000 pcm Acceptance I Criteria Reference Technical Specification 4.10.A

. _f_ YES I Design Tolerance is met Acceptance Criteria is met : ./ YES

- - NO NO VI I Comments aC 8 = -6.96 pcm/ppm Ce°= l(Ca)MARo- C 8 1; C8 is design value I Prepared B y : ~ ~ ~ Reviewed By: {J)//, .{;//Lr-.n

V I

T

I I NE-1082 S2C14 Startup Physics Tests Report Page 43 of 56

I I

SURRY POWER STATION UNIT 2 CYCLE 14 STARTU~ PHYSICS TEST RESULTS AND EVALUATION SHEET I I

Reference Test

Description:

Isothermal Temperature Coefficient - ARO*

Proc No I Section: 2-NPT-RX-008 Sequence Step No: I II Bank Positions (Steps) RCS Temperature {°F): 547 Test Conditions SDA: 227 SDB: 227 CA: 227 Power Level {o/o F.P.): 0 Other (specify):

I (Design) CB: 227 CC: 227 CD: 227 Below Nuclear Heating Ill Test Bank Positions (Steps} RCS Temperature (°F}: Slt(o.~

Power Level(% F.P.): 0 I

Conditions SDA: 227 SDB: 227 CA: 227 (Actual) CB: 227 CC: 227 CD: .?..\9 Other (specify):

Below Nuclear Heating I

Datemme Test Performed:

{g /5 /°l(p J3c; SI I Measured Parameter (ex TISO)ARO*, Isothermal Temperature (Description) Coefficient - ARO I IV Test Results Measured Value (ex

.T ISO) _

ARO - -o.<o, pcmt°F (Ce= lC)G,(p ppm)

I

. Design Value (Actual Conditions} (exTiso)ARo = -1.S'l :1:3.0 pcmfF (Ce= IC\ (o(p ppm)

I Design Value (Design Conditions} (ex TISO)ARO- _

-1.40:1:3.0 pcmfF I (Ce= 1986 ppm)

V Reference FSAR/COLR Technical Report NE-1074,Rev. 0 ex/j0 s 3.83* pcmfF I

ex/0 P = -1.67 pcmfF Acceptance Criteria Reference COLR 2.1.1, Technical Report NE-1074, Rev. O I Design Tolerance is met Acceptance Criteria is met :

./ YES

_ _ NO NO I

VI Comments *Uncertainty on ixTMOD= 0.5 pcmPF (

Reference:

memorandum from I C.T. Snow to E.J. Lozito dated June 27, 1980.)

I Prepar:ed By: ~Q.=)t\_&..e~ Reviewed By: Jfi. ~ / , I --

I I I - -

I NE-1082 S2Cl4 Startup Physics Tests Report Page 44 of 56 I

I I

SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Critical Boron Concentration - B Bank In I Reference II Pree No / Section:

Bank Positions (Steps) 2-NPT-RX-008 Sequence Step No:

RCS Temperature (°F): 547 I Test Conditions SDA: 227 SDB: 227 CA: 227 Power Level(% F.P.): 0 Other (specify):

(Design) CB: 0 CC: 227 CD: 227 Below Nuclear Heating I Ill Test Bank Positions (Steps) RCS Temperature (°F): 54, .. 0 Power Level (% F.P.): O Conditions SDA: 227 SDB: 227 CA:. 227 Other (specify):

I (Actual) CB: 0 CC: 227 Datemme Test Performed:

CD: 227 Below Nuclear Heating I <.o/ li, {9(o 04:,4<.;

Measured Parameter (Ce)Me; Critical Boron Concentration, I IV (Description) B Bank In I Test Results Measured Value (Ce)Me= \tlo3 ppm

. (Design Conditions)

I -

Design Value Ce= 1782+aCe Pnw +/- (10 + 142.5/laCel> ppm I (Design Conditions) Ce= l1Co3 +/- 30 ppm I V Reference FSAR/Tech Spec Technical Report NE-1074, Rev. 0 Not Applicable Acceptance I Criteria Reference Not Applicable

_ _ NO I Design Tolerance is met Acceptance Criteria is met : J

./ YES YES NO VI I Comments aC 8 = -6.99 pcm/ppm M

a Ce Prev = (Ca) ARO - 1986 ppm I Prepared By: ~0 Reviewed By: c}j(((-rff~ ~

7 I

I NE-1082 S2C14 Startup Physics Tests Report Page 45 of 56

I I

SURRY POWER STATION UNIT 2 CYCLE 14

STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test

Description:

Control Bank B Worth Measurement, Rod Swap Ref. Bank Reference II Pree No / Section:

Bank Positions {Steps) 2-NPT-RX-008 Sequence Step No:

RCS Temperature {°F): 547 I

Test Conditions SDA: 227 SOB: 227 CA:. 227 Power Level {% F.P.): 0 Other {specify): I

{Design) CB: moving .CC: 227 CD: 227 Below Nuclear Heating Ill Test Bank Positions {Steps) RCS Temperature (°F): . 'S'-\1 .. ;)..

Power Level (% F.P.): 0 I

Other (specify):

Conditions SDA: 227 SOB: 227 CA:.

(Actual) CB: moving CC: 227 CD:

227 227 Below Nuclear Heating I Datemme Test Performed:

lD Ito lct<P 01 ~O°t IBREF.I Integral Worth Of Control Bank B, I

Measured Parameter IV

{Description) All Other Rods Out I I REF_

Test Results Measured Value B - \4:,S. l pcm I

Design Value (Design Conditions) 18 REF= 1425 :1: 143 pcm I

Reference Technical Report NE-1074, Rev. 0 I

If Design Tolerance is exceeded, SNSOC shall V

Acceptance FSAR/Tech Spec evaluate impact of test result on safety analysis.

SNSOC may specify that additional testing I

Criteria be performed.

Reference VEP-FRD-36A I

. _ _ NO Design Tolerance is met Acceptance Criteria is met :

_:L_ YES

___£ YES __ NO I VI Comments I

~

I Prepared By: A4L:~~ Reviewed By: ~ .

I I

NE-1082 S2Cl4 Startup Physics Tests Report Page *46 of 56 I

I I

SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

HZP Boron Worth Coefficient Measurement I Reference II Proc No I Section:

Bank Positions (Steps) 2-NPT-RX-008 Sequence Step No:

RCS Temperature (°F): 547 I Test Conditions SDA: 227 SOB: 227 CA: 227 Power Level(% F.P.): 0 Other (specify):

(Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating I Ill Test Bank Positions (Steps) RCS Temperature (°F): 54~~

Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 CA: 227 Other (specify):

I (Actual) CB: moving CC: 227 CD: 227 Datemme Test Performed:

Below Nuclear Heating I ~Is'°'~ ;;J:l". so .,

Measured Parameter aC 8 ; Boron Worth Coefficient I IV (Description)

I Test Results Measured Value aC 8 = -,.03 pcm/ppm .. ,*

I <>:-.,.

Design Value aC 8 = -6.99 :1: 0.70 pcm/ppm I (Design Conditions)

I V Reference FSAR/Tech Spec Technical Report NE-1074, Rev. 0 Not Applicable Acceptance I Criteria Reference Not Applicable

. _ _ NO I Design Tolerance is met Acceptance Criteria is met :

./ YES

--:T YES NO VI I Comments I Prepared B y : ~ ~ "--A--~ Reviewed By:

I Z!Hct!JL ..

I ( l 1v* V.

I I NE-1082 S2G14 Startup Physics Tests Report Page 47 of 56

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SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I

Reference Test

Description:

Control Bank D Worth Measurement, Rod Swap Proc No / Section: 2-NPT-RX-008 Sequence Step No: I II Bank Positions (Steps} RCS Temperature (°F}: 547 Test Conditions SDA: 227 SOB: 227 CA:. 227

Power Level(% F.P.}: 0 Other (specify):

I (Design) CB: moving CC: 227 CD: moving Below Nuclear Heating Ill Test Bank Positions (Steps) RCS Temperature (uF}:

Power Level (% F.P.}: 0 54'*, I Conditions SDA: 227 SOB: 227 (Actual) CB: moving CC: 227 CA:. 227 CD: moving Other (specify}:

Below Nuclear Heating I

Datemme Test Performed:

';,t,, , oss;{ I Measured Parameter 10 Rs; Integral Worth of Control Bank D, (Description) Rod Swap I IV Test Measured Valu~ I RS_

D - I f5'ir, 3 (Adjusted Measured Critical Reference Bank Position = ,, 'Z- steps)

I Results Design Value (Actual Conditions) lls= ff "73_ 1 (Adjusted Measured Critical Reference Bank Position = "7- steps)

I Design Value (Design Conditions) 10 Rs= 1149 +/- 172 pcm I (Critical Reference Bank Position = 181 steps)

Reference FSAR/Tech Spec Technical Report NE-1074, Rev. 0, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall I

V Acceptance Criteria evaluate impact of test result on safety analysis.

SNSOC may specify that additional testing I be performed.

Reference Design Tolerance is met ..

VEP-FRD-36A

_,,._YES _ _ NO I Acceptance Criteria is met : .,, YES NO VI Comments I

I Prepared By: .4~- {/~ Reviewed By: ~ JJ. P~

I NE-1082 S2C14 Startup Physics Tests Report Page 48 of 56 I

I I

SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Control Bank C Worth Measurement, Rod Swap I Reference II Pree No / Section:

Bank Positions (Steps) 2-NPT-RX-008 Sequence Step No:

RCS Temperature (°F): 547 Test Power Level(% F.P.): O I Conditions SDA: 227 SDB: 227 CA:. 227 Other (specify):

(Design) CB: moving CC: moving CD: 227 Below Nuclear Heating I Ill Test Bank Positions (Steps) RCS Temperature (°F): S'4',-4l Power Level (% F.P .): 0 Conditions SDA: 227 SDB: 227 CA:. 227 Other (specify):

I (Actual) CB: moving CC: moving CD: 227 Datemme Test Performed:

Below Nuclear Heating

';, /'iG. J O"'Z-3 I leRS; Integral Worth of Control Bank C,

~,:=-

Measured Parameter I {Description) Rod Swap IV Measured Value I RS_ 7s<i. s {Adjusted Measured Critical I .Test Results Design Value C -

Reference Bank Position= 10

~ steps)

I RS_ ,, 7. "I I {Actual Conditions) C - (Adjusted Measured Critical Reference Bank Position = 1" ' steps)

Design Value I (Design Conditions) t/5= 775 +/- 116 pcm (Critical Reference Bank Position= 122 steps)

Reference I FSAR/Tech Spec Technical Report NE-1074, Rev. 0, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.

I Acceptance Criteria SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A I Design Tolerance is met Acceptance Criteria is met :

. v VYES YES _ _ NO NO I VI Comments I I Reviewed By: bJ, p~

I I NE-1082 S2C14 Startup Physics Tests Report Page 49 of 56

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SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I

Reference Test

Description:

Control Bank A Worth Measurement, Rod Swap Pree No / Section: 2-NPT-RX-008 Sequence Step No: I II Bank Positions {Steps) RCS Temperature (°F): 547 I

Test Power Level(% F.P.): 0 Conditions SDA: 227 SOB: 227 Ck. moving Other (specify):

{Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Test Bank Positions {Steps) RCS Temperat_ure (°F): S'f7. /

Power Level(% F.P.): 0 I

Conditions SDA:

{Actual) 227 SOB:

CB: moving CC:

227 227 Ck. moving CD: 227 Other {specify):

Below. Nuclear Heating I Datemme Test Performed:

'/r..h, I . o7Z.$

I 5

Measured Parameter l/ ; Integral Worth of Control Bank A, (Description) Rod Swap I

. I z z IV Test Measured Value RS_

A -

Sc:>. {Adjusted Measured Critical Reference Bank Position = , o steps)

I Results Design Value

{Actual Conditions) 1/S= ?-~1.'i5 .(Adjusted Measured Critical Reference Bank Position = Co steps)

I Design Value

{Design Conditions) 1/s= 268 100

+/- pcm I (Critical Refe*rence Bank Position= 72 steps)

Reference FSARffech Spec Technical Report NE-1074, Rev. 0, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall I

V evaluate impact of test result on safety analysis.

Acceptance Criteria SNSOC may specify that additional testing be performed.

I Reference Design Tolerance is met .

VEP-FRD-36A

~YES __ NO I Acceptance Criteria is met : VYES NO VI

comments I

I Prepared By: ,4:d: v144 Rev *1ewed By*. ~ ~ . ?.~ !~ c_

I NE-1082 S2Cl4 Startup Physics Tests Report Page 50 of 56 I

I I SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Shutdown Bank B Worth Measurement, Rod Swap I Reference II Pree No / Section:

Bank Positions (Steps) 2-NPT-RX-008 Sequence Step No:

RCS Temperature (°F): 547 Test Power Level(% F.P.): O I Conditions SDA: 227 SOB: moving Ck 227 (Design) CB: moving CC: 227 CD: 227 other (specify):

Below Nuclear Heating I 111 Test Bank Positions (Steps) RCS Temperature (°F): S'4'--'l Power Level (% F .P .): 0 Conditions SDA: 227 SOB: moving CA: 227 other (specify):

I (Actual) CB: moving CC: 227 Datemme Test Performed:

CD: 227 Below Nuclear Heating

'/r,.jc,r;,) OHO I Measured Parameter lseRs; Integral Worth of Shutdown Bank 8, I (Description) Rod Swap IV Measured Value lseRS= // 5".2.5' (Adjusted Measured Critical I Test Results Design Value IC.I Reference Bank Position = ~ eps)

~ l'"° 11,<}. l I (Actual Conditions) Isa RS= (Adjusted Measured Critical '

,,, i.M*~

Reference Bank Position= J.',C"""'steps)

Design Value I (Design Conditions} lseRS= 1190 +/- 179 pcm (Critical Reference Bank Position= 182 steps)

Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A I V FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.

I Acceptance Criteria SNSOC may specify that additional testing be performed.

Reference VEP-FRD-36A I Design Tolerance is met Acceptance Criteria is met .

~YES

.... YES

_ _ NO NO I VI Comments I Prepared By: ~ - t / ~ Reviewed By: ~ ...2. ~

I I I NE-1082 S2C14 Startup Physics Tests Report Page 51 of 56

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SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I I Test

Description:

Shutdown Bank A Worth Measurement, Rod Swap Reference II Proc No / Section:

Bank Positions (Steps) 2-NPT-RX-008- Sequence Step No:

RCS Temperature (°F): 547 I

Test Conditions SDA: moving SOB: 227 CA:. 227 Power Level(% F.P.): 0 Other (specify): I (Design) CB: moving CC: 227 CD: 227 Below Nuclear Heating Ill Test Ba_nk Positions (Steps) RCS Temperature (°F): 54'.'j Power Level(% F.P.): O I

Conditions SDA:. moving SOB: 227 CA:. 227 Other (specify):

(Actual) CB: moving CC: 227 CD: 227 Daternme Test Performed:

Below Nuclear Heating I r;, /ti:., /t:it>' oi<<o I

Measured Parameter ISARs; Integral Worth of Shutdown Bank A, (Description) Rod Swap I

IV Measured Value I RS_ /o9 .;.i (Adjusted Measured Critical SA -

Test Results Design Value.

Reference Bank Position = IS'/ steps) I II 3 c,. er (Actual Conditions) ISARs= (Adjusted Measured Critical Reference Bank Position = /SI steps)

I Design Value (Design Conditions) ISARs= 1034 +/- 155 pcm (Critical Reference Bank Position= 172 steps)

I Reference FSAR!Tech Spec Technical Report NE-1074, Rev. 0, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC shall I V evaluate impact of test result on safety analysis.

Acceptance Criteria SNSOC may specify that additional testing be performed.

I Reference VEP-FRD-36A Design Tolerance is met

. Acceptance Criteria is met :

. _.,_ YES

.,, YES

_ _ NO NO I

VI Comments I Prepared By: ~ t/<<14 Reviewed Hy:

-;l-**

-*- - 2.I,,)

"/

I

<./

I NE-1082 S2Cl4 Startup Physics Tests Report Page 52 of 56 I

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SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test

Description:

Total Rod Worth, Rod Swap I Reference II Pree No I Section:

Bank Positions (Steps) 2-NPT-RX-008 Res*

Sequence Step No:

Temperature (°F): 547 Test Power Level(% F.P.): 0 I Conditions (Design)

SDA: moving SDB: moving CA:. moving CB: moving CC: moving CD: moving Other (specify):

Below Nuclear Heating I Ill Test Bank Positions (Steps) RCS Temperature (°F): S47.-Z..

Power Level(% F.P;): 0 Conditions SDA: moving SDB: moving CA:. moving Other (specify):

I (Actual) CB: moving CC: moving CD: moving Datemme Test Performed:

Below Nuclear Heating I C /r, /c,fe. '

Measured Parameter 01 ot:t lro1a1: Integral Worth of AU Banks, I (Description) Rod Swap IV Measured Value Ir~=- S*'f. s pcm

'I .. ,'

I Test !

Results Design Value sci 3s. 7..

I (Actual Conditions) lro1a1= pcm

\ ~-r.;o.

.'i Design Value I (Design Conditions) l;-0131= 5919 +/- 592 pcm Reference Technical Report NE-1074, Rev. 0, VEP-FRD-36A I V FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.

I Acceptance Criteria Additional testing must be performed.

Reference VEP-FRD-3SA I Design Tolerance is met Acceptance Criteria is met :

_LYES

.,,, YES

_ _ NO NO I VI Comments -*

I Prepared By: 4~ t.1. (;( Reviewed By: -~~2.(

I I NE-1082 S2C14 Startup Physics Tests Report Page 53 of 56

I I

SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST.RESULTS AND EVALUATION SHEET I

I Reference Test

Description:

MID Flux Map - At Power Proc No / Section: 2-NPT-RX-008 ,002 Sequence Step No:

I II Bank Positions {Steps) RCS Temperature {"'F): T REF= 1 Test Conditions SDA: 227 SOB: 227 CA: 227 Power Level(% F.P.): s 30 Other (specify):

I

{Design)

Ill CB: 227 CC:

BankPositions (Steps)

CD: Must have ~ 38 thimbles**

RCS Temperature (°F}: Trc.f I Test Power Level(% F.P.): ;24-. "3 %

Conditions SDA: 227 SOB: 227 (Actual) .CB: 227 CC: :2.~'1 CD: 15' i CA: 227 Other (specify):

I Datemme Test Performed: 4,.:2. Thi r')'} 6 \es to/~j9G, ,oo'-1-3 Maximum Relative Nuclear Enthalpy Total Heat Maximum I

Measured Parameter Assembly Power%DIFF Rise Hot Channel Factor Flux Hot Channel Positive lncore Quadrant I

IV (Description) (M-P)/P FAH(N) Factor F0 (Z) Power lilt Test Results Measured Value

- "1, 1 "h:..- P '!: 0. G\O 4.'I "'"' p,40.qo I. '5~<g ;J. ;;291 l,Olll, I Design Value (Design

t:10% for P1 :i:0.9

t:15% for P1<0.9 N/A NIA ~ 1.0203 1*

Conditions) (P1= assy power)

Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 I

V FSAR/COLR None None Acceptance Criteria Reference None F"1H(N)s1.56(1+0.3(1-P))

COLR2.4 Fo(Z)s4.64"K(Z)

COLR2.3 None I

Design Tolerance is met . _:f_ YES _ _ NO I Acceptance Criteria is met : ....:L_ YES NO

. VI

As required Comments - Must have at least 16 thimbles for quarter core maps for multi-point calibrations I

I I

P.repared By: ~ 'D. ~* Reviewed B y ~ C2!/,4i' I

NE-1082 S2C14 Startup Physics Tests Report Page 54 of 56 I

I I

SURRY POWER STATION UNIT 2 CYCLE 14 I STARTUP.PHYSICS TEST RESULTS AND EVALUATION SHEET I I Reference Test

Description:

M/0 Flux Map - At Power Proc No I Section: 2-NPT-RX-008 ,002

Sequence Step No:

II Bank Positions (Steps) RCS Temperature ("'F): T REF+/- 1 I Test Conditions SDA: 22.7 SDB: 227 CA:. 227 Power Level (% F.P.):65 s P s Other (specify):

75 (Design) CB: 22.7 CC: 227 CD:

Must have ~ 38 thimbles-I Ill Bank Positions (Steps) RCS Temperature (°F): ~

Test Power Level (% F.P.): 70

j{ J I Conditions SDA: 22.7 SDB: 227 CA:.

(Actual) CB: 22.7 CC: 227 CD:

227 J/'/

Other (specify):

'/J -rt,-_Jft,}

Date/Time Test Performed:

I ~/?/?I / () "'(;,

Maximum Relative Nuclear Enthalpy Total Heat Maximum I Measured Parameter Assembly Power%D1FF Rise Hot Channel Factor Flux Hot Channel Positive lncore Quadrant IV (Description) (M-P)/P F.:\H(N) Factor F0 (Z) Power Tift I Test Results Measured Value

,_,., f,1" p ~"*

6/. I" 1,,,, P tC,. ,~ /, '{7? /,770 /. t'D:J y'° Design Value :t:10% for P1 ~0.9 I (Design Conditions)

1:15% for P1<0.9 cP1 = assy power)

NIA NIA :s: 1.0202 I Reference WCAP-7905, Rev. 1 None None WCAP-7905, Rev.1 V FSAR/COLR None FAH(N):s:1.56(1+o.3(1-P)) Fa(Z):s:2.32/P"K(Z) None I Acceptance Criteria Reference None COLR 2.4 COLR2.3 None I Design Tolerance is met .. _JL YES __ NO Acceptance Criteria is met : r/ YES NO I VI

As required Comments ** Must have at least 16 thimbles for quarter core maps for multi-point calibrations I

I Prepared By: cftf:* ~

Reviewed By: ~-#(~

I I NE-1082 S2C14 Startup Physics Tests Report Page 55 of 56

I SURRY POWER STATION UNIT 2 CYCLE 14 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I

I Test

Description:

M/D Flux Map - At Power 1*

Reference Pree No /. Section: 2-NPT-RX-008 ,002 Sequence Step No:

II Test Bank Positions (Steps) RCS Temperature (uF): T REF+/- 1 Power Level(% F.P.):95 .s: P .s; 100 Ii Conditions SDA: 227 SOB: 227 CA: 227 Other (specify):

(Design) 111 CB: 227 CC:

Bank Positions (Steps) 227 CD:

Must have ~ 38 thimbles**

RCS Temperature (°F):

s,3 I

"2.2(.o Power Level(% F.P.): \CO. rj'c) S0 Test Conditions SDA: 227 SOB: 227 CA: 227 Other (specify): I (Actual) CB: 227 CC: 227 CD:

Date/Time Tes Performed:

1 .r:, ,3)c,<o toeP I

Maximum Relative Nuclear Enthalpy Total Heat Measured Parameter Assembly Power%DIFF Rise Hot Channel Factor Flux Hot Channel Maximum Positive lncore Quadrant I

IV Test (Description)

Measured (M-P)/P

.... 3. '3 ~ p ?'0.1 FAH(N) Factor Fa(Z)

\.'c,S1 Power Tilt

\,CC'-t I "5.4io f LD.&l. (.Lf'5 I b.Lj fo Results Value Design Value :10% for Pi :.!:0.9

, .ea; <..a tJ.,,:,

~ ...., I (Design :15% for P1<0.9 NIA N/A s 1.0202 Conditions)

Reference (Pi = assy power)

WCAP-7905, Rev. 1 None None WCAP-7905, I Rev.1 V

Acceptance FSAR/COLR None F !J.H(N)s1 .56(1+0.3(1-P)) Fa(Z)s2.32/P.K(Z) None I

Criteria None COLR2.4 COLR2.3 None Reference Design Tolerance is met. _L.YES _ _ NO '

I VI Acceptance Criteria is met :

As required

__LYES NO I

Comments ** Must have at least 16 thimbles for quarter core maps for multi-point calibrations I

r

- 11 I

Prepared By: '.- tt!la,~1-r11 C/ - -

Reviewed By:

1<<<<4 M I I

NE-1082 S2C14 Startup Physics Tests Report Page 56 of 56 I

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ML18151A976: Difference between revisions

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