Text

Rev 0 to NE-1133, North Anna Unit 1,Cycle 13 Startup Physics Tests Rept, Aug 1997
	ML20198G540
Person / Time
Site:	North Anna
Issue date:	08/31/1997
From:	Ford C, Main A, Mirilovich J; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20198G516	List: ML20198G512; ML20198G540;
References
	NE-1133, NE-1133-R, NE-1133-R00, NUDOCS 9709040145
	Download: ML20198G540 (59)
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Unit 1, Cycle D StartuP Physics .
Tests Report g
L Nuclear Analysis andFuel
. NuclearEngineering & Services August,1997 O
VIRGINIA POWER
, a .; 1 a -
r -
> A :;) ' y a c. . - ,g 71 A P [)f ?
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TECHNICAL REPORT NE-1133 - REV. O NORTH ANNA UNIT 1, CYCLE 13 STARTUP PIIYSICS TESTS REPORT l
l NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES VIRGINIA POWER AUGUST 1997 PREPARED BY: '
8'N7 J. M.' Mirilovich Date REVIEWED BY: P~I 3 ~ 77 C. A. Ford Date REVIEWED BY: bW
/A. P. Main ate APPROVED BY:
7/
D. Dzia@osz
[ Date QA Category: Nuclear Safety Related Keywords: NIC13, Startup
. e CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report ar any of t,he data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability r..id disclaimers of warranties provided herein. In no event shall the Company be liable, under any Icgal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical lujury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.
I NE-1133 NIC13 Startup Physics Tests Report Page 1 of 57 J
TABLE OF CONTENTS PAGE Classification / Disclaimer............................... 1 Table of Contents.............................. ........ 2 ,
List of Tcb1es.......................................... 3 List of Fi;ures......................................... 4 Preface................................................. 5 Section 1 Introduction and Summary................... 7 Section 2 Control Rod Drop Time Measurements. . . . . . . . . 17 i
Section 3 Control Rod Bank Worth Measurements . . . . . . . . 22 Section 4 Boron Endpoint and Worth Measurements...... 27 a
Section 5 Temperature Coefficient Measurement........ 31 l Section 6 Power Distribution Measurements . . . . . . . . . . . . 33-Section 7 References................................. 40 -
APPENDIX- Startup Physics Test Results and Evaluation Sheets........................ 41 NE-1133 ' N1013 Startup Physics Tests Report Page 2 of 57
C LIST OF TABLES TABLE TITLE PAGE l- 1;1 Chronology of Tests................................... 11 l 2.1 Hot Rod Drop Time Summary............................. 19 l
l '3.1 Control Rod Bank Worth Summary........................ 24
.4.1. Boron Endpoints Summary............................... 29 '
5.1 Isothermal Temperature Coefficient Summary............ 32
. 6.1 Incore Flux Hap Summary............................... 35 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits...................... 36 NE-1133- NIC13 Startup Physics' Tests Report Page 3 . of 57
LIST OF FIGURES TITLE PAGE FIGURE' 1,1 Core' Loading Map....................is................... 12 l
1.2- Beginning of Cycle- Fuel Assembly Burnups. . . . . . . . . . . . . . . . . 13 1.3 Available Incore Moveable Detector Locations............. 14 11.4 Assembly Insert Locations................................ 15 1.5- Cont rol R od Locat ions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 2.1' Typical Rod Drop Trace................................... 20 2.2 Rod . Drop Time - Hot Fu11' Flow ' Conditions . . . . . . . . . . . . . . . . . 21 3.1 Control Bank B Integral Rod Worth - HZP ................. 25
-3.2 Control Bank B Differential Rod Worth - HZP.............. 26 4.1 Boron Worth Coefficient.................................. 30 6.1 Assemblywise Power Distribution - 25% Power. . . . . . . . . . . . . . 6.2- Assemblywise Power Distribution - 74% Power.............. 38 6.3 Assemblywise Power Distribution - 97% Power.............. 39 NE-1133 N1C13 Startup Physics Tests Report Page 4 of 57 -
i
. l l
i 1
1 PREFACE '
l This report presents the analysis and evaluation of the physics tests which were performed to verify that the North Anna Unit 1, Cycle 13 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of thin report to discuss 4 the particular methods of testing or to present the detailed data taken.
Staadard testing techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at the North Anna Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design predictions, and an evaluation of the results.
The North Anna Unit 1, Cycle 13 startup physics tests results and evaluation sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the scartup test results in a consistent format. The design test conditions and design values (at design conditions) of the measured parameters were completed prior to the startup physics testing.
' The entries for the design values ,ere based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group1 . During the tests, the data sheets were used as guidelines both NE-1133 NIC13 Startup Physics Tests Report Page 5 of 57
l _
to verify that the proper test conditions were eet and to it.cilitate the preliminary comparison between measured and predicted test results, thus enabling a quick identification of possible problems occuring during the l tests.
l NE-1133 'NIC13 Startup Phys'ics Tests Report Page 6 of 57
O SECTION 1 l'
INTRODUCTION AND
~~SUMMARY~~
On May 11, 1997 Unit No.1 of the North Anna Power Station shutdown
-for its twelf th refueling. During this shutdown, 73 of the 157 fuel assemblies in the core were replaced with 60 fresh fuel assemblies, 5- !
once-burned fuel assemblies, and 8 twice-burned fuel assemblics. The thirteenth cycle core - consists of 1( sub-batches of fuel: four once-burned batches, four assemblies Crom Cycle 4 (part of batch 6), two batches from Cycle 12 (batches 14A and 14B) and one batch from Cycle 7
'(batch 9A): four twice-burned batches, four assemblies from' Cycles 4 and 5-(bctch 6), two batches from Cycles 11 and 12 (batches 13A and 13B) and one batch f rom Cycles 6 and 7 (batch 8B); and three fresh batches (' batches 15A. ISB, and 15C).
l Changes incorporated into the NIC13 reload core include: four lead test assemblies (LTAs) manufactured by Framatome Cogema Fuels (FCF),
burnable poisen inserts with an axially shorter absorber region, five reconstituted fuel assemblics, and discontinuing the use of secondary-neutron source inserts. The four LTAs are of a 'similar design to _ the resident Westinghouse fuel assemblies with the following exceptions: use of dif ferent- zirconium-based alloys for the fuel rod cladding and fuel assembly structural tubing, some grid dimensional differences and use of three mid-span mixing grids, higher nominal fuel pellet density, a reconstitutable quick release top nozzle design and a fine mesh debris filter bottom nozzle, and the use of the FCF's axially " floating" grid NE-11331 ~N1C13 Startup Physics Tests' Report-Page 7 of 57
-_. =_ - ._ _ .-- - - - - . - .- -. - - . ~ - - - . . . . . . - - _ - . -
1 .
i
~~design. The burnable poison inserts use an absorber region that is 126 4~~
inches in length (which is nearly centered in the active fuel region) i.
j versus the 142 inch product (which was nearly the full active fuel length)
used in previous cycles, otherwise the burnable poison inserts are the i I same as in previous cycles. The five reconstituted fuel assemblies are
~~once-burned assemblies which contain a total of nine replacement solid i~~
l stainless steel reconstituted rods. Since it has been determined that j secondary neutron sources are no longer necessary to maintain adequate 4
4 source range detector count rates during offload, onload, and approach to criticality using current loading strategies, there were no secondary neutron sources loadedin NIC13.
4 Cycle 13, similar to Cycle 12, incorporated the burnabic poison rod design made of B4 C in Alumina, which is available in various enrichments of B 4C. There are no thimble plugging devices inserted in ,, N IC 13.
I i Reference 1 provides a more detailed description of the Cycle 13 core.
i
~~The core loading pattern and the design parameters for each sub-batch 4 are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2 i~~
~~and documented-in Reference 6. The available incore moveable detector i~~
~~f. locations used for the flux map analyses are identified in Figure 1.3.~~
Figure 1.4 identifies the location and number of burnable poison rods and
= source assemblies for Cycle 13, and Figure 1.5 identifies the location and number of control rods in the Cycle 13_ core.
]
On June 10, 1997 at 04:48, the Cycle 13 core achieved initial criticality. Following criticality, startup physics tests were performed 2
as outlined' ini Table - 1.1. A summary of the results of these tests 1
[ follows:
NE-1133 NIC13'Startup Physics Tests Report Page 8 of 57
- - - - - - -- - . . . _ ~ . . _ . - - - - - .. ._. _ - - - , -
~~1. The measured drop time . of each control rod was within the 2.7 second limit of Technical Specification 3.1.3.4.~~
2. Individual control rod bank worths were measured using the rod swap technique 88 5 and the results were within 8.7% of the design predictions. The sum of the individual measured control rod bank worths was within 0.9% of the design prediction. These results are within the design tolerance of 115% for individual bank worths (110% for the rod swap reference bank worth) and the design
~~! tolerance of 110% for the sum of the individual control rod bank worths.~~
~~3. Measured critical boron concentrations for two control bank configurations were within 25 ppe of the design predictions.~~
These results were within the design tolerances and also,, met the Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 11% Ak/k of the design prediction.
~~4. The boron worth coef ficient measurement was within -4.6% of the design prediction, which is within the design tolerance of 10%.~~
5. The measured isothermal temperature coefficient (ITC) for the all-rods-out (ARO) configuration was within 1.15 pcm/'F of the design prediction. This result is within the design tolerance of 13 pcm/'F. The measured ITC of -1.90 pcm/*F meets the Core Operating Limits Report (COLR) 2.1.1 criterion that the moderator temperature coefficient (MTC) be less than or equal to +6.0 NE-1133- NIC13 Startup Physics Tests Report Page 9 of 57
O pcm/'P. When the Doppler temperature coefficient and a 0.5 pcm/'F uncertainty are accounted for in the MTC limit, the MTC l requirement is satisfied as long as the ITC is less than or equal to +3.76 pcm/'F.
~~6. Mode 1 (see Reference 4) core power distributions sere within~~
! established design tolerances. Generally, the measured core power distributions were within 1.1% of the design predictions.
The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-Dil(N), were within the limits of COLR Sections 2.5.1 and 2.6, respectively.
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.
f 1
NE-1133 NIC13 Startup Physics Tests Report Page 10 of 57
Table 1.1 NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS l
CHRONOLOGY OF TESTS i
l l
l- Reference .
Test Date Time Power Procedure Hot Rod Drop - dot Full Flow 6/09/97 0819 HSD 1-PT-17.2- .
Zero Power Testing Range 6/10/97 0539 HZP 1-PT-94.0 Reactivity Computer Checkout 6/10/97 0628 HZP 1-PT-94.0 Temperature Coefficient - ARO 6/10/97 1045 HZP- 1-PT-94.0 Boron Endpoint - ARO 6/10/97 0958 HZP 1-PT-94.0 Bank B Worth 6/10/97 1222 HZP 1-PT-94.0 Boron Endpoint - B in 6/10/97 1625 HZP 1-PT-94.0 Bank D Worth - Rod Swap 6/10/97 1645 HZP- 1-PT-94.0 Bank C Worth - Rod Swap 6/10/97 1731 HZP 1-PT-94.0 Bank A Worth - Rod Swap 6/10/97 1758 HZP 1-PT-94.0 Bank SB Worth - Rod Swap 6/10/97 1820 HZP 1-PT-94.0 Bank SA Worth - Rod Swap 6/10/97 1849 HZP 1-PT-94.0 Flux Map - 25% Power
^
6/11/97 0413 25% 1-PT-94.0 Peaking Factor Verification 1-PT-21.1
& Power Range Calibration PT-21.2 1-PT-22.4 Flux Map - 74% Power- 6/13/97- 0200 74% 1-PT-94.0 Peaking Factor Verification 1-PT-21.1 6 Power Range Calibration 1-PT-21.2 1-PT-22.4 Flux Map - 97% Power 6/26/96 1017 97%- 1-PT-94.0 Peaking Factor Verification 1-PT-21.1 3
& Power Range Calibration 1-PT-21.2 1-PT-22.4 NE-1133~ N1C13 Startup Physics Tests Report Page 11 of 57 1
Figure 1.1 NORTil ANNA UNIT 1 - CYCLE 13 CORE LOADING MAP J H G F t o C s A a P M M t a I tas 13a I 13s l l 3C6 4C6 1 SC7 l &
I i 13a tea i ist its tsa I asa 134 l 1 tc2 . 007 ' 4t e 509 i rt6 205 IC6 I r*
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aSSEMsLY TYPt NUMatR OF aSSEMstat$ e 4 1 4 tr is 36 24 3r 4 264 264 264 264 264 264 264 264 FUtl RODS PER ASSEMsLY r64 264 i
I NE-1133 NIC13 Startup Physics Tests Report Page 12 of 57
l l
(
Figure 1.2 NORTH ANNA UNIT 1 - CYCLE 13 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R P N M L E J H C F E D C & a 1 3C6 1 4C4 i SCF l 1 34789 15231 34313 1 1 I l IC2 1 tot 4t4 1 509 l it6 205 l IC6 l l M9391 21637 ,
e, 17664: c ' 219es stellt t I l ' '
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Figure 1.3 NORTH ANNA UNIT 1 - CYCLE 13 AVAILABLE INCORE MOVEABLE DETECTOR LOCATIONS a p M M L E J H C F E D C & &
1 I M I i
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Moveable Detector l 11 l MD l 15 es - Locations Not available f or l l Fluu Maseleg System for Cycle 13 NE-1133- NIC13 Startup Physics Tests Report Pagc. 14 of 57
0 C
i i
Figure 1.4 I NORTH ANNA UNIT 1 - CYCLE 13 r ASSENBLY INSERT LOCATIONS J M C F E D C 3 A R P M M L K l
l 1 l l l $P 1 SP 1 1 l
l. I RCC 1 BP5961 EC SP595 RCC I 1 2 I l_c! ! I h I w 1 #1p e4P 1 Flp I, 6P l l ll l BP6 6' BP6te WCC BPsat RCC BP6tl l SP6tel 3 I I 1 I l I I l ftp I ,
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l 1 . 6P 1 l 24P l rep l 16p ll 24P l- I #4P l l SP 1 1 1 1. BP6ee RCC I SP5761 !! BP592I RCC AP M6I RCC Sp5tal RP5771 RCC i BP596 1 7 l l l 1 ._I I I 24P ,
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l h 6P E!P l II #4P I f!P 1 6P I l- 1 SP633 SP6151 RCC BP546' RCC ' BP6161 Sp631 1 13 1 I 'l .
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15 6P - 6 SupmanLE PO!50N R00 Cluster l i 11 16P - 16 tuumaltt PolsOn ROD CtusitR I I I Ftp + to tunnatLE POISON N00 CLuSIER tip 21 tuumattE Puls0M R00 Clusite ttP
~~22 suRNatLE POISON ROO ClusitR F4p~~
~~26 SuRhatLE Pol $0M ROD CLUSTER RCC~~
~~FutL LENGTH CONTROL ROO I muP l~~
~~e CF SP A00$~~
1 BPee8 or RCC l = SP 655EMSLv 10 or RCC I I NE-1133: N1C13 Startup Physics Tests Report Page 15 of 57
i Figure 1.5 NORTH ANNA UNIT 1 - CYCLE 13 CONTROL ROD LOCATIONS J H C F E D C B A R P N M L K las' i
N-35 I i i i 1 1 I I I I lA I 10 l lA I I 2 1 1 I I I I I I N-41 '1 I l l sA l l sA l l l- l' N 43 3 I I I I I I I I I I IC 1 is t l l 1 s- 1 lC 1 I 4 I
1 I l._ l I I l l I I I I I I I I sa i i i 1. 1 I sa i i i i s l I I I I I I I I I I I I I 1s l Io l lC 1 Io i Is i lA 1 6 IA i I i 1 _I i 1 1 I I -I
- I I I I I I I sA 1 1 I I sa 1 i se i i l i sA I i 1 7 I I I l l l 1 1 I I I I I I I i 90'- 1 ID l l l lC l l l lC 1 l l 1e l l - 270' S I I I l i I i i l I I I I I I I i ss i I ss I i i sA I 9 I I I sA i l i I I l I I I I I I I I I I I I I i 1 1 IA I Ia i lo l lC 1 Io l ls l IA 1 le i I I I I I I I I I I I I I I I I I ss l l l 1 1 I so I I i 1 11 1 I I I I I I I I I I I i 1, I IC l ls l l l ls t lC l l 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 l l l l l l l N 42 l iA I Io i IA I i 14 I I I I I I I I I I I I is l I I I Absorber N-36 Notorial Ag In Cd I o'
Function Number of Clusters Control Bank D 8 Control Bank C &
Control Bank B. 8 Control Bank A 8 shutdown Bank $8 8 shutdown Bank SA 8
'NE-1133' NIC13 Startup Physics Tests Report- Page 16 of 57
SECTION 2 CONTROL ROD DROP TIME HEASUREMENTS The drop time of each control rod was measured at hot full-flow reactot 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 less than or equal to the maximum allowed by Technical Specification 3.1.3.4. The control rod drop times were measured in Mode 3' with the RCS Tavg above 500'F and all reactor coolant pumps operating. ;
The rod drop times were measured by withdrawing a rod bank 229 steps and then removing the moveable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be dropped. This allowed the rod to drop into the core as it would during a plant trip. The stationary gripper coil voltage aad the Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded to determine the rod drop time. This procedure was repeated for each control rod.
-hs shown on the sample rod drop trace in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary gripper coil fuse is removed. As the rod drops, a voltage 1a induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing.
NE-1133 NIC13 Startup Physics Tests Report Page 17 of 57
__,_.._____._.___._.._........_..._.___m.m._._._..
I
}
1 4
i E' _
i The measured drop times for each control rod are recorded on Figure
! 2.2. The slowest, fastest, and average drop times are summarized in Table a
i 2.-l . Technical Specification 3.1.3.4- specifies a maximum rod drop time r
4
~~- from loss of stationary gripper coil voltage to dashpot entry of_ 2.7 4-seconds . with the RCS at hot, full flow conditions. These test results~~
~~' .e In addition, rod bounce was observed at the end i-satisfied this limit.~~
of each trace which demonstrated that no control rod stuck in the dashpot !
[ -region.
4 l
i s
v t-NE-1133 N1C13 Startup Physics-Tests Report' -Page 18 of 57
e
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Table 2.1 NORTH ANNA UNIT 1 CYCLE 13 STARTUP PHYSICS TESTS
'80T ROD DROP TIME
~~SUMMARY~~
ROD DROP TIME TO DASHPOT ENTRY ,
SLOWEST ROD FASTEST ROD AVERAGE TIME B-06 2-07 sec.
. C-09 1.57.sec. 1.75 sec.
s i
NE-1133 LN1C13 Startup' Physics Tests Report. Page 19 of 57
__j
i 9
i Figure ~2.1 NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE seg4==ing df Dashpot mottom of Dashpot Initiation of med (meginniay of.Firet .(Reginning of First Drop heat Mark Downtura in Trace) Upturn in" Trace)
/ \ /
g 3tationary Gripper coil voltage Trace
~~Rod Drop Time :~~
A AAAAAAAAAAA yyVVVVVVVl'j N( GOEs IRPI
% Primary Coil iAAAAAAJ AAA44g voltage Trace Vyyyyyyq Pk,yyyyy iAAAAAAj,AAAAAA,,p3gg444ggggggg 444g4g ga4g4ggg pyyyyyyv ( 60E Trace (If Used)
WWWWWWwwyyyyyyyyyyyyyyyyyyyy q yyyyy ROD DROP TIME MEASUREMENT NE-1133 N1C13 Startup Physics Tests Report Page 20 of 57
-F.igure 2.2 NORTH ANNA UNIT 1 - CYCLE IS STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R P N M L E J H G F E D C 8 A 1 i i l 1 i i I t-1 I I- I l i i 1 I i i l i 1.73 1 1 1.62 I I 1.75 1 1 2 1 .
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1 I I I- l l l I l t i i i i 1 1.at 1 i i i 1,72 l l t 1.7e 1 1 l l 1.92 4 a I I I I I I I I I I I L 1 1 I i L i i l 1 i I ,
1s75 1 1.64 l 11.7111 1 I I 1.57 1 1 9 1 1 .
_t l i I '
l 1 1 1 I i i i I I I I I i 1. I I i 1.se 1 I t.7s l 8 1.7e i i 1.74 I i 1.76 : 1 1.77 I i 1.as to i I I I I I i 1 1 1 I I I I I I I I i .
I I I i 1 1 1 1.45 I I I I I I 1.76 i i i I 11 1 I .
I I I I i 1 1 1 1 I l i I i i I I i i i, i I i i 1 1.69 8 1 1.et i 1 1 ' i 1,71 11 1 1,73 I I 12 l i '
I I h I I I 1 I I I i 1 1 1 I I '
li 1
-1 1 1 '! 1.72 I. i 1.72 l ll i 13 1 1 I i l i ! l i 1 i 1. I I I l I 1.97 l! I 1.75 I I 1.76 I i- 14 1 1 1 1 1 1 1 1 1 I I l i I i 15 1 1 I i 1 i i x.xx 1.-> aon onop 7:nE to easmo? Enter esten i l i
i NE-1133NIC13 Startup Physics Tests Report Page 21 of 57
?
SECTION 3
' CONTROL ROD BANK WORTH MEAS'JREMENTS Control rod bank worths were measured for the control and shutdoyn' banks using.the rod swap technique 8 '. The initial step of the rod swap method diluted the predicted most reactive control rod- bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity.
changes .resulting.' from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the -
dif ferential and integral worth of the reference bank. For Cycle 13, Control Bank B was used as the reference bank.
After the completion of the reference bank reactivity worth measurement, the . reactor coolant . system temperature and boron concentration were stabilized with the reactor -near critical and the reference bank fully inserted. Initial statepoint data for the rod swap maneuver were obtained ' with the reference bank at its fully inserted -
position 'and all other banks fully withdrawn, recording the- core reactivity and moderator temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several ' steps and then inserting one of the other contrcl rod banks (i.e. , a test bank) to balance the reactivity of the reference bank withdrawal. This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical or near the initial statopoint condition. .This measured critical position (MCP) of the reference bank with the test bank fully inserted was used to determine NE-1133 NIC13 Startup Physics Tests Report Page 22 of 57
l the integral reactivity worth of the test bank. The core reactivity, moderator- temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver then was repeated in reverse such that the reference bank 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 shutdown banks.
l A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance 't10% for the reference bank,115% for test banks of wcrth greater than 600 pcm, and 100 pcm for test banks of worth less than or equal to 600 pcm.) The sum of the individual measured rod bank worths was within 0.9% of the design prediction. This is well within the design tolerance of i10% for"the sum of the individual control rod bank worths.
The integral and differential reactivity worths - of the reference bank - (Control Bcnk B) are shown in Figures 3.1 and 3.2, respectively.
The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory.
NE-1133 NIC13 Startup Physics Tests' Report Page 23 of 57 e
~
Table 3.1 NORTH ANNA' UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
~~SUMMARY~~
L -
MEASURED PREDICTED PERCENT DIFFERENCE WORTH WORTH (%)
l BANK (PCM). (PCM). (M-P)/P X 100 l'
l- B-Reference Bank 1282.5- .1266.0 1.3 s D. 1116.2 1111.0 0.5 j;
_C- 783.71 811.4 -3.4 i A 336.8 '325.8 3.4
~~SB. '1051.2 1088.9 -3.5 SA 1022.7 941.3 8.6~~
~~. Total Worth. 5593.1 5544.4 0.9~~
~~Difference is less than 100 pcm.~~
1 i
NE-1133 'NIC13.Startup Physics Tests Report Page 24 of 57
Figure 3.1 NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 1400 -
ER
'm_
1200 .' s x
II \
3
\
t ll \
\
T 1000 m ',.
X I
Q \,
s va l \
a s, l800 u
N s
~~a. A 2~~
~
\
\
z H (
u T E \
O s B 600 = ^
~~. X h .~~
N e . s
% N, a ..
)
400 -
\
~~s T~~
\
is i
\
200 '
s
\
mt
\
't 4,
\
0 N:
0 40 80 120 160 200 B-BANK POSITION (5 STEPSIDMSION)
NE-1133 NIC13 Startup Physics Tests Report Page 25 of 57
_ _]
i o
I Figure 3.2 ,
NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP
-- ALL OTHER RODS WITHDRAWN 10 I i
A
/ (
/ \
i \
/ t
/ 1 f
/
/
" /
8 u /
/ .
/ )
~~/ ., m N h i j 2~~
o 7 ;-
5 -
r M /
/ \ / is i h / \
. it I
/
%.\ # '
N6 vs I a 1
- e as r
R ,
~
/
{ /
n
?.i. S
' {o I i '
y I a il 4 a f g l' z I w
I 6
~~u. I 3 "~~
~~16: i~~
I
/
(
2 i
I --
. )
_ /
' /
1 y
/
/
/
0'I '
200 40 80 120 160 O
B BANK POSITION (5 STEPS / DIVISION)
NE-1133 NIC13 Startup Physics Tests Report Page 26 of 57
2 SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS
~~Boron Endpoint l With the reactor critical at hot zero power, reactor coolant system~~
! l, t
I (RCS). boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For- each critical -boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured
~~critical boron concentration values were made to account for off-nominal control rod position and moderato- temperature, if necessary.~~
The results'of-these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Results and Evaluation i
Sheets given in the Appendix, the measured critical boron endpoint values i
were within their respective design tolerances. The ARO endpoint comparison to the predicted value met the requirements of Technical Specification 4.1.1.1.2 regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.
Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement, NE-1133: NIC13 Startup Physics Tests Report Page 27 of 57
Q
.the-value of the DBW over the range of boron endpoint concentrations was obtained.
A plot of the boron.. concentration versus inserted control rod worth is shown in Figure 4.1. As indicated 'in this figure and in the Appendix, the measured DBW was -6.86 pcm/ppe. This is within 4.6% of the predicted - ,
i value of -6.56 pcm/ppe 'and is well within ' the design tolerance of i10%.
'In summary..the measured boron worth coefficient was satisfactory.
1 1
i NE.1133 N1C13-Startup-Physics ~ Tests Report Page 28- of 57
Table 4.1 NORTil ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS BORON ENDPOINTS
~~SUMMARY~~
l Measured Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm)
[-
ARO 2112 2137 -25 B Bank In 1925 1919* 6
The predicted endpoint for the B Bank- In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheet in the Appendix.
NE-1133 NIC13 Startup Physics Tests Report Page 29 of 57 i
l l
l Figure 4.1 NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS
~ "
BORON WORTH COEFFICIENT Measured DBW = -6.86 PCM/ PPM 1400 0
1200
% l 1000 ,
E r 2
800 g
g %
E O 600 b '
a: ,
s 400 ,
200 ',
P h
0 I h 1980 2000 2020 2040 2060 2080 2100 2120 1920 1940 1960 BORON CONCENTRATION (PPM) e NE-1133 N1C13 Startup Physics Tests Report Page 30 of 57
q SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient (ITC).at the all-rods-out condition is measured by controlling the reactor coolant system (RCS) temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.
Reactivity was measured during the RCS cooldown of 3.5'F and RCS heatup of 3.0'F. Reactivity and temperature data were taken from the reactivity computer and strip chart recorders. Using the statepoint method, the j temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured ITC.
The predicted and measured isothermai temperature coef ficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was withic the design tolerance of 3 pcm/'F. The moderator temperature coefficient was determined to be -0.16 pcm/'F which met the requirements of COLR Section 2.1.1. In summary, the measured results were satisfactory.
NE-1133 NIC13 Startup Physics Tests Report Page 31 of 57
_--a
4 .
Table-5.1-NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS
-ISOTHERMAL TEMPERATURE COEFFICIENT
~~SUMMARY~~
ISOTHERMAL' TEMPERATURE'C0 EFFICIENT BANK TEMPERATURE BORON (PCM/'F)
POSITION RANGE CONCENTRATION
'(*F) (ppm)' AVE. DIFFER.
?(STEPS)
C/D H/U MEAS. PRED. (M-P)-
543.9 D/218 to- 2109 -2.10 -1.70 -1.90 -3.05 1.15 '
547.5 l i
s i
NE-1133 NIC13 Startup Physics Tests Report 'Page 32 of.57
SECTION 6 I
POWER DISTRIBUTION. MEASUREMENTS i:
1 - _.
[
The core power distributions were nu sured using the moveable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel. assembly _ instrumentation thimbles i
Figure 1.3- shows the available locations- i in up to 50; core locations-.
monitored by the moveable detectors for the ramp to full power flux maps for Cycle 13. For each' traverse, the ' detector - voltage output is continuously monitored _ on a strip chart recorder, and; scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are determined from this data using a Virginia Power modified version of the Combustion Engineering computer
_ program, CECOR'. CECOR couples the measured voltages with predetermined
-analytic. -power-to-flux ratios- in order to determine- the z power =
distribution for the whole core.
A list of the full-core flux maps taken-during the- startup L test program and the . measured values of the important power distribution-parameters are given in Table 6.1. A comparison of these measured values with their COLR limits is given in Table 6.'2. Flux map 1 was taken at 25% po'wer to verify the radial power distribution (RPD^). predictions at low power. Figure 6.1 shows the measured RPDs from this flux ' map. Flux
= maps 2 and 3 were taken at 74% and 97% power, respectively, with different control rod configurations. These flux maps were taken to check at power
' design . predictions and to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2'and 6.3. The radial power distributions for the maps I
'NE-1133_-NIC13 Startup Physics Tests Report Page 33 of 57
given --in . Figures - 6.1, ' 6.2, and 6.3 show that . ..su red relative assembly power values were generally within 1.1*. of the predicted values.
Further, the measured F-Q(Z) and F-DH(N) peaking factor values for the at power flux maps were within the limits.of COLR Sections 2.5.1 and 2.6, respectively. Flux maps 1, 2, and-3 were also used to perform power range l
detector calibrations. The flux map analyses are documented in Reference 7.
In conclusion, the power distribution measurement- results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR. It is - therefore anticipated that the core will continue to operate safely throughout Cycle 13.
i e
1 NE-1133 N1C13 Startup Physics Tests Report Page 34 of 57 l
TABLE 6.1.
NORTH ANNA UNIT 1 - CYCLE 13 STARTUP' PHYSICS TESTS INCORE FLUX MAP
~~SUMMARY~~
l I i i i i I (Is -1 I e i i i l i i i turn 1 1 l F-0(2) Hui- 1 F-OH(N) MDil CORE F(2) 1 (2) i l 1
.I MAP lNAPI l uP 1 . IsAsst i CNANNEL F acier I CNNt.FACTORI MAX l CORE Illil Axlatt NO.I
l. I DESCRIPfl04 lNO.1 DATE I NWO/IPWRt D l l l l l OFF 1 0F l j
[ l l l l NIU l(2 8 tSTEPSI ASSVlail All l ASSYlF-DHtN)l AMi&Li filll NAX lluCl SET liHINI
! l l l l l l 1 IP0lNilF-G(2 ) l l lPOINil l l i (%) ISLES) l 1 l_1 1 l_1 l_1 I l_1 1 -1 1 l _l 1I
! Ilow PoutR I 1 lee.!!-973 2 1 256 99 i Ne61 45 1 2.e33 i No6B 1.4a1 i es ll.seell.esFal Mul-Ir.ill *s I iP.F.W. (31 1 2 le613-971 36 l 741 189 l PtFl 31 1 1.741 l No6l 1.387 8 26 11.14618.4619 8 SE l -3.041 46 1 IHQi FUL6 POWER l 3 106-26-971 519 l 971 215 i 8091 35 l 1.654 i Clel 1.357 8 26 11.31314.84%l SEl -0.20146 i i l_l l 1l l_l l l_1 l 1 1 l_l 1.,,, l NOTES: HOT SPOT LOCA110NS ARE SPECIFIED BY CIVING ASSEleLY LOCATIONS (E.C. H-815 THE CENTER OF-CORE ASSENSLVI
l. AND CDRE NElGHT (IN THE 'T' DIAECil0N THE CCRE IS BlW10f D INTO 61 AXt AL POINIS SI ARTING FROM ItE TOP GF THE COREl.
(13 F-0(2) INCLUDES A TOTAL UNCERTAINTY OF !.05 X 4.03.
(2) CORE TILI - DEFINED AS THE AWERAGE QUADNANT PUNER TILY FROM CECOR.
(3 5 P.F.V.
~~PEARING F ACTOR VERIFICATION.~~
441 NAPS 1, 2, AND 3 WERE USED FOR POWER RANGE DETECTOR CAllSRATIONS.
i 1
- NE-1133 NIC13 Startup Physics Tests Report Page 35 of 57 1
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _. . .l
~~Table 6.2-NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PHYSICS TESTS COMPARISIOM OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS~~
? <
- PEAK F-Q(Z) HOT F-Q(Z) HOT- F-DH(N) HOT.
CHANNEL FACTOR
~~CHANNEL FACTOR ** CHANNEL FACTOR i~~
(AT NODE OF MINIMUM MARGIN)
MAP NO. MEAS. LIMIT NODE ; MEAS. LIMIT NODE MARGIN . MEAS. LIMIT MARGIN
(%) (%)
2.033 4.380 -43 2.033 4.380 43 53.6 1.481 1.827 18.9 2 1.741 2.940 31 1.739 2.904 26 40.1 1.387 1.604 .13.5 I 3 1.654 2.265 35, 1.620 2.197 19 26.3 1.357 1.505 9.8-
~~The Core Operating Limit for the heat flux hot channel factor, ,~~
F-Q(Z),- is a function of core height and power level. The value -)
for F-Q(Z)= listed above is the maximum value of F-Q(Z) in the i core. 'The COLR limit listed ebove is evaluated at'the plane of maximum F-Q(Z).
~~The value for F-Q(Z) listed above is the value at the_ plane of "~~
minimum margin. The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(Z) and the COLR limit for each map.
The measured = F-Q(Z) hot channel factors include 8.15% total uncertainty.
NE-1133' NIC13 Startup Physics Tests Report Page 36 of 57
4 I
Figure 6.1
(
NORTil ANNA UNIT 1 - CYCLE 13 STARTUP PilYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 25% POWER R P N M L R J H C F E D C B 4 PvE DICit D . 0.257 8.279 . 0.257 . . PREDICit0 .
. MF85URED . 0.261 . 0.286 . 0.262 . . MF 85URE D . 1
.PCI DIFFtpt NCE. l.4 2.6 ,
. 2.2 . .PCI Dif f t RI NCE.
. 0.34 6.669 1.030 0.779 , 1.037 6.669 . e.346 e.345 . 0.675 . 1.041 . 0.783 1.058 e.698 . 0.353 , 2 0.8 . I.e 1.1 0.5 2.1 . 4.3 1.8 .
. 0.322 . l.079 1.315 1.236 . 1.229 1.239 1.316 . 1.078 . 6.321 .
0.324 . l.086 . 1.376 I.249 . 1.245 . 1.257 3.333 . 1.084 . 0.309 3
. -e.4 0.6 . e.8 1.0 1.3 1.5 . 1.3 0.1 . -3.9 e.324 0.740 1.250 1.326 , 1.212 1.244 1.274 1.324 I.21, 0.737 0.324 .
0.334 0.749 1.234 , 1.313 . I.283 1.268 . 1.284 1.332 . 1.
15 , 0.72? 0.318 . 4 3.2 , 1.1 0.3 . 0.5 . 0.8 1. 9 , 1.0 0.6 .0 -2,1 -1.8 0.348 .......1.081 . 1.231 . l.235 . 1.249 . 1.239 1.149 . 1.235 1.246 . 1. 2. ' 1.227 1,078 0.346.
0.361 1.131 1.250 1.233 . l.245 . 1.238 1.156 . 1.237 1.235 1.19. . 1.188 1.061 . e.344 . 5 3.9 4.e 3.6 -0.2 . -0.3 . -0.1 0.6 . 0.2 -0.9 -2.8 -3.1 -1.6 -0.8 0.674 1.323 , 1.350 1.251 1.030 1.202 1.233 . 1.199 1.e28 l.247 1.524 1.314 8.66%
0.693 1.358 1.344 1.227 1.012 1.201 1.239 1.196 1.008 1.225 1.305 . 1.306 6.673 6 2.8 . <7 1.1 -1,9 , -1.7 . -0.1 0.4 -0.3 -1,3 -1.7 . -1.5 . -0.6 0.0 0.259....., ... ........... ....... ....... ............... ....... ....... ............... ....... ....... .......
.....1.046 3.?48 1.2 79 1.241 . 1.264 . 1.243 1.141 1.240 1.200 1.238 1.272 1.235 1.028 0.255 ,
0.2h4 1.070 1.280 1.296 1.245 1.204 1.258 l.14e . 1.237 1.192 1.228 1.260 1.240 . 1.058 0.261 7 2.0 2.2 2.b l.3 0.3 . 0.0 0.n 0.3 . -0.2 -0.7 -0.8 -0.9 . 0.4 2.9 2.4 0.282 0.786 1.239 1.255 .......1.157 1.239. .......
1.145.......
1.043....... ....... ......................, ....... ...............
1.142 1.233 . 1.150 1.246 1.230 0.780 0.280 .
8.?ns 0.789 1.263 1.273 1.173 1.246 1.150 1.0*6 1.142 . 1.234 . 1.147 . 1.245 1.235 0.779 0.281 4 1.2 0.5 1. 9 . l.5 1.4 0.6 , 0.4 0.3 0.0 0.1 - 0. 3 . 0.0 0.5 . -0.1 0.5 0.258 1.019 1. ?48 . l.285 1.249 l.208 1.246 1.145 , 1.242 1.200 . 1.2 36 1.273 1.243 1.040 0.258 0.2h6 1.050 1.263 1.?95 1. %2 1.205 1.245 . 1.146 1.240 1.193 1.23.5 1.275 1. 24.Y . 1.0 18 0.255 . 9 1.1 1.1 1.1 0.6 .2, -6.2 0,0 0.1 -0.1 -0.6 -0.2 . 0.2 0.2 0.2 . -1.0 .
0.677 1.335 1.343 1.262 , 1.637 , 1.207 1.238 .....1.204 1.029 1.248 1.126 . 1.317 0.671 0.681 1.343 1.34 3 1.249 , 1.015 1.199 . l.240 1.200 1.013 3.240 1.357 1.319 0.659 . le 0.9 0.7 0.0 -1.1 . -2.0 -0.6 0.2 . -0.3 -l.6 -0.6 0.8 0.1 -1.7 .
0.353...... 1.101 1.253 1.253 1.261 , l.245 L.I55 1.242 1.250 1.234 . 1.228 1.078 0.346 0.35i 1.101 1.241 1.220 l.240 1.23u 1.168 1.242 . 1.239 1.213 . 1.226 1.879 . 0.3*4 !!
6.4 0.0 -1.0 -2.6 - -1.7 -0.7 1.1 e.6 . -0.8 -1.7 -0.2 6.1 -0.6 .
. 0.335 0.331 0.175 0.765
......1.254 1.34 3 1.283 . 1.252 1.277........
1.328....... .......0.758 1.229 ........ 0.323 ....... .
1.232 1.323 . l.2n1 1.748 - 1.272 1.318 . l.218 . 0.738 0.325 12
-1.1 -3.2 -1.7 -1.5 . -l.1 -0.3. -e.4 -0.8 -0.9 6.1 . 8.6 0.332 1.100 . 1 . 3 54
~~251 1.237 , 1.241 1.318 1.088 0.322 .~~
0.328 1.085 . l.317 . . 237 1.229 . 1.239 1.301 1.070 0.320 13
. -1.3 1. 3 . -1.3 -l.2 *8.7 -0.2 . -l.3 -0.9 . -0.6 0.352 0.678 .....1.046. 0.784 1.03* 4.671 0.34 7 ,
0.348 , 0.670 1.033 0.77% l.052 8.671 0.345 . 14
-l.3, -l.2 1.2 . -l.2 1.8 0.1 0.5
'kiEbEEb' 'd[hk9' e$h8i 'hlhk9' . EYthEb5' .
DF Vlall DN 0.250 e.278 0.262 . PC f D D F I RE NCf . 15 "S.922 -3.6 -1.0 1.1 = 1.1 4
~~SUMMARY~~
MAP NU: H1-13-01 DATE! 06/11/97 POWER: 25%
CONTROL ROD POSITIONSI F-Q(Zi n 2.033 CORE TILT:
D BANK AT 99 STEPS F-DHtNI z 1.481 NW l.0078 l NE 0.9944 1
FlZI = 1.300 Sd 1.0029 i SE 6.9950____
BUiNUP 1.78 MWD /MTU A.O. a 17.7%
NE-1133 NICl3 Startup Physics Tests Report Page 37 of 57 )
.M gure 6.2 NORTil ANNA UNIT 1 - CYCLE 13 STARTUP Pl!YSICS TESTS ASSEMBLYWISE POWER DISTRIBUTICN 74% POWER
- St P N N 1 E J H C. .F E 9- C 0 8 .
. PREDICIED . . 8.294 . 0.337 . 9.294 . . PPfDICTED .
. MEA 3HREO . . . 9.295 . 0.339 . 0.296 . . sEAsuRED .
. PCT DIFFERENCE. . 4.1 . 0.5 . 0.7 . . PCT DIFT[RENCE.
. 4.351 . 0.678 . 1.044 . 0.958 . 1.493 . 0.679 . 0.351 .
. 0.350 . 0.677 . 1.064 . 0.9% .1.101 . 0.697 . e.353 .
. -0.4 . *0.1 . 8.0 . *0.5 . 0.8 . 2.7 . 0.6 .
. 0.325 . 1.435 . 1.25? . 1.224 4.241 . 1.228 . 1.258 . l.435 . 4.324
. 9.319 . 1.924 -. 3.253 . 3.224 . 1.247 . 1.233 . 1.242 . 1.026 . 0.345 .
. -1.9 . *0.7 . -0.3 . 0.0 . 4.5 .~ -0.4 0.3 . 0.9 -5.8 .
. 0.326 . 0.726 . 3.171 . 1.273 . 4.228 . l.286 . 1.227
~~1.271 1.170 . 0.724 . 0.327 .~~
. 0.331 . 0.725 . 1.158 . 1.264 . I.224 . 1.219.. 3.227 . 1.266 . 1.153 . 0.708 . 8.3?! .
. 1.6 . 0.2 . -1.0 . -0.6 . -0.3 . 0.3 . 0.0 . -0.4 . -1.5 . -2.2 . -l.6 .
. 0.35I 4.035 . 1.170. 1.299 . 1.249 1.232 . 1.133 . I.229 . 1.248 . 1.288 . 1.169 . ? .435 . e.351 .
. 0.360 . 4.963 . 1.175 . 1.193 . l.236 . 1.222 . 3.132 . 1.225 . 1.233 . 1.175 . 1.141 -. 1. 0 2-. 0.345 .
. 2.4- 2.8 . 0.4 . -l.3 . -3.1 . -0.8 . -0.1 . -0.3 . *s.2 . 2.7 . *2.4 l.a -1.6 .
0.681 . 1.261 . 1.273 . l.249 . 1.289 1.226 3.231 . 1.225 . 1.208 . 1.248 ., 8.271 . 1.256 . 0.677 .
. 0.693 . 1.281 . 1.278 . 1.229 . 1.198 . 1.223 . 1.236 . 1.224 .. 1.190 . 1.232 . 1.259 . 1.254 . 0.685 .
. 1.7 . 1.7 . 0.4 . -1.6 . -1.6 . -0.3 . 4.3 . -0.1 . -1.5 . -1.3 . 0.9 . -8.2 . 1.1
. 4.29A . 1.998 . 1.231 . 1.230 . l.231 ..l.226 1.254 . 1.143 . 1.253 . 1.226 1 232 . 1.228 . 1.224 .. 1.083 . 0.292 .
4.298 . 4.111 . 1.254 . 1.249 . l.235 . 1.228 . 1.266 . 1.153 . 1.268 . 1.225 . 1.228 . 1.224 1.231 . 1.118 . 0.299 .
. 0.9 . 1.2 . .l.8 . 0.8 . 6.3 . -0.8 . - 1. 0 -. 0.9 . 1.1 . 0.0 . 0.3 . -0.3 . 0.6 . 3.2 . 7.5 .
. 4.339 . 0.962 . 1.245 . 1.221 . 1.136 . 1.234 1.144 1.849 . 1.143 . 1.232 . 3.134 . 1,217 . 1.242 . 0.959 . 0.338 = .
. 8.340 0.959 1.250 . 1.232 . 1.1 % . 1.244 . 1.136 . 1.219 . 1.241 . 0.957 . 0.339 .
. .2. 0.3 . .4. .9. i.5 . .8. 1.154 0.9 ..l.05,9 .. . 1.15,3 G. .
. 1.237
..4 . -..! . 8.i . ...i . - .2 . .3 !
. 0.293 . l.088 1.229 1.233 . l.236 . l.229 1.2 % , 1.144 . 1.254 . 1.225 1.229 1.228 . 3.229 . 1.096 . 0.295 .'j -
. 0.294 .. 3.091 . 4.234 . 1.239 . 1.248 1.233 . 1.263 . 1.154 . 1.265 . 1.236 . 1.234 . 1.232 . 1.234 . 1.101 . 0.291 .
. 0.2 . 6.3 . 0.4 . 0.5 . 0.9 . 0.3 . 0.6 . 0.9 . 0.9 . e.8 . 8.4 6.3 . 4.4 0.4 -1.2 .
. 0.681 . 1.265 . 1.280 . 1.256 1.213 .1.224 . 4.233 . 't.227 .1.288 . 4.248 . 1.272 . 1.259 . 0.680 . -1
. 0.683 . 1.268 . 1.279 . 1.249 1.198 . 1.228 . l.246 . 1.234 . 1.201 . 1.247 . 1.217 . 1.267 . 0.690 . 1
. 0.3 . 0,2 . -0.1 . -0.5 . al.2 -0.1 . 1.0 . 0. 6 . . -0.6 -G.! . e.6 . 0.6 . 1.4 .
. 8.3 % . 1.048 . 1.185 . 1.219 . 1.255 . 1.233 . 1.135 . 1.233 . I.249 . 1.208 . 1.178 , 1.434 0.351 .
. 0.3% . 1.044 . 1.175 . 1.196 -. 4.243 . 1.235 . 3.16e 1.243 . 1.247 . 1.199 1.172 . ' t .039 . 0.3% .
. 0.0 0.3 -0.8 . -1.9 . -0.9 . 8.1 . 2.2 . 0.8 . .e.1 . -0.7 e.2 . 4.5 . 0.9 .
. 0.335 . 0.755 . 1.185 1.280 . 1.232 . 1.219 . 1.229 l.272 . 3.I70 . 0.724 . 8.326 4.32S . 0.747 . 1.171 . l.278 . 1.223 1.223 .1.233 . l .2'/2 1.169 . e.734 . 0.324 j
. -2.1 . -1.8 . -1.2 . -0.8 . -6.8 . 0.3 . 6.3 0.1 . -0.1 , 0.8 . -0.5 . -!
. 0.332 . 1.048 . 1.267 1.233 . 1.244 . 1.225 . 1.258 . 1.435. 4.324 .
. 6.329 . 1.938 . 1.257 . 1.224 . 1.236 1.228 1.2 % . l.035 . 6.325 .
. -0.9 . 0.9 . =0.8 . -8.7 . -0.7 . e.2 . -0.3 0.4 . 4.3 . ;
. 0.355 . 0.683 . 1.096 9.961 . 1.086 . 0.678 . 6.351 .
. 4.349 . 0.677'. 1.066 . 8.951 . 1.193 . 4.685 . 4.352 .
.. -1.4 . -0.8 . -0.9 . -1.1 . 1.6 . 0.7 . 4.3 .
. STANDARD . . 9.29% 4.334 . 0.295.. . AVfRACE .
. DEVIA110N . . 0.285 . f.3 % . 9.298 . .FCT DIFFIRENCE.
. 0.790 . . -3.3 . .I.o . e.9 . . .= e.8 .
SUMMAPY
' MAP NO! N1-13-02 'DATE: 06/13/97. POWERI 74%
CONTROL RCD POSITIONSI F-Q(Z1 a 1.741 CORE' TILT:
D BANK AT 189 STEPS F-DHtNI a 1.387 NW l.0007 i NE 0.9955 i
F(Z) = 1.146 SW l.0018 l SE 1.0019 BURNUP = 36 MWD /HTU A.O. = 3.00.
NE-1133- NIC13 Startup Physics Tests Report .Page 38' of 57
O Figure 6.3 NORTH ANNA UNIT 1 - CYCLE 13 STARTUP PIlYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 9 7 % PL"iER R P M M L K J H C F E D C & 8
. PREDICIE) . . G.303 . 0.351 . 0.303 . . PM p!CILO .
. ME SSUM D . . 0.304 . 0.357 . 0.304 . ME ASURED . l
. PCT DIFFEMMCE. . 9.2 . 1.7 . 0.5 . . PCT DIRERENCE.
0.355 0.679 1.878 . 0.981 1.085 . 0.679 . 0.355
. 4.354 . 0.677 1.075 0.976 . 1.086 . 0.689 . 6.356 . 2
. -0.1 -0.2 -0.3 . -0.5 . 9.1 . 1.4 . 0.2 0.335 - 1.024 . 1.237 . 1.208 . 1.234 . 1.212 . 1.238 1.024 . 0.334
. 0.325 . 1.024 . 1.235 . 1.203 . 1.219 . 1.206 . 1.2 34 . 1.018 . 0.357 . 3
. -2.9 . 0.0 . -0.2 -0.5 . -1.2 . -0.4 -0.3 . -0.6 0.7 .
0.335 0.734 1.164 1.255 1.220 . 1.200 1.219 I.255 . 1.163 0.736 0.335 .
l 0.3 38 . 0.739 1.175 1.254 1.216 . 1.215 . 1.214 1.242 . 1.144 . 0.723 . 6.330 4 0.1
. 1.0 . 1.0 . -0.4 . -0.3 . 0.6 -0.4 -l.1 -1.6 -1.8 1.7 .
0.354 . 1.022 - 1.163 .......1.206.......
1.255 .......1.232 . 3.137 . 1.229 . 1.254 1.205 1.162 1.023 . 0.354 6.359 1.04* 1.160 . 1.183 1.241 1.219 . l.136 1.226 1.238 1.170 1.128 1.007 . 0.352 . 5
. 1.3 . 1.i
~~0. 3 . -1.9 . -1.1 . -1.1 -0.1 -0.3 . -1.3 . -2.9 -2.9 -1.5 - 0. 7 .~~
. 0.681 1.240 . 1.254 1.255 1.249 1.239 1.235 . 1.234 . 1.248 1.254. 1.255 . 1.237 . 0.678 .
. 0.686 1.240 . 1.251 . 1.224 . 1.235 . 1.238 1.243 . 1.241 . 1.239 . 1.237 . 1.238 1.229 . 0.684 6 0.7 0.7 . -0,5 -2.5 . -1,1 . -0.1 . 0.7 0,2 -0.7 . *l.4 -1.3 -0.6 . 0.9 .
0.304 1.089 1.214 1.221 1.231 . 1.239 . 1.261 . 1.154 1.239 1.232 1.219 . 1.208 . 1.077 . 0.301 .
. 0.305 . 1.095 . 1.225 . 1.222 1.228 . 1.240 . 1.276 . 1.167 .1.278 1.260 1.241 . 1.227 . 1.210 . 1.210 1.109 . 0.309 7 0.3 0.5 . 0.9 0.1 . -0.2 . 0.1 1.2 1.1 . 1.4 0.2 -0.4 -0.8 0.2 3.0 2.6 .
0.353 0.984 1.237 1. 211 . 1.1 ~.0 1.237 1.155 . 1.068 1.154 1.235 1.138 1.209 1.234 0.982 . 0.352 .
. 0.352 0.981 1.235 1.215 . 1.154 1.245 1.164 . 1.078 1.165 1.244 . 1.138 1.206 1.226 . 0.999 0.354 4
. -0.2 -0.5 -0.2 0.3 1.3 0.6 0.0 . 0.9 . 0.9 0.7 0.0 -0.2 -0.6 1.8 3.7 0.302 . 1.080 1.212 1.224 1.236 1.242 . 1.262 . 1.155 1.268 1.238 1.230 1.220 I.213 1.084 . 0.304 0.300 . 1.075 . 1.206 1.221 1.242 1.243 1.266 . 3 .1 b4 1.269 1.242 . 1.232 1.222 1.222 4.110 . 0.305 9 0.5 -0,5 . *0.6 . *0.2 0 .1 , 0.2 . 0.3 0.7 . 0.7 . 0.3 0.2 0.2 0.7 2.0 0.4 .
1.2621.261 .......1.252 .......1.241 ....................... ............... .......
1.256 ...............
. 0.681 . 1.244 1.236 1.240 1.240 . 1.254 . 1.239 0.680 0.675 . 1.226 1.250 1.250 1.243 1.235 1.249 1.248 . 1.247 . 1.253 1.259 . 1.256 0.714 . 10
. -1.0 -4.4 . -1.0 - -0.9 -0.8 -0.4 1.0 . 0.7 . -0.! -0.1 . 0.3 . 1.4 . 5.0 0.358 1.034 1.176 1.215 1.260 1.233 1.139 . 1.233 1.255 1.205 1.163 . 1.022 0.354 0.351 . 1.019 1.154 4.189 . 1.248 1.234 1.173 . 1.246 1.252 1.199 1.166 . 1.033 0.364 !!
-1.3 . -1.5 -1.5 -2.1 -1.0 . 0.0 . 3.0 1.0 . -0.3 -0.5 0.3 . 1.1 2.6
. 0.343 0.7651.177 ....... 1.263 ....... 1.223...............
. 1.210 . .......
1.221 . ........
1.256 .......
1.163 . .......
0.737 ....... 0.335 0.335 0.754 1.161 1.251 1.206 . l.225 1.229 . 1.253 1.160 . 0.742 . 0.337 . 12
-2.3 -l.4 -1.4 -0.9 -1.4 1.2 0. 7 . -0.2 0.3 0.7 . 0.6 0.342 1.035 1.245 .......1.216 . 1.236 1.210 1.238 1.023 . 4.334 0.138 . 1.027 1.243 1.223 . 1.267 . 1.222 . l.222 1.017 . 0.334 13
-1.1 -0.8 -0.2 . 0.6 2. 5 - 1.1 - 1. 3 - -0.6 0.2 0.358 0.683 1.088 6.983 1.079 . 0.679 0.355 0.354 . s.645 1.104 1.002 1.104 0.681 0.354 14
-1.1 . 2.4 1.5 . 2.0 2.4 0.4 -0.2 STAMDARD 0.304 0.352 . 0.303 . AVEPACE ,
OfvlAfl0N 0.319 0.361 0.311 .PCI DirFERENCE. 15 0.863 4.9 2.6 . 2.4 = 1.0
~~SUMMARY~~
MAP NO: H1-13-03 DATE: 06/26/97 POWER: 97%
CONTROL ROD POSITIONS: F-QtZI = 1.654 CORE TILT:
D BANK AT 215 STEPS F-DHINI 2 1.357 NW 0.9985 i HE 0.9949 1
FlZI = 1.113 SW 1.0011 i SE 1.c054 BURNUP = 519 MWD /MTU A.O. s -0.001%
NE-1133 NIC13 Startup Physics Tests Report Page 39 of 57 I
_ . . . _ _ _ _ _ _ _ _ _ _ u
~
SECTION 7 REFERENCES l
! 1. C. B. LaRoe, " North Anna Unit 1, Cycle 13 Design Report", 'fechnical Report NE-1129, Revision 0, Virginia Power, May, 1997.
I
~~2. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Detereination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.~~
~~3. T. W. Schleicher, "The Virginia Power CECOR Code Package", Technical Report NE-831, Revision 3. Virginia Power, July, 1995.~~
4. North Anna Unit 1 Technical Specifications, Sections 1.19, 3.1. 3.4, 3. 2. 2, 3.2.3, 3.1.1. 4, 4.1.1.1. 2, and 4. 2. 2. 2 and Core Operating Limits Report (COLR) for North Anna 1, Cycle 13 Pattern OG, Revision 0 (May, 1997) Sections 2.1.1, 2.5.1, and 2.6.
5. Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of Startup Physics Test Program - Inspector Followup Item 280, 281/88-29-01", Serial No.89-541, December 8, 1989.
~~6. G. P. Anderson, " North Anna Unit 1, Cycle 13 TOTE Calculations",~~
~~PM-710, Revision 0, June, 1997.~~
~~7. R. A. Hall, et al, " North Anna 1, Cycle 13 Flux Map Analysis",~~
~~PM-712, Revision 0, and Addenda A and B, June, 1997.~~
~~8. R . T. Robins , " Reload Safety Evaluation, North Anna 1 Cycle 13 Pattern OG", Technical Report NE-1121, Revision 0, May, 1997.~~
NE-1133 NIC13 Startup Physics Tests Report Paga 40 of 57
l-l '
l l
APPENDIX STARTUP PilYSICS TEST RESULTS AND EVALUATION SilEETS -
(
i NE-1133 NIC13 Startup Physics Tests Report Page 41 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 3 i Test
~~Description:~~
Zero Power Testing Range Determination 1-PT-94.0 Sequence Step No:
Reference Proc No / Section:
11 Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA- 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 225 CC:
~~CD:~~
Below Nuclear Heating 111 Bank Positions (Steps) RCS Temperatute ( F): gy y, y Power Level (% F.P.): 0 Test Col.ditions SDA- 225 SDB: 225 CA: 225 Other (specify):
CB: 225 CC: 7Y CD: /Ff Below Nuclear Heating (Actual)
Date] Time Test Performed:
G/tolT7 0559 3 l Reactivity Computer Initial y Flux Background Reading N'D/0 amps $k[.((14./j IV Test Results Flux Reading At Point Of Nuclear Heating b.0 dd ) amps Zero Power Testing Range f Y10 to /O */ amps Reference Not Applicable
-' V FSAR/ Tech Spec ' tot Applicable Acceptance Criteria Reference Not Applicable r
Design Tolerance is met" : G YES NO Acceptance Criteria is met" : / YES NO VI
At The Just Critical Position Comments Design Tolerance and Acceptance Criteria are met if ZPTR is below the Point of Nuclear Heating and above background, sn A /1 A Prepared By: Reviewed By: b d
, s. /7a NE-1133 NIC13 Startup Physics Tests Report Page 42 of 57
)
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 l
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET
~
I Test
~~Description:~~
Reactivity Computer Checkout Reference Proc No / Section: 1-PT-94.0 Sequence Step No:
l - 11 Bank Positions (Steps) RCS Temperature ( F): 547 l Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA- 225 Other (specify):
(Design) CB: 225 CC:
CD:
Below Nucles: Heating til Bank Positions (Steps) RCS Temperature ( F): 54 7-(a Test Power Level (% F.P.): O Conditions SDA- 225 SDB: 225 CA: 225 Other (specify):
(Actual) CB: 225 CC: 336 CD: 1% Below Nuclear Heating -
Date/ Time Test Performed:
(o/toler7 OM 9%
Measured Parameter pe= Measured Reactivity using p-computer (Description) pi= Predicted Reactivity IV 1
Test Results Measured Value pe= -43.0 PCM 3 + Mct. O ecm p g= -94.3 Pcm 3 + 49 9 PCM
%D= -2 A % -3 O.S*/c, Design Value %D= {(p,- pt)/pd x 100% s 4.0 %
i Reference WCAP 7905, Rev.1, Table 3.6 J V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : / YES NO Acceptance Criteria is met : / YES NO
.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.~~
Allowable Range = -43.Oecm b + % 0e'e Prepared By: A b 4 LL b Reviewed By: d[o97
/" ( /
NE-1133 NIC12 Startup Physics Tests Report Page 43 of 57 l l
1
- - - . i
. NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l __ Test
~~Description:~~
Critical Boron Concentration - ARO Proc No / Section: 1-PT-94.0 Sequence Sten No:
Reference 11 Bank Positions (Steps) P.CS Temperature ( F): 547 Test Power Level (% F.P.): 0 -
Conditions SDA 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating _
lli Bank Positions (Steps) RCS Temperature ( F): sq.7,4 Test Power Level (% F.P,): 0 Conditions SDA 225 SDB: 225 CA 225 Other (specify): .
CB: 225 CC: 225 CD: 225 Below Nuclear Heating (Actual)
Date/ Time Test Performad:
4 ho 197 c el5%
Measured Parameter (Cc)"yo; Critical Boron Concentration - ARO (Description) .
IV Test Results Measured Value (L s ' o= Q112 ppm (Design Conditions)
Design Value Cs= 2137 2 50 ppm ,
(Design Conditions)
Reference Technical Report NE-1129. Rev. O V FSAR/ Tech Spec laCs x Cs l s 1000 pcm=
Acceptance Criteria Reference Technical Specification 4.1.1.1.2 Design Tolerance is met : V YES NO' Acceptance Criteria is met : V YES- NO 1 VI ,
Comments aC = -6.53 pcm/ ppm '
C. = l(Cs)"Ano- Cal; Cs is design value
~
Prepared Byi2d 'D, b _
Reviewed By: C
-NE-1133 NIC12 Startup Physics Tests Report Page 44 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
Isothermal Temperature Coefficient - ARO Reference- Proc No / Section: 1-PT-94.0 Sequence Step No:
ll Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): 0 i Conditions SDA: 225 SDB: 225 CA- 225 Other (specify):
(Design) CB: 225 CC: 225 CD: 225 Below Nuclear Heating ill Bank Positions (Steps) RCS Temperature ("F): ar43.9 . w1.5 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): .
(Actual) CB. 225 CC: 225 CD: :aa e Below Nuclear Heating Date/Tme Test Performed:
i l
6/ic 57 so45 Measured Parameter (aris)ao; Isothermal Temperature (Description) Coefficient - ARO IV Test Measured Value (aris )ao = -1.9 pcmFF Results (Cs= ci acq ppm)
Design Value .
[. (Actual Conditions) (aris )ao =-3.os i3.0 pcm8F (Cs= cacci ppm)
Design Value (Design Conditions) (aris ) o= -2.8123.0 pcm8F -
(Cs= 2137 ppm)
Reference Technical Report NE-1129. Rev. O ar s 3.76 pcmfF
V FSAR/COLR Acceptance ar " = 474 m/ F Criteria Reference COLR 2.1.1, Technical Report NE-1129, Rev. O Design Tolerance is met : v" YES NO Acceptance Criteria is met : v' YES _ __ N O VI Comments " Uncertainty on aTuoo = 0.5 pemfF (
~~Reference:~~
memorandum from ,
C.T. Snow to E.J. Lozito dated June 27,1980.)
Prepared By: M D MwN
~~Reviewed By: 8 AJ t/7 NE-1133 NIC12 Startup Physics Tests Report Page 45 of 57~~
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 -
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
Control Bank B Worth Measurement, Rod Swap Ref. Bank Reference Proc No / Section: 1-PT-94.0 Sequence Steo No:
11 Bank Positions (Steps) RCS Temperature ( F): 547
- Test Power Level (% F.P.): 0 -
Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: moving CC: 225 CD: 225 Below Nuclear Heating ill Bank Positions (Steps) RCS Temperature ( F): 5 V7.*
Test Power Level (% F.P.): O Conditions SDA- 225 SDB: 225 Other (specify):
~~CA- 225~~
- (Actual) CB: movmg CC: 225 CD: 225 Below Nuclear Heating Date/ Time Test Performeo:
//p/fy 12:22 ,
Measured Parameter I.""; IntegralWorth Of Control Bank B, (Description) All Other Rods Out IV
. Test Measured Value Is""= /BD.E# pcm Results Design Value (Design Conditions) la""= 1266
~~127 pcm 1~~
Reference Technical Report NE-1129, Rev. O If Design Tolerance is exceeded, SNSOC shall V FSAR/ Tech Spec evaluate impact of test result on safety analysis.
Acceptance SNSOC may spectfy that additional testing Criteri' be performed.
Reference -- VEP-FRD-36A Design Tolerance is met : / YES NO Acceptance Criteria is met : / YES NO VI
' Comments ,
i Prepared By:
Reviewed By: d Pdetw '
NE-1133 NIC12 Startup Physics Tests Report Pop 46 of 57
I NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TES1 RESULTS AND EVALUATION SHEET I Test
~~Description:~~
Critical Boron Concentration - B Bank in 1 PT.g4.0 Sequence Step No:
Reference . Proc No / Sectic.n:
~
Bank Positions (Steps) RCS Temperature ( F): 547 l'
Power Level (% F.P.): O Ttst 2 CA' 225 Other (speelfy):
ConJitions SDA: 225 SDB: 225 CC: 225 CD: 225 Below Nuclear Heating (Design) CB: O Bank Positions (Steps) RCS Temperature ( F): 59 7. t.
ill Test Power Level (% F.P.): O CA: 225 Other (specify):
Conditions SDA: 225 SDB: 225 CC: 225 CD: 225 Below Nuclear Heating (Actual) CB: O Date/ Time Test Performed:
1(v. 2,5 leliol9 7 (Cs)"n; Critical Boron Concentration, Measured Parameter (Description) B Bank in IV Test Measured Value (Cs)"a=(72.5 ppm Results (Des'gn Conditions)
Prw i (10 + 12G.6/laCal) ppm Design Value Cs= 1944+ A Cs (Design Condhions) Ca= lii Cf : 29 ppm Reference Technical Report NE-1129, Rev. 0 '
V FSAR/ Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met : KYES NO Acceptance Criteria is met : ( YES NO VI Comments ac a= -6.56 pcm/ ppm '
A Cs '*' = (Cs)"mo- 2137 ppm Prepared By: g/ Reviewed By: wy[
NE-1133 NIC12 Startup Physics Tests Report Page 47 of 57
1 NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
HZP Boron Worth Coefficient Measurement Reference Proc No / Section: 1-PT-94.0 Secuence Step No: ,
il Bank Positions (Steps) RCS Temperature ("F): 547 Test Power Level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA* 225 Other (specify):
(Desi;n) CB: moving CC: 225 CD: 225 Below Nuclear Heating ill Bank Positions (Steps) RCS Temperature ('F): 5+t7.4 l
Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA- 225 Other (specify):
l IActual) CB: moving CC: 225 CD. 225 Below Nuclear Heating i Date/Ti e Test Performed:
l lo lol92 0956 Measured Parameter ace: Boron Worth Ccefficient (Description)
IV Test Results Measured Value ace = - lo fle pcm/ ppm Design Value ace = 6.56 2 0.66 pcm/ ppm (Design Conditions)
Reference Technical Report NE-1129. Rev. 0 V FSAR/ Tech Spec Not Applicable +
Acceptance Criteria Reference Not Applicable Design Tolerance is met : YES NO
,A;cceptance Criteria is met : YES NO VI -
Comments ,
Prepared By: /db 7 Reviewed By: 9 O.
NE-1133 NIC12 Startup Physics Tests Report Page 48 of 57
/ NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
Control Bank D Worth Measurement, Rod Swap Proc No / Section: 1-PT 94.0 Seouence Step No:
Reference 11 Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA' 225 SDB: 225 CA: 225 Other(speelfy):
(Des'gn) CB: moving CC: 225 CD: moving Below Nuclear Heating ill Bank Positions (Steps) RCS Temperature (*F): SN7. I
Test Power Level (% F.P.)

0 l Conditions SDA: 225 SDB: 225 CA: 225 Other (speelfy):
CB: moving CC: 225 CD: moving Below Nuclear Heating (Actual)
Date/ Time Test Performed:
/_,// o/'7 7 /6 WS Measured Parameter lons; integral Worth of Control Bank D, (Description) Rod Swap IV Measured Value lons= //I(o. 2- Adjusted Measured Critical Reference Bank Position = (9 ~7 steps)
Test Results Design Value Rs lo = llll.Op (Adjusted Measured Critical (Actual Conditions)
Reference Bank Position = N'? steps)
Design Value (Desigri Conditions) loRs= 1107
~~166 pcm (Critical Reference Bank Position = 203 steps)~~
Reference Technical Report NE 1129, Rev. O, VEP-FRD-36A FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD 36A Design Tolerance is met : 7 YES NO Acceptance Criteria is met : V YES NO VI Comments Prepared By:, Mo Reviewed By:
f NE-1133 NIC12 Startup Physics Tests Report Page 49 of 57
1 NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l Test
~~Description:~~
Control Bank C Worth Measurement, Rod Swap Proc No / Section: 1-PT 94.0 Sequence Step No:
Reference 11 Bank Positions (Steps) RCS Temperature ( F): 547 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA- 225 Other (specify):
(Design) CB: meving CC: moving CD: 225 Below Nuclear Heating ill RCS Temperature ( F):
Bank Positions (Steps) fg' Test Power level (% F.P.): 0 Conditions SDA: 225 SDB: 225 CA' 225 Other (specify):
(Actual) CB: moving CC: moving CD: 225 Below Nuclear Heating Date/ Time Test Performed:
( 6-(6-91 F731 Measured Parameter lens; integralWorth of Control Bank C, (Description) Rod Swap IV Measured Value lens,7 g3.1 (Adjusted Measured Critical Test Reference Bank Position = /Tsteps)
Results Design Value (Actual Conditions) IcI8= 8//O (Adjusted Measured Critical Reference Bank Position = /94 steps)
Desig'1 Value (Design Conditions) Ic"8= 818 122 pcm (Critical Reference Bank Position = 170 steps)
Reference Technical Report NE-1129. Rev. O, VEP FRD 36A FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-3SA Design Tolerance is met : ES __._ N O Acceptance Criteria is met : YES NO VI '
Comments Prepared By: Reviewed By:
NE-1133 NIC12 Startup Physics Tests Report Page 50 of 57
) NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test Descripticn: Control Bank A Worth Measurement, Rod Swap Reference Proc No / Section: 1-PT 94.0 Seouence Sten No:
Bank Positions (Steps) RCS Temperature ("F): 547 ei Test Power Level (% F.P.): O Conditions SDA: 225 SDB: 225 CA moving Other (specify):
(Design) CB: moving CC: 225 CD: 225 Below Nucleat Heating 111 Bank Positions (Steps) RCS Temperature ('F): 547,2.
Test Power Level (% F.P.): O Conditions SDA- 225 SDB: 225 CA' moving Other (specify):
CB: moving CC: 225 CD: 225 Below Nuclear Heating (Actual)
Date/ Time Tpst Performed:
(plwf 9-) /7:56 i
Measured Parameter lys; integral Worth of Control Bank A, (Description) Rod Swap IV Measured Value Ix"S= 33(,.TgAdjusted Measured Critical Reference Bank Position = 75 steps)
Test Results Design Value Ifs = 3Z58 (Adjusted Measured Critical (Actual Conditions) ~
Reference Bank Position = 76 steps)
Design Value (Design Conditions) 14 as= 346 i 100 pcm (Critical Reference Bank Position = 96 steps)
Reference Technical Report NE-1129, Rev. O, VEP FRD-36A FSARTTech Spec if Design Tolerance is exceeded, SUSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A Design Tolerance is met : V YES NO Acceptance Criteria is met : Vj.;% NO VI '
Comments Prepared By: h- Reviewed By:
NE-1133 NIC12 Startup Physics Tests Report Page 51 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
Shutdown Bank B Worth Measurement, Rod Swap
, Reference Proc No / Section: 1-PT-94.0 Sequence Step No:
ll Bank Posit!ons (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): O Conditions SDA: 225 SDB: moving CA: 225 Other (specify):
(Design) CB: moving CC: 225 CD: 225 Below Nuclear Heating l Ill Bank Positions (Steps) RCS Temperature ("F): 5%',,7 Test Power Level (% F.P.): 0 Conditions SDA- 225 SDB: moving CA- 225 Other (specify):
(Actual) CB: moving CC: 225 CD: 225 Below Nuclear Heating l
Date/ Time Test Performed:
(,lioin /8: 10 Measured Parameter Iss"5; integral Worth of Shutdown Bank B, (Description) Rod Swap IV Measured Value iss"8= /05/. ((Adjusted Measured Critical Test Reference Bank Position = /6C steps)
Results Design Value (Actual Conditions) Iss" /0N * 'p/ (Adjusted
, Measured Critical Reference Bank Position = /55' steps)
Design Value (Design Conditions) Iss"8= 1087 a 163 pcm (Critical Reference Bank Position = 20' steps)
Reference Technical Report NE-1129. Rev. O. VEP-FRD 36A _
FSARRech Spec if Design Tolerance is exceeded, SNSOC shall V
evaluate impact of test result on safety analysis.
Acceptance SNSOC .T,ay specify that additional testing Criteria be performed.
Reference VEP FRD-36A Design Tolerance is met : V YES NO Acceptance Criteria is met : V YES NO VI '
Comments Prepared By:
y
. Reviewed By: 7-/ M NE-1133 N1C12 Startup Physics Tests Report Page 52 of 57
) NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULT 3 AND EVALUATION SHEET I
Test
~~Description:~~
Shutdown Bank A Worth Measurement, Rod Swap 1-PT 94.0 Seouence Step No:
Reference Proc No / Section:
Bank Positisns (Steps) RCS Temperature ("F): 547 ll Power Level (% F.P.): O Test Conditions SDA: moving SDB: 225 CA- 225 Other (specify):
CB: moving CC: 225 CD: 225 Below Nuclear Heating (Design) lil Bank Positions (Steps) RCS Temperature ("F): $p g Test Power Level (% F.P.): O Conditions SDA: moving SDB: 225 CA: 225 Other (specify):
CB: moving CC: 225 CD: 225 Below Nuclear Heating (Actual) l l (0-/ 6 -4 7 ghc-[+a1 Date/ Time Test Performed:
1 'i Measured Parameter Ids; integral Worth of Shutdown Bank A.
(Description) Rod Swap IV Measured Value I/8=/02.L 7 (Adjusted tAeasured Cytg Test Reference Bank Position =%teos)
Results Design Value 1/s, Sti S (Adjusted tAeasured Critical (Actual Conditions)
Reference Bank Position = / 6i steps)
Dosign Value (Design Conditions) lds= 938 141 pcm (Critical Reference Bank Position = 185 steps)
Technical Report NE 1129, Rev. O, VEP FRD 36A Reference '
FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis.
V SNSOC may specify that additional testing Acceptance be performed.
Criteria Reference VEP-FRD-36A Design Tolerance is met : V YES NO Acceptance Criteria is met : /ES NO VI .
~ Comments Reviewed By: M Prepared By: e NE-1133 NIC12 Startup Physics Tests Report Page 53 of 57
. .! NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
Total Rod Worth, Rod Swap Reference Proc No / Section: 1-PT 94.0 Sequence Step No:
11 Bank Positions (Steps) RCS Temperature (*F): 547 Test Power Level (% F.P.): O Conditions SDA moving SDB: moving CA: moving Other(specify):
(Design) CB: moving CC: moving CD: moving Below Nuclear Heating lil Bank Positions (Steps) RCS Temperature ( F): 547.O Test Power Level (% F.P.): O Conditions SDA' moving SDB: movir.g CA: moving Other (specify):
(Actual) CB: moving CC: moving CD: moving Below Nuclear Heating Date/ Time Test Performed:
6 folr7 12.: 12 Measured Parameter lys integral Worth of All Banks, (Description) Rod Swap IV Measured Value I u= 6693. / pcm t
Test Results Design Value (Actual Conditions) 17 .= $$ W Y pcm =
Design Value (Design Conditions) 17 = 5557 i 555 pcm Reference Technical Report NE-1129. Rev. O. VEP FRD 36A FSAR/ Tech Spec if Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance Additional testing must be performed.
Criteria _
Reference VEP FJ1D-36A Design Tolerance is met : ES NO Acceptance Criteria is met : YES NO VI Comments Prepared By:
V W Reviewed By: kW NE-1133 NIC12 Startup Physics Tests Report Page 54 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
M/D Flux Map - At Power Reference Proc No / Seetion: 1.PT 64.0,1M.21.1.1M 21.2 Segueace Sten No:
11 Bank Positions (Steps) RCS Temperature ("F): Tngr
~~1 Test Power Level (% F.P.): s 30 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):~~
~~(Design) CB: 225 CC:~~
~~CD:~~
Must have a 38 thlmbles" til Bank Positions (Steps) RCS Temperature ( F): y Test Power Level (% F.P.): gyo/f Conditions SDA: 225 SDB: 225 CA: 225 Other (specify); (,:t y,g 7 /s)
(Actuali CB: 225 CC: CD:
Test Performed:
Datemme/97 C,/u 0413 '
Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive incorn Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FAH(N) Factor Fo(Z) Power Tilt Test Measured 4.67, fer l.' 20.9 Results value 4M Sr ff 4M !' 2'033 O*70#/*
Design Value s10% for Pa a 0.9 (Design a15% for Pi <0.9 N/A N/A s 1.0244 Conditions) &= assy power)
Reference WCAP 7905 Rev.1 None None WCAP.7905, Rev.1 V FSAR/COLR None FAH(N)s1.49(1+0.3(1 P)) Fo(Z)s4.38*K(Z) None Acceptance Criteria Reference None COLR 2.6 COLR 2.5.1 None Design Tolerance is met : ..cf YES NO Acceptance Criteria is met : / YES NO VI
~~As required Comments " Must have at least 16 thimbles for quarter core maps for multi-point calibrations A ,k Prepared By: f Reviewed By~~
, l/ 1 NE-1133 NIC12 Startup Physics Tests Report Paga 55 of 57
NORTH ANNA POWER STATION UNIT 1 CYCLE 13 STARTUP PHYSIOS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
M/D Fhm Map - At Power Proc No / Section: 1 PT-64.0.1.PT 21.1.1.PT.21.2 SBCluence Step No:
Reference 11 Bknk Positions (Steps) RCS Temperature ("F): Tw a 1 -
Test Power Level (% F.P.):65 s P s 75 Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Design) CB: 225 CC: 225 CD:
Must have :t 38 thlmbles" lli Bank Positions (Steps) RCS Temperature ( F): 5f Test Power Level (% F.P.): ygge d Conditions SDA: 225 SDB: 225 CA: 225 Other (specify):
(Actual) CB: 225 CC: 225 CD: 189 O NMICJ Date/ Time Test Performed:
(o /t3f97 02100 Maximum Relative Nuclear Enthalpy TotalHeat Maximum Measured Assembly Rise Hot Flux Hot Positive incore Parameter Power %DIFF Channel Factor Channel Quadrartt IV (Description) (M-P)/P FAH(N) Factor Fo(Z) PowerTilt Test Measured 3.2 '4 P 2: e.8) 3p j , .7 q j, g Results value -5.s t' P d o '3 co,g .j,)
Design Value s10% for P a0.9 (Design 15% for P60.9 N/A N/A : 1.0238 Conditions) (Pi m assy power)
Reference WCAP 7905, Rev.1 None None WCAP 7905 Rev.1 V FSAR/COLR None FAH(N)st.49(1+0.3(1 P)) Fo(Z)s(2.19/PTK(Z) None Acceptance Criteria Reference None COLR 2.0 COLR 2.5.1 None Design Tolerance is met : V YES NO Acceptance Criteria is met : ./ YES No VI
~~As required Comments " Must have at least 16 thimbles for quarter core maps for multi-point calibrations Prepared By: / d /d - Reviewed By:~~
~&
NE-1133 NIC12 Startup Physics Tests Report Page 56 of 57 1
et NORTH ANNA POWER STAsTION UNIT 1 CYCLE 13 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
~~Description:~~
M/D Flux Map - At Power Reference Proo No / Section: 1.PT.94.0,1.PT 21.1.1-PT.21.2 Sequence Step No:
11 Bank Positions (Steps) RCS Temperature ("F): Tatr
~~1 Test Power Level (% F.P ):95 s P s 100 Conditions SDA: 225 SDB: 225 CA- 225 Other (specify):~~
(Design) CB: 225 CC: 225 CD: Must have 2 3B thimbles" 111 Bank Positions (Steps) RCS Temperature ( F): Tger Test Power Level (% F.P.): q(,,(, g e/,
Conditions SDA: 225 SDB: 225 CA: 225 Other (specify): //4 gg (Actual) CB: 225 CC: 225 CD: 215' Date/ Time Test Performed:
G/2t,/97 10817 Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive incore Parameter Power %DIFF Channel Factor Channel Quadrant IV (Description) (M P)/P F6H(N) Factor Fo(Z) Power Tilt Test Measured 3.09. rose P, tea I- !'
Results value 00f.' rm 6 448 Design Value s10% for P, a0.9 (Desi9 n :15% for P,<0.9 N/A N/A s 1.023B Conditions) (P = assy power) #
i WCAP-7905, Rev,1 None None WCAP.7905, Reference Rev.1 V FSAR/COLR None F A H(N)s1.49(1+0.3(1.P)) Fo(Z)s(L19/P) K(Z) None Acceptance Criteria Reference None COLR 2.6 COLR 2.5.1 None Design Tolerance is met : X YES NO Acceptance Criteria is met - X YES NO Vi
~~As required Comments " Must have at least 16 thimbles for quarter core maps for multi-point calibrations v.~~
Piepared By: 4 b Reviewed By: )l NE-1133 NIC12 Gtartup Physics Tests Report Page 57 of 57
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