B17848, Startup Test Rept Cycle 7. with
| ML20217D280 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/30/1999 |
| From: | Necci R NORTHEAST NUCLEAR ENERGY CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B17848, NUDOCS 9910150101 | |
| Download: ML20217D280 (17) | |
Text
E 4,
ggg Rope Feny Rd. (Route 156), Waterford, Cr 06385 Nuclear Energy Minstone Nuclear Power Station Northeast Nuclear Energy Company P.O. Boz 128 Waterford, CT 06385-0128 (860) 447-1791 Fax (860) 444-4277 The Northeast Utilities Synem OCT - I 1999 Docket Nos. 50-423 B17848 Re: TS 6.9.1.1 j
U.S. Nuclear Regulatory Commission i
Attention: Document Control Desk 1
Washington, DC 20555 Millstone Nuclear Power Station, Unit No. 3 Startuo Test Report for Cycle 7 Pursuant to Millstone Unit No. 3 Technical Specification 6.9.1.1, Northeast Nuclear Energy Company (NNECO) hereby' submits the enclosed Unit No. 3 Startup Test Report for Cycle 7.-
- There are no regulatory commitments contained within this letter.
If. you have any additionial questions concerning this submittal, please contact Mr. David W. Dodson at (860) 447-1791, Ext. 2346.
Very.truly yours,
' NORTHEAST NUCLEAR ENERGY COMPANY I
cc 1
Raymond P. Necci Vice President - Nuclear Oversight and Regulatory Affairs l
Enclosure:
Millstone Nuclear Power Station Unit No. 3 Startup Test Report - Cycle 7 cc:
H. J. Miller, Region i Administrator
- 7 h.
A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 J. A. Nakoski, NRC Project Manager, Millstone Unit No. 3 Y/
9910150101 990700 PDR ADOCK 05000423 P
e, a
Docket No. 50-423 B17848 1
1
?
Enclosure Millstone Nuclear Power Station, Unit No. 3 Startuo Test Report - Cycle 7 l
1 l
October 1999
Millstone Nuclear Power Station Unit No. 3 Startup Test Report Cycle 7 :
1 September 1999 i
l
)
i I
l l
l j
. r..
o U
Table of Contents t
Pane
. List of Tables..
3 j
List of Figures 4
.1.0
{
SUMMARY
5
' 2. 0 -
INTRODUCTION...
5 3.0.
FUEL' DESIGN 6
4.0 ~
LOW POWER PHYSICS TESTING...
6 4.1 '
Critical Boron Concentrations.....
6 4.2
' isothermal / Moderator Temperature Coefficients.
6
. 4.3 Control Rod Reactivity Worth Measurements 7
5.0
. POWER ASCENSION TESTING 8
5.1 -
Power Distribution, Power Peaking and Tilt Measurements.
8 5.2.
Boron Measurements.
9
- 5. 3
' Reactor Coolant System Flow Measurement 9
6.0 REFERENCES
10 Millstone Unit 3 Cycle 7 Startup Report Page 2 of 15 A
1 List of Tables I
Table Pane 1
Summary of Boron Endpoint Results...
6
.2 Isothermal / Moderator Temperature Coefficient Results..
7
(- 3 Control Bank Integral Worth Results 7
4
. Summary of Measured Axial Offset and INCORE Tilt..
8 5
Comparison of Measured Fo to FaRTP limit for each Fuel Type 8
I 6-Comparison of Measured Fah to Fah limit for each Fuel Type 9
j l
l 1
l 1
l i
I i
Millstone Unit 3 i
Cycle 7 Startup Report Page 3 of 15 i
I
.. n List of Figures Floure Pane 1
' Cycle 7 Load'ing Plan........
11 l
2
'INCORE Po' wer Distribution - 30%.
.12 3:
. INCOR$ Power Distribution - 50%....
13 4
INCORE Power Distribution - 75%....
14 5
INCORE Power Distribution - 100%...........
15 7
)
l 1
I l
I Millstone Unit 3 Cycle 7 Startup Report Page 4 of 15
s 1.0
SUMMARY
Low Power Physics Testing and Power Ascension Testing for Millstone Unit 3, Cycle 7 identified no unusual situations or anomal;es. All parameters were determined to be within their acceptance criteria. All Technical Specifications were met.
2.0 INTRODUCTION
The Millstone Unit 3 Cycle 7 fuel reload was completed on June 1,1999. The attached core map (Figure 1) shows the final core configuration. Cycle 7 uses a low leakage loading pattern consisting of 81 new Region 9 fuel assemblies,84 Region 8 once burned fuel assemblies and 28 Region 7 twice burned fuel assemblies. The 81 feed fuel assemblies are the Westinghouse 17x17 Robust Fuel Assembly (RFA) design and the 112 re-inserted fuel assemblies are the Westinghouse 17x17 Vantage 5H design (V5H).
The 81 Region 9 assemblies are comprised of 21 assemblies enriched to 4.40 w/o U23s j
and 60 assemblies enriched to 4.8 w/o U23s The top and bottom regions of the fresh fuel are comprised of a 6 inch annular blanket region enriched to 2.6 w/o U23s The region 7 and 8 fuel blanket regions were 6 inch natural enriched annular regions. The fuel assembly locations for the fresh fuel were randomly assigned to prevent power tilts across the core due to systematic deviations in the frest 'uel composition.
Other changes to the Cycle 7 core were the replacement of 2 single encapsulated secondary sources with 2 new un-activated double encapsulated secondary sources and the replacement of 10 rod control cluster assemblies (RCCA). The secondary source design is the same as those placed in service for Cycle 6 operation. The secondary source locations have been changed to core locations H3, C8, H13, and N8 from core locations G4, D9, J12, and M7. The secondary sources and RCCAs were provided by Westinghouse.
Every core location in Cycle 7 has an insert: 4 secondary sources,61 RCCAs, and 128 thimble plugs.
Subsequent operational and testing milestones were completed as follows:
Initial Criticality June 26,1999 Low Power Physics Testing completed June 27,1999 Main Turbine On-Line June 29,1999 30% Power Testing completed on June 30,1999 75% Power Testing completed on July 3,1999 100% Power Testing completed on July 7,1999 Cycle 7 operation is with 193 Westinghouse manufactured fuel assemblies. The Safety Analysis is provided by Westinghouse and the Nuclear Design Report was generated by Northeast Nuclear Energy Company.
Millstone Unit 3 Cycle 7 Startup Report Page 5 of 15
3.0 FUEL DESIGN
- The new Robust Fuel Assembly differs from the previous fuel design in that it incorporates the Westinghouse protective bottom grid (P-Grid), thicker walled control rod guide tubes and instrument tube, and modifications to the mixing vane grids and Intermediate Flow l
Mixer (IFM) grids. The P-Grid improves the fuel assembly's resistance to debris and thus i
debris related failures. The thicker walled guide and instrument tubes make the fuel assembly more resistant to bowing and twisting, thereby further reducing the possibility of an incomplete rod insertion event. The modifications to the mixing vanes grids and IFM's improve the fuel assemb!y thermal performance and increase the margin to fuel related design limits.
4.0 LOW POWER PHYSICS TESTING The low puwer physics testing program for Cycle 7 consisted of the following: Critical Boron Endpoint measurements for All Rods Out (ARO) and Control Banks Inserted conditions, ARO Moderator / Isothermal Temperature Coefficients measurements and Control Bank Worth measurements. Low power physics testing was performed at a power levels below the point of adding nuclear heat to avoid nuclear heating effects.
l 4.1 Critical Boron Concentrations The critical boron concentration was measured for two core configurations: All Rods Out and Control Banks inserted. The test results are provided in Table 1 along with the design predictions. All measured values include corrections to experimental data to account for differences between the critical rod configuration and the endpoint configuration. The acceptance criteria of11000 pcm (1162 ppm) was met for both the ARO and control ba,1ks inserted configurations. The measured boron worth (ppm) of the Control banks was consistent with the measured reactivity worth and met the review criteria of 561 ppm 156 ppm.
l l
Table 1 Summa:y of Boron Endpoint Results Measured Predicted M-P Acceptance (ppm)
(ppm)
(ppm)
Criteria i
l-(ppm)
L FWods Out (ARO) 2205 2273
-68 1162 l
Control Banks 1662 1712
-50 1162 Inserted i
_ 56 i
Difference 543 561
-18
+
i 4.2 Isothermal / Moderator Temperature Coefficients Isothermal Temperature Coefficient data were measured for the All Rods Out configuration only. Controlled heat-ups and cool-downs were performed and the reactivity change was measured. These measurements were corrected for ARO conditions and the Millstone Unit 3 Cycle 7 Startup Report Page 6 of 15 l
l
r 1
averages of the corrected results are presented in Table 2 and compared to the design predictions and acceptance criteria. The acceptance criteria were met.
The Moderator Temperature Coefficient was calcu:ated by subtracting the design doppler temperature coefficient (-1.71 pcm/ F) from the ARO Isothermal Temperature Coefficient (lTC). In addition to comparing the measured MTC to the predicted value, it was required to verify that the Technical Specification MTC Limit of MTC < +5.0 pcm/ F at ARO Hot Zero Power (HZP) was met. As shown in the data presented in Table 2, ALL acceptance criteria were met.
i l
Table 2 Isothermal / Moderator Temperature Coefficient Results Measured Predicted M-P Acceptance (pcmrF)
(pcmFF)
(pemfF)
Criteria (pcmfF)
ARO ITC
-1.60
-1.17
-0.43 12.0 ARO MTC
+0.11
+ 0.54
-0.43 12.0 & < +5.0 4.3 Cuiitrol Rod Reactivity Worth Measurements The integral reactivity worths of the Control Banks were measured using the sequential dilution method. The individual Bank worths for control banks D, C, B, and A along with the total reactivity worth of the control banks are presented in Table 3. The acceptance criteria for any individual control bank is the greater of either11.00 pcm or115% of the predicted worth. The acceptance criteria for the Total Worth of the Control Banks inserted is 110% of the predicted worth.
Table 3 Control Bank Integral Worth Results Measured Predicted M-P
% Difference (pcm)
(pcm)
(pcm)
(M-P/P)
Control Bank D 559 558 1
0.18 Control Bank C 930 914 16 1.75 Control Bank B 829 802 27 3.37 Control Bank A 1165 1184
-19
-1.60 Total 3483 3458 25 0.72 The measured results of the individual bank worths and the total control bank worths showed excellent agreement with the predicted values. All acceptance criteria for control bank worths were met.
Millstone Unit 3 Cycle 7 Startup Report Page 7 of 15
5.0 POWER ASCENSION TESTING 4
i 5.1 Power Distribution, Power Peaking and Tilt Measurements q
i The core power distribution was measured through the performance of flux maps during
_ the power ascension to ensure compliance with Technical Specifications. The results from the flux maps were used to verify compliance with the power distribution technical specifications.
1 A low power flux map, at approximately 30% rated thermal power, was performed to determine if any gross neutron flux abnormalities existed. A mid-power flux map was j
performed to gather necessary data to perform an INCORE to EXCORE calibration via j
the single point methodology. Per Technical Specification Surveillance 4.3.1.1, Table 4.3-1 Functional Un:t 2 Note 6 a flux map at approximately 75% power was performed for
'NCORE to EXCORE calibration. Once hot full power equilibrium conditions were reached, another flux map was performed to verify core power distributions were within the design limits.
Table 4 presents a summary of the Measured Axial Offset and INCORE Tilt for the flux maps performed during Power ascension. Presented in Tables 5 and 6 are comparisons of the measured Fa and F h (including uncertainties) to their respective limits from each 3
of the flux maps performed during the power ascension.
l i
As can be seen from the data presented in Tables 5 and 6, ALL acceptance criteria were j
met and no abnormalities in core power distribution were observed during power j
ascension.
Table 4 Summary of Measured Axial Offset and INCORE Tilt
" Power Burnup Rods A.O. (%)
INCORE Tilt
(%)
(MWD /MTU)
(steps) 28.9 14.2 190 8.216 1.0069 48.3 27.0 190 3.841 1.0060 74.8 55.7 203 1.796 1.0066 99.8 193.3 215
-1.223 1.0062 Tab!e5 Comparison of Measured Fa to Fa"'P limit for each Fuel Type Power Bumup Type 1 Type 2 Fa"" Limit
(%)
(MWD /MTU)
(V5H)
(RFA) 28.9 14.2 1.779 2.074 2.60 48.3 27.0 1.722 1.962 2.60 74.8 55.7 1.671 1.931 2.60 99.8 193.3 1.646 1.922 2.60 Millstone Unit 3 Cycle 7 Startup Report Page 8 of 15
a..,
u
+.
1 Table 6 Comparison of Measured Fah to Fah limit for each Fuel Type j
Power Burnup Type 1
. Type 1 Type 2 Type 2
(%)
(MWD /MTU)
(V5H)
Limit (RFA)
Limit 28.9 14.2
.1.254 1.868 1.501 1.917 46.3 27.0 1.267 1.779 1.45b 1.825 74.8 55.7 1.267 1.656 -
1.477 1.699
,99.8 193.3 1.281 1.541 1.463 1.581 Presented in Figures 2,3,4 and 5 are measured Power Distribution Maps and percent difference from the predicted power for 30%,50%, 75% a.nd 100% power. From these data it can be seen that there is good agreement between the measured and predicted i
assembly powers.
)
5.2 Boron Measurements Hot full power all rods out boron concentration measurements were performeu upon reaching equilibrium conditions. The measured All Rods Out, Hot Full Power, equilibrium xenon, boron concentration was 1563 ppm with a predicted value of 1609 ppm. The predicted to measured difference was -253 pcm which met the acceptance criteria ofi 1000 pcm.
5.3 Reactor Coolant System Flow Measurement
- The Reactor Coolant Flow rate was determined using a secondary calorimetric heat balance for each loop using the steam generators as the control vo) mes. The following
{
parameters were measured:
Reactor Coolant System Pressure j
e Hot Leg Temperatures e
Cold t.eg Temperatures e
Feedwater Temperatures e
Feedwater Flow Rates e
Feedwater Pressure e
Steam Generator Pressure Steam generator blowdown was isolated during the data acquisition period.
Per Technical Specification Surveillance 4 2.3.1.2, the Reactor Coolant System Flow was measured prior to operation above 75% rated thermal power. The measured flow at
. approximately 75% rated themmal power was 402,876 gpm with a minimum required flow cf 371,920 gpm. The reactor coolant system flow measurement was re-performed once reachinc 100% tated thermal power The measured flow at 100% power was 403,018 gpm with a minimum required flow of 371,920 gpm.
AtL accepiance criteria were met.
Millstone Unit 3 Cycle 7 Startup Report Page 9 of 15
6,.0 REFERENCES 6.1 SPROC ENG99-3-18, Cycle 7 Low Power Physics Testing (IPTE) 6.2 SPROC ENG99-3-22, Cycle 7 Power Ascension Testing 6.3 Nuclear Design and Core Physics Characteristics of the Millstone Generating Station Unit 3, Cycle 7 6.4 ANSI /ANS 19.6.1 (1985) Reload Startup Physics Tests for Pressurized Water Reactors.
6.5 M3-99-013, Reload Design for Millstone Unit 3 Cycle 7 Millstone Unit 3 Cycle 7 Startup Report Page 10 of 15
- 'y
- +.-
9 Rage 11 of 15 FIGURE 1 CORE LOADING PATTERN MILLSTONE UNIT 3 - CYCLE 7 R
~P W
14 L
K J
M-G F
E D
C B
A 7
8 7
7' 7
8
.7 1
G62 M74 004 G28 G20 ud8 G46 7
8 93 93 95 93' 93-95 95 8
7 2
G40 M64 J23 J36 J41 J60 J43 J52 J25 M69 G19 7
9a 93 9A 8
8 9A 8
8 9A 95
.92 7
3 G1d J26 J53 J14 M11 E42 J02 N79 N16 J16 J35 J31 G50 8
9a 8
8 9a 8
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93 8
8 95 8
4 M40 J56 NO3 M73 J65 H84 H23 H29 J67 M65 N07 J37 M35 7
93 9A 8
95 8
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95 8
98 8
9A 98 7
-5 081 J32 J17 M46 J76 B01 J77 H39 J59 N63 J80 N37 J19 J22 Otid 8
9s 8
sa 8
8 8
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8 8
95 8
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-6 M70 J47 N09 J61 N68 N05 X20 J04 H21 H04 B66 J71 M15 J48 1 0 7
95 8
8 95 8
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8 93 7
-7 G06 J44 M71 M45 J72 H26 J05 M77 J10 R27 J68 M31 H54 J45 G18 7
93 9A 8-B-
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8 9A 95 7
G21 J69 J11 M28 N78 J01 H52 J20 M38 J12 M72 N17 J03 J64 G25 7
9a 8
8 9a 8
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8 9a 7
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- 10 N61 J34 M14 J75 M82 MOS H25 J06 X22 N01 E56 J63 M13 J51 H50
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- 11 G74 J33 J13 M41 J62 N43 J79 M49 J78 E36 J74 N76 J21 J24 G83 0-93' 8
8 95 8-
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12 E30 J39 M06 M83 J81 N55 518 M33 J73 M75 MO2 J38 H57 7
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13 G59 J29 J55 J15 N12 M59 J07 MS3 M10 J18 J54 J30 011 7
8 93 93 95 93 93 95
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7 14 008 M67 J27 J50 J57 J70 Je9 346 J28 R50 G65 7
8 7
7 7
8 7
15 -
G48 R47 G09 G24 G07 H34 055 00 LEGEND REGION ASSEMBLIES ENRICHMENT
.R Region Identifier 7
28 4.40 ID.
Fual Assembly Identifier
'S 84 4.60 9A 21 4.40
- ' Reconstituted Fuel Assembly 95 60' 4.80
S
[.
1 a
9 Page 12 of 15 FIGURE 2 INCORE Power Distribution - 30%
MILLSTONE UN f 3 - CYCLE 7 R
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- is Page 13 of 15 FIGURE 3 ANCORE Power Distribution - 50%
NILLSTONE UNIT 3 - CYCLE 7 R-P N
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-2.7
(.9 y
.4
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(.9 j f T f T r
-.466 1.182 1.111 1.259 1.099 '
1.149 1.165 '
1.264 1.132 1.127 1.099 1.259 1.125 1.212
.477
-10 1.7
' 1.8 1.6
.6
(.5 j
.0 (1.0y
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-1.6
-1.9 7
(.8 y 4
.7
.8 l
r T
/ T
'1.157 1.307 1.116 '1.270 '
1.112 1.225 1.080 '.323
-11 r T r T
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'.318 1.062 1.170 1.084
'1.238 '
1.101 1.289
~ 1.9 d.0 '
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v1.2j
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1.1 (1.4y 1.5 2.3
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(.3 j
(-1.9j r T
/ T r T
.605 1.245 1.103 1.077
'1.247 '
1.132 1.122 1.149 1.280 1.119
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1.307
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1.7 v1.7j
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.998 1.246
'1.179 1.117 1.079
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.9
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1.0 y1.6y
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( 2.6 j r T
.-.609 1.071 1.192 '1.194 '
1.095 1.204
'1.219 1.100
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.329 14
/ T
/ T
,/
N
'.306
(-1.0j 1.0
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.469
.459
.442
.467
.480
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% Difference (M.P'/P M
t Measured Location kN 1
s
- \\
'o Page 14 of 15 FIGURZ 4 INCORE Power Distrib W in - 75%
MILLSTONE UNIT 3 - CYCLE 7 R.
P N
M L
K J
H G
F E
D C
B A
e e
i e
i e
/
T
/~
.336
.491
' 465 '
.442
.456
'.483
.332 1
4.0 4.0 (1.5y 1.4
.4 (2.5 j 2.8
'.32'T
/
/
g
.622 1.092 1.252 1.199
' 1.094 1.196 1.230 1.104
.618
.314 2
y.3 y
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.3
(.1 y
.3 2.2 -
1.5
.0 1.3
/
s
/ T
/ T
/ T
.308 1.009 1.264 1.179 1.107 1.082 1.211 '
1.088 '1.149 '
1.216 '1.273 '
1.029 '.331 '
3 6
.9
.6
-1.8
-1.7
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1.1
( 2.2 /
(609T"/
T x
1.254 1.134 1.076 1.243 1.137 '1.108 '
1.140 1.274 1.108 1.145 1.271
.620 4
v1.5jy-1.6 j
-1.9 1.9 1.7
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.6
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-1.0
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x
.325 1.090 1.199 1.095
'1.266 1.111 1.305 1.138 '1.289 '
1.100
'1.254 1.085 '1.181 '
1.069
.319
-5
.6
.2
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-1.1 41.6 j 1.7 1.2
/ T
/ T
/ T
/ T
/ T
'.482 '
1.225
'1.144 1.273 1.116
'1.144 '
1.146 '1.252 '
1.152 1.151 1.112 1.263 1.119
'1.196 '
.466
-6
( 2.3 j 1.8 y 1.5 j
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(.2 j
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1.3
/
s
/
x
/ T r T
.466 1.204 1.085 '1.137 1.311 1.145
' 1.242 1.101 1.252
' 1.152 '
1.291 1.138
' 1.084 '
1.190
.452
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/ T
/
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/ T r T r T
.437
'1.195 1.103
'1.146 1.249
'1.094 1.136 1.118
' 1.260 1.136
' 1.107 ' 1.216 1.102 '
.443
-8
(.2 j
-1.1 g 1.7j 2
x1.2j 1.5
(-2.7j
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(. 6 j
.4
(.2 j(.0 j
.8 j 1.6 (1.181T r
N r T r7
.457 1.052 1.128 1.293 1.145 1.243
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1.126
' 1.276 '
1.128 1.079 1.202 '.462 ' -9
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(.6 j
-A
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r T r N r T
.462 1.177 1.089 1.259 '1.094 '
1.144
'1.164 '
1.271 1.135 1.127 1.094
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.S
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/
'N r T
/
T r T
/
3
'.320 1.074 1.174 1.090 '1.239 1.095 1.286
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(.9 j 1.2
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' 1.238,
1.119 1.109 '1.137 '
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.612 1.278 1.129 1..
1.1
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3
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.326 1.024 1.264
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.6
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- 4 (4.5 y
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/
g
/ T
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.312
.613 1.070 1.183
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1.097
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1.7
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% Difference (M-P)/P.
U Measured Location
\\d
a4 g,
s' d
Page 15 of 15 FIGURE 5 INCORE Power Distribution - 100%
MILLSTONE UNIT 3 - CYCLE 7 R
P N
M L
K J
H G
F E,
D C
B A
s e
e e
e e
N
/ T
.342
.495
'.469
.446
.459
'.485 '
.336 1
4.6 4.7 y 2.2 j 1.8
.7
( 2.8 y 2.8
/
X
/ T
'.331
.624 1.071 1.238 1.183
' 1.081 '
1.174 1.205 1.084
.614
.318 2
g.6 j
.6
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.3 1.9
.6 1.9
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/ T r T e
s
/
s
.313 1.002 1.250 1.180 1.108 1.079
'1.198 '
1.082 '1.133 '
1.195
' 1.251 '
1.020 '.337 '
3
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.1 y.0 j
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(-2.0j
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/
T
/ T
'.607 ' 1.237 '
1.158 1.093 1.241 1.138
'1.111 '
1.139 1.267 1.109 1.170 1.261
.625 4
(-3.0 jx-3.1 j 2.4
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.8
(.7 j
.8
.4 4
1.4 1.0
.5 r T r 3 r T
/ T 1
.326 1.070 1.184 1.102
'1.269 '
1.115 1.298 1.143
'1.288 1.108
'1.255 1.096
' 1.177 '
1.058
.323
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-1.4 1.0
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.8
(.8 j
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(.3 j 1.2 s 1.8 j 1.7 1.2
{
r
'N
/
'N
,/ T
/ T
/ T
'.483 1.205
'1.141 1.270 1.121 1.152 1.155
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1.163 1.160 1.116 1.256 1.115
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.468
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/
's
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.471 1.191 1.085 '1.140 '
1.306 1.158 '1.256 '
1.129 1.267
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1.171
.454
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3.3 1.8
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(.5 j
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(.4 /
.2
-1.1 (445'N r
'N r T
/ T
/ T
/ T r T / T 1.078
'1.168 1.109 1.152 1.260
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.449
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/ T
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/
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/
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.465
'1.174 '
1.057 1.131 1.287 1.158 1.262 1.140
' 1.246 1.146 '1.280 '
1.133 1.078 1.188 '.468 ' -9 1.3
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.2
.9
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T
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.466 1.163 1.0 M 1.244
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1.147 1.279 1.152 1.142 1.104' ' 1.258 '
1.112 1.224
.489
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1.5
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.0
.6 4
(.3 y
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/
'N
/
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/ T
/
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.324 1.067 1.163 1.096
'1.239 1.100 1.287
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1.298 1.112
'1.261 1.116 1.205 1.090 '.330 ' - 11
(.9 j
.8
-2.9 1.2 x 1.6 j
.7
.7 y 1.9 y 1.8
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(.2 y
.3
.3 1.2
(.9 j r T
/ T
/ T
.623 1.265 1.153 1.085
' 1.230 1.124 1.111 1.138 1.270 1.118
' 1.199 '
1.309
.641 12 e.8 -
.7 2.9
-2.5
(-2.5y
.5
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(.8 y
.8
.8 (1.0 y 2.6 2.4 r
T r X r
T
.330 1.017 1.254
'1.172 '
1.097 1.060
' 1.191 1.078 1.128 1.205 1.289 1.044 '.330 13
.9
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(-2.4 j
-2.1
-1.7 (.6 /
.0
.7
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( 3.1 /
/ T
/ T
/ T
/
s
'.317
.617 1.057 1.161
'1.167 1.073 1.177 '1.178 '
1.078 '.632
.339 14 p.9 y
-1.4 1.9
-1,3
(.3 j
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(.3 j
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(.6 y 1.8 r N
/ 3
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.466
.458
'.441
.465
.471
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(.9 j
-1.3
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(.7 j 1.3
.4
.0 Measured Power
% Difference (M.P)/P U
Measured Location d