NL-11-049, Revised Core Operating Limits Report
| ML11133A212 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/04/2011 |
| From: | Robert Walpole Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-11-049 | |
| Download: ML11133A212 (28) | |
Text
Enterayv Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB
'Entergy P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 Robert Walpole Licensing Manger NL-1 1-049 May 4, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Revised Core Operating Limits Report Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64
Dear Sir or Madam:
Enclosures 1 and 2 to this letter provide Entergy Nuclear Operations Core Operating Limits Report (COLR) for Indian Point 3 Cycle 17. This report is submitted in accordance with Technical Specification 5.6.5.d. For completeness two revisions are enclosed. The change from revision 3 to 4 was a minor editorial change made to a procedural note. Both revisions are based on the same Westinghouse supplied COLR.
There are no new commitments contained in this letter. If you have any questions or require additional information, please contact me at 914-734-6710.
Sincerely, RW/mb cc: next page
NL-1 1-049 Docket No. 50-286 Page 2 of 2
Enclosure:
- 1. 3-GRAPH-RPC-16, Rev. 3, Core Operating Limits Report
- 2. 3-GRAPH-RPC-16, Rev. 4, Core Operating Limits Report cc: Mr. William Dean, Regional Administrator, NRC Region 1 Mr. John Boska, Senior Project Manager, NRC NRR DORL IPEC NRC Resident Inspector's Office Mr. Francis J. Murray, President and CEO, NYSERDA (w/o enclosure)
Mr. Paul Eddy, New York State Department of Public Service
ENCLOSURE 1 TO NL-11-049 3-GRAPH-RPC-16, Rev. 3, Core Operating Limits Report ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT UNIT 3 NUCLEAR POWER PLANT DOCKET No. 50-286
Enteg Procedure Use Is: Control Copy:
Nuclear Northeast 0 Continuous Effective Date: / /( ,
0 Reference
[3 Information Page 1 of 12 3-G RA0,1141PC-1'6, I~ijn3 I CORWMFRATING LIMITS$-PeREPORT 1Approved By:
Proedre DMDeIa petr ieuhm
- Procedure Owner PARTIAL REVISION
No: 3-GRAPH-RPC-16 Rev: 3 CORE OPERATING LIMITS REPORT Page 2 of 12 REVISION
SUMMARY
(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 17 Specific Data.
2.0
SUMMARY
OF CHANGES 2.1 Updated data throughout the graph to reflect cycle 17 per Indian Point Unit 3 Cycle 17 Core Operating Limits Report (COLR), Revision 0, as supplied by Westinghouse.
2.2 Changed TS 3.1.6 Control Bank Insertion Limits from each control bank shall be considered fully withdrawn at > 230 steps to each control bank shall be considered fully withdrawn at _ 225 steps.
2.3 Changed the title of Attachment 1 from OVERTEMPERATURE AT to OVERTEMPERATURE AT ALLOWABLE VALUE 2.4 Clarified reference to Technical Specification Table 3.3.1-1 Note 1 Value and deleted introductory NOTE on Attachment 1.
2.5 Changed the T' definition from loop specific T to loop specific Tavg on Attachment 1
2.6 Changed the title of Attachment 2 from OVERPOWER AT to OVERPOWER AT ALLOWABLE VALUE 2.7 Clarified the reference to Technical Specification Table 3.3.1-1 Note 2 Value and deleted introductory NOTE on Attachment 2.
2.8 Changed the 1" definition from loop specific T to loop specific Tavg on Attachment 2.
2.9 Changed Labeling on Figurel from ACCEPTABLE/ UNACCEPTABLE OPERATION to ACCEPTABLE/ UNACCEPTABLE CONSEQUENCES 2.10 Added Power Level and Tech Spec Envelope values to Figure 4
No: 3-GRAPH-RPC-16 Rev: 3 REPORT CORE OPERATING LIMITS Page 3 of 12 TABLE OF CONTENTS SECTION PAGE T S 2.1.1 Reactor C ore S Ls ................................................................................................ 4 TS 3.1.1 Shutdown Margin (SDM) ...................................................................................... 4 TS 3.1.3 Moderator Temperature Coefficient (MTC) ......................................................... 4 TS 3.1.5 Shutdown Bank Insertion Limits ........................................................................... 5 TS 3.1.6 Control Bank Insertion Limits ............................................................................. 5 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ................................................................ 5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F,\ .................................................... 5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology) .6 TS 3.3.1 RPS Instrumentation ........................................................................................... 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
L im its ....................................................................................................................................... 6 TS 3.9.1 Refueling Boron Concentration ........................................................................... 6 ATTACHMENTS Attachment 1 OVERTEMPERATURE AT ALLOWABLE VALUE ........................................ 7 Attachment 2 OVERPOWER AT ALLOWABLE VALUE ..................................................... 8 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation ......................................... 9 Figure 2 Rod Bank Insertion Limits .................................................................................. 10 Figure 3 Hot Channel Factor Normalized Operating Envelope ........................................ 11 Figure 4 Axial Flux Difference Envelope Limits ................................................................. 12
No: 3-GRAPH-RPC-16 Rev: 3 CORE OPERATING LIMITS REPORT Page 4 of 12 NOTE
- The Technical Specification references shown next to each Factor OR Limit in this COLR are there to identify the corresponding sections in the Technical Specifications that refer to the COLR.
" The COLR, including any midcycle revisions or supplements, shall be provided for each reload cycle to the NRC. {T.S. 5.6.5d.)
- The data presented in this report applies to Cycle 17 ONLY and may NOT be used for other cycles of operation. Also, it applies only to operation at a maximum power level I
of 3188.4 MWt. Any technical change to this document requires a Safety Evaluation to be performed in accordance with 10CFR50.59.
TS 2.1.1 Reactor Core SLs In MODE 1 and 2, the combination of thermal power level, pressurizer pressure, and Reactor Vessel inlet temperature SHALL not exceed the limits shown in Figure 1. The safety limit is exceeded if the point defined by the combination of Reactor Vessel inlet temperature and power level is at any time above the appropriate pressure line, TS 3.1.1 Shutdown Margin (SDM)
The shutdown margin SHALL be greater than or equal to 1.3% Ak/k.
TS 3.1.3 Moderator Temperature Coefficient (MTC)
The MTC upper limit SHALL be < 0.0 Ak/k/°F at hot zero power.
The MTC lower limit SHALL be less negative than or equal to:
-38.0 pcr/-F @ 300 ppm
-44.5 pcm/°F @ 60 ppm
-47.0 pcmI9F @ 0 ppm
No: 3-GRAPH-RPC-16 Rev: 3 CORE OPERATING LIMITS REPORT Page 5 of 12 TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position _>225 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.
TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with ken _> 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.
Each control bank shall be considered fully withdrawn at ->225 steps.
TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
NOTE
" P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
" K(Z) is the fraction given in Figure 3 and Z is the core height location of F0 .
IF P > .5, Fo(Z) < (2.50 / P) x K(Z)
IF P _ .5, Fa(Z) < (5.00) x K(Z)
TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor F6H NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
AH*-<1.70 { 1 +0.3 ( 1- P
No: 3-GRAPH-RPC-16 Rev:3 CORE OPERATING LIMITS REPORT Page 6 of 12 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
Methodologv)
The Indicated limit is the Target Band; i.e., the Target +/- 5%
The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.
- 1. Overtemperature AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1 Refer to Attachment 1
- 2. Overpower AT Allowable Value as referenced in Technical Specifications Table 3,3.1-1, Function 6, Note 2 Refer to Attachment 2 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:
- a. Reactor Coolant System loop Tavg < 576.70 F for full-power Tavg = 572.0°F
- b. Pressurizer Pressure > 2204 psig
- c. Reactor Coolant System Total Flow Rate > 364,700 gpm TS 3.9.1 Refuelina Boron Concentration When required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refuel Canal, and Reactor Cavity SHALL be the more restrictive of either Ž 2050 ppm or that which is sufficient to provide a shutdown margin _>5% Ak/k.
No: 3-GRAPH-RPC-16 Rev: 3 CORE OPERATING LIMITS REPORT Page 7 of 12 Attachment 1 OVERTEMPERATURE AT ALLOWABLE VALUE I
The Overtemperature AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1 -1, Note 1 value.
The following provides the computed value:
I AT _< AT0 [K' - K2 [(1 + "Is)/(1 + T2s)] (T -T') + K3 (P - P') - fl(AI)
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
AT, is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec 1 .
T is the measured RCS average temperature, OF.
T' is the loop specific indicated T,, 9 at RTP, 0F _ 572.0°F.
P is the measured pressurizer pressure, psig.
I P' is the nominal RCS operating pressure, > 2235 psig.
K, < 1.26 K2 - 0.022/-F K3 Ž 0.00070/psi t, _25.0 sec T2 3.0 sec fi(AI) = 4.00[ -15.75 - (qt- qb)] when qt - qb < - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb
- 6.9% RTP
+3.33[(qt - qb) - 6.91) when qt - qb > 6.9% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.
No: 3-GRAPH-RPC-16 Rev: 3 CORE OPERATING LIMITS REPORT Page 8 of 12 Attachment 2 OVERPOWER AT ALLOWABLE VALUE The Overpower AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 2 value.
The following provides the computed value:
AT < AT. [K4 - K5 [(T3s)/(1 + -3s)](T) - K8(T - T ) - f2 (AI)]
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec1.
T is the measured RCS average temperature, OF.
T" is the loop specific indicated Tavg at RTP, OF _< 572.0°F.
K<4 *1.10 K5 - 0.01 75/°F for increasing T K6 > 0.0015/°F when T> T" 0/0 F for decreasing T 0/1F when T _<
T"
- T3 Ž 10 sec f2 (Al) = 0
No: 3-GRAPH-RPC-1 6 Rev:3 CORE OPERATING LIMITS REPORT Page 9 of 12 1 Figure 1 Reactor Core Safety Limit - Four Loops in Operation 29.
0.
E Z
'0 2 W 0 600 70 W0 '10 !x 120 Reactor Power (Percent of 3216 MWt)
[Conservative relative to 3188.4 MWt; use as-is for operation at 3188.4 MWt]
No: 3-GRAPH-RPC-16 Rev: 3 REPORT CORE OPERATING LIMITS Page 10 of 12 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 104 Step Overlap 230
__ _0_76 .3,230t 220 210 -BAN...-------------------------------j
- 10,7 200 190 180 170 160 -- ------------ ---- -- k--
150
,! .... -i 140 co 130 0,12 , - - LB NK C -
120 0~
-.2 100 0,
90
-WI- -V -.
26}--t -
80 02 70 0c 60 50
.. 7 - ......
40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Power (Percent of 3188.4 MWt)
No: 3-GRAPH-RPC-16 Rev: 3 CORE OPERATING LIMITS REPORT Page 11 of 12 Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)
1.2 11_6.0, 1.00 1 0 12.0, 0.925 0.8 4-I . . .....
0 0.
0.6 0
z
, 0.4 0.2 .
0 0 2 4 6 8 10 12 Core Elevation (feet)
No: 3-GRAPH-RPC-1 6 Rev: 3 CORE OPERATING LIMITS REPORT Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits 100 95 90 85 S80 Q* 75 70 65 60 55 50 30 -20 -10 0 10 20 30 40 Axial Flux Difference
ENCLOSURE 2 TO NL-1 1-049 3-GRAPH-RPC-16, Rev. 4, Core Operating Limits Report ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT UNIT 3 NUCLEAR POWER PLANT DOCKET No. 50-286
Entergy Procedure Use Is: Control Copy:
Nuclear Northeast 21 Continuous Effective Date: Lt /[(
13 Reference 13 Information Page 1 of 12
!on: 4 CORIF, PORT i m Apr roved By:
Procedure Sponsor, DM/Designee*!..; 64,a Team 3B Procedure Owner EDITORIAL REVISION
No: 3-GRAPH-RPC-16 Rev: 4 CORE OPERATING LIMITS REPORT Page 2 of 12 REVISION
SUMMARY
(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Incorporate additional Cycle 17 changes.
2.0
SUMMARY
OF CHANGES 2.1 Deleted 1 st and 2 nd NOTE bullets on Page 4 to agree with Indian Point Unit 3 Cycle 17 Core Operating Limits Report (COLR), Revision 0, as supplied by Westinghouse.
2.2 Changed 3rd NOTE bullet on Page 4 to agree with Indian Point Unit 3 Cycle 17 Core Operating Limits Report (COLR), Revision 0, as supplied by Westinghouse.
TABLE OF CONTENTS SECTION PAGE TS 2.1.1 R eactor C ore S Ls ............................................................................... 4 TS 3.1.1 Shutdown Margin (SDM) ..................................................................................... 4 TS 3.1.3 Moderator Temperature Coefficient (MTC) .......................................................... 4 TS 3.1.5 Shutdown Bank Insertion Limits ......................................................................... 5 TS 3.1.6 Control Bank Insertion Limits .............................................................................. 5 TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ................................................................ 5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FAH...............................5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology). 6 TS 3.3.1 R PS Instrum entation............................................................................................ 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)
L im its ....................................................................................................................................... 6 TS 3.9.1 Refueling Boron Concentration ........................................................................... 6 ATTACHMENTS Attachment 1 OVERTEMPERATURE AT ALLOWABLE VALUE ...................................... 7 Attachment 2 OVERPOWER AT ALLOWABLE VALUE .................................................... 8 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation ......................................... 9 Figure 2 Rod Bank Insertion Limits .................................................................................. 10 Figure 3 Hot Channel Factor Normalized Operating Envelope ........................................ 11 Figure 4 Axial Flux Difference Envelope Limits ............................................................... 12
No: 3-GRAPH-RPC-16 Rev: 4 CORE OPERATING LIMITS REPORT Page 4 of 12 NOTE The data presented in this report applies to Cycle 17 ONLY and may NOT be used for other cycles of operation. Also, it applies only to operation at a maximum power level of 3188.4 MWt. Any technical change to this document may require a Safety Evaluation to be performed in accordance with 10CFR50.59.
TS 2.1.1 Reactor Core SLs In MODE 1 and 2, the combination of thermal power level, pressurizer pressure, and Reactor Vessel inlet temperature SHALL not exceed the limits shown in Figure 1. The safety limit is exceeded if the point defined by the combination of Reactor Vessel inlet temperature and power level is at any time above the appropriate pressure line.
TS 3.1.1 Shutdown Margin (SDM)
The shutdown margin SHALL be greater than or equal to 1.3% Ak/k.
TS 3.1.3 Moderator Temperature Coefficient (MTC)
The MTC upper limit SHALL be < 0.0 Ak/k/°F at hot zero power.
The MTC lower limit SHALL be less negative than or equal to:
-38.0 pcm/°F @ 300 ppm
-44.5 pcm/°F @ 60 ppm
-47.0 pcm/0 F @ 0 ppm
No: 3-GRAPH-RPC-16 Rev: 4 CORE OPERATING LIMITS REPORT Page 5 of 12 TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position > 225 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.
TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with keff > 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.
Each control bank shall be considered fully withdrawn at > 225 steps.
TS 3.2.1 Heat Flux Hot Channel Factor (FQWZ))
NOTE
- P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
- K(Z) is the fraction given in Figure 3 and Z is the core height location of Fa.
IF P > .5, Fa(Z) < (2.50 /P) x K(Z)
IF P < .5, FQ(Z) < (5.00) x K(Z)
TS 3.2.2 Nuclear EnthalDy Rise Hot Channel Factor FAH NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
FNH <1.70 { 1 + 0.3(1-P)}
No: 3-GRAPH-RPC-16 Rev: 4 REPORT CORE OPERATING LIMITS Page 6 of 12 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
Methodologv)
The Indicated limit is the Target Band; i.e., the Target +/- 5%
The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.
- 1. Overtemperature AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1 Refer to Attachment 1
- 2. Overpower AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2 Refer to Attachment 2 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:
- a. Reactor Coolant System loop Tavg < 576.70F for full-power Tavg = 572.00F
- b. Pressurizer Pressure Ž_2204 psig C. Reactor Coolant System Total Flow Rate _>364,700 gpm TS 3.9.1 Refuelinq Boron Concentration When required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refuel Canal, and Reactor Cavity SHALL be the more restrictive of either _>2050 ppm or that which is sufficient to provide a shutdown margin > 5% Ak/k.
Attachment 1 OVERTEMPERATURE AT ALLOWABLE VALUE The Overtemperature AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 1 value.
The following provides the computed value:
AT < ATo [Kj - K2 [(1 + Tls)/(1 + T2 s)] (T - T') + K3 (P - P') - f1(AI)]
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec1.
T is the measured RCS average temperature, OF.
T' is the loop specific indicated Tavg at RTP, OF < 572.0°F.
P is the measured pressurizer pressure, psig.
P' is the nominal RCS operating pressure, > 2235 psig.
K,
- 1.26 K2 > 0.022/°F 1K3 > 0.00070/psi
'ri > 25.0 sec T2 5 3.0 sec fd(Al) = 4.00[ -15.75 - (qt - qb)] when qt - qb*< - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb
- 6.9% RTP
+3.33[(qt - qb) - 6.9]} when qt - qb > 6.9% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.
No: 3-GRAPH-RPC-16 Rev: 4 CORE OPERATING LIMITS REPORT Page 8 of 12 Attachment 2 OVERPOWER AT ALLOWABLE VALUE The Overpower AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 2 value.
The following provides the computed value:
AT < ATo [K4 - K5 [(,3S)/(1 + r3s)](T) - K6 (T - T) - f2 (00)]
Where: AT is measured RCS AT, IF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec1.
T is the measured RCS average temperature, 'F.
T" is the loop specific indicated Tavg at RTP, °F < 572.0°F.
K4 < 1.10 K5 - 0.0175/°F for increasing T K6 > 0.0015/°F when T> T O/0F for decreasing T 0/ 0F when T < T T3 -a 10 sec f2 (AI)= 0
No: 3-GRAPH-RPC-16 Rev: 4 CORE OPERATING LIMITS REPORT Page 9 of 12 Figure 1 Reactor Core Safety Limit - Four Loops in Operation 68W a
I-
]E 0e 0 10 20 30 40 50 60 70 80 90 100 110 Reactor Power (Percent of 3216 MWt)
[Conservative relative to 3188.4 MWt; use as-is for operation at 3188.4 MWt]
No: 3-GRAPH-RPC-16 Rev: 4 REPORT CORE OPERATING LIMITS Page 10 of 12 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 104 Step Overlap 230 220 210 200 190 180 C 170 160 150 4- 140 130 (0 120 a-e 110 Cz 100 0 90 cc 80 70 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Power (Percent of 3188.4 MWt)
No: 3-GRAPH-RPC-16 Rev: 4 CORE OPERATING LIMITS REPORT Page 11 of 12 Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)
1.2 1
0.8 0
0.
0.6 Z0 S0.4 0.2 0
0 2 4 6 8 10 12 Core Elevation (feet)
Figure 4 Axial Flux Difference Envelope Limits CL
-9 30 -20 -10 0 10 20 30 40 Axial Flux Difference