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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20249C5691998-04-22022 April 1998 Rev 17 to TDB-VI, COLR for Fort Calhoun Station,Unit 1, Updating Cycle 18 Operations ML20249C5651998-03-30030 March 1998 Rev 16 to TDB-VI, COLR for Fort Calhoun Station,Unit 1, Updating Cycle 18 Boron Concentration on Page 8 of 17 ML20217G2571998-03-13013 March 1998 Rev 15 to Cycle 17 COLR, Updating Section 4.0 to Reduce Max Core Inlet Temp for Remainder of Cycle 17 Operations to Not Exceed 540 F ML20217G2491998-02-28028 February 1998 Rev 14 to Cycle 17 COLR, Revising COLR Peaking Factors to Ensure Appropriate Conservatism Is Applied ML20217Q5421997-08-13013 August 1997 Rev 13 to Colr ML20135A6581996-11-13013 November 1996 Rev 12 to COLR, Updating Cycle 17 Operations ML20135A6541996-08-27027 August 1996 Rev 11 to COLR, Updating COLR Figures 4,5,6,7A & 8 to Reflect New LCO & LSSS ML20116B6901996-07-10010 July 1996 Rev 10 to Colr ML20094D3021995-10-0606 October 1995 Rev 9 to Core Operating Limit Rept, Adding Figure, Axial Power Distribution LSSS for 4 Pump Operation ML20107H6281995-10-0606 October 1995 Corrected Rev 9 to Core Operating Limit Rept, Adding Figure to COLR for Axial Power Distribution LSS for 4 Pump Operation ML20082M4971995-04-0404 April 1995 Rev 8 to COLR, Updating COLR to Reflect Cycle 16 Setpoints & Restrictions Defined in EA-FC-95-009,Rev 0 Cycle 16 Setpoints & COLR ML20082M4791995-03-20020 March 1995 Rev 7 to COLR, Revising Refueling Boron Concentration ML20080F6601995-01-20020 January 1995 Cycle 16 Reload Evaluation Rept, for FCS Unit 1 ML20070P3721994-05-31031 May 1994 Reload Core Analysis Methodology Overview ML20059H7411993-11-22022 November 1993 Rev 6 to COLR, Reflecting Cycle 15 Operating Conditions ML20059H7351993-10-23023 October 1993 Rev 5 to COLR, Updating Min Boron Concentration to 1900 to Reflect Core Changes Prior to Cycle 15 Operation ML20046A0831993-07-19019 July 1993 Omaha Public Power District Fort Calhoun Station Unit 1 Cycle 15 Reload Evaluation. ML20045E0541993-06-25025 June 1993 Nonproprietary Revised Pages of Rev 5 to Reload Core Analysis Methodology Overview. ML20138D3091993-01-31031 January 1993 Nonproprietary OPPD Nuclear Analysis,Reload Core Analysis Methodology Overview ML20128C1981992-12-17017 December 1992 Rev 4 to COLR, Allowing Increase in Operating Space for DNB-LCO Monitoring W/O Requiring Use of Basss ML20128C1941992-11-16016 November 1992 Rev 3 to COLR Reflecting Increase in Allowable Peak Linear Heat Rate in COLR from 14.4 Kw/Ft to 15.5 Kw/Ft Until 7770 Mwd/Mtu ML20118A3931992-08-17017 August 1992 Rev 2 to Fort Calhoun Station Cycle 14 Core Operating Limits Rept ML20099B4501992-06-28028 June 1992 Rev 1 to Fort Calhoun Station Cycle 14,Core Operating Limits Rept ML20096G4061992-04-25025 April 1992 Core Operating Limit Rept ML20086F4451991-11-27027 November 1991 Cycle 14 Reload Evaluation ML20073H2521991-04-30030 April 1991 Rev 4 to Nuclear Analysis Reload Core Analysis Methodology Overview ML20073H2641991-03-31031 March 1991 Rev 3 to Omaha Public Power District Nuclear Analysis Reload Core Analysis Methodology - Transient & Accident Methods & Verification ML19354E6951990-01-26026 January 1990 Reload Evaluation Rept for Fort Calhoun Station Unit 1, Cycle 13. ML20154H6551988-04-30030 April 1988 Rev 2 to Nuclear Analysis Reload Core Analysis Methodology, Transient & Accident Methods & Verification ML20154H6351988-04-30030 April 1988 Rev 2 to Nuclear Analysis Reload Core Analysis Methodology, Neutonic Design Methods & Verification ML20153E1711988-04-30030 April 1988 Rev 3 to Nuclear Analysis Reload Core Analysis Methodology Overview ML20149F7181988-01-31031 January 1988 Rev 0 to Extended Burnup Rept for Fort Calhoun Reloads XN-4 & XN-5 (Batches K & L) ML20204F4781987-03-18018 March 1987 Errata to Rev 2 to Reload Core Analysis Methodology Overview ML20204F6311987-03-18018 March 1987 Errata to Rev 1 to Reload Core Analysis Methodology Overview ML20212N0211986-11-30030 November 1986 Rev 2 to Reload Core Analysis Methodology Overview ML20212N0271986-11-30030 November 1986 Rev 1 to Reload Core Analysis Methodology Overview ML20212N0321986-11-30030 November 1986 Rev 1 to Reload Core Analysis Methodology Overview ML20211M5271986-11-30030 November 1986 Partially Withheld Nonproprietary Omaha Batch M Reload Fuel Design Rept (Ref 10CFR2.790) ML20082D8401983-11-30030 November 1983 Nonproprietary Version of Statistical Combination of Uncertainties, Parts 1,2 & 3 ML20078D9481983-09-30030 September 1983 Reload Core Analysis Methodology Overview 1999-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
[Table view] |
Text
>
Fort Calhour Station Unit No. 1 TDB-VI TECHNICAL DATA BOOK PROCEDURE
{
Title:
CORE OPERATING LIMIT REPORT Sotpoint/ Procedure Form Number gFC-68): 38239 Reason for Change Add the COLR to the Operating Manual to-tmplement T.S. Amendment 141.
Contact Person Keith Voss-
. Typographical Correction (a); Page 8 ISSUED: 04-25-92 11:30 pm R0 9205260062 920515 PDR- ADOCK 05000285 P. PDR
R....,. .
- I '
FORT.CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 1 OF 13 wf' .'*.'
NAC ,
3
-( '
e Fort Calhoun Statior., Unit 1
_ Cycle _J:Lgpre Operatino Limits Rep _prt;,
r ASf.i Dae tc the conh,i: ,d incritical aspects of the safety analysis inputs this report, without changes may not be made to this report Nuclear 2ngineering Dept.rtment.av,icurrence of + te Production Engineering Division, FC/TDB R0
. _ _ _ - - - - - - -- - --~ ~~ ~~~
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 2 OF 13
Item p3scriptio_q Pace 1.0 Introduction 5 2.0 Core Operating Limits 5 3.0 TM/LP Limit 6 4.0 Maximum Core Inlet Tenperature 6 5.0 Power-Dependent Insertion Limit 6 6
-6.0 Linear Heat Rate 7.0 Excore Monitoring of LHR 7 0.0 Peaking Factor (F,f, T Fa)T Limits 7 9.0 DNB Monitoring 7 10.0 Fa , F,y and Core Power Limitations T T 7 11.0 Refueling Boron Concentration 7 1
1 FC/TOB RO
, . FORT *CALHOUN STATION TDB-VZ
-- TECHNTCAL = DATA' BOOK - PAGE.3 OF 13-LIST OF TABLE r
~ Table-No. Title pace TM/LP Coefficients 6 2 Maximum ~Fa and F,7 Limits 7 E
h i.-
I i; .FC/TDB R0
.c ,
FORT'CALHOUN STATION- TDB-VI ,
,, . TECHNICAL - DATA' BOOK -- PAGE 4 OF 13
-LISTS OP FIGURES
=fjaure No. Tit]e Pace 1- Thermal Margin / Low Pressure 4 Pump Operation 8
.7 Power Dependent: Insertion-Limit 9 J Allowable Peak Linear Heat Rate vs. Burnup 10
.4- Excore Monitoring of LHR 11 5 .DNB Monitoring 12 6 F,77 , FgT and Core Power Limitations 13 i
(
L l
l-L FC/TDB RO li 5.
FORT.CALHOUN STATION TDB-VI
. TECHNICAL DATA BOOK PAGE 5 OF 13 CYCLE 14 CORE OPERATING LIMIfS REPORT
1.0 INTRODUCTION
This report provides the cycle - specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 14 operation. It includes limits for:
1.1 TM/LP LSSS 4 Pump Operation (Pva) 1.2 Core Inlet Temperature (Tu) 1.3 Power Dependent Insertion Limit (PDIL) 1.4 Allowable Peak Linear Heat Rate 1.5 Excore Monitoring of LHR 1.6 Planar Radial Peaking Factor (F,yT) 1.7 Integrated Radial 3eaking Factor (Fa)I 1.8 DNB Monitoring T
1.9 Fg/F T xy vercus Power Trade off curve 1.10 Refueling Boron Concentration These limits are applicable for the duration of Cycle 14.
For subsequent cycles the limits will be reviewed and revised'as necessary. In addition, this report includes a number of cycle - specific coefficients used in the generation of certain reactor. protective system trip setpoints or allowable increases in radial peaking factors.
This report _has been prepared in accordance with the i requirements of Technical Specification 5.9.5. The core operating limits have been developed using the NRC methodologies listed in Technical Specificat'on 5.9.5.b.
(-
- f. 2.0 CORE OPERATING LIMITS The' values and limits presented within this section have been derived using the NRC - approved methodologies listed in Technical Specification 5.9 5. All values and limits in this section apply to Cycle 14 operation. Cycle 14 must be operated within the bounds of there limits and all others specified in the Technical Specifications.
FC/TDB' R0
1 FORT CALHOUN UTATION TDB-V'I TECHNICAL DATA BOOK PAGE 6 OF 13 3.0 fn/LP LIMIT The TM/LP coefficiente for Cycle 14 are shown below:
Table 1 Coefficient Value a 29.73 D 18.44 y -11325 The TM/LP setpoint is calculated by the Paa equation, shown below and in Figure 1:
Pux = 29.73 PF(B)A1(Y)B + 18.44Tu -11325 PF'B) m'1.0 B2100%
= -0.008B + 1.8 50% <B<100%
= 1.4 B550%
A1(Y) = -0.35294Y + 1.08924 Y1 s 0.25
= 0.57143Yi + 0.675 Y > 0.25 i
Where B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu Tu = Core Inlet Temperature, *F Pn2 = Reactor Coolant Syatem Pressure, psia
-4.0 MAXIMUM CORE INLET TEMPERATURE The maximum core inlet temperature (Tw) for Cycle 14 shall not exceed 543*F.
This limit is not applicable during either a thermal power ramp in excess of 5e of rated thermal power per minute or a thermal power step greater than 10% of rated thermal power.
5.0 POWER DEPENDENT INSERTION LIMIT The power dependent insertion limit is defined in Figure 2 for Cycle 14 operation.
6.0 LINEAR HEAT RATE The allowable peak linear heat rate vs. burnup is 13.8 kw/ft for Cycle 14 for all burnup points as shown on Figure 3.
Fr./TDB R0
(_
' FORT.CALHOUN' STATION- TDB-VI LTECHNICAL DATA BOOK PAGE 7 OF 13 l
-7.0 EXCORE MONITORING OF LHR The_ allowable operation for power versus axial shape index for monitoring of LHR with excore detectors for Cyc '.e 14 is shown in Figure 4.
8.0 PEAKING FACTOR LIMITS The maximum full power values for the unrodded planar radial peaking factor (F,#T) and integrated radial peaking f actor Fg T) are shown in Table 2.
Table 2 Maximum Full F;wer F, and Fn Limits Peakina Factor Limits T
Fn 1.85 FgT 1.79 9.0 DNB MONITORING The' limitu for DNB as a function of axial shape index and core power is shown in Figure 5.
Core power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertion of the lead bank of <65% (i.e., greater than or equal to 44.1 inches withdrawn)-when BASSS is operable, or within the limits of Figure 5.
10.0 f.pT, F.T AND CORE POWER LIMITATIONS Core power lJmitations versus Fgi and FnT are shown in Figure 6.
11.0 REFUELING BORON CONCENTRATION Tbe refueling boron concentration must be maintained with a boron concentration of at least 1700 ppm in the Reactor Coolant System to ensure a shutdown margin of not less than 5% with all CEAn withdrawn.
FC/10B R0
77 FORT-CALHOUN STATION TDB-VI.
TECHNICAL DATA BOOK PAGE.8 OF 13 '
y 590 .
~
ASt = -0.06 1,580 3 g.
u,i 570 -
- E
\
~
$ g_ 560. \ ~
\
. 550 -
s 2250 psia -
2 540
.$ 2100 psia -
N
~
c 5 O' 533 0
- o :- .
g E- 520 -
zO \ 1750 psia O .
! 510 -
500 - -
i- 60 -70 80 90 100 110 120 CORE POWER (% OF RATED)
'Pym =. 29.73PF(B)A1(Y)B + 18.44 TIN - 11325 PF(B) . - = 1.0 B .>_100%
= .008B + 1.8 50%<B<100%
= 1.4- B $50%
A1(Y)1 = -0.35294Y + 1.08824 Yi s.25 i i
- .= 0.57143Y + 0.875 Yi >.25 RO a l
CYCLE 14 - THERMAL MARG'N/ LOW PRESSURE FIGURE
.COLR 4 PUMP OPERATION 1
FORT CALHOUN STATION TDB-VZ
. TECHNICAL DATA BOOK PAGE 9 OF 13
- 126
- 100.8 ,
" U *I LONG TERM STEADY STATE
' ,/
[ '
INSERTION UMIT 3 (82.5) o - 75.6 . ,-,
/
SHORT TERM ,'
PPDlL
^
~ 126 - 50.4 INSERTION UNIT
-l i
- l.
a , ,
%- l ,
PDit or TRANSIENT E E - 75.6 -C l INSERTION UMIT
@ ~@ .T'
- 50.4 ,-
EMERGENCY BORATION UMIT p52) .* (12" BEUOW PDil - REFER TO AOP-3) us Z 126 - 25.2 _ (25 2) .
9 (132)
I" rn - 100.8 - 0
'O
. cL
$ E - 75.6 o
cc.
a a-O O - 50.4 .
6_:
- 25.2 126
-0 - 100.8
[ - 75.6 .
2 C - 50.4
- 25.2
-0 0 20 40- 60 80 100 REACTOR POWER (% OF ALLOWED POWER)
RO CYCLE 14 POWER DEPENDENT INSERTION LIMIT FIGURE
- a. COLR .
2
^
FORT CALHOUN STATZON TDB-VI TECHNICAL DATA BOOK ? AGE 10 OF - -
4 16~
0 UNACCEPTABLE OPERATION L
I4
-h x -
13.8 KW/FT D
w I
x- ACCEPTA3LE OPERATION 5-
-- E a -13 4
12 0 5000 10000 15000 20000 BURNUP R0
-CYCLE 14 Ai.LOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS. BURNUP 3 .
7 di '
f ^
. FORT CALHOUN STATION TDB-VI
[ TECIINICAL . DATA BOOK PAGE 11 OF 13
-g 110 100
,i-C W- 90 J 3-0 ( .os, so) (.1, 80)
.' E 80 m
o g
- 70 ( .2,7c) (.2,to)
-Q
'W 60
..g O
- j, .
50
-4 L
- O 40 F-Z W. 30 1 O
.E.
W:
-1 20 10 0 ,
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
- RO
!- CYCLE 14 FIGURE COLR EXCORE MONITORING OF LHR -
4 a . :
L- FORT CALHOU'1 STATION TDB-VI ,
l TECHNICAL DATA POOK PAGE 12 OF 13 110
('02 5'100) ('1'100) 0 p 90 m i 5 80 o
Q.
>(
70 /
w --
CE, 60 I '8'"' "' '
O
( w g- 50 -
oJ J. 40 -
< t u.
O 30 W
Z
~
D
$ 20 -
C W.
- 3. 10 c-0 -
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
NOTE: WHEN BASSS IS OPERABLE THIS FIGURE IS GUPERSCEDEP 'v THE BASSS PLOT go COLR DNB MONITORING 5 g
\-_____________-____________--_-________-__________- _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - ______ _ _ _ _ _ _ _ - _ _ _ ___
f]; a
, FORT CI1HOUN STATION- TDB-VI
' TECHNICAL DATA BOOK..
PAGE 13 OF 13 110 p,T pTm
~ LIMIT LIMIT 100 W
W 90 (1.79,90) (1.85,90)
O
\
80 W
W 70 (1.93,75) (2.01, 75)
Q W
- g. 60-oJ.
J 50 u.
-O 4o.
H Z
W-g 30
=2.
W-Q' 20 10 0
1.75 1.80 1.B'i 1.90 1.95 2.00 2.05 FT y and FrT R0
. CYCLE 14 p T, p,T, AND CORE POWER LIMITATIONS FIGURE
-COLR 6
.