|
---|
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
-c; - -
I e'
Fort Calhoun Station Unit No. 1 TDB;-VI TECHNICAL DATA BOOK PROCEDURE
Title:
CORE OPERATING LIMIT REPORT i
FC-68 Number: 41763 Reason for Change: Update minimum Boron Concentration to 1900 to reflect the core changes prior to Cycle 15 operation.
i i
Contact Person: William O. Weber
+
r 1
1 l
ISSUED: 10-23-93 9:00 pm R5 9401310135 940114 F PDR ADDCK 05000285 ,
P PDR [0
9 FORT CALHOUN STATION ~
TDB-VI'
TECHNICAL DATA BOOK PROCEDURE ~ PAGE 1 OF 13.
Fort Calhoun Station, Unit 1 Cycle 14 Core Ocerating Limits Reoort Due to the critical aspects of the safety analysis inputs contained in this report, changes may not_be made to this report-without concurrence of the Production Engineering Division, Nuclear Engineering Department.
t I
i
.i y
1 FC/TDB. R5 :
FORT CALHOUN STATION- TDB-VI-
. TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 13 i TABLE OF CONTENTS Item Descrintion page i 1.0 Introduction 5 2.0 Core Operating Limits 5 .
3.0 TM/LP Limit 6 l 4.0 Maximum Core Inlet Temperature 6 5.0 Power Dependent Insertion Limit 6 6.0 Linear Heat Rate 6 7.0 of LHR- 7- ,
8.0 Excore Peaking Monitoring Factor (Fx /, Fa') Limits 7 .;
9.0 DNB Monitoring 7 ';
10.0 Fe , F,/ and Core Power Limitations i
7 11.0 Refueling Boron Concentration 7 e
i i
a f
h FC/TDB R5 l
. _ . . _ . . ~ . . _ . . _ . . . . ._. _ _. _ -
FORT CALHOUN STATION TDB-VI "* ,
. TECHNICAL DATA BOOK PROCEDURE- PAGE 3 OF 13- '
LIST OF TABLE c;
Table No. Title pgog !
1- TM/LP Coefficients .
6 ,{
2 Maximum Fa and F,y Limits. -7
~!
t
.. l 3
i i
G r
F h
i r
f i
FC/TDB. R5 i i
~ . - .. - - . _ _ = . _ _ _ - _ . - . _ _ _ _ _ _ _ - _ _ _ _ - _ - _ _ - - - - - _ _ _ - _ _ _ - _ - _
.- FORT CALHOUN STATION TDB-VI
,, TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 13-LISTS OF FIGURES Zioure No. Title Page 1 Thermal Margin / Low Pressure 4 Pump Oneration 8 2 Power Dependent Insertion Limit 9 3 Allowable Peak Linear Heat Rate vs. Burnup 10 4 Excore Monitoring of LHR 11 5 DNB Monitoring 12 6 F,y , Fg and Core Power Limitations i i 13 i f
f l
l FC/TDB R5 .
l
TDB-VI
FORT CALHOUN. STATION :
TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 13 .
'l CYCLE 14 CORE OPERATING LIMITS 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 (Pyxa) 1.2 Core Inlet Temperature (Tn) 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 (Fxy ) I i
1.7 Integrated Radial Peaking Factor (Fa) 1.8 DNB Monitoring 1.9 Fg jpxy versus Power Trade off curve T t 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 q setpoints or allowable increases in radial peaking factors.
This report has been prepared in accordance with the requirements of Technical Specification 5.9.5. The core ,
operating limits have been developed-using the NRC methodologies listed in Technical Specification'5.9.5.b. .;
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 i this section apply to Cycle'14 operation. Cycle 14 must be operated within the bounds of these limits and allLothers -
specified in the Technical Specifications.
P FC/TDB -R5 i
g +-,.w-.-r-- _ w .- - - y e e +- __ m e n- m T
. 1
- -FORT CALHOUN' STATION TDB-VI-
.. TECHNICAL' DATA BOOK PROCEDURE PAGE 6 OF 13 I l
3.0 TM/LP LIMIT 1
The TM/LP coefficients for Cycle 14 are shown below: l 1
Table 1 Coefficient Value a -29.73 i 18.44 y -11325 I i
l The TM/LP setpoint is calculated by the Pun equation, shown l below and in Figure 1- 1 I
Pwa = 29.73 PF(B) A1(Y)B + 18.44Tno -11325 PF(B) = 1.0 B2100%
= -0.008B + 1.8 50% <B<100%
= 1.4 Bs50%
A1(Y) =
-0.35294Yi + 1.08824 Y3 s 0.25
= 0.57143Y1 + 0.875 Yi > 0.25 l
Where:
I B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu Tmi = Core Inlet-Temperature, *F Paa = Reactor Coolant System Pressure, psia i i
i 4.0 MAXIMUM CORE INLET TEMPERATURE j The maximum core inlet temperature (Tg) i for Cycle 14 shall not exceed 543*F.
l This' limit is not applicable during either a thermal power ramp ,
in excess of 5% of rated thermal power per minute or a thermal
- power step greater than 10% of rated thermal power. i 5.0 POWER DEPENDENT INSERTION LIMIT ]
1 The power dependent insertion limit is defined in Figure 2 for Cycle 14 operation.
1 FC/TDB RS
FORT CALHOUN STATION ..
TDB-VI
TECHNICAL DATA BOO
K. PROCEDURE
PAGE 7 OF 13 -
6.0 LINEAR HEAT RATE The.~ allowable peak linear heat rate vs. burnup for Cycle 14 is l 15.5 kW/ft for less than or equal to 7770 MWD /T, and 14.4 kW/ft-for greater tian 7770 MWD /T. The allowable peak linear heat rate for Cycle 14 is chown in Figure 3.
7.0 EXCORE MONITORING OF LHR The allowable operation for power versus axial shape index for monitoring of LHR with excore detectors for Cycle 14 is shown in :
Figure 4.
8.O PEAKING FACTOR LIMITS $
The maximum full power values for the unrodded planar radial peaking factor ( Fxy ) and integrated radial peaking factor FnD T
are shown in Table 2.
Table 2 Maximum Full Power F. and Fry Limits Peakina Factor Limits f
Fxy 1.85-7 Fa 1.76 '
9.0 DNB MONITORING The limits 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.'O ]ExY .
F.I'AND CORE POWER LIMITATIONS Core power limitations versus Fai and F XY are shown in Figure-6.
11.0 REFUELING BORON CONCENTRATION -- i The refueling boron concentration must be maintained with a boron concentration of at least 1900 ppm in the Reactor Coolant, l, l System to ensure a shutdown margin of not less'than 5% with all :
l CEAs withdrawn.
FC/TDB R5 ,
-- __-_____---_--_-________-___--__=_.
~ ._. .. . . ~ ... - - . -
. l
.. FORT CALHOUN STATION TDB-VI i TECHNICAL DATA BOOK PROCEDURE PAGE 8'OF 13 590 580 ASI = -0.06l 1 ,
11 I 570
$ ~
a E \ \
560 I
.m \ N N 0- .
N \ '
H 550 m.
O psia E 540 I
$ 2100 psia 530 O '
O -
uJ ,
E 520 0 \ 1750 psia O .
510
60 70 80 90 100 110 120 CORE POWER (% OF RATED) !
PVAR = 29.73PF(B)A1(Y)B + 18.44Tn i - 11325 !
l PF(B) = 1.0 B 2.100% j
= .0088 + 1.8 50%< B<100% !
= 1.4 8 s 50 %
A1(Y) = -0.35294Y i + 1.08824 Ya s .25
= 0.57143Yi + 0.875 Yi >.25 RS.
t CYCLE 14 THERMAL MARGIN / LOW PRESSURE - FIGURE l COLR 4 PUMP OPERATION 1 l t
+
FORT CALHOUN STATION .TDB-VI , ',
. TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 13
- 126 J
- 100.8 LC NG TfRM STEADYSTATE ,-
IN SERTION LIMIT
{g - 75.6 j ,
/
ISHOllTTEllM ,
' PP0ll
- 126 - 50.4 g
B l lNSERTIor I
i uMir ,'
/
$ - 100.8 - 25.2
/ .
l '
3 m - 75,s - 0 l
l ,
/ '/[ ' PDIL or TRANSil!NT .
INSHRTIOff UMIT
= s .1 '//<
- 50 4 ,
EMERG ENCY BORATION LIMIT z
c-
- 25.2 p
- 126 (25.2)
/ (12"IIELOVf PDIL - RETRTO AOF -3)
O,,,, (13 2 r -
5 -0 - 100.8 O i n.
g E - 75.6 l O 8 a: e .i O c - 50.4 w
U - 126 - 25.2 l
- 100.8 - 0
[ - 75.6 a
@ i 0 - 50.4
- 25.2 l
0 i 0 20 40 60 80 100 l
REACTOR POWER (% OF ALLOWED POWER)
R5 -!
CYCLE 14 POWER DEPENDENT INSERTION LIMIT FIGURE :
COLR 2
rw , - - - . - . - -. ,. .- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - - - _ - - _ _ _ ___________-___E.i__-
~~
FORT CALHOUN STATION TDB-Vi TECHNICAL DATA BOOK PAGE 10 OF 13 17 16 UNACCEPTABLE OPERATION
- 15.5 KW/FT k
m g 15 m
k u.
x 14.4 KW/FT g
$ 7770 MWD /MTU s
" ACCEPTABLE OPERATION 14 13 0 5000 10000 15000 20000 BURNUP (MWD /MTU) i
% l CYCLE 14 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE l COLR VS. BURNUP 3 l
FORT CALHOUN STATION TDB-VI '
TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF 13 110 100 W
LLI 90 3
O ( .os, so) (.1, 80)
Q- 80 UJ K
O 70 ( .2,70) (.2,70)
O W 60 3
O d 50 u.
O 40 l-Z W 30 0
x Lu D. 20 10 0 ,
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
R5 FIGURE CO R EXCORE MONITORING OF LHR
^
4 4
. FORT CALHOUN STABON TDB-VI TECHNICAL DATA BOOK PAGE 12 OF 13 110 l (0.0 100) (.15 100)
/ 1 5
g 80 / \
0 Q.
m 70 '
C O
O 60
- 0.3,60) g (-0.3,S8)
W 3 50 o
_a 3 40
<C LL O 30 l-Z d 20 g
W W
- 0. 10 0
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
NOTE: WHEN BASSS IS OPERABLE THIS FIGURE IS SUPERSCEDED BY THE BASSS DNB ALLOW-ABLE POWER VALUE R5 FIGURE COLR DNB MONITORING
_- . . . . - .. _ = - -. .. .-- .,
. +
d-TDB-VI , ,
FORT CALHOUN. STATION PAGE 13 OF 13- i TECmiICAL DATA BOOK PROCEDURE 110 prT pxyT LIMIT LIMIT >
100 ,
W
.W 90 (1 78'90) (1 85'90) t O
80 111 W i O 70 (1 93,75) . (2.01,75) g t O
W y 60 0 ,
3 50 4 :
u.
O 4o F :
Z LU .
o 30 .;
W i.u ,
0- 20 f
10 ,
i 0 :
1.75- 1.80 1.85 1.90 1.95 2.0O' ' 2.05 T T
[ Fxy and - Fr
' RS. ;
l FIGURE' o CYCLE 14 p T, p,T, AND CORE POWER LIMITATIONS COLR 6-
_ _