|
---|
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
P 1
\
, l l
Fort Calhoun Station Unit No. 1 l
i TDB-VI -
l TECHNICAL DATA BOOK PROCEDURE
Title:
CORE OPERATING LIMIT REPORT
)
FC-68 Number: 47372 Reason for Change: Add figure to COLR for " Axial Power Distribution LSSS for 4 Pump l Operation".
Contact Person: William O. Weber ISSUED: 10-06-95 4:00 pm R9 9511030264 951027 PDR ADOCK 05000285 p PDR
~
, FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 1 OF 16 l
Fort Calhoun Station, Unit 1 l J
Cycle 16 Core Onoratina Limits Renort l
1 I
t l
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.
R9
, FORT CALHOUN STATION TDB-VI
, , , TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 16 TABLE OF CONTENTS 11gm Descriotion EADA 1,0 Introduction 5 2.0 Core Operating Umits 5 3.0 TM/LP Umit 6 4.0 Maximum Core inlet Temperatute 6 5,0 Power Dependent insertion Umit 7 6.0 Unear Heat Rate 7 7,0 Excore Monitoring of LHR 7 8.0 Peaking Factor (Fa T, FxyT) Umits 7 9,0 DNB Monitoring 7 10,0 T Fa,FxyT and Core Power Umitations 8 11.0 Refueling Boron Concentration 8 12,0 Axial Power Distribution S l
l R9
, FORT CALHOUN STATION TDB-VI
. TECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 16 LIST OF TABLES Table No. 3 Eggg 1 TM/LP Coefficients 6 2 Maximum Fn and Fxy Umits 7 I
j i
i I
l R9 l
)
l 1
. FORT CALHOUN STATION TDB-VI
. TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 16 LIST OF FIGURES Figure No. IltlR EaQA 1 Thermal Margin / Low Pressure 4 Pump Operation 9 2 Power Dependent insertion Umit 10 3 Allowable Peak Unear Heat Rate vs. Bumup 11 4 Exco.e Monitoring of LHR 12 5 DNB Monitoring 13 6 BASSS Allowable Power 14 7 F RT. FxyT and Core Power Umitations 15 8 Axial Power Distribution LSSS for 4 Pump Operation 16 i
l i
FORT CALHOUN STATION TDB-VI l . . TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 16 l Cycle 16 Core Operating Limits Report ,
i 1.0 Introduction This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 16 operation. It includes limits for:
1.) TM/LP LSSS 4 Pump Operation (PyAn) 2.) Core inlet Temperature (TIN) 3.) Power Dependent insertion Umit (PDIL) ;
4.) Allowable Peak Unear Heat Rate 5.) Excore Monitoring of UIR T
6.) Planar Radial Peaking Factor (Fxy ) T 7.) Integrated Radial Peaking Factor (Fn )
8.) DNB Monitoring T
9.) F n /p ,yT versus Power Trade off curve 10.) Refueling Boron Concentration 11.) Axial Power Distribution l ,
These limits are applicable for the duration of Cycle 16. 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.
1 2.0 Core Operating Limits l
All values and limits in this TDB section apply to Cycle 16 operation. Cycle 16 must be operated within the bounds of these limits and all others specified in the Technical Specifications. This report l has been prepared in accordance with the requirements of Technical Specification 5.9.5. The values and limits presented within this TDB section have been derived using the NRC approved methodologies listed below:
OPPD-NA-8301, " Reload Core Analysis Methodology Overview" Rev. 6, Dated December 1994. (TAC No. M89455)
OPPD-NA-8302, " Reload Core Analysis Methodology, Neutronics Design Methods and Verificathn" Rev. 4, Dated December,1994. (TAC No, M89456)
OPPD-NA-8303," Reload Oore Analysis Methodology, Transient and Accident Methods and Verification", Rev. 04, Dated January 1993. (TAC No M85845)
R9
. FORT CALHOUN STATION TDB-VI
. , , TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 16 1 3.0 TM/LP Limit i
! The TM/LP coefficients for Cycle 16 are shown below:
Table 1 1 Coefficient he a 29.73 p 18.44 y -.11470 4
The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:
PvAn = 29.73 PF(B) A1(Y)B + 18.44 TIN - 11470 l
PF(B) = 1.0 B2,100%
= -0.0088 + 1.8 50% < B < 100%
- = 1.4 B.s,50%
A1(Y) = -0.3529Y1 + 1.0882 Y3 .s, 0.25 i
= 0.5714Y3 + 0.857 Y3 > 0.25 Where:
i B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power l Y = Axial Shape index, asiu TIN = Core inlet Temperature, F PvAn = Reactor Coolant System Pressure, psia 4.0 Maximum Core inlet Temoerature The maximum core inlet temperature (Ti s) for Cycle 16 shall not exceed 545'F.
This limit is not applicable during either a thermal power ramp fr) axcess of 5% of rated thermal power per minute or a thermal power step greater than 10% of rated therrnal power.
R9
. FORT CALHOUN STATION TOB-VI
, . TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 16 5.0 Power Deoendent insertion Limit The power dependent insertion limit is defined in Figure 2 for Cycle 16 operation. i 6.0 1.lDRAf.finat Rate The allowable peak linear heat rate vs. burnup for Cycle 16 is 15.5 kW/ft. The allowable peak linear I heat rate for Cycle 16 is shown in Figure 3. '
l l
7.0 Excore Monitorino of LHR l The allowable operation for power versus axial shape Index for monitoring of LHR with excore 1 detectors for Cycle 16 is shown in Figure 4.
l 8.0 Peakina Factor Limits The Cycle 16 maximum full power values for the unrodded planar radial peaking factor (FxyT) and integrated radial peaking factor (FnT) are shown in Table 2.
Table 2 l
Maximum Full Power Fn and 3 F Limits I Peaking Factor Limita FnT 1,77 T
Fxy 1.86 9.0 DNB Monitoring The Cycle 16 limits for DNB as a function of axial shape index and core power is shown in Figure 5.
When the Better Axlal Shape Selection System is operable, during Cycle 16, the core power is limited as a function of the axial shape Index as shown in Figure 6. Figure 6 will eliminate the need for seperate LOCA and fuel performance limits to be maintained by the operators while operating with BASSS.
R9
i FORT CALHOUN STATION TDB-VI
- TEC,HNICAL DATA BOOK PROCEDURE PAGE 8 OF 16 10.0 F T. FyT and Core Power umitations Core power limitations versus FnT and FxyT are shown in Figure 7 for Cycle 16.
11.0 Refueling Baron Concentration The refueling boron concentration must be maintained with a boron concentration of at least 2000 ppm in the reactor coolant system to ensure a shutdown margin of not less than 5% with all CEAs withdrawn.
12.0 Axlal Power Distribution l
l The axial power trip is provided to ensure that excessive axial peaking will not cause fuel damage.
The Axial Shape Index is determined from the axially split excore detectors. The set point functions, i shown in Figure 8 ensure that neither a DNBR of less than 1.18 nor a maximum linear heat rate of more than 22 kW/ft (deposited in the fuel) will exist as a consequence of axial power maldistributions. Allowances have been made for instrumentation inaccuracies and uncertainties associated with the excore symmetric offset - Incore axial peaking relationship, i l
1 R9
i *
. FORT CALHOUN STATION TDB-VI l , , . TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 10 i
, 590 i
i ASl = -0.b6 580 Ld 570 q q 2400 psia W
n.
N I 2250 psia h 550 '
t a
Z qq N \
N 2100 psia
[ %
1 2 -
o 530 o ' N 1750 psia (I: 520 ;
O '
O -
510 i
500 '
60 70 80 90 100 110 120 CORE POWER (% OF RATED)
PvAn = 29.73PF(B)A1(Y)B + 16.44Tm - 11470 PF(B) = 1.0 B 2.100%
= .006B + 1.8 50%<B <100%
= 1.4 B A50%
A1(Y) = -0.3529Y i + 1.0882 Y s.25
= 0.5714Ye + 0.857 Yi >.25 CYCLE 16 THERMAL MARGIN / LOW PRESSURE FIGURE COLR 4 PUMP OPERATION 1 R9
. FORT CALHOUN STATION TDB-VI
, , TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 16
, - 126
- 100.8 LC NGTl!RM S7EAD" STA1 E .
INBERTIDN UMIT ,
- 75.6 ,
- 126 - 50.4 , HORT TEMM . h N
'INSERTIOtI LIM {, *
$ - 100.8 - 25 2 . l O
, PDll or TR4NSII NT
'. I ohm
- 75.6 -0 ,
g" l
c .. 7/
$ - 50.4 ,
EMERC ENCY BORATION UMIT psap*/ (12"llELOVfPDil - RE1!R TO AOF -3) !
- 25.2 - 126 (u.2)
E en -0 - 100.8 E "
- 75.6 8' 8 b - 50.4 5
U .
- 126 - 25 2
- 100.8 - 0
- 75.6 8 - 50.4
- 25 2
-0 0 20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER)
CYCLE 16 POWER DEPENDENT INSERTION LIMIT FIGURE COLR 2 R9
i
, FORT CALHOUN STATION TDB-VI
, .
- TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF 10 18 UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 A ::CEPTABLE OPERATION 12 A
10 t
E 8 .
g6 2
3 4 ,
o l 0 5000 10000 1s000 20000 BURNUP (MWD /MTU)
CYCLE 16 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS.BURNUP 3 R9
.___-___..__.____________________________________________j
. FORT CALHOUN STATION TDB-VI
, . TECHNICAL DATA BOOK PROCEDURE PAGE 12 OF 16 100
"*^' 1 8 90 ( .
E W # \
80 g ( .23 so) (.23,60)
O Q. , .
W 70 E
O O
g 60 -
W 0
,,a 50 J
4 E 40 O l F- l Z l W 30-O .
E W
Q. 20 10 -
l 0
.4 .2 0 .2 .4 1
AXlAL SHAPE INDEX (ASIU)
FIGURE CO R EXCORE MONITORING OF LHR R9
FORT CALHOUN STATION TDB-VI
, . . TECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 16
. 1,10 l
100
90
' / -
x l w 1 g 80 l
w 70 I .
k g (-o.2s os) (o.:ts,ss)
O 60 ;
O i W
g 50 I
9
-3 40 4
Lt.
O 30 Z
20
.h x
W CL 10 0
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
NOTE: WHEN BASSS IS OPERABLE THIS FIGURE IS SUPERSCEDED BY FIGURE 6 - BASSS DNB ALLOWABLE POWER FIGURE .
COLlR DNS MONITORING R9
FORT CALHOUN STATION TDB-VI
, . " TECHNICAL DATA BOOK PROCEDURE PAGE 14 OF 10 1.10
( .12,m) (.12,100) 100 90 . i E
=
g 80 / \(
O n.
m 0 '
(-o.2s,es) )(0.2s,ss)
O 1 O 60 Q
W g 50 0J 3 40 4
u.
O so i
>=
Z 20 a
W
- n. 10 0
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
CY COLR BASSS DNB ALLOWABLE POWER LCO 6
R9
~
' FORT CALHOUN STATION TDB-VI
- ,
- TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 16 i
110 i
l l Fn T FnT l 3
100 l
- 3 i
! g (.s6,4 90
! uJ N N '
] ) (1.77. 80)
N N
- O 80 N w 1 Q.
W \
8 8 g ) (1 ss,7sf 70 C
O O 60 uJ 0J 50 J
> 30 Z
uJ 0
E 2d uJ G.
10 I i
0 1.75 1.80 1.85 1.00 1.95 2.00 2.05 2.10 :
PEAKING FACTOR 1
l CYCLE 16 FIGURE l COLR FnT, FxyT , and Core Power Limitations 7 R9 J
FORT CALHOUN STATION TDB-VI
,
- TECHNIC'AL DATA BOOK PROCEDURE PAGE 16 OF 16 120 ,
(0.0,112) l
(~181")
g 100
- ' ( 18:1M) j W
3 0 r , i j
W g 80 0
0 Q )
W ( ( .3,65) (.3,65) l 3 60 O
a '
l J
A l u.
O 40 W
Z W l O
g 20
0
.4 .2 0 .2 .4 l AXIAL SHAPE INDEX (ASIU) 1 l
l CYCLE 16 Axial Power Distribution LSSS FIGURE COLR for 4 Pump Operation 8 R9
. _ . _