ML100630828

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TDB-VI, Technical Data Book, Core Operating Limits Report, Rev. 39, Change EC 44759
ML100630828
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/18/2010
From:
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TDB-VI, Rev 39
Download: ML100630828 (25)
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PASSPORT DOCUMENT To HORN KRISTI Facility FC Department : TRANSMITTAL Address DIRECTOR, OFFICE OF NRC - DOCUMENT CONTROL DESK, U.S. NRC WASHINGTON, DC 20555 Page: 1 From Address DOCCON FC-2-3 Attention: Doc Management Distribution 11Hi Hiii 11Nii lili City Fort Calhoun State: Postal Code:

Country UNITED STATES Email Contact Kristi Horn 402-533-6714 6714 Date/Time 02/18/2010 0*8:48 Transmittal Group Id: 021810-1 Trans No. 000119357

Title:

02/18/10 ISSUE #1 Total Items: 00001 Item Facility Type Sub Document Number Sheet DocStatus Revision Doc Date Copy # Media Cpys 0001 FC PROC TDB TDB-VI ACTIVE 039 A 51 P 01 If a document was not received or is no longer required check the response below and return to sender.

Documents noted above not received (identify those not received).

I no longer require distribution of these documents (identify those no longer required).

Date: Signature:

Fort Calhoun Station Technical Data Book Page 1 of 5 TDB Document Document Title Revision/Date TDB-I - Core Maps TDB-I.A.2 Fuel Assembly Locations, Insert Locations, and FH-1 R26 02-16-10 Coordinates TDB-I.A.3 CEDM Locations R7 10-20-06a TDB-I.A.6 In-Core Instrumentation Location R5 03-22-05 TDB-I.A.7.A In-Core Instrumentation Mimic Numbers and Serial R7 06-06-08 Numbers TDB-I.A.7.B CECOR Octant and Reference Octant Numbers in Full R6 03-22-05 Core TDB-I.A.7.C Failed Incore Detector Status R88 08-07-08 TDB-I.A.7.E Core Exit Thermocouple (CET) Status R10 01-07-10 TDB-I.A.9 Ex-Core Instrumentation Location R5 03-22-05 TDB-I.B.1 Spent Fuel Pool Lay Out and FH-12 Coordinates R62 11-25-09 TDB-I.B.5 Dry Fuel Storage Layout R2 11-16-09 TDB-I.C.1 New Fuel Storage Rack and FH-12 Coordinates R27 02-11-10 TDB-I.D.1 Al and CB Panel List R7 03-22-05 TDB-t1 - Reactivity Curves R31 11-23-09 TDB-III - Operating Characteristics TDB-III.1 Tave Program R14 10-27-06 TDB-III.1.A Temperature Correction for Pressurizer Level Indicators R6 10-25-06 LI-101 X/Y TDB-III.1.B Pressurizer Level Correction (Density Effects Correction) R5 10-25-06 TDB-III.1.C Pressurizer Level Correction (Density Effects Correction) R5 10-25-06 TDB-III.1.D Pressurizer Level Correction (Density Effects Correction) R5 10-25-06 TDB-IIl.1.E Pressurizer Level Correction (Density Effects Correction) R5 10-25-06 February 18, 2010 6:39 AM

Fort Calhoun Station Technical Data Book Page 2 of 5 TDB Document Document Title Revision/Date TDB-III.1.F Pressurizer Component Elevations RO 10-25-06 TDB-III.2 Actual Level in Pressurizer vs. Indicated Level in R7 04-16-09 Pressurizer TDB-III.3.A Steam Generator Level Correction (Ambient Temperature R4 10-27-06 120°F)

TDB-III.3.B Steam Generator Level Correction (Ambient Temperature R4 10-27-06 200 0 F)

TDB-III.3.C Steam Generator Level Correction (Ambient Temperature R4 10-27-06 250 0 F)

TDB-III.3.D Steam Generator Level Correction (Ambient Temperature R4 10-27-06 300 0 F)

TDB-lII.3.H Wide Range to Narrow Range Conversion R3 10-27-06 TDB-III.3.1 Wide Range Steam Gen. Level Correction (Ambient R4 10-27-06 Temperature 120 0 F)

TDB-III.3.J Wide Range Steam Gen. Level Correction (Ambient R3 10-27-06 Temperature 200 0 F)

TDB-III.3.K Wide Range Steam Gen. Level Correction (Ambient R3 10-27-06 Temperature 250 0 F)

TDB-III.3.L Wide Range Steam Gen. Level Correction (Ambient R3 10-27-06 Temperature 3000 F)

TDB-III.3.P Steam Generator Component Elevations R6 04-23-09 TDB-III.5 Pressurizer Level Control Program R3 05-12-05 TDB-III.6 Pressure Control Program R6 07-17-08 TDB-III.7.a RCS Pressure and Temperature Limits R24 11-10-06 TDB-III.7.d RCS Pressure and Temperature Limits R8 05-18-08 TDB-III.8 RCS Mass vs RCS Temperature R3 10-27-06 TDB-III.8.B RCS Inventory Based on Pressurizer Level (Including SG R4 11-13-06 Tubes Plugged)

TDB-III.8.C Reactor Vessel Volumes R3 09-22-06 February 18, 2010 6:39 AM

Fort Calhoun Station Technical Data Book Page 3 of 5 TDB Document Document Title Revision/Date TDB-III.8.D Steam Generator and Primary System Piping Volumes R10 10-25-06 TDB-III.8.E Volume of RCS at Centerline of Hot Leg R2 06-23-05 TDB-III.9 Feedwater Temperature vs. Power Level R5 10-27-06 TDB-III.20 RCS Elevations vs. LI-106, LI-199, LI-1 97 and LIS-1 19 R19 10-25-06 TDB-III.22 Limitation on Power Level Increases and Rod Movements R16 02-03-09 at Power TDB-III.23.A Transient Power ASI Control Band R4 04-05-05 TDB-III.23.B Equilibrium Power ASI Control Band R3 04-13-05 TDB-III.24 Nuclear Detector Well Temperatures R7 04-13-05 TDB-III.26 Diesel Generator Capability Curve (4160 Volts) R5 03-28-06 TDB-III.26A Diesel Generator Loading Curve R15 02-03-09 TDB-III.27 Decay Heat vs. Time After Shutdown and Time to Boil R10 04-30-08 Curves and Tables TDB-III.28 Reactor Vessel Level Monitoring System (RVLMS) R13 12-31-09 TDB-III.30 Circulating Water Pump Cell and River Levels from R2 05-19-05 Pressure Gauge LI-1900 TDB-III.31 AC-10A Pump Curve R22 10-04-07 TDB-III.32 AC-10B Pump Curve R20 09-09-08 TDB-III.33 AC-10C Pump Curve R23 07-17-08 TDB-III.34 AC-10D Pump Curve R29 06-02-09 TDB-III.35 Spent Fuel Pool Rack Measurements R1 05-19-05a TDB-III.36 Containment Leakage Rate Assessment R29 02-11-10 TDB-III.37A Boron Addition Rate (HZP) - SIRWT @ 1900 ppm R2 11-21-06 TDB-III.37B Boron Addition Rate (HZP) - SIRWT @ 2000 ppm R2 11-21-06 February 18, 2010 6:39 AM

Fort Calhoun Station Technical Data Book Page 4 of 5 TDB Document Document Title Revision/Date TDB-III.37C Boron Addition Rate (HZP) - SIRWT @ 2100 ppm R2 11-21-06 TDB-III.37D Boron Addition Rate (HZP) - SIRWT @ 2200 ppm R2 11-21-06 TDB-III.37E Boron Addition Rate (HZP) - BAST's @ 3.0% BA R2 11-21-06 TDB-III.37F Boron Addition Rate (HZP) - BAST's @ 3.5% BA R2 11-21-06 TDB-III.37G Boron Addition Rate (HZP) - BAST's @ 4.0% BA R2 11-21-06 TDB-III.37H Boron Addition Rate (HZP) - BAST's @ 4.5% BA R2 11-21-06 TDB-III.371 Boron Addition Rate (HZP) - SIRWT @ 2300 ppm RO 11-21-06 TDB-III.38A Boron Addition Rate (HFP) - SIRWT @ 1900 ppm R2 11-21-06 TDB-III.38B Boron Addition Rate (HFP) - SIRWT @ 2000 ppm R2 11-21-06 TDB-III.38C Boron Addition Rate (HFP) - SIRWT @ 2100 ppm R2 11-21-06 TDB-lII.38D Boron Addition Rate (HFP) - SIRWT @ 2200 ppm R2 11-21-06 TDB-III.38E Boron Addition Rate (HFP) - BAST's @ 3.0% BA R2 11-21-06 TDB-lII.38F Boron Addition Rate (HFP) - BAST's 3.5% BA R2 11-21-06 TDB-III.38G Boron Addition Rate (HFP) - BASTS @ 4.0% BA R2 11-21-06 TDB-IlI.38H Boron Addition Rate (HFP) - BAST's @ 4.5% BA R2 11-21-06 TDB-II .381 Boron Addition Rate (HFP) - SIRWT @ 2300 ppm RO 11-21-06 TDB-lII.39 Pressurizer Heaters R7 11-27-07 TDB-lII.40 Technical Specification Required SIRWT Levels R3 06-16-05 TDB-III.42 Requirements for ECCS and Containment Cooling R3 12-23-08 Equipment Operation in Mode 3, Transition Between Modes 3 and 4 and Mode 4 and 5 TDB-IV - Chemistry TDB-IV.7 Process Monitor Setpoints R216 11-19-09 TDB-IV.8 Area Monitoring Setpoints R82 02-11-10 TDB-IV.9 Ion Exchanger Contents R7 03-11-09 February 18, 2010 6:39AM

Fort Calhoun Station Technical Data Book Page 5 of 5 TDB Document Document Title Revision/Date TDB-IV.10.a Acid Reducing Conditions (Ammonia 0.4 ppm or less) RO 04-04-06 TDB-IV.10.b Acid Reducing Condition (Ammonia greater than 0.4 ppm) RO 04-04-06 TDB-IV. 11 Operable Real Time Radiation Monitor RO 07-23-09 TDB-V - Work Sheets and Calculation Procedures TDB-V.1.B Estimated Critical Conditions Worksheet R23 12-15-09 TDB-V.3 Manual Group Mode Guide Table R4 05-27-05 TDB-V.6 Indication of Reactor Power Based on AT R7 07-05-05 TDB-V.9 Shutdown Margin Worksheet R39 05-18-08 TDB-V. 11 Instrument Bus Loads and Failure Modes R43 12-14-09 TDB-V.12 Miscellaneous Formula Sheet R10 05-02-08 TDB-V. 13 Reactor Vessel Cooldown When Sweeping Steam R3 05-13-08 Generators TDB-VI Core Operating Limit Report R39 11-20-09a TDB-VII Tank Curves R1 5 08-06-09 TDB-VIII Equipment Operability Guidance R44 12-14-09 TDB-IX RCS Pressure and Temperature Limits Report R4 05-18-08 February 18, 2010 6:39AM

PAGE 1 OF 19 Fort Calhoun Station Unit 1 TDB-VI TECHNICAL DATA BOOK CORE OPERATING LIMITS REPORT I Change No.' EC 44759 Reason for Change Updated for Cycle 26 operation.

Requestor D. Williamson Preparer L. Hautzinger Editorial Correction (a) Pages 1,2 and 6 (02-18-10)

EC 48315 ...........

Issue Date 111-20-09 3:00 pm R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 2 OF 19 Fort Calhoun Station, Unit 1 Core ODeratinq Limits ReDort I 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 Nuclear Engineering Department.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 3 OF 19 TABLE OF CONTENTS Item Description Paqe

1. INTRODUCTION............................................. 6
2. CO RE O PERATING LIM ITS ........................................................................... 6
3. T M/LP LIM IT ................................................................................................ .. 8
4. MAXIMUM CORE INLET TEMPERATURE .................................................... 8
5. POWER DEPENDENT INSERTION LIMIT .................................................... 8
6. LIN EA R HEAT RA T E ...................................................................................... 9
7. EXCORE MONITORING OF LHR............... .................. 9
8. PEAKING FACTOR LIMITS ...................................... 9
9. DNB MONITORING............................................. 9
10. FRT AND CORE POWER LIMITATIONS ........................................................ 9
11. REFUELING BORON CONCENTRATION ...................................................... 9
12. AXIAL POW ER DISTRIBUTION .................................................................. 10
13. SHUTDOWN MARGIN WITH Tcold > 210°F .................................................. 10
14. MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT ............ 10
15. STEAM GENERATOR DIFFERENTIAL PRESSURE ................................... 10 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 4 OF 19 LIST OF TABLES Table No. Title Page 1 TM/LP Coefficients .......................................................................................... 8 2 Refueling Boron Concentrations ..................................................................... 9 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 5 OF 19 LIST OF FIGURES Figure No. Title Paqe 1 Thermal Margin/Low Pressure for 4 Pump Operation ...................................... 11 2 Power Dependent Insertion Limit ................................................................... 12 3 Allowable Peak Linear Heat Rate vs. Burnup ................................................ 13 4 Excore Monitoring of LH R ................................................................................ 14 5 D NB Mo nitoring ............................................................................................ . . 15 6 FRT and Core Power Limitations ..................................................................... 16 7 Axial Power Distribution LSSS for 4 Pump Operation ..................................... 17 8 Axial Power Distribution Limits for 4 Pump Operation with Incores Inoperable.. 18 9 Minimum Boric Acid Storage Tank Level vs. Stored Boric Acid Storage Tank C o nce ntratio n .............................................................................................. . . 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 6 OF 19 CORE OPERATING LIMITS REPORT

1. INTRODUCTION This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 26 operation. It includes limits for:
  • TM/LP LSSS for 4 Pump Operation (PVAR)
  • Core Inlet Temperature (TIN)
  • Power Dependent Insertion Limit (PDIL)
  • Allowable Peak Linear Heat Rate

" Excore Monitoring of LHR

  • Integrated Radial Peaking Factor (FRT)

" FRT versus Power Trade-off Curve

  • Refueling Boron Concentration

" Axial Power Distribution (APD)

  • Most Negative Moderator Temperature Coefficient These limits are applicable for the duration of the cycle. 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.
2. CORE OPERATING LIMITS All values and limits in this TDB section apply to Cycle 26 operation. This cycle must be operated within the bounds of these limits and all others specified in the Technical Specifications.

This report has been prepared in accordance with the requirements of Technical Specification 5.9.5. The list of references below are complete citations of topical reports and include the report number, title, revision, date, and any supplements in accordance with the basis for NRC approval of License Amendment No. 196 which eliminated these specific entries from Technical Specification 5.9.5. NRC approval of Amendment No. 196 is consistent with the requirements of the Technical Specification Task Force, Improved Standard Technical Specification Change Traveler, "Revise Topical Report References in ITS 5.6.5 COLR" (TSTF-363-A, Rev. 0). In accordance with this Traveler and Amendment No. 196, this information must be maintained within this TDB section.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 7 OF 19 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," Revision 8, dated August 2004. (TAC No. MC4304)
  • OPPD-NA-8302, "Reload Core Analysis Methodology, Neutronics Design Methods and Verification," Revision 6, dated August 2004. (TAC No. MC4304)
  • OPPD-NA-8303, "Reload Core Analysis Methodology, Transient and Accident Methods and Verification," Revision 7, dated August 2005. (TAC No. MC4304)
  • XN-75-32(P)(A) Supplements 1, 2, 3, & 4, "Computational Procedure for Evaluating Fuel Rod Bowing," October 1983.
  • XN-NF-79-56(P)(A), Revision 1, Supplement 1, "Gadolinia Fuel Properties of LWR Fuel Safety Evaluation," November 1981.

" XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Revision 1, October 1986.

  • XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," August 1985.
  • ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," December 1991.

" EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs,"

Revision 0, February 1999.

  • XN-NF-78-44(P)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," October 1983.
  • XN-NF-82-21 (P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Revision 1, September 1983.

" EMF-1961(P)(A), "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Revision 0, July 2000.

" ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors:

Analysis of Non-LOCA Chapter 15 Events," Revision 0, May 1992.

  • EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Revision 1, January 2005.

" EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 0, April 2003.

  • EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based,"

Revision 0, March 2001.

  • EMF-96-029(P)(A) Volume 1, EMF-96-029(P)(A) Volume 2, EMF-96-029(P)(A)

Attachment, "Reactor Analysis System for PWRs, Volume 1 - Methodology Description, Volume 2 - Benchmarking Results," January 1997.

  • EMF-231 0(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Revision 1, May 2004.
  • BAW-10240(P)(A), "Incorporation of M5TM Properties in Framatome ANP Approved Methods," Revision 0, May 2004.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 8 OF 19

3. TM/LP LIMIT The TM/LP coefficients are shown below:

Table 1 -TM/LP Coefficients Coefficient Value a 29.6 Y3 20.63 Y -12372 The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:

PVAR = 29.6 PF(B) AI(Y)B + 20.63TIN - 12372 PF(B) = 1.0 for B _>100%

= -0.008(B)+1.8 for 50% < B < 100%

= 1.4 for B < 50%

AI(Y) = -0.6666(Y1 ) + 1.000 for Y1 < 0.00

- +0.3333(Y1 ) + 1.000 for Y, > 0.00 Where:

B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu TIN = Core Inlet Temperature, 'F PVAR = Reactor Coolant System Pressure, psia

4. MAXIMUM CORE INLET TEMPERATURE The maximum core inlet temperature (TIN) shall not exceed 545°F. This value includes instrumentation uncertainty of +/-20 F (Ref: FCS Calculation FC06292, 6/9/95).

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.

5. POWER DEPENDENT INSERTION LIMIT The power dependent insertion limit is defined in Figure 2.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 9 OF 19

6. LINEAR HEAT RATE The allowable peak linear heat rate is shown in Figure 3.
7. EXCORE MONITORING OF LHR The allowable operation for power versus axial shape index for monitoring of LHR with excore detectors is shown in Figure 4.
8. PEAKING FACTOR LIMITS The maximum full power value for the integrated radial peaking factor (FRT) is 1.732.
9. DNB MONITORING The core operating limits for monitoring of DNB are provided in Figure 5. This figure provides the allowable power versus axial shape index for the cycle.
10. FRRT AND CORE POWER LIMITATIONS Core power limitations versus FRT are shown in Figure 6.
11. REFUELING BORON CONCENTRATION The refueling boron concentration is required to ensure a shutdown margin of not less than 5% with all CEAs withdrawn. The refueling boron concentration must be at least 1,900 ppm through the end of Cycle 25 operation and is valid until the beginning of core reload for Cycle 26.

Listed below in Table 2 are the refueling boron concentration values for Cycle 26 operations:

Table 2 - Refueling Boron Concentrations Cycle Average Burnup Refueling Boron (MWD/MTU) Concentration (ppm)

BOC 2,160

> 2,000 2,016

>4,000 1,900 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 10 OF 19

12. AXIAL POWER DISTRIBUTION 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 setpoint functions, shown in Figure 7 ensure that neither a DNBR of less than the minimum DNBR safety limit nor a fuel centerline temperature greater than the associated safety limit (that which would result in fuel melting) will exist as a consequence of axial power maldistributions. The calculated cycle-specific FCM temperature for Cycle 26 corresponds to 22.845 kw/ft. Allowances have been made for instrumentation inaccuracies and uncertainties associated with the excore symmetric offset - incore axial peaking relationship. Figure 8 combines the LHR LCO tent from Figure 4, the DNB LCO tent from Figure 5, and the APD LSSS tent from Figure 7 into one figure for a visual comparison of the different limits.

13. SHUTDOWN MARGIN WITH Tcold > 210°F Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be _>3.6% Ak/k. With the shutdown margin <3.6% Ak/k, initiate and continue boration until the required shutdown margin is achieved.
14. MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT The moderator temperature coefficient (MTC) shall be more positive than

-3.25 x 104 Ap/ 0 F, including uncertainties, at rated power.

15. STEAM GENERATOR DIFFERENTIAL PRESSURE The steam generator differential pressure trip of Technical Specification Table 2-11, Item 9 at 135 psid ensures that neither a DNBR of less than the minimum DNBR safety limit nor a fuel centerline temperature greater than the associated safety limit (that which would result in fuel melting) will exist as a consequence of axial power maldistributions resulting from asymmetric steam generator transients. The calculated cycle-specific FCM temperature for Cycle 26 corresponds to 22.845 kw/ft.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 11 OF 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 12 OF 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 13 OF 19 18 UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 LL ACCEPTABLE OPERATION 12 I.-

10 UJI 8

..I w

z 6

4 2

0 5000 10000 15000 20000 BURNUP (MWD/MTU)

COLR IVS.

ALLOWABLE PEAK LINEAR HEAT RATE BURNUP 1 FIGURE 3

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 14 OF 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 15 OF 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 16 OF 19 110 (1.732,100) 100 LLJ w 90 1.765,86) 0 80 00 70 _ _ _ _ _ _ _ I I 60 0

ILl

.J 50 t $ -t I-- 40 zw 0 30 I 4 4 uLw CL 20 10 1 41. 4 0

1.70 1.75 1.80 1.85 1.90 PEAKING FACTOR R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 17 OF 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 18 OF 19 R39

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 19 OF 19 R39

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