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Category:Fuel Cycle Reload Report
MONTHYEARLIC-15-0063, Transmits Core Operating Limits Report (Colr), Revision 422015-05-0101 May 2015 Transmits Core Operating Limits Report (Colr), Revision 42 ML13128A2702013-04-30030 April 2013 Technical Data Book Core Operating Limits Report LIC-11-0057, Transmittal of Fort Calhoun Station, Unit 1, Core Operating Limit Report (Colr), Revision 402011-05-18018 May 2011 Transmittal of Fort Calhoun Station, Unit 1, Core Operating Limit Report (Colr), Revision 40 ML11146A0512011-05-16016 May 2011 TDB-VI Technical Data Book - Core Operating Limit Report, Revision 40 ML1011206522010-04-0606 April 2010 TDB-IX, Technical Data Book, RCS Pressure and Temperature Limits Report LIC-10-0014, Re-transmittal of Core Operating Limits Report (COLR) Due to Typographical Error Discovered and Corrected2010-02-22022 February 2010 Re-transmittal of Core Operating Limits Report (COLR) Due to Typographical Error Discovered and Corrected ML1006308282010-02-18018 February 2010 TDB-VI, Technical Data Book, Core Operating Limits Report, Rev. 39, Change EC 44759 LIC-09-0097, Submittal of Core Operating Limit Report (Colr), Revision 392009-11-25025 November 2009 Submittal of Core Operating Limit Report (Colr), Revision 39 ML1006308292009-11-20020 November 2009 Technical Data Book, Revision 39, Core Operating Limit Report LIC-09-0074, Transmittal of Fort Calhoun Station (Fcs), Unit 1, Core Operating Limit Report (Colr), Revision 382009-09-14014 September 2009 Transmittal of Fort Calhoun Station (Fcs), Unit 1, Core Operating Limit Report (Colr), Revision 38 ML0926502842009-09-0101 September 2009 TDB-VI Technical Data Book - Core Operating Limit Report LIC-09-0037, Transmittal of Core Operating Limit Report (Colr), Revision 372009-05-29029 May 2009 Transmittal of Core Operating Limit Report (Colr), Revision 37 ML0916704662009-05-28028 May 2009 Transmittal of Fort Calhoun Station Technical Data Book (TDB)-IV, Revision 37, Core Operating Limit Report ML0815602172008-05-22022 May 2008 Revision 36 to Technical Data Book TDB-VI, Core Operating Limit Report, Change No. EC 42580, Technical Specifications Amendment 252 LIC-08-0016, Transmittal of Fort Calhoun Station (Fcs), Unit 1, Core Operating Limit Report (Colr), Revision 342008-02-12012 February 2008 Transmittal of Fort Calhoun Station (Fcs), Unit 1, Core Operating Limit Report (Colr), Revision 34 LIC-06-0128, Transmittal of Fort Calhoun, Unit 1 (FCS) Core Operating Limit Report (Colr), Revision 332006-11-28028 November 2006 Transmittal of Fort Calhoun, Unit 1 (FCS) Core Operating Limit Report (Colr), Revision 33 ML0634102972006-11-16016 November 2006 Technical Data Book, Core Operating Limit Report LIC-06-0121, Transmittal of Fort Calhoun, Unit 1, Core Operating Limit Report (Colr), Revision 322006-10-24024 October 2006 Transmittal of Fort Calhoun, Unit 1, Core Operating Limit Report (Colr), Revision 32 ML0630406802006-10-17017 October 2006 Revision 32 to Technical Data Book, Change No. EC 38634 LIC-05-0080, Transmittal of Fort Calhoun Station Unit No. 1 (FCS) Core Operating Limit Report (Colr), Revision 312005-07-0101 July 2005 Transmittal of Fort Calhoun Station Unit No. 1 (FCS) Core Operating Limit Report (Colr), Revision 31 ML0519405622005-06-30030 June 2005 Station,Technical Data Book TDB-VI, Rev. 31, Core Operating Limit Report. LIC-05-0033, Transmittal of Fort Calhoun Station Unit No. 1 (FCS) Core Operating Limit Report (COLR) Revisions 29 & 302005-03-25025 March 2005 Transmittal of Fort Calhoun Station Unit No. 1 (FCS) Core Operating Limit Report (COLR) Revisions 29 & 30 ML0509602032005-03-24024 March 2005 BDB-VI, Technical Data Book, Core Operating Limit Report LIC-04-0097, License Amendment Request (Lar), Core Operating Limits Report and Application of CASMO-4 Methodology.2004-09-0707 September 2004 License Amendment Request (Lar), Core Operating Limits Report and Application of CASMO-4 Methodology. LIC-04-0058, Annual Report for 2003 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.462004-04-30030 April 2004 Annual Report for 2003 Loss of Coolant Accident (Loca)/Emergency Core Cooling System (ECCS) Models Pursuant to 10 CFR 50.46 LIC-02-0072, Omaha Public Power District Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 272002-05-31031 May 2002 Omaha Public Power District Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 27 LIC-02-0058, Core Operating Limits Report, Revision 262002-05-0303 May 2002 Core Operating Limits Report, Revision 26 LIC-02-0020, Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 252002-02-12012 February 2002 Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 25 2015-05-01
[Table view] Category:Letter type:LIC
MONTHYEARLIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0004, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2022-02-17017 February 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-21-0008, Organizational and Management Change2021-10-28028 October 2021 Organizational and Management Change LIC-21-0007, ISFSI Only Emergency Plan Update2021-09-0808 September 2021 ISFSI Only Emergency Plan Update LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report2021-04-29029 April 2021 Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-21-0003, Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report2021-03-30030 March 2021 Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-21-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-22022 February 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0015, Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092)2020-07-29029 July 2020 Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092) LIC-20-0014, Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2020-07-15015 July 2020 Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-20-0012, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2020-05-18018 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool LIC-20-0011, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-05-0707 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2020-04-30030 April 2020 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-20-0008, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-04-13013 April 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0006, (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2020-03-26026 March 2020 (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-03-10010 March 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-02-27027 February 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0002, Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan2020-02-27027 February 2020 Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan LIC-20-0001, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-02-0606 February 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0025, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-12-19019 December 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0007, Post-Shutdown Decommissioning Activities Report2019-12-16016 December 2019 Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-19-0022, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-11-18018 November 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0018, Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2019-11-14014 November 2019 Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-19-0020, Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis2019-10-17017 October 2019 Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis LIC-19-0017, Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 20042019-08-0808 August 2019 Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 An LIC-19-0010, License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associa2019-05-20020 May 2019 License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated LIC-19-0008, Submittal of 2018 Annual Report2019-04-0404 April 2019 Submittal of 2018 Annual Report LIC-19-0004, Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP)2019-03-28028 March 2019 Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP) LIC-19-0005, 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report2019-03-28028 March 2019 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2019-02-28028 February 2019 License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme LIC-19-0003, Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation R2019-02-28028 February 2019 Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation Requ LIC-19-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-01-0303 January 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-18-0031, Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update2018-12-17017 December 2018 Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update LIC-18-0030, Request for Partial Site Release Phase 22018-11-12012 November 2018 Request for Partial Site Release Phase 2 LIC-18-0028, Letter of Intent to Submit Request for Additional Partial Site Release2018-10-18018 October 2018 Letter of Intent to Submit Request for Additional Partial Site Release 2024-06-18
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OmahaPublic Power District Fort Calhoun Station P.O. Box 550, Fort Calhoun, NE 68023 September 14, 2009 LIC-09-0074 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Reference:
Docket No. 50-285
SUBJECT:
Transmittal of Fort Calhoun Station (FCS), Unit No. 1, Core Operating Limit Report (COLR), Revision 38 Pursuant to FCS Technical Specification 5.9.5d, Revision 38 of the FCS COLR is attached. Revision 38, issued on September 1, 2009, revised the Cycle 25 fuel centerline melt limit from 23.416 kw/ft to 22.705 kw/ft.
No regulatory commitments are contained in this submittal.
If you have any questions, please contact Ms. Susan Baughn at (402) 533-7215.
Sincerely, T. C. Matthews Manager - Nuclear Licensing TCM/mle
Attachment:
TDB-VI - Technical Data Book - Core Operating Limit Report - Revision 38 c: E. E. Collins, NRC Regional Administrator, Region IV (w/o Attachment)
A. B. Wang, NRC Project Manager (w/o Attachment)
J. C. Kirkland, NRC Senior Resident Inspector (w/o Attachment)
Employment with Equal Opportunity
PAGE 1 OF 19 Fort Calhoun Station Unit 1 TDB-VI TECHNICAL DATA BOOK CORE OPERATING LIMIT REPORT Change No. EC 46602 Reason for Change Revised Cycle 25 Fuel Centerline Melt Limit from 23.416 kw/ft to 22.705 kw/ft.
Requestor C. Waszak Preparer L. Hautzinger Issue Date 09-01-09 3:00 pm R38
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 2 OF 19 Fort Calhoun Station, Unit 1 Core Operating Limit Report 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 Pagqe
- 1. IN T R O D UC T IO N ............................................................................................ 6
- 2. CO RE O PERATING LIM ITS ........................................................................... 6
- 3. T M/LP LIM IT ...................... I......................................................................... .. 8
- 4. MAXIMUM CORE INLET TEMPERATURE .................................................... 8
- 5. POWER DEPENDENT INSERTION LIMIT .................................................... 8
- 6. LIN EA R HEA T RA TE ...................................................................................... 9
- 7. EXCORE MONITORING OF LHR ................................................................... 9
- 8. PEA KING FACTO R LIM ITS ........................................................................... 9
- 9. D N B MO NIT O R IN G ........................................................................................ 9
- 10. FRT AND CORE POWER LIMITATIONS ........................................................ 9
- 11. REFUELING BORON CONCENTRATION ...................................................... 9
- 12. AXIAL POWER DISTRIBUTION .................................................................. 10
- 13. SHUTDOWN MARGIN WITH Tcold > 210-F ................................................. 10
- 14. MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT ............ 10
- 15. STEAM GENERATOR DIFFERENTIAL PRESSURE ................................... 10 R38
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 4 OF 19 LIST OF TABLES Table No. Title Page 1 T M/LP C oeffi cients .......................................................................................... 8 2 Refueling Boron Concentrations ..................................................................... 9 R38
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 5 OF 19 LIST OF FIGURES Figure No. Title Page 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 N B Mo nito ring ............................................................................................ . . 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 R38
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 6 OF 19 CORE OPERATING LIMIT REPORT
- 1. INTRODUCTION This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 25 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
- 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 25 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-1 961 (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.
- XN-NF-82-49(P)(A), Supplement 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Revision 1, December 1994.
- 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-2310(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 20.63 13
-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(Yi) + 1.000 for Y1 > 0.00 Where:
B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu TIN = Core Inlet Temperature, OF PVAR = Reactor Coolant System Pressure, psia
- 4. MAXIMUM CORE INLET TEMPERATURE The maximum core inlet temperature (TIN) shall not exceed 5450 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. FRT 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 24 operation and is valid until the beginning of core reload for Cycle 25.
Listed below in Table 2 are the refueling boron concentration values for Cycle 25 operations:
Table 2 - Refueling Boron Concentrations Cycle Average Burnup Refueling Boron (MWD/MTU) Concentration (ppm)
BOC 2,141
> 2,000 2,014
>4,000 1,900 R38
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 25 corresponds to 22.705 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
-3.30 x 10-4 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 25 corresponds to 22.705 kw/ft.
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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 11 OF 19 R38
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 12 OF 19 R38
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 13 OF 19 18 UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 LI.. ACCEPTABLE OPERATION S12 w
I-
-0
ýz wuJ 44 Z
6 4 4 4 4 t 4 2
0 5000 10000 15000 20000 BURNUP (MWD/MTU)
COLR ALLOWABLE PEAK LINEAR HEAT RATE FIGURE ALWBEVS. BURNUP1 3 R38
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