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Category:Fuel Cycle Reload Report
MONTHYEARML22297A2292022-10-17017 October 2022 Enclosure 2 - Hope Creek Generating Station Unit 1 Core Operating Limits Report (COLR) Cycle 25 LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0005, Core Operating Limits Report, Reload 22, Cycle 23, Revision 202021-01-29029 January 2021 Core Operating Limits Report, Reload 22, Cycle 23, Revision 20 LR-N20-0083, Core Operating Limits Report, Reload 22, Cycle 23, Revision 192020-12-22022 December 2020 Core Operating Limits Report, Reload 22, Cycle 23, Revision 19 LR-N20-0064, Core Operating Limits Report, Reload 22, Cycle 23, Revision 182020-09-24024 September 2020 Core Operating Limits Report, Reload 22, Cycle 23, Revision 18 LR-N19-0101, Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 172019-11-12012 November 2019 Submittal of Core Operating Limits Report, Reload 22, Cycle 23, Revision 17 LR-N19-0074, Core Operating Limits Report, Reload 21, Cycle 22, Revision 162019-09-0303 September 2019 Core Operating Limits Report, Reload 21, Cycle 22, Revision 16 LR-N19-0015, Core Operating Limits Report, Reload 21, Cycle 22, Revision 152019-03-0606 March 2019 Core Operating Limits Report, Reload 21, Cycle 22, Revision 15 ML18129A3292018-05-0303 May 2018 Attachment 2 to LR-N18-0055, Core Operating Limits Report, Reload 21, Cycle 22, Revision 14 LR-N18-0055, Hope Creek - Attachment 2 to LR-N18-0055, Core Operating Limits Report, Reload 21, Cycle 22, Revision 142018-05-0303 May 2018 Hope Creek - Attachment 2 to LR-N18-0055, Core Operating Limits Report, Reload 21, Cycle 22, Revision 14 ML16316A1242016-11-11011 November 2016 Core Operating Limits Report, Reload 20, Cycle 21, Revision 13 LR-N16-0204, Hope Creek Generating Station - Core Operating Limits Report, Reload 20, Cycle 21, Revision 132016-11-11011 November 2016 Hope Creek Generating Station - Core Operating Limits Report, Reload 20, Cycle 21, Revision 13 LR-N16-0164, Core Operating Limits Report, Reload 19, Cycle 20, Revision 122016-09-0707 September 2016 Core Operating Limits Report, Reload 19, Cycle 20, Revision 12 LR-N15-0071, Core Operating Limits Report, Reload 18, Cycle 19, Revision 102015-03-20020 March 2015 Core Operating Limits Report, Reload 18, Cycle 19, Revision 10 LR-N14-0230, Response to Request for Additional Information Re Core Operating Limits Report2014-10-22022 October 2014 Response to Request for Additional Information Re Core Operating Limits Report LR-N13-0253, Core Operating Limits Report, Reload 18, Cycle 19, Revision 92013-11-0404 November 2013 Core Operating Limits Report, Reload 18, Cycle 19, Revision 9 LR-N13-0222, Core Operating Limits Report, Reload 17, Cycle 18, Revision 82013-09-19019 September 2013 Core Operating Limits Report, Reload 17, Cycle 18, Revision 8 LR-N12-0148, Attachment 2 to LR-N12-0148 - Core Operating Limits Report, Reload 17, Cycle 18, Revision 7 (Non-Proprietary Version)2012-05-0202 May 2012 Attachment 2 to LR-N12-0148 - Core Operating Limits Report, Reload 17, Cycle 18, Revision 7 (Non-Proprietary Version) LR-N11-0366, Core Operating Limits Report, Reload 16, Cycle 17, Revision 52011-12-0101 December 2011 Core Operating Limits Report, Reload 16, Cycle 17, Revision 5 ML1030907192010-11-0404 November 2010 Attachment 2, Core Operating Limits Report, Reload 16, Cycle 17, Revision 4 LR-N10-0290, 0000-0105-6621-SRLR, Rev. 0, Supplemental Reload Licensing Report for Hope Creek Unit 1, Reload 16 Cycle 17, Attachment 12010-07-31031 July 2010 0000-0105-6621-SRLR, Rev. 0, Supplemental Reload Licensing Report for Hope Creek Unit 1, Reload 16 Cycle 17, Attachment 1 LR-N09-0115, Core Operating Limits Report, Reload 15, Cycle 16, Revision 32009-05-14014 May 2009 Core Operating Limits Report, Reload 15, Cycle 16, Revision 3 LR-N08-0211, Core Operating Limits Report, Reload 14, Cycle 15, Revisions 1 and 22008-09-0909 September 2008 Core Operating Limits Report, Reload 14, Cycle 15, Revisions 1 and 2 LR-N08-0100, Transmittal of Supplement Reload Licensing Report,2008-05-0202 May 2008 Transmittal of Supplement Reload Licensing Report, LR-N07-0275, Core Operating Limits Report - Cycle 152007-10-25025 October 2007 Core Operating Limits Report - Cycle 15 LR-N07-0228, Core Operating Limits Reports - Cycle 14, Revision 12007-09-26026 September 2007 Core Operating Limits Reports - Cycle 14, Revision 1 LR-N06-0214, Core Operating Limits Report - Cycle 142006-05-0202 May 2006 Core Operating Limits Report - Cycle 14 LR-N06-0008, Core Operating Limits Report - Cycle 13, Revision 32006-01-31031 January 2006 Core Operating Limits Report - Cycle 13, Revision 3 LR-N05-0538, Core Operating Limits Report - Cycle 13, Revision 22005-11-0404 November 2005 Core Operating Limits Report - Cycle 13, Revision 2 LR-N05-0357, Core Operating Limits Report - Cycle 13, Revision 12005-07-14014 July 2005 Core Operating Limits Report - Cycle 13, Revision 1 LR-N05-0096, Core Operating Limits Report - Cycle 132005-02-11011 February 2005 Core Operating Limits Report - Cycle 13 LR-N03-0533, Revised Core Operating Limits Report, Cycle 122003-12-17017 December 2003 Revised Core Operating Limits Report, Cycle 12 LR-N03-0250, Core Operating Limits Report - Cycle 122003-06-0606 June 2003 Core Operating Limits Report - Cycle 12 ML0226600572002-09-11011 September 2002 Core Operating Limits Report - Cycle 11/Reload 10, Revision 1 2022-10-17
[Table view] Category:Letter type:LR
MONTHYEARLR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022 2022 Annual 10 CFR 50.46 Report LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0019, Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges2022-02-24024 February 2022 Technical Specification 6.9.1.5.b 2021 Annual Report of SRV Challenges LR-N22-0011, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2022-02-0101 February 2022 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N22-0005, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-01-0707 January 2022 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0087, Corrected Hope Creek 10 CFR 50.46 Reports2021-12-0202 December 2021 Corrected Hope Creek 10 CFR 50.46 Reports LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0081, Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments LR-N21-0056, License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System2021-11-0303 November 2021 License Amendment Request to Amend the Technical Specifications to Revise Surveillance Requirements for Electric Power Monitor Channels for the Reactor Protection System (RPS) and Power Range Neutron Monitoring System LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2021-11-0303 November 2021 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N21-0071, 2021 Annual 10 CFR 50.46 Report2021-09-30030 September 2021 2021 Annual 10 CFR 50.46 Report LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0069, Emergency Plan Document Revisions Implemented August 10, 20212021-09-0909 September 2021 Emergency Plan Document Revisions Implemented August 10, 2021 LR-N21-0059, In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage2021-08-13013 August 2021 In-Service Inspection Activities - 90 Day Twenty-Third Refueling Outage LR-N21-0054, Correction to Prior Spent Fuel Cask Registration Letter2021-07-15015 July 2021 Correction to Prior Spent Fuel Cask Registration Letter LR-N21-0046, Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2021-06-17017 June 2021 Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 32, Summary of Revised Regulatory Commitments for Salem, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N21-0040, Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-05-27027 May 2021 Response to Request for Additional Information SNSB-RAI 1 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication LR-N21-0042, Core Operating Limits Report, Reload 23, Cycle 24, Revision 212021-05-24024 May 2021 Core Operating Limits Report, Reload 23, Cycle 24, Revision 21 LR-N21-0025, License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink2021-05-0707 May 2021 License Amendment Request to Revise Technical Specification Limits for Ultimate Heat Sink LR-N21-0039, Deviation from EPRI Document 33002012244 Inspection Requirements2021-04-30030 April 2021 Deviation from EPRI Document 33002012244 Inspection Requirements LR-N21-0018, Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication2021-04-29029 April 2021 Response to Requests for Additional Information SNSB-RAI 2 and SNSB-RAI 3 License Amendment Request to Revise Low Pressure Safety Limit to Address General Electric Part 21 Safety Communication 2023-09-08
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC LR-N06-0214 MAY 0 2 2006 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 CORE OPERATING LIMITS REPORT - CYCLE 14 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 In accordance with section 6.9.1.9 of the Hope Creek Technical Specifications, PSEG Nuclear, LLC submits Revision 0 of the Core Operating Limits Report (COLR) for Hope Creek Cycle 14 (NFS-0253, Rev. 0) in Attachment 1 of this letter.
Should you have any questions, please contact James Barstow at (856) 339-1384.
Sincerely, Michael Jesse Regulatory Assurce Manager Hope Creek Attachment 400 95-2168 REV. 7/99
LR-N06-0214 2 Document Control Desk C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Bailey, Project Manager- Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08BI Washington, DC 20555 USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. 0. Box 415 Trenton, NJ 08625
Document Control Desk LR-N06-0214 Attachment I NFS-0253, Rev. 0
NFS-0253 Revision 0 Hope Creek Generating Station Unit 1 Core Operating Limits Report Cycle 14 / Reload 13 Effective Date: S /l /I6 Prepared By: 4 L.j, 9 Date: L-ulm Steven G. Bier, Nuclear Fuels Staff Engineer Reviewed By: :-,J- -F Date: _/__/_
Shie-Jeng g, i n Engineer Approved By: . Li. Date: _____6 Donald V. Notig , ger-Fuel Tedhnologytation Page 1 of 19
NFS-0253 Revision 0 Table of Contents Section Description Page
1.0 INTRODUCTION
4 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR _ 5 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE! 6 2.2 MINIMUM CRITICAL POWER RATIO 8 2.3 LINEAR HEAT GENERATION RATE 12 2.4 OPRM TRIP SETPOINT 16
3.0 REFERENCES
17 Appendix A: Method of Core Average Scram Speed Calculation __ 18 Page 2 of 19
NFS-0253 NPS-053 Revision 0 List of Tables Table Description Page Table 2.1-1: APLHGR Data for GE14 Fuel 7 Table 2.1-2: APLHGR Data for SVEA-96+ Fuel 7 Table 2.2-1: Cycle 14 MCPR Operating Limits: Cycle Exposure S 9755 MWD/MTU (S8850 MWDISTU)_ 10 Table 2.2-2: Cycle 14 MCPR Operating Limits: Cycle Exposure > 9755 MWD/MTU
(> 885OMWD/STU) 10 Table 2.2-3: Power Dependent MCPR Adjustments and Multiplier (Kp) Data _ 11 Table 2.2-4: Flow Dependent MCPR Limit (MCPR_) 11 Table 2.3-1: LHGR Limit for GE14 _ 14 Table 2.3-2: LHGR Limit for SVEA-96+ ___ 14 Table 2.3-3: Power Dependent Linear Heat Generation Rate Multiplier (LHGRFAC.) 15 Table 2.3-4: Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACf) - 15 Page 3 of 19
NFS-0253
- NFS-0253 Revision 0
1.0 INTRODUCTION
The purpose of this report is to provide the Core Operating Limits for Hope Creek Generation Station Unit i Cycle 14/ Reload 13 operation. This report provides the core thermal limits for Average Planar Linear Heat Generation Rate (APLHGR), Minimum Critical Power Ratio (MCPR), and Linear Heat Generation Rate (LHGR), as well as power and flow dependent adjustments to these limits that support off-rated operation and Single recirculation Loop Operation (SLO). Additionally, this report provides the Allowable Value for the Oscillation Power Range Monitor (OPRM) trip setpoint, and the method of average scram speed determination. Finally, this report provides a reference to the most recent revision of the implemented approved licensing methodology.
These operating limit LCO values have been determined using NRC approved methods contained in GESTAR-Il, NEDE-2401I-P-A (Revision 15) and are established such that all applicable fuel thermal-mechanical, core thermal-hydraulic, ECCS, and nuclear limits such as shutdown margin, and transient and accident analysis limits are met.
Hope Creek Technical Specifications Section 3.2 references this report as the source for certain LIMITING CONDITIONS FOR OPERATION. These are included in Section 2 of this document. Hope Creek Technical Specification 69.1.9 also requires that this report, including any mid cycle revisions, shall be provided, upon issuance, to the NRC.
This document is specific to Hope Creek Generating Station Unit 1 Cycle 14/ Reload 13 and shall not be applicable to any other core or cycle design. The thermal limits contained in this report are applicable whether the Crossflowsm correction factor is applied or not applied.
This report is applicable for Cycle 14 operation from the date of issuance through the end of effective full power capability or a cycle exposure of 12070 MWMTU (10950 MWdISTU, whichever occurs first. End of effective full power capability is reached when 100% rated power can no longer be maintained by increasing core flow (up to 105% of rated core flow),
at rated feedwater temperatures, in the all-rods-out configuration Page 4 of 19
NFS-0253 Revision 0 2.0 TECHNICAL SPECIFICATIONS THAT REFERENCE THE COLR The TECHNICAL SPECIFICATIONS TIAT RIFERENCE THE COLR presented in this section are referenced by the Hope Creek Technical Specifications.
Tech. Spec itle 2.1 Bases Safety Limit Bases 3/4.2.1 Average Planar Linear Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.3.11 Oscillation Power Range Monitor 3/4.4.1 Recirculation System Recirculation Loops 3/4.2.1 Bases Average Planar Linear Heat Generation Rate 3/4.2.4 Bases Linear Heat Generation Rate 3/4.3.11 Bases Oscillation Power Range Monitor (OPRM) 314.4.1 Bases Recirculation System 6.9.1.9 Administrative Controls, Core Operating Limits Report Page 5 of 19
NFS-0253 NFS-0253 Revision 0 2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION:
All AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGRs) shall be less than or equal to the limits specified in Table 2.1-1 and Table 2.1-2 for Two recirculation Loop Operation (TLO).
When the Technical Specification Section 314.4.1 ACTION statement a.L.d is entered from that section's Limiting Condition for Operation, reduce the APLHGR limits to the values specified in Tables 2.1-1 and 2.1-2 for Single recirculation Loop Operation (SLO).
Linear interpolation shall be used to determine APLHGR limits as a function of exposure for intermediate values in Table 2.1-1 and Table 2.1-2.
Page 6 of 19
NFS-0253 Revision 0 Table 2.1-1: APLHGR Data for GE14 Fuel Average Planar Exposure kWfLHGR Limit hWD/M TU MW STU ' Two Loop OSBnre Loop Operation 0.00 0.00 12.82 10.26 21090 19130 - 12.82 - 10.26 63500 57610 8.00 6.40 70000 63500 5.00 4.00 Table 2.1-2: APLHGR Data for SVEA.96+ Fuel Average Planar Exposure APHGflft mD/MU MWD/STU Two Loop Operation Single Loop Operation 0.00 0.00 12.85 10.28 3680 3340 12.85 10.28 16000 14510 10.97 8.78 65000 58970 7.24 5.79 Page 7 of 19
NFS-0253 Revision 0 22 MINIMUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit computed from the following steps:
- 1. Determine r as defined in Appendix A.
NOTE The SLO operating condition MCPR values in Tables 2.2-1, 2.2-2, 2.2-3 and 2.2-4 implement the increase in the MCPR Safety Limit to meet the requirements of Technical Specification Section 3/4.4.1 ACTION statement aL .c.
- 2. Linearly interpolate a MCPR value as a fimction of r from the MCPR value at t = 0 and the MCPR value at r = 1 as specified in Table 2.2-1 and Table 2.2-2 for the appropriate operating condition.
- 3. For the power dependent MCPR adjustment, when thermal power is 2 30% rated core thermal power, determine a K.p value by linearly interpolating a Kp value as a function of core rated thermal power from Table 2.2-3. Multiply the MCPR value obtained from Step 2 by the Kp value to determine the power dependent MCPR limit.
When core thermal power is > 25% rated and < 30% rated thermal power, determine the appropriate power dependent MCPR limit by linearly interpolating between the MCPR limits as a function of rated core thermal power for the appropriate core flow condition using the information in Table 2.2-3.
- 4. For the flow dependent MCPR adjustment, determine the appropriate flow dependent MCPR limit by linearly interpolating between the MCPR limits as a function of rated core flow using the information in Table 2.24.
- 5. Choose the most limiting (highest value) of the power and flow dependent MCPR limits determined in steps 2 and 3 as the value for the MCPR limit for the Limiting Condition For Operation.
Note that the MCPR limit is a function of core average scram speed (X), cycle exposure, core thermal power, total core flow, EOC-RPT operability, the number of reactor coolant recirculation loops in operation, and main turbine bypass operability.
EOC-RPT system operability is defined by Hope Creek Technical Specification 3.3.4.2.
Page 8 of 19
NPS-0253 Revision 0 2.2 MINIMUM CRITICAL POWER RATIO (Continued)
Reactor coolant recirculation loop operation is defined by Hope Creek Technical Specification 3.4.1.1.
Main Turbine Bypass operability is defined by Hope Creek Technical Specification 3.7.7.
Page 9 of 19
NFS-02.53 Revision 0 Table 2.2-1: Cycle 14 MCPR Operating Limits:
Cycle Exposure 5 9755 MWD/MTU (58850MWD/STU)
Main Turbine Byass Operable Operating Condition Scram Speed GE14 SVEA-96+
Option TLO-EOC-RPI Operable B 1.34 1.47 A 1A34 1.49 TLO-EOC-RPT Inoperable B 1.37 1.49 A 1.47 1.30 SLO-EOC-RPT Operable A 1.36 1.50 A 1.35 1.31 SLO-E0C-RPT Inoperable B 1.39 1.40 Scram Speed Option A = 1, Scram Speed Option B ' =0, TLO = Two recirculation
'r Loop Operation, SLO = Single recirculation Loop Operation Table 2.2-2: Cycle 14 MCPR Operating Limits:
Cycle Exposure > 9755 MWD/MTU ( 8850 MWD/STU)
Main Turbie yps Operable _____
Operating Condition Scram Speed GEI4 SVEA-96+
_Option TLO-EOC-RPT Operable A B ; 1 1.57 1.40 1.59 1.42 AB 1.40 1.42 TLO-EOC-RPT Inoperable A 1.61 1.62 B 1.44 1.45 SLO-EOC-RPT Operable A 1.59 1.61 13 1.42 1.44 SLO-EOC-RPT OperableBA 1.63 1.4 1.64 1.47 Scram Speed Option A T= 1,Scram Speed Option B X=0, TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Page 10 of 19
NFS-0253 Revision 0 Table 2.2-3: Power Dependent MCPR Adjustments and Multiplier (Kp) Data Core Thermal Power (% of rated)
Operating Core Flow Condition (% of rated) 225 < 30 30 45 60 l 2100 MCPR Limit MCPR Multiplier, Kp TL 60 2.25 2.12 1.481 1.280 1.150 1.000
> 60 2.93 2.70
<560 2.27 2.14 SLO 1.481 1.280 1.150 1.000
> 60 2.95 2.72 TLO = Two recirculation Loop Operation, SLO = Single recirculation Loop Operation Table 2.24: Flow Dependent MCPR Limit (MCPRt)
Core Flow (% of rated)
Operating Condition 30 1 60 1 77 J105 MCPR Limit TLO 1.53 XA 1.25 1 1.25 SID 1.55 I.s~
Page 11 of 19
NFS-0253 Revision 0 23 LINEAR HEAT GENERATION RATE LMITNG CONDITION FOR OPERATION The LINEAR HEAT GENERATION RATE (LHGR) shall not exceed the limit computed from the following steps:
- 1. Determine the exposure dependent LHOR limit for the appropriate fuel design using linear interpolation between the values in Table 2.3-1 and Table 23-2.
NOTE For Two recirculation Loop Operation utilize steps 1,2, 3 and 6 to determine the LCO LHGR limits for Two recirculation Loop Operation (TLO).
When the Technical Specification Section 3/4A. 1ACTION statement a. Le is entered from that section's Limiting Condition for Operation (LCO), utilize steps 1,4, 5 and 6 to determine the LCO LHGR limits for Single recirculation Loop Operation (SLO).
- 2. For the power dependent LHGR adjustment for TLO, determine a LHGRFACp value by linearly interpolating a LHGRFACp value as a function of rated core thermal power for the core flow condition being evaluated from the TMO entries in Table 2.3-
- 3. Multiply the LHGR values obtained from Step 1by the LHGRFACp value to determine the power dependent LHGR limits for each fuel design.
- 3. For the flow dependent LHGR adjustment for TLO, determine a LHGRFACf value by linearly interpolating a LHGRFACr value as a function of rated core flow from the TLO entries in Table 2.3-4. Multiply the LHQR values obtained from Step 1 by the LHGRFACQ value to determine the flow dependent LHGR limits for each fuel design.
- 4. For the power dependent LHGR adjustment for SLO, determine a LHGRFACp value by linearly interpolating a LHGRFACp value as a function of rated core thermal power for the core flow condition being evaluated from the SLO entries in Table 2.3-
- 3. Multiply the LHGR values obtained from Step 1 by the LHGRFACp value to determine the power dependent LHGR limits for each fuel design.
- 5. For the flow dependent LHGR adjustment for SLO, determine a LHGRFACr value by linearly interpolating a LHGRFACf value as a function of rated core flow from the SLO entries in Table 2.3-4. Multiply the LHGR values obtained from Step 1 by the LHGRFACf value to determine the flow dependent LHGR limits for each fuel design.
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NFS-0253 Revision 0 2.3 LINEAR HEAT GENERATION RATE (Continued)
- 6. Choose the most limiting (lowest value) of the power and flow dependent LHGR limits determined in steps 2 and 3 (TL) or 4 and 5 (SLO) as the value for the LHGR limit for the Limiting Condition For Operation. -
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NFS-0253 Revision 0 Table 2.31: LHGR Limit for GE14 Peak Pellet Exposure LHGR Limit MWD/M MWD/STU' kWMM 0.0 0.0 13.40 16000 14510 13.40 63500 57610 8.00 70000 63500 5.00 Table 2.3-2: LHGR Limit for SVEA-96+
Peak Pellet Exposure LHGRLimit NMWDJIU - ' MWD/STU MM/f 0.0 __0.0 13.41
_16000 14510 110.97 6500058970 7.24 Page 14 of 19
NFS-0253 Revision 0 Table 2.33: Power Dependent Linear Heat Generation Rate Multiplier (LHGRFACp)
U U Core Thermal Power (% of rated)
Operating Core Flow Condition (% of rated) 225 1 <30 1 230 1 61.7 1 70 1 2100 LHGRFACq Multiplier TLO S 60 0.577 0.590 0.634 1.000
> 60 0.476 10.502
- 60 0.577 0.590 SLO 4. 4. 0.634 0.800 0.800
>60 0.476 0.502 I - A Table 2.34: Flow Dependent Linear Heat Generation Rate Multiplier (LHGRFACO Core Flow (% of rated)
Operating Condition 30 1 50 I 52.7 1 60 1 82.2 1 105
_j0 0.500 0.782 SLO 1 0.500 1 0.782 1 0.800 0.800 Page 15 of 19
NFS-0253 Revision 0 2A OPRM TRIP SETPOINT LIMING CONDITION FOR OPERATION Four channels of the OPRM instumentation shall be OPERABLE. Each OPRM channel period based algorithm amplitude trip setpoint (Sp) shall be less tan or equal to the Allowable Value of 1.08.
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NFS-0253 Revision 0
3.0 REFERENCES
- 1. Nuclear Fuel Section Design Input File HCG,540002,:General Electric Standard Application forReactor Fuel," General Electric Company, NEDE-2401 1-P-A-15, and the U.S. Supplement NEDE-2401 1-P-A-15-US.
- 2. Nuclear Fuel Section Design Input File, HCG.5-0041, "Supplemental Reload Licensing Report for Hope Creek Unit I Reload 13 Cycle 14" GE Nuclear Energy 0000-0041-6021-SRLR, Rev. 1,March 2006.
- 3. Nuclear Fuel Section Design Input File HCG.5-0041, "Fued Bundle Information Report for Hope Creek Unit 1 Reload 13 Cycle 14," 0000-0041-6021-FBIR, Rev. 0 February 2006.
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NFS-0253 Revision 0 Appendix A: Method of Core Average Scram Speed Calculation Page 18 of 19 i
NFS-0253 Revision 0 Method of Core Average Scram Speed, X, Calculation r is defined as
'r ( ovTa)
TFA - T, where:
TA = 0.86 seconds, control rod average scram insertion time limit to notch 39 per Specification 3.1.3.3
= 0.672 +1.65l IJ (0.016)
ENN n = number of surveillance tests performed to date in cycle, N, = number of active control rods measured in the ih surveillance test, x, = average scram time to notch 39 of all rods measured in the ih surveillance test, and N. = total number of active rods measured in Specification 4.1.3.2.a.
if fre,,, S r, set r = 0 to apply Option B OLMCPR.
r shall be 1.0 (Tr = 1.0) prior to performance of the initial scram time measurements for the cycle in accordance with Specification 4.1.3.2.
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