Similar Documents at Salem |
---|
Category:Fuel Cycle Reload Report
MONTHYEARLR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N21-0077, Core Operating Limits Report - Cycle 262021-10-26026 October 2021 Core Operating Limits Report - Cycle 26 LR-N20-0075, Core Operating Limits Report - Cycle 282020-12-0707 December 2020 Core Operating Limits Report - Cycle 28 LR-N20-0029, Core Operating Limits Report - Cycle 252020-05-0404 May 2020 Core Operating Limits Report - Cycle 25 LR-N19-0067, Core Operating Limits Report - Cycle 272019-06-10010 June 2019 Core Operating Limits Report - Cycle 27 LR-N18-0120, Core Operating Limits Report - Cycle 26, Mid-Cycle2018-11-0505 November 2018 Core Operating Limits Report - Cycle 26, Mid-Cycle LR-N18-0106, Core Operating Limits Report - Cycle 242018-11-0505 November 2018 Core Operating Limits Report - Cycle 24 LR-N17-0166, Core Operating Limits Report - Cycle 262017-11-0202 November 2017 Core Operating Limits Report - Cycle 26 ML17136A1022017-05-16016 May 2017 Core Operating Limits Report, Cycle 23 LR-N17-0101, Core Operating Limits Report, Cycle 232017-05-16016 May 2017 Core Operating Limits Report, Cycle 23 LR-N16-0107, Core Operating Limits Report, Cycle 252016-07-0505 July 2016 Core Operating Limits Report, Cycle 25 LR-N15-0233, Core Operating Limits Report - Cycle 222015-11-18018 November 2015 Core Operating Limits Report - Cycle 22 LR-N14-0203, Core Operating Limits Report - Cycle 242014-11-10010 November 2014 Core Operating Limits Report - Cycle 24 LR-N14-0113, Core Operating Limits Report- Cycle 212014-04-28028 April 2014 Core Operating Limits Report- Cycle 21 LR-N13-0111, Core Operating Limits Report - Cycle 232013-05-0303 May 2013 Core Operating Limits Report - Cycle 23 LR-N13-0024, Resubmittal of the Core Operating Limits Report for Cycle 22, Revision 42013-02-0606 February 2013 Resubmittal of the Core Operating Limits Report for Cycle 22, Revision 4 ML12339A0062012-11-29029 November 2012 Submittal of Core Operating Limits Report - Cycle 20 LR-N12-0255, Update Core Operating Limits Report - Cycle 222012-08-15015 August 2012 Update Core Operating Limits Report - Cycle 22 LR-N11-0331, Core Operating Limits Report - Cycle 222011-11-0808 November 2011 Core Operating Limits Report - Cycle 22 LR-N11-0124, Core Operating Limits Report - Cycle 192011-04-27027 April 2011 Core Operating Limits Report - Cycle 19 LR-N10-0141, Submittal of Core Operating Limits Report - Cycle 212010-04-20020 April 2010 Submittal of Core Operating Limits Report - Cycle 21 LR-N09-0247, Core Operating Limits Report - Cycle 182009-10-30030 October 2009 Core Operating Limits Report - Cycle 18 LR-N08-0252, Core Operating Limits Report - Cycle 202008-11-0303 November 2008 Core Operating Limits Report - Cycle 20 LR-N08-0062, Submittal of Core Operating Limits Report - Cycle 172008-04-23023 April 2008 Submittal of Core Operating Limits Report - Cycle 17 LR-N07-0028, Core Operating Limits Report - Cycle 192007-04-11011 April 2007 Core Operating Limits Report - Cycle 19 LR-N06-0410, Core Operating Limits Report - Cycle 162006-10-0909 October 2006 Core Operating Limits Report - Cycle 16 LR-N05-0545, Core Operating Limits Report - Cycle 18, Revision 02005-11-0404 November 2005 Core Operating Limits Report - Cycle 18, Revision 0 LR-N05-0267, Core Operating Limits Report - Cycle 15, Revision 02005-05-12012 May 2005 Core Operating Limits Report - Cycle 15, Revision 0 LR-N04-0239, Core Operating Limits Report - Cycle 17, Revisions 0 and 12004-05-28028 May 2004 Core Operating Limits Report - Cycle 17, Revisions 0 and 1 LR-N04-0167, Core Operating Limits Report - Cycle 14, Revision 12004-04-14014 April 2004 Core Operating Limits Report - Cycle 14, Revision 1 LR-N04-0166, Core Operating Limits Report - Cycle 16, Revision 12004-04-14014 April 2004 Core Operating Limits Report - Cycle 16, Revision 1 LR-N03-0448, Core Operating Limits Report - Cycle 142003-11-0303 November 2003 Core Operating Limits Report - Cycle 14 LR-N02-0409, Core Operating Limits Report - Cycle 16, Revision 02002-12-0202 December 2002 Core Operating Limits Report - Cycle 16, Revision 0 LR-N02-0222, Core Operating Limits Report - Cycle 132002-06-12012 June 2002 Core Operating Limits Report - Cycle 13 2023-04-26
[Table view] Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) 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 ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 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-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 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 ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 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 ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, 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 ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) 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-N23-0012, 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 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 2024-02-05
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038"0236 PSf:G Xurh'ar IJ,C' Technical Specification 6.9.1.9 MAY 1 6 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555"0001
Subject:
Salem Generating Station Unit 2 Renewed Facility Operating License DPR" 75 NRC Docket No. 50"311 Salem Unit 2 Core Operating Limits Report-Cycle 23 In accordance with section 6.9.1.9 of the Salem Unit 2 Technical Specifications, PSEG Nuclear LLC submits the enclosed Core Operating Limits Report (COLR) for Salem Unit 2, Cycle 23. There are no commitments contained in this letter. Should you have any questions regarding this submittal, please contact Mr. Thomas Cachaza at 856"339M5038.
Enclosure Page2 LR-N 17-0101 cc: Mr. D. Dorman, US NRC 1 Mr. R Ennis, USNRC -Licensing Project Manager-Salem Mr. P. Finney, US NRC Senior Resident Inspector Mr. P. Mulligan, NJBNE Manager IV Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. M. Washington, Chief Inspector-Occupational Safety and Health Bureau of Boiler and Pressure Vessel Compliance Enclosure Salem Unlt2 Core Operating Limits Report {COLR) Cycle 23 COLRSALEM 2 Revision 7 March 2017 Core Operating Limits Report for Salem Unit 2, Cycle 23 Page 1 of 13 COLRSALEM2 PSEG Nuclear LLC Revision 7 SALEM UNIT 2 CYCLE 23 COLR Page 2 ofl3 March 2017 TABLE OF CONTENTS Section Section Title Page Number Number Table of Contents 2 List of Figures 3 1.0 Core Operating Limits Report 4 2.0 Operating Limits 5 2.1 Moderator Temperature Coefficient (Specification 3.1.1.3) 5 2.2 Control Rod Insertion Limits (Specification 3 .1.3 .5) 6 2.3 Axial Flux Difference (Specification 3 .2.1) 6 2.4 Heat Flux Hot Channel Factor-FQ(z) (Specification 3.2.2) 6 2.5 Nuclear Enthalpy Rise Hot Charmel Factor FN AH (Specification 3.2.3) 8 2.6 Boron Concentration (Specification 3.9 .1) 9 3.0 Analytical Methods 9 4.0 References 10 COLRSALEM2 Revision 7 March 2017 Figure Number 1 2 3 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR LIST OF FIGURES Figure Title Rod Bank Insertion Limits vs. Thermal Power Page 3 ofl3 Page Number 11 Axial Flux Difference Limits as a Function of Rated Thennal Power 12 K(z)-Normalized F 0 (z) as a Function of Core Height 13 TS Section 3.1.1.3 3.1.3.5 3.2.1 3.2.2 3.2.3 3.9.1 COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR 1.0 CORE OPERATING LIMITS REPORT Page 4 of13 This Core Operating Limits Report (COLR) for Salem Unit 2 Cycle 23 has been prepared in accordance with the requirements of Technical 6.9 .1.9. The Technical Specifications affected by this report are listed below along with the NRC-approved methodologies used to develop and/or determine COLR parameters identified in Technical Specifications.
NRC Approved COLR Methodology Technical Specifications COLR Parameter Section (Section 3.0 Number) Moderator Temperature Coefficient MTC 2.1 3.1, 3.6 Control Rod Insertion Limits Control Rod Insertion Limits 2.2 3.1, 3.6 Axial Flux Difference AFD 2.3 3.1, 3.2, 3.6 3.1, 3.3, 3.4, 3.5, 3.6, 3.7, Heat Flux Hot Cham1el Factor-F 0 (z) Fo(z) 2.4 3.8 Nuclear Enthalpy Rise Hot Cham1el Factor -FNAH FNAH 2.5 3.1, 3.5, 3.6, 3.8 Boron Concentration Boron Concentration 2.6 3.1, 3.6 COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR Page 5 of13 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.
These limits have been developed using the NRC-approved methodologies specified in Teclmical Specification 6.9.1.9 and in Section 3.0 of this report. 2.1 Moderator Temperature Coefficient (Specification 3 .1.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are: The BOL/ARO/HZP-MTC shall be less positive than or equal to 0 .6.klkfDF.
The EOLIARO/RTP-MTC shall be less negative than or equal to -4.4x10" 4 .6.k/k/°F.
2.1.2 The MTC Surveillance limit is: The 300 ppm/ARO/RTP-MTC should be less negative than or equal to -3.7x10" 4 .6.k/k/°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR 2.2 Control Rod Insertion Limits (Specification 3 .1.3 .5) Page 6 of13 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1. 2.3 Axial Flux Difference (Specification 3 .2.1) [Constant Axial Offset Control (CAOC) Methodology]
2.3 .1 The Axial Flux Difference (AFD) target band shall be ( +6%, -9% ). 2.3.2 The AFD Acceptable Operation Limits are provided in Figure 2. 2.4 Heat Flux Hot Channel Factor-FQ(z) (Specification 3.2.2) [Fxy Methodology]
FQRTP FQ(z) :::; p
- K(z) for P > 0.5 FQRTP FQ(z) :::;
0.5 where
P THERMAL POWER RATED THERMAL POWER 2.4.1 FlTP = 2.40 2.4.2 K(z) is provided in Figure 3. where: from BOL to 12000 MWD/MTU Fx/TP = 2. 03 for unrodded upper core planes 1 through 6 1. 83 for unrodded upper core planes 7 through 8 1. 7 4 for unrodded upper core planes 9 through 18 1. 80 for unrodded upper core planes 19 through 31 1.82for unrodded lower core planes 32 through 43 1. 83 for unrodded lower core planes 44 through 53 1.90for unrodded lower core planes 54 through 55 2. 03 for unrodded lower core planes 56 through 61 2.13 for core planes containing Bank D control rods PFxy 0.3 COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR Page 7 of13 where: from 12000 MWD/MTU to EOL Fx/TP = 1. 98 for unrodded upper core planes 1 through 6 1. 80 for unrodded upper core planes 7 through 8 1. 77 for unrodded upper core planes 9 through 18 1. 9 2 for unrodded upper core planes 19 through 31 1.95 for unrodded lower core planes 32 through 43 1. 79 for unrodded lower core planes 44 through 53 1. 84 for unrodded lower core planes 54 through 55 1.95 for unrodded lower core planes 56 through 61 2.13 for core planes containing Bank D control rods PFxy = 0.3 2.4.4 If the Power Distribution Monitoring System (PDMS) is used for core power distribution surveillance and is OPERABLE, as defined in Technical Specification 3.3.3.14, the uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(z) shall be calculated by the following formula: UFQ =(1.0+ UQ J*Ve 100.0 where: UQ = Uncetiainty for power peaking factor as defined in equation 5-19 of Analytical Method 3.5. u. =Engineering uncertainty factor. = 1.03 Note: UFQ = PDMS Surveillance Repmi Core Monitor Fxy Uncertainty in %. 2.4.5 If the INCORE movable detectors are used for core power distribution surveillance, the uncertainty, UFQ, to be applied to the Heat Flux Hot Channel Factor FQ(z) shall be calculated by the following formula: UFQ =Vqu*Vc where: Uqu =Base FQ measurement uncetiainty.
= 1.05 u. = Engineering uncertainty factor. = 1.03 COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR 2.5 Nuclear Enthalpy Rise Hot Channel Factor-FN (Specification 3.2.3) F" Llli = F LlliRTP [1.0 + PFAH (1.0-P)] where: P THERMAL POWER RATED THERMAL POWER 1.65 2.5.2 PFAH = 0.3 Page 8 ofl3 2.5.3 If the Power Distribution Monitoring System (PDMS) is used for core power distribution surveillance and is OPERABLE, as defined in Teclmical Specification 3.3.3.14, the uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, FN AH, shall be the greater of 1.04 or as calculated by the following formula: UMI UFM! = 1.0+--100.0 where: Ut;H = Uncertainty for enthalpy rise hot cham1el factor as defined in equation 5-19 of Analytical Method 3.5. 2.5.4 If the INCORE movable detectors are used for core power distribution surveillance, the uncertainty, UFAH, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor FN t>H shall be calculated by the following formula: where: UMHm =Base F t>H measurement uncertainty.
= 1.04 COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR Page 9 ofl3 2.6 Boron Concentration (Specification 3.9 .1) A Mode 6 boron concentration, maintained at or above 2222 ppm, in the Reactor Coolant System, the fuel storage pool, the refueling canal, and the refueling cavity ensures the most restrictive of the following reactivity conditions is met: a) A K-effective (Keff) of 0.95 or less at All Rods In (ARI), Cold Zero Power (CZP) conditions with a 1%
uncertainty added. b) A Keff of 0.99 or less at All Rods Out (ARO), CZP conditions with a 1%
uncertainty added. c) A boron concentration of greater than or equal to 2000 ppm, which includes a 50 ppm conservative allowance for uncertainties.
3.0 ANALYTICAL
METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents.
3.1 WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985 (Westinghouse proprietary).
Methodology for Specifications listed in 6.9.1.9.a.
Approved by Safety Evaluation dated May 28, 1985. 3.2 WCAP-8385, Power Distribution Control and Load Following Procedures -Topical Report, September 1974 (Westinghouse proprietary).
Methodology for Specification 3/4.2.1 Axial Flux Difference.
Approved by Safety Evaluation dated January 31, 1978. 3.3 WCAP-10054-P-A, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, August 1985 (Westinghouse proprietary).
Methodology for Specification 3/4.2.2 Heat Flux Hot Channel Factor. Approved for Salem by NRC letter dated August 25, 1993.
COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR Page 10 of13 3.4 WCAP-10266-P-A, Revision 2, The 1981 Version of the Westinghouse ECCS Evaluation Model Using the BASH Code, March 1987 (Westinghouse proprietary).
Methodology for Specification 3/4.2.2 Heat Flux Hot Cham1el Factor. Approved by Safety Evaluation dated November 13, 1986. 3.5 WCAP-12472-P-A, BEACON -Core Monitoring and Operations Support System, August 1994 (Westinghouse proprietary).
Approved by Safety Evaluation dated February 16, 1994. 3.6 CENPD-397-P-A, Revision 01, Improved Flow Measurement Accuracy Using Crossflow Ultrasonic Flow Measurement Technology, May 2000. Approved by Safety Evaluation dated March 20, 2000. 3.7 WCAP-10054-P-A, Addendum 2, Revision 1, Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model, July 1997 (Westinghouse proprietary).
Approved by Safety Evaluation dated August 12, 1996. 3.8 WCAP-12472-P-A, Addendum 1-A, BEACON Core Monitoring and Operations Support System, January 2000 (Westinghouse proprietary).
Approved by Safety Evaluation dated September 30, 1999.
4.0 REFERENCES
- 1. Salem Nuclear Generating Station Unit No.2, Amendment No. 297, Renewed License No. DPR-75, Docket No. 50-311.
COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR Page 11 of13 240 220 200 j 180 160 ... 140 41 ... (fj ...... z 120 0 l= 100 a. )!:: z 80 <t en 5 60 rt 40 0 20 0 FIGURE 1 ROD BANK INSERTION LIMITS VS. THERMAL POWER --% --I / 7. ! v 1 7' 1o.o122s 1 I ., I '1 BankB I / / ! I .*r----1 .. I.Q.Jru / !1ool11o II . / I / leankC I / I / 7 i / I / / I / I I / / I /leankD I I ! / / v i i I ! v I / I i v I / I v i I I 0 10 20 30 40 50 60 10 80 90 100 PERCENT OF RA TEO THERMAL POWER(%)
COLRSALEM2 Revision 7 March 2017 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR Page 12 of13 ,.-., i5: 0 A-< ........ ro 5 ...s:::: E-< "0 (!) '+-< 0 'i:l (!) (.) b) A-< 100 80 60 40 20 0 FIGURE2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER k-11,90j 1 (11,90)1 I \ UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION ACCEPTABLE OPERATION I \ I i\ 1(-31,50)1 1 (31,5o] 40 20 -10 0 10 20 30 40 Flux Difference
(% Delta I) 50 COLRSALEM2 Revision 7 March 2017 1.2 1.0 g 0.8 0.6 I 0 0.4 z 0.2 0.0 0 PSEG Nuclear LLC SALEM UNIT 2 CYCLE 23 COLR FIGURE 3 Page 13 of13 K(Z)-NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT -FQ K(Z) Height (FT) ----2.40 1.0 0.0 2.40 1.0 6.0 2.22 0.925 12.0 2 4 6 8 10 12 CORE HEIGHT (FEET)