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Category:Fuel Cycle Reload Report
MONTHYEARRA-23-0118, Cycle 29, Revision 1, Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) RA-20-0313, Cycle 28, Revision 0, Core Operating Limits Report (COLR)2020-09-30030 September 2020 Cycle 28, Revision 0, Core Operating Limits Report (COLR) MNS-18-023, Cycle 26, Revision 1 Core Operating Limits Report2018-03-31031 March 2018 Cycle 26, Revision 1 Core Operating Limits Report MNS-17-042, Cycle 26, Revision 0, Core Operating Limits Report2017-10-0909 October 2017 Cycle 26, Revision 0, Core Operating Limits Report MNS-16-025, Core Operating Limits Report2016-03-23023 March 2016 Core Operating Limits Report ML13270A0872013-09-16016 September 2013 Response to Request for Additional Information Regarding the Core Operating Limits Report for Cycle 23 ML13114A2922013-04-10010 April 2013 Cycle 23, Revision 0, Core Operating Limits Report ML12055A2892012-02-14014 February 2012 Cycle 22, Revision 3, and Unit 2, Cycle 21, Revision 2, Core Operating Limits Report ML1011004612010-04-14014 April 2010 Cycle 21, Revision 0, Core Operating Limits Report ML0930001202009-10-20020 October 2009 Cycle 20, Revision 2, Core Operating Limits Report ML0902201992009-01-0707 January 2009 Submittal of Core Operating Limits Report, Cycle 20, Revision 1 ML0709406842007-03-27027 March 2007 Cycle 19, Revision 30 Core Operating Limits Report (COLR) ML0623401882006-08-14014 August 2006 Cycle 18, Rev. 29, Core Operating Limits Report (COLR) ML0409102582004-03-24024 March 2004 Cycle 17, Revision 27, Core Operating Limits Report (COLR) ML0406506582004-02-23023 February 2004 Cycle 16 Revision 26 Core Operating Limits Report (COLR) and Unit 2, Cycle 16, Revision COLR ML0329404982003-10-0707 October 2003 Cycle 16 Core Operating Limits Report (COLR) ML0302305012002-12-30030 December 2002 Inservice Inspection Report End of Cycle Refueling Outage ML0230304602002-10-21021 October 2002 Core Operating Limits Report (COLR) ML0208703442002-03-20020 March 2002 Core Operating Limits Report (Colr), Revision 21, Cycle 15 2023-05-03
[Table view] Category:Letter
MONTHYEARIR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
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Duke GARY R. PETERSON PPowere Vice President McGuire Nuclear Station A Duke Energy Company Duke Power MGOIVP / 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters @duke-energy. corn October 7, 2003 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
McGuire Nuclear Station, Docket No.50-369 Unit 1, Cycle 16 Core Operating Limits Report (COLR)
Pursuant to McGuire Technical Specification 5.6.5.d, please find enclosed Revision 25 to the McGuire Unit 1, Cycle 16 Core Operating Limits Report (COLR).
Questions regarding this submittal should be directed to Kay Crane, McGuire Regulatory Compliance at (7N) 37*406.
Attachment 4a00 www. duke-energy. corn
U. S. Nuclear Regulatory Commission October 7, 2003 Page 2 cc: Mr. R. E. Martin, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Luis Reyes, Regional Administrator U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30323 Mr. Joe Brady Senior Resident Inspector McGuire Nuclear Station
k_. MCEI-040046 Page I of 29 Revision 25 McGuire Unit 1 Cycle 16 Core Operating Limits Report Revision 25 '
September 2003 Calculation Number: MCC-1553.05-00-0371, Rev. I Duke Power Company Date Prepared By:
Checked By: 9ib//O3 Checked By: L4(-E q 3-S o 3 I \°_/- At, Approved By: ?./ -/1°3 QA Condition 1 The information presented in this report has been prepared and issued in accordance with McGuire Technical Specification 5.6.5.
MCEI-040046 Page la of 29 Revision 25 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Ho 7ka ,
Date: f /9/
(Sponsor)
CATAWBA Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:
RES (Electrical Only) Inspected By/Date:
RES (Reactor) Inspected By/Date:
5o E]
MOD Inspected By/Date:
El:
Other ( Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) El Inspected By/Date:
RES (Electrical Only) El Inspected By/Date:
RES (Reactor) El Inspected By/Date:
MOD El Inspected By/Date:
Other( ) El Inspected By/Date:
MCGUIRE I MCQUIRE Inspection Waived MCE (Mechanical & Civil) IZI Inspected By/Date:
RES (Electrical Only) El Inspected By/Date:
RES (Reactoi) -- - Inspected By/Date:
MOD 191 Inspected By/Date:
Other ( Inspected By/Date:
MCEI-040046 Page 2 of 29 Revision 25 McGuire 1 Cycle 16 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 25 Revision 25 to the McGuire Unit 1 COLR contains new end-of-cycle moderator temperature coefficient limits. These limits should be implemented within two weeks of issuance. This revision also updates the methodology reference list included in COLR Section 1.1 to reflect recent approvals to NRC approved methods.
MCEI-040046 Page 3 of 29 Revision 25 McGuire 1 Cycle 16 Core Operating Limits Report REVISION LOG Revision Effective Date Effective Pages COLR Revisions 0-3 Superseded N/A MIC09 Revisions 4-8 Superseded N/A MIC10 Revisions 9-11 Superseded N/A MICI I Revisions 12-15 Superseded N/A MIC12 Revisions 16-17 Superseded N/A MIC13 Revision 18-20 Superseded N/A MIC14 Revision 21-23 Superseded N/A MICI5 Revision 24 August 30, 2002 5, 6, 10-29 MIC16 (Original Issue)
Revision 25 September 3, 2003 1; la, 24, 7-9 MIC16 (Revision I)
MCEI-040046 Page 4 of 29 Revision 25 McGuire I Cycle 16 Core Operating Limits Report INSERTION SHEET FOR REVISION 25 Remove.pages Insert Rev. 25 pages Pages l - 4, 7, 8 and 9 Pages l, la - 4, 7, 8 and 9
MCEI-0400-46 Page 7 of 29 Revision 25 McGuirc I Cycle 16 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 7. DPC-NE-300IPA, "Multidimensional Reactor Transients and SafetyAnalysis Physics Parameter Methodology," (DPC Proprietary).
Revision 0 Report Date: November 1991
- 8. DPC-NE-3002A, ."FSAR Chapter 15 System Transient Analysis Methodology".
Revision 4 SERDate: April 6,2001
- 9. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-0 ," (DPC Proprietary).
Revision I SER Date: February 20, 1997
- 10. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
Revision 1 SER Date: November 7, 1996
- 11. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
Revision 0 SER Date: April 3, 1995
- 12. DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report," (DPC Proprietary).
Revision 2 SER Date: December 18, 2002
- 13. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P."
Revision 1
-SER Date; April 26, 1996
- 14. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."
Revision 2 SER Date: June 24, 2003
MCEI-0400A6 Page 8 of 29 Revision 25 McGuire 1 Cycle 16 Core Operating Limits Report 1.1 Analytical Methods (continued)
- 15. DPC-NE-201 I PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
Revision 1.
SER Date: October 1, 2002 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 NRC approved methodologies specified in Section 1.1.
2.1 Requirements for Operational Mode 6 The following condition is Tequired for operational mode 6.
2.1.1 The Reactivity Condition requirement for operational mode 6 is that kd must be less than, or equal to 0.95.
2.2 Shutdown Margin - SDM (TS 3.1.1, TS 3.1.4, TS 3.1.5, TS 3.1.6 and TS 3.1.8) 2.2.1 For TS 3.1.1, SDM shall be> 1.3% AK/K in mode 2 with k-eff< 1.0 and in modes 3 and 4.
2.2.2 For TS 3.1.1, SDM shall be > 1.0% AK/K in mode 5.
2.2.3 For TS 3.1.4, SDM shall be > 1.3% AK/K in modes 1 and 2.
2.2.4 For TS 3.1.5, SDM shall be > 1.3% AK/K in mode I and mode 2 with any control bank not fully inserted.
2.2.5 For TS 3.1.6, SDM shall be > 1.3% AK/K in mode 1 and mode 2 with K-eff> 1.0.
2.2.6 For TS 3.1.8, SDM shall be > 1.3% AK/K in mode 2 during physics testing.
MCEI-040046 Page 9 of 29 Revision 25 McGuire I Cycle 16 Core Operating Limits Report 2.3 Moderator Temperature Coefficient - MTC (TS 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the upper limits shown in Figure 1. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/0 F.
The EOC, ARO, RTP MTC shall be less negative than the -4.3E-04 AK/K/ 0 F lower MTC limit.
2.3.2 The 300 PPM MTC Surveillance Limit is:
The measured 300 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to -3.65E-04 AK/K/F.
2.3.3 The 60 PPM MTC Surveillance Limit is:
The 60 PPM ARO, equilibrium RTP MTC shall be less negative than or equal to
-4.125E-04 AK/K/ 0 F.
Where, BOC = Beginning of Cycle (Burnup corresponding to the most positive MTC.)
EOC = End of Cycle ARO = All Rods Out HZP = Hot Zero Power RTP = Rated Thermal Power PPM = Parts per million (Boron) 2.4 Shutdown Bank Insertion Limit (TS 3.1.5) 2.4.1 Each shutdown bank shall be withdrawn to at least 226 steps. Shutdown banks are withdrawn in sequence and with no overlap.
2.5 Control Bank Insertion Limits (TS 3.1.6) 2.5.1 Control banks shall be within the insertion, sequence, and overlap limits shown in Figure 2. Specific control bank withdrawal and overlap limits as a function of the fully withdrawn position are shown in Table 1.