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Category:Fuel Cycle Reload Report
MONTHYEARRA-22-0347, Transmittal of Core Operating Limits Report2022-12-0202 December 2022 Transmittal of Core Operating Limits Report RA-20-0374, Transmittal of Core Operating Limits Report for Cycle 332020-11-24024 November 2020 Transmittal of Core Operating Limits Report for Cycle 33 RNP-RA/18-0060, Transmittal of Core Operating Limits Report2018-10-17017 October 2018 Transmittal of Core Operating Limits Report RNP-RA/17-0055, Transmittal of Core Operating Limits Report for Cycle 312017-07-26026 July 2017 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/17-0021, Transmittal of Core Operating Limits Report2017-03-13013 March 2017 Transmittal of Core Operating Limits Report RNP-RA/17-0050, Transmittal of Core Operating Limits Report for Cycle 312016-06-27027 June 2016 Transmittal of Core Operating Limits Report for Cycle 31 RNP-RA/15-0048, Transmits Rev 0 to the Core Operating Limits Report (COLR) for Cycle 302015-06-16016 June 2015 Transmits Rev 0 to the Core Operating Limits Report (COLR) for Cycle 30 RNP-RA/13-0110, Transmittal of Core Operating Limits Report, Cycle 292013-11-21021 November 2013 Transmittal of Core Operating Limits Report, Cycle 29 RNP-RA/12-0014, Transmittal of Core Operating Limits Report2012-03-0101 March 2012 Transmittal of Core Operating Limits Report RNP-RA/11-0091, Transmittal of Core Operating Limits Report for Cycle 272011-10-28028 October 2011 Transmittal of Core Operating Limits Report for Cycle 27 RNP-RA/10-0043, Submittal of Revision 26 to FMP-001, Core Operating Limits Report (COLR)2010-05-12012 May 2010 Submittal of Revision 26 to FMP-001, Core Operating Limits Report (COLR) RA-08-0116, Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System2008-12-0202 December 2008 Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System RNP-RA/08-0112, Transmittal of Core Operating Limits Report for Cycle 262008-11-0303 November 2008 Transmittal of Core Operating Limits Report for Cycle 26 RNP-RA/08-0103, Transmittal of Rev. 2 to Core Operating Limits Report for Cycle 252008-09-22022 September 2008 Transmittal of Rev. 2 to Core Operating Limits Report for Cycle 25 RNP-RA/08-0079, Transmittal of Core Operating Limits Report2008-07-0202 July 2008 Transmittal of Core Operating Limits Report RNP-RA/07-0037, Transmittal of Core Operating Limits Report2007-04-0909 April 2007 Transmittal of Core Operating Limits Report RNP-RA/07-0005, Transmittal of Core Operating Limits Report for Cycle 242007-01-11011 January 2007 Transmittal of Core Operating Limits Report for Cycle 24 RNP-RA/04-0059, Transmittal of Core Operating Limits Report2004-05-18018 May 2004 Transmittal of Core Operating Limits Report RNP-RA/04-0006, Transmittal of Core Operating Limits Report for Cycle 222004-01-0707 January 2004 Transmittal of Core Operating Limits Report for Cycle 22 2022-12-02
[Table view] Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 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 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000261/20230012023-05-0202 May 2023 Integrated Inspection Report 05000261/2023001 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 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000261/20220062023-03-0101 March 2023 Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23041A2272023-02-13013 February 2023 2022 Q4 Robinson_Workflow Final ML22329A2982023-01-19019 January 2023 Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16 ML22294A0922022-12-15015 December 2022 Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML22339A1362022-12-0101 December 2022 2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant ML22322A1322022-11-18018 November 2022 301, NRC Operator License Examination Report & Cover Letter Merged 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 05000261/20220032022-11-0303 November 2022 Integrated Inspection Report 05000261 2022003 IR 05000261/20224022022-10-19019 October 2022 Security Baseline Inspection Report 05000261/2022402 IR 05000261/20220102022-09-26026 September 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010 IR 05000261/20223012022-09-23023 September 2022 301 Operator License Exam Approval Letter (05000261/2022301) ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000261/20220052022-08-26026 August 2022 Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final IR 05000261/20214042022-08-10010 August 2022 Reissue - H.B. Robinson Steam Electric Plant Security Baseline Inspection Report 05000261/2021404 IR 05000261/20220022022-08-0909 August 2022 Integrated Inspection Report 05000261 2022002, 07200060 2022001 and Exercise of Enforcement Discretion ML22213A0682022-08-0505 August 2022 Request for Withholding Information from Public Disclosure for H. B. Robinson Steam Electric Plant, Unit 2 ML22193A2122022-08-0404 August 2022 Request of Alternatives to ASME Code Section XI Subsection IWE Requirements for Containment Inspections ML22159A2952022-08-0303 August 2022 Issuance of Amendment No. 271 Regarding Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves IR 05000261/20220112022-07-19019 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000261/2022011 ML22167A1702022-07-14014 July 2022 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors 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 ML22125A1942022-05-12012 May 2022 Request for Withholding Information from Public Disclosure for H.B. Robinson Steam Electric Plant, Unit 2 IR 05000261/20220012022-05-0202 May 2022 Integrated Inspection Report 05000261/2022001 IR 05000261/20224012022-04-19019 April 2022 Security Baseline Inspection Report 05000261/2022401 ML22098A2262022-04-11011 April 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22083A0032022-03-29029 March 2022 Closeout of Bulletin 2012 01, Design Vulnerability in Electric Power System IR 05000261/20210062022-03-0202 March 2022 Annual Assessment Letter for H.B. Robinson Steam Electric Plant Unit 2 (Report No. 05000261/2021006) 2024-01-08
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Pro s E10 CFR 50.46(a)(3)(ii) e~g Progress Energy Serial: RNP-RA/08-01 16 DEC 0 2 2008 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 REPORT OF CHANGES TO OR ERRORS DISCOVERED IN AN ACCEPTABLE LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL APPLICATION FOR THE EMERGENCY CORE COOLING SYSTEM Ladies and Gentlemen:
In accordance with the provisions of the Code of Federal Regulations, Title 10, Part 50.46 (10 CFR 50.46), Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. (PEC), is submitting the attached report of changes to and errors discovered in an acceptable Loss-of-Coolant Accident (LOCA) evaluation model (EM) for the Emergency Core Cooling System at the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2. The applicable LOCA EMs are referenced in the HBRSEP, Unit No. 2, Core Operating Limits Report. Changes to or errors discovered in EMs and EM applications were previously reported to the Nuclear Regulatory Commission by letter dated December 13, 2007.This submittal satisfies both the annual notification and the notification of a significant change as required by 10 CFR 50.46(a)(3)(ii).
For the Small Break LOCA (SBLOCA), the non-significant changes and error corrections in the Framatome-ANP EXEM PWR SBLOCA EM since the last annual report are provided in Attachment I. The effects of these non-significant changes and error corrections on HBRSEP, Unit No. 2, peak cladding temperature (PCT) estimates are also summarized in Attachment I. There were no significant changes or errors for the SBLOCA.For the Large Break LOCA (LBLOCA), HBRSEP, Unit No. 2, is employing for the first time the Realistic LBLOCA model "EMF-2103(P)(A), Revision 0," as the EM of record with the startup for Operating Cycle No. 26 (Mode 4 entered on November 2, 2008). The change to EMF-2103(P)(A), Revision 0, has resulted in a significant change in the calculated PCT from the previously used EM.The cumulative change is summarized in Attachment I. This change in EM results in a new baseline value for PCT for the LBLOCA. The cumulative impact of subsequent changes/errors will be compared to this new baseline value. There is no reanalysis or other corrective action planned because the changes result from changing to another approved methodology, and the changes and errors result in a net improvement in margin to PCT limits. The cumulative impact of changes will continue to be tracked.Progress Energy Carolinas, Inc.Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550 , -
United States Nuclear Regulatory Commission Serial: RNP-RA/08-0116 Page 2 of 2 License Amendment No. 209, dated September 20, 2006, provided approval to use EMF-2103(P)(A), Revision 0, at HBRSEP, Unit No. 2. In the March 3, 2005, amendment request, PEC submitted a Realistic LBLOCA analysis using the EMF-2103(P)(A), Revision 0, methodology.
That analysis showed a PCT result of 1952'F. Changes and error corrections have been made to that analysis, resulting in a calculated PCT of 1885'F. The applicable changes and error corrections are also provided in Attachment I. These changes have not been previously reported, because the analysis submitted on March 3, 2005, was not being used as the analysis of record.The latest PCT estimates for the LBLOCA and SBLOCA are included in Attachment II.If you have any questions concerning this matter, please contact me at (843) 857-1626.Sincerely, Curt Castell Supervisor
-Licensing/Regulatory Programs rac Attachments:
I. Report of Changes/Errors in Loss-of-Coolant Accident Evaluation Models for the Emergency Core Cooling System II. Peak Cladding Temperature Estimates c: L. A. Reyes, NRC, Region II M. G. Vaaler, NRC, NRR NRC Resident Inspector, HBRSEP United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/08-0116 Page 1 of 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 REPORT OF CHANGES/ERRORS IN LOSS-OF-COOLANT ACCIDENT EVALUATION MODELS FOR THE EMERGENCY CORE COOLING SYSTEM This report provides an estimate of the effect on peak cladding temperature (PCT) of changes and error corrections in the Loss-of-Coolant Accident (LOCA) evaluation models (EMs) and EM applications for the Emergency Core Cooling System (ECCS) at the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, covering the period of November 25, 2007, through November 11, 2008.Large Break Loss-of-Coolant Accident (LBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT (OF)Change in evaluation methodology to EMF-2103(P)(A), Revision 0,"Realistic Large Break Loss-of-Coolant Accident Methodology for -133'F(')Pressurized Water Reactors," Framatome ANP, April 2003, including changes and error corrections detailed below Cumulative Impact -133 0 F (1) This represents the total change in PCT resulting from the methodology change and subsequent changes and error corrections.
The following provides the changes from the Realistic LBLOCA analysis result of a PCT of 1952 OF submitted in the March 3, 2005, license amendment request, which were previously not reported because this model was not being used as the analysis of record: CHANGED CONDITION PCT IMPACT (OF)S-RELAP5 Choking Model Sensitivity
+2 0 F ICECON calculation of steam-to-pool condensation 0°F Legacy Point Kinetics error in S-RELAP5 -50.1 0 F Mixture Level error in S-RELAP5 -18.9 0 F Cross-flow junction area in RLBLOCA model 0°F Cold leg condensation underpredicted after accumulator injection 0°F Cumulative Impact -67 0 F United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/08-0116 Page 2 of 2 Small Break Loss-of-Coolant Accident (SBLOCA) Evaluation Model CHANGED CONDITION PCT IMPACT (OF)March 3, 2008 -RELAP error in reactor kinetics coding -8 0 F Cumulative Impact -8 0 F United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/08-0116 Page 1 of 1 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PEAK CLADDING TEMPERATURE ESTIMATES The current peak cladding temperature (PCT) estimates associated with Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) evaluation models are listed below. These estimates include the cumulative effects of significant and non-significant error corrections and evaluation model changes through November 11, 2008.Event PCT (OF)Large Break LOCA, ECCS Injection Mode 1885 Small Break LOCA, ECCS Injection Mode 1671