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| #REDIRECT [[RA-08-011, Oyster Creek, Response to Request for Additional Information - Exelon/Amergen Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Impro]] | | {{Adams |
| | | number = ML083400211 |
| | | issue date = 12/02/2008 |
| | | title = Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System |
| | | author name = Castell C |
| | | author affiliation = Progress Energy Carolinas, Inc |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NRR |
| | | docket = 05000261 |
| | | license number = DPR-023 |
| | | contact person = |
| | | case reference number = RNP-RA-08-0116 |
| | | document type = Fuel Cycle Reload Report, Letter type:RA |
| | | page count = 5 |
| | }} |
| | |
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| | {{#Wiki_filter: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}} |
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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 type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 22023-03-24024 March 2023 Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-23-0027, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 20222023-01-30030 January 2023 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2022 RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0347, Transmittal of Core Operating Limits Report2022-12-0202 December 2022 Transmittal of Core Operating Limits Report RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022 Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary) RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0179, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2022-06-15015 June 2022 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) RA-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-02-05
[Table view] |
Text
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