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Category:Report
MONTHYEARRA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 242022-06-0909 June 2022 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24 RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 252021-06-21021 June 2021 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25 RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data2021-06-0707 June 2021 Cycle 24 Mellla+ Eigenvalue Tracking Data RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)2021-02-24024 February 2021 Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1) RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask2020-11-16016 November 2020 10 CFR 71.95 Report on the 3-60B Cask RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-12-31031 December 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-10-23023 October 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 22019-08-15015 August 2019 Pressure and Temperature Limits Report for Unit Nos. 1 and 2 RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-07-0202 July 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0131, Technical Requirements Manual, Revision 662018-08-13013 August 2018 Technical Requirements Manual, Revision 66 ML18249A1592018-08-13013 August 2018 Technical Requirements Manual, Revision 73 RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018 Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. ML16223A7252016-08-17017 August 2016 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Phase 2 of Order EA-13-109 (Severe Accident Capable Hardened Events) CAC Nos. MF4467 and MF4468) ML18250A0022016-08-11011 August 2016 Technical Requirements Manual, Revision 70 ML18250A0032016-08-11011 August 2016 Technical Requirements Manual, Revision 63 ML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. ML16041A4352016-03-0101 March 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force ML16257A4062015-12-31031 December 2015 ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. ML15275A2902015-09-30030 September 2015 Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain.2015-07-31031 July 2015 ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. ML16257A4082015-07-31031 July 2015 ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR 2014-7395)2015-01-13013 January 2015 Enclosure 3 - Areva Operability Assessment. (CR #2014-7395) BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident2014-12-18018 December 2014 Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident ML14297A2662014-10-24024 October 2014 Record of Review, Brunswick Steam Electric Plant, Units 1 and 2, LAR Attachment U- Table U-1 Internal Events PRA Peer Review- Facts and Observations (F&Os), 10/24/14 BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-09-0404 September 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes2014-08-14014 August 2014 Report of 10 CFR 50.59 Evaluations and Commitment Changes ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13220A0902013-11-22022 November 2013 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A5922013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Brunswick Steam Electric Plant, Units 1 and 2, TAC Nos.: MF0975 and MF0976 ML13277A0412013-09-19019 September 2013 Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML16257A4072013-05-31031 May 2013 ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2013-02-28028 February 2013 Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact2013-01-14014 January 2013 Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact ML13031A0112013-01-11011 January 2013 Engineering Information Record, Document No. 51-9196989-000, Supplemental Information for Brunswick SAFLIM3D Submittal: Impact of Assemblies Outside Existing Channel Bow Fast Fluence Gradient Database BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-01332012-11-27027 November 2012 Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2012-11-27027 November 2012 Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation2012-11-14014 November 2012 Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation ML12321A3192012-11-0101 November 2012 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. ML12065A3802012-03-26026 March 2012 Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-00312012-02-29029 February 2012 Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 ML12076A0632012-02-17017 February 2012 Areva Document No. 51-9177317-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology, Engineering Information Record, Enclosure 8 to BSEP 12-0031 2022-06-09
[Table view] Category:Technical
MONTHYEARRA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data2022-05-25025 May 2022 Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data2021-06-0707 June 2021 Cycle 24 Mellla+ Eigenvalue Tracking Data RA-20-0347, 10 CFR 71.95 Report on the 3-60B Cask2020-11-16016 November 2020 10 CFR 71.95 Report on the 3-60B Cask RA-19-0411, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-10-23023 October 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 22019-08-15015 August 2019 Pressure and Temperature Limits Report for Unit Nos. 1 and 2 RA-19-0243, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-07-0202 July 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-19-0240, Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request2019-05-29029 May 2019 Response to Request for Additional Information Regarding Advanced Framatome Methodologies License Amendment Request RA-19-0139, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies2019-03-18018 March 2019 Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0100, Request for License Amendment Regarding Application of Advanced Framatome Methodologies2018-10-11011 October 2018 Request for License Amendment Regarding Application of Advanced Framatome Methodologies RA-18-0131, Technical Requirements Manual, Revision 662018-08-13013 August 2018 Technical Requirements Manual, Revision 66 ML18249A1592018-08-13013 August 2018 Technical Requirements Manual, Revision 73 RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-05-29029 May 2018 Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML16287A4222016-09-26026 September 2016 FS1-0028339 Revision 1.0, Brunswick, Unit 1, Cycle 21 and Unit 2 Cycle 23 MELLLA SLMCPR Analyses with SAFLIM30 Methodology. ML18250A0032016-08-11011 August 2016 Technical Requirements Manual, Revision 63 ML18250A0022016-08-11011 August 2016 Technical Requirements Manual, Revision 70 ML16257A4112016-07-31031 July 2016 DUKE-0B21-1104-000(NP), Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus. ML16257A4062015-12-31031 December 2015 ANP-3106(NP), Revision 2, Brunswick Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for Atrium 10XM Fuel for Mellla+ Operation. ML15275A2902015-09-30030 September 2015 Areva, Inc., - ANP-3397NP, Revision 0, Brunswick, Unit 2, Atrium 11 Lead Test Assemblies Design & Licensing Summary Report. BSEP 16-0056, ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain.2015-07-31031 July 2015 ANP-3108(NP), Revision 1, Applicability of Areva BWR Methods to Brunswick Extended Power Flow Operating Domain. ML16257A4082015-07-31031 July 2015 ANP-3105(NP), Revision 1, Brunswick Units 1 and 2 LOCA Break Spectrum Analysis for Atrium 10XM Fuel for Mellla+ Operation. ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 BSEP 14-0028, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi A2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML13220A0902013-11-22022 November 2013 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A5922013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Brunswick Steam Electric Plant, Units 1 and 2, TAC Nos.: MF0975 and MF0976 ML16257A4072013-05-31031 May 2013 ANP-3013(NP), Revision 0, Brunswick Unit 1 Cycle 19 Fuel Cycle Design Mellla+ Operating Domain. BSEP 13-0002, Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact2013-01-14014 January 2013 Technical Data Record, 12-9197120-000, Brunswick SAFLIM3D LAR Support - Calculation Error Impact ML13031A0112013-01-11011 January 2013 Engineering Information Record, Document No. 51-9196989-000, Supplemental Information for Brunswick SAFLIM3D Submittal: Impact of Assemblies Outside Existing Channel Bow Fast Fluence Gradient Database BSEP 12-0133, Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-01332012-11-27027 November 2012 Document No. 51-9195058-000, Areva Input to Process Energy: Follow-Up to SAFLIM3D LAR Request for Additional Information 3, Enclosure 3 to BSEP 12-0133 ML12321A3192012-11-0101 November 2012 1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2. ML12065A3802012-03-26026 March 2012 Request to Reinitiate Section 7 Consultation for Atlantic Sturgeon at Brunswick Steam Electric Plant, Units 1 and 2 BSEP 12-0031, Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-00312012-02-29029 February 2012 Areva Document ANP-3086(NP), Brunswick Units 1 and 2 SLMCPR Operability Assessment Critical Power Correlation for Atrium 10XM Fuel - Improved K-factor Model, Enclosure 20 to BSEP 12-0031 ML12076A0632012-02-17017 February 2012 Areva Document No. 51-9177317-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology, Engineering Information Record, Enclosure 8 to BSEP 12-0031 ML12076A0642012-02-17017 February 2012 Areva Document No. 51-9177315-000, Brunswick Unit 1 Cycle 19 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 11 to BSEP 12-0031 ML12076A0852012-02-17017 February 2012 Areva Document No. 51-9177314-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology, Enclosure 14 to BSEP 12-0031 ML12076A0862012-02-17017 February 2012 Areva Document No. 51-9177316-000, Brunswick Unit 2 Cycle 20 SLMCPR Analysis with SAFLIM3D Methodology - Operability Assessment, Enclosure 17 to BSEP 12-0031 BSEP 12-0040, ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis.2011-12-31031 December 2011 ANP-3061(NP), Revision 0, Brunswick, Unit 1, Cycle 19 Reload Safety Analysis. ML12100A0872011-05-31031 May 2011 ANP-2989(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. BSEP 11-0031, Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR2011-03-31031 March 2011 Areva Report ANP-2992NP, Revision 0, Areva Response to Additional RAI on the Brunswick RODEX4 LAR ML1111010202011-03-24024 March 2011 Reactor Pressure Vessel Flaw Evaluation BSEP 10-0141, ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars.2010-12-16016 December 2010 ANP-2978NP, Rev. 0, Areva Responses to RAIs on the Atrium 10XM Compliance Audit and Brunswick Lars. BSEP 10-0118, ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20.2010-10-12012 October 2010 ANP-2950NP, Revision 0, Atrium 10XM Fuel Rod Thermal and Mechanical Evaluation for Brunswick Unit 2 Cycle 20 Reload BRK2-20. ML1019305492010-01-20020 January 2010 Impact of Tritium Leak on Public BSEP 09-0034, Enclosure 10 to BSEP 09-0034 - ANP-2771(NP), Rev. 0, Brunswick, Unit 2 Cycle 19 Reload Safety Analysis, Dated January 20092009-01-31031 January 2009 Enclosure 10 to BSEP 09-0034 - ANP-2771(NP), Rev. 0, Brunswick, Unit 2 Cycle 19 Reload Safety Analysis, Dated January 2009 ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0909702482008-07-31031 July 2008 Enclosure 4 and 6 to BSEP 09-0034 - ANP-2729(NP), Rev. 0, Brunswick, Unit 2, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, and Areva Affidavit Withholding ANP-2727(P), Rev. 0 Form Public Disclosure ML0909702462008-06-30030 June 2008 Enclosure 7 and 9 to BSEP 09-0034 - ANP-2727(NP), Rev. 0, Brunswick, Unit 2, Cycle 19 Fuel Cycle Design, and Areva Affidavit Re Withholding ANP-2771(P), Rev. 0 from Public Disclosure BSEP 07-0102, ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel.2007-09-30030 September 2007 ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel. ML0728402192007-09-30030 September 2007 ANP-2642(NP), Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM-10 Fuel. ML0721803722007-07-31031 July 2007 Areva Report ANP-2658(NP), Revision 0, Brunswick Unit 1 Cycle 17 Fuel Cycle Design, Enclosure 3 BSEP 07-0075, Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 62007-07-31031 July 2007 Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6 2022-05-25
[Table view] |
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BSEP 12-0031 Enclosure 8 AREVA Document No. 51-9177317-000."Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)"
~.*flr~edDocunme~nt A AREVA 20004-018 (10/18/2010)
AREVA NP Inc.ENGINEERING INFORMATION RECORD Document No: 51 -9177317 -000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Page 1 of 10 C>~;ntrcHed Docunierd.
A AREVA 20004-018 (10/18/2010) 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Safety Related?MZYES nIINO Does this document contain assumptions requiring verification?
[i] YES Z NO Does this document contain Customer Required Format? L] YES Z NO Signature Block PILP, R/LR, Pages/Sections Name and AIA-CRF, Prepared/Reviewed/
TitlelDiscipline Signature AIA-CRI Date Approved or Comments D.G. Carr, Supervisor P :21t'/I- p Thermal-Hydraulics Richland D.R. Tinkler, Engineer R Thermal-Hydraulics Richland _.. 2// .//y D.W. Pruitt, Manager A/A-CRI / / ,1.//Thermal-Hydraulics Richland A.B. Meginnis, Manager A/ A /Product Licensing A X20/(2./Note: P/LP designates Preparer (P), Lead Preparer (LP)R/LR designates Reviewer (R), Lead Reviewer (LR)A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF)A/A-CRI designates Approver (A), Approver -Confirming Reviewer Independence (A-CRI)Record of Revision Revision PageslSectionsl Brief Description I No. Paragraphs Changed Change Authorization 000 All Initial issue of document Page 2 L 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)1.0 Purpose Reference 1 presents an AREVA methodology for determining the safety limit minimum critical power ratio (SLMCPR) that was recently approved by the NRC. The methodology is an update or extension of the previously approved methodology presented in Reference
- 2. The SLMCPR methodology was updated to incorporate full implementation of the ACE critical power correlation (References 3 and 4), a realistic fuel channel bow model (Reference 5), and expanded coupling with the MICROBURN-B2 core simulator (Reference 6). More detailed descriptions of these improvements are discussed in Reference
- 1. The purpose of this report is to provide SLMCPR results for Brunswick Unit 1 Cycle 19 using the Reference 1 methodology to support a change in the list of approved methodologies in the Technical Specifications and also a change in the Technical Specification SLMCPR values for two-loop operation (TLO) and single-loop operation (SLO).2.0 Methodology The analysis presented in this document used the methodology presented in Reference
- 1. The SLMCPR is defined as the minimum value of the critical power ratio which ensures that at least 99.9%of the fuel rods in the core are expected to avoid boiling transition during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis that employs a Monte Carlo process that perturbs key input parameters used in the calculation of MCPR.The set of uncertainties used in the statistical analysis include both fuel-related and plant-related uncertainties.
The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [I In the AREVA methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis.
Reference 1 discusses the application of a realistic channel bow model.Page 3 Con t~roNkld Dcumn 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)3.0 Analysis The core loading and cycle depletion from the Brunswick Unit 1 Cycle 19 (BRK1-19) fuel cycle design report (Reference
- 7) was used as the basis of the SLMCPR analysis.
Figure 1 presents the core loading, including the assembly type, the cycle the fuel was originally loaded and the number of assemblies.
The BRK1-19 core is made up of ATRIUMTM 1OXM* and ATRIUM-10 fuel. Analyses were performed
[ ] for the Brunswick power/flow map for MELLLA operation as shown in Figure 2. The BSP regions shown in the power/map are based on the methods discussed in Reference
- 8. The radial power distribution
[] is presented in Figure 3.The ACE/ATRIUM 1OXM critical power correlation (Reference
- 4) is used for the ATRIUM 1OXM fuel while the SPCB critical power correlation (Reference
- 9) is used for the ATRIUM-10 fuel.The fuel- and plant-related uncertainties used in the BRK1-19 SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the effects of up to 40%of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and a 2500 effective full power hour (EFPH) LPRM calibration interval.The BRK1-19 SLMCPR analysis supports a TLO SLMCPR of 1.07 and an SLO SLMCPR of 1.09.Table 2 presents a summary of the analysis results including the SLMCPR and the percentage of rods expected to experience boiling transition.
The percentages of the total number of fuel rods predicted to experience boiling transition in the overall Monte Carlo statistical evaluation associated with each nuclear fuel type are presented in Table 3. The results are for the []4.0 Discussion of Results Results of the SLMCPR analysis using the Reference 2 methodology based on the same BRK1-19 design step-through and the same fuel- and plant-related uncertaintiest are shown in Table 4. The results show a significant decrease in both the TLO and SLO SLMCPR limits with the Reference 1 methodology.
The SLMCPR differences are primarily a result of the following differences in the methodologies:
Implementation of the realistic channel bow model Explicit use of the [ ] as a result of the expanded coupling with MICROBURN-B2 The improved SLMCPR results with the Reference 1 methodology are consistent with the results presented in Tables 4-1 and 4-3 of Reference 1.* ATRIUM is a trademark of AREVA NP.t[Page 4
,Jc., ntro~ted Docum 1 n 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)5.0 References
- 1. ANP-1 0307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.2. ANF-524(P)(A)
Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.3. ANP-10249PA Revision 1, ACE/ATRIUM-IO Critical Power Correlation, AREVA NP, September 2009.4. ANP-10298PA Revision 0, ACE/ATRIUM IOXM Critical Power Correlation, AREVA NP, March 2010.5. BAW-1 0247PA Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, AREVA NP, February 2008.6. EMF-2158(P)(A)
Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASMO-4 / MICROBURN-B2, Siemens Power Corporation, October 1999.7. ANP-3005(P)
Revision 0, Brunswick Unit I Cycle 19 Fuel Cycle Design, AREVA NP, June 2011.8. 0G02-0119-260, Backup Stability Protection (BSP) for Inoperable Option Ill Solution, GE Nuclear Energy, July 17, 2002.9. EMF-2209(P)(A)
Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.10. EMF-2493(P), MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, AREVA NP, December 2000.11. NEDO-20340, Process Computer Performance Evaluation Accuracy, General Electric, June 1974.12. NEDO-1 0958-A, General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application, General Electric, January 1977.13. NEDO-24344, Brunswick Steam Electric Plant Units I and 2 Single-Loop Operation, General Electric, September 1981.14. Letter, H.D. Curet (AREVA) to H.J. Richings (NRC), "POWERPLEX Core Monitoring:
Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996 (38-9043714-000).
- 15. 0B21-1305 Revision 1, "Core Monitoring LPRM Uncertainty and Sensitivity Decay," Progress Energy, March 2009 (NRC Accession Number ML092370285).
Page 5
- .ofl trolle'-d Doc.,:'-,--erJ 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Table 1 Fuel- and Plant-Related Uncertainties for BRKI-19 SLMCPR Analyses Parameter Uncertainty Reference Fuel-Related Uncertainties Plant-Related Uncertainties Feedwater flow rate 1.8%* 12 Feedwater temperature 0.8%* 12 Core pressure 0.8%*- § 11 Total core flow rate TLO 2.5% 12 SLO 6.0% 13.[I t Values from Reference 10 are a result of the application of the methodology discussed in Reference 14 to the base uncertainties presented in Reference
- 6. The.uncertainties presented support operation with up to 50% of the LPRMs out-of-service, up to 40% of the TIP channels out-of-service, and a 2500 EFPH LPRM calibration interval.
The bases of these values include a core monitoring LPRM detector uncertainty of 4.3% from Reference 15.Referenced plant uncertainties were rounded up to the nearest 0.1% before use.§ The core pressure uncertainty is taken in Reference 11 to be a more conservative value than accepted in Reference 12; therefore, the more conservative value is used.Page 6
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51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)Table 2 BRK1-19 Results Summary for SLMCPR Analysis (Reference 1 SAFLIM3D Methodology)
Percentage of Rods SLMCPR in Boiling Transition TLO -1.07 0.073 SLO -1.09 0.083 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Contribution of Total Rods Nuclear Predicted To Be Fuel Fuel BurnupinB(%
Type Design Status in BT TLO SLO 30 ATRIUM-10 Twice burned [31 ATRIUM-10 Twice burned 32 ATRIUM-10 Once burned 33 ATRIUM-10 Once burned 34 ATRIUM 1OXM Fresh 35 ATRIUM 1OXM Fresh ]Table 4 BRK1-19 Results Summary for SLMCPR Analysis (Reference 2 SAFLIM2 Methodology)
Percentage of Rods SLMCPR in Boiling Transition TLO -1.11 0.098 SLO -1.13 0.098 Page 7 or'..,~. tv L 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)J: 1 2 3 4 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 I: 2 3 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 31 30 32 31 32 30 32 30 32 30 32 31 32 30 32 30 32 31 32 30 32 31 31 31 30 30 32 30 32 32 34 32 34 34 34 33 34 34 34 34 33 34 33 34 34 33 34 34 34 32 34 32 34 30 32 30 32 31 31 31 31 31 32 34 33 34 35 33 35 35 35 35 33 35 34 34 34 32 30 31 30 3 2 34 32 34 34 33 35 33 35 33 33 35 33 35 33 34 34 32 34 3 2 30 31 32 3 3 34 35 33 35 33 35 33 35 35 33 35 33 35 33 35 34 33 32 31 30 32 34 34 34 33 35 33 35 33 35 33 33 35 3 3 35 33 35 33 34 34 34 32 31 31 32 32 34 35 33 35 33 35 33-55 33 35 35 33 35 33 35 33 35 3 3 35 34 32 31 31 32 34 34 35 33 35 33 35 33 35 33 33 35 35 33 35 33 35 33 34 34 32 31 30 30 31 30 32 32 32 32 33 34 34 34 34 34 33 33 35 33 35 35 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1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 30 ATRIUM-10 17 38 31 ATRIUM-10 17 46 32 ATRIUM-10 18 80 33 ATRIUM-10 18 162 34 ATRIUM 1OXM 19 96 35 ATRIUM 1OXM 19 138 Figure 1 Brunswick Unit 1 Cycle 19 Core Loading Map Page 8 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)0 a-110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 30.0 20.0 10.0 0n I v.v 0.0 7.7 15.4 23.1 30.8 38.5 46.2 53.9 61.6 69.3 77.0 84.7 92.4 Mlbs/hr Core Flow 10 20 30 40 50 60 70 80 90 100 110 120 % Core Flow Figure 2 Brunswick Unit I Power/Flow Map With Nominal Feedwater Temperature BSP Regions Page 9 Contro'led Doci tve nt 51-9177317-000 Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology (Nonproprietary Version)J: 1 2 3 7 8 9 10 11 12 13 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 0.299 0.362 0.374 0.399 0.401 0.410 0.400 0.372 0.354 0.298 0.398 0.594 0.691 0.724 0.753 0.771 0.769 0.752 0.722 0.687 0.592 0.398 0.249 0.345 0.485 0.712 0.854 1.081 0.911 1.130 1.135 1.134 1.129 0.909 1.077 0.850 0.711 0.483 0.357 0.244 0.291 0.465 0.672 0.806 1.102 1.203 1.244 1.259 1.256 1.040 1.040 1.254 1.256 1.240 1.199 1.097 0.802 0.668 0.459 0.284 0.258 0.465 0.745 1.026 0.950 1.249 1.288 1.083 1.298 1.075 1.290 1.289 1 .073 1.294 1.079 1.282 1.243 0. 936 1.019 0.740 0.462 0.248 0.363 0.672 1 .025 1.017 1 .265 1.308 1.101 1.310 1.089 1 .301 1 .085 1 .085 1.298 1.085 1.303 1 .095 1 .301 1.258 1.014 1.018 0.668 0.357 0.492 0.807 0.940 1.265 1 .305 1 .096 1 .332 1.112 1.333 1.108 1.303 1.301 1.104 1 .326 1.097 1 .324 1.095 1.297 1.257 0.933 0.799 0.474 0.393 0.719 1.111l 1.256 1.311 1.100 1.313 1.118 1.333 1.110 1.323 1.079 1.079 1.318 1.106 1.325 1.110 1.304 1.091 1.301 1.246 1.102 0.712 0.385 0.306 0 .602 0.864 1.220 1 .301 1.101 1.319 1.100 1.316 1.087 1.310 1.082 1.294 1.292 1.076 1.302 1.085 1.307 1.093 1.308 1.087 1.291 1.211 0.857 0.597 0.301 0.361 0.702 1.105 1.271 1.093 1 .322 1.105 1.314 1.084 1.294 1 .065 1.284 1.054 1.056 1 .279 1 .065 1.287 1.074 1.302 1 .095 1.310 1.084 1.261 1 .097 0.696 0.359 0.400 0.747 0.936 1.295 1.340 1.113 1.336 1 .092 1.288 1.055 1 .260 1.038 1 .267 1.268 1.040 1.257 1.051 1.279 1.084 1.323 1.104 1.329 1.285 0.928 0.742 0.391 0.414 0.778 1.168 1.298 1 .107 1 .340 1.101 1.317 1.059 1.261 1.032 1.227 1.008 1.020 1.235 1.034 1.255 1.059 1.305 1.089 1.328 1.097 1.288 1.160 0.773 0.410 0.421 0.796 1.174 1.071 1.331 1.101 1 .322 1.076 1.284 1.047 1.243 0.997 0.987 1.210 1.003 1.241 1.042 1.276 1 .068 1.311 1.093 1.321 1.065 1.167 0.792 0.424 1 2 3 4 5 6 7 8 9 10 11 12 13 J:14 15 16 17 18 19 20 21 22 23 24 25 26 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 0.423 0.795 1.174 1 .070 1.332 1.101 1.323 1.076 1.286 1.048 1.248 1.005 1.213 0.985 0.994 1.240 1.042 1.278 1.068 1.313 1.092 1.322 1 .063 1.168 0.790 0.422 0.417 0.777 1.169 1.300 1.109 1.343 1.103 1 .321 1.063 1 .268 1.038 1.244 1.023 1.014 1.230 1.032 1.261 1.056 1.312 1.096 1 .334 1.101 1.292 1.163 0.773 0.415 0.395 0.745 0.935 1.299 1 .345 1.115 1.341 1.101 1.296 1.061 1.271 1.047 1.279 1.276 1.042 1.266 1.055 1.289 1.090 1.333 1.106 1.336 1.292 0.929 0.742 0.401 0.366 0.703 1.109 1.276 1.097 1.329 1.104 1.323 1.094 1.305 1.074 1.296 1.065 1.064 1.295 1.076 1.301 1.082 1.316 1.097 1.321 1.089 1.270 1.104 0.700 0.364 0.310 0.604 0.867 1.227 1.309 1 .107 1.329 1.109 1.328 1.091 1.323 1.091 1.311 1.311 1.091 1.323 1.095 1.324 1.103 1.323 1.101 1.304 1.222 0.864 0. 602 0.312 0.407 0.722 1.118 1 .265 1.322 1.106 1 .327 1.126 1.349 1.121 1.341 1.093 1.092 1.341 1.119 1.346 1.124 1.322 1.102 1.318 1.262 1.115 0.719 0.406 0.496 0.813 0.948 1.277 1.318 1.107 1.348 1.122 1.352 1.121 1.324 1.324 1.120 1.350 1.112 1.344 1.106 1.315 1.274 0.956 0.811 0-494 0.373 0. 678 1.034 1 .026 1.277 1.323 1.110 1.328 1.103 1.323 1.099 1.099 1.322 1.101 1.326 1.108 1.320 1.275 1.024 1 .032 0.676 0.366 0.254 0.468 0.750 1.034 0.946 1.262 1 .304 1.096 1.319 1.089 1.312 1 .312 1.089 1.317 1 .093 1.302 1.260 0.944 1.032 0.749 0.469 0.251 0.291 0.468 0.676 0.810 1.112 1.218 1.262 1.278 1.277 1.055 1 .056 1.276 1.277 1.260 1.216 1.111l 0.809 0.675 0.465 0.290 0.251 0.362 0.495 0.718 0.860 1.095 0.922 1.149 1.154 1.154 1.149 0. 921 1.094 0.860 0.716 0.489 0.364 0.252 0.401 0.598 0.694 0.735 0.765 0.782 0.783 0.765 0.736 0.694 0.598 0.399 0.304 0.360 0.386 0.420 0.414 0.415 0.419 0.385 0.359 0.302 14 15 16 17 18 19 20 21 22 23 24 25 26 Figure 3 Radial Power Distribution for Brunswick Unit 1 Cycle 19 SLMCPR[Page 10 BSEP 12-0031 Enclosure 10 AREVA Affidavit Regarding Withholding AREVA Document No. 51-9176407-000,"Brunswick Unit I Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology
-Operability Assessment (Proprietary Version)" from Public Disclosure AFFIDAVIT STATE OF WASHINGTON
)) ss.COUNTY OF BENTON 1. My name is Alan B. Meginnis.
I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA NP to determine whether certain AREVA NP information is proprietary.
I am familiar with the policies established by AREVA NP to ensure the proper application of these criteria.3. I am familiar with the AREVA NP information contained in the report 51-9176407-000, "Brunswick Unit 1 Cycle 19 SLMCPR Analysis With SAFLIM3D Methodology
-Operability Assessment (Proprietary Version)," dated February 2012 and referred to herein as"Document." Information contained in this Document has been classified by AREVA NP as proprietary in accordance with the policies established by AREVA NP for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA NP and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.
The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information." 6. The following criteria are customarily applied by AREVA NP to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA NP's research and development plans and programs or their results.(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA NP in product optimization or marketability.(e) The information is vital to a competitive advantage held by AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial harm to the competitive position of AREVA NP.The information in the Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d) and 6(e) above.7. In accordance with AREVA NP's policies governing the protection and control of information, proprietary information contained in this Document have been made available, on a limited basis, to others outside AREVA NP only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.(j&~SUBSCRIBED before me this c>__O__I day of .,- 2012.Susan K. McCoy NOTARY PUBLIC, STATE OF WASHINGTON MY COMMISSION EXPIRES: 1/14/2016