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MONTHYEARML15022A1652015-01-0909 January 2015 License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions Project stage: Supplement ML15030A0092015-01-28028 January 2015 NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance Review for License Amendment Request Transition to Areva Extended Flow Window Methodology Project stage: Acceptance Review ML15195A4472015-08-0505 August 2015 Summary of Public Meeting with Xcel Energy and Areva to Discuss Changes to the Proposed Technical Specifications and COLR in Support of the Areva Extended Flow Window License Amendment Request Project stage: Meeting L-MT-15-057, License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions2015-08-26026 August 2015 License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions Project stage: Supplement ML15140A1242015-09-28028 September 2015 Request for Withholding Information from Public Disclosure from Areva Inc. Associated with the Areva Extended Flow Window License Amendment Request Project stage: Withholding Request Acceptance ML15140A1472015-09-28028 September 2015 Request for Withholding Information from Public Disclosure (GE-Hitachi LLC) Associated with the Areva Extended Flow Window License Amendment Request Project stage: Withholding Request Acceptance ML15274A4732015-09-29029 September 2015 License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions Project stage: Supplement L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits Project stage: Response to RAI ML15274A4752015-09-29029 September 2015 Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary) Project stage: Response to RAI ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints Project stage: Other L-MT-15-081, ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.2015-12-0808 December 2015 ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. Project stage: Response to RAI ML15345A4072015-12-0808 December 2015 License Amendment Request for Areva Extended Flow Window, Supplement to Provide Revised Analysis of Anticipated Transient Without Scram Instability Project stage: Supplement ML16063A0332016-02-29029 February 2016 License Amendment Request for Areva Extended Flow Window Supplement to Disposition Changes to Non-Limiting Transient Analyses Project stage: Supplement L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology2016-04-29029 April 2016 Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology Project stage: Other ML16221A2742016-07-31031 July 2016 ANP-3435NP, Revision 2, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. Project stage: Response to RAI L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016 ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I. Project stage: Other ML16221A2752016-07-31031 July 2016 ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I. Project stage: Other ML16221A2732016-08-0404 August 2016 License Amendment Request for Areva Extended Flow Window Supplement to Provide Revised Analysis of Anticipated Transient Without Scram Instability Project stage: Supplement L-MT-16-041, License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties2016-09-14014 September 2016 License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties Project stage: Supplement L-MT-16-049, License Amendment Request for Areva Extended Flow Window Supplement to Revise the Applicability of a Topical Report Limitation2016-09-28028 September 2016 License Amendment Request for Areva Extended Flow Window Supplement to Revise the Applicability of a Topical Report Limitation Project stage: Supplement 2015-09-29
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Category:Response to Request for Additional Information (RAI)
MONTHYEARL-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) ML22220A2722022-08-0808 August 2022 Response to a Request for Additional Informational Regarding the Monticello Fuel Oil Storage Tank Inspection L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) ML22161A9152022-06-10010 June 2022 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations. L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-21-017, Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 22021-04-20020 April 2021 Response to Request for Additional Information (RAI) Related to License Amendment Request to Implement Technical Specifications Task Force Traveler TSTF-505, Revision 2 L-MT-20-036, Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times2020-12-21021 December 2020 Response to Request for Additional Information Related to License Amendment Request to Implement Technical Specification Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times L-MT-20-024, Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2020-07-20020 July 2020 Response to Request for Additional Information (RAI) Monticello 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval L-MT-20-015, Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan2020-06-0808 June 2020 Response to Request for Additional Information (RAI) Long-Term Replacement Steam Dryer Inspection Plan ML20045E8942020-02-14014 February 2020 Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS L-MT-19-030, Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors.2019-05-15015 May 2019 Supplement to a Response for a Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. L-MT-19-024, Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.12019-04-18018 April 2019 Response to a Request for Additional Information for Removal of a Note Associated with Technical Specification 3.5.1 L-MT-19-018, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-03-13013 March 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk- Informed Categorization & Treatment of Structures, Systems and Components for Nuclear Power Reactors L-MT-18-058, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ...2018-10-23023 October 2018 Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to ... L-MT-18-041, Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel2018-07-20020 July 2018 Response to Request for Additional Information Re Request for Permanent Exemption from 10CFR50, App R, III.G.2.a Requirements for Exposed Structural Steel L-MT-18-032, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-03602018-06-0101 June 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, and Supplement (EPID: L-2017-LLA-0360 ML18131A2232018-05-11011 May 2018 Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di L-MT-18-013, Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 152018-04-0505 April 2018 Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 L-MT-17-071, Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves2017-11-20020 November 2017 Response to Request for Additional Information Regarding Risk-Informed Request for Exemption from 10CFR50, Appendix R, III.G.2 Requirements for Multiple Spurious Operations of Drywell Spray Motor-Operated Valves L-MT-17-066, Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events2017-09-28028 September 2017 Supplemental Information for the Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events L-MT-17-065, License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information2017-09-25025 September 2017 License Amendment Request to Revise the Emergency Action Level Scheme - Supplement and Response to Requests for Additional Information L-MT-17-063, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times2017-09-20020 September 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times L-MT-17-025, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accid2017-04-11011 April 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident L-MT-17-022, Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2017-03-29029 March 2017 Response to Second Round PRA Related RAIs for the License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-17-007, Part 3 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2017-02-0707 February 2017 Part 3 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-17-002, Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval2017-01-31031 January 2017 Part 2 Response to Probabilistic Risk Assessment (PRA) Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50Appendix J Containment Type a Test Interval L-MT-16-062, Part 1 Response to Probabilistic Risk Assessment Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2016-12-16016 December 2016 Part 1 Response to Probabilistic Risk Assessment Related Requests for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-16-058, Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.22016-11-22022 November 2016 Supplement to License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 ML16288A0972016-10-14014 October 2016 and Monticello - Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-MT-16-044, Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval2016-10-10010 October 2016 Response to Request for Additional Information: License Amendment Request for a Permanent Extension of the 10 CFR 50 Appendix J Containment Type a Test Interval L-MT-16-045, Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.22016-10-0303 October 2016 Response to Request for Additional Information: License Amendment Request to Revise Battery Charger Surveillance Requirement 3.8.4.2 L-MT-16-041, License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties2016-09-14014 September 2016 License Amendment Request for Areva Extended Flow Window Supplement to Address Power Distribution Uncertainties L-MT-16-038, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2016-08-19019 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) L-MT-16-039, Response to Nuclear Security and Incident Response Requests for Additional Information Regarding Changes to the Monticello Nuclear Generation Plant Physical Security Plan (Revision 16) Pursuant to 10 CFR 50.54(p)(2)2016-08-15015 August 2016 Response to Nuclear Security and Incident Response Requests for Additional Information Regarding Changes to the Monticello Nuclear Generation Plant Physical Security Plan (Revision 16) Pursuant to 10 CFR 50.54(p)(2) ML16221A2742016-07-31031 July 2016 ANP-3435NP, Revision 2, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. L-MT-16-026, Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection2016-06-0202 June 2016 Response to Request for Additional Information for Approval of Alternative to Apply the BWRVIP Guidelines in Lieu of Specific ASME Section XI Code Requirements for Reactor Pressure Vessel Internals and Components Inspection L-MT-16-028, Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information2016-05-18018 May 2016 Transmittal of Extended Power Uprate, Extended Steam Dryer - Response to Requests for Additional Information L-MT-16-024, Flood Hazard Reevaluation Report2016-04-21021 April 2016 Flood Hazard Reevaluation Report ML16091A2282016-03-29029 March 2016 Monticello Nuclear Generating Plant Exemption Request for Nonconforming Dry Shielded Canister Dye Penetrant Examinations, Supplemental Information to Respond to the Second Request for Additional Information (TAC No. L25058) L-MT-15-081, ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar.2015-12-0808 December 2015 ANP-3435NP, Revision 1, Areva Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW Lar. ML15274A4732015-09-29029 September 2015 License Amendment Request for Areva Extended Flow Window Supplement to Respond to NRC Staff Questions ML15348A2172015-08-31031 August 2015 Enclosure 6, Areva Report ANP-3424NP, Non-Proprietary, Areva Responses to RAI from Scvb on MNGP EFW LAR, Revision 0, August 2015 2023-09-05
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L-MT-1 5-081 Enclosure 2 Enclosure 2 AREVA Report ANP-3435NP Non-Proprietary ARE VA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR Revision 1 November 2015 19 pages follow Contro~led Document A ARE VMA AN P-3435N P Revision 1 AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR November 2015 (c) 2015 AREVA Inc.
Controlled Document AREVA Inc.ANP-3435NP Revision 1 Copyright
© 2015 ARE VA Inc.All Rights Reserved ControD~ed Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Pagei Nature of Changes Item Pages Description and Justification
- 1. 1-1 to 1-2 Added Section 1.1 to discuss MICROBURN-B2 issues.2. 2-1 to 2-12 Updated Sections 2.1 and 2.2 to correct for MICROBURN-B2 issues.AREVA Inc.
ControD~ed Document AREVA Responses to RAI-8 and ANP-3435NP RAI-32 from SRXB and SNPB on Revision 1 MNGP EFW LAR Page ii Contents 1.0 Introduction...................................................................................
1-1 1.1 Description of MICROBURN-B2 Issues............................................
1-1 2.0 RAIs and Responses........................................................................
2-1 2.1 RAI-8: Mitigated ATWSI Calculations..............................................
2-1 2.2 RAI-32: 2RPT ATWS ..............................................................
2-10 Figures Figure 8-1 Core Inlet Subcooling Versus Time For Various Operator Intervention Times .....2-3 Figure 8-2 Hot Bundle Inlet Flow Versus Time For Various Operator Intervention Times .....2-3 Figure 8-3 Hot Bundle Power Versus Time For Various Operator Intervention Times..........
2-4 Figure 8-4 Clad Temperature Versus Time For Various Operator Intervention Times..........
2-4 Figure 8-5 Peak Clad Temperature Versus Operator Intervention Time.........................
2-5 Figure 8-6 Gap Conductance Effect on Peak Clad Temperature Versus Operator Intervention Time.......................................................................
2-7 Figure 8-7 Orifice Loss Coefficient Effect on Peak Clad Temperature Versus Operator Intervention Time .......................................................................
2-7 Figure 8-8 [ ] Effect on Peak Clad Temperature Versus Operator Intervention Time.......................................................................
2-8 Figure 32-1 Bundle Power Versus Time For [ ]..........................
2-11 Figure 32-2 Bundle Inlet Flow Versus Time For [" I ......................
2-11.Figure 32-3 Clad Temperature Versus Time For [ ]......................
2-12 AREVA Inc.
Controlled Document AREVA Responses to RAI-8 and ANP-3435NP RAI-32 from SRXB and SNPB on Revision 1 MNGP EFW LAR Page iii Nomenclature Acronym Definition 2RPT 2 Recirculation Pump Trip ATWS Anticipated Transient Without Scram ATWSi ATWS with instability BOC Beginning-of-Cycle BWR Boiling Water Reactor CPR Critical Power Ratio DBA Design Basis Accident EFW Extended Flow Window EOC End-of-Cycle EOIII Enhanced Option Ill (Stability)
EPU Extended Power Uprate MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MNGP Monticello Nuclear Generating Plant TTWBP Turbine Trip with Bypass AREVA Inc.
ControH~ed Document AREVA Responses to RAI-8 and ANP-3435NP RAI-32 from SRXB and SNPB on Revision 1 MNGP EFW LAR Page 1-1 1.0 Introduction In Reference 1, Northern States Power Company -a Minnesota corporation, doing business as Xcel Energy, submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant (MNGP). The application was supplemented by Reference
- 2. The amendment would revise the Technical Specifications and approve certain AREVA analytical methods to support plant operation in the expanded power-flow domain described as the Extended Flow Window (EFW).The U.S. Nuclear Regulatory Commission (NRC) staff in the Reactor Systems Branch (SRXB) and Nuclear Performance and Code Review Branch (SNPB) has reviewed the application and concluded that additional information is necessary to complete its review. Draft Requests for Additional Information (RAI)were provided as an attachment to Reference
- 3. AREVA responses to all of these RAI except RAI-8 and RAI-32 were documented in Reference
- 4. The RAI and the AREVA responses for RAI-8 and RAI-32 are attached.The analysis of Anticipated Transient Without Scram -Instability (ATWSi) described herein should be recognized as the licensee's analysis of record supporting the proposed amendment to allow operation in the EFW domain. []Following submittal of Revision 0 of this document, two issues have been discovered within MICROBURN-B2.
A description of these issues is found in the following section, and the results in Section 2.0 have been updated with corrected results for these issues.These responses are provided so Xcel Energy can provide a complete set of responses to the NRC by combining the ARE VA responses with the responses being prepared by Xcel Energy.1.1 Description of MICROBURN-B2 Issues The identified issues within MICROBURN-B2 are described in detail below, but it is noted that both are only a concern in regard to low flow calculations.
The first issue that was identified within MICROBURN-B2 was that at some low flow conditions (i.e., below 50% rated core flow), the MICROBURN-B2 code hydraulic convergence might not be sufficient to ensure the accuracy of the resulting solutions.
A new version of the MICROBURN-B2 code has been issued with a revised low flow convergence scheme that addresses this non-convergence issue. This new version of the code has been used in the revised calculations discussed later in this document.The second issue within MICROBURN-B2 identifies that the current implementation of the void quality correlation used within MICROBURN-B2 includes by default [ ]. Investigations AREVA Inc.
Controlled Document AREVA Responses to RAI-8 and ANP-3435NP RAI-32 from SRXB and SNPB on Revision 1 MNGP EFW LAR Page 1-2 that have been carried out revealed that the correlation produces some potentially non-physical results at very low mass fluxes and high flow qualities, which is part of the reason for the implementation of the[ ] into the correlation in MICROBURN-B2.
This default behavior for MICROBURN-B2 was implemented in 2011.The non-physical behavior is inherent in the formulation of the correlation and is not an implementation issue within the MICROBURN-B2 code. Investigation has determined that the correlation behaves in an expected manner for the following range of conditions*:
All versions of the MICROBURN-B2 code since 2011 have included a default []. While this appears to have mitigated the correlations non-physical behavior it has been determined
[Revised calculations were performed eliminating the [" ] with an existing MICROBURN-B2 input. The analyses were then reviewed to confirm that all cases fall within [] behavior is as expected.References
- 1. License Amendment Request for ARE VA Extended Flow Window, October 3, 2014, MNGP L-MT-14-044, ML14283A1 19.2. License Amendment Request for ARE VA Extended Flow Window Supplement to Response to NRC Staff Questions (TAC No. MF5002), January 9, 2015, MNGP L-MT-14-103, ML15022A165 and ML15022A167.
- 3. Monticello Nuclear Generating Plant -Request for Additional Information (SRXB/SNPB) re: AREVA Extended Flow Window Licence Amendment Request (TAO No MF5002) -email from Terry Beltz (NRC) to Glenn Adams (Xcel Energy), August 5th, 2015.4. ANP-3434P Revision 1, ARE VA Responses to RAI from SRXB and SNPB on MNGP EFW LAR, AREVA, August 2015.* The range of applicability has been defined in a conservative manner. Falling outside this range does not mean that the void-quality correlation will provide a non-physical result; instead it indicates that the potential exists.Analyses inside of this range of conditions produce the expected result.AREVA Inc.
ControD~ed Document AREVA Responses to RAI-8 and ANP-3435NP RAI-32 from SRXB and SNPB on Revision 1 MNGP EFW LAR Page 2-1 2.0 RAIs and Responses 2.1 RAI-8: Mitigated A TWSI Calculations A TWSI calculations in the Monticello MAR are for unmitigated (i.e., no operator actions) assumptions.
a) Provide realistic Anticipated Transient Without Scram with Instability (A TWSI) calculations under the expected conditions crediting operator actions. Provide sensitivity results for later operator action time.b) Provide a discussion of uncertainty treatment (e.g., hGap, inlet friction).
c) Describe the methodology used by AISHA to excite the oscillation when the decay ratio (DR) is close to 1.0.ARE VA Response a) Provide realistic Anticipated Transient Without Scram with Instability (A TWSI) calculations under the expected conditions crediting operator actions. Provide sensitivity results for later operator action time.The case that produced the maximum clad temperature excursion without operator action was repeated while crediting the operator action of lowering the water level. As is demonstrated below, the operator action [] and the transient is demonstrated to be uneventful.
The operator action was delayed by increasing time periods in a series of runs to examine the sensitivity of the action timing. It was found that a delayed action [The sensitivity runs were made with operator action initiated at 90 seconds and at larger values with incremental steps of 10 seconds. [] The sensitivity to operator action timing is illustrated in the following figures. In some of the figures, only the results of representative runs are shown to avoid crowding of data so the trends are more clearly seen.Two modifications were made to the original runs in order to properly model the mitigated cases. [AREVA Inc.
Contronled Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-2[]Figure 8-2 shows the inlet mass flow rate as a function of time for several cases with differing operator action times. [Figure 8-3 shows the limiting bundle power for the cases represented in Figure 8-2.Figure 8-4 shows the clad temperature excursion for selected cases with differing operator action timing.[]Figure 8-5 depicts the peak clad temperature that is reached in the different simulations with different operator action timing. The figure shows clearly that [AREVA Inc.
Cotrl dDoumn AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-3 Figure 8-1 Core Inlet Subcooling Versus Time For Various Operator Intervention Times Figure 8-2 Hot Bundle Inlet Flow Versus Time For Various Operator Intervention Times AREVA Inc.
Con1:roI!ed Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-4 Figure 8-3 Hot Bundle Power Versus Time For Various Operator Intervention Times Figure 8-4 Clad Temperature Versus Time For Various Operator Intervention Times AREVA Inc.
I onr~e Documentf AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-5 Figure 8-5 Peak Clad Temperature Versus Operator Intervention Time AREVA Inc.
ControDled Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-6 b) Provide a discussion of uncertainty treatment (e.g., hGap, inlet friction).
The mitigated cases as described in item a) above were performed again while varying certain parameters.
These parameters have been identified as being of higher importance and also represent a higher level of calculational uncertainty.
These parameters include* The gap conductance was [* The inlet orifice resistance was [* []]As shown in Figure 8-6 through Figure 8-8, the effect of these parameter variations on the Peak Clad Temperature (POT) is []It is important to note that the range of parameter variation imposed on the simulation is larger than the uncertainty for these parameters.
AREVA Inc.
Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR AN P-3435NP Revision I Page 2-7 Figure 8-6 Gap Conductance Effect on Peak Clad Temperature Versus Operator Intervention Time Figure 8-7 Orifice Loss Coefficient Effect on Peak Clad Temperature Versus Operator Intervention Time AREVA Inc.
Cont rolleKd Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-8 Figure 8-8 [] Effect on Peak Clad Temperature Versus Operator Intervention Time AREVA Inc.
Contro~led Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-9 c) Describe the methodology used by AISHA to excite the oscillation when the decay ratio (DR) is close to 1.0.[]References for RAI-8 8-1. ANP-3274P Revision 1, "Analytical Methods for Monticello ATWS-I," July 2014.AREVA Inc.
Controlied Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-10 2.2 RAI-32: 2RPT ATWS The A TWSI analysis of record in the LAR is Turbine Trip with Bypass (TTWBP). When operator actions are credited, the TTWBP does not show significant power oscillations and the limiting A TWSI transient becomes the 2RPT with failure to scram.Provide the results of 2RPT event with failure to scram. Describe the basis for boundary conditions and operator actions assumed for the analysis.AREVA Response The Two Recirculation Pump Trip (2RPT) differs from the Turbine Trip With Bypass (TTWBP) event in that turbines are not isolated and the steam flow to the feedwater heaters is not interrupted.
The 2RPT transient results in a much smaller feedwater temperature transient, as the feedwater temperature decreases to a new equilibrium value determined by the final power level. []The results are shown in Figure 32-1 through Figure 32-3. Figure 32-1 shows the limiting bundle power as function of time, and Figure 32-2 shows the corresponding inlet flow rate. Figure 32-3 shows the peak AREVA Inc.
Controlled Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR ANP-3435NP Revision 1 Page 2-11 powered rod clad temperature at different axial nodes. The maximum clad temperature of ["]Figure 32-1 Bundle Power Versus Time For []Figure 32-2 Bundle Inlet Flow Versus Time For []AREVA Inc.
Controg~ed Document AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW [AR ANP-3435NP Revision 1 Page 2-12 Figure 32-3 Clad Temperature Versus Time For []AREVA Inc.
L-MT-1 5-081 Enclosure 3 Enclosure 3 ARE VA Affidavit 3 pages follow AFFIDAVIT STATE OF WASHINGTON
)) ss.COUNTY OF BENTON )1. My name is Alan B. Meginnis.
I am Manager, Product Licensing, for AREVA Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary.
I am familiar with the policies established by ARE VA to ensure the proper application of these criteria.3. I am familiar with the ARE VA information contained in the report ANP-3435P, Revision 1, "AREVA Responses to RAI-8 and RAI-32 from SRXB and SNPB on MNGP EFW LAR," dated November 2015 and referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA 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 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 to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA'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.(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for ARE VA in product optimization or marketability.(e) The information is vital to a competitive advantage held by AREVA, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA.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'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 only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA 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.SUBSCRIBED before me this day of ...f)-d' 2015.NOTARY PUBLIC, STATE OF WASHI TON MY COMMISSION EXPIRES: 1/14/20 16