ML14269A325
From kanterella
Jump to navigation
Jump to search
Letter Sequence Other | |
|---|---|
TAC:MF3330, (Approved, Closed) | |
Initiation
Administration | |
MONTHYEARML14204A6232014-07-18018 July 2014
[Table View]Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7 Project stage: Request L-MT-14-060, Extended Power Uprate: Replacement Steam Dryer - Response to NRC Requests for Additional Information, Revised Limit Curves and Supporting Information2014-07-22022 July 2014 Extended Power Uprate: Replacement Steam Dryer - Response to NRC Requests for Additional Information, Revised Limit Curves and Supporting Information Project stage: Response to RAI ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. Project stage: Other ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. Project stage: Other ML14269A3222014-09-22022 September 2014 Monticello Extended Power Uprate: Replacement Steam Dryer-Revised Limit Curve Methodology Project stage: Other ML14301A5162014-10-29029 October 2014 Staff Review of Revised Limit Curves and Additional Information Regarding the Replacement Steam Dryer Acoustic and Structural Analyses in Support of Extended Power Uprate Power Ascension (Tac No. MF3330) Project stage: Approval 2014-07-22 |
| ML14269A325 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/05/2014 |
| From: | Westinghouse |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14269A321 | List: |
| References | |
| L-MT-14-075, TAC MF3330 LTR-BWR-ENG-14-037-NP | |
| Download: ML14269A325 (3) | |
Similar Documents at Monticello | |
|---|---|
Category:Report
MONTHYEARML23172A1112023-06-21021 June 2023
[Table view]SLRA - Requests for Confirmation of Information - Set 1 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-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022 Technical Specification 5.6.4 Post Accident Monitoring Report ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021 Nuclear Material Transaction Report L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange ML19308A0562019-10-0808 October 2019 Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..2019-04-25025 April 2019 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions .. L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017 Steam Dryer Visual Inspection Report L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017 Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4 ML17088A5272017-03-31031 March 2017 NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017 Mitigating Strategies Flood Hazard Assessment (MSA) Submittal ML16302A2462016-10-28028 October 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima.. ML16221A2752016-07-31031 July 2016 ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I. 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. L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016 Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints 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 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) ML15175A3362015-07-0808 July 2015 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 ML15169A3582015-06-11011 June 2015 PSP Rev 14 Technical Review 06-11-15 ML16035A1842015-01-30030 January 2015 Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. ML16035A1862015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 ML16035A1852015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014 Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. ML14204A6232014-07-18018 July 2014 Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7 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 ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records ML14136A2892014-05-12012 May 2014 14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report. L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. ML14069A0052014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14014A2682014-02-28028 February 2014 Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan ML14064A1862014-02-25025 February 2014 Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information ML13358A3732013-12-31031 December 2013 Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013 Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit ML13282A1422013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2 L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages ML13248A3462013-08-29029 August 2013 WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12 ML13248A3452013-08-29029 August 2013 WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11 ML13248A3442013-08-29029 August 2013 WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10 ML13248A3482013-08-29029 August 2013 WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13 L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 142013-08-29029 August 2013 WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14 ML13200A1922013-07-31031 July 2013 ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. ML13200A1962013-07-31031 July 2013 ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. ML13205A0852013-07-12012 July 2013 Enclosure 2 - Westinghouse Electric Co. Letter LTR-A&SA-13-14, NP-Attachment, Revision 0, Responses to the U.S. NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #5 ML13200A1902013-06-30030 June 2013 ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello. 2023-06-21 Category:Technical MONTHYEARL-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
[Table view]Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022 Technical Specification 5.6.4 Post Accident Monitoring Report ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021 Nuclear Material Transaction Report L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange ML19308A0562019-10-0808 October 2019 Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..2019-04-25025 April 2019 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions .. L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017 Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4 L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016 Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). 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) 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 ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints ML16035A1842015-01-30030 January 2015 Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. ML16035A1862015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 ML16035A1852015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014 Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. 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 ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. ML14069A0052014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14064A1862014-02-25025 February 2014 Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information ML13358A3732013-12-31031 December 2013 Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus ML13200A1962013-07-31031 July 2013 ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. ML13200A1922013-07-31031 July 2013 ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. ML13200A1952013-06-30030 June 2013 ANP-3213(NP), Rev. 1, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (Epu/Mellla). ML13200A1902013-06-30030 June 2013 ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello. ML13191B1282013-06-26026 June 2013 NEDO-33820, Revision 0, Monticello Nuclear Generating Plant Upper Shelf Energy Evaluation for Plate C2220 Material for 54 EFPY, Enclosure 5 ML13200A2002013-05-31031 May 2013 ANP-3139(NP), Rev. 1, Nuclear Fuel Design Report Monticello Cycle 28 Atrium 10XM Fuel. ML13200A1992013-05-31031 May 2013 ANP-3221NP, Rev. 0, Fuel Rod Thermal-Mechanical Design for Monticello Atrium 10XM Fuel Assemblies, Cycle 28. ML13200A1972013-05-31031 May 2013 ANP-3212(NP), Rev. 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel. ML13200A1942013-05-31031 May 2013 ANP-3215(NP), Rev. 0, Monticello Fuel Transition Cycle 28 Fuel Cycle Design (Epu/Mellla). ML13092A3492013-03-29029 March 2013 Enclosure 10 to L-MT-13-029 - WCAP-17548-NP, Revision 1, Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data. L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project.2013-03-29029 March 2013 Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project. ML13092A3502013-03-29029 March 2013 Enclosure 11 to L-MT-13-029 - WCAP-17251-NP, Revision 1, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report. ML13092A3512013-03-29029 March 2013 Enclosure 12 to L-MT-13-029 - WCAP-17252-NP, Revision 3, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project. ML13092A3522013-03-29029 March 2013 Enclosure 13 to L-MT-13-029 - WCAP-17549-NP, Revision 1, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using Ace. ML13037A2012013-01-31031 January 2013 NEDO-33800, Rev. 0, Monticello Nuclear Generating Plant Automatic Depressurization System Bypass Timer Extended Power Uprate. ML13200A1892012-11-30030 November 2012 ANP-2637, Rev. 4, Boiling Water Reactor Licensing Methodology Compendium. ML13200A1912012-10-31031 October 2012 ANP-3119NP, Rev. 0, Mechanical Design Report for Monticello Atrium 10XM Fuel Assemblies. ML12300A2202012-10-31031 October 2012 Attachment 10: BWROG-TP-12-018, Revision 0, Task 3 - Pump Operation at Reduced Npsha Conditions (Cvds Pump) L-MT-12-082, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure2012-09-28028 September 2012 Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure ML12307A4342012-08-31031 August 2012 ANP-3113(NP), Rev. 0, Monticello Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for Atrium 10XM Fuel. ML12300A2242012-08-31031 August 2012 Attachment 13: BWROG-TP-12-014, Revision 0, Task 6 - Npshr Test Instrument Inaccuracy Effect on Published Results (Cvds Pump) ML12300A2222012-08-31031 August 2012 Attachment 12: BWROG-TP-12-013, Revision 0, Task 5 - Effects of Non-Condensible Gases on Seals (Cvds Pump) ML12300A2212012-08-31031 August 2012 Attachment 11: BWROG-TP-12-012, Revision 0, Task 4 - Operation in the Maximum Erosion Rate Zone (Cvds Pump) ML12300A2192012-08-31031 August 2012 Attachment 9: BWROG-TP-12-011, Revision 0, Task 2 - Equation for Pump Speed Correction (Cvds Pump) 2022-06-06 |
Text
L-MT-14-075 ENCLOSURE 6 WESTINGHOUSE LETTER REPORT, LTR-BWR-ENG-14-037-NP NON-PROPRIETARY ALTERNATE POWER ASCENSION PROCESS 2 pages follow Westinghouse Non-Proprietary Class 3 LTR-BWR-ENG-14-037-NP Alternate Power Ascension Process September 5, 2014 Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066 USA© 2014 Westinghouse Electric Company LLC All Rights Reserved Westinghouse Non-Proprietary Class 3 LTR-B WR-ENG- 14-037-NP Proposed Alternate Approach The approach for EPU power ascension shall use the process described below.General[.rc Condition Action Pressure Load < Level 2 Increase power to the next level Level 2 < Pressure Load < Level I Perform a stress analysis at the current power level Pressure Load > Level I Reduce power to the previous step, engineering evaluation, and consideration of mitigation actions Baseline Limit Curves During the initial or baseline operating conditions (1775 MWt), data are measured with the MSL strain gauges, and these data are used to derive the MSL alternating pressure signature at the current power level. The PSD of the derived MSL pressures is calculated, and compared to the two limit curves, "L 1" and "L2", respectively.
Power Ascension Limit Curves I T, C I.rC I.rc I
Retrieved from "https://kanterella.com/w/index.php?title=ML14269A325&oldid=869210"