Pages that link to "NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure"
Jump to navigation
Jump to search
The following pages link to NRC 2019-0026, Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure:
Displayed 50 items.
- NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation (← links)
- NRC 2009-0082, Background Information to Support License Amendment Request 261, ATC Lnterim Operation and Impacts Re-Study, Appendixes B - J (← links)
- NRC 2008-0029, Pressure and Temperature Limits Report (← links)
- NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair (← links)
- NRC 2007-0093, Response to Request for Additional Information 10 CFR 50.55a Requests Relief Request RR-19 and RR-20 Associated with Examination of the Reactor Pressure Vessels Fourth Ten-Year Inservice Inspection Program Interval (← links)
- NRC 2007-0092, Pressure and Temperature Limits Report (← links)
- NRC 2007-0083, Spring 2007 Unit 1 (U1R30) Steam Generator Tube Inspection Report (← links)
- NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report (← links)
- NRC 2006-0054, Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis (← links)
- NRC 2006-0020, Fitness-For-Duty (FFD) Program Report (← links)
- NRC 2005-0128, Confirmatory Action Letter CAL 3-04-01, Excellence Plan - Revision 7 (← links)
- NRC 2019-0002, Refueling Outage U2R36 Owner'S Activity Report for Class 1, 2, 3 and Mc ISI Examinations (← links)
- ML060860028 (← links)
- RC-18-0128, (Vcsns), Unit 1 - NEI 12-06, Appendix H, Revision 4, H.4.5. Path 5: GMRS ≫ 2X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information (← links)
- L-17-222, (NEI) 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS ≫ 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information (← links)
- SBK-L-17135, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 4, H.4.4 Path 4: GMRS ≪ 2xSSE (← links)
- L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds (← links)
- NRC 2013-0061, CFR 50.59 Summary Report for 2012 (← links)
- RS-17-092, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 4, H.4.4 Path 4: GMRS ≪ 2xSSE (← links)
- BSEP 17-0069, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.4 Path 4:GMRS ≪ 2xSSE (← links)
- NRC-17-0053, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Appendix H, Revision 4, H.4.4 Path 4: GMRS ≪ 2xSSE (← links)
- NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program (← links)
- NRC 2013-0069, Supporting Documentation for July 22, 2013, Regulatory Conference to Discuss Inspection Report 05000266/2013011 and 05000301/2013011, Preliminary Yellow Finding (← links)
- L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report (← links)
- NRC 2019-0026 (redirect page) (← links)
- ML19241A492 (redirect page) (← links)
- ML19254F691 (← links)
- ML19339H747 (← links)
- ML22069B117 (← links)
- ML053320312 (← links)
- NRC 2005-0119, Post Accident Monitoring Instrumentation Report (← links)
- NRC 2005-0117, Request for Withholding of Proprietary Information from Public Disclosure (← links)
- NRC 2005-0094, Request for Review of Heavy Load Analysis (← links)
- NRC 2005-0072, to Request for Exigent Review of Heavy Load Analysis and Response to Request for Additional Information (← links)
- NRC 2005-0068, Submittal of Supporting Analyses Regarding Control of Heavy Loads (← links)
- ML051470086 (← links)
- NRC 2005-0060, Resolution of Safety-Related Questions Regarding Reactor Vessel Head Lift (← links)
- NRC 2005-0030, Supplement to Spring 2004 Unit 1 (Ul R28) Steam Generator Examination Report (← links)
- NRC 2005-0027, Fitness-For-Duty (FFD) Program (← links)
- NRC 2020-0001, Pressure Temperature Limits Report (PTLR) (← links)
- ML051400268 (← links)
- ML050950135 (← links)
- ML043570017 (← links)
- ML042660313 (← links)
- NRC 2004-0087, Supplement to Owner'S Inservice Inspection Summary Report Submitted for Point Beach Nuclear Plant Unit 1 Refueling Outage U1R27 (← links)
- ML042510283 (← links)
- NRC 2004-0081, Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 4 (← links)
- ML041310122 (← links)
- NRC 2004-0032, Excellence Plan, Revision 3 for Point Beach Nuclear Plant, Units I and 2 (← links)
- NRC 2004-0024, Submittal of Excellence Plan, Revision 2 (← links)
- NRC 2003-0046, Annual 10 CFR 50.59 Summary Report for 2002 (← links)
- ML051470063 (← links)
- NRC 2004-0059, Supplement 4 to Reactor Vessel Closure Head Penetration Repair and Flaw Characterization Relief Requests MR 02-018-1, Revision 1 and MR 02-018-2, Revision 1 (← links)