L-2022-168, and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report | 26 October 2022 | and Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report | |
L-2020-159, 10 CFR 50.59 Evaluation and Commitment Change Summary Report | 4 October 2022 | 10 CFR 50.59 Evaluation and Commitment Change Summary Report | Shutdown Margin |
L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 | 29 July 2022 | Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 | Safe Shutdown Boric Acid High winds Reactor Vessel Water Level Mission time Safe Shutdown Earthquake Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Operating Basis Earthquake FLEX Foreign Material Exclusion Large early release frequency Severe Accident Management Guideline Exemption Request Earthquake Maintenance Rule Program Turbine Missile Fuel cladding Scaffolding |
ML22140A143 | 20 May 2022 | Enclosure 4 - Information Supporting Justification of Excluding Sources of Risk Not Addressed by PRA Models | Safe Shutdown High winds Ultimate heat sink Internal Flooding Hydrostatic Probabilistic Risk Assessment FLEX Fukushima Dai-Ichi Turbine Missile |
ML22140A142 | 20 May 2022 | Enclosure 1 - List of Revised Required Actions to Corresponding PRA Functions and Additional Supporting Information | Internal Flooding Probabilistic Risk Assessment |
ML22140A141 | 20 May 2022 | Attachment 6 - Point Beach RICT Program Pre-Implementation Items | |
ML22140A135 | 20 May 2022 | RPS Instrumentation | High Radiation Area Hydrostatic Surveillance Frequency Control Program |
ML22140A138 | 20 May 2022 | Containment Isolation Valves | Safe Shutdown Offsite Circuit |
ML22140A133 | 20 May 2022 | Attachment 1 - Evaluation of the Proposed Changes | Probabilistic Risk Assessment Large early release frequency |
NRC 2022-0007, Enclosure 11 - Monitoring Program | 20 May 2022 | Enclosure 11 - Monitoring Program | Fire Barrier Probabilistic Risk Assessment Large early release frequency |
ML22140A144 | 20 May 2022 | Enclosure 8 - Attributes of the Configuration Risk Management Model | Internal Flooding Probabilistic Risk Assessment Large early release frequency |
ML22140A136 | 20 May 2022 | Containment Isolation Valves | High Radiation Area Surveillance Frequency Control Program |
ML22140A139 | 20 May 2022 | Attachment 4 - Cross-Reference of TSTF-505, Revision 2, and Point Beach Proposed Changes | |
ML22140A140 | 20 May 2022 | Attachment 5 - Evaluation of Plant-Specific Variations | Safe Shutdown Emergency Lighting Earthquake Offsite Circuit |
NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report | 21 January 2021 | Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report | Finite Element Analysis Aging Management Liquid penetrant |
ML21008A017 | 25 October 2020 | Revised ANS Design Report | |
NRC 2020-0001, Pressure Temperature Limits Report (PTLR) | 9 January 2020 | Pressure Temperature Limits Report (PTLR) | Hydrostatic Pressure and Temperature Limits Report |
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 | 29 August 2019 | Relief Request 2-RR-17 Extension of the Primary Nozzle Dissimilar Metal (DM) Weld Inspection Interval. with LTR-SDA-19-071-NP Enclosure | Safe Shutdown Earthquake Weld Overlay Nondestructive Examination VT-2 Finite Element Analysis Earthquake Liquid penetrant Dissimilar Metal Weld DM weld |
L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds | 19 March 2019 | Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds | Nondestructive Examination Dissimilar Metal Weld |
NRC 2018-0017, 10 CFR 50.59 Evaluation and Commitment Change Summary Report | 2 May 2018 | 10 CFR 50.59 Evaluation and Commitment Change Summary Report | Multiple Spurious Operation FLEX |
NRC 2017-0037, High Frequency Seismic Evaluation Confirmation Report | 2 August 2017 | High Frequency Seismic Evaluation Confirmation Report | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Seismically rugged Earthquake Coast down |
NRC 2017-0032, Focused Evaluation for Local Intense Precipitation | 22 June 2017 | Focused Evaluation for Local Intense Precipitation | Safe Shutdown Ultimate heat sink FLEX Fukushima Dai-Ichi Flooding Focused Evaluation |
ML13338A510 | 27 January 2014 | Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Tornado Missile Protection Frazil ice Battery sizing B.5.b Mitigating Strategies Earthquake |
ML14006A187 | 10 January 2014 | Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Point Beach Station, Units 1 and 2, TAC Nos.: MF0725 and MF0726 | Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Tornado Missile Protection Frazil ice Battery sizing B.5.b Mitigating Strategies Earthquake |
ML13193A032 | 11 July 2013 | Additional Equipment Height Information with Vulnerability to Flood Waters | |
NRC 2013-0057, Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 | 3 July 2013 | Filing of Owner'S Lnservice Inspection Summary Report IWE Class Mc and Iwl Class CC for Point Beach Nuclear Plant Refueling Outage U1 R34 | |
NRC 2012-0101, NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic | 26 November 2012 | NextEra Energy Point Beach, LLC Response to 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic | |
ML14006A319 | 31 March 2010 | LTR-PAFM-10-50-NP, Rev. 0, Section XI Flaw Evaluation of Indication Recorded on RC-32-MRCL-ALL-03 of the Point Beach Unit 1 Inlet Nozzle to Pipe Weld. | Aging Management Dissimilar Metal Weld |
NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation | 3 March 2010 | License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation | Safe Shutdown Mission time |
ML093570415 | 31 December 2009 | WEP-09-133 Np, Point Beach Unit 1 & Unit 2 (Wep/Wis) Extended Power Uprate License Amendment Request Responses to Request for Additional Information. | Boric Acid |
ML091250566 | 7 April 2009 | Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Introduction Through Chapter 2, Section 2.5.7 | |
ML091250569 | 7 April 2009 | Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Chapter 2, Section 2.5.8 Through Appendices | |
ML082190013 | 7 August 2008 | Monthly Operating Reports Second Quarter 2008 | Reserve Station Service Transformer Power change |
ML082240686 | 30 June 2008 | WCAP-16541-NP, Revision 2, Spent Fuel Pool Criticality Safety Analysis. | |
NRC 2008-0029, Pressure and Temperature Limits Report | 30 May 2008 | Pressure and Temperature Limits Report | Hydrostatic Pressure and Temperature Limits Report |
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 | 28 May 2008 | 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 | Safe Shutdown Earthquake Nondestructive Examination Finite Element Analysis |
NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report | 13 June 2007 | Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report | Hydrostatic Pressure and Temperature Limits Report |
NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program | 11 July 2006 | LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program | High Radiation Area Nondestructive Examination Finite Element Analysis |
NRC 2006-0054, Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis | 6 June 2006 | Public Version, Request for Review of Reactor Vessel Toughness Fracture Mechanics Analysis | |
ML060040019 | 14 December 2005 | Westinghouse LTR-RCDA-873-NP Attachment Point Beach, Unit 1 - Reactor Vessel Upper Closure Head Volume Best-Estimate Mean Fluid Temperature (Non-Proprietary) | |
ML053320312 | 18 November 2005 | Reactor Vessel CMTRs (Non-Proprietary) | |
NRC 2005-0117, Request for Withholding of Proprietary Information from Public Disclosure | 7 September 2005 | Request for Withholding of Proprietary Information from Public Disclosure | Finite Element Analysis Power Uprate Affidavit |
NRC 2005-0068, Submittal of Supporting Analyses Regarding Control of Heavy Loads | 3 June 2005 | Submittal of Supporting Analyses Regarding Control of Heavy Loads | Finite Element Analysis Control of Heavy Loads |
ML043570017 | 14 December 2004 | from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations | Time of Discovery Aging Management Through-Wall Leak Scaffolding |
ML051400268 | 8 October 2004 | Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material | Safe Shutdown Health Physics Network High winds Reactor Vessel Water Level Ultimate heat sink Offsite Dose Calculation Manual Internal Flooding Operating Basis Earthquake Nuclear Accident Reporting System Earthquake Fuel cladding Pressure Boundary Leakage Power change |
NRC 2004-0004, Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 2004 | 30 August 2004 | Fitness-For-Duty (FFD) Program for Six Month Period Ending June 30, 2004 | Fitness for Duty |
NRC 2004-0081, Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 4 | 13 August 2004 | Transmittal of Point Beach Nuclear Plant, Units 1 and 2, Excellence Plan - Revision 4 | Safe Shutdown Boric Acid Probabilistic Risk Assessment Condition Adverse to Quality |
ML042660313 | 31 July 2004 | BAW-2467NP, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessel of Point Beach Units I and 2 for Extended Life Through 53 Effective Full Power Years. | |
ML050880062 | 7 May 2004 | Licensee Procedure, HPIP 4.58, Issuance of Respiratory Equipment Revision 14 | |
ML050880043 | 30 April 2004 | NMC Incident Response Team for Issues Encountered During Unit 1 Reduced Inventory and Nozzle Dam Installation at Pbnp | |