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 Issue dateTitleTopic
BW230054, Attachment 2: MDMP Deviation Form17 November 2023Attachment 2: MDMP Deviation Form
ML23321A04517 November 2023EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 7529 September 2023Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75Boric Acid
VT-2
Finite Element Analysis
Liquid penetrant
Exclusive Use
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments7 August 2023Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License AmendmentsCyber Security
Safeguards Contingency Plan
Fire Protection Program
ML23192A44731 July 2023Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards InformationProbabilistic Risk Assessment
Fukushima Dai-Ichi
Earthquake
1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation29 June 2023Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23180A10820 June 2023ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary ReportCyber Security
Aging Management
Turbine Missile
1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version20 June 2023Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version
RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 1020 April 2023Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10Non-Destructive Examination
Code Reconciliation
ML23025A07525 January 2023American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle .
ML23088A21731 December 2022Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022Boric Acid
Nondestructive Examination
Liquid penetrant
ML22363A39228 December 2022Cycle 14 Mellla+ Eigenvalue Tracking Data
CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval12 December 2022Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing IntervalSafe Shutdown
Stroke time
Incorporated by reference
Scram Discharge Volume
Weak link
CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)9 December 2022to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Abnormal operational transient
Feedwater Controller Failure
MELLLA
BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 920 October 2022Pressure and Temperature Limits Report (Ptlr), Revision 9Hydrostatic
Pressure and Temperature Limits Report
BYRON 2022-0071, Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment13 October 2022Materials Reliability Program: Topical Report for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-335, Revision 3-A) Final Causal Report and Description of Corrective Action Assignment
CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information18 July 2022Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional InformationStroke time
Anticipated operational occurrence
Abnormal operational transient
L-22-154, Pressure and Temperature Limits Report Revision6 July 2022Pressure and Temperature Limits Report RevisionPressure and Temperature Limits Report
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits30 June 2022Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air SuitsMururoa
RA-22-0165, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 249 June 2022Inservice Inspection Program Owner'S Activity Report for Refueling Outage 24
RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds7 June 2022License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet WeldsNon-Destructive Examination
Code Reconciliation
ML22154A4043 June 2022Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data
CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use27 May 2022to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use
RA-22-0134, Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data25 May 2022Unit 1 Cycle 23 Mellla+ Eigenvalue Tracking Data
RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors8 April 2022Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods24 February 2022Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third PeriodsVT-2
Large early release frequency
Liquid penetrant
L-22-054, Steam Generator Inspection Report- Fall 2021 Refueling Outage10 February 2022Steam Generator Inspection Report- Fall 2021 Refueling OutageNondestructive Examination
ML21349A10615 December 2021Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273Non-Destructive Examination
Weld Overlay
Surveillance Frequency Control Program
Through-Wall Leak
BW210065, Pressure and Temperature Limits Report, Revision 827 October 2021Pressure and Temperature Limits Report, Revision 8Hydrostatic
Pressure and Temperature Limits Report
RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors22 October 2021Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis6 October 2021Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis
CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L6 October 2021Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L
ML21277A1234 October 2021Submittal of Browns Ferry Unit 2 Reactor Pressure Vessel Vertical Weld Flaw EvaluationFinite Element Analysis
ML21272A30330 September 2021Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise ReportSafe Shutdown
Ultimate heat sink
Anticipated operational occurrence
Probabilistic Risk Assessment
Tristructural Isotropic
ML21246A29429 September 2021Enclosufinal Ea/Fonsi for Tva'S Initial and Updated Triennial Decommissioning Funding Plans for Browns Ferry Nuclear Plant ISFSIsDecommissioning Funding Plan
Authorized possession limits
ML21246A29529 September 2021Memo to FileDecommissioning Funding Plan
RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections1 September 2021R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius SectionsFinite Element Analysis
Aging Management
IR 05000334/20210051 September 2021Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005)Fitness for Duty
Operator Manual Action
Cyber Security
Open Phase Condition
Exemption Request
Power-Operated Valves
COVID-19
ML21237A05125 August 2021Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water ReactorsNon-Destructive Examination
Safe Shutdown Earthquake
Enforcement Discretion
Probabilistic Risk Assessment
Cyber Security
Missed surveillance
Significance Determination Process
Surveillance Frequency Control Program
Large early release frequency
Time Critical Operator Action
Low Safety Significance Issue Resolution
Generic Issues Program
Fire Protection Program
BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval30 June 2021ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year IntervalSafe Shutdown
ML21081A19230 June 2021Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code AssessmentAnticipated operational occurrence
Nondestructive Examination
Exemption Request
Tristructural Isotropic
2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval29 June 2021Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth IntervalVT-2
RA-21-0198, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2521 June 2021Inservice Inspection Program Owner'S Activity Report for Refueling Outage 25
RA-21-0176, Cycle 24 Mellla+ Eigenvalue Tracking Data7 June 2021Cycle 24 Mellla+ Eigenvalue Tracking Data
ML21131A02417 May 2021Review of Reactor Pressure Vessel Capsule Y Analysis Report
RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld12 May 2021Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel WeldHydrostatic
VT-2
Finite Element Analysis
0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes10 May 2021Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes
ML21272A3381 April 2021Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise ReportUltimate heat sink
Anticipated operational occurrence
Internal Flooding
Probabilistic Risk Assessment
Design basis earthquake
Maintenance Rule Program
Turbine Missile
Fatality
ML21090A03331 March 2021Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1)Non-Destructive Examination
ML21083A13623 March 2021Completed Activities
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