Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
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
BW230054, Attachment 2: MDMP Deviation Form17 November 2023Attachment 2: MDMP Deviation Form
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
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 .
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
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
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
ML21349A10615 December 2021Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273Non-Destructive Examination
Weld Overlay
Surveillance Frequency Control Program
Through-Wall Leak
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
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
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
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
ML21131A02417 May 2021Review of Reactor Pressure Vessel Capsule Y Analysis Report
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
ML21083A13623 March 2021Completed Activities
ML21083A13722 March 2021NEIMA Reporting
ML21083A13822 March 2021Rulemaking
ML21083A13922 March 2021Strategy 1
ML21083A14022 March 2021Strategy 2
ML21083A14422 March 2021Strategy 6
ML21083A14322 March 2021Strategy 5
ML21083A14222 March 2021Strategy 4
ML21083A14122 March 2021Strategy 3
ML21055A05810 March 2021Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports
RA-20-0353, Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)24 February 2021Proposed Alternative to ASME Boiler & Pressure Vessel Code Section XI Requirements for Repair/Replacement of Service Water (SW) System Buried Piping in Accordance with 10 CFR 50.55a(z)(1)Fitness for Duty
Ultimate heat sink
Non-Destructive Examination
Safe Shutdown Earthquake
Coatings
Operating Basis Earthquake
Finite Element Analysis
Foreign Material Exclusion
Exemption Request
Affidavit
L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks1 February 2021Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks
ML21014A26714 January 2021Preapplication Engagement to Optimize Application Reviews January 12 Version - CopyProbabilistic Risk Assessment
Exemption Request
ML20303A17523 October 2020Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic22 September 2020Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 PandemicExemption Request
Pandemic
Coronavirus
1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values19 March 2020Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable ValuesOvertravel
RA-19-0479, Supplement to Request for License Amendment Regarding Application of Advanced Framatome Methodologies31 December 2019Supplement to Request for License Amendment Regarding Application of Advanced Framatome MethodologiesAnticipated operational occurrence
Affidavit
0CAN121901, Summary of Lost Specimens Investigation Report3 December 2019Summary of Lost Specimens Investigation ReportFitness for Duty
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.4630 May 2019Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46
L-19-053, Emergency Response Data System Data Point Library Update20 February 2019Emergency Response Data System Data Point Library Update
ML18192C15218 July 2018Review of Fall 2017 Steam Generator Tube Inservice Inspection Report
L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models18 June 2018Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation ModelsFuel cladding
CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions31 May 2018Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident ConditionsFLEX
Hardened vent
BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D11 April 2018Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4DWeld Overlay
Dissimilar Metal Weld
L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.15 March 2018Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.Safe Shutdown
Unanalyzed Condition
Boric Acid
Enforcement Discretion
Probabilistic Risk Assessment
FLEX
Tornado Generated Missile
Tornado Missile Protection
Tornado Missile Risk Evaluator
ML17214A02912 February 2018Staff Assessment of Flooding Focused Evaluation (CAC Nos. MF9809 and MF9810)FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
ML17355A56121 December 2017Ltr. 12/21/17 Response to Disputed Non-Cited Violation Documented in Byron Station, Units 1 and 2 - Evaluations of Changes, Tests, and Experiments Baseline Inspection Report 05000454/2017009; 05000455/2017009 (DRS-N.Feliz-Adorno)Probabilistic Risk Assessment
Surveillance Frequency Control Program
ML17291A00926 October 2017Staff Assessment Regarding Program Plan for Aging Management for Reactor Vessel Internals (CAC No. MF8155; EPID L-2016-LRO-0001)Aging Management
ML17167A08328 June 2017Arkansas Nuclear One, Unit 2 - Review of Commitment Submittal for License Renewal Regarding Nickel-Based Alloy Aging Management Program Plan (CAC No. MF8154)Aging Management
ML17170A07315 June 2017Report Pursuant to 10 CFR 71.95 (a)(3) and (B) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233Weak link
RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors7 April 2017Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML17033B1642 February 2017American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement - Cycle 11 Operation Programs
2CAN011703, Submittal of Additional Protocol Report26 January 2017Submittal of Additional Protocol Report
ML17024A03631 December 2016Operating Data Report for 2016Temporary Modification
Biofouling
Power change
Coast down
0CAN121602, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 330 December 2016Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3Ultimate heat sink
FLEX
Fukushima Dai-Ichi
Earthquake
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BCategory:Miscellaneous-5D-5D-20-5B-5BSite::Beaver-20Valley-7C-7CBrowns-20Ferry-7C-7CByron-7C-7CArkansas-20Nuclear-7C-7CBraidwood-7C-7CBrunswick-7C-7CBellefonte-5D-5D/-3FIssue-20date/-3FTitle/-3FTopic/mainlabel%3D/order%3D-20descending/sort%3D-20Issue-20date/offset%3D0/format%3Dtable/searchlabel%3D-5BTable-20view-5D"