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 Issue dateTitleTopic
ML11178A02423 June 2011Brown, Units 1, 2, and 3, Sequoyah, Units 1 and 2, and Watts Bar, Unit 1 - Response to Request for Additional Information Regarding Decommissioning Funding Status Report
ML11166A13422 June 2011Meeting Summary with the Beyond Nuclear Petitioners Regarding Their 2.206 Petition to Suspend Operating Licenses (Ols) of General Electric (GE) Boiling Water Reactors (Bwrs) Mark I (Bwrs)
ML11178A00422 June 2011NRR E-mail Capture - June 4, 2011, Petition Enforcement Action Against TVA
ML11173011922 June 2011NRC Response to Appeal of Browns Ferry Significance Determination of a Red Finding and Reply to Notice of ViolationSignificance Determination Process
ML11178A00521 June 2011NRR E-mail Capture - June 4, 2011, Petition Enforcement Action Against TVA
ML11171A20915 June 2011Revision to Response to NRC Request for Additional Information Regarding Extending Completion Times for Technical Specification 3.8.1, TS-468
ML11171A03715 June 2011BWRVIP-25 Core Plate Bolt Stress Analysis
TAC:ME170615 June 2011
ML11147A09513 June 2011Relief from the Requirements to the ASME CodeProbabilistic Risk Assessment
Nondestructive Examination
Incorporated by reference
Large early release frequency
Exemption Request
ML11164046313 June 2011Summary of Category 1 Public Meeting with TVA, Browns Ferry to Present Annual AssessmentHigh winds
ML11166A11011 June 2011G20110449/LTR-11-0345/EDATS: SECY-2011-0343 - Thomas Saporito Email 2.206 - Tennessee Valley Authority - Browns Ferry Nuclear Plant and Tom Klgore
TAC:ME651711 June 2011
ML11167A09810 June 20112 & 3; Sequoyah, Units 1 & 2 and Watts Bar, Units 1 & 2 - Response to NRC Bulletin 2011-01, Mitigating StrategiesB.5.b Mitigating Strategies
Earthquake
ML11159A05310 June 2011Request for Additional Information Regarding Relief from Weld Examination Coverage Requirements, Request for Relief 3-ISI-26
TAC:ME54009 June 2011
ML11154A0379 June 2011Request for Additional Information Regarding Relief Request 3-ISI-25Nondestructive Examination
ML1119304328 June 2011Appeal of Final Significance Determination of a Red Finding and Reply to a Notice of Violation; EA-11-018Safe Shutdown
Stroke time
Enforcement Discretion
VT-2
Significance Determination Process
Cold shutdown justification
Fire Protection Program
Flow Induced Vibration
ML1121500968 June 2011Appeal of Final Significance Determination of a Red Finding and Reply to a Notice of Violation; EA-11-018Safe Shutdown
Stroke time
Enforcement Discretion
Significance Determination Process
Flow Induced Vibration
ML11167A1148 June 2011Transcript of 10 CFR 2.206 Petition Review Board Conference Call Re GE Mark 1 Bwrs, June 08, 2011, Pages 1-74Earthquake
Hardened vent
Chernobyl
Backfit
ML11160A2057 June 2011Response to NRC Annual Assessment Letter
ML1116000777 June 2011Response to Request for Regulatory Conference or Public Management Meeting
ML11159A0417 June 2011NRR E-mail Capture - Audit Results Summary Report Supporting TAC ME3775 - BF1 Areva Fuel Transition and Related BF2/3 Request
ML1115401933 June 2011Response to Disputed Notice of Violation (EA-11-012)Time of Discovery
Past operability
ML11158A0173 June 2011Submittal of Annual Report of Changes or Errors Discovered in the Emergency Core Cooling System Evaluation Model
ML1115403882 June 201108/02-03/2011 Meeting Announcement - 2011 U.S. Nuclear Regulatory Commission (NRC) Initial Examination Writers Workshop
ML1119304232 June 2011Request for Regulatory Conference or Public Management MeetingSafe Shutdown
Fire Barrier
Stroke time
Probabilistic Risk Assessment
Operator Manual Action
Finite Element Analysis
Significance Determination Process
ML1115303282 June 2011Completion of Temporary Instruction (Ti) 184, Availability and Readiness Inspection of Severe Accident Mitigation Guidelines (Samgs) at Region II Facilities - RevisionSevere Accident Management Guideline
B.5.b Mitigating Strategies
ML11145A06627 May 2011Brown Ferry Nuclear Plant, Units 2 & 3 - Request for Additional Information Regarding a Request to Eliminate Low Pressure Coolant Injection Pump Motor Generator Sets (TAC ME5796 and ME5799)
ML11146051126 May 2011NRC Reply to Browns Ferry November 2010 Letter Regarding Response to Inspection Report No 2010004 and EA 10-215
ML11122A11324 May 2011RAI Regarding Decommissioning Funding Status Report (TAC Nos. ME5455, ME5456, ME5457, ME5535, ME5536, and 5551)
TAC:ME545524 May 2011
TAC:ME502620 May 2011
IR 05000259/201140220 May 2011IR 05000259-11-402, IR 0500260-11-402, and IR 05000296-11-402, on 02/18/2011, (Corporate Office) & 04/21/2011, (K.Polson & Members Staff at Plant), Browns Ferry Nuclear Plant, NRC Security InspectionSignificance Determination Process
Affidavit
Press Release-II-11-037, NRC Schedules Public Meeting for May 31 to Discuss Performance of Browns Ferry Nuclear Power Plant18 May 2011Press Release-II-11-037: NRC Schedules Public Meeting for May 31 to Discuss Performance of Browns Ferry Nuclear Power Plant
ML11108A03415 May 2011Resumption of Review of the Proposed Extended Power Uprate Amendment (TAC Nos. MD5262, MD5263, and MD5264) (TS-431)
ML11108A05813 May 2011Request to Use Subsequent Edition of ASME Code Repair and Replacement ActivitiesNon-Destructive Examination
Incorporated by reference
IR 05000259/201100213 May 2011IR 05000259-11-002, 05000260-11-002, 05000296-11-002 & 07200052-11-002, on 01/01/2011 - 03/31/2011, Browns Ferry, Units 1, 2 & 3, NRC Integrated Inspection and Notice of ViolationSafe Shutdown
Time of Discovery
Packing leak
High Radiation Area
Mission time
Fire Barrier
Weld Overlay
Post Accident Monitoring
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Operator Manual Action
Cyber Security
Condition Adverse to Quality
Significance Determination Process
Foreign Material Exclusion
Operability Determination
Severe Accident Management Guideline
Liquid penetrant
Fatigue Rule
Scaffolding
Grace period
Downpower
Flow Induced Vibration
Weak link
Power Uprate
IR 05000259/201100913 May 2011NRC Temporary Instruction 2515/183 Inspection Report 05000259/2011009, 05000260/2011009, 05000296/2011009Internal Flooding
B.5.b
Seismically rugged
Severe Accident Management Guideline
Earthquake
ML11126A09612 May 2011Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors
ML11137A19912 May 2011Response to NRC Request for Additional Information Regarding to Transition to Areva Fuel
ML11131066711 May 2011Notice of Forthcoming Public Meeting to Present the Annual Assessment of the Browns Ferry Nuclear Plant Performance and to Provide Opportunities to Discuss with the Public the NRC Reactor Oversight Process
Press Release-II-11-034, NRC Finds Valve Failure at Browns Ferry to Be of High Safety Significance10 May 2011Press Release-II-11-034: NRC Finds Valve Failure at Browns Ferry to Be of High Safety Significance
ML11130025510 May 2011Security Agreement
ML11132A12110 May 2011Boiling Water Reactor Vessel and Internals Project - Notification of Deviation from BWRVIP-25, BWR Core Plate Inspection and Flaw Evaluation Guidelines.Safe Shutdown
EVT-1
ML1109805389 May 2011Cyber Security Plan Implementation ScheduleCyber Security
ML1114003739 May 2011FEMA Ltr: Statement of Continuation of Reasonable Assurance for Browns Ferry Nuclear Power Plant Restart
ML1112904829 May 2011EA-11-018, Browns Ferry, Final Signficance Determination of Red Finding, Notice of Violation and Assessment Follow-up Letter 2011008Safe Shutdown
Probabilistic Risk Assessment
Operator Manual Action
Functionality Assessment
Significance Determination Process
ML1113101319 May 2011Statement of Continuation of Reasonable Assurance for Browns Ferry Nuclear Power Plant Restart
ML11118A1546 May 2011Request for Additional Information Regarding Completion Time Extension for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D (TAC No. ME5036, ME5037, and ME5038)Anticipated operational occurrence
Preplanned Activity
ML11132A1185 May 2011Bellefonte, Units 1 and 2 - Proposed Regulatory Framework for the Possible Completion of Construction ActivitiesSafe Shutdown
Boric Acid
Fitness for Duty
Shutdown Margin
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Stroke time
Commercial Grade Dedication
Probabilistic Risk Assessment
Coatings
Anchor Darling
VT-2
Cyber Security
Scram Discharge Volume
Process Control Program
Safeguards Contingency Plan
Hemyc
Control of Heavy Loads
Turbine Missile
Fuel cladding
Fire Protection Program
Brachytherapy
Uranium Hexafluoride