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 Issue dateTitle
ML20300A22417 November 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident
ML19204A28728 August 2019Approval of a Certified Fuel Handler Training and Retraining Program
ML18212A23226 July 2018Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa
ML18212A22926 July 2018Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa
ML17363A07115 December 2017Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 1 of 2
NG-17-0235, Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 1 of 215 December 2017Attachment 1: Duane Arnold Energy Center, License Amendment Request TSCR-166, Redline Markup of NEI 99-01, Revision 6. Part 1 of 2
L-2016-171, Comment (1) of Larry Nicholson, on Behalf of NextEra Energy and Florida Power and Light, on Consideration of Rulemaking to Address Prompt Remediation of Residual Radioactivity During Operations19 August 2016Comment (1) of Larry Nicholson, on Behalf of NextEra Energy and Florida Power and Light, on Consideration of Rulemaking to Address Prompt Remediation of Residual Radioactivity During Operations
ML15174A2571 September 2015Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights
ML13309A23030 September 2013Transcript of 10 CFR Petition Review Board Re(Garding) General Electric Mark I and II (Boiling Water Reactors) Bwrs, 09-30-2013, Pages 1-98(100)
ML13044A5611 March 2013Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Flooding Hazard Reevaluation for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML12054A73512 March 2012Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12054A69412 March 2012Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents
ML12054A67912 March 2012Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation
ML12056A04512 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
ML12056A04412 March 2012Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
ML12056A04312 March 2012Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events12 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status12 March 2012Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments12 March 2012Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 197114 July 2011G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971
ML11167A1148 June 2011Transcript of 10 CFR 2.206 Petition Review Board Conference Call Re GE Mark 1 Bwrs, June 08, 2011, Pages 1-74
NG-11-0117, Submittal of Proposed Changes to the Emergency Plan (TSCR-126)31 May 2011Submittal of Proposed Changes to the Emergency Plan (TSCR-126)
L-2007-147, Comment (11) of D. E. Grissette, on Behalf of Florida Power & Light Company on Draft Regulatory Guide DG-5019, Reporting of Safeguards Events.1 October 2007Comment (11) of D. E. Grissette, on Behalf of Florida Power & Light Company on Draft Regulatory Guide DG-5019, Reporting of Safeguards Events.
ML07253061421 September 2007Public Meeting Summary on the Reactor Oversight Process
L-2006-067, Request for Approval of FPL Quality Assurance Topical Report31 March 2006Request for Approval of FPL Quality Assurance Topical Report
ML0534301212 December 2005Comment (14) of Leonard L. Sueper on the Reactor Oversight Process
L-HU-05-014, Comment (14) of Edward J. Weinkam Re Draft Generic Letter 2005-XX: Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power13 June 2005Comment (14) of Edward J. Weinkam Re Draft Generic Letter 2005-XX: Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power
ML03111044913 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes13 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
NG-99-0859, Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl25 June 1999Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants,Per GL 98-01.Y2K Readiness Disclosure for Plant Encl
NRC Generic Letter 1983-1124 June 1999NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis
ML20206N75513 May 1999Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves
NRC Generic Letter 1998-0114 January 1999NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
NRC Generic Letter 1998-0414 July 1998NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
NRC Generic Letter 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
NG-98-0926, Comment Opposing Proposed Rule 10CFR50 on Codes & Standards:Ieee National Consensus Standard. Ies Utilities Believes Proposed Rule Will Impose Addl Costs & Vulnerabilities on Licensees W/No Substantial Improvement22 May 1998Comment Opposing Proposed Rule 10CFR50 on Codes & Standards:Ieee National Consensus Standard. Ies Utilities Believes Proposed Rule Will Impose Addl Costs & Vulnerabilities on Licensees W/No Substantial Improvement
NG-98-0329, Comments on Pr 10CFR50 Re Engineering Judgment for Activities or Evaluations of Components or Sys.Change to 10CFR50.55a Should Be Defined If NRC Concerned About Specific Application of Using Engineering Judgment20 February 1998Comments on Pr 10CFR50 Re Engineering Judgment for Activities or Evaluations of Components or Sys.Change to 10CFR50.55a Should Be Defined If NRC Concerned About Specific Application of Using Engineering Judgment
NRC Generic Letter 1997-0630 December 1997NRC Generic Letter 1997-006: Degradation of Steam Generator Internals
NRC Generic Letter 1997-0517 December 1997NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques
NG-97-2036, Comment on Proposed Rule 10CFR50.55(h) Re Draft RG DG-1042, Criteria for Safety Sys. Amended Rule Not Clear Regarding Application to Plants That Received Their Const Permits Prior to 197125 November 1997Comment on Proposed Rule 10CFR50.55(h) Re Draft RG DG-1042, Criteria for Safety Sys. Amended Rule Not Clear Regarding Application to Plants That Received Their Const Permits Prior to 1971
NRC Generic Letter 1997-0430 September 1997NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
NRC Generic Letter 1997-0215 May 1997NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents24 February 1997Implementation of a New Constraint on Radioactive Air Effluents
NRC Generic Letter 1995-0631 January 1997NRC Generic Letter 1995-006: Changes in Operator Licensing Program
ML20129F67424 September 1996Informs That Staff Has Completed Detailed Review of Sfsp Safety Issues & Forwards Results for Review
NRC Generic Letter 1996-0518 September 1996NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
NRC Generic Letter 1996-0426 June 1996NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks
NRC Generic Letter 1996-0331 January 1996NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits
NRC Generic Letter 1989-1024 January 1996NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors