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Issue date | Title | |
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ML20300A224 | 17 November 2020 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident |
ML19204A287 | 28 August 2019 | Approval of a Certified Fuel Handler Training and Retraining Program |
ML18212A232 | 26 July 2018 | Response 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 |
ML18212A229 | 26 July 2018 | Response 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 |
ML17363A071 | 15 December 2017 | Attachment 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 2 | 15 December 2017 | Attachment 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 Operations | 19 August 2016 | 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 Operations |
ML15174A257 | 1 September 2015 | Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events |
ML14111A147 | 9 May 2014 | Seismic 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 |
ML13309A230 | 30 September 2013 | Transcript 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) |
ML13044A561 | 1 March 2013 | Request 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 |
ML12054A735 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12054A694 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents |
ML12054A679 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation |
ML12056A045 | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12056A044 | 12 March 2012 | 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 Status |
ML12056A043 | 12 March 2012 | Order 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 Events | 12 March 2012 | Order 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 Status | 12 March 2012 | 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 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 Containments | 12 March 2012 | Order 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 1971 | 14 July 2011 | 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 1971 |
ML11167A114 | 8 June 2011 | Transcript 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 2011 | Submittal 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 2007 | Comment (11) of D. E. Grissette, on Behalf of Florida Power & Light Company on Draft Regulatory Guide DG-5019, Reporting of Safeguards Events. |
ML072530614 | 21 September 2007 | Public Meeting Summary on the Reactor Oversight Process |
L-2006-067, Request for Approval of FPL Quality Assurance Topical Report | 31 March 2006 | Request for Approval of FPL Quality Assurance Topical Report |
ML053430121 | 2 December 2005 | Comment (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 Power | 13 June 2005 | 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 Power |
ML031110449 | 13 October 1999 | Relaxation 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 Changes | 13 October 1999 | Relaxation 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 Encl | 25 June 1999 | Responds 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 1983-11 | 24 June 1999 | NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis |
ML20206N755 | 13 May 1999 | Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves |
NRC Generic Letter 1998-01 | 14 January 1999 | NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants |
NRC Generic Letter 1998-04 | 14 July 1998 | NRC 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 1998-02 | 28 May 1998 | NRC 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 Improvement | 22 May 1998 | 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 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 Judgment | 20 February 1998 | 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 Judgment |
NRC Generic Letter 1997-06 | 30 December 1997 | NRC Generic Letter 1997-006: Degradation of Steam Generator Internals |
NRC Generic Letter 1997-05 | 17 December 1997 | NRC 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 1971 | 25 November 1997 | 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 1971 |
NRC Generic Letter 1997-04 | 30 September 1997 | NRC 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 1997-02 | 15 May 1997 | NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report |
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents | 24 February 1997 | Implementation of a New Constraint on Radioactive Air Effluents |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program |
ML20129F674 | 24 September 1996 | Informs That Staff Has Completed Detailed Review of Sfsp Safety Issues & Forwards Results for Review |
NRC Generic Letter 1996-05 | 18 September 1996 | NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves |
NRC Generic Letter 1996-04 | 26 June 1996 | NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks |
NRC Generic Letter 1996-03 | 31 January 1996 | NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits |
NRC Generic Letter 1989-10 | 24 January 1996 | NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors |