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 Issue dateTitle
ML18120A35125 May 2018Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Chi Accident
ML16075A32916 March 2016OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations
ML15174A2571 September 2015Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events
ML15175A3006 August 2015Final Response to Task Interface Agreement 2015-01, Assessment of Three Mile Island Nuclear Station'S Use of a Non-Seismic Qualified Cleanup Path for the Borated Water Storage Tank
ML15049A15317 February 2015Speech-S-15-001: Prepared Remarks of NRC Chairman Stephen G. Burns Platts 11th Annual Nuclear Energy Conference February 17, 2015- Washington, D.C
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
ML14030A04620 February 2014Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1
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
ML12056A04512 March 2012Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
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
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
ML10312006912 January 2011Issuance of Amendment Request to Relocate Surveillance Frequencies to a Licensee Controlled Program
ML10078044823 November 2009Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event
ML0819202308 August 2008Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by Amergen Energy Company, LLC, for Renewal of the Operating License for Three Mile Island Nuclear Station Unit 1
ML0822000519 July 2008Comment (2) of David P. Helker, on Behalf of Exelon and Amergen, Concerning Draft Regulatory Guide DG-1195, Availability of Electric Power Sources.
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
ML03111044913 October 1999Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
NRC Generic Letter 1983-1124 June 1999NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis
NRC Generic Letter 1998-0114 January 1999NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
ML20198A51111 December 1998Comment Opposing Proposed Rule 10CFR50.65 Re Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants.Proposed Rulemaking Details Collaborative Efforts in That Rule Interjects Change
ML20195D59511 November 1998Forwards Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment
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
ML20199G83722 January 1998SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1
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
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
ML20134L03910 February 1997Forwards Response to Request for Info Per 10CFR50.54(f) Re Adequacy & Availability of Design Basis Info
NRC Generic Letter 1995-0631 January 1997NRC Generic Letter 1995-006: Changes in Operator Licensing Program
ML20128Q3813 October 1996Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues Documented in Encl Rept to Commission. Structure,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety
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
NRC Generic Letter 1996-0110 January 1996NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits
NRC Generic Letter 1995-1015 December 1995NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
NRC Generic Letter 1995-0717 August 1995NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
NRC Generic Letter 1995-0428 April 1995NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues
ML20080B49829 November 1994Appeals for Proposed Alternative to 10CFR50.55a(f)(4)(ii) for Extension of Current 10-yr IST Interval
ML0312004432 September 1994Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data
NRC Generic Letter 1994-0325 July 1994NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
NRC Generic Letter 1994-0211 July 1994NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors
NRC Generic Letter 1994-0131 May 1994NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators
Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power25 March 1994Safety Systems Response to Loss of Coolant and Loss of Offsite Power
NRC Generic Letter 1993-0829 December 1993NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits
NRC Generic Letter 1993-0728 December 1993NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans
NRC Generic Letter 1993-0625 October 1993NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas.
NRC Generic Letter 1993-0527 September 1993NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation
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