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Issue date | Title | Topic | |
---|---|---|---|
NRC Generic Letter 1999-02 | 23 August 1999 | NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal | |
NRC Generic Letter 1983-11 | 24 June 1999 | NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis | Backfit |
ML082350935 | 3 June 1999 | Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal | |
ML031110137 | 3 June 1999 | Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates | Enforcement Discretion |
NRC Generic Letter 1999-01 | 3 May 1999 | NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities | |
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 | Backfit |
ML031110160 | 3 August 1998 | Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data | |
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 | Safe Shutdown Coatings Foreign Material Exclusion Scaffolding Backfit |
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 | Reactor Vessel Water Level Backfit |
NRC Generic Letter 1997-06 | 30 December 1997 | NRC Generic Letter 1997-006: Degradation of Steam Generator Internals | Backfit |
NRC Generic Letter 1997-05 | 17 December 1997 | NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques | Nondestructive Examination Backfit |
NRC Generic Letter 1996-06 | 13 November 1997 | NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions | |
ML031200701 | 8 October 1997 | Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions | Temporary Modification |
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 | Backfit |
NRC Generic Letter 1997-03 | 9 July 1997 | NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees | |
NRC Generic Letter 1997-02 | 15 May 1997 | NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report | Backfit |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program | Backfit |
NRC Generic Letter 1996-08 | 15 December 1996 | NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators | |
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 | Stroke time Backfit |
NRC Generic Letter 1996-04 | 26 June 1996 | NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks | Backfit |
NRC Generic Letter 1995-09 | 5 April 1996 | NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials | |
NRC Generic Letter 1996-02 | 13 February 1996 | NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat | Exemption Request |
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 | Shutdown Margin Hydrostatic Incorporated by reference Backfit |
NRC Generic Letter 1989-10 | 24 January 1996 | NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors | Probabilistic Risk Assessment Backfit |
NRC Generic Letter 1996-01 | 10 January 1996 | NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits | Probabilistic Risk Assessment Backfit |
NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation | Offsite Dose Calculation Manual Process Control Program Earthquake Turbine Missile Pressure Boundary Leakage Backfit |
ML031070150 | 31 October 1995 | Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval | Exemption Request |
NRC Generic Letter 1993-03 | 20 October 1995 | NRC Generic Letter 1993-003: Verification of Plant Records | |
NRC Generic Letter 1995-07 | 17 August 1995 | NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves | Backfit |
NRC Generic Letter 1995-04 | 28 April 1995 | NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues | Tornado Missile Turbine Missile Generic Issues Program Backfit |
NRC Generic Letter 1995-03 | 28 April 1995 | NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes | Nondestructive Examination |
NRC Generic Letter 1995-02 | 26 April 1995 | NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59 | |
NRC Generic Letter 1995-01 | 26 January 1995 | NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities | Safe Shutdown Fire Barrier Fire Protection Program Uranium Hexafluoride |
ML031200443 | 2 September 1994 | Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data | Safe Shutdown Fire Barrier Backfit |
NRC Generic Letter 1994-03 | 25 July 1994 | NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors | Safe Shutdown Fire Barrier Probabilistic Risk Assessment Backfit |
NRC Generic Letter 1994-02 | 11 July 1994 | NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors | Safe Shutdown Fire Barrier Anticipated operational occurrence Backfit |
NRC Generic Letter 1994-01 | 31 May 1994 | NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators | Safe Shutdown Fire Barrier Backfit |
NRC Generic Letter 1993-08 | 29 December 1993 | NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits | Backfit |
NRC Generic Letter 1993-07 | 28 December 1993 | NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans | Backfit |
NRC Generic Letter 1993-06 | 25 October 1993 | NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas. | Backfit |
NRC Generic Letter 1993-05 | 27 September 1993 | NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation | Boric Acid Shutdown Margin Fire Barrier Scram Discharge Volume Offsite Circuit Backfit |
NRC Generic Letter 1993-04 | 21 June 1993 | NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) | Fire Barrier |
NRC Generic Letter 1993-02 | 23 March 1993 | NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication | Fire Barrier |
NRC Generic Letter 1993-01 | 3 March 1993 | NRC Generic Letter 1993-001: Emergency Response Data System Test Program | Fire Barrier Backfit |
NRC Generic Letter 1992-09 | 31 December 1992 | NRC Generic Letter 1992-009: Limited Participation by NRC in IAEA International Nuclear Event Scale | Fire Barrier Chernobyl Backfit |
NRC Generic Letter 1992-08 | 17 December 1992 | NRC Generic Letter 1992-008: Thermo-Lag 330-1 Fire Barriers | Safe Shutdown Fire Barrier Backfit |
NRC Generic Letter 1992-07 | 20 October 1992 | NRC Generic Letter 1992-007 - Office of Nuclear Reactor Regulation Reorganization | |
NRC Generic Letter 1983-28 | 7 October 1992 | NRC Generic Letter 1983-028, Supplement 1: Required Actions Based on Generic Implications of Salem ATWS Events. | Backfit |
ML031130412 | 16 September 1992 | Withdrawn NRC Generic Letter 1992-006 - Operator Licensing National Examination Schedule | |
NRC Generic Letter 1992-05 | 4 September 1992 | NRC Generic Letter 1992-005: NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program | Safe Shutdown Ultimate heat sink Nondestructive Examination Systematic Assessment of Licensee Performance |