Generic Letter# QUERYb3e4f2ee6fcbbbe712de8708e0171fac
NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report
NRC Generic Letter 93-06, Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas"
NRC Generic Letter 83-37, NUREG-0737 Technical Specifications
NRC Generic Letter 97-06, Degradation of Steam Generator Internals
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements
NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System
NRC Generic Letter 91-16, Licensed Operators' and Other Nuclear Facility Personnel Fitness for Duty
NRC Generic Letter 90-08, Simulation Facility Exemptions
NRC Generic Letter 82-10, Post-TMI Requirements
NRC Generic Letter 78-37, Revised Meeting Schedule & Locations for Upgraded Guard Qualifications
NRC Generic Letter 80-28, IEB 80-08 Examination of Containment Liner Penetration Welds
NRC Generic Letter 80-46, Generic Technical Activity A-12 Fracture Toughness
NRC Generic Letter 82-03, High Burnup MAPLHGR Limits
NRC Generic Letter 96-02, Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat
NRC Generic Letter 91-03, Reporting of Safeguards Events
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants
NRC Generic Letter 77-07, Reliability Of Standby Diesel Generator Units
NRC Generic Letter 77-06, Enclosing Questionaire Relating to Steam Generators
NRC Generic Letter 77-05, Nonconformity of Addresses of Items Directed to the Office of Nuclear Reactor Regulation
NRC Generic Letter 77-04, Shipments of Contaminated Components From NRC Licensed Nuclear Power Facilities to Vendors & Service Companies
NRC Generic Letter 77-03, Transmittal of NUREG-0321, "A Study of the Nuclear Regulatory Commission Quality Assurance Program"
NRC Generic Letter 77-02, Fire Protection Functional Responsibilities
NRC Generic Letter 77-01, Intrusion Detection Systems Handbook
NRC Generic Letter 78-42, Duplicate of GL-78-40
NRC Generic Letter 78-41, Mark II Generic Acceptance Criteria for Lead Plants
NRC Generic Letter 78-40, Training & Qualification Program Workshops
NRC Generic Letter 78-39, Forwarding of 2 Tables of Appendix I, Draft Radiological Effluent Technical Specifications, BWR, and NUREG-0133
NRC Generic Letter 78-38, Forwarding of 2 Tables Of Appendix I, Draft Radiological Effluent Technical Specifications, PWR, and NUREG-0133
NRC Generic Letter 78-36, Cessation of Plutonium Shipments by Air Except in NRC Approved Containers
NRC Generic Letter 78-35, Regional Meetings to Discuss Upgraded Guard Qualifications
NRC Generic Letter 78-34, Reactor Vessel Atypical Weld Material
NRC Generic Letter 78-32, Reactor Protection System Power Supplies
NRC Generic Letter 78-31, Notice of Steam Generator Conference Agenda
NRC Generic Letter 78-30, Forwarding of NUREG-0219
NRC Generic Letter 78-29, Notice of PWR steam generator conference
NRC Generic Letter 78-28, Forwarding pages omitted from 07/11/78 letter
NRC Generic Letter 78-27, Forwarding of NUREG-0181
NRC Generic Letter 78-26, Excessive Control Rod Guide Tube Wear
NRC Generic Letter 78-24, Model Appendix I Technical Specifications and Submittal Schedule for BWRs
NRC Generic Letter 78-23, Manpower Requirements For Operating Reactors
NRC Generic Letter 78-22, Revision to Intrusion Detection Systems and Entry Control Handbooks and Nuclear Safeguards Technology Handbook
NRC Generic Letter 78-21, Transmitting NUREG/CR-0181 Concerning Barrier & Penetration Data Needed for Physical Security System Assessment
NRC Generic Letter 78-20, Enclosing – "A Systematic Approach to the Conceptual Design of Physical Protection Systems for Nuclear Facilities"
NRC Generic Letter 78-19, Enclosing Sandia Report SAND 77-0777, "Barrier Technology Handbook"
NRC Generic Letter 78-18, Corrected Letter On Heavy Loads Over Spent Fuel
NRC Generic Letter 78-17, Corrected Letter On Heavy Loads Over Spent Fuel
NRC Generic Letter 78-16, Request for Information on Control of Heavy Loads Near Spent Fuel Pools
NRC Generic Letter 78-15, Task Action Plan for Category A Technical Activity No. A-36, "Control of Heavy Loads Near Spent Fuel"
NRC Generic Letter 78-14, Transmittal Of Draft NUREG-0219 For Comment
NRC Generic Letter 78-13, Forwarding of NUREG-0219
NRC Generic Letter 78-12, Notice of Meeting Regarding "Implementation of 10 CFR 73.55 Requirements And Status of Research..."
NRC Generic Letter 78-11, Guidance on Spent Fuel Pool Modifications
NRC Generic Letter 78-10, Guidance On Radiological Environmental Monitoring
NRC Generic Letter 78-09, Multiple-Subsequent Actuations of Safety/Relief Valves Following an Isolation Event
NRC Generic Letter 78-08, Enclosing NUREG-0408 RE Mark I Containments, and Granting Exemption from GDC 50 and Enclosing Sample Notice
NRC Generic Letter 78-05, Internal Distribution Of Correspondence - Asking For Comments On Mass Mailing System
NRC Generic Letter 78-04, GAO Blanket Clearance For Letter Dated 12/09/77
NRC Generic Letter 78-03, Request For Information On Cavity Annulus Seal Ring
NRC Generic Letter 78-02, Asymmetric Loads Background & Revised Request For Additional Information
NRC Generic Letter 78-01, Correction To Letter Of 12/15/77
NRC Generic Letter 79-70, Environmental Monitoring for Direct Radiation
NRC Generic Letter 79-69, Cladding Rupture, Swelling, and Coolant Blockage as a Result of a Reactor Accident
NRC Generic Letter 79-68, Audit of Small Break LOCA Guidelines
NRC Generic Letter 79-67, Estimates for Evacuation of Various Areas Around Nuclear Power Reactors
NRC Generic Letter 79-66, Additional Information Re 11/09/79 Letter on ECCS Calculations
NRC Generic Letter 79-65, Radiological Environmental Monitoring Program Requirements – Enclosing Branch Technical Position, Revision 1
NRC Generic Letter 79-64, Suspension of All Operating Licenses
NRC Generic Letter 79-63, Upgraded Emergency Plans
NRC Generic Letter 79-61, Discussion of Lessons Learned Short Term Requirements
NRC Generic Letter 79-60, Discussion of Lessons Learned Short Term Requirements
NRC Generic Letter 79-58, ECCS Calculations on Fuel Cladding
NRC Generic Letter 79-57, Acceptance Criteria for the Mark I Containment Long Term Program
NRC Generic Letter 79-56, Discussion of Lessons Learned Short Term Requirements
NRC Generic Letter 79-55, Summary of Meeting Held on October 12, 1979 to Discuss Responses to IE Bulletins 79-05C and 79-06C and HPI Termination Criteria
NRC Generic Letter 79-54, Containment Purging and Venting During Normal Operation
NRC Generic Letter 79-52, Radioactive Release at North Anna Unit 1 and Lessons Learned
NRC Generic Letter 79-51, Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident
NRC Generic Letter 79-50, Emergency Plans Submittal Dates
NRC Generic Letter 79-49, Summary of Meetings Held on 9/18-20/79 to Discuss Potential Unreviewed Safety Question on Systems Interaction for B&W Pl
NRC Generic Letter 79-48, Confirmatory Requirements Relating to Condensation Oscillation Loads for the Mark I Containment Long Term Program
NRC Generic Letter 79-47, Radiation Training
NRC Generic Letter 79-45, Transmittal of Reports Regarding Foreign Reactor Operating Experiences
NRC Generic Letter 79-46, Containment Purging and Venting During Normal Operation – Guidelines for Valve Operability
NRC Generic Letter 79-44, Referencing 6/29/79 Letter Re Multiple Equipment Failures
NRC Generic Letter 79-43, Reactor Cavity Seal Ring Generic Issue
NRC Generic Letter 79-42, Potential Unreviewed Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems
NRC Generic Letter 79-41, Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard
NRC Generic Letter 79-40, Follow-up Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident
NRC Generic Letter 79-39, Transmitting Division 5 Draft Regulatory Guide and Value Impact Statement
NRC Generic Letter 79-38, BWR Off-Gas Systems – Enclosing NUREG/CR-0727
NRC Generic Letter 79-37, Amendment to 10 CFR 73.55 Deferral from 8/1/79 to 11/1/79
NRC Generic Letter 79-36, Adequacy of Station Electric Distribution Systems Voltages
NRC Generic Letter 79-35, Regional Meetings to Discuss Impacts on Emergency Planning
NRC Generic Letter 79-34, New Physical Security Plans (FR 43280-285)
NRC Generic Letter 79-33, Transmitting NUREG-0576 - Security Training and Qualification Plans
NRC Generic Letter 79-32, Transmitting NUREG-0578, "TMI-2 Lessons Learned"
NRC Generic Letter 79-31, Submittal of Copies of Response to 6/29/79 NRC Request
NRC Generic Letter 79-30, Transmitting NUREG-0472, Revision 2, Draft Radiological Technical Specifications
NRC Generic Letter 79-29, Transmitting NUREG-0473, Revision 2, Draft Radiological Effluent Technical Specifications
NRC Generic Letter 79-28, Evaluation of Semi-Scale Small Break Experiment
NRC Generic Letter 79-27, Operability Testing of Relief and Safety Relief Valves
NRC Generic Letter 79-26, Upgraded Standard Technical Specification Bases Program
NRC Generic Letter 79-25, Information Required to Review Corporate Capabilities
NRC Generic Letter 79-24, Multiple Equipment Failures in Safety-Related Systems
NRC Generic Letter 79-23, NRC Staff Review of Responses to I&E Bulletin 79-08
NRC Generic Letter 79-22, Enclosing NUREG-0560, "Staff Report on the Generic Assessment of Feedwater Transients in PWRs Designed by B&W
NRC Generic Letter 79-21, Enclosing NUREG/CR 0660, "Enhancement of on Site Emergency Diesel Generator Reliability"
NRC Generic Letter 79-20, Cracking in Feedwater Lines
NRC Generic Letter 79-19, NRC Staff Review of Responses to I&E Bulletins 79-06 and 79-06a
NRC Generic Letter 79-18, Westinghouse Two-Loop NSSS
NRC Generic Letter 79-17, Reliability of Onsite Diesel Generators at Light Water Reactors
NRC Generic Letter 79-16, Meeting Re Implementation Of Physical Security Requirements
NRC Generic Letter 79-15, Steam Generators-Enclosing Summary of Operating Experience with Recirculating Steam Generators, NUREG-0523
NRC Generic Letter 79-14, Pipe Crack Study Group – Enclosing NUREG-0531 and Notice
NRC Generic Letter 79-13, Schedule for Implementation and Resolution of Mark I Containment Long Term Program
NRC Generic Letter 79-12, ATWS – Enclosing Letter to GE, with NUREG-0460, Vol. 3
NRC Generic Letter 79-11, Transmitting "Summary of Operating Experience with Recalculating Steam Generators, January 1979" NUREG-0523
NRC Generic Letter 79-10, Transmitting Regulatory Guide 2.6 for Comment
NRC Generic Letter 79-09, Staff Evaluation of Interim Multiple-Consecutive Safety-Relief Valve Actuations
NRC Generic Letter 79-08, Amendment to 10 CFR 73.55
NRC Generic Letter 79-07, Seismic (SSE) and LOCA Responses (NUREG-0484)
NRC Generic Letter 79-06, Contents of the Offsite Dose Calculation Manual
NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
NRC Generic Letter 79-04, Referencing 4/14/78 Letter – Modifications to NRC Guidance "Review and Acceptance of Spent Fuel Pool Storage and Handling"
NRC Generic Letter 79-03, Offsite Dose Calculation Manual
NRC Generic Letter 79-02, Transmitting Rev. to Entry Control Systems Handbook (SAND 77-1033), Intrusion Detection Handbook (SAND 76-0554), and Barrier Penetration Database
NRC Generic Letter 79-01, Interservice Procedures for Instructional Systems Development – TRADOC
NRC Generic Letter 80-113, Control of Heavy Loads
NRC Generic Letter 80-112, IEB 80-25 Operating Problems with Target Rock Safety Relief Valves
NRC Generic Letter 80-110, Periodic Updating of FSARS
NRC Generic Letter 80-109, Guidelines for SEP Soil Structure Interaction Reviews
NRC Generic Letter 80-111, IEB 80-17 Supplement 4, Failure of Control Rods to Insert During a Scram at a BWR
NRC Generic Letter 80-108, Emergency Planning
NRC Generic Letter 80-107, BWR Scram Discharge System
NRC Generic Letter 80-106, Report on ECCS Cladding Models, NUREG-0630
NRC Generic Letter 80-105, Implementation of Guidance for USI A-12, Potential for Low Fracture Toughness and Lamellar Tearing on Component Supports
NRC Generic Letter 80-104, Orders on Environmental Qualification of Safety Related Electrical Equipment
NRC Generic Letter 80-103, Fire Protection - Revised Federal Register Notice
NRC Generic Letter 80-102, Commission Memorandum and Order of May 23, 1980 (Referencing IEB 79-01b Supplement 2 - q.2 & 3 - Sept 30, 1980)
NRC Generic Letter 80-101, Inservice Inspection Programs for Prestressed Concrete Containment Structures
NRC Generic Letter 80-100, Appendix R to 10 CFR 50 Regarding Fire Protection-Federal Register Notice
NRC Generic Letter 80-99, Technical Specification Revisions For Snubber Surveillance
NRC Generic Letter 80-98, IEB 80-24 Prevention of Damage Due to Water Leakage Inside Containment
NRC Generic Letter 80-97, IEB 80-23 Failures of Solenoid Valves Manufactured by Valcor Engineering Corporation
NRC Generic Letter 80-96, Fire Protection
NRC Generic Letter 80-95, Generic Activity A-10
NRC Generic Letter 80-94, Emergency Plan
NRC Generic Letter 80-93, Emergency Preparedness
NRC Generic Letter 80-92, IEB 80-21 Valve Yokes Supplied by Malcolm Foundry Company, Inc.
NRC Generic Letter 80-91, Odyn Code Calculation
NRC Generic Letter 80-90, Post TMI Requirements, NUREG-0737
NRC Generic Letter 80-89, IEB 79-01b Supplement 3 Environmental Qualification of Class 1E Equipment
NRC Generic Letter 80-88, Seismic Qualification of Auxiliary Feedwater Systems
NRC Generic Letter 80-87, Notice of Meeting to Discuss Status of EPRI-Proposed Resolution of the USI A-12 Fracture Toughness Issue
NRC Generic Letter 80-86, Notice of Meeting to Discuss Final Resolution of USI A-12
NRC Generic Letter 80-85, Implementation of Guidance From Unresolved Safety Issue A-12, "Potential for Low Fracture Toughness and Lamellar Tearing on Component Supports"
NRC Generic Letter 80-84, BWR Scram System
NRC Generic Letter 80-83, Environmental Qualification of Safety-Related Equipment
NRC Generic Letter 80-82, IEB 79-01b Supplement 2 Environmental Qualification of Class 1E Equipment
NRC Generic Letter 80-81, Preliminary Clarification of TMI Action Plan Requirements - Addendum to 9/5/80 Letter
NRC Generic Letter 80-80, Preliminary Clarification of TMI Action Plan Requirements
NRC Generic Letter 80-79, IEB 80-17 Supplement 3 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR
NRC Generic Letter 80-78, Mark I Containment Long-Term Program
NRC Generic Letter 80-77, Refueling Water Level
NRC Generic Letter 80-76, Notice of Forthcoming Meeting with GE to Discussed Proposed BWR Feedwater Nozzle Leakage Detection System
NRC Generic Letter 80-75, Lessons Learned Tech Specs
NRC Generic Letter 80-74, Notice of Forthcoming Meeting with Representatives of EPRI to Discuss Program for Resolution of USI A-12, Fracture Tough
NRC Generic Letter 80-73, Functional Criteria for Emergency Response Facilities, NUREG-0696
NRC Generic Letter 80-72, Interim Criteria for Shift Staffing
NRC Generic Letter 80-71, IEB 80-20 Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches
NRC Generic Letter 80-70, IEB 80-19 Failures of Mercury-Wetted Matrix Relays in RPS of Operating Nuclear Power Plants Designed by GE
NRC Generic Letter 80-69, IEB 80-18 Maintenance of Adequate Minimum Flow Through Centrifugal Charging Pumps Following Secondary Side Helb
NRC Generic Letter 80-68, IEB 80-17 Supplement 2 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR
NRC Generic Letter 80-67, Scram Discharge Volume
NRC Generic Letter 80-66, IEB 80-17 Supplement 1 Failure of Control Rods to Insert During a Scram at a BWR
NRC Generic Letter 80-65, Request for Estimated Construction Completion and Fuel Load Schedules
NRC Generic Letter 80-64, Scram Discharge Volume Designs
NRC Generic Letter 80-63, IEB 80-17 Failure of Control Rods to Insert During a Scram at a BWR
NRC Generic Letter 80-62, TMI-2 Lessons Learned
NRC Generic Letter 80-61, TMI-2 Lessons Learned
NRC Generic Letter 80-60, Request for Information Regarding Evacuation Times
NRC Generic Letter 80-59, Transmittal of Federal Register Notice RE Regional Meetings to Discuss Environmental Qualification of Elec. Equipment
NRC Generic Letter 80-58, IEB 80-16 Potential Misapplication of Rosemount Inc. Models 1151/1152 Pressure Transmitters with "A" Or "D" Output Codes
NRC Generic Letter 80-57, Further Commission Guidance for Power Reactor Operating Licenses NUREG-0660 and NUREG-0694
NRC Generic Letter 80-56, Commission Memorandum and Order on Equipment Qualification
NRC Generic Letter 80-55, IEB 80-15 Possible Loss of Hotline With Loss of Off-Site Power
NRC Generic Letter 80-54, IEB 80-14 Degradation of Scram Discharge Volume Capability
NRC Generic Letter 80-53, Decay Heat Removal Capability
NRC Generic Letter 80-52, Five Additional TMI-2 Related Requirements - Erata Sheets to 5/7/80 Letter
NRC Generic Letter 80-51, On-Site Storage of Low-Level Waste
NRC Generic Letter 80-50, Generic Activity A-10 BWR Cracks
NRC Generic Letter 80-49, Nuclear Safeguards Problems
NRC Generic Letter 80-48, Revision to 5/19/80 Letter on Fire Protection
NRC Generic Letter 80-47, Additional Guidance on "Potential for Low Fracture Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant Pump Supports"
NRC Generic Letter 80-45, Fire Protection Rule
NRC Generic Letter 80-44, Reorganization of Functions and Assignments Within ONRR/SSPB
NRC Generic Letter 80-43, IEB 80-13 Cracking in Core Spray Spargers
NRC Generic Letter 80-42, IEB 80-12 Decay Heat Removal System Operability
NRC Generic Letter 80-41, Summary of Meetings Held on April 22 & 23, 1980 with Representatives of the Mark I Owners Group
NRC Generic Letter 80-40, Transmittal of NUREG-0654 "Report of the B&O Task Force"And Appropriate NUREG-0626 "Generic Eval of FW Transient and Sbl
NRC Generic Letter 80-39, IEB 80-11 Masonry Wall Design
NRC Generic Letter 80-38, Summary of Certain Non-Power Reactor Physical Protection Requirements
NRC Generic Letter 80-37, Five Additional TMI-2 Related Requirements to Operating Reactors
NRC Generic Letter 80-36, IEB 80-10 Contamination of Non-Radioactive System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment
NRC Generic Letter 80-35, Effect of a DC Power Supply Failure on ECCS Performances
NRC Generic Letter 80-34, Clarification of NRC Requirements For Emergency Response Facilities at Each Site
NRC Generic Letter 80-33, Actions Req. From OL Applicants of B&W Designed NSSS Resulting From NRC B&O Task Force Review of TMI2 Accident
NRC Generic Letter 80-32, Information Request on Category I Masonry Walls Employed by Plants Under CP and OL Review
NRC Generic Letter 80-31, IEB 80-09 Hydramotor Actuator Deficiencies
NRC Generic Letter 80-30, Clarification of the Term "Operable" As It Applies to Single Failure Criterion For Safety Systems Required by TS
NRC Generic Letter 80-29, Modifications to Boiling Water Reactor Control Rod Drive Systems
NRC Generic Letter 80-27, IEB 80-07 BWR Jet Pump Assembly Failure
NRC Generic Letter 80-26, Qualifications of Reactor Operators
NRC Generic Letter 80-25, IEB 80-06 Engineering Safety Feature (ESF) Reset Controls
NRC Generic Letter 80-24, Transmittal of Information on NRC "Nuclear Data Link Specifications"
NRC Generic Letter 80-23, Change of Submittal Date for Evaluation Time Estimates
NRC Generic Letter 80-22, Transmittal of NUREG-0654 "Criteria For Preparation and Evaluation of Radiological Emergency Response Plans and Prepared
NRC Generic Letter 80-21, IEB 80-05 Vacuum Condition Resulting in Damage to Chemical Volume Control System Holdup Tanks
NRC Generic Letter 80-20, Actions Req. From OL Applicants of NSSS Designs by W and CE Resulting From NRC B&O Task Force Review of TMI2 Accident
NRC Generic Letter 80-19, Resolution of Enhanced Fission Gas Release Concern
NRC Generic Letter 80-18, Crystal River 3 Reactor Trip From Approximately 100% Full Power
NRC Generic Letter 80-17, Modifications to Boiling Water Reactor Control Rod Drive Systems
NRC Generic Letter 80-16, IEB 79-01b Environmental Qualification of Class 1E Equipment
NRC Generic Letter 80-15, Request for Additional Management and Technical Resources Information
NRC Generic Letter 80-14, LWR Primary Coolant System Pressure Isolation Valves
NRC Generic Letter 80-13, Qualification of Safety Related Electrical Equipment
NRC Generic Letter 80-12, IEB 80-04 Analysis of a PWR Main Steam Sine Break with Continued Feedwater Addition
NRC Generic Letter 80-11, IEB 80-03 Loss of Charcoal From Standard Type II, 2 Inch, Tray Absorber Cells
NRC Generic Letter 80-10, Issuance of NUREG-0588, "Interim Staff Position on Equipment Qualifications of Safety-Related Electrical Equipment"
NRC Generic Letter 80-09, Low Level Radioactive Waste Disposal
NRC Generic Letter 80-08, IEB 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment
NRC Generic Letter 80-07, Information Regarding the Program For Environmental Qualification of Safety-Related Electrical Equipment
NRC Generic Letter 80-06, Issuance of NUREG-0313, Rev 1, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure"
NRC Generic Letter 80-05, IEB 79-01b Environmental Qualification of Class 1E Equipment
NRC Generic Letter 80-04, IEB 80-01 Operability of ADS Valve Pneumatic Supply
NRC Generic Letter 80-03, BWR Control Rod Failures
NRC Generic Letter 80-02, Quality Assurance Requirements Regarding Diesel Generator Fuel Oil
NRC Generic Letter 80-01, NUREG-0630 "Cladding, Swelling and Rupture - Models for LOCA Analysis"
NRC Generic Letter 81-40, Qualifications of Reactor Operators
NRC Generic Letter 81-39, NRC Volume Reduction Policy
NRC Generic Letter 81-37, ODYN Code Reanalysis Requirements
NRC Generic Letter 81-36, Revised Schedule for Completion of TMI Action Plan Item II.D.1, Relief and Safety Valve Testing
NRC Generic Letter 81-35, Safety Concerns Associated with Pipe Breaks in the BWR Scram System
NRC Generic Letter 81-34, Safety Concerns Associated with Pipe Breaks in the BWR Scram System
NRC Generic Letter 81-32, NUREG-0737, Item II.K.3.44-Evaluation of Anticipated Transients Combined with Single Failure
NRC Generic Letter 81-30, Safety Concerns Associated with Pipe Breaks in the BWR Scram System
NRC Generic Letter 81-29, Simulator Examinations
NRC Generic Letter 81-28, Steam Generator Overfill
NRC Generic Letter 81-27, Privacy and Proprietary Material in Emergency Plans
NRC Generic Letter 81-26, Licensing Requirements for Pending Construction Permit and Manufacturing License Applications
NRC Generic Letter 81-25, Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
NRC Generic Letter 81-24, Multi-Plant Issue B-56 Control Rods Fail to Fully Insert
NRC Generic Letter 81-23, INPO Plant Specific Evaluation Reports
NRC Generic Letter 81-22, Engineering Evaluation of the H.B. Robinson Reactor Coolant System Leak on 1/29/81
NRC Generic Letter 81-21, Natural Circulation Cooldown
NRC Generic Letter 81-20, Safety Concerns Associated with Pipe Breaks in the BWR Scram System
NRC Generic Letter 81-19, Thermal Shock to Reactor Pressure Vessels
NRC Generic Letter 81-18, BWR Scram Discharge System-Clarification of Diverse Instrumentation Requirements
NRC Generic Letter 81-17, Functional Criteria for Emergency Response Facilities
NRC Generic Letter 81-16, NUREG-0737 Item I.C.1 SER on Abnormal Transient Operating Guidelines (ATOG)
NRC Generic Letter 81-15, Environmental Qualification of Class 1E Electrical Equipment-Clarification of Staffs Handling of Proprietary Information
NRC Generic Letter 81-14, Seismic Qualifications for Auxiliary Feedwater Systems
NRC Generic Letter 81-13, SER for GEXL Correlation for 8X8R Fuel Reload Applications for Appendix D Submittals of the GE Topical Report
NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80)
NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619)
NRC Generic Letter 81-10, Post-TMI Requirements for the Emergency Operations Facility
NRC Generic Letter 81-09, BWR Scram Discharge System
NRC Generic Letter 81-07, Control of Heavy Loads
NRC Generic Letter 81-06, Periodic Updating of Final Safety Analysis Reports (FSARS)
NRC Generic Letter 81-05, Information Regarding the Program for Environmental Qualification Of Safety-Related Electrical Equipment
NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events
NRC Generic Letter 81-03, Implementation of NUREG-0313,Technical Report on Material Selection & Processing GL for BWR Coolant Press Boundary Piping
NRC Generic Letter 81-02, Analysis, Conclusions and Recommendations Concerning Operator Licensing
NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel
NRC Generic Letter 82-39, Problems with Submittals of Subsequent Information of CURT 73.21 For Licensing Reviews
NRC Generic Letter 82-38, Meeting to Discuss Developments for Operator Licensing Examinations
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability
NRC Generic Letter 82-32, Draft Steam Generator Report (SAI)
NRC Generic Letter 82-30, Filings Related to 10 CFR 50 Production and Utilization Facilities
NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System
NRC Generic Letter 82-27, Transmittal of NUREG-0763 - Guidelines For Confirmatory In-Plant Tests of Safety-Relief Valve Discharge for BWR Plants
NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness
NRC Generic Letter 82-25, Integrated IAEA Exercise for Physical Inventory at LWRS
NRC Generic Letter 82-24, Safety Relief Valve Quencher Loads: BWR MARK II and III Containments
NRC Generic Letter 82-23, Inconsistency Between Requirements of 10CFR 73.40(D) and Standard Tech Specs For Performing Audits of Sadeguards Contin
NRC Generic Letter 82-22, Congressional Request for Information Concerning Steam Generator Tube Integrity
NRC Generic Letter 82-21, Fire Protection Audits
NRC Generic Letter 82-20, Guidance for Implementing the Standard Review Plan Rule
NRC Generic Letter 82-19, Submittal of Copies of Documentation to NRC-Copy Requirements for Emergency Plans and Physical Security Plans
NRC Generic Letter 82-18, Reactor Operator and Senior Reactor Operator Requalification Examinations
NRC Generic Letter 82-17, Inconsistency of Requirements Between 50.54(t) and 50.15
NRC Generic Letter 82-16, NUREG-0737 Technical Specifications
NRC Generic Letter 82-14, Submittal of Documents to the NRC
NRC Generic Letter 82-13, Reactor Operator and Senior Reactor Operator Examinations
NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours
NRC Generic Letter 82-11, Transmittal of NUREG-0916 Relative to the Restart of R.E. Ginna Nuclear Power Plant
NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment
NRC Generic Letter 82-08, Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture
NRC Generic Letter 82-07, Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture
NRC Generic Letter 82-05, Post-TMI Requirements
NRC Generic Letter 82-04, Use of INPO See-in Program
NRC Generic Letter 82-02, Nuclear Power Plant Staff Working Hours
NRC Generic Letter 82-01, New Applications Survey
NRC Generic Letter 83-44, Availability of NUREG-1021, "Operator Licensing Examiner Standards"
NRC Generic Letter 83-43, Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications
NRC Generic Letter 83-42, Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants"
NRC Generic Letter 83-41, Fast Cold Starts of Diesel Generators
NRC Generic Letter 83-40, Operator Licensing Examination
NRC Generic Letter 83-39, Voluntary Survey of Licensed Operators
NRC Generic Letter 83-38, NUREG-0965, "NRC Inventory of Dams"
NRC Generic Letter 83-36, NUREG-0737 Technical Specifications
NRC Generic Letter 83-35, Clarification of TMI Action Plan Item II.K.3.31
NRC Generic Letter 83-34, Important to Safety
NRC Generic Letter 83-33, NRC Positions on Certain Requirements of Appendix R to 10 CFR 50
NRC Generic Letter 83-32, NRC Staff Recommendations Regarding Operator Action for Reactor Trip and ATWS
NRC Generic Letter 83-31, Safety Evaluation of "Abnormal Transient Operating Guidelines"
NRC Generic Letter 83-30, Deletion of STD. Tech Spec Surveillance Requirement 4.8.1.1.2.d.6 for Diesel Generator Testing
NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events
NRC Generic Letter 83-27, Surveillance Intervals in Standard Technical Specifications
NRC Generic Letter 83-26, Clarification Of Surveillance Requirements for Diesel Fuel Impurity Level Tests
NRC Generic Letter 83-24, TMI Task Action Plan Item I.G.1, "Special Low Power Testing and Training," Recommendations for BWRS
NRC Generic Letter 83-23, Safety Evaluation of "Emergency Procedure Guidelines"
NRC Generic Letter 83-22, Safety Evaluation of "Emergency Response Guidelines"
NRC Generic Letter 83-21, Clarification of Access Control Procedures for Law Enforcement Visits
NRC Generic Letter 83-20, Integrated Scheduling for Implementation of Plant Modifications
NRC Generic Letter 83-19, New Procedures for Providing Public Notice Concerning Issuance of Amendments To Operating Licenses
NRC Generic Letter 83-18, NRC Staff Review of the BWR Owners' Group (BWROG) Control Room Survey Program
NRC Generic Letter 83-17, Integrity of Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses
NRC Generic Letter 83-16, Transmittal of NUREG-0977 Relative to the ATWS Events at Salem Generating Station, Unit NO. 1
NRC Generic Letter 83-15, Implement. of Reg. Guide 1.150, "Ultrasonic Testing of RX Vessel Welds During Preservice & Inservice Examinations, REV.1
NRC Generic Letter 83-13, Clarification of Survell. Req's for HEPA Filters and Charcoal Absorber Units In STD. Tech Specs on ESF Cleanup Systems
NRC Generic Letter 83-12, Issuance of NRC FORM 398 - Personal Qualifications Statement - Licensee
NRC Generic Letter 83-14, Definition of "Key Maintenance Personnel," (Clarification of Generic Letter 82-12)
NRC Generic Letter 83-11, Licensee Qualification for Performing Safety Analyses in Support of Licensing Actions
NRC Generic Letter 83-10f, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 83-10e, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 83-10d, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 83-10c, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 83-10b, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 83-10a, Resolution of TMI Action Item II.K.3.5., "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 83-09, Review of Combustion Engineering Owners' Group Emergency Procedures Guideline Program
NRC Generic Letter 83-08, Modification of Vacuum Breakers on Mark I Containments
NRC Generic Letter 83-07, The Nuclear Waste Policy Act of 1982
NRC Generic Letter 83-06, Certificates and Revised Format for Reactor Operator and Senior Reactor Operator Licenses
NRC Generic Letter 83-05, Safety Evaluation of "Emergency Procedure Guidelines, Revision 2," June 1982
NRC Generic Letter 83-04, Regional Workshops Regarding Supplement 1 to NUREG-0737, Requirements for Emergency Response Capability
NRC Generic Letter 83-02, NUREG-0737 Technical Specifications
NRC Generic Letter 83-01, Operator Licensing Examination Site Visit
NRC Generic Letter 84-24, Certification of Compliance to 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants
NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs
NRC Generic Letter 84-22, 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 84-21, Long Term Low Power Operation in Pressurized Water Reactors
NRC Generic Letter 84-20, Scheduling Guidance for Licensee Submittals of Reloads That Involve Unreviewed Safety Questions
NRC Generic Letter 84-19, Availability of Supplement 1 to NUREG-0933, "A Prioritization of Generic Safety Issues"
NRC Generic Letter 84-18, Filing of Applications for Licenses and Amendments
NRC Generic Letter 84-17, Annual Meeting to Discuss Recent Developments Regarding Operator Training, Qualifications, and Examinations
NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants
NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability
NRC Generic Letter 84-14, Replacement and Requalification Training Program
NRC Generic Letter 84-13, Technical Specification for Snubbers
NRC Generic Letter 84-12, Compliance with 10 CFR 61 and Implementation of Radiological Effluent Tech Specs, Attendant Process Control Program
NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping
NRC Generic Letter 84-10, Administration of Operating Tests Prior to Initial Criticality
NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii)
NRC Generic Letter 84-08, Interim Procedures for NRC Management of Plant-Specific Backfitting
NRC Generic Letter 84-07, Procedural Guidance for Pipe Replacement at BWRs
NRC Generic Letter 84-06, Operator and Senior Operator License Examination Criteria For Passing Grade
NRC Generic Letter 84-05, Change to NUREG-1021, "Operator Licensing Examiner Standards"
NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)
NRC Generic Letter 84-03, Availability of NUREG-0933, "A Prioritization of Generic Safety Issues"
NRC Generic Letter 84-02, Notice of Meeting Regarding Facility Staffing
NRC Generic Letter 84-01, NRC Use Of The Terms "Important To Safety" and "Safety Related"
NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage
NRC Generic Letter 85-20, Resolution of Generic Issue 69: High Pressure Injection/Make-up Nozzle Cracking in Babcock And Wilcox Plants
NRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes
NRC Generic Letter 85-18, Operator Licensing Examinations
NRC Generic Letter 85-17, Availability of Supplements 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues"
NRC Generic Letter 85-16, High Boron Concentrations
NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants"
NRC Generic Letter 85-14, Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated by The Utility
NRC Generic Letter 85-13, Transmittal of NUREG-1154 Regarding The Davis-Besse Loss of Main And Auxiliary Feedwater Event
NRC Generic Letter 85-12, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps
NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612
NRC Generic Letter 85-10, Technical Specification for Generic Letter 83-28, Items 4.3 and 4.4
NRC Generic Letter 85-09, Technical Specifications for Generic Letter 83-28, Item 4.3
NRC Generic Letter 85-08, 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 85-07, Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related
NRC Generic Letter 85-05, Inadvertent Boron Dilution Events
NRC Generic Letter 85-04, Operating Licensing Examinations
NRC Generic Letter 85-03, Clarification of Equivalent Control Capacity for Standby Liquid Control Systems
NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity
NRC Generic Letter 85-01, Fire Protection Policy Steering Committee Report
NRC Generic Letter 86-17, Availability of NUREG-1169, "Technical Findings Related to Generic Issue C-8, BWR MSIC Leakage and Treatment Methods"
NRC Generic Letter 86-16, Westinghouse ECCS Evaluation Models
NRC Generic Letter 86-15, Information Relating to Compliance with 10 CFR 50.49 "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants"
NRC Generic Letter 86-14, Operator Licensing Examinations
NRC Generic Letter 86-13, Potential Inconsistency Between Plant Safety Analyses and Technical Specifications
NRC Generic Letter 86-12, Criteria for Unique Purpose Exemption From Conversion From the Use of HEU Fuel
NRC Generic Letter 86-11, Distribution of Products Irradiated in Research Reactors
NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs
NRC Generic Letter 86-08, Availability of Supplement 4 to NUREG-0933, "A Prioritization of Generic Safety Issues"
NRC Generic Letter 86-07, Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event
NRC Generic Letter 86-06, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 86-05, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps"
NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift
NRC Generic Letter 86-03, Applications for License Amendments
NRC Generic Letter 86-02, Technical Resolution of Generic Issue B-19 - Thermal Hydraulic Stability
NRC Generic Letter 87-16, Transmittal of NUREG-1262, "Answers to Questions on Implementation of 10 CFR 55 on Operators' Licenses"
NRC Generic Letter 87-15, Policy Statement on Deferred Plants
NRC Generic Letter 87-14, Operator Licensing Examinations
NRC Generic Letter 87-13, Integrity of Requalification Examinations at Non-Power Reactors
NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled
NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements
NRC Generic Letter 87-10, Implementation of 10 CFR 73.57, Requirements for FBI Criminal History Checks
NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements
NRC Generic Letter 87-08, Implementation of 10 CFR 73.55 Miscellaneous Amendments and Search Requirements
NRC Generic Letter 87-07, Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Confirming Amendments
NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves
NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells
NRC Generic Letter 87-04, Temporary Exemption From Provisions of the FBI Criminal History Rule for Temporary Workers
NRC Generic Letter 87-03, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46)
NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46)
NRC Generic Letter 87-01, Public Availability of the NRC Operator Licensing Examination Question Bank
NRC Generic Letter 88-19, Use of Deadly Force by Licensee Guards to Prevent Theft of Special Nuclear Material
NRC Generic Letter 88-18, Plant Record Storage on Optical Disks
NRC Generic Letter 88-17, Loss of Decay Heat Removal
NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications
NRC Generic Letter 88-15, Electric Power Systems - Inadequate Control Over Design Process
NRC Generic Letter 88-13, Operator Licensing Examinations
NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations
NRC Generic Letter 88-10, Purchase of GSA Approved Security Containers
NRC Generic Letter 88-09, Pilot Testing of Fundamentals Examination
NRC Generic Letter 88-08, Mail Sent or Delivered to the Office of Nuclear Reactor Regulation
NRC Generic Letter 88-07, Modified Enforcement Policy Relating to 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety"
NRC Generic Letter 88-06, Removal of Organization Charts from Technical Specification Administrative Control Requirements
NRC Generic Letter 88-04, Distribution of Gems Irradiated in Research Reactors
NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps"
NRC Generic Letter 88-02, Integrated Safety Assessment Program II (ISAP II)
NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping
NRC Generic Letter 89-23, NRC Staff Responses to Questions Pertaining to Implementation of 10 CFR Part 26
NRC Generic Letter 89-22, Potential for Increased Roof Loads and Plant Area Flood Runoff Depth Due to Recent Change in Probable Maximum Precipitation Criteria Developed by the National Weather Service
NRC Generic Letter 89-20, Protected Area Long-Term Housekeeping
NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements
NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f)
NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants"
NRC Generic Letter 89-17, Planned Administrative Changes to the NRC Operator Licensing Written Examination Process
NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent
NRC Generic Letter 89-15, Emergency Response Data System
NRC Generic Letter 89-14, Line-Item Improvements in Technical Specifications - Removal of 3.25 Limit on Extending Surveillance Intervals
NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment
NRC Generic Letter 89-12, Operator Licensing Examination
NRC Generic Letter 89-11, Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy"
NRC Generic Letter 89-09, ASME Section III Component Replacements
NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning
NRC Generic Letter 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs
NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f)
NRC Generic Letter 89-05, Pilot Testing of the Fundamentals Examination
NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs
NRC Generic Letter 89-03, Operator Licensing Examination Schedule
NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products
NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications
NRC Generic Letter 90-09, Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions
NRC Generic Letter 90-07, Operator Licensing National Examination Schedule
NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs"
NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping
NRC Generic Letter 90-04, Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs
NRC Generic Letter 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components"
NRC Generic Letter 90-02, Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications
NRC Generic Letter 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey
NRC Generic Letter 91-19, Information to Addressees Regarding New Telephone Numbers for NRC Offices Located in One White Flint North
NRC Generic Letter 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants"
NRC Generic Letter 91-15, Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors
NRC Generic Letter 91-14, Emergency Telecommunications
NRC Generic Letter 91-13, Request for Info Related to the Resolution of GI 130, "Essential Service Water System Failures at Multi-Unit Sites"
NRC Generic Letter 91-12, Operator Licensing National Examination Schedule
NRC Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54
NRC Generic Letter 91-10, Explosives Searches at Protected Area Portals
NRC Generic Letter 91-09, Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies for the Reactor Protection System
NRC Generic Letter 91-08, Removal of Component Lists from Technical Specifications
NRC Generic Letter 91-07, GI-23, "Reactor Coolant Pump Seal Failures" and Its Possible Effect on Station Blackout
NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f)
NRC Generic Letter 91-05, Licensee Commercial-Grade Procurement and Dedication Programs
NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
NRC Generic Letter 91-02, Reporting Mishaps Involving LLW Forms Prepared for Disposal
NRC Generic Letter 91-01, Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from Technical Specifications
NRC Generic Letter 92-09, Limited Participation by NRC in the IAEA International Nuclear Event Scale
NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers
NRC Generic Letter 92-07, Office of Nuclear Reactor Regulation Reorganization
NRC Generic Letter 92-06, Operator Licensing National Examination Schedule
NRC Generic Letter 92-05, NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program
NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f)
NRC Generic Letter 92-03, Compilation of the Current Licensing Basis: Request for Voluntary Participation in Pilot Program
NRC Generic Letter 92-02, Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown"
NRC Generic Letter 92-01, Reactor Vessel Structural Integrity
NRC Generic Letter 93-08, Relocation of Technical Specification Tables of Instrument Response Time Limits
NRC Generic Letter 93-07, Modification of the Technical Specification Administrative Control Requirements for Emergency and Security Plans
NRC Generic Letter 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation
NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f)
NRC Generic Letter 93-03, Verification of Plant Records
NRC Generic Letter 93-02, NRC Public Workshop on Commercial Grade Procurement and Dedication
NRC Generic Letter 93-01, Emergency Response Data System Test Program
NRC Generic Letter 94-04, Voluntary Reporting of Additional Occupational Radiation Exposure Data
NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
NRC Generic Letter 94-02, Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs
NRC Generic Letter 94-01, Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators
NRC Generic Letter 95-10, Relocation of Selected Technical Specifications Requirements Related to Instrumentation
NRC Generic Letter 95-09, Monitoring and Training of Shippers and Carriers of Radioactive Materials
NRC Generic Letter 95-08, 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval
NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety- Related Power-Operated Gate Valves
NRC Generic Letter 95-06, Changes in the Operator Licensing Program
NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking
NRC Generic Letter 95-04, Final Disposition of the Systematic Evaluation Program Lessons-Learned Issues
NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes
NRC Generic Letter 95-02, Use of Numarc/epri Report TR-102348, "Guideline on Licensing Digital Upgrades," in Determining the Acceptability of Performing Analog-to-Digital Replacements under 10 CFR 50.59
NRC Generic Letter 95-01, NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities
NRC Generic Letter 96-07, Interim Guidance on Transportation of Steam Generators
NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions
NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks
NRC Generic Letter 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits
NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits
NRC Generic Letter 97-05, Steam Generator Tube Inspection Techniques
NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps
NRC Generic Letter 97-03, Annual Financial Update of Surety Requirements for Uranium Recovery Licensees
NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations
NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds
NRC Generic Letter 98-04, 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 in Containment
NRC Generic Letter 98-03, NMSS Licensees' and Certificate Holders' Year 2000 Readiness Programs
NRC Generic Letter 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance
NRC Generic Letter 2003-01, Control Room Habitability
NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification
NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites
NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems