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A list of all pages that have property "Title" with value "NRC Generic Letter 1991-014: Emergency Telecommunications". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • NRC Generic Letter 1989-19  + (NRC Generic Letter 1989-019: Request for Action 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 1989-20  + (NRC Generic Letter 1989-020: Protected Area Long-Term Housekeeping)
  • NRC Generic Letter 1989-21  + (NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements)
  • NRC Generic Letter 1989-22  + (NRC Generic Letter 1989-022: Potential for Increase Roof Loads and Plant Area Flood Runoff Depth at Licensed Nuclear Power Plants Due to Recent Change in Probable Max. Precipitation Criteria Developed by National Weather Service)
  • NRC Generic Letter 1989-23  + (NRC Generic Letter 1989-023: NRC Staff Responses to Questions Pertaining to Implementation of 10 CFR Part 26)
  • NRC Generic Letter 1990-01  + (NRC Generic Letter 1990-001: Request for Voluntary Participation in NRC Regulatory Impact Survey)
  • NRC Generic Letter 1990-02  + (NRC Generic Letter 1990-002: Alternative Requirement for Fuel Assemblies in Design Features Section of Technical Specifications)
  • NRC Generic Letter 1990-03  + (NRC Generic Letter 1990-003: Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 Vendor Interface for Safety-Related Components)
  • NRC Generic Letter 1990-04  + (NRC Generic Letter 1990-004: Request for Information on Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements or Corrective Actions)
  • NRC Generic Letter 1990-05  + (NRC Generic Letter 1990-005: Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping)
  • NRC Generic Letter 1990-06  + (NRC Generic Letter 1990-006: Resolution of Generic Issue, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-Temp. Overpressure Protection for Light-Water Reactors, Pursuant to 10 CFR 50354 (F))
  • NRC Generic Letter 1990-08  + (NRC Generic Letter 1990-008: Simulation Facility Exemptions)
  • NRC Generic Letter 1990-09  + (NRC Generic Letter 1990-009: Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions)
  • NRC Generic Letter 1991-01  + (NRC Generic Letter 1991-001: Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from Technical Specifications)
  • NRC Generic Letter 1991-02  + (NRC Generic Letter 1991-002: Reporting Mishaps Involving LLW Forms Prepared for Disposal)
  • NRC Generic Letter 1991-03  + (NRC Generic Letter 1991-003: Reporting of Safeguards Events)
  • NRC Generic Letter 1991-04  + (NRC Generic Letter 1991-004: Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle)
  • NRC Generic Letter 1991-05  + (NRC Generic Letter 1991-005: Licensee Commercial-Grade Procurement and Dedication Programs)
  • NRC Generic Letter 1991-06  + (NRC Generic Letter 1991-006: Resolution of Generic Issue A-30, Adequacy of Safety-Related DC Power Supplies, Pursuant to 10 CFR 50.54(f))
  • NRC Generic Letter 1991-07  + (NRC Generic Letter 1991-007: GI-23, Reactor Coolant Pump Seal Failures and Its Possible Effect on Station Blackout)
  • NRC Generic Letter 1991-08  + (NRC Generic Letter 1991-008: Removal of Component Lists from Technical Specifications)
  • NRC Generic Letter 1991-09  + (NRC Generic Letter 1991-009: Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies for the Reactor Protection System)
  • NRC Generic Letter 1991-10  + (NRC Generic Letter 1991-010: Explosives Searches at Protected Area Portals)
  • NRC Generic Letter 1991-11  + (NRC Generic Letter 1991-011: Resolution of Generic Issues 48, LCOs for IE Vital Instrument Buses, and 49, Interlocks and LCOs for Class IE Tie Breakers Pursuant to 10 CFR 50.54 (F))
  • NRC Generic Letter 1991-13  + (NRC Generic Letter 1991-013: Request for Information Related to Resolution of Generic Issue 130, Essential Service Water System Failures at Multi-Unit Sites Pursuant to 10 CFR 50.54(f))
  • NRC Generic Letter 1991-15  + (NRC Generic Letter 1991-015: Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors)
  • NRC Generic Letter 1991-16  + (NRC Generic Letter 1991-016: Licensed Operators' and Other Nuclear Facility Personnel Fitness for Duty)
  • NRC Generic Letter 1991-17  + (NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants.)
  • NRC Generic Letter 1991-19  + (NRC Generic Letter 1991-019: Information to Addressees Regarding New Telephone Numbers for NRC Offices Located in One White Flint North)
  • NRC Generic Letter 1992-01  + (NRC Generic Letter 1992-001: Reactor Vessel Structural Integrity, 10 CFR 50.54(f))
  • NRC Generic Letter 1992-02  + (NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.)
  • NRC Generic Letter 1992-03  + (NRC Generic Letter 1992-003 - Compilation of Current Licensing Basis: Request for Voluntary Participation in Pilot Program)
  • NRC Generic Letter 1992-04  + (NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F))
  • NRC Generic Letter 1992-05  + (NRC Generic Letter 1992-005: NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program)
  • NRC Generic Letter 1992-07  + (NRC Generic Letter 1992-007 - Office of Nuclear Reactor Regulation Reorganization)
  • NRC Generic Letter 1992-08  + (NRC Generic Letter 1992-008: Thermo-Lag 330-1 Fire Barriers)
  • NRC Generic Letter 1992-09  + (NRC Generic Letter 1992-009: Limited Participation by NRC in IAEA International Nuclear Event Scale)
  • NRC Generic Letter 1993-01  + (NRC Generic Letter 1993-001: Emergency Response Data System Test Program)
  • NRC Generic Letter 1993-02  + (NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication)
  • NRC Generic Letter 1993-03  + (NRC Generic Letter 1993-003: Verification of Plant Records)
  • NRC Generic Letter 1993-04  + (NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f))
  • NRC Generic Letter 1993-05  + (NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation)
  • NRC Generic Letter 1993-06  + (NRC 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 1993-07  + (NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans)
  • NRC Generic Letter 1993-08  + (NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits)
  • NRC Generic Letter 1994-01  + (NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators)
  • NRC Generic Letter 1994-02  + (NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors)
  • NRC Generic Letter 1994-03  + (NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors)
  • NRC Generic Letter 1995-01  + (NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities)
  • NRC Generic Letter 1995-02  + (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)