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A list of all pages that have property "Title" with value "RAI, Requested Code Relief". 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

  • ML041800277  + (RAI, Request for Additional Information (RAI) Regarding Alternate Source Term)
  • ML071790277  + (RAI, Request for Additional Information Related to Measurement Uncertainty Recapture Power Uprate)
  • ML071230037  + (RAI, Request for Additional Information Regarding the Spent Fuel Pool Critically Analysis License Amendment Request)
  • ML073310170  + (RAI, Request for Additional Information Regarding Nine Mile Point Nuclear Station, Unit No.2, Revision to Drywell Spray Nozzle Testing Frequency)
  • ML071150025  + (RAI, Request for Additional Information Regarding the Proposal to Revise Technical Specification Surveillance Requirements (TAC Nos. MD3168 & MD3169))
  • ML071240411  + (RAI, Request for Additional Information Regarding Request for Extended Power Uprate)
  • ML061510252  + (RAI, Request for Additional Information Re Proposed Technical Specification Changes - Leak Detection Instruments)
  • ML031400855  + (RAI, Request for Amendment to Technical Specifications Related to TS 5.5.13, Primary Containment Leakage Rate Testing Program)
  • ML050400642  + (RAI, Request for Approval of Final Safety Analysis Report Change Regarding the Carbon Dioxide Suppression System)
  • ML041610059  + (RAI, Request for Approval of Nuclear Management Co, Quality Assurance Topical Report)
  • ML041600012  + (RAI, Request for Approval to Use Alternative Examination Volume Requirements of Code Case N-613-11 in Lieu of Certain ASME BPV Code, Section XI, Requirements)
  • ML032200131  + (RAI, Request for Change to Technical Specifications on Fuel Storage Pool Boron Concentration, Refueling Pool Boron Concentration and Fuel Assembly Storage (TAC MB634 and MB6346))
  • ML041890168  + (RAI, Request for Change to Technical Specifications - Relaxation of Requirements Applicable During Movement of Irradiated Fuel)
  • ML041330205  + (RAI, Request for Exemption to the Cladding Material Specified in Title 10 of the Code of Fed Regulations (10 CFR) 50.46 & 10 CFR Part 50 App. K to Allow Use of Optimized ZIRLO Tm Lead Test Assemblies)
  • ML030300573  + (RAI, Request for Relief for Reactor Pressure Vessel Closure Head Penetration Welds)
  • ML030500103  + (RAI, Request for Removal of Personal Home Altering Devices (Phads) from Emergency Preparedness (EP) Plan)
  • ML050390544  + (RAI, Request for Revision of TS 3.3.2)
  • ML091900753  + (RAI, Request for Supplemental Information Regarding Extension of Technical Specification Completion Time for Emergency Diesel Generators)
  • ML031470002  + (RAI, Request for Withholding Information from Public Disclosure)
  • ML040960292  + (RAI, Request for Withholding Information from Public Discolsure, TAC MC1249)
  • ML062150178  + (RAI, Request for one-time Extension)
  • ML071970358  + (RAI, Request to Modify UFSAR Related to Internal Flooding Design Basis)
  • ML041270560  + (RAI, Request to Revise Containment Equipment Hatch Technical Specification)
  • ML050870035  + (RAI, Request to Use Non-NIOSH-Approved Delta Air Supplied Suits)
  • ML042180464  + (RAI, Request to Use a Risk-Informed Inservice Inspection Plan)
  • ML070710050  + (RAI, Requests for Additional Information for the Review of the Wolf Creek Generating Station, Unit 1 License Renewal Application)
  • ML070930695  + (RAI, Requests for Additional Information for the Review of the Wolf Creek Generating Station, Unit 1, License Renewal Application)
  • ML042110166  + (RAI, Requests for Relaxation from Revised Order on Reactor Vessel Nozzles)
  • ML023220407  + (RAI, Response to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 60-Day Response)
  • ML050830188  + (RAI, Response to Bulletin 2003-01)
  • ML043130439  + (RAI, Response to Bulletin 2004-01)
  • ML060390357  + (RAI, Response to GL 2004-02)
  • ML060370463  + (RAI, Response to GL-2004-02, Potential Impact to Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060380082  + (RAI, Response to GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors)
  • ML063610061  + (RAI, Response to Generic Letter 2003-01, Control Room Habitability, MB9840)
  • ML051180042  + (RAI, Response to Generic Letter 2004-01, Requirements for Steam Generator Tube Inspection)
  • ML051470115  + (RAI, Response to Generic Letter 2004-02)
  • ML060390350  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4702, MC4703, and M4704))
  • ML060380358  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060370396  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060370387  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060380033  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060380708  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060370347  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060380017  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML060380003  + (RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors)
  • ML072950027  + (RAI, Response to Generic Letter 2007-01)
  • ML093080444  + (RAI, Response to Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal and Containment Spray Systems)
  • ML062080577  + (RAI, Response to Generic Letter 87-02, Supplement 1, Supplemental Safety Evaluation No. 2)
  • ML062130097  + (RAI, Response to Generic Letter 98-04, Potential for Degradation of the ECCS & the Containment Spray System After a LOCA Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment)
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