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List of results

• ML16295A173  + (To Regulatory Guide 1.100, Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants)
• ML16203A386  + (To Regulatory Guide 1.149, Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations)
• ML16204A219  + (To Regulatory Guide 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants)
• ML20324A742  + (To Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities)
• DCL-06-019, To Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors  + (To Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors)
• ML20010C218  + (To Reliability Analysis Rept for Balance of Plant ESF Actuation Sys)
• ML14113A461  + (To Reload Safety Evaluation,San Onofre Nuclear Generating Station Unit 1,Cycle 8)
• 05000255/LER-2077-046, To Replace Improper Terminology Seal Bladder with Term Seal Ring, LER 1977-046-00 & LER 1977-048-00 Re Service Water Pump Check Valve Failure  + (To Replace Improper Terminology Seal Bladder with Term Seal Ring, LER 1977-046-00 & LER 1977-048-00 Re Service Water Pump Check Valve Failure)
• L-03-065, To Reply to Request for Additional Information Regarding Proposed Alternative Repair Methods for Reactor Vessel Head Penetrations  + (To Reply to Request for Additional Information Regarding Proposed Alternative Repair Methods for Reactor Vessel Head Penetrations)
• ML20010J636  + (To Reporting of Operational Incidents)
• ML19242B875  + (To Rept on Reanalysis of Safety-Related Piping Sys)
• ML19274F298  + (To Rept on Reanalysis of Safety-Related Piping Sys, Prepared by S&W)
• ML20141G708  + (To Rept on Vortexing in Condensate Storage Pool)
• ML20031C528  + (To Requalification Action Plan,Qualification by Test of Class IE Equipment Per NUREG-0588)
• ML24060A123  + (To Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds)
• ML20052F698  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• ML20050A056  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• ML20049H915  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• ML20039E777  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• ML20050C649  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• ML18005A009  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• ML17319B323  + (To Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment)
• W3F1-2007-0062, To Request for Alternative W3-ISI-005 Request to Use ASME Code Case N-716  + (To Request for Alternative W3-ISI-005 Request to Use ASME Code Case N-716)
• L-HU-04-043, To Request for Approval of Nuclear Management Company Quality Assurance Topical Report  + (To Request for Approval of Nuclear Management Company Quality Assurance Topical Report)
• L-HU-04-045, To Request for Approval of Nuclear Management Company Quality Assurance Topical Report  + (To Request for Approval of Nuclear Management Company Quality Assurance Topical Report)
• NRC 2005-0072, To Request for Exigent Review of Heavy Load Analysis and Response to Request for Additional Information  + (To Request for Exigent Review of Heavy Load Analysis and Response to Request for Additional Information)

• NRC 2005-0063, To Request for Exigent Review of Heavy Load Analysis  + (To Request for Exigent Review of Heavy Load Analysis)
• ML051750619  + (To Request for Exigent Review of Heavy Load Analysis)

• CNL-22-044, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)  + (To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535))
• CNL-22-057, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use  + (To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use)
• CNL-22-083, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).  + (To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).)
• CNL-22-076, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel  + (To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel)
• CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)  + (To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535))
• CNL-22-096, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)  + (To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535))
• HNP-08-121, To Request for License Amendment to Adopt NFPA 805 Performance-based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)  + (To Request for License Amendment to Adopt NFPA 805 Performance-based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition))
• ML12363A102  + (To Request for NRC Staff to Suspend Safety Review of South Texas Project License Renewal Application)
• ML13024A413  + (To Request for NRC Staff to Suspend Safety Review of License Renewal Application)
• ML20052A895  + (To Response to NRC Action Plan Item II.K.3.30, Justification of Small Break LOCA Methods)
• ML20039D173  + (To Response to NUREG-0588 - Introduction, Methodology & Equipment List)
• ML20039D176  + (To Response to NUREG-0588 - Qualification Data Evaluation Forms, Vols 1 & 2)
• ML100430500  + (To Response to Request for Additional Information Regarding License Amendment Requests for Deviation from Fire Protection Program Requirements)
• ML19072A281  + (To Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control)
• ML16302A015  + (To Revised Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSl)-191 and Respond to Generic Letter (GL) 2004-02)
• ML13323A183  + (To Revised STP Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191)
• ML13338A165  + (To Revised STP Pilot Submittal for a Risk-Informed Approach to Resolving Generic Safety Issue (GSI)-191 to Supersede and Replace the Revised Pilot Submittal)
• ML20027E826  + (To Revised Vacuum Breaker Valve Response for Fermi-2)
• ML033580735  + (To Risk-Informed Inservice Inspection Program Plan, Kewaunee Nuclear Power Plant)
• ML032310014  + (To S. Kraft from W. Hodges - Staff Comments on the Proposed Use of (Critical Strain Energy Density) Csed for Prediction of Cladding Failure for High Burnup Fuel and the Attachment)
• ML20008F748  + (To SAR for Chem-Nuclear Sys Inc SGC-1 Type a Radwaste Shipping Cask)
• ML19345E589  + (To SAR for Chem-Nuclear Sys,Inc SGC-1,Type a Radwaste Shipping Cask)
• ML20009H319  + (To SAR for Fftf Fuel Pin Shipping Cask Model-T3)
• ML19209A687  + (To SAR for Fftf Fuel Pin Shipping Cask Model-T3)