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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML19263B949 + (NRC Brief in Support of 790103 Appeal by Petitioner to Intervene,Potomac Alliance,Appeal of ASLB 781219 Order Denying Intervention.Nrc Believes That Criteria of 10CFR2.714 Are Satisfied.Certificate of Svc Encl)
- ML19274D293 + (NRC Brief in Support of Affirmative Finding on Certified Question Whether Class 9 Accidents Are Proper Subj for Consideration in NRC Environ Statement on OPS Application. Certificate of Svc Encl)
- ML20133F512 + (NRC Brief in Support of Util 850923 Motion for Exemption from 10CFR2.786(b)(1) Re Prohibiting Party from Seeking Review of Aslab Decision on Petition for Directed Certification.Affidavit Encl)
- ML20133F516 + (NRC Brief in Support of Util 850923 Motion for Exemption from 10CFR2.786(b)(1) Re Prohibiting Party from Seeking Review of Aslab Decision on Petition for Directed Certification.Affidavit Encl)
- ML19354D529 + (NRC Brief on Dose Reduction Issue as Certified to Commission in ALAB-922.* Concludes That Commonwealth of Ma Atty General Testimony Re Quantitative Dose Reductions/Dose Consequences Properly Excluded by Aslb.Certificate of Svc Encl)
- ML19274E041 + (NRC Briefed on Proposed NRC Statement on Risk Assessment in Light of WASH-1400 & Risk Assessment Review Group Rept. No Action Taken.Nrc Requested Meeting on This Matter to Be Scheduled in Near Future)
- ML023230087 + (NRC Briefing 10/30/2002. NMC Presentation Palisades Taking Pride in Our Progress While Meeting New Challenges)
- IA-87-249, NRC Briefing Entitled, Nuclear Employee Data Sys (Neds) + (NRC Briefing Entitled, Nuclear Employee Data Sys (Neds))
- ML20235J814 + (NRC Briefing Entitled, Nuclear Employee Data Sys (Neds))
- ML041270504 + (NRC Briefing Presentation Risk-informed Technical Specifications - Initiative 5b Relocation of Surveillance Test Intervals)
- ML19254A595 + (NRC Briefing Re Ofc of Nuclear Reactor Regulation FY81 Budget)
- ML16077A349 + (NRC Briefing Slides for LaSalle Dseis Public Meeting March 22, 2016)
- ML052080213 + (NRC Briefing for Delivery of the NMP Amended License Renewal Application)
- ML20147C731 + (NRC Briefing on 781208:Technology of Nuc Fuel Cycles Pertinent to Matl Diversion. (Viewgraphs.))
- ML23130A092 + (NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides)
- ML19269C843 + (NRC Budget Estimates, FY80)
- ML070220189 + (NRC Bulletin 1975-004: Cable Fire at Browns Ferry Nuclear Power Station)
- L-75-004, NRC Bulletin 1975-004: Cable Fire at Browns Ferry Nuclear Power Station + (NRC Bulletin 1975-004: Cable Fire at Browns Ferry Nuclear Power Station)
- ML031210600 + (NRC Bulletin 1979-005A: Nuclear Incident at Three Mile Island - Supplement)
- ML031210775 + (NRC Bulletin 1979-008: Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident)
- ML022880301 + (NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, with Handwritten Notes)
- ML022700361 + (NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles)
- ML020090084 + (NRC Bulletin 2001-01, Circumferential Cracking of Reactor Vessel Head Penetration Nozzles, Inspection Results)
- L-01-002, NRC Bulletin 2001-01: Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles - Updated Response + (NRC Bulletin 2001-01: Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles - Updated Response)
- ML061870158 + (NRC Bulletin 2002-01 - Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity Supplemental Response)
- ML090350453 + (NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, Request for Additional Information Response)
- L-2003-007, NRC Bulletin 2002-01, Request for Additional Information Response + (NRC Bulletin 2002-01, Request for Additional Information Response)
- ML030350140 + (NRC Bulletin 2002-01, Request for Additional Information Response)
- ML021570032 + (NRC Bulletin 2002-01: Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity - 60-Day Response)
- ML023020066 + (NRC Bulletin 2002-02 - Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs 30-Day Response for North Anna Unit 2 Inspection Results & Response to NRC Request for Additional Information)
- ML030020565 + (NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs, Request for Additional Information)
- ML022480226 + (NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs 15-Day Response)
- ML022480317 + (NRC Bulletin 2002-02: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Program - 15 Days Response)
- NRC 2002-0091, NRC Bulletin 2002-02: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs - Response to Request for Additional Information + (NRC Bulletin 2002-02: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs - Response to Request for Additional Information)
- ML022900005 + (NRC Bulletin 2002-02: Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs - Response to Request for Additional Information)
- 0CAN080502, NRC Bulletin 2003-01 Additional Information + (NRC Bulletin 2003-01 Additional Information)
- W3F1-2005-0058, NRC Bulletin 2003-01 Additional Information + (NRC Bulletin 2003-01 Additional Information)
- ML052970147 + (NRC Bulletin 2003-01 Additional Information)
- L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors + (NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors)
- ML032240419 + (NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors)
- ML042920066 + (NRC Bulletin 2003-01 Response to NRC Request for Additional Information)
- W3F1-2005-0080, NRC Bulletin 2003-01 Response to Request for Additional Information Waterford Steam Electric Station, Unit 3 + (NRC Bulletin 2003-01 Response to Request for Additional Information Waterford Steam Electric Station, Unit 3)
- ML053410269 + (NRC Bulletin 2003-01 Response to Request for Additional Information Waterford Steam Electric Station, Unit 3)
- ML052000282 + (NRC Bulletin 2003-01 Response to Second NRC Request for Additional Information)
- ML042880336 + (NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information Date Extension)
- RC-04-0167, NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information Date Extension. + (NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information Date Extension.)
- ML052620456 + (NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors)
- RC-04-0164, NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information + (NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information)
- ML043000231 + (NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors - Request for Additional Information)
- NRC 2003-0068, NRC Bulletin 2003-01: Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors - 60-Day Response + (NRC Bulletin 2003-01: Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors - 60-Day Response)
- ML032310423 + (NRC Bulletin 2003-01: Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors - 60-Day Response)
- LR-N04-0297, NRC Bulletin 2003-02 Inspection Results Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity + (NRC Bulletin 2003-02 Inspection Results Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity)