Search by property

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

• W3F1-2004-0094, Revised Response to Waterford 3's Response Letter to Generic Letter 2003-01, Control Room Habitability  + (Revised Response to Waterford 3's Response Letter to Generic Letter 2003-01, Control Room Habitability)
• ML042880299  + (Revised Response to Waterford 3s Response Letter to Generic Letter 2003-01, Control Room Habitability)
• BW020092, Revised Response to a Notice of Violation  + (Revised Response to a Notice of Violation)
• ML033040408  + (Revised Response to a Notice of Violation, EA-03-007)
• GO2-17-173, Revised Response to a Notice of Violation; EA-17-028  + (Revised Response to a Notice of Violation; EA-17-028)
• NOC-AE-03001637, Revised Response to a RAI Regarding an Application for Order Approving Indirect Transfer of Control of Licenses  + (Revised Response to a RAI Regarding an Application for Order Approving Indirect Transfer of Control of Licenses)
• ML033460190  + (Revised Response to a RAI Regarding an Application for Order Approving Indirect Transfer of Control of Licenses)
• RS-11-064, Revised Response to a Request for Additional Information Related to Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations  + (Revised Response to a Request for Additional Information Related to Inservice Inspection Relief Request I3R-19: Alternative Requirements for the Repair of Reactor Vessel Head Penetrations)
• ML052930268  + (Revised Response to a Request of Additional Information February 25, 2002 Order Section B.5.b)
• CPSES-200601160, Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power  + (Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power)
• CP-201200599, Revised Response to the 60-Day Response to NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54 (F) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights.  + (Revised Response to the 60-Day Response to NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54 (F) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights.)
• ML031820666  + (Revised Responses to NRC Questions 1, 2 & 3 for Technical Specification (TS) Change 00-14)
• ML19150A297  + (Revised Responses to NRC Requests for Additional Information, Fire Water System, Related to the Peach Bottom Atomic Power Station, Units 2 and 3, Subsequent License Renewal Application)
• ML073230024  + (Revised Responses to Requests for Additional Information (Rais) Dated June 15, 2007, Regarding the BWROG Submittal of General Electric Nuclear Energy (Gene) Licensing Topical Report NEDC-33178P, Revision 0, General Electric Methodology for)
• CNL-16-145, Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30  + (Revised Responses to Requests for Additional Information Regarding Proposed Technical Specifications Change TS-505 - Extended Power Uprate - Supplement 30)
• ML101730195  + (Revised Responses to the NRCs Request for Additional Information Related to GL-2004-02)
• ML101730190  + (Revised Responses to the Request for Additional Information Related to GL-2004-02)
• ML20235Z291  + (Revised Restart Rept for Rancho Seco Nuclear Generating Station Following 851226 Overcooling Event)
• ML20009C472  + (Revised Results of Impingement Monitoring at Intake of Facility During May 1981)
• ML20063D012  + (Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan)
• ML20134M253  + (Revised Rev 11 to QA Program Description)
• ML20063D026  + (Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan)
• ML20203A695  + (Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam))
• ML20210C591  + (Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes)
• ML20203B036  + (Revised Rev 24 to EP 7.0, Emergency Facilities & Equipment)

• ML20151B235  + (Revised Rev 5 to QA Program Description)

• ML17342A206  + (Revised Rev 8 to Topical QA Rept)
• ML080230112  + (Revised Review Guidance for Licensee Responses to Generic Letter 2004-02)
• ML24220A165  + (Revised Review Schedule - X-energys QAPD Topical Report)
• ML101460577  + (Revised Review Schedule Regarding the Application from Florida Power Corporation for Renewal of the Operating License for Crystal River Unit 3 Nuclear Generating Plant)
• ML100050166  + (Revised Review Schedule Regarding the Application from Florida Power Corporation for Renewal of the Operating License for Crystal River Unit 3 Nuclear Generating Plant)
• ML103070380  + (Revised Review Schedule Regarding the Application from Florida Power Corporation for Renewal of the Operating License for Crystal River Unit 3 Nuclear Generating Plant)
• ML102940375  + (Revised Review Schedule Regarding the Application from Prairie Island Nuclear Generating Plant, Units 1 and 2)
• ML101480951  + (Revised Review Schedule Regarding the Application from Prairie Island Nuclear Generating Plant, Units 1 and 2)
• ML102360221  + (Revised Review Schedule Regarding the Application from PSEG Nuclear, LLC for Renewal of the Operating Licenses for Salem Nuclear Generating Station, Units 1 and 2, and Hope Creek Generating Station)
• ML110330518  + (Revised Review Schedule Regarding the License Renewal Application from Prairie Island Nuclear Generating Plant, Units 1 and 2 (Tac Nos. MD8528 and MD8529))
• ML21188A226  + (Revised Review Schedule for GE-Hitachi Licensing Topical Report NEDC-33922P, Revision 0, BWRX-300 Containment Evaluation Method (Docket No. 99900003))
• ML19323A859  + (Revised Review Sheet for Plant Design Change 320 to Annual Operating Rept of Facility Changes,Tests & Experiments, 1979)
• RIS 2006-24, Revised Review and Transmittal Process for Accident Sequence Precursor Analyses  + (Revised Review and Transmittal Process for Accident Sequence Precursor Analyses)
• ML20206S276  + (Revised Revised Charter for Acrs)
• RS-02-062, Revised Risk Analysis Sensitivity Case Support the License Amendment Request to Permit Extended Power Uprate Operation for Clinton Power Station  + (Revised Risk Analysis Sensitivity Case Support the License Amendment Request to Permit Extended Power Uprate Operation for Clinton Power Station)
• ML20207F065  + (Revised Risk Assessment & Cost Estimation for Cleanup of Radioactive Matl, Monthly Rept for June 1988.Encl Withheld)
• ML020780152  + (Revised Risk Assessment Associated with Degraded Thermolag Barrier Between Auxiliary Control Panel Room & a Train Cable Spreading Room)
• ML20117C829  + (Revised Ro/Sro Requalification)
• RBG-34-499, Revised Ro:From 901005-06,two 42X Relays in Div 1 Standby Cooling Tower Fans Experienced Failures,Rendering Fans Inoperable.Caused by Cracked Coils on Relays & Low Coil Resistance.Relays Replaced & Ventilation Sys Redesigned  + (Revised Ro:From 901005-06,two 42X Relays in Div 1 Standby Cooling Tower Fans Experienced Failures,Rendering Fans Inoperable.Caused by Cracked Coils on Relays & Low Coil Resistance.Relays Replaced & Ventilation Sys Redesigned)
• NRC-87-0088, Revised Ro:On 870130,start Failure of Emergency Diesel Generator (EDG) 14 Occurred During Monthly Surveillance Tests.History Folders for EDG Signal Generator Revised to Include Caution Sheet & Installation Check Encls  + (Revised Ro:On 870130,start Failure of Emergency Diesel Generator (EDG) 14 Occurred During Monthly Surveillance Tests.History Folders for EDG Signal Generator Revised to Include Caution Sheet & Installation Check Encls)
• ML20151Z157  + (Revised Ro:On 980817,980811 Event Re Slow Inward Drift of CR Reoccurred.Caused by Worn Worm Gear & Missing Full Turn of Worm Thread.Installed & Tested Drive Gear Coupling. Previously Submitted Ltr Rept Dtd 980911,deleted Text)
• ML20085N145  + (Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available)
• IR 05000289/1985097  + (Revised SALP Insp Rept 50-289/85-97 for 850916-860430)
• IR 05000213/1985099  + (Revised SALP Rept 50-213/85-99 for Sept 1983 - Feb 1985, Modifying Discussion Re Deviations from Normal QA Requirements & after-the-fact Determinations of Quality)
• ML17251A913  + (Revised SALP Rept 50-244/85-99 for Jan 1985 - May 1986)