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| Issue date | Title | |
|---|---|---|
| ML21104A354 | 25 September 2020 | 3 to Updated Final Safety Analysis Report, Section 3, Design Criteria- Structures, Components, Equipment, and Systems, Part 1 of 3 (Redacted) |
| ML21104A372 | 25 September 2020 | 3 to Updated Final Safety Analysis Report, Section 12, Radiation Protection (Redacted) |
| ML19100A306 | 21 June 2019 | Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 |
| L-17-253, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 | 9 October 2017 | Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 |
| IR 05000346/2013010 | 16 September 2016 | Closure of Unresolved Item 05000346/2013010-01 - Inspection Report 05000346/2016010 |
| ML15082A125 | 1 April 2015 | Final TIA Response-Laminar Cracks in the Shield Building |
| ML14136A486 | 16 May 2014 | Fenoc'S Answer Opposing Intervenors'S Motion for Admission of Contention No. 6 |
| ML14080A184 | 21 March 2014 | Summary of Webinar Meeting to Discuss NRC Inspection Activities Associated with the Davis-Besse Nuclear Power Station Installation of Two New Steam Generators |
| ML14050A290 | 28 February 2014 | NUREG-1437, Supp 52 Dfc, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse. |
| ML12254A138 | 10 September 2012 | NRC Staff'S Answer to Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking) |
| ML12131A031 | 10 May 2012 | NRC Staff Transmittal of Inspection Report Regarding Cracks Found in the Shield Building for Davis-Besse, Unit 1 |
| IR 05000346/2012007 | 7 May 2012 | IR 05000346-12-007 (Drs), 07/18/2011 - 04/17/2012, Davis-Besse Nuclear Power Station; Reactor Vessel Head Replacement and Shield Building Cracking |
| ML12037A245 | 6 February 2012 | Fenoc'S Answer Opposing Intervenors' Motion for Admission of Contention No. 5 on Shield Building Cracking |
| ML12004A010 | 4 January 2012 | Public Meeting NRC Slides |
| IR 05000346/2011011 | 13 May 2011 | IR 05000346-11-011, on 03/23/2011 - 04/29/2011, Davis-Besse Nuclear Power Station Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event |
| NRC-2010-0131, Brief of Nuclear Energy Institute as Amicus Curiae in Opposition to the Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions | 2 May 2011 | Brief of Nuclear Energy Institute as Amicus Curiae in Opposition to the Emergency Petition to Suspend All Pending Reactor Licensing Decisions and Related Rulemaking Decisions |
| ML110210999 | 21 January 2011 | NRC Staff'S Answer to Joint Petitioners' Request for a Hearing and Petition for a Leave to Intervene |
| ML100250132 | 11 January 2010 | 0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B |
| ML050120327 | 5 January 2005 | License Amendment Application to Revise Technical Specification 3/4.3.2.1, Safety Features Actuation System Instrumentation, to Permit a Single Inoperable Safety Features Actuation System (Sfas) Instrument String. |
| IR 05000346/1998018 | 22 January 1999 | Insp Rept 50-346/98-18 on 981110-990102.No Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support |
| ML20237D383 | 21 August 1998 | Forwards Response to NRC 980318 RAI Re Ipeee.Summary of Reliability Considerations for Intact RCS & Small LOCA Cases,Provided as Encl |
| ML20132C273 | 17 December 1996 | Requests Addl Info Re in Order to Complete Review of A-46 Program.Rai Encl |
| ML20116K263 | 7 August 1996 | Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle |
| ML20059L881 | 18 September 1990 | Provides Feed & Bleed Mod Summary.Feed & Bleed Cooling Would Be Required Only in beyond-design Basis Event Involving Loss of Primary to Secondary Heat Transfer |
| ML20215D674 | 12 June 1987 | Suppl 4 to Petition for Immediate Action to Relieve Undue Risk Posed by Nuclear Power Plants Designed by B&W.Ucs Reply to Responses from NRC & B&W Owners Group.* Certificate of Svc Encl |
| ML20213H083 | 16 October 1986 | Forwards Engineering Evaluation of Seismic Anchors for Electrical & Control Panels Re Several Recent Events Involving Inadequate Anchorage of Electrical & Control Panels.Usi A-46 Nearing Resolution |
| ML19347F640 | 15 May 1981 | LER 80-048/01X-2:on 800627,per IE Bulletin 79-14,pipe Support HCB-40-B1 Was Found Not installed,CCA-8-H15 Was Found Mislocated & Supports SR-11,EBB-1-H3 & EBB-1-H4 Exceeded Design Loads.Caused by Const/Installation Error |
| ML19321B199 | 22 July 1980 | LER 80-052/01T-0:on 800709,during Review of Seismic Calculations,Exhaust Ductwork of Emergency Diesel Generators Created Overstressed Conditions at Exhaust Nozzles.Caused by Design Deficiency.Supports Will Be Added |
| ML19331B664 | 10 July 1980 | LER 80-048/01T-1:on 800627,during IE Bulletin 79-14 Insp, Pipe Support HCV-40-B1 Found Not Installed & CCA-8-H15 Mislocated.Caused by Const/Installation Error.Pipe Support HCB-40-B1 to Be added.CCA-8-H15 to Be Designed & Relocated |
| ML19305D309 | 7 April 1980 | Monthly Operating Rept for Mar 1980 |
| ML19242D070 | 7 August 1979 | Monthly Operating Rept for Jul 1979 |
| ML19224C997 | 3 July 1979 | LER 79-064/01T-0 on 790621:impact Points of Eight Main Steam Line Seismic Restraint Locations May Deform If Sufficient Seismic Event Occurs.Caused by Design Deficiency.Web Reinforcing Plates Installed at Impact Points |
| ML19326B099 | 18 January 1971 | Applicants' Reply to Motion for Production of Documents & to Interrogatories Served by Intervenors Living in Finer Environ,Ii Oster & WE Reany on 710112.Ws Little Affidavit Re BAW-1338 & BAW-10006 Encl |
| ML19329C480 | 31 October 1969 | Seismological & Geological Review. |