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| Issue date | Title | |
|---|---|---|
| ML22263A418 | 20 September 2022 | Enclosure F - DBNPS, Unit 1, Technical Specification Bases, Rev. 32 |
| ML20302A287 | 25 September 2020 | 9 to Tech Spec Bases |
| L-16-256, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan | 6 September 2016 | Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan |
| ML12258A306 | 14 September 2012 | Attachment B - NRC Staff Answer to Motion for Summary Disposition of Contention 4 |
| L-09-263, Response to NRC Request for Additional Information Regarding Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. | 26 October 2009 | Response to NRC Request for Additional Information Regarding Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. |
| ML082910112 | 20 November 2008 | ITSB M - More Restrictive Changes - to Davis Besse Amendment Beyond Scope Issues |
| L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations | 7 August 2008 | Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations |
| ML082270665 | 7 August 2008 | Improved Technical Specification Conversion License Amendment Request, Volume 8, Revision 1, Section 3.3 - Instrumentation |
| ML072200481 | 3 August 2007 | Volume 14, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.9 Refueling Operations. |
| ML072200470 | 3 August 2007 | Volume 8, Revision 0, Davis-Besse, Unit 1 - Improved Technical Specifications Conversion, ITS Section 3.3 Instrumentation. |
| IR 05000346/2006003 | 11 August 2006 | IR 05000346-06-003; Firstenergy Nuclear Operating Company;4/1/2006 - 6/30/2006; Davis-Besse Nuclear Power Station; Fire Protection, Surveillance Testing, Access Control to Radiologically Significant Areas, and Identification and Resolution |
| IR 05000346/2006002 | 4 May 2006 | IR 05000346-06-002; on 1/1/2006 - 3/31/2006; Davis-Besse Nuclear Power Station; Inservice Inspection |
| IR 05000346/2005002 | 18 March 2005 | IR 05000346-05-002; 1/01/2005 - 2/19/2005; Davis-Besse Nuclear Power Station; Post-Maintenance Testing |
| Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
| ML20205G568 | 26 March 1999 | Advises of Completion of Plant Performance Review on 990202 to Develop Integrated Understanding of Safety Performance. Overall Performance of Plant Acceptable.Plant Issues Matrix & Insp Plan Encl |
| ML20198B151 | 2 December 1998 | Forwards Insp Activity Plan for Next 6 Months & Plant Issues Matrix.Infor Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite |
| IR 05000346/1998005 | 11 June 1998 | Insp Rept 50-346/98-05 on 980401-0512.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
| Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
| Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
| Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
| Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
| Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
| Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
| Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
| ML20056H090 | 27 August 1993 | SALP Rept 50-346/93-01 for 911201-930630 |
| Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
| Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
| IR 05000346/1992018 | 12 January 1993 | Insp Rept 50-346/92-18 on 921207-18.No Violations Noted. Major Areas Inspected:Design Changes,Mods & Temporary Alterations Conducted Per Insp Module 37700 |
| NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
| Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
| ML20011F428 | 21 February 1990 | Forwards Emergency Response Data Sys Data Point Library Ref Files.Util Will Contact NRC Contractor Directly in Order to Arrange Mutually Acceptable Schedule for Preliminary Testing of Sys |
| ML20148H603 | 15 December 1987 | Summary of ACRS DHR Sys Subcommittee 871117 Meeting in Washington,Dc Re Util Decision Not to Install Dedicated Blowdown Sys at Davis Besse & Implications of Diablo Canyon Loss of Shutdown Cooling Event.Viewgraphs Encl |
| ML20216H604 | 25 June 1987 | Advises That Based on B&W Analytical Studies for Primary Sys Blowdown Using RELAP5,use of Blowdown Valves Not Practicable for Feed & Bleed,Per 851204 Commitment.Listed Proposed Mods Will Be Implemented to Enhance Makeup Sys |
| ML20214T723 | 25 November 1986 | Informs of Major Discrepancies Between B&W Topical Rept BAW-10075A,Rev 1, Multinode Analysis of Small Breaks for B&W 177-Fuel Assembly...Plants W/Raised Loop Arrangements & Internal Vent Valves, & as-built Configuration of Plant |
| ML20132A424 | 18 September 1985 | Transcript of 850918 Public Meeting in Washington,Dc Re Continuation of Briefing on Plant.Pp 1-80.Supporting Documentation Encl |
| NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
| NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
| NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
| NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
| ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
| ML20087M670 | 22 March 1984 | Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in post-accident Sampling Sys & post- Accident Instrumentation for in-core Thermocouple & Reactor Coolant Hot Leg Level |
| ML20009A519 | 30 June 1981 | Abnormal Transient Operating Guideline (Atog) Program Description. |
| ML20207L334 | 9 April 1980 | Evaluation of Licensee Compliance W/Category `A' Items of NRC Recommendations Resulting from TMI-2 Lessons Learned, Davis Besse Nuclear Power Station |