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| Issue date | Title | Topic | |
|---|---|---|---|
| ML19225C786 | 10 April 1979 | B&W 177 Fuel Assembly Owners' Group Asymmetric LOCA Loads Evaluation Program,Phase 2. | |
| ML19248D162 | 8 August 1979 | Corporate Capabilities. | |
| ML19254F910 | 13 November 1979 | Draft Auxiliary Feedwater Sys,Reliability Analysis, Revision 1 | Loop seal Earthquake |
| ML19257B795 | 10 January 1980 | Safety Evaluation for Delay in Testing of Reactor Vessel Internal Vent Valves | |
| ML19260D869 | 31 January 1980 | Potential Reactor Sys Voiding During Anticipated Transients. | |
| ML19261A425 | 5 January 1979 | Reliability Study of Davis-Besse Unit 1,Decay Heat Removal Sys Suction Bypass, Prepared by Bechtel Power Corp.Analyzes Incidents Re Decay Heat Removal Sys Exposure to Overpressure Due to Improper Opening of Suction Bypass | Recently irradiated fuel |
| ML19289E907 | 19 May 1979 | Evaluation of Transient Behavior & Small Reactor Coolant Sys Breaks in 177 Fuel Assembly Plant,790516. Vol 3, Revision 1 | |
| ML19317F534 | 30 September 1976 | Evaluation of Compliance W/App I to 10CFR50. | Boric Acid |
| ML19317F550 | 20 January 1978 | Completed Questionnaire for NRC Reliability Study of Standby Diesel Generator Units. | |
| ML19317F753 | 25 May 1978 | Determination of Total Reactor Coolant Flowrate & Its Accuracy for Facility. Statement Addressing Foreign Matl & Deposits in Secondary Sys Encl | |
| ML19319B492 | 30 August 1977 | Facility & Instrument Grounding Sys, Revision 1 | |
| ML19319B878 | 30 July 1972 | Total Impact Assessment of Davis-Besse Nuclear Power Station. Prepared for State of Oh Dept of Natural Resources | High winds Earthquake |
| ML19319B945 | 20 March 1978 | Safety Evaluation Supporting Revision of Tech Spec 3.4.2 to Commit to Operability Decay Heat Removal Sys Pressure Relief Valve DH-4849 & to Remove Control Power from DH-11 & DH-12 When Open to Assure Overpressure Protection of RCS | |
| ML19319B950 | 13 January 1978 | Safety Evaluation Supporting Revision of Tech Spec 4.5.2 Assuring Proper ECCS Flows During LOCA | |
| ML19319C102 | 29 July 1977 | Safety Evaluation Supporting Change to Tech Specs | Tornado Generated Missile Offsite Circuit |
| ML19323C959 | 5 May 1979 | to Fire Hazard Analysis Rept.W/Oversize Drawings | |
| ML19323D052 | 9 July 1979 | Suppl 1 to Seismic Re-evaluation. | |
| ML19324C176 | 30 October 1989 | Hpi/Makeup Nozzle Weld Overlay Repair Contingency Plan. | Weld Overlay |
| ML19326A130 | 23 October 1978 | Safety Evaluation Supporting Change to Relevant Tables & Figures Re Actual Reactor Pump Coastdown Characteristics | |
| ML19326B174 | 25 February 1971 | Applicants Responses to Issues Raised by Limited Appearors. | Fuel cladding |
| ML19327B016 | 11 October 1989 | Cycle 7 LOCA Limits. | |
| ML19329A880 | 8 February 1977 | Fuel Rod Bow Effect on Davis Besse 1,Tech Specs. | |
| ML19329A984 | 11 November 1977 | Rept on Fracture Toughness & Potential for Lamellar Tearing of Steam Generator & Reactor Coolant Pump Supports. | |
| ML19329B055 | 10 April 1978 | Safety Evaluation Supporting Revision of Tech Spec Table 3.2-1, DNB Margin Reactor Coolant Flow Rates to Accommodate DNBR Penalty Per OL Condition | Incorporated by reference |
| ML19329B323 | 28 March 1973 | Applicants' Response to Agency Comments on Nov 1972 Des by Aec. | |
| ML19329D801 | 16 March 1979 | Safety Evaluation for Radiological Effluent Tech Specs. Supports Changes | |
| ML19353A173 | 30 December 1980 | Addendum 1 To:Analyses of Adequacy of Davis-Besse Nuclear Power Station Onsite Electrical Auxiliary Distribution Power Sys Voltages. | |
| ML20003C816 | 13 March 1981 | to Suppl 2 of Seismic Re-evaluation. Rept Reflects Revisions to Analysis Re Emergency Diesel Generator & Cooling Water Heat Exchanger | |
| ML20004B635 | 1 June 1981 | Emergency Response Facilities. | Health Physics Network |
| ML20004C648 | 31 March 1981 | Control Room Habitability Study. | Loctite |
| ML20006E367 | 11 January 1990 | Toledo Edison Co Mark-BZ Fuel Assembly Seismic & LOCA Analysis. | Safe Shutdown Earthquake Earthquake |
| ML20039E178 | 31 December 1981 | Auxiliary Feedwater Sys Reliability Analysis Final Rept, Prepared for Toledo Edison Co | Mission time Probabilistic Risk Assessment Earthquake |
| ML20039E684 | 30 December 1981 | Draft Computer Analysis & Design of Siren Prompt Notification Sys, Prepared for Toledo Edison Co | |
| ML20041D375 | 31 January 1982 | Evaluation of Davis-Besse Nuclear Power Station. | Boric Acid Temporary Modification |
| ML20058L189 | 1 August 1990 | Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1 | |
| ML20062F839 | 11 October 1978 | Atws:A Reappraisal.A Presentation to the Acrs. Concludes That Use of Addl Relief Valves in Pwr'S,Based on WASH-1400 Analysis,May Actually Increase Risk to Public | Half scram Scram Discharge Volume |
| ML20067D331 | 31 August 1993 | Technical Evaluation Rept,Evaluation of B&Wog Pressurizer Surge Line Thermal Stratification Program to Address NRC Bulletin 88-11 | Finite Element Analysis |
| ML20069K463 | 31 March 1983 | Evaluation of Davis-Besse Nuclear Power Station - 1982 | |
| ML20070Q191 | 25 March 1991 | NRC Form 474 Simulation Facility Certification | Shutdown Margin Stroke time Post Accident Monitoring Fuel cladding |
| ML20070T112 | 31 January 1983 | Rev 0 to Davis-Besse Analysis & Evaluation of Safety/Relief Valve Discharge Sys Per NRC NUREG-0737, Technical Rept. W/Two Oversize Drawings.Aperture Cards Are Available in PDR | Loop seal |
| ML20073J602 | 12 April 1983 | Continuous Reactor Vessel Head Vent Design Evaluation Rept | |
| ML20082P038 | 30 November 1983 | SAR & Implementation Plan for Davis-Besse Nuclear Power Station Safety Parameter Display Sys | Post Accident Monitoring |
| ML20085A480 | 10 October 1977 | Nuclear Svc Site Ofc Rept 59 for 770916-1009 | |
| ML20091P572 | 31 October 1991 | Reactor Containment Bldg Integrated Leak Rate Test Including,Type A,B & C Periodic Test Results | |
| ML20091S431 | 31 August 1995 | USI A-46 Seismic Evaluation Rept. W/61 Oversize Drawings | Safe Shutdown Boric Acid High Radiation Area Ultimate heat sink Mission time Safe Shutdown Earthquake Probabilistic Risk Assessment Coatings Finite Element Analysis Condition Adverse to Quality Earthquake Backfit |
| ML20092P239 | 29 June 1984 | Detailed Control Room Design Review for Davis-Besse Nuclear Power Plant, Summary Rept.Rept Prepared in Response to NUREG-0737,Item 1.D.1.Review Conducted Using Suppl 1 to NUREG-0737 | |
| ML20094J084 | 8 December 1989 | Investigation of Acoustic Leak Monitoring for NRC Region Iii. Info Partially Deleted | VT-2 Through-Wall Leak |
| ML20094J664 | 31 May 1984 | Analyses of Capsule TE1-B,Toledo Edison Co,Davis-Besse Nuclear Power Station,Unit 1 Reactor Vessel Matl Surveillance Program | Hydrostatic |
| ML20100F106 | 30 November 1984 | Comparison of Davis-Besse Abnormal Transient Operator Guidelines & Emergency Operating Procedure EP 1202.01 | |
| ML20114E640 | 9 July 1979 | Seismic Re-evaluation | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |