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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20211B027 | 13 August 1999 | SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 | Boric Acid Non-Destructive Examination Hydrostatic Nondestructive Examination Temporary Modification VT-2 Incorporated by reference Liquid penetrant Pressure boundary leak |
| ML20195K287 | 16 June 1999 | Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves | Power-Operated Valves Backfit |
| ML20199H593 | 20 January 1999 | Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant | Fire Barrier |
| ML20155B678 | 28 October 1998 | Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process | |
| ML20236R144 | 15 July 1998 | SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 | Condition Adverse to Quality |
| ML20236K398 | 30 June 1998 | SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 | Coatings Nondestructive Examination VT-2 Incorporated by reference |
| ML20236K513 | 29 June 1998 | Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 | |
| ML20198R477 | 13 January 1998 | SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Pressure Boundary Leakage Through-Wall Leak |
| ML20128L300 | 2 October 1996 | SER Supporting Dbnp IPE Process of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities | Internal Flooding |
| ML20058M959 | 28 September 1993 | SE Accepting Licensee Response to GL 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' | |
| ML20057A379 | 20 August 1993 | SE Concluding That Second 10-yr Interval Inservice Insp Program Plan for Plant Has Unacceptable Exam Sample as Discussed in Encl Inel TER | VT-2 Incorporated by reference |
| ML20056G430 | 18 August 1993 | Safety Evaluation Re Inservice Testing Program Requests for Relief.Licensee Made Changes to Subj Program to Include Exercising & fail-safe Testing of Auxiliary Feedwater Valves AF-6451 & AF-6452,in Response to TER Anomaly 8 | Stroke time Incorporated by reference |
| ML20056B272 | 20 August 1990 | Safety Evaluation Granting Relief from ASME Code Repair Requirements for ASME Code 3 Piping | |
| ML20248D827 | 29 September 1989 | Safety Evaluation Accepting Util 890228 & 0630 Submittals Presenting Proposed Designs to Comply w/10CFR50.62 ATWS Rule Requirements | Anticipated operational occurrence |
| ML20247E690 | 5 September 1989 | Safety Evaluation of Audit of Facility Design for Resolution of IE Bulletin 79-27 Re Loss of non-Class IE Instrumentation & Control Power Sys Bus During Operation.Preventive Maint & Testing Program Should Be Developed for Bus Power Sources | Safe Shutdown |
| ML20247J873 | 18 May 1989 | Safety Evaluation Supporting Amend 133 to License NPF-3 | |
| NUREG-0660, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 | 3 May 1989 | Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 | |
| ML20196D960 | 8 December 1988 | Safety Evaluation Re Util Response Concerning Auxiliary Feedwater Sys Reliability Study.Util Should Ensure That Sys Mods Do Not Result in Net Reduction in Sys Reliability | |
| ML20207K791 | 4 October 1988 | Safety Evaluation Supporting Operation in Cycle 6 W/O Removing Flaws in Cracked HPI Nozzle | |
| ML20148D039 | 19 January 1988 | SER Accepting Util 831209 Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip reliability-on-line Testing.Unit Designed to Permit on-line Functional Testing of Diverse Trip Features of Reactor Trip Breakers | |
| ML20147C263 | 12 January 1988 | Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components | |
| ML20149F962 | 11 January 1988 | SER Accepting License Response to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for safety- Related Components | Safe Shutdown |
| ML20236U653 | 27 November 1987 | Safety Evaluation Re Effects of Errors in Util Analysis of Small Break Loca.Use of Incorrect Values in Analysis Results in Incomplete Compliance w/10CFR50,App K.Plant Poses No Risk to Public Health Due to Meeting 10CFR50.46 Requirements | Coast down |
| ML20236T387 | 25 November 1987 | SER Re Conformance to Reg Guide 1.97 Concerning post-accident Monitoring Instrumentation.Design Acceptable | Grab sample |
| ML20211G864 | 11 February 1987 | Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Item 3.2.3, Post-Maint Testing & All Other Safety-Related Components | |
| ML20207Q671 | 9 January 1987 | Safety Evaluation Supporting Util Re Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events | |
| ML20212C923 | 4 August 1986 | Sser Supporting Util Reanalyses of 74 Masonry Walls | |
| ML20212G602 | 4 August 1986 | Safety Evaluation Accepting Util Response to NRC Request for Addl Info Re Question 29 Concerning Training for Infrequent, Critical & Difficult Tasks | |
| ML20212R342 | 10 June 1986 | SER Re Progress Made by Licensee in Area of Plant Maint.New Maint Organization Functioning W/No Major Weaknesses.Region III Will Continue to Monitor Maint at Plant to Assure Continued Control & Progress | |
| ML20206F304 | 27 May 1986 | Safety Evaluation Accepting Util Review Re Cold Pressurization of Secondary Side of Steam Generator During Testing on 850906 | Hydrostatic |
| ML20203N914 | 17 April 1986 | Safety Evaluation Accepting Proposed Mods to Safety Actuation Sys Re Shared Power Supply Returns as Result of 801205 Actuation | |
| NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing | 6 March 1986 | Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing | |
| ML20137J689 | 8 January 1986 | Safety Evaluation Supporting Util Identification of Root Causes for Spurious 850609 Steam & Feedwater Line Rupture Control Sys Low Level Actuation,Closure of MSIVs & Actions Taken to Prevent Recurrence.Plant Restart Acceptable | |
| ML20137J703 | 8 January 1986 | SER Supporting Util Identification of Root Causes for Source Range Nuclear Instrumentation Channels Inoperability During 850609 Steam & Feedwater Line Rupture Control Sys Low Level Actuation & Corrective Actions Taken.Plant Restart Approved | Shutdown Margin |
| ML20136B784 | 24 December 1985 | SER Re Util Development of Systematic & Thorough Troubleshooting Plans to Investigate 850609 Incident Leaving Redundant source-range Nuclear Instrumentation Channels Inoperable.Restart & Power Operation Now Acceptable | Shutdown Margin |
| ML20137R161 | 12 November 1985 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Preventive Maint & Trending of Parameters | |
| ML20138P068 | 30 October 1985 | Safety Evaluation Accepting Licensee 831107 & 850709 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability (vendor-related Mods & Sys Functional Test Description) | |
| ML20138P639 | 30 October 1985 | SER Re Proposed Mods to Maint Program.Licensee Should Identify Actions to Be Completed Prior to or After Restart. Region Should Actively Monitor Licensee Progress | |
| ML20133Q044 | 24 October 1985 | Safety Evaluation Supporting Util 831107 Response to Generic Ltr 83-28,Item 3.1.3 Re post-maint Testing (Reactor Trip Sys Components).Eg&G Technical Evaluation Rept Encl | |
| ML20062E087 | 29 July 1982 | Safety Evaluation Supporting Licensee Request for Relief from ASME Boiler & Pressure Vessel Code Section XI Hydrostatic Test (Insp) Requirements | Hydrostatic Nondestructive Examination Incorporated by reference Liquid penetrant |
| ML20214J280 | 20 December 1979 | Safety Evaluation Re Preliminary Design for Upgrading Present control-grade Anticipatory Reactor Trip Sys for Loss of Main Feedwater & Turbine Trip to safety-grade | |
| ML20125B133 | 16 December 1968 | Safety Evaluation Re Piqua Nuclear Power Facility Retirement.T Hamrick to J Schlesinger Encl | Earthquake |