Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20203F451 | 12 February 1999 | SER Finding Licensee Adequately Addressed GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Virgil C Summer Nuclear Station | Stroke time Probabilistic Risk Assessment |
ML20198F424 | 18 December 1998 | Safety Evaluation Granting Relief Request for Approval to Repair ASME Code Class 3 Service Water Piping Flaws in Accordance with GL 90-05 for VC Summer Nuclear Station | Safe Shutdown |
ML20155G455 | 4 November 1998 | Safety Evaluation Accepting Licensee Proposed Alternative to Use Code Case N-416-1 with Licensee Proposed Addl Exams | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Pressure boundary leak |
ML20154Q957 | 21 October 1998 | SER Accepting Request Seeking Approval to Use Alternative Rules of ASME Code Case N-498-1 for Class 1,2 or 3 Sys | Non-Destructive Examination Hydrostatic VT-2 Incorporated by reference |
ML20237A718 | 13 August 1998 | SER Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves | Power-Operated Valves Backfit |
ML20248J019 | 4 June 1998 | Safety Evaluation Accepting Licensee Inservice Testing Program Interim Pump Relief Request Per 10CFR50.55a(a)(3) (II) | Incorporated by reference |
ML20212C038 | 19 October 1997 | Safety Evaluation Accepting License Request for Deviation from Commitment to Meet Section III.G.2.c of App R to 10CFR50 Re Fire Protection of Safe Shutdown Capability for Plant | Safe Shutdown Fire Barrier Fire Protection Program |
ML20217E349 | 22 September 1997 | Safety Evaluation Authorizing Licensee Proposed Alternative for Current Interval Insp Program Plan | Incorporated by reference |
ML20133J555 | 15 January 1997 | Safety Evaluation Granting Licensee Request Proposing Not to Perform Increased Frequency Testing on a Charging Pump at Virgil C Summer Nuclear Station | |
ML20128G293 | 2 October 1996 | Safety Evaluation Supporting Amend 135 to License NPF-12 | |
ML20128F422 | 9 February 1993 | Safety Evaluation Re Nuclear Physics Methodology for Reload Design.Request to Perform Reload Analyses Approved | |
ML20056A793 | 6 August 1990 | Safety Evaluation Re Capability of Plant to Meet Requirements of Branch Technical Position Rsb 5-1, Design Requirements of RHR Sys. Design Satisfies License Condition 4 | Boric Acid Shutdown Margin |
ML20245F506 | 22 June 1989 | Safety Evaluation Re Request for Relief from Section XI Re Hydrostatic Test Requirement | Hydrostatic |
ML20244D736 | 12 June 1989 | Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Domestic Operating Reactors | |
ML20195B442 | 28 October 1988 | Safety Evaluation Supporting Amend 74 to License NPF-12 | |
ML20151K090 | 28 July 1988 | Safety Evaluation Supporting Util Proposed Implementation of ATWS Rule Pending Resolution of Tech Spec Issue | Anticipated operational occurrence |
ML20151K777 | 27 July 1988 | Safety Evaluation Supporting Util Request to Deviate from Recommendations of Reg Guide 1.97 Re Instrumentation to Monitor Containment Temp | |
ML20151R856 | 19 April 1988 | Safety Evaluation Supporting Related Inservice Testing Program & Request for Relief of Utils | Stroke time |
ML20236R411 | 13 November 1987 | Safety Evaluation Supporting Conformance to Reg Guide 1.97, Rev 3 | Boric Acid Anticipated operational occurrence Fuel cladding |
ML20236K770 | 5 November 1987 | SER Accepting Util 831104 & 870401 Responses to Item 2.2.1 of Genreic Ltr 83-28 Re Equipment Classification Programs | |
ML20237H366 | 22 July 1987 | Corrected Page to Safety Evaluation Issued W/Amend 67, Changing Second Paragraph & Deleting Third Paragraph on Page Three | |
ML20214S888 | 3 June 1987 | Safety Evaluation Rept Granting Relief from Hydrostatic Testing After Repair to ASME Code Section Xi,Class 1,reactor Coolant Pump Seal Injection Line | Unanalyzed Condition Hydrostatic Nondestructive Examination VT-2 |
ML20209H333 | 30 January 1987 | SER Supporting Util 831104 Response to Generic Ltr 83-28, Item 4.5.2 Re on-line Testing of Reactor Trip Sys Reliability | |
ML20213A561 | 30 January 1987 | SER Accepting Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 2) Re Vendor Interface Program for Reactor Trip Sys Components | |
ML20212F284 | 22 December 1986 | Safety Evaluation Supporting Amend 57 to License NPF-12 | |
ML20211M416 | 9 December 1986 | Safety Evalution Supporting Licensee 860123 Submittals Re Fast Neutron Fluence for Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61) | |
ML20203N015 | 15 September 1986 | Safety Evaluation Re Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Post-Maint Testing (RTS Components,All Other Safety-Related Components). Response Acceptable | |
ML20199D421 | 9 June 1986 | SER on Util 831104 & 860423 Responses to Generic Ltr 83-28, Item 1.2 Re post-trip Review Data & Info Capabilities.Data & Info Capabilities Acceptable | |
ML20211A257 | 22 May 1986 | Safety Evaluation Accepting Mods to App R,Clarified by Generic Ltrs 81-12 & 83-33,to Prevent Spurious Equipment Operation Caused by fire-induced Conductor or Cable Faults, Facilitate Operator Actions & Resolve Addl Circuit Concerns | Hot Short Safe Shutdown Fire Barrier Emergency Lighting Fire Watch |
ML20154A062 | 24 February 1986 | Safety Evaluation Supporting 850930 & 1204 Responses to 850802 & 1104 Requests,Respectively,For Addl Info Re Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events | |
ML20154D192 | 14 February 1986 | Sser 1 Re Licensee 851204 Response to Generic Ltr 83-28, Item 3.2.2 Concerning Procedures & Programs to Review Info on safety-related Equipment.Response Acceptable & Meets Intent of Generic Ltr 83-28 | |
ML20136B229 | 7 November 1985 | Safety Evaluation Supporting Amend 46 to License NPF-12 | Shutdown Margin |
ML20209H841 | 4 November 1985 | Safety Evaluation Re Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1.Response to Item 3.2.2 Incomplete & Addl Info Required | |
ML20137S578 | 24 September 1985 | SER Approving Licensee 831104 & 0715 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Program & Procedures for Restart from Unscheduled Reactor Trip Acceptable | |
ML20133H732 | 2 August 1985 | SER Re Util 831104 Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Concerning Reactor Trip Sys Reliability. Licensee Should Add Undervoltage Trip Attachment to Trending Program | |
ML20128A218 | 21 June 1985 | SER of Util Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Listed Addl Info Required Before Review Can Be Completed |