Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
ML20207E185 | 27 May 1999 | Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing |
ML20212P392 | 31 August 1986 | Safety Evaluation Report Related to the Operation of Beaver Valley Power Station,Unit 2.Docket No. 50-412.(Duquesne Light Company,Et Al) |
ML20215H226 | 30 November 1984 | Rev 2 to Post-Accident Core Damage Assessment Methodology |
ML20237B972 | 19 March 1998 | Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees |
ML20237H242 | 13 August 1987 | Forwards Advance Copy of Sser 6 |
ML20238A754 | 31 August 1987 | Safety Evaluation Report Related to the Operation of Beaver Valley Power Station,Unit 2.Docket No. 50-412.(Duquesne Light Company,Et Al) |
ML20335A142 | 23 November 2020 | 8 to Technical Specification Bases Update Status |
ML21334A034 | 22 November 2021 | Technical Specifications Bases Update Status, Revision 41 |
ML22144A127 | 18 May 2022 | Rev. 43 to Technical Specification Bases |
ML23144A307 | 23 May 2023 | Technical Specification Bases Update Status, Revision 47 |
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 |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
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) |
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 |