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Issue date | Title | |
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Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures | 9 July 1997 | Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
NRC Generic Letter 1992-02 | 6 March 1992 | NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown. |
ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability |
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping | 13 June 1991 | Thermal Stratification in Feedwater System Piping |
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break | 30 June 1989 | Degradation of Containment Isolation Capability by a High-Energy Line Break |
ML20154Q134 | 19 September 1988 | Forwards AEOD Engineering Evaluation Rept That Discusses Several Events of Immersion Heaters Inside Primary Sys Being Energized While Not Covered W/Liquid |
ML20151B323 | 30 March 1988 | Errata to Amends 97 & 98 to License DPR-54,correcting Inadvertent Errors in Tech Specs |
ML20148J846 | 17 March 1988 | Amend 98 to License DPR-54,revising Tech Specs by Reducing Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys |
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11 |
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 | 31 December 1987 | Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11 |
ML20235Q511 | 1 October 1987 | Proposed Tech Specs Re Comparison of Plant Tech Specs to STS |
NRC Generic Letter 1987-12 | 9 July 1987 | NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled |
ML20235F768 | 30 June 1987 | Proposed Tech Specs Re Radiological Effluents |
Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System | 2 February 1987 | Miswiring in a Westinghouse Rod Control System |
ML20211P612 | 31 December 1986 | Amend 2 to Action Plan for Performance Improvement |
ML20212Q019 | 15 December 1986 | Amend 2 of Rancho Seco Action Plan for Performance Improvement |
ML20214V860 | 3 September 1986 | Exam Rept 50-312/OL-86-02 on 860722-25.Exam results:11 Operators Took Written & Operating Exams.Two Senior Reactor Operators Failed Written Exam |
Information Notice 1986-53, Improper Installation of Heat Shrinkable Tubing | 26 June 1986 | Improper Installation of Heat Shrinkable Tubing |
ML20140E182 | 27 January 1986 | Proposed Tech Specs,Specifying That Beginning W/Cycle 8, 10CFR50.59 Submitted for Future Core Reloads Will Be Via Core Operating Limits Manual |
ML20138H590 | 10 December 1985 | Exam Rept 50-312/OL-85-02 on 851029-31.Exam Results:Six of Eight Reactor Operator Candidates Passed Written & Operating Exam,One Failed Both Exams & One Failed Written Exam.Senior Reactor Operator Candidate Passed |
NRC Generic Letter 1983-43 | 19 December 1983 | NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications |