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 Issue dateTitle
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn 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 Piping13 June 1991Thermal Stratification in Feedwater System Piping
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break30 June 1989Degradation of Containment Isolation Capability by a High-Energy Line Break
ML20154Q13419 September 1988Forwards AEOD Engineering Evaluation Rept That Discusses Several Events of Immersion Heaters Inside Primary Sys Being Energized While Not Covered W/Liquid
ML20151B32330 March 1988Errata to Amends 97 & 98 to License DPR-54,correcting Inadvertent Errors in Tech Specs
ML20148J84617 March 1988Amend 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 80-1131 December 1987Lessons 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 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11
ML20235Q5111 October 1987Proposed Tech Specs Re Comparison of Plant Tech Specs to STS
NRC Generic Letter 1987-129 July 1987NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled
ML20235F76830 June 1987Proposed Tech Specs Re Radiological Effluents
Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System2 February 1987Miswiring in a Westinghouse Rod Control System
ML20211P61231 December 1986Amend 2 to Action Plan for Performance Improvement
ML20212Q01915 December 1986Amend 2 of Rancho Seco Action Plan for Performance Improvement
ML20214V8603 September 1986Exam 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 Tubing26 June 1986Improper Installation of Heat Shrinkable Tubing
ML20140E18227 January 1986Proposed Tech Specs,Specifying That Beginning W/Cycle 8, 10CFR50.59 Submitted for Future Core Reloads Will Be Via Core Operating Limits Manual
ML20138H59010 December 1985Exam 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 1983-4319 December 1983NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications