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| Issue date | From | Title | Project stage | |
|---|---|---|---|---|
| ML20064N277 | 8 February 1983 | FirstEnergy Crouse R | Forwards Addl Info Re Training for Mitigating Core Damage. Station Superintendent Receives Adequate Experience in Regular Duties Which Abrogates Need for Formal Training for Mitigating Core Damage | Request |
| ML20072G034 | 21 March 1983 | FirstEnergy Crouse R | Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Extension to 830701 Requested for Submittal of Schedule for Resolution of Issue | Other |
| ML20090F697 | 30 June 1983 | FirstEnergy Crouse R | Notifies of Postponement of Submittal of Plans & Schedules for Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump (Generic Ltr 83-10) Until 830815, Due to Delay in Receipt of Generic Rept from B&W | Other |
| ML20080C103 | 12 August 1983 | FirstEnergy Crouse R | Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump. Schedule to Be Submitted by 830930,since B&W Generic Proposal Re Std Lower Loop Configuration to Be Evaluated | Other |
| ML20080N977 | 3 October 1983 | FirstEnergy Crouse R | Forwards Plan & Schedule for Resolution of NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, (Generic Ltr 83-10),per NRC 830208 Request.Operating Procedures for Pumps to Be Revised | Other |
| ML20085N570 | 27 October 1983 | FirstEnergy Crouse R | Advises of Delay in Submittal of Operating Procedures for Trip of Reactor Coolant Pumps (TMI Item II.K.3.5 & Generic Ltr 83-10).Program Reviewed in Light of Generic Ltr 83-31 Re Abnormal Transient Operating Guidelines | Other |
| ML20091H924 | 29 May 1984 | FirstEnergy Crouse R | Advises That Rept Re Resolution of TMI Action Item II.K.3.5 Automatic Trip of Reactor Coolant Pumps, in Response to Generic Ltr 83-10,will Be Submitted by 840731 | Other |
| ML20097C702 | 31 July 1984 | BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP | Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis | Other |
| ML20097C690 | 7 September 1984 | FirstEnergy Crouse R | Forwards Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis, (B&W Document 77-1152840-00) for Raised Loop Plant in Response to Generic Ltr 83-10 & TMI Item II.K.3.5 | Other |
| ML20207F605 | 29 December 1986 | FirstEnergy Williams J | Forwards Response to Generic Ltr 86-05 Re Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, Addressing plant-specific Concerns,Including Instrumentation Uncertainties & Operator Training | Other |
| ML20155G061 | 9 June 1988 | FirstEnergy Shelton D | Advises That Implementation of NUREG-0737,Item II.K.3.5 Complete.Util 861229 Response Stated That Facility Procedures Require Reactor Coolant Pump Trip When RCS Subcooling Margin Falls Below 20 F | Other |