TAC:49662
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Other: ML20072G034, ML20080C103, ML20080N977, ML20085N570, ML20090F697, ML20091H924, ML20097C690, ML20097C702, ML20155G061, ML20207F605 | |
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MONTHYEARML20064N2771983-02-0808 February 1983
[table view]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 ML20072G0341983-03-21021 March 1983 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 ML20090F6971983-06-30030 June 1983 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 ML20080C1031983-08-12012 August 1983 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 ML20080N9771983-10-0303 October 1983 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 ML20085N5701983-10-27027 October 1983 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 ML20091H9241984-05-29029 May 1984 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 ML20097C7021984-07-31031 July 1984 Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis ML20097C6901984-09-0707 September 1984 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 ML20207F6051986-12-29029 December 1986 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 ML20155G0611988-06-0909 June 1988 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 1983-08-12 |
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