TAC:43428
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Request for: Approved, Closed | |
Initiation
Questions Answers Results
Other: ML19247E427, ML19247E432, ML19247E433, ML19322D169, ML20003A916, ML20003A924, ML20004B934, ML20041D768 | |
| From | |
MONTHYEARML19322D1691978-06-0606 June 1978
[table view]Notifies That Lead Engineer Assignments Designated Re B&W Instrumentation in Response to 780517 Request.Forwards Task Definitions, & Lists Target Completion Schedule & Estimated Personpower Requirements ML20003A9241980-12-30030 December 1980 Final Version of Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater. Info Re power-operated Relief Valve Opening Probability Encl ML20003A9161981-01-30030 January 1981 Follows Up 801230 Response to NUREG-0737.Forwards Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater & Info Re power-operated Relief Valve Opening Probability ML19247E4321981-03-0303 March 1981 Provides fracture-mechanics Parametric Analysis of Overcooling Accident at Facility,In Response to Request ML19247E4331981-04-10010 April 1981 Updates Re Safety Implications of Control Sys & Dynamic Characteristics of Nuclear Facilities.Pressurized Thermal Shock Phenomena & Control Sys Implications to Safety Have Not Been Analyzed ML19247E4271981-04-28028 April 1981 Forwards Preliminary Assessment of Thermal Shock to PWR Reactor Pressure Vessels,In Response to 810416 Memo ML20004B9341981-05-22022 May 1981 Contends That 810512 B&W Rept Re Reactor Vessel Brittle Fracture Concerns Combined W/Encl Description of Facility Design Features Provide Sufficient Info to Identify That Reactor Vessel Thermal Shock Issue Is Not Safety Concern ML20030A7701981-07-20020 July 1981 Notification of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups in Bethesda,Md to Discuss Thermal Shock to Reactor Pressure Vessel Issue ML20041C6781982-02-25025 February 1982 Responds to NRC 820104 Request for Addl Info in Response to NUREG-0737 Item II.K.2.13 Re Thermal Mechanical Rept.Small Break LOCA Will Not Result in Brittle Fracture to Reactor Vessel.Further Operator Training Unwarranted ML20041D7681982-03-0303 March 1982 Submits Correction to Util Re NUREG-0737,Item II.K.2.13, Thermal-Mechanical Rept - Effect of HPI on Vessel Integrity for Small Break LOCA W/No Auxiliary Feedwater 1981-04-10 | |
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