TAC:44132
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Request for: Approved, Closed | |
Results Other: ML20054F383, ML20133K973, ML20135A372, ML20135A778, ML20137A994, ML20137N770, ML20137N995, ML20140E550, ML20155E786, ML20155E791, ML20198C257, ML20203H685, ML20236L390, ML20238A595 | |
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MONTHYEARML20054F3831982-06-11011 June 1982
[table view]Forwards Addl Info Re Implementation Schedules for NUREG-0737 Items,In Response to Generic Ltr 82-10.Items Include I.A.1.3.1,I.A.1.3.2,I.C.1,II.D.1.2,II.D.1.3, II.K.3.30,II.K.3.31,III.A.1.2,III.A.2.2 & III.D.3.4 ML20140E5501985-01-0404 January 1985 Forwards Schedule for Submitting Addl Info & Justification of Nonconformance of Core Exit Thermocouples & Subcooling Margin Monitors,Per 840202 SER on Util Response to Generic Ltr 82-28 & NUREG-0737,Item II.F.2 IR 05000344/19850141985-06-12012 June 1985 Insp Rept 50-344/85-14 on 850513-17.Violation Noted:Failure to Perform Survey (Evaluation) of Extremity Exposure Due to Nonpenetrating Radiation Per 10CFR20.201 ML20126M4801985-06-13013 June 1985 Forwards Request for Addl Info Re Core Exit Thermocouple Sys,Subcooling Margin Monitors & Reactor Vessel Level Instrumentation Sys,In Order to Complete Review of 840312 & 850104 Submittals for TMI Item II.F.2.3 ML20128B2021985-06-27027 June 1985 Advises That Response to 850612 Request for Addl Info Re NUREG-0737,Item II.D.1 Will Be Submitted by 851231 ML20129K1171985-07-19019 July 1985 Responds to 850613 Request for Addl Info Re NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation. Class 1E Platinum Resistance Temp Detectors Will Be Used to Measure Ref Junction Temp for Backup Displays ML20133K9731985-08-0707 August 1985 Proposed Tech Specs,Incorporating TMI-related Items Per NRC Model Tech Specs ML20133K9571985-08-0707 August 1985 Application for Amend to License NPF-1,consisting of License Change Application 125,incorporating Tech Specs for TMI-related Items Per NRC Model Tech Specs,NUREG-0737 & Generic Ltr 83-37 ML20133K9421985-08-0707 August 1985 Forwards Application for Amend to License NPF-1,consisting of License Change Application 125,incorporating Tech Specs for TMI-related Items Per NRC Model Tech Specs.Certificate of Svc Also Encl.Fee Paid ML20135A3721985-09-0303 September 1985 Submits Cost Estimates for Installation of NRC Emergency Communication Circuits in Emergency Operations Facility.New Emergency Facility Scheduled for Completion by 861231. Facility Drawings Encl ML20135A7781985-09-0303 September 1985 Forwards Reactor Vessel Level Instrumentation Sys Implementation Ltr Rept,In Response to NRC 850202 Safety Evaluation ML20198C2571985-11-0505 November 1985 Forwards Addl Info Re Inadequate Core Cooling Instrumentation Installed or Proposed for Installation,In Response to NRC 850910 Onsite Evaluation.W/One Oversize Drawing ML20137A9941985-11-21021 November 1985 Advises That Isolation Capability of Control Room Normal Ventilation Sys CB-2 Adequate.No Mods Required to Meet Intent of NUREG-0737,Action Item III.D.3.4, Control Room Habitability & GDC 19 Based on Listed Reasons ML20136C6401985-12-20020 December 1985 Forwards Draft SER Re Tech Spec Changes & Draft Transmittal Ltr to Licensee.Proposed Amend to License NPF-1 Approved. SALP Input Also Encl ML20136F2671985-12-31031 December 1985 Forwards Response to 850612 Request for Addl Info Re NUREG-0737,Item II.D.1 Re Performance Testing of Relief & Safety Valves.Conclusions Originally Presented in PGE-1039 Have Not Changed ML20137N7701986-01-13013 January 1986 Rev 2 to Administrative Order AO-4-7, Procedure Generation Package for Emergency Operating Procedures ML20137N9951986-01-31031 January 1986 Forwards Addl Info in Response to 850628 Generic Ltr 85-12, Implementation of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps'. Trip Provided When Needed.Trip Excluded When Continued Pump Operation Desirable ML20137N7621986-01-31031 January 1986 Forwards item-by-item Response to Comments in Procedures Generation Package Draft SER & Rev 2 to Administrative Order AO-4-7, Procedure Generation Package for Emergency Operating Procedures ML20141P0581986-03-10010 March 1986 Forwards Amend 112 to License NPF-1 & Safety Evaluation. Amend Revises Tech Specs to Add Operability & Surveillance Requirements for Core Exit Thermocouples & Reactor Vessel Level Instrumentation Sys ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20155E7911986-04-0707 April 1986 Corrected Amends 112 & 114 to License NPF-1,re Thermal Power,Surveillance Requirements & Control & Dilution to Moderate Temp Coefficient ML20155E7861986-04-0707 April 1986 Forwards Corrected Amends 112 & 114 to License NPF-1 Revising Pagination & Resolving Administrative Errors ML20203H6851986-07-31031 July 1986 Informs That Util Will Ref WCAP-11145 in Order to Satisfy Requirements of TMI Action Item II.K.3.31 in Generic Fashion,In Accordance W/Generic Ltr 83-35.Plant-specific Analysis Unnecessary ML20238A5951987-05-0606 May 1987 Intervenor Exhibit I-SC-59,consisting of Undated Summary of Objectives ML20237F7161987-08-0707 August 1987 Advises That Util Will Be Unable to Meet Original Response Time for NRC 870617 Request for Addl Info Re Testing of Relief & Safety Valves.Response Will Be Issued by 871030 ML20236L3901987-10-30030 October 1987 Provides Addl Info Re Performance Testing of Relief & Safety Valves,Per NUREG-0737,Item II.D.1 & 870617 Request. Evaluation of 83 Supports for Original Design Loads Performed.Mods Identified & Installed ML20055E7851990-07-0909 July 1990 Forwards Safety Evaluation Re Procedures Generation Program for Plant,Per Util 831110 & s.Ltrs Should Be Reviewed to Address Programmatic Improvements Outlined in Section 2 of Rept 1985-08-07 | |
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