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	Issue date	From	Title	Project stage
ML20054F383	11 June 1982	Withers B Portland General Electric	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	Other
ML20140E550	4 January 1985	Withers B Portland General Electric	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	Other
IR 05000344/1985014	12 June 1985	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) North H Yuhas S	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	Request
ML20126M480	13 June 1985	Butcher E Office of Nuclear Reactor Regulation	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	RAI
ML20128B202	27 June 1985	Withers B Portland General Electric	Advises That Response to 850612 Request for Addl Info Re NUREG-0737,Item II.D.1 Will Be Submitted by 851231	Request
ML20129K117	19 July 1985	Withers B Portland General Electric	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	Request
ML20133K973	7 August 1985	Portland General Electric	Proposed Tech Specs,Incorporating TMI-related Items Per NRC Model Tech Specs	Other
ML20133K957	7 August 1985	Portland General Electric	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	Request
ML20133K942	7 August 1985	Withers B Portland General Electric	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	Request
ML20135A372	3 September 1985	Withers B Portland General Electric	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	Other
ML20135A778	3 September 1985	Withers B Portland General Electric	Forwards Reactor Vessel Level Instrumentation Sys Implementation Ltr Rept,In Response to NRC 850202 Safety Evaluation	Other
ML20198C257	5 November 1985	Withers B Portland General Electric	Forwards Addl Info Re Inadequate Core Cooling Instrumentation Installed or Proposed for Installation,In Response to NRC 850910 Onsite Evaluation.W/One Oversize Drawing	Other
ML20137A994	21 November 1985	Withers B Portland General Electric	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	Other
ML20136C640	20 December 1985	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) Kirsch D	Forwards Draft SER Re Tech Spec Changes & Draft Transmittal Ltr to Licensee.Proposed Amend to License NPF-1 Approved. SALP Input Also Encl	Draft Approval
ML20136F267	31 December 1985	Withers B Portland General Electric	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	Request
ML20137N770	13 January 1986	Portland General Electric	Rev 2 to Administrative Order AO-4-7, Procedure Generation Package for Emergency Operating Procedures	Other
ML20137N995	31 January 1986	Withers B Portland General Electric	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	Other
ML20137N762	31 January 1986	Withers B Portland General Electric	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	Draft Other
ML20141P058	10 March 1986	Office of Nuclear Reactor Regulation Neighbors J	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	Approval
ML20154N875	12 March 1986	Holahan G Office of Nuclear Reactor Regulation	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	Request
ML20155E791	7 April 1986	NRC	Corrected Amends 112 & 114 to License NPF-1,re Thermal Power,Surveillance Requirements & Control & Dilution to Moderate Temp Coefficient	Other
ML20155E786	7 April 1986	Varga S Office of Nuclear Reactor Regulation	Forwards Corrected Amends 112 & 114 to License NPF-1 Revising Pagination & Resolving Administrative Errors	Other
ML20203H685	31 July 1986	Withers B Portland General Electric	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	Other
ML20238A595	6 May 1987	Federal Emergency Management Agency	Intervenor Exhibit I-SC-59,consisting of Undated Summary of Objectives	Other
ML20237F716	7 August 1987	Portland General Electric Cockfield D	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	Request
ML20236L390	30 October 1987	Portland General Electric Cockfield D	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	Other
ML20055E785	9 July 1990	Bevan R Office of Nuclear Reactor Regulation	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	Approval

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