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MONTHYEARML19309H4621980-05-0707 May 1980
Forwards License Change Application (Lca) 60,replacing Lca 51.Certificate of Svc Encl
Project stage: Other
ML19343B8041980-12-23023 December 1980
Responds to NRC Requesting Response to NUREG-0737 Re Implementation of TMI-2 Action Items.Util Intends to Meet Requirements & Schedules Except Where Stated.Hardware Availability Problems Could Cause Delays
Project stage: Other
ML20009C9641981-07-17017 July 1981
Suppls 801223 Response to NUREG-0737,Item II.B.1 Re Reactor Coolant Vent Sys.Also Submits Info on Items II.D.1,II.E.1.2, II.E.4.2,II.K.3.5,II.K.3.25,II.F.1.5,II.F.2 & III.A.2
Project stage: Other
ML20031H1461981-10-21021 October 1981
Forwards Supplemental Info Re Implementation Status of TMI Action Items II.B.3,II.F.1.1,II.F.1.2,II.F.1.6,II.F.2, II.D.1.2,II.K.3.1,II.K.3.5 & III.A.2.Items Will Be Completed by 820801
Project stage: Supplement
ML20039D4801981-12-28028 December 1981
Forwards Supplemental Info to Util Re Implementation of NUREG-0737 Items Requiring Licensee Action by 820101
Project stage: Supplement
ML20050B5941982-03-31031 March 1982
Discusses Status of Performance Testing of Pressure Operated Relief Valves & Safety Valves Required by Item II.D.2, NUREG-0737.Based on Review of Test Results Conditions Envelope Expected Conditions at Plant
Project stage: Other
ML20054F3831982-06-11011 June 1982
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
Project stage: Other
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
Project stage: Request
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
Project stage: Request
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
Project stage: Draft Approval
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
Project stage: Request
ML20238A5951987-05-0606 May 1987
Intervenor Exhibit I-SC-59,consisting of Undated Summary of Objectives
Project stage: Other
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
Project stage: Request
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
Project stage: Other
1982-06-11
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seum:.
une Podland General ElechicCornpany se David W. Cockfield Vice President, Nuclear Trojan Nuclear Plant Docket 50-344 License NPF-1 Nucicar Regulatory Commission ATTN: Document Control Desk Washington DC 20555
Dear Sir:
l Performance Testing of Relief and Safety Valves NUREG-0737. Item II.D.1 By 1ctter dated June 17, 1987, Terence Chan of your staff requested that Portland General Electric (PGE) provide additional information regarding the testing of relief and safety valves for the Trojan Nuclear Plant. It was requested that this information be provided within 45 days from receipt of the lett-er, or a schedule to provide this information be submitted within 15 days.
Due to activities associated with the current refueling outage, the 15-day response time for provision of a schedule was inadvertently overlooked.
PGE has reviewed your request and determined that additional time will be required to adequately address each item.
Accordingly, we plan to issue a detailed response to the five (5) items listed in the enclosure to your June 17. 1987 letter by October 30, 1967.
Sincerely, l*
c:
Mr. John B. Martin Regional Administrator, Revision V U.S. Nuclear Regulatory Commission 1
Mr. David Kish, Director i
State of Oregon
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1 Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant 8708230138 870807
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121 S W Salmon Sheet, Pomand, Oregon 97204 I
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