Letter Sequence Other |
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Results
Other: ML19309H462, ML19343B804, ML20024B657, ML20058H771, ML20263C250, ML20263C252, ML20263C255, ML20263C258, ML20263C261, ML20263C264, ML20263C267
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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 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 ML20263C2581982-03-21021 March 1982 Piping & Instrument Diagram:Residual Heat Removal System Project stage: Other ML20052D1261982-04-28028 April 1982 Forwards Supplemental Info Re Implementation Schedules for Outlined NUREG-0737 TMI Action Items in Response to Generic Ltr 82-05.Schedules for Items II.B.3 & II.F.1 Will Be Extended Due to Vendor Delays Project stage: Supplement ML20058H7711982-07-30030 July 1982 Provides Schedule for Util Response to NUREG-0737,Item II.B.3, Post-Accident Sampling Sys. Response to Criteria 1 Through 11 Will Be Provided by 821130.Post-accident Sampling Sys Completion Expected by 830701 Project stage: Other ML20263C2501982-09-15015 September 1982 Air Flow Diagram:Containment Ventilation & Cooling Systems Project stage: Other ML20263C2641982-09-29029 September 1982 Interim Piping & Instrument Diagram:Process Sampling System. Sheet 4 Project stage: Other ML20263C2611982-09-29029 September 1982 Piping & Instrument Diagram:Process Sampling System. Sheet 1 Project stage: Other ML20263C2551982-09-29029 September 1982 Piping & Instrument Diagram:Chemical & Volume Control System. Sheet 1 Project stage: Other ML20263C2671982-10-22022 October 1982 Interim Piping & Instrument Diagram:Process Sampling System. Sheet 5 Project stage: Other ML20263C2521982-10-28028 October 1982 Piping & Instrument Diagram:Reactor Coolant System Project stage: Other ML20024B6571983-07-0101 July 1983 Forwards List of post-accident Sampling Sys Items Identified During Functional Testing Requiring Resolution,Per NUREG-0737,Item II.B.3.Other Aspects of Sys Acceptable Project stage: Other 1982-10-28
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POrtiand General Electric Coirpiniy ame r
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.m, m; July 30, 1982 Trojan Nuclear Plant Docket 50-34 '+
License NPF-1 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
TROJAN NUCLEAR PLANT NUREG-0737 ITEM II.B.3 POST ACCIDENT SAMPLING SYSTEM Your letter of June 30, 1982 provided NRC staff clarifications to the NUREG-0737 criteria on the Post Accident Sampling System and requested a schedule for responding to each criterion for the Trojan Nuclear Plant.
We have reviewed the staff clarifications and provide the following schedule for our response. Due to extensive details requested in our response and specific design criteria in the NRC staff positions, the requested information responding to Criteria 1 through 11 will not be provided to the NRC until November 30, 1982.
Concerted efforts are being applied to complete detailed design, manu-facturing and installation of necessary equipment for the Post Accident Sampling System, hence requiring the above schedule for our response.
It is presently expected to complete the Post Accident Sampling System D
8208090070 820730 PDR ADOCK 05000344 P
PDR 121 SW SaWun S:*eet Ftcanci Oregon 97201 l.
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Pbrtiarid Gener-d Bectric Corig)Evinr Mr. Darrell G. Eisenhut July 30, 1982 Page two at Trojan by July 1, 1983. As we discussed in our letter of April 28, 1982, every effort will continue to be made to complete the installation as soon as possible.
Sincerely,
^-9 Bart D. Withers l
Vice President Nuclear
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Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 U. S. Nuclear Regulatory Commission Mr. Lynn Frank, Director 4
State of Oregon Department of Energy 1
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