Letter Sequence Other |
|---|
|
Results
Other: ML19309H462, ML19338G104, ML19343B804, ML20008F580, ML20052D918, ML20128G570, ML20133C386, ML20137U660, ML20137Y652, ML20137Y671, ML20140F898, ML20209C990, ML20211B297
|
MONTHYEARML19309H4621980-05-0707 May 1980
Forwards License Change Application (Lca) 60,replacing Lca 51.Certificate of Svc Encl
Project stage: Other
ML20005B5001980-06-13013 June 1980
Forwards Application for Withholding & Proprietary WCAP-9725 & Nonproprietary WCAP-9726, Westinghouse Technical Support Complex. Proprietary Version Withheld (Ref 10CFR2.790).W/o Nonproprietary Version
Project stage: Request
ML19338G1041980-10-21021 October 1980
Forwards Trojan Nuclear Plant Emergency Response Facilities, Per NRC 800905 Request.Technical Support Ctr & Emergency Operations Facility Will Be Operational by 820401 & Safety Parameter Display Sys by 820101
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
ML20008F5801981-04-15015 April 1981
Responds to Generic Ltrs 81-10 & 81-17,requesting Commitment to Implementation Schedules for TMI Action Plan Item III.A.1.2 Re Emergency Support Facilities & NUREG-0696. Exemption from Requirements of NUREG-0696 Requested
Project stage: Other
ML20005B4941981-07-0202 July 1981
Forwards Supplementary Info Re NUREG-0696 Concerning Emergency Response Facilities,Westinghouse Application for Withholding & Proprietary WCAP-9725, Westinghouse Technical Support Complex. Rept Withheld (Ref 10CFR2.790)
Project stage: Supplement
ML20038B8481981-12-0303 December 1981
Reconfirms Commitment to Conduct Human Factors Review of Backup Spdr,Per 810615 Meeting.Backup Consists of Certain Critical Plant Parameters Indicated on Panels C-02,C-05 & C-09 as Described in Util
Project stage: Meeting
ML20052D9181982-05-0303 May 1982
Forwards Summary of Plant Emergency Operations Facility, Providing Addl Info in Response to NUREG-0696.NRC Ruling Re Acceptability of Facility Requested by 820601,to Meet 821001 Deadline for Completion
Project stage: Other
ML20127P5121985-06-28028 June 1985
Forwards Response to 850502 Generic Ltr 85-07 Requesting Completion of Survey on Implementation of Integrated Schedules for Plant Mods.Completed Survey Form Encl
Project stage: Request
ML20128G5701985-07-0303 July 1985
Provides Description of Technical Support Ctr Computer Open Items Re Spds.Items Can Be Accomplished While Sys on-line W/Minimal Effect on Operation of Sys
Project stage: Other
ML20129J5291985-07-19019 July 1985
Forwards Response to 850613 Request for Addl Info Re SPDS, Identified in Safety Evaluation.Spds Color Coding Sys Will Be Evaluated
Project stage: Request
ML20133C3861985-07-30030 July 1985
Advises That 850805-07 Site Visit to Gather Info Re Implementation & Operation of SPDS Rescheduled for 850806-08
Project stage: Other
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
ML20137Y6711986-01-13013 January 1986
SPDS Progress Review for Trojan
Project stage: Other
ML20137U6601986-02-13013 February 1986
Forwards Addl Info Per NUREG-0737,Item II.D.1 Re Pressurizer Safety Valve Upper Level Position in Response to Question 9. Review by Crosby Valve & Gage Co Shows Attached Ring Setting Info Correct
Project stage: Other
ML20137Y6521986-03-0303 March 1986
Forwards NRC Pilot Audit of Util SPDS Progress Review for Info & Appropriate Action.Rept Identifies Potential Concerns in Areas of Sys Reliability,Sys Testing & Operation Training
Project stage: Other
ML20140F8981986-03-28028 March 1986
Informs That SPDS Testing Near Completion.Site Acceptance Test Completed W/One Open item.Point-by-point Input Verification 70% Complete & Will Be Finalized During Refueling Outage.Users Manual Being Prepared
Project stage: Other
ML20211B2971986-10-0909 October 1986
Discusses How Radiation Status of Secondary Sys Normally Assessed by Spds.Main Steam Line Activity Monitors Added to SPDS to Improve Secondary Sys Activity Monitoring Capability.Color Coding on SPDS Computer Changed as Noted
Project stage: Other
ML20209C9901987-01-27027 January 1987
Advises That Addition of Main Steam Line Activity Monitors (PRM-16,A-D) to SPDS for Secondary Sys Radiation Status Determination & Use of Std Convention color-coding for Display of Computer Data Acceptable
Project stage: Other
1985-06-28
[Table View] |
Text
,p i
Docket No. 50-344 July 30, 1985 L
l Mr. Bart D. Withers Vice President Nuclear Portland General Electric Company 121 S. W. Salmon Street
. Portland, Oregon 97204
Dear Mr. Withers:
SUBJECTi NRC PLANT VISIT FOR INFORMATION ON THE SAFETY PARAMETER DISPLAY SYSTEM IMPLEMENTATION AND OPERATION By letter dated June 28, 1985, we informed you th6t an NRC team planned to visit the Trojan site on August 5-7, 1985 for the purpose of gathering information in connection with the implementation and operation of the Safety Parameter Display System. This is to inform you that the schedule for that visit has been changed. The NRC team is now planning to be on site August 6-8, 1985, one day later than originally planned. The NRC Project Manager has discussed this with Mr. Gary Zimerman of your staff, who has agreed to support this new schedule.
Thank you again for your cooperation.
i Since ely, J
Edward J. Butcher. Acting Chief Operating Reactors Branch No. 3 Division of Licensing 1
cc: See next page Distribution:
Docket File NRC & LPDRs Branch Files HThompson PKreutzer Llazo EJordan BGrimes ACRS 10 OELD EButcher CMiller GLapinsky ETourigny p
C:QA60:
EBUt'efi6rp ORB #3:DL ORBf3:
PKrgutzer LLazo;ef fF(o/85 7 /b/85 7 /p/85 hk $h44 M
PM
-
