Letter Sequence Other |
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Results
Other: ML19309H462, ML19338G104, ML19343B804, ML20008F580, ML20052D918, ML20128G570, ML20133C386, ML20137U660, ML20137Y652, ML20137Y671, ML20140F898, ML20209C990, ML20211B297
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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 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
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-m EM D Wms Vee Pmset March 28, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTU:
Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555
Dear Sir:
Safety Parameter Display System on July 9, 1985, the Trojan Safety Parameter Display System (SPDS) was placed into operation. A few outstanding items / issues remained and were addressed in our July 3,1985 letter. On August 6-8, 1985, an NRC team visited Trojan to observe the SPDS and assess the status of the SPDS implementation. On March 3, 1986, the NRC team released their report which identified potential concerns in the areas of system reliability, system testing, operator training and operator acceptance of the system.
As reported in our July 3, 1985 letter, the reliability of the SPDS over the two previous years had been very poor.
This fact was also recognized by the NRC audit team. The system has, however, performed very reliably since that time. The system has been online since July 1985 with only minor outages for scheduled maintenance.
System testing is near completion. The Site Acceptance Test has been completed satisfactorily with only one minor open item. The point-by-point input verification is approximately 70 percent complete and the remainder will be completed during the upcoming refueling outage.
Initial operator training was completed prior to declaring the system operable in July 1985. At the time of the NRC audit, the operators were in the process of becoming familiar with a new system.
Since that time, the SPDS has been utilized by the operators and they are continuing to become more comfortable with the system.
In fact, the SPDS was used with great effectiveness during the 1985 Radiological Emergency Response Plan exercise in November, after the tean visit.
A user's manual is currently being prepared to aid the operators and assist in their training.
Operator 8604010215 06032s ll'0 PDR ADOCK 05000344 p
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6 W M M col 14XM1y Mr. Steven A Varga March 28, 1986 Page 2 training in 1986 will be performed at a simulator which has the same SPDS.
This~ training will improve the operator's familiarity with the capability of the SPDS during accident conditions.
In conclusion, we believe the Trojan SPDS is a reliable and useful aid to Operations personnel. We are continuing to work to improve the system and the operators knowledge of its capabilities, and we are evaluating ways to better integrate the system with other emergency response capabilities.
The audit report sununarizing perceptions that existed 8 months ago does not reflect the current status of the system.
Sincerely.
-f Bart D. Withers Vice President Nuclear c:. Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy