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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Bar1 D Wahers Vce Presdent July 3, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. Hugh Thompson, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington DC 20555
Dear Mr. Thompson:
Safety Parameter Display System Our letters of November 23, 1983 and February 15, 1985 provided a schedule of July 1985 for implementation of the Trojan Safety Parameter Display System (SPDS). The SPDS is only one of several functions performed by the Technical Support Center (TSC) computer. The SPDS portion of the TSC computer will be placed into operation for the forthcoming operating cycle, Cycle 8.
There remain, however, some open items / issues that require action. For the most part, these items can be accomplished while the system is on-line with a minimal effect on the operation of the system.
These open items are described in the attachment to this letier.
Sincerely,
%r Bart D. Withers Vice President Nuclear Attachment C'00 c:
Mr. Lynn Frank, Director j
i State of Oregon Department of Energy l jl Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission 8507090240 850703 PDR ADOCK 05000344 F
PDR 121 SW Sa!rnon Street Portty a Orey:,n 97204
W Trojan Nuclear Plant Mr. H. Thompson Docket 50-344 July 3, 1985 License NPF-1 Attachment Page 1 of 2 TSC Computer Open Items 1.
Central Processing Unit In 1984 a fourth central processing unit (CPU) was installed to improve the time response of the TSC Computer. The vendor has been unable to reliably operate the TSC Computer with all four CPUs on-line simultaneously. The SPDS will operate with three CPUs but the time response is slower when multiple users make demands on the system. Vendor representatives are working closely with PGE engineers to resolve this open item.
2.
Input Verification Due to the many TSC Computer hardware problems experienced within the last two years, including the CPU problem described above, a point-by~
point input verification has not been completed. However, most SPDS parameters have been favorably compared with control board indications in the control room. It is expected that a detailed and complete input verification will be performed by March 1, 1986 for those items that can be checked during Plant operation, and by startup from the 198' refueling outage for the others.
3.
Human Factors Review PGE is developing an ongoing human factors review program. The TSC Computer was evaluated under the Control Room Design Review for control room layout only. The remaining human factors considerations for the TSC Computer will be reviewed under the ongoing human factors review program.
This human factors review will be complete by December 1, 1985.
4.
SPDS Availability Due to numerous system startup problems within the last two years, the availability of the SPDS has been poor.
It is felt that the hardware problems, with the exception of the CPU problem described above, have been satisfactorily resolved. The availability of the TSC Computer will be monitored and reassessed during the forthcoming operating cycle.
5.
As-Built Findings j
During an as-built walkdown, it was discovered that the installation of 37 SPDS inputs (out of a total of approximately 450) was not properly completed. Parameters which are affected and the corre-sponding number of inputs for each are listed below. These discrepancies will be corrected by December 31, 1985 for items which do not affect plant operations. Remaining items will be complete by the startup from the 1986 refueling outage.
Parameters Number of Inputs Pressurizer Safety Valve Acoustic Monitor 1
RWST Level 1
Recirc Sump Level 1
Containment Temperature 4
Valve Position Indications RWST to Containment Spray 2
Recire Sump to containment Spray 2
Containment Sump Recire Suction 2
Pressurizer PORV 2
Pressurizer PORV Block Valves 2
Main Steam Line PORVs 4
Main Feedwater Isolation to Steam Generator 4
Steam Dump Valves 12 SAB/3mc 1038G.685
