Letter Sequence Request |
|---|
|
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
t 0
r-Illll M
Bart D Wens Vce PresdM July 19, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. E. J. Butcher, Jr., Acting Chief Operating Reactors Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington DC 20555
Dear Mr. Butcher:
Safety Parameter Display System Your Safety Evaluation of June 13, 1985 for the Trojan Safety Parameter Display System identified additional information which was required by the NRC staff in order to complete their review. The additional information is attached.
Sincerely, Bart D. Withers Vice President Nuclear Attachment et Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission 8507230112 850719 gDR ADOCK 05000344 PDR tfo*f
,m u mo ma nm,u%,
m
,I
1 l
Trojan Nuclear Plant Mr. E. J. Butcher, Jr.
Docket 50-344 July 19, 1985 License NPF-1 Attachment Page 1 of 1 ADDITIONAL INFORMATION ON TROJAN SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
NRC Request satisfactory justification was not provided for the omission of the steam generator liquid sample parameter. The licensee should indicate how radiation status (Radioactivity Control Critical Safety Function) of the secondary system (steam generators and steam lines) can be rapidly assessed when the steam generators and/or steam lines are isolated.
PGE Response The radiation status of the secondary system is normally assessed by the SPDS by monitoring PRM-10 (designated STM GEN BLDN on the SPDS). PRM-10 is located on the steam generator blowdown piping just downstream of the steam generator sample connections.
During accident conditions, valves in the steam generator sample system which receive automatic closure signals would have to be realigned to monitor the present activity levels.
NRC Request The Trojan SPDS appears to use a nonstandard color coding convention.
The licensee should change the color coding convention to agree with plant and/or stereotypical color codes.
If the licensee decides to leave the color code as it is now proposed, further justification should be provided to assure the staff that the present color coding scheme is:
1.
Consistent with plant conventions and is not confusing.
2.
Not distracting during normal plant conditions.
3.
Easily readable during abnormal and emergency conditions.
PGE Response The color coding of the SPDS was developed by the system vendce as part of the man-machine interface design basis. The vendor applied accepted human engineering principles in the color selection process.
It is our intent to review the color coding as part of our own human factors review of the installed system. Our review will evaluate the colors for con-sistency with Plant conventions, readability, brightness, detectability, resolution, etc. Our human factors review is discussed in our July 3, 1985 letter and is due to be complete by December 1, 1985.
SAB/3kal 1098G.785
