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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Bart D Wahors Vce Prescent October 9,1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTH:
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 (SPDS)_
Our letter of July 19, 1985 provided a response to the NRC Safety Evaluation Report request for additional information. One of the items discussed in our letter was how the radiation status of the secondary system is normally assessed try the SPDS. This assessment is made by monitoring Process and Effluent Radiation Monitor (PRM) 10 on the steam generator blowdown systcm.
In the event of a steam generator tube rupture and overfill accident, the Once the emergency procedures direct the steam generator to be isolated.
steam generator is isolated, the only method for displaying the activity level in the generator on the SPDS would be to lineup blowdown and obtain a reading on PRM-10.
This method may, however, result in the release of unmonitored and untreated liquids. Therefore, to improve the secondary system activity menitoring capability of the SPDS, we intend to add the This action main steam line activity monitors (PRM-16 A-D) to the SPDS.
will be completed by July 31, 1987. The steam generator blowdown treatment system is described in Section 10.4.8 of the Updated Trojan Final Safety Analysis Report. PRM-16 is described in Section 11.5.2.2.7 of the Updated Trojan Final Safety Analysis Report.
In November 1985, a human factors review of the SPDS was completed.
As a result of that review, the color coding on the computer has been changed.
The color coding now conforms to the standard convention of green (normal),
yellow (caution), red (alarm), and purple (bad data quality).
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W W BOCidCM Mr. Steven A. Varga October 9, 1986 Page 2 We trust this information will resolve the remaining concerns identified in the NRC Safety Evaluation Report.
Sincerely, 7
Bar
. Withers Vice President Nuclear c:
Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Conunission J
Mr. Lynn Frank, Director State-of Oregon Department of Energy i
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