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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March 3, 1986 Docket No. 50-344 DISTRIBUTION LDticket File NRC PDR LPDR Gray File PAD-3 Rdg H. Thompson Mr. Bart D. Withers OELD C. Vogan Vice President Nuclear K. Johnston J.D. Neighbors Pcrtland General Electric Company E. Jordan
- 8. Grimes 121 S.W. Salmon Street J. Partlow ACRS 10 Portland, Oregon 97204
Dear Mr. Withers:
The enclosed report of the NRC pilot audit of your Safety Display Parameter System is forwarded for your information and appropriate action. This audit was conducted at the Trojan Nuclear Plant during the period of August 6-8, 1985.
Please note that the report identifies potential concerns in the areas of system reliability, system testing and operation training. There also appears to be a lack of operator acceptance of the system.
We would be happy to meet with you to discuss these and related matters.
If you should have any questions, please contact me at (301) 492-8140.
/s/JDNeighbors Joseph D. Neighbors, Senior Project Manager PWR Project Directorate No. 3 Division of PWR Licensing-A
Enclosure:
As stated cc w/ enclosure:
See next page
- SEE PREVIOUS PAGE FOR CONCURRENCES D/PA(3
/
PAD-3*
PAD-3*
eighbors1 SVar. 't CVogan KJohnston/pws 02/26/86 02/26/86 3/86 f,03/q/86 9603120349 040303 PDR ADOCK 05000344 P
PDR
l L
Docket No. 50-344 DISTRIBUTION Docket File
'NRC PDR LPDR Gray File PAD-3 Rdg H. Thompson l
Mr. Bart D. Withers OELD C. Vogan Vice President Nuclear K. Johnston J.D. Neighbors
(
Portland General Electric Company E. Jordan B. Grfws i
121 S.W. Salmon Street J..Partlow ACRS 10 Portland, Oregon 97204
Dear Mr. Withers:
The enclosed report of the NRC pilot audit of your Safety Display Parameter
. System is forwarded for your information and appropriate action. This l-audit was conducted at the Trojan Nuclear Plant during the period of August 6-8, 1985.
[-
Please note that the report identifies potential concerns in the areas of system reliability, system testing and operation training. There also appears to be a lack of operator acceptance of the system. We would be happy to meet with you.
If you should have any questions, please contact me at (301) 492-8140.
r Joseph D.' Neighbors Senior Project Manager i
PWR Project Directorate No. 3 Division of PWR Licensing-A
Enclosure:
l As stated i
cc w/ enclosure:
See next page l
l l
i PAD-3 PAD-34 PAD-3 D/ PAD-3 CVogan KJohnt
/pws JDNeighbors SVarga 02/pf86 02/4/86 02/ /86 02/ /86
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