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| Portland General ElectricCompany r - E: | | Portland General ElectricCompany r - E: |
| Birt D Weers Vce Presdert August 7, 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 | | Birt D Weers Vce Presdert August 7, 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 |
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| ==Dear Sir:== | | ==Dear Sir:== |
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| License Change Application 125 Attached are three signed originals and 40 conformed copies of License Change Application 125, requesting amendment of Operating License NPF-1. | | License Change Application 125 Attached are three signed originals and 40 conformed copies of License Change Application 125, requesting amendment of Operating License NPF-1. |
| License Change Application 125 requests incorporation of Technical Specifications for TMI-related items pursuant to the NRC model Technical Specificat.lons. An application fee of $150 is attached in accordance with 10 CFR 170. | | License Change Application 125 requests incorporation of Technical Specifications for TMI-related items pursuant to the NRC model Technical Specificat.lons. An application fee of $150 is attached in accordance with 10 CFR 170. |
| PCE has transmitted a copy of this request to the Oregon Department of Energy in accordance with 10 CFR 50.91. | | PCE has transmitted a copy of this request to the Oregon Department of Energy in accordance with 10 CFR 50.91. |
| Also attached is one signed copy of a certificate of Service for License Change Application 125 to the chief executive of the county in which the facility is located, and the Director of the State of Oregon, Department of Energy. | | Also attached is one signed copy of a certificate of Service for License Change Application 125 to the chief executive of the county in which the facility is located, and the Director of the State of Oregon, Department of Energy. |
| Sincerely. | | l Sincerely. |
| l l
| | l |
| * a . , ,/
| | .,,/ |
| Bart D. Withers f Vice President Nuclear l | | a Bart D. Withers f |
| Attachments c: Mr. Lynn Frank, Director State of Oregon p []p Department of Energy y | | Vice President Nuclear l |
| Mr. Robert L. King Chairman of County Commissioners , | | Attachments c: |
| b h f I It 8500120429 850007 PDR ADOCK 05000344 P PDR 1218 '/, l l :Tn th t't POTind Cmg.n 97204
| | Mr. Lynn Frank, Director |
| *}}
| | []p State of Oregon p |
| | Department of Energy y |
| | Mr. Robert L. King h |
| | f Chairman of County Commissioners b |
| | I It 8500120429 850007 PDR ADOCK 05000344 P |
| | PDR 1218 '/, l l :Tn th t't POTind Cmg.n 97204 |
| | *}} |
Letter Sequence Request |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement
Results
Other: ML17255A937, ML19309H462, ML19318A584, ML19337B217, ML19343B804, ML20003H940, ML20009C964, ML20024B941, ML20038A631, ML20040E980, ML20049J615, ML20051M285, ML20054F383, ML20055C134, ML20133K973, ML20135A778, ML20137A994, ML20137N995, ML20140E550, ML20155E786, ML20155E791, ML20198C257
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MONTHYEARML19289C2151978-11-28028 November 1978
Forwards List of Requests for Design Changes & Other Work Items Suppl Previous Lists.Items on This List Will Not Affect Load Carrying Capability of Any Major Shear Wall
Project stage: Request
ML19209C3961979-09-27027 September 1979
Forwards Request for Addl Info Re Plant Control Bldg Design Mods.Encl Questions Comprise NRC Positions Re Acceptable Util Response
Project stage: Request
ML19262C4321980-02-0505 February 1980
Forwards Response to NRC 791003 Generic Request for Info Re Auxiliary Feedwater Flow Requirements.Info Pertains to Design Bases for Auxiliary Feedwater Sys
Project stage: Request
ML19309H4621980-05-0707 May 1980
Forwards License Change Application (Lca) 60,replacing Lca 51.Certificate of Svc Encl
Project stage: Other
ML19318A5841980-06-16016 June 1980
Forwards Response to NRC Re Implementation of Five Addl TMI-2 Related Action Items
Project stage: Other
05000344/LER-1980-017, Forwards LER 80-017/03L-01980-09-0505 September 1980
Forwards LER 80-017/03L-0
Project stage: Request
ML19337B2171980-09-29029 September 1980
Notifies of Delay in Implementation of TMI-2 Lessons Learned Items Scheduled for 810101 Until Resolution of Matl Delivery Problems.Summary of Util Commitments Per NUREG-0578 & Comments on NRC to Licensees & Applicants Encl
Project stage: Other
ML19339B0061980-10-23023 October 1980
Forwards Safety Evaluation Re Implementation of Recommendations for Auxiliary Feedwater Sys.Requests Response to Two Unresolved Items Identified in Rept within 45 Days
Project stage: Approval
ML19339B0091980-10-23023 October 1980
Safety Evaluation Re Implementation of Recommendations for Auxiliary Feedwater Sys
Project stage: Approval
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
ML20003H9401981-05-0404 May 1981
Advises That Mods Needed Re TMI Action Item II.F.1.6, Containment Hydrogen Monitoring,To Achieve Acceptable Levels of Reliability Based on NUREG-0737 Criteria.Three solenoid- Operated Valves Will Be Added Inside Containment
Project stage: Other
ML20009C9641981-07-17017 July 1981
Suppls 801223 Response to NUREG-0737,Item II.B.1 Re Reactor Coolant Vent Sys.Also Submits Info on Items II.D.1,II.E.1.2, II.E.4.2,II.K.3.5,II.K.3.25,II.F.1.5,II.F.2 & III.A.2
Project stage: Other
ML20031H1461981-10-21021 October 1981
Forwards Supplemental Info Re Implementation Status of TMI Action Items II.B.3,II.F.1.1,II.F.1.2,II.F.1.6,II.F.2, II.D.1.2,II.K.3.1,II.K.3.5 & III.A.2.Items Will Be Completed by 820801
Project stage: Supplement
ML20038A6311981-11-0606 November 1981
Forwards Addl Info Requested in NRC Re Reactor Vessel Level Indication Sys Being Installed at Facility
Project stage: Other
ML20236A0681981-12-0404 December 1981
Safety Evaluation Re Containment Purging & Venting During Normal Operation of Plant.Purge/Vent Sys Design & Operating Practices for Facility Acceptable Subj to Implementation of Recommended Actions
Project stage: Approval
ML20039D4801981-12-28028 December 1981
Forwards Supplemental Info to Util Re Implementation of NUREG-0737 Items Requiring Licensee Action by 820101
Project stage: Supplement
ML20040E9801982-01-29029 January 1982
Provides Addl Clarification of TMI Action Items II.F.1.1 & II.F.1.2 Re Capability of Radioactive Gaseous Waste Sys & Isokinetic Sampling,Per NRC .Diagram of Waste Gas Sys Recycle Vent Encl
Project stage: Other
ML20049J6151982-03-0404 March 1982
Advises That TMI Action Item II.K.3.3, Reporting Relief Valve & Safety Valve Failures & Challenges, Resolved Based on 801223 & 810102 Responses
Project stage: Other
ML20052D1261982-04-28028 April 1982
Forwards Supplemental Info Re Implementation Schedules for Outlined NUREG-0737 TMI Action Items in Response to Generic Ltr 82-05.Schedules for Items II.B.3 & II.F.1 Will Be Extended Due to Vendor Delays
Project stage: Supplement
ML20052F5451982-05-0707 May 1982
Responds to 820224 Request for Addl Info on NUREG-0737, Item II.B.1 Re RCS Vent.Design Parameters & Max Rate of Reactor Coolant Through Reactor Vessel Head Vent Sys Flow Restriction Orifices Provided
Project stage: Request
ML20051M2851982-05-10010 May 1982
Forwards Addl Info Re NUREG-0737 Action Items I.A.2.1, Upgraded Senior Reactor Operator & Reactor Operator Training & II.B.4,training for Mitigating Core Damage,Per NRC 820318 Request
Project stage: Other
ML20054F3831982-06-11011 June 1982
Forwards Addl Info Re Implementation Schedules for NUREG-0737 Items,In Response to Generic Ltr 82-10.Items Include I.A.1.3.1,I.A.1.3.2,I.C.1,II.D.1.2,II.D.1.3, II.K.3.30,II.K.3.31,III.A.1.2,III.A.2.2 & III.D.3.4
Project stage: Other
ML20055C1341982-08-0303 August 1982
Advises That Main Steam Line Radiation & Containment Hydrogen Monitors Will Be Operational by 821001,per NUREG-0737 Items II.F.1.1 & II.F.1.6
Project stage: Other
ML17255A9371983-04-21021 April 1983
Operating Reactor PORV Repts (F-37) TMI Action Plan Requirements,Westinghouse Owners Group,WCAP-9804, Technical Evaluation Rept
Project stage: Other
ML20024B9411983-07-0808 July 1983
Discusses Continued Problems in Making Control Room Ventilation Sys Operational Per TMI Action Plan Item III.D.3.4.Only One Area Radiation Monitor Necessary,Per TMI Action Plan Item III.A.1.2
Project stage: Other
ML20140E5501985-01-0404 January 1985
Forwards Schedule for Submitting Addl Info & Justification of Nonconformance of Core Exit Thermocouples & Subcooling Margin Monitors,Per 840202 SER on Util Response to Generic Ltr 82-28 & NUREG-0737,Item II.F.2
Project stage: Other
ML20126M4801985-06-13013 June 1985
Forwards Request for Addl Info Re Core Exit Thermocouple Sys,Subcooling Margin Monitors & Reactor Vessel Level Instrumentation Sys,In Order to Complete Review of 840312 & 850104 Submittals for TMI Item II.F.2.3
Project stage: RAI
ML20129K1171985-07-19019 July 1985
Responds to 850613 Request for Addl Info Re NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation. Class 1E Platinum Resistance Temp Detectors Will Be Used to Measure Ref Junction Temp for Backup Displays
Project stage: Request
ML20133K9571985-08-0707 August 1985
Application for Amend to License NPF-1,consisting of License Change Application 125,incorporating Tech Specs for TMI-related Items Per NRC Model Tech Specs,NUREG-0737 & Generic Ltr 83-37
Project stage: Request
ML20133K9421985-08-0707 August 1985
Forwards Application for Amend to License NPF-1,consisting of License Change Application 125,incorporating Tech Specs for TMI-related Items Per NRC Model Tech Specs.Certificate of Svc Also Encl.Fee Paid
Project stage: Request
ML20133K9731985-08-0707 August 1985
Proposed Tech Specs,Incorporating TMI-related Items Per NRC Model Tech Specs
Project stage: Other
ML20135A7781985-09-0303 September 1985
Forwards Reactor Vessel Level Instrumentation Sys Implementation Ltr Rept,In Response to NRC 850202 Safety Evaluation
Project stage: Other
ML20198C2571985-11-0505 November 1985
Forwards Addl Info Re Inadequate Core Cooling Instrumentation Installed or Proposed for Installation,In Response to NRC 850910 Onsite Evaluation.W/One Oversize Drawing
Project stage: Other
ML20137A9941985-11-21021 November 1985
Advises That Isolation Capability of Control Room Normal Ventilation Sys CB-2 Adequate.No Mods Required to Meet Intent of NUREG-0737,Action Item III.D.3.4, Control Room Habitability & GDC 19 Based on Listed Reasons
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
ML20137N9951986-01-31031 January 1986
Forwards Addl Info in Response to 850628 Generic Ltr 85-12, Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Trip Provided When Needed.Trip Excluded When Continued Pump Operation Desirable
Project stage: Other
ML20141P0581986-03-10010 March 1986
Forwards Amend 112 to License NPF-1 & Safety Evaluation. Amend Revises Tech Specs to Add Operability & Surveillance Requirements for Core Exit Thermocouples & Reactor Vessel Level Instrumentation Sys
Project stage: Approval
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
Project stage: Request
ML20155E7911986-04-0707 April 1986
Corrected Amends 112 & 114 to License NPF-1,re Thermal Power,Surveillance Requirements & Control & Dilution to Moderate Temp Coefficient
Project stage: Other
ML20155E7861986-04-0707 April 1986
Forwards Corrected Amends 112 & 114 to License NPF-1 Revising Pagination & Resolving Administrative Errors
Project stage: Other
1982-04-28
[Table View] |
Text
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a.
1 m
Portland General ElectricCompany r - E:
Birt D Weers Vce Presdert August 7, 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 Sir:
License Change Application 125 Attached are three signed originals and 40 conformed copies of License Change Application 125, requesting amendment of Operating License NPF-1.
License Change Application 125 requests incorporation of Technical Specifications for TMI-related items pursuant to the NRC model Technical Specificat.lons. An application fee of $150 is attached in accordance with 10 CFR 170.
PCE has transmitted a copy of this request to the Oregon Department of Energy in accordance with 10 CFR 50.91.
Also attached is one signed copy of a certificate of Service for License Change Application 125 to the chief executive of the county in which the facility is located, and the Director of the State of Oregon, Department of Energy.
l Sincerely.
l
.,,/
a Bart D. Withers f
Vice President Nuclear l
Attachments c:
Mr. Lynn Frank, Director
[]p State of Oregon p
Department of Energy y
Mr. Robert L. King h
f Chairman of County Commissioners b
I It 8500120429 850007 PDR ADOCK 05000344 P
PDR 1218 '/, l l :Tn th t't POTind Cmg.n 97204
