ML20237F716
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Letter Sequence Request | |
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TAC:44625, (Approved, Closed) | |
Administration Results Other: ML20054F383, ML20133K973, ML20135A372, ML20135A778, ML20137A994, ML20137N770, ML20137N995, ML20140E550, ML20155E786, ML20155E791, ML20198C257, ML20203H685, ML20236L390, ML20238A595 | |
MONTHYEARML20054F3831982-06-11011 June 1982
[Table View]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 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 IR 05000344/19850141985-06-12012 June 1985 Insp Rept 50-344/85-14 on 850513-17.Violation Noted:Failure to Perform Survey (Evaluation) of Extremity Exposure Due to Nonpenetrating Radiation Per 10CFR20.201 Project stage: Request 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 ML20128B2021985-06-27027 June 1985 Advises That Response to 850612 Request for Addl Info Re NUREG-0737,Item II.D.1 Will Be Submitted by 851231 Project stage: Request 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 ML20133K9731985-08-0707 August 1985 Proposed Tech Specs,Incorporating TMI-related Items Per NRC Model Tech Specs Project stage: Other 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 ML20135A3721985-09-0303 September 1985 Submits Cost Estimates for Installation of NRC Emergency Communication Circuits in Emergency Operations Facility.New Emergency Facility Scheduled for Completion by 861231. Facility Drawings Encl 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 ML20136F2671985-12-31031 December 1985 Forwards Response to 850612 Request for Addl Info Re NUREG-0737,Item II.D.1 Re Performance Testing of Relief & Safety Valves.Conclusions Originally Presented in PGE-1039 Have Not Changed Project stage: Request ML20137N7701986-01-13013 January 1986 Rev 2 to Administrative Order AO-4-7, Procedure Generation Package for Emergency Operating Procedures Project stage: Other 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 ML20137N7621986-01-31031 January 1986 Forwards item-by-item Response to Comments in Procedures Generation Package Draft SER & Rev 2 to Administrative Order AO-4-7, Procedure Generation Package for Emergency Operating Procedures Project stage: Draft 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 ML20203H6851986-07-31031 July 1986 Informs That Util Will Ref WCAP-11145 in Order to Satisfy Requirements of TMI Action Item II.K.3.31 in Generic Fashion,In Accordance W/Generic Ltr 83-35.Plant-specific Analysis Unnecessary Project stage: Other ML20238A5951987-05-0606 May 1987 Intervenor Exhibit I-SC-59,consisting of Undated Summary of Objectives Project stage: Other ML20237F7161987-08-0707 August 1987 Advises That Util Will Be Unable to Meet Original Response Time for NRC 870617 Request for Addl Info Re Testing of Relief & Safety Valves.Response Will Be Issued by 871030 Project stage: Request ML20236L3901987-10-30030 October 1987 Provides Addl Info Re Performance Testing of Relief & Safety Valves,Per NUREG-0737,Item II.D.1 & 870617 Request. Evaluation of 83 Supports for Original Design Loads Performed.Mods Identified & Installed Project stage: Other ML20055E7851990-07-0909 July 1990 Forwards Safety Evaluation Re Procedures Generation Program for Plant,Per Util 831110 & s.Ltrs Should Be Reviewed to Address Programmatic Improvements Outlined in Section 2 of Rept Project stage: Approval 1985-08-07 |
| ML20237F716 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/07/1987 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TAC-44625, NUDOCS 8708130138 | |
| Download: ML20237F716 (1) | |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217E9711999-10-13013 October 1999
[Table view]Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211Q3281999-09-0909 September 1999 Forwards Insp Rept 50-344/99-06 on 990630-0701,21 & 0408-08. No Violations Noted.Insp Conducted to Review Decommissioning Activities Underway at Trojan Site & to Accompany Shipment of Reactor Vessel to Hanford,Washington for Burial ML20211J2101999-08-30030 August 1999 Forwards Request for Addl Info Re Application for Approval of Proposed Corporate Merger of Pacificorp & Scottishpower ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20211B4091999-08-16016 August 1999 Forwards Environ Assessment & Finding No Significant Impact to Application for an Exemption & License Amend Dated 980129.Proposed Exemption & License Amend Would Delete Security Plan Requirements of 10CFR50.54(p) & 10CFR73.55 ML20211A7131999-08-16016 August 1999 Forwards Environ Assessment & Finding of No Significant Impact to Application for Exemption & License Amend Dtd 980827.Proposed Exemption & License Amend Would Delete EP Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,app E ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20210H5971999-07-27027 July 1999 Forwards Notice of Consideration of Approval of Application Re Merger & Opportunity for Hearing.Notice Being Forwarded to Ofc of Fr for Publication ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210A6401999-07-19019 July 1999 Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209D6231999-07-0808 July 1999 Forwards RAI Re Licensee 980827 Request for Amend That Would Delete Number of License Conditions & TS Requirements That Would Be Implemented After All Sf Has Been Removed from 10CFR50 Licensed Area.Response Requested within 30 Days ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20207A2751999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20206J8681999-05-0707 May 1999 Forwards Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Insp Observed Work Activities Associated with Lifting of Reactor Vessel in Preparation for Removal & Shipment to Hanford Reservation for Burial ML20206J7931999-05-0707 May 1999 Forwards Insp Repts 50-344/99-04 & 72-0017/99-02 on 990322- 25 & 29-0408.One Violations Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206H4331999-05-0505 May 1999 Forwards Amend 201 to License NPF-1 & Se.Amend Revises PDTSs by Deleting ISFSI Area,Revises Subsection 4.1.1,replaces Figure 4.1-1 with New Figure 4.1-1 & Adds New Page to Figure 4.1-1 to Reflect Access Control (ISFSI) Area ML20206N1571999-05-0404 May 1999 Forwards Util Quarterly Decommissioning Status Rept for First Quarter of 1999,IAW State of or Energy Facility Siting Council Order Approving Trojan Decommissioning Plan, ML20206E1731999-04-29029 April 1999 Informs That NRC Staff Has Performed an Acceptance Review of Trojan Nuclear Plant License Termination Plan,Submitted by ,To Determine Whether LTP Provides Adequate Info to Allow Staff to Conduct Detailed Review ML20206E0211999-04-28028 April 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re 970212 Application for Amend.Proposed Amend Would Revise Trojan Permanently Defueled TS to Delete ISFSI Area ML20206C9591999-04-23023 April 1999 Forwards Amend 200 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20206C9221999-04-23023 April 1999 Forwards Amend 199 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205T5471999-04-20020 April 1999 Forwards Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted ML20205N9061999-04-13013 April 1999 Forwards Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted.Inspectors Examined Portions of Physical Security, Access Authorization & FFD Programs ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20202C1621999-01-21021 January 1999 Forwards Insp Repts 50-344/98-04 & 72-0017/98-01 & NOV Re Inadequate Actions Taken by Radiation Protection Technician to Ensure That Radiological Conditions Safe Prior to Removing Warning Signs for Airborne Radioactivity Area 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARML20217E9711999-10-13013 October 1999
[Table view]Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20199J1661999-01-14014 January 1999 Submits Summary of ISFSI Lid Welding Demonstration to Be Held 990118-25.Dates & Days Are Tentative & Can Be Adjusted as Necesssary or as Required ML20199J0801999-01-12012 January 1999 Forwards Schedule for Trojan Nuclear Plant ISFSI pre-op Test,Per Request ML20206Q0121999-01-0808 January 1999 Forwards Rev 1 to PGE-1073 Tnp ISFSI Security Plan,As Result of 981208 Telcon with Nrc.Encl Withheld,Per 10CFR73.21 ML20206P5991999-01-0404 January 1999 Requests That Svc List for Delivery of Documents from NRC Be Updated,Per 981230 Telcon.Substitute for Listings of HR Pate & J Westvold,Submitted ML20198T1651999-01-0404 January 1999 Forwards Rev 5 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Table 2.2-5 Is Revised to Depict Major Components Removed from Plant During 1998.Revs Are Denoted by Side Bars ML20198E3981998-12-17017 December 1998 Forwards Updated ISFSI Emergency Plan,Per 981123 & Discussion in Meeting with NRC on 981119.Description of Changes Encl ML20196E2851998-11-25025 November 1998 Forwards Final Rept of Matl Properties of Neutron Shielding Matl to Be Used in Trojan ISFSI & Test Repts That Verified Matl Properties ML20196D9831998-11-24024 November 1998 Forwards Listed ISFSI Calculation Refs,Per 981110 Telcon ML20196B2321998-11-23023 November 1998 Informs That,Per Commitments Made in 981119 Meeting with Nrc,Rev to PGE-1075 Will Be Submitted No Later than 981218 ML20195J2321998-11-17017 November 1998 Forwards Rev 7 to Trojan Nuclear Plant Defueled Sar. Attachment to Ltr Includes Brief Description of Each Change Included in Rev ML20195E4811998-11-10010 November 1998 Forwards Rev 51 to Trojan Nuclear Plant Security Plan.Rev Withheld,Per 10CFR73.21 ML20155E0331998-10-27027 October 1998 Forwards Amend 7 to PGE-1052, Quality-Related List Classification for Tnp. Amend Removes Ref to Several Clean Up Sys,Deletes Exemptions Allowed by Reg Guide 1.143 & Deletes Figures No Longer Required to Support Discussion ML20154M4151998-10-14014 October 1998 Requests That Further Review of License Change Application LCA-238 Be Suspended as Result of Progress Made in Decommissioning,Installation of Natural Gas Pipe Line ML20154A4751998-09-28028 September 1998 Forwards Amend 20 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Reflecting Revisions to Fire Protection Program Made During Decommissioning Activities ML20153D3021998-09-21021 September 1998 Forwards Rev 0 to PGE-1077, Tnp Reactor Vessel & Internals Removal Project Transportation Safety Plan, Per Request That Util Submit Description of Measures to Be Taken to Ensure Safe Transport of Tnp Rv & Internals Package ML20151X7171998-09-10010 September 1998 Forwards Rev 3 to PGE-1063, Trojan Nuclear Power Station, Suppl to Applicant Environ Rept. Section 4.5 Revised to Delete Ref to Selected Room Coolers ML20151X8571998-09-10010 September 1998 Provides Rev 2 to Poge, Trojan NPP Permanently Defueled TS Bases. Changes Identified in Revised Text by Side Bars ML20153B0001998-09-0909 September 1998 Forwards Figures & Tables Identifying Nodes Assigned for Trojan ISFSI Transfer Station Analysis,TI-056,Rev 1 ML20237E9421998-08-27027 August 1998 Requests Exemption of Emergency Plan Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,App E Following Transfer of Spent Nuclear Fuel to ISFSI ML20237E1811998-08-25025 August 1998 Forwards Description of Review Methodology & Summary of Results,Including List of Identified Variations from Guidance Contained in Std Review Plan,Per NUREG-1536 ML20151W5381998-08-25025 August 1998 Forwards Rev 22 to PGE-8010, Poge Nuclear QA Program for Trojan Nuclear Plant. Rev Reflects Administrative Changes That Continue to Meet Requirements of 10CFR50,App B 1999-09-23 Category:UTILITY TO NRC MONTHYEARML20059L6651990-09-21021 September 1990
[Table view]Forwards Application for Amend to License NPF-1,consisting of License Change Application 203,Rev 1.Rev Reduces Scope of Previous Changes Re Tech Spec Table 3.6-1, Containment Isolation Valves ML20059J9841990-09-14014 September 1990 Responds to Re Violations Noted in Insp Rept 50-344/90-21.Corrective Action:Individual Employee Terminated on Day of Event ML20059J9691990-09-14014 September 1990 Forwards Estimates of Facility Operator Licensing, Requalification & Generic Fundamentals Exam Requirements for FY91-94,per Generic Ltr 90-07 ML20059J0321990-09-0707 September 1990 Requests That Six Listed Candidates Take PWR & Generic Fundamentals Exam to Be Administered on 901010 ML20059D8031990-08-31031 August 1990 Forwards Update on Actions for NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20059D2401990-08-30030 August 1990 Extends Commitment Date from 900831 to 901031 to Amend FSAR Per Util 900404 Response to Notice of Violation ML20059D0831990-08-30030 August 1990 Revises Response to Violations Noted in Insp Rept 50-344/90-02.License Document Change Request Correcting FSAR Discrepancy Noted in App A,Violation C Re Request for Design Change Initiated & Will Be Incorporated Into Amend 14 ML20059C1741990-08-28028 August 1990 Forwards Rev 31 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059D5601990-08-28028 August 1990 Forwards Fitness for Duty Performance Rept for 900103-0630. Overall Positive Rate for All Testing Conducted at Plant from 900103-0630 Is 0.71% ML20059D3201990-08-28028 August 1990 Responds to Deficiencies Identified by FEMA During 891115 Emergency Preparedness Exercise at Plant.Corrective Actions: Procedures Revised to Prioritize Roadblocks & Clearly Define Roadblocks for 5-mile & 10-mile Locations ML20058M7861990-08-0303 August 1990 Forwards Monthly Operating Rept for Jul 1990.W/o Encl ML20056A1551990-07-31031 July 1990 Forwards Updated Response to Address Maint/Surveillance Area of SALP for Period from Jan 1989 - Mar 1990.Overall Plant Performance During Period Acceptable & Found to Be Directed Toward Safe Operation ML20055J3421990-07-26026 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Plant,Per 10CFR50.75.Certifies That Finanical Assurance Utilizing Methodology as Listed Will Be Available to Decommission Plant ML20055G7131990-07-20020 July 1990 Comments on Operator Licensing Exams Administered on 900717 ML20055G7141990-07-19019 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Plant Has Four Rosemount Model 1153DD6 Differential Pressure Transmitters Installed to Associated Logics for Safety Injection ML20055F8791990-07-16016 July 1990 Forwards 1989 Annual Repts for Portland General Corp,Eugene Water & Electric Board & Pacific Power & Light Co ML20055F8161990-07-13013 July 1990 Advises of New Addressee for Nrc/Util Correspondence ML20055F6911990-07-13013 July 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML20055F2441990-07-12012 July 1990 Forwards Response to SALP Evaluation for Jan 1989 - Mar 1990 Re Maint/Surveillance.Util Plans to Improve Performance in Areas of Operation Through Commitment of Support from Nuclear Div Mgt & Personal Involvement of Corporate Mgt ML20055F2961990-07-0606 July 1990 Forwards Addl Info Re ATWS Mitigating Sys Actuation Circuitry ML20055E0241990-07-0606 July 1990 Responds to NRC Re Violations Noted in Insp Rept 50-344/90-11.Corrective Actions:Generic Issues That Contributed to Violation Will Be Discussed During Mgt Meetings & Quality Insp Supervisor Counseled ML20055E0281990-07-0606 July 1990 Informs That Actions Committed to in Util Re Replacement of Breaker During 1990 Refueling Outage & Provision of Rept Documenting Replacement of Breaker, Complete,Per NRC Bulletin 88-010 ML20055E3401990-07-0606 July 1990 Forwards Application for Renewal of Plant NPDES Permit ML20055E1751990-07-0606 July 1990 Provides Update to 891130 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Rev to Maint Procedure 12-4, Valve Air Actuators, to Include Maint Insp Completed in Apr 1990 ML20058K4891990-06-30030 June 1990 Discusses Reduced Min Measured RCS Flow for Plant.Encl Figure 3.2-3 & Evaluation Support Operation W/No Tech Spec Setpoint Changes ML20055D0441990-06-29029 June 1990 Advises That Response to Generic Ltr 90-04 Re Status of Generic Safety Issues at Facility Delayed from 900629 to 900713 ML20055D0411990-06-29029 June 1990 Discusses Design Verification Program Re Main Steam Support Structure.Extension of Completion Date for Project Justified Since Documentation,Not Mod of Main Steam Support Structure Is Reason for Delay ML20055D7091990-06-26026 June 1990 Forwards Steam Generator Tube Plugging Rept,Per Inservice Insp ML20055C2691990-02-20020 February 1990 Responds to NRC Re Violations Noted in Insp Rept 50-344/89-30.Corrective Actions:Administrative Order 5-8 Temporary Mods to Be Evaluated for Need to Improve Control Over Temporary Mods Issued for Both Trains of Sys ML17311A1041989-10-30030 October 1989 Advises That Commitment Date for Performance of Surveillance Moved to 891130 to Allow for Incorporation in Biennial Audit Per Rev 1 to LER 89-08.NRC Resident Inspector Informed of Change on 891013 ML20248G7631989-10-0606 October 1989 Forwards Description of Alternate Compensatory Measures Implemented During Upgrade Activities.W/O Encl ML20248G3131989-10-0303 October 1989 Forwards Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Revised Topical Rept PGE-1048 Will Be Submitted by 891117 ML20248E2391989-09-29029 September 1989 Forwards Summary of Action Plan to Resolve Fuel Bldg Overstress Conditions ML20248D3711989-09-29029 September 1989 Forwards Rept of Util Plan for Improving Performance of Nuclear Div Staff.New Mgt Described in Plan Will Serve as Catalyst for Decisive Performance Changes ML20248G9001989-09-29029 September 1989 Forwards Rev 1 to PGE-1049, Inservice Insp Program for Second 10-Yr Interval from 860520-960519 ML20248D6161989-09-28028 September 1989 Requests 14-day Extension Until 890928 to Respond to Violations Noted in Insp Rept 50-344/89-09.Individuals Involved in Providing Input to Response Currently Assigned to Solving Problems During Current Forced Outage ML20248G1071989-09-28028 September 1989 Advises That Util Will Submit Final Closeout of NRC Bulletin 88-004, Potential Safety-Related Pump Losss, by 900115 05000344/LER-1989-007, Informs That Rev 1 to LER 89-07 Will Be Submitted by 891013, Due to Forced Outage & Difficulties1989-09-28028 September 1989 Informs That Rev 1 to LER 89-07 Will Be Submitted by 891013, Due to Forced Outage & Difficulties ML20248D4211989-09-27027 September 1989 Suppls 881004 Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. NDE Confirmed That No Existing Flaws Exist in Critical Piping Locations Re Thermal Stratification ML20247G9011989-09-15015 September 1989 Responds to Generic Ltr 89-06 Re SPDS Requirements,Per NUREG-0737,Suppl 1 as Clarified by NUREG-1342.Concludes That Isolators Used Were Acceptable for Interfacing SPDS W/Safety Sys,Therefore Util Does Not Intend to Make Mods to SPDS ML20247C2801989-09-0808 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-344/89-18.Corrective Action:Reevaluation of OAR 87-29, Involving Mods to Hydrogen Gas Supply Sys Implemented as Part of 1989 Refueling Outage 05000344/LER-1989-012, Advises That Rev 1 to LER 89-012 Will Be Submitted by 890920 Due to Extension of 1989 Refueling Outage & Plant Trip of 8908091989-09-0808 September 1989 Advises That Rev 1 to LER 89-012 Will Be Submitted by 890920 Due to Extension of 1989 Refueling Outage & Plant Trip of 890809 ML20247B9281989-09-0808 September 1989 Responds to NRC Re Violations Noted in Insp Rept 50-344/89-12 & Forwards Review of Closeout of First 10-yr Inservice Insp Interval.Concurs That Primary Reason for Individual Problems Was Lack of Insp Contractor Activities ML20247E9371989-09-0707 September 1989 Discusses Nuclear Div Improvement Plan,Per Recent Event Re Containment Recirculation Sump.Util Corrective Actions, Including Organizational Changes,Encl.Plant Improvement Plan Will Be Submitted by 891001 ML20247A6171989-09-0505 September 1989 Informs That Intake Structure Mod Completed as Scheduled & Security Plan Rev Will Be Submitted by 891015 ML20246M5181989-08-31031 August 1989 Forwards Update on Action Plan Developed in Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment ML20246M5771989-08-31031 August 1989 Forwards Status of Progress in Achieving Improvement Goals Identified in 890515 SALP Response Re Safety Assessment/ Quality Verification.Addl Resources Applied to Qualify commercial-grade Suppliers ML20246M5651989-08-31031 August 1989 Discusses long-term Pipe Support Design Verification Program for Plant.Evaluation of Fuel Bldg Confirmed & Quantified Code Overstresses Existing Under Seismic & Tornado Loading Conditions.Details of Action Plan Will Be Sent by 890929 1990-09-07 |
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seum:. une se Podland General ElechicCornpany David W. Cockfield Vice President, Nuclear Trojan Nuclear Plant Docket 50-344 License NPF-1 Nucicar Regulatory Commission ATTN: Document Control Desk Washington DC 20555
Dear Sir:
l Performance Testing of Relief and Safety Valves NUREG-0737. Item II.D.1 By 1ctter dated June 17, 1987, Terence Chan of your staff requested that Portland General Electric (PGE) provide additional information regarding the testing of relief and safety valves for the Trojan Nuclear Plant. It was requested that this information be provided within 45 days from receipt of the lett-er, or a schedule to provide this information be submitted within 15 days.
Due to activities associated with the current refueling outage, the 15-day response time for provision of a schedule was inadvertently overlooked. ,
PGE has reviewed your request and determined that additional time will be required to adequately address each item. Accordingly, we plan to issue a detailed response to the five (5) items listed in the enclosure to your June 17. 1987 letter by October 30, 1967.
Sincerely, l*
c: Mr. John B. Martin Regional Administrator, Revision V U.S. Nuclear Regulatory Commission 1
Mr. David Kish, Director i State of Oregon ]
Department of Energy 1 Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant
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8708230138 870807 PDR P
ADOCK 05000344 O
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