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| Issue date | Title | |
|---|---|---|
| ML20083G800 | 10 March 2020 | Trojan Site-Specific Independent Spent Fuel Storage Installation (ISFSI) License Change Application (Lca) 72-08, Potential Explosion Effects on ISFSI |
| ML20209C653 | 6 July 1999 | Rev 8 to Defueled SAR, for Trojan Nuclear Plant |
| ML20204C515 | 17 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 |
| ML20249B408 | 17 June 1998 | Rev 6 to Trojan Nuclear Plant Defueled Sar |
| ML20203B034 | 26 November 1997 | Rev 5 to Trojan Nuclear Plant Defueled Sar |
| ML20135B524 | 27 November 1996 | Rev 4 to Trojan Nuclear Plant Defueled Sar |
| Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites | 5 June 1995 | Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites |
| ML20248E239 | 29 September 1989 | Forwards Summary of Action Plan to Resolve Fuel Bldg Overstress Conditions |
| IR 05000344/1989009 | 22 August 1989 | Insp Rept 50-344/89-09 on 890522-0609 & 0719-21.Violations Noted.Major Areas Inspected:Effectiveness of Licensee Programs in Identifying & Correcting Design Related Plant Vulnerabilities |
| ML20245E809 | 20 June 1989 | Safety Evaluation Supporting Amend 154 to License NPF-1 |
| ML20247Q640 | 31 May 1989 | Forwards Response to NRC Info Notice 89-044, Hydrogen Storage on Roof of Control Room, Per 890505 Commitment. Release of Nitrogen or Hydrogen Gas from Breaks on Ruptures Near Nitrogen Tanks Do Not Affect Control Room Habitability |
| ML20244D601 | 14 April 1989 | Forwards Responses to Six Questions Re Feb 1989 Review of long-term Pipe Support Design Verification Program.List of Items Requiring Extended Due Dates & Supporting Info Also Encl |
| ML20235H134 | 15 February 1989 | Forwards Response to 890208 Request for Addl Info on Proposed Increase in Control Bldg Wall Shear Forces.No Alterations of Major Structural Members of Complex Required to Accommodate Mods Already Installed |
| ML20235H187 | 15 February 1989 | Forwards Addl Info Re Amend 6 to Updated Fsar,Sections 3.2, 7.2 & 9.1,per 880831 Request.Tables 1 & 2 Illustrate Changes Made to Tables 7.2-3 & 7.3-4 in Rev 6 to FSAR |
| ML20151T419 | 5 August 1988 | Safety Evaluation Supporting Elimination of Postulated Primary Loop Pipe Ruptures as Design Basis for Facility |
| ML20148A533 | 3 March 1988 | Requests That Proprietary WCAP-11699 Be Withheld from Public Disclosure,Per 10CFR2.790.Affidavit Encl |
| ML20148A540 | 29 February 1988 | Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Trojan Plant |
| ML20195H897 | 24 December 1987 | Proposed Tech Specs Deleting Sections Re Fire Protection |
| IR 05000344/1987034 | 25 November 1987 | Insp Rept 50-344/87-34 on 870921-25.Violations Noted.Major Areas Inspected:Licensee Fire Protection Program Implementation & Action on Previous Insp Findings |
| ML20236J874 | 4 August 1987 | Forwards Request for Addl Info Re Util Proposed Application of Leak Before Break Methodology to Eliminate Dynamic Effect of Postulated Primary Loop Pipe Ruptures from Design Basis, Per GDC-4.Response Requested within 30 Days of Ltr Receipt |
| ML20235J910 | 1 July 1987 | Forwards Amend 6 to Updated Fsar.Amend Includes Effects of Changes Made in Facility or Procedures as Described in 820720 FSAR & Amends 1-5 & Safety Evaluation Performed by Util in Support of Requested License Amends |
| NRC Generic Letter 1987-11 | 19 June 1987 | NRC Generic Letter 1987-011: Relaxation in Arbitrary Intermediate Pipe Rupture Requirements |
| IR 05000344/1987007 | 21 April 1987 | Insp Rept 50-344/87-07 on 870301-0411.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Maint,Surveillance & Followup on Previously Identified Items |
| IR 05000344/1986044 | 16 December 1986 | Insp Rept 50-344/86-44 on 861026-1206.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Corrective Action,Maint,Surveillance & Followup on Previously Identified Items |
| ML20215E934 | 16 December 1986 | Responds to 861103 Petition Per 10CFR2.206 Alleging That Plant Operator Failed to Disclose Conditions That Undermine Safety in Case of Seismic Event.Requests to Suspend OL & for Document Production & Discovery Denied.Fr Notice Encl |
| ML20215E969 | 16 December 1986 | Notice of Receipt of 861103 Petition for Director'S Decision Under 10CFR2.206 Seeking Suspension of License NPF-1 Due to Licensee Failure to Disclose Conditions Undermining Safety in Case of Seismic Event |
| ML20212N247 | 3 November 1986 | Partially Withheld Petition to Suspend OL Due to Util Failure to Disclose Conditions That Undermine Safety in Case of Seismic Event.Directors Should Issue Order Under 2.206 to Show Cause Why OL Should Not Be Suspended |
| ML20215N167 | 31 October 1986 | Rev 1 to, Leak-Before-Break Evaluation of Reactor Coolant Loop |
| ML20215N550 | 31 October 1986 | Forwards Response to Resident Inspector 861029 Concerns Re Condition of Turbine Bldg & safety-related Equipment Contained Within,Per Util Identification of Potential Problem in Event of Steam Line Break |
| ML20211A194 | 27 May 1986 | SER Supporting Conclusion That Items 2(b) & 3 of IE Bulletin 80-11 Re Masonry Wall Design Fully Implemented & Reasonable Assurance Exists That safety-related Walls Will Withstand Specified Load Conditions,Including 0.15g OBE |
| NRC Generic Letter 1986-10 | 24 April 1986 | NRC Generic Letter 1986-010: Implementation of Fire Protection Requirements |
| ML20138H895 | 30 June 1985 | Rev 0 to Leak-Before-Break Evaluation of Reactor Coolant Loop, Final Rept |
| ML20140E550 | 4 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 |
| NRC Generic Letter 1984-01 | 5 January 1984 | NRC Generic Letter 1984-001: NRC Use of the Terms, Important to Safety and Safety Related |
| NRC Generic Letter 1980-11 | 22 December 1980 | NRC Generic Letter 1980-113, Control of Heavy Loads. |
| NRC Generic Letter 1980-10 | 24 November 1980 | NRC Generic Letter 1980-100: Appendix R to 10 CFR Regarding Fire Protection - Federal Register Notice |
| ML20150E782 | 12 December 1978 | Transcript of Hearing on 781212 at Salem,Or.Pp 2574-2738 |
| ML20150B945 | 2 November 1978 | Transcript of Portland Gas & Electric Co Control Bldg 781102 proceedings.Pp2064-2299 |
| ML20148E605 | 24 October 1978 | Transcript of 781024 Hearing in Salem,Or.Appearances Made by Rf Banks,M Axelrad,R Johnson,W Kinsey,Jh Socolofsky,J Gray, G Kafoury,E Rosolie & N Bell |
| ML20147F096 | 16 October 1978 | Licensee'S Testimony on Capability of Subj Facil to W/Stand Seismic Events.Statements of Qualifications,Ref & Append Are Attached.Description of Affected Structure & Deficiencies Such as Amount & Arrangement of Reinforcing Steel Provided |
| ML20148A060 | 6 October 1978 | Direct Testimony of Harold Laursen Re Assignment to Eval Ability of Subj Facil Bldg Shear Walls to Resist Seismic Loading.Determined Shear Walls Can Withstand .25g Safe Shutdown Earthquake |
| ML20147E640 | 3 October 1978 | Transcript of SR Christensen Testimony Re Description of Seismic Instrumentation & Engineering Investigations to Be Conducted Following Earthquake |
| ML20147E632 | 3 October 1978 | Transcript of Dj Broehl Testimony Re Plant History, Chronology of Events Since Apr 1978 & Summary of Licensee Efforts to Ensure Safe Interim Operation of Control Bldg |
| ML20150A658 | 21 September 1978 | Order Re Responses to NRC Interrogatories by Coalition for Safe Pwr & Consolidation.Cfsp Must:Respond W/In 14 Days to S1,S2,E1,G1,G2,G3,G8 & All Other Interrogatories;Clarify the Status of Spokesmen.Motion for Reconsideration Is Denied |
| ML20248H760 | 28 April 1978 | PNO-78-099:on 780413 Licensee Reported to Region V Ofc That re-analysis by Bechtel Revealed That Both OBE & SSE, Calculated Rebar Stress Levels in Control Building Walls Exceeds Seismic Design Criteria.Licensee Will Submit Rept |
| ML20147F982 | 24 February 1978 | Request Pursuant to 10CFR2.206 to Institute Proc to Revoke Oper Lic & for Interim Relief.Believes Subj Facil Is in Violation of 1954 Atomic Energy Act by Being a Hazard to Pub Health & Safety.W/Attached Supporting Matls |