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	Issue date	From	Title	Project stage
ML20197E758	31 January 1986	ABB IMPELL CORP. (FORMERLY IMPELL CORP.) Grubb R Bak W Mcleod W	Rev 0 to Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant	Other
IR 05000344/1986017	19 May 1986	Jim Melfi NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) Mendonca M Pereira D	Insp Rept 50-344/86-17 on 860505-09.No Noncompliance or Deviations Noted.Major Areas Inspected:Onsite Review Committee,Qa Test & Measurement Equipment Program & Surveillance Program	Request
ML20198S051	23 May 1986	BECHTEL GROUP INC.	Interim Rept of Independent Review of Trojan Nuclear Plant Reactor Coolant Loop Thermal Movements Evaluation Program. Supporting Info Encl	Other
ML20198Q928	3 June 1986	Withers B Portland General Electric	Forwards Test Rept 17822, PG&E - Trojan - 1986 Snubber Valve Failure Analysis, Rev 0 to Temporary Plant Test TPT-166, RCS Thermal ... & Westinghouse Amend 3,Rev 2 to Procedure ISI-205,per NRC 860529 Meeting Request	Meeting
ML20198R908	4 June 1986	Portland General Electric Zimmerman G	Forwards Impell Summary Rept, Evaluation of Reactor Coolant Loop for Restrained Thermal Expansion,Trojan Nuclear Plant	Other
ML20206G753	5 June 1986	Varga S Office of Nuclear Reactor Regulation	Concludes That Adequate Assurance of RCS Integrity Demonstrated for Mode 3,hot Standby,Based on Review of 860521,0603 & 04 Ltrs & 860521 Meeting.Safety Evaluation Will Be Issued After Certification Received	Approval
ML20198S019	6 June 1986	Withers B Portland General Electric	Forwards Documentation from Bechtel Corp Re Review & Evaluation of Final Results of RCS Thermal Expansion Analysis & Hot Leg Shell Analysis Performed by Impell Corp. Encl Info Should Close Out Concerns in	Other
ML20199B510	13 June 1986	Steele R Portland General Electric Wehage R	Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves,Heatup of 860608-10	Other
ML20199B502	13 June 1986	Withers B Portland General Electric	Forwards Temporary Plant Test TPT-166, Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves, Heatup of 860608-10, Per .Future Monitoring Program Will Be Documented by 861001	Other
ML20211G407	16 June 1986	Withers B Portland General Electric	Forwards Rev 0 to Temporary Plant Test TPT-166, Reactor Coolant Thermal Expansion Test Final Predictive Curves Heatup of 860615-16, Demonstrating That Acceptance Criteria Met	Other
ML20211G419	16 June 1986	Steele R Portland General Electric Wehage R	Rev 0 to Reactor Coolant Thermal Expansion Test Final Predictive Curves,Heatup of 860615-16	Other
ML20202C354	26 June 1986	Withers B Portland General Electric	Informs That Remote Monitoring of Electronic Instrumentation Will Be Used to Assure That Steam Generator Snubbers Allow RCS Thermal Movement,Per 860616 Safety Evaluation.Only Remote Monitoring Will Be Repeated During Each Heatup	Other
ML20206F998	30 June 1986	Office of Nuclear Reactor Regulation	SER in Support of Conclusion That Util Adequately Addressed Technical & Programmatic Aspects of Cause & Effects of Restrained Thermal Growth of Rcs.Ser Re Util Response to TMI Item III.D.3.4, Control Room Habitability Also Encl	Other
ML20198R016	30 June 1986	Portland General Electric	Rev 0 to Temporary Plant Test TPT-166, RCS Thermal Expansion Test. Addl Info on Insp of Cast Stainless Steel Hot Leg Elbows Encl	Other
ML20198R985	30 June 1986	ABB IMPELL CORP. (FORMERLY IMPELL CORP.)	Rev 0 to Evaluation of Reactor Coolant Loop for Restrained Thermal Expansion,Trojan Nuclear Plant, Summary Rept	Other
ML20204F441	22 July 1986	Withers B Portland General Electric	Rev 0 to Temporary Plant Test Procedure TPT-175, RCS Thermal Expansion Long-Term Monitoring	Other
ML20210L720	24 September 1986	Chan T Office of Nuclear Reactor Regulation	Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl	Meeting
ML20210V194	25 September 1986	Withers B Portland General Electric	Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation	Other
ML20235Z787	15 October 1986	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) Martin J	Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty	Other
ML20212D368	19 December 1986	Lindblad W Portland General Electric	Submits Assessment of Impact of Replacing Graphite Shims W/ Carbon Steel Shims on Hot Leg Pipe Whip Restraints.Potential Effect on RCS Piping in Event of Future Contact Between Hot Leg Piping & Whip Restraints Addressed	Other
ML20235K098	30 September 1987	Portland General Electric Cockfield D	Informs That Periodicity of RCS Thermal Expansion Monitoring Surveillances Returned to Normal Following Completion of Twice Per Shift Exam to Detect Possible RCS Leakage as Reported to NRC on 870724	Other

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