ML20198R016
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Letter Sequence Other | |
|---|---|
TAC:61405, (Approved, Closed) | |
Initiation
Results Other: 05000344/LER-1985-013-01, Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon, ML19267A316, ML19274E248, ML19274E250, ML20197E758, ML20198Q962, ML20198R016, ML20198R908, ML20198R985, ML20198S019, ML20198S051, ML20199B502, ML20199B510, ML20202C354, ML20204F441, ML20206F998, ML20210S227, ML20210V194, ML20211G407, ML20211G419, ML20212D368, ML20235K098, ML20235Z787 | |
MONTHYEARML19267A3161978-12-29029 December 1978
[Table View]Informs That Due to Control Bldg Proceeding,The Mod to Operating Status Alarms of Diesel Generators Will Not Be Completed Until 790131 Project stage: Other ML19261B7371979-01-26026 January 1979 Forwards Request for Addl Info in Order to Complete Review Re Revised Westinghouse Thermal Design Procedure & WRB-1 Critical Heat Flux Correlation.Requests Response as Soon as Possible Project stage: RAI ML19259B6041979-02-0707 February 1979 Forwards Request for Addl Info Re Revised Westinghouse Thermal Design Procedure & Critical Heat Flux Correlation for Facility Project stage: RAI ML19274E2481979-03-15015 March 1979 Forwards License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs.Certificate of Svc & Class III Fee Encl Project stage: Other ML19274E2501979-03-15015 March 1979 License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs Project stage: Other ML19254F2471979-10-31031 October 1979 Supplements 790315 License Change Application 50 Incorporating 10CFR50,App I,Radiological Effluent Tech Specs.Includes Spec Implementing 40CFR50.Util to Implement 10CFR190 Until Application 50 Approved & Issued as Amend Project stage: Supplement ML20197E7581986-01-31031 January 1986 Rev 0 to Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant Project stage: Other 05000344/LER-1985-013-01, Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon1986-05-0909 May 1986 Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon Project stage: Other ML20210S2271986-05-15015 May 1986 Trip Rept of 860510-11 Site Visit to Participate in Licensee Cold Walkdown of Reactor Coolant Loop Piping & Components, Including Supports,To Assess Whether Cause of LER 85-013, Rev 1 Determined Project stage: Other IR 05000344/19860171986-05-19019 May 1986 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 Project stage: Request ML20198S0511986-05-23023 May 1986 Interim Rept of Independent Review of Trojan Nuclear Plant Reactor Coolant Loop Thermal Movements Evaluation Program. Supporting Info Encl Project stage: Other ML20198Q9621986-05-31031 May 1986 PG&E - Trojan - 1986 Snubber Valve Failure Analysis Project stage: Other ML20198Q9281986-06-0303 June 1986 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 Project stage: Meeting ML20198R9081986-06-0404 June 1986 Forwards Impell Summary Rept, Evaluation of Reactor Coolant Loop for Restrained Thermal Expansion,Trojan Nuclear Plant Project stage: Other ML20206G7531986-06-0505 June 1986 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 Project stage: Approval ML20198S0191986-06-0606 June 1986 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 Project stage: Other ML20199B5101986-06-13013 June 1986 Reactor Coolant Thermal Expansion Test,Summary of Data & Predictive Curves,Heatup of 860608-10 Project stage: Other ML20199B5021986-06-13013 June 1986 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 Project stage: Other ML20211G4191986-06-16016 June 1986 Rev 0 to Reactor Coolant Thermal Expansion Test Final Predictive Curves,Heatup of 860615-16 Project stage: Other ML20211G4071986-06-16016 June 1986 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 Project stage: Other ML20202C3541986-06-26026 June 1986 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 Project stage: Other ML20198R9851986-06-30030 June 1986 Rev 0 to Evaluation of Reactor Coolant Loop for Restrained Thermal Expansion,Trojan Nuclear Plant, Summary Rept Project stage: Other ML20198R0161986-06-30030 June 1986 Rev 0 to Temporary Plant Test TPT-166, RCS Thermal Expansion Test. Addl Info on Insp of Cast Stainless Steel Hot Leg Elbows Encl Project stage: Other ML20206F9981986-06-30030 June 1986 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 Project stage: Other ML20204F4411986-07-22022 July 1986 Rev 0 to Temporary Plant Test Procedure TPT-175, RCS Thermal Expansion Long-Term Monitoring Project stage: Other ML20210L7201986-09-24024 September 1986 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 Project stage: Meeting ML20210V1941986-09-25025 September 1986 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 Project stage: Other ML20235Z7871986-10-15015 October 1986 Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty Project stage: Other ML20212D3681986-12-19019 December 1986 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 Project stage: Other ML20235K0981987-09-30030 September 1987 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 Project stage: Other 1986-05-09 |
| ML20198R016 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/30/1986 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20198Q932 | List: |
| References | |
| TAC-61405, TPT-166, NUDOCS 8606090436 | |
| Download: ML20198R016 (213) | |
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