ML17255A937
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Letter Sequence Other | |
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Initiation
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MONTHYEARML19289C2151978-11-28028 November 1978
[Table View]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 |
| ML17255A937 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/21/1983 |
| From: | Delgaizo T, Delgazio T, Joel Jenkins, Overbeck G FRANKLIN INSTITUTE |
| To: | Chow E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17255A938 | List: |
| References | |
| CON-NRC-03-81-130, CON-NRC-3-81-130, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.02, TASK-TM TAC-45253, TAC-45299, TER-C5506-408, NUDOCS 8309140108 | |
| Download: ML17255A937 (108) | |
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