Letter Sequence Other |
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Results
Other: ML19211A952, ML19260C712, ML19309H462, ML19318A584, ML19337B217, ML19338G104, ML19339A680, ML19343B804, ML19350E501, ML20008F580, ML20024B941, ML20039A940, ML20039A943, ML20052D918, ML20054F383
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MONTHYEARML19289C2151978-11-28028 November 1978
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
ML19209C0131979-10-0303 October 1979
Request by State DOE to Be Notified If SER Will Be Delayed Longer than One Month
Project stage: Request
ML19250C0081979-10-17017 October 1979
Responds to 790913 Request for Commitments to Meet Requirements of NUREG-0578.Forwards Response Delineating Plant Design & Improvements in Emergency Preparedness
Project stage: Request
ML19210C6271979-10-30030 October 1979
Discussion of TMI Lessons Learned Short-Term Requirements
Project stage: Request
ML19211A9521979-12-14014 December 1979
Forwards Addl Info in Response to NRC 791210 Request Re Automatic Initiation of Auxiliary Feedwater Sys & Auxiliary Feedwater Flow Indication to Steam Generator.Thirteen Oversized Drawings Available in Central Files Encl
Project stage: Other
ML19260C7121980-01-0202 January 1980
Forwards Addl Info Re NUREG-0578 short-term Lessons Learned Task Force Action Items Concerning Design Details of Mods. Provides Schedule Info Re Items Required to Be Completed by 810101
Project stage: Other
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
ML19309E6031980-04-15015 April 1980
Forwards Supplemental Info Re short-term Lessons Learned Task Force Recommendations
Project stage: Supplement
ML19309H4621980-05-0707 May 1980
Forwards License Change Application (Lca) 60,replacing Lca 51.Certificate of Svc Encl
Project stage: Other
ML20005B5001980-06-13013 June 1980
Forwards Application for Withholding & Proprietary WCAP-9725 & Nonproprietary WCAP-9726, Westinghouse Technical Support Complex. Proprietary Version Withheld (Ref 10CFR2.790).W/o Nonproprietary Version
Project stage: Request
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
ML19338G1041980-10-21021 October 1980
Forwards Trojan Nuclear Plant Emergency Response Facilities, Per NRC 800905 Request.Technical Support Ctr & Emergency Operations Facility Will Be Operational by 820401 & Safety Parameter Display Sys by 820101
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
ML19339A6801980-10-30030 October 1980
Responds to .Licensee Will Be in Compliance W/Shift Staffing Requirements for Having Two Senior Reactor Operators,Two Reactor Operators & Two Nonlicensed Operators on Shift During Operational Modes 1-4 by 820701
Project stage: Other
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
ML20008F5801981-04-15015 April 1981
Responds to Generic Ltrs 81-10 & 81-17,requesting Commitment to Implementation Schedules for TMI Action Plan Item III.A.1.2 Re Emergency Support Facilities & NUREG-0696. Exemption from Requirements of NUREG-0696 Requested
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
ML19350E4051981-06-17017 June 1981
Summary of 810615 Meeting W/Util in Bethesda,Md Re Emergency Response Facilities
Project stage: Meeting
ML19350E5011981-06-17017 June 1981
Viewgraphs Entitled Applicable NRC Requirements for Guidance for Emergency Response
Project stage: Other
ML20005B4941981-07-0202 July 1981
Forwards Supplementary Info Re NUREG-0696 Concerning Emergency Response Facilities,Westinghouse Application for Withholding & Proprietary WCAP-9725, Westinghouse Technical Support Complex. Rept Withheld (Ref 10CFR2.790)
Project stage: Supplement
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
ML20032A7331981-10-26026 October 1981
Forwards Supplemental Info on NUREG-0696, Emergency Operations Facilities, Per 810902 Request.Previous Submittals ,810415 & 0702 Encl
Project stage: Supplement
ML20039A9431981-10-31031 October 1981
Evaluation of Emergency Response Facilities for Trojan Nuclear Plant
Project stage: Other
ML20038A6311981-11-0606 November 1981
Forwards Addl Info Requested in NRC Re Reactor Vessel Level Indication Sys Being Installed at Facility
Project stage: Other
ML20039A9401981-12-0303 December 1981
Forwards Evaluation of Design Plan for Emergency Response Facilities Submitted Per Generic Ltr 81-10.Info Inadequacies Listed & Condition for Addl Review Prior to Insp Outlined
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
ML20040D8981982-01-27027 January 1982
Forwards Supplemental Info Re NUREG-0696, Emergency Response Facilities. Review of Habitability Features Continuing & Should Be Complete by 820401.Draft NUREG-0814 Contains Number of New Requirements
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
ML20052D9181982-05-0303 May 1982
Forwards Summary of Plant Emergency Operations Facility, Providing Addl Info in Response to NUREG-0696.NRC Ruling Re Acceptability of Facility Requested by 820601,to Meet 821001 Deadline for Completion
Project stage: Other
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
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
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
ML20135A7781985-09-0303 September 1985
Forwards Reactor Vessel Level Instrumentation Sys Implementation Ltr Rept,In Response to NRC 850202 Safety Evaluation
Project stage: Other
1981-12-28
[Table View] |
Text
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I M
M N M MCOufgXzV g
Donald J. Brochi Asststart Vce Presdent July 8, 1983 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington DC 20555
Dear Mr. Eisenhut:
TROJAN NUCLEAR PLANT NUREG-0737 Items III.A.1.2 and III.D.3.4 THI-2 Action Plan Items Our letter of March 31, 1983 on Action Plan Item III.D.3.4, control Room Habitability, described problems we were having in making operational the control room ventilation system ammonia detectors and requested a sched-ule extension to startup of Cycle 6.
Although a great deal of time and effort has been expended on the ammonia detectors since then, they are still not operational. At the present time, there is no indication of when that status might be changed. The vendor has been consulted and replacement parts have been obtained and installed; however, the system still will not maintain calibration for the low range of monitoring sen-sitivity for thich it is expected to operate.
The vendor is scheduled to arrive onsite again next week for further work and evaluation of the problems. At that time, we will attempt to make the system operational. Therefore, we are notifying you of an additional schedule slippage for these detectors, but we are unable to give you a new date by which the ammonia detectors will be operational. As soon as the problem can be evaluated and a solution found, we will provide a new date for scheduled completion.
In regard to Action Plan Item III.A.1.2, Upgrade Emergency Operations Facilities, we would like to clarify a point regarding the area radiation monitor in the Technical Support Center (TSC). Our original description of the TSC stated that the area radiation monitor (ARN) would be provided on the first level of the TSC, the level where personnel occupancy occurs.
A subsequent letter of January 27, 1982 stated that two ARMS would be provided, one on each level. Further evaluation of the system indicates that one ARN hf bli that is necessary, installed on the first floor of the TSC, the it ; with personnel occupancy. The basement level will not have substantial personnel occupancy, therefore, it does not require an additional ARN.
8307120029 830708 PDR ADDCK 05000344 P
PDR 1
121 S W Sa rnon Street. Portand. Gregon 97204 l
I N Geritrd MCoriixu1y Mr. Darrell C. Eisenhut July 8, 1983 Page two Should you have any further questions regardin5 the.above two items, please do not hesitate to contact me.
Sincerely, l 6W c:
Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. John B. Martin, Regional Adaluistrator NRC Region V
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