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 Issue dateTitleFromTo
NRC Generic Letter 1984-152 July 1984NRC Generic Letter 1984-015: Proposed Actions to Improve and Maintain Diesel Generator ReliabilityEisenhut D
Office of Nuclear Reactor Regulation
ML20093M40517 October 1984Responds to Generic Ltr 84-15, Proposed Staff Actions to Improve & Maintain Diesel Generator Reliability. Actions to Reduce Number of Diesel Generator Fast Starts to Enhance Reliability by Minimizing Testing Degradation DiscussedFirstEnergy
Hukill H
Eisenhut D
Office of Nuclear Reactor Regulation
Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators22 April 1985Recent Engine Failures of Emergency Diesel GeneratorsJordan E
NRC/IE
ML20127N07917 May 1985Notifies That 850602 Expected Response to Generic Ltr 84-15, Diesel Generator Reliability, Will Be Submitted by 850630. Addl Time Required to Develop Thorough & Accurate ResponseFirstEnergy
Standerfer F
Snyder B
Office of Nuclear Reactor Regulation
ML20129A52627 June 1985Forwards Response to Generic Ltr 84-15, Proposed Staff Actions to Improve & Maintain Diesel Generator Reliability. Time History of Last 100 Valid Starts of Each Diesel Generator ProvidedFirstEnergy
Standerfer F
Eisenhut D
Office of Nuclear Reactor Regulation
ML20133E23530 September 1985Ack Receipt of 841017 Response to Generic Ltr 84-15 Re Reduction of Diesel Generator Fast Starts.Response Acceptable.No Further Action RequiredStolz J
Office of Nuclear Reactor Regulation
FirstEnergy
Hukill H
ML20210R5112 May 1986Requests Review of plant-specific List Re Regulatory Info Tracking Sys,Adding Omitted Significance Actions & Providing Date All Aspects of Requirements Completed/Implemented or Expected.Info Requested by 860531Office of Nuclear Reactor Regulation
Thoma J
FirstEnergy
Hukill H
ML20195E4552 June 1986Requests Addl Clarification Re 860502 Request for Status of Implementation of Generic Requirements,Per Encl List of multi-plant Actions.Required Effort to Respond Underestimated by NRCFirstEnergy
Hukill H
Office of Nuclear Reactor Regulation
Thoma J
ML20206T68426 June 1986Forwards Markup of NRC List of Generic Requirements Indicating Estimated Status Re Implementation of multi-plant Actions,Per 860627 Commitment.Some multi-plant Actions Require Addl Clarification on Generic RequirementsFirstEnergy
Hukill H
Office of Nuclear Reactor Regulation
Toma J
ML20212D54324 December 1986Forwards Resolution of Inservice Testing (IST) Issues for Second 10-yr Interval & Description of IST Program for Pumps & Valves,In Response to 861027 Meeting.Requests Response by 870115 Re Whether or Not NRC in Agreement W/ApproachFirstEnergy
Hukill H
Stolz J
Office of Nuclear Reactor Regulation
ML20215J25317 February 1987Forwards Suppl 1 to EGG-NTA-7296, Supplemental Technical Evaluation Rept,Pump & Valve Inservice Testing Program, TMI-1. Proposed Program in Accordance W/Established NRC Requirements W/Noted ExceptionsINC.
EG&G IDAHO
IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
Obenchain C
Carrington M
Office of Nuclear Reactor Regulation
ML20207S38228 February 1987Suppl 1 to Supplemental Technical Evaluation Rept,Pump & Valve Inservice Testing Program TMI-1Cook T
INC.
EG&G IDAHO
IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
Rockhold H
NRC
ML20214A00712 May 1987Forwards Table I,Reflecting Status of Activities Associated w/multi-plant Action Items.Changes from 860626 Submittal Listed.Table Also Incorporates Comments from 860709 Telcon & Info Provided on 860902FirstEnergy
Hukill H
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
ML20063H79310 February 1994TS Change Request 230 to License DPR-50,replacing Word Tested W/Words Verified to Be Operable in TS Section 3.7.2.c,including New Page 3-43aFirstEnergy
Broughton T
TMI-10-054, Technical Specifications Change Request (Tscr) No. 348 Relocation of Equipment Load List from TS 4.5.1.1 B, Sequence and Power Transfer Test, to the Updated Final Safety Analysis Report22 September 2010Technical Specifications Change Request (Tscr) No. 348 Relocation of Equipment Load List from TS 4.5.1.1 B, Sequence and Power Transfer Test, to the Updated Final Safety Analysis ReportExelon
Cowan P
Office of Nuclear Reactor Regulation
Document Control Desk