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ML20073J659 +
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April 15, 1983 +
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08:38:24, 15 December 2024 +
NUREG-0705 +, NUREG-070 +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-0582, Clarifies Reasons to Proceed W/Development of Preliminary Calculational Tool for Steam Bubble Induced Water Hammer. Proposed Use Need Is Essential Adjunct to Efforts in Resolving Water Hammer Task.Graphs Encl +, NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +, NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 + and NUREG-0460 +
87 +
Request +
April 15, 1983 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, High Pressure Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam + and Containment Spray +
Answer Opposing State of La,Louisiana Consumer League, Louisianans for Safe Energy & Gr Rothchild Contentions & Therefore Petitions to Intervene.Contentions Inadequate or Premature.Certificate of Svc Encl +
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