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ML20059K706
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Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
Accession number
ML20059K706  +
CFR
10 CFR 50.54 +
Docket
05000285  +
From
Quay T +  and Office of Nuclear Reactor Regulation +
Generic letter
NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +
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ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +, ML20059K706 +...
Issue date
September 14, 1990  +
Letter
LIC-90-0627, Responds to Generic Ltr 89-19 Re USI A-47 on Safety Implications of Control Sys in Lwrs.Util Reconsidered Original Commitment Noted in & Does Not Plan to Implement Automatic Steam Generator Overfill Protection +  and 05000285/LER-1990-003, :on 900216,determined That Auxiliary Feedwater Piping Outside Normal Stress Limits of ASME Code & Design Basis Specified in Updated Sar.Caused by Design Deficiency.Valve Operators Will Be Inspected +
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06:25:02, 17 December 2024  +
Page count
4  +
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ML20059K706 +
Project
TAC:74944 +
Project reference
TAC:74944 +
Project stage
Other  +
Site
Fort Calhoun +
Start date
September 14, 1990  +
State
Washington +, Nebraska +  and New Hampshire +
System
Steam Generator +  and Feedwater +
Title
Disagrees W/Position That More Detailed Design & Safety Assessment Using Ipe/Pra Appropriate Framework,Per Generic Ltr 89-19  +
To
Gates W +  and Omaha Public Power District +
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http://pbadupws.nrc.gov/docs/ML2005/ML20059K706.pdf  +
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