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ML021570043
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Category
Letter
ASME section
ASME Section XI +
Accession number
ML021570043  +
Atomic Element
Carbon +  and Chromium +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +  and 10 CFR 50.54#f +
Docket
05000382  +  and 00382  +
From
Venable J +  and Entergy Nuclear South +
Generic letter
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +
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ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +, ML021570043 +  and ML021570043 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
Issue date
May 16, 2002  +
Letter
CNRO-2002-00025, Response to NRC Request for Additional Information Regarding Proposed Alternative to American Society of Mechanical Engineers Boiler & Pressure Vessel Code Examination Requirements for Repairs Performed on Reactor Vessel Head Penetra +, ML20155B147 +  and 05000382/LER-2002-003, Re Inoperable Auxiliary Component Cooling Water Pump Due to Lack of Lubrication +
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23:09:39, 16 January 2025  +
NRC bulletin
NRC Bulletin 02-01 +  and NRC Bulletin 01-01 +
Page count
9  +
Project stage
Request  +
SSC
W3F1-2002-0051 +, W3F1-2002-0032, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +, W3P88-1207, Responds to Generic Ltr 88-05,providing Schedule Requested for Implementing Program Consisting of Systematic Measures to Ensure That Boric Acid Corrosion Not Lead to Abnormal Leakage,Rapidly Propagating Failure or Gross RCPB Rupture +  and W3F17-2002-0051 +
Site
Waterford +
Start date
May 16, 2002  +
State
Washington +  and Louisiana +
System
Steam Generator +, Reactor Coolant System +  and Reactor Pressure Vessel +
TS
TS-3.4.5.2 +
Title
Submittal of 60-Day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity  +
To
Document Control Desk +  and Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Non-Destructive Examination +, Coatings +, VT-2 +, Stress corrosion cracking +, Pressure Boundary Leakage +, Scaffolding +, Unidentified leakage +  and Operational leakage +
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http://pbadupws.nrc.gov/docs/ML0215/ML021570043.pdf  +
 
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