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ML20067E716
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Category
CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS
ASME code
IWB-2500 +, IWC-5221 +, IWC-2500 +, IWC-5222 +, IWB-5222 +, IWB-2412 +, IWB-1220 +, IWC-1220 +, IWB-5221 +, IWC-2520 +, IWC-2412 +, IWC-2411 +, IWB-3518 +, IWA-5000 +, IWA-5214 +, IWA-2240 +, IWA-2400 +  and IWA-7000 +
ASME section
ASME Section XI +  and ASME Section III +
Accession number
ML20067E716  +
Atomic Element
Nickel +, Carbon +  and Tin +
CFR
10 CFR 50 +, 10 CFR 50.55a +, 10 CFR 50.55a#g5iii +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g4iv +, 10 CFR 50.55a#b2 +, 10 CFR 50.55a#g3 +, 10 CFR 50.55a#b2ivA +, 10 CFR 50.50#a +, 10 CFR 50.55#a +  and 10 CFR 50.55a#g3iii +
Code case
ASME Code Case N-408 +
Correspondence
L 16 +
Docket
05000423  +
From
SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY +
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ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +, ML20067E716 +  and ML20067E716 +
In package
ML20067E690 +
Issue date
March 31, 1989  +
L
L 16 +
Letter
A07492, Responds to NRC Re Violations Noted in Insp Rept 50-423/88-04.Corrective actions:Litton-Veam Connectors Will Be Replaced W/Qualified feed-through Devices During May 1989 Refueling Outage +, A07458, Forwards Responses to 13 Items Re First 10-yr Inservice Insp Program Plan,Per NRC 880816 Request.Responses Incorporated Into Encl Rev 1 to Plan +  and B12064, Submits Comments on 851106 10CFR50,App R Exemption & Associated SER Re Safe Shutdown in Event of Fire,For Incorporation Into Next Sser +
Manufacturer
Westinghouse +
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16:23:26, 16 December 2024  +
NUREG
NUREG-1031, Forwards Safety Evaluation Re Emergency Operating Procedures Upgrade Program Per TMI Action Item 1.C.1.Eight Procedures Validated on Simulator & Actions Acceptable +
Page count
92  +
Regulatory Guide
Regulatory Guide 1.150 +
SSC
1WB-25001 +
Site
Millstone +
Start date
March 31, 1989  +
State
Idaho +
System
Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Control Rod +  and Main Steam +
Title
First Interval ISI Program Millstone Nuclear Power Station Unit 3, Technical Evaluation Rept  +
To
NRC +
Topic
Hydrostatic +, VT-2 +, Incorporated by reference +, Dissimilar Metal Weld +  and Thermal fatigue +
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http://pbadupws.nrc.gov/docs/ML2006/ML20067E716.pdf  +
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