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ML20132D090
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Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
ANSI code
ANSI 81.1-1982 +
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML20132D090  +
Agency
Department of Natural Resources +
Atomic Element
Nitrogen +, Carbon +, Oxygen +, Hydrogen +  and Lead +
BWRVIP
BWRVIP-03 +
CFR
10 CFR 21 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 2.201 +, 10 CFR 2.205 +, 10 CFR 2 Appendix C +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 2.790 +  and 10 CFR 50 Appendix B Criterion III, Design Control +
Docket
05000277  +, 05000278  +, 00277  +, 00278  +  and 00270  +
Equipment trip
Turbine Trip +
From
Office of Nuclear Reactor Regulation +  and Johnston W +
Generic letter
NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +, ML20132D090 +...
Hours
2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +
In package
ML20112H946 +
Intervenor
Sierra Club +
Issue date
June 6, 1985  +
Letter
ML20059M988 +, ML20078L754 +, ML20093G902 +  and ML20093E975 +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
General Electric +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
15:04:24, 12 December 2024  +
NRC bulletin
NRC Bulletin 80-13 +  and NRC Bulletin 94-01 +
Page count
1  +
Person
Stephen Dembek +
Power source
4kV +
Procedure
ST +, SAP +, ST-J-080-940-2 +  and ST-J-080-940 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20132D090 +
Project
TAC:55174 +
Project reference
TAC:M88098 +, TAC:M92639 +  and TAC:55174 +
Project stage
Other  +
SSC
62A-1 +, 52A-5 +, 63C-5 +, 07-95-506 +  and 16A-K063 +
Scram
Automatic Scram +
Site
Peach Bottom +
Site license
Peach Bottom +
Start date
June 6, 1985  +
State
Pennsylvania +, Maryland +  and Washington +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +  and Low Pressure Coolant Injection +
TS
TS-3.5.1 +, TS-1.1 +, TS-3.7.C +, TS-3.5 +, TS-6.10.2 +  and TS-3.0.C +
Title
Advises That Facility Can Be Safely Returned to Full Power Operation.Conclusion Based on Replacement of Nonconforming Piping in Recirculation Rhr,Rhr Head Spray Reactor Water Cleanup & Core Spray Sys,Except for Seven Welds  +
To
Office of Nuclear Reactor Regulation +  and Lainas G +
Topic
Unanalyzed Condition +, Reactor Vessel Water Level +, Packing leak +, High Radiation Area +, Ultimate heat sink +, Non-Destructive Examination +, Hydrostatic +, Notice of Violation +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Operability Determination +, Earthquake +, Fire Watch +, Scaffolding +, Unidentified leakage +, Affidavit +, Manual Operator Action +, Water rod +, Hardened grease +  and Reactive Inspection +
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http://pbadupws.nrc.gov/docs/ML2013/ML20132D090.pdf  +
Ultimate Heat Sink
Cooling Tower +, Susquehanna River +  and Conowingo Pond +
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