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ML20235S440
Show incoming properties
Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
Accession number
ML20235S440  +
Agency
Occupational Safety and Health Administration +
Atomic Element
Oxygen +, Sodium +, Hydrogen +  and Chlorine +
CFR
10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 20.1#c +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +
Docket
05000245  +  and 00245  +
From
Office of Nuclear Reactor Regulation +
General design criterion
GDC 3, Fire protection +
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>.
ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +, ML20235S440 +  and ML20235S440 +
In package
ML20235S413 +
Isotope
Nitrogen-16 +  and N-16 +
Issue date
September 29, 1987  +
Letter
05000000/LER-1986-030, Partially Deleted LER 86-030-00:on 861211,unauthorized Opening Into Protected Area Discovered.Caused by Area Not Properly Identified as Area for Security Concern.Signs Posted +  and 05000336/LER-1987-001, :on 861222,intermittent Fire Alarms Received from Heat Detectors Above Reactor Coolant Pump 5.Caused by Heat Detector Failure.Faulty Detector Will Be Replaced.W/ +
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09:24:23, 3 December 2024  +
NUREG
NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
Page count
5  +
Procedure
CP.DA +
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.
ML20235S440 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 8.8 +
Site
Millstone +
Site license
DPR-21 +
Start date
September 29, 1987  +
System
Main Steam Isolation Valve +, Primary containment +, Standby Gas Treatment System +, Main Steam Line +, Control Rod +  and Main Steam +
Title
Safety Evaluation Supporting Amend 12 to License DPR-21  +
Topic
Offsite Dose Calculation Manual +, Excess Flow Check Valve +  and Main Steam Line Radiation Monitor +
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http://pbadupws.nrc.gov/docs/ML2023/ML20235S440.pdf  +
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