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ML20140H307
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Category
CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC, TEXT-PROCUREMENT & CONTRACTS  and NUREG REPORTS
ASME section
ASME Section XI +
Accession number
ML20140H307  +
Atomic Element
Boron +, Hydrogen +  and Lead +
Cornerstone
Emergency Preparedness +
Docket
05000286  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Brookhaven National Laboratory +, Taylor J +, Fresco A +  and Fullwood R +
Generic letter
NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +
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>.
ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +, ML20140H307 +  and ML20140H307 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 0.00417 d (0.1 hours, 5.952381e-4 weeks, 1.3698e-4 months)  +
Issue date
March 31, 1986  +
Manufacturer
Westinghouse +
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>.
21:19:05, 11 December 2024  +
NUREG
NUREG/CR-2300 +, NUREG/CR-3385 +, NUREG/CR-4565 +, NUREG/CR-4441 +, NUREG/CR-4372 +, NUREG-1145, Forwards NRC Annual Rept for 1998,required by Section 307(c) of Energy Reorganization Act of 1974.Rept Discusses Activities Pursued in Fy 1998 in Support of Agency Goals to Ensure No Undue Risk from Licensed Uses of Nuclear Matls +, NUREG/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
73  +
Procedure
CH +  and ESP +
Project stage
Other  +
SSC
3PT-M14A +, 3P3-R3 +, 3PT-R3A +, 3PT-R3B +, 3PT-R3E +  and 111egi-ble +
Scram
Manual Scram +
Site
Indian Point +
Start date
March 31, 1986  +
State
Maryland +, Washington +  and New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
Title
Probabilistic Safety Study Applications Program for Inspection of Indian Point Unit 3 Nuclear Power Plant  +
To
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +
Topic
Probabilistic Risk Assessment +, Systematic Assessment of Licensee Performance +  and Fatality +
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http://pbadupws.nrc.gov/docs/ML2014/ML20140H307.pdf  +
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