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ML030640203
Show incoming properties 
Category
- No Document Type Applies
Accession number
ML030640203  +
Atomic Element
Lead +
Cornerstone
Initiating Events +
Cross cutting aspect
H.1(n) +
Docket
05000266  +  and 05000301  +
Emergency Facility
Technical Support Center +
Equipment trip
Turbine Trip +  and Reactor Trip +
FOIA
FOIA/PA-2003-0094 +
From
Nuclear Management Co +
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>.
ML030640203 +, ML030640203 +, ML030640203 +, ML030640203 +, ML030640203 +, ML030640203 +, ML030640203 +, ML030640203 +  and ML030640203 +
Issue date
February 6, 2003  +
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>.
17:09:15, 16 January 2025  +
NUREG
NUREG/CR-2005 +, NUREG-0899, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 +, NUREG-1358, Forwards NRC Info Notice 92-076, Issuance of Suppl 1 to NUREG-1358, Lessions Learned from Special Insp Program for EOPs (Conducted Oct 1988-Sept 1991). W/O Encl +  and NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +
Operating procedure
OP-1 +  and OP-11 +
Page count
137  +
Person
Steven Smith +
Power source
4V +
Procedure
AM +, AOP +, ES +, ST +, EOP-1 +, EOP-0 +, Emergency Operating Procedure +, AOP-9A +, EOP-0.1 +, AOP-5B +, AOP-9B +, AOP-29 +, EOP-1.3 +, EOP-3.1 +, EOP-1.4 +, EOP-0.2 +, EOP-0.3 +, EOP-0.4 +, EOP-3.2 +, EOP-3.3 +, AOP-in +, ST-X +, EOP-l.1 +, AOP-Water +  and AOP-Cues +
Project stage
Request  +
SSC
2P-29 +, 1P-15A +, 1P-15B +, 1X-04 +, 1A-05 +, 1A-06 +, 1E-6 +, 2A-01 +, 2A-02 +, 2B-01 +, 2B-02 +, 1E-3 +, 2B-04 +, 2X-04 +, 2A-05 +, 2B-03 +, 2A-06 +, 1N-31 +, 1N-32 +, 1B-03 +, 2B-42 +, 1A-03 +, 1A-04 +, 2A-03 +, 2A-04 +, 5th-percent +, 2B-39 +, 3E-0 +, 2B-43 +, 8A-C +...
Site
Point Beach +
Start date
February 6, 2003  +
State
Colorado +, Washington +  and Wisconsin +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Residual Heat Removal +, Auxiliary Feed Water +  and Containment Spray +
Title
Compilation of AFW Corrective Actions, Taken in Response to Potential Common Mode Failure Due to a Loss of Station Air and Operator Actions, Volume 2 of 4 (Provided by Licensee in Response to a Question from Ken Obrien, Usnrc), State Change  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Stroke time +, Probabilistic Risk Assessment +, Core Exit Thermocouple +, Failure to Scram +  and Skill of the craft +
Training curricula
F-EOP-0-04 +
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http://pbadupws.nrc.gov/docs/ML0306/ML030640203.pdf  +
 
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