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ML100710755
Show incoming properties 
Category
- No Document Type Applies
Accession number
ML100710755  +
Atomic Element
Lead +
Cornerstone
Initiating Events +
Correspondence
DCL-10-028, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating +
DCL
DCL-10-028, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating +
Docket
05000275  +  and 05000323  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Pacific Gas & Electric +
Generic letter
NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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>.
ML100710755 +, ML100710755 +, ML100710755 +, ML100710755 +, ML100710755 +, ML100710755 +, ML100710755 +, ML100710755 +  and ML100710755 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
Issue date
March 11, 2010  +
Manufacturer
Westinghouse +
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11:08:25, 14 January 2025  +
NUREG
NUREG/CR-5750 +, NUREG/CR-6268 +, NUREG/CR-5726 +, NUREG/CR-5497 +, NUREG/CR-5500, Discusses Issuance of Final Rept, Reliability Study Auxiliary Emergency Feedwater System 1987-1995, (NUREG/CR-5500,Vol 1).Summary of Comment Resolutions Encl +, NUREG-0675, Forwards Decision DD-86-12 in Response to Petition & Suppls Re Licensing Actions Based on Allegations.Nrc Evaluation of Allegation & Basis for Conclusions in Decision DD-86-12 Contained in Sser 33 to NUREG-0675,transmitted on 860527 +  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 +
Page count
28  +
Power source
4kV +
Procedure
RT +  and Emergency Operating Procedure +
Project stage
Other  +
Regulatory Guide
Regulatory Guide 1.200 +
SSC
6E-2 +
Site
Diablo Canyon +
Start date
March 11, 2010  +
System
Steam Generator +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, HVAC +  and Emergency Core Cooling System +
Title
Attachment 6 to DCL-10-028, Impacts of PRA Open Items/Gaps on Application  +
To
Office of Nuclear Reactor Regulation +
Topic
Internal Flooding +, Probabilistic Risk Assessment +, High Energy Line Break +, Large early release frequency +, Loss of Offsite Power +  and Earthquake +
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http://pbadupws.nrc.gov/docs/ML1007/ML100710755.pdf  +
 
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