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ML040090230
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Category
Letter  and Inspection Report
ASME section
ASME Section III +
Accession number
ML040090230  +
Atomic Element
Carbon +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 50 +  and 10 CFR 2.790 +
Cornerstone
Initiating Events +  and Mitigating Systems +
Docket
05000327  +, 05000328  +  and 00327  +
FOIA
FOIA/PA-2003-0358 +
From
Ogle C +  and NRC/RGN-II/DRS/EB +
Generic letter
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +
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ML040090230 +, ML040090230 +, ML040090230 +, ML040090230 +, ML040090230 +, ML040090230 +, ML040090230 +, ML040090230 +, ML040090230 +  and ML040090230 +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +
Inspection Manual Chapter
NRC Inspection Manual 0609 +
Inspection report
IR 05000327/2002003 +, IR 05000327/200203 +  and IR 05000328/200203 +
Issue date
April 30, 2002  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
10:39:51, 16 January 2025  +
NFPA
NFPA 30 +, NFPA 20 +, NFPA 13 +, NFPA 14 +, NFPA 80 +, NFPA 12 +  and NFPA 101 +
NUREG
NUREG-1600, PR-MISC - 62FR06677 - (NUREG-1600) Policy and Procedure for Enforcement Actions, Policy Statement Amendment +  and NUREG-1552, Informs That During 454th Meeting of ACRS on 980708-10, Representatives of NRC Staff Met W/Licensee to Discuss Suppl 1 to NUREG-1552 +
Page count
24  +
Procedure
AOP +, Emergency Operating Procedure +, AOP-N.01 +, AOP-N.08 +, AOP-C.04 +  and AOP-C +
Regulatory Guide
Regulatory Guide 1.33 +
SSC
1A-A +, 45N824-16 +, 1AI-A +, 16-6fR-50 +, 2FCV-63 +  and 45E890-103-1 +
See also
IR 05000327/2002003 +
Site
Sequoyah +
Start date
April 30, 2002  +
State
Tennessee +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Primary containment +, HVAC +, Residual Heat Removal +  and Remote shutdown +
TS
TS-6.8.1.a +
Title
Draft IR 05000327-02-003 and IR 05000328-02-003 on 03/25-29/02, Sequoyah Nuclear Plant. Non-Cited Violations Noted  +
To
Tennessee Valley Authority +  and Scalice J +
Topic
Safe Shutdown +, Loop seal +, Fire Barrier +, Probabilistic Risk Assessment +, Operator Manual Action +, Emergency Lighting +, Significance Determination Process +, Job Performance Measure +, Loss of Offsite Power +  and Fire Protection Program +
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http://pbadupws.nrc.gov/docs/ML0400/ML040090230.pdf  +
 
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