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ML091280241
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Category
Letter
Accession number
ML091280241  +
Atomic Element
Boron +
CFR
10 CFR 21 +, 10 CFR 50.59 +, 10 CFR 5 +, 10 CFR 5.59 +, 10 CFR 50.59#d2 +  and 10 CFR 50.71#e +
Correspondence
L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +
Docket
05000443  +  and 00443  +
Equipment trip
Reactor Trip +
From
St.Pierre G +  and Florida Power & Light Energy Seabrook +
General design criterion
GDC 57 +
Generic letter
NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 04-02 +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +  and NRC Generic Letter 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components" +
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ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +, ML091280241 +  and ML091280241 +
Issue date
November 3, 2008  +
L
L-2003-201, NRC Bulletin 2003-01 Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors +
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>.
16:58:13, 14 January 2025  +
NEI
NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +
NRC bulletin
NRC Bulletin 03-01 +
NUREG
NUREG-07037 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
Page count
26  +
Project stage
Request  +
SSC
07-07-005 +, 07-08-022 +, 07-07-046 +, 07-07-040 +, 07-07-019 +, 07-08-023 +, 07-08-009 +, 07-08-021 +, 07-07-021 +, 07-07-032 +, 07-08-010 +, 07-05-018 +, 07-07-024 +, 07-07-055 +, 07-07-035 +  and 07-07-054 +
Site
Seabrook +
Start date
November 3, 2008  +
State
Washington +
System
Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +  and Containment Spray +
Title
Rev. 12 to Updated Final Safety Analysis Report, Revision 9 to Appendix R, Fire Protection Safe Shutdown Capability, Revision 10 to Appendix a, Evaluation & Comparison to BTP Apcsb 9.5-1, & Revision 112 to Technical Requirements Manual  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Temporary Modification +, Shift Technical Advisor +, Time Critical Operator Action +, Fire Protection Program +  and Stretch Power Uprate +
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http://pbadupws.nrc.gov/docs/ML0912/ML091280241.pdf  +
 
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