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ML030760550
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Category
Report  and Technical
ANSI code
ANSI/ANS-5.1-1979 +
ASME section
ASME Section XI +, ASME Section III +, ASME Section IX +  and ASME Section II +
Accession number
ML030760550  +
Atomic Element
Boron +, Cobalt +, Nickel +, Copper +, Nitrogen +, Carbon +  and Lead +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.62 +  and 10 CFR 50.55a +
Cross cutting aspect
P.5(o) +
Design basis document
DBD-01 +, DBD-06 +, DBD-12 +  and DBD-16 +
Docket
05000266  +  and 05000301  +
Drawing
FE-4014 +, SE-CPS-34 +, SE-CPS-527 +  and FP-3771 +
Equipment trip
Turbine Trip +  and Reactor Trip +
FOIA
FOIA/PA-2003-0094 +
From
Westinghouse Electric Corp +
Generic letter
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 81-21, Natural Circulation Cooldown +, NRC Generic Letter 81-14, Seismic Qualifications for Auxiliary Feedwater Systems +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" +, NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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ML030760550 +, ML030760550 +, ML030760550 +, ML030760550 +, ML030760550 +, ML030760550 +, ML030760550 +, ML030760550 +, ML030760550 +  and ML030760550 +
Hours
5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 6.944444e-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months)  +  and 4.050926e-4 d (0.00972 hours, 5.787037e-5 weeks, 1.33175e-5 months)  +
Issue date
June 7, 2002  +
Manufacturer
Westinghouse +, Foxboro +  and Conval +
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>.
16:50:26, 16 January 2025  +
NRC bulletin
NRC Bulletin 80-04 +, NRC Bulletin 88-04 +, NRC Bulletin 79-14 +, NRC Bulletin 85-01 +  and NRC Bulletin 85-03 +
NRC information notice
Information Notice 84-06 +  and Information Notice 93-12 +
NUREG
NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Operating procedure
OP-7A +  and OP-13A +
Page count
160  +
Power source
345kV +
Procedure
AOP +, EOP-3 +, EOP-1 +, EOP-2 +, EOP-0 +, Emergency Operating Procedure +, Emergency Plan +, AOP-9A +, EOP-0.1 +, AOP-10A +, AOP-5B +, AOP-10B +, EOP-1.2 +, EOP-3.1 +, AOP-18B +, AOP-2C +, AOP-0.0 +, EOP-3.2 +, EOP-3.3 +, AOP-0.1 +  and AOP-1C +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +
SER
SER 50-84 +
SOER
SOER 85-5 +, SOER 86-01 +, SOER 86-03 +  and SOER 84-03 +
SSC
1P-29 +, 2P-29 +, 2HX-1A +, 1AF-4002 +, 2AF-4002 +, 1MS-2082 +, 2AF-108 +, 1FE-4037 +, 1P-029-T +, 2P-029 +, 2P-29-T +, 2HX-1B +, 1P-29-T +, 2MS-2019 +, 2MS-2020 +, 2AF-4000 +, 2AF-4001 +, 2AF-107 +, 2C173B-F +, 2MS-2082 +, 1AF-4000 +, 1AF-4001 +, 2P-029-T +, 1HX-1A +, 1HX-1B +, 07-84-270 +, 07-91-220 +, 07-01-124 +, 1MS-2019 +, 1C171B-F +...
Scram
Manual Scram +
Site
Point Beach +
Site license
DPR-24 +  and DPR-27 +
Start date
June 7, 2002  +
State
Michigan +  and Wisconsin +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Turbine +, Residual Heat Removal +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Auxiliary Feed Water +, Main Steam +  and Emergency Feedwater System +
TS
TS-3.3.2 +  and TS-5.5.7 +
Title
DBD-01, Auxiliary Feedwater System Design Basis Document, Revision 2, Section 3.4.1 - Attachment B, Page B-2  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, High winds +, Mission time +, Stroke time +, Internal Flooding +, Hydrostatic +, Anchor Darling +, High Energy Line Break +, Loss of Offsite Power +, Exemption Request +, Earthquake +, Fire Protection Program +, Overspeed trip +, Overspeed +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML0307/ML030760550.pdf  +
WCAP
WCAP-7306 +, WCAP-7769 +, WCAP-8404 +, WCAP-7451 +, WCAP-8113 +  and WCAP-12327 +
Westinghouse report
WCAP-7306 +, WCAP-7769 +, WCAP-8404 +, WCAP-7451 +, WCAP-8113 +  and WCAP-12327 +
 
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