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ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis
Show incoming properties 
Category
License-Application for Facility Operating License (Amend/Renewal) DKT 50  and Letter type:ULNRC
ASME section
ASME Section III +, ASME Section I +  and ASME Section X +
Accession number
ML031950570  +
Agency
Environmental Protection Agency +  and Department of Natural Resources +
Atomic Element
Boron +, Iodine +, Carbon +, Hydrogen +  and Lead +
CFR
10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50.59 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50A#6 +, 10 CFR 50.36#c2ii +, 10 CFR 50.91#b1 +, 10 CFR 51.22#b +, 10 CFR 51.22#c9 +  and 10 CFR 50.92#c +
Cornerstone
Barrier Integrity +
Correspondence
ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04845 +  and ULNRC-01518 +
Docket
05000483  +  and 00483  +
Drawing
SE-01 +  and FC-FV-310 +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
AmerenUE +  and Shafer D +
General design criterion
GDC 34 +, GDC 54 +, GDC 56 +, GDC 35 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 3, Fire protection +
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ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +, ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +  and ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +
Hours
4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
IEEE
IEEE 279 +
Isotope
Kr-85 +, I-131 +  and Iodine-131 +
Issue date
June 27, 2003  +
License amendment topic
Alternate Source Term +
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>.
13:52:01, 16 January 2025  +
NUREG
NUREG/CR-0255, Forwards NUREG/CR-0255 Re Contempt Program for Predicting Containment Pressure & Temp response,NUREG/CR-0009,TID-14844 & ORNL-TM-2412,in Response to Request for Info on Containment Analysis.W/O Encls +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0409, Discusses NUREG-0409 Iodine Behavior in PWR Cooling Sys Following Postulated Steam Generator Tube Rupture Accident +
Page count
177  +
Procedure
ST +, SP +, Emergency Operating Procedure +, EP-HV-8879D +, EP-V-8879C +, EP-WHV-8880 +  and CH-8404 +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis +
Project
TAC:MB9875 +  and TAC:MB9879 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.195 +  and Regulatory Guide 1.26 +
SR
SR-3.7.5.2 +, SR-3.7.5.3 +, SR-3.7.3.1 +  and SR-3.7.3.2 +
SSC
15A-1 +, 15A-2 +, 15A-4 +, 3A-58 +, 10A-29 +, 1A6E-01 +, 54r-MA +  and T1x-5 +
Scram
Automatic Scram +
Site
Callaway +
Site license
Diablo Canyon +  and NPF-30 +
Start date
June 27, 2003  +
State
Texas +, Washington +  and Missouri +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +, Main Steam +  and Containment Spray +
TS
TS-3.7.3 +, TS-3.7 +, TS-1.1 +  and TS-5.5.5 +
Title
Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Safe Shutdown +, Stroke time +, Safe Shutdown Earthquake +, High Energy Line Break +, Feedwater Heater +, Loss of Offsite Power +, Earthquake +, Power Uprate +, Affidavit +, Loss of condenser vacuum +  and Water hammer +
Training curricula
F-delta-H +
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http://pbadupws.nrc.gov/docs/ML0319/ML031950570.pdf  +
WCAP
WCAP-10961 +, WCAP-10444-P-A +, WCAP-10266-P-A +, WCAP-9226 +, WCAP-14882-P-A +, WCAP-13451 +, WCAP-9227 +, WCAP-10080-A +, WCAP-9561-P-A +, WCAP-10062 +, WCAP-10267-A +  and WCAP-10079-PA +
Westinghouse report
WCAP-10961 +, WCAP-10444-P-A +, WCAP-10266-P-A +, WCAP-9226 +, WCAP-14882-P-A +, WCAP-13451 +, WCAP-9227 +, WCAP-10080-A +, WCAP-9561-P-A +, WCAP-10062 +, WCAP-10267-A +  and WCAP-10079-PA +
 
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