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ML19296B575
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI N101.4-1972 +
Accession number
ML19296B575  +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Uranium +, Nickel +, Copper +, Nitrogen +, Hydrogen +  and Xenon +
CFR
10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 54 +, 10 CFR 72.212 +, 10 CFR 54.29#a +  and 10 CFR 50.71#e +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
NRC 2019-0036, 2018 Update to Final Safety Analysis Report, Appendix T, Technical Requirement Manual +  and SECY-90-343 +
Cross cutting aspect
H.2(n) +
Docket
05000266  +, 05000301  +, 00266  +  and 00301  +
Document
ML112030452 +  and ML11045159 +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Point Beach +
Fuel cladding
ZIRLO +
General design criterion
GDC 33 +, GDC 18 +, GDC 11 +, GDC 40 +, GDC 37 +, GDC 27 +, GDC 32 +, GDC 36 +, GDC 69 +, GDC 70 +, GDC 65 +, GDC 66 +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 26, Reactivity control system redundancy and capability +
Generic letter
NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 95-04, Final Disposition of the Systematic Evaluation Program Lessons-Learned Issues +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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ML19296B575 +, ML19296B575 +, ML19296B575 +, ML19296B575 +, ML19296B575 +, ML19296B575 +, ML19296B575 +, ML19296B575 +, ML19296B575 +  and ML19296B575 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
In package
ML19296B589 +
Isotope
I-131 +
Issue date
October 18, 2019  +
License amendment topic
Alternate Source Term +  and License Renewal Application +
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>.
12:39:29, 2 January 2025  +
NRC
NRC 2019-0036, 2018 Update to Final Safety Analysis Report, Appendix T, Technical Requirement Manual +
NUREG
NUREG-1839, (2:2) Section 3 - End, Safety Evaluation Report Related to the License Renewal of the Point Beach Nuclear Plant, Units 1 & 2 +
Page count
56  +
Power source
345kV +  and 4.16kV +
Project reference
TAC:MB4956 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.99 +  and Regulatory Guide 1.54 +
SECY
SECY-90-343 +
Scram
Manual Scram +
Site
Point Beach +
Start date
October 18, 2019  +
State
Wisconsin +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Moisture Separator Reheater +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.7.11 +
Title
2018 Update to Final Safety Analysis Report, Chapter 1, Introduction and Summary  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Tornado Missile +, Coatings +, Emergency Lighting +, Aging Management +, Feedwater Heater +, Loss of Offsite Power +, License Renewal +, Earthquake +, Turbine Missile +, Fuel cladding +, Power change +, Power Uprate +  and Measurement Uncertainty Recapture +
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http://pbadupws.nrc.gov/docs/ML1929/ML19296B575.pdf  +
Ultimate Heat Sink
Lake Michigan +
 
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