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ML19137A134
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI N45.4 - 1972 +
ASME section
ASME Section III +, ASME Section V +  and ASME Section VIII +
Accession number
ML19137A134  +
Atomic Element
Iodine +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Lead +  and Zinc +
BWRVIP
BWRVIP-190 +
CFR
10 CFR 50.67 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.44 +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a3 +  and 10 CFR 54.4#a1 +
Control panel
9-3 +  and 9-4 +
Docket
05000298  +, 00341  +, 00333  +  and 00205  +
From
Nebraska Public Power District +
General design criterion
GDC 19, Control room +
Generic letter
NRC Generic Letter 79-46, Containment Purging and Venting During Normal Operation – Guidelines for Valve Operability +, NRC Generic Letter 84-09, Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii) +  and NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +
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ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +, ML19137A134 +  and ML19137A134 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +
IER
IER 84-20 +
In package
ML19137A206 +
Interim Staff Guidance
JLD-ISG-2013-02 +
Issue date
April 24, 2019  +
Letter
ML20072P540 +
Manufacturer
General Electric +
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>.
07:26:35, 5 January 2025  +
NUMARC
NUMARC 93-01 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +
Page count
85  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.7 +  and Regulatory Guide 1.97 +
Report
NEDO-10320 +, NEDO-30832 +, NEDO-31695 +, NEDE-21885 +  and NEDO-30382 +
SR
SR-3.6.1.1 +
Site
Cooper +
Site license
Palisades +
Start date
April 24, 2019  +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +
TS
TS-3.6.1.3 +
Title
Rev. 29 to Updated Safety Analysis Report, Section V, Containment  +
To
Office of Nuclear Reactor Regulation +
Topic
Loop seal +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Nondestructive Examination +, High Energy Line Break +, Aging Management +, Excess Flow Check Valve +, Integrated leak rate test +, License Renewal +, Fuel cladding +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML1913/ML19137A134.pdf  +
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