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ML25107A234
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI N18.1-1971 +, ANSI N18.7 -1976 +, ANSI N18.1 - 1971 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +
ASME code
IWA-6320 +
ASME section
ASME Section V +  and ASME Section XI +
Accession number
ML25107A234  +
CFR
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 26 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.49 +, 10 CFR 50.69 +, 10 CFR 50.46a#b +, 10 CFR 59.69 +, 10 CFR 59.69#d +, 10 CFR 50.69#b1 +, 10 CFR 50.69#f2 +, 10 CFR 50.69#d1 +, 10 CFR 50.59#2 +, 10 CFR 50.55a#g +, 10 CFR 50.55a#f +, 10 CFR 50.55a#h +  and 10 CFR 50.55#e +
Cornerstone
Emergency Preparedness +
Docket
05000263  +
Equipment trip
Reactor Trip +
From
Xcel Energy +  and Minnesota +
Generic letter
NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +  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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ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +, ML25107A234 +  and ML25107A234 +
IEEE
IEEE 279 +  and IEEE 603-1991 +
In package
ML25105A246 +
Inspection Manual Chapter
NRC Inspection Manual 7597 +, NRC Inspection Manual 7611 +  and NRC Inspection Manual 8887 +
Issue date
April 10, 2025  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
07:43:54, 21 February 2026  +
NEI
NEI 04-10, E-mail from J. Whited to D. Filchner: Susquehanna Steam Electric Station Acceptance of License Amendment Request Implementation of TSTF-425 (TAC Nos. MF5151 and MF5152) +  and NEI 00-04 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
1  +
Procedure
Emergency Operating Procedure +
Project reference
TAC:MC7505 +, TAC:53608 +, TAC:52937 +, TAC:52856 +, TAC:53691 +, TAC:54001 +, TAC:44317 +, TAC:76260 +  and TAC:53774 +
Project stage
Request  +
Report
NEDC-30844 +  and NEDC-30844A +
Site
Monticello +
Site license
Monticello +
Start date
April 10, 2025  +
State
Minnesota +
System
Service water +, High Pressure Coolant Injection +, Core Spray +  and Residual Heat Removal +
TS
TS-5.2.1.a +
Title
Rev. 42 to the Updated Final Safety Analysis Report, Chapter 13, Plant Operations  +
To
Document Control Desk +  and Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Fitness for Duty +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Cyber Security +, Incorporated by reference +, Surveillance Frequency Control Program +, Shift Technical Advisor +  and Severe Accident Management Guideline +
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http://pbadupws.nrc.gov/docs/ML2510/ML25107A234.pdf  +
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