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ML20056E605
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Category
SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT
ASME section
ASME Section XI +
Accession number
ML20056E605  +
Atomic Element
Nitrogen +, Oxygen +, Sodium +  and Hydrogen +
CFR
10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +
Docket
05000277  +, 05000278  +, 00277  +  and 00278  +
FR
57 FR 55587 +
From
Office of Nuclear Reactor Regulation +
Generic letter
NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +, ML20056E605 +  and ML20056E605 +
IEEE
IEEE-450 +
In package
ML20056E600 +
Issue date
August 2, 1993  +
Letter
ML20045D813 +, ML20044H167 +  and 05000277/LER-1993-012, :on 930607,discovered That Surveillance Test on Fire Protection Sys Missed on 930601.Caused by Insufficient Degree of Attention Applied by Nonlicensed Individual.Test Satisfactorily Completed +
Licensing Basis Document
Updated Final Safety Analysis Report +
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18:18:16, 17 December 2024  +
Page count
40  +
Power source
4kV +
Procedure
ST +
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ML20056E605 +
Project stage
Request  +
Report
NEDC-31336 +, NEDC-30936P +, NEDC-31366 +, NEDC-32160P +, NEDO-30883 +, NEDC-31366A +  and NEDC-31366PA +
SR
SR-4.14.D.I +
Scram
Automatic Scram +  and Manual Scram +
Site
Peach Bottom +
Site license
Peach Bottom +
Start date
August 2, 1993  +
State
Pennsylvania +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Intermediate Range Monitor +, Remote shutdown +, Main Steam Line +, Safety Relief Valve +, Control rod blade +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +
TS
TS-3.7 +, TS-3.7.A +, TS-4.7.A +, TS-4.5.D +, TS-4.5.G +, TS-1.0 +, TS-4.5.C +, TS-4.7.D +, TS-4.7.E +, TS-4.4.A +, TS-6.14 +, TS-4.7.C +, TS-4.3.C +, TS-4.3.B +, TS-4.7.B +, TS-4.9.A +, TS-4.7 +, TS-4.11.C +, TS-4.7.4 +, TS-4.5.A +, TS-4.7.8.1 +, TS-4.11.A +, TS-4.6.D +, TS-4.8.C +, TS-4.5.E +, TS-4.5.K +, TS-4.14.C +, TS-4.11.D +, TS-4.1.D +, TS-4.8.G +...
Title
Safety Evaluation Supporting Amends 179 & 182 to Licenses DPR-44 & DPR-56,respectively  +
Topic
Safe Shutdown +, Fire Barrier +, Abnormal operational transient +, Scram Discharge Volume +, Excess Flow Check Valve +, Main Steam Line Radiation Monitor +, Overtravel +, Earthquake +, Fire Protection Program +  and Grace period +
Trip
Turbine Control Valve Fast Closure +
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http://pbadupws.nrc.gov/docs/ML2005/ML20056E605.pdf  +
 
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