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ML17158B940
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Category
Inspection Report, NRC-GENERATED  and TEXT-INSPECTION & AUDIT & I&E CIRCULARS
ANSI code
ANSI B31.1 +
ASME section
ASME Section IX +  and ASME Section III +
Accession number
ML17158B940  +
Atomic Element
Boron +, Iodine +, Oxygen +, Sodium +  and Tin +
CFR
10 CFR 50.73 +, 10 CFR 19.11 +, 10 CFR 50.54 +, 10 CFR 50 Appendix B Criterion XVI +  and 10 CFR 50.54k +
Code case
ASME Code Case N-416-1 +
Cornerstone
Emergency Preparedness +
Docket
05000387  +, 05000388  +, 00387  +  and 00388  +
Drawing
SE-030-A09 +  and SE-104-103 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) +
Generic letter
NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +
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ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +, ML17158B940 +  and ML17158B940 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
In package
ML17158B938 +
Issue date
January 29, 1997  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
00:30:35, 9 January 2025  +
NUREG
NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
69  +
Power source
4.16kV +
Procedure
TP-150-018 +  and SP-DCB-201-6 +
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.
ML17158B940 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.33 +  and Regulatory Guide 1.84 +
SSC
2A203-04 +
See also
IR 05000387/1996013 +
Site
Susquehanna +
Site license
Susquehanna +
Start date
January 29, 1997  +
State
Pennsylvania +, Maryland +, New Jersey +  and Florida +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Main Steam Line +, Control Rod +  and Containment Spray +
TS
TS-3.5.1 +, TS-3.7.7 +, TS-3.6.1 +, TS-3.1.3.1 +, TS-6.2.2 +, TS-6.8.1 +  and TS-3.1.3.5 +
Title
Insp Repts 50-387/96-13 & 50-388/96-13 on 961203-970113. Violations Noted.Major Areas Inspected:Operations, Engineering,Maint & Plant Support  +
Topic
Safe Shutdown Earthquake +, Anchor Darling +, Squib +, High Energy Line Break +, Notice of Violation +, Operability Determination +, Fire Watch +, Grace period +, Power Uprate +, Failure to Scram +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1715/ML17158B940.pdf  +
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