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ML20196K180
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Category
TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT
ASME section
ASME Section III +
Accession number
ML20196K180  +
Atomic Element
Boron +, Iron +, Nitrogen +, Oxygen +, Hydrogen +  and Zinc +
CFR
10 CFR 50.59 +, 10 CFR 20.2002 +, 10 CFR 50 Appendix H +, 10 CFR 50.59#a2 +  and 10 CFR 50.59#b +
Docket
05000352  +, 05000353  +, 00352  +  and 00353  +
Drawing
SE-1-1 +
From
Exelon +, Gallagher M +  and (FORMERLY PHILADELPHIA ELECTRIC +
GE SIL
SIL 377 +
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>.
ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +, ML20196K180 +  and ML20196K180 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
Issue date
June 30, 1998  +
Manufacturer
Westronics +  and 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>.
20:50:57, 10 December 2024  +
NRC bulletin
NRC Bulletin 96-03 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +
Page count
27  +
Procedure
Emergency Operating Procedure +, ST-6-107-590-1 +, ST.4 +, SP-S-067 +  and ST-6-107-Unit +
Regulatory Guide
Regulatory Guide 1.63 +, Regulatory Guide 1.45 +  and Regulatory Guide 1.82 +
SR
SR-4.8.2.1.b +, SR-4.4.1.2.a +  and SR-4.4.6.1.4 +
SSC
114A-G-F-08 +, 114A-G-F-37 +  and 1C-X101 +
Scram
Automatic Scram +
Site
Limerick +
Site license
Limerick +
Start date
June 30, 1998  +
System
Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Residual Heat Removal Service Water +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Electrohydraulic Control +, Control Rod +, Main Steam +  and Containment Spray +
Title
Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with  +
To
Office of Information Resources Management +
Topic
Safe Shutdown +, Loop seal +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Post Accident Monitoring +, Temporary Modification +, Process Control Program +, Stress corrosion cracking +, Severe Accident Management Guideline +, Fuel cladding +, Overspeed trip +  and Simmer margin +
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http://pbadupws.nrc.gov/docs/ML2019/ML20196K180.pdf  +
 
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