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ML17286A630
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Category
TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT
ASME section
ASME Section XI +
Accession number
ML17286A630  +
Agency
Bonneville Power Administration +
Atomic Element
Iodine +, Uranium +, Iron +, Nitrogen +  and Lead +
CFR
10 CFR 50.73 +, 10 CFR 20 +, 10 CFR 50.46 +  and 10 CFR 50.59 +
Cornerstone
Emergency Preparedness +
Docket
05000397  +  and 00397  +
Document
ML14350A144 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
John Baker +  and Energy Northwest +
GE SIL
SIL 502 +
Generic letter
NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells +
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ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +, ML17286A630 +  and ML17286A630 +
Hours
0.0209 d (0.503 hours, 0.00299 weeks, 6.88705e-4 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Isotope
I-131 +
Issue date
December 31, 1990  +
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>.
10:40:44, 8 January 2025  +
NFPA
NFPA 80 +
NRC bulletin
NRC Bulletin 90-01 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
149  +
Procedure
ES +, ST +, RT +  and Emergency Operating Procedure +
Regulatory Guide
Regulatory Guide 1.108 +  and Regulatory Guide 1.16 +
SSC
07-90-031 +, 07-90-109 +, 07-90-061 +, 1V-Dl +, 07-90-274 +  and 7C-B +
Scram
Manual Scram +
Site
Columbia +
Site license
Columbia +
Start date
December 31, 1990  +
State
Washington +
System
Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Spray Pond +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +  and Main Steam +
TS
TS-3.9.9 +, TS-4.0.5 +, TS-4.8.1.1 +, TS-3.1.3.5 +, TS-4.7.7.1 +, TS-4.7.6.1 +, TS-6.9 +, TS-3.7.6.4 +, TS-3.3.7.9 +, TS-6.9.1.5 +, TS-3.7.6.2 +, TS-6.9.1.4 +, TS-4.7.6.3 +, TS-4.7.7.2 +, TS-3.7.6.5 +, TS-4.7.6.5 +  and TS-4.3.7.9 +
Title
Annual Operating Rept of WNP-2 for 1990  +
To
Martin +  and Office of Information Resources Management +
Topic
Packing leak +, Non-Destructive Examination +, Stroke time +, Nondestructive Examination +, High Energy Line Break +, Local Leak Rate Testing +, Loss of Offsite Power +, Integrated leak rate test +, Main Steam Line Radiation Monitor +, Fuel cladding +, Continuous fire watch +, Fire Protection Program +  and Overspeed +
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http://pbadupws.nrc.gov/docs/ML1728/ML17286A630.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
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