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ML17285A313
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Category
TEXT-SAFETY REPORT  and ANNUAL OPERATING REPORT
ASME section
ASME Section XI +
Accession number
ML17285A313  +
Agency
Bonneville Power Administration +
Atomic Element
Iodine +, Nitrogen +, Carbon +, Lead +, Aluminum +  and Tin +
CFR
10 CFR 50.73 +, 10 CFR 21 +, 10 CFR 50.59 +, 10 CFR 50.61 +  and 10 CFR 50.62 +
Control rod
Control rod 46-07 +
Docket
05000397  +  and 00397  +
Equipment trip
Reactor Trip +
From
Energy Northwest +  and Powers C +
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ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +, ML17285A313 +  and ML17285A313 +
Hours
5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Isotope
U-235 +  and I-131 +
Issue date
December 31, 1988  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +  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>.
10:59:04, 8 January 2025  +
NRC bulletin
NRC Bulletin 88-01 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
99  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.108 +
SSC
1O-1 +  and 1O-4 +
Scram
Manual Scram +
Site
Columbia +
Site license
Columbia +
Start date
December 31, 1988  +
State
Washington +
System
Steam Generator +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Control Room Emergency Ventilation +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Moisture Separator Reheater +, Main Condenser +, Control Rod +, Main Steam +  and Extraction steam +
TS
TS-4.8.1.1 +  and TS-6.9 +
Test
Post maintenance test +
Title
Annual Operating Rept 1988  +
To
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) +  and Martin J +
Topic
Hot Short +, Safe Shutdown +, Unanalyzed Condition +, Stroke time +, Safe Shutdown Earthquake +, High Energy Line Break +, Notice of Violation +, Feedwater Heater +, Scram Discharge Volume +, Stress corrosion cracking +, Loss of Offsite Power +, Pressure Boundary Leakage +, Fire Protection Program +, Power change +, Unidentified leakage +, Overspeed +  and Spent fuel rack +
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http://pbadupws.nrc.gov/docs/ML1728/ML17285A313.pdf  +
 
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