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ML17334B336 +
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 2 +, 10 CFR 50.9 +, 10 CFR 50.38 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 51.22 +, 10 CFR 100.11 +, 10 CFR 50.54 +, 10 CFR 5059 +, 10 CFR 5071#e +, 10 CFR 2.714 +, 10 CFR 5023 +, 10 CFR 2.714#a1i +, 10 CFR 5092 +, 10 CFR 50.72#b2 +, 10 CFR 50.54#a3 +, 10 CFR 50.91#a +, 10 CFR 5#a92 +, 10 CFR 51.12#b +, 10 CFR 51.22#b +, 10 CFR 100.11#a3 +, 10 CFR 50.92#c +...
51 FR 7744 +, 48 FR 14870 +, 51 FR 7751 +, 51 FR 7750 +, 53 FR 45890 +, 54 FR 23319 +, 54 FR 7845 +, 54 FR 23308 +, 54 FR 1021 +, 54 FR 13762 +, 54 FR 23314 +, 54 FR 5165 +, 54 FR 21308 +, 54 FR 23316 +, 54 FR 13766 +, 52 FR 48891 +, 54 FR 23325 +, 54 FR 21311 +, 54 FR 15838 +, 54 FR 18961 +, 54 FR 21318 +, 54 FR 23306 +, 54 FR 21300 +, 50 FR 25481 +, 50 FR 20970 +, 52 FR 13333 +, 54 FR 9913 +, 54 FR 15821 +, 53 FR 40982 +, 54 FR 13759 +...
NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-27, Surveillance Intervals in Standard Technical Specifications +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping + and NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +
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>.
ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +, ML17334B336 +...
9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months) +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months) +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months) +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months) +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months) +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months) +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months) + and 0.00701 d (0.168 hours, 0.001 weeks, 2.30583e-4 months) +
December 4, 1989 +
ML031150236 +, ML17326B516 +, ML17325B253 +, ML17325B197 +, ML17325A474 +, 05000316/LER-1989-005, :on 890221,containment Type B & C Leak Rate Exceeded Limiting Condition for Operation Using Min Pathway Calculation Method,Causing Excessive Leakage in Several Valves.Valves Repaired & Retested + and ML17328A038 +
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18:33:34, 7 January 2025 +
65 +
Request +
Beaver Valley +, Millstone +, Peach Bottom +, Browns Ferry +, Salem +, Nine Mile Point +, Palisades +, Sequoyah +, Braidwood +, Brunswick +, Surry +, North Anna +, Vermont Yankee +, Ginna +, Farley +, San Onofre +, Cook +, Zion +, McGuire +, LaSalle +, NPF-51 +, DPR-51 +, NPF-73 +, DPR-19 +, DPR-25 +, NPF-52 +, NPF-35 +, DPR-5 +, DPR-21 +...
December 4, 1989 +
Ohio +, Tennessee +, Pennsylvania +, Connecticut +, Kansas +, Arizona +, Georgia +, Illinois +, Colorado +, Minnesota +, Maryland +, North Carolina +, Washington +, California +, Massachusetts +, Alabama +, Virginia +, New Jersey +, South Carolina +, New York +, Michigan +, Wisconsin +, Florida +, Louisiana +, Missouri +, Indiana +, Mississippi +, Nebraska +, Arkansas +, Vermont +...
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Control Room Emergency Ventilation +, Control Room Emergency Filtration System +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Containment Spray + and Low Pressure Coolant Injection +
TS-3.6.4.1 +, TS-3.8.1 +, TS-3.3.3.6 +, TS-3.0.4 +, TS-3.6.6.1 +, TS-3.4.4 +, TS-3.3.4 +, TS-3.6.5.1 +, TS-3.14 +, TS-4.0.5 +, TS-4.8.1.1 +, TS-4.3.1 +, TS-5.6.1 +, TS-4.1 +, TS-6.12 +, TS-5.3.1 +, TS-4.8.1 +, TS-3.2.6 +, TS-4.5.1 +, TS-4.16 +, TS-6.5.B +, TS-6.2.1 +, TS-8.13 +, TS-3.64.1 +, TS-3.68.1 +, TS-4.8.A +, TS-4.3.8 +, TS-8.5.1.8 + and TS-3.8.5.1 +
Forwards Radiological Emergency Preparedness Rept for 880823-24 Exercise.No Deficiencies noted.Twenty-one Areas Requiring Corrective Action Noted.Offsite Radiological Emergency Preparedness Adequate +
Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Offsite Dose Calculation Manual +, Fire Barrier +, Anticipated operational occurrence +, Hydrostatic +, Emergency Lighting +, Locked High Radiation Area +, Process Control Program +, Integrated leak rate test +, Operability Determination +, Pressure Boundary Leakage +, Hourly Fire Watch +, Unidentified leakage +, Overexposure +, Overspeed + and Control Room Habitability +
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