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ML20246E615 +
10 CFR 55 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 73.55 +, 10 CFR 73.57 +, 10 CFR 140.21 +, 10 CFR 50.55a +, 10 CFR 50.33#k1 +, 10 CFR 50.62#d +, 10 CFR 50.55a#g +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#g4 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g2 +, 10 CFR 50.55a#g3 +, 10 CFR 50.55#g2 +, 10 CFR 50.55a#n3 +, 10 CFR 50.44#c3i + and 10 CFR 50.71#e +
March 1, 1988 +
NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes +, NRC Generic Letter 85-18, Operator Licensing Examinations +, NRC Generic Letter 85-17, Availability of Supplements 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 85-15, Information on Deadlines for 10CFR50.49, "Environmental Qualification of Electric Equipment Important to Safety at Nuclear Power Plants" +, NRC Generic Letter 85-14, Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated by The Utility +, NRC Generic Letter 85-13, Transmittal of NUREG-1154 Regarding The Davis-Besse Loss of Main And Auxiliary Feedwater Event +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 85-07, Implementation of Integrated Schedules for Plant Modifications +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 86-17, Availability of NUREG-1169, "Technical Findings Related to Generic Issue C-8, BWR MSIC Leakage and Treatment Methods" +, NRC Generic Letter 86-15, Information Relating to Compliance with 10 CFR 50.49 "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants" +, NRC Generic Letter 86-14, Operator Licensing Examinations +, NRC Generic Letter 86-12, Criteria for Unique Purpose Exemption From Conversion From the Use of HEU Fuel +, NRC Generic Letter 86-11, Distribution of Products Irradiated in Research Reactors +, NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +, NRC Generic Letter 86-08, Availability of Supplement 4 to NUREG-0933, "A Prioritization of Generic Safety Issues" +, NRC Generic Letter 86-07, Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event +, NRC Generic Letter 86-04, Policy Statement On Engineering Expertise on Shift +, NRC Generic Letter 86-03, Applications for License Amendments +, NRC Generic Letter 86-02, Technical Resolution of Generic Issue B-19 - Thermal Hydraulic Stability +, NRC Generic Letter 87-16, Transmittal of NUREG-1262, "Answers to Questions on Implementation of 10 CFR 55 on Operators' Licenses" +, NRC Generic Letter 87-15, Policy Statement on Deferred Plants +, NRC Generic Letter 87-14, Operator Licensing Examinations +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +...
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April 30, 1989 +
ML20150B297 +, ML20195F882 +, ML20207P209 +, ML20236J193 +, ML20214V179 +, ML20211B709 +, ML20210N385 +, 05000352/LER-1989-017, :on 890302,drywell H Mixing Sys Low Air Flow Elements Not in Compliance W/Environ Qualification Requirements.Caused by Failure of Architect/Engineer to Transfer Info Re Revised Environ Qualification + and 05000352/LER-1986-014, :on 860227,reactor Encl Isolation Occurred W/ Actuation of Recirculation Sys & Standby Gas Treatment Sys. Caused by Break in Equipment Access Airlock.Sys Reset & HVAC Returned to Normal +
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>.
04:56:45, 2 December 2024 +
NUREG/CR-3950 +, NUREG-1262, Discusses Review of Plant Simulation Facility Development Plan,Submitted on 880526.Overall Approach of Plan Acceptable Due to Reliance on Util Simulation Facility Group Baseline Document.Issues Requiring Resolution Stated +, NUREG-1169, Notification of 870902 Meeting W/Util in Bethesda,Md to Discuss MSIV Leakage Control Sys & NUREG-1169 Applicability. Proposed Agenda Encl +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0991, Advises That Rev 1 to Plant Preservice Insp Program for Reactor Coolant Pressure Boundary & for ASME Code Class 2 & 3 Sys & Components Acceptable & in Compliance W/ 10CFR50.55a(g)(2).Evaluation Included in NUREG-0991,Suppl 7 +, NUREG-991 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl + and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Nozzle:N2 + and Nozzle:N12 +
88 +
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Request +
April 30, 1989 +
Pennsylvania +, Georgia +, Maryland +, Washington +, California +, New Jersey +, Idaho +, New York +, Vermont + and Maine +
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Reactor Enclosure Recirculation System +, Remote shutdown +, Spray Pond +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Rod Sequence Control System +, Control Rod +, Main Steam + and Extraction steam +
Safety Evaluation Report Related to the Operation of Limerick Generating Station,Units 1 and 2.Docket Nos. 50-352 and 50-353.(Philadelphia Electric Company) +
Boric Acid +, Offsite Dose Calculation Manual +, Hydrostatic +, Probabilistic Risk Assessment +, Incorporated by reference +, Feedwater Heater +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Liquid penetrant +, Scaffolding +, Thermal fatigue + and Water hammer +
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