Browse wiki

NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

National Environmental Policy Act of 1969 +  and Atomic Energy Act of 1954 +

Copper +, Oxygen +  and Sodium +

10 CFR 50 Appendix R +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix J +, 10 CFR 72 +, 10 CFR 2.109 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 50.54#f +  and 10 CFR 50.62#c6 +

00255  +  and 05000255  +

Emergency Operations Facility +  and Technical Support Center +

Masciantonio A +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 78-02, Asymmetric Loads Background & Revised Request For Additional Information +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +

ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +, ML18057A616 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

ML18054A974 +, ML18054A696 +, 05000255/LER-1988-023, :on 881117,component Cooling Water Room Radwaste Drain Line Isolation Valve MV-RW118 Found Not Fully Closed.Caused by Inadequate post-mod Testing of Installed Chain Operator.Valve Operator Modified +, ML18053A675 +, ML18052A398 +, ML18051B238 +, 05000255/LER-1990-013, :on 900818,determined That Overtime Limit Exceeded Due to Scheduling Oversight.Shift Engineer Worked 28 H in 48 H Period.Caused by Personnel Error.Occurrence Incorporated Into Operations Training Programs +, 05000255/LER-1989-001-01, :on 890127,primary Coolant Sys Leak Rate Determination Not Completed,Per Plant Tech Specs Table 4.2.2,Item 8.Caused by in-progress Plant Derate.Leak Rate Determination Completed & Evaluation Ongoing +, 05000255/LER-1987-034, :on 871002,normal Range Gas Stack Effluent & Particulate Stack Effluent Monitors Found Inoperable Due to Low Flow Condition.Caused by Inadequate Tech Spec Procedure. Alarm Window Will Be Modified +  and ML18052B160 +

NUREG/CR-1161 +, NUREG/CR-5347 +, NUREG-0343 +, NUREG/CR-1233 +, NUREG-1233, Informs of NRC Plans to Visit Tokyo on 890920-28.Requests Meeting W/Ministry of Intl Trade & Industry on 890921 to Discuss Advanced BWR Licensing Issues & Review Status.Srp, NUREG-1233 & Questions & Discussion Topics Encl.W/O SRP +, 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-1174, Summary of CRGR Meeting 163 on 890524 Re Proposed Generic Ltr on Emergency Response Data Sys,Usi A-17 on Sys Interactions,Generic Issue A-30 on safety-related Dc Power Sys & USI A-47 on Control Sys +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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-0820, Safety Evaluation Supporting Amend 125 to License DPR-20 +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG-0569, Forwards NUREG-0569, Evaluation of Integrity of SEP Reactor Vessels, Completing Review of SEP Topic V-6.W/o Encl +, NUREG/CR-5556 +, NUREG/CR-1833, Forwards Request for Addl Info Necessary to Complete SEP Seismic Review.Info Identified as Open Items from Draft NUREG/CR-1833, Seismic Review of Palisades Nuclear Power Plant,Unit 1,As Part of Sep. W/O NUREG +, NUREG-1424, Forwards SER of Util 900122 Application Re full-term OL for Plant.Conversion of Provisional OLs Subsumed in SEP Program. Issues Releval to Provisional OL Conversions Not Covered in SEP Program,Covered in Ser.W/O Encl +, NUREG-0609, Forwards Request for Addl Info on Generic Ltr 84-04,Safety Evaluation of Westinghouse Topical Repts Dealing W/ Eliminating of Postulated Pipe Breaks in PWR Primary Main Loops. Response Requested by 840731 +, NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Emergency Operating Procedure +  and CP +

Regulatory Guide 1.97 +, Regulatory Guide 1.155 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.154 +

Maryland +, Washington +, New York +  and Michigan +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Safety Parameter Display System +, Reactor Pressure Vessel +, Standby Liquid Control +, Circulating Water System +  and Decay Heat Removal +

Safe Shutdown +, Probabilistic Risk Assessment +, Incorporated by reference +, Loss of Offsite Power +, Exemption Request +, Earthquake +, Control of Heavy Loads +, Backfit +, Leak-Before-Break +  and Leak Before Break +

Lake Michigan +  and Cooling Tower +