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ML20059F960 +
10 CFR 50 + and 10 CFR 50.54#F +
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-22, Potential for Increased Roof Loads and Plant Area Flood Runoff Depth Due to Recent Change in Probable Maximum Precipitation Criteria Developed by the National Weather Service +, 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) +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-11, Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy" +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 91-13, Request for Info Related to the Resolution of GI 130, "Essential Service Water System Failures at Multi-Unit Sites" +, NRC Generic Letter 91-11, Resolution of Generic Issues 48, "LCOs for Class 1E Vital Instrument Buses," and 49, "Interlocks and LCOs for Class 1E Tie Breakers," Pursuant to 10 CFR 50.54 +, NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 92-02, Resolution of Generic Issue 79, "Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown" + and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +
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October 31, 1993 +
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21:17:31, 26 May 2025 +
NUREG-1341 +, NUREG-1273 +, NUREG/CR-5745 +, NUREG/CR-5744 +, NUREG/CR-5604 +, NUREG/CR-5167 +, NUREG/CR-5659 +, NUREG/CR-4948 +, NUREG/CR-5747 +, NUREG/CR-5787 +, NUREG/CR-4821 +, NUREG/CR-5078 +, NUREG/CR-6084 +, NUREG/CR-5458 +, NUREG/CR-4544 +, NUREG-1401 +, NUREG/CR-4294 +, NUREG/CR-4400 +, NUREG/CR-5669 +, NUREG/CR-5439 +, NUREG/CR-4643 +, NUREG/CR-5918 +, NUREG-1289, Submits Revised Agenda for CRGR Meeting 141 on 880714 in Bethesda,Md.Items for Review Include Proposed Generic Ltr on Instrument Air Problems & Proposed Draft Rule to Require College Degrees for Senior Reactor Operators +, NUREG-0667, 06-10-80 Report on NUREG-0667 Transient Response of Babcock - Wilcox-Designed Reactors +, NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-1461, Discusses Resolution of GI 153 Re Loss of Essential Svc Water in Lwrs.Insights from Study Will Be Informative to on-going Programs & Will Be Published as NUREG-1461 +...
121 +
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October 31, 1993 +
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve + and Control Rod +
Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Tornado Missile +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Scram Discharge Volume +, Stress corrosion cracking +, Excess Flow Check Valve +, Earthquake +, Power-Operated Valves +, Turbine Missile +, Backfit +, Manual Operator Action +, Water hammer + and Control Room Habitability +
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