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TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT

Boron +, Iodine +, Nickel +, Carbon +, Oxygen +, Hydrogen +, Lead +  and Platinum +

BWRVIP-25 +, BWRVIP-03 +, BWRVIP-05 +, BWRVIP-06 +, BWRVIP-17 +, BWRVIP-19 +, BWRVIP-14 +, BWRVIP-07 +  and BWRVIP-08 +

10 CFR 50.59 +  and 10 CFR 50.54#F +

CR-ECH-11-00096 +  and CR-ECH-06-00097 +

SECY-95-245 +, SECY-96-134 +, SECY-88-147 +, SECY 95-059 +  and SECY-90-232 +

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 85-10, Technical Specification for Generic Letter 83-28, Items 4.3 and 4.4 +, 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 89-19, 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 89-06, 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" +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20149G316 +, ML20149G316 +, ML20149G316 +, ML20149G316 +, ML20149G316 +  and ML20149G316 +

C-14 +  and Krypton-85 +

Westinghouse +, General Electric +  and Target Rock +

Information Notice 92-81 +, Information Notice 95-03 +, Information Notice 96-34 +, Information Notice 93-17 +, Information Notice 93-34 +, Information Notice 88-28 +, Information Notice 92-85 +, Information Notice 93-53 +, Information Notice 93-83 +, Information Notice 94-38 +, Information Notice 95-42 +  and Information Notice 95-47 +

NUREG/CR-6260 +, NUREG-1341 +, NUREG/CR-5167 +, NUREG/CR-4948 +, NUREG-1544 +, NUREG/CR-4821 +, NUREG/CR-4544 +, NUREG-1401 +, NUREG/CR-4294 +, NUREG/CR-4400 +, NUREG-1332 +, NUREG/CR-5918 +, NUREG/CR-4077, Recommends Board & Industry Notification of Westinghouse Owners Group Ack of Possible Failure of Secondary O-ring Seal Matl Used in Reactor Coolant Pump Seal Assemblies. NUREG/CR-4077 Re Aecl Seal Test Program Encl +, 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-1216, Safety Evaluation Supporting Amend 16 to License NPF-35 +, 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-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-1192, Summary of Operating Reactor Events Meeting 87-37 on 871027. Viewgraphs & Summary of Reactor Scrams Encl +, NUREG/CR-6105, Forwards Preliminary Draft Version of NUREG/CR-6105, Human Factors Engineering Guidelines for Review of Advanced Alarm Sys & Draft of NUREG/CR-5908, Advanced Human Sys Interface Design Review Guideline +, 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-1352, Informs Commission of Status of Activities That NRC Performing & Has Planned to Resolve Concerns W/Performance of MOVs & Check Valves in Nuclear Power Plants +, NUREG/CR-6224, Requests That Encl Documents Be Available Through NRC PDR & Central Files.Documents Provided Background or Ref Info for Resolution of BWR Strainer Blockage Issue,As Ref by Draft NUREG/CR-6224, Parametric Study of Potential for Bwr.. +, NUREG-1474, Forwards Rept of Staff Actions Resulting from Review of Effect of Hurricane Andrew on Plant,For Review +  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 +

AM +, ES +, ST +, CH +, RT +, TP +, TOP +, IMP +  and Emergency Plan +

Regulatory Guide 1.106 +  and Regulatory Guide 1.8 +

SECY-95-245 +, SECY-96-134 +, SECY-88-147 +, SECY 95-059 +  and SECY-90-232 +

Texas +, Virginia +  and Idaho +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, 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 +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Coatings +, Operating Basis Earthquake +, Main transformer failure +, Corrosion bonding +, Scram Discharge Volume +, Stress corrosion cracking +, Severe Accident Management Guideline +, License Renewal +, Earthquake +, Commercial Grade +, Power-Operated Valves +, Turbine Missile +, Fire Protection Program +, Stolen +, Backfit +, Power Uprate +, Overexposure +, Water hammer +  and Reactive Inspection +