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ML071030397 +
NRC Generic Letter 98-01 +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-08, Modification of Vacuum Breakers on Mark I Containments +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs +, 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 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 89-06, Task Action Item I.D.2 - Safety Parameter Display System - 10 CFR 50.54 (f) +, NRC Generic Letter 92-04, Resolution of the Issues Related to Reactor Vessel Water Level Instrumention in BWRs Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 94-02, Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in BWRs +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves +, NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +, NRC Generic Letter 2003-01, Control Room Habitability + and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +
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April 13, 2007 +
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>.
07:05:03, 15 January 2025 +
NRC Bulletin 88-04 +, NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 93-03 +, NRC Bulletin 84-02 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 80-06 +, NRC Bulletin 95-02 +, NRC Bulletin 88-10 +, NRC Bulletin 90-01 +, NRC Bulletin 88-03 +, NRC Bulletin 79-12 +, NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors + and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +
NUREG-1843, Supp 1, Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2 & 3 +, NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, NUREG-1342, Discusses New multi-plant Action MPA F-72, SPDS-Response to Generic Ltr 89-06, Initiated to Accurately Reflect Status of SPDS Issue in Sims.Procedures Should Be Followed by Affected Plants as Indicated +, 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-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +, 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-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +
151 +
TAC:MC1705 +, TAC:MB7679 +, TAC:MC3381 +, TAC:MC8826 +, TAC:MA1179 +, TAC:MC3125 +, TAC:MC3186 +, TAC:MC3392 +, TAC:MA1810 +, TAC:MB7747 +, TAC:56104 +, TAC:59072 +, TAC:00459 +, TAC:62260 +, TAC:M96135 +, TAC:M68517 +, TAC:M82687 +, TAC:M97020 +, TAC:62259 +, TAC:M93436 +, TAC:M86882 +, TAC:M93876 +, TAC:M69430 +, TAC:M75635 +, TAC:M85361 +, TAC:73852 +, TAC:60627 + and TAC:73970 +
Request +
April 13, 2007 +
Reactor Coolant System +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, HVAC +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam + and Containment Spray +
Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Probabilistic Risk Assessment +, Coatings +, Operator Manual Action +, Emergency Lighting +, Notice of Violation +, Intergranular Stress Corrosion Cracking +, Containment high range radiation monitor +, License Renewal +, Hardened vent +, Fire Protection Program +, Power Uprate +, Water hammer + and Control Room Habitability +
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