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ML20154S245 +
NRC Generic Letter 81-34, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-43, Reporting Requirements of 10 CFR 50, Sections 50.72 and 50.73, and Standard Technical Specifications +, NRC Generic Letter 83-36, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-23, Safety Evaluation of "Emergency Procedure Guidelines" +, NRC Generic Letter 84-23, Reactor Vessel Water Level Instrumentation in BWRs + and NRC Generic Letter 31-34 +
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March 24, 1986 +
B12006, Advises That 850830 Calibr Block Review Request Being Evaluated Via NRC Review of Inservice Insp & Testing Program,Per Insp 50-336/85-08.Action on Request Considered Complete +, A05377, Reaffirms Certification of Changes to Final Draft Tech Specs,Including Additions to Meteorological Monitoring Instrumentation Tables 3.3-8 & 4.3-5 & Snubber Surveillance Functional Test Requirement + and A04824, Submits ATWS Rule Schedule Required by 10CFR50.62(d),per Generic Ltr 85-06.Facilities Participating in NRC Integrated Safety Assessment Program.Justification for Absence of Schedules for Haddam Neck & Millstone Unit 1 Provided +
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03:48:00, 11 December 2024 +
NUREG-0761, Certified Minutes of ACRS Subcommittees on Site Evaluation & on Reactor Radiological Effects 810430 & 0501 Joint Meeting in Washington,Dc Re 10CFR100,10CFR20,radiation Protection Plan (NUREG-0761) & Health Physics Appraisal Plan +, NUREG-0303 +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required + and 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 +
90 +
Request +
March 24, 1986 +
Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Reactor Water Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Decay Heat Removal +, Main Steam Line +, Rod Worth Minimizer +, Main Condenser +, Control Rod + and Extraction steam +
Summary of 860312-14 Meetings W/Util in Berlin & Waterford, CT Re Actions to Resolve Isap Topics.List of Attendees & Draft Preliminary Assessment of Isap Topics Encl +
Safe Shutdown +, Reactor Vessel Water Level +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Operating Basis Earthquake +, Tornado-Generated Missile +, Tornado Missile Protection +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Exemption Request +, Earthquake +, Fuel cladding +, Biofouling +, Backfit +, Water hammer + and Control Room Habitability +
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