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

Copper +, Hydrogen +, Chloride +  and Lead +

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 2 +, 10 CFR 73 +, 10 CFR 50 Appendix E +, 10 CFR 50.47#b +, 10 CFR 50.47#a2 +  and 10 CFR 50.42#a2 +

00373  +, 05000373  +, 05000374  +  and 00374  +

Technical Support Center +, Emergency Operations Facility +  and Emergency Facility +

NRC Generic Letter 81-22, Engineering Evaluation of the H.B. Robinson Reactor Coolant System Leak on 1/29/81 +, NRC Generic Letter 81-18, BWR Scram Discharge System-Clarification of Diverse Instrumentation Requirements +, NRC Generic Letter 81-06, Periodic Updating of Final Safety Analysis Reports (FSARS) +, NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +, NRC Generic Letter 81-03, Implementation of NUREG-0313,Technical Report on Material Selection & Processing GL for BWR Coolant Press Boundary Piping +  and NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel +

ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +, ML20005A931 +...

ML19347F581 +, ML19343D410 +, ML19351F654 +, ML19345H441 +, ML20003H565 +, ML20076B455 +, IR 05000373/1981007 +, IR 05000373/1981018 +, IR 05000373/1981013 +, ML19338G223 +, ML17252A672 +, ML17053C239 +, ML17193B275 +, ML17193B358 +  and ML17193B277 +

NUREG-519 +, NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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-0787, Safety Evaluation Report Related to the Operation of Waterford Steam Electric Station, Unit 3 (Redacted) +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0152, Comments on Pressure Interlocks on Valves Interfacing Between Low Pressure ECCS & Reactor Pressure Vessel. Redundant Protection Against Overpressurization of Low Pressure Sys Should Be Provided,Per NUREG-0152 +, 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 +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

ST +, RT +  and TOP +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.101 +, Regulatory Guide 1.8 +, Regulatory Guide 1.23 +, Regulatory Guide 1.99 +, Regulatory Guide 1.104 +  and Regulatory Guide 1.13 +

Illinois +, Washington +, Idaho +, Wisconsin +  and Iowa +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Reactor Water Cleanup +, Automatic Depressurization System +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Rod Worth Minimizer +, Rod Sequence Control System +, Control Rod +, Main Steam +  and Low Pressure Coolant Injection +

Safe Shutdown +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Emergency Lighting +, High Energy Line Break +, Scram Discharge Volume +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Core Exit Thermocouple +, Siren +  and Water rod +