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NUREG REPORTS, RAINBOW BOOKS  and TEXT-SAFETY REPORT

Hydrogen +  and Lead +

ML20024A601 +, ML20024A601 +, ML20024A601 +, ML20024A601 +, ML20024A601 +  and ML20024A601 +

General Electric +  and Westinghouse +

NUREG/CR-2791 +, NUREG/CR-2069 +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-8588 +, 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-606 +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG-8783 +, NUREG-8313 +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, 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-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 +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, 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 +

AM +, ST +, SAP +, CP +, Emergency Plan +  and ST.esARv +

Washington +, California +, Massachusetts +, Idaho +  and New York +

Steam Generator +, Feedwater +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Decay Heat Removal +, Main Steam Line +  and Safety Relief Valve +

Safe Shutdown +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Water hammer +  and Leak Before Break +