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TECHNICAL SPECIFICATIONS & TEST REPORTS  and TEST/INSPECTION/OPERATING PROCEDURES

ASME Section IV +  and ASME Section V +

10 CFR 50.59 +, 10 CFR 50.54f +  and 10 CFR 50.54#f +

05000423  +  and 00423  +

NORTHEAST UTILITIES SERVICE CO. +, Brothers M +, Vargas J +  and Rothen F +

NRC Generic Letter 93-06, Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" +, NRC Generic Letter 81-28, Steam Generator Overfill +, NRC Generic Letter 81-22, Engineering Evaluation of the H.B. Robinson Reactor Coolant System Leak on 1/29/81 +, NRC Generic Letter 82-11, Transmittal of NUREG-0916 Relative to the Restart of R.E. Ginna Nuclear Power Plant +, NRC Generic Letter 83-42, Clarification to GL 81-07 Regarding Response to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" +, NRC Generic Letter 83-33, NRC Positions on Certain Requirements of Appendix R to 10 CFR 50 +, NRC Generic Letter 83-32, NRC Staff Recommendations Regarding Operator Action for Reactor Trip and ATWS +, NRC Generic Letter 84-21, Long Term Low Power Operation in Pressurized Water Reactors +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 85-13, Transmittal of NUREG-1154 Regarding The Davis-Besse Loss of Main And Auxiliary Feedwater Event +, NRC Generic Letter 85-05, Inadvertent Boron Dilution Events +, NRC Generic Letter 86-16, Westinghouse ECCS Evaluation Models +, NRC Generic Letter 86-07, Transmittal of NUREG-1190 Regarding the San Onofre Unit 1 Loss of Power and Water Hammer Event +, NRC Generic Letter 88-15, Electric Power Systems - Inadequate Control Over Design Process +, NRC Generic Letter 89-22, Potential for Increased Roof Loads and Plant Area Flood Runoff Depth Due to Recent Change in Probable Maximum Precipitation Criteria Developed by the National Weather Service +, NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +, NRC Generic Letter 91-15, Operating Experience Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors +  and NRC Generic Letter 95-04, Final Disposition of the Systematic Evaluation Program Lessons-Learned Issues +

ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +, ML20116L021 +  and ML20116L021 +

Information Notice 96-06 +, Information Notice 95-35 +, Information Notice 93-31 +  and Information Notice 94-57 +

ISP +, MP-2 +, MP-3 +  and MP-1 +

Service water +  and Auxiliary Feedwater +

Temporary Modification +  and Operability Determination +