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TEXT-SAFETY REPORT  and REFERENCE SAFETY ANALYSIS REPORT & AMENDMENTS (RSAR)

Boron +, Copper +, Hydrogen +, Zirconium +, Chloride +  and Lead +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +  and 10 CFR 50.54f +

05000601  +  and 00601  +

Turbine Trip +  and Reactor Trip +

WESTINGHOUSE ELECTRIC COMPANY +  and DIV OF CBS CORP. +

NRC Generic Letter 82-32, Draft Steam Generator Report (SAI) +, NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 82-07, Transmittal of NUREG-0909 Relative to the Ginna Tube Rupture +  and NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +

ML20084P674 +, ML20084P674 +, ML20084P674 +, ML20084P674 +, ML20084P674 +, ML20084P674 +, ML20084P674 +, ML20084P674 +, ML20084P674 +  and ML20084P674 +

4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

IEEE 384 +, IEEE 344 +, IEEE 323 +, IEEE 279 +  and IEEE 379 +

NUREG-0918 +, NUREG-744 +, 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-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-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, 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-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, 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-0517, Advises That Review of NUREG-0737 Item III-D.3.3 Re Input Radiation Monitoring Is Complete.Equipment & Procedures Described by Licensee Meet NRC Position in NUREGs 0578,0694 & 0737,per Suppl 5 to SER (NUREG-0517) +, 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 +  and NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +

Regulatory Guide 1.1 +, Regulatory Guide 1.82 +, Regulatory Guide 1.100 +, Regulatory Guide 1.26 +, Regulatory Guide 1.99 +, Regulatory Guide 1.13 +, Regulatory Guide 1.89 +, Regulatory Guide 1.79 +, Regulatory Guide 1.83 +, Regulatory Guide 1.139 +  and Regulatory Guide 1.150 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Residual Heat Removal +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Steam +, Containment Spray +  and Emergency Feedwater System +

Safe Shutdown +, Ultimate heat sink +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Emergency Lighting +, Scram Discharge Volume +, Loss of Offsite Power +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Backfit +, Overexposure +, Affidavit +, Water hammer +, Control Room Habitability +  and Spill +