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

Boron +, Nickel +, Carbon +, Sodium +  and Lead +

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.50 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 2.790 +, 10 CFR 50.55a +, 10 CFR 50.44#c3i +  and 10 CFR 50.44#c3iiB +

COR-056 +, COR 056 +  and COR-034 +

COR-056 +, COR 056 +  and COR-034 +

00352  +, 00353  +, 05000352  +  and 05000353  +

Turbine Trip +  and Reactor Trip +

GDC 56 +, GDC 31 +, GDC 32 +  and GDC 1, Quality standards and records +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 89-11, Resolution of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy" +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +, ML20247A550 +  and ML20247A550 +

IEEE 323 +  and IEEE 279 +

ML19327B856 +, ML20196D580 +, ML20207G163 +, IR 05000352/1989006 +, IR 05000352/1988021 +, 05000352/LER-1989-028, :on 890424,reactor Encl Ventilation Sys Inoperable Beyond Tech Spec Limits.Caused by Tavis Corp Providing Incorrect Info About Actions Needed to Ensure That Transmitters Operated within Required Accuracy +, 05000352/LER-1989-040, :on 890512,seismic Monitoring Sys Triaxial Response Spectrum Analyzer Printer Failed to Operate During Calibr Functional Test.Caused by Design Deficiency.Upgraded Controller Circuit Board & Printer Installed +, 05000352/LER-1989-031, :on 890505,scent of Wintergreen,Indicative of Carbon Dioxide,Sensed by Plant Operations Personnel in Main Control Room.Caused by Procedural Inadequacy in That No Guidance Existed for Response to Scent +  and ML20244A422 +

Westinghouse +, Limitorque +, Valcor +  and General Electric +

NRC Bulletin 88-05 +  and NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors +

NUREG-1371, Forwards Tech Specs,NUREG-1371,issued by NRR Re Application for Ol.W/O Stated Encl +, NUREG-0991, Advises That Rev 1 to Plant Preservice Insp Program for Reactor Coolant Pressure Boundary & for ASME Code Class 2 & 3 Sys & Components Acceptable & in Compliance W/ 10CFR50.55a(g)(2).Evaluation Included in NUREG-0991,Suppl 7 +, NUREG-1360, Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl +, NUREG-991 +  and 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 +

George Thomas +  and Michele Evans +

AM +  and RT +

Regulatory Guide 1.75 +, Regulatory Guide 1.8 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.68 +

NEDE-24011 +, NEDC-31578P +  and NEDC-31577P +

Limerick +, NPF-27 +, NPF-83 +  and NPF-84 +

Pennsylvania +, Maryland +, Washington +  and Idaho +

Reactor Coolant System +, Feedwater +, Service water +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Spray Pond +, Rod Worth Minimizer +, Rod Sequence Control System +, Control Rod +  and Low Pressure Coolant Injection +

Safe Shutdown +, Reactor Vessel Water Level +, Anticipated operational occurrence +, High Energy Line Break +, Notice of Violation +, Feedwater Heater +, Loss of Offsite Power +, Coast down +  and Affidavit +