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MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)

Boron +  and Lead +

10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 2.202 +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50.54#a +, 10 CFR 50.54#F +, 10 CFR 50.34#f +, 10 CFR 50.54#O +  and 10 CFR 50.71#e +

NRC (Affiliation Not Assigned) +  and Wen P +

GDC 50 +, GDC 10 +, GDC 55 +, GDC 61 +, GDC 35 +, GDC 60 +, GDC 13 +, GDC 28 +, GDC 27 +  and GDC 2, Design bases for protection against natural phenomena +

NRC Generic Letter 81-14, Seismic Qualifications for Auxiliary Feedwater Systems +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 91-06, Resolution of Generic Issue A-30, "Adequacy of Safety-Related DC Power Supplies," Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 93-04, Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +, NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML20217Q140 +, ML20217Q140 +, ML20217Q140 +, ML20217Q140 +, ML20217Q140 +, ML20217Q140 +  and ML20217Q140 +

Westinghouse +  and Valcor +

NEI 96-07 +  and NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +

NRC Bulletin 80-04 +, NRC Bulletin 88-04 +, NRC Bulletin 80-11 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 80-07 +, NRC Bulletin 88-11 +, NRC Bulletin 88-08 +, NRC Bulletin 79-07 +, NRC Bulletin 80-18 +, NRC Bulletin 85-03 +, NRC Bulletin 88-02 +, NRC Bulletin 79-21 +, NRC Bulletin 80-17 +, NRC Bulletin 79-12 +, NRC Bulletin 90-02 +, NRC Bulletin 89-03 +, NRC Bulletin 80-16 +, NRC Bulletin 83-07 +, NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +  and NRC Bulletin 88-07, Power Oscillations in Boiling Water Reactors +

Nureg-0737 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Jenny Weil +, Brian Holian +, Frank Akstulewicz +  and Ralph Beedle +

Pennsylvania +, Maryland +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Main Steam Line +  and Control Rod +

NRC (Affiliation Not Assigned) +  and Essig T +

Safe Shutdown +, Shutdown Margin +, Reactor Vessel Water Level +, Enforcement Discretion +, Intergranular Stress Corrosion Cracking +, Power Uprate +, Subsequent actuation +  and Loss of condenser vacuum +