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Carbon +, Lead +, Silicon +  and Tin +

10 CFR 50.46 +, 10 CFR 50 +  and 10 CFR 50.54#f +

L-913 +, L-003 +  and L-817 +

05000003  +, 05000010  +, 05000029  +, 05000133  +, 05000155  +, 05000171  +, 05000206  +, 05000213  +, 05000219  +, 05000220  +, 05000237  +, 05000244  +, 05000245  +, 05000247  +, 05000249  +, 05000250  +, 05000251  +, 05000254  +, 05000255  +, 05000259  +, 05000260  +, 05000261  +, 05000263  +, 05000265  +, 05000266  +, 05000267  +, 05000269  +, 05000270  +, 05000271  +, 05000272  +...

Partlow J +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 81-35, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-34, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-23, Safety Evaluation of "Emergency Procedure Guidelines" +, NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +, NRC Generic Letter 85-09, Technical Specifications for Generic Letter 83-28, Item 4.3 +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 88-17, Loss of Decay Heat Removal +, NRC Generic Letter 88-03, Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 90-04, Request for Information on the Status of Licensee Implementation of GSIs Resolved with Imposition of Requirements or CAs +  and NRC Generic Letter 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components" +

NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +  and NRC Generic Letter 1990-04 +

L-913 +, L-003 +  and L-817 +

B058 +  and Westinghouse +

NRC Bulletin 80-14 +, NRC Bulletin 85-01 +, NRC Bulletin 82-03 +, NRC Bulletin 81-03 +, NRC Bulletin 80-17 +  and NRC Bulletin 83-02 +

NUREG/CR-5015 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0785, Forwards Draft NUREG-0785, Safety Concerns Associated W/Pipe Breaks in BWR Scram Sys. Requests Rept Re Applicability to Facility & Determination of Remedial Measures +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, NUREG-0978, Informs That CRGR Meeting 44 on 830803 Rescheduled for 830810 in Bethesda,Md.Proposed NUREG-0978 Re Generic Issue B-10, Behavior of BWR Mark III Containments, Will Be Discussed +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

NRC Generic Letter 1990-04 +, NRC Generic Letter 1990-04 +  and NRC Generic Letter 1990-04 +

Regulatory Guide 1.97 +, Regulatory Guide 1.52 +  and Regulatory Guide 1.140 +

Beaver Valley +, Millstone +, Hatch +, Monticello +, Calvert Cliffs +, Dresden +, Davis Besse +, Peach Bottom +, Browns Ferry +, Salem +, Oconee +, Mcguire +, Nine Mile Point +, Palisades +, Palo Verde +, Perry +, Indian Point +, Fermi +, Kewaunee +, Catawba +, Harris +, Wolf Creek +, Saint Lucie +, Point Beach +, Oyster Creek +, Watts Bar +, Hope Creek +, Grand Gulf +, Cooper +, Sequoyah +...

Texas +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Decay Heat Removal +  and Control Rod +

Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Biofouling +, Backfit +  and Water hammer +