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ANSI B31.1 +  and ANSI B31.5 +

ASME Section XI +, ASME Section III +  and ASME Section VIII +

Carbon +, Hydrogen +, Zirconium +, Lead +, Sulfur +  and Tin +

10 CFR 50.54#f +  and 10 CFR 50 Appendix B +

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 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-02, Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products +  and NRC Generic Letter 91-17, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear Power Plants" +

NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +, NRC Generic Letter 1991-17 +  and NRC Generic Letter 1991-17 +

NRC Bulletin 79-14 +, NRC Bulletin 82-02 +, NRC Bulletin 74-03 +, NRC Bulletin 89-02 +, NRC Bulletin 79-07 +, NRC Bulletin 87-02 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

Information Notice 80-27 +, Information Notice 88-11 +, Information Notice 89-70 +, Information Notice 82-06 +, Information Notice 86-25 +, Information Notice 89-59 +, Information Notice 89-22 +, Information Notice 80-29 +, Information Notice 87-56 +  and Information Notice 80-36 +

NUREG/CR-3604 +, NUREG-1095 +, NUREG/CR-2467 +, NUREG/CR-2793 +, NUREG-0943 +, NUREG/CR-3853 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, 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 +  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 1991-17 +  and NRC Generic Letter 1991-17 +

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 +...

Maryland +, Washington +, California +, New York +  and Maine +

Steam Generator +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Emergency Core Cooling System +  and Control Rod +

Boric Acid +, Fitness for Duty +, Coatings +, Anchor Darling +, Nondestructive Examination +, Stress corrosion cracking +, Backfit +  and Leak-Before-Break +