Semantic search

Jump to navigation Jump to search
 Issue dateFromTitleProject stage
ML20081C2229 March 1984LEBOEUF
LAMB
LEIBY & MACRAE
OMAHA PUBLIC POWER DISTRICT
Forwards Application for Amend to License DPR-40,revising Tech Specs to Add Limiting Conditions for Operation, Surveillance Requirements & Administrative Requirements,Per NUREG-0737Request
ML20091C46422 May 1984William Jones
OMAHA PUBLIC POWER DISTRICT
Forwards Calculations Supporting Util Position That During Seismic Event,Attachments to Masonry Walls Would Fail Prior to Pull Out,Per 840206 Request for Addl Info Re IE Bulletin 80-11, Masonry Wall DesignRequest
ML20133P0102 February 1985OMAHA PUBLIC POWER DISTRICT
Andrews R
Requests That Requirements for mid-cycle Insp of Steam Generators Be Waived on Basis of Encl Info & Provides Info on Programs to Reduce Recurrence of IGSCC & IGSCC- Induced Steam Generator Tube FailureOther
ML20102B7041 March 1985OMAHA PUBLIC POWER DISTRICT
Andrews R
Forwards Formal Responses to NRC Questions Re 850202 Justification That mid-cycle Insp of Steam Generators Unwarranted.Response Includes Epri/Util Secondary Side Chemistry Program ComparisonOther
ML20138F5689 December 1985OMAHA PUBLIC POWER DISTRICT
Andrews R
Notifies That 16 Tubes Plugged in Steam Generator RC-2A & 17 Plugged in Generator RC-2B During Inservice Insp Conducted During 1985 Refueling & Maint Outage,Per Tech Spec 3.3(2)e(i).Details Will Be Provided in 6-month ReptOther
ML20138R48817 December 1985OMAHA PUBLIC POWER DISTRICT
Andrews R
Suppls 840619 Submittal Outlining Installation of in-line Injection of Boric Acid to Secondary Side of Facility. Maintaining Concentration of Acid Should Reduce Denting in Steam Generators & Prevent IGSCCOther
ML20154H85521 February 1986OMAHA PUBLIC POWER DISTRICTSpecial Rept on Steam Generator Denting Derived from 1985 Eddy Current Insp Data for Fort Calhoun StationOther
ML20154H82721 February 1986OMAHA PUBLIC POWER DISTRICT
Andrews R
Forwards Special Rept on Steam Generator Denting Derived from 1985 Eddy Current Insp Data for Fort Calhoun Station. Rept Should Also Be Used to Fulfill Eddy Current Reporting RequirementsOther
ML20211G33612 February 1987Office of Nuclear Reactor Regulation
Paulson W
Forwards Safety Evaluation Re 860221 Special Rept on Steam Generator Tube Denting Derived from 1985 Eddy Current Insp Data.Corrective Actions,Including Improving Secondary Chemistry Limits,AppropriateApproval
ML20211G36814 February 1987Office of Nuclear Reactor RegulationSafety Evaluation Re 860221 Special Rept on Steam Generator Tube Denting Derived from 1985 Eddy Current Insp Data. Corrective Actions Appropriate & Steam Generators Acceptable for Continued OperationApproval