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MONTHYEARML20081C2221984-03-0909 March 1984
Forwards Application for Amend to License DPR-40,revising Tech Specs to Add Limiting Conditions for Operation, Surveillance Requirements & Administrative Requirements,Per NUREG-0737
Project stage: Request
ML20091C4641984-05-22022 May 1984
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 Design
Project stage: Request
ML20133P0101985-02-0202 February 1985
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 Failure
Project stage: Other
ML20102B7041985-03-0101 March 1985
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 Comparison
Project stage: Other
ML20138F5681985-12-0909 December 1985
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 Rept
Project stage: Other
ML20138R4881985-12-17017 December 1985
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 IGSCC
Project stage: Other
ML20154H8551986-02-21021 February 1986
Special Rept on Steam Generator Denting Derived from 1985 Eddy Current Insp Data for Fort Calhoun Station
Project stage: Other
ML20154H8271986-02-21021 February 1986
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 Requirements
Project stage: Other
ML20211G3361987-02-12012 February 1987
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,Appropriate
Project stage: Approval
ML20211G3681987-02-14014 February 1987
Safety 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 Operation
Project stage: Approval
1985-02-02
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Text
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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402!536 4000 February 21, 1986 ni,- p; ;;._,_.______._h LIC-86-041 (c'
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Mr. R. D. fiart'n
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d' Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Reference:
Docket No. 50-285
Dear Mr. fiartin:
Special Report on Steam Generator Denting Derived from 1985 Eddy Current Inspection Data for the Fort Calhoun Station The Omaha Public Power District, holder of Operating License DPR-40, submits this special report pursuant to previous discussions between OPPD and the Commission concerning steam generator integrity at the Fort Calhoun Station. This report should also be used to fulfill eddy current reporting requirements as per Technical Specification 3.3(2)e(ii).
Si ncerely, 0S R. L. Andrews Division Manager Nuclear Production RLA/GSJ/1p Attachment cc:
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.
Washington, DC 20036 Mr. E. G. Tourigny, NRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector
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