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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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Omaha Public Power District 1623 Harney Omaha Nebraska 68102 2247 402/536-4000 December 9, 1985 LIC-85-560 Mr. Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing - B Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Reference:
(1) Docket No. 50-285 (2) Fort Calhoun Station Unit No. 1 Technical Specification 3.3(2)e(i)
(3) Fort Calhoun Station Unit Nr. 1 Technical Specification 3.3(2)e(ii)
Dear Mr. Thadani:
. Steam Generator Tube Plugging The Omaha Public Power District, pursuant to Reference (2), provides this letter as a report of the number of tubes plugged in the Fort Calhoun Station steam generators during the most recent inservice in-spection conducted during the 1985 refueling and maintenance outage.
Sixteen (16) tubes were plugged in steam generator RC-2A and seventeen (17) were plugged in steam generator RC-2B.
Specific details in regard to the steam generator tube plugging will be provided in the six (6) month report required by Reference (3).
Sincerely,
'gk/c4/
R. L. Andrews Division Manager Nuclear Production RLA/AND/me l
cc: LeBoeuf, Lamb, Leiby & MacRae l
1333 New Hampshire Ave., N.W.
Washington, DC 20036 Mr. E. G. Tourigny, Project Manager Mr. P. H. Harrell, Senior Resident 8512160123 851209
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