ML20070R964

Interim Deficiency Rept Re Missing Swagelock Fittings in Reactor Vessel.Initially Reported on 821229.Missing Swagelock Caps Will Be Replaced & Remaining Caps Tightened & Tackwelded to Prevent Loosening.Next Rept Due by 830527

ML20070R964
Person / Time
Site:	Fermi
Issue date:	01/27/1983
From:	Wells D DETROIT EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
10CFR-050.55E, 10CFR-50.55E, EF2-61531, EF2-61531.55E, NUDOCS 8302040116
Download: ML20070R964 (2)

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January 27, 1983 EF2-61531 Mr. James G. Keppler, Regional Admildstrator Region III U.S. Nuclear Regulatory Ccmnission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Report of Potential 10CFR50.55(e) Item on Missing Swagelock Fit-tings in Reactor Vessel (#86)

Dear Mr. Keppler:

On December 29, 1982, Detroit Edison's Mr. D. Ferencz, Acting Supervisor -

Construction Quality Assurance telephoned Mr. P. Pelke of NRC Region III to report on a potential problem with missing Swagelock fittings in the Reactor Vessel at the Fermi 2 site.

This probim was discovered during post test inspection. Three (3) Swage-lock fittings (3/8" Stainless Steel) became detached frm the Reactor Vocaal steam separator during the Flow Induced Vibration Test. Six (6) other fit-tings were found to be loose. The three (3) missing fittings and six (6) icose fittings are part of instrument lines connected to the steam separator

. standpipes.

Information available discloses that the original design called for the instrurrentation to be used for monitoring the steam. However, the original methods to nonitor the steam have changed, and there was an oversight to provide necessary action to assure the fittings were secured.

To correct the condition, the missing swagelock caps will be replaced, all remaining caps will be tightened and tackwelded to prevent further loosen-ing. One missing cap was found in the guide tubes. Efforts are underway to locate the rmaining two (2) caps. A lost parts analysis to justify that the missing fittings will not affect the safety of the plant (provided they are not introduced into the CRD housing and guide tube before the CRD drives and blades are installed) is forthcoming.

Another report on this its , either interim or final, is scheduled to be sent on or before May 27, 1983. If you have questions concerning this mat-ter, please contact Mr. G.M. Trrhey, Assistant Director - Project Quality Assurance.

Very truly yours, e e l

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DAW /DF/AT/pn 8302040116 830127 PDR ADCCK 05000341 0 PDR JAN 31 1983'

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r Mr. James G. Keppler, Regional Administrator January 27, 1983 Page Two EF2-61531 cc: Mr. Richard DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Cmmission Washington, D.C. 20555 Mr. Bruce Little, Senior Resident Inspector U.S. Nuclear Regulatc'y Cmmission 6450 North Dixie Highway Newport, Michigan 48166 1

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