ML20051D486
| ML20051D486 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/30/1982 |
| From: | Wells D DETROIT EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, EF2-58065, NUDOCS 8205140562 | |
| Download: ML20051D486 (1) | |
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|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARNRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997
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Sensors to Be Replaced at 6-month Intervals & Tested Every 30 Days to Ensure Operability ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. 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ru Mr. Jarres G. Keppler, Regional Administrator Region III U.S. Nuclear Regulatory Ccmnission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Interim Report of 10CFR50.55(e) Item on 3/4" Carbon Steel Pipe Cracking (#64)
Dear Mr. Keppler:
On April 1,1982, Project Quality Assurance's Mr. E.L. Thompson, Acting Supervisor-Construction Quality Assurance, telephoned Mr. J. Konklin of NRC-Region III, to report on a problem with 3/4" Carbon Steel Pipe Crack-ing at the Fermi 2 site.
This item deals with a length of 3/4" Carbon Steel Pipe, that cracked during a flushing operation. The vendor was contacted even though the Certified Mill Test Report shows an acceptable hydrostatic test pressure of 2,500 psi.
The vendor responded that the flaw appeared to be caused by a defective extru-sion mandrul. Investigation is continuing to determine where similar material is located. Reportability will be determined by the safety implications of the installed pipe.
Another report on this item, either interim or final, is scheduled to be sent to you on or before August 27, 1982. If you have questions concerning this matter, please contact Mr. H.A. Walker, Supervisor-Construction Quality Assurance.
Very truly yours 1
/
DAW / HAW /cp cc:
Mr. Richard DeYoung, Director Office of Inspection and Enforcement Division of Reactor Inspection Programs U.S. Nuclear Regulatory Comrnission Washington, D.C. 20555 Mr. Bruce Little, Resident Insp2ctor U.S. Nuclear Regulatory Connission 6450 North Dixie Highway Newport, Michigan 48166 5140562 820430 10 m ADOCK 0500034j g
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