ML17252A234

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Transmittal of Reportable Occurrence Report No. 50-249/1976-10
ML17252A234
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 07/15/1976
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS Ltr. #76-533 50-249/1976-10
Download: ML17252A234 (3)


Text

CommonweA Edison Dresden Nuclea~wer Station R.R. #1 Morris, lllinoi~ 6045~ .

Telephone 8'15/942-2920 BBS Ltr. #76-533 July 15, 1976 sEGf/V£D JUL2J1976 ~

U1'4 NUet.!A Mr. James G. Keppler, Regional Director COMM R REGULAroar lllall ISS ION Directorate of Regulatory Operations - Region III . Secuilii U. S. Nuclear Regulatory Commission ~

799 Roosevelt Road Glen Ellyn, r-llinois 60137 Enclosed please find Reportable Occurrence report number 50-249/1976-10.

This report is being submitted to your off ice in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B.

~-==--~

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  • B. B. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 7320

, LICENSEE EVENT REPORTe CONTROL BLOCK: I I I I I I CPLEAsE PRlf.IT ALL REQUIRED INFORMATION) 1 6

. LICENSEE LICENSE -EVENT NAME LICENSE NUMBER TYPE TYPE

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rn 8 RELEASED lZJ 9

OF RELEASE lKJI 10 . 11 L...;,,_

AMOUNT OF ACTIVITY

__._N."'-'-'fi_ ____.

44 45 A.Ill LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION A 7

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8 9 101010111 012 13 80 PERS'ONNEL INJURIES NUMBER DESCRIPTION 7

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80 OFFSITE CONSEQUENCES

. GE Nit 80 7 8 9 LOSS OR DAMAGE JO FACILITY TYPE DESCRIPTION

~.l.lJ NA 7 8 9 10 80 PUBLICITY 7

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[iliJ8 9 7 00 NAME: £. L. SECf<JN(.,£f<.

--------**-*\-**

EVENT DESCRIPTION (Continued)

The diaphragm acts as a seal inside the heat exchanger. Leakage was contained with-in a controlled area and was routinely processed by the radwaste system.

The cracks were ground out, and the affected area was rewelded and dye-penetrant tested. No discontinuities were noted, The heat exchanger was successfully leak-tested and was subsequently returned to service.

In ~ay, 1972, a crack was discovered and repaired at a different location in the sam~ circumferential diaphragm-to-tube sheet weld. No other failures of this nature/have occurred on the cleanup non-regenerative heat exchangers on Units 2 and 3. (50-249/1976-10)