05000237/LER-1979-031, Forwards LER 79-031/03L-0

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Forwards LER 79-031/03L-0
ML17173A904
Person / Time
Site: Dresden 
Issue date: 06/07/1979
From: Stephenson B
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A905 List:
References
79-455, NUDOCS 7906120376
Download: ML17173A904 (2)


LER-1979-031, Forwards LER 79-031/03L-0
Event date:
Report date:
2371979031R00 - NRC Website

text


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Commonwealt'9ison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR #79-455 Ja~es G. Keppler, Regional Dir~ctor June 7, 1979 Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence_ Repori- #79-31/03L Docket. #050-237 is hereby submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2.(d),

abnormal degradation of systems other than those specified in '

item B.1. e. above' designed to contain radioactive material resulting from the fission process.

nson Station Superintendent Dresden Nuclear Power Station BBS:lcg Enclosure cc:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC JUN O 8 1979 i.

(1-77)

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. ACENSEE EVENT REPORT

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LICENSEE CODE 14 15 LICENSE NUMBl:R

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60 61 DOCKET NUMBER 68 G9 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I During routine inspection, crack found on the 2Dl feedwater heater emergency spill to condenser line (2-3509A-6).

Crack located at pipe to condenser weld and continued CI:ITI LI ~~~~~~~~~~---~~~~~~--=--=-~~~~~___;~~~~~~.,--~

approximately half way around weld.

No previous leaks of.this nature have occurred.

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I Minimal safety significance since the leakage contained in the turbine building floor

, drain system.

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.8 9 BO SYSTEM CODE I Cl HI@

9 10 LE R/RO LVEIH YEAR REPORT I 7 I 9 I

  • NUMBER 21 22

CAUSE

CAUSE COMP.

VALVE CODE SUOCODE COMPONENT CODE SUS CODE SUS CODE

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11 12 13 SEQUENTIAL REPORT NO.

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- CODE I o I 3 I
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REPORT TYPE

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23 24 26 27 28 29 30 31 ACTION FUTURE.

  • EFFECT SHUTDOWN Q

ATTACHMENT NPRD-4 PRIME C.OMP.

SUPPLIER

. REVISION NO.

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T AK*EN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :;UB.

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33 34 35 36 37 40.

41 42 Li IPl2lll2l@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@

43 44 47 IJJ1J I P,recise cause unknown but probably mechanical failure assisted by long term vibration.

  • ITTIJ Cracked portion of weld removed and rewelded'. *No further corrective action* deemed necessary.

Pipe material is class 150, carbon steel with rated pressure of 150 PSI and norinally operating urider a vacuum.

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9 FACILIT?

STATUS

% POWER

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44 ACTIVITY CONTENT

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RELEASED OF RELEASE AMOUNT OF ACTIVITY [QI)~@) l:J@L...l __

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10 11 44 PEl1SONNEL EXPOSURES

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DISCOVERY DISCOVERY DESCRIPTION \\31

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  • 45 80 NUMBER

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11 12 13 PERSONNEL INJURIES "l CY NUMBEH

'oESCRIPTION 41.

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- LOSS OF OR DAMAGE TO FACILITY t;\\31

. TYPE

DESCRIPTION

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so NRC USE ONLY ISSUEDQ UESCJUPTION ~.

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