05000249/LER-1980-038, Forwards LER 80-038/03L-0

Forwards LER 80-038/03L-0

ML17193A543
Person / Time
Site:	Dresden
Issue date:	11/13/1980
From:	Scott D COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17193A544	List: 05000249/LER-1980-038, Forwards LER 80-038/03L-0 05000249/LER-1980-038-03, /03L-0:on 801021,crack Was Found on Reactor Water Cleanup Heat Exchanger Equalizing Line (3-1292-2-A).Cause Unknown.Leak Was Temporarily Patched
References
80-241, NUDOCS 8011210543
Download: ML17193A543 (2)

LER-1980-038, Forwards LER 80-038/03L-0

Event date:
Report date:
2491980038R00 - NRC Website

text

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• "- *1"-,;.~--*i---e Comm.ealth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 DJS LTR l/80-241 November 13,.1980 g

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James G. Keppler, Regional Director Directorate of Regulatory Operations U.S. NuclearRegulatoryCommission 799 Roosevelt Road Region III ZZ;:ti Oen~

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Reportable Occurrence Report #80-38/03L-0 Docket #050-249 is being submitted to your off ice 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.l.e. above designed to contain radioactive material resulting from the fission process.

DJS:lg Enclosure D. J. Scott Station Superintendent Dresden Nuclear Power Station cc:

Director of Inspection & Enforcement Director of Management Information & Program Control U.S. NRC, Document Mgt. Branch File/NRC s

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LICENSEE EVENT REPORT e U.S. NUCLEAR REGULATORY COMMISSION*

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(Pl.EASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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15 LICENSE NUMBER lo I o 101 4 11 11 11 I 1 101 I I 0 25 26 LICENSE TYPE

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68 69 EVENT DATE.

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REPORT DATE

• 80 EVENT OESCRIPTION.AN.O PROBABLE CONSEQUENCES.@

[§]IJ. I During normal unit operation while performing maintenance inspections, a crack was

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found on Reactor Water Cleanup. heat exchanger equ<:lizing line (3-1292.;..2-A).

Leak I

l7r."1 located on a two inch pipe near a coupling. socket weld.

System remained operational.

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• !:Im I Safety significance minimal.since all leakage contained in Reactor Bldg. Floor Drain cmJ,__s_y_s_t_em_,_a_n_d_l_i_* n_e_i_* s_._1_o_c_a_t_e_d_o_u_t_s_i_d_e_p_r_im_a_ry_*_c_o_n_t_a_i_run_e_n_t_i_s_o_1_a_t_i_o_n_-_v_a_1_v_e_s_. _A_s_im_i_l_a_r _ __.

GJI]* I occurrenc.e* was repor.te~ on Unit 3 by R.O. ll79-8/03L-0.

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SYSTEM CODE I c1 GI@

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LEA/RO CVENT YEAR

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CAUSE

CAUSE CODE SUBCOOE COMPONENT CODE:

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11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO.

COOS I I I 0 I 3 I 8 I I......-1 I 0 13 I 23.

24 26 27 28 29 COMP.

SUBCODE

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19 REPORT TYPE

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30 VALVE su0coDE L:J@

20 l.=J 31 ACTION FUTURE EFFECT SHUTDOWN

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ATTACHMENT NPR0-4 FORMl;UB.

PRIME COMP.

SUPPLIER REVISION NO.

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32 COMPONENT

. MANUFACTURER TAKEN ACTION ON PLANT METHOD..

HOURS ~ SUBMITTEO W@~@ W@ LU I 01010101 W@

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CAUSE DESCRIPTION AND. CORRECTIVE ACTIONS @.

42 43 44 47 IJJ)) I The cause is unknown..

Leak was temporarily patched.

Final fix will include removal l"7'l."'"'1 and replacement of stnall section of pipe and rewelding the two inch pipe to. coupling.

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L.l...J..l..J No further corrective action deemed necessary.

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RELEASED OF RELEASE AMOUNT OF ACTIVITY (IE]_ l£j @* ~1---. __

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METHOD OF

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DISCOVERY DISCOVERY DESCRIPTION ~

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45 46 80 44 NA LOCATION OF RELEASE @

44 45 80 PERSONNEL EXPOSURES

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NUMBER

~TYPE~

DESCRIPTION

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11 12 13 PERSONNEL INJURIES

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• NUMBER DESCRIPTION~

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8* 9 11 12 LOSS OF OR DAMAGE TO FACILITY 143'.

TYPE

DESCRIPTION

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10 80 80 80 PUBLICITY Q\\

NRC USE ONLY ISSUEOt,;°;;\\ DESCRIPTION~

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• S.* A. Cieszkiewicz NAME OF PREPARER---------------------

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