ML17252B513

LER 77-039/03L-0 for Dresden, Unit 2 Re a Gasket Failure Was Found on Torus Drain Flange 313A Which Degraded the Primary Containment Boundary

ML17252B513
Person / Time
Site:	Dresden
Issue date:	10/14/1977
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR 959-77 LER 77-039/03L-0
Download: ML17252B513 (2)

Text

Commonweal18dison ff>-o<'~

Dresden Nuclear P~ Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 REGlJl.Am~v DOCKET fllf COPY.

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October 14, 1977 BBS LTR 11959- 77 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commi~sion 799 Roosevelt Road Glen Ellyn, IL_ 60137 Reportable Occurrence ~1'.*Interim Report" 77-039/03L-0 is hereby submitted to. your office in acco~dance with Dresden Nuclear Power Station Techni-cal Specification*6.6.B.2.d,, abIJ.ormal degradation of -systems other than those specified in Technical Specification B.l.e. designed to contain radioactive material resulting_from the fission process.

son Station Superintendent Dresden Nuclear Power Stati~n BBSrdlz Enclosure

-cc: Director ot Inspection* & Enforcement Director -of Management Information & Program Control File/NRC 1'

I OCT 1 7 1977

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~ ... - L-NSEE EVENT REPORT

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C-;JNfROL BLOCK: ._I_,___..__..._~__...___,I G) * (PLEASE PRINT OR TYPE All REQUIRED INFORMATION) 1 6 E  ! I I L I D I R I s I 2 101 OI OI - I o I o I o I a I a I -: .I O I o 101 4 I 1 I 1 I 1 I 1 I©I I I G) -.

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9 LICENSEE CODE 14 15 LICENSE NUMBER

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• 1---1--1--1--18-------- ---~f 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO -

EVENT DESCRIPTION ~ND PROBABLE CONSEQUENCES@*

IIJ-+-~Dur-ing *testing required by LLRT Procedure DTS 1600-15 a gasket failure was found on mJ I torus drain flange 313A which degraded the primary* containment*ba~nda-ri1; CfieaStfre<;l*

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~ I public health or safety since the redundant outer gasket was leaktight. There are no

)))) I previous events of a similar nature at this facility. I 0 j a I 80 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE ill] I SjAI@ UJ@ UJ@ Ip IE I N I Ei/:I T IE 1@ L21 L~@

8* 9 10 11 12 13 . ' 18 19 20 e LE R/RO REPORT NUMBER CVI 7 I 7 I ENT YEAR L=.l SEQUENTIAL REPORT NO.

I 0 I3 I 9 I OCCURRENCE CODE I oI 31 REPORT TYPE L1J L=:J REVISION NO.

L£.J 21 22 23 - 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN r:;::;.. ATTACHMENT NPR0-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 0 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~@~@) ~@ W I 01 01 01 ol ~@ W@ ~ I 2 I 91 91 91@

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @

J)) I The cause of the failure is unknown at this time. Investigation of the event has been!

delayed during torus cleaning which is currently in progress. A supplemental report will be submitted by _December 15, 1977. I Till8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION @

TIJ ~ I 01 01 01@ I.....___N_A_ __

~'46 Local Leak Rate Iest 8 9 10 12 1'.l 44 45 BO Al'.;TIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @

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@ LlJ@I 10 11 NA 44 45 .

NA *I 80 PERSONNEL EXPOSURES r::;::..

NUMBER r:;-;,. TYPE DESCRIPTION TIJ8 jOIO joj'31~@).__~~~~~~~~~~---N_A~~~~~~~~~~~~--'

9 11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCRIPTION6 li] Oj Oj ol@).__~~~~~~~~~~~~~-N_A~~~~~~~~~~~~---1 8 9 11 12 - 80 LOSS OF OR DAMAGE TO FACILITY 143' TYPE DESCRIPTION \::::,1 li]~@-_ NA 8 91 ~O-!~~~~~~~~~~~~~~~~~-~~~~~-~~~~~~~~~~~~~~~~~--'BO

• PUBLICITY (.';;\

ISSUE Of,;";\ DESCRIPTION NRC USE ONLY .,

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l 2 10 6B 69 80 ;:;;

R~ndolph c, Weidner 265 0

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