ML17252B491

LER 78-046/03L-0 for Dresden, Unit 2 Re Drywell Inspection Was Made After Observing Increased Leakage Into Equipment and Floor Drain Sumps

ML17252B491
Person / Time
Site:	Dresden
Issue date:	09/11/1978
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR 78-1236 LER 78-046/03L-0
Download: ML17252B491 (2)

Text

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e Comn9wealth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 f"'.

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~...: -;:~ C:J BBS Ltr, #78-1236 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL

• 60137 Reportable Occurrence Report lt78-046/03L-0, Docket 11050-237 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 speci'fied in i tern B. 1. e. designed to contain

• radioactive mater.i,al resulting frol!I the fission process.

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Dresden BBS/deb Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC 7E: 1500286 81918

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NRC FORM 366 . U'. S. NUCLEAR REGULATORY COMMISSION* .

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• U(:ENS~E .EVENT REPOR * .

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• DOCKET NUMBER

• 68 . 69 . EVENT OATE  ;*,. 75 REPORT DATE 80 EVENT.DESCRIPTION AND PROBABLE CONSEQUENCES@ * . * **

• J During normal unit startup, a drywell inspection was ma.de after observi~g increased* I

'[2))] I leakage inter equipment and floor drai.n sumps. Two cracked socket welds. were fourid Till] I on 2B tecirculat+/-*on pump suction bowl '2." drain line, downstream of manual isolation

[II)) I valve 2-220-63B. This degradation of the primary system resulted in leakage less thanj

• !II§] I T.S.3*6.D limit. Therefore, event *had minimal safety significance: Similar event. .I III2J *I reported by RO. US0-'23 7_/_1_9_7.....;4-"--7_3_~---"--'--'-------------~-'----------'

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SEQUENTIAL OCCURRENCE REPORT* REVISION

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ACTION FUTURE EFFECT SHUTDOWN .*. ~ ATTACHMENT NPR0-4 . PRIME COMP.

• COMPONENT TAKEN ACTION ON PLANT METHOD HOURS \!3J SUBMITTED FORM 5UB. SUPPLIER MANUFACTURER*

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

.*.DJ)) I The two cracked welds were ground out* The joints had been improperly fitted with the 1*

• ITJTI I pipe end positioned flush against the socket bottom. A gap is required between the I.

.. [JJil I pipe end and socket. bottom tci prevent overs tressing the weld due to t.hermal cycling.

O:I~:J I The line was repaired. using the appropriate. welding. procedure.* No additional action

• . [ill] required

• .7 . 8 *9 . 80

. FACILITY STATUS  % POWER OTHER STATUS. @ METHOD OF DISCOVERY DISCOVERY DESCRIPTION

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