ML17252A246

Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B

ML17252A246
Person / Time
Site:	Dresden
Issue date:	11/04/1976
From:	Stephenson B B Commonwealth Edison Co
To:	Keppler J G NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)

See also: IR 05000249/2019076

Text

.**. Comrnonv.h

Edison * Dresde,1 Nuclear Power Station R.R. #i Morris, Illinois 60450 Telephone

815/942-2920

BBS Ltr. #76-775 November 4, 1976 Mr. James Keppler, Regional Director Directorate

of

Operations

-.Region III U. S. Nuclear Regulatory

Commission

799 Roosevelt

Road Glen Ellyn, Illinois 60137 Enclosed please find Reportable

Occurrence

report number 50-249/1976-23.

This report is being submitted

to your office in accordance

with the Dresden Nuclear

Station Techriical

Section 6.6.B. A n n . : . *1Y) _/) .. * -I-. .. . B. Stephensori

• tation Superintendent. . Dresden Nuclear Power Station BBS :jo Enclosure

cc: Director of Inspection

& *Enforcement . Direct'or

of Management

Information

& Program Control File/NRC

. LICENSEE EVd\JT REPOR. *. -. . * .. ' CONTROL BLOCK: I ' I *.1 1. I I (PLEASE PRll'JT ALL REQUIRED INFORMATION)

' 1 6 .* '*. LICENSEE * < NAME .@El I I I L. ID IR I s 13 I 7 8 9 ' 14 CATEGORY REPORT TYPE. LICENSE NUMBER 10101-10101010101-10101

15 25 REPORT SOURCE OOCl\ET NUM6ER * LICENSE TYPE 1!1111111111

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61 68 11 IOIOl?l71(,l

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REFUELING-

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TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80. lol31 ltSO.L..ATION'.

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• DISCOVERY

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EXPOSURES

NUMBER * * TYPE DESCRIPTION lo Io JO I : .

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INJURIES NUMBER . OESCRIPTION

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ADDITIONAL

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, . . ... .. ,. '* .. ;; . . ; ** EVENT DESCRIPTION (Continued)

the as-found leakage of 61.0 SCFH was attributed

entirely to leakage through check valve 1501-25B.

A second leak test using valves 1501-26B, i501-22B, and 1001-SB as boundaries

yielded a leakage rate of 4.2 SCFH: Since .the second test volume included the volume of the previous test, total through-leakage

for the penetration

was well under the Tech Spec limit. A similar valve on Unit-2 failed 16cal

testing in early 1975. (50-249/1976-23)

CAUSE DESCRIPTION. (Continued)

The valve was disassembled, the seat was lapped, and the packing and _Flexitallic

gasket were replaced.

Leak-rate

testing of the reassembled

valve was satisfactory.

In 1975, a test/drain

line was installed

on this penetration

which permitted

leak-rate

testing of check valve 3-1501-25B

for the first time since unit oper-ation began. Since this valve has performed*

satisfactorily

over a period of . several years, testing of this vaLve on an approximately

annual basis should permit timely identification

of a recurring

problem. * Valve 3-15.0l-25B

is a 16-inch tilting disc check valve, manufactured

by.Atwood

and Morrill Company, Inc.