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 Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS Ltr. #76-775
Download: ML17252A246 (3)

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 G~ Keppler, Regional Director Directorate of R~gulatory 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 Powe~ Station Techriical ~pecifications, Section 6.6.B.

A n n.: .*1Y).. _/) ~. * -I- .

h un~ ~

. 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)

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' 1 6 LICENSEE LICENSE EVENT

• < NAME LICENSE NUMBER TYPE TYPE

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• EVENT* DATE REPORT DATE lof1 IcoN1 I I I llJ LLl 101s101~101~1~191 11 IOIOl?l71(,l .*II II 1014171(, L 7 8 57 58' 59 60 61 68 69 74 75 80 EVENT DESCRIPTION .

(filg].lD!JRtAJ.G- REFUELING- OUTAGE LDC.AL l.t:Ak-:-RATE TESTING; *LPC/ PRtrnARV I 7* 8' 9 . ' 80.

7 lol31Ei' 9ltSO.L..ATION'.

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• SYSTEM CAUSE COMPONENT COMPON!:NT - .

. CODE CODE

• COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

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. CAUSE DES.CA!PTION

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' STATUS * %.. POWER OTHER STATUS - OISCOVEAY

• DISCOVERY DESC.RIPTION EE] , 9*lHJ

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LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER *

• TYPE DESCRIPTION

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. LOSS ~F;l DAMAGE . TO FACILITY TYPE .DESCRIPTION *

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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 leak~rate 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.

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