05000249/LER-1980-006, Forwards LER 80-006/03L-0

Forwards LER 80-006/03L-0

ML17192A579
Person / Time
Site:	Dresden
Issue date:	03/13/1980
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17192A580	List: 05000249/LER-1980-006, Forwards LER 80-006/03L-0 05000249/LER-1980-006-03, /03L-0:on 800215,during Local Leak Rate Test Performed on a Feedwater Inboard Check Valve 3-220-58A Measured Leakage Exceeded Tech Specs.Caused by Worn Seat/ Disc Assembly Pins
References
80-213, NUDOCS 8003190549
Download: ML17192A579 (2)

LER-1980-006, Forwards LER 80-006/03L-0

Event date:
Report date:
2491980006R00 - NRC Website

text

Commonwea1t9C1ison Dresden* Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR /180--213 March 13, 1980 James G. Keppler, Regional Dir.ector Directorate of Regulatory Operations.. Region III U.S. Huclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report /180-06/031-0, Docket 11050-249, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2. (d),,abno.rmal de-gradation of systems othei:: than those specified in item B.1.e.

. above designed.to contain radioactive material resulting from the fission proce'ss.

BBS:lcg Eric lo sure

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B. ~t~~~,~

Station Superintendent Dresden Nuclear Power Station cc:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

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• LICENSEE EVENT REPORT

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9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58

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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80

=-EVENT DESCRIPTION Af'o'.'D PROBABLE CONSEQUENCES@

2m I During Unit 3 refueling outage, a LLRT was performed on "A" feedwater inbOardcheck

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I valve 3-220-58A.

The measured leakage was 1,104.51 SCFH, which exceeded the limit

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I for a single isolation valve (29.38 SCFH, Tech. Spec. 4.7.A).

This was of minimal

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£ITJ 8 9 SYSTEM CODE is IA I@

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CAUSE

CAUSE

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COMP.

CODE SUBCODE COMPONENT CODE SUBCODE L!J@ ~@) /VIA/LIV/E/X/@ ~@

11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT VALVE SUBCODE L~@

20

~-.. LEA/RO LVENTYEAR REPORT NO.

CODE TYPE

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REPORT I 8 I 0 I I

I I 0 I 0 I 6 I I /I I 0 I 3 I w

I I NUMBER 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE TAKEN ACTION EFFECT SHUTDOWN

~ ATTACHMENT NPRD-4 PRIME COMP.

80 REVISION NO.

LQJ 32 COMPONENT MANUFACTURER ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB.

SUPPLIER

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L!J@ LU 33 34 35 36 37 40 41 42 43 I c 16 16 IS I@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

44 47

~I Excessive leakage through feedwater check valve 3-220-58A was due to worn seat/disc assembly pins, which prevent proper alignment of the disc to the seat.

The seat/disc

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assembly was replaced and the valve retested.

Leakage was reduced to 0.520 SCFH,

Im *I well below Tech. Spec. limits.* The replacement assembly pins. and bushings are made*

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I from a hardened alloy.

No further corrective action deemed necessary.

8 9

FACILITY STATUS

% POWER OTHER STATUS Im l..!!J@ I 0 I 0 I 0 lI..... _ _;,.N""-'/ A _____.....

8 9

10 12 11 44 ACTIVITY CONTENT

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>;-r;"'lRELEASED OF RELEASE AMOUNT OF ACTIVITY e

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W@ UJI N/A 8

9 10 11 44 PERSONNEL EXPOSURES

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METHOD OF DISCOVERY DISCOVERY DESCRIPTION W@l Local Leak Rate Test 45 46 LOCATION OF RELEASE @

NLA 45 I*

80 80 I

80 NUMBER

(:;":;\\TYPE

DESCRIPTION

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11 12 13 80 NUMBER DESCRIPTION 41 PERSONNEL INJURIES

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3:0 I 0 I 0 I 0 l@L-.. _ ___:N;;.:..,.:.;.A..,..., -----------------------....;....,...-----'

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11

. 12 80 LOSS OF OR DAMAGE TO FACILITY t4:;\\

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TYPE

DESCRIPTION

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W@

N/A e 9 10 80 PUBLICITY

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NRC USE ONLY ISSUE Dr,;:;\\ DESCRIPTION~

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