05000263/LER-1980-018-03, /03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure

/03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure

ML112900722
Person / Time
Site:	Monticello
Issue date:	05/09/1980
From:	Hammer S Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900723	List: 05000263/LER-1980-018, Forwards LER 80-018/03L-0 05000263/LER-1980-018-03, /03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure
References
LER-80-018-03L, LER-80-18-3L, NUDOCS 8005150483
Download: ML112900722 (3)

LER-1980-018, /03L-0:on 800411,during Routine Operator Insp, Attachment Weld of Ripple to Level Switch Float Chamber Assembly on Moisture Separator Level Switch LS-1188 Found Cracked.Caused by Improper Weld Procedure

Event date:
Report date:
2631980018R03 - NRC Website

text

REGULATORY *ORMATION DISTRIBUTION SYOM (RIDS)

ACCESSION NBR:8005150483 DOCDATE: 80/05/09 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION HAMMERS,J.

Nobthern States Power C4..

RECIP.NAME RECIPIENT AFFILI TION Region 3, Chicago, Office of the Director

SUBJECT:

DOCKET #

05000263 LER 80-018/03L*O;on 800411,during routine operator insp, attachment weld of ripple to level switch float chymber assembly on moisture'separator level switch LS-1188 found crackedCauded by improper weld proceduree DISTRIBUTION CODE: A002S, COPIES RECEIVED;LTR.LENCL.j SIZE;..

Lt.

TITLE: Incident Reports NOTES: --------

RECIPIENT ID CODE/NAME ACTION; 05 BC OR&

'3 INTERNAL: 0 EG F 14 TA/EDO 16 EEB 18 PLANT SYS OR 20 AD PLANT SYS 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR 29 AUX SYS BR AEOD DOUG MAY-TERA JORDANE,/IE EXTERNAL:

03 LPDR 29 ACRS COPIES LTTR ENCL 4

4 1

2 1

1 1

1I 1

1 1I 1

10 1

1 1

16 1

2 to 1 1

1 1

1 1

1 1

16 RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS AD/ORP-DOR BERLINGER,C.

HANAUER,$.

04 NSIC COPIES LTTR ENCL 1

3 3 1 1

1 1

1 1

1 3

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1 MAY 19 1980 TOTAL NUMBER OF COPIES REQUIRED: LTTR 61 ENCL 61

0 0

NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 May 9, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Moisture Separator Level Switch Fitting Crack The Licensee Event Report for this occurrence is reproduced on the back of thisletter. Enclosed are three copies.

This event is reported in accordance with Technical Specification 6.7.B.2.d in that the event involved abnormal degradation of a system designed to contain radioactive material resulting from the fission process.

Yours very truly, L

Mayer, PE nager of Nuclear Support Services LOM/JAG/jh cc:

Director, IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn:

J W Ferman

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NRC FOR (7-77) 7 8

CON'T 7

8 057-21 FE-TJ F07 5-7 8

IM 366 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT 8 00515OXITS COTI 1()

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPO 10 15 101 01 01 21 61 3 l 10 l 41 11 A 81 0'01_ 01 51 019 18 O0 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (

During normal operation, routine operator inspection detected a through -

wall crack on a fitting on moisture separator level switch, LS-1188. This constitutes an abnormal degradation of a system designed to contain radioactive material result ing from the fission process (T.S. 6.7.B.2.d).

There was no effect on system or plant operation. There are no similar previous events.

9 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE E )

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10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.

CODE TYPE NO.

NUMBER L.

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1 L.01 1.2 1 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER 1J J@

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- 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS L T 1 1Attachment weld of niDole to level switch float chamber assembly was found I

IE I cracked. Assembly is ASTM A-335 P!11.. Nipple was installed in field. PnSilAted I

I 1 Iimproper weld procedure caused weld failure. Weld ground Out and replaced.

SimilaIr 0

Ilevel switches were visually examined, Two other cracks found and repairep l

7 8

9 80 FACILITY METHOD OF STATUS

% POWER OTHER STATUS &

DISCOVERY DISCOVERY DESCRIPTION IT110 10 Igi NA I L.JI Operator observation 1

7 8

9 10 12 13 44 45 46 80 ACTIVITY CONTENT 80 RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE E

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9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

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11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION 41 I

1 (lla I MA 7

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11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

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