05000263/LER-1979-024-03, /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld

/03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld

ML112900977
Person / Time
Site:	Monticello
Issue date:	01/18/1980
From:	Overlid T Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900978	List: 05000263/LER-1979-024, Forwards LER 79-024/03L-0 05000263/LER-1979-024-03, /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld
References
LER-79-024-03L-01, LER-79-24-3L-1, NUDOCS 8001250535
Download: ML112900977 (3)

LER-1979-024, /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld

Event date:
Report date:
2631979024R03 - NRC Website

text

REGULATORY IN!

~AT1L)N DISTNif3UTION sYSFr 0 R105 A6CESSION NbR:6001250535 DUC.DAl't: 60/01/18 NOTARIZED): NO FACIL':.50-263 Monticello Nuclear Generating Plant, or ern States A0'I,NAME AUl'HUR AFFILIATiUN UVE.RLIV,1.W, Northern Sta tes Power Co.

RECXP,*NAme RECIHIENJ AFFILIATION Region 3p Chicagop Office of the Director L)OCKEl" #

0$000263-SUt3JECr: LEK 79-024/U3L"0:o, 791220,.during normal operationfroutine operator insp.revealed 'steam leak in 1-inch'90 degree elbow in reactor core insulation cooling steam line drain to Conaenser.Cawsed by pin~hole faih.,re of 3000 lb socket weld, DISTRIBUT ION CU&: A0028 COPIES RECEIVEL):LFR

/NC L

9'z TIrL~i Incideni keports

• ~

I~:-

NOT S -- - - - - - - - - - - -

RECIPITIJ I1) CODE/NAmE ACTION; 05 bC*

INTERNAL: 01.-jjIGiF1 14 TA/EDO lb EEB3 18 PLANT SYS 6H 20 At) PLANT1Si8 23 ENGR-8H 25 PWR SYS 8HR 27 OPERA-LIQC bR 29 AUX 5Y$6R H ANA) ERPSg ",

STS GROUP LLAOR COPIES 4 4 RECIPIENT ID) CODE/NAME 02 NHC PL)R 11 MPA 1$ NOVAK/KNiEL 17 AD FOR ENGR 19 1M2 S'YS t$

22 kEAC-sAFt8R 24* KREGtER 26 AU/SITE ANAL 28 ACOENT ANLYs E JORDAN/IE N IRELAND EXTERNAL:

03 LPDN 29 ACRS 1

16 04 NS1C JAN 2 8 1980 IOIALI, NUMUER OF COPIES REOUID: L1lR 5

NL C OPI.1ES LTN ENC, 1

1 50 ENC L 50 17

NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 January 18, 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 RCIC Steam Drain Line Steam Leak The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.

This event is reported in compliance with Technical Specification 6.7.B.2.d since it represents abnormal degradation of a line designed to contain radioactive material resulting from the fission process.

Yours very truly, L 0 Mayer, PE Manager 'of Nuclear Support Services LOM/DMMNjh cc:

Director, IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn:

J W Ferman

- over-8001250 ';

NRC FORM 366 (7-77)

[E]E 7

8 CON'T DE]

7 8

P 1

7 8

U.S. NUCLEAR REGULATORY COMMISSION no errect on system operability and no effect on public health or safety.

I 80 9

SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE UK e1LE@

e)IEl LxJ (9 I I llGlXIXI LAJ@O L 7

8 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION 11 ERIO EVENT YEAR IREPORT NO.

CODE TYPE NO.

RERTm L_7L

_J1-]

10 1 2 141 I In6

(

1] -4(--j

~NUMBER I 19

~

024

&LJ LLJ LJ LQJi 21 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 l^J@LW J@

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33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Pinhole failure of 3000 lb socket weld 900 elbow occurred due to suspected erosion l

from high velocity steam passing through a leaking valve. Leaking elbow, upstream I

elbow and connecting pipe replaced. Leaking valve will be repaired during appropriate outage when parts arrive. Remaining original fittings in line down-I stream of leaking valve will be replaced during next appropriate outage.

7 8

9 FACILITY METHOD OF STATUS

%POWER OTHERSTATUS DISCOVERY DISCOVERY DESCRIPTION [i]

W3 0191 1(31 NB I Operator observation 7

8 9

10 12 13 44 45 46 ACTIVITY CONTENT 3

RELEASED OF RELEASE AMOUNT OF ACTIVITY L

[E] L @

JI NA I

NA 7

8 9

10 11 44 45 PERSONNEL EXPOSURES 80 NUMBER TYPE DESCRIPTION (B 1 01 0 0 () Z ()I NA 1

7 8

9 11 12 13 80 PERSONNEL INJURIES NUMBER

DESCRIPTION

0 10 1 0 I

NA 7

8 9

11 12 LOSS OF OR DAMAGE TO FACILITY TYPE

DESCRIPTION

7 8

9 10 80 PUBLICITY NRC USE ONLY ISSUED

DESCRIPTION

NA 01 1 LZ 1L NA 1

8 9

10 68 69 80 T W 612/295-5151 0

NAME OF PREPARMER OFPHONE 80012508 LICENSEE EVENT REPORT CONTROL BLOCK:

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

INIMI NIP 1 1ll 0 o0 - lo loll olo 1-10 lo l0l 41 11 11 1l11 10L L D

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

0 5 010 10 21 61 3l l 11 21 21 01 71 91 1 01 111 18 18 I0 SOURCE

@__________1____

60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During normal operation routine operator inspection revealed a steam knlk in n one inch 90o elbow in the RCIC steam line drain to the condenser. Reportable under TS 6.7.B.2.d. One previous similar occurrence (M-RO-79-09), Event had