05000263/LER-1979-015-03, /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell

/03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell

ML112900889
Person / Time
Site:	Monticello
Issue date:	08/10/1979
From:	Hammer S Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900890	List: 05000263/LER-1979-015, Forwards LER 79-015/03L-0 05000263/LER-1979-015-03, /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell
References
LER-79-015-03L-01, LER-79-15-3L-1, NUDOCS 7908140783
Download: ML112900889 (3)

LER-1979-015, /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell

Event date:
Report date:
2631979015R03 - NRC Website

text

REGULATORY INFORMATION DISTRIBUTION SYOTEM (RIDS)

ACCESSION NBR:7908140783 DOC.DATE: 79/08/10 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTH,NAME AUTHUR AFFILIATION HAMMERS,J.

Northern States Power Co, RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director SUBJECT: LER 79-015/03L00 on 790712:discovered steam leak from DOCKET #

05000263 intermediate pressure feedwater heater,Cause undetermined.

Temporary patch installed pending replacement of heater shell.

DISTRIBUTION CODE: A0028 COPIES RECEIVED:LTR i ENCL SIZE:,

TITLE: INCIDENT REPORTS NOT ES :-----------------------------------

RECIPIENT ID CODE/NAME ACTION:

05 BC ORB'

1. 3 INTERNAL: 0 EG F 09 14 TA/EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL4 28 ACDENT ANLYS E JORDAN/IE I&C SYS BR COPIES LTTR ENCL 4

4 1

2 1

1 1

1 1

1 1

1 1

1 1

2 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR 21 AD SYS/PROJ 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC SR 29 AUX SYS BR HANAUERPS, TMI-H STREET COPIES LTTR ENCL 1

3 1

1 1

1 1

1 1

1 1

1 EXTERNAL:

03 LPDR 29 ACRS 1

16 1

16 04 NSIC TOTAL NUMBER OF COPIES REQUIRED: LTTR 1

1 aok UL-p 49 ENCL 49

NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 August 10, 1979 Mr J G Keppler Office of Inspection &

U S Nuclear Regulatory 799 Roosevelt Road Glen Ellyn, IL 60137 Enforcement Commission

Dear Mr Keppler:

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 13A Feedwater Heater Shell 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 in that it represents degradation of piping designed to contain radioactive material resulting from the fission process.

Yours very truly, L O Mayer, PE Manager of Nuclear Support Services LOM/DMM/ak cc:

Director, IE, USNRC (30) 4-rector, MIPC, USNRC (3)

MPCA Attn:

J W Ferman

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LICENSEE CODE 14 lb LICENSE NUMIILII 7b 26,

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.7i 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 THE EXISTENCE OF A STEAM LEAK FROM THE E-13A INTERMEDIATE PRESSURE FEEDWATER HEATER.

REMOVAL OF SHELL INSULATION REVEALED A THROUGH-WALL FLAW IN THE HEATER SHELL WHICH CONSTITUTES AN AB NORMAL DEGRADATION OF A SYSTEM DESIGNED TO CONTAIN RADIOACTIVE MATERIAL RESULTING FROMI THE FISSION PROCESS AS DEFINED BY T.S. 6.7.B.2.d.

THIS EVENT HAD NO EFFECT ON SYSTEM OPERATION OR THE PUBLIC HEALTH OR SAFETY.

THERE WERE NO PREVIOUS SIMILAR OCCURRENCES.;

80 SYSTEM

CAUSE

CAUSE COMP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE I0I l lG LEJ 0 LxJ G I H IT IE Ix IC IH ISI1zIG 7

8 9

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

CODE TYPE NO.

i(17 REcP"OT NUMBER LII L9 UOL-J LsJ L0-1 0 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHIDOWN ATTACHMENT NPRD-4 PRIME COMP.

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

SUPPLIER MANUFACTURER L @LEJ_

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LZiO 10 10 10 181 INJ@

LYJ LAJ ISI 21 9 01 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS D W

I NDE EXAMINATION OF THE FEEDWATER HEATER SHELL REVEALED AN AREA OF EROSION LOCALIZED

[ T IN THE VICINITY OF THE EXTRACTION STEAM INLET NOZZLE. CAUSE OF THE FLAW IS UNDETER 1 MINED. THE FLAW IS 1"1 LONG AND IS CRACK-LIKE IN APPEARANCE. A TEMPORARY PATCH TO 1

3 STOP THE STEAM LEAK WAS INSTALLED PENDING REPLACEMENT OF PORTION OF HEATER SHELL 1r-4 SCHEDULED FOR NEXT APPROPRIATE OUTAGE.

7 8

9 so FACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 1

LE 11 I 0 1 0 NA IlJI OPERATOR OBSERVATION 7

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11 12 13 80 PERSONNEL INJUnIES NJMRER1 DESCIllPTION 8

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DESCRIPTION

[II IZ18 NA 8

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DISCOVERYEDESCRIPTION I N18)I NA_

OPRAO OBSERVATION9 PE:

612/295-5151 Y

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NAME OF PREPARER J. HANWR o

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