ML112900880

LER 79-014/03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired

ML112900880
Person / Time
Site:	Monticello
Issue date:	08/06/1979
From:	Nolan L Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900881	List: 05000263/LER-1979-014, Forwards LER 79-014/03L-0 ML112900880
References
LER-79-014-03L, LER-79-14-3L, NUDOCS 7908090565
Download: ML112900880 (3)

Text

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I_ Ui' - ki JIrV K ' At4 LU N U -k. I IPif-1DL 1U~'N 1M r tL ACCESSION NBR:7908090565 00C.OATE: 79/08/06 NOTAR ED: NO DOCKET #

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTHNAME AUTHUR AFFILIATION NOLANLL, Northern States Power Co.

RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director SURJECT: LER 79-014/03L-0 on 790709:water leak discovered in 1/2 inch instrument line from reactor water cleanup sys nonregenerative heat exchanger.Cause not determined.Leaking line isolated & will be further inve.stigated & repaired.

DISTRIBUTION CODE: A002S COPIE$ RECEIVED:LTR -L ENCL / SIzE: L./

TITLE: INCIDENT REPORTS NOTES:

RECIPIENT C riPIES RECIPIENT COPIES 10 COD.E/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BC ofd#3 4 4 INTERNAL: 0 1 02 NRC POP 2 .1 M PA 14 TA/EDO 1 15 NOVAK/KNIEL 16 EFB 1 17 AD FOR ENGR 18 PLANT SYS B 1 19 I&C SYS BR 20 AD PLANT SYS 1 21 AD SYS/PROJ 22 REAC SAFT B 1 23 ENGR BR 24 KREGER 1 25 PWR SYS BR 26 AD/SITE ANAL 1 27 OPERA LIC 6R 28 ACDENT ANLYS 1 29 AUX SYS BR E JORDANI/IE 1 HANAUER,S.

I&C SYS BR 1 TNI-H STREET EXTERNAL: 03 LPOR 1 1 04 NSIC 1 1 29 ACRS 16 16 an!C*

361 qA00 j% CW TOTAL NUMBER OF COPIES REQUIRED: LTTR 49 E NCL, 49

MSP NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 August 6, 1979 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 Instrument Line Leakage 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 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc: Director,.IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman

-over- i/

7 908090 5'~O

NiHf I OIIM;IllII it. I Ni:3I a All 1 41111Al I ( IMMIIIILIUN (14/1 LICLNSLL LVI N I HILPOiH I CON t1111flROCK: I I ( f:AMI PRIN 0I4 Oil IYPE ALL ItEIrED INI-OItMATION) 7 8 IMIN IMINIP 11 10lo0 1o 1- to lo lo lo lo 1- 1o 10 1014 11 11 11 1 104 9 LICENSEE CODE 14 15 LICENSE NUMBLI 25 26 . LICENSE TYPE JO 157 CAT 58 Q

CON'T 701 REPORE IL]

60 l10 1 5 l0 l0 10 l2 l6 l3 I 61 DOCKET NUMBER 68 l0 69 17 10 19 17 19 EVENT DATE 1l0 18 10 16 17 19 7 8 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES IDURING NORMAL OPERATION, A WATER LEAK WAS DISCOVERED FROM A 1/2" INSTRUMENT LINE 0O-3 FROM THE REACTOR WATER CLEANUP SYSTEM NONREGENERATIVE HEAT EXCHANGER. THIS CONSTITUTED A DEGRADATION OF A SYSTEM DESIGNED TO CARRY RADIOACTIVE MATERIAL RESULT ING FROM THE FISSION PROCESS. (T.S. 6.7.B.2.d) NO EFFECT ON PUBLIC HEALTH OR SAFETY.0 7a 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7

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8 9

..GL U@ Lzj Iz Iz Iz Iz Iz z IS LzJ 10 11 12 13 18 19 IJ 20 SEQUENTIAL OCCURRENCE REPORT REVI SION LERI/RO [lVENT YEAR REPORT NO. CODE TP O.

()REPORT 9 1-l0o1 11 1 0 L 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 2 SUBMITTED FORM Ull. SUPPLIER MAN UFACTURER (x@L.J [z1 10zj10 1 1LNJ@ LNJ@D LAjD I ZI 919!9 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS

[Tjj] lIINTERIM REPORT. LEAKING LINE ISOLATED. LEAK NOT ACCESSIBLE AT POWER, WILL BE l 1T1 IFURTHER INVESTIGATED AND REPAIRED DURING FUTURE PLANT OUTAGE. I 7 8 9 80 FACILITY METHOD OF STATUS %POWER OTHER STATUS & DISCOVERY DISCOVERY DESCRIPTION

[IDI]

7 8 Li1 0 10 10 121111 NA 44 I [B RI 45 46 OPERATOR OBSERVATION so ACTIVITY CONTENT RELEASED OF IELFASE AMOUNT OF ACTIVITY (D LOCATION OF RELEASE 7 8 9 Zl BL10 zJl11 NA 44 I I45 NA s0 1

PERSONNEL EXPOSURlES ENUMBERR W~oo~oW NAI 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER TEDcECPPTION TI 8 9 0 1-0 10 11 9NANA 12 13o8 I 8 9 11 12 8 LOSS OF OR DAMAGE TO FACILITY 8 TYPE DESCRIPTION 1 I zZi4l2 9 10 NA . 80 PIlILICI TY NRC USE ONLY ISSUED DESCRIPTION j LU 1NA 9 to0 68 69 80 5 NAME OF PREPARER L PHON 612/295-5151

,. I-70 5-65 TYPY DESCRIPTION S