ML112760110

Forwards LER#78-027/03L-0

ML112760110
Person / Time
Site:	Monticello
Issue date:	12/21/1978
From:	Mayer L Northern States Power Co
To:	James Keppler NRC/OI/RGN-III/FO
Shared Package
ML112760111	List: ML112760110 ML20062G261
References
NUDOCS 7812270246
Download: ML112760110 (5)

Text

i REGULATO*INFORMATION DISTRIBUTION *TEM (RIDS)

ACCESSION NBR:7812270246 DOC.DATE: 78/.12/21 NOTARIZED: NO DOCKET #

FACIL:50-263 MONTICELLO #1, NORTHERN STATES POWER CO. 05000263 AUTH.NAME AUTHOR AFFILIATION MAYER,L.O. NORTHER.N STATES POWER RECIP.NAME RECIPIENT AFFILIATION KEPPLER,J.G. **REG.3,CHICAGO,OFF.OF THE DIRECTOR

SUBJECT:

Forwards LER# 8-027/03L-0.

DISTRIBUTION CODE: A002S CO-PIES RECEI VED:LTR / ENCL I SIZE: 11Jl TITLE: INCIDENT REPORTS NOTES:

RECIPIENT COP I ES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BC OP8 3 4 4

• INTERNAL: 1 02 NRC PDR 2 11 MPA 31 31 14 HANAUER 21 15 NOVAK/KNIEL 16 EEB 17 AD FOR ENGR 18 PLANT SYS BR 19 I&C SYS BR 20 AD PLANT SYS .1 21 AD SYS/PROJ 22 REAC SAFT BR 1 23 ENGR BR 24 COLLINS 0 0 24 KREGER 25 PNR SYS BR 26 HOUSTON 1 0 26 VOLLMER E JORDAN/IE 1 EXTERNAL: 03 LPDR 16 1 04 NSIC 1 I 27 ACRS 16 16 DEC 29 1w/8

• TOTAL NUMBER OF COPIES REQUIRED: LTTR 43 ENCL 43 0

0 REGULATOOINFORMATION DISTRIBUTION *TEM (RIDS)

ACCESSLON NBR:7812270251 DOC.DATE: 78/.12/21 NOTARIZED: No DOCKET #

FACIL:50-263 MONTICELLO #1, NORTHERN STATES POWER Co. 05000263 AUTH.NAME AUTHOR AFFILIATION TILLY,D.D. NORTHERN .STATES PONER RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER#78-027/03L-0 son 781121-:during normal oper a steam leak was found in tee downstream of MO-1197 on the 2" HP Turbine

"[" bend drain line to condenser,probably due to flow of steam & water from restricting orifice into tee.

DISTRIBUTION CODE-: A002S COPIES RECEIVED:LTR -_ ENCL SIZE,:

TITLE: INCIDENT REPORTS NOTES:

RECIPIENT COPIES RECIPIENT COPI ES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BC 4 4 INTERNAL: 0.1 REG FILE 1 1 02 NRC PDR 1 09 I&E 2 2 .11 MPA 3 3 14 HANAUER 15 NOVAK/KNIEL 16 EEB 17 AD FOR ENGR 18 PLANT .SYS BR .1 19 I&C SYS BR 20 AD PLANT SYS .1 21 AD SYS/PROJ 22 REAC SAFT BR 23 ENGR BR 24 COLLINS 0 0 24 KREGER 25 PWR SYS BR .1 26 HOUSTON 0 0 26 VOLLMER E JORDAN/IE 1 1 EXTERNAL: 03 LPDR 16 04 NSIC 1 1 27 ACRS 16 16 0 0

0 0

TOTAL NUMBER OF CO.PIES REOUIRED: LTTR 43 ENCL -43

NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 December 21, 1978 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

HONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Leak in HP Turbine U-Bend Drain 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 main steam system component.

Yours very truly, L 1 M ager of Nuclear Support Services LOM/JAG/deh cc: Director, IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman

-over-

NRC FOR M 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)

LIC NSEE EVENT REPORT CONTROL BLOCK: . 1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

S I IMINIMINIPI il lo l0 I- l0 l0 ololol-!

LICENSE NUMBER

- ol01I4 li 11 11 i OL.LJE 25 26 LICENSE 15Y 30 C

.AI 58 LICENSEE CODE 14 CONT SOE IL(D 05101002311117 21 11 7181 11 2 12 11 17 1 810 7 4 75 REPORI DATE 80 0DOCET Nu ER 6 3 69 1 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONS QUENCES 0 1194 During normal operation a steam leak was discovered in a tee downstream of MO on h1-- two inch HP Turb' e "U" Bend Drain Line to the condenser. This constitutedj sultin from Ldegradation of a syst designed to carry radioactive material the fission process. (TS.6.7.B.2.d). Six previous similar occurrences in other 24: M-RO-77-19: and M-RO-78-07.-' No affect /n public I I lines (M-RO-76-1, /6 2 : M-RO-77-19; and M-RO 7. 1/

No affect I n public I 7 S IhealthoQr I / I

'I 80 I

SYST I CAUSE CAUSE COMP. VA E COM NENTCODE SUBCODE SUB ODE CO CODE SUBCODE B10I @D [E HB0[~0L~1E 1( P I PPEXXI E X X 118 WO L6A 9 11 18 12XSEQUENTIA 13 OCCURRENCE 19 REPORT 0 REVISION CUDE TYPE NO.

ER RO Q1-REPORT ENT YEAR J 0' REPORT 7 Ld 1..31 LL -j LoJ NUMBER 21 22 23 2 26 27 28 29 . 30 31 32 H ATTACHMENT NPRD 4 P SME COMP. COMPONENT ACTION PUT RE EFFECT SHUTOD MET D HOURS (22 SUBMITTED FORM ),UB. SUPPLIER MANUFACTURER TAKEN ACT ON ON PLANT 021A36 0 0 100 0j N NJ. Lj 24 A i L 10 2 15 6) 3 35 37 40 41 4? 43 444 47 33 CAUSE DE CRIPTION CORRECTIVE ACTIONS 0 Leak is believed to be due to erosi on caused by flow of team and water from

-1 ~rnr~ tvnc, Leaking tee nd I restricting orifice into tee. Temp ,sonm vi ryv-e mad-.

l d-.. / ire ryio~r to the d o associated piping will be inspected and rep ace as reQu the next refueling outage, 7 8 9 FACILITY METHOD OF POWER OTHER STATUS DISCOVER DISCOVERY DES IPTION STAT US T LEJ 9 101 8 I 5 10 12 13 NA 44 45 I[B 46 NA 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCAT OF RELEASE 8LzJ 9 9

) LZ10 NA 11 44 45 NA PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

[ 1 o1 10joj go 3 NA I3(

/8 911 PERSONNEL 12 INJURIES 13 80

[E] I 010 oljl NUMBER DESCRIPTION8 NA N WIL0 78 911 0~JOD 12 NA

>7 "Ix so LOSS oF OR DAMAGE TO FACILITY rYPE DESCRIPTION

[ Z] 4J@ NA 80 so PUBLICITY NRC USE ONLY ISSUED DESCRIPTION 2I 7 8/

LL81 10 NA 68 69 80 5 612/295-5151 0 NAME OF PREPARER & il U

• UCLEAR REGULATORY COMMISSION NRC FORM 366 (7 77 L 7 771 LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION)

N IN00-00000-00 M1 ILICENSEE -I i 44 11 11 57 CAT 58 COD E 14 15LICEN.E NUMBER 26 26 LICES YE 3 CON T HE LLJ@D 015 10 10 0 12 6 13 j7 [1 11 121 11 718 111 12 12 1i 7 1 8 G)

C0 6i DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE i80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (

During normal operation a steam leak was discovered in a tee downstream of MO 119q on the two inch HP Turbine "U" Bend Drain Line to the condenser. This constitutedl Ldegradation of a system designed to carry radioactive material resulting from the fission process. (TS.6.7.B.2.d). Six previous similar occurrences in other lines (M-RO-76-1. 16, 24: M-RO-77-19; and M-RO-78-07. 13). No affect on public 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE 7 -

LHI 9 10 E

11 Li 12 13 COMPONENT CODE I IIIP IE I XI XlO 18 SUBCODE 19 A)

SUBCODE L

20 SEQUENTIAL OCCURRENCE REPORT REVISION LER RO EVENT YEAR REPORT NO. CUDE TYPE NO.

,7 RPORT 121 17 18 22

-- I 23 Lo 12 171 24 26 1/J ILJ 1-j 27 L

28 29 30 31 LOJ 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 3 0L 34 JLJ LzJ@1 35 LIzJ 1010ololo 1 40 WJ LJ L43 jL0 2 5 i 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 36 37

© 41 42 44

• 0 I Leak is believed to be due to erosion caused by flow of steam and water from m I restricting orifice into tee. Temporary clamp type repair made. Leaking tee and m I associated piping will be inspected and replaced as required prior to the end of m the next refueling outage.

FACILITY METHOD OF

% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

[L i]LE STATUS 1 10 8 510 80 12 13 NA 44 IB 45 J(3D) NA 46 50 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE E La&J 3 LZI 10 11 NA 44 I 45 NA PERSONNEL EXPOSURES NUIMBER TYPE DESCRIPTION (B3 E 1 00 1

10 11 j0[z 12 Il 13 NA 80 PFRSONNE L INJURIES NUMBER DESCRIPTION I0 0!O01 NA 1 11 12 81o U OF OR DAMAGE TO FACILITV

'v:' DESCRIPTION EELO@1 NA 7 , 9 10 so PUBICITY ON I5SUEUD IS[

DSCRIPTION @g NA 812 27 0 -Af) NRC USE ONLY E l9 II 10 A 68 69 80 5 NAME OF PREPARER D D Tilly 612/295-5151 0 PHONF: