ML112760118

LER 78-016/03X-1 on 780908:during Normal Operation,Trip of Essential MCC B33A Supply Breaker 52-304 Resulted in Operation in Degraded Mode.Caused by Low Setpoint on Trip Device & by Loss of Dash Pot Oil in Trip Device

ML112760118
Person / Time
Site:	Monticello
Issue date:	01/29/1979
From:	Galen Smith Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112760119	List: ML112760118 ML19269C520
References
LER-78-016-03X, LER-78-16-3X, NUDOCS 7902050206
Download: ML112760118 (5)

Text

,* REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) 0 ACCESSION NBR:7902050200 DOC.DATE: 79/01/29 NOTOIZED: NO DOCKET #

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000260 AUTH .NAME AUTHOR AFFILIATION SMITHG.R. Northern States Power Co.

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

SUBJECT:

LER 78-016/03X-1 on 780908:during normal operationtrip of essential MCC B33A supply hreaker 52-304 resulted in ooeration in degraded mode.Caused hy low getpoint on trip device & by loss of dash pot oil in trip device.

DISTRIBUTION CODE: A002S COPIES RECEIVED:L.TR _ ENCL _ SIZE: I#a TITLE: INCIDENT REPORTS NOTES: -- ----

RECIPIENT COPIES RECIPIENT COPIES ID COL)E/NAME LTTR ENCL ID CODE/NAME LTTR ENCL

• ACTION: 05 BC~p ~ 4 4 1 1 14 TA/EDO 1 1 15 NOVAK/KNIEL 3 3 16 EEB 1 1 17 AD FOR ENGR 18 PLANT SYS BR 1 1 19 I&C SYS BR 20 AD PLANT SYS 1 1 21 AD SYS/PROJ 22 REAC SAFT BR 1 1 23 ENGR BR 24 KREGER 1 1 25 PWR SYS BR 26 AD/SITE ANAL 1 1 27 OPERA LIC BR 28 ACDENT ANLYS 1 1 E JORDAN/IE EXTERNAL: 03 LPDR 16 1 04 NSIC 1 I 29 ACRS 16 16 0

0 FEB 6 1979 TOTAL. NUMBER OF COPIES REQUIRED: LTTR 4 45 C ENCL 4 45

NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 January 29, 1979 Mr J G Keppler, Director 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 UPDATE REPORT Trip of Essential Motor Control Center 133 A Supply Breaker 52-304 The Licensee Event Report for this occurrence is reproduced on the back of this letter and continued on an attached sheet. Attached are three copies.

This event was reported on.October 6, 1978 in accordance with Technical Specification 6.7.B.2.b. The cause related and corrective action items on the form.have been updated to reflect results of further investigation of the event.

Yours very truly, 4'

Manager of Nuclear Support Services LOM/JAG/deh cc: Director, IE, USNRC (30)

Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman 790205cAol 17

-over-

NIM: I Oil M 3h6 IJ. S NIllIC All Ill (Hll.AlOIlYCOMMISSION UPDATE .ICLNSI IV NI II P (II - PREVIOUS REPORT DATE 10-6-78 CON 11101 BLOCK : (PLEASE PHlIN I OIl TYPE ALL 14LOUIHED INF OilMATION)

IMIN IM IN P 1 0 0 - 0 0 0 0 0 - 00 1 41 1 1 11 101 LICENSE TYPE 1

57 CAT 58 7 9 LICENSEE CODE 14 5 LICENSE NUMIIER 25 20 CON'T 0 15 0 0 0 2 6 310 19 0 18 17 18( 0')0 2 9 7 l9 80 7 8 60 61 DocKE UMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CO EQUENCES DURING NORMAL OPERATION A T IP OF ESSENTIAL MCC B33A SUPPLY BRF R 52-304 RESULTED win4 IN OPERATION IN A DEGRZADED N E PERMITTED BY VARIOUS LIMITING)CONDITIONS FORl OERATION. SYSTEMS DEGRADED b CORE SPRAY (..3.5.A.2) T7WO ISOLATION VALVES (T.S. 3.7.D.3), SBLC (T.S. 3.4.B. ), SBGI'S (T.S. 3.7.B.1a) N N MREC EVC EF-0 8- WATER PUMP. NO SIGNIFICANT OCC CE TOOK PLACE AS A ULT OF THE EVENT. NO EFFECT ON PUBLIC HEALTH OR SAFETY. DUNDANT PORTIONS F ALL SYSTEMS MENTIONED WERE AVAILABLE AND OPERABLE. ONE PRE\QUS EVENT REPO/ (78-009).

7 89 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUICODE C lPONENT CODE SUBCODE SUUCODE 7

09 8 9 W 10

@A WXO IC K TB 11 12 13 R KG 18

_A 19 WZ16 20 SEQUENTIAL (0 UIlIONCE REPORT REVISION REPORT NO. . CODE TYPE NO.

LER/RO EVENT YEAR

@ g 0 _] L-_J 1 11 61 1-0 LxJ1 1--J LOJ NUM 21 7 1 22 23 24 ?G 27 2H 29 30 311 32 ACTION FUTURE EFFECT SHODOWN AT1 CHMENT NPHD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 2) S ITTED FORM SUB. SUPPLIER MANUFACTURER LA] 0H8 @ Lz@ LO I ol ol ol ol WL L[Ale 43 I

44 1l ol 81 o1@

47 33 34 35 36 37 40 41 42 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS SEE ATTACHED SHEET. I I 7 89 80 FACILITY METHOD OF STATUS %POWER DISCOVERY DISC VERY DESCRIPTION OTHERSTATUS S ] E 10 1I1 01 0 12 11 NA 44 LAjOL 45 41 OPERATOR OBS VATION J 80

-J 7 8 9 ACTIVIiY CONTENT RELEASED OF HELEANF AMOUN .O .AC1 V LOCAlI ON\HELEASE S EE LzJ Z L ZJ l NA L NA 7 8 9 10 1144 45 80 PERSONNEL FXPOSURES NUMBER TYPE DESCRIPTION 9 7

WT1 ol1 01 8 9 11 12 z R 13 NA 80 PEHSONNEL INJUR1ES NUMBER DESCRIPTION 7

II 8 9 01 01 011 NA 11 12 80 1O'S OF OR DAMAGE TO FACIL TYPE )DESCRIPTION ZNA 80 7 8 9 10 80 PUBLICI TY NRC USE ONLY 1SSUED DESCRIPT N(

.I

/M 89 16]1ue 1

79020E S 68 69 80 '

. NAME OF PREPARER R. SMITH PHO 612/295-5151 '

0

tJ JCI I.All III (.1UI.AltOIY COMMISSION NIHC I OitM 366 v/ in UPDATE I ICI.NStI' I V N I ill Poit I - PREVIOUS REPORT DATE 10-6-78 CONiOL.ULUC:[ (PLEASE PHINI Oil TYPE ALL HLOUIHED INI OR1MATION) 7 s IMIN IMIN 9 LICENSEE CODE 14 1 )15 0 0 - 0 LICENSE 1P 0 Ou NUMIEII 1 - 0 28

!4126 CNE TYP E0 LICEN 57 H o" I I 0 15 10 10 E10 12 6 13 0 19 10 18 17 18 @ 0I 11 121917 19 8 74 78 REPURT DATE 80 DOCKET NUMBER 68 69 EVENT DATE 7 8 60 61 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES RESULTED I DURING NORMAL OPERATION A TRIP OF ESSENTIAL MCC B33A SUPPLY BREAKER 52-304 IN OPERATION IN A DEGRADED MODE PERMITTED BY VARIOUS LIMITING CONDITIONS FOR SYSTEMS DEGRADED WERE CORE SPRAY (T.S. 3.5.A.2), TWO ISOLATION VALVES I OPERATION.

(T.S. 3.7.D.3), SBLC (T.S. 3.4.B.1), SBGTS (T.S. 3.7.B.1a) AND ONE EMERGENCY SERVICE j FOr6 IWATER PUMP. NO SIGNIFICANT OCCURRENCE TOOK PLACE AS A RESULT OF THE EVENT. NO I EFFECT ON PUBLIC HEALTH OR SAFETY. REDUNDANT PORTIONS OF ALL SYSTENS MENTIONED I WERE AVAILABLE AND OPERABLE. ONE PREVIOUS EVENT REPORT (78-009).

CAUSE CAUSE COMP VALVE SYSTEM SUBCODE SU RCOIE COMPONENT CODE SUHCODE CODE CODE OB 93 1L 0 1X1AJ9 CI K ITIBIRIKI LAJ( 18 19 L

w0 C

9 10 11 12 13 7 8 OCCUIHIIENCE REPORT REVISION SEQUENTIAL CODE TYPENO REPORT NO.

LER;RO REPORT NUMBE IEVENT YEAR

[

. 1122 2 23 '14 21116 2G 27 10a3J

'11 29 LLJ 30 1=1j 11 W 72 AT1ACHMENT NPD4 PRIME COMP. COMPONENT ACTION FUTURE EFFECT SHLT DOWN MANUFACTURER

( 22 SUBMITTED FORM ,UB. SUPPLIER TAKEN ACTION LALU I Z ON PLANT METHOD 1olololol 37 HOURS 40 41 23 LY.

42 .

2 43 44 44 I 01 81 0@ 47 33 3 536 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 0 SEE ATTACHED SHEET.

2so 0

7 8 I METHOD OF FTATS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

-]LE_ STTU J@ 11%~i POE0 01 0 o 1 NA Ii LAJ I- OPERATOR OBSERVATION 80 8

10 12 11 44 4M 4UL 7 8 9 ACTIVI TY CONTENT IIIyLC O F1EES . .

OAIN rFEES RELE*A5EI)(IF IiELE Ali AMOLINI 0I ACtI:Y~J E L (D L.0 I NA I NA 7 8 9 10 11 PERSONNEL FXPOSURES NUMBER TYPE DESCRIPTION

[1 7 I o01 01 ol@LzJ l NA 7 8 9 11 12 13 PEHSONNEL INJURIES NUMBER DESCRIPTION 6 01 o 01 A 1-NA S 8 9 11 12 10;S OF OR DAMAGE TO FACILITY TYPE DESCRIPTION I z 18 NA 7 8 9 10 80 PUBLICITY INSUER DESCRIPU ION

2) Li1 9

NA 790205OG"6ILLLLLLJ 68 69 80 R 9 10 GARY R. SMITH PIIONE 612/295-5151 NAME OF PREPARER

27. CAUSE DESCRIPTION AND CORRECTIVE ACTIONS.

Low setpoint on trip device. Type of offsite personnel uncertain.

Contributing cause was a loss of dash pot oil in the trip device (GE Type EC-2A). Parts were replaced in kind and setpoints adjusted.

The following actions are planned: (1) retrain appropriate per sonnel in setpoint adjustment, (2) check the setpoints on similar devices, (3) rebuild devices in safety related breakers and periodi cally replace devices in all breakers if oil leaks occur.