05000263/LER-1978-016-03, /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

/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: 05000263/LER-1978-016, Forwards LER 78-016/03X-1 05000263/LER-1978-016-03, /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
References
LER-78-016-03X, LER-78-16-3X, NUDOCS 7902050206
Download: ML112760118 (5)

LER-1978-016, /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

Event date:
Report date:
2631978016R03 - NRC Website

text

,*

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:7902050200 DOC.DATE: 79/01/29 NOTOIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 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.

0 DOCKET #

05000260 DISTRIBUTION CODE: A002S COPIES RECEIVED:L.TR ENCL SIZE:

I#a TITLE: INCIDENT REPORTS NOTES:

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

• ACTION:

05 BC~p

~

4 4

14 TA/EDO 1

1 15 NOVAK/KNIEL 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 29 ACRS 16 16 1

16 04 NSIC COPIES LTTR ENCL 1

3 1

3 1

I 0

0 FEB 6 1979 TOTAL. NUMBER OF COPIES REQUIRED:

LTTR 4

C 4

45 ENCL 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 Technical Specification 6.7.B.2.b. The cause action items on the form.have been updated to further investigation of the event.

accordance with related and corrective reflect results of 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

- over-17

NIM: I Oil 7

CON'T 7

8 win4 EF-0 8-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 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 ONE PRE\\QUS EVENT REPO/

(78-009).

7 89 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUICODE C

lPONENT CODE SUBCODE SUUCODE 09 W

@ A WXO IC K TB R KG

_A WZ 7

8 9

10 11 12 13 18 19 20 SEQUENTIAL (0

UIlIONCE REPORT LER/RO EVENT YEAR REPORT NO.

CODE TYPE

@ g 0 _]

L-_J 1

11 61 1-0 LxJ1 1--J NUM 7 1 21 22 23 24

?G 27 2H 29 30 311 ACTION FUTURE EFFECT SHODOWN AT1 CHMENT NPHD-4 PRIME COMP.

TAKEN ACTION ON PLANT METHOD HOURS

2)

S ITTED FORM SUB.

SUPPLIER LA] 0H8 Lz@

LO I ol ol ol ol WL L[Ale 33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 16 80 REVISION NO.

LOJ 32 COMPONENT MANUFACTURER I

1l ol 81 o1@

44 47 SEE ATTACHED SHEET.

7 89 FACILITY STATUS

%POWER OTHERSTATUS S ] E 1 I1 01 0 NA 7

8 9

10 12 11 44 ACTIVIiY CONTENT RELEASED OF HELEANF AMOUN O

AC1 V

EE LzJ Z

L ZJ l NA 7

8 9

10 1144 PERSONNEL FXPOSURES NUMBER TYPE

DESCRIPTION

9 WT1 ol1 01 z R NA 7

8 9

1 1 12 13 PEHSONNEL INJUR1ES NUMBER

DESCRIPTION

I I 01 01 011 NA 7

8 9

11 12 1O'S OF OR DAMAGE TO FACIL TYPE

)DESCRIPTION ZNA 7

8 9

10 PUBLICI TY 1SSUED DESCRIPT N (

.I 16]1ue 79020E

/M 89 1

S NAME OF PREPARER R.

SMITH I

80 METHOD OF DISCOVERY LAjOL 45 41 L

NA 45 DISC VERY DESCRIPTION OPERATOR OBS VATION

- J 80 LOCAlI ON\\HELEASE S 80 80 80 80 NRC USE ONLY 68 69 80 '

612/295-5151 M 3h6 IJ. S NIllIC All Ill (Hll.AlOIlY COMMISSION UPDATE

.ICLNSI IV NI II P I

(I

- PREVIOUS REPORT DATE 10-6-78 CON 11101 BLOCK :

(PLEASE PHlIN I OIl TYPE ALL 14LOUIHED INF OilMATION)

IM IN IM IN P 1 0 0

0 0 0 0 0 00 1 41 1 1 11 101 1

9 LICENSEE CODE 14 5

LICENSE NUMIIER 25 20 LICENSE TYPE 57 CAT 58 0 5 1 0 0 0 2 6 310 19 0 18 17 18(

0')0 2 9 7 l9 60 61 DocKE UMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CO EQUENCES DURING NORMAL OPERATION A T IP OF ESSENTIAL MCC B33A SUPPLY BRF R 52-304 RESULTED WERE AVAILABLE AND OPERABLE.

0 PHO I

J 80

NIHC I OitM 366 v/ in UPDATE tJ JCI I.All III (.1UI.AltOIY COMMISSION 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)

IM IN IM IN 1P 1 ) 0 0 -

0 0 Ou 1 -

0

!41 CNE TYP E0 57 7

s 9

LICENSEE CODE 14 15 LICENSE NUMIEII 28 26 LICEN 2so 7

8 I

METHOD OF FTATS

% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION STTU

%~i POE Ii 0 o LAJ I OPERATOR OBSERVATION 8

-]LE_ J@ 11 01 0 1

NA 80 7

8 9

10 1 2 1 1 4 4 4M 4UL ACTIVI TY CONTENT IIIyLC O

F1EES RELE*A5EI)(IF IiELE Ali AMOLINI 0I ACtI:Y~J OAIN rFEES E

L (D L.0 I NA I

NA 7

8 9

10 11 PERSONNEL FXPOSURES NUMBER TYPE

DESCRIPTION

[1 7 I o 01 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 Li NA 790205OG"6ILLLLLLJ

)

9 1

68 69 80 R

9 10 PIIONE 612/295-5151 NAME OF PREPARER GARY R. SMITH o"

H I

I 0 15 10 10 E1 0 12 6 13 0 19 10 18 17 18

@ 0 I 11 121917 19 8 7

8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 78 REPURT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES DURING NORMAL OPERATION A TRIP OF ESSENTIAL MCC B33A SUPPLY BREAKER 52-304 RESULTED I

IN OPERATION IN A DEGRADED MODE PERMITTED BY VARIOUS LIMITING CONDITIONS FOR OPERATION.

SYSTEMS DEGRADED WERE CORE SPRAY (T.S. 3.5.A.2),

TWO ISOLATION VALVES I

(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).

SYSTEM

CAUSE

CAUSE COMP VALVE CODE CODE SU RCOIE COMPONENT CODE SUHCODE SUBCODE OB 93 1 L 0 1X1AJ9 C I K ITIBIRIKI LAJ (

L C

7 8

9 10 1 1 12 13 1 8 19 w0 SEQUENTIAL OCCUIHIIENCE REPORT REVISION LER;RO IEVENT YEAR REPORT NO.

CODE TYPENO REPORT

[

NUMBE 122 21116 10 a3J LLJ 1=1j W

. 1 2

23

'14 2G 27

'11 29 30 11 72 ACTION FUTURE EFFECT SHLT DOWN AT1ACHMENT NPD4 PRIME COMP.

COMPONENT 22 SUBMITTED FORM,UB.

SUPPLIER MANUFACTURER TAKEN ACTION ON PLANT METHOD HOURS (

LALU I Z

1olololol 23 LY. 2 44 I 0 1 81 0@

33 3

536 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 0 SEE ATTACHED SHEET.

0

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.