05000029/LER-1976-013-01, /01T-0:on 761128,following Plant Trip from Power, Main Collant Pump 3 Inadvertently Restarted During Scram Recovery.Caused by Jammed Trip Mechanism on Air Circuit Breaker.New Trip Coil Installed

/01T-0:on 761128,following Plant Trip from Power, Main Collant Pump 3 Inadvertently Restarted During Scram Recovery.Caused by Jammed Trip Mechanism on Air Circuit Breaker.New Trip Coil Installed

ML19347C430
Person / Time
Site:	Yankee Rowe
Issue date:	12/13/1976
From:	Janet Staub YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19347C429	List: 05000029/LER-1976-013, Forwards LER 76-013/01T-0 05000029/LER-1976-013-01, /01T-0:on 761128,following Plant Trip from Power, Main Collant Pump 3 Inadvertently Restarted During Scram Recovery.Caused by Jammed Trip Mechanism on Air Circuit Breaker.New Trip Coil Installed
References
LER-76-013-01T, LER-76-13-1T, NUDOCS 8011190332
Download: ML19347C430 (9)

LER-1976-013, /01T-0:on 761128,following Plant Trip from Power, Main Collant Pump 3 Inadvertently Restarted During Scram Recovery.Caused by Jammed Trip Mechanism on Air Circuit Breaker.New Trip Coil Installed

Event date:
Report date:
0291976013R01 - NRC Website

text

i LER 76-13/1T

{lCENSEE EVENT REPORT C

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NAME LCENSE NUMBER E

TYPE

@ lM l A lY l Kl Rl Il l0 l0 l-l 0 l 0l 0l 0l 0l-l 0 l 0 l l 4l 1l1l 1l 1l l0l1l 7 89 14 15 25 26 30 31 32 CATEGOAY TYP SO E

DOCKET NuvBER EVENT DATE ACPOAT DATE

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LTJ W l0 l5 10 l-l0l01 2l 91 l1 l1 l2 l 8 l 7l 6l l1 l2 l1 l 3 l 7 l 6l 7 8 57 58 59 60 61 68 69 74 75 80

EVENT DESCRIPTION

95 I (See Attached Sheet) l 7 89 80 8i I

7 89 80 EI l

7 89 80

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7 89 pnuE 80 CE CODE COMPONENT CODE fER M

AC A

VOLATON 8 I El cl LFJ l C I Kl Tl El Rl K l [Nj l WI ll 2l Ol lN l 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

@l (See Attached Sheet) l

'7 d9 80 BE I l

7 89 80 1

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F ACluTY METHOD OF STATUS

% POWEA OTHEA STATUS OfSCOVERY DISCOVEAY DESCRiPTON y

l 0l 0l 0l l Scram Recovery l

l NA l

J 7 8 9

10 12 13 44 45 46 80 AE E SED OF EL ASE AMOUNT OF ACTMTY LOCATON OF AELEASE L.J LzJ l

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I 7 8 9

10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TfPE DESCA:DTION 1

l0l Ol0l Ul NA l

7 89 11 12 13 80 PERSONNEL INJURIES NuveEA DE SC A'PTON 8 1 01 0101 l NA l

7 89 11 12 80 OFFSITE CONSEQUENCES 1

l NA l

7 89 80 LOSS OR DAMAGE TO FACILITY TYPE DEF' ASTION

- l NA l

1 7 89 10 80 PUBLICITY lNA l

17 7 89 80 ADDITIONAL FACTORS el 1

7 89 80 8011190 33 2

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7 89 80 NAME: James L. Staub 413-625-6140 PHONE:

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G EVENT DESCRIPTION-i Following a plant trip from power the number three (3) Main Coolant Pump (MCP) was inadvertently restarted during the scram recovery when the No.1, 2400 volt bus was re-energi::ed. The MCP breaker should have opened automatically on loss of power to its bus. The operator was unable to trip the MCP from the Control Board. This event is reported as Reportable Occurrence 50-29/76-13.

CAUSE DESCRIFTION The Westinghouse MCP De Ion Air circuit breaker, 50 DH 250-E, trip.

mechanism had apparently jambed, preventing the trip coil from tripping the breaker, which resulted in the trip coil burning out.

Attempts to manually trip the breaker were also unsuccessful. The breaker was removed from service and inspected. A new trip coil was installed and the breaker was tested. The breaker failed to trip once out of 30 trips. This was considered sufficient cause to replace it with a spare breaker, that tested satisfactorily. The Air Circuit Breaker was disassembled and refurbished, no apparent reason for the binding could be identified. The Breaker will be tested by multiple trips prior to return to service.

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J Novecher 19, 1976 a-f y

United States Na:1 ear Regulatory Agency c

Office of Inspection and Enfcrccoent Region I-631 Park Avcnue King of Prussia, Pennsylvania 19406 Attenticrt:

Mr. J. P. O'Reilly g

Dear Mr. O'Reilly:

Pursuanc to the recuirmts of T~,..h: ical Specifications Accendix A, Sectica E.2.a (9) the following is reported as Reportsble Occurrence

~

i 50-29/76-12 "Perforun e of structures, systc=s, or ccc:p;nents that require re edial action or corrective ceasures to prevcat operatica in a less conservative canner".

i The safety injwtion acc=ulator boron concentration was found to be 2432 ppa.

Tne safety analysis linits are 2200-2400 p;c.

ik. ever, i

based en time after startup, 2432 paa does not violate barca precipi-tatica cor.centrations follcroing a LCG.

Cnange No.117 Sep. 3 Enclosure j !

A restricts the weighted barca concentratica of:

the reacsor coolant,

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safety injection tank and the acctenlator to 2314 p;n. Inc weighted i

l concentration is now 203S p;n.

l 'j A more detailed report will be sulnitted 15110 days.

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i Very truly yours, ht-kch k kJ

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Herbert A. Autio g

I Plant Superintendent

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gggpggy 105 U.S. NUCLE AR REGbL ATOHY coy' 03 TON DOCKET NUMDEH s

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FILE tJU'A BE R NRC DISTRIBUTION ron PAF'T 50 DOCKET MATERIAL INCIDENT REPORT 4

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I FROM:

DATE oF DOCUMENT l

T Yankee Atomic Electric Company 12/13/76 u

inss.

DATE RECEIVED

' :r. J. P. O'Leilly

!!r. Herbert A. Au tio 12/16/76 [LE T T E R ONOTORIZED PROP INPUT FORM NUMBER oF COPIES RECEIVE D CoRIGINAL N,J NC L ASSIFIE D One si;ned copy N O*Y

DESCRIPTION

E N CLOSU R E 1

Ltr. trcn; the follo"in;:

Licensee Event Report (R0 50-29/76-13/01T) on 11/25/76 concerning ::o. 3 main Coolant Pump Breaker Failure.

(1-P)

(2-P)

OWLEDGED PLANT NA!G:

DO NOT REliOVE y mn ucc 7.0..,

NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION /INFORMATION 12/16/76 IGL

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