05000289/LER-1978-025-01, /01T-0:on 780818-19,neither of Two Inservice Nuclear River Water Pumps Were Selected to Start on Engineered Safeguards Signal.Caused by Personnel Error. Pumps Selected & Personnel to Be Briefed

/01T-0:on 780818-19,neither of Two Inservice Nuclear River Water Pumps Were Selected to Start on Engineered Safeguards Signal.Caused by Personnel Error. Pumps Selected & Personnel to Be Briefed

ML19253B853
Person / Time
Site:	Crane
Issue date:	08/30/1978
From:	Mitchell D METROPOLITAN EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19253B850	List: 05000289/LER-1978-025, Forwards LER 78-025/01T-0 05000289/LER-1978-025-01, /01T-0:on 780818-19,neither of Two Inservice Nuclear River Water Pumps Were Selected to Start on Engineered Safeguards Signal.Caused by Personnel Error. Pumps Selected & Personnel to Be Briefed
References
LER-78-025-01T, LER-78-25-1T, NUDOCS 7910310604
Download: ML19253B853 (2)

LER-1978-025, /01T-0:on 780818-19,neither of Two Inservice Nuclear River Water Pumps Were Selected to Start on Engineered Safeguards Signal.Caused by Personnel Error. Pumps Selected & Personnel to Be Briefed

Event date:
Report date:
2891978025R01 - NRC Website

text

NHC FOHM 366 U. S. NUCLE AR REGULATORY COMMISS102-(7 77)

J LICENSEE EVENT REPORT CONTROL BLOCK l l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1

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8 9 LICENSEE CODE 14 15 LICENSE NUM85R 25 26 LICENSE TYPE JO 57 bAI 5d CON'T lL Cl 5 l0 l0 l0 l2 l8 l9 @ l0 l8 l1 l9 17 l8l@l0 8 l3 lo 1718 l@

RE*0R7 o

i 3g ne 7

8 60 61 DOCKET NUMBER 48 8 69 E'v ENT DATE 74 75 RE

• ORT D ATE 33 EVENT DESCRIPTION ANC, PROBABLE CONSEQUENCES h Oi2 l For a period cf time frc= Okh0 hours on 18 Aucust 1978 until lh00 hours on 19 Aupst o

3 l 1978, neither of the two inservice NRWP vere selected to start en an E.S. signal.

l This is a violation of T.S. 3.3 and reportable per T.S. 6.9.2. A.

The consequence cf o

ois I this error is that the pumps vould not have autc=atically restarted following a postu-l lated IS conditien acec=panied by a loss of pcver.

o s

Ol7 l

0 8

l 7

8 9 t

SYSTEM

CAUSE

CAUSE COMP-VA LV E CODE CODE SUBCOCE COMPONENT CODE SUSCOCE SUBCOCE l El Zl@ { Al@ l 3 lQ l Z l Z l Z l 2 l 2 l Z Q gg gg O

9 7

8 9

to 11 12 13 18 19 20 SEQU ENTI AL OCCURRENCE PE* ORT R EVISION LE R. RO EVENT YE A R RE' ORT NC.

CCCE TYPE NO.

O17REPOa7 lTlA l-l0l2l5l l/l lo l1 l l Tl l-l l0 l NUM8ER 21 22 23 24

'6 27 28 29

Q 31 32 ACTION FUTURE EFFECT SHUT 00WN ATT ACHM c NT NP R O-4 PRIME COMP.

COMPONENT Tef(EN ACTjpN ON PLANT VETHCO HOURS SUB MtTT ZD FORM bub.

SU PP LIE R MANUFACTURER P l@l "l@

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z lo lo lo 33 34 35 36 37 40 di 42 43 44 4-CAUSE CESCRIPTION AND CORRECTIVE ACTIONS The cause of this ncnce:pliance which occurred during the switching and tagging o

=anipulations to allev =aintenance en the "A" Nuclear River Pu=p strainers was persen-nel error. Upen discovery, the NRWP vere ccrrectly selected for ES actuatien. All y

operating personnel vill be briefed en this incident and a procedure change made

, requiring IS selecter switch positiens to be added to switching crders.

7 8 9 B;

F ACILITY METHOD OF STATUS

% POWER OTHER STATUS DISCOVERY DISCOVERY OESCRIPTION 32 El@ l 1 l 0 l 0 lhl NA l

U @l Oterster cbservation 1

5 7

8 9 10 12 11 44 45 46 8:

ACTivtTY CONTENT RELE ASEC OF RELE ASE AMOUNT CF ACTivtTY LOCATION OF RE EASE 1

6 Nf.

l 7A 7

8 9 10 tt 44 45 3

PERSONNEL EXPOSURES j

Q{

jQ NUMBER TYPE

DESCRIPTION

g UJ l /

l Ol Ol 0 l2 l

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7 7

8 9 11 12 13 SC PERSONNE L INJURIES NUMBER CESCRIPTION el of al@l NA i

i s

7 8 9 11 12 8.

LOSS OF CR DAMAGE TO FACILITY Q 7 910810 6C TYPE CESCRipTION v

1 9 l El NA 1

i 8 9 10 6:

Pt '3 L ICITY NRC USE ONLY OESCRIPTION rSSUEL@l I Yl w e n Nevs Felease I

i i i Ii!IIII III 2

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8 3 to 68 69 a:

. G.

itchell pynyg, 215-929-3601 Z:ct. 169 NAME OF PREPARER

2

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..A=.=a.,

m. e. m._.

During normal operatien at 100% F. P. en August 18, 1978, it was deter =ined that for the previcus 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> and 20 =i

'es, neither of the two running Nuclear River Water Pu=ps was selected tc, autc=atically start en an Engineered Safeguards signal.

"ad there been a Ices cf offsite pcVer acec=panied by an ES condition, the inservice pu=ps veuld not have autc=atie9117 restarted when the emergency diesel generators reenergize their respective supply buses.

When the ncnce=pliance was discovered, the Nuclear ?dver P't.=ps were correctly selected for Engineered Safeguards actuaticn.

Se cause of this ncnec=pliance was persennel arrer. All operating personnel vill be triefed on the incident and a precedure change =ade requiring ES selecter switch posftien to be added to the svitching orders.

1505 195