ML19332C851

LER 89-013-00:on 891023,discovered That Monitor Used to Satisfy Requirements of Tech Spec 3.3.3.1,Action 27 Had Been Unplugged.Caused by Personnel Error.Individual Counseled & Meeting Held W/Health Physics technicians.W/891122 Ltr

ML19332C851
Person / Time
Site:	Seabrook
Issue date:	11/22/1989
From:	Belanger R, Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-013, LER-89-13, NYN-89151, NUDOCS 8911290079
Download: ML19332C851 (4)

Text

-r..,

Q

.. n.P*

< ~

f)ij i

L d New Hampshire.

,,c.. m j,

' Senior Vice President and i Chief Operating CWicer  ;

l i, .

NYN-89151 November 22, 1989 ,

i: l ii United States Nuclear Regulatory Commisteion Washington, DC' 20555 X

Attention Document Control Desk f

Reference:

' Facility Operating License NPF-67. Docket No. 50-443 ,

i >

Subjects' Facility Operating Report (LER) No. 89-13-00: Noncompliance with I

, Technical Specification Action Requirements [

. +

Gentlemen:- I L Enclosed please find Licensee Event Report (LER) No. 89-013-00 for a

Seabrook Station. .This submittal documents an event which occurred on October 23, 1989, and~is being reported pursuant to 10 CFR 50.73(a)(2)(I).

Should you require further information regarding this matter, please '

contact Mr. Richard R. Belanger at (603) 474-9521, extension 4048.

Very truly yours. [

o  ;

[ W f -l$+eb l Teu C. Feigenbaum  ;

Enclosures:

NRC Forms 366, 366A 1

l cca Mr. William T. Russell

! Regional Administrator L = United States Nuclear Regulatory Commission i Region 1  ;

475 Allendale Road King of Prussia PA 19406 t

Mr. Antone C. Cerne NRC Senior Resident Inspector la P.O. Box 1149 ,

i Seabrook, NH 03874 i

INPO Records Center 1100 Circio 75 Parkway Atlanta, GA 30339 8911290079 891122 PDR .ADOCK 05000443 '

ll s PDC New Hampshire Yankee Division of Public Service Company of New Hampshire i g I' -

P.O. Box 300

• Seabrook, NH 03874

• Telephone (603) 474 9521 Y _

' A* -  :

1 g.,RC .e,. 3a. , U s. Nuct8:.R RE:Uaf ony Co=MesioN APPROVE) 0848 NO. 31440198

. UCENSEE EVENT REPOhT (LER) EKP'at5 8'82'"

P

1. ACILITv tegent til oDCKET NUMDER (21 PAGE G1 Seabrook Stat'.cn oI610l0l0l4g4l3 i jorl 0l3 l TITLE i.i l Non-compliance with Technical Specification Action Requiremes.ts event oaf t m .en NuentR m RecoRT oAn tTi ofnth e Aciuf mNvoLyto m l

moNTu oAv vtAR v8AR 6ag;^6 = woNTw oAv vtAR * *Cii.sv v aa-es ooCat? NUMnRm 01610 l o t o i l l

~ ~

1l0 2l 3 8 9 8l9 0l 1l3 0l0 1l1 2l2 8l9 o iss oioici l l THIS OFOR W SUERef778D PUROUAlff TO THE RSouthtes0NTS 0810 CFR $: ICaere sae er more et ene assie,vnpi (11)

OPGRATING moot = 5 ., n 4.i .0.n sH H i n.Tu ) -

R 30 4EtteH1Hil 98.384eHil 00.736sH2Hel ?8.71ta) n., 0i0i0 . sinh.) _

.m _

..nNimi ,

_ =;g,7,,,,,

s

,,, 30.4EtteH1 Hall y 90.731siGHil 50.ntelmivulHAl 386AJ En ? ."

'iPE. 8' '""'" H"' es.n wH Hal m.nNH2H,uiHel ,

M 4 4sH1Hel 06.734s}# Haul 30.734eH2Hal LICleeHE CONT ACT POR TH16 L8R nt)

NAME TELEPHONE NUMBER AmtACODE Richard R. Belangere Lead Engineer - Compliance (extension 4048) 6, 0,3 4,7,4 , ,9,5,2,1 COedPttti ONE LING FOR E4cei C0egPONtNT $ AILORE ot9CnittD IN TM18 REPORT (13i CAUS$ SYSTEM COMPONE NT "A

f0' "h'O PR CAUSE SYSTEM COMPOktNT "A

kO' " 'gOA,TAffI g

b "

I I I I I l l l I I i 1 ! I I I I I i 1 1 '

I I I I I I l 6

$UPPLge#ENT At R$ PORT EMPGCTED ti4l MONTH DAY YEAR SUBMIESION 7iS (19 ves. eeonnen RX9tCTLD SUOhtISstON DMil NO l l l ASSTAACT t&amir op ##0 assess. ta. appresonesser titssen s#,yse.asese ryseertron haast nel On October 23, 1989, it was discovered that a monitor being used to satisfy the requirements of Technical Specification 3.3.3.1, ACTION 27 had been unplugged.

Seabrook Station Technical Specifications require that the Containment Post LOCA Monitor be OPERABLE in all modes. On October 2, 1989 monitor 1-RM-6576B was removed from service and a portable monitor was used to satisfy the requirements of ACTION 27 which requires an alternate method of monitoring.

At approximately 2:30 am on October 23, 1989, a Health Physics Technician unplugged the monitor to take an air sample. This monitor was discovered unplugged at 7:30 am and re-energized . This resulted in a non-compliance with the Technical Specifications for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

The root cause of this event is attributed to personnel error. The HP Technician involved was not familiar with the Technical Specification requirement, had not been cautioned regarding unplugging equipment, and did not consider the consequences of de-energizing the monitor.

The individual was counselled regarding the consequences of the event and cautioned about unplugging equipment. A meeting was held with HP Technicians to discuss this event and actions to prevent recurrence.

There were no adverse safety consequences as a result of this event. A review of primary coolant system activity indicated that no abnormal radiological condition existed.

,'qL, -

e . m.a va =cott.a rs:v6t.voav commission.

• • • **= ovso oue =o vio-o *

. LICENSEE EVENT REPORT (LER) TEXT CONTINUATK)N EXPings: Stat /s pacegety naast tu t'oCEEv 8eveasta tal Lea asunsett tai *A05 (3)

. .. m '4d,,,;;',a ,

"'#.0 Seabrook Station 01510101014l4l3 8l9 --

0l1 l 3 --

0l0 0l2 0F 0l3 von,, . aacu mawim On October 23, 1989 at 7:30 am EST, it was discovered that a portable area monitor being used to satisfy the requirements of Technical Specification 3.3.3.1, ACTION 27 had been unplugged.

Seabrook Station Technical Specification 3.3.3.1, ' Radiation Monitoring for Plant Operations ' requires that the radiation monitoring instrumentation channels for plant operation shown in Table 3.3-6 be OPERABLE with their alarm / trip setpoints within the specified limits. Table 3.3-6 Item 1.A requires that the Containment Post LOCA Monitor be OPERABLE in all modes. On Octobsr 2, 1989 Containment Post LOCA monitor 1-RM-6576B was removed from service to perform a design change for its power supply. A portable area monitor was used to satisfy the requirements of ACTION 27 which requires, in part, the initiation of a preplanned alternate method of monitoring the appropriate parameter (s).

At approximately 2:30 am on October 23, 1989, a Health Physics Technician unplugged the portable monitor to take an air sample in the area. This monitor was discovered unplugged at 7:30 that morning. The monitor was immediately re-energized . This resulted in a non-compliance with the requirements of Technical Specification 3.3.3.1, ACTION 27 for a period of approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

ROOT CAUSE The root cause of this event is attribdted to personnel error. The Health Physics Technician involved was not familiar with the Technical Specification requirement, had not been cautioned regarding unplugging equipment, and did not consider the consequences of de-energizing the monitor.

CORRECTIVE ACTIONS The individual involved in this event was counselled on October 26, 1989 regarding the consequences of the event and cautioned about unplugging equipment. Additionally, a meeting was held with Health Physics Technicians to discuss this event and actions to prevent recurrence. These actions include placing a tag on the plug of the portable area monitor being used to satisfy this Technical Specification requirement which reads ' Caution: DO NOT UNPLUG, HP TECH SPEC ACTION.' Health Physics procedures will be revised to include instructions to tag power cords on instruments being used to satisfy Technical Specification requirements.

A Training Development Reconsendation has been initiated to include a discussion of the consequences of unplugging equipment in General Employee Training to ensure that all site personnel are aware of the consequences of this type of event. A caution statement regarding the unplugging of equipment was included in the " Station Manager's Messenger" on October 26, 1989.

, , , , , , , , , , , .uaoPoiese+e2+5S d*

GMb

- . _ _ _ _ _ -_. _ . . _ _ _ _ _ _ _ _ _ . - _.__ . . _ . - _ _ _ _ _ _ . - ~

sens ee h us. mucLau Estuatoav counesson ,

• • ' aaeaovio ous ao mo-e*

UCENSEE EVENT REPORT (LER) TEXT CONTINUATION [

exames: nu.  ;

easio ,veinmu m . oocati numee= a: t i . o u,,,, ... . . . , j

. .. ae:p.%  :.;: ,

Seabrook Station olslololol4l4l3 8l9 -

0l1l3 -

0l0 0J3 or 0 l3  !

T SAFETY CONSEQUENCES ,

f

=There were no adverse safety. consequences as a result of this event. A review of primary coolant system activity during this period indicated that no abnormal 4 radiological condition existed and.the health and safety of employees or the public was not adversely affected by this event. .

PLANT CONDITIONA l At the time of this event, Seabrook Station was in MODE 5 (Cold Shutdown) with  !

the Reactor Coolant System at atmospheric pressure.

i i

A I

l-r l

[

l

,u.

, 0.. . . v ..o.o ......=d.

. - . - . . , - - - - . - , . , ._ . . _ . . , ..