ML20043C331

From kanterella
Jump to navigation Jump to search
LER 90-006-00:on 900501,data Processing Module Was Taken to Purge Which Rendered Both Monitors 2RE-2562C & 2RE-2562A Inoperable.Caused by Personnel Error.Memo Issued to Chemistry Dept Personnel Re Appropriate action.W/900529 Ltr
ML20043C331
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 05/29/1990
From: Hairston W, Odom R
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ELV-01707, ELV-1707, LER-90-006-01, LER-90-6-1, NUDOCS 9006050067
Download: ML20043C331 (5)


Text

.. __ . . _ _

M- 1 Gecwgia Power Canpany i 333 Petmont Avenio -

Atlanta, Georg:a 30308 l .;

., Teleptone 404 b20 3195 -

MMing Address 40 lnverness centor Parkwar j Post Offee oax 1295 1 Dirmingham, A!abama 35201 >

1eicpbono 205 068 5581 May 29, 1990- me mov"" <*wmum .

'W. G. Hairston, til l Sensor Vcc President Nuciem operot.ons ELV-01707-0401-i Docket' No. 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk-Washington, D. C. 20555 Gentlemen:

V0GTLE ELECTRIC GENERATING PLANT LICENSEE EVENT REPORT' PERSONNEL ERROR LEADS T0 UNIT OPERATION-PER TECHNICAL SPECIFICATION 3.0.3 In accordance with 10 CFR 50.73, Georgia Power Company hereby submits the

. enclosed report related to an event which occurred on May 1,1990.=

Sincerely, (d- kd

13. G. Hairston, III WGH,III/NJS/gm

Enclosure:

LER 50-425/1990-006 i xc: Georoia Power Company Mr. C. K. McCoy Mr. G. Bockhold, Jr. -

Mr. R. M. Odom Mr. P. D. Rushton NORMS 1 U. S. Nuclear Reaulatory Comm_jssion Mr. S. .D. ' Ebneter, Regional Administrator Mr. T. A. Reed, Licensing Project Manager, NRR Mr. R. F. Aiello, Senior Resident Inspector, Vogtle 9006050067 900529

[DR ADOCK 05000423 PDC f6x

_=

W

e NMC Feem Joe U S. NUCLit.3 at10taf 0RV COMMis5 ION tJ PIO*/E D OMe t'O 3160 0t04

. LICENSEE EVENT REPORT (LER) '""'S""

  • LCattiv NAMt nl Docatt huwsta (2) GE 8 3 V0GTLE ELECTRIC GENERATING PLANT - UNIT 2 o is I o i o I o 1412 15 1 lod 014 Ilitt les PERSONNEL ERROR LEADS TO UNIT OPERATION PER TECHNICAL SPECIFICATION 3.0.3  :

$ VENT DAf k (Si LE R NUMe t a tel Ri&Onf DAf f 176 OTHER F ACILifit$ INvotytD lei MONTH DAY Y(AM Y$AR "

,, MONTH DAV V E Af! ' Acattie haves DOC R t 1 NuM9t Hist 016101010I I l 0j5 Ojl 90 9l0 0l 0 l 6 0l0 0 l5 2 l9 9 l0 o isio io , oi i i y,,,,,,,, 1His ainoat is u.Minio uniu AN, to iHi aiouia:M Nn o, i0 C,. i <ca-4 ,, ., -,,. ., ,,, ,,,-,, n u W 20 402thi 20 4068el 60 73 eH2Hisl 73 PHbl g n 40.i.in H.i .0 =<.Hu .0 ni.n:H.i n eu.i 1101 i l0 .0 0.i.in H H

.0 mi.na,

.0 ni,Han. H

_ g gs,~;,g g; g ,

to 406tellt H,ial j to 13tsHJHal to 73teH2HvenHA) 366 As to 406te H1Havl SO 73(aH2HeH 60.73isH2Hvit4He1 70 408deln Het 60 736eHtliehl to 73teH2Han tlCEN54E CONT ACT FOR THis LIM Hal NAMt TE LEPHONE NUMBEH AH4 A Copt R. M. 000M, NUCLEAR SAFETY AND COMPLIANCE 40i i 4 82 i i 6i 320l i 1 1 i ,

COMPLif t ONE teht Fon E ACH COMPONENr F AILURE DischistD IN vHit REPOmi H3) l CAuse systiu cOveow N1 *^lW'*C "$'f",'^j!' CAuss sysTsu CoucoNeNt "'[XC ""o",!!'

5

1 I I I I I I i i i i l i i h 1 I I I I I I I I I I I I I sueetiMeNTAt nicoar excictio nei mon 1H oAv v An
  • E'An",??

-,,- anecreo svowss,o~ one, 1 vts H,,., 3 No i  ; l t..r ACr n . . . .,~ ,,.. .,,,..- ., m, - , ,,,,,,,,,,- ,,.u. ..,n.,

On 5-1-90, a Chemistry foreman advised the Unit Shift Supervisor (USS) that work was required on the Containment Atmosphere Gaseous Monitor 2RE-2562C. The USS authorized the work but specified that 2RE-2562C and the Containment Atmosphere Particulate Monitor, 2RE-2562A, could not both be taken out of service simultaneously. Both monitors being out of service in conjunction with other

  • RCS Leakage Detection Systems would constitute a condition prohibited by the Technical Specifications (TS).

The foreman instructed a technician to proceed with the work and at 1303 CDT, the Data Processing Module (DPM) was taken to purge, which effectively rendered both 2RE-2562C and 2RE-2562A inoperable. The USS was alerted to this condition at 1422 CDT. Since the TS action statement does not clearly address these two monitors being out of service simultaneously with another leakage detection system which was already out of service, the USS conservatively entered TS 3.0.3, which requires unit shutdown to commence after one hour. At 1513 CDT, 2RE-2562A was returned to service and TS 3.0.3 was exited.

The cause of this event was a cognitive personnel error by the Chemistry foreman. He failed to recognize that the work being performed would render both channels inoperable and he failed to notify the USS that both channels would be inoperable. The foreman has been counseled.

" M ' "* '"

. g.,cy .M A u.. ocumuwo., c-i .

t#1185 4/30892 c

LICENSEE EVENT REPORT (LER) 'Sa^'#lo*,u"?,M,",M'*;?,"Si,P.o jT.po'" 'J' l TEXT CONTINUATION 1#A",'o'."i"o^Loni g"f',Mt'e'0,'47,N".' "M?"n I 0?"t#a".'Ji*=#",a,'!;2inM.c##:0?M  !

OF MANAGEMENT AND BUDGET. WASHINGTON, DC 70601 ,

fiCitif Y NAMt (H DOCEST NUCASt. (2)

' Lt. NUMSER (G) PAOS (3) u*a "$!?.;'. -

07J.0 j VEGP - UNIT 2 o ls jo lo lo l4 l2 l 5 9p or 0l 4 un w, . % = % me.mn 0l0l6 -

0l0 0l2 i

A. REQUIREMENT FOR REPORT This report is required per 10 CFR 50.73 (a)(2)(1) because the unit operated ,

under the requirements of Technical Specification (TS) 3.0.3. Entry into TS 3.0.3 was a conservative measure because the action statement wording for TS 4 3.4.6.1 was unclear as to whether or not a TS 3.0.3 entry was required.

B. UNIT STATUS AT TIME OF EVENT l At the time of this event, Unit 2 was operating in Mode 1 (power operation) at 100% of rated thermal power. The Containment Condensate Leakage Detection System (CCLDS) was out of service for troubleshooting and repair-of a level indicator. There was no other inoperable equipment which contributed to the occurrence of this event.

1 C. DESCRIPTION OF EVENT On 5-1-90, the Chemistry superintendent was reviewing the status of radiation monitors using the computer in the Chemistry Lab. He noticed that the reading from Containment Atmosphere Gaseous Monitor 2RE-2562C was such that a background update was advisable and directed personnel to check the  !

background value. - A Chemistry foreman advised the Unit Shift Supervisor (USS) that work on 2RE-2562C was required. The USS authorized the work but specified that 2RE-2562C and the Containment Atmosphere Particulate Monitor, 2RE-2562A, could not both be taken out of service simultaneously. Both monitors being out of service in conjunction with the CCLDS would constitute a condition prohibited by TS 3.4.6.1, which reads as follows:

"The following Reactor Coolant System Leakage Detection Systems shall be OPERABLE:

a. The Containment Atmosphere Gaseous or Particulate Radioactivity Monitoring System,
b. The Containment Normal Sumps Level and Reactor Cavity Sump level, and
c. Either the containment air cooler condensate flow rate or a Containment Atmosphere Gaseous or Particulate Radioactivity Monitoring System not taken credit for in 3.4.6.la."

The TS action statement provides for the case where only two of the required Leakage Detection Systems are operable; it does not specifically address the case where less than two Leakage Detection Systems are operable. Since the CCLDS (i.e., the containment air cooler condensate flowrate) was already out of service, either 2RE-2562A or 2RE-2562C had to remain in service in order to comply with the Limiting Condition for Operation as provided in the TS action statement.

NIC Perm 386A (64M

1 go.M A u.. vCuAu.1omo , co EUtItt 4/30/92 -

. LICENSEE EVENT REPORT (LER)

.- TEXT CONTINUATION .(?""',",'o'."!

Ss",W?,Nigg,W,oR'5%"M

^" d '","J',".R'C'"MM' 5CNN

.#7& ,To

="MA"JJi",",.Tuno"'=iWW.'4"#dy 'a 07 MAhAGEMENT AND OUD0ti, WASHINGTON DC 20603.

f ACMIY sAMt (O DoCKlf NV.St R (2) LIR ,dMER (Gl PA04 (3) n s" .

"M.w "V;;:

F VEGP - UNIT 2 o p lo lo jo l4 2 l5 9p -

0 l0] 6 -] q 0 0l3 OF 0l4 ttxtn, - . < =ci., nn I

The Chemistry foreman instructed a technician to proceed with a background, determination on the gaseous channel, per procedure 34317-C, " Operation of-  !

DRMS Containment' Atmosphere Process Monitor 1(2)RE-2562". The technician set up the gaseous channel setpoint parameters for background determination, while the existing setpoint parameters were left unchanged in the particulate channel. At 1303 COT,.the monitor skid containing both the particulate channel and the gaseous channel was then taken to purge, for background determination. This condition diverts sample flow from the containment atmosphere to outside air, such that neither the particulate '

channel (2RE-2562A) nor the gaseous channel (2RE-2562C) are monitoring containment atmosphere. The procedure requires that the Shift Supervisor be i notified that both channels will be out of service for a) proximately two hours. The Chemistry foreman failed to notify the USS t1at both channels would be out of service. ,

While this work was being performed, a spurious high radiation alarm was generated in the control room at-1422 CDT. Investigating this alarm, the control room operators found that both 2RE-2562A and 2RE-2562C were out of .

service. Since the TS action statement does not clearly address the case-where less than two RCS Leakage Detection Systems are operable, the USS consqrvatively entered the TS 3.0.3 action statement, which requires unit shutiown to commence after one hour. At 1513 CDT, 2RE-2562A was returned to serv.ce and the TS 3.0.3 action statement was exited. At 1515 CDT, 2RE-2362C was returned to service. -

D. CAUSE Of EVENT l

The cause of this event was a cognitive personnel error on the part of the Georgia Power Company Chemistry foreman. He failed to recognize that the background determination would render both channels inoperable and he failed to notify the USS (as required by procedure 34317-C) that both channels would be inoperable. There were no unusual characteristics of the work location which contributed to the occurrence of this error.

The cause of the spurious- high radiation alarm could not be determined.

Although the technician was working on the monitor at the time of the high alarm, her actions should not have generated an alarm.

E. ANALYSIS OF EVENT The Containment Normal Sumps level and the Reactor Cavity Sump level indicated no unusual rise during the period of time involved. Additionally, the Containment Area Radiation Monitors showed no abnormal activity during-this time. Based on these considerations, there was no adverse effect on plant safety or public health and safety as a result of this event.

E".C Form 3 A 16401

. . g,,. .M =. A o u uCa m m u u u m o M.. ,,,,,,,,,,,,,,,,,,

tK' int 4 4/30/97 (

c

. LICENSEE EVENT REPORT (LER) ISs".^1',90,18'"t"Jo"'oi%"",,1.o fW ,"o'," M's ~ <

~

TEXT CONTINUATlON  ?"*n't,'o',7. u'Z"ni e'Of'," ",'C,"','!# 'u".' "MTfA PAPE Rwo at T t0N J l'3 Ml O (C OF MANAGEMENT AND SUDGET,WASHINOTON. DC 20603.

F ACILif Y NAME lll DOCKt) NU.dSSR (21 LtR NuMSIR (Gl PA06 (31 Y" NwNe '

.ekEw*eYn axTn, -.,

VEGP - UNIT 2 o ls j o l o l o l4 l2 l 5 9 l 0 0l 0 l 6__0 p 0 l 4 or Op M we%muwnn F. CORRECTIVE ACTIONS

, 1. The chemistry foreman has been counseled regarding the importance of complying with TS requirements.

2. A memo has been sent to appropriate chemistry department personnel describing this event and the correct course of action to be taken in the future.
3. Since this event was discovered as a result of a spurious high alarm, a search of operating records is being performed to determine if previous ,

similar events may have occurred. This- review will be completed by 6-29-90 and any positive results will be reported in a supplemental LER.

4. A review has been initiated to make appropriate clarifications to the TS wording. This review will be completed by 8-1-90.

G. ADDITIONAL INFORMATION

1. Failed Components: 7 None
2. Previous Similar Events:

l LER 50-424/1989-011,-dated May 29, 1989.

The initial conditions for this ~1989 event were different from the i 5-1-90 event. Therefore, the corrective actions were not applicable to l

the prevention of the 5-1-90 event.

LER 50-425/1989-012, dated April 21, 1989.

In this case, an Instrument and Controls technician inadvertently placed 2RE-2562A and 2RE-2562C in purge instead of activating the paper drive on 2RE-2562A by operating the wrong switch.

3. Energy Industry Identification System Code:

Radiation Monitoring System - IL Reactor Coolant System - AB Containment Building - hH NIC Fe m 3 6A 1649)