05000295/LER-1990-021, :on 900922,gas Sample Not Analyzed Due to Personnel Error

:on 900922,gas Sample Not Analyzed Due to Personnel Error

ML20058A726
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	10/22/1990
From:	Geyer J, Joyce T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-021, LER-90-21, NUDOCS 9010290123
Download: ML20058A726 (4)

LER-1990-021, on 900922,gas Sample Not Analyzed Due to Personnel Error

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(x)
2951990021R00 - NRC Website

text

......

Commonwealth Edison NN"d* aNNSinan-I Zion, lilinois 60099 Telephone 708 / 746 2084 I

x October 22, 1990-

{

U.S. Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555

Dear Sir:

'.ne enclosed Licensee Event Report' number 90-021-00, Docket No.

50-295/DPP-39 from Z1on Generating Station-i', being transmitted to you in accordance with the requirements of 10CFR50.73(a)(2)(1), which requires a 30 day written report when a condition has occurred that is prohibited by the plant's Technical Specifications.

i Very truly-yours,

$Q d

i T. P. Joyce f Station Manager Zion Generating Station TPJ/dff

Enclosure:

Licensee Event Report cc: NRC Region III Administrator NRC Resident Inspector INPO Record Center CECO Distribution List 4

1 9010296123 901022 PDR ADOCK 05000296 109 D kl

o LICENSEE EVENT REPORT (LER)

Form Rev 2.0 facility Nanje (1)

Docket Number (2) lage (3) do!L. Unit 1 0151010_[D_j2l915 1lofl0 3

litle (4) 081.jampltlotAnalyreiDue_Inle.r.sonnel Error

__CvtaLQate (5)

LLRJumber (6)

REE2LLDate (7)

_Qther Facilities Involved (8)

Honth Day Year Year fj/j Sequential

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/ Revision Month Day Year Facility Names Docket Numbir(s)

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/j]_f_junkgL

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Number Zion Unit 2 015101010131D_l_4 ala_ LlL Llo_ 9 !0_

o l 2 11 OLO 110 21 2 91 0 l l l l l l l OPERATDIG (Check one or_more of the followino) (11)

H0DE (9) 1 20.402(b) 20.405(c) 50.73(a)(2)(iv) 75.71(b)

POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vil)

Other (Specify

_1 19) 9 9

20.405(a)(1)(ill) l_ 50.73(a)(2)(1) 50.73(a)(2)(vill)(A) in Abstract

///,/,///////,/////////,//////

20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(vili)(B) below and in

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20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

Text)

LICENSEE CONTACTl0R THIS LER (12)

Name TELEPH01E NUMBER AREA CODE t ohann Geyer. Radiation Protection ext.

2674 710l8 714,[6l-12101814 l

CQfiP.LflLQu(llNE FOR EACH CQHEDM N FAILURE DESCRIBED _ItLIlijj lEPORT (13)

{ REPORTABLE

CAUSE

SYSTEM COMP 0HEHT MANUFAC-REPORTABLE

CAUSE

SYSTEM COMPONENT MANUFAC-TURER TO NPRDS TURER TO NPRDS I

l l l l

!. I N

l I l l l l l I

I I I I I I I

I I I I I I SUPPLEMENTAL REPORT EXPECTED (14)

Expected Month LDay ! Year Submlssion j g lg l11LLILytL_Canlete EXPECTED SUBMISSION DATE) 71 NO Date (15)

Radiation monitors I and 2 RT-PR12 (Reactor Vessel Leak Detection Radiation Monitors) were out of service, requiring shif tly air samples to be taken and analyzed. On 9/22/90-on the 3-11 pm shift, the samples were taken, but inadvertantly were not analyzed. This is reportable under 10CFR50.73(A)(2)(1)(B).

The cause of this event was procedural deficiency.

There was no safety significance to this event, as redundant monitoring equipment was operable.

Co rective actions include tailgate sessions with both Radiation and Chemistry Technicians, and a procedure change to require signatures when any sample is transferred between Radiation Protection Department and Chemistry Department.

l l

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LICENSEE EYENT REPORULER) TEXT CONIINUATION Form Rev 2.0 FACILITY NAME (1)

DOCKET NUMBER (2)

_LER HUPSER (6)

Page_.ilL_,_

Year Sequential Revision Number Number lion _ Unit 1 QJ 510l_LLQ_ll[1 1J_l0 Oil l 'l

.0l L L{L_0F 01 3 TEXT Energy Industry Identification System (Ells) codes are identified in the text as (XX)

A.

CONDITION PRIOR TO EVENT

H0DE 1

_ Power RX Power,_91L RCS (AB) Temperature / Pressure 559 *F/2235 psig B.

DESCRIPTION OF EVENT

The shiftly out of service samples for 1 and 2 RT-PR12 (Reactor Vessel Leak Detection Radiation Monitors) were not analyzed for one shift on 9/22/90. At the time 1 and 2 RT-PR12 were out of service.

This condition requires shif tly gas samples f rom 1 and 2 RIA-PR40 or the containment. A Radiation Technician obtained the gas samples from 1 and 2 RIA-PR40 at 15:10 on 9/22/90. He delivered the samples to the counting room for analysis. The Chemistry Technician responsible for the Counting Room was not

- j present at the time of delivery. The Chemistry Technician operating the counting room failed to recognize that the samples required counting, and consequently did not perform the appropriate analysis. The gas samples were later discarded.

C.

AP1ABIMLCAUILOF EVENT The root cause of this event was lack of administrative control over the gas sample. No formal means existed of transferring air samples f rom the Radiation Protection Department (who draws the sample), to the Chemistry Department (who analyzes the sample). This transfer has occurred informally in the past. This lack of a procedure created the event.

A contributing cause was personnel error by the Radiation Technician on shift. In the review of the out of service radiation monitor survelliance sheets, he failed to notice that the isotopic results for this monitor were missing.

D.

SAFETY ANALYSIS OF EVENT The 1 and 2 RT-PR12 monitors serve as one means of detecting reactor vessel ~1eakage. They-perform

- l no accident mitigation or control functions. Due to the sample point proximity to the vessel, these monitors are considered sensitive indicators of vessel leakage. Thus, when these monitors are inoperable, some loss of sensitivity in vessel leakage detection ability occurs. However, other means of detecting reactor vessel leakage (Volume Control Tank level recorder, Containment Sump level recorder, etc.) were operable at the time this sample analysis was missed. Thus no safety consequenses.

resulted from this event.

E.

CORRECTIVE ACTIONS

The event was reviewed with both the Chemistry and Radiction Technicians. The Radiation Protection Department revised "Alr Sampling in Radiologically Controlled Areas" ZRP 1801-1 and created a new procedure " Air Sample Evaluation" ZRP 1801-3. A radiological sample sheet will now accompany each out of service sample to the counting room. The Radiation Technician must deliver each sample to the Chemistry Technician, and the Chemistry Technician must sign each sample sheet to acknowledge receipt of each sample. In addition, verification of sample analysis by Radiation Protection Supervision is documented on the sample sheet.

10940

m LICENSEE EVEP{I_jtEPORT (LER) TEXT C0ft{llt(VAIION form Rey LD.

FACILITY NAME (1)

DOCKET NUPEER (2)

LER NUttetfLift)

_ f. age _11L _

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Sequential //j/

/

Revision o

Year' ff ff

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Number -

//

Number

.21pft Unit 1 0 1 5 1 0 1 0 1 0 1 21 91 5 9 10 01 2 l l_

01 0 0 13 0F._Q.L3 TEXT Energy Industry Identification System (Ell 5) codes are identified in the text as [XX)

I F.

11EY10VS EVENTS None G.

C0tLPONENT FAILURE DATA None i

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