ML19351A465

LER 89-021-00:on 891111,when Low Level Radwaste Water in Waste Condensate Tank Aligned to Be Released,Discovered That Radiation Monitor Inoperable for Duration of Release.Caused by Personnel Error.Procedure revised.W/891211 Ltr

ML19351A465
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/11/1989
From:	Ewing E, Millar D ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN128907, LER-89-021-01, LER-89-21-1, NUDOCS 8912180064
Download: ML19351A465 (4)

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December 11, 1989 2CAN128967 U. S. Nuclear Regulatory Commission Document Control Desk f Mail Station P1-137 Washington, D. C. 20555 Arkansas Nuclear One - Unit 2

$UBJECT:

Docket No. 50-368 License No. NPF-6 Licensee Event Report No. 50-368/89-021-00 Gentlemen: .

In accordance with 10CFR50.73(a)(2)(1)(B), attached is the subject report regarding a personnel error which caused a liquid effluent radiation monitor to be inoperable resulting in an unmonitored radioactive liquid release.

Very truly yours, S

E. C. Ewing General Manager, Technical Support and Assessment ECE/DM/sgw attachme.G cc: Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 INPO Records Center 1500 Circle 75 Parkway Atlanta, GA 30339-3064 l

l 8912100064 891211 JC gyg PDR ADOCK 05000368 S PDC II

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, Form 1062.01A ;

kkC Fore 366 U.S. Nuclear Regulatory Commission ,

(9 83) Approved DMB No. 3150-0104  :

. Expires: 8/31/85 L!CEN$(( [ VENT R[P0RT (L E R)

FACILITY k%ME (1) Arkansas huclear one Unit Two 100CKET NUMB [R (2) IFAGL (3) 10151010101 31 61 B1110Fl013 TITLE (4) Personnel Error caused a Liquid Ef fluent Radiation Monitor to be Inoperable Resulting in an Unmonitored Radioactive Liquid Release (VEKT DATI (5) i L(R NJMBER (6) l REPORT DATE (7) i OTHER F ACILIT115 !NVOLVED (6)

.I i i i l$equentiell IRevisioni l l l l Monthi Day lYear lYear I i Number I i Number IMonth! Day (Year i Feetiity Names IDocket Number (s)

I i l I i i i l I i i 10151010101 I i 11 11 11 11 81 91 81 91--I Of 21 11--I 01 Of 11 21 Il 11 81 91 10151010101 1 I OPERATING l iTHIS R[ PORT 15 5UBMITTED PUR$UANT TO THE REQUIREMENT 5 0F 10 CFR 6:  !

MODE (9) 1 El (Check one or more of the followino) (11)

P0wtRI l__l 20.402(b) l_,1 20.405(c) 1 _l 50.73(a)(2)(iv) l_,1 73.71(b)

LIVILI l _l 20.405(a)(1)(1) l__I 50.36(c)(1) 1._l 50.73(a)(2)(v) l I 73.71(c) ,

(10) 1010101 1 20.405(a)(1)(ii) 1 _l 50.36(c)(2) l I 50.73(a)(2)(v11) l__I Other (Specify in '

1 _I 20.405(a)(1)(111) 1,xt 50.73(a)(2)(1) 1 _l 50.73(a)(2)(v111)(A)l Abstract below and l l 20.405(a)(1)(iv) l_,1 50.73(a)(2)(11) 1 _t 50.73(a)(2)(viii)(B)l in Text, NRC form i 1 20,405(a)(1)(v) I i 50.73(a)(2)(111) I i 50.73(a)(2)(x) l 366A)

LICEN5Et CONTACT FOR TH15 LER (12)

Name i Telephone Number lArea 1 Dana Miller. Nuclear Safety and Licensing Specialist l Code l 1610111916141-13111010 CDNPLETE ON[ LINE FOR ( ACH COMPONENT F AILURf DESCRIBID IN TH15 RE PORT (13) i i i IReportabiel I i l i IReportabiel Causel$ysteel Component IManufacturert to NPRO$ l ICausel$ysteel Component lNanuf acturert to NPRO$ 1 1 I I i l l I J l I i l I I I I I i l ! I i 1 i 1 ! I I I i 1 I l 1 1 l l l l l l l l 1 l l 1 1 1 i i l i i l I l I i i i I I I I 1 i l i 1 i

$UPPL[M[N" REPORT EXPICTED (la) i EXPICTED l Montnl Day lvear

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_l l Yes (if yes complete Exceeted subeMssion Date) til No l DATE (15) l l i l l I ABSTRACT (Limit to 1400 spaces, i.e., approximately fifteen single-space typewritten lines) (16) on November 10. 1989, a Weste Condsnsate Tank which contained low level radioactive waste water was aligned to be released. A radiation monitor in the discharge flowpath provides a signal to close a control valve in the unlikely event a high level of activity is sensed at any time during the release.

With the use of a procedure, a Senior Reactor Operator located in the Unit Two Control Room coordinated with a Weste Control Operator to align the system and test the radiation monitor. At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on November 11. 1989 when the release was completed it was recognized that the radiation monitor had not been operable for the duration of the release. The root cause of this event was personnel error. A licensed operator failed to place a multipurpose selector switch on the control cabinet of the radiation honitor in the operate position prior to the start of the release. The event was discussed with the individual by his Shift Supervisor. The curie content of the liquid in the tank was analyzed by Chemistry personnel prior to releasing the contents of the tank and the quarterly and annual whole body and organ doses established by Technical $pecifications were not exceeded. Therefore, there were no significant safety concerns. Technical Specifications require that a radiation monitor in the discharge flowpath of a liquid radioactive release be operable during a relsase. This event is therefore reporta51e pursuant to 10CFR50.73(a)(2)(1)(B).

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i Form 1062.01B i N6C Fom 366A U.S. Nuclear Regulatory Commission  ;

(9 83) Approved OMB No. 3150 0104  ;

Expires: 8/31/85 ^

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) IDOCAET NUMBER (2) l LER NUMB [R (6) [ FAGE (3) s l l l l$equentiell lRevisient l Arkansas Nuclear One, Unit Two l l Yearl i Number I i Number l 10101010101 31 61 81 61 91--I 01 21 Il--t 01 0101210F1013 TEXT (If more space is required, use additional NRC Fom 366A's) (17) i A. Plant Status At the time of occurrence of this event Arkansas Nuclear One, Unit Two ( ANO 2) was in Mode $

(Cold $hutdown). The seventh refueling outage, which began September 25, 1989, was in progress.  ;

B. Event Description The Weste Management $ystem (WMS) [WD) is designed to provide controlled collection, handling, treatment, and disposal of low level radioactive waste water from plant operation. Liquid waste influents to the WM5 include those from chemical lantatory drains, decontaminated area drains, sampling drains, equipment drains and building sumps which are collected in storage tanks. Prior to releasing a tank of liquid waste water, the tank is isolated and placed on recirculation by an ANO 2 Weste Control Operator and a release request permit is submitted to Chemistry. After sufficient time on recirculation, a sample of the tank contents is obtained and analyzed by Chemistry personnel to determine the amount and type of radioisotopes in the tank. Chemistry personnel compare the sample results with limits established in Technical $pecifications. When the sample results are acceptable, en AND-2 $hift Supervisor reviews the release permit and authorizes the release of the contents of the tank. An AND-2 Weste Control Operator coordinates with ANO-2 Control Room personnel to perform the low level radioactive release. The contents of the tank are pumped to the Arkansas Nuclear One, Unit One (AND*1) circulating water discharge fiume through a radiation monitor (IL) which monitors activity and will automatically terminate the release by  ;

closing a control valve if s specified level of activity is sensed. Based upon the curie content of the tank as analyzed by Chemistry and the dilution flowrote provided by AND-1 Circulating Water Pumps, a setpoint is established to provide a signal to close the control valve, thereby, ensuring the flowpath is isolated in the unlikely event high activity of the waste water is detected by the radiation monitor located in the discharge flowpath.

Prior to releasing the contents of a WMS tank, the setpoint provided by Chemistry is set at the control cabinet of the radiation monitor. The radiation monitor located in the discharge line is verified by procedure to be operable by performing a source check and ensuring the control valve in the discharge line closes upon sensing high radiation 0y simulating a high radiation condition.

After the radiation monitor is verified operable, the WMS is aligned to begin the release.

After the Chemistry analysis and $hift Supervisor review and approval were completed, at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> on November 10, 1989, a liquid release en 'B' Weste Condensate Tank (2T21B) commenced.

The procedure for perfJrming and aligning for the release was followed and at 0300 on November 11, 1989, the release was completed. Upon securing from the release, a chart recorder which monitors

the flowrote and the activity of the release is notated with information regarding the release.

It was recognited at this time that the indicated activity level had not changed for the dutation of the release. Further investigation by Control Room personnel resulted in finding that the radiation neonitor had been left in a reset position for the duration of the release and therefore, the release was unmonitored.

C. $afety significance Chemistry personnel maintain cumulative quarterly and annual whole body and organ doses that are

, expected to be received by members of the general public as a result of the release of various l

radioactive liquids *.o the Au0-1 circulating water discharge flume. Prior to releasing the contents of the tank, these totals are compared to the limits established by Technical

$pecifications to ensure no ifmits are exceeded. Cumulative totals from this release did not result in exceeding the limits of Technical $pecifications, and therefore, the radiological doses as a result of this unmonitored liquid release did not pose any increased hazard to members of the general public. No significant safety concerns existed.

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Fore 1062.01B NRC F0re B664 U.S. Nuclear Regulatory Commission (9-83) Approved 046 No. 3150-01D4 Expiresi B/31/85 LICENSEE EVENT REPORT <(LER) TEXT CONTINUATION FACILITY N4ME (1) IDOCKET NUMBER (2) I tER NJMBFR (6) i PAGE (3) l l l 15equentiell (Revision l Arkansas Nuclear One, Unit Two l I Yearl i Number i I humber l 10151010101 31 61 81 81 91--I 01 21 11--I 01 0101310Fl013 TEXT (If more space is required, use accitional NRC Fore 366A's) (17)

D. Root Cause The rect cause of this event was personnel error. In order to determine operability of the radiation monitor, a multipurpose selector switch on the face of the cor. trol cabinet for the radiation monitor is selected to various positions to verify the radiation monitor responds as oesi red. The radiation monitor is operable only when the selector switch is placed in the operate position. The procedure used to perfore the radiation monitor operability test requires the operator to initial the step verifying the switch has been returned to the operate position.

However, due to inattention to detal), the procedure step was initialed as being completed without actually being performed. The switch was inappropriately left in the reset position. A Senior Reactor 09erator was responsible for verifying radiation e.onitor operability.

E. Basis for Reportability Technical Specification 3.3.3.10 requires that a radiation moniter in a liquid effluent pathway be operable anytime releases are in progress via tne pathway. Therefore, this event is reportable pursuant to 10CFR50.73(a)(2)(1)(B), operation prohibited by Technical Specifications.

On November 11, 1989 at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, the NRC was notified of this event in accordance with 10CFR50.72(b)(2)(iii).

F. Corrective Actions This event was discussed with the Senior Rasetor Operator by his Shift Supervisor. Included in the discussion was the need to improve attention to detail when performing the operability verification for the radiation monitor.

A procedure revision to the release permit is being made to ensure the multipurpose selector switch for the radiation monitor is in the operate position by the performance of an irdependent verification. This revision is expected to be completed by December 21, 1989.

During the presently scheouled Operations training cycle, the Unit Two Plant Manager is providing a review of this event and previous operational events to help improve overall attention to detail, to esemphasize the responsibilities of each licensed individual and to provide Operations management expectations. This training will be completed by December 31, 1989.

G. Additional Information There have been no previously reported events regarding unmonitored liquid radioactive releases.

Energy Industry Identification Systee (E115) codes are identified in the text by (XX).

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