05000382/LER-1990-009
| ML20056A350 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/01/1990 |
| From: | Labonte W, Mcgaha J ENTERGY CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-90-009, LER-90-9, W3A90-0183, W3A90-183, NUDOCS 9008070098 | |
| Download: ML20056A350 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| 3822090009R00 - NRC Website | |
text
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Ref: 10CRF50.73(a)(2)(1)
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s~ Te' 60,1-T;94650 W3A90-0180 A4.05 QA August.1, 1990 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Reporting of Licensee Event Report Centlement Attached is Licensee Event Report Number LER-90-009-00 for Waterford Steam Electric Station Unit 3. This Licensee Event Report is submitted pursuant to 10CFR50.73(a)(2)(1).
Very truly yours, 5
- /J.R. McCaha
( Plant Manager ~- Nuclear JRM/JEFirk (w/ Attachment) cc Messrs. R.D. Martin J.T. Wheelock - INPO Records Center E.L. Blake W.M. Stevenson D.L. Wigginton NRC Resident Inspectors Office
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' DOCK 4 T NUMSE R (21 P AGE 53' FACILITY NAME HI Waterford Steam Electric Statton Unit 3 01510 [ 010 l 3[812 1}0Fl014 TIT LE I41 Missed Monthly and Quarterly Composite Analysis Due to Personnel Error oTHE R F ACIEITit t INyotvED Isi IvtNT DATE @ Lt h NUMBE R 44' R E POR T D A T E 17'
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NAME TE LEPHONE NUMBE R Ant A CODE W.T. LaBonte, Radiation Protectton Superintendent 5o14 t 4 [ 6 j 4 l -l 3 l1 l419 COMPLE TE ONE Lint p oa E ACH COMPONENT F Altunt DESCniBEo IN THis mE ponT 613i V* C REPOHfAS E "# 8AC REIOR f A LE CAUSE SvlTEM COMPONENT n C Aust S v $'E M COMPONEN' p I I I l i l i I ! 1 1 1 1 I i 1 i l l I I I I 1 ! I I I SuP9LEMENT AL REPORT E RPECT E D ildt MONTH DAY vtAR SvP ui S5lON vi$ rU ves con *0de's f 4PECTIO SUSWSSION DA Pf ND
} l [ j ABST R ACT Il-st eu ' dX smes e approsaere v toteen seg a spece typewretree' < aes: list On July 3, 1990, with Waterford Steam Electric Station operating at 100% power, the batch release liquid effluent sample drawn on June 6, 1990, from waste condensate tank (WCT) B was discovered to have been discarded prior to performing composite analyses. The monthly and quarterly composite analyses could not be perf ormed as required by technical speeification (TS) 4.I1.1.1.I and is therefore reportable under 10CFR50.73 (a)(2)(il as plant operation prohibited by TS.
The root cause of this event is personnel error. The on-shift FlP technician failed to store the sample in the proper location for future composite analyses and the sample was subsequently discarded. To prevent recurrence of this event, the proper handling of effluent liquid samples used for composite analyses was reviewed with all HP technicians. A procedure for liquid effluent sampling is being developed for HP technicians and will ensure proper control and accountability of liquid effluent samples .is maintained. Conservative estimates of the dose to the general public from the unanalyzed radionuclides released from WCT B were well within the quarterly radioactive dose limits established by TS 3.11.1.2 for liquid e.fluents released to unrestricted areas; therefore, this event did not result in an increased risk to the health and safety of the public or plant personnel.
NRC Fovm 36616#F
OfRC PORM 300A U.S.LUCLE R LEiULATORY COMMISSION (649) PPROYtO OMS NO. 3M0104 i 1XTIIts 4/3011 LICENSEE EVENT REPORT (LER) M','gMDN*ugggpgesp,Nge,,3,coug 7gw,T,wg TEXT CONTINUATION C#4",1,,';l $
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OF MANAGEMENT AND SUDGET W A$HINGTON.DC 20603
' ACILif V NAMt 113 DOCK 41 NUMSER (2) LIR NUMSER ISD PA06 (3)
Watsrford Steam m, ,, o v, , , , o ',,,,,o, l_ Elsetric Station Unit 3 p o l6 l0 l0 l0 l 3l8 l 2 9l0 -
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on July 3, 1990, with Waterford Steam Electric Station operating at 100% power, l the batch release liquid effluent sample drawn on June 6,' 1990, from waste j ll condensate tank (WCT) B (EIIS Identifier WD) was discovered to have been l l: 'l lC l
discarded prio: to performing the monthly composite analyses for tritium (H-3) l l
and gross alpha and quarterly composite analyses for strontium (Sr)-89, Sr-90, l and iron (Fe)-55. The composite analyses could not be performed as required i by Technical Specification (TS) 4.11.1.1.1 and is therefore reportable under l 10CFR50.73 (a)(2)(1)(B) as plant operation prohibited by TS.
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1 L WCT B was sampled by the on-shift chemistry technician at 0050 on June 7, 1990, I l l l for routine ~ analyses required for a liquid effluent release from WCT B. The ,
1 l l typical sample volume collected is approximately one gallon. The on-shift l l
health physics (HP) technician analyzed a portion of the sample for the 1 1
. radionuclides required for the issuance of a release permit. The pre-release I sample includes analyses for principle gamma emitters, dissolved and entrained gases. and Iodine (I)-131. The resultant activities were less than the TS limits for effluent release to unrestricted areas. The release permit was l
1 approved on June 7, 1990, and a total of 11,620 gallons of liquid effluent was released from WCT B.
The remaining sample collected for the effluent batch release was transferred I to the hot chemistry lab (EIIS Identifier NF) for storage until composite L. analyses for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 could be performed. The sample was not stored in the proper location inside of the hot chemistry lab l and subsequently discarded by the relieving shift HP technician prior to
! performance of the monthly composite analyses. The root cause of this event is personnel error. The on-shift HP technician failed to store the WCT B sample in the designated location for composite analyses, despite the shelf labeling used to indicate composite sample storage.
NRC Perm 344A dikd91
PORM 3044. . U S. NVCL E Ad 081UCTORY COMulestok l IRPt1El 4/30r3
- LICENSEE EVENT REPORT (LER)-- l#sMo'M80/CWoffA;tiir%eop,i yg,Ygg TEXT CONTINUATION TJ",fi4'.%'M23'J3'."RC,"^,'!# L".' "M Ri
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P APE RWo RE UCYiON J l'3 0 0 IC OF MANAGEMENT AND SUDGE T, WASHINGTON. DC 20603.
i P ACILitY NAM 4 til . DOCIL4T NUMSLR (U ggn NUMegn ts) Pact 13) I W:terford Steam "'" "UEa" Iu*w*sU Elsctric Station Unit 3 ran a N % unc,em.aOn4w(m 0l5l0l0l0l3l8l2 9[0 -
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0l0 013 0F 0 14 Calculations were made to estimate the exposure during the 244 minute release duration of the missed composite sample. The missing sample was conservatively
' 'I assumed to have radioactive levels equal to'the worst case activities for H-3, Sr-89 and Fe-89 from all of the 1990 composite samples taken. The results are -f 1
as followst j i
NUCLIDE' ACTIVITY (uCi/cc) DOSE (mrem) TS QUARTERLY LIMITS (mrem) {
l l
H-3 8.19E-5 1.29E-5 whole 1.5 whole ;
body body >
Sr-89 5.0E-8 2.22E-7 gastronomical 5 any organ intestine ;
r Fe-55 1.3E-5 7.49E-6 liver i Gross alpha and Sr-90 were assumed to have negligible doses since neither radionuclide had any recorded activition greater than the lower limit of j detection in 1990. l To prevent recurrence of this event, the proper handling of effluent liquid samples used for. composite analyses was reviewed with all HP technicians. A {
procedure for liquid effluent samples will be developed by August 31, 1990, to ensure that HP technicians maintain proper control and accountability of liquid effluent sampics. 1 N!C Penn 306A t&49)
_ u.s. WWCL t Aa 2.80ULATORY COMulate0N Ne.t.Ponts EstA _ APPROvtD OMt NO. 31604104
. . 8 KPl%f 8' 4/30/92 LICENSEE EVENT REPORT (LER) llUs*y4c,o'upgg, ggt 3g,g,$o,,Cpyy ,y,w,; wig TEXT CONTINUATION !??'4"4'#,$'"
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P APC RWO RE U TION C 3 60 IC OF MANAOCMENT AND ev0GET WASHINGTON. DC 20603, 9 ACIL11V NAMt nl DOCkti NUMBER (2) LER NUMOGR to PA08 (31
'Wsterford Steam viaa -
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- /#J Elsetric Station Unit 3 .
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The indicated dose calculations show that the estimated dose from the unanalyzed
. radionuclides released from WCT B were well within the quarterly radioactive
, dose limits' established by TS 3.11.1.2 for liquid effluents released to unrestricted areas; therefore, this event did not result in an increased risk l to the health and safety of the public or plant personnel. .l 1 Similiar Events LER 87-025 described a missed weekly Fuel Handling Building (FHB) (EIIS-Identifier ND) normal exhaust ventilation tritium sample due to a failure in j the method used to track due samples. A turnover checklist.was impicmented per l!
HP Directive ~87-1 to ensure TS sample requirements were performed within the l allowed time limit. LER 88-029 reported a missing weekly particulate and iodine analyses from the FHB normal ventilation exhaust due to cognitive l personnel error in:not completing the turnover checklist properly, i
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Plant
Contact:
W.T. LaBonte, Radiation Protection Superintendent, 504/464-3149 ;
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GL.C Fenn 306A HL80: