05000029/LER-1977-055, Forwards LER 77-055/03L-0.Detailed Event Analysis Encl

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Forwards LER 77-055/03L-0.Detailed Event Analysis Encl
ML20038A073
Person / Time
Site: Yankee Rowe
Issue date: 01/16/1978
From: Autio H
YANKEE ATOMIC ELECTRIC CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20038A074 List:
References
NUDOCS 8109170315
Download: ML20038A073 (5)
v • d • e


LER-1977-055, Forwards LER 77-055/03L-0.Detailed Event Analysis Encl
Event date:
Report date:
0291977055R00 - NRC Website
v • d • e

text

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UL URUU A TG Dl0 ELUG TRES GG G P/10 V

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l January 16, 1978

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!!r. B. II. Grier, Director

'I U.S. t'ucicar Regulatory Co: mission Office of Inspection and Enforcement '

l llegion 1 631 Park Avenue King of Prussia, Pennsylvania.19406 Subject: Reportable Occurrence 50-29/77-55/03L-0 Dose Equivalent Iodine 131 > 1 p Ci/mi

Dear ?4r. Gricr:

In necordaice nith Technical Specifications, Section 6.9.4.b, the nttached I,icensco Event Report is hereby submitted.

Very truly yours, l

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!!arbart A. Autio Plant Superintendent i

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Enclosure:

k cc: [33] Ulrector, Office of Inn,.cction and linforcer.cnt l

U.S. !!uclear licgulatory Ceraissicn t'achingten, D.C.

20555 i

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Director, Office of thnancment Infonntlen G Prograra Ccatrol U.S. I!ucicar Itegulatory Ceraission

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ljR 77-55/03L-0 Yankee Atc.alc !!!cetric Company l

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t IJENT l)ESCRIPTION A"D PROBABLE CONSEQiffNCES Ihring an approxirate 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shutdaten for operator training, the dose equivalent Iodine-131 concentration of the primary coolant system exceeded ILCi/ml.

Technical Specification 3.4.7 limits the specific activity of the primary coolant systen to < 1.0 pCi/ gram Dose Equiv-alent 1-131, i

j 1he reactor was operatinr, at 100', pc.eer prior to the shutdown. Normal

- j cleanup flou through the primary coolant purification systea was abcut 25 ppa. 'ihere was no degassing operations prior to or during the shutdow.

i The doce equivalent iodine concentratica exceeded 1.0 uCi/gra a for one ccatinuous interval of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />, lhe maxirnt concentratica teasured uas 2.4 pCi/ gram D.E.1-131 approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after shu tdo'..n.

There after the primary ccolant purification syste:a reduced i

the D.E.1-131 cencrat ratica to less than 1.0 pCi/ gram in 16 hotes.

The attached table u~ urires the prinary coolant specific activities during the peried.

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During the evcat all plant systcar, ft acticned norrally. 1here tras

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no 1 css of inter,rity in any systca ccataining fissica prcJucts, thus, thare was no adverce affect ca the public h.'alth and safety.

CMBE DESCRIPflON N:D COB"ECTIVil ACTIE 3 i

lhe root cause of the probica is acstad to ha a cladding defect in a sin $e fuel red frca a sccend cycle Euan :,uricar Cc..;my fuel nsw.bly.

1his possii>1e def(ct was su: p;cted < ad enluated during no 1977 Core XII refuelinr cutane.

It is su;p;ctcd that the cculo of the d:'fect is the failure of the t.cided cud eco of cae fuci red.

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possibility of a cladling defect, cnJ tha c: crqu.tcc during rub-equent pc::er eparation were ev::!uatcd by L Cw < nd by E::'en

?:uc]cer Company.

iheir report, 21-:,F-77-33, pudicted fi: ;ica pra:h::t ccncentratics in the prin:ry cool: it c3 a result of a sin:.le l

gross c1:'dding defect.

Their prudicticas ~ greed uith thu. e of Y;.:0.y;e's, and, in general, uith the nearuicd fissica lu ch:t cc:~:catratico in the primary ccolunt during the filet fcur unths of pu..cr cparaticn.

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So called spihes are a 1:c11 knom changes in reactor thernal power. phenc;:.enen associated with rapid l

In order to uinini:e reoccurrence of the prob 1cn during Core Xill, reactor power will be adjusted nradually.

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i It is believed that the suspected defective fuel rod is contained in a second cycle assa;bly and will be removed during the Cere XIll, XIV refceling, scheduled for October 1973.

This event was revie..cd by the Plant Operational Review Co:mittec i

at Mocting No. 73-1 on January 0,1978, with no additienal cc=Tnts j

or reco:=cndation.

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