ML20084D185

AO 50-219/74/34:on 740529,indications of Coolant Leakage Existing in Area of in-core Flux Monitor Reactor Vessel Housing Noted.Cause Not Determined

ML20084D185
Person / Time
Site:	Oyster Creek
Issue date:	05/30/1974
From:	Carroll J, Sullivan J JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20084D093	List: ML20084D185
References
AO-50-219-74-34, NUDOCS 8304080489
Download: ML20084D185 (4)

Text

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Q Initial Telephone Date of P.cport Date:

5/30 Occurren ce :

5/29/74 i

I Initial Written Time of 5/30/74 Occurrence:

1900 Reportgate:

l OYSTER CREEK NUCLEAR GENERATING STATION FORKED RIVER, NEh' JERSEY 08731 i

Abnormal Occurrence j

i Report No. 50-219/74/ 34

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J IDE.YrIFICATION Violation of the Technical Specifications, paragraph N/A i

OF OCCURRENCE:

Indications of coolant Icakage existing in the area of an incore flux monitor reactor vessel housing located at core coor-dinate 28-05.

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'Ihis event is considered to be an abnormal occurrence as de-

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j fined in the Technical Specifications, paragraph _1.15E 1

j CONDITIONS PRIOR l

TO OCCURRENCE:

__ Steady State Power Routine Shutdown

]

Ilot Standby Operation j

Cold Shutdown Load Changes During

[x Rcfueling Shutdown Routino Power Operation Routine Startup Other (Specif>)

l Ope ation l

We reacter was in the REFUEL mode during a hydrostatic test l

at 850 psig pressure and with coolant temperature approximately i

155 F.

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l DESCRIPTION On Tuesday, May 28, 1974, during a scheduled reactor vessel 0F OCCURRl!NCE:

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hydrostatic test to inspect the pressure boundary following j

refueling maintenance activities, leakage was observed in the vicinity of an incore flux monitor tube located at the bottom I

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j of the reactor vessel.

Further investigation conducted on

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j' Wednesday, May 29, 1974, showed evidence of possible Icakage i

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in the area of an incore flux monitor housing penetration

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V Abnormal Occurrence Report No. 50-219/74/34 Page 2 J

r located in the reactor vessel bottom head.

A second hydro-static test was conducted at a pressure of 857 psig at approxi-mately 7:00 p.m. on May 29, 19 74, whereupon, water was observed leaking between the monitor housing and the reactor vessel.

The leakage was measured under the conditions of 850 psig with a temperature of 164 F, and calculated to be on the order of approximately 0.02 gallons per hour.

APPARENT CAUSE Design Procedure 5

0F OCCURRENCE :

Manufacture Unusual Service Condition Installation /

Inc. Environmental Construction Component Fallure Operator Other (Specify)

The cause of this event has yet to be determined.

ANALYSIS OF As stated in Uncan a ondren; 437, ; p t.1;;;3 g;;;...,..

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OCCURRENCE :

flux monitor tube would result in vessel leakage at a rate which would not cause excessive cladding temperatures and for whidi core reflooding is possible by engineered safety features.

This situation is less severe than the design basis accident.

To determine the consequences of a weld failure at a housing for an in-core monitor tube, it is assumed that the weld between the housing and the reactor vessel bottom head fails, allowing the housing and the in-core monitor tube to be ejected from the vessel. The hole provided in the bottom head for the housing has a diameter of two inches; this is the assumed break si:c.

The hole has a break area of.0218 ft2 Assuming worst condi-tions, this results in peak clad temperatures less than 1000 F, l

as updated in FDSAR Amendment #67.

This value is well within

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acceptable limits of the applicable ECCS criteria.

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.@ normal Occurrence Report No. 50-219/74/34 Page 3

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e CORRECTI\\Ti lhe nuclear steam supply vendor and the reactor vessel manu-ACTION :

facturer have been contacted with regard to this condition.

Discussion will ensue as to the proper course of action to be taken to resolve this catter, Reco:xnendations will be forth-coming pending complete review of this event by the Plant Opera-tions Review Committee.

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Date:

5/30/74

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Prepared by:

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s To:

James P. O'Reilly cf 7...

Pirectorate of Regulatory Operations

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Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 From:

Jersey Central Power S Light Company Oyster Creek Nuclear Generating Station, Docket #50-219 s

Forked River, New Jersey 08731

Subject:

Abnormal Occurrence Report No. 50-219/74/34

'Ihe following is a prelitinary report being submitted in co::pliance with the Technical Specifications paragraph 6.6.2.

Preliminary Approval:

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5/30/74

. T. Carroll, Jr. '/

Date cc:

Mr. A. Giambusso,

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ATOMIC Et4tRGY COMMISSION j

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cancevon a,t or ac c.utaron e occ amisont M

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11. D. Thornburg, Chief 1

3 Field Support and Enforcement Branch h

Directorate of Regulatory Operations, IIQ JERSEY CENTKAL PO'ER AND LIGHT COPJAtN i

OYSTER CREEK - IMit ADN0!UiiL OCCURRPEE A0 74-34 The subject abnormal occurrence report is forwarded for action, i

Based on our review of the licensee's preliminary report, that RO Ileadquarters transfer the lead responsibility to DL for review it is recor. mended l

cvaluation of this penetration failure involving primary coolant and l

at the reactor vessel's bottom head.

leakage to evaluate potential genaric aspects of this probleta. Additionally, DL should be requestcJ RO:1 will continue to provide field follow up and review of any forthcoming corrective measures by the licensee in this ratter.

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. Brunner, Chief Re ctor Operations Branch Enclosure eO 74-34 4\\ +,' s,Y 1

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Jtits P. O'Imilly Directorato of Tegulatory Operations Ttol:lon I 631 Park Avente King of Prussic, Permsylvania 19406-From:.

Jersoy Contral Power G 1,1ght Corguny-0/ ster cmok fluolcar Gonorating Statico, Dotlet 850-219 Posked River, How.Jorsey 08751 SWjoott Abnonual Occurrento Roport 110. 50-210/74/34 I

1ho following is a]elidnny uport boinc senitted in en)plianco ulth the 'lbchnical f>pocificat10,1s I

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phragraph 6.6;2.

Prolic.inary Approval l

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OYSTflR CRl!BK HUCl,BAR GENnRATIllG STATION FORXI!D RIV83, NnN JfiRS!3Y 08731 KS N

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Abnormal occurrenco Report No. 50-219f/4/ 34 p;

IOUNTIFICATION

'VLolatLon of the Tochnical Spocifications, paragraph H/A b@;,

01) OCCURRl!HCB:

Indications of coolnnt leakago existinig in the aron or on h[i Y incoro flux tntitor reactor vossol housing located at coro coor-dinato 28 05 U-Fr V

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'!his event is considorod to be an abnormal occurronco as do-y <.

fined in the Tochnical Spacifications, paragraph I'.158 Ih CO,'lDITIONS PRIOR I lp ;.

ky',/ TO OCCURROHCfi:

Stoady Stato Power Routino Shutdown i

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_llot Standby Oporation i

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The reactor was in the PMIRR uodo during a hydrostatic test I

l at 850.psig pressure and with coolant tecporaturo approxltntoly

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OUSCRIPTION Cn Tuesday, Hay 28, 1974, during a scheduled ronctor vosso['l" -

p" 0F OCCURRUNClit t

f hydrostatic tost to inspect thd prostur'o boundary following h

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refueling maintenanco activittos, lonkago was oYsorved in the g

vicinity of on incore flux conitor tubo located at the bottom w

l M of the ionctor vossol. 'Further investigation conducted on p(b Wadnosday, Hay. 29,1974, showed eviIlonce of possible loakago u

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. in the aron of an. Incore flux monitor' housing podottation pi d[

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located in iho-reactor-vessol bottoa hon 0 s

A second hydro-d static' test was 'ccoduc'ted at a pressuro of 850 psig at ppml-

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t observed looking between tho ruitor housing and the reactor j

i vossol.

The Icaloge was nonsured under the ecoditiont of 850 3j A

. psig with a torporaturo of'164*P, and calculated:to bo on,thn j

order of approvisatoly 0.02 gallons por hour.

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Donign Procedure lip OCCU10M G Hanufacture Unusual Service Conditico

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Inn ta116 tion /,

Inca.Environrental-Conntruction Operator Corponent Failuro-

~ Otherv(Specify) g 1ho cause of this oyent. has yet to bo deteminods WM3 SIS OP.

As stbted in PIGAR Anendmnt 837, a pos'ulkted failure of the t

)CCUPJiulCB f

.'J flux monitor ttbo would ronuit in vossololenlogo at a rato Y.e which would not causo.excessivo cladding <.to:Toraturoc cad for eids coro rofloodirig is popsible by ensinoured safety fontures.

i lhis situatice is loss novem than the design basis ' accident.

To detomine the ecosoqtences of a wold fUlum at a housing for'an in coro n(citor ttko, it, ip asne:cd that the veld botWcon o

the housing and the reactor vosuol bottoa hend fails, ollcuing,,

the housing and the in-core monitor tubo to Uo ojected froa the vossol.

.'iho holo providod in tho botton hond for the housing

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has a ditator of two inchos; this is the asstimod break size.

1ho hole has a bronk area of.0218'ft. Assuming worst condi-2 tion,s,.this result $ in peak clad torporatures loss them 1000*P, es updAtod in PIGAR Arendient f67.

7his valtki is voll uithin i

acooptablo liutts of the opplienblo HOCS critoria.

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f acturor have boon contacted with rocard'to this t<oditico.

gb 0'; Q Dlacuoton will ensuo os to t.ho proper courso of stetico to to li.

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token to ror401vo this asutter. Recotanondations will be furth-j j cottlig pending: corpleto rovics of this event"by the Plttnt Opera.

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TO:

B. H. Grier. R rs t.r r, /.

c:: rn:crnni. For" A.

Action Code F0# (/(j Creek) liare of I.icennec and racility Jersey Central Power and Light Co.(Oyster /

I Docket ::o. o r Licen..e t'o.

50-219 Title Transfer of Responsibility Origin Region I Date nec'd 5/ 31/ 74 B.

PS!.I:I; liranch Coordinator:

Bryan Dreher _ X II. D. Thornburg 1:111s Paulua G. Gewer C.

Actton Pequested of:

X ADRE:rP

_ !!sPPOB EPd RPH ADco OB Cn TAB ODE REGIO::

Date nequented 6/6/74 Corpletion Requented by __7/3/74 neference __ Memo - E. J. Brunner to H. D. Thornburs dated 5/31/_7_4_,

7 and A0-50-219/74-34 D.

Action nequested:

Please review above referenced documents and if agreeable transfer lead responsibility to DL.

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Date Actica Completed close-out (Date t.::ethod)

Coteenta:

If completion date in not conciatent with your work schedule, please let us know.

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V liarold 1. Thornburg, Chief Field Support & Enforcement > ranch Directorate of Regulatory 0,nerations

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