ML20107E244

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Forwards Preliminary AO Rept 50-219/74/6
ML20107E244
Person / Time
Site: Oyster Creek
Issue date: 01/23/1974
From: Carroll J
JERSEY CENTRAL POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 NUDOCS 9604190256
Download: ML20107E244 (1)


Text

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'To:

James P. O'Reilly 11irectorate of Regulatory Operations Region I 631 Park Avenue Ks,g of Prussia, Pennsylvania 19406 Prom:

Jersey Central Power G Light Company Dyster Creek Nuclear Generating Station Docket 750-219 Forked River, New Jersey 08731 s

Subject:

Abnornal occurrence Report No. 50-219/74/ 6- _

The following is a preliminary report being submitted '

in compliance with the Technical Specifications paragrpph 6.6.2, Pre 31tninary Approval:

/84f 3/ 74 J. T. Carrob, Jr.

V Dato cc: Mr. A. Gianhusso.

9604190256 960213 PDR FOIA DEKOK95-258 PDR

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Date:

~1/ /74 e rences 1000 2N/0YSTER CREEK NUCLEAR GENY[NG3kkTl0N Ap4 FORKED RIVER, NEW JERSEY 08731 Abnorme!' Occurrence Raport No. 50-219/74/ 6 ItlENTIFICATION Violation of the Technical Specifications, paragraph 3.5.A.6.

-OP OCCURRENCE:

Twenty-four hours after piscing the mode selector switch into RUN,' the torus atmosphefe. contained 6.24 0, which is above 2

the limit pf 5.0% 0 -

2 This event is considered to be an abnormal occurrence as de-fined in the Technical Specifications, paragraph 1.158 CXWb1TIONS PRIOk TO OCCURRhNCE:

Steady State Power Routsne 1utdown 9

Hot Standby Operation Cold Shutdown Load Otanges buring Refueling Shutdown

- Routine Power Operation 7 Routine Startup

_ Other (Specify)

Operation Reactor Power

- 1075 MWt c340 Mfe S

- 7.4 X IO Recirculation Flow

- 3.8 X 10' gpm lb/hr Fet;dwater Flow 0

Feedy:stor Tenperature - 275 P Renctor Pressure

- 1020 psig keactor Water Level

- 78" Yaw ay t

DESCRIPTION At 2030 on Januazy 21, 1974, the primary containment inerting OF OCCURRENCE process was initiated by first performing n calibration on the torus /drywo11 02 analyzer, as por the operating proccdtrre. The torus atmosphere was then inerted with nitrogen to 4.8% 02 85 indicated in the drywe11/ torus oxygen recorder and drywell inerting was then commenced.

During this process, a "zero t-check" on the analyzer showed that the Instrument "zero" was Iow. Correcting this. condition brought the indicated 02 level'

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i in the torus to 6.2%.

Sinca'dryw311 inerting was tJreedy in

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progress, it was decided to reinert the torus after drywell

.inerting was-complete.

Due to a alsunderstanding on the part of the duty Shift Foreman, an ettempt was made to inert the dry-well to less than 1% 02 content, Prior to attaining this con-dition, the plant nitrogen supply reached a level Where further consumption in the inerting process would have exhausted the operational supply nooded for the nitrogon/ air system in the drywell.

An orderly plant shutdown was started 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after going into the RUN mode at 1000 on January 22,1974 at a 30 We/hr. rate.

Power was reduced to 292 We at which time a temporary Technl-l cal Specification change was obtained which allowed operation at $0% reactor power with greater than 5% 02 concentrstion in the primary containment until 1230 on January 24, 1974 APPAREXT CAUSE Design Procedure OF OCCURRENCE:

Manufacture Unusual Servico Condition Installation /

~ Inc. Environmental Construction Component Failure X

Operator

~ Other (Specify) 1he duty Shift Foreman ~in charge of this operation misjudged the capacity of the plant nitrogen system.

In addition, the FCI4m#n Was'infor16cd that a nf trogen truck was enroute and w uld arrive Tuesday.inorning with the additions! ' nitrogen needed o

to complete the inerting process. Unfortunately, due to internal problems, the nitrogen vendor was unable to meet the required delivery time.

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'Ahnormal Occurrence page 3 Report No. 50239/74/1 ANALYSIS OF The significance of this cvont lics in operating the reactor i

OCCURRENCE:

et power with an inadequately. Inerted containment which, under design bases ihCA conditions, would have created a condition f

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whereby the probability of experiencing an explosive concen-

)i tration of oxygen'and hydrogen in the containment would have I

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been increased, l

l, CORRECTIVE Corrective action to provent recurrence of this event is to

ACTJON, be determined after the 6ppropriate review process by the Plant Operations keview Committee.

PAIIAIRP DATA, Not - spplicable, f/

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