05000219/LER-1981-016, Forwards LER 81-016/03L-0

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Forwards LER 81-016/03L-0
ML20004B961
Person / Time
Site: Oyster Creek
Issue date: 05/21/1981
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20004B962 List:
References
NUDOCS 8106010358
Download: ML20004B961 (4)
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LER-1981-016, Forwards LER 81-016/03L-0
Event date:
Report date:
2191981016R00 - NRC Website
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text

I OYSTER CREEK NUCLEAR GENERATING STATION Cdf*T!CO'M (609)693-6000 P.O. BOX 388

  • FORKED RIVER
  • 08731

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'May 21, 1981 4

O Mr. Boyce H. Grier, Director

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Office cf Inspection and Enforcement p

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Y United States duelear Regulatory Ccmission jut! 01 gggj w Tg 631 Park Avenue 2

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King of Prussia, Pennsylvania 19406 N

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Dear Mr. Grier:

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'\\1 IBY' SUBJECT: Oyster Creek Nuclear Generating Static Docket No. 50-219 Licensee Event Report Reportable Occurrence No. 50-219/81-16/3L This letter forwards three copies of a Licensee Event Report to report Reportable occurrence No. 50-219,'31-16/3L in etnpliance with paragraph 6.9.2.b.4 of the Technical Specifications.

Very truly yours, Ivan R. Fi.

Jr.

Vice President - JCP&L Director - Oyster Creek IRF:dh Enclosures cc: Director (40 copies)

Office of Inspection and Enforcement United States Nuclear Regulatory Ccmnission Washington, D.C.

20555 Director (3)

Office of Manage ent Infor: ration and Program Control United States Nuclear Regulatory Catmission Washington, D. C. 20555 NRC Pasident Inspector (1)

Oyster Creek Nuclear Generating Station Forked River, N. J.

81060/03f4 6

OYSTER CREEK NUCLEAR GENERATING STATIM Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/81-16/3L Report Date May 21, 1981 Occurrence Date April 21, 1981 Identification of Occurrence An unmonitored release of radioactive water occurred due to leakage frm a valve inside the Condensate Transfer Pump Building. The water seeped through the ground in the biilding and under the walls which constitutes the foundation of the bi41 dig and leaked to areas north and south of the bi41 ding.

This event is considered to be a reportablo occurrence as defined in the Technical Specifications, paragraph 6.9.2.b.4.

Conditions Prior to Occurrence The plant was in the cold shutdown condition.

Description of Occurrence At approximately 0054 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />, leakage was discovered frcm valve V-2-88, a Condensate System valve located in the Condensate Transfer Pump Building. Isakage frcm the biilding was also found, and by performing the app 14raSle water balance, the total leakage frcm the Condensate System has been estimated at approximately 10,000 gallons.

Apparent Cause of Occorrence The cause of the occurrence was attributed to failure of the valve packing.

Apparently, vibration of the valve stem caused the packing material to loosen and allow leakage. The severity of the leakage increased due to the pressure of the fluid forcing packing material out past the gland. An inspection of the valve revealed no other visible damage - the gland was intact and in position, the valve body was not dam =W and the studs were also intact.

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Reportable Occurrence Page 2 Report No. 50-219/81-16/3L Analysis of Occurrence, By performing a water balance utilizing valtes frm applicable Control Rom and OLerating Iogs, a total of approximately 10,000 gallons could not be accountai for, and, therefore,nust be considered as leakage. It should be noted that this figure is subject to the accuracy of the various tank ar.d hotwell level indications involved. It has been estinated that the leakage through the valve occurred over a pariM of about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (5:00 P.M. April 20 to 1:00 A.M. April 21). Fran this, leakage through the valve was estimated at about 21 gpn, which appears to be a relistic nunber when the Condensate Systs operating pressure of 350 psig is taken into account. Based on the 10,000 gallon figure, a total activity of 1674 microcuries was released.

The valve which failed, V-2-88, is designed to be used as a bypass for V-2-17, the flow control valve. However, valve V-2-17 was tagged out of service at the.

time, due to problens with the valve internals. With valve V-2-17 out of service, valve V-2-88 was being used to control the flow. V-2-88 is a globe valve with a swivel disc. This design allows it to be used to control flow. However, it was being operated with the disc very close to the seat (the valve was only approxi-mately one-eighth open), which is the nest probable cause of the sts vibrations.

Several soil and water sanples were taken over a period of three days to determine the effect of the leakage and what future actions would be necessary. On April 21, 1981, sanples of Condensate System water and water which had leaked through the building were tested and showed the majority of the activity was due to La140 and Cel41

'Ihe net activity g each nuclide was 1.59 x 10-5 pCi/ml for Lal40 and 2.69 x 10-5 pCi/ml for Ce Several scil sanples taken fran the north and south sides of the biilding were also tested and showed the majority of the activity was due to Co 0 and Csl37, and the highest concentrations observed 6

for each nuclide were 2.65 x 10-5 pCi/migrCo60and1.04x10-5 uCi/ml for Cs137 The fact that neither Co60 or Cs were detected in sanples of Condensate Syst s water would indicate that this activity was there prior to the leakage.

Soil samples taken on April 22, 1981 and April 23, 1981 showed the highest activity areas to be very close to the biilding and only at the surface. Samples taken at a depth of 3 feet with a hand auger and ones taken at surface locations further away from the biilding showed considerably lower levels of activity.

The low levels of the 3 foot deep sanples (only Cel41 was detected, with a concentration of 5.99 x 10-6 pCi/ml) are a good indication that the activity did not penetrate deep enough into the soil to get into any aquift r, which is at least 20 feet below the surface.

Corrective Action

hwaiately after discovering the leaking valve, the "A" Condensate Punp was shut down and the Condensate Storage Tank was isolated. The araa in front of the chlorination Bi41 ding was diked to trap any water collecting by the roadside, and this trapped water was punped into 55 gallon drums. It is important to note that none of this water was allowed to enter a roadside storm drain, which leads to the discharge canal. 'Ihe area around the Condensate Transfer Punp Building was roped off and plastic covering was laid down on the ground for added protecticn.

Reportable Occurrence Page 3 Peport No. 50-219/81-16/3L Valve V-2-88 was repackcd on April 21, 1981, and a replacanent valve was pror.ured.

'Ihis new valve was installed during the current spring outage, and the repair work for the flow control valve V-2-17 was also cmpleted at the sane time. On April 24, the Radiological Ccntrols Departnunt renoved the barriers and the area was cleared as a cxmtamination area. Plant Engineering has been requested by the PORC to seal the floor in the Condensate transfer biilding to minimize the probability of future leakage fran the b'41 ding to tl.a environs, and to install a water detection alann in the bi41 ding with an alar.n in the Control Rocm.

Failure Data Manufaqturer - Ohio Injector Co.

}edel -j 3043 Butt - Welded Series Pressure - 300 lb.

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