ML19098B270

LER 1975-003-00 (Special Report SR-Sl-75-03) for Surry Unit 1 Ventilation Vent Gaseous Activity

ML19098B270
Person / Time
Site:	Surry
Issue date:	07/25/1975
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Moseley N NRC/IE, NRC/RGN-II
References
Serial No. 612 LER 1975-003-00
Download: ML19098B270 (4)

Text

.'r' VIRGINIA ELECTRIC .A.ND PowER COMPANY RICHMOND, VIRGINIA 23261 July .25, 1975 C:-iie Gy~ ~

Mr. Norman.C. Moseley, Director Serial No *.*612 Office of Inspection and Enforcement PO&M/JrB:clw U.S. Nuclear Regulatory Commission Region II - Suite 818 Docket No. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Geo_rgia 30303

Dear Mr. Moseley:

Pursuant to Surry Power Station Technical Specification 3.11.B.1 the Virginia Electric and Power Company.hereby submits forty (40) .copies of Special Report No. SR~Sl~75-03.

The substance of this report has been reviewed by the Station Nuclear Safety and Operating Committee and will be placed on the _agenda for the next meeting of the System Nuclear Safety and Operating Committee.

Enclosure cc: Mr. K. R. Goller 39 copies SR~Sl~75-03 8021

i SPECIAL REPORT .

SR-Sl-75-03 VENTILATION VENT GASEOUS ACTIVITY DOCKET NO. 50-280.

LICENSE NO. DPR-32 JULY *22, 1975 SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY

I. INTRODUCTION e

In accordance with Technical Specification 6.6.B.3 for Surry Power Station, this report describes the release of gaseous wastes in excess of 4 per cent of the Technical Specification limit established by Technical Specification 3.11.B.1.

II.

SUMMARY

OF OCCURRENCE On July 9, 1975, routine sampling of the ventilation vent activity revealed an Iodine-131 activity of 4.6 per cent of the Technical Specification limit. Purging operations and maintenance activities associated with Unit No. 2 shutdown are believed to have led to the increase in the level of activity in the ventilation vent. This, in conjunction with the existing auxiliary building activity levels due to the processing of liquid waste, raised the total vent activity above the 4 per cent limit. In order to reduce the level of activity in the ventilation vent, the containment purge exhaust was diverted through the charcoal filter system. Subsequent sampling on July 10, 1975 indicated the operation had reduced the level of I-131 activity to approximately 2.9 per cent of the Technical Specification limit, a value consistent with previous levels immediately prior to the

• shutdown.

III. CONCLUSION The excess ventilation vent I-131 activity was believed to be caused by containment purging operations and containment maintenance activities with some contribution from processing liquid waste. The activity was a

reduced below the 4 per cent limit by diverting the containment purge exhaust through the charcoal filter system. Procedure changes have been implemented to ensure all future containment purges are directed through the charcoal filters.

The releases described herein were well below the limits established by 10 CFR 20;. therefore, there were no safety implications associated with the occurrence.