ML20086Q837

SR-S1-75-05:on 750929,routine Sampling of Ventilation Vent Gaseous Activity Revealed I-131 Activity in Excess of 4% of Tech Spec Limit.Caused by Containment Purging Operations, Filter Problems & Leakage & Treatment of Radioactive Water

ML20086Q837
Person / Time
Site:	Surry
Issue date:	03/04/1975
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20086Q840	List: ML20086Q837 ML20086Q877
References
SR-S1-75-055, SR-S1-75-55, NUDOCS 8402280560
Download: ML20086Q837 (5)

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w Serial No. 764 Mr. Norman C. Moscicy, Director P0&M/JTB:clw Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Docket No. 50-280 Region II - Suite 818 License No. DPR-32 230 Peachtree Street, Northwest Atlanta, Georgia 30303

Dear Mr. Moscicy:

Pursuant to Surry Power Station Technical Specification 6.6.B.3, the Virginia Electric and Power Company hereby submits forty (40) copies of Special Report No. SR-SI-75-05.

The substance of this report has been reviewed by the Station Nuclear Saf ety and Operating Committee and will be placed on the agenda for the next meeting of.the System Nu'c1 car Safety and Operating Committee.

Very,truly yours,

h. ok. Wbh lW C. !!. Stallings Vice President-Power Supply and Production -Operations

< Enclosure cc: Mr. Robert W. Reid 39 copics SR-SI-75-05 Mr. Bryce P. Schofield Director, Bureau of Industrial llygienc ,

Department of Ilcalth-Commonwealth of Virginia l

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PDR ADOCK 05000280 PDR S

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e COPY SENT REGION. m,

O v (my SPECIAL REPORT SR-SI-75-05_

VENTILATION VENT GASEOUS RELEASE DOCKET NO. 50-280 LICENSE NO. DPR-32_

OCTOBER 29, 1975 SURRY PO'..'ER _S'l ATION.

VIRGINIA ELECTRIC AND POWER COMPANY t

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I. . ETRODUCTION In accordance with Technical Specification 6.6.B.3 for Surry Power Station, this repcrt describes the release of gaseous wastes in excess of 4 per cent of the Technical Spec,fication limits established by 5

• Technical Specification 3.11.B.1. -

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11. SUmtARY OF OCCURRENCE ,

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.' On September 29, 1975, routine sampling of the ventilation vent i

gaseous activity revealed an Iodine-131 activity in. cxcess of 4 per cent of the Technical Specification limit. This condition has lasted until October 23, 1975, as sumcari::cd in Attachment A of this report.

a This condition has been attributed to a number of operational cir-cuestances. During normal Unit No. I operation prior to the current refueling outage, contaminated liquid had ! accumulated on the basement floor of the containment as a result of a leaking equipment as reported ,

This water apparently got into the containment iodinc in A0-SI-75-18.

' filters in the basement and saturated some of the charcoal which greatly reduced the efficiency of these filters. Also a fact or is t'he f act that the "B" bank of the auxiliary building i11ter banks was not functioning .

at maximum efficiency, as determined from results of the routine periodic test ofsthese filters. As a result of these. filter problems along with the processing of contaminated. liquids from both_the containment and auxiliary building basements and through purging operations of Unit.No.

1 for refueling, the -4 per cent .of Technical Specification ' limit. was exceeded.

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The charcoal.in the auxiliary building filter banks and the con-i

.tainment iodine filters is being replaced during this outage. Also to avoid the problem of floodin'g the containment iodine filters in the future, a. design change is in ptogress to construct 4. flood control i

dike for this f11ter and should be completed during the current out-age. During the current outage portable iodine filters have been placed S

in the Unit No. I containment to miniraize the ventilation sont release rate condition. .

III . CONCl._USION

The ventilation vent Iodine-131 activity exceeded 4 per cent of the Technical Specification limit from September 29, 1975 to October 23, 1975 due to Unit No. I containment purging operations, filter problems, b

and Icakage and subsequent treatment of radioactive water which had App 1'icable liuits contained accurtulated in the containment basement.

in Technical Specification 3.11.B.wcre not exceeded.

The lodine-131 activity from the ventilation vent should decrease ,

below the 4 per cent of Technical Specification limit in the near. future-as the replacement of filter charcoal and the. processing of contaminated liquids is completed.

The health and safety of the general public was not adversely effected'by this occurrence.

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ATTACIC*ENT-A ..

' < ~ .I i * * * ' SD01ARY OF GASE0'JS REI.EAS'n AS A :'ER_CE'.~. OF MPC SEP'ir.'t!,ER 29. 1975 to OCT011ER 23,:1975-DATE ,

% of MPC

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9-29-75 15.6 9-30-75 27.4 10-1-75 28.1 10-2-75 34.6 10-3-75 22.5 10-4-75, 16.7.

10-5-75 16.7 ,

10-6-75 18.7 '

10-7-75 17.8 10-8-75 15.1 10-9-75 8.78 10-10-75 43.5 10-11-75 23.9- 1 10-12-75 34.5 10-13-75 17.4 10-14-75 . '26.3 10-15-75 '

33.3 30.4 10-16-75 10-17-75 -16.5 10-18-75 - 10.5 .

10-19-75 12.1 10-20-75 9.7 '

10-21-75 12.5 -

10-22-75 . 11.4 10-23-75 -

, 24.0 10-24-75 16.7 10-25-75 . 12.5 10-26-75 < 4 .' 0*

10-27-75 <4.0*

10-28-75 5.4

.10-29-75 4.1. l 1

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• Flow reduced'because of maintenance activity'in containment.

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