ML19337A317

LER 80-018/03L-0:on 800808,while Attempting to Monitor Gas Space on Vct,Inadvertent Release of Radioactive Matl to Auxiliary Bldg Environ Occurred.Caused by Deteriorated Surgical Tubing on Gas Analyzer.Tubing Replaced

ML19337A317
Person / Time
Site:	Fort Calhoun
Issue date:	09/05/1980
From:	Hyde K OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19337A309	List: ML19337A305 ML19337A317
References
LER-80-018-03L, LER-80-18-3L, NUDOCS 8009090519
Download: ML19337A317 (4)

Text

._ - .

' ~ ~

3 " 77 3

. LICENSEE EVENT REPORT NTGCL SLOCK: l l l l ~l l l (PLEASE PRINT oR TYPE ALL REQUIRED INPoRMATioN) 1 6

+

10 I8 t9 l l NLICENSEE 7 I E lCODE F l C l S l 1 l@15-l 14 O lNUMBER

. LICENSE 0101010101010 loLICENSE 25 26 1010 TvPEl@l411 JG I

57 CAT11 l@

58 Il Il l@l con'T loliI 3E l L j@l 015 l 01010 l 218 ( 5 l@l 69 0 l810181810 }@l01910151810 74 75 REPORT CATE l@

80 7 8. 60 61 COCXET NUMBER 68 EVENT CATE EVENT oESCRIPTioN ANo PROBABLE CONSEQUENCES O'o Ioi2i l During normal operation a sample of the gas space on the VCT was beino drawn througbj

. i o i 3, i the gas analyzer. A malfunction of the sampling apparatus caused the inadvertant re-I io i i i lease of a small ~ quantity of radioactive material to the auxiliary buildino environ-l lo isi i ment. Subsequently the material was passed to the atmosphere through the auxiliary I g o is i i building ventilation system. The release was monitored.of short duration and was I jaj7ll Within the Tech. Spec. limits. Notification of the NRC and offsite support acencies l was made per I.E. Infonnation Notice 80-06, Tech. Spec. 5.9.2.b(4) and FCS Emergency i o ia i i Plan. I

'ESIE T80E Su'E$$E COMPONENT CODE SL8 CODE SU OCE lol9l l P l B l@ l E l@ l Z l@ l P l I l P l E l X l X l@ l A l@ [.Z,_j @

7 8 9 to 11 12 13 18 19 20

_ SEQUENTIAL OCCURRENCE REPORT REVISION LER EVENT YE A R REPORT NO. CODE TYPE NO.

@ ,ag/RO g 18 10 l l-l l 011181 y 1013l lL I 30 l-1 LQ.J

_21. 22 23 24 26 27 28 29 31 32 K N 'AC C P T ME HOURS S8 I POR 8. SU t MANUP C RER lAl@lGl@ l Zl@ l36 Zl@ l010101Ol 37 l41Y l@ lNl@ W@ lX191919l@

33 34 35 40 42 43 44 47 CAUSE oESCRIPTioN AND CORRECTIVE ACTIONS 27 iiio i l Investigation revealed deteriorated surcical tubino on the cas analyzer allnwed a I i,i,i i small amount of material release. The tubino was reolaced and a nravantativa m h- I

,,,,, i tenance program initiated. Normal radiation control procedures were used to miticatel i, t ai i personnel exposures, evaluate consequences and return auxiliary buildino areas to I iii4i i service. l l

-7 8 g 80 i ST T  % POWER OTHER STATtJS bl O Y OlSCOVERY DESCRIPTION It i5l W @ l0l9l9l@l NA l W@l Radiation Monitor in Hioh Alarm l

)

ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE li Is l lG l @ l Mi@l 8.23 curies total If I Gas analy7. - to at nsnhara l PERSONNEL EXPOS ES NuM8ER TYPE DESCRiPTiOu@

I i 171 1010 'l 0 l@l Z l@l NA  !

*~' ' " "

l PERSONN E't iN2u'iliES l NUMSER DESCRIPT10N

( li 181 8 9 l01010 l@l12 11 NA 80 l

7 YE CESCR PTION l i 191 l Z l@l 10- NA l

[ F 8 9 .

30

( PUBLIC! NRC USE ONLY 1,2,j,oj lY f@l Standard release to newscacer, t.v. and +adtn _ l lIIIIIIIIIIIIi r 8 " "

• 9.-

'NAME

- 8009090F/#

oF PREPARER

' ~K. C. Hyde pNons: 402 426 4011 2,

LER No.80-018 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 1 Safety Analysis

. A gas analyzer is installed in the auxiliary building to facilitate sampling of various processes and equipment containing radioactive materials. Degradation of tubing in this equipment caused radioactive material to be released-to the lower level of the auxiliary building and subsequently to the atmosphere through the ventilation stack.

Stack monitor strip charts show that the release was of approximately two (2) minutes duration before being terminated by the sampling personnel.

Increased readings and alarm on stack effluent monitors resulted in control of the area, surveys and appropriate support notification per implemented sections of the plant emergency procedures. No personnel exposures or contamination resulted from this incident other than the negligible doses commonly assigned to plant health physics personnel during conduct of routing daily surveys.

The total amount of radioactivity has been calculated to be 8.23 curies.

The maximum calculated release rate of particulate was 3.51E-5 pCi/sec. as compared with Technical Specification 2.9(2)b limit of 2.05 E-3 pC1/sec.

The maximum calculated release rates for iodine and gross gaseous  !

activity were 5.21 E-5 pCi/sec. and 6.86 E+4 pCi/sec. respectively. 1 Technical Specification 2.9(2)b sets a limit for iodine release rate at 9.4 E-2 pCi/sec and Technical Specification 2.9(2)a limits gaseous activity- release rates to 8.3 E+4 uCi/sec.

CONCLUSION: No Technical Specifications limits were exceeded and no health hazard was presented to the general public as a result of the icw level activity release.

1 sa

. ~ .

1

LER No.80-018

-Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTACHMENT N0. 2 Corrective Action The gas analyzer has been added to the plant preventative main-tenance program. In accordance with this program the gas analyzer will be inspected on regular intervals to prevent the operation of the equipment when component degradation is indicated.

Nysa 4"

. LER No.-80-018-Omaha Pubite Power. District Fort Calhoun Station Unit.No.1

- Docket No. 05000285 ATTACHMENT NO. 3

- Failure Data There has been no previous occurrence of tnis type at the Fort Calhoun Station.

9 i

a f

E~

g .%

~\x\

, , . . . - , - - ,