ML19305C720

LER 80-029/03L-0:on 800226,during Normal Operation at 100% Power,Found Water Leaking Onto Ground from Refueling Water Storage Tank Cooler Fitting.Caused by Failure to Remove Temporary Pressure Gauge.Leak Secured & Gauge Removed

ML19305C720
Person / Time
Site:	North Anna
Issue date:	03/27/1980
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19305C716	List: ML19305C715 ML19305C720
References
LER-80-029-03L, LER-80-29-3L, NUDOCS 8003310307
Download: ML19305C720 (2)

Text

_ .. . _ . _

g,~-

y) LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 0 t 8 9 l Vl Al Nl Al Sl 1l@l LICENSEE CODE 14 0

15 l 0 l -l 0 l 0LICENSE l 0 lNUMBER 0 l 0 l- l 0 l 0 l@l 23 426 l 1LICENSE l 1 l 1TYPE l 1Jul@l5 7 ClAI b8l@

CON'T O i 8

[ ORT 60L Ql0 l3 l0 l0 l0 l3 l3 l8 l@l0l2l2l6l8l0l@l0[3l2l7l8l0l@

61 DOCK ET P.UYSER 63 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCHIPTION AND PROBAOLE CONSEQUENCES h lOl2l l On February 26, 1980, during normal operation at 100% power, water was observed leakink O 3 l from a fitting on one of the refueling water storage tank coolers onto the ground. Anj O 4 l evaluation of the incident by Health Physics determined that the unplanned release of l l 0 l s l l radioactive material which occurred was minor and that no radiological hazard to -l O 6 l station personnel or the general public resulted. Reportable pursuant to T.S. l l 0 l 7 l l 6.9.1.9.d. l I

1 O I e I [_ 80 7 8 9 DE CODE SU8C E COMPONENT CODE SU8 CODE E O 9 9

l Sl Bl@ W@ l E l@ lP lI lP lE lX lX l@ y@*) []@

10 12 18 19 7 8 11 13 SEQUENTI AL OCCURRENCE REPORT REVISION LE R/RO EVENT YE AR REPORT NO. CODE TYPE NO.

h RE sU l8 l0 l g l0 l2 l9 l 24 26

]/l l 0l 3l 29 lLl 30

[._ j ]

32 21 22 2J 27 28 31 i KEN ACT ON ON PL PT T HOURS 22 S B IT O FOR h B. SU PL1 MAN FACTURER l33 X l g g g l5Zlg 3 g@

36 l0 l0l0l 3/

l g g lN lg 41 42 l Al @ lX l9 l9 l9 [g 44 47 34 40 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ITTTl i The leak occurred because a temporary pressure gauge, which was installed during the l i i l contruction phase with a carbon steel elbow instead of stainless steel, was never re- I

, , l moved af ter the initial testing of the system had been completed. The leak was secure 4

, 3 l by isolating and depressurizing the cooler. 'lhen the leaky fitting and downstream l i 4 l pressure gauge were removed and the line was capped. I 7 8 9 80 ST S  % POWER oTHE R STATUS DISCO RY DISCOVERY DESCRIPTION

[Ej@ l 1 l 0 l 0 l@l NA Observation by HP Tech.

i s l

lAl@l

• l AETiviTY CO0 TENT AMOUNT OF ACTIVITY LOCATION OF RELEASE 7

i s 89_

[ Lj REMASE@D [PJglOF 9.676E-3 10 REM ASE Curies T@otall 44 l

45 RWST Cooler to Ground Soil l 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIP TION i 7 l ol 01 Ol@l zi@l l PERSONNE L INJURIES NUMBER DESCRIPTION i R I0101Ol@l n I 7 8 9 11 12 83 LOSS OF OR DAMAGE TO FACILITY Q TYPE DESCRIPTION v

"^

7 i o 8 9 Lz]@l10 l 80 I PUBLICI NRC USE ONLY ,

2 O E@L_NA l lllllllllllllj a S 'a

i

8003310 3ej!

tf p rnreur4 b

• I NAME OF PREPARER 3+ PHONE: ( 103) 49 ^-515 i ,

. 1 Virginic Electric cnd Power Comp ny North Anna Power Station, Unit #1

Attachment:

Page 1 of 1 Docket No. 50-338 Report No. LER 80-29 /03L-0 Description of Event On February 26, 1980, with the reactor operating at 100% power, water was observed leaking from a fitting on the "B" RWST cool outlet pressure gauge line onto the ground resulting in an unplanned relet i of radioactive ma;erial.

This event is reportable pursuant to T.S. 6.9.1.9.d.

Probable Consequence of Occurrence The consequences of this event were minimal because the Health Physics Depa r tment immediately performed a radiological survey and determined that the activity released did not enter the environs through the storm drain system but was confined to the top layers of soil in the immediate area. The survey also determined that the amount of activity released was only 1.3 times MPC for an unrestricted area and that the curies of non-tritium and tritium released were only 5.6E-5 and 9.62E-3 respectively. As a result, the health and safety of station personnel and the general public were not af fected by the release.

There are no generic implications associated with this occurrence.

Cause of Event The leak occurred because the architect engineer installed a carbon steel elbou in the pressure gauge line instead of stainless steel which resulted in corrcsion of the fitting due to the boric acid in the system. Af ter the Icak occurred it was discovered that the pressure gauges were only temporary connections used for testing purposes and should have been removed af ter initial testing

)

of the system had been completed prior to commercial operation.

I_mmediate Corrective Action To secure the Icak, the inlet and outlet of the cooler were isolated e and the cooler was depressurized. The leaky fitting and pressure gauge were then removed and the line was capped.

Scheduled Corrective Action The Unit No. 2 Master Deficiency List will be checked for temporary modifications to insure that these modifications are removed or appropriately documented. Unit No. 1 and No. 2 systems will be walked down on a selected basis to check for other temporary modifications that are not authorized.

Actions Taken to Prevent Recurrence The pressure gauge and carbon steel fitting on the "A" RWST cooler outlet were removed and a stainless steel cap was installed on the lihe. Also, the

~

systems on Unit No. 2 RWST were surveyed for 2 similar deficient installations and none were found.

l