05000368/LER-1981-008-03, /03L-0:on 810217,during Mode 3 Operation,Following Reactor Trip from 100% power,I-131 Dose Equivalent of 1.59 Uci Observed.Caused by Expected Spike in Coolant Activity. Liquid Processed Through Primary Demineralizers

/03L-0:on 810217,during Mode 3 Operation,Following Reactor Trip from 100% power,I-131 Dose Equivalent of 1.59 Uci Observed.Caused by Expected Spike in Coolant Activity. Liquid Processed Through Primary Demineralizers

ML19345G253
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/12/1981
From:	Fiser G, Rogers P, Shively C ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19345G252	List: 05000368/LER-1981-008-03, /03L-0:on 810217,during Mode 3 Operation,Following Reactor Trip from 100% power,I-131 Dose Equivalent of 1.59 Uci Observed.Caused by Expected Spike in Coolant Activity. Liquid Processed Through Primary Demineralizers
References
LER-81-008-03L, LER-81-8-3L, NUDOCS 8103170452
Download: ML19345G253 (2)

LER-1981-008, /03L-0:on 810217,during Mode 3 Operation,Following Reactor Trip from 100% power,I-131 Dose Equivalent of 1.59 Uci Observed.Caused by Expected Spike in Coolant Activity. Liquid Processed Through Primary Demineralizers

Event date:
Report date:
3681981008R03 - NRC Website

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Ov NRC FORM 364 U. S. NUCLE AR REGULATORY COMMISSION LIMNSEE EVENT REPORT EXHIBIT A CONTROL BLOCK: l l l l l l lh (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 6

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8 to 6s oocgETNUMsgm 68 EO EVENTo*'8' 34 FS Mf,OHTomit 80 EV,ENT OESCRIPTION AND PROSA8LE CONSEQUENCES h ITTT1 IDurina Mode 3 operation followino a Reactor trip from 100% rated reactor i ipower, an Iodine-131 dose equivalent value of 1.59 microcuries per gram i

o 3 Iwas observed, exceeding the limit of T.S. 3.4.8.a.

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e3 as of CAUSE DESCR4PTION AND CORRECflVE ACTIONS 27 IThe occurrence was caused by an expected spike in coolant activity follow i o IT1T) lina a reactor trip. The reactor coolant lit;uid was processed through the i IDrimary demineralizers which reduced the concentration of radioactive i

i 2 EE] liodine to within acceptable limits. Additional historical information is i lattached per the requirements of T.S. 3.4.8.d.

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Attachment to LER 50-368/81-0d8

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O Rx Power LD Flow CHRG PUMP 0600 100%

S38 Gpm 446 Gpm 0700 0800 0900 1000

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u 3r 1100 0%

83 Gpm 89 Gpm 1200 38 Gpm 45 Gpm 1300 1400

' f 1500 Item 2.

FUEL BURNUP BY CORE REGION Fuel Type Batch Exposure (MWD /MTU) 1 6383.4543 2

8558.8705 3

10076.9981' 4

11735.7655 5

12500.5411 6

11931.9310 7

6657.'1972 Core Avg.

11089.5 MWD /MTU Item 4.

HISTORY OF DEGASSING OPERATION No degassing prior to exceeding IDE of 1.0 pCi/gm.

Normal letdown / makeup up until time of Operations notification of >1.0 ~pCi/gm than LD/MU flow doubled.

' Item 5.

TIME DURATION OF DE I-131 >1.0 pCi/gm The duration of activit, >1.0 pCi/ gram was approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

A sample of reactor coolant was taken at 1312 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.99216e-4 months <br /> on 2/17/81, showing an activity of 1.59 pCi/gm.

Samples were taken at four hour intervals until activity indicated I-131 DE equal to 0.69 pCi/gm.

The cumulative operating time at a' primary coolant specific activity >1.0 yCi/gm DE I-131 equals approximately 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> for the last six month period (less than 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> limit of T.S. 3.4.8. Action a. ).

Q ATTACHMENT ~1 'ER 50-368/81-008 ITEMS 1 & 3 REACTOR POWER & CLEANUP FLOW HISTORY STARTING 48 HOURS PRIOR TO 1st SAMPLE IN WHICH LIMIT WAS EXCEECED Iodine DE = 1.59 pCi/GM 2/17/81 0 1515 (Sample time 1312)

Rx Power LD Flow CHRG PUMP 1300 100%

438Gpm S46 Gpm 1400 2/15/81 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2/16/81 0100 0200 0300 0400 0500 0600 0700 0800 0900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2/17/81 2400 0100 0200 0300 0400 0500

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