ML19257A182

LER 79-119/03L-0:on 791203,post-accident Radiation Monitors Could Have Had High Setpoint for Release Set Higher than Allowed by Tech Specs.Caused by Procedural Deficiency. Procedure Mods Prepared

ML19257A182
Person / Time
Site:	Davis Besse
Issue date:	12/21/1979
From:	Scott R TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19257A180	List: ML19257A179 ML19257A182
References
LER-79-119-03L, LER-79-119-3L, NUDOCS 8001020421
Download: ML19257A182 (2)

Text

U.S. NUCLE AR REGULATORY COMMISSION AC FORM 366 771 LICENSEE EVENT REPORT l l l l l IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI CONTROL BLOCK: {l 6 i

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l 0 l H l D l B l S l 1 l@l 0 l 0 l- l 0 l 0 l N l P l F l- l 0 l 3 l@[4 l 9- LICENSEE CODE le 15 LICENSE buMbEH 25 2G LICENSE TYPE JO 57 CATbd CON'T o i

[,g"cl ] L '@l 0 l 5 l 0 l - l 0 l 3 l 4 [ 6 ]@l 1 l 2 l 0 l 3 l 7 l 9 j@l1 l E,0CNET NUVSCH to 63 EVENT DATE 74 75 REPORT D AT E 60 8 63 G1 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES post-accident h radiation monitors RE l o 2 l It was discovered at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on 12/3/79 that l set higher than allowed by J o 3 ) l 1878A and B could have had the high setpoint for re ease There was no danger to the health and l

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to 4 l Environmental Technical Specification 2.4.1.d.

j The tanks are recirculated and a sample o 5 l saf ety of the public or station personnel.

I 0 16 1 drawn from the tank for independent monitoring prior to the tank being discharg l

io j7 j lAlso a normal release is discharged at less than 25% of the maximum permissible I

80 o a centration. (hT-33-7 9-14 0)

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[C j@dh AC T O I Zlh l/ O! 0l 0 Ol l Ylh 41 42 l43 lh 44 47 3J 34 l35Z lh 36 3 40 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS The h current valve lineups allow l i o lThe cause of the occurrence was procedure deficiency.

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I the radioactive liquid from the miscellaneous liquid waste monitor tank to flow into Proce- l

, 7 l the radioactivity monitors during recirculation of the tank prior to release.

, 3 l dure modifications have been prepared to isolate the radioactivity monitors a l

g,g4; l demineralized water flush which occurs before tank recirculation. 80 7 8 9 DISCOVERY DESCRIPTION oTHER STATUS IS OV RY A 5  % POWER NA l i s Lcj@ 'l0 0l0l@l NA l lA[@l* a

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l i c REMASED OF REM ASE lzl@lZl@l NA AMOUNT OF ACTIVITY 44 l

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@l 80 7 8 9 10 11 PERSONNEL E XPOSURES NUVBE R TYPE DESCRIPTION l N^

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NUVBER 80 i a 10l 0101@l12NA 11 7 8 9 LOSS OF OH OAVAGE TO F ACILITV TYPE D E SCRIPTION 8001000 4.' l, l NA 80 9 ,

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2 o [N,jhl NA 68 69 60 ;

7 8 9 10 419-259-5000, Ext. 268 {

"' ^ Ronald Scott PHONE:

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-140 DATE OF EVENT: December.3, 1979 FACILITY: Davis-Besse Unit 1 IDEhTIFICATION OF OCCURRENCE: Liquid radioactivity effluent monitors improper setpoint Conditions Prior to Occurrence: The unit was in Mode 3, with Power (NWT) = 0, and Load (Gross MWE) = 0.

Description of Occurrence: It was discovered at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on December 3,1979 that post-accident radiation monitors RE 1878A and B could have had the high setpoint for release set higher than what it should have been. Environmental Technical Specifica-tion 2.4.1.d states that during release of radioactive wastes, the effluent control monitor shall be set to alarm and to initiate the automatic closure of each waste isolation valve prior to exceeding the limits specified in 2.4.1.a.

Designation of Apparent Cause of Occurrence: The cause of the occurrence was pro-cedure deficiency. The current valve lineups allow the radioactive liquid from the miscellaneous liquid waste monitor tank to flow into the radioactivity monitors during recirculation of the tank prior to release. Since the background reading is: taken after recirculation, this reading includes both the actual background and the radio-activity in the water.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The tanks are recirculated and a sample drawn from the tank for independent monitoring prior to the tank being discharged. Also a normal release is discharged at less than 257. of the maximum permissible concentration due to the administrative safety factors included in the release rate determination.

Corrective Action: Procedure modifications have been prepared to isolate the radio-activity monitors after the demineralized water flush which occurs before tank recir-culation for both the miscellaneous and clean liquid waste disposal procedures, SP 1104.30 and SP 1104. 29, respectively.

Failure Data: There have been no previously reported similar events.

LER #79-119 1663 262

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