05000267/LER-1981-061, Forwards LER 81-061/03L-0.Detailed Event Analysis Encl

Forwards LER 81-061/03L-0.Detailed Event Analysis Encl

ML20032C281
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/30/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20032C282	List: 05000267/LER-1981-061, Forwards LER 81-061/03L-0.Detailed Event Analysis Encl 05000267/LER-1981-061-03, /03L-0:on 811002,total Dissolved Solids in Nonradiological Liquid Plant Effluent Exceeded Tech Spec Limits on Five Separate Occasions.Caused by Sudden Increase in Ratio of Total Dissolved Solids to Conductivity
References
P-81273, NUDOCS 8111090589
Download: ML20032C281 (4)

LER-1981-061, Forwards LER 81-061/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671981061R00 - NRC Website

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' fM # jf 16805 Road 19 1/2, Platteville, Colorado 80651-9298 October 30, 1981 Fort St. Vrain Unit No. 1 P-81273 m

O Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission T

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Reference:

Facility Operating'[f No. DPR-34 Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/81-061, Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/81-061.

Very truly yours, Ww w $

Don Warembourg Manager, Nuclear Production 0W/cis Enclosure cc:

Director, MIPC 8111090589 811030 PDR ADOCK 05000267 S

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REPORT DATE:

October 30, 1981 REPORTABLE' OCCURRENCE S1-061-ISSUE O OCCURRENCE DATE:

October 2, 1981 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/81-061/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On five separate occasions in October, 1981, it was determined that the total dissolved solids in the plant non-radiological liquid effluent exceeded 2300 parts per million. This is a degraded mode of LCO NR 1.1 and is repertable per Fort St.

Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

Over the period from October 2, 1981, to October 7, 1981, with the plant. operating at steady state 70% puwer and 230 MWE, the total dissolved solids limit of 2300 pp:a for non-radiological liquid effluent was exceeded on five occasions. These events are listed as follows:

Event #1 On October 2, 1981, the swing shift total dissolved solids sample was determined to be 2350 ppm. Adjustments were made to the cooling water tower blowdown and total dissolved solids decreased to less than 2300 ppm on dsy shift October 3,1981.

Event #2 On October 4, 1981, the swing shift total dissolved solids sample was determined to be 2350 ppm. Adjustments were made to the cooling water tower blowdowr. and total dis.colved olids decreased to less than 2300 ppm on graveyard shift October 5, 1981.

Event #3 On October 5, 1981, the day shift total dissolved solids sample was determined to be 2422 ppm. Adjustments were made to cooling water tower blowdown and the total dissolved solids decreased to less than 2300 ppn on swing shift October 5, 1981.

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o REPORTABLE OCCURRENCE 81-061 ISSUE O Page 2 of 3 t

Event #4 On October 6, 1981, the graveyard total dissolved solids sample was determined to be 2519 ppm. Adjustments were made to cooling water tower blowdown and total dissolved solids decreased to less than 2300 ppm on swing shift October 6, 1981.

Fvent #5 On October 7, 1981, the graveyard total dissolved solids sample was determined to be 2470 ppm. Adjustments were made to cooling water tower blowdown and total dissolved solids decreased to less than 2300 ppm on graveyard shift on October 8, 1981.

CAUSE

DESCRIPTION:

The cause for these occurrences was a sudden, unpredictable change in the ratio of total dissolved solids to conductivity due to increased solids in the plant makeup water. A total dissolved solids factor is calculated monthly based on the total dissolved solids value and the conouctivity of the process sample.

This calculation recuires a couple of days to perform; samples collected during the interim are subject to this new total dissolved solids factor.

In this instance, tho total dissolved factor increased from 0.797 to 0.94, thereby increasing total dissolved solids in the circulat'ng water tower basin, which could only be reduced by blowdown. Attempts to blowdown the excess total dissolved solids and provide adequate dilution water with less margin for error due to the high". total dissolved solids factor resulted in several occurrences of exceeding the 2300 ppm total dissolved solids limit.

CORRECTIVE ACTION:

In all instances, circulating water tower cold side blowdown and raw water dilution valves were adjusted to reduce the total dissolved solid levels to acceptable limits.

The Che.nistry Departmer.t is investigating a means of predicting when the totsl dissolved solids factor has taken a significant change.

In the interim, the total dissolved solids factor is being calculated on a weekly basis. No further corrective action is anticipated or required.

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9 REPORTABLE OCCURRENCE 81-061 ISSUE 0 Page 2 of 3 a

Prepared By:

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Paul Moore Technical Services Technician Reviewed By:

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Charles Fuller Technical Services Engineering Supervisor

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Reviewed By:

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Edwi n 'D. tii W v

Station Manager i

l Approved By:

N Don Warembourg

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l Manager, Nuclear Production h

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