ML19344E045

Forwards LER 80-035/03L-0

ML19344E045
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/25/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19344E046	List: ML19344E045 ML19344E049
References
P-80230, NUDOCS 8008260548
Download: ML19344E045 (5)

Text

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PLATTEV1LLE, COLOR ADO 80651 July 25, 1980 Fort St. Vrain Unit No.1 P-80230 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012

Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/

80-35, 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. 50-267/80-35.

Very truly yours,

&w . . ,

y Don Warembourg Manager, Nuclear Production DW/cls Enclosure cc: Director, MIPC 4 O

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OCCI'RRENCE REPORT DISTRISUTION Number of Copies Department of Energy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Sam Franc 1Sco Operations Office Attn: California Patent Group 1333 Broadway Oakland California 94612 De pa r tmen t o f E ne rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .- 1 (P Letter)

Office of Nuclear Engineering Programs Washington D.C. 20545 Dep a r t:nen t o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Mr. Glen A. Newby, Chief dTR Branch Divistort of Nuclear Power Development Mail Station 3-107 Wasuington, D.C. 20545 De p artme n t o f E ne r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Acts: Senior Program Coordinator P. O. Box 81325 San Diego. California 92138 Mr. Karl V. Seyfrit. Director ------------------------- 1) (Original of P Letter Region IV V and Copy of LER)

Of fice of Inspection and Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington. Texas 76012 Di r e c to r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter, LER)

Of fice of Management Information and Program Control U. S. Nuclear Regulatory Connaission Washington, D.C. 20555 W. Bushnell. Site Manager - -------------------------- 10 (Original of FPLC L-ner General Atomic Company plus Two Copias, One P. O. Box 426 Copy of P Letter. One Platteville, Colorado 60651 Copy of LER)

NRC Resident Site Inspector -------------------------- 1 (P Letter. LER)

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REPORT DATE: July 25, 1980 REPORTABLE OCCURRENCE 80-35 ISSUE 0 OCCURRENCE DATE: June 25, 1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 UELD COUNTY ROAD 191/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-35/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

During the regeneration of a batch of condensate polisher resin, waste water was di. .narged to the plant liquid effluent system instead of the waste neutralizing tank. This resulted in a degraded mode of LCO NR 1.1, and is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

On June 25, 1980, at approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the valves which control the discharge path of waste water from -he condensate polisher resin regener-acion system did not automatically line up properly and L aact arged the waste acid and caustic used in resin regeneration to the Turbire Guilding sump in-stead of the waste neutralization tank. This resulted in the waste water being discharged to the yard drain and then to the Goosequill Ditch.

Fort St. Vrain Technical Specification LCO NR 1.1 requires that the regener-ation effluent be stored in lined evaporation ponds, and establishes limits for various chemicals in the effluent. The discharge of the regeneration waste water to the Goosequill Ditch was not in accordance with the Technical Specifica tion. Three of the chemical limits of LCO NR 1.1 were exceeded as noted below Maximum Concentration Actual Constituent Or Value Value Cu 1 ppm 1.3 ppm Zn 5 ppm 9.2 ppm

, pH 6.0 - 9.0 1.9 - 9.8 1

REPORTABLE OCCURRENCE 80-35 ISSUE O Page 2 of 3 EVENT DESCRIPTION: (Cont'd)

The remaining requirements of the LCO were satisfied as the liquid effluent did follow the prescribed discharge paths.

When the abnormal Goosequill chemistry was observed, the possible sources were investigated and the problem with the condensate polisher resin regen-eration system was discovered. Immediate action was taken to terminate the release of regeneration chemicals by manually overriding the discharge path selector and putting all the waste water to the neutralizing tank. Corrective action returned chemical constituents to acceptable concentrations within the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> required.

CAUSE DESCRIPTION:

The inadvertent discharge of the regeneration waste water was due to a failed conductivity cell in the waste water line which prevented proper automatic valve line up. This equipment failure could not have been avoided or the dis-charge prevented by more frequent process sampling or testing of the instrument.

C01RECTIVE ACTION:

Immediate action consisted of manually directing regeneration waste water to the neutralizing tank.

Followup actions were to continue the sampling until chemical concentrations were within LCO NR 1.1 limits. The conductivity element was replaced, and discharge valve operability was verified.

No further corrective action is anticipated or required.

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4 REPORTABLE OCCURRENCE 80-35 ISSUE O Page 3 of 3 Prepared By: h v Asa Bd Reed 7 Technical Services Technician d,'M j/ h Reviewed By: 'W-J4 W. Gahs echnical Services Supervisor Reviewed By: Mr'L Frank 11. Mathie Operations Manager l

Approved By: s Don Warembourg b wh w!@

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Manager, Nuclear Production l

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