ML19305D807

Forwards LER 80-013/03L-0

ML19305D807
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/09/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19305D808	List: ML19305D807 ML19305D815
References
P-80075, NUDOCS 8004150542
Download: ML19305D807 (5)

Text

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R public service company of comade l

.,j j 16805 Weld County Road 191/2, Platteville, Colorado 80651

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April 9,1980 Fort St. Vrain Unit No. 1 P-80075 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Conunission 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/

80-13, 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. 50-267/80-13.

i Very truly yours, D War r Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC

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800.4150542

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REPORT DATE: April 9, 1980 REPORTABLE OCCURRENCE 80-13 ISSUE O OCCURRENCE DATE: March 10, 1980 Page 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/80-13/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

On March 10, 1980, the indicated sample flow for two of the primary coolant dewpoint moisture monitors was discovered to be less than required by LCO 4.4.1, Note (t) .

This is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT DESCRIPTION:

On March 10, 1980, while operating at 58% thermal power and 182 5' electrical, it was discovered that the indicated sample flow for two of the low level primary coolant dewpoint moisture monitors was less than required by LCO 4.4.1, '

Note (t).

Instrument personnel investigated the sample flow problems and found that the flow elements for MM-1117 and MM-1122 were reading incorrectly. See Figure 1. i The indicated flow through the flow element @ , was less than required for

• the moisture monitor to be considered operable. Howev conditions and the position of the bypass valve h , er,the considering actual flowsystem should have been greater than the indicated and the required flow. Plant power level was reduced, and as the actual ample flow rate decreased, the sample flow indicated by the flow element 1 began correspond to. the expected actual flow rate through the moisture monitori .

The Instrument personnel could not determine what caused the erroneous readings '

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in either of the flow elements, and it was heided to replace both of the flow elements.

CAUSE DESCRIPTION:

The insufficient indicated sample flow was the result of incorrect readings from respective moisture montior flow elements.

REPORTABLE OCCURRENCE 80-13 ISSUE O Page 2 of 4 ,

CORRECTIVE ACTION:

The flow element for 191-1122 was replaced and the flow element for MM-1117 will be replaced as plant conditions allow.

There was no affect on public health or safety. .

No further corrective action is anticipated or required. t i

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. REPORTABLE OCCURRENCE 80-013 ISSUE O Page 3 of 4 Sample Return ,

Flow Element '

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= 8 ,

a j i Moisture g __.J i

Monitor

'k Bypass Valve Sample C S upply---

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FIGURE 1 l i

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REPORTABLE OCCURRENCE 80-13 ISSUE O Page 4 of 4 Prepared By: /dL 4* ll Asa B. Reed Technical Services Technician Reviewed By:

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J'. W. Gahm'

, Technical Services Supervisor Reviewed By:

Frank M. Mathie Operations Manager Approved By: O Y /z4 2 % [ u Don Warembourg g Manager, Nuclear Production

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