05000267/LER-1981-001, Forwards LER 81-001/03L-0.Includes Narrative Description of Event Re High Outlet Temp in Pcrv Cooling Water Sys

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Forwards LER 81-001/03L-0.Includes Narrative Description of Event Re High Outlet Temp in Pcrv Cooling Water Sys
ML20003A611
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 01/30/1981
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20003A612 List:
References
P-81031, NUDOCS 8102040401
Download: ML20003A611 (4)


LER-1981-001, Forwards LER 81-001/03L-0.Includes Narrative Description of Event Re High Outlet Temp in Pcrv Cooling Water Sys
Event date:
Report date:
2671981001R00 - NRC Website

text

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fIp ~{y puhuc Service Company @ CcBondo jf. e 5. i 16805 ROAD 19%

PLATTEV1LLE, COLOR ADO 80651 t"-

January 30, 1981 Fort St. Vrain Unit No. 1 P-61031 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/

81-001, 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. 50-267/80-001.

Very truly yours,

' Wou Don Warembourg Manager, Nuclear Production DW/cis Enclosure cc: Director, MIPC

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REPORT DATE:

January 30, 1981 REPORTABLE OCCL2RE' CF S1-001 ISSUE O OCCURRENCE DATE:

December 31, 1980 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATION PU3LIC SEP,VICE COMPAn~ OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO S0631 REPORT NO. 50-267/SI-001/03-L-0 Final IDENTIFICATION OF OCCURRENCE :

On Dece=ber 31, 1980, the outlet water te=perature of the Loop 2 PCRV cooling water system exceeded 120*F.

This event constitutes cperation in a degraded mode allowed by LCO 4.2.15.b) and is reportable per Fort S t. Vrain Technical Specification AC 7.5.2(b)2.

EVFliT DESCRI? TION:

The control scheme for the PCRV liner cooling system is designed to maintain the average of the inlet water temperature and the outlet water te=perature at a constant value. The controller setpoint determines this value when operating in automatic. During calibration of system instruments (te=perature elements, indicators, etc.), the temperature controllers - for both PCRV liner cooling loops were placed in =anual to avoid erroneous control action. When calibration was complete, the loop outlet water temperature had increased to ll5'F in both loops. The operator nulled the controller demand to match the p resent. temperature and placed both controllers in automatic. The catching of controller demand to actual conditions is done to allev s=coch transfer from =anual to automatic control. The next step is to gradually adjust the controller setpoint to the desired value. However, af ter placing the con-trollers in automatic, the operator was distracted by other events in the Control Room and the controller setpoints re=ained at 115*F.

Therefore, when the setpoint was lef t at 115'F, the inlet and outlet water temperature in--

creased until the average was ll5'F.

This average was reached when the out-let water temperature was 121* F..

An operator noted that both te=perature controllers for the PCRV liner cooling system were set at temperatures greater than the 120*F limit specified in LCO 4.2.15b).

He reset the control'lers to the normal value and the ' outlet water temperature decreased f rom 121*F to below the LCO 11=1t.

Review of the temperature re-corder chart showed that the outlet _ water temperature had been above the limit for approximately eleven hours with a maxizum temperature of 122*F.

REPORTABLE OCCURRENCE '81-001-ISSUE O Page 2 of 3

CAUSE

DESCRIPTION:

The operator was distracted by other events in the Control Room and the con-troller setpoints remained at 115*F.

CORRICTIVE ACTION:

The temperature controllers were returned to their normal setpoint and-the Loop 2. outlet water temperature decreased below the LCO li=it.

Personnel have been re:inded of the i=portance of verifying setpoint limits.

In addition, the Training Ceparr:ent has been requested to. hold a special review on this control system and the associated Technica1' Specifications.

No further corrective action is anticipated or' required.

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9 REPORTABLE OCCURRENCE 81-001 ISSUE O Page 3 of 3 b

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, h 4 eg Prepared By:

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Richard R. Frost Technical Services Technician

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Reviewed By:

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Gahm echnical Services Supervisor Revieued By:

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/Y)s_E/w fy />$)W Y

l Frank M. Mathie.

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Operations Manager i.

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Approved By:

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Don Warembourg g

i Manager, Nuclear Production i

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