05000267/LER-1979-047-03, /03L-0:on 791010,prestressed Concrete Realtor Vessel Cooling Water Sys Determined Impaired.Caused by Insufficient Hangar Base Plate & Bolts Out of Concrete.Base Redesigned & Modified to Provide Adequate Strength

/03L-0:on 791010,prestressed Concrete Realtor Vessel Cooling Water Sys Determined Impaired.Caused by Insufficient Hangar Base Plate & Bolts Out of Concrete.Base Redesigned & Modified to Provide Adequate Strength

ML19210C691
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/09/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19210C688	List: 05000267/LER-1979-047, Forwards LER 79-047/03L-0 05000267/LER-1979-047-03, /03L-0:on 791010,prestressed Concrete Realtor Vessel Cooling Water Sys Determined Impaired.Caused by Insufficient Hangar Base Plate & Bolts Out of Concrete.Base Redesigned & Modified to Provide Adequate Strength
References
LER-79-047-03L, LER-79-47-3L, NUDOCS 7911190434
Download: ML19210C691 (3)

LER-1979-047, /03L-0:on 791010,prestressed Concrete Realtor Vessel Cooling Water Sys Determined Impaired.Caused by Insufficient Hangar Base Plate & Bolts Out of Concrete.Base Redesigned & Modified to Provide Adequate Strength

Event date:
Report date:
2671979047R03 - NRC Website

text

NRC PORM 366 U. S. NUCLEAR REGULATORY COMMISSION mm 1.lCENSEE EVENT REPORT CONTROL BLOCK: l l

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1

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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O

2 lOn October 10.1979. at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> the c res tressed concrete resitor vessel cooline l

I water system was determined to be impaired due to an impaired hanger.11A-H-46890.

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1 This is a degraded mode of Fort St. Vrain Technical Specification LCO 4.3.10 and is l

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O s l reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2. There was no l

O s ] affect on public health and safety.

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N 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i

O lThe hancer. 11A-H-46890. base plate was insuf ficient and the anchor bolts had oulled g Iout of the concrete. The hanger was inadequate and the base was redesigned and I

y w l modified to provide adequate strength. No further corrective action _is antipated or i 1

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E, J.W. Gahm (303) 785-225'l NAME OF PREPARER _

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REPORT DATE:

November 9. 1979 REPORTALLE OCCURRENCE 79-47 ISSUE O OCCURRENCE DATE:

October 10, 1979 Page 1 of 2 FORT ST. VRAIN NUCLEAR GENERATLNG STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATIEVILLE, COLORADO 80651 REPORT NO. 50-267/79-47/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> October 10, 1979, the PCRV cooling water system was determined to be impaired due to an impaired hanger,11A-H-46890. This is a degradec' mode per Fort St. Vrain Technical Specification LCO 4.3.10 and is reportabAe per Fort St. Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

On October 10, 1979, with the plant operating at 36% thermal power and 140 W electrical power, a hanger,11A-H-46890, was determined to be impaired and also caused System 46 to be considered impaired.

This put the plant in a degraded mode of Fort S t. Vrain Technical Specification LCO 4.3.10 which allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of continued operation while the hanger is being repaired. The necessary work was done and the hanger returned to service October 12,1979, at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br /> within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limit.

CAUSE

DESCRIPTION:

The hanger base plate was inadequate and the anchor bolts had pulled out of the concrete.

CORRECTIVE ACTION:

The base plate was redesigned and the hanger modified accordingly. There was no affect on public health or safety and no further corrective action is anti-cipated or required.

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REPORTABLE OCCURRENCE 79-47 ISSUE O Page 2 of 2 Prepared by:

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p Asa B. Reed Technical Services Technician

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Reviewed by:

. W.'Cahm Technical Services Supervisor Reviewed by:

Frank M. Mathie Operations Manager Approved by:

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Don Warembourg N '

Manager, Nuclear Production 1353 054