05000267/LER-1980-006-03, /03L-0:on 800218,w/reactor at Less than 2% Power, Vent Stack Snubber VSS-117 Was Inoperable & Degraded Mode of Tech Spec LCO 4.3.10 Existed.Caused by Taking Reactor Critical W/Vent Stack Snubber Out of Svc for Maint

/03L-0:on 800218,w/reactor at Less than 2% Power, Vent Stack Snubber VSS-117 Was Inoperable & Degraded Mode of Tech Spec LCO 4.3.10 Existed.Caused by Taking Reactor Critical W/Vent Stack Snubber Out of Svc for Maint

ML19305C061
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/19/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19305C059	List: 05000267/LER-1980-006, Forwards LER 80-006/03L-0 05000267/LER-1980-006-03, /03L-0:on 800218,w/reactor at Less than 2% Power, Vent Stack Snubber VSS-117 Was Inoperable & Degraded Mode of Tech Spec LCO 4.3.10 Existed.Caused by Taking Reactor Critical W/Vent Stack Snubber Out of Svc for Maint
References
LER-80-006-03L, LER-80-6-3L, NUDOCS 8003250537
Download: ML19305C061 (1)

LER-1980-006, /03L-0:on 800218,w/reactor at Less than 2% Power, Vent Stack Snubber VSS-117 Was Inoperable & Degraded Mode of Tech Spec LCO 4.3.10 Existed.Caused by Taking Reactor Critical W/Vent Stack Snubber Out of Svc for Maint

Event date:
Report date:
2671980006R03 - NRC Website

text

U. S. NUCLEAO R E!ULATCY COMMISSION NRC FORM 364 LICENSEE EVENT REPORT l

(PLEAsE PRINT OR TYPE ALL REQUIRED INFCCMATION)

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60 St DOCKET NUMagR 68 69 EVENT DATE 74 75 RE, ORT CATE 80 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h lTITI l On February 18, 1980, with the reactor critical at less than 2Z power, it was l

ITTTII determined that a vent stack snubber, VSS-117, was inoperable and a degraded mode of I lo l4I I Fo rt S t. Vrain Technical Specification LCO 4.3.10 existed. This is reportable per I

ITTTI l Fort St. Vrain Technical Specification AC 7.5.2(b)3.

The reactor was taken sub-l iTTii1 I critical and remained suberitical till the snubber was replaced. No accompanying oc-l lo til I currence. No affect on public health or safety. A similar occurrence was RO 79-64. l I

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gl VSS-117, a vent stack snubber, was removed from service during a maintenance shut-I

['iTO l dcwn without informing the Shif t Supervisor. On February 17, 1980, the reactor was I l taken critical with operations personnel unaware that VSS-117 had been removed.

I gl Personnel involved were reprimanded and the igortance of following approved pro-l gl cedures re-emphasized. No other corrective action anticipated or required.

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