05000029/LER-1976-003-01, /01T-0:on 760513,review of ECCS Analysis Found Error in Accident Analysis.Caused by Error in Assumption of Accident Analysis.Reanalysis Performed.Proposed Change to Tech Specs Submitted

/01T-0:on 760513,review of ECCS Analysis Found Error in Accident Analysis.Caused by Error in Assumption of Accident Analysis.Reanalysis Performed.Proposed Change to Tech Specs Submitted

ML19343B089
Person / Time
Site:	Yankee Rowe
Issue date:	05/27/1976
From:	Janet Staub YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19343B088	List: 05000029/LER-1976-003, Forwards LER 76-003/01T-0 05000029/LER-1976-003-01, /01T-0:on 760513,review of ECCS Analysis Found Error in Accident Analysis.Caused by Error in Assumption of Accident Analysis.Reanalysis Performed.Proposed Change to Tech Specs Submitted
References
LER-76-003-01T, LER-76-3-1T, NUDOCS 8012040184
Download: ML19343B089 (3)

LER-1976-003, /01T-0:on 760513,review of ECCS Analysis Found Error in Accident Analysis.Caused by Error in Assumption of Accident Analysis.Reanalysis Performed.Proposed Change to Tech Specs Submitted

Event date:
Report date:
0291976003R01 - NRC Website

text

u IIR 76-03 01 T LICENSEE E ENT REPORT

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3 LER 76-03/01 T

Event Description

hhile shutdown for main exciter repairs a review i

of the emergency core cooling system (ECCS) analysis discovered an i

error in the accident analysis that could have permitted reactor operation on a manner less conservative than assumed in the analysis.

The ECCS accumulator flow was discovered to be higher than that assumed in the analysis. This event is reported in accordance with i

Technical Specification E.2.a. (7).

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Cause Description: 'lhis event was an error in the assumption of the j

accident analysis. A reanalysis was performed to correct the dis-j crepancy. A proposed change to the technical specifications was submitted to reduce the ECCS accumulator pressure and, thereby, i

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reduce the flow to be consistent with that assumed on the accident analysis., The proposed change was approved and the reactor was l

returned to power operation.

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NRC DISTRIBUTION von PART 50 DOCKET MATERIAL

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LER 50-29 (76-03/01 T) ON 5-13-76 RE REVIEW I

CT 5]CCS NOTED AN ERROR IN THE ACCIDENT ANALYSIS l

WHICH CAUSED THE ACCU:EILATOR FIDW TO EE HIGHER

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