05000029/LER-1976-007-01, /01T-0:on 760624,investigation of RO 76-06 Revealed That Assumed Boron Concentration of LOCA Analysis Was Exceeded During Hydrostatic Leak Test of Reactor Vessel. Caused by Personnel Error.Personnel Reinstructed

/01T-0:on 760624,investigation of RO 76-06 Revealed That Assumed Boron Concentration of LOCA Analysis Was Exceeded During Hydrostatic Leak Test of Reactor Vessel. Caused by Personnel Error.Personnel Reinstructed

ML19345A415
Person / Time
Site:	Yankee Rowe
Issue date:	07/08/1976
From:	Janet Staub YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19345A413	List: 05000029/LER-1976-007, Forwards LER 76-007/01T-0 05000029/LER-1976-007-01, /01T-0:on 760624,investigation of RO 76-06 Revealed That Assumed Boron Concentration of LOCA Analysis Was Exceeded During Hydrostatic Leak Test of Reactor Vessel. Caused by Personnel Error.Personnel Reinstructed
References
LER-76-007-01T, NUDOCS 8011210344
Download: ML19345A415 (4)

LER-1976-007, /01T-0:on 760624,investigation of RO 76-06 Revealed That Assumed Boron Concentration of LOCA Analysis Was Exceeded During Hydrostatic Leak Test of Reactor Vessel. Caused by Personnel Error.Personnel Reinstructed

Event date:
Report date:
0291976007R01 - NRC Website

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LER 76-07/01T EVENT DESCRIPTIGN During normal operation an investigation uns initiated into the details of Reportable Occurrence 76-06, Personnel Error.

The in-vestigation discovered that during the hydrostatic leak test of the reactor vessel and portions of the Physics Testing program for Core XII startup the assteed baron concentration, of the IDCA Analysis was exceeded.

Amendment No. 21, Enclosure A to the Technical Specifications asstned maximum boron concentration limits for the main coolant, safety injection tank and safety injection accumulator to minimize Se effects of boren precipitation following a loss of coolant accident.

i With the boron concentrations in excess of those assumed 'on the analysis the post LOCA sump and core concentration would have exceed that assined in the analysis.

This incident is reported as Reportabic Occurrence 50-29/76-07.

CAUSE DESCRIPTION Based on a Post IDCA sump and core concentration of 2314 ppm (from analysis)

Hot Leg Injection would be required in 20 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to preclude flow channel blockage.. A reanalysis perfonned with the higher boron concentration during Core XII startup (2407 ppm) indicated that the i

time required to hot leg injection would not have changed.

Therefore, it is concluded that this incident wuuld not have been inimical to the public health and safety.

. Personnel have been reminded of their responsibilities to review accident analysis assumptions.

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IIR 76-07/01T ADDITIOXAL FACIORS The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report of June 28, 1976 reported that the main coolant boron exceeded that assumed in the accident analysis by approximately 75 ppm during initial power operation.

Further eyaluation of the data revealed that the actual worst case occurrdd during the main coolant system hydrostatic test when the boron concentration reached 2420 ppm.

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DESCRIPTION

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