05000251/LER-1980-014-01, /01T-0:on 801126,insp Per IE Bulletin 79-14 Revealed Deficiency in Portions of Accumulator & RHR Sys Piping Inside Containment.Calculated Max Stress Exceeded Criteria.Mod Will Be Made Before Unit Returns to Svc

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/01T-0:on 801126,insp Per IE Bulletin 79-14 Revealed Deficiency in Portions of Accumulator & RHR Sys Piping Inside Containment.Calculated Max Stress Exceeded Criteria.Mod Will Be Made Before Unit Returns to Svc
ML17340A549
Person / Time
Site: Turkey Point 
Issue date: 12/10/1980
From: Pace P
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17340A544 List:
References
IEB-79-14, LER-80-014-01T-01, LER-80-14-1T-1, NUDOCS 8101050534
Download: ML17340A549 (3)


LER-1980-014, /01T-0:on 801126,insp Per IE Bulletin 79-14 Revealed Deficiency in Portions of Accumulator & RHR Sys Piping Inside Containment.Calculated Max Stress Exceeded Criteria.Mod Will Be Made Before Unit Returns to Svc
Event date:
Report date:
2511980014R01 - NRC Website

text

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The unit is currentl in refuelin shutdown.

A lant chan e moQification will be im lementeQ to su ort the i in before the unit is returneQ to service.

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REPORTABLE OCCURRENCE 251-80 LICENSEE EVENT REPORT PAGE TWO Additional Event Descri tion and Probable Conse uences:

On Wednesday, November 26, 1980, notification was received from our Architect-Engineer that inspections and reanalyses in progress in accordance with USNRC IaE Bulletin 79-14 had revealed a potential problem involving inadequate support of the Safety Injection System piping from the accumulator and interconnected Residual EIeat Removal piping to the Reactor Coolant System loops inside containment.

Specifically, the results indicated that the calculated maximum stress associated with the piping exceeded the acceptance criteria established for this review.

USNRC IGE Region II was notified of the above in ormation both verbally and by facsimile transmission.

Similar occurrences (relating to the inspections pursuant to USNRC I&E Bulletin 79-14) were reported as LER 250-79-26, LER 250-79-40, LER 250-80-08, and LER 250-80-14.

Additional Cause Description and Corrective Actions:

The evaluation conf'rmed that an overstress condition could potentially exist.

Based on these results, a plant change/modification was designed and will be implemented pr'or to heatup following the current refueling shutdown.

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inspection results and repairs will be made in response to USNRC IGE Bulletin 79-14.