05000285/LER-1976-032, Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve

Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve

ML20087H817
Person / Time
Site:	Fort Calhoun
Issue date:	10/04/1976
From:	Dermyer B OMAHA PUBLIC POWER DISTRICT
To:	Seidle B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20087H755	List: 05000285/LER-1976-032, Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve
References
FC-1127-76, HLWR, NUDOCS 8403210204
Download: ML20087H817 (1)

LER-2076-032, Summary of 761004 Telephone Communication on LER 76-32/01L Re Reactor Coolant Observed Spraying from Weld Area on Seal Leakoff Line on Reactor Coolant Pump RC-3C.Leakage Isolated by Manual Isolation Valve

Event date:
Report date:
2852076032R00 - NRC Website

text

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f* Le ORECORD OF TELEPHONE C ] MUNICATION FC-1127-76 J

DATE: October h, 1976 TIME: 1700 PARTY CALLING: Bill Dermyer OPPD (Name) (Company)

PARTY ANSWERING: Bill Seidle NRC-OIE Region IV (Name) (Company) ' '

SUBJECT:

LER 50_285/76-32 TELECON

SUMMARY

(Including Decisions and Commitments)

.t After the reactor was shutdown for the 1976 refueling outage and during a containment inspection, reactor coolant was observed to be -

spraying from a weld area on the seal leakoff line on Reactor Coolant Pump RC-30. Leak rate could not be determined; however, it is estimated to be less than 0.2 gpm. After the reactor coolant system was cooled to cold shutdown, the leakage was isolated by a manual isolation valve.

This incident is similar to LER 50-285/75-26, however, the leak rate was much smaller. No increase in containment activity or dev point was indi-cated, nor was leakage indicated by a leak rate calculation. This is considered an " abnormal degradation of one of the several boundaries which are designed to contain radioactive materials "

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