ENS 40192: Difference between revisions

v t e ENS Event
08:00 Sep 23, 2003
Title	Unanalyzed Condition Due to Potential Rcs Leakage at Oconee 1
Event Description	During a scheduled bare metal visual inspection of the Unit 1 reactor vessel head prior to RV head retirement, evidence of possible through wall leakage was observed on two control rod drive mechanism (CRDM) and one thermocouple (T/C) penetrations (nozzles 6 and 16 and T/C nozzle 7). Of these locations, only the T/C had been previously repaired (plugged) in December 2000. Initial Safety Significance: Any RCS leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process. Total measured RCS leakage prior to unit shutdown was varying between 0.15 gallons per minute and .24 gallons per minute. Corrective Action: The reactor vessel head is scheduled for replacement during the present refueling outage. Therefore, there are no plans at this time to perform additional inspections or repairs on the current head. The NRC Resident Inspector was notified.

ENS 40192 +/-
Where
Oconee South Carolina (NRC Region 2)
Reporting

10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition
Time - Person (Reporting Time:+3.25 h0.135 days <br />0.0193 weeks <br />0.00445 months <br />)
Opened:	Randy Todd 11:15 Sep 23, 2003
NRC Officer:	Rich Laura
Last Updated:	Sep 23, 2003
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v • d • e

v t e Emergency Notification System
Oconee with 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition
WEEKMONTHYEAR2014-03-28T17:00:00 [Table view]
[ENS list for Oconee]

@@ Line 16: / Line 16: @@
 | event date = 09/23/2003 04:00 EDT
 | last update date = 09/23/2003
-| title = Unanalyzed Condition Due To Potential Rcs Leakage At Oconee 1
+| title = Unanalyzed Condition Due to Potential Rcs Leakage at Oconee 1
 | event text = During a scheduled bare metal visual inspection of the Unit 1 reactor vessel head prior to RV head retirement, evidence of possible through wall leakage was observed on two control rod drive mechanism (CRDM) and one thermocouple (T/C) penetrations (nozzles 6 and 16 and T/C nozzle 7). Of these locations, only the T/C had been previously repaired (plugged) in December 2000.
 Initial Safety Significance: Any RCS leakage from these penetrations would have been below the threshold of measurability by the reactor coolant system leakage measurement process. Total measured RCS leakage prior to unit shutdown was varying between 0.15 gallons per minute and .24 gallons per minute.

Latest revision as of 21:25, 1 March 2018