ENS 45131

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v t e ENS Event
18:30 Jun 13, 2009
Title	Degraded Condition Due to Reactor Coolant Pressure Boundary Leak
Event Description	This notification is made pursuant to 10CFR50.72(b)(3)(ii) to report degradation of a principal safety barrier. During ASME Section XI (Table 2500-1 Code Category B-P, Item Number B15.10) refuel outage system leak testing of the reactor vessel and reactor coolant pressure boundary, leakage of approximately 1 drop per minute was detected from the bonnet vent leak-off connection on the reactor recirculation pump inlet isolation valve (RRC-V-23A) in the reactor coolant recirculation loop A. This condition is consistent with example (A)(2) provided in NUREG-1022, rev. 2 'Event Reporting Guidelines 10CFR50.72 and 50.73.' This example indicates that reporting under the above criteria is required for 'Welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.' A cause evaluation will be performed and a 60-day follow-up report provided pursuant to the corresponding 10CFR50.73 reporting requirement. The licensee notified the NRC Resident Inspector. * * RETRACTION FROM FRED SCHILL TO VINCE KLCO AT 1955 EDT ON 6/19/09 * * * Subsequent evaluation of the point where leakage was observed reveals that the 1 drop per minute leakage from RRC-V-23A was actually emanating from the packing chamber leak-off connection and not from the bonnet vent leak-off connection as reported. The packing chamber leak-off connection provides a means to monitor leakage from the packing. It does not provide a pressure containing function at its location on the valve and, therefore, is not part of the Reactor Coolant Pressure Boundary (RCPB) as defined in Part 50.2. Since the packing chamber leak-off connection is not a pressure-retaining structure it is not part of the RCPB, therefore the condition reported in event report #45131 is not a degradation of a principle safety barrier and is not reportable pursuant to Part 50.72(b)(3)(ii)(A). For this reason, the subject event report is hereby retracted. The licensee notified the NRC Resident Inspector. R4DO (Cain) notified.

ENS 45131 +/-
Where
Columbia Generating Station Washington (NRC Region 4)
Reporting

10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
Time - Person (Reporting Time:+0.83 h0.0346 days <br />0.00494 weeks <br />0.00114 months <br />)
Opened:	Nick Rullman 19:20 Jun 13, 2009
NRC Officer:	Donald Norwood
Last Updated:	Jun 19, 2009
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v • d • e

v t e Emergency Notification System
Columbia with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
WEEKMONTHYEAR2021-11-03T19:31:00 [Table view]
[ENS list for Columbia]

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