ENS 41536: Difference between revisions

From kanterella

Latest revision as of 22:21, 1 March 2018

v t e ENS Event
15:35 Mar 28, 2005
Title	Rcs Through Wall Leakage Identified at Welded Piping Junction
Event Description	At 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> on the morning of 3/28/05, investigation into a previously reported leak (Event #41530) identified an approximate 3 inch through wall flaw at the welded junction of the 4 inch diameter decon port and the 28 inch diameter 'B' Reactor Recirculation Systems pump suction piping. The identification of the indication required the removal of insulation in order to complete the inspection. The unidentified leakage rate is below Tech Spec limits and the leak location is within the isolable boundary of the 'B' Reactor Recirculation Pump. This failure constitutes a welding or material defect in the primary coolant system that is not acceptable under ASME Section XI for ASME Code Class 1 piping. This report is being made under Hope Creek Event Classification Guide RAL# 11.2.1 in accordance with 10CFR50.72(b)(3)(ii). At the time of this notification, the Hope Creek Generating Station is in OPCON 4 at 150 degrees reactor coolant temperature to support piping repairs. The licensee informed the Lower Alloways Creek Township and NRC Resident Inspector.

ENS 41536 +/-
Where
Hope Creek New Jersey (NRC Region 1)
Reporting

10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
Time - Person (Reporting Time:+0.28 h0.0117 days <br />0.00167 weeks <br />3.83544e-4 months <br />)
Opened:	Clyde Bauer 15:52 Mar 28, 2005
NRC Officer:	Steve Sandin
Last Updated:	Mar 28, 2005
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v • d • e

v t e Emergency Notification System
Hope Creek with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded
WEEKMONTHYEAR2024-05-03T08:11:00 [Table view]
[ENS list for Hope Creek]

@@ Line 16: / Line 16: @@
 | event date = 03/28/2005 10:35 EST
 | last update date = 03/28/2005
-| title = Rcs Through Wall Leakage Identified At Welded Piping Junction
+| title = Rcs Through Wall Leakage Identified at Welded Piping Junction
 | event text = At 1035 hours on the morning of 3/28/05, investigation into a previously reported leak (Event #41530) identified an approximate 3 inch through wall flaw at the welded junction of the 4 inch diameter decon port and the 28 inch diameter 'B' Reactor Recirculation Systems pump suction piping. The identification of the indication required the removal of insulation in order to complete the inspection. The unidentified leakage rate is below Tech Spec limits and the leak location is within the isolable boundary of the 'B' Reactor Recirculation Pump. This failure constitutes a welding or material defect in the primary coolant system that is not acceptable under ASME Section XI for ASME Code Class 1 piping.
 This report is being made under Hope Creek Event Classification Guide RAL# 11.2.1 in accordance with 10CFR50.72(b)(3)(ii). At the time of this notification, the Hope Creek Generating Station is in OPCON 4 at 150 degrees reactor coolant temperature to support piping repairs.