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Category:Licensee 30-Day Written Event Report
MONTHYEARL-2019-058, CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-03-25025 March 2019
CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report
L-2018-063, CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications2018-03-26026 March 2018
CFR 50.46 Annual Reporting and 30-day Notification of Changes or Errors in Emergency Core Cooling System Models or Applications
NRC-2017-0012, Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result2017-02-24024 February 2017
Submitting 10 CFR 26.719(c) Report on Inaccurate Reporting of Laboratory Test Result
L-2016-124, 10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach2016-06-17017 June 2016
10 CFR 50.46 30-Day Report for Turkey Point, Seabrook, and Point Beach
NRC 2016-0015, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2016-04-0606 April 2016
Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report
NRC 2014-0086, 10 CFR 50.46 30-Day Report2014-12-11011 December 2014
10 CFR 50.46 30-Day Report
NRC 2014-0029, CFR 50.46 Annual Report/30-Day Report2014-04-18018 April 2014
CFR 50.46 Annual Report/30-Day Report
NRC 2014-0012, Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report2014-02-13013 February 2014
Large Break Loss-of-Coolant Accident Margin Summary Sheet - 30-Day Report
NRC 2013-0081, Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report2013-08-23023 August 2013
Large Break Loss-of Coolant Accident Margin Summary Sheet- 30-Day Report
NRC 2012-0038, ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum2012-05-30030 May 2012
ECCS 30-Day Report for the Thermal Conductivity Degradation Impact on Large Break Loss of Coolant Accident Analyses with Astrum
NRC-2007-0055, Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.462007-07-0303 July 2007
Error Identified in ECCS Evaluation Model 30-Day Report Required by 10 CFR 50.46
ML0508303282004-05-0606 May 2004
Event Notification 40728 for Point Beach
NRC 2003-0042, Reporting of Fire Barriers Degraded for More than Seven Days2003-05-0909 May 2003
Reporting of Fire Barriers Degraded for More than Seven Days
NRC 2002-0095, Reporting of Fire Barriers Degraded for More than Seven Days2002-10-22022 October 2002
Reporting of Fire Barriers Degraded for More than Seven Days
NRC 2002-0083, Reporting of Fire Barriers Degraded for More than Seven Days2002-09-26026 September 2002
Reporting of Fire Barriers Degraded for More than Seven Days
ML0307702772002-08-0707 August 2002
2-page Abnormal Occurrence Writeup for 11/29/2001 Event Potential Loss of All Auxiliary Feedwater at Point Beach Plant
2019-03-25
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Category:Written Event Report (30 or 60 day)
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Text
-- Event Notification Report for July 21, 2004 Page 1 of 1 U.S. Nuclear Regulatory Commission Operation Center Power Reactor Event Number:40728 Facility: POINT BEACH Notification Date 05/06/2004 Region:3 State: WI Notification Time:13:30 [EST]
Unit: [1] Event Date:05106/2004 RX Type:[1] W-2-LP,[2] W-2-LP Event Time:10:46 [CDT]
NRC Notified By:JIM FOUSE Last Update Date:05/06/2004 HQ OPS Officer: MIKE RIPLEY Emergency Class: NON EMERGENCY Person (Organization):
10 CFR Section: CHRISTINE LIPA (R3) 50.72(b)(3)(ii)(A) - DEGRADED CONDITION TERRY REIS (NRR)
SCAM Initial Current Unit Code RX CRIT PWR Initial RX Mode PWR Current RX Mode 1 N 0 0 Refueling 0 Refueliny Event Text REACTOR VESSEL HEAD NOZZLE WELD AREA FLAW During performance of NDE examinations of the Point Beach Nuclear Plant (PBNP) Unit 1 reactor pressure vessel (RPV) head required by the First Revised NRC Order (EA-03-009), flaw indications were identified on Nozzle 26. The ultrasonic examination (UT) signal for nozzle 26 identified flaw indications in the J-groove weld area that extend into the CRDM tube base material.
'A dye-penetrant (PT) examination of the nozzle 26 CRDM J-groove material was also performed. The PT exams showed minor surface indications that required further evaluation. Following minor excavation of the weld surface, additional examinations of the J-groove surface were performed. The results of these exams indicated the existence of flaws in the weld that do not meet accepted flaw evaluation guidance.
'Based upon preliminary analysis, it is expected that these indications would not be found acceptable under ASME standards. Therefore, this condition represents degradation of a principal safety barrier reportable under 10 CFR 50.72(b)(3)(ii)(A).
"PBNP Unit 1 Nozzle 26 is planned to be repaired prior to placing the RPV Head back into service.
"The condition was determined to be reportable at 1046 CDT on May 6, 2004. The licensee has notified the Resident Inspectors."
