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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
Nuclear Management Company, LLC NMC Committed to Nuclear Excellence Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241 NRC 2002-0095 10 CFR 50.48 October 22, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Dockets 50-266 and 50-301 Point Beach Nuclear Plant, Units 1 and 2 Reporting Of Fire Barriers Degraded For More Than Seven Days Enclosed is a 30-day report for Point Beach Nuclear Plant (PBNP), Unit 1 and Unit 2. This report is provided in accordance with the PBNP Fire Protection Evaluation Report (FPER),
Section 8.1.5. That section requires the submittal of a report to the U. S. Nuclear Regulatory Commission when degradation of fire protection systems or components exceeds the time listed in FPER Section 8.1.3. Paragraph C.1.b (4) of that section requires a report if an inoperable fire barrier is not restored to an operable status within a seven-day period.
The damming boards for fire penetration seals M-5-3-29-F05 and M-5-3-29-F1 3 were removed from the penetrations to facilitate the removal and replacement of 4.16 KVA, 1P-28 Main Feed Water Pump, power feeder cables. These penetrations are located in the 3-hr fire rated barrier (floor/ceiling assembly) separating the Vital Switchgear Room (below) from the Non-Vital Switchgear Room (above). Removal of the boards was performed on September 18, 2002.
Final acceptance of the restored seals was performed on September 28 for penetration M-5 29-F5 and on September 29 for penetration M-5-3-29-F1 3, resulting in an out-of-service time of 10 and 11 days, respectively. Appropriate compensatory measures (hourly fire rounds) were initiated and maintained from the time the damming boards were removed until restoration of these seals was complete.
This report contains no new commitments.
If you have any questions concerning this activity, please contact Norm Hoefert at 920-755-7590.
Sinc ely, T. H. Taylor Plant Manager CWK/kmd cc: NRC Regional Administrator NRC Project Manager NRC Resident Inspector PSCW
