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Category:Meeting Briefing Package/Handouts
MONTHYEARML23317A2032023-12-13013 December 2023 Pre-Submittal Meeting: Tech Spec Amendment Request for HPCI Flow Switch Setpoint Change ML23150A1382023-06-0101 June 2023 Pre Submittal Meeting: Containment Inservice Inspection (Cisi) Relief Request, June 1, 2023 ML23150A1372023-06-0101 June 2023 Pre-Submittal Meeting: Diesel Generator Fuel Oil Storage Tank Cleaning/Inspection, June 1, 2023 ML21125A0372021-05-0606 May 2021 May 6, 2021 Public Meeting (Observation) Slides for RAP Back Program Presentation to Industry(003) ML20080M1582020-02-21021 February 2020 PFHA-2020-3B-3-Vossmar_Stafford-2019_CNS_FCS_Flooding ADAMS Version ML18255A0102018-09-12012 September 2018 NRC Slides for Target Rock Public Meeting ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML14149A0742014-05-30030 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Response to Question 1 Part 2 ML14149A0902014-05-22022 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Detailed Schedule June 2012 Through February 2015 Gantt Chart ML14149A0882014-05-22022 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Detailed Schedule May 2014 Through February 2015 Gantt Chart ML14149A0852014-05-22022 May 2014 5/22/14 Meeting Handouts - Meeting with OPPD and NPPD to Discuss Flooding Hazard Reevaluation Extension Requests for Fort Calhoun Station and Cooper Nuclear Station - Hi-Level Overview Schedule for Flooding Hazard Reevaluation Report ML14129A1492014-05-0909 May 2014 Station/Cooper Nuclear Station - Meeting Slide for Flood Hazard Reevaluation Report Schedule Extension Review ML13178A1592013-06-26026 June 2013 Summary of Meeting for Public Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML12311A0492012-09-18018 September 2012 Part 26 Public Meeting NEI Presentation Slides ML1129715762011-10-24024 October 2011 Licensee Slides from 10/24/11 Meeting with Nebraska Public Power District to Discuss Cooper Nuclear Station ML1121401792011-07-11011 July 2011 Licensee Slides from Conference Call with Nebraska Public Power District IR 05000298/20110092011-06-10010 June 2011 EA-11-204, Cooper Nuclear Station, Final Significance Determination of White Finding and Notice of Violation, NRC Inspection Report 05000298/2011009 ML1112606772011-05-0606 May 2011 Summary of Meeting with Nebraska Public District, Cooper Discussed the Significance, Cause and Corrective Action Associated with an Apparent Violation with Low-to-Moderate Safety Significance ML1029202962010-10-19019 October 2010 Meeting Handouts for October 19, 2010 with Nebraska Public Power District Regarding Cooper Nuclear Station ML1016001102010-06-0909 June 2010 Summary of Annual Performance Assessment Meeting for Cooper Nuclear Station ML1011904802010-04-29029 April 2010 Summary of Meeting with Nebraska Public Power District to Discuss Issues Associated with the Independent Spent Fuel Storage Installation (ISFSI) ML1011103782010-04-20020 April 2010 Public Meeting Summary from 4/7/2010 ML1010503762010-04-0707 April 2010 Preliminary Site-Specific Results of the License Renewal Environmental Review for Cooper Nuclear Station ML0909700972009-04-0707 April 2009 Summary of Annual Performance Assessment Meeting with Nebraska Public Power District to Discuss Safety Performance at Cooper Nuclear Station Between January 1 & December 31, 2008 ML0907506862009-02-25025 February 2009 Scoping and Process Public Meeting Sides of February 25, 2009 ML0816201532008-06-10010 June 2008 End-of-Cycle Meeting Summary 6/2/08 ML0815501022008-05-28028 May 2008 Meeting Summary for Regulatory Conference with Nebraska Public Power District to Discuss the Significance of an Inspection Finding Associated with Two Procedures That Were Not Adequate ML0712005272007-04-30030 April 2007 Nrc/Entergy Operations, Inc. Management Meeting to Discuss the Performance of Arkansas Nuclear One, Cooper, Grand Gulf, River Bend and Waterford, Unit 3 ML0721104822006-10-31031 October 2006 Significance Determination Process Refresher Training ML0612904602006-05-0505 May 2006 May 5, 2006 Meeting Slides ML0524300942005-10-0303 October 2005 Slides from August 29, 2005 Meeting with NPPD ML0503405322005-02-0303 February 2005 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0413802292004-05-17017 May 2004 Summary of Confirmatory Action Letter 5th Quarterly Inspection Exit Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0410503302004-04-14014 April 2004 Meeting Summary for End-of-Cycle Performance Assessment for Cooper Nuclear Station ML0402800142004-01-27027 January 2004 Summary of CAL 4th Quarterly Inspection Exit Meeting with Nebraska Public Power District Cooper Nuclear Station ML0331402912003-11-0707 November 2003 Summary of Meeting with Nebraska Public Power District Regarding Cooper Nuclear Station ML0302905232002-12-13013 December 2002 Briefing Slides for Presentation Status of the CNS BWRVIP Program from 12/13/2002 Meeting with Nebraska Public Power District ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary ML0205703522002-02-26026 February 2002 02-07-02 Cooper/Nebraska Public Power District Meeting Summary ML17252A1571977-09-14014 September 1977 Summary of Meeting Held with Representatives of the Mark I Owner'S Group to Discuss the Structural Acceptance Criteria for the Mark I Containment Long Term Program 2023-06-01
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Significance Determination Process Refresher Training DRS Inspector Counterpart Meeting October, 2006
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Cooper Nuclear Station, Brownville, NE
Significance Determination Process Refresher Training DRS Inspector Counterpart Meeting October, 2006 Objective: Improve Inspector Knowledge on the Significance Determination Process Including the Use of the Plant-Specific Risk-Informed Notebooks Method: The Inspectors will be asked to perform a risk estimate for an example inspection issue. These results will be reviewed and discussed with the Senior Reactor Analysts during an open session in the counterpart meeting.
Activities: Prior to the session to be held on October 11, 2006 at *******, inspectors should read the following documented inspection issue, review the appropriate portions of Inspection Manual Chapters 0609 and 0612, and conduct the following:
- 1) Identify and document the performance deficiency to be evaluated;
- 2) Make and document the minor determination including appropriate references;
- 3) Complete a Phase 1 screening of the issue and document by completely filling out the attached form; and
- 4) Conduct a Phase 2 estimate using the Cooper Nuclear Station Site-Specific Risk-Informed Notebook and completing the appropriate worksheets (attached).
Issue: The following was an inspection issue modified to better exercise various portions of the significance determination process:
On December 29, 2004, at 7:28 pm, control room operators at the Cooper Nuclear Station attempted to start Service Water Pump A from the main control room. During the attempt, the circuit breaker closed and then immediately tripped open. As a result, Service Water Pump A was declared inoperable in accordance with Technical Specification 3.7.2. Operators were dispatched to the switchgear and were able to start the pump successfully via local operation of the breaker. The breaker was removed from service and replaced with a spare on December 30, at 1:37 am. The inspectors determined that the pump had last been successfully started at 8:34 am on December 25 for routine pump rotation.
The circuit breaker for Pump A is a 4160 V General Electric Magne-Blast
breaker. Troubleshooting on the breaker by the licensee and by the original equipment manufacturer indicated that a critical clearance between the prop pin and the breaker frame was inadequate. There was also evidence that the prop pin had come in contact with the frame which would have prevented the breaker from latching in the closed position during operation. The breaker had been overhauled by a vendor in January 2000 and, during receipt inspection by the licensee, the prop pin clearance was verified to be adequate. The licensee determined that, although the clearance was adequate in 2000, insufficient spacers between the prop pin and frame allowed the prop pin to travel along its shaft during breaker operation until it contacted the frame. Travel of the prop pin was determined by the manufacturer to occur only during cycling of the breaker.
In December 2000, Resolve Condition Report 2000-1165 documented a similar failure of Service Water Booster Pump B caused by inadequate clearances between the prop pin and frame. This breaker had also been overhauled by the same vendor and the licensee was able to verify that the prop pin clearance was adequate following overhaul but inadequate spacers had allowed the pin to travel along the shaft and become misaligned during successive breaker operations.
As a result, the licensee's breaker engineer recommended the addition of washers between the pin and frame to ensure the critical clearance was maintained. In addition, the entire population of safety-related breakers were inspected, including the breaker for Service Water Pump A, to ensure that adequate clearance existed between the pin and frame; however, the work request to perform this inspection did not require the verification or addition of adequate spacers. The breaker for Service Water Pump A had been verified to have adequate clearances during this inspection, but no spacers were added to ensure this clearance was maintained.
Minor Determination EDMinor E More than Minor Specific
Reference:
Reason: