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Category:Meeting Briefing Package/Handouts
MONTHYEARML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor ML21126A3032021-05-10010 May 2021 Entergy Operations, Inc. Pre-Submittal Meeting - Grand Gulf Nuclear Station, Unit 1 Relief Request to Adopt Performance-based Testing for Pressure Isolation Valves (Pivs) ML20357B0592020-12-16016 December 2020 Enc 2 - Grand Gulf Nuclear Station Regulatory Conference December 2020 - NRC Presentation ML20357B0612020-12-16016 December 2020 Enc 3 - Entergy Slides for Regulatory Conference December 2020 - Final ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML19122A4202019-05-0202 May 2019 Summary of Public Meeting with Entergy Operations, Inc ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML17283A4122017-10-10010 October 2017 Grand Gulf Nuclear Station, Unit 1 - Meeting Slides - October 10, 2017 Pre-Application Meeting with Grand Gulf Concerning Tornado Missile Risk Evaluator Submittal ML13199A3502013-07-16016 July 2013 Predecisional Enforcement Conference Presentation Slides July 16, 2013 ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML1203401902012-01-30030 January 2012 (Non- Proprietary) Licensee Slides from 1/30/12 Meeting with Entergy Operations, Inc ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1109600692011-04-0505 April 2011 Licensee Slides from 4/5/11 Pre-Submittal Meeting with Entergy Operations, Inc. Regarding Changes to TSs and QA Program Manual for Unit Staff Qualifications ML1003603572010-02-18018 February 2010 Steam Dryer 2/18/10 NRC Presentation, Redacted Version ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0932102002009-11-12012 November 2009 Licensee Slides, Extended Power Uprate - Impact on Steam Dryer ML0921003112009-07-29029 July 2009 Presentation Slides, SFST June 2009 Monthly Seminar - Operational Experience. ML0909100632009-03-31031 March 2009 Entergy Operations, Inc., Project Planning Slides for March 31, 2009, Nrc/Entergy Pre-Application Meeting - Power Uprates 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 ML0634500682006-12-0505 December 2006 12/5/06 Public Meeting Handout from Entergy/Epri Re GGNS Application of N-716 ML0613103512006-05-11011 May 2006 Summary of Meeting with Entergy Operations, Inc., Annual Performance Assessment for Grand Gulf Nuclear Station ML0510203182005-05-0404 May 2005 Licensee'S Slides for 04/11/2005 Summary of Category 1 Meeting with Entergy Corporation, to Discuss an Alternate Compliance Strategy for Meeting Fire Wrap Requirements in Certain Plant Areas ML0418202762004-06-30030 June 2004 Summary of Meeting with Entergy Operations, Inc Re Initial Examination and Requalification Program Improvements ML0324717142003-09-0202 September 2003 Meeting with Entergy Nuclear Potomac Plans for NRC to Conduct Inspections of Quality Assurance Measures in Support of Prospective ESP Application for Grand Gulf Site ML0323705292003-08-22022 August 2003 Summary of Nrc/Entergy Operations, Inc. Management Meeting ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary 2024-09-10
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML22301A1412022-10-27027 October 2022 Overview of 10 CFR Part 21- Tim Steadham SRI Region IV ML22164A8012022-06-13013 June 2022 Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides ML21319A2452021-11-15015 November 2021 Natrium Energy Island Decoupling Strategy - 11-17-2021 ML21306A3162021-11-0909 November 2021 Digital IC Presentation 11/09/2021 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21280A0282021-10-0404 October 2021 GG - NRC Slides for the October 4, 2021 Regulatory Performance Meeting and 95002 Supplemental Inspection Exit Meeting ML21280A0322021-10-0404 October 2021 GG - Entergy Presentation Slides for the October 4, 2021 Regulatory Performance Meeting and 95002 Supplemental Inspection Exit Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor ML21126A3032021-05-10010 May 2021 Entergy Operations, Inc. Pre-Submittal Meeting - Grand Gulf Nuclear Station, Unit 1 Relief Request to Adopt Performance-based Testing for Pressure Isolation Valves (Pivs) ML21092A1542021-04-0202 April 2021 GG 2020 EOC Public Meeting Summary of Public Meeting with Entergy Operations, Inc ML20357B0612020-12-16016 December 2020 Enc 3 - Entergy Slides for Regulatory Conference December 2020 - Final ML20357B0592020-12-16016 December 2020 Enc 2 - Grand Gulf Nuclear Station Regulatory Conference December 2020 - NRC Presentation ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20176A3452020-06-24024 June 2020 Slides for Public Meeting Confirmatory Success Criteria Using Grand Gulf Nuclear Station ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML17318A1592017-11-0808 November 2017 Meeting Slides - November 8, 2017 Teleconference with NEI Concerning Feedback on Tornado Missile Risk Evaluator Methodology -Final ML17101A4402017-04-11011 April 2017 Summary of Public Meeting with Entergy Operations, Inc. to Discuss Results of the Annual Assessment of Safety Performance at Grand Gulf Nuclear Station for 2016 ML14142A0412014-05-22022 May 2014 NRC Public Meeting Presentation Grand Gulf Flooding Hazard Reevaluation ML13199A3502013-07-16016 July 2013 Predecisional Enforcement Conference Presentation Slides July 16, 2013 ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML12034A0172012-01-31031 January 2012 License Renewal Process and Environmental Scoping Meeting ML1109600692011-04-0505 April 2011 Licensee Slides from 4/5/11 Pre-Submittal Meeting with Entergy Operations, Inc. Regarding Changes to TSs and QA Program Manual for Unit Staff Qualifications ML1003603572010-02-18018 February 2010 Steam Dryer 2/18/10 NRC Presentation, Redacted Version ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0932102002009-11-12012 November 2009 Licensee Slides, Extended Power Uprate - Impact on Steam Dryer ML0921003112009-07-29029 July 2009 Presentation Slides, SFST June 2009 Monthly Seminar - Operational Experience. ML0909100632009-03-31031 March 2009 Entergy Operations, Inc., Project Planning Slides for March 31, 2009, Nrc/Entergy Pre-Application Meeting - Power Uprates ML0634500682006-12-0505 December 2006 12/5/06 Public Meeting Handout from Entergy/Epri Re GGNS Application of N-716 ML0613103512006-05-11011 May 2006 Summary of Meeting with Entergy Operations, Inc., Annual Performance Assessment for Grand Gulf Nuclear Station ML0617802712006-03-0707 March 2006 RIC 2006 Presentation - T2E - Vincent Coulehan - Use of Operating Experience (Regulator/Operator/Licensee) ML0615902322006-03-0707 March 2006 2006/03/07- - RIC 2006 Presentation - T1F - Garry G. Young - License Renewal ML0615901582006-03-0707 March 2006 03/07/2006 - RIC 2006 Presentation - T1E - John F. Mccann - License Renewal ML0607204302006-03-0101 March 2006 March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations. ML0532206852005-11-17017 November 2005 Nrc/Entergy Operations, Inc. Management Meeting 11/10/05 ML0514701102005-05-25025 May 2005 Summary of End of Cycle Public Meeting with Entergy Operations, Inc. on Grand Gulf Nuclear Station Performance for Period of 01/01/2004 - 12/31/2004 ML0510203182005-05-0404 May 2005 Licensee'S Slides for 04/11/2005 Summary of Category 1 Meeting with Entergy Corporation, to Discuss an Alternate Compliance Strategy for Meeting Fire Wrap Requirements in Certain Plant Areas ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0323705292003-08-22022 August 2003 Summary of Nrc/Entergy Operations, Inc. Management Meeting ML0316400872003-04-28028 April 2003 Summary of Annual Performance Assessment Meeting for Grand Gulf Nuclear Station ML0210903352002-04-17017 April 2002 Annual Performance Assessment Meeting for Grand Gulf to Discuss Safety Performance at Grand Gulf Between 04/01/2001 & 12/31/2001 2024-09-10
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Grand Gulf Nuclear Station Radioactive Material Transportation Regulatory Conference December 10, 2020 ML20357B061
Introduction and Agenda Jim Shaw Regulatory Assurance Manager Grand Gulf Nuclear Station 1
Agenda Introduction and Agenda Jim Shaw, Regulatory Assurance Manager Management Overview Bob Franssen, Site Vice President - Grand Gulf Condition Description and Event Details Mark Travis, Radiation Protection Manager Root Cause and Corrective Actions Brad Cole, Senior Manager - Fleet Radiation Protection Safety Significance Jim Shaw, Regulatory Assurance Manager Closing Comments Bob Franssen, Site Vice President - Grand Gulf 2
Management Overview Bob Franssen Vice President Grand Gulf Nuclear Station 3
4 Condition Description and Event Details Mark Travis Radiation Protection Manager Grand Gulf Nuclear Station 5
Condition Description
- On May 22, 2020, a radioactive waste shipment left Grand Gulf Nuclear Station (Grand Gulf) with incorrect radioactive material shipment marking, numbering, and provision of emergency response information. This error caused violations of federal regulations:
10 CFR 71 (Compliance with 49 CFR 172) 49 CFR (Transportation Characterization and Packaging Requirements) 6
Based on the facts that the radioactive waste was shipped in the proper cask, transported correctly and relevant information about the ERGs, Entergys assessment is that this issue has very low safety significance.
7
Cask is Robust Designed to 10 CFR 71.71 and 10 CFR 71.73 requirements for Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC)
Approved by NRC for transport Outer shell - 1.5 thick steel Inner shell - 0.75 thick steel Annular space between the shells is 3.35 and is filled with lead Cask base is (2) 3.25 thick circular steel plates Cask lid is (2) 3.25 thick circular steel plates Top and bottom of the cask have impact limiters Pre-shipment leak testing is performed by a qualified test individual to assure package integrity 8-120 Type B Shipping Package 8
Example of Robust Cast Transportation Configuration 9
Shipment Preparation
- Package Characterization Preparation Resin loaded Waste stream selected Container weighed and surveyed Surveys used for characterization Proper Shipping Name selected
- Shipping Cask Classification Preparation Inspected Container loaded in cask Cask closed and leak tested Cask surveyed Shipping papers created and provided to driver 10
Actual Cask For May 22, 2020 Shipment 11
As shipped Correct marking First Responders and Carrier required to have 12
Page 80 Page 65 13
ERG 162 ERG 163 14
ERG Summary In this case, the Emergency Response Guidance provided by the Hazard Identification Number would have provided the necessary actions to first responders ERG 162 and ERG 163 have no significant differing directions to first responders for this shipment Because of the information from ERG 162, public safety would have been appropriately provided for this shipment 15
Root Cause and Corrective Actions Brad Cole Entergy Fleet Senior Manager Radiation Protection 16
Root Cause Evaluation Root Cause: The Grand Gulf process for preparing and shipping Type A and Type B radioactive material shipments did not include designation for risk significance and consequently the opportunity for Grand Gulf leadership to have the necessary level of added oversight and management of the shipment preparation.
17
Completed Corrective Actions
- Revised Fleet Radiological Risk Procedure, EN-RP-110-04 Radioactive Shipments involving Type B packaging are now considered high risk Provides visibility of work during planning that has a high-risk task Requires Radiation Protection Manager approval of mitigating plan Embeds mitigating strategies, where identified, in work control documents or Radiation Work Permit Requires direct leadership oversight 18
Completed Corrective Actions
- Clarified the Independent Reviewer Responsibilities
- Clarified the role and proficiency requirements to perform the independent verification sign offs during the review of technical information 19
Completed Corrective Actions Procedure Revision Measured data will be used versus calculated data when available Process steps that, if performed incorrectly, could weaken barriers for public safety are required to have an independent verification Revised specific guidance for use of the override function of RADMAN software 20
Safety Significance Jim Shaw Regulatory Assurance Manager Grand Gulf Nuclear Station 21
Safety Significance Apparent Violation Violation of 49 CFR 172 involving Grand Gulf Nuclear Stations failure to ensure that shipment was manifested and marked, and driver was provided with correct emergency response information 22
Safety Significance Assessed under the NRCs Reactor Oversight Process (ROP)
Public Radiation Safety Significance Determination Process (SDP)
- Transportation branch of the logic diagram focuses on the licensees radioactive material packaging and transportation program o Assesses the licensees ability to safely transport radioactive material on public roadways in accordance with regulations o The regulatory basis for the transportation program is contained in 10 CFR Parts 20, 61, and 71, and Department of Transportation regulations contained in 49 CFR Parts 170-189 23
NRC Preliminary Significance Assessment (Based on Grand Gulf NRC Inspection Report 2020-015 / EA 20-094)
Failure to make notifications or No Green provide emergency info The significance of the finding was assessed using IMC 0609, Appendix D, Public Radiation Safety SDP.
The finding was preliminarily determined to be of low to moderate safety significance (WHITE) because it was a finding in the transportation branch in which ... it was a failure to provide emergency response Yes information as required by 49 CFR 172.602.
N2 No N3 No N4 No N1 No Failure to provide Failure to Failure to Failure to emergency respond during make Green comply with 10 CFR 71.97 response info actual request notification Yes Yes Yes Yes White White White White For Block N2, if the licensee fails to provide the required emergency response information to the shipment carrier (the shipment leaves the Licensees facility and control without the required information), the finding is WHITE. If the carrier misplaces or loses the information (beyond the licensees control), the finding is GREEN. 24
Entergys Assessment of Significance IMC 0609, Appendix D, Section VII: Failure to provide these required notifications could seriously hamper or prevent the ability of the federal, state and local agencies to adequately respond as needed to transportation events and accidents. By hampering or preventing this regulatory response, the public health and safety could be negatively impacted.
Entergys Assessment:
Entergy provided sufficient information that would not seriously hamper or prevent an adequate response to a transportation event or accident. The public health and safety was not and would not have been negatively impacted.
Safety Significance is Very Low 25
Enforcement Perspective Possibility of a Release of Radioactivity was Very Low (robust, correct cask used)
Potential Consequences to the Public was Very Low (acceptable emergency response information)
Grand Gulf - May 22, 2020 Radioactive Waste Shipment Public Confidence Maintained For this Shipment 26
Possibility of a Release of Radioactivity was Very Low Package meets requirements of 10 CFR 71.71 and 71.73 Properly tested and packaged as Type B Properly placarded Category II requirements met Radiation limits not exceeded No breach in transit - safely transported No Certificate of Compliance issues 27
Potential Consequences to the Public was Very Low Assessed the significance of the impact to public health and safety (IMC 0609, Appendix D)
Potential impact is very low based on package testing and qualification Qualification encompass potential scenarios that impact public safety Cask is accepted and certified by the NRC The Emergency Response telephone number was provided with the shipment Actual emergency response would likely not have been impacted due to the similarities of the ERGs in this instance 28
Public Confidence Maintained For This Shipment Emergency Response Information in ERG 162 and ERG 163 very similar with no significant differing direction to first responders Possibility of a Release of Radioactivity was Very Low Potential Consequences to the Public was Very Low Shipment arrived safely in correct package with no actual consequences IMC 0609, Appendix D - should be assessed as very low safety significance Entergys view is that the significance of the apparent violations at Grand Gulf should be assessed as one finding of very low safety significance (GREEN) 29
Closing Remarks Bob Franssen Vice President Grand Gulf Nuclear Station 30