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Category:Letter type:GNRO
MONTHYEARGNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019 Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation. GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
[Table view] Category:Report
MONTHYEARML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML22011A2982022-01-11011 January 2022 ANS Evaluation Report CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy ML21075A2752020-12-22022 December 2020 FAQ 20-06 GGNS Scram - Final Approved ML18123A3142018-05-0707 May 2018 Staff Assessment of Flooding Focused Evaluation (CAC No. MF9897; EPID L-2017-JLD-0015) ML18085A5792018-03-26026 March 2018 Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML17290B1372017-10-17017 October 2017 Recommendations for Future Inspection - Replacement Steam Dryer. with GE Hitachi Nuclear Energy Report 0000-0125-6316-R2-NP GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package2017-07-12012 July 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package GNRO-2017/00038, Focused Evaluation of External Flooding2017-06-27027 June 2017 Focused Evaluation of External Flooding GNRO-2016/00053, Mitigating Strategies Assessment (MSA) for Flooding Submittal2016-12-30030 December 2016 Mitigating Strategies Assessment (MSA) for Flooding Submittal GNRO-2016/00046, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 20162016-08-23023 August 2016 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 2016 GNRO-2016/00015, Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/000112016-03-23023 March 2016 Non-Proprietary Version of MP Machinery and Testing, LLC (Mpm) Proprietary Report 814779, Revs 1 & 2, Neutron Transport Analysis for Grand Gulf Nuclear Station, Previously Included in Letters GNRO-2014/0080 and GNRO-2015/00011 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al GNRO-2014/00072, 2014 Report of Changes and Errors to 10CFR50.462014-11-12012 November 2014 2014 Report of Changes and Errors to 10CFR50.46 GNRO-2014/00060, Entergy'S Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-26026 August 2014 Entergy'S Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML14232A7392014-08-20020 August 2014 Report of 10CFR72.48 Evaluations - July 1, 2012 Through June 30, 2014 ML14098A1752014-05-0101 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident GNRO-2014/00027, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi. ML14007A7182014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2972014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Grand Gulf Nuclear Station, Unit 1, TAC No.: MF0954 ML13217A0532013-07-24024 July 2013 Summary of Root Cause Evaluation - Apparent Violation of 10CFR54.13 for Grand Gulf License Renewal GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report2013-03-11011 March 2013 Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report CNRO-2013-00002, Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments2013-01-29029 January 2013 Responses to NRC Request for Additional Information Regarding Application for Order Approving Transfers of Licenses and Conforming License and ESP Amendments GNRO-2012/00150, Final Report for Replacement Steam Dryer2012-12-0606 December 2012 Final Report for Replacement Steam Dryer GNRO-2012/00140, Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from ..2012-11-26026 November 2012 Unit No.1 - Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from .. GNRO-2012/00141, Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 151 of 345 Through Page 251 of 3452012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 151 of 345 Through Page 251 of 345 ML12352A0712012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Cover Through Attachment C, Seismic Walkdown Checklists (Swcs), Page 150 of 345 ML12352A0692012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment D, Area Walk-by Checklist (Awcs), Page 1 of 167 Through End ML12352A0682012-11-15015 November 2012 Attachment 1, Seismic Walkdown Report GGNS-CS-12-00002, Rev. 0, Attachment C, Seismic Walkdown Checklists (Swcs), Page 252 of 345 Through Page 345 of 345 GNRO-2012/00113, Vibration Data Report2012-09-18018 September 2012 Vibration Data Report GNRO-2012/00109, Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation2012-09-0606 September 2012 Stress Analysis Summary Demonstrating That the Nozzle to Safe-End DMW, N06B-KB, Will Perform Its Intended Design Function After Weld Overlay Installation GNRO-2012/00099, Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp2012-08-21021 August 2012 Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp ML12159A5152012-06-11011 June 2012 Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident 2023-09-27
[Table view] Category:Miscellaneous
MONTHYEARML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML22011A2982022-01-11011 January 2022 ANS Evaluation Report CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1392021-03-22022 March 2021 Strategy 1 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy ML21075A2752020-12-22022 December 2020 FAQ 20-06 GGNS Scram - Final Approved ML18123A3142018-05-0707 May 2018 Staff Assessment of Flooding Focused Evaluation (CAC No. MF9897; EPID L-2017-JLD-0015) ML18085A5792018-03-26026 March 2018 Proposed Revision of Replacement of Turbine First Stage Pressure Signals with Power Range Neutron Monitoring System Signals ML17290B1372017-10-17017 October 2017 Recommendations for Future Inspection - Replacement Steam Dryer. with GE Hitachi Nuclear Energy Report 0000-0125-6316-R2-NP GNRO-2017/00042, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package2017-07-12012 July 2017 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package GNRO-2017/00038, Focused Evaluation of External Flooding2017-06-27027 June 2017 Focused Evaluation of External Flooding GNRO-2016/00053, Mitigating Strategies Assessment (MSA) for Flooding Submittal2016-12-30030 December 2016 Mitigating Strategies Assessment (MSA) for Flooding Submittal GNRO-2016/00046, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 20162016-08-23023 August 2016 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations for the Period July 1, 2014 Through June 30, 2016 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al GNRO-2014/00072, 2014 Report of Changes and Errors to 10CFR50.462014-11-12012 November 2014 2014 Report of Changes and Errors to 10CFR50.46 GNRO-2014/00060, Entergy'S Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-26026 August 2014 Entergy'S Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML14232A7392014-08-20020 August 2014 Report of 10CFR72.48 Evaluations - July 1, 2012 Through June 30, 2014 ML14098A1752014-05-0101 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident GNRO-2014/00027, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.2014-03-31031 March 2014 Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi. ML13217A0532013-07-24024 July 2013 Summary of Root Cause Evaluation - Apparent Violation of 10CFR54.13 for Grand Gulf License Renewal GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report2013-03-11011 March 2013 Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report GNRO-2012/00113, Vibration Data Report2012-09-18018 September 2012 Vibration Data Report GNRO-2012/00099, Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp2012-08-21021 August 2012 Requested Information Vibration Data for the Main Steam Line Piping and Safety Relief Valves 4102 Mwt (105% Pltp ML12159A5152012-06-11011 June 2012 Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML12157A1812012-05-23023 May 2012 Attachment 8 to GNRO-2012/00039 - from Diskette Labeled: Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment K Labeled Condition Reports. ML12157A4262012-05-23023 May 2012 Attachment 38 to GNRO-2012/00039 - Ensr. 2007, Impingement Mortality and Entrainment Characterization Study (Imecs), Entergy -Waterford 3. December 2007 ML12157A1832012-05-23023 May 2012 Attachment 10 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment P Labeled Thermal Monitoring Procedural Protocols. ML12157A2462012-05-23023 May 2012 Attachment 22 to GNRO-2012/00039, Er Reference - Entergy 2010e (NPDES Crs) ML12157A2512012-05-23023 May 2012 Attachment 27 to GNRO-2012/00039, Er Reference - GGNS 2007b (2006 Wmp Report) Grand Gulf Nuclear Station 2006 Waste Minimization Certified Report ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages GNRO-2010/00058, Report of 10CFR50.59 Evaluations and Commitment Changes - July 1, 2009 Through June 30, 20102010-08-17017 August 2010 Report of 10CFR50.59 Evaluations and Commitment Changes - July 1, 2009 Through June 30, 2010 GNRO-2009/00036, Report of 10CFR50.59 Evaluations and Commitment Changes - April 1, 2008 Through June 30, 20092009-07-16016 July 2009 Report of 10CFR50.59 Evaluations and Commitment Changes - April 1, 2008 Through June 30, 2009 ML1019004062009-04-30030 April 2009 GPI Data Review, Grand Gulf Nuclear Station GNRO-2008/00052, Special Report 2008-001 - Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System2008-07-17017 July 2008 Special Report 2008-001 - Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System GNRO-2007/00068, Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints2007-09-21021 September 2007 Supplement 2 to Amendment Request Changes to the Condensate Storage Tank Level-Low Setpoints ML0723203352007-05-30030 May 2007 GG-05-2007-FINAL Operating Exam, Operations Training, Determine Shift Staffing to Meet Shift Requirements CNRO-2006-00043, Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-7162006-09-22022 September 2006 Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-716 CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests2006-04-24024 April 2006 Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests ML0607204302006-03-0101 March 2006 March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations. 2023-11-21
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~Entergy Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150 Dave Ellis Acting Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2489 GNRO-2017/00042 July 12, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Report Pursuant to 10 CFR 71.95 (a)(3) and (b) of Seven Potential Instances of Noncompliance with Certificate of Compliance no. 9233 for TN-RAM Package Grand Gulf Nuclear Station - Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCE:
- 1. Areva Letter E-48377 Notification of Registered Users (Licensees) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233
Dear Sir or Madam:
Entergy Operations, Inc. (Entergy) is submitting this report pursuant to Title 10 Code of Federal Regulations 10 CFR 71.95(a)(3) and (b) with respect to Certificate of Compliance (CoC) No. 9233, Revision 14, for the TN-RAM Packaging, Docket No. 71-9233 (Reference 1).
Grand Gulf Nuclear Station (GGNS) is an authorized user of the TN-RAM Packaging under the provisions of 10 CFR 71.17 General License: NRC-approved package.
Only one TN-RAM packaging has been fabricated and in use since 1989, prior to the discovery that the attachment points not intended for package lifting or tie-down were not rendered inoperable for transport operations as required by 10 CFR 71.87(h) and 49 CFR 173.41 (b). The failure to render the impact limiter lifting lugs inoperable was noted during routine operations.
Further review of the design determined that the attachment points intended for lifting the impact limiters will not withstand the static force required for lifting and tie-down in 10 CFR 71.45.
Immediate action was taken to install a cover on each impact limiter lug retained by a bolt installed in the lifting lug through hole, which renders the attachment point inoperable. In addition to installing the cover, a durable marking, stating "IMPACT LIMITER LIFTING ONLY,"
was placed near each impact limiter lifting lug to identify the intended use of the lifting lugs.
The Areva written report, as required by CFR 71.95(c), is provided in Attachment 1.
The seven potential instances of noncompliance with the CoC were identified. Attachment 2 contains the shipment numbers, shipment dates, material shipped and the final destination of each shipment.
GNRO-2017/00042 Page 2 of 3 This letter contains no new Regulatory Commitments.
Should you have any questions concerning the content of this letter, please contact Dave Ellis at 601-437-2489.
Sincerely, DRE/sas : Areva Written Report Pursuant to 10 CFR 71.95(c) : Grand Gulf Generating Station Potential Instances of Certificate of Noncompliance cc: see next page
GNRO-2017/00042 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Siva Lingham Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss M. Kennedy Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
Attachment 1 to GNRO-2017/00042 Areva Written Report Pursuant to 10 CFR 71.95(c)
April 19, 2017 E-48377 To: Registered Users for CoC Number 9233, Revision 14
Subject:
Notification to Registered Users (Licensees) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233 As the certificate holder of Certificate of Compliance (CoC) No. 9233 for the TN-RAM Packaging, TN Americas LLC wishes to inform you of the discovery of a situation involving a failure to follow conditions in the TN-RAM Packaging CoCo It has been determined that this situation is reportable under 10 CFR 71.95 if you used the TN-RAM from the time of first use in 1989 until now.
A sample cover letter and a written report are provided for licensees to report the use of the package without rendering the impact limiter lifting attachment points inoperable. The written report contains the narrative description of the event as required by 10 CFR 71.95(c).
A cover has been installed on each of the impact limiter lifting lugs that renders these attachment points inoperable during transport operations. The covers may be removed for lifting the impact limiter only, and users should install these covers after installing the impact limiters on the TN-RAM.
Additionally, a durable marking, stating IIIMPACT LIMITER LIFTING ONLY," was placed near each irnpactlimlter lifting lug to identify the intended use of the lifting lugs.
Should 'You require additional information regarding this situation, please do not hesitate to contact Glenn Mathues of my staff at 410-910-6538 or me at (410)-910-6878.
Sincerely, Don Shaw Licensing Manager cc: John Vera (NRC PM for the TN-RAM, SFM Licensing Branch)
Glenn Mathues (TN Americas LLC)
Peter Vescovi (TN Americas LLC)
Jay Thomas (TN Americas LLC)
Enclosures:
- 1. Sample Cover Letter
- 2. Written Report per 10 CFR 71.95(c)
TN AMERICAS LLC 7135 Mlnstral Way, Suite 300. Columbia, Maryland 21045 Tel.: 410 910 6900* Fax: 4109106902* www.us,areva,comITNAmericas to TN E-48377 Sam pie Cover Letter
Month Day, Year
[Licensee reference]
U.S. Nuclear RegUlatory Commission Attn: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards One White Flint North 11555 Rockville Pike Rockville, MD 20852
Subject:
Report Pursuant to 10 CFR 71.95 (a)(3) and (b) - Failure to Follow Conditions of TN-RAM Packaging Certificate of Compliance No. 9233
Reference:
Certificate of Compliance No. 9233 for the TN-RAM Packaging, Revision 11
[Licensee] is submitting this report pursuant to 10 CFR 71.95 (a)(3) and (b) with respect to Certificate of Compliance (CoC) No. 9233, Revision 14, for the TN-RAM Packaging, Docket No. 71-9233.
[Licensee] is an authorized user of the TN-RAM packaging under the provisions of 10 CFR § 71.17 General license: NRC-approved package.
Only one TN-RAM packaging has been fabricated and in use since 1989, prior to the discovery that the attachment points not intended for package lifting or tie-down were not rendered inoperable for transport operations as required by 10 CFR 71.87(h) and 49 CFR 173.41(b). The failure to render the impact limiter lifting *Iugs inoperable was noted during routine operations. Further review of the design determined that the attachment points intended for lifting the impact limiters will not withstand the static force required for lifting and tie-down in 10 CFR 71.45.
Immediate action was taken to install a cover on each impact limiter lifting lug retained by a bolt installed in the lifting lug through hole, which renders the attachment point inoperable. In addition to installing the cover, a durable marking, stating "IMPACT LIMITER LIFTING ONLV/' was placed near each impact limiter lifting lug to identify the intended use of the lifting lugs.
A written report, as required by CFR 71.95(c), is provided as Enclosure 1. Should the NRC staff require additional information regarding this report, please do not hesitate to contact [Licensee designee] at [licensee phone number].
Sincerely,
[Licensee designee]
[Licensee designee title]
cc: XXX)( (NRC)
XXX)( (NRC)
John Vera (NRC PM for the TN-RAM, SFM Licensing Branch)
[Licensee distribution]
Enclosures:
Month Day, Year
[Licensee reference]
Page 2 of2
- 1. [Licensee Evaluation Written Report]
to TN E-48377 rl en Report per 10 CFR 71.95(c)
10 CFR 71.95 Written Report (1) Abstract The TN-RAM package has trunnions intended as attachment points for lifting and tie-down. The trunnions are a structural part of the package that is designed to meet the requirements of the regulatio~ for lifting and tie-down. Attachment points for lifting the impact limiters during installation and removal are a structural part of the impact limiters that are part of the TN-RAM package. An evaluation of the TN-RAM lifting attachment points demonstrates that the trunnions and impact limiter lifting lugs have been designed only for their intended use. Inadvertent use of the impact limiter lifting lugs to lift or tie-down the TN-RAM would impair the ability of the package to meet requirements for transport. However, operation of the TN-RAM has not included any controls to render the impact limiter lifting lugs inoperable during transport operations as required by transport regulations. An evaluation of the lifting and tie-down operations has been done to determine the extent of the condition and appropriate corrective actions to render the impact limiter lugs inoperable. A review of the NRC 10 CFR Part 71.78(h) regulatory requirements for Operating Controls and Procedures determined that use of the cask without rendering the impact limiter lugs inoperable is a practice that did not follow the conditions of the certificate of compliance.
(2) Description of the event (i) Status of components or systems that were inoperable at the start of the event and that contributed to the event The TN RAM cask system is a Type B transportation package design approved by the NRC (71-9233). The package is a steel encased lead shielded cask with wood impact limiters attached at both ends. The impact limiters are a packaging component that is required by the NRC approval of the package design. Impact limiters protect the cask shell and contents by absorbing shocks from impacts incidental to normal and accident transportation conditions. The cask shell is a right circular cylinder with trunnions welded to the outer shell for lifting and tie-down. The overall dimensions of the packaging are approximately 178 inches long and 92 inches diameter with the impact limiters installed.
The cask body is approximately 129 inches long with an outer diameter of 51 inches. The maximum gross weight of the package is approximately 80,000 Ibs. The structural evaluation for tie-down and lifting devices in the TN-RAM SAR states that there are no other structural parts of the package which can be used for tie down attachments.
(ii) Dates and approximate times of occurrences The TN-RAM package first use was on or about 1989. The lifting lugs were not rendered inoperable during the period of operation since first use.
(iii) The cause of each component or system failure or personnel error The TN-RAM SAR contains loading and handling guidelines that include general instructions for removal of the impact limiters using a "suitable crane and two legged sling", rotating and lifting the cask using a "suitable crane hook" to "engage the lift beam to the two front trunnions", and removal and installation of "front and rear trunnion tie-downs." The Operations and Maintenance Manual for the TN-RAM (OM-7) expands on the handling guideline and describes the trunnions intended purpose for lifting and tie-down of the cask.
OM-7 also describes the impact limiter lifting lugs as "located such that the limiter is 1
10 CFR 71.95 Written Report balanced when it is lifted." The glossary of terms in OM-7 defines lifting lugs as "attachments provided on the impact limiters for handling operations," lift beams as "devices for cask lifting and handling operations," and trunnions as "handling attachments provided for cask primary lifting, support and tie-down." These definitions describe the intended purpose of attachment points. The design of the impact limiter rigging equipment is sized for attachment to the lifting lugs, and lift beams are specialized lifting devices that are designed for attachment to the trunnions. A dynamometer is installed between the crane hook and sling that is attached to the lifting lugs. The dynamometer is used to support the weight to allow removal of impact limiter bolts, and the procedure requires "lift up on the sling until a reading of 3700, +0, -100 pounds is indicated on the dynamometer." Any attempt to lift the weight of the TN-RAM package would exceed 3700 pound reading on the dynamometer. TIe-down members for the TN-RAM are trailer support pedestals specially designed for attachment to the trunnions.
The tarp installed over the support frame during transport has been considered a control to render the impact limiter lugs inoperable. The tarp when installed blocks access to the impact limiter lugs, but the lifting lugs are accessible when the tarp and support frame are removed for handling operations. Transport operations include the preparation of the package for transport (installing impact limiters), securing the package to the trailer for transit (tie-down), and receiving the package (removing impact limiters). During preparation for transport and receipt of the TN-RAM, the impact limiters are installed without the tarp in place. Prior to removal of the impact limiters and after installation the lift lugs are accessible.
Rigging equipment or tie-down members could inadvertently be attached to the lift lugs.
However, lifting or tie-down of the TN-RAM using the lifting lugs would require intentional misuse of the rigging equipment and tie-down members, and violate operational controls and procedures for handling the cask. A method for rendering the lift lugs inoperable is required to prevent attachment to these points during preparation and receipt phases of transport operations. The tarp does not meet the intent of the requirement in the regulation to render the attachment point inoperable during all phases of transport operations.
(iv) The failure mode, mechanism, and effect of each failed component The impact limiter attachment points are intended only for lifting the impact limiter during removal and installation while the TN-RAM package is attached to the transportation trailer. Each impact limiter weighs approxirnatelv 3700 Ibs. The impact limiter shell is a structural part of the packaging that retains the wood shock absorber. The shell is sealed to protect the wood material from environmental conditlons incident to routine use.
The impact limiter lifting lugs are designed for a safety factor against yield that is consistent with accepted industry standards for material handling using standard rigging equipment.
2
10 CFR 71.95 Written Report The nominal design weight of the impact limiter is 3695 Ibs. The most likely failure mechanism or "weak link" in the attachment point on the impact limiter would be a tensile breakage of the lifting lug. Attempting to lift the package using the impact limiter lifting lugs would not result in damage to the structural impact limiter shell that would impair the ability to meet transport requirements.
The lifting lugs were not intended to tie-down of the TN-RAM during for transport. The stress applied to the lifting lugs used at attachment points for tie-down would be different than for the intended use to lift the impact limiters. A review of the impact limiter lifting design basis indicates that the lifting lugs would not withstand the stress applied by static forces required for tie-down in 71.45(a) or static force required by DOTfor Protection Against Shifting and Falling Cargo (49 CFR 393).
(v) A list of systems or secondary functions that were also affected for failures of components with multiple functions lifting lugs are designed for the single purpose of lifting the impact limiter.
(vi) The method of discovery of each component or system failure or procedural error Failure to render the impact limiter lugs inoperable was noted during routine operation of the TN-RAM.
(vii) For each human performance-related root cause, a discussion of the cause(s) and circumstances Approved operational procedures and controls in place were followed since first use of the cask. There is no known instance of lifting or tie-down of the TN-RAM using the lifting lugs during nearly 30 years operating experience.
(viii) The manufacturer and model number (or other identification) of each component that failed during the event No failure of the impact limiter lifting lugs occurred on the TN-RAM No. 001.
(ix) For events occurring during use of a packaging, the quantities and chemical and physical formes) of the package contents Quantities of radioactive material in form of activated metals shipped during use of the package varied during use. During this period of use the package contents was limited to about 14/000 Ci Co-60 equivalent activity that was recently increased in 2015 to a allow up to 30/000 Ci Co-60 equivalent activity.
(3) Safety Significance The lifting lugs when used as intended have been evaluated to meet industry standards for rigging and material handling. Attempting to lift the TN--RAM using the lifting lugs would result in a yielding and tensile failure of the lifting lug. The structural shell of the impact limiter would not likely be damaged due to attempting to lift the package using the lifting lugs. Stressesgenerated in the impact limiter shell when used as a tie-down attachment point for securement of load during 3
10 CFR 71.95 Written Report transport have not been analyzed. Using the impact limiter lifting lugs as tie-down attachment points could generate stresses in the impact limiter shell that could result in tears or cracks.
Undetected during the normal use or periodic inspections, these defects would allow moisture ingress and eventual degradation of the wood impact absorbing material that would impair the performance of the package during normal and accident transport conditions.
(4) Corrective Actions Both engineering and administrative controls have been implemented to prevent inadvertent use of the impact limiter lugs for lifting or tie-down of the package. The engineering control is a cover for each impact limiter lifting lug that is retained by a bolt installed in the lifting lug through hole to render the attachment point inoperable. The lifting lug covers prevent attachment of rigging equipment or tie down members to the impact limiters lift lugs during transport (Figure 1).
Figure 1- Lifting Lug Cover An administrative control identifies the intended use of the impact limiter lifting lugs by a durable marking near each impact limiter lifting lug stating "IMPACT LIMITER LIFTING ONLY" (Figure 2).
Additionally a statement should be added in the SAR Chapter 7- Operations and Operations and Maintenance Manual, OM-07 "TN RAM Operations Manual" subsection 8.5 that would require rendering the impact limiter lifting lugs inoperable and stating the allowed attachment points for lifting and tie-down of the TN-RAM. The SAR Chapter 7 is a condition of the § 71.17, General license: NRC-approved package, and OM-7 is provided to the cask users as a guide with more detailed instructions on implementing the operations requirements in the SAR.
4
10 CFR 71.95 Written Report Neither TN-RAM SAR Ch. 7-0perations or previous versions of Operations and Maintenance manual OM-7 include a requirement to render inoperable attachment points that are structural part of the package and not designed for intended package lifting or tie-down. The most recent version of OM-7 however, did add a requirement to render the lifting lugs inoperable by installing a bolt through the lug, or other similar method.
Figure 2 - lifting Lug Marking (5) Extent of the Condition Operating procedures and design of the lift beam that are intended for lifting the cask and the lifting lugs make it improbable that the lift beam would be attached to the lifting lugs.
Furthermore, the trailer trunnion pedestals are tie-down members specifically designed for attachment to the trunnions making it improbable that generic tie-down members attached to the lifting lugs would be used to secure the TN-RAM to the trailer.
The design and operation of the TN-RAM limits the possibility of inadvertent use of the impact limiter lifting lugs as package lifting or tie-down attachment points. All lifting and tie-down operations are controlled by detailed operating procedures and performed by trained and qualified personnel. The TN-RAM cask shell is lifted without the impact limiters installed. Impact limiters are removed from the cask shell prior to lifting operations to remove the cask shell from the trailer, and likewise the impact limiters are installed after lifting operations to place cask shell on the trailer is complete. Handling is done exclusively by persons trained in operation of the TN-RAM at the loading facility and unloading facilities, and transport is by exclusive use on a specialized trailer.
(6) Contact information
[The name and telephone number of a person within the licensee's organization who is knowledgeable about the event and can provide additional information]
5
10 CFR 71.95 Written Report (7) Extent of exposure of individuals to radiation or to radioactive materials No individuals were exposed to radiation or to radioactive materials as a consequence of not rendering the impact limiter lifting lugs inoperable during transport operations.
6
Attachment 2 to GNRO-2017/00042 Grand Gulf Generating Station Potential Instances of Certificate of Noncompliance to GNRO-2017/00042 Page 1 of 1 Grand Gulf Nuclear Station Generating Station Potential Instances of Certificate of Noncompliance Shipment Number Shipment Date Material Shipped 98-0401 04/14/1998 8 Control Rod Blades (CRBs) and 193 Fission Chambers 99-1001 10/27/1999 8CRBs 2003-0605 07/01/2003 11 CRBs and 10 Velocity Limiters (VLs) 2003-0804 08/15/2003 11 CRBs and 6 VLs 2003-0805 08/28/2003 12 CRBs 2003-0905 09/22/2003 12 CRBs 2003-1101 10/06/2003 12 CRBs and 11 VLs The final shipping destination for the above shipments was Chem Nuclear in Barnwell, South Carolina