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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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Text
GNRO-201 2/00 113 September 1 8 , 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Vibration Data Report Grand Gulf Nuclear Station, Unit 1 Docket No. 50
-416 License No.
NPF-29
REFERENCE:
Entergy Operations, Inc. letter to the NRC (GNRO
-2012/00079), Summary Report of Replacement Steam Dryer Data
- Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession #ML12221A198)
Dear Sir or Madam:
In the referenced letter , Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program.
The vibrati on data collected at or near the current licensed thermal power of 4408 MWt (1 13% of 3898 MWt, the previous licensed thermal power
) is provided in the attachment to this letter.
If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756. This letter contains no new regulatory commitments
. Sincerely, BSF/ghd Attachment
- Vibration Data for the Main Steam Line Piping and Safety Relief Valves
- 4 408 MW t Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368
-5516 GNRO- 2012/00113 Page 2 of 2 cc: Mr. Elmo E. Collins, Jr.
Regional Administrator, Region I V U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011
-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. A. B. Wang, NRR/DORL (w/2)
ATTN: ADDRESSEE ONLY ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852
-2378 State Health Officer Mississippi Department of Health P. O. Box 1700 Jackson, MS 39215
-1700 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150
ATTACHMENT GRAND GULF NUCLEAR STATION GNRO-2012/00 113 VIBRATION DATA FOR T HE MAIN STEAM LINE PIPING AND SAFETY RELIEF VALVES - 4 408 MW t Attachment t o GNRO-2012/00113 Page 1 of 8 VIBRATION DATA FOR T HE MAIN STEAM LINE PIPI NG AND SAFETY RELIEF VALVES - 4 408 MW t In a letter to the NRC staff 1, Entergy Operations, Inc. (Entergy) committed to provide vibration data along with acceptance limits for the main steam line (MSL) piping and the MSL safety relief valves (SRVs) for Grand Gulf Nuclear Station based on data collected at various power plateaus during the Extended Power Uprate (EPU) power ascension testing program. The vibration data collected at or near the current licensed thermal power of 4408 MWt (113% of 3898 MWt, the previous licensed thermal power) is provided in Sections I and II, below.
Node 1008 o n MSL-A has reported data that contained intermittent high
-amplitude spikes. These types of spikes were not seen in the corresponding data for the other valves at the same valve location (top) nor were they seen in the data at any of the nodes. For these reasons, the data at this location were deemed unusable.
Node 3010 o n MSL-C has also reported data that indicates a failure in the mounting system. Two sets of data were retrieved at the 105% power plateau
- one was taken directly after the plateau was reached and a subsequent set was taken before the ascension to the 107
.5% plateau. While the plant data indicated a small increase in main steam flow, there was a markedly higher increase in the X (longitudinal), Y (vertical), and Z (lateral) acceleration s at Node 3010 on M SL-C. This magnitude increase for Node 3010 is in excess of 2 standard deviations above the response noted for the other 15 SRVs. PSD comparisons were made to the MSL response at SRV monitoring points on two valves at Nodes 1008 and 3010 on MSL-C. The PSD comparison for X, Y, and Z response s shows a large change in frequency response through much of the 1
- 250-Hz range at Node 3010 and only a small change in magnitude at the Node 1008 location. The three accelerometers at Node 3010 are mounted on the same block and strapped to the valve actuator.
It is expected that the mounting straps have loosened and the sensor has shifted.
The measured response is most likely being affected by the response of the accelerometer mounting system; therefore, this measured response is unusable.
I. Main Steam Line (MSL) Piping Vibration Data and Acceptance Limits Table 1, below, contains the results from the MSL piping vibration testing performed as part of the GGNS Extended Power Uprate (E PU) Power Ascension Test Plan (PAT P) at ~4 408 MWt. The measured accelerations were taken in the major axes for each of the nodes. A band pass filter (RMS) for the test data was applied based on:
Lower Limit
- Capturing frequencies below the lowest piping frequency which corresponds to the highest piping stresses.
Generally , this number is higher than 1 Hz, which typically contains voltage drift and DC signals that need to be removed.
1 Entergy Operations, Inc. letter to the NRC (GNRO
-2012/00079), Summary Report of Replacement Steam Dryer Data
- Responses to Requests for Additional Information, August 7, 2012 (ADAMS Accession #ML12221A198)
Attachment t o GNRO-2012/00113 Page 2 of 8 Upper Limit
- The upper limit frequency should be sufficiently high so there is no significant modal participation on the maximum piping stresses.
Also , the intent is to remove the high frequency noise, generally above 100 Hz.
The acceptance criteria are based on applying a constant 1
-g acceleration spectrum to the piping model and determining the maximum stress.
The maximum stress was compared with the OM criteria alternating stress allowable per ASME OM
-S/G-1997, Standards and Guides for Operation and Maintenance of Nuclear Power Plants. The resulting ratio was used to modify the output accelerations at the location for each of the test points.
Table 1 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
NOTES Piping associated with B21-F041A (Top of Valve)
MSL-A, Node 1008 X 1X N/A 0.720 / 1.440 N/A Non-Operable Sensor Piping associated with B21-F041A (Top of Valve)
MSL-A, Node 1008 Y 1Y N/A 0.160 / 0.320 N/A Non-Operable Sensor Piping associated with B21-F041A (Top of Valve)
MSL-A, Node 1008 Z 1Z N/A 0.671 / 1.341 N/A Non-Operable Sensor Piping associated with B21-F041A (Actuator)
MSL-A, Node 1010 X 2X 0.363 0.447 / 0.893 18.8 / 59.4 Acceptable Piping associated with B21-F041A (Actuator)
MSL-A, Node 1010 Y 2Y 0.157 0.231 / 0.461 32.0 / 65.9 Acceptable Piping associated with B21-F041A (Actuator)
MSL-A, Node 1010 Z 2Z 0.212 0.434 / 0.868 51.2 / 75.6 Acceptable Piping associated with B21-F051A (Actuator)
MSL-A, Node 2010 X 3X 0.200 0.349 / 0.697 42.7 / 71.3 Acceptable Piping associated with B21-F051A (Actuator)
MSL-A, Node 2010 Y 3Y 0.193 0.224 / 0.447 13.8 / 56.8 Acceptable
Attachment t o GNRO-2012/00113 Page 3 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
NOTES Piping associated with B21-F051A (Actuator)
MSL-A, Node 2010 Z 3Z 0.248 0.389 / 0.778 36.2 / 68.1 Acceptable Piping associated with B21-F047A (Actuator)
MSL-A, Node 4010 X 4X 0.171 0.420 / 0.8 40 59.3 / 79.6 Acceptable Piping associated with B21-F047A (Actuator)
MSL-A, Node 4010 Y 4Y 0.031 0.310 / 0.619 90.0 / 95.0 Acceptable Piping associated with B21-F047A (Actuator)
MSL-A ,Node 4010 Z 4Z 0.217 0.474 / 0.948 54.2 / 77.1 Acceptable Piping associated with B21-F051B (Top of Valve)
MSL-B, Node 1008 X 5X 0.004 0.701 / 1.402 99.4 / 99.7 Acceptable Piping associated with B21-F051B (Top of Valve)
MSL-B, Node 1008 Y 5Y 0.098 0.185 / 0.370 47.0 / 73.5 Acceptable Piping associated with B21-F051B (Top of Valve) MSL-B, Node 1008 Z 5Z 0.706 0.756 / 1.512 6.6 / 53.3 Acceptable Piping associated with B21-F051F (Actuator)
MSL-B, Node 3010 X 6X 0.040 0.389 / 0.778 89.7 / 94.9 Acceptable Piping associated with B21-F051F (Actuator)
MSL-B, Node 3010 Y 6Y 0.09 3 0.212 / 0.424 56.1 / 78.1 Acceptable Piping associated with B21-F051F (Actuator)
MSL-B, Node 3010 Z 6Z 0.166 0.436 / 0.872 61.9 / 81.0 Acceptable Piping associated with B21-F041F (Top of Valve)
MSL-B, Node 4008 X 7X 0.254 0.645 / 1.290 60.6 / 80.3 Acceptable Attachment t o GNRO-2012/00113 Page 4 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
NOTES Piping associated with B21-F041F (Top of Valve)
MSL-B, Node 4008 Y 7Y 0.120 0.181 / 0.362 33.7 / 66.9 Acceptable Piping associated with B21-F041F (Top of Valve)
MSL-B, Node 4008 Z 7Z 0.572 0.800 / 1.600 28.5 / 64.3 Acceptable Piping associated wi th B21-F041K (Top of Valve)
MSL-B, Node 6008 X 8X 0.176 0.663 / 1.326 73.5 / 86.7 Acceptable Piping associated with B21-F041K (Top of Valve)
MSL-B, Node 6008 Y 8Y 0.155 0.229 / 0.457 32.3 / 66.1 Acceptable Piping associated with B21-F041K (Top of Valve)
MSL-B, Node 6008 Z 8Z 0.505 0.677 / 1.353 25.4 / 62.7 Acceptable Piping associated with B21-F041C (Top of Valve)
MSL-C, Node 1008 X 9X 0.218 0.701 / 1.402 68.9 / 84.5 Acceptable Piping associated with B21-F041C (Top of Valve)
MSL-C, Node 1008 Y 9Y 0.127 0.185 / 0.370 31.4 / 65.7 Acceptable Piping associated with B21-F041C (Top of Valve)
MSL-C, Node 1008 Z 9Z 0.156 0.756 / 1.512 79.4 / 89.7 Acceptable Piping associated with B21-F051C (Actuator)
MSL-C, Node 3010 X 10AX N/A 0.389 / 0.778 N/A Non-Operable Sensor Piping associated with B21-F051C (Actuator)
MSL-C, Node 3010 Y 10AY N/A 0.212 / 0.424 N/A Non-Operable Sensor Piping associated with B21-F051C (Actuator)
MSL-C, Node 3010 Z 10AZ N/A 0.436 / 0.872 N/A Non-Operable Sensor Attachment t o GNRO-2012/00113 Page 5 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
NOTES Piping associated with B21-F047G (Top of Valve)
MSL-C, Node 4008 X 10BX 0.565 0.645 / 1.290 12.4 / 56.2 Acceptable Piping associated with B21-F047G (Top of Valve)
MSL-C, Node 4008 Y 10BY 0.046 0.181 / 0.362 74.6 / 87.3 Acceptable Piping associated with B21-F047G (Top of Valve)
MSL-C, Node 4008 Z 10BZ 0.724 0.800 / 1.600 9.5 / 54.8 Acceptable Piping associated with B21-F047L (Top of Valve)
MSL-C, Node 6008 X 10CX 0.540 0.663 / 1.326 18.6 / 59.3 Acceptable Piping associated with B21-F047L (Top of Valve)
MSL-C, Node 6008 Y 10CY 0.22 1 0.229 / 0.457 3.5 / 51.6 Acceptable Piping associated with B21-F047L (Top of Valve)
MSL-C, Node 6008 Z 10CZ 0.408 0.677 / 1.353 39.7 / 69.8 Acceptable Piping associated with B21-F047D (Top of Valve)
MSL-D, Node 1008 X 10DX 0.304 0.720 / 1.440 57.8 / 78.9 Acceptable Piping associated with B21-F047D (Top of Valve)
MSL-D, Node 1008 Y 10DY 0.143 0.160 / 0.320 10.6 / 55.3 Acceptable Piping associated with B21-F047D (Top of Valve)
MSL-D, Node 1008 Z 10DZ 0.349 0.671 / 1.341 48.0 / 74.0 Acceptable Piping associated with B21-F047D (Actuator)
MSL-D, Node 1010 X 10EX 0.432 0.447 / 0.893 3.4 / 51.6 Acceptable Piping associated with B21-F047D (Actuator)
MSL-D, Node 1010 Y 10EY 0.176 0.231 / 0.461 23.8 / 61.8 Acceptable
Attachment t o GNRO-2012/00113 Page 6 of 8 PIPING DESCRIPTION/ SEGMENT MONITOR LOC./DIR. POINT NUM. MEASURED ACCEL (g) ACCEL. LIMIT LEVEL 2 / LEVEL 1 (g)
ACCEL. LEVEL 2 / LEVEL 1 MARGIN (%)
NOTES Piping associated with B21-F047D (Actuator) MSL-D, Node 1010 Z 10EZ 0.132 0.434 / 0.868 69.6 / 84.8 Acceptable Piping associated with B21-F014D (Actuator)
MSL-D, Node 2010 X 10FX 0.297 0.349 / 0.697 14.9 / 57.4 Acceptable Piping associated with B21-F014D (Actuator)
MSL-D, Node 2010 Y 10FY 0.186 0.224 / 0.447 17.0 / 58.4 Acceptable Piping associated with B21-F014D (Actuator)
MSL-D, Node 2010 Z 10FZ 0.255 0.389 / 0.778 34.4 / 67.2 Acceptable Piping associated with B21-F051D (Actuator)
MSL-D, Node 4010 X 10GX 0.247 0.420 / 0.840 41.2 / 70.6 Acceptable Piping associated with B21-F051D (Actuator)
MSL-D, Node 4010 Y 10GY 0.142 0.310 / 0.619 54.2 / 77.1 Acceptable Piping associated with B21-F051D (Actuator)
MSL-D, Node 4010 Z 10GZ 0.450 0.474 / 0.948 5.1 / 52.5 Acceptable Piping associated with Pipe Support N11G001H14 Turbine Bldg.
MSL-D, Node 412 X 15X 0.092 0.213 / 0.426 56.8 / 78.4 Acceptable II. Main Steam Safety Relief Valve (SRV) Vibration Data and Acceptance Limits Table 2, below, contains the results from the SRV vibration testing performed as part of the GGNS EPU PAT P at ~4 408 MWt. The measured acceleration (ACC. ACTUAL) represents the peak acceleration reported by the tri-axial accelerometer in that particular direction for the individual node. This peak was gathered from the time
-history data after band
-pass filtering (2
- 250 Hz) and DC
-offset removal.
Attachment t o GNRO-2012/00113 Page 7 of 8 The methodology for developing the acceleration limits (ACC. LIMIT) below was through analytical methods involving ASME NB
-3500 calculations as well as structural sub
-models of individual components. For both the top
-of-valve and actuator locations, the horizontal limits (X and Z) seen below are a resultant limit calculated through the square root sum of the squares (SRSS) method. The vertical limit (Y) is an individual limit that is not used to calculate any resultant limits.
Table 2 COMP./PIPING DESCRIPTION / SEGMENT MONITOR. LOC./DIR. PT. NUM. MEASURED ACC EL (g) ACC EL LIMIT (g) MARGIN (%) NOTES B21-F041A X 1 N/A N/A Non-Op Sensor Top of Valve Y N/A Non-Op Sensor MSL-A, Node 1008 Z Non-Op Sensor B21-F041A X 2 1.20 3.78 68.28 Actuator Y 1.09 3.77 71.04 Acceptable MSL-A, Node 1010 Z 1.20 3.78 68.28 B21-F051A X 3 1.19 3.78 68.47 Actuator Y 1.11 3.77 70.49 Acceptable MSL-A, Node 2010 Z 1.19 3.78 68.47 B21-F047A X 4 0.70 3.78 81.58 Actuator Y 0.01 3.77 99.76 Acceptable MSL-A, Node 4010 Z 0.70 3.78 81.58 B21-F051B X 5 1.32 6.62 80.05 Top of Valve Y 2.08 3.42 39.27 Acceptable MSL-B, Node 1008 Z 1.32 6.62 80.05 B21-F051F X 6 1.57 3.78 58.50 Actuator Y 1.20 3.77 68.15 Acceptable MSL-B, Node 3010 Z 1.57 3.78 58.50 B21-F041F X 7 5.01 6.62 24.29 Top of Valve Y 0.12 3.42 96.57 Acceptable MSL-B, Node 4008 Z 5.01 6.62 24.29 B21-F041K X 8 1.40 6.62 78.80 Top of Valve Y 0.72 3.42 79.02 Acceptable MSL-B, Node 6008 Z 1.40 6.62 78.80 B21-F041C X 9 3.50 6.62 47.18 Top of Valve Y 3.27 3.42 4.31 Acceptable MSL-C, Node 1008 Z 3.50 6.62 47.18 B21-F051C X 10a N/A N/A Non-Op Sensor Actuator Y N/A Non-Op Sensor MS L-C, Node 3010 Z Non-Op Sensor B21-F047G X 10b 2.93 6.62 55.71 Top of Valve Y 0.08 3.42 97.81 Acceptable MSL-C, Node 4008 Z 2.93 6.62 55.71 Attachment t o GNRO-2012/00113 Page 8 of 8 COMP./PIPING DESCRIPTION / SEGMENT MONITOR. LOC./DIR. PT. NUM. MEASURED ACC EL (g) ACC EL LIMIT (g) MARGIN (%) NOTES B21-F047L X 10c 1.50 6.62 77.40 Top of Valve Y 0.85 3.42 75.23 Acceptable MSL-C, Node 6008 Z 1.50 6.62 77.40 B21-F047D X 10d 1.43 6.62 78.35 Top of Valve Y 0.76 3.42 77.69 Acceptable MSL-D, Node 1008 Z 1.43 6.62 78.35 B21-F047D X 10e 2.66 3.78 29.63 Actuator Y 1.07 3.77 71.63 Acceptable MSL-D, Node 1010 Z 2.66 3.78 29.63 B21-F041D X 10f 1.33 3.78 64.79 Actuator Y 0.85 3.77 77.57 Acceptable MSL-D, Node 2010 Z 1.33 3.78 64.79 B21-F051D X 10g 1.46 3.78 61.23 Actuator Y 0.59 3.77 84.31 Acceptable MSL-D, Node 4010 Z 1.46 3.78 61.23