|
---|
Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24016A1902024-01-30030 January 2024 International, Inc. - Notice of Violation; the U.S. Nuclear Regulatory Commission Inspection Report 07201014/2022201 IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 ML24018A1992024-01-18018 January 2024 International, Administrative Change to HI-2200343-A IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23363A0312024-01-0404 January 2024 Application for HI-STORM 100 Cask System, Amendment No. 19 - Acknowledgement of Withdrawal and Notification of the U.S. Nuclear Regulatory Commission Staff Efforts Closure ML23355A0842023-12-21021 December 2023 International, Withdrawal of HI-STORM I00 Multipurpose Canister Storage System Amendment ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23324A0952023-12-0606 December 2023 Amendment No. 19 to Certificate of Compliance No. 1014 for the HI-STORM 100 Multi-purpose Canister Storage System - Request for Additional Information ML23328A0052023-12-0505 December 2023 Issuance of Renewed Certificate of Compliance No. 1014, Amendment No. 17 for the Hi-Storm 100 Cask System (Cac/Epid 001028/L-2021-LLA-0140) ML23338A3052023-12-0404 December 2023 International, Submittal of Supplement to RAI Responses on HI-STORM 100 Amendment 18 ML23334A1912023-11-30030 November 2023 International, Submittal of Topical Report HI-2210161-A Version ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23321A2172023-11-17017 November 2023 International, Responses to NRC Questions Form EA-23-044 Pre-Decisional Enforcement Conference IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use ML23310A0362023-11-0909 November 2023 International, Inc. - U.S. Nuclear Regulatory Commission Inspection Report 07201014/2023201 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23283A1262023-11-0202 November 2023 Letter - Second Request for Additional Information - HI-STORM 100 Amd 18 ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23263B1232023-09-20020 September 2023 HI-STORM 100 Amendment 16 Responses to Second Round Requests for Additional Information ML23234A1572023-09-14014 September 2023 Letter to Holtec International Final Safety Evaluation for Hi-2210161, Revision No. 4, Topical Report on the Radiological Fuel Qualification Methodology for Dry Storage Systems ML23145A1752023-09-12012 September 2023 NRC Choice Letter to Holtec International with Attached Safety Inspection Report, IR 72-1014/2022-201, December 12-15, 2022, Inspection of Holtec International in Camden, New Jersey (Docket Nos.: 72-1014, 72-1032) ML23251A2512023-09-0808 September 2023 International, Submittal of Supplement to RAI Responses on HI-STORM 100 Amendment 18 ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 ML23230B1582023-08-28028 August 2023 Amendment 16 to Certificate of Compliance 1014 for HI-STORM 100 Multipurpose Canister Storage System Request for Additional Information Second Round IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 NL-23-0620, ISFSI, and Edwin I. Hatch Nuclear Plant ISFSI, Registration of Spent Fuel Cask Use2023-08-0303 August 2023 ISFSI, and Edwin I. Hatch Nuclear Plant ISFSI, Registration of Spent Fuel Cask Use IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 2024-01-04
[Table view] Category:Report
MONTHYEARML24018A0852024-01-31031 January 2024 Safety Determination of a Potential Structural Failure of the Full Basket During Accident Conditions for the HI-STORM 100 and HI-STORM Flood/Wind Dry Cask Storage Systems ML23338A3082023-12-0404 December 2023 Attachment 3: HI-STORM 100 Amendment 18 Proposed FSAR Revision 22E Pages (non-proprietary) ML23325A1422023-11-21021 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 ML23068A4452023-06-29029 June 2023 60. Renewed Certificate of Compliance No. 1014, Amendment No. 14, Appendix B ML23068A4542023-06-29029 June 2023 69. Renewed Certificate of Compliance No. 1014, Amendment No. 15, Appendix D ML23068A4522023-06-29029 June 2023 67. Renewed Certificate of Compliance No. 1014, Amendment No. 15, Appendix B-100U ML23068A4502023-06-29029 June 2023 65. Renewed Certificate of Compliance No. 1014, Amendment No. 15, Appendix B ML23068A4472023-06-29029 June 2023 62. Renewed Certificate of Compliance No. 1014, Amendment No. 14, Appendix B-100U ML23068A4252023-06-29029 June 2023 40. Renewed Certificate of Compliance No. 1014, Amendment No. 10, Appendix B ML23068A4222023-06-29029 June 2023 37. Renewed Certificate of Compliance No. 1014, Amendment No. 9, Rev. 1, Appendix B-100U ML23068A4192023-06-29029 June 2023 35. Renewed Certificate of Compliance No. 1014, Amendment No. 9, Rev. 1, Appendix B ML23068A4162023-06-29029 June 2023 32. Renewed Certificate of Compliance No. 1014, Amendment No. 8, Rev. 1, Appendix B-100U ML23068A4142023-06-29029 June 2023 30. Renewed Certificate of Compliance No. 1014, Amendment No. 8, Rev. 1, Appendix B ML23068A4112023-06-29029 June 2023 27. Renewed Certificate of Compliance No. 1014, Amendment No. 7, Appendix B-100U ML23068A4092023-06-29029 June 2023 25. Renewed Certificate of Compliance No. 1014, Amendment No. 7, Appendix B ML23068A4062023-06-29029 June 2023 22. Renewed Certificate of Compliance No. 1014, Amendment No. 6, Appendix B ML23068A4042023-06-29029 June 2023 20. Renewed Certificate of Compliance No. 1014, Amendment No. 6 ML23068A4032023-06-29029 June 2023 19. Renewed Certificate of Compliance No. 1014, Amendment No. 5, Appendix B ML23068A4012023-06-29029 June 2023 17. Renewed Certificate of Compliance No. 1014, Amendment No. 5 ML23068A4002023-06-29029 June 2023 16. Renewed Certificate of Compliance No. 1014, Amendment No. 4, Appendix B ML23068A3992023-06-29029 June 2023 15. Renewed Certificate of Compliance No. 1014, Amendment No. 4, Appendix a ML23068A3982023-06-29029 June 2023 14. Renewed Certificate of Compliance No. 1014, Amendment No. 4 ML23068A3972023-06-29029 June 2023 13. Renewed Certificate of Compliance No. 1014, Amendment No. 3, Appendix B ML23068A3962023-06-29029 June 2023 12. Renewed Certificate of Compliance No. 1014, Amendment No. 3, Appendix a ML23068A3952023-06-29029 June 2023 11. Renewed Certificate of Compliance No. 1014, Amendment No. 3 ML23068A3932023-06-29029 June 2023 9. Renewed Certificate of Compliance No. 1014, Amendment No. 2, Appendix a ML23068A3942023-06-29029 June 2023 10. Renewed Certificate of Compliance No. 1014, Amendment No. 2, Appendix B ML23068A3922023-06-29029 June 2023 8. Renewed Certificate of Compliance No. 1014, Amendment No. 2 ML23068A3902023-06-29029 June 2023 6. Renewed Certificate of Compliance No. 1014, Amendment No. 1, Appendix a ML23068A3912023-06-29029 June 2023 7. Renewed Certificate of Compliance No. 1014, Amendment No. 1, Appendix B ML23068A3892023-06-29029 June 2023 5. Renewed Certificate of Compliance No. 1014, Amendment No. 1 ML23068A4022023-06-29029 June 2023 18. Renewed Certificate of Compliance No. 1014, Amendment No. 5, Appendix a ML23068A3882023-06-29029 June 2023 4. Renewed Certificate of Compliance No. 1014, Amendment No. 0, Appendix B ML23068A3862023-06-29029 June 2023 2. Renewed Certificate of Compliance No. 1014, Amendment No. 0 ML23146A1422023-05-26026 May 2023 Attachment 3 - Implementation of Topical Reports ML22276A2892022-10-0303 October 2022 Attachment 2: HI-STORM 100 FSAR Proposed Revision 21C, Changed Pages ML22249A3522022-09-0909 September 2022 Attachment 4: HI-STORM 100 FSAR Proposed Revision 21B, Changed Pages ML22245A1072022-09-0202 September 2022 Attachment 3:HI-STORM 100 FSAR Proposed Revision 22B, Changed Pages ML22243A2742022-08-31031 August 2022 Attachment 4: HI-STORM 100 FSAR Proposed Revision 21B, Changed Pages (non-proprietary) 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 ML21211A6072021-07-30030 July 2021 Attachment 3: HI-STORM 100 FSAR Proposed Revision 23 Revised Pages ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment ML21118A8632021-05-13013 May 2021 Issuance of Certificate of Compliance No. 1014, Amendment No. 15 for the HI-STORM 100 Multipurpose Canister Storage System 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) 2024-01-31
[Table view] Category:Miscellaneous
MONTHYEARML24018A0852024-01-31031 January 2024 Safety Determination of a Potential Structural Failure of the Full Basket During Accident Conditions for the HI-STORM 100 and HI-STORM Flood/Wind Dry Cask Storage Systems ML23325A1422023-11-21021 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 ML21083A1372021-03-22022 March 2021 NEIMA Reporting 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 ML21083A1382021-03-22022 March 2021 Rulemaking 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 ML20280A7772020-10-0606 October 2020 List of Previous Holtec Applications Which Justify Use of Q/I BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 20192019-06-20020 June 2019 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019 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 ML15231A5712015-07-28028 July 2015 Holtec Information Bulletin (HIB) No. 67 (Rev. 0), VCT Restraint Strap Weld Failure 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 ML12157A2462012-05-23023 May 2012 Attachment 22 to GNRO-2012/00039, Er Reference - Entergy 2010e (NPDES Crs) 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 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 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. 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. 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 ML0929604282009-10-23023 October 2009 Independent Spent Fuel Storage Installation Control of Heavy Loads Inspection Document Request 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 2024-01-31
[Table view] |
Text
-::::::-Entergy GNRO-2008/00052 July 17, 2008 Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S.Nuclear Regulatory Commission Washington, D.C.20555-0001 Entergy Operations, Inc.P.O.Box 756 Port Gibson, MS 39150 Tel 601 437 2800 Attention:
Subject:
Document Control Desk Special Report 2008-001 Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System Grand Gulf Nuclear Station, Unit 1 Docket No.50-416 License No.NPF-29
Dear Sir or Madam:
This Special Report is submitted in accordance with the HI-STORM Certificate of Compliance (CoC)1014 Amendment 2, Section 2.2, which requires notification of any spent fuel cask storage system that is loaded in a manner inconsistent with the fuel specifications of Section 2.1.Specifically, during a data update of the CASKLOADER Database, it was discovered that one HI-STORM 100S-B model multi-purpose canister (MPC)serial number 045 had been loaded with spent fuel bundles that exceeded the CoC Section 2.0 approved content requirements.
Verification of the database has determined that 8 fuel assemblies loaded in this MPC exceeded the maximum allowed Decay Heat per Fuel Storage Location Limit or the Fuel Burn-up Limit as specified in CoC Section 2.4 at the time of loading.These conditions are reportable in accordance withCoCSectionViolations.
Additionally, this MPC as well as three other MPCs contained at least one fuel assembly that required the use of, but were not placed on supplemental cooling as defined in section 3.1.4 of the CoCo The four MPCs involved are HI-STORM 100 MPC serial numbers 045,069,214, and 215.Upon discovery of the condition, the actions contained in Appendix B, Section 2.2 of the CoC, Fuel Specifications and Loading Conditions, were initiated.
The affected fuel assemblies were verified to be in a safe condition and the NRC Operations Center was notified of the event within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Attachment 1 completes the final action of submitting a Special Report within 30 days.A commitment is included in this submittal and summarized in Attachment
- 2.
GNRO-2008/00052 Page 2 If you have any questions or require additional information regarding this matter, please contact Dennis Coulter at 601-437-6595.
Sincerely, Michael J.Larson Acting Licensing Manger MJUDMC/dmc Attachments:
1.Special Report 2008-001 2.Licensee Identified Commitments Table cc: Document Control Desk U.S.Nuclear RegUlatory Commission Washington, DC 20555-0001 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S.Nuclear Regulatory Commission A TIN: Mr.Elmo E.Collins, Jr.(w/2)Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S.Nuclear RegUlatory Commission ATTN: Mr.Jack N.Donohew, Jr.,NRRlADRO/DORL (w/2)ATTN: ADDRESSEE ONLY ATTN: U.S.Postal Delivery Address Only Mail Stop OWFN/O-8G 14 Washington, D.C.20555-0001 G080052 Attachment 1 GNRO-2008/00052 Special Report 2008-001 Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System 8080052 Attachment 1 to GNRO-2008/00052 Page 1 Special Report 2008-001 Violation of Certificate of Compliance 1014 Cask Load Limits for HI-STORM 100 System BACKGROUND
.Successful fuel bundle selection for dry fuel storage loading requires the proper assignment of fuel parameters to each bundle.These parameters include the initial bundle characteristics (fuel type, length, total weight, uranium weight, uranium enrichment, etc.)and the bundles operating history (burn-up, discharge dates, etc.).The CASKLOADER database is used by Entergy as a repository for this information and to assist in the development of a cask loading plan.The Corporate BWRlPWR Fuel Engineering group is responsible for assembling the data from various sources, preparing the database (CASKLOADER), and transmitting the database back to the site Reactor Engineering groups.Site Reactor Engineering groups maintain the bundle operating history and transmits this information to the Corporate BWRlPWR Fuel Engineering group as required.Site Reactor Engineering groups use theprocesseddata to develop strategies for loading individual dry fuel storage casks.Bundle characteristics are verified against the dry fuel storage cask certificate of compliance (CoC)to ensure acceptability for loading as part of the CASKLOADER database.Site Reactor Engineering groups then use the database to maximize efficiency in loading the casks from an exposure (dose)and heat load perspective.
DESCRIPTION OF OCCURRENCE Entergy discovered on June 18, 2008 at 1412 that due to an error in the CASKLOADER Database, four spent fuel multi-purpose canisters (MPC)were loaded in a manner inconsistent with the CoC for the HI-STORM 100System.This event is not safety significant since all MPC design limits (e.g., heat load, radiation levels, and criticality) continue to be met although some specific spent fuel assemblies loaded were outside of the conservative individual fuel assembly limits specified in the CoCo Upon discovery of the condition, the actions contained in Appendix B, Section 2.2 of the CoC, Fuel Specifications and Loading Conditions, were initiated by Grand Gulf Nuclear Station (GGNS).The affected fuel assemblies were verified to be in a safe condition and the NRC Operations Center was notified of the event within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Specifically, during a data update of the CASKLOADER Database, it was discovered that oneSTORM 100S-B model MPC serial number 045 had been loaded with spent fuel bundles that exceeded the CoC Section 2.0 approved content requirements.
Verification of the database has determined that 8 fuel assemblies loaded in this MPC exceeded the maximum allowed Decay Heat per Fuel Storage Location Limit or the Fuel Burn-up Limit as specified in CoC Section 2.4 at the time of loading.These conditions are reportable in accordance withCoCSection 2.2-Violations.
Additionally, this MPC as well as three other MPCs contained at least one fuel assembly that required the use of but were not placed on supplemental cooling as defined in section 3.1.4 of the CoCo The four MPCs involved are HI-STORM 100 MPC serial numbers 045, 069, 214, and 215.8080052 Attachment 1 to GNRO-2008/00052 Page 2 CAUSE OF THE VIOLATION In 2006 work was started on developing the GGNS Dry Fuel Storage program.An engineer in the Corporate BWRlPWR Fuel Engineering group was assigned to develop the CASKLOADER database.The River Bend Station (RBS)database had already been developed and was in use.The assigned engineer used the RBS database development methodology as a model for developing the GGNS database.Modifications to the RBS approach were due to differences in operating history data (format and media).The engineer made these modifications and completed the database development.
A second engineer in the Corporate BWRlPWR Fuel Engineering group performed a review of the database.The completed database was then sent to GGNS site reactor engineering.
The first engineer and the second review engineer failed to recognize one important difference between the content of the RBS fuel history data and the GGNS fuel history data.The RBS fuel data was updated annually to capture additional burn-up.The GGNS data was based on the end of each cycle's conditions and were effectively"snapshots" in time.This difference in data content ultimately led to unaccounted burn-up for some of the GGNS fuel that was resident in the core past the cutoff date for the selected data.This ultimately led to a HI-STORM 100S-B model MPC being loaded with fuel bundles that slightly exceeded allowed CoC Decay Heat per Fuel Storage Location Limit and the Fuel Burn7up Limit.Two root causes were identified.
The first root cause was over reliance on a user's knowledge in selection of the scope of data being used for cask loading calculations.
No procedure governed this selection process.The second root cause was an inadequate verification process resulting in a program break down by a single human error.IMMEDIATE CORRECTIVE ACTIONS THAT HAVE BEEN TAKEN Reviewed fuel assembly burn-up data for the complete GGNS CASKLOADER database.There were 188 fuel assemblies found eligible for MPC loading with incorrect burn-up values.Only a few of these fuel assemblies violated the burn-up limitsatthe time they were loaded in the affected MPCs.This review did not consider the requirements for the MPCs to be transported off-site.Additional reviews will be required prior to considering these MPCs for transportation.
Reviewed fuel assembly burn-up data for all Entergy CASKLOADER databases.
No other potential for errors in burn-up were identified.
Reviewed current decay heat loads for all fuel assemblies loaded in the affected MPCs and determined them to be less than the CoC limits.All MPCs are below the MPC total heat load limit of 28.19 kW and all cooling features for the cask systems are functioning properly.Since the total heat loads in the MPCs are below the required limits, the structural integrity of the MPCs is not challenged.
An evaluation of the as loaded configurations was performed on the four MPCs.This evaluation concludes that fuel cladding in the affected MPCs is not adversely affected since the fuel cladding temperature will not exceed the fuel cladding design limit of 400 degrees centigrade.
Verified that fuel assembly exposure assumed in the dose calculations was within the bounds of the exposure of the loaded fuel assemblies.
Radiation levels of stored MPCs are within Cask Technical Specification limits and there are no radiation anomalies.
Verified that reactivity parameters are not affected by the identified errors.G080052 Attachment 1 to GNRO-2008/00052 Page 3 All four MPCs are currently considered operable and performing their intended safety functions; all surveillance parameters are within acceptance limits GGNS Management suspended MPC loading activities.
No further load activities will be performed until a procedure for developing the CASKLOADER database is implemented.
In the interim, MPCs may be loaded if the load data receives an independent third party review.LONG TERM CORRECTIVE ACTIONS TO PREVENT RECURRENCE Condition Report CR-GGN-2008-02844 has been written and will address long term corrective actions to prevent recurrence.
DATE WHEN FULL COMPLIANCE WILL BE ACHIEVED While loading of fuel assemblies outside CoC limits is not allowed, it is Entergy's position that unloading the affected MPCs to restore compliance is not prudent.Rather, an exemption will be pursued to allow the affected MPCs to remain in storage.Although Entergy is fully capable of doing so, unloading the subject MPCs would subject personnel to unnecessary radiation exposure, generate additional contaminated waste, increase the risk of a possible fuel handling accident, and increase the risk of a possible heavy load handling accident.Entergy plans to submit the required exemption within 90 days of submitting this special report.Full compliance will be achieved upon the NRC's approval of the submitted exemption.
G080052 G080052 Attachment 2 GNRO-2008/00052 Licensee Identified Commitments Table Attachment 2 to GNRO-2008/00052 Licensee Identified Commitments Table Thistableidentifies actions discussed in this letter for which Entergy commits to perform.Any other actions discussed in this submittal are described for the NRC's information and are not commitments.
TYPE (Check one)SCHEDULED ONE-CONTINUING COMPLETION COMMITMENT TIME DATE ACTION COMPLIANCE (If Required)An exemption will be submitted to allow continued storage of the affected fuel X 10/14/2008 assemblies in their associated multi-purpose canisters.
G080052