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Category:Annual Operating Report
MONTHYEARML22104A0782022-04-14014 April 2022 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 0CAN022103, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-10010 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 ML20120A4212020-04-29029 April 2020 Annual 10 CFR 50.46 Report for Calendar Year 2019 Emergency Core Cooling System Evaluation Changes ML19094B0782019-04-0303 April 2019 Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 0CAN061801, Annual 10 CFR 50.46 Report for Calendar Year 2017, Emergency Core Cooling System Evaluation Changes2018-06-0505 June 2018 Annual 10 CFR 50.46 Report for Calendar Year 2017, Emergency Core Cooling System Evaluation Changes 0CAN051801, Submittal of Annual Radiological Environmental Operating Report for 20172018-05-0909 May 2018 Submittal of Annual Radiological Environmental Operating Report for 2017 0CAN071701, Annual 10 CFR 50.46 Report for Calendar Year 2016, Emergency Core Cooling System Evaluation Changes2017-07-26026 July 2017 Annual 10 CFR 50.46 Report for Calendar Year 2016, Emergency Core Cooling System Evaluation Changes 0CAN011701, Submittal of 10 CFR 72.48 Summary Report for the Reporting Period January 1, 2015, Through December 31, 20162017-01-13013 January 2017 Submittal of 10 CFR 72.48 Summary Report for the Reporting Period January 1, 2015, Through December 31, 2016 ML15161A1232015-06-0909 June 2015 Annual 10CFR 50.46 Report for Calendar Year 2014 Emergency Core Cooling System Evaluation Changes 0CAN051502, Annual Radiological Environmental Operating Report for 20142015-05-12012 May 2015 Annual Radiological Environmental Operating Report for 2014 0CAN081405, Units 1 and 2 - Correction to Annual Radiological Environmental Operating Report for 20122014-08-0606 August 2014 Units 1 and 2 - Correction to Annual Radiological Environmental Operating Report for 2012 0CAN041407, Annual Radiological Environmental Operating Report for 20132014-04-30030 April 2014 Annual Radiological Environmental Operating Report for 2013 CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G 0CAN051302, Annual Radiological Environmental Operating Report for 20122013-05-14014 May 2013 Annual Radiological Environmental Operating Report for 2012 0CAN051204, Annual 10 CFR 50.46 Report for Calendar Year 2011, Emergency Core Cooling System Evaluation Changes2012-05-17017 May 2012 Annual 10 CFR 50.46 Report for Calendar Year 2011, Emergency Core Cooling System Evaluation Changes 0CAN051201, Units 1 and 2, Annual Radiological Environmental Operating Report for 20112012-05-0707 May 2012 Units 1 and 2, Annual Radiological Environmental Operating Report for 2011 CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G 0CAN041104, Annual Radioactive Effluent Release Report for 20102011-04-29029 April 2011 Annual Radioactive Effluent Release Report for 2010 0CAN041102, Annual Radiological Environmental Operating Report for 20102011-04-20020 April 2011 Annual Radiological Environmental Operating Report for 2010 0CAN031101, Annual 10 CFR 50.46 Report for Calendar Year 2010 Emergency Core Cooling System Evaluation Changes2011-03-30030 March 2011 Annual 10 CFR 50.46 Report for Calendar Year 2010 Emergency Core Cooling System Evaluation Changes 0CAN051001, Annual Radiological Environment Operating Report for 20092010-05-11011 May 2010 Annual Radiological Environment Operating Report for 2009 ML1006300912010-02-25025 February 2010 Offsite Dose Calculation Manual ML1006300892010-02-25025 February 2010 Annual Radioactive Effluent Release Report for 2009 CNRO-2009-00006, Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2009-04-13013 April 2009 Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G 0CAN050603, Annual Radiological Environmental Operating Report for 20052006-05-15015 May 2006 Annual Radiological Environmental Operating Report for 2005 ML0414903342004-05-27027 May 2004 Units 1 and 2, Errors or Changes in the Emergency Core Cooling System Evaluation Model; Annual Report for 2003 0CAN050306, Arkansas, Units 1 and 2, Errors or Changes in the Emergency Core Cooling System Evaluation Model; Annual Report for 20022003-05-29029 May 2003 Arkansas, Units 1 and 2, Errors or Changes in the Emergency Core Cooling System Evaluation Model; Annual Report for 2002 2022-04-14
[Table view] Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, 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 42023-04-0505 April 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 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, 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 42022-12-22022 December 2022 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 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
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Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Regulatory Assurance Arkansas Nuclear One 0CAN011701 January 13, 2017 ATTN: Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Rockville, MD 20555-0001
SUBJECT:
10 CFR 72.48 Summary Report for the Reporting Period January 1, 2015, through December 31, 2016 Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313, 50-368, and 72-13 License Nos. DPR-51 and NPF-6
Dear Sir or Madam:
In accordance with 10 CFR 72.48(d)(2), Arkansas Nuclear One, Units 1 and 2 (ANO-1 & 2) are required to submit a 10 CFR 72.48 report at intervals not to exceed 24 months. The report contains a brief description of any changes in the facility, the Ventilated Storage Cask (VSC),
and/or the Holtec HI-STORM 100 designs. The report also contains changes in procedures and test/experiments as described in the VSC or HI-STORM 100 Safety Analyses Reports. The attached summary report addresses the reporting period from January 1, 2015, through December 31, 2016.
This letter contains no new regulatory commitments.
0CAN011701 Page 2 of 2 If you have any questions concerning this submittal or Entergy Operations storage of spent fuel at ANO under the general license, please contact me.
Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/rwc
Attachment:
10 CFR 72.48 Summary Report for Reporting Period January 1, 2015, through December 31, 2016 cc: Mr. Kriss Kennedy Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 U. S. Nuclear Regulatory Commission Attn: Mr. William Allen MS 14A44 One White Flint North 11555 Rockville Pike Rockville, MD 20852
ATTACHMENT TO 0CAN011701 10 CFR 72.48
SUMMARY
REPORT FOR REPORTING PERIOD JANUARY 1, 2015, THROUGH DECEMBER 31, 2016
0CAN011701 Page 1 of 3 10 CFR 72.48
SUMMARY
REPORT FOR REPORTING PERIOD JANUARY 1, 2015, THROUGH DECEMBER 31, 2016 During the stated reporting period, two 10 CFR 72.48 evaluations were performed at Arkansas Nuclear One, Units 1 and 2 (ANO-1 & 2). These evaluations are summarized below.
DFS-15-001, Revision 0 Summary of Change During Multi-Purpose Canister (MPC) load verification for HI-STORM MPC-24-059, Operators and Reactor Engineering discovered foreign material (FM) on the upper end fitting of a fuel assembly NJ065P. The FM was identified as a piece of torn grid strap from a fuel assembly.
Attempts to remove the torn grid strap were not successful and it fell into the flux trap gap between basket cells. Visual inspection of adjacent fuel assemblies was performed. During inspection of assembly NJO65X, personnel identified that two (2) grid straps were torn in similar locations (at the corner of two adjacent straps). Therefore, it was determined that there was an additional FM item in the MPC. There are a total of two (2) FM items, both identified as torn grid straps, each having similar characteristics, and located at the bottom of the MPC in the area between cells. The fuel assembly with the torn grid straps has been removed from the MPC and replaced with an intact assembly. The condition was evaluated to accept the presence of the foreign material and continue loading the MPC.
Summary of 10 CFR 72.48 Evaluation The Holtec HI-STORM 100 Certificate of Conformance (CoC), Amendment 5, defines Fuel Debris and NON-FUEL HARDWARE in Appendix B, as:
FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly pads, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.
NON-FUEL HARDWARE is defined as Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices (TPDs), Control Rod Assemblies (GRAs), Axial Power Shaping Rods (APSRs),
Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs),
Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, vibration suppressor inserts, and components of these devices such as individual rods.
The two small pieces of grid strap material, identified as Zircaloy, do not meet any of the definitions above for Fuel Debris or Non-Fuel Hardware; therefore, the material is simply classified as FM. As such the evaluation performed by Holtec treats the material as FM. Holtec evaluated the material with regard to Normal Conditions of Storage, Off-Normal Conditions of Storage, and Accident Conditions of Storage. In all cases the small weight of the two pieces, conservatively calculated at 0.0038 pounds combined, yielded insignificant impact to the evaluated and analyzed conditions.
0CAN011701 Page 2 of 3 With Holtec as the License Holder for the HI-STORM 100 Cask System, with ANO as a General User under the license provisions of 10 CFR 72, ANO requested that Holtec perform the technical review and 72.48 Evaluation for this Foreign Material.
The Holtec 72.48 evaluation determined that there are no malfunctions associated with the HI-STORM system due to the FM and, since the containment boundary remained unchanged, no increase in malfunction likelihood or consequences is created, nor does the FM result in the possibility of a different type of malfunction than what has been previously analyzed. Methods of handling and operating the cask system are not affected and no new accidents can be created. Cask system temperatures, including fuel cladding, are not increased and MPC internal pressures are not increased; therefore, no fission product boundary limit is exceeded.
In addition, no new evaluation methods are used.
DFS-16-001 Summary of Change EC 52619 applies a concrete sealant, MasterProtect H400, to the EnergySolutions VSC-24 Dry Fuel Storage Ventilated Concrete Casks (VCCs) to address identified long term degradation due to Alkali-Silica Reaction (ASR). Application of the sealant should minimize further ASR degradation.
Summary of 10 CFR 72.48 Evaluation The VSC-24 Final Safety Analysis Report (FSAR) thermal analyses for the Normal Long-Term Storage (75 °F ambient air) case, and the associated cask system temperatures presented in FSAR Figure 4.4-5, would remain conservative even if the radiant heat transfer off the VCC concrete surface were completely neglected.
For the Severe Steady-State Hot (100 °F ambient air) case, the elimination of all VCC concrete surface radiant heat transfer would cause system temperatures to increase by at most ~2.7 °F, with interior temperatures such as the maximum cladding temperature increasing by a smaller amount. Those temperature increases are a small fraction of the component temperature margins shown in the VSC-24 FSAR. These small temperature increases are based on the extremely conservative (and unrealistic) assumption that the VCC concrete surface emissivity drops to zero (with no reduction in absorptivity) as a result of sealant application, despite the fact that the sealant does not alter surface appearance, according to its product data sheet.
Thus, the proposed change clearly will not cause any of the thermal acceptance criteria to be exceeded.
Finally, it must be noted that the temperature margins presented in Table 4.1-1 of the VSC-24 FSAR are based upon a VSC system heat load of 24 kW. All of the casks at ANO had an overall heat load of less than 15 kW at the time of loading. At present, the heat loads of all ANO VSC-24 casks are significantly less than 15 kW, which in turn is far below the design basis heat load of 24 kW. Furthermore, a condition limiting any future VSC-24 cask payloads to 15 kW will soon be implemented, as part of the VSC-24 CoC renewal. These lower heat loads more than offset any effects from reduced VCC concrete surface emissivity by a very wide margin; thus, the licensing basis thermal analyses, and the temperatures presented in the FSAR, will bound those present in any of the ANO casks, after the sealant is applied, by a very wide margin.
0CAN011701 Page 3 of 3 Based on the above, it is concluded that the application of the proposed sealant to the VCC concrete surfaces at ANO will have no significant impact on the thermal performance of the VSC-24 system. The FSAR thermal analyses and associated temperatures (presented in the FSAR) will remain bounding for the resulting cask configuration. The coating (which has negligible weight) also has no impact on the structural or shielding performance of the cask system. Thus, the proposed application of sealant is an acceptable configuration change that can be performed via a 72.48 evaluation.