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Category:Letter type:GNRO
MONTHYEARGNRO-2013/00079, 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013)2023-10-11011 October 2023 2013-10-13 (GNRO-2013-00079) Response to RAI Set 49 (Dated Sep-12-2013) 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-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-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-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report 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-2018/00054, 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-2018/00055, 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-2018/00052, 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-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report 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-2018/00048, 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 2023-06-06
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......."....... Ope-ratilons, Inc.
Entergy Christina L Perino GNRO-2011/00086 UCltoDE~r 14, 2011 u.s. Nuclear Regulatory Commission AnN: Document Control Desk nraj....Tnr Division of Spent Storage and Transportation Office of Nuclear Material Safety and Safeguards Washington, DC 20555-0001
Subject:
HI-STORM 100 Cask System Supplemental Cooling System (SCS) Validation Test Grand Gulf Nuclear Station, Unit 1 Docket Nos. 50-416 and 72-50 License No. NPF-29
Dear Sir or Madam:
Section 9, Special Requirements for First Systems in Place, of the Holtec HI-STORM 100 System Certificate of Compliance (CoC), requires a report of the Supplemental Cooling System (SCS) validation test and analysis for each first time user of a HI-STORM 100 Cask System SCS that uses components or a system that is not essentially identical to components or a system that has been previously tested. The SCS was tested at Grand Gulf Nuclear Station, Unit 1 (GGNS) on July 13, 2011, during the loading of Holtec Cask 534 which had a measured decay heat load of 18.74 kW.
Cask Data:
Cask Certificate Number: 1014 Amendment 5 Cask Model Number: HI-STORM 100S-B Cask Identification Number: Holtec Cask 534 Date of Test: July 13, 2011 Cask Heat Load: 18.74 kW The results of the SCS testing are contained in Attachment 1, Thermal Validation of Grand Gulf (GGNS) Supplemental Cooling System (SCS). These results show that system performance limits the coolant temperature to below 180 degrees Fahrenheit under steady-state conditions for the design basis heat load at an ambient air temperature of 100 degrees Fahrenheit as required by the Final Safety Analysis Report for the HI-STORM 100 Cask System, revision 7.
If you have any questions or require additional information, please contact Christina L. Perino at 601-437-6299.
Attachments: 1 Thermal Validation of Grand Gulf (GGNS) Supplemental Cooling System (SCS) cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission AnN: Mr. Elmo Collins, Jr.
Region Administrator, Region IV 612 East Lamar Blvd, Suite 400 Arlington, 76011-41 U. S. Nuclear Regulatory Commission AnN: Mr. Alan Wang, NRR/DORL Mail Stop OWFN/8 B1 Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission AnN: Mr. Blair Spitzberg RSFS Branch Chief, Region IV 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125 to 1
1 of 4 Attachment 1 GNRO-2011/00086 Thermal Validation of Grand Gulf (GGNS) Supplemental Cooling System (SCS) to GNRO-2011/00086 2 of 4 Holtec 555 Lincoln Drive West Marlton, NJ 08053 Telephone (856) 797*0900 HOLTEC INTERNATIONAL Fax (856) 797*0909 September 30, 2011 Mr. David Ellis Senior Project Manager, Dry Fuel Storage Entergy Operations, Inc. (Grand Gulf)
P. O. Box 756 Port Gibson, MS 39150
References:
GGNS SCS Thermal Validation Test Request letter, 8/4/2011
Subject:
Thermal Validation of Grand Gulf (GGNS) Supplemental Cooling System (SCS)
Dear Mr. Ellis:
In accordance with the above referenced letter, Holtec was requested to review the operating performance data for the Supplemental Cooling System (SCS).
HI-STORM FSAR Revision 7 section 2.C.2 states:
0 If the system uses water as the coolant, the system is sized to limit the coolant temperature to below 180 P under steady-state conditions for the design basis heat load at an ambient air temperature of 1OOoF. Active components (Le., pump or air cooler fan) are powered by electric motors with a backup power supply for uninterrupted operation.
After review of GONS SCS performance data, Holtec has confirmed that the SCS is operating in accordance with Appendix 2.C of the HI-STORM FSAR.
Please feel free to contact us with any questions or concerns.
~.~"
Debu Mitra-Majumdar cc: Suzanne Leblang (Entergy) John Griffiths (Holtec) Pankaj Chaudhary (Holtec) Kevin Cuthill (Holtec)
Doc. J.D.: 2005-001 to GNRO-2011/00086 3 of 4 Date: 4 11 To: Larry Project Manager, Holtec International From: David Senior Project Manager, Dry Fuel Storage Grand Gulf Nuclear Station Operations, Inc.
Certificate of Compliance 1014 Amendment 5 Condition 9 Mr.
This letter is sent to transmit operating performance data for equipment subject to the above referenced CoC license condition, and to request that your firm, as the certificate holder, perform a thermal validation test based on the provided data and provide the results of the test to Entergy.
Included in this letter is the data set from the first use of the Supplemental Cooling System (SCS) under conditions which were required by the certificate, and a copy of the Component Completion Record for the SCS supplied to Entergy by your firm.
If further information is required, please do not hesitate to contact me at 601.437.2489 or via email to =~~=-='::~~'-"-='
Thank you, David Ellis cc: Susan Leblang Dennis Coulter Jerrell Campell to GNRO-2011/00086 Grand Gulf Nuclear Station Page 4 of4 Cycle 18 Dry Fuel Storage Supplemental Cooling System First Time Use Data Set for Certificate of Compliance 1014 Amendment 5 License Condition 9 Hour SCS Inlet SCS Outlet Flow (F degrees) (F degrees) (Gal/min)
GGN SCS Performance Data 0 154 133 18 1 142 128 16 160 2 138 125 17 3 138 124 17 4 134 120 17 150 5 132 120 17 6 130 118 17 \
7 128 116 17 u..
140 8 123 117 17
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9 122 117 16 ;:, 130
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10 11 121 121 116 110 16 16 8-E 120
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12 120 109 16 {:!.
13 118 108 16 .. ..
14 118 108 16 110 15 117 103 16 16 115 102 16 100 17 113 102 16 18 112 102 16 90 19 110 102 16 ~
" '? I>- '0 'b 'l> ,,<:c> ,," ,,~ ,,'? "I>-
20 108 100 16 21 108 100 15 - - - SCS Inlet (F - - S C S Outlet (F MPC Backfill Pressure = 51.5 PSIG Cask Heat Load = 18.74kW