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Category:Letter
MONTHYEARML24030A7522024-01-30030 January 2024 Technical Specification Bases Pages IR 05000336/20234022024-01-30030 January 2024 Security Baseline Inspection Report 05000336/2023402 and 05000423/2023402 (Cover Letter Only) ML23341A0172024-01-12012 January 2024 Issuance of Amendment No. 288 Revision to Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature Limitations Figures IR 05000336/20234402024-01-11011 January 2024 Special Inspection Report 05000336/2023440 and 05000423/2023440 (Cover Letter Only) ML24004A1052024-01-0404 January 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000336/2024010 & 05000423/2024010 ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . ML23283A3052023-12-20020 December 2023 Review of Appendix F to DOM-NAF2, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code (EPID L-2022-LLT-0003) (Nonproprietary) ML23361A0312023-12-20020 December 2023 Intent to Pursue Subsequent License Renewal ML23352A0202023-12-18018 December 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23334A2242023-11-30030 November 2023 Request for Exemption from Enhanced Weapons Firearms Background Checks, and Security Event Notifications Implementation ML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23317A2702023-11-13013 November 2023 Core Operating Limits Report, Cycle 23 IR 05000336/20230032023-11-0606 November 2023 Integrated Inspection Report 05000336/2023003 and 05000423/2023003 ML23298A1652023-10-26026 October 2023 Requalification Program Inspection IR 05000336/20234202023-10-0404 October 2023 Security Inspection Report 05000336/2023420 and 05000423/2023420 ML23230A0502023-10-0202 October 2023 5 of the Quality Assurance Topical Report - Review of Program Changes ML23226A0052023-09-26026 September 2023 Issuance of Amendment No. 287 Supplement to Spent Fuel Pool Criticality Safety Analysis IR 05000245/20230012023-09-19019 September 2023 Safstor Inspection Report 05000245/2023001 IR 05000336/20230102023-09-0808 September 2023 Commercial Grade Dedication Report 05000336/2023010 and 05000423/2023010 IR 05000336/20230052023-08-31031 August 2023 Updated Inspection Plan for Millstone Power Station, Units 2 and 3 (Report 05000336/2023005 and 05000423/2023005) ML23248A2132023-08-30030 August 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise the Applicability Term for Reactor Coolant System Heatup and Cooldown Pressure-Temperature. ML23242A0142023-08-30030 August 2023 Operator Licensing Examination Approval ML23223A0552023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23223A0482023-08-18018 August 2023 Request for Withholding Information from Public Disclosure for License Amendment Request to Use Framatome Small Break and Realistic Large Break LOCA Evaluation Methodologies for Establishing COLR Limits IR 05000336/20230022023-08-0909 August 2023 Integrated Inspection Report 05000336/2023002 and 05000423/2023002 ML23188A0432023-07-31031 July 2023 Authorization and Safety Evaluation for Alternative Request No. IR-04-11 ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23207A1102023-07-26026 July 2023 NRC Regulatory Issues Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000336/20234012023-07-17017 July 2023 Material Control and Accounting Program Inspection Report 05000336/2023401 and 05000423/2023401 - (Cover Letter Only) ML23175A0052023-07-12012 July 2023 Alternative Request P-07 for Pump Periodic Verification Testing Program for Containment Recirculation Spray System Pumps ML23193A8562023-06-28028 June 2023 Submittal of Updates to the Final Safety Analysis Reports ML23178A1682023-06-26026 June 2023 2022 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML23153A1732023-06-16016 June 2023 Correction to Amendment Nos. 346 & 286 Millstone, 294 & 277 North Anna, 311 & 311 Surry, and 225 Summer to Revise Technical Specifications to Adopt TSTF-554,Rev Reactor Coolant Leakage Requirement ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23159A2202023-06-0808 June 2023 Associated Independent Spent Fuel Storage Installation Revision to Emergence Plan - Report of Changes IR 07200047/20234012023-06-0808 June 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report No. 07200047/2023401 2024-01-04
[Table view] Category:Report
MONTHYEARML23324A4222023-11-20020 November 2023 Reactor Vessel Internals Inspections Aging Management Program Submittal Related to License Renewal Commitment 13 ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23103A2282023-04-12012 April 2023 Stations Units 1 and 2; Millstone Power Station Units 2 and 3, DOM-NAF-2-P/NP-A, Revision 0.4, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML22193A1432022-06-23023 June 2022 5 to Updated Final Safety Analysis Report, Technical Requirements Manual Current Through Change No. 207 ML21175A2472021-06-24024 June 2021 2020 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the....- ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML21042B3212021-02-11011 February 2021 Stations, Units 1 & 2; Millstone Power Station, Units 2 & 3 - Request for Approval of Fleet Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code ML20352A3342020-12-17017 December 2020 Proposed Alternative Requests RR-05-04 and IR-4-02, Use of Alternative Pressure/Flow Testing Requirements for Service Water System Supply Piping ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20203M1602020-07-20020 July 2020 VA Elec. & Power Co., Dominion Energy Nuclear Co. Inc., Dominion Energy Sc Inc., Millstone Power Station 2, N. Anna & Surry Power Stations 1 & 2, Virgil C. Summer Station 1, Updated Anchor Darling Double Disc Gate Valve Information & Status ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19352B8982019-12-17017 December 2019 Proposed Alternative Request RR-05-05, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML19246A1162019-10-0707 October 2019 Supplement to Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood Causing Mechanism Reevaluation(Epid Nos. 000495\05000336\L- 2015-JLD-0011 and 000495\05000423\L-2015-JLD-0012 - (2019Aug21) ML19249B7742019-08-29029 August 2019 Enclosure 5 - Surry Power Station EAL Technical Bases Document Final (Updated) ML19249B7782019-08-29029 August 2019 Enclosure 6 - Millstone Power Station, Unit 2, Comparison Matrix RCS Pot. Loss A.1 ML19249B7682019-08-29029 August 2019 Enclosure 3 - Millstone Power Station EAL Technical Bases Documents Final (Updated) ML19249B7722019-08-29029 August 2019 Enclosure 4 - North Anna Power Station, EAL Technical Bases Document Final (Updated) ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML19070A2172019-04-0303 April 2019 Supplement to Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood - Causing Mechanism Reevaluation ML19064A5902019-02-28028 February 2019 Proposed Alternative Request IR-3-39, Alternative to ASME Code, Section XI, IWA-4221(C), to Permit Two Fillet Welds Not in Compliance with the Construction Code to Remain in Service ML19011A1742019-01-0404 January 2019 Enclosure 5 - Surry Power Station, EAL Scheme Revisions-Supporting Documents ML19011A1722019-01-0404 January 2019 Enclosure 3, Attachments 2C-3C - MPS3 EAL Technical Bases Document (Marked-Up) ML19011A1732019-01-0404 January 2019 Enclosure 4 - North Anna Power Station Units 1 & 2, EAL Scheme Revisions-Supporting Documents ML18256A2002018-10-0303 October 2018 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (EPID L00495\05000336 L-2015-JLD-0011 and 00495\05000423\L-2015-JLD-0012) ML18247A2752018-06-18018 June 2018 Technical Requirements Manual ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15253A2062015-09-0101 September 2015 ANP-3315NP, Revision 0, Millstone Unit 2 M5 Upgrade, Small Break LOCA Analysis Licensing Report. ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML15078A2052015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 1 Through 2-57 ML15078A2082015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-172 Through the End ML15078A2072015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-126 Through 2-171 ML15078A2062015-03-12012 March 2015 to Engineering Evaluation 14-E16, Dominion Flooding Hazard Reevaluation Report for Millstone, Units 2 and 3, in Response to 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding, Pp. 2-58 Through 2-125 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML13338A4332014-01-31031 January 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13357A3982014-01-24024 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Milestone Power Station, Unit 2, TAC No.: MF0858 ML14006A1592014-01-0808 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Millstone Power Station, Unit 3, TAC No.: MF0859 ML14087A0992013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 2023-07-26
[Table view] Category:Miscellaneous
MONTHYEARML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 ML23188A0202023-07-26026 July 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23151A0742023-06-12012 June 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML22353A6202022-12-19019 December 2022 Request for Approval of Appendix F Fleet Report DOM-NAF-2-P, Qualification of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion Energy VIPRE-D Computer Code ML21113A1352021-04-27027 April 2021 Review of the Spring 2017 Steam Generator Tube Inspection Report ML20345A3682020-12-16016 December 2020 Review of the Fall 2017 and Spring 2019 Steam Generator Tube Inspection Reports ML20247J6162020-09-0303 September 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20171A5342020-08-13013 August 2020 Staff Assessment of Flood Hazard Focused Evaluation and Integrated Assessment ML20105A0782020-04-14014 April 2020 Supplement to License Amendment Request to Revise TS 3.8.1.1, A.C. Sources - Operating, to Support Maintenance and Replacement of the 'A' Reserve Station Service Transformer and 345 Kv South Bus Switchyard Components ML19211B1682019-07-24024 July 2019 Day Special Report for One Train of Reactor Vessel Level Monitor Inoperable ML17187A1692017-06-28028 June 2017 Mitigating Strategies Assessment (MSA) Report) ML17108A3272017-04-0606 April 2017 Reactor Vessel Standby Surveillance Capsule Z Dosimetry Analysis and Storage Confirmation ML17051A0012017-02-27027 February 2017 Summary of the NRC Staff'S Review of the Spring 2015 Steam Generator Tube Inservice Inspections ML16193A6702016-06-30030 June 2016 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2014 and 2015, and Commitment Change Report for 2015 ML15328A2682015-12-15015 December 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15275A2882015-10-19019 October 2015 Summary of the NRC Staff'S Review of the Fall 2014 Steam Generator Tube Inservice Inspections ML15194A0572015-06-30030 June 2015 ISFSI - NRC Commitment Change Report for 2014 ML14220A0172014-07-30030 July 2014 Startup Test Report for Cycle 23 ML14013A2712014-01-30030 January 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13303B9072013-10-17017 October 2013 10 CFR 71.95 Report - 8-120B Cask Certificate of Compliance Noncompliance Due to an Inadequate Vendor Leak Test Procedure ML13192A1022013-07-18018 July 2013 Closure Evaluation for 30-Day Report for Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46 ML12362A3922012-11-30030 November 2012 Spent Fuel Pool Criticality Analysis with No Credit for Boraflex. ML12353A2422012-11-27027 November 2012 Report in Response to March 12, 2012 Information Request Regarding Seismic Aspects of Recommendation 2.3 ML12187A1752012-06-25025 June 2012 ISFSI - 10 CFR 50.59, 10 CFR 72.48 Change Report for 2010 and 2011, and Commitment Change Report for 2010 and 2011 ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review ML12046A8362012-01-31031 January 2012 Inservice Inspection Program - Owner'S Activity Report ML12031A1472012-01-25025 January 2012 Day Report for Emergency Core Cooling System Model Changes of 10 CFR 50.46 ML1116002202011-06-13013 June 2011 Exhibit D (Part 3): Millstone 2001 Safstor Cost Analysis (Normal Dollars) ML1028504382010-09-30030 September 2010 Attachments 2, 3, 5, 7, 8 & 9, to 10-579A, Westinghouse Electric Co. LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Revision 2, Dated Sep ML1019403352010-06-30030 June 2010 Units, 1, 2, 3, & ISFSI, 10 CFR 50.59, 10 CFR 72.48 Change Report for 2008 and 2009, and the Commitment Change Report for 2009 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1009702062010-03-29029 March 2010 Chemistry Procedure, Liquid Waste Sample Sink, Rev. 003-00 ML0931701762009-11-12012 November 2009 Part 3 of 4--Weld Overlay Examination Report 2R19 ML0931701732009-11-12012 November 2009 Part 2 of 4--Weld Overlay Examination Report 2R19 ML0931701662009-11-12012 November 2009 Part 1 of 4--Weld Overlay Examination Report 2R19 ML0931701852009-09-23023 September 2009 Part 4 of 4--Weld Overlay Examination Report 2R19 ML0921908942009-08-0404 August 2009 Units 1 & 2, Millstone, Units 2 and 3 and Kewaunee - Approved Topical Report DOM-NAF-2, Revision 0.1-A ML0913204602009-04-28028 April 2009 2008 Occupational Radiation Exposure Information ML0901303822008-12-26026 December 2008 Revision 002 to CP 3804L Procedure Action Request, Pass Containment Air Sample, Dated 12/26/2008 ML0830903962008-10-24024 October 2008 End of Cycle 18 Steam Generator Tube Inspection Report ML0827701132008-09-30030 September 2008 Response to Request for Additional Information Regarding Spent Fuel Pool Storage License Amendment Request ML0819800752008-07-0707 July 2008 Revision to Control Room and OSC Assembly Area Building 475 1st Floor, and SAP Locker ML0818406072008-07-0101 July 2008 Final Evaluation of Weld Overlay Examinations in Refueling Outage 18 ML0727504022007-09-27027 September 2007 Alternative Request RR-89-64 for Use of a Limited One-Sided Ultrasonic Examination Technique LBDCR 07-MP2-034 ML0720003902007-07-13013 July 2007 Attachment 1, Millstone Power Station Unit 3, License Amendment Request, Stretch Power Uprate, Descriptions, Technical Analysis and Regulatory Analysis for the Proposed Operating License and Technical Specifications Changes ML0715203992007-05-30030 May 2007 Fy 2007 Final Fee Rule Workpapers ML0713501882007-05-17017 May 2007 Review of Steam Generator Tube Inservice Inspection Report for the 2005 Refueling Outage at Millstone Power Station, Unit No. 2 ML0713502492007-05-0808 May 2007 Steam Generator Tube Plugging Report ML0708805652007-03-28028 March 2007 Response to Request for Additional Information Regarding an Alternative for the Weld Overlay of Pressurizer Nozzle Welds ML0705903272007-02-27027 February 2007 Fitness-For-Duty Program Semi-Annual Performance Data Report 2023-07-26
[Table view] |
Text
Dominion Nuclear Connecticut, Inc.
Rope Ferry Road, Warerford, CT 06385 ominion Web Address: www.dom.com OCT 17 2013 U. S. Nuclear Regulatory Commission Serial No.13-552 Attention: Document Control Desk MPS Lic/GJC RO Washington, DC 20555 Docket No. 50-245 License No. DPR-21 Docket No. 50-336 License No. DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS I AND 2 10 CFR 71.95 REPORT 120B CASK CERTIFICATE OF COMPLIANCE NONCOMPLIANCE DUE TO AN INADEQUATE VENDOR LEAK TEST PROCEDURE Dominion Nuclear Connecticut Inc. (DNC) is submitting this report pursuant to 10 CFR 71.95(a)(3) regarding instances in which the conditions of approval in the Certificate of Compliance #9168 for the 8-120B cask were not observed when making shipments from Millstone Power Station Unit Nos. 1 and 2 (MPS1 and MPS2). This report is based on a 10 CFR 71.95 report dated August 14, 2013 by the certificate holder, EnergySolutions, to the NRC which is enclosed.
The enclosed notification is applicable to use of the 8-120B cask by MPS1 and MPS2. DNC records show that MPS1 and MPS2 made a total of 4 Type B shipments using the 8-120B cask since 2001 which are listed in the attachment. During 2 of those shipments the vendor leak test procedure required the vent port seal test be performed for 20 minutes rather than 60 minutes as required by the cask's Safety Analysis Report (SAR).
EnergySolutions has revised the procedure to include a 60 minute test of the vent port seal.
If you have any questions or require additional information, please contact Mr. William D. Bartron at (860) 444-4301.
Sincerely, Step nV Sc ce -"
Site Vice President - Millstone
Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3) Report Page 2 of 2
Enclosure:
EnergySolutions 10 CFR 71.95 Report on the 8-120B Cask dated August 14, 2013.
Attachment:
List of MPS1 and MPS2 Type B shipments using the 8-120B cask since 2001.
Commitments made in this letter: None cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 J. S. Kim Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C2A Rockville, MD 20852-2738 M. D. Lombard Director - Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington DC 20555-0001 NRC Senior Resident Inspector Millstone Power Station
Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3) Report ENCLOSURE EnerciySolutions Letter CD13-0232, Dated: August 14, 2013.
To: M. D. Lombard Director - Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards, USNRC, From: D. B. Shrum, Senior Vice President, Regulatory Affairs, EnerqySolutions, Subiect: 10 CFR 71.95 Report on the 8-120B Cask.
MILLSTONE POWER STATION UNIT I AND 2 DOMINION NUCLEAR CONNECTICUT, INC.
EN ERGYSOLUTIONS August 14, 2013 CD1 3-0232 Mark Lombard, Director Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington DC 20555-0001 ATTN: Document Control Desk
Subject:
10 CFR 71.95 Report on the 8-120B Cask
Dear Mr. Lombard:
EnergySolutions hereby submits the attached report providing the information required by 10 CFR 71.95(a)(3) for instances in which the conditions of approval in the Certificate of Compliance for the 8-120B Cask (Certificate of Compliance #9168) may not have been observed in making certain shipments. The circumstances described in thisreport are applicable to all licensed users of the cask.
If you have any questions regarding this submittal, please contact me at 801-649-2109.
Sincer Daniel B. Shrum Senior Vice President, Regulatory Affairs EnergySolutions
Attachment:
Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time cc: Michele Sampson, Chief Thermal and Containment Branch Pierre M. Saverot Licensing Branch 423 West 300 South, Suite 200 . Salt Lake City, UT 84101 www.energysolutions.com
EN ERGYSOLUTIONS Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Test Hold Time August 14, 2013
- 1) Abstract This report provides the information required by 10 CFR 71.95(a)(3) for instances in which the conditions of approval in the Certificate of Compliance for the 8-120B Cask (Certificate of Compliance #9168) may not have been observed in making certain shipments. The circumstances described in this report-are applicable to all licensed users of the cask.
EnergySolutions' air pressure drop test procedure TR-TP-002 describes a 20-minute hold time for the pre-shipment leak test of the cask vent port. The 8-120B Safety Analysis Report (SAR), however, specifies a hold time of 60 minutes for the leak test of the vent port; therefore the conditions of approval in the Certificate of Compliance may not necessarily have been observed in making shipments. TR-TP-002 is the basis for leak tests on all EnergySolutionsshipments, as well as the suggested procedure content for most shipments by our authorized users.1 The 8-120B CoC requires the package to be prepared for shipment and operated. in accordance with Chapter 7 of the SAR, and tested and maintained in accordance with Chapter 8 of the SAR. TR-TP-002 captures the applicable SAR requirements and provides further detail for the development of a shipper's operating procedure. Recently, an 8-120B cask user identified the hold time discrepancy between TR-TP-002 and the SAR (i.e., 20 versus 60 minutes). Based on a review of past revisions of CoCs, SARs, and cask handling procedures, it appears that this discrepancy has existed for approximately 12 years, spanning approximately 88 cask users and approximately 1,400 shipments.
Upon notification and after confirmation of the discrepancy, EnergySolutions revised TR-TP-002 to incorporate the SAR required 60-minute vent port leak test. This change to TR-TP-002 was communicated to all EnergySolutions registered cask users on June 13, 2013. The SAR requires pre-shipment leak testing of the vent port only when the port has been opened since the preceding vent port leak test. EnergySolutions issued a notice to registered cask users on July 2, 2013 to clarify this issue. Operation of a package vent port is infrequent. However some vent ports may have been opened during the past 12 years; and therefore the pre-shipment leak testing would have been required.
The licensing basis for the pre-shipment leak tests for all three of the 8-1 20B lid containment seals is a pressure drop calculation for the largest of the three seals (the primary lid seal).
The required hold time is therefore conservative for the two seals with smaller test volumes.
Because of the small size of the vent port seal test volume, EnergySolutions has determined that the 20-minute hold time meets the same criterion by which the 60-minute hold time was derived for the larger primary lid seal. In fact, in the case of the vent port leak test, the 20-minute hold time provides substantial margin for detecting any leakage from the vent port. It therefore follows that there is no safety significance associated with the condition.
Since registered users of the 8-120B package are licensees, these licensees would normally prepare and issue an approved procedure to control their pre-shipment activities.
ENERGYSOLUTIONS Furthermore, there is no continuing safety concern as new lids are required to be used after August 31, 2013 with different testing procedures.
Due to the long timeframe over which this condition has existed, the large number of 8-120B cask users, the many shipments that have occurred, the difficulty of determining which if any shipments may have been out of compliance, and the finding of no significant safety impact, EnergySolutions hereby submits this notification to summarize the issue as it applies to all 8-120B users. Because of the imminent rollout of new lids and related test procedures, no further corrective actions by certificate users are necessary to address this leak test procedure.
- 2) Narrative Description of the Event a) Status of Components All 8-120B components are operating normally.
b) Dates of Occurrences February 2001 to present.
c) Cause of Error Discrepancy between EnergySolutions air pressure drop test procedure TR-TP-002 and Chapter 8 of the 8-120B SAR.
d) Failure Mode, Mechanism, and Effects Not applicable; no 8-120B packaging components have failed.
e) Systems or Secondary Functions Affected Not applicable.
f) Method of Discovery of the Error The condition was identified by an 8-120B cask user.
- 3) Assessment of Safety Consequences There is no safety consequence of performing the pre-shipment leak test of the 8-120B cask vent port using a 20-minute hold time versus the 60-minute hold time that is required by the 8-120B CoC. The required hold time varies in proportion to the test volume if the test pressure and acceptance criterion remain unchanged. Larger test volumes require longer hold times. The test volume includes the free volume of the space to be tested and the volume of the test manifold. For the original subject 8-120B lids, Section 4.4 of the July 2012 SAR Addendum shows the calculation basis for a 60-minute hold time. Only one calculation was presented for the large primary lid containment seal. Since the other seals have smaller test volumes, a 60-minute hold time was conservatively specified for all seals, including the vent port.
ENERGYSOLUTIONS The SAR test volume for the primary containment seal was 103.2 cc. For the pre-shipment vent port leak test, there is no safety impact from a 20-minute hold time provided that the test volume is less than or equal to the 20/60 times the primary containment seal test chamber volume, or (20/60)* 103.2 = 34.4 cc. The vent port test volume is equal to the combined volume of the test manifold (10 cc) plus a very small residual volume inside the vent port, which is less than 34.4 cc. Therefore, pre-shipment leak tests of the vent port performed using a 20-minute hold time are adequate to demonstrate compliance with maximum leak rate acceptance criteria, and there is no safety consequence from testing vent ports for 20 minutes instead of 60 minutes.
- 4) Planned Corrective Actions As noted above, upon notification and after confirmation of the discrepancy, EnergySolutionsv revised TR-TP-002 to incorporate the SAR required 60-minute vent port leak test and notified registered cask users of the change.
Beginning September 1, 2013, the 8-120B fleet will ship with a new lid design, authorized in the latest revision of the CoC. 2 Thereafter, the 8-120B cask may no longer be used with the old seals that were authorized in Revision No. 17 of the 8-120B CoC. Shipments with the new lids will be required to use the seals authorized in Revision 19 of the CoC. The EnergySolutions air pressure drop test procedure TR-TP-002 is being revised and reissued based on the requirements of Revision 19 of the 8-120B CoC. These revisions are reviewed and approved by the EnergySolutions Cask Licensing Manager to assure that they are compliant with the requirements of the CoC.
EnergySolutions also has initiated a lifecycle procedure for managing Type B casks to assure that CoC requirements flow through the design, fabrication, and operational phases. This is a new procedure that also would identify existing inconsistencies and prevent future inconsistencies between the SAR and operating procedures. The procedure will be effective August 19, 2013.
The error in incorporating the revised 60-minute vent port leak rate criteria into TR-TP-002 raises a question as to whether there are other similar errors involving the flow-down of requirements into operating procedures. Accordingly, EnergySolutionsplans to conduct a review of the 8-120B and other EnergySolutions Type B packagings to verify that CoC and SAR requirements have been accurately translated into the prescribed operating procedures.
If any such discrepancies are found, EnergySolutions will expand the scope of these reviews as necessary.
- 5) Previous Similar Events Involving the 8-120B No previous similar events have been identified.
2No shipments have been made using the new lids to date.
EN ERGYSOLUTIONS
- 6) Contact for Additional Information Dan Shrum EnergySolutions Senior Vice President, Regulatory Affairs (801) 649-2109 Materials
- 7) Extent of Exposure of Individuals to Radiation or Radioactive None.
Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3) Report ATTACHMENT LIST of MPS1 and MPS2 TYPE B SHIPMENTS SINCE 2001 USING the 8-120B CASK MILLSTONE POWER STATION UNIT 1 AND 2 DOMINION NUCLEAR CONNECTICUT, INC.
Serial No.13-552 Docket No. 50-245 and 50-336 10 CFR 71.95(a)(3) Report Attachment List of MPS1 and MPS2 Type B Shipments Since 2001 Using the 8-120B Cask Shipments Which Did Not Require the Vent Port Test I
RMRS # Cask Used Destination Date of Shipment Unit 03-012-1 8-120B Chem-Nuclear, Barnwell, SC 08/04/2003 1 03-017-1 8-120B Chem-Nuclear, Barnwell, SC 10/01/2003 1 Shipments Which Required the Vent Port Test RMRS # Cask Used Destination Date of Shipment Unit 05-098-1 8-120B Chem-Nuclear, Barnwell, SC 06/23/2005 1 -
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-4 i 06-029 8-120B Chem-Nuclear, Barnwell, SC 03/23/2006 2 I