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Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023 License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023 Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023 Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2 DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023 Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023 Request Regarding Senior Reactor Operator License Application DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023 Annual Sea Turtle Report DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023 (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022 Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022 Core Operating Limits Report for Unit 2 Cycle 24 DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022 Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022 Site-Specific Decommissioning Cost Estimate, Revision 1 DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022 Post-Shutdown Decommissioning Activities Report, Revision 1 2024-01-29
[Table view] Category:Report
MONTHYEARML23307A1622023-11-0303 November 2023 OIG-24-A-01 Inspector Generals Assessment of the Most Serious Management and Performance Challenges Facing the U.S. Nuclear Regulatory Commission in Fiscal Year 2024 ML23130A0052023-06-27027 June 2023 Report to Congress Regarding Diablo Canyon ML22108A2892022-05-0303 May 2022 Enclosure - Response to Representative Carbajal Regarding OIG Report on Diablo ML22108A1662022-05-0303 May 2022 Enclosure 1 - Assessment Event Inquiry Into the Nuclear Regulatory Commission Oversight of the Auxiliary Feedwater System at Diablo Canyon Nuclear L-22-003, Independent Spent Fuel Storage Installation - License Renewal Application for the Diablo Canyon Independent Spent Fuel Storage Installation2022-03-0909 March 2022 Independent Spent Fuel Storage Installation - License Renewal Application for the Diablo Canyon Independent Spent Fuel Storage Installation DCL-21-071, Federally Listed Species Affects Determination Memorandum2021-10-14014 October 2021 Federally Listed Species Affects Determination Memorandum ML21188A0362021-07-0707 July 2021 Draft PG&E Letter DCL-21-046 - Diablo Canyon Unit 1: Emergency License Amendment Request 21-05, Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System ML21076A6142021-03-17017 March 2021 NRC Examination Report 05000275/2021301 and 05000323/2021301 ML20353A3972020-12-18018 December 2020 NRC Response to Public Comment Regarding Spent Fuel Canister Drop from 2019 Regcon DCL-20-102, Nuclear Material Transaction Report for New Fuel2020-12-0909 December 2020 Nuclear Material Transaction Report for New Fuel ML20335A0132020-11-30030 November 2020 NRC Response to Public Watchdogs November 2 ML20328A3012020-11-23023 November 2020 NERC Reliability Standards for the Bulk Electric System of North America Updated July 20, 2020 (Cgnp Public Comments on Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Pre-submittal Meeting of 11/24/2020) ML20309A5052020-11-0303 November 2020 Inspector Notes Cover Sheet ML20239A9562020-08-26026 August 2020 Evaluation of the Potential Piping Degradation Safety Concern on the Auxiliary Feedwater System at Diablo Canyon Unit 1 DCL-19-054, Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 12019-07-0101 July 2019 Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 1 ML18254A0402019-01-22022 January 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic DCL-18-050, Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 22018-09-11011 September 2018 Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 2 IR 05000275/20180052018-08-31031 August 2018 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2018005 and 05000323/2018005) DCL-18-058, Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-72018-08-0808 August 2018 Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-7 DCL-18-027, Seismic Probabilistic Risk Assessment for the Diablo Canyon Power Plant, Units 1 & 2 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1: Seismic of the Near-Term Task Force Review of Insight2018-04-24024 April 2018 Seismic Probabilistic Risk Assessment for the Diablo Canyon Power Plant, Units 1 & 2 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1: Seismic of the Near-Term Task Force Review of Insights NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test ML17024A2072017-12-18018 December 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation ML17341A0652017-11-30030 November 2017 Technical Evaluation Report Diablo Canyon Nuclear Power Plant Tsunami Hazard Reevaluation Review ML17334A1052017-11-29029 November 2017 Reactor Coolant System Pressure and Temperature Limits Report ML17229B6172017-08-17017 August 2017 Flaw Evaluation of Residual Heat Removal Suction Weld Joint DCL-17-064, Plant Focused Evaluation Report for External Flooding2017-07-19019 July 2017 Plant Focused Evaluation Report for External Flooding DCL-17-049, Flaw Evaluation of Unit 2 Residual Heat Removal Suction Weld Joint2017-05-18018 May 2017 Flaw Evaluation of Unit 2 Residual Heat Removal Suction Weld Joint DCL-16-117, Reactor Coolant System Pressure and Temperature Limits Report, Revision 152016-11-10010 November 2016 Reactor Coolant System Pressure and Temperature Limits Report, Revision 15 ML16314B0822016-11-0909 November 2016 Criteria for Protection Against Dynamic Effects Associated with a Postulated Rupture of Piping ML16314C6912016-11-0909 November 2016 Enclosure, Statement of the Problem Concerning PWR Primary Coolant System Pipe Rupture DCL-16-124, Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 52016-11-0909 November 2016 Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 5 ML16287A7552016-10-0606 October 2016 Technical Assessment Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4 ML16215A1092016-08-0202 August 2016 OEDO-16-00436 - Supplemental Information from Mr. Lochbaum 10 CFR 2.206 Petition on Apparent Violation of 10 CFR 50.9 at Diablo Canyon Nuclear Power Plant ML16169A2652016-05-18018 May 2016 Technical Report, Implementation of Alternative Source Terms Summary of Dose Analysis and Results, Revision 3 ML16146A0952016-04-21021 April 2016 54006-CALC-01, Diablo Canyon Power Plant: Evaluation of Risk Significance of Permanent ILRT Extension. DCL-16-081, 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm).2016-03-31031 March 2016 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm). ML16238A1042016-03-31031 March 2016 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm). ML16019A2242016-02-0101 February 2016 Record of Review, Dispositions to Diablo Canyon Nuclear Plant, Units 1 and 2, Internal Events, Internal Flooding, Seismic, and Fire PRA Facts and Observations ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi2016-01-15015 January 2016 Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi DCL-16-020, Diablo Canyon, Units 1 and 2 - 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV2016-01-15015 January 2016 Diablo Canyon, Units 1 and 2 - 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV ML16061A4642016-01-15015 January 2016 Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi ML16061A4682016-01-15015 January 2016 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV ML16061A4592016-01-14014 January 2016 Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report2016-01-14014 January 2016 Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report ML16048A2152015-12-15015 December 2015 Fleet Vehicle-Asset List ML16048A2072015-12-15015 December 2015 Once Through Cooling ML16004A3542015-12-11011 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Terms Summary of Dose Analysis & Results, Revision 1 PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 ML15321A4542015-11-13013 November 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask 2023-06-27
[Table view] Category:Miscellaneous
MONTHYEARML23130A0052023-06-27027 June 2023 Report to Congress Regarding Diablo Canyon ML22108A2892022-05-0303 May 2022 Enclosure - Response to Representative Carbajal Regarding OIG Report on Diablo ML22108A1662022-05-0303 May 2022 Enclosure 1 - Assessment Event Inquiry Into the Nuclear Regulatory Commission Oversight of the Auxiliary Feedwater System at Diablo Canyon Nuclear DCL-21-071, Federally Listed Species Affects Determination Memorandum2021-10-14014 October 2021 Federally Listed Species Affects Determination Memorandum ML21188A0362021-07-0707 July 2021 Draft PG&E Letter DCL-21-046 - Diablo Canyon Unit 1: Emergency License Amendment Request 21-05, Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-20-102, Nuclear Material Transaction Report for New Fuel2020-12-0909 December 2020 Nuclear Material Transaction Report for New Fuel ML20335A0132020-11-30030 November 2020 NRC Response to Public Watchdogs November 2 ML20328A3012020-11-23023 November 2020 NERC Reliability Standards for the Bulk Electric System of North America Updated July 20, 2020 (Cgnp Public Comments on Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Pre-submittal Meeting of 11/24/2020) ML18254A0402019-01-22022 January 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic IR 05000275/20180052018-08-31031 August 2018 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2018005 and 05000323/2018005) NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test ML17024A2072017-12-18018 December 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation DCL-16-117, Reactor Coolant System Pressure and Temperature Limits Report, Revision 152016-11-10010 November 2016 Reactor Coolant System Pressure and Temperature Limits Report, Revision 15 ML16215A1092016-08-0202 August 2016 OEDO-16-00436 - Supplemental Information from Mr. Lochbaum 10 CFR 2.206 Petition on Apparent Violation of 10 CFR 50.9 at Diablo Canyon Nuclear Power Plant ML16019A2242016-02-0101 February 2016 Record of Review, Dispositions to Diablo Canyon Nuclear Plant, Units 1 and 2, Internal Events, Internal Flooding, Seismic, and Fire PRA Facts and Observations ML16028A2952016-01-29029 January 2016 10 CFR 71.95 Notification Associated with the Failure to Observe Certificate of Compliance Condition of the 8-120B Secondary Lid Test Port Configuration ML16048A2152015-12-15015 December 2015 Fleet Vehicle-Asset List ML16048A2072015-12-15015 December 2015 Once Through Cooling PLA-7414, Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-11-19019 November 2015 Redacted - Susquehanna, Units 1 and 2 - Submittal of 10 CFR 71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 ML15321A4542015-11-13013 November 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ZS-2015-0156, Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask2015-10-26026 October 2015 Zionsolutions, LLC - Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15313A1642015-10-0808 October 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask DCL-15-102, 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask2015-08-24024 August 2015 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al NL-15-1461, Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2015-08-21021 August 2015 Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B PLA-7374, Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 91682015-08-20020 August 2015 Submittal of 10 CFR71.95 Report Regarding Energy Solutions 8-120B Cask Certificate of Compliance 9168 NRC-15-0085, Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask2015-08-19019 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Shipping Cask ZS-2015-0131, Zionsolutions, LLC - Submittal of10 CFR 71.95 Report on the 8-120B Cask2015-08-18018 August 2015 Zionsolutions, LLC - Submittal of10 CFR 71.95 Report on the 8-120B Cask ML15246A1452015-08-11011 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask ML15231A5712015-07-28028 July 2015 Holtec Information Bulletin (HIB) No. 67 (Rev. 0), VCT Restraint Strap Weld Failure ML15160A2612015-07-0101 July 2015 Letter to NMFS Notice of Intent to Reinitiate Scoping Process for Diablo Canyon Power Plant Units 1 and 2 License Renewal Application ML16048A2042015-06-30030 June 2015 Notice of Intent, General Permit to Discharge Storm Water ML16048A2132015-06-22022 June 2015 Permit Renewal No. 49-1 ML15355A2972015-05-31031 May 2015 DCPP Fsaru R22 File a Drawings - Combined - (Redacted) ML15355A0792015-05-31031 May 2015 DCPP Fsaru R22 File B Drawings - Combined (Redacted) ZS-2014-0271, Zionsolutions' 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance No. 9168, Revision No. 20 - Cask 8-120B2014-08-18018 August 2014 Zionsolutions' 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance No. 9168, Revision No. 20 - Cask 8-120B ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 DCL-14-030, Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 20132014-04-17017 April 2014 Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 2013 DCL-14-021, Reactor Coolant System Pressure and Temperature Limits Report for Units 1 and 22014-03-25025 March 2014 Reactor Coolant System Pressure and Temperature Limits Report for Units 1 and 2 2023-06-27
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Pacific Gas and Electric Company Barry S. Allen Diablo Canyon Power Plant Vice President, Nuclear Services Mail Code 104/6 P. 0. Box 56 Avila Beach; CA 93424 August 24, 2015 805.545.4888 Internal: 691.4888 PG&E Letter DCL-15-102 Fax : 805.545.6445 Mr. Mark Lombard, Director 10 CFR 71.95 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 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon, Units 1 and 2 Diablo Canyon Power Plant 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-1208 Shipping Cask
Dear Mr. Lombard:
Pacific Gas and Electric Company (PG&E) hereby submits the enclosed report pursuant to 10 CFR 71.95(a)(3) regarding instances in which the conditions of approval in Certificate of Compliance Number 9168, for the EnergySo/utions' Model 8-1208 shipping cask, were not met when making radwaste shipments from the Diablo Canyon Power Plant.
Enclosure 1 contains the 10 CFR 71.95 Report, prepared by PG&E, regarding the EnergySolutions' Model 8-1208 Shipping Cask.
Enclosure 2 contains a copy of the Customer Notification letter and associated 10 CFR 71 .95 Report, provided by EnergySolutions, regarding the EnergySolutions' Model 8-1208 Shipping Cask.
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this report. PG&E will implement corrective actions in accordance with the site Corrective Action Program.
If you have any questions concerning this submittal, please contact Mr. Hossein Hamzehee at 805-545-4720, or Mr. Timothy Irving at 805-545-3015.
Sincerely,
~(fr;§.~
Barry S. "'en A member of the STARS (Strategic Teaming and Resource Sharing) Alliance
m Document Control Desk
~&~ August 24, 2015 PG&E Letter DCL-15-102 Page 2 dqmg/6192/50708969 Enclosures cc/enc: . Marc L. Dapas, Regional Administrator Mark Lewis, EnergySolutions LLC Siva Lingam, NRC Project Manager John P. Reynoso, Acting Senior Resident Inspector IN PO Diablo Distribution 2
Enclosure 1 PG&E Letter DCL-15-1 02 Diablo Canyon Power Plant 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-1208 Shipping Cask
- 1. Abstract:
This report provides information required by 10 CFR 71.95, "Reports," for instances in which the conditions of approval in Certificate of Compliance (CoC) Number 9168, issued to EnergySolutions, LLC (EnergySo/utions), for its Model 8-1208 shipping cask, were not observed in making radioactive waste shipments. The circumstances described in this report apply specifically to Pacific Gas and Electric Company's (PG&E's) Diablo Canyon Power Plant (DCPP). On June 24, 2015, DCPP identified 4 shipments that failed to comply with the recently interpreted, vent port leak test requirements associated with the subject CoC.
Between 2013 and 2015, DCPP made 4 Type-8 shipments with this cask and removed the cask vent port plug each time. After replacing the vent port plug, DCPP leak tested the vent port in accordance with PG&E's Maintenance Procedure (MP) M-50.23, "Loading Pre-Loaded Liners Into The Chem-Nuclear CNS 8-1208 Radioactive Waste Shipping Cask," and the vendor's cask procedure.
There were no components or system failures that contributed to this event.
- 2. Narrative Description of Event The Model 8-1208 shipping cask is a cylindrical, carbon steel, lead-shielded package designed for the transport of radioactive waste containers. The cask has both a full-opening primary lid and a smaller, inner-secondary lid. Test ports for leak testing these package lids are located between the twin 0-ring seals for both the primary and secondary lids. Each package has a vent and optional drain port which can be used to inert the cask cavity with nitrogen, or vent pressure within the containment cavity which may be generated during transport, prior to lid removal. The vent hole in the primary lid is sealed with a removable plug and silicone gasket. There are no complex operational requirements associated with the package. An air test rig with a pressure gauge is engaged above each of the test ports or vent hole to pressurize the cavity. During leak testing, the air supply is isolated and the gauge is monitored to ensure a pressure drop of no more than 0.05 pounds-per-square-inch over the 15 minute test period.
DCPP procedure MP M-50.23, "Loading Pre-Loaded Liners into EnergySo/utions' 8-1208 Radwaste Shipping Cask," specified a 15-minute hold time for the pre-shipment leak test of the cask vent port, which was successfully completed for all 4 shipments. However, DCPP now recognizes the test manifold gasket may have reduced test sensitivity below the value required for the vent port plug. Therefore, the conditions of approval in the CoC were not met when making these shipments. This failure was identified on June 24, 2015, by a letter from Energy Solutions.
Enclosure 1 PG&E Letter DCL-15-1 02
- i. Status of inoperable components or systems Not applicable. None of the components or systems were inoperable.
ii. Dates and approximate times of occurrences The testing for these 4 shipments occurred between July 2014 and April2015.
iii. Cause of Error Test manifold gasket blocked the full air pressure on the vent port plug.
iv. Failure Mode, Mechanism, and Effects Not applicable.
- v. Systems or Secondary Functions Affected Not applicable.
vi. Method of Discovery of the Error During an industry audit of Energy Solutions, a concern was raised that the test manifold gasket could reduce the preshipment leak test sensitivity below the require value for the vent port plug.
vii. Discussion of Cause The test manifold gasket, when compressed, may deform and cover the vent port plug reducing the sensitivity of the leak test.
viii. Manufacturer and Model Number Manufacturer: EnergySolutions, LLC Model Number: 8-1208 ix. Quantities and chemical and physical form(s) of the package contents These shipments were all Physical/Chemical form Solid/Oxides on resin and their quantities are as shown in the table below.
Quantity Date (Curies)
RWS-14-001 07/16/14 49.7 2
Enclosure 1 PG&E Letter DCL-15-1 02 Quantity Date (Curies)
RWS-14-002 07/25/14 48.2 RWS-15-002 03/25/15 82.5 RWS-15-003 04/01/15 28.5
- 3. Assessment of Safety Consequences Based on the safety evaluation conducted by Energy Solutions, there is no safety consequence of performing the preshipment leak test of the Model 8-120B cask vent port plug.
- 4. Corrective Actions PG&E is reviewing the need to use this cask in the future. If used in the future, DCPP will revise DCPP procedure MP M-50.23, "Loading Pre-Loaded Liners into EnergySolutions' 8-120B Radwaste Shipping Cask," prior to using it. EnergySo/utions revised Procedure TR-TP-002 to replace the test manifold gasket with a different type.
- 5. Previous Similar Events In 2013, PG&E submitted a report on an inadequate leak test time for the vent port plug on this model cask (PG&E Letter DCL-13-094, "Diablo Canyon Power Plant and Humboldt Bay Power Plant 10 CFR 71.95 Reports Regarding Energy Solutions' Model 8-120B Shipping Cask," dated September 30, 2013).
- 6. Contact for Additional Information Clint Miller, DCPP Radwaste Engineer, 805-545-4582.
- 7. Extent of Exposure of Individuals to Radiation or Radioactive Materials The vent port was adequately sealed, and there was no additional exposure of individuals to radiation or radioactive material as the result of the deficient leak test.
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Enclosure 2 PG&E Letter DCL-15-1 02 Copy of Energy Solutions Customer Notification Letter and 10 CFR 71.95 Report on the 8-1208 Cask
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I June 24, 2015 l ES-CD-0-2015-002 It
Dear Valued Customer:
I On Monday June 1, 2015, an 8-1208 cask user identified a concern that the neoprene gasket could Il potentially affect the integrity of the vent port seal pre-shipment leak test. In response, EnergySolutions I performed a series of tests that confirmed that the neoprene gasket can constrict on the head of the vent I port plug cap screw when it is compressed by the manifold, resulting in a reduction of the test sensitivity.
The amount of reduction of the test sensitivity cannot be determined for any particular shipment due to f several reasons. It is uncertain whether, or by how much, the sensitivity of the vent port pre-shipment leak tests was reduced because: 1) Use of the gasket was optional- the gasket may," or may not have been in place for the tests, and 2) The force with which the gasket was compressed during testing is Iff unknown, so it is uncertain if it caused the gasket to constrict onto the head of the vent port cap screw. I The gasket may have been used on as many as 100 shipments by EnergySo!utions or its customers with EnergySolutions as the licensee from September 2013 through June 2015. It was September 2013 when newly designed lids were installed. The condition was determined not to have significant safety Ir consequence becavse the seals receive periodic helium leak testing as required by the SAR, the vent I
I ports are rarely opened, there is a margin of conservatism of approximately a factor of 9 on the prescribed vent port leak rate test, and there have been no observations of contamination around the vent I ~
port openings that would suggest leakage. There will be no further tests made using the gaskets since EnergySolutions has replaced all of the subject gaskets with a modified version that does not have the I i potenti<;~l to reduce the test sensitivity. i!
I Energy Solutions filed the attached report with the NRC containing the information required by 10 CFR 71.95 on June 24, 2015. In the report, EnergySolutions describes the cause of the discrepancy and provides information that supports that there is no safety significance. We expect that the information I
required for individual users to make their own notifications is contained in this report. Reference to this report in individual user reports would be appropriate if you so choose.
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We sincerely apologize for any inconvenience this issue may have caused within in your organization. i
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Our corrective actions as a result of this issue are intended to prevent recurrence of similar issues and to i I
ensure the highest quality of products and services that we provide.
I For additional details, please contact Aleksandr Gelfand at axgelfond@energysolutions.com or 803-591- t 9074. r II Sincerely, I l
MarkS. Lewis General Manager, Cask Logistics Logistics, Processing and Disposal Il l
EnergySo!utions, LLC
Attachment:
Letter and Report to NRC on 8-1208 Cask cc: Dan Shum I Aleksandr Gelfand i
740 Osborn Road. Barnwell, South Carolina 29812 803.259.1781. Fax 803.259.1477 l l I
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June 24, 2015 CD15-0149 l I
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Mark .Lornbard, Director II Division of Spent Fuel *M anagement I Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission I
Washington DC 20555-0001 I!
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A1TN: Document Control Desk I I
Subject:
10 CFR 71.95 Report on the 8~120B Cask
Dear Mr. Lombard:
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I EnefgySo!utions 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 #91.68) may not have been I
observed in making certain shipments. The circumstances desc.dbed in this report are applicable to approximately 235 shipments made by BnergySolutions as a licensee and user of the 8-120B cask over a 21 month period. II If you have any questions regarding this submitta~ please contact me at 801-649-2109. i;--
1 Daniel B. Shrum I l
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Dan Shrum t Jun 24 2015 2:58PM I i
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Senior Vice President, Regulatory Affairs J EnergySolutions LLC Attachment; Fa:ilure to Obse.rVe Certificate of Compliance Conditions for the 8-120B Vent Port Leak Pre-Shipment Leak Test I l l
cc: Michele Sampson, Chief Spent Fuel Licensing Branch I Pierre M. Saverot l
Licensing Branch IL l
299 So.uth Main Street, Suite 1700 *Salt Lake City, Utah 84ii1 (801} 649*2000
- www.energysolutions;com I1 l
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Failure to Observe Certificate of Compliance Conditions for the 8-120B Vent Port Pre-Shipment Leak Test June 24, 2015
- 1) Abstract Durfug the vent port seal pre-shipment leak rate test, a neoprene gasket that was added under the test manifold may have reduced the test sensitivity below the requ.ired value. The test manifold and gasket are not licensed packaging components. The gasket was added to the test manifold on some or all shipments to more reliably seal the manifold, saving test time and reducing personnel exposures. The amount of reduction ofthe test sensitivity cannot be determined for any particular shipment due to several reasons as discussed below. The gasket may have been used on as many as 100 shipments by EnergySolutions as the licensee
- fi*om September 2013 through June 2015. The condition was detennined not to have significant safety consequence because the seals receive periodic helium leak testing as required by the SAR, the vent ports are only opened rarely, there is a margin of conservatism of approximately a factor of 9 on the prescribed vent port leak rate test, and there have been no observations of contamination around the vent port openings that would suggest leakage.
There will be no further tests made using the gaskets since EnergySolutions has replaced all of the subject gaskets with a modified version that does not have the potential to reduce the test sensitivity.
It is uncertain whether, or by how much, the sensitivity.ofthe vent p01t pre-shipment leak tests was reduced because: 1) Use of the gasket was optional- the gasket may, or may not have been in place for the tests, and 2) The force with which the gasket was compressed during testing is unknown, so it is uncertain if caused the gasket to constrict onto the head of the vent p01t cap screw.
- 2) Narrative Description of the Event a) Status of Component$
All of the 8-120B packaging components are operating normally. The neoprene gaskets that caused the event have all be removed from service and replaced with a new manifold gasket, as discussed in (4) below.
b) Dates of Occurrences From September 2013, when pre-shipment leak tests were first performed using the neoprene gasket, to present~ approximately 100 shipments were made by EnergySolutions as the licensee. Most of these shipments used the neoprene gasket to perfo1m the pre-
. shipment leak rate test of the vent port.
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ENERGYSOLUTIONs-----------------
c) Cau.se of Error New 8-120B lids went into service in September 2013. It was found that the manifold sometimes had problems sealing w*i th the vent port on these new lids. Ene~gySolutions personnel found that adding an extra neoprene gasket helped to reduce the false test failures. Since the pre-shipment leak rate test is performed in a radiation environment, false fallures are undesirable because they increase the persoimel exposure. The pers_onnel did not realize that the gaskets had the pot~ntial to reduce th~ test sensitivity.
Attachment 1 has a detailed description of the test configuration.
d) Failure Mode, Mechanism, and Effects The neoprene gasket can constrict on the head of the vent port plug cap screw when it is compressed by the bottom end of the test manifold stinger, which could reduce the sensitivity of the pre-shipment ieak test. Consequently, the vent port pre-shipment leak tests perfonned using the neoprene gasket may not have provided the required test sensitivity of lx 1o-3 ref-cm3I sec.
e) Systems or Secondary Functions Affected Not applicable.
f) Method ofDiscovery of the Error On Monday June 1, 2015, an 8-120B cask user identified a concern that the neoprene gasket could potentially affect the integrity of the vent port seal pre-shipment leak test.
Later that week EnergySolutions performed a bench test that confirmed that the neoprene gasket can constrict on the head of the vent port plug cap screw when it is compressed by the manifold, resulting in a reduction of the test sensitivjty.
_3) Assessment of Safety Consequences
- Pre-shipment leak tests of all containment seals, includip.g the vent port, were performed prior to every shipment in accordance with the requirements of Chapter 7 of the SAR. In addition, periodic and maintenance leak tests of the containment seals) using helium as the test gas, were performed after maintenance, repair, Or replacement of the containment Sya}s ID accordance with therequirements of Chapter 8 oft)J.eSAR.
The 8-120B preshipment leak rate test criteria Were sized for the large primary lid. Since the vent port has a much sn1aller test volume, the test specification is conservative. Calculations
- show that the test specified in the SARis a factor of 9 more sensitive than the lxl 3 o-ref~cm 3 /sec required by Chapter 8 of the SAR. However; due to the uncertainties in the effects ofthe gasket, and the behavior of seaLs in series, it is not possible to c*o nfum whether the reduction ill sensitivity is offset by the test criteria conservatism.
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There has been no indication of any leakage from the vent poti from any shipment, and therefore> no exposure of individuals to radiation or radioactive materials due to the gaskets.
It is also noted that it is unusual for the vent pmt seal to be opened during cask operations, in which case the previous helium leak test of the vent port seal provides added assurance of seal integrity.
Therefore, it is concluded that there has been no safety consequence from performing vent port pre-shipment leak tests that may not have provided the requited test sensitivity of lxl0-3 3
ref-cm /sec.
- 4) Planned Corrective Actions EnergySolutions has taken corrective actions to assure that use of the old neoprene gasket design for the vent port pre-shipment leak test is immediately discontinued. -
- EnergySolutions notified all 8-120B cask users with upcoming shipments to require use of a new procedure, in conjunction with the new manifold gasket design, for pre-shipment leak testing of the vent port seal on all future shipments.
- EnergySolutions designed and tested new manifold gasket design that does not constrict onto the head of the vent port plus screw when compressed, and therefore it does not reduce the test sensitivity. The new gaskets have been distributed to all upcoming shipment users. The new manifold gasket design is shown in Attachment 1.
The En~rgySolutions dTawing for the 8-120B air drop manifold have been revised to include the new gasket seal~ and the air pressure drop test procedure TR-TP-002 has been revised to incorporate the new pre-shipment leak test procedure for the vent port. Use of the new procedure and the new manifold gasket will assure that the pre-shipment leak test satisfies the required test sensitivity and that the manifold gasket is removed from the test port after cmnpleting the pre-shipment leak test.
- 5) Previous Similar Events Involving the 8-120B No previous slinilar events have been identified.
- 6) Contact for Additional Information Dan Shrum EnergySolutions Senior Vice President, Regulatory Affairs (801) 649-2109
- 7) Extent of Exposure oflndividuals to Radiation or Radioactive Materials None.
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Attachment 1 Details of the 8-120B Vent Port Leak Rate Test Setup 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.
Step 7 .1.14 of the SAR requires a pre-shipment leak test of the primary lid) secondary lid> and vent port seals to be performed in accordance with Section 83.2.2 prior to every shipment to assure that the containment system is properly f!Ssembled. Per Table 8-2 ofthe SAR, the pre-shipment leak test of the vent port is performed by connecting a test manifold to the vent port, pressuriZing the seal and head ofthe vent pmt cap screw to 18 psig with dry air or nitrogen, and monitoring the pressure for at least '15 minutes to assure that it does not drop by more than 0.1 psig.
The pre-shipment leaktest of the vent port is a pressure drop test performed using a dedicated test manifold. The test manifold is not a part ofthe licensed package. It includes a stinger (shown below), an 0-ring seal that contacts the* stinger and the bottom of the vent port hole, and a sleeve nut to compress the 0-ring seal. The test manifold was designed so that it surround~ the vent port cap screw, leaving a small gap between itself and the vent port cap screw. The 8-120B j caskfleet began to ship with a new lid design in September 2013, and operations staff noted more frequent difficulty getting the manifold to seal. It became desirable to find a better way to seal the.bottom of the manifold in order to minimize operator exposure. They found that adding a neoprene ga,sket (also not part of the licensed package) under the base of the stinger as shown Il below helped reduce testing time and exposure. !*
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==============~ENERGYSOLUTIONS MANIFOLD STINGER PRIMARY LID MANIFOLD SLEEVE NUT MANIFOLD 0-RING SEAL t
(NOT LICENSED I EQUIPMENT) l f
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I NEOPRENE GAS.KET- SHOWN UNCOMPRESSED Il VENT PORT i CAP SCREW (NOT LICENSED EQUIPMENT)
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.<;.01 ~u .1 .LVl Y0 Corrective Action.- Modified Test Seal I!l The new manifold gasket design, shown below, replaces the manifold 0-ring seal and neoprene gasket previously used with a neoprene gasket that fits within the notch at the base of the manifold stinger. II l
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