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Category:Legal-Affidavit
MONTHYEARML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML22320A5592022-11-16016 November 2022 2022 Annual Report - Guarantees of Payment of Deferred Premiums ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML21307A0542021-11-0202 November 2021 Annual Report - Guarantees of Payment of Deferred Premiums ML21272A2772021-09-29029 September 2021 Update to Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21182A1002021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML20310A1152020-11-0404 November 2020 Annual Report - Guarantees of Payment of Deferred Premiums ML19318G1702019-11-14014 November 2019 2019 Annual Report - Guarantees of Payment of Deferred Premiums ML18316A0032018-11-0707 November 2018 Submittal of 2018 Annual Report - Guarantees of Payment of Deferred Premiums ML16088A3962016-03-28028 March 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision RS-16-058, Clinton, Unit 1 - Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision2016-03-28028 March 2016 Clinton, Unit 1 - Transmittal of Exelon Nuclear Radiological Emergency Plan Addendum Revision ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow RS-14-160, Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package2014-07-0202 July 2014 Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) RS-12-227, Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package2012-12-19019 December 2012 Exelongeneration, Submission of Standard Practice Procedure Plans and Updated Foreign Ownership Control or Influence Package ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML1031904262010-11-0808 November 2010 Corp. - 2010 Annual Report - Guarantees of Payment of Deferred Premiums ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference RS-05-068, Affidavit for Withholding of Global Nuclear Fuel Proprietary Information in Support of Onsite Spent Fuel Storage Expansion2005-05-25025 May 2005 Affidavit for Withholding of Global Nuclear Fuel Proprietary Information in Support of Onsite Spent Fuel Storage Expansion RS-05-019, Reactor Core Shroud Repair Relief Request2005-03-15015 March 2005 Reactor Core Shroud Repair Relief Request RS-03-185, Additional Information Supporting the Request for Amendment to Technical Specifications 3.6.5.1, Drywell, and 5.5.13, Primary Containment Rate Testing Program.2003-09-15015 September 2003 Additional Information Supporting the Request for Amendment to Technical Specifications 3.6.5.1, Drywell, and 5.5.13, Primary Containment Rate Testing Program. RS-02-013, Response to Request for Additional Information Regarding Risk Aspects of Inclined Fuel Transfer System License Amendment Request for Clinton Power Station2002-01-15015 January 2002 Response to Request for Additional Information Regarding Risk Aspects of Inclined Fuel Transfer System License Amendment Request for Clinton Power Station 2023-11-10
[Table view] Category:Letter type:RS
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-067, Constellation Radiological Emergency Plan Addendum and Procedure Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum and Procedure Revision RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022 Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-013, Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval2022-02-0909 February 2022 Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval N RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements 2024-09-09
[Table view] Category:Report
MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting U-604712, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2020-06-24024 June 2020 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18360A4722018-12-14014 December 2018 Attachment 4: Training Material on Diesel Generator Malfunctions ML18360A4712018-12-14014 December 2018 Attachment 3: EC 626319, Battery Coping Time Evaluation to Support Inadvertent Isolation of Div. II Air Start Receiver Valves ML18360A4692018-12-14014 December 2018 Attachment 1: Summary of Exelon Position ML18360A4702018-12-14014 December 2018 Attachment 2: Response to NRC Questions and Documentation Requests ML18360A4852018-12-14014 December 2018 Attachment 17: Inconsistencies Between FLEX SE and Choice Letter Assumptions ML18360A4842018-12-14014 December 2018 Attachment 16: Graph of RPV Water Level ML18360A4832018-12-14014 December 2018 Attachment 15: FLEX and Cross-tie Training Material ML18360A4732018-12-14014 December 2018 Attachment 5: Senior Reactor Operator Surveys ML18360A4742018-12-14014 December 2018 Attachment 6: CPS Shift Manager Surveys Regarding ELAP Scenarios ML18360A4752018-12-14014 December 2018 Attachment 7: Time Validation - Performance of SBO and Starting of Division 2 Diesel Generator ML18360A4822018-12-14014 December 2018 Attachment 14: CPS Procedure 4200.01 C002, DC Load Shedding During a 580, Rev 5a ML18360A4812018-12-14014 December 2018 Attachment 13: Simulator Exercise Guide SE-JIT-42, Loss of AC, Loss of SDC and Lowering RPV Level, Rev 1 ML18360A4802018-12-14014 December 2018 Attachment 12: Time Validation - Performance of Division 3 DG to Division 2 Bus Cross-tie ML18360A4792018-12-14014 December 2018 Attachment 11: Procedures and Training Material on Maintaining RPV Pressure Low ML18360A4782018-12-14014 December 2018 Attachment 10: HEP Evaluation Related to Shutdown Cooling Isolation ML18360A4772018-12-14014 December 2018 Attachment 9: Procedures on Shutdown Cooling Isolation ML18360A4762018-12-14014 December 2018 Attachment 8: 2017 Training Material on Diesel Generator Air Start Flow Plow RS-15-320, Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-0492015-12-14014 December 2015 Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049 RS-15-269, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15062A1152014-12-22022 December 2014 International Atomic Energy Agency (Iaea), Operational Safety Review Team (Osart) Mission to Clinton Report - 11- 28 August 2014 RS-14-312, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-11-0303 November 2014 Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14164A2982014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML13338A6562013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Clinton Power Station, Unit 1, TAC No.: MF0901 IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12340A3492012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-1432012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-142012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 ML12340A3482012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 2023-06-07
[Table view] Category:Technical
MONTHYEARNMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping U-604712, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2020-06-24024 June 2020 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 RS-15-320, Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-0492015-12-14014 December 2015 Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049 RS-14-312, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-11-0303 November 2014 Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML13338A6562013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Clinton Power Station, Unit 1, TAC No.: MF0901 ML12340A3492012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-1432012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-142012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report2012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report ML12340A3482012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 ML12340A3472012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Report RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-144 Through C-2852012-10-0101 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-144 Through C-285 RS-12-082, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2012-05-14014 May 2012 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0636202642006-12-31031 December 2006 Hydraulic Model Study of High Pressure Core Spray Pump Suction to Evaluate the Formation of Air Drawing Vortices and Air Withdrawal ML0636202662006-12-21021 December 2006 Attachment 2, U-603798, Engineering Change Evaluation 363975 Revision 0 U-603798, Attachment 3, U-603798, SA-1578, Revision 3, Significance Determination Process (SDP) Evaluation for CPS HPCS RCIC Storage Tank Suction Vortexing2006-12-21021 December 2006 Attachment 3, U-603798, SA-1578, Revision 3, Significance Determination Process (SDP) Evaluation for CPS HPCS RCIC Storage Tank Suction Vortexing ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier ML0508202832005-03-31031 March 2005 GENE-0000-0023-6259-05NP, Rev 1, Amergen Energy Co, LLC Clinton Power Station BWRVIP-04A Core Shroud Repair Design Submittal to the Nuclear Regulatory Commission (Nrc). ML0508202932005-02-28028 February 2005 GENE-0000-0023-6259-03NP, Rev 2, Amergen Energy Co, LLC Clinton Power Station Non-Core Support Structural Components Assessment. ML0508202982005-02-28028 February 2005 GENE-0000-0023-6259-04NP, Rev 0, Amergen Energy Co., LLC Clinton Power Station Unit 1 Core Shroud Repair GE Input to IOCFR50.59 Evaluation by Cps. ML0423901812004-07-16016 July 2004 Holtec International Report No. HI-2033124 Spent Fuel Storage Expansion at Clinton Power Station. RS-04-024, Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-042004-05-20020 May 2004 Request for Amendment to Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles in Accordance with the Guidance of Generic Letter 91-04 ML0412109162004-04-22022 April 2004 Technical Evaluation of Extending Division 1 and 2 Inverter Completion Time (CT) ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 ML0327216212003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Chapter 6, Response of Soil and Rock to Dynamic and Static Loading ML0327216132003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Table of Contents, Appendix a, Attachment A-4, Stratigraphics Cone Penetrometer Test Report ML0327216152003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Attachment A-5, Geovision Suspension Logging Report ML0327216172003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Attachment A-6, TSC, Laboratory Test Results ML0327216192003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Attachment A-7, Results of Resonant Column/Cyclic Torsional Shear Testing ML0327216202003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix a, Geotechnical Report, Table of Contents Through Figure 5-24 ML0327306082003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Attachment 1, Table of Contents Through Figure B-1-6 ML0327306092003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Attachment 1, Figures B-1-6 Through B-1-11 ML0327306102003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Attachment 1, Figures B-1-12 Through Figure B-2-2 ML0327306122003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Table of Contents Through Figure 2.1-19 ML0327306132003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Appendix B, Seismic Hazards Report, Figures 2.1-20 Through Plate 1 ML0327306142003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Table of Contents Through Figure 2.1-2 ML0327306152003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.1-3 Through 2.4-1 ML0327306162003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.4-2 Through 2.4-11 ML0327306172003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.4-12 Through 2.4-19 ML0327306182003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.4-20 Through 2.5-5 ML0327306192003-09-25025 September 2003 Site Safety Analysis Report for the Exelon Generation Company, LLC Early Site Permit, Figures 2.5-6 Through Chapter 3, Table 3.3-33 RS-03-013, Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program2003-01-29029 January 2003 Request for Amendment to TS 3.6.5.1, Drywell & 5.5.13, Primary Containment Leakage Rate Testing Program 2022-06-30
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Attachment 1 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 1, this cover letter is decontrolled.
RS-14-112 March 27, 2014 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Reports Associated with Results of Post-Irradiation Examination (PIE) of Global Nuclear Fuel (GNF) GE14i Isotope Test Assembly (ITA)
Reference:
Letter from C. S. Goodwin (U. S. NRC) to C. G. Pardee (Exelon Generation Company, LLC), "Clinton Power Station, Unit No.1 -Issuance of Amendment Re: Request to Modify Facility Operating License in Support of the Use of Isotope Test Assemblies (TAC NO. ME1643)," dated January 15,2010 The purpose of this letter is to report the results of portions of the PIE of a GNF GE14i ITA bundle performed by GNF for Facility Operating License No. NPF-62 for Clinton Power Station (CPS). The reporting of this information is specified by Condition 11 of the Conditions and Limitations section of the referenced letter.
This letter provides GNF Report NEDC-33845P, *Clinton EOC14 GE14i (ITA) Fuel Examination October 2013,* Revision 0, dated January 2014, which GNF considers to contain proprietary information. The proprietary information is identified by bracketed text. GNF requests that the proprietary information in Attachment 1 be withheld from public disclosure, in accordance with the requirements of 10 CFR 2.390, "Public inspections, exemptions, requests for withholding,*
paragraph (a)(4). A signed affidavit supporting this request is provided in Attachment 2 to this letter. Attachment 3 to this letter provides a non-proprietary version of the GNF Report (Le.,
NEDO-33845).
Attachment 1 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 1, this cover letter is decontrolled.
March 27, 2014 U. S. Nuclear Regulatory Commission Page 2 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2818.
Attachments:
- 1. NEDC-33845P, "Clinton EOC14 GE14i (ITA) Fuel Examination October 2013," Revision 0, dated January 2014 (Proprietary)
- 2. Global Nuclear Fuel - Americas Affidavit
- 3. NEDO-33845, "Clinton EOC14 GE14i (ITA) Fuel Examination October 2013," Revision 0, dated January 2014 (Non-Proprietary)
Attachment 1 contains proprietary information. Withhold from public disclosure under 10 CFR 2.390. When separated from Attachment 1, this cover letter is decontrolled.
ATTACHMENT 2 Global Nuclear Fuel - Americas Affidavit
Global Nuclear Fuel- Americas AFFIDAVIT I, Russell E. Stachowski, state as foHows:
(1) I am Chief Consulting Engineer, Nuclear Physics, Global Nuclear Fuel Americas, LLC (GNF-A), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in GNF-A proprietary repOlt, NEDC-33845P, Clinton EOC14 GENi (ITA) Fuel Examination October 2013, Revision 0, Januaty 2014. GNF-A proprietary infonnation in NEDC-33845P, Clinton EOC14 GENi (ITA) Fuel Examination October 2013, Revision 0, Januaty 2014 is identified by a dotted underline inside double square brackets. (([ht? ..~~m~m:.~.j~ .. .1m.J~?HP.:np.h~~:=.}J] Figures and large equation objects containing GNF proprietary information are identified with double square brackets before and after the object. In all cases, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the basis for the proprietalY determination.
(3) In making this application for withholding of proprietaty infonnation of which it is the owner or licensee, GNF-A relies upon the exemption £I'om disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the nalTower definition of "trade secret", within the meanings assigned to those tenns for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Proiect v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GNF-A's competitors without license from GNF-A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; C. Infonnation which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;
- d. Infonnation which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
Affidavit for NEDC-33845P Revision 0 Affidavit Page] of 3
(5) To address 10 CFR 2.390 (b) (4), the infOimation sought to be withheld is being submitted to NRC in confidence. The infol111ation is of a sort customarily held in confidence by GNF-A, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is 110t available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the infOimation in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set f011h in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the infonnation in relation to industry knowledge, or subject to the terms under which it was licensed to GNr-A. Access to such documents within GNF-A is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GNF-A are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the infornlation, and then only in accordance with appropriate regulatOl1' provisions or proprieta11' agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains details of GNF-A's fuel design and licensing methodology. The development of this methodology, along with the testing, development and approval, was achieved at a significant cost to GNF-A.
The development of the fuel design and licensing methodology along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GNr -A asset.
(9) Public disclosure of the infOlmation sought to be withheld is likely to cause substantial halm to GNF-A's competitive position and foreclose or reduce the availability of profit-making oPPOItunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to detemline and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical, and hIRC review costs comprise a substantial investment oftime and money by GNF-A.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
Affidavit for NEDC-33845P Revision 0 Affidavit Page 2 of 3
GNF-A's competitive advantage will be lost if its competitors are able to use the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can alTive at the same or similar conclusions.
The value of this information to GNF -A would be lost if the information were disclosed to the public. Making such infonllation available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive Gl\;'F-A of the 0ppoltunity to exercise its competitive advantage to seek an adequate retum on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of peljury that the foregoing affidavit and the matters stated therein are true and COlTect to the best of my knowledge, information, and belief.
Executed on this 9th day ofJanuruy 2014.
Russell E. Stachowski Chief Consulting Engineer, Nuclear Physics Global Nuclear Fuel- Americas, LLC Affidavit for NEDC-33845P Revision 0 Affidavit Page 3 of 3
ATTACHMENT 3 NEDO-33845 "Clinton EOC14 GE14i (ITA) Fuel Examination October 2013" Revision 0, dated January 2014 (Non-Proprietary)
Global Nuclear Fuel Global Nuclear Fuel NEDO-33845 Revision 0 January 2014 Non-Proprietm:v Information - Class I (Public)
Fuel Exam Services Field Test Report Clinton EOC14 GE14i (ITA)
Fuel Examination October 2013 Copyright 2014 Global Nuclear Fuel- Americas. LLC All Rights Reserved
NEDO-33845 Non-Proprietary Information - Class I (Public)
FUEL EXAM SERVICES FIELD TEST REPORT
(
Reference:
PRI 21-01)
TITLE: Clinton EOC14 GE14i (ITA) Fuel Examination DATE: October 2013, Revision 0 Prepared By:
121412013 James Kersey / Site Date Leader Reviewed By:
Approved By:
Services II
NEDO-33845 Non-Proprietary Infomlation Class I (Public)
INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33845P, Revision 0, which has the proprietary information removed, P0l1ions of the document that have been removed are indicated by an open and closed bracket as shown here (( )),
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The only undertakings of Global Nuclear Fuel - Americas, LLC (GNF-A) with respect to infonnation in this document are contained in contracts between GNF-A and its customers, and nothing contained in this document shall be construed as changing those contracts, The use of this information by anyone other than those pal1icipating entities and for any purposes other than those for which it is intended is not authorized; and with respect to any unauthorized use, GNF-A makes no representation or wan'anty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.
This document records technical information status at the date of publication and may not represent final disposition or conclusion related to the rep0l1ed study, Changes in test data, analytical models, and evaluations subsequent to publication of this document may supersede the reported work and verification of applicability should be made before results are used in final design work.
III
NEDO-33845 Non-Proprietary Information - Class I (Public) 1.0 Introduction In accordance with an agreement between Exelon and GNF, an irradiated fuel examination of one GE14i isotope (Co-60) test assembly (ITA) was perfonned during the end of cycle 14 (EOC14) refueling outage in October 20 by GNF.
Clinton is aGE BWRJ6 at which the GNF examination team has performed channel exams, measurements, and replacements during the last few outages. This was the second inadiated fuel examination on a GE14i assembly; the first examination occul1'ed two years ago after one cycle of operation was completed. The visual exam will be used to evaluate the performance of one of the eight GE14i ITA bundles operated in Clinton for Cycles 14 and 13 and to evaluate acceptability for continued irradiation.
2.0 Work Scope and Summary The work scope performed is identified in Table 1. Visual characteristics observed for the bundle are listed in Table 2.
The examination work scope included a bundle visual examination on all four sides of the assembly in the unbrushed condition. Also included was a post-brush two-sided visual examination. The bundle side identification convention reflects the GNF designations of Sides 3 and 4 adjacent to the control blade (CB) with Sides 1 and 2 away from the CB. Sides 1 through 4 advance in a clockwise direction looking down from the top of the bundle.
The following sections will provide detailed visual findings that are noteworthy relative to what is normal (from Table 2). In all cases, the findings are not significantly atypical for irradiated fueL That is, some types of debris (crud flakes or clumps or fiber-like) are not hannful, some spacer movement is acceptable (minor raising or cocking) and some variance in rod-to-rod spacing is acceptable (provided rods are not close to touching). No rod gap variation of 50% or more closure was observed.
3.0 GE14i Isotope (Co-60) Test Assembly - JYK693 Results/Observations The assembly was installed in the fuel prep machine (FPM) and the channel fastener and channel were removed. A bundle peripheral. visual examination of the full length of all four sides was completed. Moderate to heavy crud was seen on the fuel rods; however, the crud deposition was much lighter, as expected, on the Co-60 rods. Two sides of the bundle were then brushed (mid-span between spacers) to remove loose, fluffy crud and enable better characterization of the underlying cladding cOlTosion condition. The brushed sides were re-examined, and showed no unusual cOlTosion or oxide spalling, and virtually no crud spalling. No unusual differential rod lengths or rod bow were observed. The visual examinations con filmed that the fuel bundle/rods and Co-60 rods are performing as designed with no atypical results. The customer was informed that this bundle was fully acceptable for reinsertion during the outage.
NEDO-33845 Non-Proprietary Infonnation - Class I (Public)
The channel and channel fastener were installed and proper torque applied; the assembly was confinned acceptable for continued ilTadiation/operational use. The assembly was retumed to the spent fuel racks and was retumed to the core for continued operation.
Photographs summarizing the visual examination are attached including (elevation infonnation in aU photos is in inches from the bottom (lower tie plate (LTP) top surface) of the bundle):
- Figure 1: JYK693 Bundle Observations (Unbrushed)
- Figure 2: JYK693 Bundle Observations (Brushed Two Sides)
Noteworthy observations for JYK693:
))
4.0 Conclusion The GE14i ITA assembly NK693 is suitable for continued operation. Overall fuel cOlTosion and crud condition and mechanical performance is exce))ent.
5.0 References 5.1 GNP Test Plan and Procedures, "Co-60 Isotope Bundle (GE14i) Fuel Examination & Channel Exchange," Clinton EOC 14, Revision 0, October 2013.
5.2 J. Kersey, Site Exit RepOlt, "Clinton EOC 14 CO-60 Isotope (GE14i) Fuel Exam
& Channel Exchange Site Exit Report," October 16, 2013.
2
NEDO-33845 Non-Proprietary lnfonnation - Class I (Public)
Table 1 - Proposed Examination Plan Comments Bundle Visual (pre- and Brush two sides and post-brushing) re-visual after brush in 3
NEDO-33845 Non-Proprietary InfOimation - Class I (Public)
Table 2 Visual Charactel'istics Obsel'Ved Bundle Periphery*
- Upper tie plate and L TP/component condition
- Expansion spring compression
- Upper and lower end plug weld and heat affected zone appearance
- Peripheral fuel rod and spacer band oxide coverage (if not covered by crud)
- Bar code region corrosion condition where present
- Spacer band weld integrity
- Presence of obvious foreign material (debris)
- Crud deposition characteristics
- Visible rod-to-rod spacing on aU assemblies
- Partial length rod (PLR) upper spacer contact points
- If applicable, debris filter LTP visual exam - for trapped debris and crud buildup
- The side identification convention on the photographs reflects the GE designations of Sides 3 and 4 adjacent to the CB with Sides 1 and 2 away from the CB. Sides 1 through 4 advance in a clockwise direction.
4
NEDO-33845 Non-Proprietary Information - Class I (Public)
Figure 1 - JYK693, GE14i, 40.30 GWdfMTU, Bundle Observations (Unbrushed)
(( ((
)) ))
Side 1,161", UEPs, (( )) @ far right Side 3, 100", (( )) @ far left,
(( )) @ far right
(( ((
)) ))
nd Side 2, 85", Mid-tier in unbrushed condition ((( Side 3, 45", Mid-tier between 2 and spacers, ((
)) @ far left) )) @ far left, (( )) @ far right
(( ((
)) ))
st Side 4, 18", 1 spacer ((( )) @ far left Side 4, 6", Transition area ((( )) @ far left
(( )) @ far right; Segment hex connection just
(( )) @ far right) below Spacer 1) 5
NEDO-33845 Non-Proprietary Infonnation Class I (Public)
Figure 2 - JYK693, GE14i, 40.30 GWd/MTU, Bundle Observations (Brushed)
(( ((
)) ))
th th Side 2, 99", Mid-tier between 5 and 6 spacers ((( Side 4, 100", ((( )))
)) @ far left)
(( ((
)) ))
nd Side 2,44",80-100" oxide on fuel rods ((( Side 4, 45", Mid-tier between 2 and 3rd spacers (((
)) @ far left) )))
(( ((
)) ))
Side 2, 23", ((( )), on left) Side 4, 25" less corrosion on ([ )) @ far left, (( )) @ far right) 6