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| #REDIRECT [[RA-18-055, Oyster Creek Nuclear Generating Station - 10 CFR 50.46 Annual Report]] | | {{Adams |
| | | number = ML18143A397 |
| | | issue date = 05/23/2018 |
| | | title = Oyster Creek Nuclear Generating Station - 10 CFR 50.46 Annual Report |
| | | author name = Helker D P |
| | | author affiliation = Exelon Generation Co, LLC |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NRR |
| | | docket = 05000219 |
| | | license number = DPR-016 |
| | | contact person = |
| | | case reference number = RA-18-055 |
| | | document type = Annual Operating Report, Letter |
| | | page count = 7 |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Exelon Generation,, RA-18-055 May 23, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 |
| | |
| | ==Subject:== |
| | 1 O CFR 50.46 Annual Report 10 CFR 50.46 |
| | |
| | ==Reference:== |
| | |
| | Letter from David P. Helker, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Report," dated May 23, 2017 The purpose of this letter is to transmit the annual 1 O CFR 50.46 reporting information for Oyster Creek Nuclear Generating Station (OCNGS). The previous annual 50.46 report for OCNGS submitted on May 23, 2017 (Reference), provided the cumulative Peak Cladding Temperature (PCT) errors for the most recent fuel de sig ns. Since the referenced annual report was issued, two vendor notifications of Emergency Core Cooling System (ECCS) model errors/changes that are applicable to OCNGS have been issued. These notifications have no impact on the OCNGS LOCA analysis. |
| | Also, no related changes or modifications have occurred at OCNGS that affect the assumptions of the ECCS analyses. |
| | Two attachments are included with this letter that provide the current OCNGS 1 O CFR 50.46 status. Attachment 1, "Peak Cladding Temperature Rack-Up Sheet," provides information regarding the PCT for the limiting Loss of Coolant Accident (LOCA) analysis evaluations for OCNGS. Attachment 2, "Assessment Notes," contains a detailed description for each change or error reported. |
| | There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. David J. Distel at (610} 765-5517. |
| | Respectfully, David P. Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company , LLC May 23, 2018 U.S. Nuclear Regulatory Commission Page 2 Attachments: |
| | : 1) Peak Cladding Temperature Rack-Up Sheet 2) Assessment Notes cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, OCNGS USNRC Senior Project Manager, OCNGS Manager, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ ATTACHMENT 1 10 CFR 50.46 "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors" Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Peak Cladding Temperature Rack-Up Sheet Oyster Creek Nuclear Generating Station Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Peak Cladding Temperature Rack-Up Sheet for OCNGS Attachment 1 Page 1 of 2 PLANT NAME: ECCS EVALUATION MODEL: Oyster Creek Nuclear Generating Station (OCNGS) SAFER/CORCUPRIME REPORT REVISION DATE: 05/23/2018 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD CALCULATIONS Calculations: |
| | : 1. Report 0000-0098-3503-R2, Revision 2, "Oyster Creek Generating Station GNF2 LOCA Evaluation," GEH Nuclear Energy, dated November 201 O 2. Report 002N6964 Rev 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016 Fuel: Limiting Fuel Type: Limiting Single Failure: Limiting Break Location: |
| | Limiting Break Size GNF2 GNF2 ADS Valve Recirculation Discharge Line 4.66 ft 2 Double-Ended Guillotine (DEG) Reference Peak Cladding Temperature (PCT) for GNF2 Fuel: 2175°F Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Peak Cladding Temperature Rack-Up Sheet for OCNGS MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 23, 2017 (Note 1) NET PCT B. CURRENT LOCA MODEL ASSESSMENTS Notification 2017-01 (Note 2) Notification 2017-02 (Note 2) Total PCT Change from Current Assessments (see note 2) Cumulative PCT Change from Current Assessments NET PCT Attachment 1 Page 2 of 2 GNF2: |
| | 0°F GNF2: 2175°F GNF2: |
| | 0°F GNF2: |
| | 0°F GNF2: |
| | = 0°F GNF2: |
| | = 0°F GNF2: 2175°F ATTACHMENT 2 10 CFR 50.46 "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors" Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Assessment Notes Oyster Creek Nuclear Generating Station Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Assessment Notes, OCNGS 1. Prior LOCA Model Assessment Attachment 2 Page 1 of 1 A new LOCA/MAPLHGR analysis for fresh GNF2 fuel was performed for Cycle 26, and restated/confirmed the MAPLHGRs for the existing GNF2 fuel (Reference 1 ). These analyses maintained the licensing basis PCT at 2175°F and superseded all prior LOCA assessments. |
| | This analysis incorporated all ECCS/LOCA methodology errors and changes resolved at that time (as of August 2016). 2017 Annual 1 OCFRS0.46 Report (Reference |
| | : 2) documents no new notifications as of May 2017. [Reference 1: GNF Report 002N6964 Rev. 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016.] [Reference 2: Letter from David P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "1 O CFR 50.46 Annual Report," dated May 23, 2017.] 2. Current LOCA Model Assessment Since the issuance of the previous Annual Report (Reference 2 in Note 1 ), two new error notifications that are applicable to the Oyster Creek LOCA analysis, 2017-01 and 2017-02, were received from the fuel vendor. Notification 2017-01, dated June 12, 2017, addresses an incorrect assumption of lower tie plate leakage with an estimated PCT impact of 0°F for GNF2 fuel. Notification 2017-02, dated August 2, 2017, addresses a change in the fuel rod upper plenum modeling with an estimated PCT impact of 0°F for GNF2 fuel.}} |
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Category:Annual Operating Report
MONTHYEARML22118A5822022-04-28028 April 2022 Annual Radioactive Effluent Release Report for 2021 ML21120A0872021-04-30030 April 2021 Submittal of Annual Radioactive Effluent Release Report for 2020 ML21120A1052021-04-30030 April 2021 Submittal of Annual Radioactive Environmental Operating Report for 2020 RA-18-055, 10 CFR 50.46 Annual Report2018-05-23023 May 2018 10 CFR 50.46 Annual Report RA-18-046, Oyster Creek, Unit 1, Annual Radiological Environmental Operating Report for 20172018-04-30030 April 2018 Oyster Creek, Unit 1, Annual Radiological Environmental Operating Report for 2017 ML18123A3532018-04-30030 April 2018 Annual Radiological Environmental Operating Report for 2017 RA-18-046, Annual Radiological Groundwater Protection Program Report for 20172018-04-30030 April 2018 Annual Radiological Groundwater Protection Program Report for 2017 RA-17-034, Transmittal of 10 CFR 50.46 Annual Report2017-05-23023 May 2017 Transmittal of 10 CFR 50.46 Annual Report RA-16-109, Independent Spent Fuel Storage Installation - Annual Report2016-12-28028 December 2016 Independent Spent Fuel Storage Installation - Annual Report RA-16-048, Transmittal of 10 CFR 50.46 Annual Report2016-05-26026 May 2016 Transmittal of 10 CFR 50.46 Annual Report RA-16-039, Independent Spent Fuel Storage Facility, Submittal of Annual Radioactive Effluent Release Report for 20152016-04-29029 April 2016 Independent Spent Fuel Storage Facility, Submittal of Annual Radioactive Effluent Release Report for 2015 RA-15-101, Independent Spent Fuel Storage Installation (ISFSI) - Transmittal of Annual Report2015-12-0303 December 2015 Independent Spent Fuel Storage Installation (ISFSI) - Transmittal of Annual Report RA-15-040, Submittal of 10 CFR 50.46 Annual Report2015-05-19019 May 2015 Submittal of 10 CFR 50.46 Annual Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report RA-14-110, Independent Spent Fuel Storage Installation, Annual Report for 20142015-01-23023 January 2015 Independent Spent Fuel Storage Installation, Annual Report for 2014 RA-14-064, Independent Spent Fuel Storage Installation Annual Report for 20132014-07-25025 July 2014 Independent Spent Fuel Storage Installation Annual Report for 2013 RA-14-047, CFR 50.46 Annual Report2014-05-20020 May 2014 CFR 50.46 Annual Report RA-14-042, Annual Radiological Groundwater Protection Program Report for 20132014-05-0101 May 2014 Annual Radiological Groundwater Protection Program Report for 2013 RA-14-042, Oyster Creek Nuclear Generating Station - Submittal of Annual Radiological Environmental Operating Report for 20132014-05-0101 May 2014 Oyster Creek Nuclear Generating Station - Submittal of Annual Radiological Environmental Operating Report for 2013 RA-14-042, Oyster Creek Nuclear Generating Station, Unit 1 - Annual Radiological Environmental Operating Report for 20132014-05-0101 May 2014 Oyster Creek Nuclear Generating Station, Unit 1 - Annual Radiological Environmental Operating Report for 2013 ML14126A7832014-05-0101 May 2014 Annual Radiological Environmental Operating Report for 2013 ML14126A7822014-05-0101 May 2014 Submittal of Annual Radiological Environmental Operating Report for 2013 RA-13-056, CFR 50.46 Annual Report2013-05-31031 May 2013 CFR 50.46 Annual Report RA-13-048, Annual Radiological Environmental Operating Report, from January 1 Through December 31, 20122013-04-30030 April 2013 Annual Radiological Environmental Operating Report, from January 1 Through December 31, 2012 RS-13-004, Independent Spent Fuel Storage Installation Annual Report2013-01-10010 January 2013 Independent Spent Fuel Storage Installation Annual Report ML12354A4182012-12-0505 December 2012 Revised Annual Radioactive Effluent Release Report for 2006 ML12354A4192012-12-0505 December 2012 Revised Annual Radioactive Effluent Release Report for 2007 RA-12-004, Revised Annual Radioactive Effluent Release Report for 20082012-12-0505 December 2012 Revised Annual Radioactive Effluent Release Report for 2008 RA-12-004, Oyster Creek, Revised Annual Radioactive Effluent Release Report for 20072012-12-0505 December 2012 Oyster Creek, Revised Annual Radioactive Effluent Release Report for 2007 RA-12-004, Oyster Creek - Revised Annual Radioactive Effluent Release Report for 20062012-12-0505 December 2012 Oyster Creek - Revised Annual Radioactive Effluent Release Report for 2006 RA-12-060, CFR 50.46 Annual Report2012-06-0101 June 2012 CFR 50.46 Annual Report RA-12-055, Independent Spent Fuel Storage Facility - Annual Radioactive Effluent Release Report for 20112012-04-27027 April 2012 Independent Spent Fuel Storage Facility - Annual Radioactive Effluent Release Report for 2011 RA-12-056, Submittal of Annual Radiological Environmental Operating Report for 20112012-04-27027 April 2012 Submittal of Annual Radiological Environmental Operating Report for 2011 RA-11-097, Annual Sea Turtle Incidental Take Report - 20112011-12-21021 December 2011 Annual Sea Turtle Incidental Take Report - 2011 RA-11-003, Annual Radiological Environmental Operating Report, 1 January Through 31 December 20102011-04-30030 April 2011 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2010 ML11130A0662011-04-30030 April 2011 Oyster Creek Nuclear Generating Station - Annual Radiological Environmental Operating Report - 2010 RA-11-003, Oyster Creek Nuclear Generating Station - Annual Radiological Environmental Operating Report - 20102011-04-30030 April 2011 Oyster Creek Nuclear Generating Station - Annual Radiological Environmental Operating Report - 2010 RA-10-083, Independent Spent Fuel Storage Installation - Annual Report2010-11-0101 November 2010 Independent Spent Fuel Storage Installation - Annual Report RA-10-040, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 20092010-09-24024 September 2010 Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 NEI 07-07, Oyster Creek, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 20092010-09-24024 September 2010 Oyster Creek, Submittal of Revised Annual Radiological Groundwater Protection Program Report for 2009 RA-10-002, Oyster Creek, Annual Radioactive Effluent Release Report for 20092010-04-30030 April 2010 Oyster Creek, Annual Radioactive Effluent Release Report for 2009 ML1012411392010-04-30030 April 2010 Oyster Creek, Annual Radioactive Effluent Release Report for 2009 RA-09-081, Independent Spent Fuel Storage Installation Annual Report for November 2008 Through October 20092009-11-19019 November 2009 Independent Spent Fuel Storage Installation Annual Report for November 2008 Through October 2009 RA-09-047, CFR 50.46 Annual Report2009-06-0505 June 2009 CFR 50.46 Annual Report RA-09-038, Annual Radiological Environmental Operating Report, January 1 - December 31, 20082009-04-30030 April 2009 Annual Radiological Environmental Operating Report, January 1 - December 31, 2008 RA-10-002, Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report2008-12-31031 December 2008 Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report ML1012411412008-12-31031 December 2008 Oyster Creek, Revised 2008 Annual Radioactive Effluent Release Report RA-08-099, Independent Spent Fuel Storage Installation - Annual Report2008-10-22022 October 2008 Independent Spent Fuel Storage Installation - Annual Report RA-08-050, 10 CFR 50.46 Annual Report2008-06-0606 June 2008 10 CFR 50.46 Annual Report ML0715806512007-06-0707 June 2007 10 CFR 50.46 Annual Report 2022-04-28
[Table view] Category:Letter
MONTHYEARML23342A1162024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 IR 05000219/20230022023-11-0909 November 2023 EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002 ML23286A1552023-10-13013 October 2023 Defueled Safety Analysis Report (DSAR) ML23249A1212023-09-0606 September 2023 NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076) ML23242A1162023-08-30030 August 2023 Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022 ML23214A2472023-08-22022 August 2023 NRC Inspection Report 05000219/2023002 IR 05000219/20230012023-05-31031 May 2023 NRC Inspection Report No. 05000219/2023001 IR 07200015/20234012023-05-16016 May 2023 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401 ML23114A0912023-04-24024 April 2023 Annual Radioactive Effluent Release Report for 2022 ML23114A0872023-04-24024 April 2023 Annual Radioactive Environmental Operating Report for 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000219/20220022023-02-0909 February 2023 NRC Inspection Report No. 05000219/2022002 ML23031A3012023-02-0808 February 2023 Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System ML23033A5052023-02-0202 February 2023 First Use Notification of NRC Approved Cask RT-100 ML23025A0112023-01-24024 January 2023 LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G ML22347A2732022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 ML22297A1432022-12-15015 December 2022 Part 20 App G Exemption Letter L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 IR 07200015/20224012022-12-0606 December 2022 NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1) ML22280A0762022-11-0202 November 2022 Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22286A1402022-10-13013 October 2022 NRC Confirmatory Order EA-21-041 IR 05000219/20220012022-08-11011 August 2022 NRC Inspection Report 05000219/2022001 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22214A1732022-08-0202 August 2022 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E ML22207B8382022-07-26026 July 2022 NRC Confirmatory Order EA-21-041 ML22130A6882022-05-10010 May 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22118A6122022-04-28028 April 2022 Annual Radioactive Environmental Operating Report for 2021 ML22118A5822022-04-28028 April 2022 Annual Radioactive Effluent Release Report for 2021 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22069A3762022-03-10010 March 2022 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML22032A0582022-03-0808 March 2022 EA-21-139; EA-150: Oyster Creek Nuclear Generating Station - NRC Investigation Report Nos.. 1-2021-002 & 1-2021-014 ML22060A2202022-03-0202 March 2022 NRC Office of Investigations Case No. 1-2021-009 ML22049B2452022-02-19019 February 2022 Late Low Level Radwaste Shipment Report Pursuant to 10 CFR 20 Appendix G IR 05000219/20214022022-01-26026 January 2022 EA-21-041: Confirmatory Order Related to Oyster Greek Nuclear Generating Station - NRC Investigation Report I-2020-007; NRC Inspection Report Nos. 05000219/2021402 & 07200015/2021401 ML22025A3422022-01-25025 January 2022 and Big Rock Point - Changes to Site Organization ML22025A2182022-01-25025 January 2022 Late LLRW Shipments Investigation Report Pursuant to 10 CFR 20, Appendix G ML22021B5512022-01-21021 January 2022 Compensatory Measures Not Implemented Per Site'S Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure L-21-134, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2021-12-17017 December 2021 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations ML21349A5192021-12-15015 December 2021 Commitment Change Summary Report ML21285A1912021-11-30030 November 2021 Nrc'S Analysis of Holtec Decommissioning International'S Decommissioning Funding Status Report for Oyster Creek Nuclear Generating Station and Pilgrim Nuclear Power Station, Docket Nos 50-219 and 50-293 IR 05000219/20210032021-11-16016 November 2021 NRC Inspection Report No. 05000219/2021003 L-21-118, Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades2021-11-0909 November 2021 Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades IR 05000219/20214042021-08-26026 August 2021 NRC Independent Spent Fuel Storage Security Inspection Report No. 07200015/2021402 and Security Decommissioning Inspection Report 05000219/2021404 - (Public) 2024-01-09
[Table view] |
Text
Exelon Generation,, RA-18-055 May 23, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
1 O CFR 50.46 Annual Report 10 CFR 50.46
Reference:
Letter from David P. Helker, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission, "10 CFR 50.46 Annual Report," dated May 23, 2017 The purpose of this letter is to transmit the annual 1 O CFR 50.46 reporting information for Oyster Creek Nuclear Generating Station (OCNGS). The previous annual 50.46 report for OCNGS submitted on May 23, 2017 (Reference), provided the cumulative Peak Cladding Temperature (PCT) errors for the most recent fuel de sig ns. Since the referenced annual report was issued, two vendor notifications of Emergency Core Cooling System (ECCS) model errors/changes that are applicable to OCNGS have been issued. These notifications have no impact on the OCNGS LOCA analysis.
Also, no related changes or modifications have occurred at OCNGS that affect the assumptions of the ECCS analyses.
Two attachments are included with this letter that provide the current OCNGS 1 O CFR 50.46 status. Attachment 1, "Peak Cladding Temperature Rack-Up Sheet," provides information regarding the PCT for the limiting Loss of Coolant Accident (LOCA) analysis evaluations for OCNGS. Attachment 2, "Assessment Notes," contains a detailed description for each change or error reported.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. David J. Distel at (610} 765-5517.
Respectfully, David P. Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company , LLC May 23, 2018 U.S. Nuclear Regulatory Commission Page 2 Attachments:
- 1) Peak Cladding Temperature Rack-Up Sheet 2) Assessment Notes cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, OCNGS USNRC Senior Project Manager, OCNGS Manager, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ ATTACHMENT 1 10 CFR 50.46 "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors" Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Peak Cladding Temperature Rack-Up Sheet Oyster Creek Nuclear Generating Station Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Peak Cladding Temperature Rack-Up Sheet for OCNGS Attachment 1 Page 1 of 2 PLANT NAME: ECCS EVALUATION MODEL: Oyster Creek Nuclear Generating Station (OCNGS) SAFER/CORCUPRIME REPORT REVISION DATE: 05/23/2018 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD CALCULATIONS Calculations:
- 1. Report 0000-0098-3503-R2, Revision 2, "Oyster Creek Generating Station GNF2 LOCA Evaluation," GEH Nuclear Energy, dated November 201 O 2. Report 002N6964 Rev 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016 Fuel: Limiting Fuel Type: Limiting Single Failure: Limiting Break Location:
Limiting Break Size GNF2 GNF2 ADS Valve Recirculation Discharge Line 4.66 ft 2 Double-Ended Guillotine (DEG) Reference Peak Cladding Temperature (PCT) for GNF2 Fuel: 2175°F Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Peak Cladding Temperature Rack-Up Sheet for OCNGS MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 1 O CFR 50.46 Report dated May 23, 2017 (Note 1) NET PCT B. CURRENT LOCA MODEL ASSESSMENTS Notification 2017-01 (Note 2) Notification 2017-02 (Note 2) Total PCT Change from Current Assessments (see note 2) Cumulative PCT Change from Current Assessments NET PCT Attachment 1 Page 2 of 2 GNF2:
0°F GNF2: 2175°F GNF2:
0°F GNF2:
0°F GNF2:
= 0°F GNF2:
= 0°F GNF2: 2175°F ATTACHMENT 2 10 CFR 50.46 "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors" Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Assessment Notes Oyster Creek Nuclear Generating Station Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Assessment Notes, OCNGS 1. Prior LOCA Model Assessment Attachment 2 Page 1 of 1 A new LOCA/MAPLHGR analysis for fresh GNF2 fuel was performed for Cycle 26, and restated/confirmed the MAPLHGRs for the existing GNF2 fuel (Reference 1 ). These analyses maintained the licensing basis PCT at 2175°F and superseded all prior LOCA assessments.
This analysis incorporated all ECCS/LOCA methodology errors and changes resolved at that time (as of August 2016). 2017 Annual 1 OCFRS0.46 Report (Reference
- 2) documents no new notifications as of May 2017. [Reference 1: GNF Report 002N6964 Rev. 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016.] [Reference 2: Letter from David P. Helker (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "1 O CFR 50.46 Annual Report," dated May 23, 2017.] 2. Current LOCA Model Assessment Since the issuance of the previous Annual Report (Reference 2 in Note 1 ), two new error notifications that are applicable to the Oyster Creek LOCA analysis, 2017-01 and 2017-02, were received from the fuel vendor. Notification 2017-01, dated June 12, 2017, addresses an incorrect assumption of lower tie plate leakage with an estimated PCT impact of 0°F for GNF2 fuel. Notification 2017-02, dated August 2, 2017, addresses a change in the fuel rod upper plenum modeling with an estimated PCT impact of 0°F for GNF2 fuel.