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| | issue date = 05/23/2018 | | | issue date = 05/23/2018 |
| | title = 10 CFR 50.46 Annual Report | | | title = 10 CFR 50.46 Annual Report |
| | author name = Helker D P | | | author name = Helker D |
| | author affiliation = Exelon Generation Co, LLC | | | author affiliation = Exelon Generation Co, LLC |
| | addressee name = | | | addressee name = |
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| {{#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 | | {{#Wiki_filter:Exelon Generation,, |
| | RA-18-055 10 CFR 50.46 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 |
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| ==Subject:== | | ==Subject:== |
| 1 O CFR 50.46 Annual Report 10 CFR 50.46
| | 10 CFR 50.46 Annual Report |
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| ==Reference:== | | ==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 10 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 desig 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 ECCS-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 10 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 |
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| | 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 |
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| | 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 |
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| 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.
| | Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Attachment 1 Peak Cladding Temperature Rack-Up Sheet for OCNGS Page 1 of 2 PLANT NAME: Oyster Creek Nuclear Generating Station (OCNGS) |
| Also, no related changes or modifications have occurred at OCNGS that affect the assumptions of the ECCS analyses.
| | ECCS EVALUATION MODEL: SAFER/CORCUPRIME REPORT REVISION DATE: 05/23/2018 CURRENT OPERATING CYCLE: 26 ANALYSIS OF RECORD CALCULATIONS Calculations: |
| 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.
| | : 1. Report 0000-0098-3503-R2, Revision 2, "Oyster Creek Generating Station GNF2 ECCS-LOCA Evaluation," GEH Nuclear Energy, dated November 201 O |
| 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.
| | : 2. Report 002N6964 Rev 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016 Fuel: GNF2 Limiting Fuel Type: GNF2 Limiting Single Failure: ADS Valve Limiting Break Location: Recirculation Discharge Line Limiting Break Size 4.66 ft2 Double-Ended Guillotine (DEG) |
| Respectfully, David P. Helker Manager, Licensing and Regulatory Affairs Exelon Generation Company , LLC May 23, 2018 U.S. Nuclear Regulatory Commission Page 2 Attachments:
| | Reference Peak Cladding Temperature (PCT) for GNF2 Fuel: 2175°F |
| : 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:
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| : 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: | | Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Attachment 1 Peak Cladding Temperature Rack-Up Sheet for OCNGS Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 23, 2017 (Note 1) GNF2: ~PCT= 0°F NET PCT GNF2: 2175°F B. CURRENT LOCA MODEL ASSESSMENTS Notification 2017-01 (Note 2) GNF2: ~PCT= 0°F Notification 2017-02 (Note 2) GNF2: ~PCT= 0°F Total PCT Change from Current Assessments (see note 2) GNF2: I~PCT = 0°F Cumulative PCT Change from Current Assessments GNF2: Il~PCTI = 0°F NET PCT GNF2: 2175°F |
| 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:
| | 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 |
| 0°F GNF2:
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| 0°F GNF2:
| | Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of May 23, 2018 Attachment 2 Assessment Notes, OCNGS Page 1 of 1 |
| = 0°F GNF2: | | : 1. Prior LOCA Model Assessment 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 10CFRS0.46 Report (Reference 2) documents no new notifications as of May 2017. |
| = 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. | | [Reference 1: GNF Report 002N6964 Rev. 0, "Supplemental Reload Licensing Report for Oyster Creek Reload 26 Cycle 26," dated August 2016.] |
| 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 | | [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) 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.}}
| | : 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 type:RA
MONTHYEARRA-19-091, Commitment Change Summary Report - 20192019-12-27027 December 2019 Commitment Change Summary Report - 2019 RA-19-080, Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report2019-10-18018 October 2019 Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report RA-19-076, Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC2019-09-12012 September 2019 Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC RA-19-065, Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-162019-08-28028 August 2019 Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-16 RA-19-052, Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18)2019-06-11011 June 2019 Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18) RA-19-023, Annual Radioactive Effluent Release Report for 20182019-04-30030 April 2019 Annual Radioactive Effluent Release Report for 2018 RA-19-019, Submittal of Changes to Technical Specifications Bases2019-04-12012 April 2019 Submittal of Changes to Technical Specifications Bases RA-19-012, Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-03-0707 March 2019 Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements RA-19-007, Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation)2019-02-13013 February 2019 Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation) RA-19-003, Amendment No. 17 to Indemnity Agreement No. 8-372019-01-0808 January 2019 Amendment No. 17 to Indemnity Agreement No. 8-37 RA-18-103, Annual Sea Turtle Incidental Take Report - 20182018-12-13013 December 2018 Annual Sea Turtle Incidental Take Report - 2018 RA-18-080, License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements2018-11-12012 November 2018 License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements RA-18-098, License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-11-0606 November 2018 License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-097, Exelon Nuclear Radiological Emergency Plan and Addendum Revisions2018-10-24024 October 2018 Exelon Nuclear Radiological Emergency Plan and Addendum Revisions RA-18-092, License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-10-22022 October 2018 License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-093, Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement2018-10-16016 October 2018 Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement RA-18-091, Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses2018-10-0101 October 2018 Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses RA-18-090, Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements2018-10-0101 October 2018 Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements RA-18-083, Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station2018-09-25025 September 2018 Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station RA-18-088, Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek.2018-09-25025 September 2018 Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek. RA-18-087, Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report2018-09-24024 September 2018 Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018 Secondary Containment Capability Test RA-18-078, Submittal of Sea Turtle Incidental Take Report 2018-0042018-08-15015 August 2018 Submittal of Sea Turtle Incidental Take Report 2018-004 RA-18-077, Sea Turtle Incidental Take Report 2018-0032018-08-14014 August 2018 Sea Turtle Incidental Take Report 2018-003 RA-18-072, Pressure and Temperature Limit Report Revision 12018-06-29029 June 2018 Pressure and Temperature Limit Report Revision 1 RA-18-066, Response to Questions Pertaining to Licensed Operator2018-06-18018 June 2018 Response to Questions Pertaining to Licensed Operator RA-18-070, Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 20182018-06-0808 June 2018 Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 2018 RA-18-068, Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station2018-06-0606 June 2018 Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station RA-18-065, Registration of Use of Cask to Store Spent Fuel2018-05-31031 May 2018 Registration of Use of Cask to Store Spent Fuel RA-18-059, Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-05-30030 May 2018 Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events RA-18-055, 10 CFR 50.46 Annual Report2018-05-23023 May 2018 10 CFR 50.46 Annual Report RA-18-053, Update to Spent Fuel Management Plan2018-05-21021 May 2018 Update to Spent Fuel Management Plan RA-18-052, Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ...2018-05-0808 May 2018 Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ... RA-18-049, Registration of Use of Cask to Store Spent Fuel2018-05-0707 May 2018 Registration of Use of Cask to Store Spent Fuel RA-18-046, Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 20172018-04-30030 April 2018 Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 2017 RA-18-047, Annual Radioactive Effluent Release Report for 20172018-04-30030 April 2018 Annual Radioactive Effluent Release Report for 2017 RA-18-018, Submittal of Changes to Technical Specifications Bases2018-04-13013 April 2018 Submittal of Changes to Technical Specifications Bases RA-18-021, Request for Exemption from Record Retention Requirements2018-04-12012 April 2018 Request for Exemption from Record Retention Requirements RA-18-028, Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2018-04-12012 April 2018 Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109) RA-18-027, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2018-04-12012 April 2018 Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-18-036, Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ...2018-03-29029 March 2018 Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ... RA-18-019, Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance2018-03-29029 March 2018 Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance RA-18-020, Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance2018-03-29029 March 2018 Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance RA-18-032, Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2018-03-27027 March 2018 Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues RA-18-034, Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv)2018-03-22022 March 2018 Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) RA-18-015, Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations2018-02-15015 February 2018 Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations RA-18-014, Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-02-13013 February 2018 Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-102018-02-0808 February 2018 Summary of Changes to Quality Assurance Topical Report, NO-AA-10 RA-18-010, Supplement to Relief Request for Extension of Torus Examinations2018-01-24024 January 2018 Supplement to Relief Request for Extension of Torus Examinations RA-17-086, Commitment Change Summary Report - 20172017-12-21021 December 2017 Commitment Change Summary Report - 2017 2019-09-12
[Table view] |
Text
Exelon Generation,,
RA-18-055 10 CFR 50.46 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:
10 CFR 50.46 Annual Report
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 10 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 desig 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 ECCS-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 10 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 Attachment 1 Peak Cladding Temperature Rack-Up Sheet for OCNGS Page 1 of 2 PLANT NAME: Oyster Creek Nuclear Generating Station (OCNGS)
ECCS EVALUATION MODEL: 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 ECCS-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: GNF2 Limiting Fuel Type: GNF2 Limiting Single Failure: ADS Valve Limiting Break Location: Recirculation Discharge Line Limiting Break Size 4.66 ft2 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 Attachment 1 Peak Cladding Temperature Rack-Up Sheet for OCNGS Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May 23, 2017 (Note 1) GNF2: ~PCT= 0°F NET PCT GNF2: 2175°F B. CURRENT LOCA MODEL ASSESSMENTS Notification 2017-01 (Note 2) GNF2: ~PCT= 0°F Notification 2017-02 (Note 2) GNF2: ~PCT= 0°F Total PCT Change from Current Assessments (see note 2) GNF2: I~PCT = 0°F Cumulative PCT Change from Current Assessments GNF2: Il~PCTI = 0°F NET PCT 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 Attachment 2 Assessment Notes, OCNGS Page 1 of 1
- 1. Prior LOCA Model Assessment 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 10CFRS0.46 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.