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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
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Text
AmerGen Energy Company, LLC www.exeloncorp.com Amerftn An Exelon Company 2oo Exelon Way Kennett Square, PA 19348 10 CFR 50.46 June 6, 2008 RA-08-050 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
10 CFR 50.46 Annual Report
Reference:
- 1) Letter from David P. Helker (AmerGen Energy Company, LLC) to U.S.
Nuclear Regulatory Commission, "10 CFR 50.46 Annual Report," dated June 7, 2007 The purpose of this letter is to transmit the 10 CFR 50.46 reporting information for Oyst'er Creek Nuclear Generating Station (OCNGS). The previous 50.46 report for OCNGS (Reference 1) provided the cumulative Peak Cladding Temperature (PCT) errors for the most recent fuel designs through May 18, 2007.
Since the referenced annual report was issued, no vendor notifications of Emergency Core Cooling System (ECCS) model error/changes that are applicable to OCNGS have been issued. 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 Large Break 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 commitments contained in this letter. If you have any questions, please contact Tom Loomis at 610-765-5510.
Very truly yours, David P. Helker Manager - Licensing
U.S. Nuclear Regulatory Commission June 6,. 2008 Page 2 Attachments: 1) Peak Cladding Temperature Rack-Up Sheet
- 2) Assessment Notes cc: S. J. Collins, USNRC Administrator, Region I G. E. Miller, USNRC Project Manager, OCNGS M. S. Ferdas, USNRC Senior Resident Inspector, OCNGS
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 June 5, 2008 Peak Cladding Temperature Rack-Up Sheet Oyster Creek Nuclear Generating Station
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of June 5, 2008 Attachment 1 Peak Cladding Temperature Rack-Up Sheet, OCNGS Page 1 of 2 PLANT NAME: Oyster Creek ECCS EVALUATION MODEL: SAFER/CORCL/GESTR-LOCA REPORT REVISION DATE: 06/05/08 CURRENT OPERATING CYCLE: 21 ANALYSIS OF RECORD Evaluation Model:
- 1. NEDC-23785-1-PA Rev. 1, 'The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-Of-Coolant Accident Volume 11,SAFER - Long Term Inventory Model for BWR Loss-Of-Coolant Analysis," October 1984.
- 2. NEDC-30996P-A, "SAFER Model for Evaluation of Loss-of-Coolant Accidents for Jet Pump and Non-jet Pump Plants, Volume I, SAFER - Long Term Inventory Model for BWR Loss-of-Coolant Analysis," October 1987.
- 3. NEDC-32950P, "Compilation of Improvements to GENE's SAFER ECCS-LOCA Evaluation Model," January 2000. (Application Methodology Description)
- 4. NEDC-30996P-A, "SAFER Model for Evaluation of Loss-of-Coolant Accidents for Jet Pump and Non-jet Pump Plants, Volume II, SAFER Application Methodology for Non-jet Pump Plants," October 1987. (Non-jet Pump Plant - SAFER/CORCL)
Calculations:
- 1. GE-NE-0000-0001-7486-01P, "Oyster Creek Generating Station Loss-of-Coolant Accident Evaluation for GEl 1," GE Nuclear Energy, dated July 2002.
- 2. GE-NE-0000-0006-3699-01 P-R1, "ECCS-LOCA Evaluation for Oyster Creek with Improved GE9 LHGR Limits," GE Nuclear Energy, dated September 2002.
Fuel: GE9, GE11 Limiting Fuel Type: GE9/GE1 1 (same)
Limiting Single Failure: ADS Valve Limiting Break Size and Location: 4.66 ft2 Double-Ended Guillotine (DEG) in a Recirculation Discharge Pipe Reference Peak Cladding Temperature (PCT) PCT = 2150'F
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of June 5, 2008 Attachment 1 Peak Cladding Temperature Rack-Up Sheet, OCNGS Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS New LOCA analyses were performed for both GE9 and APCT = 0°F GEl 1 fuel in support of operating cycle 19 (See Note 1)
WEVOL Code Error (See Note 2) APCT = 0°F Hydrogen-Oxygen Recombination (See Note 3) APCT = +25°F CORCL Boundary Conditions (See Note 4) APCT = 0°F Hydrogen-Oxygen Recombination (See Note 5) APCT = -25°F 2007 Annual Report (See Note 6) APCT = 0°F NET PCT (GE9) 2150°F NET PCT (GEl1) 2150°F B. CURRENT LOCA MODEL ASSESSMENTS None (see Note 7) APCT = 0°F Total PCT Change from Current Assessments Y-APCT = 0°F Cumulative PCT Change from Current Assessments YZ1APCT 1= 0°F NET PCT (GE9) 2150°F NET PCT (GEl1) 2150°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 Assessment Notes Oyster Creek Nuclear Generating Station
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of June 5, 2008 Attachment 2 Assessment Notes, OCNGS Page 1 of 2
- 1. Prior LOCA Assessment New LOCA analyses-were performed for both GE9 and GEl 1 fuel in support of operating cycle
- 19. These analyses supersede all prior LOCA assessments. These analyses incorporate all errors and changes known at that time (as of July 2002).
[
Reference:
GE-NE-0000-0006-3699-01 P-R1, "ECCS-LOCA Evaluation for Oyster Creek with Improved GE9 LHGR Limits," GE Nuclear Energy, dated September 2002.]
[
Reference:
GE-NE-0000-0001-7486-01 P, "Oyster Creek Generating Station Loss-of-Coolant Accident Evaluation for GEl 1," GE Nuclear Energy, dated July 2002.]
From August 2002 until May 2004, GE notified Exelon of two errors applicable to Oyster Creek, identified below (Notes 2 and 3).
The annual 50.46 Report for Oyster Creek erroneously reported no update to the LOCA model assessment for GE9 fuel and correctly reported the new LOCA analysis for the introduction of GEl 1 fuel. A Peak Clad Temperature of 2183°F was erroneously reported for GE9 fuel (correct value was 2150)F).
[
Reference:
Letter from Michael P. Gallagher (AmerGen) to U.S. NRC, "10 CFR 50.46 Reporting Requirements," 2130-02-20349, dated December 18, 2002.]
- 2. Prior LOCA Assessment GE reported that an error was found in the WEVOL code, which affects the calculated vessel volume in the downcomer region. The free volume in the region of the shroud head is calculated incorrectly, resulting in the calculated value to be underpredicted by 4 - 10 ft3.
[
Reference:
GE Letter, "10 CFR 50.46 Notification Letter," 2002-05, August 26, 2002.]
- 3. Prior LOCA Assessment GE reported that a new heat source term has been postulated. This heat source involves the recombination of hydrogen and oxygen within the fuel bundle during the core heatup. The additional heat will raise the temperature of the steam heat sink in the bundle, resulting in a potential increase in the peak cladding temperature and local oxidation. This recombination is spontaneous at temperatures above approximately 900 0 F. The hydrogen is generated by the steam-zirconium reaction during heatup. The oxygen enters the vessel either as a dissolved gas in the ECCS water or through the break when the vessel fully depressurizes and draws the containment non-condensable gases back into the vessel. The current LOCA evaluation models do not include this new heat source. Pending disposition of this phenomenon, a change notification was supplied to provide the impact of hydrogen-oxygen recombination on the cladding temperature and local oxidation.
[
Reference:
GE Letter, "10 CFR 50.46 Notification Letter," 2003-05, May 13, 2004.]
Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Assessments as of June 5, 2008 Attachment 2 Assessment Notes, OCNGS Page 2 of 2
- 4. Prior LOCA Assessment GE reported that the representative exposure point at which the 'long duration' SAFER run is performed to provide the boundary conditions for the CORCL evaluations may not be bounding and can have a non-conservative effect on the CORCL results. 'Short duration' SAFER runs are performed at each analyzed exposure point to provide the fuel bundle initial conditions.
Long duration SAFER runs were performed for each analyzed exposure point. The PCT impact for the reported condition was determined to be 0°F for GE9 and GEl 1 fuel.
[
Reference:
GE Letter, "10 CFR 50.46 Notification Letter," 2005-01, April 01, 2005.]
- 5. Prior LOCA Assessment In item 3 above, GE reported that a new heat source term has been postulated. This heat source involves the recombination of hydrogen and oxygen within the fuel bundle during the core heatup. GE has performed a detailed evaluation of this phenomenon and has determined that there is sufficient conservatism in the Appendix K analysis which bounds the Upper Bound PCT and Oxidation with hydrogen-oxygen recombination in both PCT limited and oxidation limited exposure ranges. Therefore, the current SAFER/CORCL application methodology for conformance of the Appendix K analysis 10 CFR50.46 limits remains applicable. The hydrogen-oxygen recombination phenomenon does not need to be considered in the Appendix K analysis.
[
References:
GE Letter, "10 CFR 50.46 Notification Letter," 2003-05, Rev. 2, April 27, 2006 and AmerGen Letter 2130-06-20347, David P. Helker to U.S. NRC, "10 CFR 50.46 Annual Report,"
dated June 8, 2006.]
- 6. Prior LOCA Assessment The reference letter documented that no ECCS model errors/changes were reported since the prior Oyster Creek annual report was issued.
[
Reference:
Letter from David P. Helker to U.S. NRC, 2130-07-20499, "10 CFR 50.46 Annual Report," dated June 07, 2007.]
- 7. Current LOCA Assessment Since the last annual report (see Note 6), no vendor notifications of Emergency Core Cooling System (ECCS) model error/changes that are applicable to Oyster Creek have been issued.
Also, no ECCS-related changes or modifications have occurred at Oyster Creek that affect the assumptions of the ECCS analyses.