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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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k=-'!~/ Exelon Generation Oyster Creek Nuclear Generating Station www.exeloncorp.com Route 9 South PO Box 388 Forked River, NJ 08731 NEI 99-04 RA-17-086 December 21, 2017 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 NRG Docket No. 50-219
Subject:
Commitment Change Summary Report - 2017 Enclosed is the Oyster Creek Nuclear Generating Station Commitment Change Summary Report for regulatory commitments during calendar year 2017. This report is being submitted in accordance with the guidance provided by NEI 99-04.
Please contact Tom Powell at (609) 971-2279 if any further information or assistance is needed.
Sincerely, Timothy Moore Vice President Oyster Creek Nuclear Generating Station Attachment - Summary of Commitment Changes cc: Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek
Attachment Summary of Commitment Changes Docket No. 50-219 Page 1 of 2 Attachment Summary of Commitment Changes The following U.S. Nuclear Regulatory Commission (NRG) commitments tracked in the Oyster Creek Nuclear Generating Station (OCNGS) commitment-tracking database were changed during the calendar year 2017. These changes were evaluated in accordance with Exelon Generation Company, LLC (Exelon) Procedure LS-AA-110, Commitment Management, and determined to require NRG notification in this Commitment Change Summary Report, consistent with the guidance provided in NEI 99-04, "Guidelines for Managing NRG Commitments".
16-001: Backup Pressure Regulator Original Commitment and Revised Commitment - If one of .the two regulators become inoperable while operating between 25% and 90%, the pressure regulator will be repaired or power will be increased to above 90% power within the next two hours. The previous restrictions on operation between 25% and 90% are NOT required IF a specific analysis is performed for operation in this region.
Justification - In 2000 OCNGS submitted Licensee Event Report (LER) 2002-002-02, "Unanalyzed Condition with Backup Pressure Regulator Inoperable Between 25% and 90 %
Power". This LER stated that OCNGS was not analyzed to operate with one pressure regulator between 25% and 90%. As part of the corrective actions OCNGS committed to operate, above 90% power or below 25% Core Thermal Power, for no longer than 30 days with one pressure regulator out of service.
In 2005, General Electric (GE) performed an evaluation, (GE-NE-0000-0043-3118 RO), in which they determined that if the station experienced a pressure regulator failure while having only one in service OCNGS will still be bounded by other transient event analysis and there will be no impact to fuel operating limits. This analysis was incorporated into the Updated Final Safety Analysis Report (UFSAR), Section 15.2.1 in 2005.
After this analysis was performed, it was incorporated into the UFSAR therefore the conditions for which the commitment was made in LER 2002-002-02 no longer exist and the commitment is no longer needed.
17-001: Vendor Interface Original Commitment and Revised Commitment - This change refers to commitments made in response to both NRG Generic Letters (Gls) 83-28 and 90-03. Exelon will discontinue the program of periodic contact with the vendors of other (non- Nuclear Steam System Supplier (NSSS)) key safety-related components. The program with the NSSS vendor which covers all the safety-related components within the NSSS scope of supply will not be affected.
Justification - The periodic re-contact of vendors is redundant. The reliability of safety related components at OCNGS is assured by preventive maintenance and performance monitoring actions implemented after the commitments made in response to these two NRG Gls. The preventive maintenance tasks, frequencies, and detailed actions are subject to continuous improvement and monitoring for effectiveness.
Attachment Summary of Commitment Changes Docket No. 50-219 Page 1 of 2 17-002: Vital AC Power 96-Hour to 7-Day Limit Original Commitment and Revised Commitment - This change refers to commitments made in response to NRC GL 91-11. Station procedure revisions were made that imposed a 96-hour time limit restriction for vital AC power panels redundancy. The bases for this limit was that it provided a - "reasonable amount of time" - to make repairs and assure minimal exposure risks described in GL-91-11.
OCNGS revised the affected procedures to change the 96-hour limitation to a 7-day limitation to be consistent with the Technical Specifications {TS) as applied to other safety related AC electrical power panels.
Justification - The 96-hour restriction was arbitrarily chosen since there is no restriction applied to vital AC power panels in the TS. To allow for repairs to vital AC power supplies and return redundancy to vital AC power systems, a repair window of 96-hours may be too restrictive to facilitate adequate repairs and return redundancy to these systems. Additionally, the 7-day time restriction is consistent with the TS for minimizing exposure risks identified in GL-91-11.
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k=-'!~/ Exelon Generation Oyster Creek Nuclear Generating Station www.exeloncorp.com Route 9 South PO Box 388 Forked River, NJ 08731 NEI 99-04 RA-17-086 December 21, 2017 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 NRG Docket No. 50-219
Subject:
Commitment Change Summary Report - 2017 Enclosed is the Oyster Creek Nuclear Generating Station Commitment Change Summary Report for regulatory commitments during calendar year 2017. This report is being submitted in accordance with the guidance provided by NEI 99-04.
Please contact Tom Powell at (609) 971-2279 if any further information or assistance is needed.
Sincerely, Timothy Moore Vice President Oyster Creek Nuclear Generating Station Attachment - Summary of Commitment Changes cc: Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek
Attachment Summary of Commitment Changes Docket No. 50-219 Page 1 of 2 Attachment Summary of Commitment Changes The following U.S. Nuclear Regulatory Commission (NRG) commitments tracked in the Oyster Creek Nuclear Generating Station (OCNGS) commitment-tracking database were changed during the calendar year 2017. These changes were evaluated in accordance with Exelon Generation Company, LLC (Exelon) Procedure LS-AA-110, Commitment Management, and determined to require NRG notification in this Commitment Change Summary Report, consistent with the guidance provided in NEI 99-04, "Guidelines for Managing NRG Commitments".
16-001: Backup Pressure Regulator Original Commitment and Revised Commitment - If one of .the two regulators become inoperable while operating between 25% and 90%, the pressure regulator will be repaired or power will be increased to above 90% power within the next two hours. The previous restrictions on operation between 25% and 90% are NOT required IF a specific analysis is performed for operation in this region.
Justification - In 2000 OCNGS submitted Licensee Event Report (LER) 2002-002-02, "Unanalyzed Condition with Backup Pressure Regulator Inoperable Between 25% and 90 %
Power". This LER stated that OCNGS was not analyzed to operate with one pressure regulator between 25% and 90%. As part of the corrective actions OCNGS committed to operate, above 90% power or below 25% Core Thermal Power, for no longer than 30 days with one pressure regulator out of service.
In 2005, General Electric (GE) performed an evaluation, (GE-NE-0000-0043-3118 RO), in which they determined that if the station experienced a pressure regulator failure while having only one in service OCNGS will still be bounded by other transient event analysis and there will be no impact to fuel operating limits. This analysis was incorporated into the Updated Final Safety Analysis Report (UFSAR), Section 15.2.1 in 2005.
After this analysis was performed, it was incorporated into the UFSAR therefore the conditions for which the commitment was made in LER 2002-002-02 no longer exist and the commitment is no longer needed.
17-001: Vendor Interface Original Commitment and Revised Commitment - This change refers to commitments made in response to both NRG Generic Letters (Gls) 83-28 and 90-03. Exelon will discontinue the program of periodic contact with the vendors of other (non- Nuclear Steam System Supplier (NSSS)) key safety-related components. The program with the NSSS vendor which covers all the safety-related components within the NSSS scope of supply will not be affected.
Justification - The periodic re-contact of vendors is redundant. The reliability of safety related components at OCNGS is assured by preventive maintenance and performance monitoring actions implemented after the commitments made in response to these two NRG Gls. The preventive maintenance tasks, frequencies, and detailed actions are subject to continuous improvement and monitoring for effectiveness.
Attachment Summary of Commitment Changes Docket No. 50-219 Page 1 of 2 17-002: Vital AC Power 96-Hour to 7-Day Limit Original Commitment and Revised Commitment - This change refers to commitments made in response to NRC GL 91-11. Station procedure revisions were made that imposed a 96-hour time limit restriction for vital AC power panels redundancy. The bases for this limit was that it provided a - "reasonable amount of time" - to make repairs and assure minimal exposure risks described in GL-91-11.
OCNGS revised the affected procedures to change the 96-hour limitation to a 7-day limitation to be consistent with the Technical Specifications {TS) as applied to other safety related AC electrical power panels.
Justification - The 96-hour restriction was arbitrarily chosen since there is no restriction applied to vital AC power panels in the TS. To allow for repairs to vital AC power supplies and return redundancy to vital AC power systems, a repair window of 96-hours may be too restrictive to facilitate adequate repairs and return redundancy to these systems. Additionally, the 7-day time restriction is consistent with the TS for minimizing exposure risks identified in GL-91-11.