|
---|
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
k=-'!~/ Exelon Generation Oyster Creek Nuclear Generating Station Route 9 South PO Box 388 Forked River, NJ 08731 RA-17-086 December 21, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 www.exeloncorp.com Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRG Docket No. 50-219
Subject:
Commitment Change Summary Report -2017 NEI 99-04 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.