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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
[Table view] Category:Status Report
MONTHYEARL-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) 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. 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 RS-17-045, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2017-03-30030 March 2017 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-16-046, Annual Property Insurance Status Report2017-03-29029 March 2017 Annual Property Insurance Status Report RA-16-065, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)2016-08-26026 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049) ML16239A0442016-08-26026 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RS-16-094, Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isl2016-04-25025 April 2016 Property Insurance Status Report for Braidwood Station, Byron Station, Calvert Cliffs, Clinton Power, Dresden Nuclear, LaSalle County, Limerick Generating, Nine Mile Point, Oyster Creek, Peach Bottom, Quad Cities, R.E Ginna, Three Mile Isla RA-16-010, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RA-16-011, Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2016-02-26026 February 2016 Sixth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-15-066, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-15-065, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-08-28028 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RA-15-009, Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-02-27027 February 2015 Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-14-052, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-14-002, Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049)2014-02-28028 February 2014 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (EA-12-049) RS-13-125, First Six-Month Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RA-13-050, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) RA-13-051, First Six-Month Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2013-08-28028 August 2013 First Six-Month Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-13-100, Report on Status of Decommissioning Funding for Reactors2013-04-0101 April 2013 Report on Status of Decommissioning Funding for Reactors RA-13-030, Annual Property Insurance Status Report2013-04-0101 April 2013 Annual Property Insurance Status Report RA-12-032, Annual Property Insurance Status Report2012-03-30030 March 2012 Annual Property Insurance Status Report ML1009200492010-04-0101 April 2010 Annual Property Insurance Status Report ML0919606072009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps (as of 12/18/2008) ML0919606002009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps, Rev. 4, as of 12/02/2008 ML0919606022009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps, Rev. 4, as of 12/02/2008 ML0919606082009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps (as of 12/18/2008) ML0919606052009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps, Rev 4, with Handwritten Notes (as of 12/10/2008) ML0919606032009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps, Rev 4, (as of 12/10/2008), with Handwritten Notes ML0919606012009-06-17017 June 2009 Commitment Inspection Per IP 71003 - App. C Mc 2515, Infrequent Procedures Status and Next Steps, Rev. 4, as of 12/02/2008, with Handwritten Notes ML0909202562009-04-0101 April 2009 Annual Property Insurance Status Report RS-09-041, Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC2009-03-31031 March 2009 Submittal of Exelon Generation Company, LLC, Report on Status of Decommissioning Funding for Reactors Owned by EGC ML0917005242008-12-10010 December 2008 E-mail from R. Conte of USNRC to Various, Regarding Oc Exit Meeting Next Steps ML0634502502006-12-19019 December 2006 November 2006 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 ML0607504022006-02-17017 February 2006 E-mail: Fwd: Status of Oyster Creek LRA Draft RAIs (PD) ML0508703272005-03-25025 March 2005 Annual Property Insurance Status Report RS-05-035, Report on Status of Decommissioning Funding for Reactors2005-03-24024 March 2005 Report on Status of Decommissioning Funding for Reactors ML0713401622003-08-21021 August 2003 Post Strike Monitoring Activities - Updated 8/21/03 ML0713401502003-08-0707 August 2003 Strike Monitoring Activities - Updated 8/07/03 ML0713401492003-07-31031 July 2003 Strike Monitoring Activities - Updated 7/31/03 ML0713401462003-07-25025 July 2003 Strike Monitoring Activities - Updated 7/25/03 ML0726703681978-12-31031 December 1978 Jersey Central Power & Light Company. 1978. Oyster Creek and Forked River Nuclear Generating Stations 316(a) and (B) Demonstration, Seventh Progress Report, June 25, 1971, Through Eighth Progress Report, August 18, 1972 2024-03-29
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1 Exelon Generation Order No. EA-12-049 RS-13-125 RA-13-051 August 28,2013 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:
First Six-Month Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
References:
- 1. NRC Order Number EA-12-049, " Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12,2012
- 2. NRC Interim Staff Guidance JLD-ISG-2012-01, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," Revision 0, dated August 29, 2012
- 3. NEI12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide,"
Revision 0, dated August 2012
- 4. Exelon Generation Company, LLC's Initial Status Report in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated October 25, 2012
- 5. Exelon Generation Company, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), dated February 28, 2013 (RS-13-023)
On March 12, 2012, the Nuclear Regulatory Commission ("NRC" or "Commission") issued an order (Reference 1) to Exelon Generation Company, LLC (EGC). Reference 1 was immediately effective and directs EGC to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities in the event of a beyond-design-basis external event. Specific requirements are outlined in of Reference 1.
U.S. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28,2013 Page 2 Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI12-06, Revision 0 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the EGC initial status report regarding mitigation strategies. Reference 5 provided the Oyster Creek Nuclear Generating Station overall integrated plan.
Reference 1 requires submission of a status report at six-month intervals following submittal of the overall integrated plan. Reference 3 provides direction regarding the content of the status reports. The purpose of this letter is to provide the first six-month status report pursuant to Section IV, Condition C.2, of Reference 1, that delineates progress made in implementing the requirements of Reference 1. The enclosed report provides an update of milestone accomplishments since the last status report, including any changes to the compliance method, schedule, or need for relief and the basis, if any.
The enclosed report, Section 4, describes changes to the method of compliance with NEI 12-06 (Reference 3) that have been made to the Oyster Creek FLEX conceptual designs. These changes are alternatives to NEI 12-06, but still meet the requirements of NRC Order EA-12-049 (Reference 1). The compensatory measures described in Section 4 provide technical justification for the alternative methods of compliance.
This letter contains no new regUlatory commitments. If you have any questions regarding this report, please contact David P. Helker at 610-765-5525.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 28 th day of August 2013.
Respectfully submitted, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosure:
- 1. Oyster Creek Nuclear Generating Station First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 3 cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region I NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Project Manager, NRR - Oyster Creek Nuclear Generating Station Ms. Jessica A. Kratchman, NRR/JLD/PMB, NRC Mr. Robert J. Fretz, Jr, NRRlJLD/PMB, NRC Mr. Robert L. Dennig, NRR/DSS/SCVB, NRC Mr. Eric E. Bowman, NRR/DPRlPGCB, NRC Manager, Bureau of Nuclear Engineering - New Jersey Department of Environmental Protection Mayor of Lacey Township, Forked River, NJ
u.s. Nuclear Regulatory Commission Integrated Plan Report to EA-12-049 August 28, 2013 Page 4 bcc: Site Vice President - Oyster Creek Nuclear Generating Station Vice President Operations Support Plant Manager, Oyster Creek Nuclear Generating Station Site Engineering Director - Oyster Creek Nuclear Generating Station Regulatory Affairs Manager Regulatory Assurance Manager - Oyster Creek Nuclear Generating Station Severe Accident Management Director Site Operations Director - Oyster Creek Nuclear Generating Station Corporate Licensing Manager - East Corporate Licensing Director - East Exelon Records Management Vinod Aggarwal Steven Pierson David Schupp Eric DeMonch
Enclosure Oyster Creek Nuclear Generating Station First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (8 pages)
Enclosure Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 1 Introduction Oyster Creek Nuclear Generating Station developed an Overall Integrated Plan (Reference 1 in Section 8), documenting the diverse and flexible strategies (FLEX), in response to Reference 2. This enclosure provides an update of milestone accomplishments since submittal of the Overall Integrated Plan including any changes to the compliance method, schedule, or need for relief/relaxation and the basis, if any.
2 Milestone Accomplishments None.
3 Milestone Schedule Status The following provides an update to Attachment 2 of the Overall Integrated Plan. It provides the activity status of each item, and whether the expected completion date has changed. The dates are planning dates subject to change as design and implementation details are developed.
The revised milestone target completion dates do not impact the order implementation date.
Milestone Schedule Target Revised Target Activity Completion Activity Status Completion Date Date Submit 60 Day Status Report October 2012 Complete Submit Overall Integrated Plan February 2013 Complete Contract with RRC Complete Submit 6 Month Updates:
Complete with Update 1 August 2013 this submittal Update 2 February 2014 Not Started Update 3 August 2014 Not Started Update 4 February 2015 Not Started Update 5 August 2015 Not Started Update 6 February 2016 Not Started Update 7 August 2016 Not Started Page 1 of 8
Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28, 2013 Target Revised Target Activity Completion Activity Status Completion Date Date Submit Completion Report October 2016 Not Started Modification Development &
Implementation:
Modification Development (All FLEX August 2015 Not Started August 2016 Phases)
Modification Implementation (All FLEX October 2016 Not Started Phases)
Procedures:
Create Site-Specific Procedures October 2016 Not Started Validate Procedures (NEI 12-06, Sect.
October 2016 Not Started 11.4.3)
Create Maintenance Procedures October 2016 Not Started Perform Staffing Analysis June 2016 Not Started Storage Plan and Construction October 2016 Not Started FLEX Equipment Acquisition October 2016 Started Training Completion October 2016 Not Started Regional Response Center Operational December 2015 Started December 2014 Unit 1 FLEX Implementation October 2016 Not Started Full Site FLEX Implementation October 2016 Not Started 4 Changes to Compliance Method The following changes to the method of compliance with NEI 12-06 (Reference 3) have been made to the Oyster Creek FLEX conceptual designs. These changes are alternatives to NEI 12-06 but still meet the requirements of NRC Order EA 049 (Reference 2). The compensatory measures described below provide technical justification for the alternative methods of compliance.
- 1. NEI 12-06, Section 5.3.2 Deployment of FLEX Equipment Requirement: At least one connection point of FLEX equipment will only require access through seismically robust structures.
Change to compliance method:
Access to the Oyster Creek Reactor Building used for the strategies is not a robust structure.
Page 2 of 8
Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28,2013 Compensatory measure(s) implemented:
In the event of a seismic event, an alternate access path will be used. This path will be pre-identified in the implementing strategies. To satisfy the deployment in a seismic event Oyster Creek will utilize an alternate routing path for the hoses and cables. This path would be through the northwest door of the turbine building north mezzanine, through the hallway past the lower cable spreading room, and down the stairs to the northwest airlock to the manifold. The time to complete the routing will not significantly affect the time of deployment. This path will be validated once the strategies have been finalized.
- 2. Section 8.3.1 Protection of FLEX Equipment Requirement: These considerations apply to the protection of FLEX equipment from snow, ice, and extreme cold hazards:
- 1. For sites subject to significant snowfall and ice storms, portable FLEX equipment should be stored in one of two configurations:
- a. In a structure that meets the plant's design basis for the snow, ice and cold conditions (e.g., existing safety-related structure).
- b. In a structure designed to or evaluated equivalent to ASCE 7-10, Minimum Design Loads for Buildings and Other Structures for the snow, ice, and cold conditions from the site's design basis
- c. Provided the N FLEX equipment is located as described in a. or b. above, the N+ 1 equipment may be stored in an evaluated storage location capable of withstanding historical extreme weather conditions and the equipment is deployable
- 2. Storage of FLEX equipment should account for the fact that the equipment will need to function in a timely manner. The equipment should be maintained at a temperature within a range to ensure its likely function when called upon. For example, by storage in a heated enclosure or by direct heating (e.g., jacket water, battery, engine block heater, etc.).
Change to compliance method:
Oyster Creek will store FLEX portable equipment outside. The equipment will have block heaters installed.
Compensatory measure(s):
The Oyster Creek severe weather procedure will be revised to require moving the FLEX portable equipment from the outside storage location to the inside truck bays (6) during periods of predicted snow fall, ice, or extreme cold to protect the equipment from these hazards.
5 Need for ReliefIRelaxation and Basis for the ReliefIRelaxation Oyster Creek expects to comply with the order implementation date and no relieflrelaxation is required at this time.
Page 3 of8
Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28, 2013 6 Open Items from Overall Integrated Plan and Draft Safety Evaluation The following tables provide a summary of the open items documented in the Overall Integrated Plan or the Draft Safety Evaluation (SE) and the status of each item.
Section Reference Overall Integrated Plan Open Item Status Sequence of events (p. 10-12) The times to complete actions in the Not Started Events Timeline are based on operating judgment, conceptual designs, and current supporting analyses. The final timeline will be time validated once detailed designs are completed and procedures developed.
Sequence of events (p. 11-12) Initial evaluations were used to Not Started determine the fuel pool timelines.
Formal calculations will be performed to validate this information during development of the spent fuel pool cooling strategy detailed design.
Identify how strategies will be Transportation routes will be developed Not Started deployed in all modes (p. 13) from the equipment storage area to the FLEX staging areas. An administrative program will be developed to ensure pathways remain clear or compensatory actions will be implemented to ensure all strategies can be deployed during all modes of operation.
Identification of storage areas and creation of the administrative program are open items.
Identify how the programmatic An administrative program for FLEX to Not Started controls will be met (p. 14) establish responsibilities, and testing &
maintenance requirements will be implemented.
Maintain Spent Fuel Pool Complete an evaluation of the spent fuel Not Started Cooling (p.36) pool area for steam and condensation.
Safety Functions Support (p. 44) Evaluate the habitability conditions for Not started the Main Control Room and develop a strategy to maintain habitability.
Safety Functions Support (p. 44) Develop a procedure to prop open Not Started Page 4 of 8
Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28, 2013 battery room doors upon energizing the battery chargers to prevent a buildup of hydrogen in the battery rooms.
Sequence of events (p. 10) Issuance of BWROG document NEDC- Completed. Attached to 33771P, "GEH Evaluation of FLEX this 6-month update Implementation Guidelines" on (Attachment 1) 01/31/2013 did not allow sufficient time to perform the analysis of the deviations between Exelon's engineering analyses and the analyses contained in the BWROG document prior to commencing regulatory reviews of the Integrated Plan. This analysis is expected to be completed, documented on Attachment lB, and provided to the NRC in the August 2013 six month status update.
Draft Safety Evaluation Open Item Status NIA NIA 7 Potential Draft Safety Evaluation Impacts There are no potential impacts to the Draft Safety Evaluation identified at this time.
8 References The following references support the updates to the Overall Integrated Plan described in this enclosure.
- 1. Oyster Creek's Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)," dated February 28, 2013.
- 2. NRC Order Number EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," dated March 12,2012.
- 3. NEI 12-06, Rev. 0, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated August 2012.
- 4. NEDC-33771P, GEH Evaluation of FLEX Implementation Guidelines, Rev. 1, January 2013.
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Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28, 2013 9 Attachments
- 1. NSSS Significant Reference Analysis Deviation Table (Attachment 1B of Overall Integrated Plan)
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Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28, 2013 Attachment 1 NSSS Significant Reference Analysis Deviation Table (Attachment IB of Overall Integrated Plan)
NEDC-33771 NEDC-33771P P Design Item Parameter of Interest Rev 2 Value Page Plant Applied Value Value Gap and Discussion NEDC-33771P Rev 1 Section 4.5.1.1 (BWR/2/3. Mark I and EC System Assumptions) and Table 4.5.2-1 Appendix A are closest to the Oyster Creek Nuclear Generating Station and associated response. Differences between the GEH SHEX case and the MAAP analysis of the Oyster Creek strategy are listed below.
Input Parameter Values 1 Core thermal power Proprietary 15 1930 MWT NA The GEH model BWR 2/3 Mark I information. reference plant has lower core thermal Refer to report power rating.
for value.
2 Primary System Leakage Proprietary 15 35gpm NA The reference plant has a higher leak information. rate. The leak rate for Oyster Creek was Refer to report calculated using the Recirculation pump for value. seal vendor input and worst case unidentified leakage.
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Oyster Creek Nuclear Generating Station First Six Month Status Report for the Implementation of FLEX August 28, 2013 NEDC-33771 NEDC-33771P P Design Item Parameter of Interest Rev 2 Value Page Plant Applied Value Value Gap and Discussion 3 Emergency Condenser capacity Proprietary 15 (2.05xl08 Btu/hr)x2 4.1xl08 Two Emergency condensers provide a information. Oyster Creek has Btu/hr heat removal capability of 4.1xl08 Refer to report two Emergency Btu/hr which is more than what was used for value. condensers in the referenced plant (accounts for higher thermal power).
4 Wetwell Free Volume Proprietary 16 122,400fe NA The differences in reference plant information. structural design and minor differences in Refer to report assumed parameter values at time zero for value. should have a negligible effect on the I progression of the event after a few hours.
5 EC actuation pressure Proprietary 16 1051 psig EC actuation pressure for Oyster Creek is information. at a lower pressure than the referenced Refer to report plant. ECs will initiate at a lower reactor for value pressure to limit the reactor pressure on the RPV isolation.
6 Suppression pool volume and initial Proprietary 16 87,000 cubic feet at The differences in reference plant temperature information. 90.2 degrees (F) structural design and minor differences in Refer to report assumed parameter values at time zero for value should have a negligible effect on the progression of the event after a few hours.
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