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MONTHYEARRA-15-091, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-12-0404 December 2015 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Supplement RA-16-034, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.1 Path L: GMRS Less than or Equal to SSE2016-05-25025 May 2016 Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information - NEI 12-06, Appendix H, Revision 2, H.4.1 Path L: GMRS Less than or Equal to SSE Project stage: Other ML16161A4772016-06-16016 June 2016 Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter Project stage: Approval 2016-05-25
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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:Response to Request for Additional Information (RAI)
MONTHYEARML21168A0172021-06-10010 June 2021 E-mail from HDI: RAI Response ML21168A0182021-06-10010 June 2021 E-mail from HDI: RAI Response (Attachment) ML21120A1102021-04-30030 April 2021 Response to Request for Additional Information (RAI) - License Amendment Request to Approve the Oyster Creek Nuclear Generating Station Independent Fuel Storage Installation Only Emergency Plan ML20345A1462020-12-0909 December 2020 E-mail - Response to Request for Additional Information: HDI Request for One-Time Exemption from Part 73, Appendix B FOF Requirements 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 ML19162A2242019-06-11011 June 2019 NRC to NMFS, NRC Responses to NMFS Requests for Additional Information for Oyster Creek ESA Section 7 Consultation 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-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-18-068, 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 RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) 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 ML18011A0872018-01-30030 January 2018 Letter to Senator Cory Booker from Chairman Svinicki Regarding Constituent Questions Regarding the Decommissioning of Oyster Creek Nuclear Generating Station in Lacey Township, New Jersey - Enclosure RA-17-078, Response to Request for Additional Information (RAI) Regarding Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E2017-12-0606 December 2017 Response to Request for Additional Information (RAI) Regarding Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E RA-17-071, Response to Request for Additional Information (RAI) and Supplemental Information Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition2017-11-10010 November 2017 Response to Request for Additional Information (RAI) and Supplemental Information Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition RA-17-056, Response to Request for Additional Information (RAI) and Supplemental Information Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition2017-09-20020 September 2017 Response to Request for Additional Information (RAI) and Supplemental Information Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition RA-17-013, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-04-28028 April 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 RA-16-093, Response to Request for Additional Information and Supplemental Information Regarding Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition2016-11-0202 November 2016 Response to Request for Additional Information and Supplemental Information Regarding Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition 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) RA-16-058, Response to Request for Additional Regarding Approval of Certified Fuel Handler Training Program2016-06-0808 June 2016 Response to Request for Additional Regarding Approval of Certified Fuel Handler Training Program RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure NEI 12-01, Response to March 12, 2012, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency..2016-05-11011 May 2016 Response to March 12, 2012, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency.. RA-16-017, Supplemental Response to Nrg Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2016-04-15015 April 2016 Supplemental Response to Nrg Audit Review Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report RA-16-029, Response to Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate2016-04-0505 April 2016 Response to Request for Additional Information Regarding Preliminary Decommissioning Cost Estimate RA-16-008, Response to Request for Additional Information Regarding Request for Extension to Comply with Phase 2 of NRC Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe..2016-02-15015 February 2016 Response to Request for Additional Information Regarding Request for Extension to Comply with Phase 2 of NRC Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe.. RA-15-091, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-12-0404 December 2015 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RA-15-057, Supplemental Response to Request for Additional Information Regarding Request for Extension to Comply with NRC Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under..2015-10-0101 October 2015 Supplemental Response to Request for Additional Information Regarding Request for Extension to Comply with NRC Order EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under.. 2021-06-10
[Table view] |
Text
Exelon Generation RS-15-290 10 CFR 50.54(f)
RA-15-091 December 4, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, Rockville, MD 20852 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
References:
- 1. NRC Letter, Request for Information Pursuant to Title 1O of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012(ML12053A340)
- 2. NRC Letter, Electric Power Research Institute Report 3002000704, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," As An Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ML13106A331)
- 3. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287), dated November 27, 2012(ML12333A168 and ML12333A170)
- 4. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance", dated February 15, 2013 (ML12319A074)
- 5. Exelon Generation Company, LLC letter to NRC, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10CFR50.54(f)
Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, dated March 31, 2014 (RS-14-070)
- 6. NRC Letter, Screening and Prioritization Results Regarding Information Pursuant to Title 1O of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Re-evaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights from the Fukushima Dai-I chi Accident, dated May 9, 2014 (ML14111A147)
U.S. Nuclear Regulatory Commission Seismic Hazard 2.1 High Frequency Supplement December 4, 2015 Page 2
- 7. NRG Letter, Support Document for Screening and Prioritization Results Regarding Seismic Hazard Re-Evaluation for Operating Reactors in the Central and Eastern United States, dated May 21, 2014 (ML14136A126)
- 8. NEI Letter, Request for NRG Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396),
dated July 30, 2015 (ML15223A100/ML15223A102)
- 9. NRG Letter, September 17, 2015 to NEI: Endorsement of Electric Power Research Institute Final Draft Report 3002004396: "High Frequency Program: Application Guidance for Functional Confirmation and Fragility" (ML15218A569) 1O. NRG Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, dated October 27, 2015 (ML15194A015)
On March 12, 2012, the Nuclear Regulatory Commission (NRG) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 of Reference 1 indicated that licensees should provide a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of the letter for Central and Eastern United States (CEUS) nuclear power plants. By NRG letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.
By letter dated May 9, 2014 (Reference 6), the NRG transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for Oyster Creek Nuclear Generating Station (Reference 5). In accordance with the screening, prioritization, and implementation details report (SPID) (References 3 and 4), and Augmented Approach guidance (Reference 2), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE) High Confidence of Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required to perform a high frequency confirmation evaluation. As noted in the May 9, 2014 letter from the NRG (Reference 6) on page 2 of Enclosure 2, Oyster Creek Nuclear Generating Station is to conduct a limited scope High Frequency Evaluation (Confirmation).
Within the May 9, 2014 letter (Reference 6), the NRG acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 8, the Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396) for NRG review and endorsement. NRG endorsement was provided by Reference 9. Reference 1O provided the NRG final seismic hazard evaluation screening determination results, and the associated schedules for submittal of the remaining seismic hazard evaluation activities. This submittal is provided in accordance with Reference 10, Table 1a, to address the High Frequency Evaluation information request for Oyster Creek Nuclear Generating Station.
U.S. Nuclear Regulatory Commission Seismic Hazard 2.1 High Frequency Supplement December 4, 2015 Page 3 The High Frequency Confirmation for Oyster Creek Nuclear Generating Station, provided in the attachment to this letter, shows that the GMRS exceedance area between the control point GMRS and SSE is "on the order of 10% or less" (Reference 8, Section 3.1.2) over the frequency range of exceedance. As such, the GMRS exceedances are consistent with the criteria identified in Section 3.1.2 of Reference 8. Therefore, no additional evaluation is necessary.
The attachment to this letter provides the SSE and GMRS information from Reference 5.
This transmittal completes the scope of work described in Section 4.2 of Reference 5, for Oyster Creek Nuclear Generating Station.
This letter contains no new regulatory commitments and closes Commitment No. 2 contained in Reference 5 for Oyster Creek Nuclear Generating Station.
If you have any questions regarding this report, please contact Ronald Gaston at 630-657-3359.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 4th day of December 2015.
Respectfully submitted, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Oyster Creek Nuclear Generating Station GMRS and SSE Supporting Information cc: Regional Administrator - NRG Region I NRG Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRG Project Manager, NRR - Oyster Creek Nuclear Generating Station Mr. Nicholas Difrancesco, NRR/JLD/JHMB, NRG
Attachment Oyster Creek Nuclear Generating Station GMRS and SSE Supporting Information (Reference 5)
(2 Pages)
Table 1 - Oyster Creek Nuclear Generating Station SSE and GMRS Data SSE GMRS Freq Acee I Freq AceeI (Hz) (Q) (Hz) (g) 0.5 0.03 0.1 1.84E-02 0.6 0.05 0.125 2.30E-02 0.7 0.06 0.15 2.77E-02 0.8 0.08 0.2 3.69E-02 0.9 0.09 0.25 4.61 E-02 1 0.11 0.3 5.53E-02 1.25 0.15 0.35 6.45E-02 1.5 0.19 0.4 7.38E-02 2 0.27 0.5 9.22E-02 2.5 0.29 0.6 1.15E-01 3 0.36 0.7 1.28E-01 3.5 0.39 0.8 1.44E-01 4 0.41 0.9 1.58E-01 5 0.44 1 1.68E-01 6 0.43 1.25 1.96E-01 7 0.42 1.5 2.20E-01 8 0.39 2 2.56E-01 9 0.37 2.5 2.70E-01 10 0.36 3 2.96E-01 12.5 0.31 3.5 3.12E-01 15 0.26 4 3.20E-01 20 0.22 5 3.28E-01 25 0.20 6 3.11E-01 50 0.18 7 2.97E-01 100/PGA 0.18 8 2.86E-01 9 2.75E-01 10 2.66E-01 12.5 2.48E-01 15 2.35E-01 20 2.25E-01 25 2.22E-01 30 2.13E-01 35 2.06E-01 40 2.01 E-01 50 1.94E-01 60 1.88E-01 70 1.84E-01 80 1.80E-01 90 1.77E-01 100 1.74E-01 Page 1of2
Figure 1 Oyster Creek Nuclear Generating Station GMRS to SSE Comparison
- SSE - GMRS 0.500 0.450 --+- !__ _
0.400 ,-------~'--
0.350 - + - - - - -- I*
~ 0.300 c
-+-------1-~'
0
~ I .__..-.:: ....
~ 0.250 I ,::. ~
a>
a>
~ 0.200 I ff # I .....,, :=t ct 0.150 -~-+-----------
0.100 0.050 L-1-- - - - -
0.000 0.1 1 10 100 Frequency {Hz)
Page 2of2
Exelon Generation RS-15-290 10 CFR 50.54(f)
RA-15-091 December 4, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, Rockville, MD 20852 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
References:
- 1. NRC Letter, Request for Information Pursuant to Title 1O of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012(ML12053A340)
- 2. NRC Letter, Electric Power Research Institute Report 3002000704, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," As An Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ML13106A331)
- 3. NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287), dated November 27, 2012(ML12333A168 and ML12333A170)
- 4. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance", dated February 15, 2013 (ML12319A074)
- 5. Exelon Generation Company, LLC letter to NRC, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10CFR50.54(f)
Regarding Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, dated March 31, 2014 (RS-14-070)
- 6. NRC Letter, Screening and Prioritization Results Regarding Information Pursuant to Title 1O of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Re-evaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights from the Fukushima Dai-I chi Accident, dated May 9, 2014 (ML14111A147)
U.S. Nuclear Regulatory Commission Seismic Hazard 2.1 High Frequency Supplement December 4, 2015 Page 2
- 7. NRG Letter, Support Document for Screening and Prioritization Results Regarding Seismic Hazard Re-Evaluation for Operating Reactors in the Central and Eastern United States, dated May 21, 2014 (ML14136A126)
- 8. NEI Letter, Request for NRG Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396),
dated July 30, 2015 (ML15223A100/ML15223A102)
- 9. NRG Letter, September 17, 2015 to NEI: Endorsement of Electric Power Research Institute Final Draft Report 3002004396: "High Frequency Program: Application Guidance for Functional Confirmation and Fragility" (ML15218A569) 1O. NRG Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, dated October 27, 2015 (ML15194A015)
On March 12, 2012, the Nuclear Regulatory Commission (NRG) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 of Reference 1 indicated that licensees should provide a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of the letter for Central and Eastern United States (CEUS) nuclear power plants. By NRG letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.
By letter dated May 9, 2014 (Reference 6), the NRG transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for Oyster Creek Nuclear Generating Station (Reference 5). In accordance with the screening, prioritization, and implementation details report (SPID) (References 3 and 4), and Augmented Approach guidance (Reference 2), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing safe shutdown earthquake (SSE) or Individual Plant Examination for External Events (IPEEE) High Confidence of Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required to perform a high frequency confirmation evaluation. As noted in the May 9, 2014 letter from the NRG (Reference 6) on page 2 of Enclosure 2, Oyster Creek Nuclear Generating Station is to conduct a limited scope High Frequency Evaluation (Confirmation).
Within the May 9, 2014 letter (Reference 6), the NRG acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 8, the Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396) for NRG review and endorsement. NRG endorsement was provided by Reference 9. Reference 1O provided the NRG final seismic hazard evaluation screening determination results, and the associated schedules for submittal of the remaining seismic hazard evaluation activities. This submittal is provided in accordance with Reference 10, Table 1a, to address the High Frequency Evaluation information request for Oyster Creek Nuclear Generating Station.
U.S. Nuclear Regulatory Commission Seismic Hazard 2.1 High Frequency Supplement December 4, 2015 Page 3 The High Frequency Confirmation for Oyster Creek Nuclear Generating Station, provided in the attachment to this letter, shows that the GMRS exceedance area between the control point GMRS and SSE is "on the order of 10% or less" (Reference 8, Section 3.1.2) over the frequency range of exceedance. As such, the GMRS exceedances are consistent with the criteria identified in Section 3.1.2 of Reference 8. Therefore, no additional evaluation is necessary.
The attachment to this letter provides the SSE and GMRS information from Reference 5.
This transmittal completes the scope of work described in Section 4.2 of Reference 5, for Oyster Creek Nuclear Generating Station.
This letter contains no new regulatory commitments and closes Commitment No. 2 contained in Reference 5 for Oyster Creek Nuclear Generating Station.
If you have any questions regarding this report, please contact Ronald Gaston at 630-657-3359.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 4th day of December 2015.
Respectfully submitted, James Barstow Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Oyster Creek Nuclear Generating Station GMRS and SSE Supporting Information cc: Regional Administrator - NRG Region I NRG Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRG Project Manager, NRR - Oyster Creek Nuclear Generating Station Mr. Nicholas Difrancesco, NRR/JLD/JHMB, NRG
Attachment Oyster Creek Nuclear Generating Station GMRS and SSE Supporting Information (Reference 5)
(2 Pages)
Table 1 - Oyster Creek Nuclear Generating Station SSE and GMRS Data SSE GMRS Freq Acee I Freq AceeI (Hz) (Q) (Hz) (g) 0.5 0.03 0.1 1.84E-02 0.6 0.05 0.125 2.30E-02 0.7 0.06 0.15 2.77E-02 0.8 0.08 0.2 3.69E-02 0.9 0.09 0.25 4.61 E-02 1 0.11 0.3 5.53E-02 1.25 0.15 0.35 6.45E-02 1.5 0.19 0.4 7.38E-02 2 0.27 0.5 9.22E-02 2.5 0.29 0.6 1.15E-01 3 0.36 0.7 1.28E-01 3.5 0.39 0.8 1.44E-01 4 0.41 0.9 1.58E-01 5 0.44 1 1.68E-01 6 0.43 1.25 1.96E-01 7 0.42 1.5 2.20E-01 8 0.39 2 2.56E-01 9 0.37 2.5 2.70E-01 10 0.36 3 2.96E-01 12.5 0.31 3.5 3.12E-01 15 0.26 4 3.20E-01 20 0.22 5 3.28E-01 25 0.20 6 3.11E-01 50 0.18 7 2.97E-01 100/PGA 0.18 8 2.86E-01 9 2.75E-01 10 2.66E-01 12.5 2.48E-01 15 2.35E-01 20 2.25E-01 25 2.22E-01 30 2.13E-01 35 2.06E-01 40 2.01 E-01 50 1.94E-01 60 1.88E-01 70 1.84E-01 80 1.80E-01 90 1.77E-01 100 1.74E-01 Page 1of2
Figure 1 Oyster Creek Nuclear Generating Station GMRS to SSE Comparison
- SSE - GMRS 0.500 0.450 --+- !__ _
0.400 ,-------~'--
0.350 - + - - - - -- I*
~ 0.300 c
-+-------1-~'
0
~ I .__..-.:: ....
~ 0.250 I ,::. ~
a>
a>
~ 0.200 I ff # I .....,, :=t ct 0.150 -~-+-----------
0.100 0.050 L-1-- - - - -
0.000 0.1 1 10 100 Frequency {Hz)
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