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| | number = ML16161A477 | | | number = ML16161A477 |
| | issue date = 06/16/2016 | | | issue date = 06/16/2016 |
| | title = Oyster Creek Nuclear Generating Station - 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 | | | title = 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 |
| | author name = Vega F G | | | author name = Vega F |
| | author affiliation = NRC/NRR/JLD | | | author affiliation = NRC/NRR/JLD |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000219 | | | docket = 05000219 |
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| | page count = 4 | | | page count = 4 |
| | project = CAC:MF7766 | | | project = CAC:MF7766 |
| | stage = Other | | | stage = Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 June 16, 2016 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C . 20555-0001 June 16, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville , IL 60555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| OYSTER CREEK NUCLEAR GENERATING STATION -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 (CAC NO. MF7766) | | OYSTER CREEK NUCLEAR GENERATING STATION - 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 (CAC NO. MF7766) |
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| ==Dear Mr. Hanson:== | | ==Dear Mr. Hanson:== |
| The purpose of this letter is to provide the U.S. Nuclear Regulatory Commission's (NRC) assessment of the seismic hazard mitigation strategies assessment (MSA}, as described in the May 25, 2016, letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16147A150), submitted by Exelon Generation Company, LLC, (Exelon, the licensee) for Oyster Creek Nuclear Generating Station (Oyster Creek). The MSA confirms that the licensee has adequately addressed the reevaluated seismic hazard within its mitigating strategies for beyond-design-basis external events. BACKGROUND By letter dated March 12, 2012 (ADAMS Accession No. ML 12053A340}, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The 50.54(f) letter was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested licensees reevaluate the seismic hazard using present-day methodologies and guidance. Concurrent with the reevaluation of seismic hazards, the NRC issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 12054A736). The order requires holders of operating power reactor licenses and construction permits issued under 10 CFR Part 50 to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling following a beyond-design-basis external event. By letter dated March 31, 2014 (ADAMS Accession No. ML 14090A241}, the licensee provided its reevaluated seismic hazard for Oyster Creek in response to the 50.54(f) letter. | | |
| B. Hanson On December 10, 2015 (ADAMS Accession No. ML 16005A621), the Nuclear Energy Institute (NEI) submitted Revision 2 to NEI 12-06, including guidance for mitigating strategies assessments regarding reevaluated hazard information. The NRC subsequently endorsed NEI 12-06, Revision 2, with exceptions, clarifications, and additions in, Japan Lessons-Learned Division (JLD) interim staff guidance (ISG) JLD-ISG-2012-01, Revision 1, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML 15357A163). MITIGATION STRATEGIES ASSESSMENT By letter dated February 17, 2016 (ADAMS Accession No. ML 15350A353), the NRC staff documented its review of the licensee's reevaluated seismic hazard, also referred to as the mitigating strategies seismic hazard information. The staff stated that the licensee's reevaluated seismic hazard is bounded by the original design-basis (i.e., Housner-shape design spectrum) at frequencies above 1 Hertz (Hz). In addition, the staff concluded that the Ground Motion Response Spectrum determined by the licensee adequately characterizes the reevaluated hazard for the Oyster Creek site. The licensee stated that the Oyster Creek MSA was performed consistent with NEI 12-06, Revision 2. Appendix H of NEI 12-06, Revision 2, describes acceptable methods for demonstrating that the reevaluated seismic hazard is addressed within the Oyster Creek mitigating strategies for beyond-design-basis external events. The NRC staff confirmed that the licensee's seismic hazard MSA is consistent with the guidance in Appendix H.4.1 of NEI 12-06, Revision 2, as endorsed, by JLD-ISG-2012-01, Revision 1. Therefore, the methodology used by the licensee is appropriate to perform an assessment of the mitigation strategies that addresses the reevaluated seismic hazard. The NRC staff has reviewed the seismic hazard MSA for Oyster Creek. The NRC staff concludes that sufficient information has been provided to demonstrate that the licensee's plans for the development and implementation of guidance and strategies under Order EA-12-049 appropriately address the reevaluated seismic hazard information stemming from the 50.54(f) letter. | | The purpose of this letter is to provide the U.S. Nuclear Regulatory Commission's (NRC) assessment of the seismic hazard mitigation strategies assessment (MSA}, as described in the May 25, 2016, letter (Agencywide Documents Access and Management System (ADAMS) |
| B. Hanson If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov. Docket No. 50-219 cc: Distribution via Listserv Frankie Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation B. Hanson If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov. Docket No. 50-219 cc: Distribution via Listserv DISTRIBUTION: PUBLIC JHMB R/F RidsNrrDorlLPL 1-2 Resource RidsNrrPMOysterCreek Resource RidsNrrLASLent Resource RidsAcrsAcnw_MailCTR Resource Sincerely, IRA/ Frankie Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation FVega, NRR BTitus, NRR EBowman, NRR MShams, NRR ADAMS Accession No. ML 16161A477 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME FVega Slent MShams FVega DATE 06/14/2016 06/10/2016 06/16/2016 06/16/2016 OFFICIAL RECORD COPY | | Accession No. ML16147A150), submitted by Exelon Generation Company, LLC , (Exelon , the licensee) for Oyster Creek Nuclear Generating Station (Oyster Creek). The MSA confirms that the licensee has adequately addressed the reevaluated seismic hazard within its mitigating strategies for beyond-design-basis external events. |
| }} | | BACKGROUND By letter dated March 12, 2012 (ADAMS Accession No. ML12053A340}, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR), |
| | Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The 50.54(f) letter was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested licensees reevaluate the seismic hazard using present-day methodologies and guidance. Concurrent with the reevaluation of seismic hazards, the NRC issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A736). The order requires holders of operating power reactor licenses and construction permits issued under 10 CFR Part 50 to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling following a beyond-design-basis external event. |
| | By letter dated March 31 , 2014 (ADAMS Accession No. ML14090A241}, the licensee provided its reevaluated seismic hazard for Oyster Creek in response to the 50.54(f) letter. |
| | |
| | B. Hanson On December 10, 2015 (ADAMS Accession No. ML16005A621), the Nuclear Energy Institute (NEI) submitted Revision 2 to NEI 12-06, including guidance for mitigating strategies assessments regarding reevaluated hazard information. The NRC subsequently endorsed NEI 12-06, Revision 2, with exceptions, clarifications, and additions in, Japan Lessons-Learned Division (JLD) interim staff guidance (ISG) JLD-ISG-2012-01 , Revision 1, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML15357A163). |
| | MITIGATION STRATEGIES ASSESSMENT By letter dated February 17, 2016 (ADAMS Accession No. ML15350A353), the NRC staff documented its review of the licensee's reevaluated seismic hazard, also referred to as the mitigating strategies seismic hazard information. The staff stated that the licensee's reevaluated seismic hazard is bounded by the original design-basis (i.e., Housner-shape design spectrum) at frequencies above 1 Hertz (Hz). In addition, the staff concluded that the Ground Motion Response Spectrum determined by the licensee adequately characterizes the reevaluated hazard for the Oyster Creek site. |
| | The licensee stated that the Oyster Creek MSA was performed consistent with NEI 12-06, Revision 2. Appendix H of NEI 12-06, Revision 2, describes acceptable methods for demonstrating that the reevaluated seismic hazard is addressed within the Oyster Creek mitigating strategies for beyond-design-basis external events. The NRC staff confirmed that the licensee's seismic hazard MSA is consistent with the guidance in Appendix H.4.1 of NEI 12-06, Revision 2, as endorsed , by JLD-ISG-2012-01 , Revision 1. Therefore, the methodology used by the licensee is appropriate to perform an assessment of the mitigation strategies that addresses the reevaluated seismic hazard. |
| | The NRC staff has reviewed the seismic hazard MSA for Oyster Creek. The NRC staff concludes that sufficient information has been provided to demonstrate that the licensee's plans for the development and implementation of guidance and strategies under Order EA-12-049 appropriately address the reevaluated seismic hazard information stemming from the 50.54(f) letter. |
| | |
| | B. Hanson If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov. |
| | Frankie Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-219 cc: Distribution via Listserv |
| | |
| | ML16161A477 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME FVega Slent MShams FVega DATE 06/14/2016 06/10/2016 06/16/2016 06/16/2016}} |
Letter Sequence Approval |
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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
[Table View] |
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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
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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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C . 20555-0001 June 16, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville , IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - 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 (CAC NO. MF7766)
Dear Mr. Hanson:
The purpose of this letter is to provide the U.S. Nuclear Regulatory Commission's (NRC) assessment of the seismic hazard mitigation strategies assessment (MSA}, as described in the May 25, 2016, letter (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML16147A150), submitted by Exelon Generation Company, LLC , (Exelon , the licensee) for Oyster Creek Nuclear Generating Station (Oyster Creek). The MSA confirms that the licensee has adequately addressed the reevaluated seismic hazard within its mitigating strategies for beyond-design-basis external events.
BACKGROUND By letter dated March 12, 2012 (ADAMS Accession No. ML12053A340}, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.54(f) (hereafter referred to as the 50.54(f) letter). The 50.54(f) letter was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 1 to the 50.54(f) letter requested licensees reevaluate the seismic hazard using present-day methodologies and guidance. Concurrent with the reevaluation of seismic hazards, the NRC issued Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A736). The order requires holders of operating power reactor licenses and construction permits issued under 10 CFR Part 50 to develop, implement, and maintain guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling following a beyond-design-basis external event.
By letter dated March 31 , 2014 (ADAMS Accession No. ML14090A241}, the licensee provided its reevaluated seismic hazard for Oyster Creek in response to the 50.54(f) letter.
B. Hanson On December 10, 2015 (ADAMS Accession No. ML16005A621), the Nuclear Energy Institute (NEI) submitted Revision 2 to NEI 12-06, including guidance for mitigating strategies assessments regarding reevaluated hazard information. The NRC subsequently endorsed NEI 12-06, Revision 2, with exceptions, clarifications, and additions in, Japan Lessons-Learned Division (JLD) interim staff guidance (ISG) JLD-ISG-2012-01 , Revision 1, "Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML15357A163).
MITIGATION STRATEGIES ASSESSMENT By letter dated February 17, 2016 (ADAMS Accession No. ML15350A353), the NRC staff documented its review of the licensee's reevaluated seismic hazard, also referred to as the mitigating strategies seismic hazard information. The staff stated that the licensee's reevaluated seismic hazard is bounded by the original design-basis (i.e., Housner-shape design spectrum) at frequencies above 1 Hertz (Hz). In addition, the staff concluded that the Ground Motion Response Spectrum determined by the licensee adequately characterizes the reevaluated hazard for the Oyster Creek site.
The licensee stated that the Oyster Creek MSA was performed consistent with NEI 12-06, Revision 2. Appendix H of NEI 12-06, Revision 2, describes acceptable methods for demonstrating that the reevaluated seismic hazard is addressed within the Oyster Creek mitigating strategies for beyond-design-basis external events. The NRC staff confirmed that the licensee's seismic hazard MSA is consistent with the guidance in Appendix H.4.1 of NEI 12-06, Revision 2, as endorsed , by JLD-ISG-2012-01 , Revision 1. Therefore, the methodology used by the licensee is appropriate to perform an assessment of the mitigation strategies that addresses the reevaluated seismic hazard.
The NRC staff has reviewed the seismic hazard MSA for Oyster Creek. The NRC staff concludes that sufficient information has been provided to demonstrate that the licensee's plans for the development and implementation of guidance and strategies under Order EA-12-049 appropriately address the reevaluated seismic hazard information stemming from the 50.54(f) letter.
B. Hanson If you have any questions, please contact me at (301) 415-1617 or via e-mail at Frankie.Vega@nrc.gov.
Frankie Vega, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-219 cc: Distribution via Listserv
ML16161A477 *via e-mail OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME FVega Slent MShams FVega DATE 06/14/2016 06/10/2016 06/16/2016 06/16/2016