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MONTHYEARLR-N13-0205, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity...2013-09-10010 September 2013 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident-Base Case Velocity... Project stage: Response to RAI 0CAN091301, Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi..2013-09-12012 September 2013 Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi.. Project stage: Response to RAI LR-N14-0051, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) 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.2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) 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. Project stage: Response to RAI 0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima2014-03-28028 March 2014 ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima Da Project stage: Response to RAI ML14092A4172014-03-31031 March 2014 Response to March 12, 2012 Information Request Seismic Hazard and Screening Report (CEUS Sites) for Recommendation 2.1 Project stage: Request RS-14-065, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The..2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of The.. Project stage: Response to RAI LIC-14-0047, Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response 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 Fukushi2014-03-31031 March 2014 Omaha Public Power District - Seismic Hazard and Screening Report (CEUS Sites), Response 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 Project stage: Request ML14204A6192014-07-21021 July 2014 Response to March 12, 2012 Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 Project stage: Request PLA-7224, Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-72242014-08-28028 August 2014 Response to March 12, 2012 Information Request - Supplemental Information Related to the Seismic Hazard and Screening Report for Recommendation 2.1 - PLA-7224 Project stage: Request RS-14-206, Third 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)2014-08-28028 August 2014 Third 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) Project stage: Other RS-14-230, Supplemental Information Related to the Seismic Hazard and Screening Report in 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...2014-08-29029 August 2014 Supplemental Information Related to the Seismic Hazard and Screening Report in 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... Project stage: Supplement ML14224A5262014-09-22022 September 2014 Screening and Prioritization Results of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Project stage: Other LIC-14-0124, Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...2014-10-22022 October 2014 Supplemental Information Related to Seismic Hazard and Screening Report in Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The... Project stage: Supplement LR-N14-0227, Seismic Hazard and Screening Report - Supplemental 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 Accident2014-10-30030 October 2014 Seismic Hazard and Screening Report - Supplemental 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 Project stage: Supplement 0CAN111401, Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-11-0404 November 2014 Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Other ML14310A0332014-12-15015 December 2014 NRC Response to Licensees Notification of Revised Regulatory Commitments Associated with Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Revie Project stage: RAI ML15329A1812015-12-0808 December 2015 Staff Assessment of Information Provided Pursuant of Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f)Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights.. Project stage: Approval LIC-16-0039, Ft. Calhoun, Unit 1 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident2016-05-25025 May 2016 Ft. Calhoun, Unit 1 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident Project stage: Response to RAI 2014-03-28
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Category:Letter
MONTHYEARLIC-24-0012, Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information2024-10-0707 October 2024 Independent Spent Fuel Storage Installation - Response to Proposed Revision to Decommissioning Quality Assurance Plan (DQAP) - Request for Additional Information LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024 Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24255A0962024-09-12012 September 2024 License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285) ML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 ML24235A0822024-08-10010 August 2024 Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024 ML24180A2082024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information Letter ML24183A3222024-07-0808 July 2024 Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024 License Amendment Request (LAR) to Revise License Termination Plan (LTP) IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024 Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024 Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024 (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan ML24079A1702024-03-10010 March 2024 ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report ML24019A1672024-01-31031 January 2024 Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 LIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements – Request for Additional Information IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 ML23276A0042023-09-28028 September 2023 U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 (License No. DPR-40, Docket No. 50-285) IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 ML23082A2202023-06-26026 June 2023 Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 ML23151A0032023-06-0505 June 2023 Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - 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Calhoun Station LTP ML22258A2732022-09-29029 September 2022 Letter to John Swigart, Shpo; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1 ML22265A0262022-09-26026 September 2022 U.S. Nuclear Regulatory Commission'S Analysis of Omaha Public Power District'S Decommissioning Status Report (License No. DPR-40, Docket No. 50-285) IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 ML22138A1222022-08-0303 August 2022 Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1302022-08-0303 August 2022 Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22138A1242022-08-0303 August 2022 Letter to Mr. Reggie Wassana, Governor, Cheyenne and Arapaho Tribes, Oklahoma, Re., Ft Calhoun LTP Section 106 ML22101A1092022-08-0303 August 2022 Letter to Mr. Durell Cooper, Chairman, Apache Tribe of Oklahoma; Re., Ft Calhoun LTP Section 106 ML22138A1212022-08-0303 August 2022 Letter to Mr. Edgar Kent, Chairman, Iowa Tribe of Oklahoma, Re., Ft Calhoun LTP Section 106 2024-09-18
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 22, 2014 Mr. Louis Cortopassi Site Vice President and Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-4 9610 Power Lane Blair, NE 68008
SUBJECT:
FORT CALHOUN STATION, UNIT 1 -SCREENING AND PRIORITIZATION RESULTS OF INFORMATION PROVIDED PURSUANT TO TITLE 10 OF THE CODE OF FEDERAL REGULATIONS PART 50, SECTION 50.54(f), SEISMIC HAZARD REEVALUATIONS FOR RECOMMENDATION 2.1 OF THE NEAR-TERM TASK FORCE REVIEW OF INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT (TAC NO. MF3735)
Dear Mr. Cortopassi:
The purpose of this letter is to inform Omaha Public Power District (OPPD) of the results for Fort Calhoun Station (FCS), Unit 1, regarding the U.S. Nuclear Regulatory Commission's (NRC) seismic screening and prioritization review. The staff has determined that FCS screens out of conducting a seismic risk evaluation since the Individual Plant Examination for External Events (IPEEE) demonstrates plant seismic capacity to levels higher than the ground motion response spectra (GMRS) in the 1-10 Hertz (Hz) range and OPPD demonstrated that the IPEEE-related screening criteria in the NRC-approved industry guidance was met. This determination is predicated on the licensee fulfilling certain commitments as discussed later.
Additionally, the NRC staff concurs with OPPD's determination to conduct the spent fuel pool evaluation at FCS which is consistent with commitments in the March 31, 2014 letter (Agencywide Documents Access and Management System {ADAMS) Accession No. ML 14097A08). The spent fuel pool evaluation will be performed because spent fuel pools were not included in the original scope of the IPEEE evaluation. Additionally, FCS screens out of performing a high frequency evaluation because the IPEEE capacity exceeds the GMRS in the greater than 10 Hz range.
This letter only transmits the NRC staff's result of the screening and prioritization of the seismic hazard submittal for FCS. The NRC staff is continuing its review of the seismic hazard reevaluation submittal and may request additional plant-specific information to support this review. The NRC staff plans to issue an assessment for FCS on the reevaluated seismic hazard no later than the third quarter 2015.
BACKGROUND On March 12, 2012, the NRC issued a request for information pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.54(f) (hereafter referred to as the 50.54(f) letter)
(ADAMS Accession No. ML12053A340}. The purpose of that request was to gather information
L. Cortopassi concerning, in part, seismic hazards at each operating reactor site and to enable the NRC staff to determine whether licenses should be modified, suspended, or revoked. Further, the 50.54(f) letter stated that the NRC would provide screening and prioritization results to indicate deadlines, if necessary, for individual plants to complete seismic risk evaluations that assess the total plant response to the reevaluated seismic hazard. In response to the 50.54(f) letter, all addressees committed to follow the Electric Power Research Institute Report (EPRI), "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic," 1 as supplemented by the EPRI Report, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic" 2 (referred to as the expedited approach}.
In response to the 50.54(f) letter, OPPD submitted their reevaluated hazard for FCS in March 2014. The Report specified that FCS screens out for performing a seismic risk evaluation.
The Report also specified that for the limited-scope evaluations, a high frequency evaluation was not necessary for FCS; however, a spent fuel pool seismic evaluation will be performed.
Subsequently, by letter dated May 9, 2014 (ADAMS Accession No. ML14111A147), the NRC staff informed all licensees of operating reactors in the central and eastern United States of the screening and prioritization results to support completing seismic risk and limited-scope evaluations, as described in Enclosure 1 of the 50.54(f) letter. In the May 2014 letter, the NRC staff identified that FCS conditionally screens in to perform a seismic risk evaluation (Prioritization Group 3), high frequency evaluation, and spent fuel pool evaluation for the purposes of the screening and prioritization review because additional information was needed to demonstrate FCS's IPEEE adequacy for the purpose of seismic screening.
SCREENING PROCESS As discussed in the May 2014 letter, the NRC staff's screening review was performed using the SPID guidance. The SPID provides guidance on seismic screening when the ground motion response spectra (GMRS) is above the safe shutdown earthquake (SSE), but bounded by the IPEEE capacity spectrum. To use the IPEEE capacity spectrum for seismic screening, OPPD needed to demonstrate the adequacy of FCS's IPEEE evaluation by satisfying specific criteria in the SPID. If the IPEEE capacity is greater than the GMRS in the 1-10Hz range and meets the IPEEE-related screening criteria in the SPID, a plant would screen out of conducting a seismic risk evaluation.
SCREENING REVIEW ASSESSMENT A public meeting (Meeting Summary available in ADAMS Accession No. ML14175A518) was conducted on June 17, 2014, between the NRC staff and OPPD, in part, to address the staff's questions regarding FCS's IPEEE evaluation to demonstrate plant seismic capacity and meet the corresponding screening criteria in the SPID. The staff issued OPPD a request for additional information (RAI) on July 16, 2014 (ADAMS Accession No. ML14195A086) to support the NRC's final screening and prioritization determination for FCS. By letter dated 1
The SPID guidance document is found in ADAMS under Accession No. ML12333A170. The staff endorsement letter for the SPID guidance is found in ADAMS under Accession No. ML12319A074.
2 The Expedited Approach guidance document is found in ADAMS under Accession No. ML13102A142.
L. Cortopassi July 25, 2014, (ADAMS Accession No. ML142068064), OPPD submitted its response to the RAI.
The RAI response discussed how the Class I structural members inside the containment and auxiliary building that were determined to be non-conforming with FCS's current licensing basis will be brought into compliance and support screening based on IPEEE capacity. The NRC staff reviewed the information provided by OPPD and understands that upon completion of Commitment 4 in Confirmatory Action Letter (CAL) EA-13-243, dated December 17, 2013 (ADAMS Accession No. ML13351A395), the identified structures will be restored to full design margin as described in FCS's current licensing basis. This work activity to restore full design margin is scheduled to begin in 2015 with expected completion during the 2016 refueling outage. Based on the staff's review of the March 2014 Seismic Hazard Evaluation and Screening Report, information provided in the OPPD's RAI response, and the CAL EA-13-243 commitment to correct the condition, FCS will meet the IPEEE-related screening standards.
Upon completion of Commitment 4, the NRC will verify that OPPD effectively implemented the commitment. If the structural modification does not meet the IPEEE screening capacity, FCS is expected to perform and submit a seismic risk evaluation to the NRC by December 31, 2020.
FINAL SCREENING AND PRIORITIZATION Seismic Risk Limited-scope Evaluations Plant name Screening Expedited Evaluation High Low Spent Result Approach (Prioritization Frequency Frequency Fuel Pool Evaluation Group) Evaluation Evaluation Evaluation Fort Calhoun Station, Unit 1 Out x2 X If you have any questions on this matter, please contact Michael Balazik, Project Manager for the Japan Lessons-Learned Division at (301) 415-2856 or at Michaei.Balazik@nrc.gov.
Sincerely, Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Listserv 2
As committed in the March 31, 2014 letter (ADAMS Accession No. ML 14097A08).
ML142068064), OPPD submitted its response to the RAI.
The RAI response discussed how the Class I structural members inside the containment and auxiliary building that were determined to be non-conforming with FCS's current licensing basis will be brought into compliance and support screening based on IPEEE capacity. The NRC staff reviewed the information provided by OPPD and understands that upon completion of Commitment 4 in Confirmatory Action Letter (CAL) EA-13-243, dated December 17, 2013 (ADAMS Accession No. ML13351A395), the identified structures will be restored to full design margin as described in FCS's current licensing basis. This work activity to restore full design margin is scheduled to begin in 2015 with expected completion during the 2016 refueling outage. Based on the staff's review of the March 2014 Seismic Hazard Evaluation and Screening Report, information provided in the OPPD's RAI response and the CAL EA-13-243 commitment to correct the condition, FCS will meet the IPEEE-related screening standards.
Upon completion of Commitment 4, the NRC will verify that OPPD effectively implemented the commitment. If the structural modification does not meet the IPEEE screening capacity, FCS is expected to perform and submit a seismic risk evaluation to the NRC by December 31, 2020.
FINAL SCREENING AND PRIORITIZATION Seismic Risk Limited-scope Evaluations Plant name Screening Expedited Evaluation High Low Spent Result Approach (Prioritization Frequency Frequency Fuel Pool Evaluation Group) Evaluation Evaluation Evaluation Fort Calhoun Station, Unit 1 Out x2 X If you have any questions on this matter, please contact Michael Balazik, Project Manager for the Japan Lessons-Learned Division at (301) 415-2856 or at Michaei.Balazik@nrc.gov.
Sincerely, IRA/
Daniel H. Dorman, Acting Director Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Listserv DISTRIBUTION PUBLIC JLD R/F RidsAcrsAcnw_MaiiCTR RidsNrrDorllp14-1 Resource RidsNrrOd RidsEdoMaiiCenter RidsOgcMaiiCenter MMarkley, NRR RidsOgcRp RidsNrrPMFortCalhoun RidsNrrLASLent RidsRgn4MaiiCenter ADAMS Accession No* .. ML14224A526 *concurrence via e-mail OFFICE NRRIJLD/JHMB/PM NRRIJLD/JHMB/LA NRO/DSEAIRGS2/BC NRR/JLD/JHMB/BC NAME MBalazik SLent DJackson SWhaley DATE 08/15/14 08/14/14 08/19/14 08/15/14 OFFICE NRR/DORLILPL4-1/PM* OGC NRR/JLD/D NRRIAD NAME Flyon BHarris JDavis (JMcHale for) DOorman DATE 08/19/14 09/04/14 09/15/14 09/22/14