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| | number = ML13115A095 | | | number = ML13115A095 |
| | issue date = 04/24/2013 | | | issue date = 04/24/2013 |
| | title = Fort Calhoun Station 05000285-13-405-LTR-Non-SGI-JMR-1 | | | title = 05000285-13-405-LTR-Non-SGI-JMR-1 |
| | author name = Hay M C | | | author name = Hay M |
| | author affiliation = NRC/RGN-IV/DRP | | | author affiliation = NRC/RGN-IV/DRP |
| | addressee name = Cortopassi L | | | addressee name = Cortopassi L |
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| =Text= | | =Text= |
| {{#Wiki_filter:" " April 24, 2013 Louis Cortopassi, Vice President | | {{#Wiki_filter:UNITE D S TATE S NUC LEAR RE GULATOR Y C OMMI S SI ON ril 24, 2013 |
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| and Chief Nuclear Officer Omaha Public Power District
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| | | FORT CALHOUN STATION - NRC IMC 0350 SECURITY INSPECTION REPORT 05000285/2013405 |
| Fort Calhoun Station FC-2-4 P.O. Box 550 Fort Calhoun, NE 68023-0550
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| SUBJECT: FORT CALHOUN STATION - NRC IMC 0350 SECURITY INSPECTION REPORT 05000285/2013405 | |
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| ==Dear Mr. Cortopassi:== | | ==Dear Mr. Cortopassi:== |
| On March 14, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at your Fort Calhoun Station. The enclosed inspection report documents the inspection results, which were discussed on March 14, 2013, with you and other members of | | On March 14, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at your Fort Calhoun Station. The enclosed inspection report documents the inspection results, which were discussed on March 14, 2013, with you and other members of your staff. |
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| your staff. | |
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| In accordance with Inspection Manual Chapter (IMC) 0350, "Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns," this supplemental inspection was performed to follow-up on performance issues which occurred in the first, second, and third quarter of 2011, and again during the second quarter of 2012. These issues were previously documented and assessed in NRC Inspection Reports 05000285/2011404, 05000285/2011406, and 05000285/2012403. | | In accordance with Inspection Manual Chapter (IMC) 0350, Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns, this supplemental inspection was performed to follow-up on performance issues which occurred in the first, second, and third quarter of 2011, and again during the second quarter of 2012. These issues were previously documented and assessed in NRC Inspection Reports 05000285/2011404, 05000285/2011406, and 05000285/2012403. |
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| The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes. | | The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes. |
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| During this inspection, the NRC determined that your staff had not performed a comprehensive evaluation of the causes for the Greater-than-Green findings. Specifically, the team identified significant problems with your staff's collective evaluation of the events and the extent of cause reviews. This led the NRC to conclude that the fundamental performance issues within security, and their impact on security processes, have yet to be identified and corrected. Based on these findings, the Greater-than-Green security violations will be held open until adequate causal analyses, extent of cause reviews, and corrective actions are completed by | | During this inspection, the NRC determined that your staff had not performed a comprehensive evaluation of the causes for the Greater-than-Green findings. Specifically, the team identified significant problems with your staffs collective evaluation of the events and the extent of cause reviews. This led the NRC to conclude that the fundamental performance issues within security, and their impact on security processes, have yet to be identified and corrected. Based on these findings, the Greater-than-Green security violations will be held open until adequate causal analyses, extent of cause reviews, and corrective actions are completed by your staff, and are assessed by the NRC during a future inspection. |
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| your staff, and are assessed by the NRC during a future inspection. | |
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| Additionally, nine NRC identified findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) were identified during this inspection. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the team left the area. | | Additionally, nine NRC identified findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) were identified during this inspection. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the team left the area. |
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| Nine of these findings were determined to involve violations of NRC requirements. Further, a licensee-identified violation which was determined to be of very low security significance is listed | | Nine of these findings were determined to involve violations of NRC requirements. Further, a licensee-identified violation which was determined to be of very low security significance is listed in this report. The NRC is treating these violations as noncited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy. |
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| in this report. The NRC is treating these violations as noncited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy. | |
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| If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at Fort Calhoun Station Seven cross-cutting aspects were assigned to the findings in the area of Human Performance, and two cross-cutting aspects were assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because
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| your staff failed to: 1) make safety-significant decisions using a systemic process [H1.(a)]; 2) use conservative assumptions in decision making [H1.(b)]; 3) ensure the availability of complete, accurate, and up-to-date procedures [H.2(c)]; and 4) ensure the availability of adequate equipment [H2.(d)]. Cross-cutting aspects were assigned in the area of Problem Identification and Resolution because your staff failed to thoroughly evaluate problems such that the resolutions address causes and extent of conditions, as necessary [P1.(c)]. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspectors at Fort Calhoun Station.
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| In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be
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| available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
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| However, the material enclosed contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response "Security-Related Information - Withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
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| Sincerely,/RA/
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| Michael C. Hay, Chief Project Branch F Division of Reactor Projects
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| Docket No.: 50-285 License No.: DPR-40
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| Nonpublic
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| ===Enclosure:===
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| NRC Inspection Report 05000285/2013405
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| ===w/Attachment:===
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| Supplemental Information
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| cc w/enclosure:
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| Mr. Dennis A. Bakalar Manager, Site Security Omaha Public Power District
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| Fort Calhoun Station | | If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at Fort Calhoun Station Seven cross-cutting aspects were assigned to the findings in the area of Human Performance, and two cross-cutting aspects were assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because your staff failed to: 1) make safety-significant decisions using a systemic process [H1.(a)]; 2) |
| | use conservative assumptions in decision making [H1.(b)]; 3) ensure the availability of complete, accurate, and up-to-date procedures [H.2(c)]; and 4) ensure the availability of adequate equipment [H2.(d)]. Cross-cutting aspects were assigned in the area of Problem Identification and Resolution because your staff failed to thoroughly evaluate problems such that the resolutions address causes and extent of conditions, as necessary [P1.(c)]. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspectors at Fort Calhoun Station. |
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| Mail Stop FC-2-1
| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| 9610 Power Lane Blair, NE 68008
| | However, the material enclosed contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information - Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. |
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| cc w/o enclosure: | | Sincerely, |
| | /RA/ |
| | Michael C. Hay, Chief Project Branch F Division of Reactor Projects Docket No.: 50-285 License No.: DPR-40 Nonpublic Enclosure: |
| | NRC Inspection Report 05000285/2013405 w/Attachment: Supplemental Information cc w/enclosure: |
| | Mr. Dennis A. Bakalar Manager, Site Security Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-1 9610 Power Lane Blair, NE 68008 cc w/o enclosure: |
| Electronic Distribution for Fort Calhoun Station | | Electronic Distribution for Fort Calhoun Station |
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Category:Inspection Report
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 IR 05000285/20240022024-08-21021 August 2024 NRC Inspection Report 05000285/2024002 IR 05000285/20240012024-06-0505 June 2024 NRC Inspection Report 05000285/2024001 IR 05000285/20230062023-12-21021 December 2023 NRC Inspection Report 05000285/2023006 IR 05000285/20230052023-11-0202 November 2023 NRC Inspection Room 05000285/2023005 IR 05000285/20230042023-09-13013 September 2023 NRC Inspection Report 05000285/2023-004 IR 05000285/20230032023-07-10010 July 2023 NRC Inspection Report 05000285/2023003 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 IR 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 IR 05000285/20220042022-09-14014 September 2022 NRC Inspection Report 05000285/2022004 IR 05000285/20220032022-06-15015 June 2022 NRC Inspection Report 05000285/2022003 IR 05000285/20220022022-04-28028 April 2022 NRC Inspection Report 050-00285/2022-002 IR 05000285/20220012022-02-25025 February 2022 NRC Inspection Report 050-00285/2022-001 IR 05000285/20210042021-11-18018 November 2021 NRC Inspection Report 050-00285/2021-004 IR 05000285/20210032021-08-11011 August 2021 NRC Inspection Report 050-00285/2021-003 (Public) IR 05000285/20210022021-05-0707 May 2021 NRC Inspection Report 05000285/2021002 IR 05000285/20210012021-02-17017 February 2021 NRC Inspection Report 05000285/2021001 IR 07200054/20204012020-10-29029 October 2020 Independent Spent Fuel Storage Installation Physical Security Requirements for Independent Spent Fuel Storage Installations Inspection Report 07200054/2020401 IR 05000285/20200022020-09-22022 September 2020 NRC Inspection Report 05000285/2020002 IR 05000285/20190052020-03-12012 March 2020 Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report 050-00285/2019-005 and 072-00054/2019-001 IR 05000206/20190042020-02-20020 February 2020 Independent Spent Fuel Storage Installation (ISFSI) - NRC Inspection Report 05000206/2019 004; 05000361/2019 007; 05000362/2019 007; and 07200054/2019-002 IR 05000285/20190042019-11-26026 November 2019 Inspection Report 050-00285/2019-004 IR 05000285/20190032019-09-13013 September 2019 NRC Inspection Report 050-00285/2019-003 IR 05000285/20190022019-07-23023 July 2019 NRC Inspection Report 05000285/2019002 IR 05000285/20194042019-07-11011 July 2019 NRC Security Baseline Inspection Report 05000285/2019404 IR 05000285/20194032019-06-0404 June 2019 NRC Security Baseline Inspection Report 05000285/2019403 IR 05000285/20190012019-02-12012 February 2019 NRC Inspection Report 050-00285/2019-001 IR 05000285/20180042018-11-19019 November 2018 Omaha Public Power District; Fort Calhoun Station - NRC Inspection Report 05000285/2018-004 IR 05000285/20180032018-09-27027 September 2018 NRC Inspection Report 05000285/2018003 IR 05000285/20184102018-05-17017 May 2018 NRC Security Baseline Inspection Report 05000285/2018410 IR 05000285/20184032018-05-17017 May 2018 NRC Physical Security Inspection Report 05000285/2018403 IR 05000285/20180012018-04-13013 April 2018 NRC Inspection Report 05000285/2018001 IR 05000285/20174032018-04-10010 April 2018 Cancellation of NRC Inspection Report 05000285/2017403 IR 05000285/20170112018-02-0101 February 2018 NRC Inspection Report 05000285/2017-011 IR 05000285/20170022017-11-0909 November 2017 NRC Inspection Reports 05000285/2017002 Through 05000285/2017007 IR 05000285/20170122017-11-0808 November 2017 NRC Inspection Report 05000285/2017-012 IR 05000285/20160062017-09-18018 September 2017 NRC Inspection Report 05000285/2016006 IR 05000285/20170092017-08-0404 August 2017 NRC Inspection Report 05000285/2017-009 IR 05000285/20174052017-06-26026 June 2017 NRC Security Inspection Report 05000285/2017405 and NRC Investigation Report 4-2015-030 IR 05000285/20174062017-06-26026 June 2017 NRC Security Baseline Inspection Report 05000285/2017406 IR 05000285/20170102017-06-15015 June 2017 Independent Spent Fuel Storage Installation Inspection Report 05000285/2017010 and 07200054/2017001 IR 05000285/20170012017-05-0808 May 2017 NRC Inspection Report 05000285/2017001 and 05000285/2017008 IR 05000285/20160042017-01-18018 January 2017 NRC Integrated Inspection Report 05000285/2016004 IR 05000285/20165012017-01-17017 January 2017 NRC Emergency Preparedness Annual Inspection Report 05000285/2016501 IR 05000285/20160032016-11-0808 November 2016 NRC Integrated Inspection Report Number 05000285/2016003 IR 05000285/20164042016-10-28028 October 2016 NRC Security Baseline Inspection Report 05000285/2016404 IR 05000285/20160082016-09-22022 September 2016 NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications Baseline Inspection Report 05000285/2016008 IR 05000285/20160052016-09-12012 September 2016 Errata for Mid-Cycle Assessment Letter for Fort Calhoun Station (Report 05000285/2016005) 2024-08-21
[Table view] Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024 NRC Inspection Report 05000285/2024003 LIC-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 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) 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) 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 ML23234A2412023-08-18018 August 2023 Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request ML23234A2392023-08-18018 August 2023 Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf 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 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 IR 05000285/20230022023-06-0505 June 2023 NRC Inspection Report 05000285/2023002 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 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information 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 05000285/20230012023-02-24024 February 2023 NRC Inspection Report 05000285/2023001 LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML23020A0462023-01-19019 January 2023 Threatened and Endangered Species List: Nebraska Ecological Services Field Office IR 05000285/20220062023-01-0505 January 2023 NRC Inspection Report 05000285/2022-006 ML22357A0662022-12-30030 December 2022 Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan IR 05000285/20220052022-10-26026 October 2022 NRC Inspection Report 05000285/2022-005 ML22276A1052022-09-30030 September 2022 Conclusion of Consultation Under Section 106 NHPA for Ft. 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 ML22138A1252022-08-0303 August 2022 Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106 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 ML22214A0922022-08-0303 August 2022 Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106 2024-09-18
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UNITE D S TATE S NUC LEAR RE GULATOR Y C OMMI S SI ON ril 24, 2013
SUBJECT:
FORT CALHOUN STATION - NRC IMC 0350 SECURITY INSPECTION REPORT 05000285/2013405
Dear Mr. Cortopassi:
On March 14, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed a supplemental inspection at your Fort Calhoun Station. The enclosed inspection report documents the inspection results, which were discussed on March 14, 2013, with you and other members of your staff.
In accordance with Inspection Manual Chapter (IMC) 0350, Oversight of Reactor Facilities in a Shutdown Condition Due to Significant Performance and/or Operational Concerns, this supplemental inspection was performed to follow-up on performance issues which occurred in the first, second, and third quarter of 2011, and again during the second quarter of 2012. These issues were previously documented and assessed in NRC Inspection Reports 05000285/2011404, 05000285/2011406, and 05000285/2012403.
The objectives of this supplemental inspection were to provide assurance that: (1) the root causes and the contributing causes for the significant issues were understood; (2) the extent of condition and extent of cause of the issues were identified; and (3) corrective actions were or will be sufficient to address and preclude repetition of the root and contributing causes.
During this inspection, the NRC determined that your staff had not performed a comprehensive evaluation of the causes for the Greater-than-Green findings. Specifically, the team identified significant problems with your staffs collective evaluation of the events and the extent of cause reviews. This led the NRC to conclude that the fundamental performance issues within security, and their impact on security processes, have yet to be identified and corrected. Based on these findings, the Greater-than-Green security violations will be held open until adequate causal analyses, extent of cause reviews, and corrective actions are completed by your staff, and are assessed by the NRC during a future inspection.
Additionally, nine NRC identified findings of very low security significance (i.e., Green as determined by the Physical Protection Significance Determination Process) were identified during this inspection. The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the team left the area.
Nine of these findings were determined to involve violations of NRC requirements. Further, a licensee-identified violation which was determined to be of very low security significance is listed in this report. The NRC is treating these violations as noncited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest these violations or the significance of these NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspectors at Fort Calhoun Station Seven cross-cutting aspects were assigned to the findings in the area of Human Performance, and two cross-cutting aspects were assigned in the area of Problem Identification and Resolution. Cross-cutting aspects were assigned in the area of Human Performance because your staff failed to: 1) make safety-significant decisions using a systemic process [H1.(a)]; 2)
use conservative assumptions in decision making [H1.(b)]; 3) ensure the availability of complete, accurate, and up-to-date procedures H.2(c); and 4) ensure the availability of adequate equipment [H2.(d)]. Cross-cutting aspects were assigned in the area of Problem Identification and Resolution because your staff failed to thoroughly evaluate problems such that the resolutions address causes and extent of conditions, as necessary [P1.(c)]. If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region IV; and the NRC Resident Inspectors at Fort Calhoun Station.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information - Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Michael C. Hay, Chief Project Branch F Division of Reactor Projects Docket No.: 50-285 License No.: DPR-40 Nonpublic Enclosure:
NRC Inspection Report 05000285/2013405 w/Attachment: Supplemental Information cc w/enclosure:
Mr. Dennis A. Bakalar Manager, Site Security Omaha Public Power District Fort Calhoun Station Mail Stop FC-2-1 9610 Power Lane Blair, NE 68008 cc w/o enclosure:
Electronic Distribution for Fort Calhoun Station