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| | issue date = 09/10/2014 | | | issue date = 09/10/2014 |
| | title = Errata to IR 05000483/2014003, March 22, 2014 Through June 20, 2014, Callaway Plant - NRC Integrated Inspection | | | title = Errata to IR 05000483/2014003, March 22, 2014 Through June 20, 2014, Callaway Plant - NRC Integrated Inspection |
| | author name = O'Keefe N F | | | author name = O'Keefe N |
| | author affiliation = NRC/RGN-IV/DRP | | | author affiliation = NRC/RGN-IV/DRP |
| | addressee name = Diya F | | | addressee name = Diya F |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:ber 10, 2014 |
| [[Issue date::September 10, 2014]]
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| Mr. Fadi Diya, Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251
| | ==SUBJECT:== |
| | ERRATA - CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003 |
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| SUBJECT: ERRATA - CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003
| | ==Dear Mr. Diya:== |
| | Please remove the cover page, and enclosure pages 1 and 2, from the Callaway Plant - |
| | NRC Integrated Inspection Report 05000483/20140003 (ML14216A691), and replace them with the pages enclosed with this letter. The purpose of this change is to correct the inspection period dates and minor typographical errors on these pages. |
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| ==Dear Mr. Diya:==
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agencywide Documents 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). |
| Please remove the cover page, and enclosure pages 1 and 2, from the Callaway Plant - NRC Integrated Inspection Report 05000483/20140003 (ML14216A691), and replace them with the pages enclosed with this letter. The purpose of this change is to correct the inspection period dates and minor typographical errors on these pages. In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents 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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| Sincerely,/RA/ Neil O'Keefe, Branch Chief Project Branch B Division of Reactor Projects Docket Nos.: 50-483 License Nos: NPF-30 | | Sincerely, |
| | /RA/ |
| | Neil OKeefe, Branch Chief Project Branch B Division of Reactor Projects Docket Nos.: 50-483 License Nos: NPF-30 Enclosure: |
| | NRC Inspection Report 05000483/2014003 |
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| ===Enclosure:===
| | Letter to Fadi Diya from Neil OKeefe, dated September 10, 2014 SUBJECT: ERRATA - CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003 DISTRIBUTION: |
| NRC Inspection Report 05000483/2014003 Letter to Fadi Diya from Neil O'Keefe, dated September 10, 2014
| | Regional Administrator (Marc.Dapas@nrc.gov) |
| | Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) |
| | Acting DRP Director (Troy.Pruett@nrc.gov) |
| | Acting DRP Deputy Director (Michael.Hay@nrc.gov) |
| | DRS Director (Anton.Vegel@nrc.gov) |
| | DRS Deputy Director (Jeff.Clark@nrc.gov) |
| | Senior Resident Inspector (Thomas.Hartman@nrc.gov) |
| | Resident Inspector (Zachary.Hollcraft@nrc.gov) |
| | Branch Chief, DRP/B (Neil.OKeefe@nrc.gov) |
| | Senior Project Engineer, DRP/B (David.Proulx@nrc.gov) |
| | Project Engineer, DRP/B (Fabian.Thomas@nrc.gov) |
| | CW Administrative Assistant (Dawn.Yancey@nrc.gov) |
| | Public Affairs Officer (Victor.Dricks@nrc.gov) |
| | Public Affairs Officer (Lara.Uselding@nrc.gov) |
| | Project Manager (Fred.Lyon@nrc.gov) |
| | Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov) |
| | RITS Coordinator (Marisa.Herrera@nrc.gov) |
| | ACES (R4Enforcement.Resource@nrc.gov) |
| | Regional Counsel (Karla.Fuller@nrc.gov) |
| | Technical Support Assistant (Loretta.Williams@nrc.gov) |
| | Congressional Affairs Officer (Jenny.Weil@nrc.gov) |
| | RIV/ETA: OEDO (John.Jandovitz@nrc.gov) |
| | ROPreports Electronic Distribution for Callaway Plant ADAMS ACCESSION NUMBER: ML142533A503/ADAMS Pkg ML14253A505 SUNSI Review ADAMS Publicly Available Non-Sensitive By: N. O'Keefe Yes No Non-Publicly Sensitive Available OFFICE C:DRP/RPBB NAME NOKEEFE/dll SIGNATURE /RA/ |
| | DATE 9/10/14 |
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| SUBJECT: ERRATA - CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003 DISTRIBUTION: Regional Administrator (Marc.Dapas@nrc.gov) Deputy Regional Administrator (Kriss.Kennedy@nrc.gov) Acting DRP Director (Troy.Pruett@nrc.gov) Acting DRP Deputy Director (Michael.Hay@nrc.gov) DRS Director (Anton.Vegel@nrc.gov) DRS Deputy Director (Jeff.Clark@nrc.gov) Senior Resident Inspector (Thomas.Hartman@nrc.gov) Resident Inspector (Zachary.Hollcraft@nrc.gov) Branch Chief, DRP/B (Neil.OKeefe@nrc.gov) Senior Project Engineer, DRP/B (David.Proulx@nrc.gov) Project Engineer, DRP/B (Fabian.Thomas@nrc.gov) CW Administrative Assistant (Dawn.Yancey@nrc.gov) Public Affairs Officer (Victor.Dricks@nrc.gov) Public Affairs Officer (Lara.Uselding@nrc.gov) Project Manager (Fred.Lyon@nrc.gov) Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov) RITS Coordinator (Marisa.Herrera@nrc.gov) ACES (R4Enforcement.Resource@nrc.gov) Regional Counsel (Karla.Fuller@nrc.gov) Technical Support Assistant (Loretta.Williams@nrc.gov) Congressional Affairs Officer (Jenny.Weil@nrc.gov) RIV/ETA: OEDO (John.Jandovitz@nrc.gov) ROPreports Electronic Distribution for Callaway Plant ADAMS ACCESSION NUMBER: SUNSI Review By: N. O'Keefe ADAMS Yes No Publicly Available Non-Publicly Available Non-Sensitive Sensitive OFFICE C:DRP/RPBB NAME NOKEEFE/dll SIGNATURE /RA/ DATE 9/10/14 August 4, 2014 Mr. Fadi Diya, Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251
| | UNITED STATES ust 4, 2014 |
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| SUBJECT: CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003 | | ==SUBJECT:== |
| | CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003 |
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| ==Dear Mr. Diya:== | | ==Dear Mr. Diya:== |
| On June 20, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Callaway Plant. On July 1, 2014, the NRC inspectors discussed the results of this inspection with you and members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report. NRC inspectors documented two findings of very low safety significance (Green) in this report. One of these findings involved a violation of NRC requirements. Further, inspectors documented a licensee-identified violation, which was determined to be of very low safety significance. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the NRC Enforcement Policy. If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC resident inspector at the Callaway Plant. | | On June 20, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Callaway Plant. On July 1, 2014, the NRC inspectors discussed the results of this inspection with you and members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report. |
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| | NRC inspectors documented two findings of very low safety significance (Green) in this report. |
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| | One of these findings involved a violation of NRC requirements. Further, inspectors documented a licensee-identified violation, which was determined to be of very low safety significance. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the NRC Enforcement Policy. |
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| | If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC resident inspector at the Callaway Plant. |
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| If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement 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 inspector at the Callaway Plant. | | If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement 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 inspector at the Callaway Plant. |
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| -1- Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION IV Docket: 05000483 License: NPF-30 Report: 05000483/2014003 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Highway CC and Highway O Steedman, MO Dates: March 22 through June 20, 2014 Inspectors: T. Hartman, Senior Resident Inspector Z. Hollcraft, Resident Inspector J. Braisted, Reactor Inspector P. Elkmann, Senior Emergency Preparedness Inspector G. George, Senior Reactor Inspector P. Jayroe, Reactor Inspector D. Proulx, Senior Project Engineer R. Stroble, Resident Inspector Approved By: N. O'Keefe Chief, Project Branch B Division of Reactor Projects
| | U.S. NUCLEAR REGULATORY COMMISSION |
| -2- Enclosure SUMMARY IR 05000483/2014003; 03/22/2014 - 06/20/2014; Callaway Plant, Integrated Resident and Regional Report; Operability Determinations and Functionality Assessments, and Other Activities. The inspection activities described in this report were performed between March 22 and June 20, 2014, by the resident inspectors at the Callaway Plant and other inspectors from Region IV. Two findings of very low safety significance (Green) are documented in this report. One finding involved a violation of NRC requirements. The significance of inspection findings is indicated by their color (Green, White, Yellow, or Red), which is determined using Inspection Manual Chapter 0609, "Significance Determination Process." Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Components Within the Cross-Cutting Areas." Violations of NRC requirements are dispositioned in accordance with the NRC Enforcement Policy. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process." Cornerstone: Mitigating Systems Green. The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," for the licensee's failure to perform an adequate extent of condition assessment. While performing an evaluation of pitting corrosion identified on buried refueling water storage piping, the licensee failed to provide an adequate technical justification for not expanding the scope of their review beyond the specific piping when pitting corrosion was identified in the original sample selection. Licensee procedural guidance for a Significance Level 3 adverse condition requires the reviewer to identify other potentially susceptible systems or components and fully explain the boundary for the extent of condition, but this was not done. This finding does not represent an immediate safety concern. The licensee entered the finding into their corrective action program as Callaway Action Request 201402168. This finding affected safety-related piping in which pitting was observed and repaired prior to being returned to service. The licensee's failure to perform an adequate extent of condition review of the pitting of the buried 24-inch refueling water storage tank piping in the essential core cooling system supply line is a performance deficiency. The performance deficiency is more than minor, and therefore a finding, because if left uncorrected, it has the potential to lead to a more significant safety concern if other welds on this same pipe render it susceptible to pitting corrosion in the weld heat affected zone. The finding affects the Mitigating System Cornerstone because the performance deficiency is related to the essential core cooling system's ability to conduct short-term decay heat removal. The finding is of very low safety significance (Green) because the finding is not a design or qualification deficiency, did not result in the loss of operability or functionality of a single train for greater than the technical specification allowed outage time, and did not represent an actual loss of safety function for greater than 24 hours. This finding has a cross-cutting aspect in the conservative bias component of the human performance cross-cutting area because the licensee did not use conservative decision-making practices that emphasize prudent choices over those that are simply allowable [H.14]. (Section 4OA5)
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| | ==REGION IV== |
| | Docket: 05000483 License: NPF-30 Report: 05000483/2014003 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Highway CC and Highway O Steedman, MO Dates: March 22 through June 20, 2014 Inspectors: T. Hartman, Senior Resident Inspector Z. Hollcraft, Resident Inspector J. Braisted, Reactor Inspector P. Elkmann, Senior Emergency Preparedness Inspector G. George, Senior Reactor Inspector P. Jayroe, Reactor Inspector D. Proulx, Senior Project Engineer R. Stroble, Resident Inspector Approved By: N. OKeefe Chief, Project Branch B Division of Reactor Projects-1- Enclosure |
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| | SUMMARY IR 05000483/2014003; 03/22/2014 - 06/20/2014; Callaway Plant, Integrated Resident and Regional Report; Operability Determinations and Functionality Assessments, and Other Activities. |
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| | The inspection activities described in this report were performed between March 22 and June 20, 2014, by the resident inspectors at the Callaway Plant and other inspectors from Region IV. Two findings of very low safety significance (Green) are documented in this report. One finding involved a violation of NRC requirements. The significance of inspection findings is indicated by their color (Green, White, Yellow, or Red), which is determined using Inspection Manual Chapter 0609, Significance Determination Process. |
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| | Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, Components Within the Cross-Cutting Areas. Violations of NRC requirements are dispositioned in accordance with the NRC Enforcement Policy. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process. |
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| | Cornerstone: Mitigating Systems |
| | * Green. The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensees failure to perform an adequate extent of condition assessment. While performing an evaluation of pitting corrosion identified on buried refueling water storage piping, the licensee failed to provide an adequate technical justification for not expanding the scope of their review beyond the specific piping when pitting corrosion was identified in the original sample selection. |
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| | Licensee procedural guidance for a Significance Level 3 adverse condition requires the reviewer to identify other potentially susceptible systems or components and fully explain the boundary for the extent of condition, but this was not done. This finding does not represent an immediate safety concern. The licensee entered the finding into their corrective action program as Callaway Action Request 201402168. This finding affected safety-related piping in which pitting was observed and repaired prior to being returned to service. |
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| | The licensees failure to perform an adequate extent of condition review of the pitting of the buried 24-inch refueling water storage tank piping in the essential core cooling system supply line is a performance deficiency. The performance deficiency is more than minor, and therefore a finding, because if left uncorrected, it has the potential to lead to a more significant safety concern if other welds on this same pipe render it susceptible to pitting corrosion in the weld heat affected zone. The finding affects the Mitigating System Cornerstone because the performance deficiency is related to the essential core cooling systems ability to conduct short-term decay heat removal. The finding is of very low safety significance (Green) because the finding is not a design or qualification deficiency, did not result in the loss of operability or functionality of a single train for greater than the technical specification allowed outage time, and did not represent an actual loss of safety function for greater than 24 hours. This finding has a cross-cutting aspect in the conservative bias component of the human performance cross-cutting area because the licensee did not use conservative decision-making practices that emphasize prudent choices over those that are simply allowable [H.14]. (Section 4OA5) |
| | -2- Enclosure |
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Category:Inspection Report
MONTHYEARIR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 IR 05000483/20240022024-07-18018 July 2024 and Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections IR 05000483/20230012023-04-12012 April 2023 Integrated Inspection Report 05000483/2023001 IR 05000483/20234022023-03-29029 March 2023 NRC Security Baseline Inspection Report 05000483/2023402 IR 05000483/20220062023-03-0101 March 2023 Annual Assessment Letter for Callaway Plant (Report 05000483/2022006) ML23019A0802023-01-19019 January 2023 Notification of Comprehensive Engineering Team Inspection (05000483/2023011) and Request for Information IR 05000483/20220042023-01-12012 January 2023 Integrated Inspection Report 05000483/2022004 IR 05000483/20220132022-11-15015 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2022013 IR 05000483/20220032022-10-17017 October 2022 Integrated Inspection Report 05000483/2022003 IR 05000483/20220102022-10-12012 October 2022 Biennial Problem Identification and Resolution Inspection Report 05000483-2022010 - Draft IR 05000483/20224032022-09-27027 September 2022 Security Baseline Inspection Report 05000483/2022403 IR 05000483/20220052022-08-23023 August 2022 Updated Inspection Plan for Callaway Plant (Report 05000483/2022005) IR 05000483/20224022022-08-11011 August 2022 NRC Security Inspection Report 05000483/2022402 (Cover Letter Only) IR 05000483/20220112022-08-0202 August 2022 Triennial Fire Protection Inspection Report 05000483 2022011 IR 05000483/20220022022-07-27027 July 2022 Integrated Inspection Report 05000483/2022002 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information IR 05000483/20220402022-05-0606 May 2022 95001 Supplemental Inspection Report 05000483/2022040 and Follow-Up Assessment Letter IR 05000483/20224012022-05-0505 May 2022 Cyber Security Inspection Report 05000483/2022401 IR 05000483/20220012022-04-26026 April 2022 Integrated Inspection Report 05000483/2022001 IR 05000483/20223012022-04-12012 April 2022 NRC Examination Report 05000483/2022301 ML22082A2012022-03-28028 March 2022 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2022011) and Request for Information IR 05000483/20224042022-03-24024 March 2022 Final Security Baseline Inspection Report 05000483/2022404 (Letter) IR 05000483/20210062022-03-0202 March 2022 Annual Assessment Letter for Callaway Plant (Report 05000483/2021006) IR 05000483/20210042022-01-0707 January 2022 Integrated Inspection Report - 05000483/2021004 IR 05000483/20210032021-11-0808 November 2021 Integrated Inspection Report 05000483/2021003 IR 05000483/20214202021-10-29029 October 2021 NRC Security Baseline Inspection Cover Letter 050004832021420 IR 05000483/20214022021-10-26026 October 2021 Security Baseline Inspection Report 05000483/2021402 IR 05000483/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Callaway Plant (Report 05000483/2021005) IR 05000483/20210022021-08-0505 August 2021 Integrated Inspection Report 05000483/2021002 and Independent Spent Fuel Storage Installation Report 07201045/2021001 IR 05000483/20214012021-05-26026 May 2021 Security Baseline Inspection Report 05000483/2021401 IR 05000483/20210012021-05-11011 May 2021 Integrated Inspection Report 05000483/2021001 IR 05000483/20214032021-04-15015 April 2021 Material Control and Accounting Program Inspection Report 05000483-2021403 (Public) IR 05000483/20200042021-02-0909 February 2021 CWY2020004-RP-DSB, Callaway Plant - Integrated Inspection Report and Assessment Follow-Up Letter (05000483/2020004) IR 05000483/20200032020-11-0202 November 2020 Integrated Inspection Report 05000483/2020003 IR 05000483/20204112020-10-27027 October 2020 Security Baseline Inspection Report 05000483/2020411 IR 05000483/20203012020-10-13013 October 2020 NRC Examination Report 05000483/2020301 2024-08-05
[Table view] Category:Letter
MONTHYEARIR 05000483/20253012024-08-0505 August 2024 Notification of NRC Initial Operator Licensing Examination 05000483/2025301 ML24212A2822024-08-0202 August 2024 Regulatory Audit Summary Concerning Review of Request No. C3R-01 for Proposed Alternative to ASME Code, Section XI Requirements for Containment Building Inspections IR 05000483/20240022024-07-18018 July 2024 and Independent Spent Fuel Storage Installation Integrated Inspection Report 05000483/2024002 and 07201045/2024001 ML24185A1032024-07-16016 July 2024 2024 Biennial Problem Identification and Resolution Inspection Report ULNRC-06891, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00052024-06-26026 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0005 ULNRC-06892, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00062024-06-26026 June 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0006 ULNRC-06884, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00022024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0002 ULNRC-06886, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00042024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0004 ULNRC-06885, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00032024-06-12012 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0003 ML24144A0492024-06-11011 June 2024 Requests for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML24178A1132024-06-0606 June 2024 Ameren Missouris Intent to Adopt Revision 1 to Amendment 0 of Certificate of Compliance No. 1040 as Applicable to the ISFSI at the Callaway Plant Site ML24158A5222024-06-0606 June 2024 Application to Revise Technical Specifications to Adopt Tstf-569, Rev. 2, Revise Response Time Testing Definition (LDCN 24-0008) ML24143A1632024-05-23023 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Storage Canister HGMPC0001 ULNRC-06882, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC00122024-05-16016 May 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0012 ML24137A2342024-05-16016 May 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Canister HGMPC0011 ML24122A1502024-05-0707 May 2024 Audit Plan to Support Review of Steam Generator License Renewal Response to Commitment Nos 34 and 35 IR 05000483/20244022024-05-0606 May 2024 Security Baseline Inspection Report 05000483/2024402 (Full Report) ULNRC-06877, Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 252024-05-0606 May 2024 Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25 ULNRC-06856, CFR 50.59 and 10 CFR 72.48 Summary Report2024-05-0101 May 2024 CFR 50.59 and 10 CFR 72.48 Summary Report IR 05000483/20240112024-05-0101 May 2024 NRC Post-Approval Site Inspection for License Renewal (Phase 2) Report 05000483/2024011 ML24122A1132024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radioactive Effluent Release Report ULNRC-06869, Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024 Submittal of Callaway, Unit 1, 2023 Annual Radiological Environmental Operating Report ULNRC-06876, Registration of Dry Spent Fuel Storage Canister HGMPC00102024-04-25025 April 2024 Registration of Dry Spent Fuel Storage Canister HGMPC0010 ULNRC-06872, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00082024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0008 ML24108A1082024-04-17017 April 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Canister HGMPC0009 ULNRC-06871, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC00072024-04-17017 April 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Canister HGMPC0007 ULNRC-06866, Submittal of Cycle 26 Commitment Change Summary Report2024-04-17017 April 2024 Submittal of Cycle 26 Commitment Change Summary Report IR 05000483/20240012024-04-16016 April 2024 Integrated Inspection Report 05000483/2024001 IR 05000483/20244042024-04-0909 April 2024 Cyber Security Inspection Report 05000483/2024404 05000483/LER-2024-001, Submittal of LER 2024-001-00 for Callaway Plant, Unit 1, Reactor Trip Due to Turbine Trip2024-04-0404 April 2024 Submittal of LER 2024-001-00 for Callaway Plant, Unit 1, Reactor Trip Due to Turbine Trip ULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) 2024-08-05
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Text
ber 10, 2014
SUBJECT:
ERRATA - CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003
Dear Mr. Diya:
Please remove the cover page, and enclosure pages 1 and 2, from the Callaway Plant -
NRC Integrated Inspection Report 05000483/20140003 (ML14216A691), and replace them with the pages enclosed with this letter. The purpose of this change is to correct the inspection period dates and minor typographical errors on these pages.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agencywide Documents 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).
Sincerely,
/RA/
Neil OKeefe, Branch Chief Project Branch B Division of Reactor Projects Docket Nos.: 50-483 License Nos: NPF-30 Enclosure:
NRC Inspection Report 05000483/2014003
Letter to Fadi Diya from Neil OKeefe, dated September 10, 2014 SUBJECT: ERRATA - CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003 DISTRIBUTION:
Regional Administrator (Marc.Dapas@nrc.gov)
Deputy Regional Administrator (Kriss.Kennedy@nrc.gov)
Acting DRP Director (Troy.Pruett@nrc.gov)
Acting DRP Deputy Director (Michael.Hay@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
DRS Deputy Director (Jeff.Clark@nrc.gov)
Senior Resident Inspector (Thomas.Hartman@nrc.gov)
Resident Inspector (Zachary.Hollcraft@nrc.gov)
Branch Chief, DRP/B (Neil.OKeefe@nrc.gov)
Senior Project Engineer, DRP/B (David.Proulx@nrc.gov)
Project Engineer, DRP/B (Fabian.Thomas@nrc.gov)
CW Administrative Assistant (Dawn.Yancey@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Fred.Lyon@nrc.gov)
Branch Chief, DRS/TSB (Geoffrey.Miller@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
ACES (R4Enforcement.Resource@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
Technical Support Assistant (Loretta.Williams@nrc.gov)
Congressional Affairs Officer (Jenny.Weil@nrc.gov)
RIV/ETA: OEDO (John.Jandovitz@nrc.gov)
ROPreports Electronic Distribution for Callaway Plant ADAMS ACCESSION NUMBER: ML142533A503/ADAMS Pkg ML14253A505 SUNSI Review ADAMS Publicly Available Non-Sensitive By: N. O'Keefe Yes No Non-Publicly Sensitive Available OFFICE C:DRP/RPBB NAME NOKEEFE/dll SIGNATURE /RA/
DATE 9/10/14
UNITED STATES ust 4, 2014
SUBJECT:
CALLAWAY PLANT - NRC INTEGRATED INSPECTION REPORT 05000483/2014003
Dear Mr. Diya:
On June 20, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Callaway Plant. On July 1, 2014, the NRC inspectors discussed the results of this inspection with you and members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
NRC inspectors documented two findings of very low safety significance (Green) in this report.
One of these findings involved a violation of NRC requirements. Further, inspectors documented a licensee-identified violation, which was determined to be of very low safety significance. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the NRC Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC resident inspector at the Callaway Plant.
If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement 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 inspector at the Callaway Plant.
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket: 05000483 License: NPF-30 Report: 05000483/2014003 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Highway CC and Highway O Steedman, MO Dates: March 22 through June 20, 2014 Inspectors: T. Hartman, Senior Resident Inspector Z. Hollcraft, Resident Inspector J. Braisted, Reactor Inspector P. Elkmann, Senior Emergency Preparedness Inspector G. George, Senior Reactor Inspector P. Jayroe, Reactor Inspector D. Proulx, Senior Project Engineer R. Stroble, Resident Inspector Approved By: N. OKeefe Chief, Project Branch B Division of Reactor Projects-1- Enclosure
SUMMARY IR 05000483/2014003; 03/22/2014 - 06/20/2014; Callaway Plant, Integrated Resident and Regional Report; Operability Determinations and Functionality Assessments, and Other Activities.
The inspection activities described in this report were performed between March 22 and June 20, 2014, by the resident inspectors at the Callaway Plant and other inspectors from Region IV. Two findings of very low safety significance (Green) are documented in this report. One finding involved a violation of NRC requirements. The significance of inspection findings is indicated by their color (Green, White, Yellow, or Red), which is determined using Inspection Manual Chapter 0609, Significance Determination Process.
Their cross-cutting aspects are determined using Inspection Manual Chapter 0310, Components Within the Cross-Cutting Areas. Violations of NRC requirements are dispositioned in accordance with the NRC Enforcement Policy. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.
Cornerstone: Mitigating Systems
- Green. The inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensees failure to perform an adequate extent of condition assessment. While performing an evaluation of pitting corrosion identified on buried refueling water storage piping, the licensee failed to provide an adequate technical justification for not expanding the scope of their review beyond the specific piping when pitting corrosion was identified in the original sample selection.
Licensee procedural guidance for a Significance Level 3 adverse condition requires the reviewer to identify other potentially susceptible systems or components and fully explain the boundary for the extent of condition, but this was not done. This finding does not represent an immediate safety concern. The licensee entered the finding into their corrective action program as Callaway Action Request 201402168. This finding affected safety-related piping in which pitting was observed and repaired prior to being returned to service.
The licensees failure to perform an adequate extent of condition review of the pitting of the buried 24-inch refueling water storage tank piping in the essential core cooling system supply line is a performance deficiency. The performance deficiency is more than minor, and therefore a finding, because if left uncorrected, it has the potential to lead to a more significant safety concern if other welds on this same pipe render it susceptible to pitting corrosion in the weld heat affected zone. The finding affects the Mitigating System Cornerstone because the performance deficiency is related to the essential core cooling systems ability to conduct short-term decay heat removal. The finding is of very low safety significance (Green) because the finding is not a design or qualification deficiency, did not result in the loss of operability or functionality of a single train for greater than the technical specification allowed outage time, and did not represent an actual loss of safety function for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This finding has a cross-cutting aspect in the conservative bias component of the human performance cross-cutting area because the licensee did not use conservative decision-making practices that emphasize prudent choices over those that are simply allowable [H.14]. (Section 4OA5)
-2- Enclosure