IR 05000483/2014003

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Errata to IR 05000483/2014003, March 22, 2014 through June 20, 2014, Callaway Plant - NRC Integrated Inspection
ML14253A503
Person / Time
Site: Callaway Ameren icon.png
Issue date: 09/10/2014
From: O'Keefe N F
NRC/RGN-IV/DRP
To: Diya F
Union Electric Co
References
IR 2014003
Download: ML14253A503 (5)


Text

September 10, 2014

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

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 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).

Sincerely,/RA/ Neil O'Keefe, 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 O'Keefe, 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: 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

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.

-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

-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 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)