ML18131A260
ML18131A260 | |
Person / Time | |
---|---|
Site: | 99901419 |
Issue date: | 05/11/2018 |
From: | Jonathan Ortega-Luciano NRC/NRO/DCIP/QVIB2 |
To: | Kerri Kavanagh NRC/NRO/DCIP/QVIB2 |
Ortega-Luciano J, NRO/DCIP | |
References | |
IR 2012201 | |
Download: ML18131A260 (5) | |
Text
May 11, 2018 MEMORANDUM TO: Kerri A. Kavanagh, Chief Quality Assurance Vendor Inspection Branch-2 Division of Construction Inspection and Operational Programs Office of New Reactors FROM: Jonathan Ortega-Luciano /RA/ KKavanagh for Reactor Operations Engineer Quality Assurance Vendor Inspection Branch-2 Division of Construction Inspection and Operational Programs Office of New Reactors
SUBJECT:
CLOSURE OF INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA RELATED-FINDING FOR CIVES STEEL COMPANY INSPECTION REPORT NO. 99901419/2012-201 The purpose of this memorandum is to document the U.S. Nuclear Regulatory Commission (NRC) staffs closure of the Notice of Nonconformance (NON) documented in Cives Steel Company (hereafter referred to as Cives) Inspection Report (IR) No. 99901419/2012-201, dated March 19, 2013 (Agencywide Document Access and Management System (ADAMS) Accession No. ML13042A397).
On December 10-14, 2012, the NRC staff completed an inspection at the Cives facility in Thomasville, GA. The purpose of this technically-focused, limited-scope inspection was to evaluate Cives implementation of quality activities associated with the fabrication of concrete embedments for the Westinghouse Electric Companys (WEC) AP1000 reactor design for the Vogtle Electric Generating Plant, Units 3 and 4, currently under construction.
In IR No. 99901419/2012-201, the NRC staff issued Notice of Nonconformance (NON) 99901419/2012-201-03, which the NRC staff determined that two of the examples documented in this NON were material to the acceptance criteria of inspections, tests, analyses, and acceptance criteria (ITAAC) No. 3.3.00.02a.i.a (760), 3.3.00.02a.i.b (761), 3.3.00.02a.i.c (762),
and 3.3.00.02a.i.d (763) from Revision 19 of the certified AP1000 Design Control Document.
CONTACT: Jonathan Ortega-Luciano, NRO/DCIP 301-415-1159
K. Kavanagh NON 99901419/2012-201-03 documents a finding against Criterion X, Inspection, of Appendix B, Quality Assurance Program Criteria for Nuclear Power Plants and Fuel Processing Plants, to Title to 10 of the Code of Federal Regulations Part 50, Domestic Licensing of Production and Utilization Facilities, for Cives failure to adequately identify a stud that did not show a full 360-degree flash and to test at least 1 out of every 100 studs welded by each operator in accordance with applicable procedures, design requirements, and industry standards.
In letters dated April 16, 2013 (ADAMS Accession No. ML13109A020), August 16, 2013 (ADAMS Accession No. ML13240A039), and October 2, 2013 (ADAMS Accession No. ML13281A243), Cives described their corrective actions to address the issues identified in NON 99901419/2012-201-03.
The NRC staff reviewed Cives corrective actions taken to address the issues identified in NON 99901419/2012-201-03. Based on this review, the NRC staff has determined that the corrective actions taken by Cives are adequate to address the identified nonconformance.
NON 99901419/2012-201-03 is closed and no additional inspection follow-up is required to verify completion/adequacy of the corrective actions.
Enclosure:
Summary of NRC Inspection of Cives Affecting ITAAC
ML18131A260 NRO-002 OFFICE NRO/DCIP NRO/DCIP NAME JOrtega-Luciano KKavanagh (PPrescott for)
DATE 05/11/18 05/11/18 Summary of NRC Inspection of Cives Affecting ITAAC
- 1. AFFECTED INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA The U.S. Nuclear Regulatory Commission (NRC) inspectors identified the following inspection, test, analysis, and acceptance criteria (ITAAC) related to components being fabricated by Cives Steel Company (here after referred to as Cives). For the ITAAC listed below, the NRC staff reviewed Cives corrective actions in response to Notice of Nonconformance (NON) 99901419/2012-201-03. The ITAACs design commitment referenced below are for future use by the NRC staff during the ITAAC closure process; the listing of these ITAAC design commitments does not constitute that they have been met and closed. The NRC staff identified one finding associated with the ITAAC identified below.
Source Document ITAAC Index No. ITAAC Acceptance Criteria i.a) A report exists which reconciles deviations during construction and concludes that the as-built Appendix C from the containment internal structures, Combined License including the critical sections, for Vogtle Electric No. 760 3.3.00.02a.i.a conform to the approved design and Generating Plant will withstand the design basis loads Units 3 and 4 specified in the Design Description without loss of structural integrity or the safety-related functions.
i.b) A report exists which reconciles deviations during construction and concludes that the as-built shield Appendix C from the building structures, including the Combined License critical sections, conform to the for Vogtle Electric No. 761 3.3.00.02a.i.b approved design and will withstand Generating Plant the design basis loads specified in Units 3 and 4 the Design Description without loss of structural integrity or the safety-related functions.
i.c) A report exists which reconciles deviations during construction and concludes that the as-built structures in the non-radiologically Appendix C from the controlled area of the auxiliary Combined License building, including the critical for Vogtle Electric No. 762 3.3.00.02a.i.c sections, conform to the approved Generating Plant design and will withstand the design Units 3 and 4 basis loads specified in the Design Description without loss of structural integrity or the safety-related functions.
Enclosure
i.d) A report exists which reconciles deviations during construction and concludes that the as-built structures in the radiologically Appendix C from the controlled area of the auxiliary Combined License building, including the critical for Vogtle Electric No. 763 3.3.00.02a.i.d sections, conform to the approved Generating Plant design and will withstand the design Units 3 and 4 basis loads specified in the Design Description without loss of structural integrity or the safety-related functions.
- 2. FINDINGS AND OBSERVATIONS Based on review of the additional information, the NRC staff has determined that the corrective actions taken by Cives in response to NON 99901419/2012-201-03 is adequate to address the identified nonconformances. NON 99901419/2012-201-03 is closed and no additional inspection follow-up is required to verify completion/adequacy of the corrective actions.
- 3. ITEMS OPENED, CLOSED, AND DISCUSSED Item Number Status Type Description Applicable ITAAC 3.3.00.02a.i.a, 3.3.00.02a.i.b, 99901419/2012-201-03 CLOSED NON Criterion X 3.3.00.02a.i.c, and 3.3.00.02a.i.d