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| | issue date = 12/05/2017 | | | issue date = 12/05/2017 |
| | title = Reissue - Assessment Follow-up Letter for Vogtle Electric Generating Plant - NRC Inspection Report 05000424/2017013 and 05000425/2017013 | | | title = Reissue - Assessment Follow-up Letter for Vogtle Electric Generating Plant - NRC Inspection Report 05000424/2017013 and 05000425/2017013 |
| | author name = Munday J T | | | author name = Munday J |
| | author affiliation = NRC/RGN-II/DRP | | | author affiliation = NRC/RGN-II/DRP |
| | addressee name = Myers D | | | addressee name = Myers D |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES ecember 5, 2017 |
| [[Issue date::December 5, 2017]]
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| Mr. Darin Myers Vice President Southern Nuclear Operating Company, Inc.
| | ==SUBJECT:== |
| | | REISSUE - ASSESSMENT FOLLOWUP LETTER FOR VOGTLE ELECTRIC GENERATING PLANT - NRC INSPECTION REPORT 05000424/2017013 AND 05000425/2017013 |
| Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
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| SUBJECT: REISSUE - ASSESSMENT FOLLOWUP LETTER FOR VOGTLE ELECTRIC GENERATING PLANT - NRC INSPECTION REPORT 05000424/2017013 AND 05000425/2017013 | |
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| ==Dear Mr. Myers:== | | ==Dear Mr. Myers:== |
| On November 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) issued the assessment followup letter for Vogtle Electric Generating Plant - NRC inspection report (IR) 05000424/2017013 and 05000425/2017013, (ADAMS Accession Number ML17334A290). | | On November 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) issued the assessment followup letter for Vogtle Electric Generating Plant - NRC inspection report (IR) |
| | 05000424/2017013 and 05000425/2017013, (ADAMS Accession Number ML17334A290). |
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| In the subject section of the cover letter, we did not document the NRC inspection report number for the assessment followup letter. We request that the entire letter be replaced as the enclosure to this letter. | | In the subject section of the cover letter, we did not document the NRC inspection report number for the assessment followup letter. We request that the entire letter be replaced as the enclosure to this letter. |
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| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 "Public inspection, exemptions, requests for withholding" of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of from the Publicly Available records (PARS) component of NRC's ADAMS; accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact Alan Blamey at 404-997-4415 with any questions you have regarding this letter. | | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 Public inspection, exemptions, requests for withholding of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of from the Publicly Available records (PARS) component of NRCs ADAMS; accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| | Please contact Alan Blamey at 404-997-4415 with any questions you have regarding this letter. |
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| Sincerely,/RA/ | | Sincerely, |
| Joel T. Munday, Director Division of Reactor Projects Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Distribution via ListServ | | /RA/ |
| | Joel T. Munday, Director Division of Reactor Projects Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Distribution via ListServ |
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| ML 17339A701 OFFICE RII/DRP RII/DRP RII/DRP NAME JHickman ABlamey JMunday DATE 12/1/2017 12/1/2017 12/4/2017 Enclosure November 30, 2017 Mr. Darin Myers Vice President Southern Nuclear Operating Company, Inc.
| | ML17339A701 OFFICE RII/DRP RII/DRP RII/DRP NAME JHickman ABlamey JMunday DATE 12/1/2017 12/1/2017 12/4/2017 |
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| Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
| | UNITED STATES ber 30, 2017 |
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| SUBJECT: REISSUE - ASSESSMENT FOLLOWUP LETTER FOR VOGTLE ELECTRIC GENERATING PLANT - NRC INSPECTION REPORT 05000424/2017013 AND 05000425/2017013 | | ==SUBJECT:== |
| | REISSUE - ASSESSMENT FOLLOWUP LETTER FOR VOGTLE ELECTRIC GENERATING PLANT - NRC INSPECTION REPORT 05000424/2017013 AND 05000425/2017013 |
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| ==Dear Mr. Myers:== | | ==Dear Mr. Myers:== |
| As a result of our review of plant performance, which was completed on November 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) updated its assessment of Vogtle Electric Generating Plant. The NRC's evaluation consisted of a review of performance indicators (PIs) and inspection results. This letter informs you of the NRC's assessment of your facility and supplements, but does not supersede the mid-cycle letter issued on August 31, 2017. On April 24, 2017, the NRC forwarded a letter that stated the final significance determination of a White inspection finding in the Emergency Preparedness Cornerstone (NRC Inspection Report 05000424/2017-504 and 05000425/2017-504). Since this was identified on October 7, 2016, this White finding was considered an input to the Reactor Oversight Process (ROP) Action Matrix beginning in the fourth quarter of 2016. On August 31, 2017, the NRC completed a review of your corrective actions for the White inspection finding using Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The inspectors determined that your staff's evaluation identified the root and apparent cause of the White finding to a level of detail commensurate with the significance of the problems, and reached reasonable conclusions as to the root and contributing causes of the event. The NRC also concluded that you identified reasonable and appropriate corrective actions for each root and contributing cause, and that the corrective actions appeared to be prioritized commensurate with the safety significance of the issues. The NRC's inspection is documented in inspection report (IR) 05000424/2017011 and 05000425/2017011, which is publically available in the Agencywide Document Access and Management System (ADAMS) using accession number ML17286A120. After reviewing Vogtle Electric Generating Plant's performance in addressing the White finding subject of this Inspection Procedure 95001, "Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," the NRC concluded your actions met the objectives of this inspection procedure. Therefore, in accordance with the guidance in Inspection Manual Chapter (IMC) 0305, "Operating Reactor Assessment Program," the Enclosure White finding will only be considered in assessing plant performance for a total of four quarters. As a result, the NRC determined the performance at Vogtle Electric Generating Plant to be in the Licensee Response Column (Column 1) of the ROP Action Matrix as of October 1, 2017. | | As a result of our review of plant performance, which was completed on November 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) updated its assessment of Vogtle Electric Generating Plant. The NRCs evaluation consisted of a review of performance indicators (PIs) |
| | and inspection results. This letter informs you of the NRCs assessment of your facility and supplements, but does not supersede the mid-cycle letter issued on August 31, 2017. |
| | |
| | On April 24, 2017, the NRC forwarded a letter that stated the final significance determination of a White inspection finding in the Emergency Preparedness Cornerstone (NRC Inspection Report 05000424/2017-504 and 05000425/2017-504). Since this was identified on October 7, 2016, this White finding was considered an input to the Reactor Oversight Process (ROP) Action Matrix beginning in the fourth quarter of 2016. On August 31, 2017, the NRC completed a review of your corrective actions for the White inspection finding using Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The inspectors determined that your staffs evaluation identified the root and apparent cause of the White finding to a level of detail commensurate with the significance of the problems, and reached reasonable conclusions as to the root and contributing causes of the event. The NRC also concluded that you identified reasonable and appropriate corrective actions for each root and contributing cause, and that the corrective actions appeared to be prioritized commensurate with the safety significance of the issues. The NRCs inspection is documented in inspection report (IR) 05000424/2017011 and 05000425/2017011, which is publically available in the Agencywide Document Access and Management System (ADAMS) |
| | using accession number ML17286A120. |
| | |
| | After reviewing Vogtle Electric Generating Plants performance in addressing the White finding subject of this Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," the NRC concluded your actions met the objectives of this inspection procedure. Therefore, in accordance with the guidance in Inspection Manual Chapter (IMC) 0305, Operating Reactor Assessment Program, the Enclosure White finding will only be considered in assessing plant performance for a total of four quarters. As a result, the NRC determined the performance at Vogtle Electric Generating Plant to be in the Licensee Response Column (Column 1) of the ROP Action Matrix as of October 1, 2017. |
| | |
| | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 Public inspection, exemptions, requests for withholding of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of from the Publicly Available records (PARS) component of NRCs ADAMS; accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
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| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 "Public inspection, exemptions, requests for withholding" of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of from the Publicly Available records (PARS) component of NRC's ADAMS; accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Please contact Alan Blamey at 404-997-4415 with any questions you have regarding this letter.
| | Please contact Alan Blamey at 404-997-4415 with any questions you have regarding this letter. |
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| Sincerely,/RA/ | | Sincerely, |
| Joel T. Munday, Director Division of Reactor Projects Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Distribution via ListServ | | /RA/ |
| | Joel T. Munday, Director Division of Reactor Projects Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Distribution via ListServ Enclosure |
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| ML17334A290 OFFICE RII/DRP RII/DRP RII/DRP NAME JHickman ABlamey JMunday DATE 11/29/2017 11/29/2017 11/29/2017 | | ML17334A290 OFFICE RII/DRP RII/DRP RII/DRP NAME JHickman ABlamey JMunday DATE 11/29/2017 11/29/2017 11/29/2017 |
| }} | | }} |
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Category:Letter
MONTHYEARIR 05000424/20243012024-11-19019 November 2024 Operator Licensing Examination Approval 05000424/2024301 and 05000425/2024301 ML24313A0632024-11-14014 November 2024 Integrated Inspection Report and Assessment Follow-Up Letter 05200025/2024003 and 05200026/2024003 ML24305A1662024-11-0606 November 2024 Vogle Electric Generating Plant, Unit 3 - Summary of Conference Call Regarding the Fall 2024 Steam Generator Tube Inspections NL-24-0217, License Amendment Request: Source Range Neutron Flux Doubling Function Applicability2024-11-0101 November 2024 License Amendment Request: Source Range Neutron Flux Doubling Function Applicability NL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) 2024-09-09
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Inspection Report - Vogtle - 2017013 |
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UNITED STATES ecember 5, 2017
SUBJECT:
REISSUE - ASSESSMENT FOLLOWUP LETTER FOR VOGTLE ELECTRIC GENERATING PLANT - NRC INSPECTION REPORT 05000424/2017013 AND 05000425/2017013
Dear Mr. Myers:
On November 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) issued the assessment followup letter for Vogtle Electric Generating Plant - NRC inspection report (IR)
05000424/2017013 and 05000425/2017013, (ADAMS Accession Number ML17334A290).
In the subject section of the cover letter, we did not document the NRC inspection report number for the assessment followup letter. We request that the entire letter be replaced as the enclosure to this letter.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 Public inspection, exemptions, requests for withholding of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of from the Publicly Available records (PARS) component of NRCs ADAMS; accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact Alan Blamey at 404-997-4415 with any questions you have regarding this letter.
Sincerely,
/RA/
Joel T. Munday, Director Division of Reactor Projects Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Distribution via ListServ
ML17339A701 OFFICE RII/DRP RII/DRP RII/DRP NAME JHickman ABlamey JMunday DATE 12/1/2017 12/1/2017 12/4/2017
UNITED STATES ber 30, 2017
SUBJECT:
REISSUE - ASSESSMENT FOLLOWUP LETTER FOR VOGTLE ELECTRIC GENERATING PLANT - NRC INSPECTION REPORT 05000424/2017013 AND 05000425/2017013
Dear Mr. Myers:
As a result of our review of plant performance, which was completed on November 20, 2017, the U.S. Nuclear Regulatory Commission (NRC) updated its assessment of Vogtle Electric Generating Plant. The NRCs evaluation consisted of a review of performance indicators (PIs)
and inspection results. This letter informs you of the NRCs assessment of your facility and supplements, but does not supersede the mid-cycle letter issued on August 31, 2017.
On April 24, 2017, the NRC forwarded a letter that stated the final significance determination of a White inspection finding in the Emergency Preparedness Cornerstone (NRC Inspection Report 05000424/2017-504 and 05000425/2017-504). Since this was identified on October 7, 2016, this White finding was considered an input to the Reactor Oversight Process (ROP) Action Matrix beginning in the fourth quarter of 2016. On August 31, 2017, the NRC completed a review of your corrective actions for the White inspection finding using Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area." The inspectors determined that your staffs evaluation identified the root and apparent cause of the White finding to a level of detail commensurate with the significance of the problems, and reached reasonable conclusions as to the root and contributing causes of the event. The NRC also concluded that you identified reasonable and appropriate corrective actions for each root and contributing cause, and that the corrective actions appeared to be prioritized commensurate with the safety significance of the issues. The NRCs inspection is documented in inspection report (IR) 05000424/2017011 and 05000425/2017011, which is publically available in the Agencywide Document Access and Management System (ADAMS)
using accession number ML17286A120.
After reviewing Vogtle Electric Generating Plants performance in addressing the White finding subject of this Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area," the NRC concluded your actions met the objectives of this inspection procedure. Therefore, in accordance with the guidance in Inspection Manual Chapter (IMC) 0305, Operating Reactor Assessment Program, the Enclosure White finding will only be considered in assessing plant performance for a total of four quarters. As a result, the NRC determined the performance at Vogtle Electric Generating Plant to be in the Licensee Response Column (Column 1) of the ROP Action Matrix as of October 1, 2017.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 Public inspection, exemptions, requests for withholding of the NRCs Agency Rules of Practice and Procedure, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room, of from the Publicly Available records (PARS) component of NRCs ADAMS; accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact Alan Blamey at 404-997-4415 with any questions you have regarding this letter.
Sincerely,
/RA/
Joel T. Munday, Director Division of Reactor Projects Docket Nos.: 50-424 and 50-425 License Nos.: NPF-68 and NPF-81 Distribution via ListServ Enclosure
ML17334A290 OFFICE RII/DRP RII/DRP RII/DRP NAME JHickman ABlamey JMunday DATE 11/29/2017 11/29/2017 11/29/2017