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| The Reactor Operator (RO) applicant passed the retake operating test. A waiver was granted for the written examination and the simulator portion of the operating test. There were no post- | | The Reactor Operator (RO) applicant passed the retake operating test. A waiver was granted for the written examination and the simulator portion of the operating test. There were no post- |
| examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2. The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/ reading-rm/adams.html (the Public Electronic Reading Room). If you have any questions concerning this letter, please contact me at (404) 997-4662. | | examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2. The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/ reading-rm/adams.html (the Public Electronic Reading Room). If you have any questions concerning this letter, please contact me at (404) 997-4662. |
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| Sincerely,/RA: Gerald J. McCoy for/ Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79
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| ===Enclosures:===
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| 1. Report Details 2. Simulator Fidelity Report cc: Distribution via Listserv If you have any questions concerning this letter, please contact me at (404) 997-4662.
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| Sincerely,/RA: Gerald J. McCoy for/ Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79 | | Sincerely,/RA: Gerald J. McCoy for/ Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79 |
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| 1. Report Details 2. Simulator Fidelity Report cc: Distribution via Listserv | | 1. Report Details 2. Simulator Fidelity Report cc: Distribution via Listserv |
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| PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:____________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE DXB2 VIA EMAIL GJM1 DOR EFG NAME BACON GUTHRIE DATE 9/12/2016 9/12/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\OLEXAMS\SEQUOYAH EXAMINATIONS\RE-EXAM 2016-302\CORRESPONDENCE\SEQUOYAH 2016-302 EXAM REPORT.DOCX Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II
| | ____________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE DXB2 VIA EMAIL GJM1 DOR EFG NAME BACON GUTHRIE DATE 9/12/2016 9/12/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II |
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| Docket No.: 50-327, 50-328 | | Docket No.: 50-327, 50-328 |
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Category:Letter
MONTHYEARML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 2024-09-08
[Table view] Category:License-Operator Examination Report
MONTHYEARML24211A0542024-07-29029 July 2024 Operator License Examination Report IR 05000237/20203012020-08-27027 August 2020 NRC Initial License Examination Report 05000237/2020301; 05000249/2020301 IR 05000327/20203012020-04-24024 April 2020 NRC Operator License Examination Report 05000327/2020301 and 05000328/2020301 IR 05000327/20173012018-02-15015 February 2018 NRC Operator License Examination Reports 05000327/2017301 and 05000328/2017301 IR 05000327/20163022016-09-12012 September 2016 NRC Operator License Examination Report 05000327/2016302 and 05000328/2016302 IR 05000327/20163012016-05-10010 May 2016 NRC Operator License Examination Report 05000327/2016301 and 05000328/2016301, March 7-11, 2016, Written Examination March 23, 2016 IR 05000327/20153012015-04-23023 April 2015 Er 05000327/2015301, 05000328/2015301, March 2-11, 2015 & March 18, 2015; Sequoyah Nuclear Plant; Operator License Examinations ML14069A5222014-03-0505 March 2014 Confirmation of Requested Initial Operator License Examinations for Sequoyah Nuclear Plant IR 05000327/20133022014-01-23023 January 2014 Er 05000327-13-302, 05000328-13-302, December 2 - 10, 2013 & December 18, 2013; Sequoyah Nuclear Plant; Operator License Examinations IR 05000327/20133012013-06-25025 June 2013 Operator License Examination Report 05000327/13-301, 05/13-16/2013, Sequoyah ML13161A0632013-06-10010 June 2013 Initial Exam 2013-301 Final RO Written Exam ML13161A0642013-06-10010 June 2013 Initial Exam 2013-301 Final SRO Written Exam IR 05000327/20123022013-02-0404 February 2013 Er 05000327-12-302, 05000328-12-302, on 12/3 - 6/2012 & 12/12/2012, Sequoyah Nuclear Plant, Operator License Examinations IR 05000327/20123012012-03-0606 March 2012 Er 05000327-12-301, 05000328-12-301, 01/17-25/2012 & 02/1/2012; Sequoyah Nuclear Plant; Operator License Examinations IR 05000327/20103022010-12-23023 December 2010 Er 05000327-10-302, 05000328-10-302, 09/13-22/2010 & 09/29/2010; Sequoyah Nuclear Plant; Operator License Examinations IR 05000237/20103012010-04-16016 April 2010 Er 05000237-10-301(DRS), 05000249-10-301(DRS), on 2/8/2010 - 3/17/2010, Exelon Nuclear Generating Company, LLC, Dresden Station, Initial License Examination Report IR 05000327/20103012010-03-29029 March 2010 Er 05000327/10-301 and 05000328/10-301 on 02/16/10 - 02/22/10 for Sequoyah, Unit 1 & 2, Operator License Examination ML0907200372009-03-13013 March 2009 Operator License Exam Report 05000327-09-301 and 05000328-09-301 on 01/20/09 - 01/29/09 for Sequoyah Nuclear Plant, Units 1 & 2 ML0805703882008-02-25025 February 2008 Er 05000327-08-301, 05000328-08-301, on 1/28-2/8/2008, Sequoyah Nuclear Power Plant, Units 1 and 2; Licensed Operator Examinations ML0716602712007-06-15015 June 2007 Er 05000327-07-301, 05000328-07-301; 4/9-5/9/2007; Sequoyah Nuclear Power Plant, Units 1 and 2; Licensed Operator Examinations ML0526601132005-09-20020 September 2005 Preparation and Scheduling of Operator License Examinations - NRC Regulatory Issue Summary (RIS) 2005-19 ML0306904742003-03-0707 March 2003 NRC Examination Report 50-327/03-301 and 50-328/03-301 2024-07-29
[Table view] |
Text
September 12, 2016
Joseph Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402
SUBJECT: SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000327/2016302 AND 05000328/2016302
Dear Mr. Shea:
On July 28, 2016, the Nuclear Regulatory Commission (NRC) administered a walk-through and administrative topics retake operating test to an employee of your company who had applied for a license to operate the Sequoyah Nuclear Plant. At the conclusion of the test, the examiner discussed preliminary findings related to the operating test with those members of your staff identified in the enclosed report.
The Reactor Operator (RO) applicant passed the retake operating test. A waiver was granted for the written examination and the simulator portion of the operating test. There were no post-
examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2. The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/ reading-rm/adams.html (the Public Electronic Reading Room). If you have any questions concerning this letter, please contact me at (404) 997-4662.
Sincerely,/RA: Gerald J. McCoy for/ Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79
Enclosures:
1. Report Details 2. Simulator Fidelity Report cc: Distribution via Listserv
____________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE DXB2 VIA EMAIL GJM1 DOR EFG NAME BACON GUTHRIE DATE 9/12/2016 9/12/2016 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II
Docket No.: 50-327, 50-328
License No.: DRP-77, DPR-79
Report No.: 05000327/2016302, 05000328/2016302 Licensee: Tennessee Valley Authority (TVA) Facility: Sequoyah Nuclear Plant, Units 1 & 2 Location: Sequoyah Access Road Soddy-Daisy, TN 37379 Dates: Operating Test-July 28, 2016 Examiners: D. Bacon, Chief Examiner, Senior Operations Engineer Approved by: Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety SUMMARY ER 05000327/2016302, 05000328/2016302, July 28, 2016; Sequoyah Nuclear Plant; Operator License Examinations.
A Nuclear Regulatory Commission (NRC) examiner conducted a walk-through and administrative topics retake operating examination in accordance with the guidelines in Revision 10, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable. Members of the Sequoyah Nuclear Plant staff developed the retake operating test. The retake operating test submittal met the quality guidelines contained in NUREG-1021. The NRC administered the retake operating test on July 28, 2016. The simulator portion of the operating test and the written examination were waived. One Reactor Operator (RO) applicant passed the retake operating test. The applicant was issued a license commensurate with the level of examination administered.
There were no post-examination comments.
No findings were identified.
REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Operator Licensing Examinations a. Inspection Scope The NRC evaluated the submitted retake operating test by determining the percentage of submitted JPMs that required replacement or significant modification. The percentage of submitted test items that were unacceptable was compared to the acceptance criteria of NUREG-1021, "Operator Licensing Standards for Power Reactors." The NRC reviewed the licensee's examination security measures while preparing and administering the retake operating test in order to ensure compliance with 10 CFR §55.49, "Integrity of examinations and tests." The NRC administered the retake operating test on July 28, 2016. The NRC examiner evaluated one Reactor Operator (RO) applicant using the guidelines contained in NUREG-
1021. Evaluation of the applicant and review of associated documentation was performed to determine if the applicant, who applied for a license to operate the Sequoyah Nuclear Plant, met the requirements specified in 10 CFR Part 55, "Operators' Licenses." The NRC evaluated the performance or fidelity of the simulation facility during the preparation and conduct of the retake operating test. b. Findings No findings were identified.
Members of the Sequoyah Nuclear Plant training staff developed the retake operating test.
All examination material was developed in accordance with the guidelines contained in Revision 10 of NUREG-1021. The NRC examiner reviewed the proposed examination. Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021 and incorporated into the final version of the examination materials. The NRC determined, using NUREG-1021, that the licensee's retake operating test submittal was within the range of acceptability expected for a proposed examination.
One RO applicant passed the retake operating test. The applicant was issued a license. A copy of the individual examination report was sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training. The licensee did not submit any post-examination comments. 4OA6 Meetings, Including Exit Exit Meeting Summary On July 28, 2016, the NRC examination team discussed generic issues associated with the retake operating test with K. Smith, Director of Training, and members of the Sequoyah Nuclear Plant staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.
KEY POINTS OF CONTACT Licensee personnel K. Smith, Director of Training M. McMullin, Manager of Operations Training J. Johnson, Licensing T. Rieger, Operations W. Harris, Operations/Training A. Roddy, Operations/Training Enclosure 2 SIMULATOR FIDELITY REPORT Facility Licensee: Sequoyah Nuclear Plant Facility Docket No.: 50-327, 50-328 Operating Test Administered: July 28, 2016 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with Inspection Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations. No simulator fidelity or configuration issues were identified.