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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
April 23, 2015
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000327/2015301 AND 05000328/2015301
Dear Mr. Shea:
During the period March 2-11, 2015, the Nuclear Regulatory Commission (NRC) administered operating tests to employees of your company who had applied for licenses to operate the Sequoyah Nuclear Plant. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests and the written examination submittal with those members of your staff identified in the enclosed report. The written examination was administered by your staff on March 18, 2015.
One Reactor Operator (RO) and eight Senior Reactor Operator (SRO) applicants passed both the operating test and written examination.
One SRO applicant, who previously passed the operating test, also passed the written examination. One SRO applicant failed the operating test and written examination. 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 9, Supplement 1.
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/ 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
REGION II==
Docket No.: 50-327, 50-328
License No.: DRP-77, DPR-79
Report No.: 05000327/2015301, 05000328/2015301
Licensee: Tennessee Valley Authority (TVA)
Facility: Sequoyah Nuclear Plant, Units 1 & 2
Location: Sequoyah Access Road Soddy-Daisy, TN 37379
Dates: Operating Test - March 2 - 11, 2015 Written Examination - March 18, 2015
Examiners: Bruno Caballero, Chief Examiner, Senior Operations Engineer Michael G. Donithan, Operations Engineer Newton T. Lacy, Operations Engineer Ronald Crews, Senior Reactor Technology Instructor (Observer)
Approved by: Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety SUMMARY ER 05000327/2015301, 05000328/2015301, March 2-11, 2015 & March 18, 2015; Sequoyah Nuclear Plant; Operator License Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 9, Supplement 1, 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 both the operating tests and the written examination. The initial operating test, written RO examination, and written SRO examination submittals met the quality guidelines contained in NUREG-1021.
The NRC administered the operating tests during the period March 2-11, 2015. Members of the Sequoyah Nuclear Plant training staff administered the written examination on March 18, 2015.
One Reactor Operator (RO) and eight Senior Reactor Operator (SRO) applicants passed both the operating test and written examination.
One SRO applicant, who previously passed the operating test, also passed the written exam ination. Ten applicants were issued licenses 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 operating test by combining the scenario events and JPMs in order to determine the percentage of submitted test items that required replacement or significant modification. The NRC also evaluated the submitted written examination questions (RO and SRO questions considered separately) in order to determine the percentage of submitted questions that required replacement or significant modification, or that clearly did not conform with the intent of the approved knowledge and ability (K/A) statement. Any questions that were deleted during the grading process, or for which the answer key had to be changed, were also included in the count of unacceptable questions. 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 examinations in order to ensure compliance with 10 CFR §55.49,
"Integrity of examinations and tests."
The NRC administered the operating tests during the period March 2-11, 2015. The NRC examiners evaluated one Reactor Operator (RO) and nine Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. Members
of the Sequoyah Nuclear Plant training staff administered the written examination on March 18, 2015. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses 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 operating tests.
b. Findings No findings were identified.
Members of the Sequoyah Nuclear Plant training staff developed both the operating test and the written examination. All examination material was developed in accordance with the guidelines contained in Revision 9, Supplement 1, of NUREG-1021. The NRC examination team 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 initial examination submittal was within the range of acceptability expected for a proposed examination.
4 One RO applicant and eight SRO applicants passed both the operating test and written examination. One SRO applicant, who previously passed the operating test, also passed the written examination. One SRO applicant did not pass the operating test and the written examination. One RO applicant and nine SRO applicants were issued licenses.
Copies of all individual examination reports were 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. A copy of the final written examination and answer key, with all changes incorporated, may be accessed not earlier than April 15, 2017, in the ADAMS system (ADAMS Accession Numbers ML15092A848 and ML15092A854).
4OA6 Meetings, Including Exit Exit Meeting Summary
On March 11, 2015, the NRC examination team discussed generic issues associated with the operating test with Tim Rieger, Superintendent Nuclear Operations, 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
Tim Rieger, Superintendent Nuclear Operations Koda Smith, Director of Training Matthew McMullin, Manager of Operations Training Jeremy Bailey, Initial License Training Supervisor Jim Kecy, Simulator Manager Russell Joplin, Corporate Program Manager Michael Buckner, Lead Exam Writer Joe Welch, Facility SRO Representative Tony Cross, Director Plant Support Jon Johnson, Program Manager
James Cross, Emergency Preparedness Manager
Enclosure 2 SIMULATOR FIDELITY REPORT Facility Licensee: Sequoyah Nuclear Plant
Facility Docket No.: 50-327, 50-328
Operating Test Administered: March 2-11, 2015
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.