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Category:Letter
MONTHYEARCNL-25-009, And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 262025-01-29029 January 2025 And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 26 IR 05000327/20240042025-01-28028 January 2025 Integrated Inspection Report 05000327/2024004 and 05000328/2024004 ML25023A0572025-01-23023 January 2025 Cycle 27 Core Operating Limits Report Revision 2 CNL-25-016, Comments on Preliminary Accident Sequence Precursor Program Analysis2025-01-16016 January 2025 Comments on Preliminary Accident Sequence Precursor Program Analysis CNL-24-084, Response to Request for Confirmatory Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.32025-01-13013 January 2025 Response to Request for Confirmatory Information Regarding Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3 ML25006A1892025-01-0606 January 2025 ISFSI Inspection (Request for Information) ML24341A2102024-12-23023 December 2024 Exemption from the Requirements of 10 CFR Part 26, Section 205(D)(4) (EPID L-2024-LLE-0029) (Letter) ML24312A3222024-12-23023 December 2024 Issuance of Amendment Nos. 334, 357, & 317; 368 & 362; 172 & 77 Regarding Revision to TS 5.4 & 5.7.1 IR 05000327/20240102024-12-19019 December 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000327/2024010 and 05000328/2024010 CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations ML24347A0592024-12-12012 December 2024 Annual Non-Radiological Environmental Operating Report - 2024 ML24339B8242024-12-11011 December 2024 Summary of November 20, 2024, Public Pre-Submittal Meeting with TVA Regarding a One-Time Exemption Request from the Requirements of Title 10 of the Code of Federal Regulations Part 26, Section 26.205, Work Hours ML24337A1912024-12-0202 December 2024 Discharge Monitoring Report (Dmr), April 2024 ML24337A1932024-12-0202 December 2024 Discharge Monitoring Report (Dmr), June 2024 ML24337A1952024-12-0202 December 2024 Discharge Monitoring Report (Dmr), August 2024 ML24337A1942024-12-0202 December 2024 Discharge Monitoring Report (Dmr), July 2024 ML24337A1972024-12-0202 December 2024 Discharge Monitoring Report (Dmr), October 2024 ML24337A1962024-12-0202 December 2024 Discharge Monitoring Report (Dmr), September 2024 ML24337A1922024-12-0202 December 2024 Discharge Monitoring Report (Dmr), May 2024 CNL-24-073, Request for Exemption from Requirements of 10 CFR 26.205, Fitness for Duty Programs - Work Hours2024-11-27027 November 2024 Request for Exemption from Requirements of 10 CFR 26.205, Fitness for Duty Programs - Work Hours CNL-24-075, Response to Request for Additional Information for 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-TSTS-23-02 and W2024-11-27027 November 2024 Response to Request for Additional Information for 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-TSTS-23-02 and WBN CNL-24-071, Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the (SQN-TS-24-04)2024-11-26026 November 2024 Expedited Application to Revise Technical Specifications to Revise the Reactor Coolant System Pressure Isolation Valve Leakage Testing Frequency for the (SQN-TS-24-04) 05000327/LER-2024-002, Reactor Trip Due to a Turbine Trip2024-11-20020 November 2024 Reactor Trip Due to a Turbine Trip ML24319A2672024-11-14014 November 2024 Discharge Monitoring Report (DMR) Quality Assurance Study 44 Final Report 2024 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) ML24312A1552024-11-0606 November 2024 Cycle 27 Core Operating Limits Report, Revision 1 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) ML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 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-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 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), 2025-01-06
[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 05000327/20163022016-09-12012 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
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Tennessee Valley Authority ATTN: Thomas Marshall Site Vice President Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, TN 37384-2000
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000327/2024301 AND 05000328/2024301
Dear Thomas Marshall:
During the period June 10-18, 2024, 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 findings related to the operating tests with those members of your staff identified in the enclosed report.
The written examination was administered by your staff on June 26, 2024.
Seven Reactor Operator (RO) and seven Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One Senior Reactor Operator was exempted from the operating test and passed the written exam. One RO and one SRO applicant failed the written examination. There were no post-administration comments concerning any part of the exam. A Simulator Fidelity Report is included in this report as Enclosure 2.
The written examination and operating test were developed by the NRC. 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 12.
In accordance with 10 CFR 2.390 of the NRCs 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 NRCs document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room).
July 29, 2024
T. Marshall 2
If you have any questions concerning this letter, please contact me at (404) 997-4807.
Sincerely, Thomas A. Stephen, Chief Operations Branch 1 Division of Reactor Safety Docket Nos: 05000327, 05000328 License Nos: DPR-77, DPR-79
Enclosures:
- 1. Report Details
- 2. Simulator Fidelity Report cc: Distribution via Listserv Signed by Stephen, Tom on 07/29/24
ML24211A054 Cover Letter Only:
X SUNSI Review X Non-Sensitive Sensitive X Publicly Available Non-Publicly Available OFFICE RII/DRS RII/DRS RII/DRS NAME K. Wallace D. Lanyi T. Stephen DATE 07/29/24 07/29/24 07/29/24
Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION II Examination Report Docket No.:
05000327, 05000328 License No.:
DPR-77, DPR-79 Report No.:
05000327/2024301 and 05000328/2024301 Enterprise Identifier:
L-2024-OLL-0014 Licensee:
Tennessee Valley Authority Facility:
Sequoyah Nuclear Plant Location:
Soddy-Daisy, TN Dates:
Operating Test - June 10 - 18, 2024 Written Examination - June 26, 2024 Examiners:
D. Lanyi, Chief Examiner, Senior Operations Engineer K. Kirchbaum, Senior Operations Engineer N. Lacy, Operations Engineer V. Furr, Operations Engineer L. Nist, Reactor Operator (Examiner Qualified)
Approved by:
Thomas A. Stephen, Chief Operations Branch 1 Division of Reactor Safety
T. Marshall 3
2
SUMMARY
ER 05000327/2024301, 05000328/2024301; June 10 - 18, 2024 & June 26, 2024; Sequoyah Nuclear Plant; Operator License Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 12 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.
The operating test and written examination were developed by the NRC. The initial operating test, written Reactor Operator (RO) examination, and written Senior Reactor Operator (SRO) examination met the quality guidelines contained in NUREG-1021.
The NRC administered the operating tests during the period June 10 - 18, 2024. Members of the Sequoyah Nuclear Plant training staff administered the written examination on June 26, 2024. Seven RO and seven SRO applicants passed both the operating test and written examination. One SRO was exempted from the operating test and passed the written exam.
Fifteen (15) 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 reviewed the licensees 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 performed an audit of license applications during the preparatory site visit in order to confirm that they accurately reflected the subject applicants qualifications in accordance with NUREG-1021.
The NRC administered the operating tests during the period June 10 - 18, 2024. The NRC examiners evaluated eight Reactor Operator (RO) and nine Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. One of the SRO applicants previously passed the operating test and therefore was exempted from taking another one. Members of the Sequoyah Nuclear Plant training staff administered the written examination on June 26, 2024. 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.
The NRC developed the written examination sample plan outline, the written examination, and the operating test outlines. All examination material was developed in accordance with the guidelines contained in Revision 12, of NUREG-1021. The licensee reviewed the examination and proposed modifications. The NRC examination team reviewed the proposed modifications. 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.
Seven RO applicants and seven SRO applicants passed both the operating test and written examination. One SRO applicant was exempted from the operating test and passed the written exam. One RO applicant and one SRO applicant passed the operating test but did not pass the written examination. Seven RO applicants and eight SRO applicants were issued licenses.
Copies of all individual examination reports were sent to the facility Training Director for evaluation of weaknesses and determination of appropriate remedial training.
T. Marshall 3
2 The licensee submitted no post-examination comments. A copy of the final written examination and answer key may be accessed not earlier than December 26, 2026, thirty months after administration of the written exam, in the ADAMS system (ADAMS Accession Numbers ML24208A057and ML24208A058).
3 4OA6 Meetings, Including Exit Exit Meeting Summary On July 25, 2024, the NRC examination team discussed generic issues associated with the operating test with Mr. T. Marshall, Sequoyah Plant Site Vice President, and other 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 T. Marshall, Site Vice President B. Jenkins, Sequoyah Plant Manager G. Garner, Director of Site Training R. Medina, Site Licensing Manager J. Ward, Manager, Initial License Training R. Joplin, TVA Corporate Nuclear Examination Program Manager A. Forsha, Sequoyah Training Examination Development D. Neff, Sequoyah Training Examination Development
T. Marshall 3
SIMULATOR FIDELITY REPORT Facility Licensee: Sequoyah Nuclear Plant Facility Docket No.: 05000327 and 05000328 Operating Test Administered: June 10-18, 2024 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.