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Category:Inspection Report
MONTHYEARIR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23296A0242023-10-24024 October 2023 Biennial Problem Identification and Resolution Inspection Report and Preliminary Greater than Green Finding and Apparent Violation IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 IR 05000390/20234012023-03-13013 March 2023 Security Baseline Inspection Report 05000390 2023401 and 05000391 2023401 IR 05000390/20220062023-03-0101 March 2023 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022006 and 05000391/2022006 IR 05000390/20220042023-02-10010 February 2023 Integrated Inspection Report 05000390/2022004 and 05000391/2022004 IR 05000390/20224202022-12-0101 December 2022 Security Baseline Inspection 05000390/2022420 and 05000391/2022420 Cover Letter ML22318A0072022-11-14014 November 2022 Integrated Inspection Report 05000390/2022003 and 05000391/2022003 IR 05000390/20220102022-10-28028 October 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000390/2022010 and 05000391/2022010 IR 05000390/20223012022-09-30030 September 2022 NRC Operator License Examination Report 05000390/2022301 and 050000391/2022301 ML22256A2952022-09-14014 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07201048/2022001 IR 05000390/20220052022-08-31031 August 2022 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2022005 and 05000391/2022005 - Final IR 05000390/20220022022-08-12012 August 2022 Integrated Inspection Report 05000390/2022002 and 05000391/2022002 and Exercise of Enforcement Discretion IR 05000390/20224012022-08-0303 August 2022 Security Baseline Inspection Report 05000390/2022401 and 05000391/2022401 IR 05000390/20220012022-05-11011 May 2022 Integrated Inspection Report 05000390/2022001 and 05000391/2022001 ML22123A2412022-05-11011 May 2022 Review of the Fall 2021 Mid-Cycle Steam Generator Tube Inspection Report IR 05000390/20210062022-03-0202 March 2022 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 (Report No. 05000390/2021006 and 05000391/2021006) IR 05000390/20210042022-02-10010 February 2022 Integrated Inspection Report 05000390/2021004 and 05000391/2021004 IR 05000390/20210032021-11-10010 November 2021 Integrated Inspection Report 05000390/2021003 and 05000391/2021003 IR 05000390/20214022021-11-0202 November 2021 Security Baseline Inspection Report 05000390/2021402 and 05000391/2021402 IR 05000390/20214032021-10-26026 October 2021 Material Control and Accounting Program Inspection Report 05000390/2021403 and 05000391/2021403 (OUO Removed) ML21263A0042021-09-24024 September 2021 Review of the Fall 2020 Steam Generator Tube Inspection Report IR 05000390/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000390/2021401 and 05000391/2021401 IR 05000390/20210052021-08-24024 August 2021 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 & 2 Report 05000390/2021005 and 05000391/2021005 IR 05000390/20210022021-08-0404 August 2021 Integrated Inspection Report 05000390/2021002 and 05000391/2021002 IR 05000390/20210122021-07-0101 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000390/2021012 and 05000391/2021012 IR 05000390/20210102021-05-0606 May 2021 NRC Inspection Report 05000390/2021010 and 05000391/2021010 IR 05000390/20210012021-05-0505 May 2021 Integrated Inspection Report 05000390/2021001 and 05000391/2021001 IR 05000390/20210112021-04-13013 April 2021 Triennial Fire Protection Inspection Report 05000390/2021011 and 05000391/2021011 IR 05000390/20200062021-03-0303 March 2021 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020006 and 05000391/2020006 IR 05000390/20200042021-02-11011 February 2021 Integrated Inspection Report 05000390/2020004, 05000391/2020004, 07201048/2020002, and Exercise of Enforcement Discretion IR 05000390/20203012021-01-19019 January 2021 Reissue - Watts Bar Nuclear Plant - NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 IR 05000390/20204032020-12-15015 December 2020 Security Baseline Inspection Report 05000390/2020403 and 05000391/2020403 IR 05000390/20204012020-11-30030 November 2020 Security Baseline Inspection Report 05000390/2020401 and 05000391/2020401 IR 05000390/20200032020-11-10010 November 2020 Integrated Inspection Report 05000390/2020003 and 05000391/2020003 IR 05000390/20200112020-10-20020 October 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000390/2020011 and 05000391/2020011 IR 05000390/20200052020-08-31031 August 2020 Assessment Followup Letter and Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020005 and 05000391/2020005 IR 05000390/20200022020-08-11011 August 2020 Nuclear Regulatory Commission Integrated Inspection Report 05000390/2020002, 05000391/2020002, and 07201048/2020001 IR 05000390/20200012020-05-0505 May 2020 Integrated Inspection Report 05000390/2020001 and 05000391/2020001 IR 05000390/20204102020-03-31031 March 2020 Security Baseline Inspection Report 05000390/2020410 and 05000391/2020410 IR 05000390/20190062020-03-0303 March 2020 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - NRC Report 05000390/2019006 and 05000391/2019006 2023-08-09
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] Category:License-Operator Examination Report
MONTHYEARIR 05000390/20223012022-09-30030 September 2022 NRC Operator License Examination Report 05000390/2022301 and 050000391/2022301 IR 05000390/20203012021-01-19019 January 2021 Reissue - Watts Bar Nuclear Plant - NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 ML20281A5622020-10-0606 October 2020 NRC Operator License Examination Report 05000390/2020301 and 05000391/2020301 IR 05000390/20193012019-10-24024 October 2019 NRC Operator License Examination Report 05000390/2019301 and 05000391/2019-301 ML18044A9892018-02-13013 February 2018 Notification of Licensed Operator Initial Examination 05000390/2018301, 05000391/2018301 IR 05000390/20163012016-09-16016 September 2016 NRC Operator License Examination Report 05000390/2016301 and 05000391/2016301 IR 05000390/20153012015-09-0303 September 2015 Er 05000390/2015301; 07/20-22/2015 & July 29, 2015, Written Examination, July 29, 2015; Watts Bar Nuclear Power Plant; Operator License Examinations IR 05000390/20133022013-12-11011 December 2013 Er 05000390-13-302; Operating Test, October 22 - 25, 2013, & Written Examination, October 30, 2013; Watts Bar Nuclear Power Plant; Operator License Examinations IR 05000390/20113022012-01-19019 January 2012 Er 05000390/11-302, on December 19-22, 2011, Watts Bar Nuclear Plant - NRC Operator Licensing Examination Report IR 05000390/20113012011-08-10010 August 2011 Er 05000390-11-301, on June 6 - 16, 2011, and June 22, 2011, Watts Bar Nuclear Plant Unit 1, Licensed Operator Examinations IR 05000390/20103012010-11-0909 November 2010 NRC Operator License Examination Report 05000390-10-301 IR 05000390/20093022010-01-20020 January 2010 Operator License Examinations Report 05000390-09-302 on 11/30/09 - 12/02/09 for Watts Bar IR 05000390/20093012009-07-0606 July 2009 Er 05000390-09301, Operating Test, May 18-21, 2009 & Written Exam, May 27, 2009, Watts Bar, Operator License Examinations IR 05000390/20063012006-10-24024 October 2006 Er 05000390-06-301; 09/05-13/2006 & 09/18/2006; Watts Bar, Unit 1, Licensed Operator Examinations IR 05000390/20023012003-01-17017 January 2003 NRC Examination Report 05000390/02-301, on 11/26/2002 & 12/09-12/2002, Licensed Operator Examinations 2022-09-30
[Table view] |
Text
UNITED STATES ber 11, 2013
SUBJECT:
WATTS BAR NUCLEAR POWER PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000390/2013302
Dear Mr. Shea:
During the period of October 22 - 25, 2013, the Nuclear Regulatory Commission (NRC)
administered operating tests to employees of your company who had applied for licenses to operate the Watts Bar Nuclear Power 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 October 30, 2013.
One Reactor Operator (RO) and five Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One RO applicant and one SRO applicant, who were granted waivers for a previously passed operating test, passed the written exam. One SRO applicant passed the operating test, but failed the written examination. There were two post-administration comments concerning the written examination. These comments, and the NRC resolution of these comments, are summarized in Enclosure 2. A Simulator Fidelity Report is included in this report as Enclosure 3.
The initial written SRO examination submitted by your staff failed to meet the guidelines for quality contained in NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1, as described in the enclosed report.
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). If you have any questions concerning this letter, please contact me at (404) 997-4550.
Sincerely,
/RA/
Malcolm T. Widmann, Chief Operations Branch 1 Division of Reactor Safety Docket No: 50-390 License No: NPF-90
Enclosures:
1. Report Details 2. Facility Comments and NRC Resolution 3. Simulator Fidelity Report
REGION II==
Docket No.: 50-390 License No.: NPF-90 Report No.: 05000390/2013302 Licensee: Tennessee Valley Authority Facility: Watts Bar Location: Spring City, Tennessee Dates: Operating Test - October 22 - 25, 2013 Written Examination - October 30, 2013 Examiners: M. Meeks, Chief Examiner, Senior Operations Engineer A. Goldau, Operations Engineer M. Donithan, Operations Engineer J. Viera, Operations Engineer (in training status)
Approved by: Malcolm T. Widmann, Chief Operations Branch 1 Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS
ER 05000390/2013302; Operating Test, October 22 - 25, 2013, & Written Examination, October 30, 2013; Watts Bar Nuclear Power 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 Watts Bar Nuclear Power Plant staff developed both the operating tests and the written examination. The NRC developed the written examination outline. The initial written Senior Reactor Operator (SRO) examination submittal did not meet the quality guidelines contained in NUREG-1021.
The NRC administered the operating tests during the period of October 22 - 25, 2013.
Members of the Watts Bar Nuclear Power Plant training staff administered the written examination on October 30, 2013. One Reactor Operator (RO) and five SRO applicants passed both the operating test and written examination, and were issued licenses commensurate with the level of examination administered.
One SRO applicant passed the operating test, but failed the written examination.
One RO applicant, who was granted a waiver for a previously passed operating test, passed the written examination with a score between 80 and 82 percent. One SRO applicant passed the operating test, but passed the SRO-only portion of the written examination with a score between 70 and 74 percent. Each of these applicants were issued a letter stating that they passed the examination and issuance of their license has been delayed pending any written examination appeals that may impact the licensing decision for their application.
There were two post-examination comments submitted on the written exam.
No findings were identified.
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a. Inspection Scope
Members of the Watts Bar Nuclear Power Plant staff developed both the operating tests and the written examination. The written examination outline was developed by the NRC. All examination material was developed in accordance with the guidelines contained in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." 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 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 examiners evaluated two Reactor Operator (RO) and seven Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period of October 22 - 25, 2013.
Members of the Watts Bar Nuclear Power Plant training staff administered the written examination on October 30, 2013. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Watts Bar Nuclear Power Plant, met the requirements specified in 10 CFR Part 55, Operators Licenses.
b. Findings
The NRC determined that the licensees SRO written examination submittal was outside the range of acceptable quality specified by NUREG-1021, because more than 20 percent (10 of 25) of questions sampled for review contained unacceptable flaws.
Individual questions were evaluated as unsatisfactory for the following reasons:
- One question failed to meet the K/A statement contained in the examination outline.
- Five questions contained two or more implausible distractors.
- Two questions were not written at the SRO license level.
- Two questions contained multiple unacceptable flaws.
The NRC determined that the licensees initial operating test submittal and the initial RO written examination submittal were within the range of acceptability expected for a proposed examination.
One RO and four SRO applicants passed both the operating test and written examination, and were issued licenses commensurate with the level of examination administered. One SRO applicant, who was granted a waiver for a previously passed operating test, also passed the written examination and was issued a license.
One SRO applicant passed the operating test, but failed the written examination.
One RO applicant, who was granted a waiver for a previously passed operating test, passed the written examination with a score between 80 and 82 percent. One SRO applicant passed the operating test, but passed the SRO-only portion of the written examination with a score between 70 and 74 percent. Each of these applicants were issued a letter stating that they passed the examination and issuance of their license has been delayed pending any written examination appeals that may impact the licensing decision for their application.
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 submitted two post-examination comments concerning the written examination. A copy of the final written examination and answer key, with all changes incorporated, and the licensees post-examination comments may be accessed not earlier than December 2, 2015, in the ADAMS system (ADAMS Accession Numbers ML13312A419, ML13312A425, and ML13312A453).
4OA6 Meetings, Including Exit
Exit Meeting Summary
On October 25, 2013, the NRC examination team discussed generic issues associated with the operating test with Mr. T. Cleary, Site Vice President, and other members of the Watts Bar Nuclear Power Plant staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.
On December 6, 2013, the NRC examination team discussed the final exam results via phone call with Ms. Eiford-Lee, Training Director, and other members of the Watts Bar Nuclear Power Plant staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- A. Bergeron, Corporate Operations Training Manager
- G. Boerschig, Plant Manager
- M. Bottorff, Operations Superintendent
- T. Cleary, Site Vice President
- L. Cross, Assistant Operations Manager
- B. Eiford-Lee, Training Director
- R. Fruth, Initial License Training Supervisor
- R. Joplin, Corporate Exam Manager
- J. Kecy, Simulator Manager
- K. Skubisz, Principal Exam Author
- B. Sprinkle, Operations Support Superintendent
- J. Thompson, Instructor
NRC personnel
None
FACILITY POST-EXAMINATION COMMENTS AND NRC RESOLUTIONS
A complete text of the licensees post-examination comments can be found in ADAMS under
Accession Number ML13312A453.
Item
Question 55, K/A 103 K1.08
Comment
The facility licensee recommends that the correct answer be changed from the keyed answer of
B, to
- A.
After listing the text of the question and the distractor analysis, the facility licensee submitted a
detailed analysis of the safeguards circuitry included in Watts Bar/Westinghouse print 1082H70-
1. The facility licensee provided discussion and detailed circuit analysis for three cases: (1) no
actuation signal (Safety Injection) exists and no reset push-button is depressed, (2) an actuation
signal exists and the reset push-button is not depressed, and (3) the actuation signal exists and
the reset push-button is depressed. These circuit analyses result in the conclusion that the
ON/OFF retentive memory affiliated with the Phase A isolation signal will change to the OFF
state with a safety injection signal present when the reset push-button is depressed, and will
remain in the OFF state after the reset push-button is released.
The answer as listed in the key is B, which states that the Phase A containment isolation signal
will not be removed. Question 55 asked the applicants to consider whether the Phase A
containment isolation could be reset if its initiating signal had NOT been reset. Given the
aforementioned circuit design, the correct answer should be that it could. Therefore, the keyed
answer to question 55 should be A.
The facility recommends changing the answer to question 55 to A.
NRC Resolution
The licensees recommendation was accepted.
An analogous argument to the facility licensees more detailed examination of the circuit in
question can be made using the Watts Bar Unit 1 functional logic diagram 1-47W611-88-1,
ELECTRICAL LOGIC DIAGRAM CONTAINMENT ISOLATION, which diagrams the A train
portion of the phase A containment isolation logics. A NOTE on this print explains that B train
operation is the same.
With an SI actuation signal present, when the operator depresses the RESET button, the upper
OR gate output becomes a logical 1. This output, along with the logical 1 of the SI signal
present, generates a logical 1 output from the following AND gate. This output is then routed
back into the upper OR gate as a seal in circuit. The logical 1 output from the AND gate is
then inverted (logical 0) and sent to a final AND gate along with the SI actuation signal. The
output of this final AND gate is therefore switched to a logical 0 and the phase A containment
isolation signal is turned off/reset.
After the operator releases the RESET button to neutral, with an SI actuation signal present, the
upper OR gate output remains a logical 1 due to the seal in circuit input. This output, along
with the continued logical 1 of the SI signal present, continues the logical 1 output from the
first AND gate, which keeps the seal in present. The logical 1 output from the first AND
gate remains inverted (logical 0) when it is sent to the final AND gate, and the containment
isolation signal remains off/reset.
Therefore, the facility licensee is correct that A is the one and only correct answer to question
on the written examination. The correct answer was changed to A.
Item
Question 88, K/A 059 A2.05
Comment
The facility licensee recommends that the correct answer be changed from the keyed answer of
B to
- D.
After listing the text of the question and the distractor analysis, the facility licensee submitted the
following:
The facility's intent in constructing this question was to elicit the knowledge that 1-E-0
did not contain any guidance to ensure that the feedwater leak was isolated. The facility
did not consider the fact that Tl-12.04, "User's Guide For Abnormal And Emergency
Operating Instructions" contains the following in section 2.2.4 Immediate Action Steps:
B. During immediate operator action steps the operators will ensure automatic
actions have occurred or initiate signals as appropriate. Diagnostic or repair
actions will be delayed until the immediate actions are complete to allow for
evaluation of plant response.
One comment is that while the Operator at the controls is performing the immediate actions of
1-E-0, the Balance of Plant Operator (and the Unit Supervisor) would verify that as Reactor
Coolant System average temperature lowered to less than 564°F, a feedwater isolation
occurred. Therefore, three facts exist:
1. Tl-12.04 contains the verbiage that "operators will ensure automatic actions
have occurred."
2. Tl-12.04 is in effect when 1-E-0 is entered.
3. A feedwater isolation is an automatic action.
When a feedwater isolation signal occurs, both the Main Feed Regulating Valves and
the Main Feed Isolation valves will close. The Main Feed Regulating Valves are located
inside of the Turbine Building and the Main Feed Isolation Valves are located inside of
the applicable Valve Vault Room. For the #4 Steam Generator, the Main Feed Isolation
Valve is located inside of the South Valve Vault Room. Because the question indicated
that the Feedwater leak was on the #4 S/G supply line between the Turbine Building
wall and the South Valve Vault Room, the feedwater isolation would cause the leak to
be isolated.
The facility considered the amount of time between a reactor trip (initiated on the basis
of a sufficiently sized feedwater leak. Using its simulator, the facility ran a test case
which placed a 3% feedwater leak on the feed line for the #4 S/G (the criteria presented
in AOI-38, "MAIN STEAM OR FEEDWATER LINE LEAK" which requires a reactor trip).
The facility validated that a feedwater isolation occurred well before the OAC completed
his immediate actions. Because the isolation occurs before the OAC had completed his
immediate actions, it occurs before a transition out of 1-E-0 exists.
Given the aforementioned, the following deductions must be made:
1. Procedural guidance exists which directs the operators to ensure that a
feedwater isolation occurs.
2. The feedwater isolation will isolate the leak presented in the question.
3. The isolation will occur before a transition out of 1-E-0.
Therefore, the facility agrees that procedural direction to ensure the leak is isolated will
be directed prior to the transition from 1-E-0, "Reactor Trip or Safety Injection," to the
applicable procedure.
The facility recommends that the correct answer be keyed as D.
NRC Resolution
The licensees recommendation was partially accepted.
The first part of the question specifically asks when Procedural direction to ensure the leak is
isolated will be directed . [underlines not in original]. The applicant is to decided whether this
direction will occur either prior to a transition from 1-E-0, or only after a transition from 1-E-0.
As specified in the facility licensees discussion, it would be acceptable for a SRO to direct leak
isolation before transition from 1-E-0 by invoking guidance contained in Watts Bar procedure TI-
2.04. However, it would also be acceptable for a SRO to wait until a transition from 1-E-0
when direct procedural guidance in the EOP/AOP procedural network could also be invoked.
Therefore, the question forces the applicant to make unwarranted assumptions regarding the
situation; i.e., the question stem did not provide all necessary information.
Furthermore, it is logically incompatible (contradictory) that the feedwater leak isolation can be
directed both prior to and only after a transition from 1-E-0 as stated in the question.
NUREG 1021 ES-403 section D.1.c states the following:
If it is determined that there are two correct answers, both answers will be accepted
as correct. If, however, both answers contain conflicting information, the question
will likely be deleted. For example, if part of one answer states that operators are
required to insert a manual reactor scram, and part of another answer states that a
manual scram is not required, then it is unlikely that both answers will be accepted
as correct, and the question will probably be deleted. []
In this case, the two first-part answers contained conflicting information (specifically via use of
the unique distractor only after). Therefore, in accordance with NUREG 1021 ES-403,
question 88 was deleted from the SRO-only written examination, which was graded using a final
total of 24 questions on the SRO-only portion and a total of 99 questions overall for the SRO
applicants.
SIMULATOR FIDELITY REPORT
Facility Licensee: Watts Bar Nuclear Power Plant
Facility Docket No.: 05000390/2013-302
Operating Test Administered: October 22 - 25, 2013
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.
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