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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] |
See also: IR 05000390/2020301
Text
October 06, 2020
Mr. Anthony L. Williams, IV
Site Vice President
Watts Bar Nuclear Plant
Tennessee Valley Authority
P.O. Box 2000, ADM 1V-WBN
Spring City, TN 37381
SUBJECT: WATTS BAR NUCLEAR PLANT - NRC OPERATOR LICENSE
EXAMINATION REPORT 05000390/2020301 AND 05000391/2020301
Dear Mr. Williams:
During the period August 24 - September 1, 2020, the Nuclear Regulatory Commission (NRC)
administered operating tests to employees of your company who had applied for licenses to
operate the Watts Bar 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 September 3, 2020.
Thirteen Senior Reactor Operator (SRO) applicants passed both the operating test and written
examination. There were no post-examination comments concerning the operating test.
Simulator Fidelity Report is included in this report as Enclosure 3.
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 11.
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).
A. Williams 2
If you have any questions concerning this letter, please contact me at (404) 997-4551.
Sincerely,
/RA/
Gerald J. McCoy, Chief
Operations Branch 1
Division of Reactor Safety
Docket Nos: 50-390, 50-391
License Nos: NPF-90, NPF-96
Enclosures:
1. Report Details
2. Simulator Fidelity Report
cc: Distribution via Listserv
ML20281A562 : SUNSI REVIEW COMPLETE FORM 665 ATTACHED
OFFICE RII:DRS/OB1 RII:DRS/OB1
NAME DDUMBACHER GMCCOY
DATE 10/ 6 /2020 10/ 6 /2019
E-MAIL COPY? YES NO YES NO
U.S. NUCLEAR REGULATORY COMMISSION
REGION II
Examination Report
Docket No.: 05000390, 05000391
License No.: NPF-90, NPF-96
Report No.: 05000390/2020301 and 05000391/2020301
EPID No.: L-2020-OLL-0032
Licensee: Tennessee Valley Authority
Facility: Watts Bar Nuclear Plant, Units 1 and 2
Location: Spring City, TN
Dates: Operating Test - August 24 -September 1, 2020
Written Examination - September 3, 2020
Examiners: D. Dumbacher, Chief Examiner, Senior Operations Engineer
M. Meeks, Senior Operations Engineer
A. Goldau, Operations Engineer
M. Donithan, Operations Engineer
Approved by: Gerald J. McCoy, Chief
Operations Branch 1
Division of Reactor Safety
Enclosure 1
SUMMARY
ER 05000390/2020301 and 05000391/2020301; operating test August 24 - September 1, 2020
& written exam September 3, 2020; Watts Bar Nuclear Plant, Units 1 and 2; Operator License
Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in
accordance with the guidelines in Revision 11 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 Plant staff developed both the operating test and the written
examination. The initial operating test, written Reactor Operator (RO) examination, and written
Senior Reactor Operator (SRO) examination submittals met the quality guidelines contained in
NUREG-1021.
The NRC administered the operating tests during the period of August 24 - September 1, 2020.
Members of the Watts Bar Nuclear Plant training staff administered the written examination on
September 3, 2020. Thirteen SRO applicants passed both the operating test and written
examination. Eight applicants were issued licenses commensurate with the level of examination
administered on September 30, 2020. Although the other five applicants passed their
examinations, the associated licenses will not be issued until Watts Bar notifies the NRC in
writing that all deferred requirements have been met.
There were no post-examination comments.
No findings were identified.
2
REPORT DETAILS
3. OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a. Inspection Scope
The NRC evaluated the submitted operating test by combining the scenario events and job
performance measures (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 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 administered the operating tests during the period August 24 - September 1,
2020. NRC examiners evaluated thirteen SRO applicants using the guidelines contained in
NUREG-1021. Members of the Watts Bar Nuclear Plant training staff administered the
written examination on September 3, 2020. 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 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. Members of the Watts Bar
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
11 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 that the licensees written examination and operating test submittals
were within the range of acceptable quality for a proposed examination specified by NUREG-
1021.
3
No issues related to examination security were identified during preparation and
administration of the examination.
All applicants passed both the operating test and written examination and on
September 30, 2020, eight of the applicants were issued licenses. Although the other
five applicants passed their examinations, the associated licenses will not be issued
until Watts Bar notifies the NRC in writing that all deferred requirements have been
met.
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 no post-examination comments. A copy of the final written RO
and SRO examinations and answer key may be accessed not earlier than October 2,
2022 in the ADAMS system (ADAMS Accession Numbers ML20276A151 and
ML20276A205).
4OA6 Meetings, Including Exit
Exit Meeting Summary
On August 28, 2020 the NRC examination team discussed generic issues associated
with the operating test with A. Williams, Site Vice President, and members of the Watts
Bar 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
Williams, Anthony - WBN Site Vice President
Rice, Christopher - WBN Director of Nuclear Plant Operations
McMullin, Matthew - WBN Director of Nuclear Training
McIlnay, Brian S - WBN Facility Representative / Shift Manager
Joplin, Russell Wayne - Program Manager, Corporate Nuclear Exams
Williams, Pedro Arthur Jr - WBN Operations Training Liaison / Shift Manager
Deschaine, Wesley David - NRC Senior Resident
O'Brien, Patrick Clinton - WBN Initial License Training Supervisor
Gabosch, Timothy - WBN Exam Project Manager
4
SIMULATOR FIDELITY REPORT
Facility Licensee: Watts Bar Nuclear Plant
Facility Docket No.: 050000390 and 050000391
Operating Test Administered: August 24 -September 1, 2020
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.
One simulator fidelity and two configuration issues were identified.
One simulator fidelity issue arose when the simulator ICS computer crashed.
This caused the plant computer on the simulator to go down for the course of the scenario.
The scenario was completed without the use of ICS. The licensee stated that the cause was
indeterminate. Condition Report 1641066 was written to capture and correct the issue.
The first configuration issue was that JPM B Initial Condition (IC) was found to have had an error
in the code. CR 1638012 was generated to address the issue. With the malfunction
inserted, break flow goes to 0 after soon after going to run. There was an error introduced during
IC construction that wasn't observed during validation due to the shorter run time but became
readily apparent during the examination. All simulator Instructor Station indications were that the
malfunction was inserted. The IC for JPM B has been repaired.
The second configuration issue was related to a JPM where a lockout relay indicating light was lit
during validation but initially, for the first applicant, was not. This setup issue was corrected for
the remaining applicants and did not affect the JPM result for the affected applicant.
Enclosure 2