IR 05000327/2016302: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:September 12, 2016 | ||
==SUBJECT:== | ==SUBJECT:== | ||
SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000327/2016302 AND 05000328/2016302 | SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE | ||
EXAMINATION REPORT 05000327/2016302 AND 05000328/2016302 | |||
==Dear Mr. Shea:== | ==Dear Mr. Shea:== | ||
| Line 34: | Line 36: | ||
Sincerely, | Sincerely, | ||
/RA: Gerald J. McCoy for/ | /RA: Gerald J. McCoy for/ | ||
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79 | |||
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety | |||
Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79 | |||
===Enclosures:=== | ===Enclosures:=== | ||
1. Report Details 2. Simulator Fidelity Report | 1. Report Details 2. Simulator Fidelity Report | ||
REGION II== | REGION II== | ||
Docket No.: 50-327, 50-328 License No.: DRP-77, DPR-79 Report No.: 05000327/2016302, 05000328/2016302 Licensee: Tennessee Valley Authority (TVA) | Docket No.: | ||
Facility: Sequoyah Nuclear Plant, Units 1 & 2 | 50-327, 50-328 | ||
License No.: | |||
DRP-77, DPR-79 | |||
Report No.: | |||
05000327/2016302, 05000328/2016302 | |||
Licensee: | |||
Tennessee Valley Authority (TVA) | |||
Facility: | |||
Sequoyah Nuclear Plant, Units 1 & 2 | |||
SUMMARY ER 05000327/2016302, 05000328/2016302, July 28, 2016; Sequoyah Nuclear Plant; Operator License Examinations. | Location: | ||
Sequoyah Access Road | |||
Soddy-Daisy, TN 37379 | |||
Dates: | |||
Operating TestJuly 28, 2016 | |||
Examiners: | |||
D. Bacon, Chief Examiner, Senior Operations Engineer | |||
Approved by: | |||
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety | |||
SUMMARY | |||
ER 05000327/2016302, 05000328/2016302, July 28, 2016; Sequoyah Nuclear Plant; Operator License Examinations. | |||
A Nuclear Regulatory Commission (NRC) examiner conducted a walk-through and administrative topics retake operating examination in accordance with the guidelines in Revision 10, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable. | A Nuclear Regulatory Commission (NRC) examiner conducted a walk-through and administrative topics retake operating examination in accordance with the guidelines in Revision 10, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable. | ||
| Line 56: | Line 89: | ||
No findings were identified. | No findings were identified. | ||
REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Operator Licensing Examinations a. Inspection Scope The NRC evaluated the submitted retake operating test by determining the percentage of submitted JPMs that required replacement or significant modification. The percentage of submitted test items that were unacceptable was compared to the acceptance criteria of NUREG-1021, Operator Licensing Standards for Power Reactors. | REPORT DETAILS | ||
4. | |||
OTHER ACTIVITIES | |||
4OA5 Operator Licensing Examinations | |||
a. | |||
Inspection Scope | |||
The NRC evaluated the submitted retake operating test by determining the percentage of submitted JPMs that required replacement or significant modification. The percentage of submitted test items that were unacceptable was compared to the acceptance criteria of NUREG-1021, Operator Licensing Standards for Power Reactors. | |||
The NRC reviewed the licensees examination security measures while preparing and administering the retake operating test in order to ensure compliance with 10 CFR §55.49, Integrity of examinations and tests. | The NRC reviewed the licensees examination security measures while preparing and administering the retake operating test in order to ensure compliance with 10 CFR §55.49, Integrity of examinations and tests. | ||
| Line 64: | Line 109: | ||
The NRC evaluated the performance or fidelity of the simulation facility during the preparation and conduct of the retake operating test. | The NRC evaluated the performance or fidelity of the simulation facility during the preparation and conduct of the retake operating test. | ||
b. Findings No findings were identified. | b. | ||
Findings | |||
No findings were identified. | |||
Members of the Sequoyah Nuclear Plant training staff developed the retake operating test. | Members of the Sequoyah Nuclear Plant training staff developed the retake operating test. | ||
| Line 80: | Line 129: | ||
The licensee did not submit any post-examination comments. | The licensee did not submit any post-examination comments. | ||
4OA6 Meetings, Including Exit Exit Meeting Summary On July 28, 2016, the NRC examination team discussed generic issues associated with the retake operating test with K. Smith, Director of Training, and members of the Sequoyah Nuclear Plant staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified. | 4OA6 Meetings, Including Exit | ||
Exit Meeting Summary | |||
On July 28, 2016, the NRC examination team discussed generic issues associated with the retake operating test with K. Smith, Director of Training, and members of the Sequoyah Nuclear Plant staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified. | |||
KEY POINTS OF CONTACT | |||
Licensee personnel | |||
SIMULATOR FIDELITY REPORT Facility Licensee: Sequoyah Nuclear Plant Facility Docket No.: 50-327, 50-328 Operating Test Administered: July 28, 2016 This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with Inspection Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations. | K. Smith, Director of Training M. McMullin, Manager of Operations Training J. Johnson, Licensing T. Rieger, Operations W. Harris, Operations/Training A. Roddy, Operations/Training | ||
Enclosure 2 SIMULATOR FIDELITY REPORT | |||
Facility Licensee: Sequoyah Nuclear Plant Facility Docket No.: 50-327, 50-328 Operating Test Administered: July 28, 2016 | |||
This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with Inspection Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations. | |||
No simulator fidelity or configuration issues were identified. | No simulator fidelity or configuration issues were identified. | ||
}} | }} | ||
Latest revision as of 20:21, 9 January 2025
| ML16256A769 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/12/2016 |
| From: | Eugene Guthrie Division of Reactor Safety II |
| To: | James Shea Tennessee Valley Authority |
| References | |
| 2016302 | |
| Download: ML16256A769 (8) | |
Text
September 12, 2016
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE
EXAMINATION REPORT 05000327/2016302 AND 05000328/2016302
Dear Mr. Shea:
On July 28, 2016, the Nuclear Regulatory Commission (NRC) administered a walk-through and administrative topics retake operating test to an employee of your company who had applied for a license to operate the Sequoyah Nuclear Plant. At the conclusion of the test, the examiner discussed preliminary findings related to the operating test with those members of your staff identified in the enclosed report.
The Reactor Operator (RO) applicant passed the retake operating test. A waiver was granted for the written examination and the simulator portion of the operating test. There were no post-examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2.
The initial examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 10.
In accordance with 10 CFR 2.390 of the 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) 997-4662.
Sincerely,
/RA: Gerald J. McCoy for/
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety
Docket Nos: 50-327, 50-328 License Nos: DPR-77, DPR-79
Enclosures:
1. Report Details 2. Simulator Fidelity Report
REGION II==
Docket No.:
50-327, 50-328
License No.:
DRP-77, DPR-79
Report No.:
05000327/2016302, 05000328/2016302
Licensee:
Tennessee Valley Authority (TVA)
Facility:
Sequoyah Nuclear Plant, Units 1 & 2
Location:
Sequoyah Access Road
Soddy-Daisy, TN 37379
Dates:
Operating TestJuly 28, 2016
Examiners:
D. Bacon, Chief Examiner, Senior Operations Engineer
Approved by:
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety
SUMMARY
ER 05000327/2016302, 05000328/2016302, July 28, 2016; Sequoyah Nuclear Plant; Operator License Examinations.
A Nuclear Regulatory Commission (NRC) examiner conducted a walk-through and administrative topics retake operating examination in accordance with the guidelines in Revision 10, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.
Members of the Sequoyah Nuclear Plant staff developed the retake operating test. The retake operating test submittal met the quality guidelines contained in NUREG-1021.
The NRC administered the retake operating test on July 28, 2016. The simulator portion of the operating test and the written examination were waived. One Reactor Operator (RO) applicant passed the retake operating test. The applicant was issued a license commensurate with the level of examination administered.
There were no post-examination comments.
No findings were identified.
REPORT DETAILS
4.
OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a.
Inspection Scope
The NRC evaluated the submitted retake operating test by determining the percentage of submitted JPMs that required replacement or significant modification. The percentage of submitted test items that were unacceptable was compared to the acceptance criteria of NUREG-1021, Operator Licensing Standards for Power Reactors.
The NRC reviewed the licensees examination security measures while preparing and administering the retake operating test in order to ensure compliance with 10 CFR §55.49, Integrity of examinations and tests.
The NRC administered the retake operating test on July 28, 2016. The NRC examiner evaluated one Reactor Operator (RO) applicant using the guidelines contained in NUREG-1021. Evaluation of the applicant and review of associated documentation was performed to determine if the applicant, who applied for a license to operate the Sequoyah Nuclear Plant, met the requirements specified in 10 CFR Part 55, Operators Licenses.
The NRC evaluated the performance or fidelity of the simulation facility during the preparation and conduct of the retake operating test.
b.
Findings
No findings were identified.
Members of the Sequoyah Nuclear Plant training staff developed the retake operating test.
All examination material was developed in accordance with the guidelines contained in Revision 10 of NUREG-1021. The NRC examiner reviewed the proposed examination.
Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021 and incorporated into the final version of the examination materials.
The NRC determined, using NUREG-1021, that the licensees retake operating test submittal was within the range of acceptability expected for a proposed examination.
One RO applicant passed the retake operating test. The applicant was issued a license.
A copy of the individual examination report was sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training.
The licensee did not submit any post-examination comments.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On July 28, 2016, the NRC examination team discussed generic issues associated with the retake operating test with K. Smith, Director of Training, and members of the Sequoyah Nuclear Plant staff. The examiners asked the licensee if any of the examination material was proprietary. No proprietary information was identified.
KEY POINTS OF CONTACT
Licensee personnel
K. Smith, Director of Training M. McMullin, Manager of Operations Training J. Johnson, Licensing T. Rieger, Operations W. Harris, Operations/Training A. Roddy, Operations/Training
Enclosure 2 SIMULATOR FIDELITY REPORT
Facility Licensee: Sequoyah Nuclear Plant Facility Docket No.: 50-327, 50-328 Operating Test Administered: July 28, 2016
This form is to be used only to report observations. These observations do not constitute audit or inspection findings and, without further verification and review in accordance with Inspection Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee action is required in response to these observations.
No simulator fidelity or configuration issues were identified.