IR 05000327/2013301
| ML13177A347 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/25/2013 |
| From: | Widmann M Division of Reactor Safety II |
| To: | James Shea Tennessee Valley Authority |
| References | |
| 50-327/13-301 | |
| Preceding documents: |
|
| Download: ML13177A347 (8) | |
Text
June 25, 2013
SUBJECT:
SEQUOYAH NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000327/2013301 AND 05000328/2013301
Dear Shea:
During the period May 13 - 16, 2013, the Nuclear Regulatory Commission (NRC) administered operating tests to employees of your company who had applied for licenses to operate the Sequoyah Nuclear Plant. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests with those members of your staff identified in the enclosed report. The written examination was administered by your staff on May 23, 2013.
Three Reactor Operator (RO) and one Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One SRO applicant failed the written examination.
There were no post exam comments. A Simulator Fidelity Report is included in this report as Enclosure 2.
The initial written RO examination and 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
J. Shea
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 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.:
Report No.:
05000327/2013301, 05000328/2013301
Licensee:
Tennessee Valley Authority (TVA)
Facility:
Sequoyah Nuclear Plant, Units 1 & 2
Location:
Sequoyah Access Road Soddy-Daisy, TN 37379
Dates:
Operating Test - May 13-16, 2013
Written Examination - May 23, 2013
Examiners:
Michael Meeks, Chief Examiner, Senior Operations Engineer
Daniel Bacon, Chief Examiner (Under Instruction), Operations Engineer
David Lanyi, Operations Engineer
Approved by:
Malcolm T. Widmann, Chief
Operations Branch 1
Division of Reactor Safety
Enclosure 1 SUMMARY OF FINDINGS
ER 05000327/2013301, 05000328/2013301, May 13 - 16, 2013 & May 23, 2013; Sequoyah Nuclear Plant; Operator License Examinations.
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 9, Supplement 1, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.
Members of the Sequoyah Nuclear Plant training staff developed both the operating tests and the written examination. The initial written RO examination and initial written SRO examination submittals did not meet the quality guidelines contained in NUREG-1021.
The NRC administered the operating tests during the period May 13-16, 2013. Members of the Sequoyah Nuclear Plant training staff administered the written examination on May 23, 2013.
Three Reactor Operator (RO) applicants and one Senior Reactor Operator (SRO) applicant passed both the operating test and written examination. Four applicants were issued licenses commensurate with the level of examination administered.
There were no post-examination comments.
No findings were identified.
Enclosure 1 REPORT DETAILS
4.
OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a.
Inspection Scope
Members of the Sequoyah Nuclear Plant training staff developed both the operating tests and the written examination. 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. Four minor issues of concern related to examination security were identified during preparation and administration of the examination. All of these issues were immediately evaluated by the Chief Examiner and discussed with the Branch Chief. In each case, it was determined that no actual compromise of the examination occurred. The following examination security related events occurred:
- The NRC exam room key was lost during the evening of 4/2/2013. All examination material stored in the NRC exam room was also locked in a separate security container. The NRC exam room lock was replaced upon discovery. Refer to Sequoyah Problem Evaluation Report (PER) # 706756.
- Upon completion of a scenario validation during preparation week, a pink tag identifying a failed component was found by an evening shift instructor following disestablishment of simulator examination security. The scenario event that potentially could have been compromised was modified. Refer to PER # 716741 and the associated Apparent Cause Evaluation.
- During validation of a scenario, an NRC examiner discovered markings on a laminated sheet that contained information from a scenario validated the previous day. Refer to PER # 716741 and the associated Apparent Cause Evaluation.
- An instructor not on the NRC exam security agreement momentarily entered the back of the simulator while simulator exam security was set and a Job Performance Measure (JPM) was being administered by the NRC. This event did not cause a disruption in the administered JPM. The involved instructor was immediately counseled and added to the NRC exam security agreement. Refer to PER # 728788.
The NRC examiners evaluated three Reactor Operator (RO) applicants and two Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021.
The examiners administered the operating tests during the period May 13-16, 2013.
Members of the Sequoyah Nuclear Plant training staff administered the written examination on May 23, 2013. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses
Enclosure 1 to operate the Sequoyah Nuclear Plant, met the requirements specified in 10 CFR Part 55, Operators Licenses.
b.
Findings
The NRC determined that the licensees examination submittal was outside the range of acceptable quality specified by NUREG-1021. The initial RO written examination submittal and initial SRO written examination submittal were outside the range of acceptable quality because more than 20% (RO exam: 23 of 75 and SRO exam: 8 of 25) of questions sampled for review contained unacceptable flaws. Individual questions were evaluated as unsatisfactory for the following reasons:
- One RO question failed to meet the K/A statement contained in the examination outline.
- Twenty-two RO questions contained two or more implausible distractors.
- Five SRO questions contained two or more implausible distractors.
- One SRO question contained other unacceptable psychometric flaws.
- Three RO questions contained multiple unacceptable flaws.
Administration of the written examination was delayed by one day, in part, because the quality of the licensees examination submittal was unacceptable. Future examination submittals need to incorporate lessons learned.
The NRC determined that the licensees initial operating test submittal was within the range of acceptability expected for a proposed examination.
Three RO applicants and one SRO applicant passed both the operating test and written examination. One SRO applicant passed the operating test but did not pass the written examination. Three RO applicants and one SRO applicant were issued licenses.
Copies of all individual examination reports were sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training.
The licensee did not submit any post-examination comments. A copy of the final written examination and answer key, with all changes incorporated may be accessed not earlier than May 25, 2015, in the ADAMS system (ADAMS Accession Number(s)
ML13161A063 and ML13161A064.
4OA6 Meetings, Including Exit
Exit Meeting Summary
On May 16, 2013, the NRC examination team discussed generic issues associated with the operating test with Mr. Paul Simmons, Sequoyah Nuclear Plant Manager, 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.
Enclosure 1 KEY POINTS OF CONTACT
Licensee personnel P. Simmons, Sequoyah Nuclear Plant Manager S. Connors, Operations Manager K. Smith, Director of Training D. Hawes, Operations Training Manager M. McMullin, Operations Training Supervisor S. Smith, Operations Instructor M. Buckner, Operations Instructor, Exam Developer N. Good, Simulator Manager J. Johnson, Program Manager K. Wilkes, Operations Training Liaison, SRO M. Hime, Operations Instructor, Class Lead S. Nakamine, Operations SRO, Site Representative
NRC personnel G. Smith, Senior Resident Inspector
Enclosure 2 SIMULATOR FIDELITY REPORT
Facility Licensee: Sequoyah Nuclear Plant
Facility Docket No.: 50-327, 50-328
Operating Test Administered: May 13-16, 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.
While conducting the simulator portion of the operating test, examiners observed the following:
Item DR # 5546 SR-726751 / PER-727218 Description The Hydrogen Recombiner A-A power switch 1-HS-83-5005 was not working reliably. There was no spare available for repairs.