IR 05000259/2012301

Er 05000259-12-301, 05000260-12-301 & 05000296-12-301; 05/17 - 18/2012 & Written Exam 05/18/2012; Browns Ferry Nuclear Plant, Operator License Examinations

ML12201B521
Person / Time
Site:	Browns Ferry
Issue date:	07/16/2012
From:	Franke M E Division of Reactor Safety II
To:	Shea J W Tennessee Valley Authority
References
50-259/12-301, 50-260/12-301, 50-296/12-301
Preceding documents:	ML120440372 (10 February 2012)
Download: ML12201B521 (12)

Text

July 16, 2012

Mr. Joseph Manager, Corp. Nuclear Licensing Programs Tennessee Valley Authority 1101 Market Street, LP 4B-C Chattanooga, TN 37402-2801

SUBJECT: BROWNS FERRY NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT NOS 05000259/2012301, 05000260/2012301 AND 05000296/2012301

Dear Mr. Shea:

During the period May 7 - 17, 2012, the Nuclear Regulatory Commission (NRC) administered operating tests to employees of your company who had applied for licenses to operate the Browns Ferry 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 18, 2012.

Four Reactor Operator (RO) applicants, four Senior Reactor Operator (SRO) upgrade and five SRO instant applicants were administered both the operating test and written examination. One of these RO applicants was a retake examination. Additionally, two RO and one SRO applicants who were granted waivers for a previously passed operating test were administered only the written examination. A total of sixteen applicants received a portion or the entire examination. All applicants passed the written and the operating examination with the exception of three SRO instant applicants who failed only the written examination. There was one post-examination comment concerning the written examination. This comment, and the NRC resolution of the comment, is summarized in Enclosure 2. A Simulator Fidelity Report is included in this report as Enclosure 3. Two applicants, one RO and one SRO, who passed the operating test and passed the written exam with a score between 80% and 82% for the RO applicant and a score between 70% and 74% for the SRO applicant were issued a letter identifying that the issuance of their license has been delayed pending any written examination appeals that may impact the licensing decision for their application.

The initial SRO portion of the written 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. 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 9, Supplement 1. In accordance with 10 CFR 2.390 of the NRC's "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 NRC's 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) 997-4436.

Sincerely,/RA/ Mark E. Franke, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-259, 50-260, 50-296 License Nos: DPR-33, DPR-52, DPR-68

Enclosures:

1. Report Details 2. Facility Comments and NRC Resolution 3. Simulator Fidelity Report cc w/encls. (See page 3) In accordance with 10 CFR 2.390 of the NRC's "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 NRC's 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) 997-4436.

Sincerely,/RA/ Mark E. Franke, Chief Operations Branch 2 Division of Reactor Safety Docket Nos: 50-259, 50-260, 50-296 License Nos: DPR-33, DPR-52, DPR-68

Enclosures:

1. Report Details 2. Facility Comments and NRC Resolution 3. Simulator Fidelity Report cc w/encls. (See page 3)

XG PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE XG NON-SENSITIVE ADAMS:X G Yes ACCESSION NUMBER:_________________________ XG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII;DRP RUI;DRS SIGNATURE RA RA RA RA RA NAME RBALDWIN KSCHAAF MRICHES EGUTHRIE MFRANKE DATE 7/16/2012 7/16/2012 7/16/2012 7/16/2012 7/16/2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\OLEXAMS\BROWNS FERRY EXAMINATIONS\BF 2012-301 INITIAL EXAM (RICK)\CORRESPONDENCE\BROWNS FERRY 2012301 EXAMINATION REPORT FINAL RSB REV 0_MJR 7-16.DOCX cc w/encls: K. J. Polson Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution C.J. Gannon General Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution James E. Emens Manager, Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution Manager, Corporate Nuclear Licensing - BFN Tennessee Valley Authority Electronic Mail Distribution Edward J. Vigluicci Assistant General Counsel Tennessee Valley Authority Electronic Mail Distribution T. A. Hess Tennessee Valley Authority Electronic Mail Distribution Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Donald E. Williamson State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017

James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Mr. Michael J. Wilson Training Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609-2000 Letter to Joseph from Mark E. Franke dated July 16, 2012.

SUBJECT: BROWNS FERRY NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT NOS 05000259/2012301, 05000260/2012301 AND 05000296/2012301 Distribution w/encls: RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II

Docket Nos.: 50-259, 50-260, AND 50-296 License Nos.: DPR-33, DPR-52, and DPR-68 Report Nos.: 05000259/2012301, 05000260/2012301, and 05000296/2012301 Licensee: Tennessee Valley Authority (TVA), LLC Facility: Browns Ferry Nuclear Plant, Units 1, 2, and 3 Location: Athens, AL 35611 Dates: Operating Test - May 7 - 17, 2012 Written Examination - May 18, 2012 Examiners: Richard S. Baldwin, Chief Examiner, Senior Operations Engineer, RII/DRS/OLB2 Kenneth D. Schaaf, Operations Engineer, RII/DRS/OLB1 Mark J. Riches, Operations Engineer, RII/DRS/OLB1 Approved by: Mark E. Franke, Chief Operations Branch 2 Division of Reactor Safety Enclosure 1 SUMMARY OF FINDINGS ER 05000259/2012301, 05000260/2012301, and 05000296/2012301; operating test May 7 - 17, 2012, & written exam May 18, 2012; Browns Ferry 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. The NRC developed the written examination outline. Members of the Browns Ferry Nuclear Plant staff developed both the operating tests and the written examination. Four Reactor Operator (RO) applicants, four Senior Reactor Operator (SRO) upgrade and five SRO instant applicants were administered both the operating test and written examination. One of these RO applicants was a retake examination. Additionally, two RO and one SRO applicants who were granted waivers for a previously passed operating test were administered only the written examination. A total of sixteen applicants received a portion or the entire examination. All applicants passed the written and the operating examination with the exception of three SRO instant applicants who failed only the written examination. There was one post-examination comment concerning the written examination. This comment, and the NRC resolution of the comment, is summarized in Enclosure 2. A Simulator Fidelity Report is included in this report as Enclosure 3. Two applicants, one RO and one SRO, who passed the operating test and passed the written exam with a score between 80% and 82% for the RO applicant and a score between 70% and 74% for the SRO applicant were issued a letter identifying that the issuance of their license has been delayed pending any written examination appeals that may impact the licensing decision for their application. There was one post-examination comment.

No findings were identified.

Enclosure 1 REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Operator Licensing Examinations a. Inspection Scope The NRC developed the written examination outline. Members of the Browns Ferry Nuclear Plant 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 licensee's 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 six Reactor Operator (RO) and ten Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period May 7 - 17, 2012. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on May 18, 2012. Evaluations of applications and reviews of associated documentation were performed to determine if the applicants who applied for licenses to operate the Browns Ferry Nuclear Power Plant met the requirements specified in 10 CFR Part 55, "Operators' Licenses." b. Findings The NRC determined that the licensee's written examination submittal was outside the range of acceptable quality specified in NUREG-1021. The initial written examination submittal was outside the range of acceptable quality because more than 20 percent [SRO Exam: 6 of 25] of questions sampled for review contained unacceptable flaws. Individual questions were evaluated as unsatisfactory due to questions not meeting the K/A statement contained in the examination outline, questions containing two or more implausible distractors, questions on the SRO examination not written at the SRO license level, and questions containing other unacceptable psychometric flaws. The NRC determined that the licensee's initial operating test submittal was within the range of acceptability expected for a proposed examination. Four Reactor Operator (RO) applicants, four Senior Reactor Operator (SRO) upgrade and five SRO instant applicants were administered both the operating test and written examination. One of these RO applicants was a retake examination. Additionally, two RO and one SRO applicants who were granted waivers for a previously passed operating test were administered only the written examination. A total of sixteen applicants received a portion or the entire examination. All applicants passed the 4 Enclosure 1 written and the operating examination with the exception of three SRO instant applicants who failed only the written examination. There was one post-examination comment concerning the written examination. This comment, and the NRC resolution of the comment, is summarized in Enclosure 2. A Simulator Fidelity Report is included in this report as Enclosure 3.

Two applicants, one RO and one SRO, who passed the operating test and passed the written exam with a score between 80% and 82% for the RO applicant and a score between 70% and 74% for the SRO applicant were issued a letter identifying that the 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 one post-examination comment concerning the written examination (ADAMS under Accession Number ML12188A684). A copy of the final SRO and RO written examination and answer key, with all changes incorporated, and the licensee's post-examination comments may be accessed not earlier than July 03, 2014, in the ADAMS system (ADAMS Accession Numbers ML12188A682 and ML12188A680). 4OA6 Meetings Exit Meeting Summary On May 17, 2012, the NRC examination team discussed generic issues associated with the operating test with Mr. M. Rasmussen, Operations Manager, and members of the Browns Ferry 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 J. Davenport, Site Licensing M. Rasmussen, Operations Superintendent J. Ruby, Examination Team, Operations Training J. Emens, Site Licensing Manager B. Stetson, Operations Training D. Hakenewerth, Operations Examination Facility Representative D. Zielinski, Examination Team, Operations Training W. Rees, Operations J. Barker, Operations DTC B. Tidwell, Acting Training Director J. Dills, Operations Training Supervisor M. Gibson, Examination Team, Operations Training NRC personnel C. Stancil, Resident Inspector Enclosure 2 FACILITY POST-EXAMINATION COMMENT AND NRC RESOLUTION A complete text of the licensee's post examination comments can be found in ADAMS under Accession Number ML 12188A684. SRO Question #92 LICENSEE COMMENT:

The question deals with the determination of the required action statement associated with Technical Requirements Manual (TRM) 3.3.5, "Surveillance instrumentation," and the control rod position in accordance with Technical Specification (TS) SR 3.1.3.1, "Determine the position of each Control Rod," associated with the loss of Panel 2-9-9 Cabinet 6, Unit Preferred. The licensee contends that the initially selected answer, "D," was not correct and that was proven by use of the TRM bases and TRM Table 3.3.5-1 documentation and discussions between the training and operations departments. The licensee states that answering the first part of the question associated with TRM 3.3.5 requires entry into TRM 3.3.5.2.C, which is indicated in the TRM Bases. Because of this the licensee states that the correct answer should be changed from "D" to "B." NRC DISCUSSION:

The NRC agrees with the licensee's comment. Based on the above discussion, the licensee's recommendation is accepted and the answer to the question will be changed from "D" to the new correct answer of "B." The answer key will be changed to reflect that the question's answer was changed to "B."

Enclosure 3 SIMULATOR FIDELITY REPORT Facility Licensee: Browns Ferry Nuclear Plant Facility Docket No.: 05000259, 05000260, 05000296 Operating Test Administered: May 07 - 17, 2012 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 Description NONE NA