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==Dear Mr. Krich:== | ==Dear Mr. Krich:== | ||
During the period August 8 - 12, 2011, 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 the plant staff identified in the enclosed report. The written examination was administered by the plant training department staff on August 19, 2011. Four Reactor Operator (RO) and three Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One RO applicant failed both the written and operating exam. Four RO applicants and one SRO applicant failed the written examination. There were no post-examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2. | During the period August 8 - 12, 2011, 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 the plant staff identified in the enclosed report. The written examination was administered by the plant training department staff on August 19, 2011. | ||
Four Reactor Operator (RO) and three Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One RO applicant failed both the written and operating exam. Four RO applicants and one SRO applicant failed the written examination. There were no post-examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2. | |||
The initial operating examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and the plant training staff were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1. | The initial operating examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and the plant training staff were made according to NUREG-1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1. | ||
| Line 34: | Line 36: | ||
TVA 2 If you have any questions concerning this letter, please contact me at (404) 997- 4436 | TVA 2 If you have any questions concerning this letter, please contact me at (404) 997- 4436 | ||
Sincerely,/RA: Malcolm Widmann for/ 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 | Sincerely,/RA: Malcolm Widmann for/ | ||
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:=== | ===Enclosures:=== | ||
1 Report Details 2. Simulator Fidelity Report cc w/encls: (See page 3) | 1 Report Details 2. Simulator Fidelity Report cc w/encls: (See page 3) | ||
TVA | |||
_ML112640385____________ | |||
G SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RIV:DRS RII:DRP RII:DRS SIGNATURE R A R A R A R A R A R A NAME BCABALLERO ELEA MRICHES GAPGER EGUTHRIE MFRANKE DATE 9/8/2011 9/ 8 /2011 9/14 /2011 9/16/2011 9/ 14/2011 9/19 /2011 9/ /2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO TVA 3 cc w/encl: 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 J. E. Emens Manager, Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution | |||
T. C. Matthews Manager, Corporate Nuclear Licensing - | |||
BFN Tennessee Valley Authority Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel 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 U.S. Nuclear Regulatory Commission 10833 Shaw Road Athens, AL 35611-6970 | |||
Mr. Jeff Morris Training Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609-2000 | |||
TVA 4 Letter to R. from Mark E. Franke dated September 19, 2011. | |||
SUBJECT: BROWNS FERRY NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000259/2011302, 05000260/2011302, AND 05000296/2011302 Distribution w/encl: | |||
RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource | |||
Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II | |||
Docket No.: 50-259, 50-260, AND 50-296 | |||
License No.: DPR-33, DPR-52, and DPR-68 Report No.: 05000259/2011302, 05000260/2011302, and 05000296/2011302 | |||
Licensee: Tennessee Valley Authority (TVA), LLC | |||
Facility: Browns Ferry Nuclear Plant, Units 1, 2, and 3 Location: Athens, AL 35611 | |||
Dates: Operating Test - August 8 - 12, 2011 Written Examination - August 19, 2011 | |||
Examiners: Bruno Caballero, Chief, Senior Operations Engineer, RII/DRS/OLB2 Edwin Lea, Senior Operations Engineer, RII/DRS/OLB2 Mark Riches, Operations Engineer, RII/DRS/OLB1 Gabe Apger, Senior Operations Engineer, RIV/DRS/OLB Approved by: Mark E. Franke, Chief Operations Branch 2 Division of Reactor Safety Enclosure 1 | |||
=SUMMARY OF FINDINGS= | =SUMMARY OF FINDINGS= | ||
| Line 58: | Line 78: | ||
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. | 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 operating tests were developed by members of the Browns Ferry Nuclear Plant staff and the written examination was developed by the NRC. The NRC administered the operating tests during the period August 8 - 12, 2011. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on August 19, 2011. Four Reactor Operator (RO) and three Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. Five applicants were issued licenses commensurate with the level of examination administered. Two 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. | The operating tests were developed by members of the Browns Ferry Nuclear Plant staff and the written examination was developed by the NRC. | ||
The NRC administered the operating tests during the period August 8 - 12, 2011. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on August 19, 2011. Four Reactor Operator (RO) and three Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. Five applicants were issued licenses commensurate with the level of examination administered. Two 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 no post-examination comments. | |||
No findings were identified. | |||
1 | 1 | ||
| Line 71: | Line 95: | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
The operating tests were developed by members of the Browns Ferry Nuclear Plant staff and the written examination 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 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 potential for an exam security compromise occurred on May 23, 2011 (SR# 374670) when the Unit 3 simulator computers were prematurely reconnected to the network; however, no actual exam compromise occurred. | The operating tests were developed by members of the Browns Ferry Nuclear Plant staff and the written examination 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 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 potential for an exam security compromise occurred on May 23, 2011 (SR# 374670) when the Unit 3 simulator computers were prematurely reconnected to the network; however, no actual exam compromise occurred. | |||
The NRC examiners evaluated eight Reactor Operator (RO) and four Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period August 8 - 12, 2011. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on August 19, 2011. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Browns Ferry Nuclear Plant, met the requirements specified in 10 CFR Part 55, "Operators' Licenses." | The NRC examiners evaluated eight Reactor Operator (RO) and four Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period August 8 - 12, 2011. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on August 19, 2011. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Browns Ferry Nuclear Plant, met the requirements specified in 10 CFR Part 55, "Operators' Licenses." | ||
| Line 86: | Line 112: | ||
* During job performance measures (JPMs), several applicants did not locate 1-FCV-23-57, Standby Coolant Valve from RHRSW. | * During job performance measures (JPMs), several applicants did not locate 1-FCV-23-57, Standby Coolant Valve from RHRSW. | ||
* During JPMs, most of the applicants did not readily locate the main steam line drain valves' position indicator, ZI-1-174, at Panel 9-3. | * During JPMs, most of the applicants did not readily locate the main steam line drain valves' position indicator, ZI-1-174, at Panel 9-3. | ||
* During an alternate path JPM associated with emergency venting the drywell via the suppression chamber hardened vent valves, several applicants still attempted to open the inboard hardened vent valve even though the outboard hardened vent valve (in series) had already failed to open. Consequently, in two instances, the primary containment pressure exceeded 55 psig before the applicants abandoned the hardened vent valves and continued in the procedure to vent the drywell directly to the reactor building. 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 RO and SRO written examinations and answer keys, with all changes incorporated, may be accessed not earlier than August 19, 2013, in the ADAMS system (ADAMS Accession Numbers ML112370110 and ML112370111, respectively). | * During an alternate path JPM associated with emergency venting the drywell via the suppression chamber hardened vent valves, several applicants still attempted to open the inboard hardened vent valve even though the outboard hardened vent valve (in series) had already failed to open. Consequently, in two instances, the primary containment pressure exceeded 55 psig before the applicants abandoned the hardened vent valves and continued in the procedure to vent the drywell directly to the reactor building. | ||
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 RO and SRO written examinations and answer keys, with all changes incorporated, may be accessed not earlier than August 19, 2013, in the ADAMS system (ADAMS Accession Numbers ML112370110 and ML112370111, respectively). | |||
{{a|4OA6}} | {{a|4OA6}} | ||
==4OA6 Meetings, Including Exit== | ==4OA6 Meetings, Including Exit== | ||
===Exit Meeting Summary=== | |||
On August 12, 2011, the NRC Chief Examiner discussed generic issues associated with the operating test with Daniel L. Hughes, Operations Manager, and members of the Browns Ferry staff. The examiners asked the licensee if any of the examination material was proprietary. The information that the licensee identified as proprietary was handled in a manner consistent with NRC and licensee guidelines for this type of information. | On August 12, 2011, the NRC Chief Examiner discussed generic issues associated with the operating test with Daniel L. Hughes, Operations Manager, and members of the Browns Ferry staff. The examiners asked the licensee if any of the examination material was proprietary. The information that the licensee identified as proprietary was handled in a manner consistent with NRC and licensee guidelines for this type of information. | ||
| Line 97: | Line 129: | ||
=SUPPLEMENTAL INFORMATION= | =SUPPLEMENTAL INFORMATION= | ||
SUPPLEMENTAL INFORMATION | SUPPLEMENTAL INFORMATION | ||
KEY POINTS OF CONTACT | |||
===Licensee personnel=== | ===Licensee personnel=== | ||
: [[contact::D. L. Hughes]], Operations Manager Matthew | : [[contact::D. L. Hughes]], Operations Manager Matthew | ||
| Line 106: | Line 140: | ||
: [[contact::J. Doyle]], Assistant Site Vice President Technical Assistant James Emens, Site Licensing Manager James | : [[contact::J. Doyle]], Assistant Site Vice President Technical Assistant James Emens, Site Licensing Manager James | ||
: [[contact::W. Davenport]], Site Licensing Cris Boschetti, BFN Quality Assurance Manager | : [[contact::W. Davenport]], Site Licensing Cris Boschetti, BFN Quality Assurance Manager | ||
Steve Bono, BFN Maintenance Manager Bill Nurenberger, Work Control Manager Robert Norris, Radiation Protection Manager Michael Durr, Engineering Director Steve Brown, Projects Supervisor | Steve Bono, BFN Maintenance Manager Bill Nurenberger, Work Control Manager Robert Norris, Radiation Protection Manager Michael Durr, Engineering Director Steve Brown, Projects Supervisor | ||
===NRC personnel=== | ===NRC personnel=== | ||
Thierry Ross, Senior Resident Inspector | Thierry Ross, Senior Resident Inspector | ||
SIMULATOR FIDELITY REPORT | SIMULATOR FIDELITY REPORT | ||
Facility Licensee: Browns Ferry | Facility Licensee: Browns Ferry | ||
Operating Test Administered: August 8 - 12, 2011 | Facility Docket No.: 50-259, 50-260, and 50-296 | ||
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. | Operating Test Administered: August 8 - 12, 2011 | ||
This form is used only to report observations. The 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. | |||
}} | }} | ||
Revision as of 01:22, 3 August 2018
| ML112640385 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/19/2011 |
| From: | Franke M E Division of Reactor Safety II |
| To: | Krich R M Tennessee Valley Authority |
| References | |
| 50-259/11-302, 50-260/11-302, 50-296/11-302 | |
| Download: ML112640385 (11) | |
Text
September 19, 2011
Tennessee Valley Authority ATTN: Mr. R. Vice President, Nuclear Licensing 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT: BROWNS FERRY NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000259/2011302, 05000260/2011302, AND 05000296/2011302
Dear Mr. Krich:
During the period August 8 - 12, 2011, 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 the plant staff identified in the enclosed report. The written examination was administered by the plant training department staff on August 19, 2011.
Four Reactor Operator (RO) and three Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One RO applicant failed both the written and operating exam. Four RO applicants and one SRO applicant failed the written examination. There were no post-examination comments. A Simulator Fidelity Report is included in this report as Enclosure 2.
The initial operating examination submittal was within the range of acceptability expected for a proposed examination. All examination changes agreed upon between the NRC and the plant training 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).
TVA 2 If you have any questions concerning this letter, please contact me at (404) 997- 4436
Sincerely,/RA: Malcolm Widmann for/
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. Simulator Fidelity Report cc w/encls: (See page 3)
_ML112640385____________
G SUNSI REVIEW COMPLETE G FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RIV:DRS RII:DRP RII:DRS SIGNATURE R A R A R A R A R A R A NAME BCABALLERO ELEA MRICHES GAPGER EGUTHRIE MFRANKE DATE 9/8/2011 9/ 8 /2011 9/14 /2011 9/16/2011 9/ 14/2011 9/19 /2011 9/ /2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO TVA 3 cc w/encl: 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 J. E. Emens Manager, Licensing Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution
T. C. Matthews Manager, Corporate Nuclear Licensing -
BFN Tennessee Valley Authority Electronic Mail Distribution E. J. Vigluicci Assistant General Counsel 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 U.S. Nuclear Regulatory Commission 10833 Shaw Road Athens, AL 35611-6970
Mr. Jeff Morris Training Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609-2000
TVA 4 Letter to R. from Mark E. Franke dated September 19, 2011.
SUBJECT: BROWNS FERRY NUCLEAR PLANT - NRC OPERATOR LICENSE EXAMINATION REPORT 05000259/2011302, 05000260/2011302, AND 05000296/2011302 Distribution w/encl:
RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource
Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II
Docket No.: 50-259, 50-260, AND 50-296
License No.: DPR-33, DPR-52, and DPR-68 Report No.: 05000259/2011302, 05000260/2011302, and 05000296/2011302
Licensee: Tennessee Valley Authority (TVA), LLC
Facility: Browns Ferry Nuclear Plant, Units 1, 2, and 3 Location: Athens, AL 35611
Dates: Operating Test - August 8 - 12, 2011 Written Examination - August 19, 2011
Examiners: Bruno Caballero, Chief, Senior Operations Engineer, RII/DRS/OLB2 Edwin Lea, Senior Operations Engineer, RII/DRS/OLB2 Mark Riches, Operations Engineer, RII/DRS/OLB1 Gabe Apger, Senior Operations Engineer, RIV/DRS/OLB Approved by: Mark E. Franke, Chief Operations Branch 2 Division of Reactor Safety Enclosure 1
SUMMARY OF FINDINGS
ER 05000259/2011302, 05000260/2011302, and 05000296/2011302; operating test August 8 - 12, 2011 & written exam August 19, 2011; 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 operating tests were developed by members of the Browns Ferry Nuclear Plant staff and the written examination was developed by the NRC.
The NRC administered the operating tests during the period August 8 - 12, 2011. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on August 19, 2011. Four Reactor Operator (RO) and three Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. Five applicants were issued licenses commensurate with the level of examination administered. Two 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 no post-examination comments.
No findings were identified.
1
REPORT DETAILS
OTHER ACTIVITIES
4OA5 Operator Licensing Examinations
a. Inspection Scope
The operating tests were developed by members of the Browns Ferry Nuclear Plant staff and the written examination 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 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 potential for an exam security compromise occurred on May 23, 2011 (SR# 374670) when the Unit 3 simulator computers were prematurely reconnected to the network; however, no actual exam compromise occurred.
The NRC examiners evaluated eight Reactor Operator (RO) and four Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. The examiners administered the operating tests during the period August 8 - 12, 2011. Members of the Browns Ferry Nuclear Plant training staff administered the written examination on August 19, 2011. Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Browns Ferry Nuclear Plant, met the requirements specified in 10 CFR Part 55, "Operators' Licenses."
b. Findings
No findings were identified. The NRC determined, using NUREG-1021, that the licensee's initial operating examination submittal was within the range of acceptability expected for a proposed examination.
Four RO applicants and three SRO applicants passed both the operating test and written examination. Three RO applicants and one SRO applicant passed the operating test but did not pass the written examination. One RO applicant failed both the written and operating exam. Additionally, one RO "retake" applicant, who was waived from taking the operating exam, did not pass the written examination. Two RO applicants and three SRO applicants were issued licenses.
Two RO applicants passed the operating test, but passed the written examination with overall scores between 80% and 82%. Each of these applicants was 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.
1 During administration of the operating exam, the examiners noted the following generic weaknesses.
- During exam scenarios, after the control rod drive (CRD) flow controller had failed to operate in the automatic mode, the applicants did not promptly restore system flow by operating the controller in manual mode, which resulted in several CRD temperatures exceeding 350 °F, which was an operability concern.
- During job performance measures (JPMs), several applicants did not locate 1-FCV-23-57, Standby Coolant Valve from RHRSW.
- During JPMs, most of the applicants did not readily locate the main steam line drain valves' position indicator, ZI-1-174, at Panel 9-3.
- During an alternate path JPM associated with emergency venting the drywell via the suppression chamber hardened vent valves, several applicants still attempted to open the inboard hardened vent valve even though the outboard hardened vent valve (in series) had already failed to open. Consequently, in two instances, the primary containment pressure exceeded 55 psig before the applicants abandoned the hardened vent valves and continued in the procedure to vent the drywell directly to the reactor building.
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 RO and SRO written examinations and answer keys, with all changes incorporated, may be accessed not earlier than August 19, 2013, in the ADAMS system (ADAMS Accession Numbers ML112370110 and ML112370111, respectively).
4OA6 Meetings, Including Exit
Exit Meeting Summary
On August 12, 2011, the NRC Chief Examiner discussed generic issues associated with the operating test with Daniel L. Hughes, Operations Manager, and members of the Browns Ferry staff. The examiners asked the licensee if any of the examination material was proprietary. The information that the licensee identified as proprietary was handled in a manner consistent with NRC and licensee guidelines for this type of information.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- D. L. Hughes, Operations Manager Matthew
- M. Rasmussen, Operations Superintendent Micah Nash, Operations Shift Manager Joe Bennett, Operations Unit Supervisor David Malinowski, Operations Training Manager
Barry
- D. Tidwell, Training Supervisor Dan Zielinski, Exam Team Developer David
- C. Matherly, Senior Manager, BFN Focus Gerald
- J. Doyle, Assistant Site Vice President Technical Assistant James Emens, Site Licensing Manager James
- W. Davenport, Site Licensing Cris Boschetti, BFN Quality Assurance Manager
Steve Bono, BFN Maintenance Manager Bill Nurenberger, Work Control Manager Robert Norris, Radiation Protection Manager Michael Durr, Engineering Director Steve Brown, Projects Supervisor
NRC personnel
Thierry Ross, Senior Resident Inspector
SIMULATOR FIDELITY REPORT
Facility Licensee: Browns Ferry
Facility Docket No.: 50-259, 50-260, and 50-296
Operating Test Administered: August 8 - 12, 2011
This form is used only to report observations. The 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.