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#REDIRECT [[IR 05000259/2011302]]
{{Adams
| number = ML112640385
| issue date = 09/19/2011
| title = Er 05000259-11-302, 05000260-11-302, and 05000296-11-302, Operating Test August 8 - 12, 2011 & Written Exam August 19, 2011; Browns Ferry Nuclear Plant, Operator License Examinations
| author name = Franke M
| author affiliation = NRC/RGN-II/DRS
| addressee name = Krich R
| addressee affiliation = Tennessee Valley Authority
| docket = 05000259, 05000260, 05000296
| license number = DPR-033, DPR-052, DPR-068
| contact person =
| case reference number = 50-259/11-302, 50-260/11-302, 50-296/11-302
| document type = Letter, License-Operator Examination Report
| page count = 11
}}
See also: [[see also::IR 05000296/2011302]]
 
=Text=
{{#Wiki_filter:UNITED STATES
                                NUCLEAR REGULATORY COMMISSION
                                              REGION II
                            245 PEACHTREE CENTER AVENUE NE, SUITE 1200
                                    ATLANTA, GEORGIA 30303-1257
                                        September 19, 2011
Tennessee Valley Authority
ATTN: Mr. R. M. Krich
        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 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).
 
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          RA            RA            RA              RA            RA              RA
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:                              Senior Resident Inspector
K. J. Polson                            U.S. Nuclear Regulatory Commission
Site Vice President                      Browns Ferry Nuclear Plant
Browns Ferry Nuclear Plant              U.S. Nuclear Regulatory Commission
Tennessee Valley Authority              10833 Shaw Road
Electronic Mail Distribution            Athens, AL 35611-6970
C.J. Gannon                              Mr. Jeff Morris
General Manager                          Training Manager
Browns Ferry Nuclear Plant              Browns Ferry Nuclear Plant
Tennessee Valley Authority              Tennessee Valley Authority
Electronic Mail Distribution            P. O. Box 2000
                                        Decatur, AL 35609-2000
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
 
TVA                                        4
Letter to R. M. Krich 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
 
              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.
                                                                                    Enclosure 1
 
                                      REPORT DETAILS
4.    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 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 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
      licensees 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.
                                                                                    Enclosure 1
 
                                            4
    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
                                                                                    Enclosure 1
 
                              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
                                                                  Attachment
 
                                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.
                                                                                      Enclosure 2
}}

Revision as of 14:19, 12 November 2019

Er 05000259-11-302, 05000260-11-302, and 05000296-11-302, Operating Test August 8 - 12, 2011 & Written Exam August 19, 2011; Browns Ferry Nuclear Plant, Operator License Examinations
ML112640385
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 09/19/2011
From: Mark Franke
Division of Reactor Safety II
To: Krich R
Tennessee Valley Authority
References
50-259/11-302, 50-260/11-302, 50-296/11-302
Download: ML112640385 (11)


See also: IR 05000296/2011302

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

September 19, 2011

Tennessee Valley Authority

ATTN: Mr. R. M. Krich

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 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).

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 RA RA RA RA RA RA

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: Senior Resident Inspector

K. J. Polson U.S. Nuclear Regulatory Commission

Site Vice President Browns Ferry Nuclear Plant

Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission

Tennessee Valley Authority 10833 Shaw Road

Electronic Mail Distribution Athens, AL 35611-6970

C.J. Gannon Mr. Jeff Morris

General Manager Training Manager

Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant

Tennessee Valley Authority Tennessee Valley Authority

Electronic Mail Distribution P. O. Box 2000

Decatur, AL 35609-2000

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

TVA 4

Letter to R. M. Krich 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

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.

Enclosure 1

REPORT DETAILS

4. 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 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 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

licensees 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.

Enclosure 1

4

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.

23-57, Standby Coolant Valve from RHRSW.

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

Enclosure 1

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

Attachment

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.

Enclosure 2