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{{#Wiki_filter:July 17, 2006
{{#Wiki_filter:July 17, 2006
Tennessee Valley Authority
Tennessee Valley Authority
ATTN: Mr. Karl W. Singer
ATTN:
          Chief Nuclear Officer and
Mr. Karl W. Singer
            Executive Vice President
Chief Nuclear Officer and
  Executive Vice President
6A Lookout Place
6A Lookout Place
1101 Market Street
1101 Market Street
Chattanooga, TN 37402-2801
Chattanooga, TN 37402-2801
SUBJECT:       BROWNS FERRY NUCLEAR PLANT - NRC INSPECTION REPORT
SUBJECT:
              05000259/2006013, 05000260/2006013 AND 05000296/2006013
BROWNS FERRY NUCLEAR PLANT - NRC INSPECTION REPORT  
05000259/2006013, 05000260/2006013 AND 05000296/2006013
Dear Mr. Singer:
Dear Mr. Singer:
On June 23, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection at
On June 23, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection at
your Browns Ferry Nuclear Plant. The enclosed inspection report documents the inspection
your Browns Ferry Nuclear Plant. The enclosed inspection report documents the inspection
results, which were discussed on June 23, 2006, with Mr. B. OGrady and other members of
results, which were discussed on June 23, 2006, with Mr. B. OGrady and other members of
your staff.
your staff.  
The inspection examined activities conducted under your license as they relate to safety and
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
compliance with the Commissions rules and regulations and with the conditions of your license.  
The inspectors reviewed selected procedures and records, observed activities, and interviewed
The inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel.
personnel.
Line 40: Line 42:
enclosure will be available electronically for public inspection in the NRC Public Document
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRC's document system
Room or from the Publicly Available Records (PARS) component of NRC's document system
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this letter, please contact us.
Should you have any questions concerning this letter, please contact us.
                                              Sincerely,
Sincerely,
                                              /RA/
/RA/
                                              Brian R. Bonser, Chief
Brian R. Bonser, Chief
                                              Plant Support Branch 2
Plant Support Branch 2
                                              Division of Reactor Safety
Division of Reactor Safety
Docket Nos. 50-259, 05-260, 50-296
Docket Nos. 50-259, 05-260, 50-296
License No. DPR-33, DPR-52, DPR-68
License No. DPR-33, DPR-52, DPR-68
Enclosure: (See page 2)
Enclosure: (See page 2)


TVA                                         2
TVA
Enclosure:     NRC Inspection Report 05000259/2006013, 05000260/2006013, and
2
              05000296/2006013 w/Attachment: Supplemental Information
Enclosure:
NRC Inspection Report 05000259/2006013, 05000260/2006013, and
05000296/2006013 w/Attachment: Supplemental Information
cc w/encl:
cc w/encl:
Ashok S. Bhatnagar
Ashok S. Bhatnagar
Line 93: Line 97:
(cc w/encl contd - See page 3)
(cc w/encl contd - See page 3)


TVA                             3
TVA
3
(cc w/encl contd)
(cc w/encl contd)
William D. Crouch, Manager
William D. Crouch, Manager
Line 105: Line 110:
Suite 1552
Suite 1552
P. O. Box 303017
P. O. Box 303017
Montgomery, AL 36130-3017
Montgomery, AL 36130-3017
Chairman
Chairman
Limestone County Commission
Limestone County Commission
310 West Washington Street
310 West Washington Street
Athens, AL 35611
Athens, AL 35611
Masoud Bajestani, Vice President
Masoud Bajestani, Vice President
Browns Ferry Unit 1 Restart
Browns Ferry Unit 1 Restart
Line 115: Line 120:
Tennessee Valley Authority
Tennessee Valley Authority
P. O. Box 2000
P. O. Box 2000
Decatur, AL 35609
Decatur, AL 35609
Robert G. Jones, General Manager
Robert G. Jones, General Manager
Browns Ferry Site Operations
Browns Ferry Site Operations
Line 121: Line 126:
Tennessee Valley Authority
Tennessee Valley Authority
P. O. Box 2000
P. O. Box 2000
Decatur, AL 35609
Decatur, AL 35609
Distribution w/encl:
Distribution w/encl:
M. Chernoff, NRR
M. Chernoff, NRR  
E. Brown, NRR
E. Brown, NRR
S. Shaeffer, RII
S. Shaeffer, RII
Line 131: Line 136:


_________________________
_________________________
OFFICE             RII:DRS       RII:DRP       RII:DRS
OFFICE
SIGNATURE         RA             RA           RA
RII:DRS
NAME               LMILLER       MWIDMANN     BBONSER
RII:DRP
DATE                   7/17/2006     7/13/2006     7/17/2006     8/   /2006     8/   /2006   8/ /2006     8/ /2006
RII:DRS
E-MAIL COPY?         YES      NO   YES       NO YES       NO   YES      NO   YES     NO  YES     NO    YES    NO
SIGNATURE
       
RA
            U. S. NUCLEAR REGULATORY COMMISSION
RA
                                REGION II
RA
Docket No.:        50-259, 50-260, 50-296
NAME
License No.:      DPR-33, DPR-52, DPR-68
LMILLER
Report No:        05000259/2006013, 05000260/2006013, 05000296/2006013
MWIDMANN
Licensee:          Tennessee Valley Authority
BBONSER
Facility:          Browns Ferry Nuclear Power Plant
DATE
Location:          10833 Shaw Road
7/17/2006
                  Athens, AL
7/13/2006
Dates:            June 19-23, 2006
7/17/2006
Inspectors:        Lee Miller, Senior Emergency Preparedness Inspector
8/     /2006
                  Section 1EP2, 1EP3, 1EP4, 1EP5, 4OA1
8/     /2006
Approved by:      Brian R. Bonser, Chief
8/     /2006
                  Plant Support Branch 2
8/     /2006
                  Division of Reactor Safety
E-MAIL COPY?
                                                                  Enclosure
    YES
NO     YES
NO     YES
NO     YES
NO     YES
NO     YES
NO      YES
NO     


                                  SUMMARY OF FINDINGS
Enclosure
U. S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket No.:
50-259, 50-260, 50-296
License No.:
DPR-33, DPR-52, DPR-68
Report No:
05000259/2006013, 05000260/2006013, 05000296/2006013
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Power Plant
Location:
10833 Shaw Road
Athens, AL
Dates:
June 19-23, 2006
Inspectors:
Lee Miller, Senior Emergency Preparedness Inspector
Section 1EP2, 1EP3, 1EP4, 1EP5, 4OA1
Approved by:
Brian R. Bonser, Chief
Plant Support Branch 2
Division of Reactor Safety
 
SUMMARY OF FINDINGS
IR 05000259/2006013, 05000260/2006013, 05000296/2006-013; 06/19-23/2006; Browns Ferry
IR 05000259/2006013, 05000260/2006013, 05000296/2006-013; 06/19-23/2006; Browns Ferry
Nuclear Plant, Units 1, 2, and 3; Baseline Inspection
Nuclear Plant, Units 1, 2, and 3; Baseline Inspection
The report covered an announced inspection by a Region II emergency preparedness
The report covered an announced inspection by a Region II emergency preparedness
inspector. The NRCs program for overseeing the safe operation of commercial nuclear power
inspector. The NRCs program for overseeing the safe operation of commercial nuclear power
reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated
reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated
July 2000.
July 2000.
A.     NRC-Identified and Self-Revealing Findings
A.
      Cornerstone: Emergency Preparedness
NRC-Identified and Self-Revealing Findings
      None
Cornerstone: Emergency Preparedness
B.     Licensee-Identified Violations.
None
      None
B.
Licensee-Identified Violations.
None


                                                3
3
1.   REACTOR SAFETY
1.
    Cornerstone: Emergency Preparedness
REACTOR SAFETY
1EP2 Alert and Notification System Testing
Cornerstone: Emergency Preparedness
a. Inspection Scope
1EP2   Alert and Notification System Testing
    The inspectors evaluated the adequacy of licensee methods for testing the alert and
  a.
    notification system in accordance with NRC Inspection Procedure 71114, Attachment
Inspection Scope
    02, Alert and Notification System (ANS) Testing. The applicable planning standard
The inspectors evaluated the adequacy of licensee methods for testing the alert and
    10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D
notification system in accordance with NRC Inspection Procedure 71114, Attachment
    requirements were used as reference criteria. The criteria contained in NUREG-0654,
02, Alert and Notification System (ANS) Testing. The applicable planning standard
    Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and
10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D
    Preparedness in Support of Nuclear Power Plants, Revision 1, was also used as
requirements were used as reference criteria. The criteria contained in NUREG-0654,
    references.
Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and
    The inspectors reviewed various documents which are listed in the Attachment to this
Preparedness in Support of Nuclear Power Plants, Revision 1, was also used as
    report.
references.
b. Findings
The inspectors reviewed various documents which are listed in the Attachment to this
    No findings of significance were identified.
report.
1EP3 Emergency Response Organization (ERO) Augmentation
  b.
a. Inspection Scope
Findings
    The inspectors reviewed the ERO augmentation staffing requirements and the process
No findings of significance were identified.
    for notifying the ERO to ensure the readiness of key staff for responding to an event and
1EP3   Emergency Response Organization (ERO) Augmentation
    timely facility activation. The results of the December 20, 2005, unannounced off-hours
  a.
    augmentation drill was reviewed. The inspectors conducted a review of the backup
Inspection Scope
    notification systems. The qualification records of key position ERO personnel was
The inspectors reviewed the ERO augmentation staffing requirements and the process
    reviewed to ensure ERO qualifications were current. A sample of problems identified
for notifying the ERO to ensure the readiness of key staff for responding to an event and
    from augmentation drills or system tests performed since the last inspection were
timely facility activation. The results of the December 20, 2005, unannounced off-hours
    reviewed to assess the effectiveness of corrective actions.
augmentation drill was reviewed. The inspectors conducted a review of the backup
    The inspection was conducted in accordance with NRC Inspection Procedure 71114,
notification systems. The qualification records of key position ERO personnel was
    Attachment 03, Emergency Response Organization (ERO) Augmentation Testing.
reviewed to ensure ERO qualifications were current. A sample of problems identified
    The applicable planning standard, 10 CFR 50.47(b)(2) and its related 10 CFR 50,
from augmentation drills or system tests performed since the last inspection were
    Appendix E requirements were used as reference criteria.
reviewed to assess the effectiveness of corrective actions.
    The inspectors reviewed various documents which are listed in the Attachment to this
The inspection was conducted in accordance with NRC Inspection Procedure 71114,
    report.
Attachment 03, Emergency Response Organization (ERO) Augmentation Testing.  
The applicable planning standard, 10 CFR 50.47(b)(2) and its related 10 CFR 50,
Appendix E requirements were used as reference criteria.
The inspectors reviewed various documents which are listed in the Attachment to this
report.


                                                  4
4
b. Findings
  b.
    No findings of significance were identified.
Findings
1EP4 Emergency Action Level (EAL) and Emergency Plan Changes
No findings of significance were identified.
a. Inspection Scope
1EP4   Emergency Action Level (EAL) and Emergency Plan Changes
    The inspectors evaluated the associated 10 CFR 50.54(q) reviews associated with non-
  a.
    administrative emergency plan, implementing procedures and EAL changes. The
Inspection Scope
    revision 81 of the Emergency Plan covered the period from 03/22/2005 to 06/19/2006.
The inspectors evaluated the associated 10 CFR 50.54(q) reviews associated with non-
    The inspection was conducted in accordance with NRC Inspection Procedure 71114,
administrative emergency plan, implementing procedures and EAL changes. The
    Attachment 01, Emergency Action Level and Emergency Plan Changes. The
revision 81 of the Emergency Plan covered the period from 03/22/2005 to 06/19/2006.
    applicable planning standard, 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix
The inspection was conducted in accordance with NRC Inspection Procedure 71114,
    E requirements were used as reference criteria. The criteria contained in
Attachment 01, Emergency Action Level and Emergency Plan Changes. The
    NUMARC/NESP-007, Methodology for Development of Emergency Action Levels,
applicable planning standard, 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix
    Revision 2, Regulatory Guide 1.101 were also used as references.
E requirements were used as reference criteria. The criteria contained in
    The inspectors reviewed various documents which are listed in the Attachment to this
NUMARC/NESP-007, Methodology for Development of Emergency Action Levels,
    report.
Revision 2, Regulatory Guide 1.101 were also used as references.
b. Findings
The inspectors reviewed various documents which are listed in the Attachment to this
    No findings of significance were identified.
report.
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies
  b.
a.  Inspection Scope
Findings
    The inspectors reviewed the corrective actions identified through the EP program to
No findings of significance were identified.  
    determine the significance of the issues and to determine if repeat problems were
1EP5   Correction of Emergency Preparedness Weaknesses and Deficiencies
    occurring. The facilitys self-assessments and audits were reviewed to assess the
  a.   
    licensees ability to be self-critical, thus avoiding complacency and degradation of their
Inspection Scope
    EP program. In addition, inspectors review licensees self-assessments and audits to
The inspectors reviewed the corrective actions identified through the EP program to
    assess the completeness and effectiveness of all EP-related corrective actions.
determine the significance of the issues and to determine if repeat problems were
    The inspection was conducted in accordance with NRC Inspection Procedure 71114,
occurring. The facilitys self-assessments and audits were reviewed to assess the
    Attachment 05, Correction of Emergency Preparedness Weaknesses and
licensees ability to be self-critical, thus avoiding complacency and degradation of their
    Deficiencies. The applicable planning standard, 10 CFR 50.47(b)(14) and its related 10
EP program. In addition, inspectors review licensees self-assessments and audits to
    CFR 50, Appendix E requirements were used as reference criteria.
assess the completeness and effectiveness of all EP-related corrective actions.
    The inspectors reviewed various documents which are listed in the Attachment to this
The inspection was conducted in accordance with NRC Inspection Procedure 71114,
    report.
Attachment 05, Correction of Emergency Preparedness Weaknesses and
b.  Findings
Deficiencies. The applicable planning standard, 10 CFR 50.47(b)(14) and its related 10
    No findings of significance were identified.
CFR 50, Appendix E requirements were used as reference criteria.
The inspectors reviewed various documents which are listed in the Attachment to this
report.
  b.   
Findings
No findings of significance were identified.


                                                5
5
4.   OTHER ACTIVITIES
4.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
4OA1 Performance Indicator (PI) Verification
a. Inspection Scope
  a.  
    The inspectors reviewed the licensees procedure for developing the data for the
Inspection Scope
    Emergency Preparedness PIs which are: (1) Drill and Exercise Performance; (2) ERO
The inspectors reviewed the licensees procedure for developing the data for the
    Drill Participation; and (3) ANS Reliability. The inspectors examined data reported to the
Emergency Preparedness PIs which are: (1) Drill and Exercise Performance; (2) ERO
    NRC for the period April 1, 2005 to March 31, 2006. Procedural guidance for reporting
Drill Participation; and (3) ANS Reliability. The inspectors examined data reported to the
    PI information and records used by the licensee to identify potential PI occurrences
NRC for the period April 1, 2005 to March 31, 2006. Procedural guidance for reporting
    were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and
PI information and records used by the licensee to identify potential PI occurrences
    exercise performance through review of a sample of drill and event records. The
were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and
    inspectors reviewed selected training records to verify the accuracy of the PI for ERO
exercise performance through review of a sample of drill and event records. The
    drill participation for personnel assigned to key positions in the ERO. The inspectors
inspectors reviewed selected training records to verify the accuracy of the PI for ERO
    verified the accuracy of the PI for alert and notification system reliability through review
drill participation for personnel assigned to key positions in the ERO. The inspectors
    of a sample of the licensees records of periodic system tests.
verified the accuracy of the PI for alert and notification system reliability through review
    The inspection was conducted in accordance with NRC Inspection Procedure 71151,
of a sample of the licensees records of periodic system tests.
    Performance Indicator Verification. The applicable planning standard, 10 CFR 50.9
The inspection was conducted in accordance with NRC Inspection Procedure 71151,
    and NEI 99-02, Revision 3, Regulatory Assessment Performance Indicator Guidelines,
Performance Indicator Verification. The applicable planning standard, 10 CFR 50.9
    were used as reference criteria. This inspection activity represents three samples on an
and NEI 99-02, Revision 3, Regulatory Assessment Performance Indicator Guidelines,
    annual basis.
were used as reference criteria. This inspection activity represents three samples on an
    The inspectors reviewed various documents which are listed in the Attachment to this
annual basis.
    report.
The inspectors reviewed various documents which are listed in the Attachment to this
b. Findings
report.
    No findings of significance were identified.
  b.
Findings
No findings of significance were identified.
4OA6 Meetings, including Exit
4OA6 Meetings, including Exit
    On June 23, 2006, the inspector presented the inspection results to Mr. E. Willis,
On June 23, 2006, the inspector presented the inspection results to Mr. E. Willis,
    Manager - Operations, and other members of his staff acknowledged the findings. The
Manager - Operations, and other members of his staff acknowledged the findings. The
    team lead stated that additional information would be accepted and reviewed. The
team lead stated that additional information would be accepted and reviewed. The
    inspectors confirmed that proprietary information was not provided or taken during the
inspectors confirmed that proprietary information was not provided or taken during the
    inspection.
inspection.
ATTACHMENT: SUPPLEMENTAL INFORMATION
ATTACHMENT: SUPPLEMENTAL INFORMATION


                              SUPPLEMENTAL INFORMATION
Attachment
                                KEY POINTS OF CONTACT
A-1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
Licensee personnel
B. OGrady, Site Vice President
B. OGrady, Site Vice President
Line 280: Line 334:
J. Wallace, Site Licensing Engineer
J. Wallace, Site Licensing Engineer
D. White, Nuclear Assurance
D. White, Nuclear Assurance
                    LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Openned
Openned
None
None
Line 289: Line 343:
Discussed
Discussed
None
None
                                          A-1                  Attachment


                              LIST OF DOCUMENTS REVIEWED
Attachment
Section 1EP2: Alert and Notification System Testing
A-2
LIST OF DOCUMENTS REVIEWED
Section 1EP2:   Alert and Notification System Testing
Procedures
Procedures
EPIL (Emergency Preparedness Instruction Letter) -14, Facilitation of the Prompt Notification
EPIL (Emergency Preparedness Instruction Letter) -14, Facilitation of the Prompt Notification
System and Pager Tests, Rev. 9
  System and Pager Tests, Rev. 9
EPFS(Emergency Preparedness Field Support)-9, Inspection, Service, and Maintenance of the
EPFS(Emergency Preparedness Field Support)-9, Inspection, Service, and Maintenance of the
Prompt Notification System (PNS) at Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants,
Prompt Notification System (PNS) at Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants,
Rev. 1
  Rev. 1
Records and Data
Records and Data
Reviewed the maintenance records 2nd quarter 05 - 1st quarter 06
Reviewed the maintenance records 2nd quarter 05 - 1st quarter 06
Miscellaneous
Miscellaneous
Observed annual maintenance on siren #10 6/20/06
Observed annual maintenance on siren #10 6/20/06
Line 309: Line 364:
EPIL-14, Facilitation of the Prompt Notification System and Pager Tests, Rev. 9
EPIL-14, Facilitation of the Prompt Notification System and Pager Tests, Rev. 9
ETP-101, Site Emergency Director Training, Rev. 8 (lesson plan, handouts, written
ETP-101, Site Emergency Director Training, Rev. 8 (lesson plan, handouts, written
examination)
  examination)
ETP-102, Site Technical Support Center (TSC), Rev. 7 (lesson plan, handouts, lessons
ETP-102, Site Technical Support Center (TSC), Rev. 7 (lesson plan, handouts, lessons
learned, written examination)
  learned, written examination)
ETP-103, Operations Support Center (OSC), Rev. 7, (lesson plan, handouts, lessons learned,
ETP-103, Operations Support Center (OSC), Rev. 7, (lesson plan, handouts, lessons learned,
written examination)
  written examination)  
Records and Data
Records and Data
R92060104851, Orange Team Emergency Preparedness (EP) Unannounced Staffing Drill,
R92060104851, Orange Team Emergency Preparedness (EP) Unannounced Staffing Drill,
12/21/05
  12/21/05
Section 1EP4:Emergency Action Level (EAL) and Emergency Plan Changes
Section 1EP4:Emergency Action Level (EAL) and Emergency Plan Changes  
Procedures
Procedures
EPIP-1, Emergency Classification Procedure, Rev. 40
EPIP-1, Emergency Classification Procedure, Rev. 40
Line 325: Line 380:
EPIP-6, Activation and Operation of the TSC, Rev. 23
EPIP-6, Activation and Operation of the TSC, Rev. 23
Radiological Emergency Plan , Rev. 81
Radiological Emergency Plan , Rev. 81
                                                A-2                              Attachment


Attachment
A-3
Plans and Changes packages
Plans and Changes packages
Change package for Radiological Emergency Plan, Rev. 81
Change package for Radiological Emergency Plan, Rev. 81
Line 356: Line 412:
PER 100952, Discrepancy identified on EOI Team dispatched from OSC
PER 100952, Discrepancy identified on EOI Team dispatched from OSC
PER 102322, 3 of 5 candidates misapplied the Emergency Exposure Guidelines in EPIP-15
PER 102322, 3 of 5 candidates misapplied the Emergency Exposure Guidelines in EPIP-15
Section 4OA1: Performance Indicator (PI) Verification
Section 4OA1: Performance Indicator (PI) Verification
Procedures
Procedures
EPIL [Emergency Preparedness Instruction Letter] -15, Emergency Preparedness Performance
EPIL [Emergency Preparedness Instruction Letter] -15, Emergency Preparedness Performance
Line 368: Line 424:
Blue Team Training Drill package (scenario, time line, event notification forms, player logs and
Blue Team Training Drill package (scenario, time line, event notification forms, player logs and
completed procedures), 10/5/05
completed procedures), 10/5/05
                                                A-3                                  Attachment


Attachment
A-4
Green Team SAMG Training Drill package (scenario, time line, event notification forms, player
Green Team SAMG Training Drill package (scenario, time line, event notification forms, player
logs and completed procedures), 4/26/06
logs and completed procedures), 4/26/06
Line 379: Line 436:
Siren weekly and monthly tests 4/05 thru 3/06
Siren weekly and monthly tests 4/05 thru 3/06
Siren Maintenance records 4/05 thru 3/06
Siren Maintenance records 4/05 thru 3/06
                                    LIST OF ACRONYMS
LIST OF ACRONYMS
ANS       Alert and Notification System
ANS
EAL       Emergency Action Level
Alert and Notification System  
EP         Emergency Plan
EAL
ERO       Emergency Response Organization
Emergency Action Level
PI         Performance Indicator
EP
                                              A-4                                    Attachment
Emergency Plan  
ERO
Emergency Response Organization
PI
Performance Indicator
}}
}}

Latest revision as of 07:37, 15 January 2025

IR 05000259-06-013, 05000260-06-013, 05000296-06-013; 06/19-23/2006; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Baseline Inspection
ML062150108
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/17/2006
From: Brian Bonser
NRC/RGN-II/DRS/PSB2
To: Singer K
Tennessee Valley Authority
References
IR-06-013
Download: ML062150108 (13)


See also: IR 05000259/2006013

Text

July 17, 2006

Tennessee Valley Authority

ATTN:

Mr. Karl W. Singer

Chief Nuclear Officer and

Executive Vice President

6A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT - NRC INSPECTION REPORT

05000259/2006013, 05000260/2006013 AND 05000296/2006013

Dear Mr. Singer:

On June 23, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection at

your Browns Ferry Nuclear Plant. The enclosed inspection report documents the inspection

results, which were discussed on June 23, 2006, with Mr. B. OGrady and other members of

your staff.

The inspection examined activities conducted under your license as they relate to safety and

compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed

personnel.

Based on the results of this inspection no findings of significance were identified.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its

enclosure will be available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records (PARS) component of NRC's document system

(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this letter, please contact us.

Sincerely,

/RA/

Brian R. Bonser, Chief

Plant Support Branch 2

Division of Reactor Safety

Docket Nos. 50-259,05-260, 50-296

License No. DPR-33, DPR-52, DPR-68

Enclosure: (See page 2)

TVA

2

Enclosure:

NRC Inspection Report 05000259/2006013, 05000260/2006013, and

05000296/2006013 w/Attachment: Supplemental Information

cc w/encl:

Ashok S. Bhatnagar

Senior Vice President

Nuclear Operations

Tennessee Valley Authority

Electronic Mail Distribution

Larry S. Bryant, Vice President

Nuclear Engineering & Technical Services

Tennessee Valley Authority

Electronic Mail Distribution

Brian O'Grady

Site Vice President

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Preston D. Swafford

Senior Vice President

Nuclear Support

Tennessee Valley Authority

Electronic Mail Distribution

General Counsel

Tennessee Valley Authority

Electronic Mail Distribution

John C. Fornicola, Manager

Nuclear Assurance and Licensing

Tennessee Valley Authority

Electronic Mail Distribution

Bruce M. Aukland, Plant Manager

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Glenn W. Morris, Manager

Corporate Nuclear Licensing

and Industry Affairs

Tennessee Valley Authority

Electronic Mail Distribution

(cc w/encl contd - See page 3)

TVA

3

(cc w/encl contd)

William D. Crouch, Manager

Licensing and Industry Affairs

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

State Health Officer

Alabama Dept. of Public Health

RSA Tower - Administration

Suite 1552

P. O. Box 303017

Montgomery, AL 36130-3017

Chairman

Limestone County Commission

310 West Washington Street

Athens, AL 35611

Masoud Bajestani, Vice President

Browns Ferry Unit 1 Restart

Browns Ferry Nuclear Plant

Tennessee Valley Authority

P. O. Box 2000

Decatur, AL 35609

Robert G. Jones, General Manager

Browns Ferry Site Operations

Browns Ferry Nuclear Plant

Tennessee Valley Authority

P. O. Box 2000

Decatur, AL 35609

Distribution w/encl:

M. Chernoff, NRR

E. Brown, NRR

S. Shaeffer, RII

RIDSNRRDIRS

PUBLIC

_________________________

OFFICE

RII:DRS

RII:DRP

RII:DRS

SIGNATURE

RA

RA

RA

NAME

LMILLER

MWIDMANN

BBONSER

DATE

7/17/2006

7/13/2006

7/17/2006

8/ /2006

8/ /2006

8/ /2006

8/ /2006

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO

Enclosure

U. S. NUCLEAR REGULATORY COMMISSION

REGION II

Docket No.:

50-259, 50-260, 50-296

License No.:

DPR-33, DPR-52, DPR-68

Report No:

05000259/2006013, 05000260/2006013, 05000296/2006013

Licensee:

Tennessee Valley Authority

Facility:

Browns Ferry Nuclear Power Plant

Location:

10833 Shaw Road

Athens, AL

Dates:

June 19-23, 2006

Inspectors:

Lee Miller, Senior Emergency Preparedness Inspector

Section 1EP2, 1EP3, 1EP4, 1EP5, 4OA1

Approved by:

Brian R. Bonser, Chief

Plant Support Branch 2

Division of Reactor Safety

SUMMARY OF FINDINGS

IR 05000259/2006013, 05000260/2006013, 05000296/2006-013; 06/19-23/2006; Browns Ferry

Nuclear Plant, Units 1, 2, and 3; Baseline Inspection

The report covered an announced inspection by a Region II emergency preparedness

inspector. The NRCs program for overseeing the safe operation of commercial nuclear power

reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated

July 2000.

A.

NRC-Identified and Self-Revealing Findings

Cornerstone: Emergency Preparedness

None

B.

Licensee-Identified Violations.

None

3

1.

REACTOR SAFETY

Cornerstone: Emergency Preparedness

1EP2 Alert and Notification System Testing

a.

Inspection Scope

The inspectors evaluated the adequacy of licensee methods for testing the alert and

notification system in accordance with NRC Inspection Procedure 71114, Attachment

02, Alert and Notification System (ANS) Testing. The applicable planning standard

10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D

requirements were used as reference criteria. The criteria contained in NUREG-0654,

Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and

Preparedness in Support of Nuclear Power Plants, Revision 1, was also used as

references.

The inspectors reviewed various documents which are listed in the Attachment to this

report.

b.

Findings

No findings of significance were identified.

1EP3 Emergency Response Organization (ERO) Augmentation

a.

Inspection Scope

The inspectors reviewed the ERO augmentation staffing requirements and the process

for notifying the ERO to ensure the readiness of key staff for responding to an event and

timely facility activation. The results of the December 20, 2005, unannounced off-hours

augmentation drill was reviewed. The inspectors conducted a review of the backup

notification systems. The qualification records of key position ERO personnel was

reviewed to ensure ERO qualifications were current. A sample of problems identified

from augmentation drills or system tests performed since the last inspection were

reviewed to assess the effectiveness of corrective actions.

The inspection was conducted in accordance with NRC Inspection Procedure 71114,

Attachment 03, Emergency Response Organization (ERO) Augmentation Testing.

The applicable planning standard, 10 CFR 50.47(b)(2) and its related 10 CFR 50,

Appendix E requirements were used as reference criteria.

The inspectors reviewed various documents which are listed in the Attachment to this

report.

4

b.

Findings

No findings of significance were identified.

1EP4 Emergency Action Level (EAL) and Emergency Plan Changes

a.

Inspection Scope

The inspectors evaluated the associated 10 CFR 50.54(q) reviews associated with non-

administrative emergency plan, implementing procedures and EAL changes. The

revision 81 of the Emergency Plan covered the period from 03/22/2005 to 06/19/2006.

The inspection was conducted in accordance with NRC Inspection Procedure 71114,

Attachment 01, Emergency Action Level and Emergency Plan Changes. The

applicable planning standard, 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix

E requirements were used as reference criteria. The criteria contained in

NUMARC/NESP-007, Methodology for Development of Emergency Action Levels,

Revision 2, Regulatory Guide 1.101 were also used as references.

The inspectors reviewed various documents which are listed in the Attachment to this

report.

b.

Findings

No findings of significance were identified.

1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies

a.

Inspection Scope

The inspectors reviewed the corrective actions identified through the EP program to

determine the significance of the issues and to determine if repeat problems were

occurring. The facilitys self-assessments and audits were reviewed to assess the

licensees ability to be self-critical, thus avoiding complacency and degradation of their

EP program. In addition, inspectors review licensees self-assessments and audits to

assess the completeness and effectiveness of all EP-related corrective actions.

The inspection was conducted in accordance with NRC Inspection Procedure 71114,

Attachment 05, Correction of Emergency Preparedness Weaknesses and

Deficiencies. The applicable planning standard, 10 CFR 50.47(b)(14) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.

The inspectors reviewed various documents which are listed in the Attachment to this

report.

b.

Findings

No findings of significance were identified.

5

4.

OTHER ACTIVITIES

4OA1 Performance Indicator (PI) Verification

a.

Inspection Scope

The inspectors reviewed the licensees procedure for developing the data for the

Emergency Preparedness PIs which are: (1) Drill and Exercise Performance; (2) ERO

Drill Participation; and (3) ANS Reliability. The inspectors examined data reported to the

NRC for the period April 1, 2005 to March 31, 2006. Procedural guidance for reporting

PI information and records used by the licensee to identify potential PI occurrences

were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and

exercise performance through review of a sample of drill and event records. The

inspectors reviewed selected training records to verify the accuracy of the PI for ERO

drill participation for personnel assigned to key positions in the ERO. The inspectors

verified the accuracy of the PI for alert and notification system reliability through review

of a sample of the licensees records of periodic system tests.

The inspection was conducted in accordance with NRC Inspection Procedure 71151,

Performance Indicator Verification. The applicable planning standard, 10 CFR 50.9

and NEI 99-02, Revision 3, Regulatory Assessment Performance Indicator Guidelines,

were used as reference criteria. This inspection activity represents three samples on an

annual basis.

The inspectors reviewed various documents which are listed in the Attachment to this

report.

b.

Findings

No findings of significance were identified.

4OA6 Meetings, including Exit

On June 23, 2006, the inspector presented the inspection results to Mr. E. Willis,

Manager - Operations, and other members of his staff acknowledged the findings. The

team lead stated that additional information would be accepted and reviewed. The

inspectors confirmed that proprietary information was not provided or taken during the

inspection.

ATTACHMENT: SUPPLEMENTAL INFORMATION

Attachment

A-1

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

B. OGrady, Site Vice President

J. DeDomenico, Assistant Plant Manager

T. Elms, Manager - Operations

T. Feltman, Emergency Preparedness

B. Marks, Emergency Services - Corporate

R. Delong, Site Engineering Manager

W. Crouch, Site Licensing Manager

J. Wallace, Site Licensing Engineer

D. White, Nuclear Assurance

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Openned

None

Openned and Closed

None

Closed

None

Discussed

None

Attachment

A-2

LIST OF DOCUMENTS REVIEWED

Section 1EP2: Alert and Notification System Testing

Procedures

EPIL (Emergency Preparedness Instruction Letter) -14, Facilitation of the Prompt Notification

System and Pager Tests, Rev. 9

EPFS(Emergency Preparedness Field Support)-9, Inspection, Service, and Maintenance of the

Prompt Notification System (PNS) at Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants,

Rev. 1

Records and Data

Reviewed the maintenance records 2nd quarter 05 - 1st quarter 06

Miscellaneous

Observed annual maintenance on siren #10 6/20/06

Section 1EP3: Emergency Response Organization (ERO) Augmentation

Procedures

TRN-30, Radiological Emergency Preparedness Training, Rev. 12

EPIP-1, Emergency Classification Procedure, Rev. 40

EPIL-14, Facilitation of the Prompt Notification System and Pager Tests, Rev. 9

ETP-101, Site Emergency Director Training, Rev. 8 (lesson plan, handouts, written

examination)

ETP-102, Site Technical Support Center (TSC), Rev. 7 (lesson plan, handouts, lessons

learned, written examination)

ETP-103, Operations Support Center (OSC), Rev. 7, (lesson plan, handouts, lessons learned,

written examination)

Records and Data

R92060104851, Orange Team Emergency Preparedness (EP) Unannounced Staffing Drill,

12/21/05

Section 1EP4:Emergency Action Level (EAL) and Emergency Plan Changes

Procedures

EPIP-1, Emergency Classification Procedure, Rev. 40

EPIP-3, Alert, Rev. 30

EPIP-4, Site Area Emergency, Rev. 28

EPIP-5, General Emergency, Rev. 33

EPIP-6, Activation and Operation of the TSC, Rev. 23

Radiological Emergency Plan , Rev. 81

Attachment

A-3

Plans and Changes packages

Change package for Radiological Emergency Plan, Rev. 81

Change package for EPIP-1, Emergency Classification Procedure, Rev. 39

Change package for EPIP-1, Emergency Classification Procedure, Rev. 40

Change package for EPIP-3, Alert, Rev. 30

Change package for EPIP-2, Notification of Unusual Event, Rev. 27

Change package for EPIP-4, Site Area Emergency, Rev. 29

Change package for EPIP-5, General Emergency, Rev. 35

Change package for EPIP-6, Activation and Operation of the Technical Support Center (TSC) -

Rev. 24

Section 1EP5:Correction of Emergency Preparedness Weaknesses and Deficiencies

Procedures

EPIL [Emergency Preparedness Instruction Letter] -5, EP Tracking System Activities

Management Oversight System (AMOS), Rev. 5

Records and Data

Matrix of Scenarios versus Shift Manager and Site Emergency Directors

PER 101086, Reutilized scenario resulted in Shift Manager being evaluated on same scenario.

PER 79742, Ambulance Communications problems

PER 82137, EPIP-1, Table data not displayed

PER 81140, EPIP-3, Appendix A wrong date entered and faxed to Operations Duty Specialist

PER 82142, OSC Staging Area craftsmen lacking Mask fits

PER 82145, Integrated Training Drill - Containment venting not reduced or isolated

PER 82147, 2005 Integrated Training Drill - 2-AOI 100-1 two procedure change identified

PER 84027, Alternate Source Term and Standby Liquid Control system questions

PER 86493, Incorrect revision of training material used during Maintenance Block training

PER 89240, Emergency Responders - two doors marked Emergency Exits were locked shut

PER 100950, Missed Performance Indicator during 2006 Blue Team Training Drill

PER 100952, Discrepancy identified on EOI Team dispatched from OSC

PER 102322, 3 of 5 candidates misapplied the Emergency Exposure Guidelines in EPIP-15

Section 4OA1: Performance Indicator (PI) Verification

Procedures

EPIL [Emergency Preparedness Instruction Letter] -15, Emergency Preparedness Performance

Indicators, Rev. 10

Records and Data

Documentation of DEP opportunities from Operations Simulator evaluations on 04/27/2005,

06/8/2005, 07/13/2005, 10/5/2005,11/14/05, 11/19/05, 11/21/05, 11/28/05, 12/5/05, 12/12/05

Selected training records of drill/exercise participation by ERO personnel during 2005

R92051201851, 2005 Radiochemistry (Post Accident Sampling) Drill, 12/1/2005

EPIP-10, MERT, actual event 3/29/05 - contaminated injured person transported to hospital

Blue Team Training Drill package (scenario, time line, event notification forms, player logs and

completed procedures), 10/5/05

Attachment

A-4

Green Team SAMG Training Drill package (scenario, time line, event notification forms, player

logs and completed procedures), 4/26/06

Red Team Training Drill package (scenario, time line, event notification forms, player logs and

completed procedures), 7/13/06

Blue Team Training Drill package (scenario, time line, event notification forms, player logs and

completed procedures), 4/12/06

Data for Drill/Exercise Performance (1 quarter 2005 - 1 quarter 2006)

Siren weekly and monthly tests 4/05 thru 3/06

Siren Maintenance records 4/05 thru 3/06

LIST OF ACRONYMS

ANS

Alert and Notification System

EAL

Emergency Action Level

EP

Emergency Plan

ERO

Emergency Response Organization

PI

Performance Indicator