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Line 3: Line 3:
| issue date = 06/22/2009
| issue date = 06/22/2009
| title = Notification of Browns Ferry Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 0500259-09-008, 05000260-09-008, and 05000296-09-008
| title = Notification of Browns Ferry Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 0500259-09-008, 05000260-09-008, and 05000296-09-008
| author name = Desai B B
| author name = Desai B
| author affiliation = NRC/RGN-I/DRS/EB1
| author affiliation = NRC/RGN-I/DRS/EB1
| addressee name = Swafford P D
| addressee name = Swafford P
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000259, 05000260, 05000296
| docket = 05000259, 05000260, 05000296
Line 14: Line 14:
| page count = 4
| page count = 4
}}
}}
See also: [[followed by::IR 05000259/2009008]]
See also: [[see also::IR 05000259/2009008]]


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER  61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA  30303-8931
{{#Wiki_filter:UNITED STATES  
  June 22, 2009  
NUCLEAR REGULATORY COMMISSION  
REGION II  
SAM NUNN ATLANTA FEDERAL CENTER   
61 FORSYTH STREET, SW, SUITE 23T85  
ATLANTA, GEORGIA  30303-8931  
June 22, 2009  
   
   
Mr. Preston D. Swafford  
Mr. Preston D. Swafford  
Line 26: Line 32:
1101 Market Street  
1101 Market Street  
Chattanooga, TN 37402-2801  
Chattanooga, TN 37402-2801  
   
   
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT  
SUBJECT:  
NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT  
DESIGN BASES INSPECTION - NRC INSPECTION REPORT  
05000259/2009008, 05000260/2009008, AND 05000296/2009008  
05000259/2009008, 05000260/2009008, AND 05000296/2009008  
   
   
Dear Mr. Swafford:  
Dear Mr. Swafford:  
   
   
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
Region II staff will conduct a com
Region II staff will conduct a component design bases inspection at your Browns Ferry Nuclear  
ponent design bases inspection at your Browns Ferry Nuclear  
Plant during the period of September 28 - November 20, 2009.  The inspection team will be led  
Plant during the period of September 28 - November 20, 2009.  The inspection team will be led by Mr. Robert Berryman, a Senior Reactor Inspector from the NRC's Region II Office.  This  
by Mr. Robert Berryman, a Senior Reactor Inspector from the NRC's Region II Office.  This  
inspection will be conducted in accordance with the baseline  
inspection will be conducted in accordance with the baseline inspection procedure, Procedure
inspection proc
71111.21, Component Design Bases Inspection, issued August 19, 2008.  
edure, Pr ocedure 71111.21, Component Design Bases Inspection, issued August 19, 2008.  
 
   
   
The inspection will evaluate the capability of risk significant / low margin components to function  
The inspection will evaluate the capability of risk significant / low margin components to function  
as designed and to support proper system operation.  The inspection will also include a review of selected operator actions, operating experience, and modifications.   
as designed and to support proper system operation.  The inspection will also include a review  
 
of selected operator actions, operating experience, and modifications.   
   
   
During a telephone conversation on June 18, 2009, Mr. Berryman confirmed, with Mr. Jim  
During a telephone conversation on June 18, 2009, Mr. Berryman confirmed, with Mr. Jim  
Davenport of your staff, arrangements for an information gathering site visit and the three-week  
Davenport of your staff, arrangements for an information gathering site visit and the three-week  
onsite inspection. The schedule is as follows:  
onsite inspection. The schedule is as follows:  
 
* Information gathering visit:  Week of September 28-October 2, 2009.  
*  
* Onsite weeks:  Weeks of October 19 - 23, November 2 - 6, and November 16 - 20, 2009.   
Information gathering visit:  Week of September 28-October 2, 2009.  
*  
Onsite weeks:  Weeks of October 19 - 23, November 2 - 6, and November 16 - 20, 2009.   
   
   
The purpose of the information gathering visit is to meet with members of your staff to identify  
The purpose of the information gathering visit is to meet with members of your staff to identify  
risk-significant components and operator actions.  Information and documentation needed to  
risk-significant components and operator actions.  Information and documentation needed to  
support the inspection will also be identified and  
support the inspection will also be identified and gathered or requested.  Mr. Walt Rogers, a  
gathered or requested.  Mr. Wa
Region II Senior Reactor Analyst, may accompany Mr. Berryman during the information  
lt Rogers, a Region II Senior Reactor Analyst, may accompany Mr. Berryman during the information  
gathering visit to review probabilistic risk assessment data and identify risk significant  
gathering visit to review pr
components which will be examined during the inspection.  
obabilistic risk a
ssessment data and identify risk significant components which will be exami
ned during the  
inspection.  
   
   
   
   
Line 69: Line 71:
   
   
   
   
 
TVA 2   The enclosure lists documents that will be needed prior to the information gathering visi
 
t.  Please contact Mr. Berryman with any questions prior to preparing materials listed in the enclosure and  
TVA  
2  
The enclosure lists documents that will be needed prior to the information gathering visit.  Please  
contact Mr. Berryman with any questions prior to preparing materials listed in the enclosure and  
provide the referenced information to the Region II office by September 15, 2009.  The  
provide the referenced information to the Region II office by September 15, 2009.  The  
inspectors will try to minimize your administrative burden by specifically identifying only those documents required for the inspection preparation.  
inspectors will try to minimize your administrative burden by specifically identifying only those  
 
documents required for the inspection preparation.  
   
   
During the information gathering visit, the team leader will also discuss the following inspection support administrative details: office space; site, plant and information system access; required  
During the information gathering visit, the team leader will also discuss the following inspection  
support administrative details: office space; site, plant and information system access; required  
resources; and information exchange protocol.  
resources; and information exchange protocol.  
   
   
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its  
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 ins
enclosure will be available electronically for public inspection in the NRC Public Document Room  
pection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system  
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).  
(ADAMS).  ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
 
rm/adams.html (the Public Electronic Reading Room).  
   
   
Thank you for your cooperation in this matter.  If you have any questions regarding the  
Thank you for your cooperation in this matter.  If you have any questions regarding the  
information requested or the inspection, please contact Mr. Berryman at (404) 562-4817 or me  
information requested or the inspection, please contact Mr. Berryman at (404) 562-4817 or me  
at (404) 562-4519.  
at (404) 562-4519.  
   
   
      Sincerely,
   
   
      /RA/  
 
Binoy B. Desai, Chief       Engineering Branch 1 Division of Reactor Safety  
  Docket Nos.: 50-259, 50-260, 50-296   
Sincerely,
/RA/  
Binoy B. Desai, Chief
Engineering Branch 1  
Division of Reactor Safety  
   
Docket Nos.: 50-259, 50-260, 50-296  
   
License Nos.:  DPR-33, DPR-52, DPR-68  
License Nos.:  DPR-33, DPR-52, DPR-68  
   
   
Enclosure:  Information Request for Browns Ferry Nuclear Plant Component Design Bases  
Enclosure:  Information Request for Browns Ferry Nuclear Plant Component Design Bases  
Inspection  
Inspection  
   
   
cc w/encl:  (See page 3)  
cc w/encl:  (See page 3)  


_________________________
  SUNSI REVIEW COMPLETE
OFFICE
RII:DRS
RII:DRS
   
   
   
   
SIGNATURE
/RA/
/RA/
   
   
   
   
    
NAME
R. Berryman
B. Desai
DATE
06/22/2009
06/22/2009
E-MAIL COPY?
    YES      NO      YES      NO   
   YES        NO   
  YES        NO   
  YES        NO   
  YES      NO   
  YES        NO   


_________________________    SUNSI REVIEW COMPLETE
TVA
  OFFICE RII:DRS RII:DRS      SIGNATURE /RA/ /RA/      NAME R. Berryman B. Desai      DATE 06/22/2009 06/22/2009      E-MAIL COPY?    YES      NO      YES      NO      YES        NO      YES        NO      YES        NO      YES      NO      YES        NO     
TVA      3   cc w/encls: Ashok S. Bhatnagar, Senior VP  
   
3  
cc w/encls:  
Ashok S. Bhatnagar, Senior VP  
Nuclear Generation Development and  
Nuclear Generation Development and  
Construction  
Construction  
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Preston D. Swafford  
Preston D. Swafford  
Line 125: Line 201:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
William R. Campbell, Senior VP  
William R. Campbell, Senior VP  
Line 133: Line 208:
1101 Market Place  
1101 Market Place  
Chattanooga, TN 37402-2801  
Chattanooga, TN 37402-2801  
   
   
Thomas Coutu, Vice President  
Thomas Coutu, Vice President  
Line 139: Line 213:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
R. G. (Rusty) West, Site Vice President  
R. G. (Rusty) West, Site Vice President  
Line 145: Line 218:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Frederick Russell Godwin  
Frederick Russell Godwin  
Line 153: Line 225:
P.O. Box 2000  
P.O. Box 2000  
Decatur, AL 35609  
Decatur, AL 35609  
   
   
James J. Randich, Plant Manager  
James J. Randich, Plant Manager  
Line 159: Line 230:
Tennessee Valley Authority  
Tennessee Valley Authority  
P.O. Box 2000  
P.O. Box 2000  
   
   
Ludwig E. Thibault, General Manager  
Ludwig E. Thibault, General Manager  
Line 167: Line 237:
1101 Market Street  
1101 Market Street  
Chattanooga, TN 37402-2801  
Chattanooga, TN 37402-2801  
 
General Counsel Tennessee Valley Authority  
General Counsel  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Larry E. Nicholson, General Manager  
Larry E. Nicholson, General Manager  
Line 176: Line 246:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Michael A. Purcell  
Michael A. Purcell  
Line 183: Line 252:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Michael J. Lorek, Vice President  
Michael J. Lorek, Vice President  
Line 189: Line 257:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Fredrick C. Mashburn, Acting Manager  
Fredrick C. Mashburn, Acting Manager  
Line 196: Line 263:
Tennessee Valley Authority  
Tennessee Valley Authority  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Senior Resident Inspector  
Senior Resident Inspector  
Line 203: Line 269:
10833 Shaw Road  
10833 Shaw Road  
Athens, AL 35611-6970  
Athens, AL 35611-6970  
   
   
Kirksey E. Whatley, Director  
Kirksey E. Whatley, Director  
Line 209: Line 274:
Alabama Dept. of Public Health  
Alabama Dept. of Public Health  
Electronic Mail Distribution  
Electronic Mail Distribution  
   
   
Chairman  
Chairman  
Line 215: Line 279:
310 West Washington Street  
310 West Washington Street  
Athens, AL 35611  
Athens, AL 35611  
   
   
Dr. D. E. Williamson  
Dr. D. E. Williamson  
Line 221: Line 284:
Alabama Dept. of Public Health  
Alabama Dept. of Public Health  
Electronic Mail Distribution  
Electronic Mail Distribution  


 
TVA  
TVA     4  Letter to Preston D. Swafford from Binoy B. Desai, dated June 22, 2009
   
   
SUBJECT: NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT DESIGN BASES INSPECTION  - NRC INSPECTION REPORT  
4
Letter to Preston D. Swafford from Binoy B. Desai, dated June 22, 2009
SUBJECT:  
NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT  
DESIGN BASES INSPECTION  - NRC INSPECTION REPORT  
05000259/2009008, 05000260/2009008, AND 05000296/2009008  
05000259/2009008, 05000260/2009008, AND 05000296/2009008  
   
   
Distribution w/encl
Distribution w/encl:
: Eva Brown, NRR  
Eva Brown, NRR  
PUBLIC  
PUBLIC  
RidsNrrPMBrownsFerry Resource  
RidsNrrPMBrownsFerry Resource  
Institute of Nuclear Power Operations (INPO)  
Institute of Nuclear Power Operations (INPO)
  Enclosure INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR PLANT  COMPONENT DESIGN BASES INSPECTION  
 
Enclosure  
INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR PLANT   
COMPONENT DESIGN BASES INSPECTION  
   
   
Please provide the information electronically in ".pdf" files, Excel, or other searchable format on  
Please provide the information electronically in .pdf files, Excel, or other searchable format on  
CDROM.  The CDROM should be indexed and possibly hyperlinked to facilitate ease of use.  Information in "lists" should contain enough information to be easily understood to someone who  
CDROM.  The CDROM should be indexed and possibly hyperlinked to facilitate ease of use.   
Information in lists should contain enough information to be easily understood to someone who  
has knowledge of pressurized water reactor technology.  
has knowledge of pressurized water reactor technology.  
1. From your most
recent probabilistic safety analysis (PSA) excluding external events and fires, please provide: a. Two risk rankings of components from your site-specific probabilistic safety analysis (PSA) - one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance. b. A list of the top 500 cutsets.
2. From your most
recent probabilistic safety analysis (PSA) including external events and fires, please provide: a. Two risk rankings of components from your site-specific probabilistic safety analysis (PSA) - one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance. b. A list of the top 500 cutsets.
   
   
3. Risk ranking of operator actions from your site specific PSA sorted by RAW.  Provide copies of your human reliability worksheets for  
1.
these items. 4. Any pre-existing evaluation or list of components and calculations with low design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close  
From your most recent probabilistic safety analysis (PSA) excluding external events and
fires, please provide:
a.
Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA) - one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance.
b.
A list of the top 500 cutsets.
2.
From your most recent probabilistic safety analysis (PSA) including external events and
fires, please provide:
a.
Two risk rankings of components from your site-specific probabilistic safety
analysis (PSA) - one sorted by Risk Achievement Worth (RAW), and the other
sorted by Birnbaum Importance.
b.
A list of the top 500 cutsets.
3.  
Risk ranking of operator actions from your site specific PSA sorted by RAW.  Provide  
copies of your human reliability worksheets for these items.  
4.  
Any pre-existing evaluation or list of components and calculations with low design  
margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close  
to design required output, heat exchangers close to rated design heat removal, MOV risk-
to design required output, heat exchangers close to rated design heat removal, MOV risk-
margin rankings, etc.). 5. A list of station applicability evaluations/reviews performed and document
margin rankings, etc.).  
ed in the station corrective action program in the past two years for industry events, critical equipment  
5.  
failures, and safety related equipment vul
A list of station applicability evaluations/reviews performed and documented in the station  
nerabilities (as communicated by NRC generic communications, industry communications, 10 CFR Part 21 notifications, etc.). 6. A list of operability evaluations completed within the last two years, sorted by associated component or system. 7. A list of common-cause failures of components that have occurred at Browns Ferry Nuclear Plant and have been identified within the last five years. 8. A list of equipment currently planned for upgrade/improvement by the site (e.g. "ONE" List), including a description of the reason(s) why each  
corrective action program in the past two years for industry events, critical equipment  
component (i.e. not a programmatic or system level concern) is on that list and summaries (if available) of your  
failures, and safety related equipment vulnerabilities (as communicated by NRC generic  
plans to address those reasons. 9. A list of equipment currently in RIS 05-020 (formerly GL 91-18) status, or in MR (a)(1) status. 10. Contact information for a person to discuss PRA information prior to the information  
communications, industry communications, 10 CFR Part 21 notifications, etc.).  
6.  
A list of operability evaluations completed within the last two years, sorted by associated  
component or system.  
7.  
A list of common-cause failures of components that have occurred at Browns Ferry  
Nuclear Plant and have been identified within the last five years.  
8.  
A list of equipment currently planned for upgrade/improvement by the site (e.g. ONE  
List), including a description of the reason(s) why each component (i.e. not a  
programmatic or system level concern) is on that list and summaries (if available) of your  
plans to address those reasons.  
9.  
A list of equipment currently in RIS 05-020 (formerly GL 91-18) status, or in MR (a)(1)  
status.  
10.  
Contact information for a person to discuss PRA information prior to the information  
gathering trip: name, title, phone number, and e-mail address.
gathering trip: name, title, phone number, and e-mail address.
}}
}}

Latest revision as of 11:17, 14 January 2025

Notification of Browns Ferry Nuclear Plant - Component Design Bases Inspection - NRC Inspection Report 0500259-09-008, 05000260-09-008, and 05000296-09-008
ML091740032
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/22/2009
From: Binoy Desai
Engineering Region 1 Branch 1
To: Swafford P
Tennessee Valley Authority
References
IR-09-008
Download: ML091740032 (4)
v • d • e


See also: IR 05000259/2009008

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

SAM NUNN ATLANTA FEDERAL CENTER

61 FORSYTH STREET, SW, SUITE 23T85

ATLANTA, GEORGIA 30303-8931

June 22, 2009

Mr. Preston D. Swafford

Chief Nuclear Officer and Executive Vice President

Tennessee Valley Authority

3R Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

SUBJECT:

NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT

DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000259/2009008, 05000260/2009008, AND 05000296/2009008

Dear Mr. Swafford:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region II staff will conduct a component design bases inspection at your Browns Ferry Nuclear

Plant during the period of September 28 - November 20, 2009. The inspection team will be led

by Mr. Robert Berryman, a Senior Reactor Inspector from the NRC's Region II Office. This

inspection will be conducted in accordance with the baseline inspection procedure, Procedure

71111.21, Component Design Bases Inspection, issued August 19, 2008.

The inspection will evaluate the capability of risk significant / low margin components to function

as designed and to support proper system operation. The inspection will also include a review

of selected operator actions, operating experience, and modifications.

During a telephone conversation on June 18, 2009, Mr. Berryman confirmed, with Mr. Jim

Davenport of your staff, arrangements for an information gathering site visit and the three-week

onsite inspection. The schedule is as follows:

Information gathering visit: Week of September 28-October 2, 2009.

Onsite weeks: Weeks of October 19 - 23, November 2 - 6, and November 16 - 20, 2009.

The purpose of the information gathering visit is to meet with members of your staff to identify

risk-significant components and operator actions. Information and documentation needed to

support the inspection will also be identified and gathered or requested. Mr. Walt Rogers, a

Region II Senior Reactor Analyst, may accompany Mr. Berryman during the information

gathering visit to review probabilistic risk assessment data and identify risk significant

components which will be examined during the inspection.

TVA

2

The enclosure lists documents that will be needed prior to the information gathering visit. Please

contact Mr. Berryman with any questions prior to preparing materials listed in the enclosure and

provide the referenced information to the Region II office by September 15, 2009. The

inspectors will try to minimize your administrative burden by specifically identifying only those

documents required for the inspection preparation.

During the information gathering visit, the team leader will also discuss the following inspection

support administrative details: office space; site, plant and information system access; required

resources; and information exchange protocol.

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).

Thank you for your cooperation in this matter. If you have any questions regarding the

information requested or the inspection, please contact Mr. Berryman at (404) 562-4817 or me

at (404) 562-4519.

Sincerely,

/RA/

Binoy B. Desai, Chief

Engineering Branch 1

Division of Reactor Safety

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

License Nos.: DPR-33, DPR-52, DPR-68

Enclosure: Information Request for Browns Ferry Nuclear Plant Component Design Bases

Inspection

cc w/encl: (See page 3)

_________________________

SUNSI REVIEW COMPLETE

OFFICE

RII:DRS

RII:DRS

SIGNATURE

/RA/

/RA/

NAME

R. Berryman

B. Desai

DATE

06/22/2009

06/22/2009

E-MAIL COPY?

YES NO YES NO

YES NO

YES NO

YES NO

YES NO

YES NO

TVA

3

cc w/encls:

Ashok S. Bhatnagar, Senior VP

Nuclear Generation Development and

Construction

Tennessee Valley Authority

Electronic Mail Distribution

Preston D. Swafford

Chief Nuclear Officer and Executive VP

Tennessee Valley Authority

Electronic Mail Distribution

William R. Campbell, Senior VP

Fleet Engineering

Tennessee Valley Authority

6A Lookout Place

1101 Market Place

Chattanooga, TN 37402-2801

Thomas Coutu, Vice President

Nuclear Support

Tennessee Valley Authority

Electronic Mail Distribution

R. G. (Rusty) West, Site Vice President

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Frederick Russell Godwin

Manager, Licensing and Industry Affairs

Browns Ferry Nuclear Plant

Tennessee Valley Authority

P.O. Box 2000

Decatur, AL 35609

James J. Randich, Plant Manager

Browns Ferry Nuclear Plant

Tennessee Valley Authority

P.O. Box 2000

Ludwig E. Thibault, General Manager

Nuclear Oversight & Assistance

Tennessee Valley Authority

3R Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

General Counsel

Tennessee Valley Authority

Electronic Mail Distribution

Larry E. Nicholson, General Manager

Performance Improvement

Tennessee Valley Authority

Electronic Mail Distribution

Michael A. Purcell

Senior Licensing Manager

Nuclear Power Group

Tennessee Valley Authority

Electronic Mail Distribution

Michael J. Lorek, Vice President

Nuclear Engineering & Projects

Tennessee Valley Authority

Electronic Mail Distribution

Fredrick C. Mashburn, Acting Manager

Corporate Nuclear Licensing and Industry

Affairs

Tennessee Valley Authority

Electronic Mail Distribution

Senior Resident Inspector

Browns Ferry Nuclear Plant

U.S. Nuclear Regulatory Commission

10833 Shaw Road

Athens, AL 35611-6970

Kirksey E. Whatley, Director

Office of Radiation Control

Alabama Dept. of Public Health

Electronic Mail Distribution

Chairman

Limestone County Commission

310 West Washington Street

Athens, AL 35611

Dr. D. E. Williamson

State Health Officer

Alabama Dept. of Public Health

Electronic Mail Distribution

TVA

4

Letter to Preston D. Swafford from Binoy B. Desai, dated June 22, 2009

SUBJECT:

NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT - COMPONENT

DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000259/2009008, 05000260/2009008, AND 05000296/2009008

Distribution w/encl:

Eva Brown, NRR

PUBLIC

RidsNrrPMBrownsFerry Resource

Institute of Nuclear Power Operations (INPO)

Enclosure

INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR PLANT

COMPONENT DESIGN BASES INSPECTION

Please provide the information electronically in .pdf files, Excel, or other searchable format on

CDROM. The CDROM should be indexed and possibly hyperlinked to facilitate ease of use.

Information in lists should contain enough information to be easily understood to someone who

has knowledge of pressurized water reactor technology.

1.

From your most recent probabilistic safety analysis (PSA) excluding external events and

fires, please provide:

a.

Two risk rankings of components from your site-specific probabilistic safety

analysis (PSA) - one sorted by Risk Achievement Worth (RAW), and the other

sorted by Birnbaum Importance.

b.

A list of the top 500 cutsets.

2.

From your most recent probabilistic safety analysis (PSA) including external events and

fires, please provide:

a.

Two risk rankings of components from your site-specific probabilistic safety

analysis (PSA) - one sorted by Risk Achievement Worth (RAW), and the other

sorted by Birnbaum Importance.

b.

A list of the top 500 cutsets.

3.

Risk ranking of operator actions from your site specific PSA sorted by RAW. Provide

copies of your human reliability worksheets for these items.

4.

Any pre-existing evaluation or list of components and calculations with low design

margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close

to design required output, heat exchangers close to rated design heat removal, MOV risk-

margin rankings, etc.).

5.

A list of station applicability evaluations/reviews performed and documented in the station

corrective action program in the past two years for industry events, critical equipment

failures, and safety related equipment vulnerabilities (as communicated by NRC generic

communications, industry communications, 10 CFR Part 21 notifications, etc.).

6.

A list of operability evaluations completed within the last two years, sorted by associated

component or system.

7.

A list of common-cause failures of components that have occurred at Browns Ferry

Nuclear Plant and have been identified within the last five years.

8.

A list of equipment currently planned for upgrade/improvement by the site (e.g. ONE

List), including a description of the reason(s) why each component (i.e. not a

programmatic or system level concern) is on that list and summaries (if available) of your

plans to address those reasons.

9.

A list of equipment currently in RIS 05-020 (formerly GL 91-18) status, or in MR (a)(1)

status.

10.

Contact information for a person to discuss PRA information prior to the information

gathering trip: name, title, phone number, and e-mail address.

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