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{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                                  NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                                  REGION II
REGION II  
                                  SAM NUNN ATLANTA FEDERAL CENTER
SAM NUNN ATLANTA FEDERAL CENTER
                                  61 FORSYTH STREET, SW, SUITE 23T85
61 FORSYTH STREET, SW, SUITE 23T85  
                                      ATLANTA, GEORGIA 30303-8931
ATLANTA, GEORGIA 30303-8931  
                                              February 29, 2008
Mr. David A. Baxter
February 29, 2008  
Site Vice President
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC
Mr. David A. Baxter  
Oconee Nuclear Station
Site Vice President  
7800 Rochester Highway
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC  
Seneca, SC 29672
Oconee Nuclear Station  
SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
7800 Rochester Highway  
              (NRC INSPECTION REPORT 05000269/2008007, 05000270/2008007 AND
Seneca, SC 29672  
              05000287/2008007)
Dear Mr. Baxter:
SUBJECT:   NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
(NRC INSPECTION REPORT 05000269/2008007, 05000270/2008007 AND  
Region II staff will conduct a triennial fire protection baseline inspection at the Oconee Nuclear
05000287/2008007)  
Station, Units 1, 2 and 3 in July 2008. The inspection will be led by Mr. Reinaldo Rodriguez,
NRC Senior Reactor Inspector, of the Region II Office. The team will be composed of personnel
Dear Mr. Baxter:  
from the NRC Region II Office. The inspection will be conducted in accordance with Inspection
Procedure 71111.05TTP, the NRCs baseline fire protection inspection procedure for plants in
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
the process of implementing 10 CFR 50.48(c) and National Fire Protection Association
Region II staff will conduct a triennial fire protection baseline inspection at the Oconee Nuclear  
Standard (NFPA) 805. The inspection guidance is different from the regular triennial
Station, Units 1, 2 and 3 in July 2008. The inspection will be led by Mr. Reinaldo Rodriguez,  
inspections in that the inspectors will concentrate on the fire protection program infrastructure
NRC Senior Reactor Inspector, of the Region II Office. The team will be composed of personnel  
and the adequacy of compensatory measures implemented for identified departures from code
from the NRC Region II Office. The inspection will be conducted in accordance with Inspection  
requirements. Inspection of circuit analysis is not included in the inspection procedure;
Procedure 71111.05TTP, the NRCs baseline fire protection inspection procedure for plants in  
however, electrical topics will be addressed by the team.
the process of implementing 10 CFR 50.48(c) and National Fire Protection Association  
On February 21, 2008, during a telephone conversation, between Mr. Jim Weast, of your staff,
Standard (NFPA) 805. The inspection guidance is different from the regular triennial  
and Mr. Rodriguez, of the NRC Region II Office, our respective staffs confirmed arrangements
inspections in that the inspectors will concentrate on the fire protection program infrastructure  
for a three-day information gathering onsite visit and a two-week onsite inspection. The
and the adequacy of compensatory measures implemented for identified departures from code  
schedule for the inspection is:
requirements. Inspection of circuit analysis is not included in the inspection procedure;  
            *   Information gathering visit: July 1 - 3, 2008
however, electrical topics will be addressed by the team.  
            *   Week 1 of onsite inspection: July 21 - 25, 2008
            *   Week 2 of onsite inspection: August 4 - 8, 2008
On February 21, 2008, during a telephone conversation, between Mr. Jim Weast, of your staff,  
The purposes of the information gathering visit are to obtain information and documentation
and Mr. Rodriguez, of the NRC Region II Office, our respective staffs confirmed arrangements  
needed to support the inspection, and to become familiar with the Oconee Nuclear Station fire
for a three-day information gathering onsite visit and a two-week onsite inspection. The  
protection program, fire protection features, post-fire shutdown capabilities and plant layout.
schedule for the inspection is:  
The types of documents the team will be interested in reviewing, and possibly obtaining, are
listed in the Enclosure.
*  
Information gathering visit:  
July 1 - 3, 2008  
*  
Week 1 of onsite inspection: July 21 - 25, 2008  
*  
Week 2 of onsite inspection: August 4 - 8, 2008  
The purposes of the information gathering visit are to obtain information and documentation  
needed to support the inspection, and to become familiar with the Oconee Nuclear Station fire  
protection program, fire protection features, post-fire shutdown capabilities and plant layout.
The types of documents the team will be interested in reviewing, and possibly obtaining, are  
listed in the Enclosure.  


Duke                                               2
Duke  
Please contact Mr. Rodriguez prior to preparing copies of the materials listed in the Enclosure.
2
The inspection team will try to minimize your administrative burden by specifically identifying
Please contact Mr. Rodriguez prior to preparing copies of the materials listed in the Enclosure.
those documents required for inspection preparation.
The inspection team will try to minimize your administrative burden by specifically identifying  
During the information gathering visit, the team will also discuss the following administrative
those documents required for inspection preparation.  
details - office space; specific documents to be made available to the team in its office space;
arrangements for reactor site access (including radiation protection training, security, safety and
During the information gathering visit, the team will also discuss the following administrative  
fitness for duty requirements); and the availability of knowledgeable plant engineering and
details - office space; specific documents to be made available to the team in its office space;  
licensing organization personnel to serve as points of contact during the inspection.
arrangements for reactor site access (including radiation protection training, security, safety and  
We request that during the inspection weeks you ensure that copies of analyses, evaluations or
fitness for duty requirements); and the availability of knowledgeable plant engineering and  
documentation regarding the implementation and maintenance of the Oconee Nuclear Station
licensing organization personnel to serve as points of contact during the inspection.  
fire protection program, including post-fire safe shutdown capability, be readily accessible to the
team for its review. Of specific interest are those documents which establish that your fire
We request that during the inspection weeks you ensure that copies of analyses, evaluations or  
protection program satisfies NRC regulatory requirements and conforms to applicable NRC and
documentation regarding the implementation and maintenance of the Oconee Nuclear Station  
industry fire protection guidance. Also, personnel should be available at the site during the
fire protection program, including post-fire safe shutdown capability, be readily accessible to the  
inspection who are knowledgeable regarding those plant systems required to achieve and
team for its review. Of specific interest are those documents which establish that your fire  
maintain safe shutdown conditions from inside and outside the control room (including the
protection program satisfies NRC regulatory requirements and conforms to applicable NRC and  
electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant fire protection
industry fire protection guidance. Also, personnel should be available at the site during the  
systems and features, and the Oconee Nuclear Station fire protection program and its
inspection who are knowledgeable regarding those plant systems required to achieve and  
implementation.
maintain safe shutdown conditions from inside and outside the control room (including the  
Your cooperation and support during this inspection will be appreciated. If you have questions
electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant fire protection  
concerning this inspection, or the inspection teams information or logistical needs, please
systems and features, and the Oconee Nuclear Station fire protection program and its  
contact Mr. Rodriguez at (404) 562-4498, or me at (404) 562-4639.
implementation.  
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its
enclosure will be available electronically for public inspection in the NRC Public Document
Your cooperation and support during this inspection will be appreciated. If you have questions  
Room or from the Publicly Available Records (PARS) component of NRCs document system
concerning this inspection, or the inspection teams information or logistical needs, please  
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
contact Mr. Rodriguez at (404) 562-4498, or me at (404) 562-4639.  
rm/adams.html (the Public Electronic Reading Room).
                                              Sincerely,
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its  
                                              /RA/
enclosure will be available electronically for public inspection in the NRC Public Document  
                                              Shakur Walker, Acting Chief
Room or from the Publicly Available Records (PARS) component of NRCs document system  
                                              Engineering Branch 2
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
                                              Division of Reactor Safety
rm/adams.html (the Public Electronic Reading Room).  
Docket Nos.: 50-269, 50-270, 50-287
License Nos.: DPR-38, DPR-47, DRP-55
Enclosure: Triennial Fire Protection Inspection Support Documentation
cc w/encl: (See page 3)
Sincerely,  
/RA/  
Shakur Walker, Acting Chief  
Engineering Branch 2  
Division of Reactor Safety  
Docket Nos.: 50-269, 50-270, 50-287  
License Nos.: DPR-38, DPR-47, DRP-55  
Enclosure: Triennial Fire Protection Inspection Support Documentation  
cc w/encl: (See page 3)  


Duke                                           3
Duke  
cc w/encl:
3
B. G. Davenport
cc w/encl:  
Compliance Manager (ONS)
B. G. Davenport  
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC
Compliance Manager (ONS)  
Electronic Mail Distribution
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC  
Lisa F. Vaughn
Electronic Mail Distribution  
Associate General Counsel
Duke Energy Corporation
Lisa F. Vaughn  
526 South Church Street-EC07H
Associate General Counsel  
Charlotte, NC 28202
Duke Energy Corporation  
Kathryn B. Nolan
526 South Church Street-EC07H  
Senior Counsel
Charlotte, NC   28202  
Duke Energy Corporation
526 South Church Street-EC07H
Kathryn B. Nolan  
Charlotte, NC 28202
Senior Counsel  
David A. Repka
Duke Energy Corporation  
Winston Strawn LLP
526 South Church Street-EC07H  
Electronic Mail Distribution
Charlotte, NC   28202  
Beverly Hall
Chief
David A. Repka  
Radiation Protection Section
Winston Strawn LLP  
N.C. Department of Environmental Commerce & Natural Resources
Electronic Mail Distribution  
Electronic Mail Distribution
Henry J. Porter
Beverly Hall  
Assistant Director
Chief  
Division of Radioactive Waste Mgmt.
Radiation Protection Section  
S.C. Department of Health and Environmental Control
N.C. Department of Environmental Commerce & Natural Resources  
Electronic Mail Distribution
Electronic Mail Distribution  
Lyle Graber
LIS
Henry J. Porter  
NUS Corporation
Assistant Director  
Electronic Mail Distribution
Division of Radioactive Waste Mgmt.  
R. L. Gill, Jr.
S.C. Department of Health and Environmental Control  
Manager
Electronic Mail Distribution  
Nuclear Regulatory Issues and Industry Affairs
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC
Lyle Graber  
526 South Church Street
LIS  
Charlotte, NC 28201-0006
NUS Corporation  
(cc w/encl contd - See page 4)
Electronic Mail Distribution  
R. L. Gill, Jr.  
Manager  
Nuclear Regulatory Issues and Industry Affairs  
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC  
526 South Church Street  
Charlotte, NC   28201-0006  
(cc w/encl contd - See page 4)  


Duke                                     4
Duke  
(cc w/encl contd)
4
Charles Brinkman
(cc w/encl contd)  
Director
Charles Brinkman  
Washington Operations
Director  
Westinghouse Electric Company
Washington Operations  
12300 Twinbrook Parkway, Suite 330
Westinghouse Electric Company  
Rockville, MD 20852
12300 Twinbrook Parkway, Suite 330  
Dhiaa M. Jamil
Rockville, MD   20852  
Group Executive and Chief Nuclear Officer
Duke Energy Carolinas, LLC
Dhiaa M. Jamil  
P.O. Box 1006 - EC03XM
Group Executive and Chief Nuclear Officer  
526 South Church St.
Duke Energy Carolinas, LLC  
Charlotte, NC 28201-1006
P.O. Box 1006 - EC03XM  
Distribution w/encl:
526 South Church St.  
RIDSNRRDIRS
Charlotte, NC   28201-1006  
PUBLIC
Distribution w/encl:  
RIDSNRRDIRS  
PUBLIC  
L. Olshan, NRR
L. Olshan, NRR




_________________________
_________________________  
OFFICE             RII:DRS       RII:DRS         RII:DRP
OFFICE  
  SIGNATURE                       RA               RA
RII:DRS  
  NAME               R. RODRIGUEZ S. WALKER         J. MOORMAN
RII:DRS  
  DATE                                 2/28/2008       2/29/2008
RII:DRP  
  E-MAIL COPY?         YES     NO YES         NO YES         NO YES   NO  YES     NO   YES     NO YES N
   
       
              Triennial Fire Protection Inspection Support Documentation
    Note: This is a broad list of the documents the NRC inspection team may be interested
    in reviewing, and possibly obtaining, during the information gathering site visit. The
SIGNATURE  
    current version of these documents is expected unless specified otherwise. Electronic
    media is preferred, if readily available. (The preferred file format is searchable .pdf
RA  
    files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of
RA  
    use. Please provide 5 copies of each CDROM submitted.) Information in lists should
   
    contain enough information to be easily understood by someone who has knowledge of
    the technology. The lead inspector will discuss specific information needs with the
    licensee staff and may request additional documents.
1.  The Fire Protection Program document and the Fire Hazards Analysis.
NAME  
2.  The Fire Protection Program implementing procedures (e.g., administrative controls,
R. RODRIGUEZ S. WALKER  
    surveillance testing, fire brigade).
J. MOORMAN  
3.  The fire brigade training program document and the pre-fire plans for the selected fire
   
    areas/zones (to be determined during information gathering visit).
4.  The post-fire safe shutdown analysis, including system and separation analyses.
5.  The alternative shutdown analysis.
6.  Piping and instrumentation (flow) diagrams for the fire suppression systems.
DATE  
7.  Piping and instrumentation (flow) diagrams for the systems and components used to
    achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
2/28/2008  
    the control room.
2/29/2008  
8.  Piping and instrumentation (flow) diagrams for the systems and components used to
   
    achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
    alternative or dedicated shutdown capability.
9.  Plant layout and equipment drawings which identify the physical plant locations of hot
    standby and cold shutdown equipment.
E-MAIL COPY?  
10. Plant layout drawings which identify plant fire area and/or fire zone delineation, areas
    YES  
    protected by automatic fire suppression and detection, and the locations of fire
NO   YES  
    protection equipment for the selected fire areas/zones (to be determined during
NO   YES  
    information gathering visit).
NO   YES  
11. Plant layout drawings which identify the general location of the post-fire emergency
NO  YES  
    lighting units.
NO   YES  
12. Plant operating procedures that describe and are used to shutdown from inside the
NO   YES  
    control room with a postulated fire occurring in any plant area outside the control room.
N
13. Plant operating procedures used to implement the alternative shutdown capability from
    outside the control room with a fire in either the control or cable spreading room (or any
    other alternative shutdown area).
                                                                                      Enclosure


                                                2
14. Maintenance and surveillance testing procedures for alternative shutdown capability
Enclosure
    (including Appendix R emergency lights and communication systems) and fire barriers,
    detectors, fire pumps and fire suppression systems.
15. Calculations and/or justifications that verify fuse/breaker coordination for the selected fire
Triennial Fire Protection Inspection Support Documentation
    areas/zones (to be determined during information gathering visit) that are fed off the
    same electrical buses as components in the protected train. Also, a list of the
Note: This is a broad list of the documents the NRC inspection team may be interested
    maintenance procedures used to routinely verify fuse/breaker coordination in
in reviewing, and possibly obtaining, during the information gathering site visit.  The
    accordance with the post-fire safe shutdown coordination analysis.
current version of these documents is expected unless specified otherwise.  Electronic
16. A list of the significant fire protection and post-fire safe shutdown design change
media is preferred, if readily available.  (The preferred file format is searchable .pdf
    descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter
files on CDROM.  The CDROM should be indexed and hyperlinked to facilitate ease of
    (GL) 86-10 evaluations.
use.  Please provide 5 copies of each CDROM submitted.)  Information in lists should
17. A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,
contain enough information to be easily understood by someone who has knowledge of
    Section III.G) used to achieve regulatory compliance for the selected fire areas/zones (to
the technology.  The lead inspector will discuss specific information needs with the
    be determined during information gathering visit). That is, please specify whether 3-hour
licensee staff and may request additional documents.
    rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and
    suppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression
1.
    (Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for the
The Fire Protection Program document and the Fire Hazards Analysis.
    selected fire areas/zones.
18. Procedures or instructions that govern the implementation of plant modifications,
2.
    temporary modifications, maintenance, and special operations, and their impact on fire
The Fire Protection Program implementing procedures (e.g., administrative controls,
    protection.
surveillance testing, fire brigade).
19. Organization chart(s) of site personnel down to the level of the fire protection staff.
20. Procedures or instructions that control the configuration of the fire protection program,
3.
    features, and post-fire safe shutdown methodology and system design.
The fire brigade training program document and the pre-fire plans for the selected fire
21. A list of applicable codes and standards related to the design of plant fire protection
areas/zones (to be determined during information gathering visit).
    features and evaluations of code deviations (i.e., a listing of the NFPA code editions
    committed to (Code of Record)).
4.
22. The three most recent fire protection QA audits and/or fire protection self-assessments.
The post-fire safe shutdown analysis, including system and separation analyses.
23. A list of open and closed fire protection problem identification and resolution reports
    [also known as action reports/condition reports/problem investigation
5.
    reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
The alternative shutdown analysis.
    past three years.
24. A list of plant fire protection licensing basis documents (i.e., a list of the SERs and
6.
    change evaluations which form the licensing basis for the facilitys post-fire safe
Piping and instrumentation (flow) diagrams for the fire suppression systems.
    shutdown configuration).
25. A list of fire protection or Appendix R calculations.
7.
26. A list of fire impairments identified during the previous year.
Piping and instrumentation (flow) diagrams for the systems and components used to
27. A list of abbreviations/designators for plant systems.
achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
the control room.
8.
Piping and instrumentation (flow) diagrams for the systems and components used to
achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
alternative or dedicated shutdown capability.
9.
Plant layout and equipment drawings which identify the physical plant locations of hot
standby and cold shutdown equipment.
10.
Plant layout drawings which identify plant fire area and/or fire zone delineation, areas
protected by automatic fire suppression and detection, and the locations of fire
protection equipment for the selected fire areas/zones (to be determined during
information gathering visit).
11.
Plant layout drawings which identify the general location of the post-fire emergency
lighting units.
12.
Plant operating procedures that describe and are used to shutdown from inside the
control room with a postulated fire occurring in any plant area outside the control room.
13.
Plant operating procedures used to implement the alternative shutdown capability from
outside the control room with a fire in either the control or cable spreading room (or any
other alternative shutdown area).
 
2
14.  
Maintenance and surveillance testing procedures for alternative shutdown capability  
(including Appendix R emergency lights and communication systems) and fire barriers,  
detectors, fire pumps and fire suppression systems.  
15.  
Calculations and/or justifications that verify fuse/breaker coordination for the selected fire  
areas/zones (to be determined during information gathering visit) that are fed off the  
same electrical buses as components in the protected train. Also, a list of the  
maintenance procedures used to routinely verify fuse/breaker coordination in  
accordance with the post-fire safe shutdown coordination analysis.  
16.  
A list of the significant fire protection and post-fire safe shutdown design change  
descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter  
(GL) 86-10 evaluations.  
17.  
A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,  
Section III.G) used to achieve regulatory compliance for the selected fire areas/zones (to  
be determined during information gathering visit). That is, please specify whether 3-hour  
rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and  
suppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression  
(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for the  
selected fire areas/zones.  
18.  
Procedures or instructions that govern the implementation of plant modifications,  
temporary modifications, maintenance, and special operations, and their impact on fire  
protection.  
19.  
Organization chart(s) of site personnel down to the level of the fire protection staff.  
20.  
Procedures or instructions that control the configuration of the fire protection program,  
features, and post-fire safe shutdown methodology and system design.  
21.  
A list of applicable codes and standards related to the design of plant fire protection  
features and evaluations of code deviations (i.e., a listing of the NFPA code editions  
committed to (Code of Record)).  
22.  
The three most recent fire protection QA audits and/or fire protection self-assessments.  
23.  
A list of open and closed fire protection problem identification and resolution reports  
[also known as action reports/condition reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the  
past three years.  
24.  
A list of plant fire protection licensing basis documents (i.e., a list of the SERs and  
change evaluations which form the licensing basis for the facilitys post-fire safe  
shutdown configuration).  
25.  
A list of fire protection or Appendix R calculations.  
26.  
A list of fire impairments identified during the previous year.  
27.  
A list of abbreviations/designators for plant systems.
}}
}}

Latest revision as of 17:51, 14 January 2025

IR 05000269-08-007, IR 05000270-08-007, IR 05000287-08-007, Notification of Triennial Fire Protection Baseline Inspection
ML080650306
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 02/29/2008
From: Sandra Walker
NRC/RGN-II/DRS/EB2
To: Baxter D
Duke Energy Carolinas, Duke Power Co
References
IR-08-007
Download: ML080650306 (7)
v • d • e


See also: IR 05000269/2008007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

SAM NUNN ATLANTA FEDERAL CENTER

61 FORSYTH STREET, SW, SUITE 23T85

ATLANTA, GEORGIA 30303-8931

February 29, 2008

Mr. David A. Baxter

Site Vice President

Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC

Oconee Nuclear Station

7800 Rochester Highway

Seneca, SC 29672

SUBJECT: NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

(NRC INSPECTION REPORT 05000269/2008007, 05000270/2008007 AND

05000287/2008007)

Dear Mr. Baxter:

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

Region II staff will conduct a triennial fire protection baseline inspection at the Oconee Nuclear

Station, Units 1, 2 and 3 in July 2008. The inspection will be led by Mr. Reinaldo Rodriguez,

NRC Senior Reactor Inspector, of the Region II Office. The team will be composed of personnel

from the NRC Region II Office. The inspection will be conducted in accordance with Inspection

Procedure 71111.05TTP, the NRCs baseline fire protection inspection procedure for plants in

the process of implementing 10 CFR 50.48(c) and National Fire Protection Association

Standard (NFPA) 805. The inspection guidance is different from the regular triennial

inspections in that the inspectors will concentrate on the fire protection program infrastructure

and the adequacy of compensatory measures implemented for identified departures from code

requirements. Inspection of circuit analysis is not included in the inspection procedure;

however, electrical topics will be addressed by the team.

On February 21, 2008, during a telephone conversation, between Mr. Jim Weast, of your staff,

and Mr. Rodriguez, of the NRC Region II Office, our respective staffs confirmed arrangements

for a three-day information gathering onsite visit and a two-week onsite inspection. The

schedule for the inspection is:

Information gathering visit:

July 1 - 3, 2008

Week 1 of onsite inspection: July 21 - 25, 2008

Week 2 of onsite inspection: August 4 - 8, 2008

The purposes of the information gathering visit are to obtain information and documentation

needed to support the inspection, and to become familiar with the Oconee Nuclear Station fire

protection program, fire protection features, post-fire shutdown capabilities and plant layout.

The types of documents the team will be interested in reviewing, and possibly obtaining, are

listed in the Enclosure.

Duke

2

Please contact Mr. Rodriguez prior to preparing copies of the materials listed in the Enclosure.

The inspection team will try to minimize your administrative burden by specifically identifying

those documents required for inspection preparation.

During the information gathering visit, the team will also discuss the following administrative

details - office space; specific documents to be made available to the team in its office space;

arrangements for reactor site access (including radiation protection training, security, safety and

fitness for duty requirements); and the availability of knowledgeable plant engineering and

licensing organization personnel to serve as points of contact during the inspection.

We request that during the inspection weeks you ensure that copies of analyses, evaluations or

documentation regarding the implementation and maintenance of the Oconee Nuclear Station

fire protection program, including post-fire safe shutdown capability, be readily accessible to the

team for its review. Of specific interest are those documents which establish that your fire

protection program satisfies NRC regulatory requirements and conforms to applicable NRC and

industry fire protection guidance. Also, personnel should be available at the site during the

inspection who are knowledgeable regarding those plant systems required to achieve and

maintain safe shutdown conditions from inside and outside the control room (including the

electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant fire protection

systems and features, and the Oconee Nuclear Station fire protection program and its

implementation.

Your cooperation and support during this inspection will be appreciated. If you have questions

concerning this inspection, or the inspection teams information or logistical needs, please

contact Mr. Rodriguez at (404) 562-4498, or me at (404) 562-4639.

In accordance with 10 CFR 2.390 of the NRCs 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 NRCs 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).

Sincerely,

/RA/

Shakur Walker, Acting Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-269, 50-270, 50-287

License Nos.: DPR-38, DPR-47, DRP-55

Enclosure: Triennial Fire Protection Inspection Support Documentation

cc w/encl: (See page 3)

Duke

3

cc w/encl:

B. G. Davenport

Compliance Manager (ONS)

Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC

Electronic Mail Distribution

Lisa F. Vaughn

Associate General Counsel

Duke Energy Corporation

526 South Church Street-EC07H

Charlotte, NC 28202

Kathryn B. Nolan

Senior Counsel

Duke Energy Corporation

526 South Church Street-EC07H

Charlotte, NC 28202

David A. Repka

Winston Strawn LLP

Electronic Mail Distribution

Beverly Hall

Chief

Radiation Protection Section

N.C. Department of Environmental Commerce & Natural Resources

Electronic Mail Distribution

Henry J. Porter

Assistant Director

Division of Radioactive Waste Mgmt.

S.C. Department of Health and Environmental Control

Electronic Mail Distribution

Lyle Graber

LIS

NUS Corporation

Electronic Mail Distribution

R. L. Gill, Jr.

Manager

Nuclear Regulatory Issues and Industry Affairs

Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC

526 South Church Street

Charlotte, NC 28201-0006

(cc w/encl contd - See page 4)

Duke

4

(cc w/encl contd)

Charles Brinkman

Director

Washington Operations

Westinghouse Electric Company

12300 Twinbrook Parkway, Suite 330

Rockville, MD 20852

Dhiaa M. Jamil

Group Executive and Chief Nuclear Officer

Duke Energy Carolinas, LLC

P.O. Box 1006 - EC03XM

526 South Church St.

Charlotte, NC 28201-1006

Distribution w/encl:

RIDSNRRDIRS

PUBLIC

L. Olshan, NRR

_________________________

OFFICE

RII:DRS

RII:DRS

RII:DRP

SIGNATURE

RA

RA

NAME

R. RODRIGUEZ S. WALKER

J. MOORMAN

DATE

2/28/2008

2/29/2008

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO YES

N

Enclosure

Triennial Fire Protection Inspection Support Documentation

Note: This is a broad list of the documents the NRC inspection team may be interested

in reviewing, and possibly obtaining, during the information gathering site visit. The

current version of these documents is expected unless specified otherwise. Electronic

media is preferred, if readily available. (The preferred file format is searchable .pdf

files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of

use. Please provide 5 copies of each CDROM submitted.) Information in lists should

contain enough information to be easily understood by someone who has knowledge of

the technology. The lead inspector will discuss specific information needs with the

licensee staff and may request additional documents.

1.

The Fire Protection Program document and the Fire Hazards Analysis.

2.

The Fire Protection Program implementing procedures (e.g., administrative controls,

surveillance testing, fire brigade).

3.

The fire brigade training program document and the pre-fire plans for the selected fire

areas/zones (to be determined during information gathering visit).

4.

The post-fire safe shutdown analysis, including system and separation analyses.

5.

The alternative shutdown analysis.

6.

Piping and instrumentation (flow) diagrams for the fire suppression systems.

7.

Piping and instrumentation (flow) diagrams for the systems and components used to

achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from

the control room.

8.

Piping and instrumentation (flow) diagrams for the systems and components used to

achieve and maintain hot standby, and cold shutdown, for fires in areas requiring

alternative or dedicated shutdown capability.

9.

Plant layout and equipment drawings which identify the physical plant locations of hot

standby and cold shutdown equipment.

10.

Plant layout drawings which identify plant fire area and/or fire zone delineation, areas

protected by automatic fire suppression and detection, and the locations of fire

protection equipment for the selected fire areas/zones (to be determined during

information gathering visit).

11.

Plant layout drawings which identify the general location of the post-fire emergency

lighting units.

12.

Plant operating procedures that describe and are used to shutdown from inside the

control room with a postulated fire occurring in any plant area outside the control room.

13.

Plant operating procedures used to implement the alternative shutdown capability from

outside the control room with a fire in either the control or cable spreading room (or any

other alternative shutdown area).

2

14.

Maintenance and surveillance testing procedures for alternative shutdown capability

(including Appendix R emergency lights and communication systems) and fire barriers,

detectors, fire pumps and fire suppression systems.

15.

Calculations and/or justifications that verify fuse/breaker coordination for the selected fire

areas/zones (to be determined during information gathering visit) that are fed off the

same electrical buses as components in the protected train. Also, a list of the

maintenance procedures used to routinely verify fuse/breaker coordination in

accordance with the post-fire safe shutdown coordination analysis.

16.

A list of the significant fire protection and post-fire safe shutdown design change

descriptions (including their associated 10 CFR 50.59 evaluations) and Generic Letter

(GL) 86-10 evaluations.

17.

A list of the protection methodologies (as identified in 10 CFR Part 50, Appendix R,

Section III.G) used to achieve regulatory compliance for the selected fire areas/zones (to

be determined during information gathering visit). That is, please specify whether 3-hour

rated fire barriers (Section III.G.2.a), 20-foot separation along with detection and

suppression (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression

(Section III.G.2.c), or alternative shutdown capability (Section III.G.3) is used for the

selected fire areas/zones.

18.

Procedures or instructions that govern the implementation of plant modifications,

temporary modifications, maintenance, and special operations, and their impact on fire

protection.

19.

Organization chart(s) of site personnel down to the level of the fire protection staff.

20.

Procedures or instructions that control the configuration of the fire protection program,

features, and post-fire safe shutdown methodology and system design.

21.

A list of applicable codes and standards related to the design of plant fire protection

features and evaluations of code deviations (i.e., a listing of the NFPA code editions

committed to (Code of Record)).

22.

The three most recent fire protection QA audits and/or fire protection self-assessments.

23.

A list of open and closed fire protection problem identification and resolution reports

[also known as action reports/condition reports/problem investigation

reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the

past three years.

24.

A list of plant fire protection licensing basis documents (i.e., a list of the SERs and

change evaluations which form the licensing basis for the facilitys post-fire safe

shutdown configuration).

25.

A list of fire protection or Appendix R calculations.

26.

A list of fire impairments identified during the previous year.

27.

A list of abbreviations/designators for plant systems.

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