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{{#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  
  February 29, 2008
NUCLEAR REGULATORY COMMISSION  
Mr. David A. Baxter Site Vice President
REGION II  
Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672
SAM NUNN ATLANTA FEDERAL CENTER   
61 FORSYTH STREET, SW, SUITE 23T85  
ATLANTA, GEORGIA  30303-8931  
   
   
SUBJECT:  NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION REPORT 05000269/2008007, 05000270/2008007 AND 05000287/2008007)  
February 29, 2008
  Dear Mr. Baxter:  
 
Mr. David A. 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 NRC's baseline fire protection inspection procedure for plants in  
Site Vice President
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;  
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.  
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  
   
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:  
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  
Information gathering visit:  
  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. 
July 1 - 3, 2008  
Duke 2Please 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;
Week 1 of onsite inspection: July 21 - 25, 2008  
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
Week 2 of onsite inspection: August 4 - 8, 2008  
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.
The purposes of the information gathering visit are to obtain information and documentation  
Your cooperation and support during this inspection will be appreciated.  If you have questions
needed to support the inspection, and to become familiar with the Oconee Nuclear Station fire  
concerning this inspection, or the inspection team's information or logistical needs, please contact Mr. Rodriguez at (404) 562-4498, or me at (404) 562-4639.
protection program, fire protection features, post-fire shutdown capabilities and plant layout.   
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).
The types of documents the team will be interested in reviewing, and possibly obtaining, are  
      Sincerely,
listed in the Enclosure.  
      /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
 
2
 
Please contact Mr. Rodriguez prior to preparing copies of the materials listed in the Enclosure. 
Duke 3cc w/encl: B. G. Davenport Compliance Manager (ONS) Duke Power Company, LLC d/b/a Duke Energy Carolinas, LLC Electronic Mail Distribution
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)
   
   
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  
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
   
   
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
(cc w/encl contd - See page 4)


  Lyle Graber LIS NUS Corporation Electronic Mail Distribution  
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


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 cont'd - See page 4)
_________________________
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


 
   
Duke 4(cc w/encl cont'd) Charles Brinkman Director Washington Operations Westinghouse Electric Company 12300 Twinbrook Parkway, Suite 330
Enclosure
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
Triennial Fire Protection Inspection Support Documentation  
  Distribution w/encl:
  RIDSNRRDIRS PUBLIC
Note: This is a broad list of the documents the NRC inspection team may be interested  
L. Olshan, NRR
in reviewing, and possibly obtaining, during the information gathering site visit.  The  
 
current version of these documents is expected unless specified otherwise.  Electronic  
_________________________ 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
media is preferred, if readily available.  (The preferred file format is searchable .pdf  
N
files on CDROM.  The CDROM should be indexed and hyperlinked to facilitate ease of  
Enclosure
use.  Please provide 5 copies of each CDROM submitted.)  Information in lists should  
  Triennial Fire Protection Inspection Support Documentation
contain enough information to be easily understood by someone who has knowledge of  
  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  
the technology.  The lead inspector will discuss specific information needs with the  
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.  
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).  
1.
  4. The post-fire safe shutdown analysis, including system and separation analyses.  
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.  
   
   
5. The alternative shutdown analysis.  
7.  
6. Piping and instrumentation (flow) diagrams for the fire suppression systems.
Piping and instrumentation (flow) diagrams for the systems and components used to  
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.  
achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from  
  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  
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.  
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).  
9.
  11. Plant layout drawings which identify the general location of the post-fire emergency lighting units.  
Plant layout and equipment drawings which identify the physical plant locations of hot
  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.
standby and cold shutdown equipment.
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).
 
10.  
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.  
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.  
   
   
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.
13.  
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.
Plant operating procedures used to implement the alternative shutdown capability from
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
outside the control room with a fire in either the control or cable spreading room (or any
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.
other alternative shutdown area).  
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 facility's 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.  
2
  27. A list of abbreviations/designators for plant systems.
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).

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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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