ML031910112: Difference between revisions

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Tennessee Valley Authority
Tennessee Valley Authority
ATTN: Mr. J. A. Scalice
ATTN: Mr. J. A. Scalice
        Chief Nuclear Officer and
Chief Nuclear Officer and
          Executive Vice President
  Executive Vice President
6A Lookout Place
6A Lookout Place
1101 Market Street
1101 Market Street
Chattanooga, TN 37402-2801
Chattanooga, TN 37402-2801
SUBJECT:         NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
SUBJECT:
                (NRC INSPECTION REPORT NO. 50-260/03-07, 50-296/03-07)
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
(NRC INSPECTION REPORT NO. 50-260/03-07, 50-296/03-07)
Dear Mr. Scalice:
Dear Mr. Scalice:
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 triennial fire protection baseline inspection of Units 2 and 3 at the
Region II staff will conduct a triennial fire protection baseline inspection of Units 2 and 3 at the
Browns Ferry Nuclear Plant in September 2003. The inspection team will be led by Mr. Charles
Browns Ferry Nuclear Plant in September 2003. The inspection team will be led by Mr. Charles
Payne, Team Leader, of the Region II Office. The team will be composed of personnel from
Payne, Team Leader, of the Region II Office. The team will be composed of personnel from
the NRC Region II Office and a contracted national laboratory. The inspection will be
the NRC Region II Office and a contracted national laboratory. The inspection will be
conducted in accordance with the NRCs baseline fire protection inspection procedure
conducted in accordance with the NRCs baseline fire protection inspection procedure
71111.05.
71111.05.
The inspection objective will be to evaluate your fire protection program implementation with
The inspection objective will be to evaluate your fire protection program implementation with
emphasis on post-fire safe shutdown capability and the fire protection features provided to
emphasis on post-fire safe shutdown capability and the fire protection features provided to
ensure at least one post-fire safe shutdown success path is maintained free of fire damage.
ensure at least one post-fire safe shutdown success path is maintained free of fire damage.  
The inspection team will focus their review on the separation of the systems and equipment
The inspection team will focus their review on the separation of the systems and equipment
necessary to achieve and maintain safe shutdown and fire protection features of selected fire
necessary to achieve and maintain safe shutdown and fire protection features of selected fire
Line 43: Line 44:
On July 3, 2003, during a telephone conversation with Mr. Tim Abney, Licensing and Industry
On July 3, 2003, during a telephone conversation with Mr. Tim Abney, Licensing and Industry
Affairs Manager, our respective staffs confirmed arrangements for a three-day information
Affairs Manager, 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 as
gathering onsite visit and a two-week onsite inspection. The schedule for the inspection is as
follows:
follows:
            Information gathering onsite visit - August 19-21, 2003

            Week 1 of onsite inspection - September 8-12, 2003
Information gathering onsite visit - August 19-21, 2003
            Week 2 of onsite inspection - September 22-26, 2003

Week 1 of onsite inspection - September 8-12, 2003

Week 2 of onsite inspection - September 22-26, 2003
The purposes of the information gathering visit are to obtain information and documentation
The purposes of the information gathering visit are to obtain information and documentation
needed to support the inspection, and to become familiar with the Browns Ferry Nuclear Plant
needed to support the inspection, and to become familiar with the Browns Ferry Nuclear Plant
fire protection program, fire protection features, post-fire safe shutdown capabilities and plant
fire protection program, fire protection features, post-fire safe shutdown capabilities and plant
layout. The types of documents the team will be interested in reviewing, and possibly obtaining,
layout. The types of documents the team will be interested in reviewing, and possibly obtaining,
are listed in the Enclosure. Please contact Mr. Payne prior to preparing copies of the materials
are listed in the Enclosure. Please contact Mr. Payne prior to preparing copies of the materials
listed in the Enclosure. The inspection team will try to minimize your administrative burden by
listed in the Enclosure. The inspection team will try to minimize your administrative burden by
specifically identifying those documents required for inspection preparation.
specifically identifying those documents required for inspection preparation.


TVA                                               2
TVA
2
During the information gathering visit, the team will also discuss the following inspection support
During the information gathering visit, the team will also discuss the following inspection support
administrative details - office space, specific documents to be made available to the team in its
administrative details - office space, specific documents to be made available to the team in its
Line 66: Line 71:
documentation regarding the implementation and maintenance of the Browns Ferry Nuclear
documentation regarding the implementation and maintenance of the Browns Ferry Nuclear
Plant fire protection program, including post-fire safe shutdown capability, be readily accessible
Plant 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
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
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
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
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
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
electrical aspects of the relevant post-fire safe shutdown analyses), reactor plant fire protection
systems and features, and the Browns Ferry fire protection program and its implementation.
systems and features, and the Browns Ferry fire protection program and its implementation.
Your cooperation and support during this inspection will be appreciated. If you have questions
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
concerning this inspection, or the inspection teams information or logistical needs, please
contact Mr. Payne at (404) 562-4669, or me at (404) 562-4605.
contact Mr. Payne at (404) 562-4669, or me at (404) 562-4605.
                                              Sincerely,
Sincerely,
                                              /RA/
/RA/
                                              Charles R. Ogle, Chief
Charles R. Ogle, Chief
                                              Engineering Branch 1
Engineering Branch 1
                                              Division of Reactor Safety
Division of Reactor Safety
Docket Nos.: 50-260, 50-296
Docket Nos.: 50-260, 50-296
License Nos.: DPR-52, DPR-68
License Nos.: DPR-52, DPR-68
Enclosure:     Triennial Fire Protection Inspection
Enclosure:   Triennial Fire Protection Inspection
                Support Documentation
    Support Documentation
cc w/encl:
cc w/encl:
Karl W. Singer
Karl W. Singer
Line 93: Line 98:
(cc w/encl contd - See page 3)
(cc w/encl contd - See page 3)


TVA                               3
TVA
3
(cc w/encl contd)
(cc w/encl contd)
James E. Maddox, Vice President
James E. Maddox, Vice President
Line 111: Line 117:
Tennessee Valley Authority
Tennessee Valley Authority
Electronic Mail Distribution
Electronic Mail Distribution
Michael D. Skaggs, Plant Manager
Michael D. Skaggs, Plant Manager
Browns Ferry Nuclear Plant
Browns Ferry Nuclear Plant
Tennessee Valley Authority
Tennessee Valley Authority
Line 129: Line 135:
Suite 1552
Suite 1552
P. O. Box 303017
P. O. Box 303017
Montgomery, AL 36130-3017
Montgomery, AL 36130-3017
(cc w/encl contd - See page 4)
(cc w/encl contd - See page 4)


        TVA                                                 4
TVA
        (cc w/encl contd)
4
        Chairman
(cc w/encl contd)
        Limestone County Commission
Chairman
        310 West Washington Street
Limestone County Commission
        Athens, AL 35611
310 West Washington Street
        Distribution w/encl:
Athens, AL 35611
        K. Jabbour, NRR
Distribution w/encl:
        RIDSNRRDIPMLIPB
K. Jabbour, NRR  
        PUBLIC
RIDSNRRDIPMLIPB
OFFICE             RII:DRS       RII:DRP       RII:DRS       RII:DRS
PUBLIC
SIGNATURE         PAYNE         CAHILL
OFFICE
NAME               PAYNE         CAHILL       OGLE
RII:DRS
DATE                   7/7/2003     7/8/2003     7/ /2003     7/   /2003   7/   /2003 7/ /2003 7/ /2003
RII:DRP
E-MAIL COPY?         YES      NO YES       NO YES      NO   YES     NO   YES     NO YES   NO YES   NO
RII:DRS
PUBLIC DOCUMENT     YES     NO
RII:DRS
        OFFICIAL RECORD COPY       DOCUMENT NAME: C:\ORPCheckout\FileNET\ML031910112.wpd
SIGNATURE
PAYNE
CAHILL
NAME
PAYNE
CAHILL
OGLE
DATE
7/7/2003
7/8/2003
7/   /2003
7/       /2003
7/     /2003
7/     /2003
7/     /2003
E-MAIL COPY?
    YES
NO     YES
NO     YES
NO     YES
NO     YES
NO     YES
NO      YES
NO     
PUBLIC DOCUMENT
    YES
NO  
OFFICIAL RECORD COPY           DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML031910112.wpd


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


                                                3
3
25. A list of fire protection or Appendix R calculations.
Enclosure
26. A list of fire impairments identified during the previous year.
25.
27. A list of abbreviations/designators for plant systems.
A list of fire protection or Appendix R calculations.
                                                                    Enclosure
26.
A list of fire impairments identified during the previous year.
27.
A list of abbreviations/designators for plant systems.
}}
}}

Latest revision as of 09:00, 16 January 2025

Notification of Triennial Fire Protection Baseline Inspection (NRC Inspection Report No. 50-260/03-007 and 50-296/03-007)
ML031910112
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/08/2003
From: Ogle C
NRC/RGN-II/DRS/EB
To: Scalice J
Tennessee Valley Authority
References
IR-03-007
Download: ML031910112 (7)
v • d • e


See also: IR 05000260/2003007

Text

July 8, 2003

Tennessee Valley Authority

ATTN: Mr. J. A. Scalice

Chief Nuclear Officer and

Executive Vice President

6A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

SUBJECT:

NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

(NRC INSPECTION REPORT NO. 50-260/03-07, 50-296/03-07)

Dear Mr. Scalice:

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 of Units 2 and 3 at the

Browns Ferry Nuclear Plant in September 2003. The inspection team will be led by Mr. Charles

Payne, Team Leader, of the Region II Office. The team will be composed of personnel from

the NRC Region II Office and a contracted national laboratory. The inspection will be

conducted in accordance with the NRCs baseline fire protection inspection procedure

71111.05.

The inspection objective will be to evaluate your fire protection program implementation with

emphasis on post-fire safe shutdown capability and the fire protection features provided to

ensure at least one post-fire safe shutdown success path is maintained free of fire damage.

The inspection team will focus their review on the separation of the systems and equipment

necessary to achieve and maintain safe shutdown and fire protection features of selected fire

areas.

On July 3, 2003, during a telephone conversation with Mr. Tim Abney, Licensing and Industry

Affairs Manager, 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 as

follows:



Information gathering onsite visit - August 19-21, 2003



Week 1 of onsite inspection - September 8-12, 2003



Week 2 of onsite inspection - September 22-26, 2003

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

needed to support the inspection, and to become familiar with the Browns Ferry Nuclear Plant

fire protection program, fire protection features, post-fire safe shutdown capabilities and plant

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

are listed in the Enclosure. Please contact Mr. Payne 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.

TVA

2

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

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 Browns Ferry Nuclear

Plant 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 Browns Ferry 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. Payne at (404) 562-4669, or me at (404) 562-4605.

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-260, 50-296

License Nos.: DPR-52, DPR-68

Enclosure: Triennial Fire Protection Inspection

Support Documentation

cc w/encl:

Karl W. Singer

Senior Vice President

Nuclear Operations

Tennessee Valley Authority

Electronic Mail Distribution

(cc w/encl contd - See page 3)

TVA

3

(cc w/encl contd)

James E. Maddox, Vice President

Engineering and Technical Services

Tennessee Valley Authority

Electronic Mail Distribution

Ashok S. Bhatnagar

Site Vice President

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

General Counsel

Tennessee Valley Authority

Electronic Mail Distribution

Robert J. Adney, General Manager

Nuclear Assurance

Tennessee Valley Authority

Electronic Mail Distribution

Michael D. Skaggs, Plant Manager

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

Mark J. Burzynski, Manager

Nuclear Licensing

Tennessee Valley Authority

Electronic Mail Distribution

Timothy E. Abney, Manager

Licensing and Industry Affairs

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

State Health Officer

Alabama Dept. of Public Health

RSA Tower - Administration

Suite 1552

P. O. Box 303017

Montgomery, AL 36130-3017

(cc w/encl contd - See page 4)

TVA

4

(cc w/encl contd)

Chairman

Limestone County Commission

310 West Washington Street

Athens, AL 35611

Distribution w/encl:

K. Jabbour, NRR

RIDSNRRDIPMLIPB

PUBLIC

OFFICE

RII:DRS

RII:DRP

RII:DRS

RII:DRS

SIGNATURE

PAYNE

CAHILL

NAME

PAYNE

CAHILL

OGLE

DATE

7/7/2003

7/8/2003

7/ /2003

7/ /2003

7/ /2003

7/ /2003

7/ /2003

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO

PUBLIC DOCUMENT

YES

NO

OFFICIAL RECORD COPY DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML031910112.wpd

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 (i.e., on CD-ROM or computer disc). If electronic media is

offered, we request that an index of files or a simple menu be provided. 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

zones/areas (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 outside the control room.

8.

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

achieve and maintain hot standby, and cold shutdown, in areas requiring alternative

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 zones/areas (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 used to, and describing, 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

Enclosure

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

zones/areas (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 zones/areas (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 zones/areas.

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 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).

3

Enclosure

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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