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{{#Wiki_filter:March 6, 2006
{{#Wiki_filter:March 6, 2006
Virginia Electric and Power Company
Virginia Electric and Power Company
ATTN: Mr. David A. Christian
ATTN:
          Senior Vice President and
Mr. David A. Christian
            Chief Nuclear Officer
Senior Vice President and
  Chief Nuclear Officer
Innsbrook Technical Center
Innsbrook Technical Center
5000 Dominion Boulevard
5000 Dominion Boulevard
Glen Allen, VA 23060
Glen Allen, VA 23060
SUBJECT:       NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION
SUBJECT:
                (NRC INSPECTION REPORT 05000280/2006009 AND 05000281/2006009)
NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION  
(NRC INSPECTION REPORT 05000280/2006009 AND 05000281/2006009)
Dear Mr. Christian:
Dear Mr. Christian:
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 at the Surry Power
Region II staff will conduct a triennial fire protection baseline inspection at the Surry Power
Station, Units 1 and 2, in June 2006. The inspection team will be led by Mr. McKenzie Thomas,
Station, Units 1 and 2, in June 2006. The inspection team will be led by Mr. McKenzie Thomas,
NRC Senior Reactor Inspector, of the Region II Office. The team will be composed of
NRC Senior Reactor Inspector, of the Region II Office. The team will be composed of
personnel from the NRC Region II Office and a contractor. The inspection will be conducted in
personnel from the NRC Region II Office and a contractor. The inspection will be conducted in
accordance with the NRCs baseline fire protection inspection procedure 71111.05T.
accordance with the NRCs baseline fire protection inspection procedure 71111.05T.
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 the fire protection features of selected
necessary to achieve and maintain safe shutdown and the fire protection features of selected
Line 42: Line 44:
On March 2, 2006, during a telephone conversation between Mr. Barry Garber, Surry Licensing
On March 2, 2006, during a telephone conversation between Mr. Barry Garber, Surry Licensing
Supervisor, and Mr. Thomas, our respective staffs confirmed arrangements for a three-day
Supervisor, and Mr. Thomas, our respective staffs confirmed arrangements for a three-day
information gathering onsite visit and a two-week onsite inspection. The schedule for the
information gathering onsite visit and a two-week onsite inspection. The schedule for the
inspection is as follows:
inspection is as follows:
        *     Information gathering visit: May 16-18, 2006
*
        *     Week 1 of onsite inspection: June 12-16, 2006
Information gathering visit:
        *     Week 2 of onsite inspection: June 26-30, 2006
May 16-18, 2006
*
Week 1 of onsite inspection: June 12-16, 2006
*
Week 2 of onsite inspection: June 26-30, 2006
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 Surry Power Station fire
needed to support the inspection, and to become familiar with the Surry Power Station fire
protection program, fire protection features, post-fire safe shutdown capabilities and plant
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.
are listed in the Enclosure.  


VEPCO                                             2
VEPCO
Please contact Mr. Thomas prior to preparing copies of the materials listed in the Enclosure.
2
Please contact Mr. Thomas prior to preparing copies of the materials listed in the Enclosure.  
The inspection team will try to minimize your administrative burden by specifically identifying
The inspection team will try to minimize your administrative burden by specifically identifying
those documents required for inspection preparation.
those documents required for inspection preparation.
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
office space; arrangements for reactor site access (including radiation protection training,
office space; arrangements for reactor site access (including radiation protection training,  
security, safety and fitness for duty requirements); and the availability of knowledgeable plant
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
engineering and licensing organization personnel to serve as points of contact during the
Line 66: Line 73:
documentation regarding the implementation and maintenance of the Surry Power Station fire
documentation regarding the implementation and maintenance of the Surry Power Station fire
protection program, including post-fire safe shutdown capability, be readily accessible to the
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
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
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
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
Line 74: Line 81:
systems and features, and the Surry Power Station fire protection program and its
systems and features, and the Surry Power Station fire protection program and its
implementation.
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 team's information or logistical needs, please
concerning this inspection, or the inspection team's information or logistical needs, please
contact Mr. Thomas at (404) 562-4673, or me at (404) 562-4669.
contact Mr. Thomas at (404) 562-4673, or me at (404) 562-4669.
Line 80: Line 87:
enclosure will be available electronically for public inspection in the NRC Public Document
enclosure will be available electronically for public inspection in the NRC Public Document
Room or from the Publicly Available Records (PARS) component of NRCs document system
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-
(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.html (the Public Electronic Reading Room).
rm/adams.html (the Public Electronic Reading Room).
                                              Sincerely,
Sincerely,
                                              \\RA\\
\\\\RA\\\\
                                              D. Charles Payne, Chief
D. Charles Payne, Chief
                                              Engineering Branch 2
Engineering Branch 2
                                              Division of Reactor Safety
Division of Reactor Safety
Docket Nos.: 50-280, 50-281
Docket Nos.: 50-280, 50-281
License Nos.: DPR-32, DPR-37
License Nos.: DPR-32, DPR-37
Enclosure: Triennial Fire Protection Inspection Support Documentation
Enclosure: Triennial Fire Protection Inspection Support Documentation
cc w/encl: (See page 3)
cc w/encl: (See page 3)


VEPCO                                 3
VEPCO
3
cc w/encl:
cc w/encl:
Chris L. Funderburk, Director
Chris L. Funderburk, Director
Nuclear Licensing and
Nuclear Licensing and
Operations Support
  Operations Support
Virginia Electric & Power Company
Virginia Electric & Power Company
Electronic Mail Distribution
Electronic Mail Distribution
Line 107: Line 115:
Division of Energy Regulation
Division of Energy Regulation
P. O. Box 1197
P. O. Box 1197
Richmond, VA 23209
Richmond, VA 23209
Lillian M. Cuoco, Esq.
Lillian M. Cuoco, Esq.
Senior Counsel
Senior Counsel
Line 115: Line 123:
Supreme Court Building
Supreme Court Building
900 East Main Street
900 East Main Street
Richmond, VA 23219
Richmond, VA 23219




_________________________
_________________________
OFFICE             RII:DRS         RII:DRS       RII:DRP         RII:DRS
OFFICE
SIGNATURE         MXT2           PJF           KDL             DCP
RII:DRS
NAME               M. Thomas       P. Fillion     K. Landis       C. Payne
RII:DRS
DATE                   3/3/2006       3/3/2006       3/6/2006       3/6/2006     3/   /2006   3/ /2006     3/ /2006
RII:DRP
E-MAIL COPY?         YES       NO   YES       NO YES       NO   YES       NO   YES      NO YES   NO    YES    NO
RII:DRS
       
SIGNATURE
              Triennial Fire Protection Inspection Support Documentation
MXT2
    Note: This is a broad list of the documents the NRC inspection team may be interested
PJF
    in reviewing, and possibly obtaining, during the information gathering site visit. The
KDL
    current version of these documents is expected unless specified otherwise. Electronic
DCP
    media is preferred, if readily available. (The preferred file format is searchable .pdf
NAME
    files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of
M. Thomas
    use. Please provide 5 copies of each CDROM submitted.) Information in lists should
P. Fillion
    contain enough information to be easily understood by someone who has a knowledge
K. Landis
    of the technology. The lead inspector will discuss specific information needs with the
C. Payne
    licensee staff and may request additional documents.
DATE
1.  The Fire Protection Program document and the Fire Hazards Analysis.
3/3/2006
2.  The fire protection program implementing procedures (e.g., administrative controls,
3/3/2006
    surveillance testing, fire brigade).
3/6/2006
3.  The fire brigade training program document and the pre-fire plans for the selected fire
3/6/2006
    areas/zones (to be determined during information gathering visit).
3/     /2006
4.  The post-fire safe shutdown analysis, including system and separation analyses.
3/     /2006
5.  The alternative shutdown analysis.
3/     /2006
6.  Piping and instrumentation (flow) diagrams for the fire suppression systems.
E-MAIL COPY?
7.  Piping and instrumentation (flow) diagrams for the systems and components used to
    YES
    achieve and maintain hot standby, and cold shutdown, for fires involving shutdown from
NO     YES
    the control room.
NO     YES
8.  Piping and instrumentation (flow) diagrams for the systems and components used to
NO     YES
    achieve and maintain hot standby, and cold shutdown, for fires in areas requiring
NO     YES
    alternative or dedicated shutdown capability.
NO     YES
9.  Plant layout and equipment drawings which identify the physical plant locations of hot
NO     YES
    standby and cold shutdown equipment.
NO     
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 used to, and describing, shutdown from inside the control
    room with a postulated fire occurring in any plant area outside the control room.
                                                                                    Enclosure


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


                                                3
2
24. A list of plant fire protection licensing basis documents (i.e., a list of the SERs and
Enclosure
    change evaluations which form the licensing basis for the facilitys post-fire safe
13.
    shutdown configuration).
Plant operating procedures used to implement the alternative shutdown capability from
25. A list of fire protection or Appendix R calculations.
outside the control room with a fire in either the control or cable spreading room (or any
26. A list of fire impairments identified during the previous year.
other alternative shutdown area).
27. A list of abbreviations/designators for plant systems.
14.
                                                                                    End Enclosure
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 reports/problem investigation
reports/NCRs/EARs] associated with fire protection or Appendix R safe shutdown for the
past three years.
 
3
Enclosure
End Enclosure
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 11:08, 15 January 2025

Notification of Triennial Fire Protection Baseline Inspection, NRC Inspection Report 05000280-06-009 and 05000281-06-009
ML060660023
Person / Time
Site: Surry  
Issue date: 03/06/2006
From: Payne D
NRC/RGN-II/DRS/EB2
To: Christian D
Virginia Electric & Power Co (VEPCO)
References
IR-06-009
Download: ML060660023 (7)
v • d • e


See also: IR 05000280/2006009

Text

March 6, 2006

Virginia Electric and Power Company

ATTN:

Mr. David A. Christian

Senior Vice President and

Chief Nuclear Officer

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA 23060

SUBJECT:

NOTIFICATION OF TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

(NRC INSPECTION REPORT 05000280/2006009 AND 05000281/2006009)

Dear Mr. Christian:

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 Surry Power

Station, Units 1 and 2, in June 2006. The inspection team will be led by Mr. McKenzie Thomas,

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

personnel from the NRC Region II Office and a contractor. The inspection will be conducted in

accordance with the NRCs baseline fire protection inspection procedure 71111.05T.

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 the fire protection features of selected

fire areas.

On March 2, 2006, during a telephone conversation between Mr. Barry Garber, Surry Licensing

Supervisor, and Mr. Thomas, 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 visit:

May 16-18, 2006

Week 1 of onsite inspection: June 12-16, 2006

Week 2 of onsite inspection: June 26-30, 2006

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

needed to support the inspection, and to become familiar with the Surry Power Station 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.

VEPCO

2

Please contact Mr. Thomas 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 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 Surry Power 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 Surry Power 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 team's information or logistical needs, please

contact Mr. Thomas at (404) 562-4673, or me at (404) 562-4669.

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 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\\\\

D. Charles Payne, Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-280, 50-281

License Nos.: DPR-32, DPR-37

Enclosure: Triennial Fire Protection Inspection Support Documentation

cc w/encl: (See page 3)

VEPCO

3

cc w/encl:

Chris L. Funderburk, Director

Nuclear Licensing and

Operations Support

Virginia Electric & Power Company

Electronic Mail Distribution

Donald E. Jernigan

Site Vice President

Surry Power Station

Virginia Electric & Power Company

Electronic Mail Distribution

Virginia State Corporation Commission

Division of Energy Regulation

P. O. Box 1197

Richmond, VA 23209

Lillian M. Cuoco, Esq.

Senior Counsel

Dominion Resources Services, Inc.

Electronic Mail Distribution

Attorney General

Supreme Court Building

900 East Main Street

Richmond, VA 23219

_________________________

OFFICE

RII:DRS

RII:DRS

RII:DRP

RII:DRS

SIGNATURE

MXT2

PJF

KDL

DCP

NAME

M. Thomas

P. Fillion

K. Landis

C. Payne

DATE

3/3/2006

3/3/2006

3/6/2006

3/6/2006

3/ /2006

3/ /2006

3/ /2006

E-MAIL COPY?

YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO YES

NO

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 a 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 used to, and describing, shutdown from inside the control

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

2

Enclosure

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).

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 reports/problem investigation

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

past three years.

3

Enclosure

End Enclosure

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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