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See also: [[followed by::IR 05000269/2022010]]
See also: [[see also::IR 05000269/2022010]]


=Text=
=Text=
{{#Wiki_filter:UNITED STATES
{{#Wiki_filter:UNITED STATES  
                                            NUCLEAR REGULATORY COMMISSION
NUCLEAR REGULATORY COMMISSION  
                                                                    REGION II
REGION II  
                                    245 PEACHTREE CENTER AVENUE NE, SUITE 1200
245 PEACHTREE CENTER AVENUE NE, SUITE 1200  
                                                  ATLANTA, GEORGIA  30303-1257
ATLANTA, GEORGIA  30303-1257  
January 18, 2022
Steven M. Snider
Site Vice President, Oconee Nuclear Station
Duke Energy Carolinas, LLC
7800 Rochester Highway
Seneca, SC  29672-0752
SUBJECT: 
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - NOTIFICATION OF AN
NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION
REPORT 05000269/2022010, 05000270/2022010, 05000287/2022010) AND
REQUEST FOR INFORMATION (RFI)
Dear Mr. Snider:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
Region II staff will conduct a fire protection team inspection at the Oconee Nuclear Station,
Units 1, 2 and 3, in March and April of 2022.  The inspection team will be led by Mr. Jonathan
Montgomery, a Senior Reactor Inspector from the NRC Region II Office.  The inspection team
will be comprised of four inspectors from the NRC Region II office.  The inspection will be
conducted in accordance with Inspection Procedure 71111, Attachment 21N.05, Fire Protection
Team Inspection, the NRCs baseline fire protection inspection procedure.
On January 12, 2022, during a phone call between Samuel Adams of your staff and 
Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite
inspection.  The schedule for the inspection is as follows:
*
Week 1 of onsite inspection: March 21-25, 2022
*
Week 2 of onsite inspection:  April 4-8, 2022
The team lead and senior reactor analyst will work with your staff prior to the start of the
inspection to select the scope of structures, systems, and components for evaluation; identify
additional documents needed to support the inspection; and obtain unescorted access. 
The enclosure to this letter provides an initial list of the documents the team will need for their
review.  We request that your staff transmit copies of the documents listed in the enclosure to
the NRC Region II office for team use in preparation for the inspection.  Please send this
information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.


S. Snider
2
During the weeks leading up to the inspection, the team leader will discuss with your staff the
following inspection support administrative details:  (1) office space size and location; (2)
specific documents requested to be made available to the team in their office spaces; (3)
arrangements for reactor site access (including radiation protection training, security, safety,
and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and
licensing organization personnel to serve as points of contact during the inspection.
We request that during the on-site inspection weeks you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the station fire
protection program, including the success path necessary to achieve and maintain the nuclear
safety performance criteria, be readily accessible to the team for their review.  Of specific
interest for the fire protection portion of the inspection are those documents which establish that
your fire protection program satisfies NRC regulatory requirements and conforms to applicable
NRC and industry fire protection guidance (i.e., fire protection compliance assessment
documents).  Also, personnel should be available at the site during the inspection who are
knowledgeable regarding those plant systems required to achieve and maintain safe and stable
plant conditions, including the electrical aspects of the nuclear safety capability assessment,
reactor plant fire protection systems and features, and the station fire protection program and its
implementation.
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).  Existing information collection
requirements were approved by the Office of Management and Budget under control
number 3150-0011.  The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget control
number.
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
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 Jonathan Montgomery, the team lead inspector, in the Region II office at 
(404) 997-4880 or jonathan.montgomery@nrc.gov, or call me at (404) 997-4506.
Sincerely, 
James Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-269, 50-270, 50-287
License No. DPR-38, DPR-47, DPR-55
Enclosures:
Fire Protection Team Inspection 
Document Request
cc w/enclosure:  via ListServ 
James B.
Baptist
Digitally signed by James B.
Baptist
Date: 2022.01.18 15:03:01
-05'00'


                                                                January 18, 2022
Fire Protection Team Inspection Document Request
Enclosure
The initial request for information (i.e., first RFI) concentrates on providing the inspection team
with the general information necessary to select appropriate samples to develop a site-specific
inspection plan.  The first RFIs requested information is specified below in items A.1 thru A.22,
and is requested to be provided by February 17, 2022, or sooner, to facilitate the selection of
the specific items that will be reviewed during the onsite inspection weeks.
Electronic format is the preferred format, except where specifically noted.  If electronic files are
made available via a secure document management service, then the remote document access
must allow inspectors to download, save, and print the documents in the NRCs regional office.
If a secure document management service is utilized, it is recommended that a separate folder
be used corresponding to each item listed below. Documents should be identified by both
document number and noun name.  Electronic media on compact disc or paper records (hard
copy) are also acceptable.
The inspection team will examine the returned documentation from the first RFI and
identify/select specific samples to provide a more focused follow-up request to develop the
second RFI.  The inspection team will submit the specific selected samples to your staff by
February 25, 2022.  We request that the additional information provided from the second RFI be
made available by March 11, 2022.
This document request is based on typical documents that a generic plant might have.  As such,
this generic document request is not meant to imply that any specific plant is required to have all
the listed documents.  It is recognized that some documents listed below may not be available
for your plant.  In addition, the document titles listed below are based on typical industry
document names; your plant-specific document titles may vary.


2
A.
DESIGN AND LICENSING BASIS DOCUMENTS
A.1
The current version of the Fire Protection Program and Fire Hazards Analysis 
A.2
Post-fire Nuclear Safety Capability, Systems, and Separation Analysis, and the
supporting calculations that demonstrate acceptable plant response.
A.3
Fire PRA Summary Report, and list of Fire PRA calculations
A.4
NFPA 805 Transition Report, developed in accordance with NEI 04-02
A.5
LIST of post-fire safe shutdown systems and components (i.e., safe shutdown
equipment list).
A.6
LIST of fire areas with automatic fire suppression systems
A.7
LIST, with descriptions, of design change packages performed since the last fire
protection team inspection associated with fire protection or post-fire safe
shutdown systems.
A.8
LIST, with descriptions, of any fire protection program changes and evaluations
(not limited to Generic Letter 86-10 evaluations) performed since the last fire
protection team inspection 
A.9
Fire Protection System(s) Design Basis Document.
A.10
LIST of applicable NFPA codes and standards and issuance dates (i.e., codes of
record).
A.11
A list or document identifying any deviations from the NFPA codes of record.
A.12
Facility Operating License.
A.13
Technical Specifications (electronic format only).
A.14
Updated Final Safety Analysis Report (electronic format only).
A.15
COPY of NRC Safety Evaluation Reports that form the licensing basis for:
* Fire Protection Program; and
* Post-fire Nuclear Safety Capability.
A.16 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear
safety capability features.
A.17 COPY of exemption requests submitted but not yet approved for plant fire
protection and post-fire nuclear safety capability features.
A.18 LIST of nuclear safety capability design changes completed in the last three years
(including their associated 10 CFR 50.59 and NFPA 805 plant change
evaluations).


Steven M. Snider
   
Site Vice President, Oconee Nuclear Station
3  
Duke Energy Carolinas, LLC
   
7800 Rochester Highway
   
Seneca, SC 29672-                                                                                                                        0752
A.19
 
LIST of the top 25 highest fire CDF scenarios for each unit  
SUBJECT:                                    OCONEE NUCLEAR STATION, UNITS 1                        , 2 AND 3 -          NOTIFICATION OF AN
                        NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION
A.20  
                        REPORT 05000269/202                                                                                                                                                                              2010,                                            05000270                                                                                                            /2022                                                                010, 05000287                                                                                                            /2022                                                                010                                          ) AND
LIST of the top 25 highest fire LERF scenarios for each unit  
                        REQUEST FOR INFORMATION (RFI)
 
A.21  
Dear Mr. Snider          :
From your most recent PRA including external events and fires:  
 
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
a. Two risk rankings of components from your site-specific PRA:  one sorted by  
Region II staff will conduct a fire protection team          inspection at the                                            Oconee Nuclear Station,
Risk Achievement Worth (RAW), and the other sorted by Birnbaum  
Units 1, 2 and 3, in                                March and April of 2022.  The inspection team will be led by Mr. Jonathan
Importance  
Montgomery, a Senior Reactor Inspector from the NRC Region II Office.  The inspection team
will be comprised of four          inspectors from the NRC Region                                            II office.  The inspection will be
b. A list of the top 500 cut-sets  
conducted in accordance with Inspection Procedure                      71111, Attachment 21N.05, Fire Protection
Team Inspection, the NRCs baseline fire protection inspection procedure.
A.22  
 
COPY of the Quality Assurance Program Manual (including specific fire  
On January 12, 2022, during a                                                                                                                                                        phone call between Samuel Adams of your staff and
protection QA manual, if applicable)
Mr. Montgomery, our respective staffs confirmed arrangements for a two-                  week onsite
inspection.  The schedule for the inspection is as follows:
 
      *                                  Week 1 of onsite inspection:                                            March 21-                                                      25, 2022
      *                                  Week 2 of onsite inspection:                                              April 4-          8, 2022
 
The team lead                                                                            and senior reactor analyst will                                                                work with your staff prior to the start of the
inspection to select the scope of structures, systems, and components for evaluation;                                                                identify
additional documents needed to support the inspection;                                          and obtain unescorted access.
 
The enclosure to this letter provides an initial list of the documents the team will need for their
review.  We request that your staff transmit copies of the documents listed in the enclosure to
the NRC Region II office for team use in preparation for the inspection. Please send this
information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.
 
S. Snider                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                                2
 
During the weeks leading up to the inspection, the team                                                    leader will                                                      discuss                                        with your staff the
following inspection support administrative details: (1) office space size and location; (2)
specific documents requested to be made available to the team in their office spaces; (3)
arrangements for reactor site access (including radiation protection training, security, safety,
and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and
licensing organization personnel to serve                    as points of contact during the inspection.
 
We request that during the on-                                                                                                site inspection weeks you ensure that copies of analyses,
evaluations, or documentation regarding the implementation and maintenance of the station fire
protection program, including the success path necessary to achieve and maintain the nuclear
safety performance criteria, be readily accessible to the team for their review.  Of specific
interest for the fire protection portion of the inspection are those documents which establish that
your fire protection program satisfies NRC regulatory requirements and conforms to applicable
NRC and industry fire protection guidance (i.e., fire protection compliance assessment
documents).  Also, personnel should be available at the site during the inspection                                            who are
knowledgeable regarding those plant systems required to achieve and maintain safe and stable
plant conditions, including the electrical aspects of the                                          nuclear safety capability assessment,
reactor plant fire protection systems and features, and the station fire protection program and its
implementation.
 
This letter does not contain new or amended information collection requirements subject to the
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).  Existing information collection
requirements were approved by the Office of Management and Budget under        control
number 3150-                                                                                      0011.  The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection requirement unless the
requesting document displays a currently valid Office of Management and Budget control
number.
 
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-                                          rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
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 Jonathan Montgomery, the team lead inspector, in the Region II office at
(404)                                                                  997-                                                                  4880 or jonathan.montgomery@nrc.gov, or call                me at (404) 997-4506.
 
                                                                        Sincerely,
 
 
 
                                                                        James Baptist, Chief
                                                                        Engineering Branch 1
                                                                        Division of Reactor Safety
 
Docket No. 50-269, 50-                                          270, 50-287
License No. DPR-                                      38, DPR-47, DPR-                            55
 
Enclosures:
Fire Protection                                            Team Inspection
  Document Request
 
cc w/enclosure:  via ListServ
                      Fire Protection Team Inspection Document Request
 
The initial request for information (i.e., first RFI) concentrates on providing the inspection team
with the general information necessary to select appropriate samples          to develop a site-specific
inspection plan.  The first RFIs requested information is s                                      pecified below in items A.1 thru A.22,
and is requested to be provided by February 17, 2022, or sooner, to facilitate the selection of
the specific items that will be reviewed during the onsite inspection weeks.
 
Electronic format is the preferred format                                          , except where specifically noted.  If electronic files are
made available via a secure document management service, then the remote document access
must allow inspectors to download, save, and print the documents in the NRCs regional office.
 
If a secure document management service                    is utilized, it is          recommended that a separate folder
be used corresponding to each item listed below. Documents should be identified by both
document number and noun name.                      Electronic media on compact disc or paper records (hard
copy) are also acceptable.
 
The inspection team will examine the returned documentation from the first RFI and
identify/select specific samples          to provide a more focused follow-up request to develop the
second RFI.  The inspection team will submit the specific selected samples          to your staff by
February 25, 2022.                                                                                                    We request that the additional information provided from the second RFI be
made available by March 11, 2022.
 
This document request is based on typical documents that a generic plant might have.  As such,
this generic document request is not meant to imply that any specific plant is required to have all
the listed documents.  It is recognized that some documents listed below may not be available
for your plant.  In addition, the document titles listed below are based on typical industry
document names; your plant-specific document titles may vary.
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                                                                    Enclosure
A.                                                                                DESIGN AND LICENSING BASIS DOCUMENTS
 
          A.1                                                          The current version of the Fire Protection Program and Fire Hazards Analysis
 
          A.2                                                          Post-fire Nuclear Safety Capability, Systems, and Separation Analysis, and the
                      supporting calculations that demonstrate acceptable plant response.
 
          A.3                                                          Fire PRA Summary Report, and list          of Fire PRA calculations
 
          A.4                                                          NFPA 805 Transition Report, developed in accordance with NEI 04-                                                    02
 
          A.5                                                          LIST of post-fire safe shutdown                      systems and components (i.e., safe shutdown
                      equipment list).
 
          A.6                                                          LIST of fire areas with automatic fire suppression systems
 
          A.7                                                          LIST, with descriptions, of design change packages performed since the last fire
                      protection                                            team inspection associated with fire protection or post-fire safe
                      shutdown systems.
 
          A.8                                                          LIST, with descriptions, of any fire protection program changes and evaluations
                      (not limited to Generic Letter 86-10 evaluations) performed since the last fire
                      protection                                            team inspection
 
          A.9                                                          Fire Protection System(s) Design Basis Document.
 
          A.10                                                                                LIST of applicable NFPA codes and standards and issuance dates (i.e., codes of
                      record).
 
          A.11                                    A list or document identifying any deviations from the NFPA codes of record.
 
          A.12                                    Facility Operating License.
 
          A.13                                    Technical Specifications (electronic format only).
 
          A.14                                    Updated Final Safety Analysis Report (electronic format only).
 
          A.15                                    COPY of NRC Safety Evaluation Reports that form the licensing basis for:
 
              *                      Fire Protection Program; and
              *                      Post-fire Nuclear Safety Capability.
 
          A.16          COPY of NRC approved exemptions for plant fire protection and post-fire nuclear
                    safety capability features.
 
          A.17          COPY of exemption requests submitted but not yet approved for plant fire
                    protection and post-fire nuclear safety capability features.
 
          A.18          LIST of nuclear safety capability design changes completed in the last three years
                    (including their associated 10 CFR 50.59 and NFPA 805 plant change
                    evaluations).
 
                                                                        2
        A.19                                    LIST of the top 25 highest fire CDF scenarios for each unit
 
        A.20                                     LIST of the top 25 highest fire LERF scenarios for each unit
 
        A.21                                     From your most recent PRA including external events and fires:
 
                  a.         Two risk rankings of components from your site-                   specific PRA:  one sorted by
                      Risk Achievement Worth (RAW), and the other sorted by Birnbaum
                      Importance
 
                  b.       A list of the top 500 cut-sets
 
        A.22                                     COPY of the Quality Assurance Program Manual (including specific fire
                  protection QA manual, if applicable)
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                              3
}}
}}

Latest revision as of 19:01, 27 November 2024

Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI)
ML22019A244
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/18/2022
From: James Baptist
NRC/RGN-II/DRS/EB2
To: Snider S
Duke Energy Carolinas
References
IR 2022010
Download: ML22019A244 (5)


See also: IR 05000269/2022010

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

January 18, 2022

Steven M. Snider

Site Vice President, Oconee Nuclear Station

Duke Energy Carolinas, LLC

7800 Rochester Highway

Seneca, SC 29672-0752

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - NOTIFICATION OF AN

NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION

REPORT 05000269/2022010, 05000270/2022010, 05000287/2022010) AND

REQUEST FOR INFORMATION (RFI)

Dear Mr. Snider:

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

Region II staff will conduct a fire protection team inspection at the Oconee Nuclear Station,

Units 1, 2 and 3, in March and April of 2022. The inspection team will be led by Mr. Jonathan

Montgomery, a Senior Reactor Inspector from the NRC Region II Office. The inspection team

will be comprised of four inspectors from the NRC Region II office. The inspection will be

conducted in accordance with Inspection Procedure 71111, Attachment 21N.05, Fire Protection

Team Inspection, the NRCs baseline fire protection inspection procedure.

On January 12, 2022, during a phone call between Samuel Adams of your staff and

Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite

inspection. The schedule for the inspection is as follows:

Week 1 of onsite inspection: March 21-25, 2022

Week 2 of onsite inspection: April 4-8, 2022

The team lead and senior reactor analyst will work with your staff prior to the start of the

inspection to select the scope of structures, systems, and components for evaluation; identify

additional documents needed to support the inspection; and obtain unescorted access.

The enclosure to this letter provides an initial list of the documents the team will need for their

review. We request that your staff transmit copies of the documents listed in the enclosure to

the NRC Region II office for team use in preparation for the inspection. Please send this

information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.

S. Snider

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During the weeks leading up to the inspection, the team leader will discuss with your staff the

following inspection support administrative details: (1) office space size and location; (2)

specific documents requested to be made available to the team in their office spaces; (3)

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

and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and

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

We request that during the on-site inspection weeks you ensure that copies of analyses,

evaluations, or documentation regarding the implementation and maintenance of the station fire

protection program, including the success path necessary to achieve and maintain the nuclear

safety performance criteria, be readily accessible to the team for their review. Of specific

interest for the fire protection portion of the inspection are those documents which establish that

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

NRC and industry fire protection guidance (i.e., fire protection compliance assessment

documents). Also, personnel should be available at the site during the inspection who are

knowledgeable regarding those plant systems required to achieve and maintain safe and stable

plant conditions, including the electrical aspects of the nuclear safety capability assessment,

reactor plant fire protection systems and features, and the station fire protection program and its

implementation.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget under control

number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to

respond to, a request for information or an information collection requirement unless the

requesting document displays a currently valid Office of Management and Budget control

number.

This letter and its enclosure will be made available for public inspection and copying at

http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in

accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

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 Jonathan Montgomery, the team lead inspector, in the Region II office at

(404) 997-4880 or jonathan.montgomery@nrc.gov, or call me at (404) 997-4506.

Sincerely,

James Baptist, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-269, 50-270, 50-287

License No. DPR-38, DPR-47, DPR-55

Enclosures:

Fire Protection Team Inspection

Document Request

cc w/enclosure: via ListServ

James B.

Baptist

Digitally signed by James B.

Baptist

Date: 2022.01.18 15:03:01

-05'00'

Fire Protection Team Inspection Document Request

Enclosure

The initial request for information (i.e., first RFI) concentrates on providing the inspection team

with the general information necessary to select appropriate samples to develop a site-specific

inspection plan. The first RFIs requested information is specified below in items A.1 thru A.22,

and is requested to be provided by February 17, 2022, or sooner, to facilitate the selection of

the specific items that will be reviewed during the onsite inspection weeks.

Electronic format is the preferred format, except where specifically noted. If electronic files are

made available via a secure document management service, then the remote document access

must allow inspectors to download, save, and print the documents in the NRCs regional office.

If a secure document management service is utilized, it is recommended that a separate folder

be used corresponding to each item listed below. Documents should be identified by both

document number and noun name. Electronic media on compact disc or paper records (hard

copy) are also acceptable.

The inspection team will examine the returned documentation from the first RFI and

identify/select specific samples to provide a more focused follow-up request to develop the

second RFI. The inspection team will submit the specific selected samples to your staff by

February 25, 2022. We request that the additional information provided from the second RFI be

made available by March 11, 2022.

This document request is based on typical documents that a generic plant might have. As such,

this generic document request is not meant to imply that any specific plant is required to have all

the listed documents. It is recognized that some documents listed below may not be available

for your plant. In addition, the document titles listed below are based on typical industry

document names; your plant-specific document titles may vary.

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A.

DESIGN AND LICENSING BASIS DOCUMENTS

A.1

The current version of the Fire Protection Program and Fire Hazards Analysis

A.2

Post-fire Nuclear Safety Capability, Systems, and Separation Analysis, and the

supporting calculations that demonstrate acceptable plant response.

A.3

Fire PRA Summary Report, and list of Fire PRA calculations

A.4

NFPA 805 Transition Report, developed in accordance with NEI 04-02

A.5

LIST of post-fire safe shutdown systems and components (i.e., safe shutdown

equipment list).

A.6

LIST of fire areas with automatic fire suppression systems

A.7

LIST, with descriptions, of design change packages performed since the last fire

protection team inspection associated with fire protection or post-fire safe

shutdown systems.

A.8

LIST, with descriptions, of any fire protection program changes and evaluations

(not limited to Generic Letter 86-10 evaluations) performed since the last fire

protection team inspection

A.9

Fire Protection System(s) Design Basis Document.

A.10

LIST of applicable NFPA codes and standards and issuance dates (i.e., codes of

record).

A.11

A list or document identifying any deviations from the NFPA codes of record.

A.12

Facility Operating License.

A.13

Technical Specifications (electronic format only).

A.14

Updated Final Safety Analysis Report (electronic format only).

A.15

COPY of NRC Safety Evaluation Reports that form the licensing basis for:

  • Post-fire Nuclear Safety Capability.

A.16 COPY of NRC approved exemptions for plant fire protection and post-fire nuclear

safety capability features.

A.17 COPY of exemption requests submitted but not yet approved for plant fire

protection and post-fire nuclear safety capability features.

A.18 LIST of nuclear safety capability design changes completed in the last three years

(including their associated 10 CFR 50.59 and NFPA 805 plant change

evaluations).

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A.19

LIST of the top 25 highest fire CDF scenarios for each unit

A.20

LIST of the top 25 highest fire LERF scenarios for each unit

A.21

From your most recent PRA including external events and fires:

a. Two risk rankings of components from your site-specific PRA: one sorted by

Risk Achievement Worth (RAW), and the other sorted by Birnbaum

Importance

b. A list of the top 500 cut-sets

A.22

COPY of the Quality Assurance Program Manual (including specific fire

protection QA manual, if applicable)