ML22019A244: Difference between revisions

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| number = ML22019A244
| number = ML22019A244
| issue date = 01/18/2022
| issue date = 01/18/2022
| title = Notification of an NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI)
| title = Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI)
| author name = Baptist J
| author name = Baptist J
| author affiliation = NRC/RGN-II/DRS/EB2
| author affiliation = NRC/RGN-II/DRS/EB2
Line 17: Line 17:


=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
January 18, 2022  
Steven M. Snider
Site Vice President, Oconee Nuclear Station
Duke Energy Carolinas, LLC
Steven M. Snider  
7800 Rochester Highway
Site Vice President, Oconee Nuclear Station  
Seneca, SC 29672-0752
Duke Energy Carolinas, LLC  
SUBJECT:       OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - NOTIFICATION OF AN
7800 Rochester Highway  
                NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION
Seneca, SC 29672-0752  
                REPORT 05000269/2022010, 05000270/2022010, 05000287/2022010) AND
                REQUEST FOR INFORMATION (RFI)
SUBJECT:  
Dear Mr. Snider:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - NOTIFICATION OF AN  
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),
NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION  
Region II staff will conduct a fire protection team inspection at the Oconee Nuclear Station,
REPORT 05000269/2022010, 05000270/2022010, 05000287/2022010) AND  
Units 1, 2 and 3, in March and April of 2022. The inspection team will be led by Mr. Jonathan
REQUEST FOR INFORMATION (RFI)  
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
Dear Mr. Snider:  
conducted in accordance with Inspection Procedure 71111, Attachment 21N.05, Fire Protection
Team Inspection, the NRCs baseline fire protection inspection procedure.
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC),  
On January 12, 2022, during a phone call between Samuel Adams of your staff and
Region II staff will conduct a fire protection team inspection at the Oconee Nuclear Station,  
Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite
Units 1, 2 and 3, in March and April of 2022. The inspection team will be led by Mr. Jonathan  
inspection. The schedule for the inspection is as follows:
Montgomery, a Senior Reactor Inspector from the NRC Region II Office. The inspection team  
    * Week 1 of onsite inspection: March 21-25, 2022
will be comprised of four inspectors from the NRC Region II office. The inspection will be  
    * Week 2 of onsite inspection: April 4-8, 2022
conducted in accordance with Inspection Procedure 71111, Attachment 21N.05, Fire Protection  
The team lead and senior reactor analyst will work with your staff prior to the start of the
Team Inspection, the NRCs baseline fire protection inspection procedure.  
inspection to select the scope of structures, systems, and components for evaluation; identify
additional documents needed to support the inspection; and obtain unescorted access.
On January 12, 2022, during a phone call between Samuel Adams of your staff and
The enclosure to this letter provides an initial list of the documents the team will need for their
Mr. Montgomery, our respective staffs confirmed arrangements for a two-week onsite  
review. We request that your staff transmit copies of the documents listed in the enclosure to
inspection. The schedule for the inspection is as follows:  
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.
*  
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
S. Snider  
During the weeks leading up to the inspection, the team leader will discuss with your staff the
2  
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)
During the weeks leading up to the inspection, the team leader will discuss with your staff the  
arrangements for reactor site access (including radiation protection training, security, safety,
following inspection support administrative details: (1) office space size and location; (2)  
and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and
specific documents requested to be made available to the team in their office spaces; (3)  
licensing organization personnel to serve as points of contact during the inspection.
arrangements for reactor site access (including radiation protection training, security, safety,  
We request that during the on-site inspection weeks you ensure that copies of analyses,
and fitness for duty requirements); and (4) the availability of knowledgeable plant staff and  
evaluations, or documentation regarding the implementation and maintenance of the station fire
licensing organization personnel to serve as points of contact during the inspection.  
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
We request that during the on-site inspection weeks you ensure that copies of analyses,  
interest for the fire protection portion of the inspection are those documents which establish that
evaluations, or documentation regarding the implementation and maintenance of the station fire  
your fire protection program satisfies NRC regulatory requirements and conforms to applicable
protection program, including the success path necessary to achieve and maintain the nuclear  
NRC and industry fire protection guidance (i.e., fire protection compliance assessment
safety performance criteria, be readily accessible to the team for their review. Of specific  
documents). Also, personnel should be available at the site during the inspection who are
interest for the fire protection portion of the inspection are those documents which establish that  
knowledgeable regarding those plant systems required to achieve and maintain safe and stable
your fire protection program satisfies NRC regulatory requirements and conforms to applicable  
plant conditions, including the electrical aspects of the nuclear safety capability assessment,
NRC and industry fire protection guidance (i.e., fire protection compliance assessment  
reactor plant fire protection systems and features, and the station fire protection program and its
documents). Also, personnel should be available at the site during the inspection who are  
implementation.
knowledgeable regarding those plant systems required to achieve and maintain safe and stable  
This letter does not contain new or amended information collection requirements subject to the
plant conditions, including the electrical aspects of the nuclear safety capability assessment,  
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
reactor plant fire protection systems and features, and the station fire protection program and its  
requirements were approved by the Office of Management and Budget under control
implementation.  
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
This letter does not contain new or amended information collection requirements subject to the  
requesting document displays a currently valid Office of Management and Budget control
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection  
number.
requirements were approved by the Office of Management and Budget under control  
This letter and its enclosure will be made available for public inspection and copying at
number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to  
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
respond to, a request for information or an information collection requirement unless the  
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
requesting document displays a currently valid Office of Management and Budget control  
Your cooperation and support during this inspection will be appreciated. If you have questions
number.  
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
This letter and its enclosure will be made available for public inspection and copying at  
(404) 997-4880 or jonathan.montgomery@nrc.gov, or call me at (404) 997-4506.
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in  
                                                  Sincerely,
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.  
                                                  James B.            Digitally signed by James B.
Your cooperation and support during this inspection will be appreciated. If you have questions  
                                                                        Baptist
concerning this inspection, or the inspection teams information or logistical needs, please  
                                                  Baptist              Date: 2022.01.18 15:03:01
contact Jonathan Montgomery, the team lead inspector, in the Region II office at
                                                                        -05'00'
(404) 997-4880 or jonathan.montgomery@nrc.gov, or call me at (404) 997-4506.  
                                                  James Baptist, Chief
                                                  Engineering Branch 1
Sincerely,
                                                  Division of Reactor Safety
Docket No. 50-269, 50-270, 50-287
License No. DPR-38, DPR-47, DPR-55
Enclosures:
James Baptist, Chief  
Fire Protection Team Inspection
Engineering Branch 1  
  Document Request
Division of Reactor Safety  
cc w/enclosure: via ListServ
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
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 specified below in items A.1 thru A.22,
Enclosure
and is requested to be provided by February 17, 2022, or sooner, to facilitate the selection of
The initial request for information (i.e., first RFI) concentrates on providing the inspection team  
the specific items that will be reviewed during the onsite inspection weeks.
with the general information necessary to select appropriate samples to develop a site-specific  
Electronic format is the preferred format, except where specifically noted. If electronic files are
inspection plan. The first RFIs requested information is specified below in items A.1 thru A.22,  
made available via a secure document management service, then the remote document access
and is requested to be provided by February 17, 2022, or sooner, to facilitate the selection of  
must allow inspectors to download, save, and print the documents in the NRCs regional office.
the specific items that will be reviewed during the onsite inspection weeks.  
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
Electronic format is the preferred format, except where specifically noted. If electronic files are  
document number and noun name. Electronic media on compact disc or paper records (hard
made available via a secure document management service, then the remote document access  
copy) are also acceptable.
must allow inspectors to download, save, and print the documents in the NRCs regional office.  
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
If a secure document management service is utilized, it is recommended that a separate folder  
second RFI. The inspection team will submit the specific selected samples to your staff by
be used corresponding to each item listed below. Documents should be identified by both  
February 25, 2022. We request that the additional information provided from the second RFI be
document number and noun name. Electronic media on compact disc or paper records (hard  
made available by March 11, 2022.
copy) are also acceptable.  
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 inspection team will examine the returned documentation from the first RFI and  
the listed documents. It is recognized that some documents listed below may not be available
identify/select specific samples to provide a more focused follow-up request to develop the  
for your plant. In addition, the document titles listed below are based on typical industry
second RFI. The inspection team will submit the specific selected samples to your staff by  
document names; your plant-specific document titles may vary.
February 25, 2022. We request that the additional information provided from the second RFI be  
                                                                                            Enclosure
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.  


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


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
3
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
A.19  
        Importance
LIST of the top 25 highest fire CDF scenarios for each unit  
    b. A list of the top 500 cut-sets
A.22 COPY of the Quality Assurance Program Manual (including specific fire
A.20  
    protection QA manual, if applicable)
LIST of the top 25 highest fire LERF scenarios for each unit  
                                      3
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)
}}
}}

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)
v • d • e


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

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'

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:

  • 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).

3

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)

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