ML22019A244: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
Line 14: Line 14:
| page count = 5
| page count = 5
}}
}}
See also: [[see also::IR 05000269/2022010]]
See also: [[followed by::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
 
 
                                                                January 18, 2022
 
 
Steven M. Snider
Steven M. Snider
Site Vice President, Oconee Nuclear Station
Site Vice President, Oconee Nuclear Station
Duke Energy Carolinas, LLC
Duke Energy Carolinas, LLC
7800 Rochester Highway
7800 Rochester Highway
Seneca, SC 29672-0752
Seneca, SC 29672-                                                                                                                         0752
SUBJECT:       OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - NOTIFICATION OF AN
 
                NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION
SUBJECT:                                     OCONEE NUCLEAR STATION, UNITS 1                         , 2 AND 3 -           NOTIFICATION OF AN
                REPORT 05000269/2022010, 05000270/2022010, 05000287/2022010) AND
                        NRC FIRE PROTECTION TEAM INSPECTION (FPTI) (NRC INSPECTION
                REQUEST FOR INFORMATION (RFI)
                        REPORT 05000269/202                                                                                                                                                                              2010,                                             05000270                                                                                                             /2022                                                                010, 05000287                                                                                                             /2022                                                                010                                          ) AND
Dear Mr. Snider:
                        REQUEST FOR INFORMATION (RFI)
 
Dear Mr. Snider         :
 
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 fire protection team inspection at the Oconee Nuclear Station,
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
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
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
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
conducted in accordance with Inspection Procedure                     71111, Attachment 21N.05, Fire Protection
Team Inspection, the NRCs baseline fire protection inspection procedure.
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
On January 12, 2022, during a                                                                                                                                                       phone call between Samuel Adams of your staff and
inspection. The schedule for the inspection is as follows:
Mr. Montgomery, our respective staffs confirmed arrangements for a two-                   week onsite
    * Week 1 of onsite inspection: March 21-25, 2022
inspection. The schedule for the inspection is as follows:
    * 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
      *                                   Week 1 of onsite inspection:                                             March 21-                                                     25, 2022
inspection to select the scope of structures, systems, and components for evaluation; identify
      *                                   Week 2 of onsite inspection:                                             April 4-         8, 2022
additional documents needed to support the inspection; and obtain unescorted access.
 
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
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
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
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.
information so that it will arrive in the NRC Region II office by the dates listed in the enclosure.


S. Snider                                       2
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)
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)
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,
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
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.
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,
 
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
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
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
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
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
your fire protection program satisfies NRC regulatory requirements and conforms to applicable
NRC and industry fire protection guidance (i.e., fire protection compliance assessment
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
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
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,
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
reactor plant fire protection systems and features, and the station fire protection program and its
implementation.
implementation.
This letter does not contain new or amended information collection requirements subject to the
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
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
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
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
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
requesting document displays a currently valid Office of Management and Budget control
number.
number.
This letter and its enclosure will be made available for public inspection and copying at
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
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.
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
Your cooperation and support during this inspection will be appreciated. If you have questions
concerning this inspection, or the inspection teams information or logistical needs, please
concerning this inspection,                     or the inspection teams information or logistical needs, please
contact Jonathan Montgomery, the team lead inspector, in the Region II office at
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.
(404)                                                                 997-                                                                 4880 or jonathan.montgomery@nrc.gov, or call                 me at (404) 997-4506.
                                                  Sincerely,
 
                                                  James B.            Digitally signed by James B.
                                                                        Sincerely,
                                                                        Baptist
 
                                                  Baptist              Date: 2022.01.18 15:03:01
 
                                                                         -05'00'
 
                                                  James Baptist, Chief
                                                                         James Baptist, Chief
                                                  Engineering Branch 1
                                                                        Engineering Branch 1
                                                  Division of Reactor Safety
                                                                        Division of Reactor Safety
Docket No. 50-269, 50-270, 50-287
 
License No. DPR-38, DPR-47, DPR-55
Docket No. 50-269, 50-                                           270, 50-287
License No. DPR-                                     38, DPR-47, DPR-                           55
 
Enclosures:
Enclosures:
Fire Protection Team Inspection
Fire Protection                                             Team Inspection
   Document Request
   Document Request
cc w/enclosure: via ListServ


                      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
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
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,
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
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.
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
 
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
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.
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
 
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
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
document number and noun name.                       Electronic media on compact disc or paper records (hard
copy) are also acceptable.
copy) are also acceptable.
The inspection team will examine the returned documentation from the first RFI and
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
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
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
February 25, 2022.                                                                                                     We request that the additional information provided from the second RFI be
made available by March 11, 2022.
made available by March 11, 2022.
This document request is based on typical documents that a generic plant might have. As such,
 
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
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
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
for your plant. In addition, the document titles listed below are based on typical industry
document names; your plant-specific document titles may vary.
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
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                                                                    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
}}
}}

Revision as of 23:45, 18 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 05000269/202 2010, 05000270 /2022 010, 05000287 /2022 010 ) 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

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:

  • 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

Retrieved from "https://kanterella.com/w/index.php?title=ML22019A244&oldid=3737373"