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{{#Wiki_filter:
{{#Wiki_filter:January 7, 2022
Mr. Christopher P. Domingos
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  NOTIFICATION OF NRC
            FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;
            INSPECTION REPORT 05000282/2022010; 05000306/2022010
Dear Mr. Domingos:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region III staff will conduct a Fire Protection Team Inspection at your Prairie Island Nuclear
Generating Plant beginning March 28, 2022. The inspection will be conducted in accordance
with Inspection Procedure 71111.21N.05, Fire Protection Team Inspection, dated June 12,
2019.
The inspection will verify that plant structures, systems and components (SSCs) and/or
administrative controls credited in the approvedFire Protection Program can perform their
licensing basis function.
The schedule for the inspection is as follows:
      Preparation week (R-III office):        March 21 - 25, 2022
      Week 1 of onsite inspection:            March 28 - April 1, 2022
      Week 2 of onsite inspection:            April 11 - 15, 2022
Experience has shown that the baseline fire protection team inspections are extremely resource
intensive, both for the NRC inspectors and the licensee staff. In order to minimize the
inspection impact on the site and to ensure a productive inspection for both organizations, we
have enclosed a request for documents needed for the inspection. These documents have
been divided into three groups.
      The first group lists information necessary to aid the inspection team in choosing
        specific focus areas for the inspection and to ensure that the inspection team is
        adequately prepared for the inspection. It is requested that this information be
        provided to the lead inspector via mail or electronically no later than February 21, 2022.
      The second group of requested documents consists of those items that the team will
        review, or need access to, during the inspection. Please have this information
        available by the first day of the first onsite inspection week March 28, 2022.
 
C. Domingos                                      -2-
      The third group lists the information necessary to aid the inspection team in tracking
        issues identified as a result of the inspection. It is requested that this information be
        provided to the lead inspector as the information is generated during the inspection. It is
        important that all of these documents are up to date and complete in order to minimize
        the number of additional documents requested during the preparation and/or the onsite
        portions of the inspection.
The lead inspector for this inspection is Ms. J. Gilliam. We understand that our regulatory
contact for this inspection is Ms. C. Seipp of your organization. If there are any questions about
the inspection or the material requested, please contact the lead inspector at 630-829-9831 or
via e-mail at Jasmine.Gilliam@nrc.gov.
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, 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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,
Exemptions, Requests for Withholding.
                                                Sincerely,
                                                                      Signed by Gilliam, Jasmine
                                                                        on 01/07/22
                                                Jasmine Gilliam, Senior Reactor Inspector
                                                Engineering Branch 3
                                                Division of Reactor Safety
Docket Nos. 50-282 and 50-306
License Nos. DPR-42 and DPR-60
Enclosure:
Fire Protection Team Inspection Supporting
Documentation
cc: Distribution via LISTSERV
 
C. Domingos                                  -3-
Letter to Christopher P. Domingos from Jasmine Gilliam dated January 7, 2022.
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  NOTIFICATION OF NRC
            FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;
            INSPECTION REPORT 05000282/2022010; 05000306/2022010
DISTRIBUTION:
Jessie Quichocho
Linda Howell
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDroIrib Resource
John Giessner
Mohammed Shuaibi
Shelbie Lewman
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML22007A154
    Publicly Available      Non-Publicly Available        Sensitive      Non-Sensitive
OFFICE      RIII
NAME        JGilliam:mb
DATE        01/07/2022
                                OFFICIAL RECORD COPY
 
        FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
I. Information Requested prior to the Inspection Preparation Week
  The following information is requested by February 21, 2022. If you have any questions
  regarding this request, please call the lead inspector as soon as possible. All information
  should be sent to Jasmine Gilliam (e-mail address Jasmine.Gilliam@nrc.gov). Electronic
  media or database is preferred. The preferred file format is a searchable pdf or Microsoft
  Excel file. If a CD is use it should be indexed and hyper-linked to facilitate ease of use, if
  possible. Please provide three copies of each CD submitted (one for each inspector).
  1. One set of hard-copy documents for facility layout drawings which identify plant fire area
      delineation; areas protected by automatic fire suppression and detection; and locations
      of fire protection equipment.
  2. Licensing Information:
      a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
            applicable to fire protection (specifically including those SERs referenced by the
            plant fire protection license condition) and all licensing correspondence referenced by
            the SERs;
      b. All licensing correspondence associated with the comparison to Standard Review
            Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;
      c. Exemptions from Title 10 of the Code of Federal Regulations (CFR), Part 50.48 and
            10 CFR Part 50, Appendix R, and associated licensing correspondence;
      d. For pre-1979 plants, all licensing correspondence associated with those sections of
            10 CFR Part 50, Appendix R, that are not applicable to the plant under
            10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with
            those fire protection features proposed or implemented by the licensee that have
            been accepted by the NRC staff as satisfying the provisions of Appendix A to Branch
            Technical Position APCSB 9.5-1 reflected in the NRC fire protection SERs issued
            before February 19, 1981 (10 CFR 50.48(b)(1)(i)); or those fire protection features,
            which were accepted by the NRC staff in comprehensive fire protection SERs issued
            before Appendix A to Branch Technical Position APCSB 9.5-1 was published in
            August 1976 (10 CFR 50.48(b)(1)(ii)); and
      e. The final safety analysis report sections applicable to fire protection, fire hazards
            analysis (FHA), and safe shutdown analysis (SSA) in effect at the time of original
            licensing.
  3. Fire Protection Program:
      a. A listing of changes made to the Fire Protection Program since the last triennial fire
            protection inspection;
      b. For pre-1979 plants, a listing of the protection methodologies identified under
            10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for fire
            zones/areas. That is, please specify whether 3-hour rated fire barriers;
            (Section III.G.2.a), 20-foot separation along with detection and suppression;
            (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression;
                                                                                          Enclosure
 
      FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
        (Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a
        strategy for each selected fire zone/area;
  c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe shutdown
        evaluations);
  d. A list of applicable codes and standards related to the design of plant fire protection
        features. The list should include National Fire Protection Association (NFPA) code
        versions committed to (i.e., the NFPA Codes of Record);
  e. List of plant deviations from code commitments and associated evaluations;
  f.  Fire Protection Program and/or Fire Protection Plan document;
  g. (If available) Fire Probabilistic Risk Assessment (PRA) Summary Report or full PRA
        document (if summary document not available);
  h. List of the top 25 highest fire core damage frequency (CDF) scenarios for each unit;
  i.  List of Fire Areas/Zones ranked by contribution to CDF (i.e., ranking of highest to
        lowest risk fire areas/zones);
  j.  List of the top 25 highest fire large early release frequency (LERF) scenarios for
        each unit; and
  k. Risk ranking of operator actions and/or recovery actions from your site-specific PRA
        sorted by risk assessment worth (RAW) and human reliability worksheets for these
        items.
4. Facility Information:
  a. Piping and instrumentation (flow) diagrams showing the components used to achieve
        and maintain hot standby and cold shutdown for fires outside the control room, and
        those components used for those areas requiring alternative shutdown capability;
  b. One-line schematic drawings of the electrical distribution system for 4160 Volts
        alternating current (Vac) down to 480 Vac;
  c. One-line schematic drawings of the electrical distribution system for 250 Volts direct
        current (Vdc) and 125 Vdc systems as applicable;
  d. Logic diagrams showing the components used to achieve and maintain hot standby
        and cold shutdown; and
  e. Safe shutdown cable routing database (requested electronically, such as on compact
        disc, if available).
5. Operations Response for Fire Protection:
  a. Pre-fire plans for fire zones/areas; and
                                              2
 
          FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
        b. Plant operating procedures which specify the initial operations response to a fire
            alarm or annunciator.
    6. Corrective Actions:
        a. Listing of open and closed fire protection condition reports (i.e., problem identification
            forms and their resolution reports) since the date of the last triennial fire protection
            inspection; and
        b. List of current fire impairments, including duration.
    7. General Information:
        a. A listing of abbreviations and/or designators for plant systems;
        b. Organization charts of site personnel down to the level of fire protection staff
            personnel; and
        c. A phone list for onsite licensee personnel.
II. Information Requested to Be Available on First Day of the FIRST ONSITE Inspection
    Week (MARCH 28, 2022)
    The following information is requested to be provided on the first day of inspection. It is
    requested that this information be provided on three sets of CDs (searchable, if possible).
    1. Program Procedures:
        a. Procedures for:
              i.  Administrative controls (such as allowed out of service times and
                  compensatory measures) for fire protection systems and components;
              ii. Control of transient combustibles; and
              iii. Control of hot work.
        b. List of maintenance and surveillance testing procedures for alternative shutdown
            capability and fire barriers, detectors, pumps, and suppression systems; and
        c. List of maintenance procedures which routinely verify fuse breaker coordination in
            accordance with the post-fire safe shutdown coordination analysis.
    2. Design and Equipment Information (for only selected fire zone/area(s) and/or SSCs
        to be determined during inspection preparation week):
        a. Coordination calculations and/or justifications that verify fuse/breaker coordination for
            SSCs that are fed off of the same electrical buses as components in the protected
            safe shutdown train;
                                                  3
 
      FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
  b. Copies of significant fire protection and post-fire safe shutdown related design
        change package descriptions (including their associated 10 CFR 50.59
        evaluations) and Generic Letter 86-10 (or adverse to safe shutdown) evaluations;
  c. Gaseous suppression system pre-operational testing, if applicable, for selected fire
        zones/areas;
  d. Hydraulic calculations and supporting test data which demonstrate operability for
        water suppression systems;
  e. Alternating current (ac) coordination calculations for 4160 Vac down to 480 Vac
        electrical systems; and
  f.  List of all fire protection or Appendix R calculations.
3. Assessment and Corrective Actions:
  The three most recent fire protection Quality Assurance audits and/or fire protection
  self-assessments.
4. Any updates to information previously provided.
5. Classic Fire Protection (for only selected fire zone/area(s) and/or SSCs to be
  determined during inspection preparation week):
  a. Copy of Fire Protection Program implementing procedures (e.g., administrative
        controls, surveillance testing, and fire brigade);
  b. Pre-fire plans for selected fire area(s); and
  c. List of fire protection system design changes completed in the last 3 years.
6. Electrical (for only selected fire zone/area(s) and/or SSCs to be determined during
  inspection preparation week):
  a. Nuclear safety circuit coordination analysis for fuse and breaker coordination of safe
        shutdown components;
  b. Administrative or configuration control procedures that govern fuse replacement
        (e.g., fuse control procedures);
  c. Maintenance procedures that verify breaker over-current trip settings to ensure
        coordination remains functional, for post-fire nuclear safety capability components;
  d. Last surveillance demonstrating operability of those components operated from the
        primary control stations;
  e. Schematic or elementary diagrams for circuits (only for selected SSCs) to be
        reviewed (C-size paper drawings);
                                                4
 
            FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
        f.  Cable routing for components and equipment credited for post-fire nuclear safety
              capability systems and components;
        g. List of post-fire nuclear safety capability system and component design changes
              completed, in the last 3 years; and
        h. List of identified fire induced circuit failure analyses.
    7. Operations:
        a. List of procedures that implement Cold Shutdown Repairs (if applicable for selected
              fire area);
        b. For Cold Shutdown Repairs, provide the following:
                i. Procedure for inventory and inspection (i.e., needed tools, material, etc.); and
                ii. Most recent inspection and inventory results.
        c. List of licensed operator Job Performance Measures for operator actions required to
              achieve and maintain post-fire nuclear safety performance criteria (for selected SSCs
              and fire area);
        d. For Radio communications, provide the following:
                i.  Communications Plan for firefighting and post-fire safe shutdown manual
                      actions;
                ii.  Repeater locations;
                iii. Cable routing for repeater power supply cables;
                iv.  Radio coverage test results; and
                v.  Radio Dead Spot locations in the plant.
        e. Environmental and habitability evaluations for post-fire operator actions (temperature,
              smoke, humidity, SCBAs, etc.).
    8. Administrative Control, Oversight, and Corrective Action Programs:
        a. Self-assessments, peer assessments, and audits of fire protection activities for the
              last 3 years;
        b. Self-assessments, peer assessments, and audits of post-fire nuclear safety capability
              methodology for the last 3 years; and
        c. List of fire event analysis reports for the last 3 years.
    9. Any updates to information previously provided.
III. Information Requested to Be Provided Throughout the Inspection
    1. Copies of any corrective action documents generated as a result of the inspection teams
        questions or queries during this inspection.
                                                      5
 
    FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION
2. Copies of the list of questions submitted by the inspection team members and the
  status/resolution of the information requested (provided daily during the inspection to
  each inspection team member).
                                            6
}}
}}

Revision as of 09:32, 18 January 2022

Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000282/2022010 and 05000306/2022010
ML22007A154
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 01/07/2022
From: Jasmine Gilliam
Engineering Branch 3
To: Domingos C
Northern States Power Company, Minnesota
References
IR 2022010
Download: ML22007A154 (9)


See also: IR 05000282/2022010

Text

January 7, 2022

Mr. Christopher P. Domingos

Site Vice President

Prairie Island Nuclear Generating Plant

Northern States Power Company, Minnesota

1717 Wakonade Drive East

Welch, MN 55089-9642

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT NOTIFICATION OF NRC

FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;

INSPECTION REPORT 05000282/2022010; 05000306/2022010

Dear Mr. Domingos:

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

Region III staff will conduct a Fire Protection Team Inspection at your Prairie Island Nuclear

Generating Plant beginning March 28, 2022. The inspection will be conducted in accordance

with Inspection Procedure 71111.21N.05, Fire Protection Team Inspection, dated June 12,

2019.

The inspection will verify that plant structures, systems and components (SSCs) and/or

administrative controls credited in the approvedFire Protection Program can perform their

licensing basis function.

The schedule for the inspection is as follows:

Preparation week (R-III office): March 21 - 25, 2022

Week 1 of onsite inspection: March 28 - April 1, 2022

Week 2 of onsite inspection: April 11 - 15, 2022

Experience has shown that the baseline fire protection team inspections are extremely resource

intensive, both for the NRC inspectors and the licensee staff. In order to minimize the

inspection impact on the site and to ensure a productive inspection for both organizations, we

have enclosed a request for documents needed for the inspection. These documents have

been divided into three groups.

The first group lists information necessary to aid the inspection team in choosing

specific focus areas for the inspection and to ensure that the inspection team is

adequately prepared for the inspection. It is requested that this information be

provided to the lead inspector via mail or electronically no later than February 21, 2022.

The second group of requested documents consists of those items that the team will

review, or need access to, during the inspection. Please have this information

available by the first day of the first onsite inspection week March 28, 2022.

C. Domingos -2-

The third group lists the information necessary to aid the inspection team in tracking

issues identified as a result of the inspection. It is requested that this information be

provided to the lead inspector as the information is generated during the inspection. It is

important that all of these documents are up to date and complete in order to minimize

the number of additional documents requested during the preparation and/or the onsite

portions of the inspection.

The lead inspector for this inspection is Ms. J. Gilliam. We understand that our regulatory

contact for this inspection is Ms. C. Seipp of your organization. If there are any questions about

the inspection or the material requested, please contact the lead inspector at 630-829-9831 or

via e-mail at Jasmine.Gilliam@nrc.gov.

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, 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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,

Exemptions, Requests for Withholding.

Sincerely,

Signed by Gilliam, Jasmine

on 01/07/22

Jasmine Gilliam, Senior Reactor Inspector

Engineering Branch 3

Division of Reactor Safety

Docket Nos. 50-282 and 50-306

License Nos. DPR-42 and DPR-60

Enclosure:

Fire Protection Team Inspection Supporting

Documentation

cc: Distribution via LISTSERV

C. Domingos -3-

Letter to Christopher P. Domingos from Jasmine Gilliam dated January 7, 2022.

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT NOTIFICATION OF NRC

FIRE PROTECTION TEAM INSPECTION REQUEST FOR INFORMATION;

INSPECTION REPORT 05000282/2022010; 05000306/2022010

DISTRIBUTION:

Jessie Quichocho

Linda Howell

RidsNrrPMPrairieIsland Resource

RidsNrrDorlLpl3

RidsNrrDroIrib Resource

John Giessner

Mohammed Shuaibi

Shelbie Lewman

Allan Barker

DRPIII

DRSIII

ADAMS Accession Number: ML22007A154

Publicly Available Non-Publicly Available Sensitive Non-Sensitive

OFFICE RIII

NAME JGilliam:mb

DATE 01/07/2022

OFFICIAL RECORD COPY

FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION

I. Information Requested prior to the Inspection Preparation Week

The following information is requested by February 21, 2022. If you have any questions

regarding this request, please call the lead inspector as soon as possible. All information

should be sent to Jasmine Gilliam (e-mail address Jasmine.Gilliam@nrc.gov). Electronic

media or database is preferred. The preferred file format is a searchable pdf or Microsoft

Excel file. If a CD is use it should be indexed and hyper-linked to facilitate ease of use, if

possible. Please provide three copies of each CD submitted (one for each inspector).

1. One set of hard-copy documents for facility layout drawings which identify plant fire area

delineation; areas protected by automatic fire suppression and detection; and locations

of fire protection equipment.

2. Licensing Information:

a. All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)

applicable to fire protection (specifically including those SERs referenced by the

plant fire protection license condition) and all licensing correspondence referenced by

the SERs;

b. All licensing correspondence associated with the comparison to Standard Review

Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;

c. Exemptions from Title 10 of the Code of Federal Regulations (CFR), Part 50.48 and

10 CFR Part 50, Appendix R, and associated licensing correspondence;

d. For pre-1979 plants, all licensing correspondence associated with those sections of

10 CFR Part 50, Appendix R, that are not applicable to the plant under

10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with

those fire protection features proposed or implemented by the licensee that have

been accepted by the NRC staff as satisfying the provisions of Appendix A to Branch

Technical Position APCSB 9.5-1 reflected in the NRC fire protection SERs issued

before February 19, 1981 (10 CFR 50.48(b)(1)(i)); or those fire protection features,

which were accepted by the NRC staff in comprehensive fire protection SERs issued

before Appendix A to Branch Technical Position APCSB 9.5-1 was published in

August 1976 (10 CFR 50.48(b)(1)(ii)); and

e. The final safety analysis report sections applicable to fire protection, fire hazards

analysis (FHA), and safe shutdown analysis (SSA) in effect at the time of original

licensing.

3. Fire Protection Program:

a. A listing of changes made to the Fire Protection Program since the last triennial fire

protection inspection;

b. For pre-1979 plants, a listing of the protection methodologies identified under

10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for fire

zones/areas. That is, please specify whether 3-hour rated fire barriers;

(Section III.G.2.a), 20-foot separation along with detection and suppression;

(Section III.G.2.b), 1-hour rated fire barriers with detection and suppression;

Enclosure

FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION

(Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a

strategy for each selected fire zone/area;

c. A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe shutdown

evaluations);

d. A list of applicable codes and standards related to the design of plant fire protection

features. The list should include National Fire Protection Association (NFPA) code

versions committed to (i.e., the NFPA Codes of Record);

e. List of plant deviations from code commitments and associated evaluations;

f. Fire Protection Program and/or Fire Protection Plan document;

g. (If available) Fire Probabilistic Risk Assessment (PRA) Summary Report or full PRA

document (if summary document not available);

h. List of the top 25 highest fire core damage frequency (CDF) scenarios for each unit;

i. List of Fire Areas/Zones ranked by contribution to CDF (i.e., ranking of highest to

lowest risk fire areas/zones);

j. List of the top 25 highest fire large early release frequency (LERF) scenarios for

each unit; and

k. Risk ranking of operator actions and/or recovery actions from your site-specific PRA

sorted by risk assessment worth (RAW) and human reliability worksheets for these

items.

4. Facility Information:

a. Piping and instrumentation (flow) diagrams showing the components used to achieve

and maintain hot standby and cold shutdown for fires outside the control room, and

those components used for those areas requiring alternative shutdown capability;

b. One-line schematic drawings of the electrical distribution system for 4160 Volts

alternating current (Vac) down to 480 Vac;

c. One-line schematic drawings of the electrical distribution system for 250 Volts direct

current (Vdc) and 125 Vdc systems as applicable;

d. Logic diagrams showing the components used to achieve and maintain hot standby

and cold shutdown; and

e. Safe shutdown cable routing database (requested electronically, such as on compact

disc, if available).

5. Operations Response for Fire Protection:

a. Pre-fire plans for fire zones/areas; and

2

FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION

b. Plant operating procedures which specify the initial operations response to a fire

alarm or annunciator.

6. Corrective Actions:

a. Listing of open and closed fire protection condition reports (i.e., problem identification

forms and their resolution reports) since the date of the last triennial fire protection

inspection; and

b. List of current fire impairments, including duration.

7. General Information:

a. A listing of abbreviations and/or designators for plant systems;

b. Organization charts of site personnel down to the level of fire protection staff

personnel; and

c. A phone list for onsite licensee personnel.

II. Information Requested to Be Available on First Day of the FIRST ONSITE Inspection

Week (MARCH 28, 2022)

The following information is requested to be provided on the first day of inspection. It is

requested that this information be provided on three sets of CDs (searchable, if possible).

1. Program Procedures:

a. Procedures for:

i. Administrative controls (such as allowed out of service times and

compensatory measures) for fire protection systems and components;

ii. Control of transient combustibles; and

iii. Control of hot work.

b. List of maintenance and surveillance testing procedures for alternative shutdown

capability and fire barriers, detectors, pumps, and suppression systems; and

c. List of maintenance procedures which routinely verify fuse breaker coordination in

accordance with the post-fire safe shutdown coordination analysis.

2. Design and Equipment Information (for only selected fire zone/area(s) and/or SSCs

to be determined during inspection preparation week):

a. Coordination calculations and/or justifications that verify fuse/breaker coordination for

SSCs that are fed off of the same electrical buses as components in the protected

safe shutdown train;

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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION

b. Copies of significant fire protection and post-fire safe shutdown related design

change package descriptions (including their associated 10 CFR 50.59

evaluations) and Generic Letter 86-10 (or adverse to safe shutdown) evaluations;

c. Gaseous suppression system pre-operational testing, if applicable, for selected fire

zones/areas;

d. Hydraulic calculations and supporting test data which demonstrate operability for

water suppression systems;

e. Alternating current (ac) coordination calculations for 4160 Vac down to 480 Vac

electrical systems; and

f. List of all fire protection or Appendix R calculations.

3. Assessment and Corrective Actions:

The three most recent fire protection Quality Assurance audits and/or fire protection

self-assessments.

4. Any updates to information previously provided.

5. Classic Fire Protection (for only selected fire zone/area(s) and/or SSCs to be

determined during inspection preparation week):

a. Copy of Fire Protection Program implementing procedures (e.g., administrative

controls, surveillance testing, and fire brigade);

b. Pre-fire plans for selected fire area(s); and

c. List of fire protection system design changes completed in the last 3 years.

6. Electrical (for only selected fire zone/area(s) and/or SSCs to be determined during

inspection preparation week):

a. Nuclear safety circuit coordination analysis for fuse and breaker coordination of safe

shutdown components;

b. Administrative or configuration control procedures that govern fuse replacement

(e.g., fuse control procedures);

c. Maintenance procedures that verify breaker over-current trip settings to ensure

coordination remains functional, for post-fire nuclear safety capability components;

d. Last surveillance demonstrating operability of those components operated from the

primary control stations;

e. Schematic or elementary diagrams for circuits (only for selected SSCs) to be

reviewed (C-size paper drawings);

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FIRE PROTECTION TEAM INSPECTION SUPPORTING DOCUMENTATION

f. Cable routing for components and equipment credited for post-fire nuclear safety

capability systems and components;

g. List of post-fire nuclear safety capability system and component design changes

completed, in the last 3 years; and

h. List of identified fire induced circuit failure analyses.

7. Operations:

a. List of procedures that implement Cold Shutdown Repairs (if applicable for selected

fire area);

b. For Cold Shutdown Repairs, provide the following:

i. Procedure for inventory and inspection (i.e., needed tools, material, etc.); and

ii. Most recent inspection and inventory results.

c. List of licensed operator Job Performance Measures for operator actions required to

achieve and maintain post-fire nuclear safety performance criteria (for selected SSCs

and fire area);

d. For Radio communications, provide the following:

i. Communications Plan for firefighting and post-fire safe shutdown manual

actions;

ii. Repeater locations;

iii. Cable routing for repeater power supply cables;

iv. Radio coverage test results; and

v. Radio Dead Spot locations in the plant.

e. Environmental and habitability evaluations for post-fire operator actions (temperature,

smoke, humidity, SCBAs, etc.).

8. Administrative Control, Oversight, and Corrective Action Programs:

a. Self-assessments, peer assessments, and audits of fire protection activities for the

last 3 years;

b. Self-assessments, peer assessments, and audits of post-fire nuclear safety capability

methodology for the last 3 years; and

c. List of fire event analysis reports for the last 3 years.

9. Any updates to information previously provided.

III. Information Requested to Be Provided Throughout the Inspection

1. Copies of any corrective action documents generated as a result of the inspection teams

questions or queries during this inspection.

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2. Copies of the list of questions submitted by the inspection team members and the

status/resolution of the information requested (provided daily during the inspection to

each inspection team member).

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