ML20079J097: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
Line 14: Line 14:
| page count = 9
| page count = 9
}}
}}
See also: [[see also::IR 05000341/2020011]]
See also: [[followed by::IR 05000341/2020011]]


=Text=
=Text=
{{#Wiki_filter:March 19, 2020
{{#Wiki_filter:March 19, 2020  
Mr. Peter Dietrich
Mr. Peter Dietrich  
Chief Nuclear Officer
Chief Nuclear Officer  
DTE Energy Company
DTE Energy Company  
Fermi 2 - 260 TAC
Fermi 2 - 260 TAC  
6400 North Dixie Highway
6400 North Dixie Highway  
Newport, MI 48166
Newport, MI 48166  
SUBJECT: FERMI POWER PLANT, UNIT 2 - NOTIFICATION OF NRC FIRE PROTECTION
            TEAM INSPECTION REQUEST FOR INFORMATION; INSPECTION REPORT
SUBJECT: FERMI POWER PLANT, UNIT 2 - NOTIFICATION OF NRC FIRE PROTECTION  
            NUMBERS 05000341/2020011
TEAM INSPECTION REQUEST FOR INFORMATION; INSPECTION REPORT  
Dear Mr. Dietrich,
NUMBERS 05000341/2020011  
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 (FPTI) at your Fermi Power Plant,
Dear Mr. Dietrich,  
Unit 2 beginning June 29, 2020. The inspection will be conducted in accordance with IP
71111.21N.05, Fire Protection Team Inspection (FPTI), dated June 12, 2019.
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
The inspection will verify that plant SSCs and/or administrative controls credited in the approved
Region III staff will conduct a Fire Protection Team Inspection (FPTI) at your Fermi Power Plant,  
Fire Protection Program (FPP) can perform their licensing basis function.
Unit 2 beginning June 29, 2020. The inspection will be conducted in accordance with IP  
The schedule for the inspection is as follows:
71111.21N.05, Fire Protection Team Inspection (FPTI), dated June 12, 2019.  
    *   Preparation week (R-III office): June 22 - 26, 2020
    *   Week 1 of onsite inspection: June 29 - July 3, 2020
The inspection will verify that plant SSCs and/or administrative controls credited in the approved  
    *   Week 2 of onsite inspection: July 13 - 17, 2020
Fire Protection Program (FPP) can perform their licensing basis function.  
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
The schedule for the inspection is as follows:  
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
Preparation week (R-III office): June 22 - 26, 2020  
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
Week 1 of onsite inspection: June 29 - July 3, 2020  
lead inspector via mail or electronically no later than June 12, 2020. The second group of
*  
requested documents consists of those items that the team will review, or need access to,
Week 2 of onsite inspection: July 13 - 17, 2020  
during the inspection. Please have this information available by the first day of the first onsite
inspection week June 29, 2020. The third group lists the information necessary to aid the
Experience has shown that the baseline fire protection team inspections are extremely resource  
inspection team in tracking issues identified as a result of the inspection. It is requested that
intensive, both for the NRC inspectors and the licensee staff. In order to minimize the  
this information be provided to the lead inspector as the information is generated during the
inspection impact on the site and to ensure a productive inspection for both organizations, we  
inspection. It is important that all of these documents are up to date and complete in order
have enclosed a request for documents needed for the inspection. These documents have  
to minimize the number of additional documents requested during the preparation and/or the
been divided into three groups. The first group lists information necessary to aid the inspection  
onsite portions of the inspection.
team in choosing specific focus areas for the inspection and to ensure that the inspection team  
The lead inspector for this inspection is Mr. Atif Shaikh. We understand that our regulatory
is adequately prepared for the inspection. It is requested that this information be provided to the  
contact for this inspection is Mr. Shane Gatter of your organization. If there are any questions
lead inspector via mail or electronically no later than June 12, 2020. The second group of  
about the inspection or the material requested, please contact the lead inspector at
requested documents consists of those items that the team will review, or need access to,  
630-829-9824 or via e-mail at Atif.Shaikh@nrc.gov.
during the inspection. Please have this information available by the first day of the first onsite  
inspection week June 29, 2020. 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 Mr. Atif Shaikh. We understand that our regulatory  
contact for this inspection is Mr. Shane Gatter of your organization. If there are any questions  
about the inspection or the material requested, please contact the lead inspector at  
630-829-9824 or via e-mail at Atif.Shaikh@nrc.gov.  


P. Dietrich                                 -2-
P. Dietrich  
This letter, its enclosure, and your response (if any) will be made available for public inspection
-2-  
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
This letter, its enclosure, and your response (if any) will be made available for public inspection  
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document  
Withholding.
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for  
                                              Sincerely,
Withholding.  
                                              /RA/
                                              Atif Shaikh, Senior Reactor Inspector
Sincerely,  
                                              Engineering Branch 3
                                              Division of Reactor Safety
/RA/  
Docket No:       50-341
License No:       NPF- 43
Enclosure:
Information Request for Fire Protection
Team Inspection
cc: Distribution via LISTSERV
Atif Shaikh, Senior Reactor Inspector  
Engineering Branch 3  
Division of Reactor Safety
Docket No:  
50-341  
License No:  
NPF- 43
Enclosure:  
Information Request for Fire Protection
  Team Inspection  
cc: Distribution via LISTSERV  


P. Dietrich                                 -3-
P. Dietrich  
Letter to Peter Dietrich from Atif Shaikh dated March 19, 2020.
-3-  
SUBJECT: FERMI POWER PLANT, UNIT 2 - NOTIFICATION OF NRC FIRE PROTECTION TEAM
Letter to Peter Dietrich from Atif Shaikh dated March 19, 2020.  
            INSPECTION REQUEST FOR INFORMATION; INSPECTION REPORT NUMBERS
            05000341/2020011
SUBJECT: FERMI POWER PLANT, UNIT 2 - NOTIFICATION OF NRC FIRE PROTECTION TEAM  
DISTRIBUTION:
INSPECTION REQUEST FOR INFORMATION; INSPECTION REPORT NUMBERS
Jessie Quichocho
05000341/2020011  
Omar Lopez-Santiago
RidsNrrDorlLpl3
DISTRIBUTION:  
RidsNrrPMFermi2 Resource
Jessie Quichocho  
RidsNrrDroIrib Resource
Omar Lopez-Santiago  
Darrell Roberts
RidsNrrDorlLpl3  
John Giessner
RidsNrrPMFermi2 Resource  
Jamnes Cameron
RidsNrrDroIrib Resource  
Allan Barker
Darrell Roberts  
DRPIII
John Giessner  
DRSIII
Jamnes Cameron  
ADAMS Accession Number: ML20079J097
Allan Barker  
OFFICE       RIII
DRPIII  
  NAME         AShaikh:mb via
DRSIII  
              email
  DATE         3/19/2020
                                        OFFICIAL RECORD COPY
ADAMS Accession Number: ML20079J097  
OFFICE  
RIII  
   
NAME  
AShaikh:mb via  
email  
   
DATE  
3/19/2020  
OFFICIAL RECORD COPY  


                    Fire Protection Team Inspection Supporting Documentation
Fire Protection Team Inspection Supporting Documentation
I.Information Requested Prior To the Inspection Preparation Week
Enclosure
  The following information is requested by June 12, 2020. If you have any questions
I.Information Requested Prior To the Inspection Preparation Week  
  regarding this request, please call the lead inspector as soon as possible. All information
The following information is requested by June 12, 2020. If you have any questions  
  should be sent to Atif Shaikh (e-mail address Atif.Shaikh@nrc.gov). Electronic media is
regarding this request, please call the lead inspector as soon as possible. All information  
  preferred. The preferred file format is a searchable pdf or Microsoft Excel file on a
should be sent to Atif Shaikh (e-mail address Atif.Shaikh@nrc.gov). Electronic media is  
  compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of use, if
preferred. The preferred file format is a searchable pdf or Microsoft Excel file on a  
  possible. Please provide three copies of each CD submitted (one for each inspector).
compact disk (CD). The CD should be indexed and hyper-linked to facilitate ease of use, if  
  1. One set of hard-copy documents for facility layout drawings which identify plant fire area
possible. Please provide three copies of each CD submitted (one for each inspector).  
      delineation; areas protected by automatic fire suppression and detection; and locations
      of fire protection equipment.
1. One set of hard-copy documents for facility layout drawings which identify plant fire area  
  2. Licensing Information:
delineation; areas protected by automatic fire suppression and detection; and locations  
      a.     All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)
of fire protection equipment.  
            applicable to fire protection (specifically including those SERs referenced by
            the plant fire protection license condition) and all licensing correspondence
2. Licensing Information:  
            referenced by the SERs;
      b.     All licensing correspondence associated with the comparison to Standard Review
a.  
            Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;
All Nuclear Regulatory Commission (NRC) Safety Evaluation Reports (SERs)  
      c.     Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and associated
applicable to fire protection (specifically including those SERs referenced by  
            licensing correspondence;
the plant fire protection license condition) and all licensing correspondence  
      d.     For pre-1979 plants, all licensing correspondence associated with those
referenced by the SERs;  
            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
b.  
            those fire protection features proposed or implemented by the licensee that have
All licensing correspondence associated with the comparison to Standard Review  
            been accepted by the NRC staff as satisfying the provisions of Appendix A to
Plan (NUREG-0800), Section 9.5.1 or equivalent for licensing purposes;  
            Branch Technical Position (BTP) 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
c.  
            protection features, which were accepted by the NRC staff in comprehensive fire
Exemptions from 10 CFR 50.48 and 10 CFR Part 50, Appendix R, and associated  
            protection SERs issued before Appendix A to BTP APCSB 9.5-1 was published in
licensing correspondence;  
            August 1976 (10 CFR 50.48(b)(1)(ii)); and
      e.     The final safety analysis report (FSAR) sections applicable to fire protection, FHA,
d.  
            and SSA in effect at the time of original licensing.
For pre-1979 plants, all licensing correspondence associated with those  
  3. Fire Protection Program:
sections of 10 CFR Part 50, Appendix R, that are not applicable to the plant under  
      a.     A listing of changes made to the FPP since the last triennial fire protection
10 CFR 50.48(b)(1). Specifically, the licensing correspondence associated with  
            inspection;
those fire protection features proposed or implemented by the licensee that have  
                                                                                        Enclosure
been accepted by the NRC staff as satisfying the provisions of Appendix A to  
Branch Technical Position (BTP) 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 BTP APCSB 9.5-1 was published in  
August 1976 (10 CFR 50.48(b)(1)(ii)); and  
e.  
The final safety analysis report (FSAR) sections applicable to fire protection, FHA,  
and SSA in effect at the time of original licensing.  
3. Fire Protection Program:  
a.  
A listing of changes made to the FPP since the last triennial fire protection  
inspection;  


                Fire Protection Team Inspection Supporting Documentation
Fire Protection Team Inspection Supporting Documentation
  b.   For pre-1979 plants, a listing of the protection methodologies identified under
2
        10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for fire
b.  
        zones/areas. That is, please specify whether 3-hour rated fire barriers;
For pre-1979 plants, a listing of the protection methodologies identified under  
        (Section III.G.2.a), 20 foot separation along with detection and suppression;
10 CFR Part 50, Appendix R, Section III.G used to achieve compliance for fire  
        (Section III.G.2.b), 1-hour rated fire barriers with detection and suppression;
zones/areas. That is, please specify whether 3-hour rated fire barriers;  
        (Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a
(Section III.G.2.a), 20 foot separation along with detection and suppression;  
        strategy for each selected fire zone/area;
(Section III.G.2.b), 1-hour rated fire barriers with detection and suppression;  
  c.     A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe-shutdown
(Section III.G.2.c), or alternative shutdown capability; (Section III.G.3) is used as a  
          evaluations);
strategy for each selected fire zone/area;  
  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
c.  
          (NFPA) code versions committed to (i.e., the NFPA Codes of Record);
A list of Generic Letter 86-10 evaluations (i.e., a list of adverse to safe-shutdown  
  e.     List of plant deviations from code commitments and associated evaluations;
evaluations);  
  f.     Fire Protection Program and/or Fire Protection Plan document;
  g.     (If available) Fire Probabilistic Risk Assessment (PRA) Summary Report or full
d.  
          PRA document (if summary document not available);
A list of applicable codes and standards related to the design of plant fire  
  h.     List of the top 25 highest fire CDF scenarios for each unit;
protection features. The list should include National Fire Protection Association  
  i.     List of Fire Areas/Zones ranked by contribution to CDF. i.e., ranking of highest to
(NFPA) code versions committed to (i.e., the NFPA Codes of Record);  
          lowest risk fire areas/zones;
  j.     List of the top 25 highest fire LERF scenarios for each unit; and
e.  
  k.     Risk ranking of operator actions and/or recovery actions from your site-specific
List of plant deviations from code commitments and associated evaluations;  
          PRA sorted by RAW and human reliability worksheets for these items.
4. Facility Information:
f.  
  a.     Piping and instrumentation (flow) diagrams showing the components used to
Fire Protection Program and/or Fire Protection Plan document;  
          achieve and maintain hot standby and cold shutdown for fires outside the control
          room, and those components used for those areas requiring alternative shutdown
g.  
          capability;
(If available) Fire Probabilistic Risk Assessment (PRA) Summary Report or full  
  b.     One-line schematic drawings of the electrical distribution system for 4160 Volts
PRA document (if summary document not available);  
          alternating current (Vac) down to 480Vac;
  c.     One-line schematic drawings of the electrical distribution system for 250 Volts
h.  
          direct current (Vdc) and 125Vdc systems as applicable;
List of the top 25 highest fire CDF scenarios for each unit;  
  d.     Logic diagrams showing the components used to achieve and maintain hot
          standby and cold shutdown; and
i.  
  e.     Safe shutdown cable routing database (requested electronically, such as on
List of Fire Areas/Zones ranked by contribution to CDF. i.e., ranking of highest to  
          compact disc, if available).
lowest risk fire areas/zones;  
                                                2
j.  
List of the top 25 highest fire LERF scenarios for each unit; and  
k.  
Risk ranking of operator actions and/or recovery actions from your site-specific  
PRA sorted by 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 480Vac;  
c.  
One-line schematic drawings of the electrical distribution system for 250 Volts  
direct current (Vdc) and 125Vdc 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).  


                  Fire Protection Team Inspection Supporting Documentation
Fire Protection Team Inspection Supporting Documentation
  5.   Operations Response for Fire Protection:
3
      a.   Plant operating procedures which specify the initial operations response to a fire
5.  
            alarm or annunciator.
Operations Response for Fire Protection:  
  6. Corrective Actions:
      a.   Listing of open and closed fire protection condition reports (i.e., problem
a.  
            identification forms and their resolution reports) since the date of the last triennial
Plant operating procedures which specify the initial operations response to a fire  
            fire protection inspection; and
alarm or annunciator.  
      b.   List of current fire impairments, including duration.
  7. General Information:
6. Corrective Actions:  
      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
a.  
            personnel; and
Listing of open and closed fire protection condition reports (i.e., problem  
      c.   A phone list for onsite licensee personnel.
identification forms and their resolution reports) since the date of the last triennial  
II. Information Requested to be Available on First Day of the FIRST ONSITE Inspection
fire protection inspection; and
  Week (JUNE 29, 2020)
  The following information is requested to be provided on the first day of inspection. It is
b.  
  requested that this information be provided on three sets of CDs (searchable, if possible).
List of current fire impairments, including duration.  
  1. Program Procedures:
      a.     Procedures for:
7. General Information:  
                    i. Administrative controls (such as allowed out of service times and
                        compensatory measures) for fire protection systems and components;
a.  
                    ii. Control of transient combustibles; and
A listing of abbreviations and/or designators for plant systems;
                  iii. Control of hot work.
      b.     List of maintenance and surveillance testing procedures for alternative shutdown
b.  
              capability and fire barriers, detectors, pumps, and suppression systems; and
Organization charts of site personnel down to the level of fire protection staff  
      c.     List of maintenance procedures which routinely verify fuse breaker coordination
personnel; and
              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
c.  
      to be determined during inspection preparation week):
A phone list for onsite licensee personnel.  
      a.     Coordination calculations and/or justifications that verify fuse/breaker
              coordination for SSCs that are fed off of the same electrical buses as
II. Information Requested to be Available on First Day of the FIRST ONSITE Inspection  
              components in the protected safe shutdown train;
Week (JUNE 29, 2020)  
                                                  3
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;  


                Fire Protection Team Inspection Supporting Documentation
Fire Protection Team Inspection Supporting Documentation
  b.     Copies of significant fire protection and post-fire safe shutdown related design
4
          change package descriptions (including their associated 10 CFR 50.59
b.  
          evaluations) and Generic Letter (GL) 86-10 (or adverse to safe shutdown)
Copies of significant fire protection and post-fire safe shutdown related design  
          evaluations;
change package descriptions (including their associated 10 CFR 50.59  
  c.     Gaseous suppression system pre-operational testing, if applicable, for selected
evaluations) and Generic Letter (GL) 86-10 (or adverse to safe shutdown)  
          fire zones/areas;
evaluations;  
  d.     Hydraulic calculations and supporting test data which demonstrate operability for
          water suppression systems;
c.  
  e.     Alternating current (ac) coordination calculations for 4160Vac down to 480Vac
Gaseous suppression system pre-operational testing, if applicable, for selected  
          electrical systems; and
fire zones/areas;  
  f.     List of all fire protection or Appendix R calculations.
3. Assessment and Corrective Actions:
d.  
  a.     The three most recent fire protection Quality Assurance (QA) audits and/or fire
Hydraulic calculations and supporting test data which demonstrate operability for  
          protection self-assessments.
water suppression systems;  
4. Any updates to information previously provided.
5. Classic Fire Protection (for only selected fire zone/area(s) and/or SSCs to be
e.  
  determined during inspection preparation week):
Alternating current (ac) coordination calculations for 4160Vac down to 480Vac  
  a. Copy of fire protection program implementing procedures (e.g., administrative
electrical systems; and  
      controls, surveillance testing, and fire brigade);
  b. Pre-fire plans for selected fire area(s); and
f.  
  c. List of fire protection system design changes completed in the last three years.
List of all fire protection or Appendix R calculations.  
6. Electrical (for only selected fire zone/area(s) and/or SSCs to be determined during
  inspection preparation week):
3. Assessment and Corrective Actions:  
  a. Nuclear safety circuit coordination analysis for fuse and breaker coordination of safe
      shutdown components;
a.  
  b. Administrative or configuration control procedures that govern fuse replacement
The three most recent fire protection Quality Assurance (QA) audits and/or fire  
      (e.g., fuse control procedures);
protection self-assessments.  
  c. Maintenance procedures that verify breaker over-current trip settings to ensure
      coordination remains functional, for post-fire nuclear safety capability components;
4. Any updates to information previously provided.  
  d. Last surveillance demonstrating operability of those components operated from the
      primary control stations;
5. Classic Fire Protection (for only selected fire zone/area(s) and/or SSCs to be  
                                              4
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 three 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;  


              Fire Protection Team Inspection Supporting Documentation
Fire Protection Team Inspection Supporting Documentation
  e. Schematic or elementary diagrams for circuits (only for selected SSCs) to be
5
      reviewed (C-size paper drawings);
e. Schematic or elementary diagrams for circuits (only for selected SSCs) to be  
  f. Cable routing for components and equipment credited for post-fire nuclear safety
reviewed (C-size paper drawings);  
      capability systems and components;
  g. List of post-fire nuclear safety capability system and component design changes
f. Cable routing for components and equipment credited for post-fire nuclear safety  
      completed, in the last three years; and
capability systems and components;  
  h. List of identified fire induced circuit failure analyses.
7. Operations:
g. List of post-fire nuclear safety capability system and component design changes  
  a. List of procedures that implement Cold Shutdown Repairs (if applicable for selected
completed, in the last three years; and  
      fire area);
  b. For Cold Shutdown Repairs, provide the following:
h. List of identified fire induced circuit failure analyses.  
        i. Procedure for inventory and inspection (i.e., needed tools, material, etc.); and
      ii. Most recent inspection and inventory results.
7. Operations:  
  c. List of licensed operator Job Performance Measures (JPMs) for operator actions
      required to achieve and maintain post-fire nuclear safety performance criteria (for
a. List of procedures that implement Cold Shutdown Repairs (if applicable for selected  
      selected SSCs and fire area);
fire area);  
  d. For Radio communications, provide the following:
        i. Communications Plan for firefighting and post-fire safe shutdown manual actions;
b. For Cold Shutdown Repairs, provide the following:  
        ii. Repeater locations;
      iii. Cable routing for repeater power supply cables;
i. Procedure for inventory and inspection (i.e., needed tools, material, etc.); and  
      iv.   Radio coverage test results; and
      v.   Radio Dead Spot locations in the plant.
ii. Most recent inspection and inventory results.  
  e. Environmental and habitability evaluations for post-fire operator actions
      (temperature, smoke, humidity, SCBAs, etc.).
c. List of licensed operator Job Performance Measures (JPMs) for operator actions  
8. Administrative Control, Oversight, and Corrective Action Programs:
required to achieve and maintain post-fire nuclear safety performance criteria (for  
  a. Self-assessments, peer assessments, and audits of fire protection activities for the
selected SSCs and fire area);  
      last three years;
  b. Self-assessments, peer assessments, and audits of post-fire nuclear safety
d. For Radio communications, provide the following:  
      capability methodology for the last three years; and
  c. List of fire event analysis reports for the last three years.
i. Communications Plan for firefighting and post-fire safe shutdown manual actions;  
9. Any updates to information previously provided.
ii. Repeater locations;  
                                              5
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 three years;  
b. Self-assessments, peer assessments, and audits of post-fire nuclear safety  
capability methodology for the last three years; and  
c. List of fire event analysis reports for the last three years.  
9. Any updates to information previously provided.  


                    Fire Protection Team Inspection Supporting Documentation
Fire Protection Team Inspection Supporting Documentation
III.Information Requested to Be Provided Throughout the Inspection
6
    1. Copies of any corrective action documents generated as a result of the inspection
III.Information Requested to Be Provided Throughout the Inspection  
        teams questions or queries during this inspection.
    2. Copies of the list of questions submitted by the inspection team members and the
1. Copies of any corrective action documents generated as a result of the inspection  
        status/resolution of the information requested (provided daily during the inspection to
teams questions or queries during this inspection.  
        each inspection team member).
                          PAPERWORK REDUCTION ACT STATEMENT
2. Copies of the list of questions submitted by the inspection team members and the  
This letter contains voluntary information collections that are subject to the Paperwork
status/resolution of the information requested (provided daily during the inspection to  
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)
each inspection team member).  
approved these information collections (approval number 3150-0011). The burden to the public
for these information collections is estimated to average 60 hours per response. Send
comments regarding this information collection to the Information Services Branch, Office of the
Chief Information Officer, Mail Stop: O-1F13, U.S. Nuclear Regulatory Commission,
PAPERWORK REDUCTION ACT STATEMENT  
Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk
This letter contains voluntary information collections that are subject to the Paperwork  
Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)  
Management and Budget, Washington, DC 20503.
approved these information collections (approval number 3150-0011). The burden to the public  
                                    Public Protection Notification
for these information collections is estimated to average 60 hours per response. Send  
The NRC may not conduct nor sponsor, and a person is not required to respond to, a request
comments regarding this information collection to the Information Services Branch, Office of the  
for information or an information collection requirement unless the requesting document
Chief Information Officer, Mail Stop: O-1F13, U.S. Nuclear Regulatory Commission,  
Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk  
Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of  
Management and Budget, Washington, DC 20503.  
Public Protection Notification  
The NRC may not conduct nor 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 OMB control number.
displays a currently valid OMB control number.
                                                  6
}}
}}

Revision as of 23:26, 14 December 2024

Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report Number 05000341/2020011
ML20079J097
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 03/19/2020
From: Atif Shaikh
Engineering Branch 3
To: Peter Dietrich
DTE Energy
References
IR 2020011
Download: ML20079J097 (9)


See also: IR 05000341/2020011

Text

March 19, 2020

Mr. Peter Dietrich

Chief Nuclear Officer

DTE Energy Company

Fermi 2 - 260 TAC

6400 North Dixie Highway

Newport, MI 48166

SUBJECT: FERMI POWER PLANT, UNIT 2 - NOTIFICATION OF NRC FIRE PROTECTION

TEAM INSPECTION REQUEST FOR INFORMATION; INSPECTION REPORT

NUMBERS 05000341/2020011

Dear Mr. Dietrich,

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 (FPTI) at your Fermi Power Plant,

Unit 2 beginning June 29, 2020. The inspection will be conducted in accordance with IP

71111.21N.05, Fire Protection Team Inspection (FPTI), dated June 12, 2019.

The inspection will verify that plant SSCs and/or administrative controls credited in the approved

Fire Protection Program (FPP) can perform their licensing basis function.

The schedule for the inspection is as follows:

Preparation week (R-III office): June 22 - 26, 2020

Week 1 of onsite inspection: June 29 - July 3, 2020

Week 2 of onsite inspection: July 13 - 17, 2020

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 June 12, 2020. 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 June 29, 2020. 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 Mr. Atif Shaikh. We understand that our regulatory

contact for this inspection is Mr. Shane Gatter of your organization. If there are any questions

about the inspection or the material requested, please contact the lead inspector at

630-829-9824 or via e-mail at Atif.Shaikh@nrc.gov.

P. Dietrich

-2-

This letter, its enclosure, and your response (if any) 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.

Sincerely,

/RA/

Atif Shaikh, Senior Reactor Inspector

Engineering Branch 3

Division of Reactor Safety

Docket No:

50-341

License No:

NPF- 43

Enclosure:

Information Request for Fire Protection

Team Inspection

cc: Distribution via LISTSERV

P. Dietrich

-3-

Letter to Peter Dietrich from Atif Shaikh dated March 19, 2020.

SUBJECT: FERMI POWER PLANT, UNIT 2 - NOTIFICATION OF NRC FIRE PROTECTION TEAM

INSPECTION REQUEST FOR INFORMATION; INSPECTION REPORT NUMBERS

05000341/2020011

DISTRIBUTION:

Jessie Quichocho

Omar Lopez-Santiago

RidsNrrDorlLpl3

RidsNrrPMFermi2 Resource

RidsNrrDroIrib Resource

Darrell Roberts

John Giessner

Jamnes Cameron

Allan Barker

DRPIII

DRSIII

ADAMS Accession Number: ML20079J097

OFFICE

RIII

NAME

AShaikh:mb via

email

DATE

3/19/2020

OFFICIAL RECORD COPY

Fire Protection Team Inspection Supporting Documentation

Enclosure

I.Information Requested Prior To the Inspection Preparation Week

The following information is requested by June 12, 2020. If you have any questions

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

should be sent to Atif Shaikh (e-mail address Atif.Shaikh@nrc.gov). Electronic media is

preferred. The preferred file format is a searchable pdf or Microsoft Excel file on a

compact disk (CD). The CD 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 10 CFR 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 (BTP) 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 BTP APCSB 9.5-1 was published in

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

e.

The final safety analysis report (FSAR) sections applicable to fire protection, FHA,

and SSA in effect at the time of original licensing.

3. Fire Protection Program:

a.

A listing of changes made to the FPP since the last triennial fire protection

inspection;

Fire Protection Team Inspection Supporting Documentation

2

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;

(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 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 LERF scenarios for each unit; and

k.

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

PRA sorted by 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 480Vac;

c.

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

direct current (Vdc) and 125Vdc 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).

Fire Protection Team Inspection Supporting Documentation

3

5.

Operations Response for Fire Protection:

a.

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 (JUNE 29, 2020)

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;

Fire Protection Team Inspection Supporting Documentation

4

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 (GL) 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 4160Vac down to 480Vac

electrical systems; and

f.

List of all fire protection or Appendix R calculations.

3. Assessment and Corrective Actions:

a.

The three most recent fire protection Quality Assurance (QA) 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 three 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;

Fire Protection Team Inspection Supporting Documentation

5

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

reviewed (C-size paper drawings);

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 three 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 (JPMs) 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 three years;

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

capability methodology for the last three years; and

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

9. Any updates to information previously provided.

Fire Protection Team Inspection Supporting Documentation

6

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.

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).

PAPERWORK REDUCTION ACT STATEMENT

This letter contains voluntary information collections that are subject to the Paperwork

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)

approved these information collections (approval number 3150-0011). The burden to the public

for these information collections is estimated to average 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per response. Send

comments regarding this information collection to the Information Services Branch, Office of the

Chief Information Officer, Mail Stop: O-1F13, U.S. Nuclear Regulatory Commission,

Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk

Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of

Management and Budget, Washington, DC 20503.

Public Protection Notification

The NRC may not conduct nor 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 OMB control number.