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{{#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  
                                            February 18, 2016
Mano Nazar
February 18, 2016  
President and Chief Nuclear Officer
Nuclear Division
Mano Nazar  
NextEra Energy
President and Chief Nuclear Officer  
P.O. Box 14000
Nuclear Division  
Juno Beach, FL 33408-0420
NextEra Energy  
SUBJECT: SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A
P.O. Box 14000  
              TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
Juno Beach, FL 33408-0420  
              REPORT NOS. 05000335/2016011 AND 05000389/2016011
Dear Mr. Nazar:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
SUBJECT: SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A
staff will conduct a triennial fire protection baseline inspection at St. Lucie Nuclear Plant,
Units 1 and 2. The inspection team will be led by David Jones, a Senior Reactor Inspector from
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION  
the NRC Region II Office. The team will be composed of personnel from the NRC Region II
Office. The inspection will be conducted in accordance with IP 71111.05T, the NRC's baseline
REPORT NOS. 05000335/2016011 AND 05000389/2016011  
fire protection inspection procedure, dated January 31, 2013.
Dear Mr. Nazar:  
On February 8, 2016, during a telephone conversation between Mr. E. Katzman (Licensing) and
Mr. D. Jones of our respective staffs, arrangements for an information gathering onsite visit and
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)  
a two-week onsite inspection were confirmed. The schedule for the inspection is as follows:
staff will conduct a triennial fire protection baseline inspection at St. Lucie Nuclear Plant,
                  *   Information Gathering Visit:       May 02 - 05, 2016
Units 1 and 2. The inspection team will be led by David Jones, a Senior Reactor Inspector from  
                  *   Week 1 of onsite inspection:       June 06 - 10, 2016
the NRC Region II Office. The team will be composed of personnel from the NRC Region II  
                  *   Week 2 of onsite inspection:       June 20 - 24, 2016
Office. The inspection will be conducted in accordance with IP 71111.05T, the NRC's baseline  
The purposes of the information gathering visit are to obtain information and documentation
fire protection inspection procedure, dated January 31, 2013.  
needed to support the inspection, to become familiar with the fire protection program, fire
protection features, post-fire safe shutdown capabilities, plant layout, mitigating strategies to
On February 8, 2016, during a telephone conversation between Mr. E. Katzman (Licensing) and  
address Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2); and, as necessary,
Mr. D. Jones of our respective staffs, arrangements for an information gathering onsite visit and  
obtain plant specific site access training and badging for unescorted site access.
a two-week onsite inspection were confirmed. The schedule for the inspection is as follows:  
An initial list of the documents the team will review during the conduct of the inspection is listed
in Enclosures 1 and 2. The team leader will contact you with any additional specific document
*  
requests prior to the information gathering visit.
Information Gathering Visit:  
During the information gathering visit, the team will also discuss the following inspection support
May 02 - 05, 2016  
administrative details: office space size and location; specific documents requested to be made
*  
available to the team in their office spaces; arrangements for reactor site access (including
Week 1 of onsite inspection:  
radiation protection training, security, safety and fitness for duty requirements); and the
June 06 - 10, 2016  
availability of knowledgeable plant staff and licensing organization personnel to serve as points
*  
Week 2 of onsite inspection:  
June 20 - 24, 2016  
The purposes of the information gathering visit are to obtain information and documentation  
needed to support the inspection, to become familiar with the fire protection program, fire  
protection features, post-fire safe shutdown capabilities, plant layout, mitigating strategies to  
address Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2); and, as necessary,  
obtain plant specific site access training and badging for unescorted site access.  
An initial list of the documents the team will review during the conduct of the inspection is listed  
in Enclosures 1 and 2. The team leader will contact you with any additional specific document  
requests prior to the information gathering visit.  
During the information gathering visit, the team will also discuss the following inspection support  
administrative details: office space size and location; specific documents requested to be made  
available to the team in their office spaces; arrangements for reactor site access (including  
radiation protection training, security, safety and fitness for duty requirements); and the  
availability of knowledgeable plant staff and licensing organization personnel to serve as points  
of contact during the inspection.
of contact during the inspection.


M. Nazar                                       2
M. Nazar  
We request that during the on-site inspection weeks that you ensure that be readily accessible to
2  
the team for their review copies of analyses, evaluations or documentation regarding the
implementation and maintenance of the station fire protection program, including post-fire safe
We request that during the on-site inspection weeks that you ensure that be readily accessible to  
shutdown capability. Of specific interest for the fire protection portion of the inspection are
the team for their review copies of analyses, evaluations or documentation regarding the  
documents which establish that your fire protection program satisfies NRC regulatory
implementation and maintenance of the station fire protection program, including post-fire safe  
requirements and conforms to applicable NRC and industry fire protection guidance (i.e., fire
shutdown capability. Of specific interest for the fire protection portion of the inspection are  
protection compliance assessment documents). For the 10 CFR 50.54(hh)(2) portion of the
documents which establish that your fire protection program satisfies NRC regulatory  
inspection, those documents implementing your mitigating strategies and demonstrating the
requirements and conforms to applicable NRC and industry fire protection guidance (i.e., fire  
management of your commitments for the strategies are of specific interest. Also, personnel
protection compliance assessment documents). For the 10 CFR 50.54(hh)(2) portion of the  
should be available at the site during the inspection that are knowledgeable regarding plant
inspection, those documents implementing your mitigating strategies and demonstrating the  
systems required to achieve and maintain safe shutdown conditions from inside and outside the
management of your commitments for the strategies are of specific interest. Also, personnel  
control room; including the electrical aspects of the relevant post-fire safe shutdown analyses,
should be available at the site during the inspection that are knowledgeable regarding plant  
reactor plant fire protection systems and features, and the station fire protection program and its
systems required to achieve and maintain safe shutdown conditions from inside and outside the  
implementation.
control room; including the electrical aspects of the relevant post-fire safe shutdown analyses,  
This letter does not contain new or amended information collection requirements subject to the
reactor plant fire protection systems and features, and the station fire protection program and its  
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
implementation.  
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
This letter does not contain new or amended information collection requirements subject to the  
request for information or an information collection requirement unless the requesting document
Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection  
displays a currently valid Office of Management and Budget control number.
requirements were approved by the Office of Management and Budget, under control number  
In accordance with 10 CFR 2.390 of the NRC Rules and Practices, a copy of this letter and its
3150 0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a  
enclosures will be available electronically for public inspection in the NRC Public Document
request for information or an information collection requirement unless the requesting document  
Room or from the Publically Available Records (PARS) component of NRCs document
displays a currently valid Office of Management and Budget control number.  
system(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-
rm/adams.hmtl (the Public Electronic Reading Room).
In accordance with 10 CFR 2.390 of the NRC Rules and Practices, a copy of this letter and its  
Your cooperation and support during this inspection will be appreciated. If you have questions
enclosures will be available electronically for public inspection in the NRC Public Document  
concerning this inspection, or the inspection team's information or logistical needs, please
Room or from the Publically Available Records (PARS) component of NRCs document  
contact David Jones, the team leader, in the Region II Office at 404-997-4631 or me at
system(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-  
404-997-4521.
rm/adams.hmtl (the Public Electronic Reading Room).  
                                                Sincerely,
                                                /RA/
Your cooperation and support during this inspection will be appreciated. If you have questions  
                                                Scott M. Shaeffer, Chief
concerning this inspection, or the inspection team's information or logistical needs, please  
                                                Engineering Branch 2
contact David Jones, the team leader, in the Region II Office at 404-997-4631 or me at
                                                Division of Reactor Safety
404-997-4521.  
Docket Nos.: 50-335; 50-389
License Nos.: DPR-67 and NPF-16
Sincerely,  
Enclosures:
1. Triennial Fire Protection Inspection Supporting Documentation
2. Mitigating Strategies Supporting Documentation
cc: Distribution via Listserv
/RA/  
Scott M. Shaeffer, Chief  
Engineering Branch 2  
Division of Reactor Safety  
Docket Nos.: 50-335; 50-389  
License Nos.: DPR-67 and NPF-16  
Enclosures:  
1. Triennial Fire Protection Inspection Supporting Documentation  
2. Mitigating Strategies Supporting Documentation
cc: Distribution via Listserv  




_________________________                       SUNSI REVIEW COMPLETE   FORM 665 ATTACHED
_________________________  
OFFICE               RII:DRS         RII:DRS
  SIGNATURE           DAJ2           SMS
SUNSI REVIEW COMPLETE  
  NAME                 DJONES         SSHAEFFER
FORM 665 ATTACHED  
  DATE                     2/18/2016       2/18/2016       3/ /2016       3/ /2016       3/ /2016     3/ /2016     3/ /2016
OFFICE  
E-MAIL COPY?           YES    NO     YES     NO     YES     NO    YES     NO    YES     NO   YES   NO    YES    NO
RII:DRS  
       
RII:DRS  
Letter to Mano Nazar from Scott M Shaeffer dated February 18, 2016.
   
SUBJECT: SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A
            TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
            REPORT NOS. 05000335/2016011 AND 05000389/2016011
DISTRIBUTION:
RIDSNRRDIRS PUBLIC
SIGNATURE  
RidsNrrPMSt. Lucie Resource
DAJ2  
SMS  
   
NAME  
DJONES  
SSHAEFFER  
   
DATE  
2/18/2016  
2/18/2016  
3/   /2016  
3/   /2016  
3/   /2016  
3/   /2016  
3/   /2016  
E-MAIL COPY?  
     YES  
NO       YES  
NO     
  YES  
NO     
  YES  
NO       YES  
NO     
  YES  
NO      
  YES
NO   


                  Triennial Fire Protection Inspection Supporting Documentation
The documents and information requested below should generally be made available to the
Letter to Mano Nazar from Scott M Shaeffer dated February 18, 2016.  
inspection team during the on-site information gathering visit for the team's use both on-site and
off-site during the inspection. Electronic format is the preferred media, except where specifically
SUBJECT: SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A
noted, if readily available (The preferred file format is searchable .pdf files). If electronic media
is made available via an internet based remote document management system, then the remote
TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION
document access must allow inspectors to download, save, and print the documents in the
NRC's regional office. Electronic media on compact disc or paper records (hard copy) are
REPORT NOS. 05000335/2016011 AND 05000389/2016011
acceptable. At the end of the inspection, the documents in the team's possession will not be
retained.
DISTRIBUTION:  
Approximately three weeks before the on-site information gathering visit, the following
RIDSNRRDIRS PUBLIC
documents should be made available to the team leader for review in the regional office:
RidsNrrPMSt. Lucie Resource
              *  Post-fire Safe Shutdown or Alternative Shutdown Analysis (request A.1)
              *  Fire Hazards Analysis (request A.2)
              *  Individual Plant Examination for External Events (Fire Chapter ONLY)
                    (request A.3)
Based on review of the above three documents, the team leader will identify a preliminary list of
fire areas being considered for inspection prior to the on-site information gathering visit. During
the information gathering visit, or shortly thereafter, the fire areas selected for inspection will be
determined.
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
of the listed documents. It is recognized that some documents listed below may not be available
for your plant. In addition, the document titles listed below are based on typical industry
document names; your plant specific document titles may vary.
A.    DESIGN AND LICENSING BASIS DOCUMENTS
      A.1  Post-fire Safe Shutdown or Alternative Shutdown Analysis.
      A.2  Fire Hazards Analysis.
      A.3  Individual Plant Examination for External Events (IPEEE) (Fire Chapter
            ONLY), including:
            * Results of any post-IPEEE reviews; and
            * LIST of actions taken or plant modifications performed in response to the
                IPEEE results.
      A.4  Fire Protection Program and/or Fire Protection Plan.
      A.5  LIST of post-fire safe shutdown or alternative shutdown systems (i.e., safe
            shutdown equipment list).
      A.6  Fire Protection System Design Basis Document.
                                                                                            Enclosure 1


                                              2
  A.7 Post-fire Safe Shutdown or Alternative Shutdown Design Basis Document.
  A.8 LIST of applicable NFPA codes and standards and issuance dates (i.e., codes
Enclosure 1
        of record).
Triennial Fire Protection Inspection Supporting Documentation
  A.9 LIST of deviations from NFPA codes of record.
   
  A.10 NFPA Compliance Review Report.
The documents and information requested below should generally be made available to the
  A.11 Report or evaluation that compares the fire protection program to the NRC
inspection team during the on-site information gathering visit for the team's use both on-site and
        Branch Technical Position (BTP) 9.5-1 Appendix A.
off-site during the inspectionElectronic format is the preferred media, except where specifically
  A.12 Electronic copy of licensee submittals and NRC safety evaluation reports that
noted, if readily available (The preferred file format is searchable .pdf files). If electronic media
        are specifically listed in the facility operating license for the approved fire
is made available via an internet based remote document management system, then the remote
        protection program.
document access must allow inspectors to download, save, and print the documents in the
  A.13 NRC Safety Evaluation Reports for fire protection program and post-fire
NRC's regional office.  Electronic media on compact disc or paper records (hard copy) are
        safe shutdown or alternative shutdown features.
acceptableAt the end of the inspection, the documents in the team's possession will not be
  A.14 NRC approved exemptions for plant fire protection and post-fire safe shutdown
retained.  
        or alternative shutdown features.
  A.15 Exemption requests submitted but not yet approved for plant fire protection and
Approximately three weeks before the on-site information gathering visit, the following
        post- fire safe shutdown or alternative shutdown features.
documents should be made available to the team leader for review in the regional office:
  A.16 Facility Operating License (electronic format only).
  A.17 Technical Specifications (electronic format only).
*
  A.18 Technical Requirements Manual (electronic format only).
Post-fire Safe Shutdown or Alternative Shutdown Analysis (request A.1)
  A.19 Updated Final Safety Analysis Report (electronic format only).
*
B. GENERAL PLANT DESIGN DOCUMENTS
Fire Hazards Analysis (request A.2)
  B.1  Piping and instrumentation diagrams (P&IDs) and legend list for post-fire safe
*
        shutdown or alternative shutdown systems (C-size paper drawings and
Individual Plant Examination for External Events (Fire Chapter ONLY)
        electronic copy).
  (request A.3)
  B.2 P&IDs and legend list for fire protection systems, including fire water supply,
        water suppression sprinklers & deluge, and CO2 and Halon systems (C-size
Based on review of the above three documents, the team leader will identify a preliminary list of  
        paper drawings and electronic copy).
fire areas being considered for inspection prior to the on-site information gathering visit.  During
  B.3 AC and DC electrical system single line diagrams, from off-site power down to the
the information gathering visit, or shortly thereafter, the fire areas selected for inspection will be
        highest safety-related bus level (typically 4kV, EDG bus) (C-size paper drawings
determined.
        and electronic copy ).
  B.4  Single line diagrams for motor control centers (MCCs) that supply post-fire safe
This document request is based on typical documents that a generic plant might have. As such,
        shutdown or alternative shutdown loads (only for selected fire areas) (C-size
this generic document request is not meant to imply that any specific plant is required to have all
        paper drawings and electronic copy).
of the listed documents. It is recognized that some documents listed below may not be available
                                                                                          .
for your plant.  In addition, the document titles listed below are based on typical industry
document names; your plant specific document titles may vary.  
A.  
DESIGN AND LICENSING BASIS DOCUMENTS
A.1
Post-fire Safe Shutdown or Alternative Shutdown Analysis.  
A.2
Fire Hazards Analysis.  
A.3
Individual Plant Examination for External Events (IPEEE) (Fire Chapter
ONLY), including:
* Results of any post-IPEEE reviews; and
* LIST of actions taken or plant modifications performed in response to the
IPEEE results.  
   
A.4
Fire Protection Program and/or Fire Protection Plan.  
   
A.5
LIST of post-fire safe shutdown or alternative shutdown systems (i.e., safe
shutdown equipment list).
A.6
Fire Protection System Design Basis Document.


                                            3
2
  B.5  Equipment location drawings which identify the physical plant locations of post-
        fire safe shutdown or alternative shutdown equipment (C-size paper drawings
.
        and electronic copy).
A.7
  B.6 Plant layout drawings which identify: (C-size paper drawings and electronic copy)
Post-fire Safe Shutdown or Alternative Shutdown Design Basis Document.  
        *    Plant fire area boundaries;
   
        *    Combustible control zone drawings;
A.8
        *    Areas protected by automatic fire suppression and detection; and
LIST of applicable NFPA codes and standards and issuance dates (i.e., codes
        *    Locations of fire protection equipment.
of record).
C. CLASSICAL FIRE PROTECTION
  C.1 Fire protection program implementing procedures (e.g., administrative
A.9
        controls, surveillance testing, fire brigade).
LIST of deviations from NFPA codes of record.  
  C.2  LIST of calculations and engineering analyses, studies, or evaluations for the
        fire protection system, including the fire water system.
A.10 NFPA Compliance Review Report.  
  C.3  Hydraulic calculation or analysis for fire protection water system in the selected
   
        fire areas.
A.11 Report or evaluation that compares the fire protection program to the NRC
  C.4  Last two completed surveillance's records of fire protection features in the
Branch Technical Position (BTP) 9.5-1 Appendix A.  
        selected fire areas (detection, suppression, damper inspections, damper tests,
        penetration inspections, barrier inspections, etc.).
A.12 Electronic copy of licensee submittals and NRC safety evaluation reports that
  C.5 LIST of routine tests, surveillances, and preventive maintenance on fire
are specifically listed in the facility operating license for the approved fire
        pumps, including pump controllers and batteries.
protection program.
  C.6 Last two completed annual fire pump pressure and flow tests.
  C.7  Last two completed monthly and/or quarterly fire pump tests.
A.13 NRC Safety Evaluation Reports for fire protection program and post-fire  
  C.8 Last two completed fire loop flow tests and loop flushes.
safe shutdown or alternative shutdown features.  
  C.9 CO2 and Halon initial discharge testing or calculation that determined appropriate
        concentrations and soak or hold times can be achieved (only for selected fire
A.14 NRC approved exemptions for plant fire protection and post-fire safe shutdown
        areas).
or alternative shutdown features.  
  C.10 Last five hot work permits (at power).
  C.11 Last five transient combustible permits (at power).
A.15 Exemption requests submitted but not yet approved for plant fire protection and
                                                                                          .
post- fire safe shutdown or alternative shutdown features.
A.16 Facility Operating License (electronic format only).
A.17 Technical Specifications (electronic format only).  
A.18 Technical Requirements Manual (electronic format only).  
   
A.19 Updated Final Safety Analysis Report (electronic format only).  
B.  
GENERAL PLANT DESIGN DOCUMENTS
   
B.1
Piping and instrumentation diagrams (P&IDs) and legend list for post-fire safe
shutdown or alternative shutdown systems (C-size paper drawings and  
electronic copy).  
B.2
P&IDs and legend list for fire protection systems, including fire water supply,
water suppression sprinklers & deluge, and CO2 and Halon systems (C-size
paper drawings and electronic copy).  
   
B.3
AC and DC electrical system single line diagrams, from off-site power down to the
highest safety-related bus level (typically 4kV, EDG bus) (C-size paper drawings
and electronic copy ).  
   
B.4
Single line diagrams for motor control centers (MCCs) that supply post-fire safe
shutdown or alternative shutdown loads (only for selected fire areas) (C-size
paper drawings and electronic copy).  


                                                4
3
C.12 For Fire Brigade Drills, provide the following:
    * Last drill critique for a drill with off-site fire department support;
.
    * Summary of any unsatisfactory drill performance items for last three years; and
B.5
    * Last unannounced drill critique by a qualified individual independent of the
Equipment location drawings which identify the physical plant locations of post-
        licensee's staff.
fire safe shutdown or alternative shutdown equipment (C-size paper drawings
C.13 For fire brigade equipment provide the following:
and electronic copy).
    *    Procedure for inventory and inspection; and
    *    Most recent inspection and inventory results.
B.6
C.14 Fire Brigade Medical Evaluations and Qualifications, including self-contained
Plant layout drawings which identify: (C-size paper drawings and electronic copy)
    breathing apparatus (SCBA) and training lesson plans.
C.15 Electronic copy of the mutual aid agreement for the first-due local fire department
*  
    that is currently in effect.
Plant fire area boundaries;  
C.16 Flooding analysis for selected fire areas which demonstrates:
*  
    * a fire water pipe break in the selected fire areas, wont affect safe shutdown (SSD)
Combustible control zone drawings;  
      capability for equipment in the selected fire areas;
*  
    * a fire water pipe break in an adjacent fire area, wont affect SSD capability for
Areas protected by automatic fire suppression and detection; and
      equipment in the selected fire areas;
*
    * hydrostatic rating of any floor penetration seals installed within the fire areas that
Locations of fire protection equipment.
      are credited with keeping water from leaking into fire areas below.
C.17 Pre-fire plans for the selected fire areas and their adjacent fire areas.
C. CLASSICAL FIRE PROTECTION
C.18 For Emergency Lighting Units (ELU), provide the following:
    *    LIST of Preventive Maintenance tasks, frequencies, and bases;
C.1
    *    Most recently performed monthly or quarterly functional test;
Fire protection program implementing procedures (e.g., administrative
    *    Most recently performed battery discharge performance test; if applicable
controls, surveillance testing, fire brigade).  
    *    ELU battery loading analysis;
    *    vendor manual(s);
C.2
    *    results of black-out testing (if performed);
LIST of calculations and engineering analyses, studies, or evaluations for the  
    *    Maintenance Rule program information related to the ELU, if applicable; and
fire protection system, including the fire water system.
    *    Compensatory measures taken when ELU are out of service.
C.19 Impairment Log (for period of 3 months before the start of inspection), for fire
C.3
    protection features that are out of service.
Hydraulic calculation or analysis for fire protection water system in the selected  
C.20 LIST of Fire Protection screening reviews since the last inspection for recent design
fire areas.
    changes, modifications, or temporary modifications (e.g., a Generic Letter 86-10
    review that screened out).
C.4
C.21 LIST of fire protection system design changes completed in the last three years
Last two completed surveillance's records of fire protection features in the  
    (including their associated 10 CFR 50.59 and Generic Letter 86-10 evaluations).
selected fire areas (detection, suppression, damper inspections, damper tests,
                                                                                              .
penetration inspections, barrier inspections, etc.).
C.5
LIST of routine tests, surveillances, and preventive maintenance on fire  
pumps, including pump controllers and batteries.  
C.6
Last two completed annual fire pump pressure and flow tests.  
C.7
Last two completed monthly and/or quarterly fire pump tests.
C.8
Last two completed fire loop flow tests and loop flushes.
C.9
CO2 and Halon initial discharge testing or calculation that determined appropriate
concentrations and soak or hold times can be achieved (only for selected fire  
areas).  
C.10 Last five hot work permits (at power).  
C.11 Last five transient combustible permits (at power).  


                                            5
4
  C.22 LIST of penetration seal work, re-work, or installation activities, in the last three years.
  C.23 LIST of fire wrap work, re-work, or installation activities, in the last three years.
.
  C.24 Fire protection system health reports for the two most recent years.
  C.25 Fire protection program health report for the two most recent years.
C.12 For Fire Brigade Drills, provide the following:
  C.26 Emergency lighting system health reports for the two most recent years.
  C.27 Licensee evaluation of industry operating experience, related to the Fire Protection
* Last drill critique for a drill with off-site fire department support;
        Program for the three most recent years.
*
D. ELECTRICAL
Summary of any unsatisfactory drill performance items for last three years; and
  D.1  Identify whether the cables in the selected fire areas are predominantly Thermoset or
* Last unannounced drill critique by a qualified individual independent of the
        Thermoplastic. Specifically identify any Thermoplastic cable in the selected fire
licensee's staff.  
        areas.
  D.2  Breaker and fuse coordination calculation for post-fire safe shutdown or alternative
C.13 For fire brigade equipment provide the following:
        shutdown equipment (only for selected fire areas).
  D.3 Administrative or configuration control procedures that govern fuse replacement (e.g.,
*
        fuse control procedures).
Procedure for inventory and inspection; and
  D.4 Maintenance procedures that verify breaker over-current trip settings to ensure
*
        coordination remains functional, for post-fire safe shutdown or alternative shutdown
Most recent inspection and inventory results.  
        equipment.
  D.5 Electrical system health reports for the two most recent years.
C.14 Fire Brigade Medical Evaluations and Qualifications, including self-contained
  D.6  Last completed preventive maintenance of those components as tested from the safe
breathing apparatus (SCBA) and training lesson plans.  
        shutdown or alternative shutdown panel.
  D.7  Schematic or elementary diagrams for circuits to be reviewed, as requested by
C.15 Electronic copy of the mutual aid agreement for the first-due local fire department
        inspector (C-size paper drawings and electronic copy).
that is currently in effect.  
  D.8 Cable routing for components and equipment credited for post-fire safe shutdown or
        alternative shutdown (only for selected fire areas).
C.16 Flooding analysis for selected fire areas which demonstrates:
  D.9  LIST of post-fire safe shutdown or alternative shutdown design changes completed,
        since the last inspection.
* a fire water pipe break in the selected fire areas, wont affect safe shutdown (SSD)
E. SPURIOUS FIRE INDUCED CIRCUIT FAULTS
capability for equipment in the selected fire areas;
  E.1  LIST of identified fire induced circuit failure configurations (only for selected fire
* a fire water pipe break in an adjacent fire area, wont affect SSD capability for
        areas).
equipment in the selected fire areas;
  E.2  Multiple Spurious Operation (MSO) Expert Panel Report.
* hydrostatic rating of any floor penetration seals installed within the fire areas that
                                                                                                    .
are credited with keeping water from leaking into fire areas below.  
C.17 Pre-fire plans for the selected fire areas and their adjacent fire areas.  
C.18 For Emergency Lighting Units (ELU), provide the following:
   
*
LIST of Preventive Maintenance tasks, frequencies, and bases;
*
Most recently performed monthly or quarterly functional test;
*
Most recently performed battery discharge performance test; if applicable
*
ELU battery loading analysis;
*
vendor manual(s);
*
results of black-out testing (if performed);
*
Maintenance Rule program information related to the ELU, if applicable; and
*
Compensatory measures taken when ELU are out of service.  
   
C.19 Impairment Log (for period of 3 months before the start of inspection), for fire  
protection features that are out of service.  
   
C.20 LIST of Fire Protection screening reviews since the last inspection for recent design
changes, modifications, or temporary modifications (e.g., a Generic Letter 86-10
review that screened out).  
   
C.21 LIST of fire protection system design changes completed in the last three years
(including their associated 10 CFR 50.59 and Generic Letter 86-10 evaluations).  


                                            6
5
  E.3 Corrective actions for fire-induced circuit failures, both single and multiple spurious
        actuations for the selected fire areas.
.  
F. OPERATIONS
  F.LIST of calculations and engineering analyses, studies, or evaluations for the safe
   
        shutdown or alternative shutdown methodology.
C.22 LIST of penetration seal work, re-work, or installation activities, in the last three years.  
  F.2 LIST of licensed operator Job Performance Measures (JPMs) for operator manual
        actions required by post-fire safe shutdown or alternative shutdown.
C.23 LIST of fire wrap work, re-work, or installation activities, in the last three years.
  F.3 LIST of non-licensed operator training associated with post-fire safe shutdown or
        alternative shutdown manual actions which would be performed by a non-licensed
C.24 Fire protection system health reports for the two most recent years.
        operator (including JPMs, in-field training walkdowns, simulations, or initial
        qualification).
C.25 Fire protection program health report for the two most recent years.  
  F.4 LIST of lesson plans for post-fire safe shutdown or alternative shutdown training for
        licensed and non-licensed operators.
C.26 Emergency lighting system health reports for the two most recent years.  
  F.5  For operator manual actions (OMAs) provide the following:
   
        *  Manual Action Feasibility Study;
C.27 Licensee evaluation of industry operating experience, related to the Fire Protection
        *  Operator Time Critical Action Program;
Program for the three most recent years.
        *  Time lines for time-critical OMAs; and
        *  Time line validations.
D. ELECTRICAL
        *  Environmental and habitability evaluations for post-fire operator manual actions
            (temperature, smoke, humidity, SCBAs, etc.).
D.1
  F.6 Thermal hydraulic calculation or analysis that determines the time requirements for
Identify whether the cables in the selected fire areas are predominantly Thermoset or  
        time-critical manual operator actions.
Thermoplastic. Specifically identify any Thermoplastic cable in the selected fire
  F.7  Operating procedures for post-fire safe shutdown from the control room with a
areas.  
        postulated fire in the selected fire areas.
   
  F.8  Operating procedures for post-fire safe shutdown or alternative shutdown from
D.2
        outside the control room.
Breaker and fuse coordination calculation for post-fire safe shutdown or alternative
  F.9 For safe shutdown equipment and tools, provide the following:
shutdown equipment (only for selected fire areas).
        *  Procedure for inventory and inspection; and
        *  Most recent inspection and inventory results.
D.3
  F.10 LIST of procedures that implement Cold Shutdown Repairs.
Administrative or configuration control procedures that govern fuse replacement (e.g.,  
  F.11 For Cold Shutdown Repairs, provide the following:
fuse control procedures).  
        *  Procedure for inventory and inspection (i.e., needed tools, material, etc.); and
        *  Most recent inspection and inventory results.
D.4  
                                                                                                .
Maintenance procedures that verify breaker over-current trip settings to ensure
coordination remains functional, for post-fire safe shutdown or alternative shutdown  
equipment.  
D.5  
Electrical system health reports for the two most recent years.
   
D.6
Last completed preventive maintenance of those components as tested from the safe
shutdown or alternative shutdown panel.
D.7
Schematic or elementary diagrams for circuits to be reviewed, as requested by
inspector (C-size paper drawings and electronic copy).  
   
D.8
Cable routing for components and equipment credited for post-fire safe shutdown or
alternative shutdown (only for selected fire areas).  
D.9
LIST of post-fire safe shutdown or alternative shutdown design changes completed,
since the last inspection.  
E.  
SPURIOUS FIRE INDUCED CIRCUIT FAULTS
   
E.1
LIST of identified fire induced circuit failure configurations (only for selected fire
areas).  
E.2
Multiple Spurious Operation (MSO) Expert Panel Report.  


                                              7
6
  F.12 Calculation or analysis that demonstrates pressurizer level will remain within the
        indicating range for a PWR, or reactor water level will remain above the top of active
.
        fuel for a BWR, at the safe shutdown or alternative shutdown panel, in accordance
        with the requirements of 10 CFR 50 Appendix R III.L performance goals.
  F.13 For Radio communications, provide the following:
E.3
        *    Communications Plan for fire fighting and post-fire safe shutdown manual actions;
Corrective actions for fire-induced circuit failures, both single and multiple spurious
        *   Repeater locations;
actuations for the selected fire areas.
        *   Cable routing for repeater power supply cables;
        *   Radio coverage test results; and
F.
        *   Radio Dead Spot locations in the plant.
OPERATIONS
  F.14 NRC approved exemption requests for operator manual actions for
        10 CFR 50 Appendix R III.G.2 fire areas.
F.1
  F.15 Exemption requests submitted but not yet approved, for operator manual actions for
LIST of calculations and engineering analyses, studies, or evaluations for the safe
        10 CFR 50 Appendix R III.G.2 fire areas.
shutdown or alternative shutdown methodology.
G. ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION PROGRAMS
  G.1  Corrective actions for fire-induced circuit failures (including but not limited to NRC IN
F.2
        92-18), both single and multiple spurious actuations (only for selected fire areas).
LIST of licensed operator Job Performance Measures (JPMs) for operator manual
  G.2  Corrective actions associated with post-fire safe shutdown or alternative shutdown
actions required by post-fire safe shutdown or alternative shutdown.
        operator manual actions.
  G.3 Internal and external self assessments, peer assessments, and audits of fire
F.3
        protection activities for the last three years.
LIST of non-licensed operator training associated with post-fire safe shutdown or
  G.4  Internal and external self assessments, peer assessments, and audits of post-fire
alternative shutdown manual actions which would be performed by a non-licensed
        safe shutdown or alternative shutdown capabilities for the last three years.
operator (including JPMs, in-field training walkdowns, simulations, or initial
  G.5  LIST of condition reports for the fire protection system for the last three years.
qualification).  
  G.6 LIST of condition reports for emergency lighting units for the last three years.
  G.7  LIST of condition reports for post-fire safe shutdown (SSD) or alternative shutdown
F.4
        (ASD) issues for the last three years. This includes issues affecting the SSD or ASD
LIST of lesson plans for post-fire safe shutdown or alternative shutdown training for
        analysis, fire hazards analysis, SSD or ASD operating procedures and/or training,
licensed and non-licensed operators.
        timeline evaluations for operator actions, and supporting engineering evaluations,
        analysis, or calculations.
F.5
  G.LIST of all Generic Letter 86 - 10 evaluations.
For operator manual actions (OMAs) provide the following:
  G.9 Copy of all Generic Letter 86 - 10 evaluations performed in the last three years.
  G.10 All fire loading calculations and evaluations performed (only for selected fire areas
*  
        and their adjacent fire areas).
Manual Action Feasibility Study;  
                                                                                                  .
*  
Operator Time Critical Action Program;  
*  
Time lines for time-critical OMAs; and  
*  
Time line validations.  
*
Environmental and habitability evaluations for post-fire operator manual actions  
(temperature, smoke, humidity, SCBAs, etc.).  
F.6
Thermal hydraulic calculation or analysis that determines the time requirements for  
time-critical manual operator actions.  
   
F.7
Operating procedures for post-fire safe shutdown from the control room with a
postulated fire in the selected fire areas.  
   
F.8
Operating procedures for post-fire safe shutdown or alternative shutdown from
outside the control room.
F.9
For safe shutdown equipment and tools, provide the following:
*
Procedure for inventory and inspection; and  
*
Most recent inspection and inventory results.  
F.10 LIST of procedures that implement Cold Shutdown Repairs.  
F.11 For Cold Shutdown Repairs, provide the following:
   
*
Procedure for inventory and inspection (i.e., needed tools, material, etc.); and  
*
Most recent inspection and inventory results.  


                        Mitigating Strategies Supporting Documentation
7
H. 10 CFR 50.54(hh)(2) - MITIGATING STRATEGIES DOCUMENTS
  H.1 LIST of all changes to regulatory commitments made to meet the requirements
.
        of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2).
  H.2  LIST of procedures and guidelines that were revised or generated to implement
F.12 Calculation or analysis that demonstrates pressurizer level will remain within the
        the mitigating strategies. These could be extensive damage mitigation guidelines
indicating range for a PWR, or reactor water level will remain above the top of active
        (EDMGs), severe accident management guidelines (SAMGs), emergency
fuel for a BWR, at the safe shutdown or alternative shutdown panel, in accordance
        operating procedures (EOPs), abnormal operating procedures (AOPs), etc.
with the requirements of 10 CFR 50 Appendix R III.L performance goals.
  H.3 A matrix that shows the correlation between the mitigation strategies identified in
        Nuclear Energy Institute 06-12, Revision 2, "B.5.b Phase 2 & 3 Submittal
F.13 For Radio communications, provide the following:
        Guideline," issued December 2006, and the site-specific procedures or guidelines
        that are used to implement each strategy.
*
  H.4  LIST of engineering evaluations or calculations that were used to verify
Communications Plan for fire fighting and post-fire safe shutdown manual actions;
        the engineering bases for the mitigating strategies.
*
  H.5  Piping and instrumentation diagrams (P&ID) and legend list or simplified flow
Repeater locations;
        diagrams for systems relied upon in the mitigating strategies. These could be
*
        the type used for training. (C-size paper drawings and electronic copy)
Cable routing for repeater power supply cables;
  H.6 LIST of modification packages or summary descriptions of modifications
*
        with simplified drawings, for necessary facility changes to implement the
Radio coverage test results; and
        mitigating strategies.
*
  H.7 LIST of routine tests, surveillances, and preventive maintenance for equipment
Radio Dead Spot locations in the plant.  
        and tools needed to implement 10 CFR 50.54(hh)(2) strategies.
   
  H.8  For equipment and tools needed to implement 10 CFR 50.54(hh)(2)
F.14 NRC approved exemption requests for operator manual actions for
        strategies, provide the following:
10 CFR 50 Appendix R III.G.2 fire areas.
        *  Procedures for inventory, testing, and inspection; and
        *  Most recent inspection, inventory, and testing results.
F.15 Exemption requests submitted but not yet approved, for operator manual actions for
        *  Copies of the last two completed performance tests, surveillances, and
10 CFR 50 Appendix R III.G.2 fire areas.
            preventative maintenance performed on the pumps, including the
   
            pump controllers and batteries.
G. ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION PROGRAMS
  H.LIST of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details
        that differ from that documented in the submittals or the safety evaluation report.
G.1 Corrective actions for fire-induced circuit failures (including but not limited to NRC IN
  H.10 Site general arrangement drawings that show the majority of buildings and areas
92-18), both single and multiple spurious actuations (only for selected fire areas).  
        referenced in 10 CFR 50.54(hh)(2) documents (C-size paper drawings and
   
        electronic copy).
G.2 Corrective actions associated with post-fire safe shutdown or alternative shutdown
  H.11 Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2).
operator manual actions.  
                                                                                  .Enclosure 2
G.3 Internal and external self assessments, peer assessments, and audits of fire
protection activities for the last three years.  
G.4 Internal and external self assessments, peer assessments, and audits of post-fire
safe shutdown or alternative shutdown capabilities for the last three years.  
G.5 LIST of condition reports for the fire protection system for the last three years.  
G.6 LIST of condition reports for emergency lighting units for the last three years.
G.7 LIST of condition reports for post-fire safe shutdown (SSD) or alternative shutdown
(ASD) issues for the last three years. This includes issues affecting the SSD or ASD
analysis, fire hazards analysis, SSD or ASD operating procedures and/or training,
timeline evaluations for operator actions, and supporting engineering evaluations,  
analysis, or calculations.
G.8 LIST of all Generic Letter 86 - 10 evaluations.  
G.9 Copy of all Generic Letter 86 - 10 evaluations performed in the last three years.  
G.10 All fire loading calculations and evaluations performed (only for selected fire areas  
and their adjacent fire areas).  


                                      2
H.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments)
    required to implement any mitigating strategies.
.Enclosure 2
H.13 Docketed correspondence for 10 CFR 50.54(hh) to include license amendment
Mitigating Strategies Supporting Documentation
    requests (LARS); Safety Evaluation Reports (SER); Request for Information
    (RFI) and associated responses; and other pertinent documents.
H. 10 CFR 50.54(hh)(2) - MITIGATING STRATEGIES DOCUMENTS
H.1
LIST of all changes to regulatory commitments made to meet the requirements
of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2).
H.2
LIST of procedures and guidelines that were revised or generated to implement
the mitigating strategies. These could be extensive damage mitigation guidelines
(EDMGs), severe accident management guidelines (SAMGs), emergency
operating procedures (EOPs), abnormal operating procedures (AOPs), etc.
H.3
A matrix that shows the correlation between the mitigation strategies identified in
Nuclear Energy Institute 06-12, Revision 2, "B.5.b Phase 2 & 3 Submittal
Guideline," issued December 2006, and the site-specific procedures or guidelines
that are used to implement each strategy.
H.4
LIST of engineering evaluations or calculations that were used to verify
the engineering bases for the mitigating strategies.
H.5
Piping and instrumentation diagrams (P&ID) and legend list or simplified flow
diagrams for systems relied upon in the mitigating strategies. These could be
the type used for training. (C-size paper drawings and electronic copy)
H.6
LIST of modification packages or summary descriptions of modifications
with simplified drawings, for necessary facility changes to implement the
mitigating strategies.
H.7
LIST of routine tests, surveillances, and preventive maintenance for equipment
and tools needed to implement 10 CFR 50.54(hh)(2) strategies.
H.8
For equipment and tools needed to implement 10 CFR 50.54(hh)(2)
strategies, provide the following:
*
Procedures for inventory, testing, and inspection; and
*
Most recent inspection, inventory, and testing results.
*
Copies of the last two completed performance tests, surveillances, and
preventative maintenance performed on the pumps, including the
pump controllers and batteries.
H.9
LIST of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details
that differ from that documented in the submittals or the safety evaluation report.
H.10 Site general arrangement drawings that show the majority of buildings and areas
referenced in 10 CFR 50.54(hh)(2) documents (C-size paper drawings and
electronic copy).
H.11 Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2).
 
2
H.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments)  
required to implement any mitigating strategies.  
H.13 Docketed correspondence for 10 CFR 50.54(hh) to include license amendment  
requests (LARS); Safety Evaluation Reports (SER); Request for Information  
(RFI) and associated responses; and other pertinent documents.
}}
}}

Latest revision as of 03:07, 10 January 2025

Notification of a Triennial Fire Protection Baseline Inspection (NRC Inspection Report Nos. 05000335/2016011 and 05000389/2016011)
ML16054A073
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 02/18/2016
From: Scott Shaeffer
NRC/RGN-II/DRS/EB2
To: Nazar M
Nextera Energy
References
IR 2016011
Download: ML16054A073 (13)


See also: IR 05000335/2016011

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

245 PEACHTREE CENTER AVENUE NE, SUITE 1200

ATLANTA, GEORGIA 30303-1257

February 18, 2016

Mano Nazar

President and Chief Nuclear Officer

Nuclear Division

NextEra Energy

P.O. Box 14000

Juno Beach, FL 33408-0420

SUBJECT: SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION

REPORT NOS. 05000335/2016011 AND 05000389/2016011

Dear Mr. Nazar:

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

staff will conduct a triennial fire protection baseline inspection at St. Lucie Nuclear Plant,

Units 1 and 2. The inspection team will be led by David Jones, a Senior Reactor Inspector from

the NRC Region II Office. The team will be composed of personnel from the NRC Region II

Office. The inspection will be conducted in accordance with IP 71111.05T, the NRC's baseline

fire protection inspection procedure, dated January 31, 2013.

On February 8, 2016, during a telephone conversation between Mr. E. Katzman (Licensing) and

Mr. D. Jones of our respective staffs, arrangements for an information gathering onsite visit and

a two-week onsite inspection were confirmed. The schedule for the inspection is as follows:

Information Gathering Visit:

May 02 - 05, 2016

Week 1 of onsite inspection:

June 06 - 10, 2016

Week 2 of onsite inspection:

June 20 - 24, 2016

The purposes of the information gathering visit are to obtain information and documentation

needed to support the inspection, to become familiar with the fire protection program, fire

protection features, post-fire safe shutdown capabilities, plant layout, mitigating strategies to

address Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2); and, as necessary,

obtain plant specific site access training and badging for unescorted site access.

An initial list of the documents the team will review during the conduct of the inspection is listed

in Enclosures 1 and 2. The team leader will contact you with any additional specific document

requests prior to the information gathering visit.

During the information gathering visit, the team will also discuss the following inspection support

administrative details: office space size and location; specific documents requested to be made

available to the team in their office spaces; arrangements for reactor site access (including

radiation protection training, security, safety and fitness for duty requirements); and the

availability of knowledgeable plant staff and licensing organization personnel to serve as points

of contact during the inspection.

M. Nazar

2

We request that during the on-site inspection weeks that you ensure that be readily accessible to

the team for their review copies of analyses, evaluations or documentation regarding the

implementation and maintenance of the station fire protection program, including post-fire safe

shutdown capability. Of specific interest for the fire protection portion of the inspection are

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). For the 10 CFR 50.54(hh)(2) portion of the

inspection, those documents implementing your mitigating strategies and demonstrating the

management of your commitments for the strategies are of specific interest. Also, personnel

should be available at the site during the inspection that are knowledgeable regarding plant

systems required to achieve and maintain safe shutdown conditions from inside and outside the

control room; including the electrical aspects of the relevant post-fire safe shutdown analyses,

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.

In accordance with 10 CFR 2.390 of the NRC Rules and Practices, a copy of this letter and its

enclosures will be available electronically for public inspection in the NRC Public Document

Room or from the Publically Available Records (PARS) component of NRCs document

system(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.hmtl (the Public Electronic Reading Room).

Your cooperation and support during this inspection will be appreciated. If you have questions

concerning this inspection, or the inspection team's information or logistical needs, please

contact David Jones, the team leader, in the Region II Office at 404-997-4631 or me at

404-997-4521.

Sincerely,

/RA/

Scott M. Shaeffer, Chief

Engineering Branch 2

Division of Reactor Safety

Docket Nos.: 50-335; 50-389

License Nos.: DPR-67 and NPF-16

Enclosures:

1. Triennial Fire Protection Inspection Supporting Documentation

2. Mitigating Strategies Supporting Documentation

cc: Distribution via Listserv

_________________________

SUNSI REVIEW COMPLETE

FORM 665 ATTACHED

OFFICE

RII:DRS

RII:DRS

SIGNATURE

DAJ2

SMS

NAME

DJONES

SSHAEFFER

DATE

2/18/2016

2/18/2016

3/ /2016

3/ /2016

3/ /2016

3/ /2016

3/ /2016

E-MAIL COPY?

YES

NO YES

NO

YES

NO

YES

NO YES

NO

YES

NO

YES

NO

Letter to Mano Nazar from Scott M Shaeffer dated February 18, 2016.

SUBJECT: SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A

TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION

REPORT NOS. 05000335/2016011 AND 05000389/2016011

DISTRIBUTION:

RIDSNRRDIRS PUBLIC

RidsNrrPMSt. Lucie Resource

Enclosure 1

Triennial Fire Protection Inspection Supporting Documentation

The documents and information requested below should generally be made available to the

inspection team during the on-site information gathering visit for the team's use both on-site and

off-site during the inspection. Electronic format is the preferred media, except where specifically

noted, if readily available (The preferred file format is searchable .pdf files). If electronic media

is made available via an internet based remote document management system, then the remote

document access must allow inspectors to download, save, and print the documents in the

NRC's regional office. Electronic media on compact disc or paper records (hard copy) are

acceptable. At the end of the inspection, the documents in the team's possession will not be

retained.

Approximately three weeks before the on-site information gathering visit, the following

documents should be made available to the team leader for review in the regional office:

Post-fire Safe Shutdown or Alternative Shutdown Analysis (request A.1)

Fire Hazards Analysis (request A.2)

Individual Plant Examination for External Events (Fire Chapter ONLY)

(request A.3)

Based on review of the above three documents, the team leader will identify a preliminary list of

fire areas being considered for inspection prior to the on-site information gathering visit. During

the information gathering visit, or shortly thereafter, the fire areas selected for inspection will be

determined.

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

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

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

document names; your plant specific document titles may vary.

A.

DESIGN AND LICENSING BASIS DOCUMENTS

A.1

Post-fire Safe Shutdown or Alternative Shutdown Analysis.

A.2

Fire Hazards Analysis.

A.3

Individual Plant Examination for External Events (IPEEE) (Fire Chapter

ONLY), including:

  • Results of any post-IPEEE reviews; and
  • LIST of actions taken or plant modifications performed in response to the

IPEEE results.

A.4

Fire Protection Program and/or Fire Protection Plan.

A.5

LIST of post-fire safe shutdown or alternative shutdown systems (i.e., safe

shutdown equipment list).

A.6

Fire Protection System Design Basis Document.

2

.

A.7

Post-fire Safe Shutdown or Alternative Shutdown Design Basis Document.

A.8

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

of record).

A.9

LIST of deviations from NFPA codes of record.

A.10 NFPA Compliance Review Report.

A.11 Report or evaluation that compares the fire protection program to the NRC

Branch Technical Position (BTP) 9.5-1 Appendix A.

A.12 Electronic copy of licensee submittals and NRC safety evaluation reports that

are specifically listed in the facility operating license for the approved fire

protection program.

A.13 NRC Safety Evaluation Reports for fire protection program and post-fire

safe shutdown or alternative shutdown features.

A.14 NRC approved exemptions for plant fire protection and post-fire safe shutdown

or alternative shutdown features.

A.15 Exemption requests submitted but not yet approved for plant fire protection and

post- fire safe shutdown or alternative shutdown features.

A.16 Facility Operating License (electronic format only).

A.17 Technical Specifications (electronic format only).

A.18 Technical Requirements Manual (electronic format only).

A.19 Updated Final Safety Analysis Report (electronic format only).

B.

GENERAL PLANT DESIGN DOCUMENTS

B.1

Piping and instrumentation diagrams (P&IDs) and legend list for post-fire safe

shutdown or alternative shutdown systems (C-size paper drawings and

electronic copy).

B.2

P&IDs and legend list for fire protection systems, including fire water supply,

water suppression sprinklers & deluge, and CO2 and Halon systems (C-size

paper drawings and electronic copy).

B.3

AC and DC electrical system single line diagrams, from off-site power down to the

highest safety-related bus level (typically 4kV, EDG bus) (C-size paper drawings

and electronic copy ).

B.4

Single line diagrams for motor control centers (MCCs) that supply post-fire safe

shutdown or alternative shutdown loads (only for selected fire areas) (C-size

paper drawings and electronic copy).

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.

B.5

Equipment location drawings which identify the physical plant locations of post-

fire safe shutdown or alternative shutdown equipment (C-size paper drawings

and electronic copy).

B.6

Plant layout drawings which identify: (C-size paper drawings and electronic copy)

Plant fire area boundaries;

Combustible control zone drawings;

Areas protected by automatic fire suppression and detection; and

Locations of fire protection equipment.

C. CLASSICAL FIRE PROTECTION

C.1

Fire protection program implementing procedures (e.g., administrative

controls, surveillance testing, fire brigade).

C.2

LIST of calculations and engineering analyses, studies, or evaluations for the

fire protection system, including the fire water system.

C.3

Hydraulic calculation or analysis for fire protection water system in the selected

fire areas.

C.4

Last two completed surveillance's records of fire protection features in the

selected fire areas (detection, suppression, damper inspections, damper tests,

penetration inspections, barrier inspections, etc.).

C.5

LIST of routine tests, surveillances, and preventive maintenance on fire

pumps, including pump controllers and batteries.

C.6

Last two completed annual fire pump pressure and flow tests.

C.7

Last two completed monthly and/or quarterly fire pump tests.

C.8

Last two completed fire loop flow tests and loop flushes.

C.9

CO2 and Halon initial discharge testing or calculation that determined appropriate

concentrations and soak or hold times can be achieved (only for selected fire

areas).

C.10 Last five hot work permits (at power).

C.11 Last five transient combustible permits (at power).

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.

C.12 For Fire Brigade Drills, provide the following:

  • Last drill critique for a drill with off-site fire department support;

Summary of any unsatisfactory drill performance items for last three years; and

  • Last unannounced drill critique by a qualified individual independent of the

licensee's staff.

C.13 For fire brigade equipment provide the following:

Procedure for inventory and inspection; and

Most recent inspection and inventory results.

C.14 Fire Brigade Medical Evaluations and Qualifications, including self-contained

breathing apparatus (SCBA) and training lesson plans.

C.15 Electronic copy of the mutual aid agreement for the first-due local fire department

that is currently in effect.

C.16 Flooding analysis for selected fire areas which demonstrates:

  • a fire water pipe break in the selected fire areas, wont affect safe shutdown (SSD)

capability for equipment in the selected fire areas;

  • a fire water pipe break in an adjacent fire area, wont affect SSD capability for

equipment in the selected fire areas;

are credited with keeping water from leaking into fire areas below.

C.17 Pre-fire plans for the selected fire areas and their adjacent fire areas.

C.18 For Emergency Lighting Units (ELU), provide the following:

LIST of Preventive Maintenance tasks, frequencies, and bases;

Most recently performed monthly or quarterly functional test;

Most recently performed battery discharge performance test; if applicable

ELU battery loading analysis;

vendor manual(s);

results of black-out testing (if performed);

Maintenance Rule program information related to the ELU, if applicable; and

Compensatory measures taken when ELU are out of service.

C.19 Impairment Log (for period of 3 months before the start of inspection), for fire

protection features that are out of service.

C.20 LIST of Fire Protection screening reviews since the last inspection for recent design

changes, modifications, or temporary modifications (e.g., a Generic Letter 86-10

review that screened out).

C.21 LIST of fire protection system design changes completed in the last three years

(including their associated 10 CFR 50.59 and Generic Letter 86-10 evaluations).

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.

C.22 LIST of penetration seal work, re-work, or installation activities, in the last three years.

C.23 LIST of fire wrap work, re-work, or installation activities, in the last three years.

C.24 Fire protection system health reports for the two most recent years.

C.25 Fire protection program health report for the two most recent years.

C.26 Emergency lighting system health reports for the two most recent years.

C.27 Licensee evaluation of industry operating experience, related to the Fire Protection

Program for the three most recent years.

D. ELECTRICAL

D.1

Identify whether the cables in the selected fire areas are predominantly Thermoset or

Thermoplastic. Specifically identify any Thermoplastic cable in the selected fire

areas.

D.2

Breaker and fuse coordination calculation for post-fire safe shutdown or alternative

shutdown equipment (only for selected fire areas).

D.3

Administrative or configuration control procedures that govern fuse replacement (e.g.,

fuse control procedures).

D.4

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

coordination remains functional, for post-fire safe shutdown or alternative shutdown

equipment.

D.5

Electrical system health reports for the two most recent years.

D.6

Last completed preventive maintenance of those components as tested from the safe

shutdown or alternative shutdown panel.

D.7

Schematic or elementary diagrams for circuits to be reviewed, as requested by

inspector (C-size paper drawings and electronic copy).

D.8

Cable routing for components and equipment credited for post-fire safe shutdown or

alternative shutdown (only for selected fire areas).

D.9

LIST of post-fire safe shutdown or alternative shutdown design changes completed,

since the last inspection.

E.

SPURIOUS FIRE INDUCED CIRCUIT FAULTS

E.1

LIST of identified fire induced circuit failure configurations (only for selected fire

areas).

E.2

Multiple Spurious Operation (MSO) Expert Panel Report.

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.

E.3

Corrective actions for fire-induced circuit failures, both single and multiple spurious

actuations for the selected fire areas.

F.

OPERATIONS

F.1

LIST of calculations and engineering analyses, studies, or evaluations for the safe

shutdown or alternative shutdown methodology.

F.2

LIST of licensed operator Job Performance Measures (JPMs) for operator manual

actions required by post-fire safe shutdown or alternative shutdown.

F.3

LIST of non-licensed operator training associated with post-fire safe shutdown or

alternative shutdown manual actions which would be performed by a non-licensed

operator (including JPMs, in-field training walkdowns, simulations, or initial

qualification).

F.4

LIST of lesson plans for post-fire safe shutdown or alternative shutdown training for

licensed and non-licensed operators.

F.5

For operator manual actions (OMAs) provide the following:

Manual Action Feasibility Study;

Operator Time Critical Action Program;

Time lines for time-critical OMAs; and

Time line validations.

Environmental and habitability evaluations for post-fire operator manual actions

(temperature, smoke, humidity, SCBAs, etc.).

F.6

Thermal hydraulic calculation or analysis that determines the time requirements for

time-critical manual operator actions.

F.7

Operating procedures for post-fire safe shutdown from the control room with a

postulated fire in the selected fire areas.

F.8

Operating procedures for post-fire safe shutdown or alternative shutdown from

outside the control room.

F.9

For safe shutdown equipment and tools, provide the following:

Procedure for inventory and inspection; and

Most recent inspection and inventory results.

F.10 LIST of procedures that implement Cold Shutdown Repairs.

F.11 For Cold Shutdown Repairs, provide the following:

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

Most recent inspection and inventory results.

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.

F.12 Calculation or analysis that demonstrates pressurizer level will remain within the

indicating range for a PWR, or reactor water level will remain above the top of active

fuel for a BWR, at the safe shutdown or alternative shutdown panel, in accordance

with the requirements of 10 CFR 50 Appendix R III.L performance goals.

F.13 For Radio communications, provide the following:

Communications Plan for fire fighting and post-fire safe shutdown manual actions;

Repeater locations;

Cable routing for repeater power supply cables;

Radio coverage test results; and

Radio Dead Spot locations in the plant.

F.14 NRC approved exemption requests for operator manual actions for

10 CFR 50 Appendix R III.G.2 fire areas.

F.15 Exemption requests submitted but not yet approved, for operator manual actions for

10 CFR 50 Appendix R III.G.2 fire areas.

G. ADMINISTRATIVE CONTROL, OVERSIGHT, AND CORRECTIVE ACTION PROGRAMS

G.1 Corrective actions for fire-induced circuit failures (including but not limited to NRC IN 92-18), both single and multiple spurious actuations (only for selected fire areas).

G.2 Corrective actions associated with post-fire safe shutdown or alternative shutdown

operator manual actions.

G.3 Internal and external self assessments, peer assessments, and audits of fire

protection activities for the last three years.

G.4 Internal and external self assessments, peer assessments, and audits of post-fire

safe shutdown or alternative shutdown capabilities for the last three years.

G.5 LIST of condition reports for the fire protection system for the last three years.

G.6 LIST of condition reports for emergency lighting units for the last three years.

G.7 LIST of condition reports for post-fire safe shutdown (SSD) or alternative shutdown

(ASD) issues for the last three years. This includes issues affecting the SSD or ASD

analysis, fire hazards analysis, SSD or ASD operating procedures and/or training,

timeline evaluations for operator actions, and supporting engineering evaluations,

analysis, or calculations.

G.8 LIST of all Generic Letter 86 - 10 evaluations.

G.9 Copy of all Generic Letter 86 - 10 evaluations performed in the last three years.

G.10 All fire loading calculations and evaluations performed (only for selected fire areas

and their adjacent fire areas).

.Enclosure 2

Mitigating Strategies Supporting Documentation

H. 10 CFR 50.54(hh)(2) - MITIGATING STRATEGIES DOCUMENTS

H.1

LIST of all changes to regulatory commitments made to meet the requirements

of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(hh)(2).

H.2

LIST of procedures and guidelines that were revised or generated to implement

the mitigating strategies. These could be extensive damage mitigation guidelines

(EDMGs), severe accident management guidelines (SAMGs), emergency

operating procedures (EOPs), abnormal operating procedures (AOPs), etc.

H.3

A matrix that shows the correlation between the mitigation strategies identified in

Nuclear Energy Institute 06-12, Revision 2, "B.5.b Phase 2 & 3 Submittal

Guideline," issued December 2006, and the site-specific procedures or guidelines

that are used to implement each strategy.

H.4

LIST of engineering evaluations or calculations that were used to verify

the engineering bases for the mitigating strategies.

H.5

Piping and instrumentation diagrams (P&ID) and legend list or simplified flow

diagrams for systems relied upon in the mitigating strategies. These could be

the type used for training. (C-size paper drawings and electronic copy)

H.6

LIST of modification packages or summary descriptions of modifications

with simplified drawings, for necessary facility changes to implement the

mitigating strategies.

H.7

LIST of routine tests, surveillances, and preventive maintenance for equipment

and tools needed to implement 10 CFR 50.54(hh)(2) strategies.

H.8

For equipment and tools needed to implement 10 CFR 50.54(hh)(2)

strategies, provide the following:

Procedures for inventory, testing, and inspection; and

Most recent inspection, inventory, and testing results.

Copies of the last two completed performance tests, surveillances, and

preventative maintenance performed on the pumps, including the

pump controllers and batteries.

H.9

LIST of 10 CFR 50.54(hh)(2) strategies, if any, which have implementing details

that differ from that documented in the submittals or the safety evaluation report.

H.10 Site general arrangement drawings that show the majority of buildings and areas

referenced in 10 CFR 50.54(hh)(2) documents (C-size paper drawings and

electronic copy).

H.11 Training records, training matrix, and lesson plans related to 10 CFR 50.54(hh)(2).

2

H.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments)

required to implement any mitigating strategies.

H.13 Docketed correspondence for 10 CFR 50.54(hh) to include license amendment

requests (LARS); Safety Evaluation Reports (SER); Request for Information

(RFI) and associated responses; and other pertinent documents.