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| number = ML16054A073
| number = ML16054A073
| issue date = 02/18/2016
| issue date = 02/18/2016
| title = 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)
| title = Notification of a Triennial Fire Protection Baseline Inspection (NRC Inspection Report Nos. 05000335/2016011 and 05000389/2016011)
| author name = Shaeffer S M
| author name = Shaeffer S
| author affiliation = NRC/RGN-II/DRS/EB2
| author affiliation = NRC/RGN-II/DRS/EB2
| addressee name = Nazar M
| addressee name = Nazar M
Line 14: Line 14:
| page count = 13
| page count = 13
}}
}}
See also: [[followed by::IR 05000335/2016011]]
See also: [[see also::IR 05000335/2016011]]


=Text=
=Text=
{{#Wiki_filter: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  
{{#Wiki_filter: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  
Nuclear Division  
NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420  
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).
   
   
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     
3  
  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 officeElectronic media on compact disc or paper records (hard copy) are acceptableAt the end of the inspection, the documents in the team's possession will not be retained.   
B.5
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 determinedThis 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 documentsIt is recognized that some documents listed below may not be available for your plantIn addition, the document titles listed below are based on typical industry
Equipment location drawings which identify the physical plant locations of post-
document names; your plant specific document titles may vary. A. DESIGN AND LICENSING BASIS DOCUMENTS  A.1 Post-fire Safe Shutdown or Alternative Shutdown AnalysisA.2 Fire Hazards AnalysisA.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 PlanA.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.  
fire safe shutdown or alternative shutdown equipment (C-size paper drawings
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 AA.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
and electronic copy).
safe shutdown or alternative shutdown featuresA.14 NRC approved exemptions for plant fire protection and post-fire safe shutdown or alternative shutdown featuresA.15 Exemption requests submitted but not yet approved for plant fire protection and
   
post- fire safe shutdown or alternative shutdown featuresA.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
B.6
electronic copy).  B.2 P&IDs and legend list for fire protection systems, including fire water supply,
Plant layout drawings which identify: (C-size paper drawings and electronic copy)
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)
   
3  . 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
Plant fire area boundaries;
areas). C.10 Last five hot work permits (at power)C.11 Last five transient combustible permits (at power). 
*
4  .  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 staffC.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 plansC.15 Electronic copy of the mutual aid agreement for the "first-due" local fire department that is currently in effectC.16 Flooding analysis for selected fire areas which demonstrates: * a fire water pipe break in the selected fire areas, won't affect safe shutdown (SSD) capability for equipment in the selected fire areas; * a fire water pipe break in an adjacent fire area, won't affect SSD capability for equipment in the selected fire areas; * hydrostatic rating of any floor penetration seals installed within the fire areas that are credited with keeping water from leaking into fire areas belowC.17 Pre-fire plans for the selected fire areas and their adjacent fire areasC.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 serviceC.19 Impairment Log (for period of 3 months before the start of inspection), for fire protection features that are out of serviceC.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).   
Combustible control zone drawings;
.   C.22 LIST of penetration seal work, re-work, or installation activities, in the last three yearsC.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 yearsC.26 Emergency lighting system health reports for the two most recent yearsC.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 equipmentD.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. 
*
6  .  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 shutdownF.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 operatorsF.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 actionsF.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 resultsF.10 LIST of procedures that implement Cold Shutdown RepairsF.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.   
Areas protected by automatic fire suppression and detection; and  
7 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 goalsF.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 plantF.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 areasG. 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 actionsG.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 yearsG.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
Locations of fire protection equipment.  
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.
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).  
 
4
   
.  
   
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;
* 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).
 
5
   
.
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.
 
6
.
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.  
 
7
   
.  
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.
}}
}}

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).

3

.

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).

4

.

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).

5

.

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.

6

.

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.

7

.

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.