ML16054A073: Difference between revisions

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M. Nazar 2  
M. Nazar 2  
  We request that during the on-site inspection weeks that you ensure that be readily accessible to  
  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,
the team for their review copies of analyses, evaluations or documentation regarding the implementation and maintenance of the station fire
evaluations or documentation regarding the implementation and maintenance of the station fire
  protection program, including 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
  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
  requirements and conforms to applicable NRC and industry fire protection guidance (i.e., fire
Line 64: Line 63:
  should be available at the site during the inspection that are knowledgeable regarding plant
  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
  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,
  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
reactor plant fire protection systems and features, and the station fire protection program and its
  implementation.  
  implementation.  
  This letter does not contain new or amended information collection requirements subject to the
  This letter does not contain new or amended information collection requirements subject to the
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  In accordance with 10 CFR 2.390 of the NRC Rules and Practices, a copy of this letter and its
  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
  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-
  Room or from the Publically Available Records (PARS) component of NRC s 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).  
  rm/adams.hmtl (the Public Electronic Reading Room).  
  Your cooperation and support during this inspection will be appreciated. If you have questions
  Your cooperation and support during this inspection will be appreciated. If you have questions
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404-997-4521.  
404-997-4521.  


  Sincerely,  
  Sincerely,   
   
       /RA/  Scott M. Shaeffer, Chief  
       /RA/  Scott M. Shaeffer, Chief  
Engineering Branch 2  
Engineering Branch 2  
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_________________________  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       
_________________________  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
  Letter to Mano Nazar from Scott M Shaeffer dated February 18, 2016.  
  Mano Nazar from Scott M Shaeffer dated February 18, 2016.  
  SUBJECT:  SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A
  SUBJECT:  SAINT LUCIE NUCLEAR PLANT (UNIT 1 AND 2) - NOTIFICATION OF A
   TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION  REPORT NOS.  
   TRIENNIAL FIRE PROTECTION BASELINE INSPECTION (NRC INSPECTION  REPORT NOS.  
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  the information gathering visit, or shortly thereafter, the fire areas selected for inspection will be
  the information gathering visit, or shortly thereafter, the fire areas selected for inspection will be
  determined.  
  determined.  
  This document request is based on typical documents that a generic plant might have.  As such,
  This document request is based on typical documents that a generic plant might have.  As such, this generic document request is not meant to imply that any specific plant is required to have all
this generic document request is not meant to imply that any specific plant is required to have all
  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  
  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.  
document names; your plant specific document titles may vary.  
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  * Results of any post-IPEEE reviews; and  
  * Results of any post-IPEEE reviews; and  
* LIST of actions taken or plant modifications performed in response to the  
* LIST of actions taken or plant modifications performed in response to the  
IPEEE results.  
IPEEE results.  A.4 Fire Protection Program and/or Fire Protection Plan.  
  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  
  A.5 LIST of post-fire safe shutdown or alternative shutdown systems (i.e., safe  
shutdown equipment list).  
shutdown equipment list).  
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2  . A.7 Post-fire Safe Shutdown or Alternative Shutdown 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  
  A.8 LIST of applicable NFPA codes and standards and issuance dates (i.e., codes  
of record).  
of record).  A.9 LIST of deviations from NFPA codes of record.  
  A.9 LIST of deviations from NFPA codes of record.  
  A.10 NFPA Compliance Review Report.  
  A.10 NFPA Compliance Review Report.  
  A.11 Report or evaluation that compares the fire protection program to the NRC  
  A.11 Report or evaluation that compares the fire protection program to the NRC  
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are specifically listed in the facility operating license for the approved fire  
are specifically listed in the facility operating license for the approved fire  
protection
protection
  program.  
  program.  A.13 NRC Safety Evaluation Reports for fire protection program and post-fire  
  A.13 NRC Safety Evaluation Reports for fire protection program and post-fire  


safe shutdown or alternative shutdown features.  
safe shutdown or alternative shutdown features.  
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electronic
electronic
  copy).  B.2 P&IDs and legend list for fire protection systems, including fire water supply,  
  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  
water suppression sprinklers & deluge, and CO2 and Halon systems (C-size  
paper drawings and electronic copy).
paper drawings and electronic copy).
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  C. CLASSICAL FIRE PROTECTION  
  C. CLASSICAL FIRE PROTECTION  
  C.1 Fire protection program implementing procedures (e.g., administrative  
  C.1 Fire protection program implementing procedures (e.g., administrative  
controls,
controls, surveillance testing, fire brigade).  
surveillance testing, fire brigade).  
  C.2 LIST of calculations and engineering analyses, studies, or evaluations for the  
  C.2 LIST of calculations and engineering analyses, studies, or evaluations for the  
fire protection system, including the fire water system.  
fire protection system, including the fire water system.  
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fire areas.  C.4 Last two completed surveillance's records of fire protection features in the  
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,  
selected fire areas (detection, suppression, damper inspections, damper tests, penetration
penetration
  inspections, barrier inspections, etc.).  
  inspections, barrier inspections, etc.).  
  C.5 LIST of routine tests, surveillances, and preventive maintenance on fire  
  C.5 LIST of routine tests, surveillances, and preventive maintenance on fire  
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  areas.  D.2 Breaker and fuse coordination calculation for post-fire safe shutdown or alternative
  areas.  D.2 Breaker and fuse coordination calculation for post-fire safe shutdown or alternative
  shutdown equipment (only for selected fire areas).  
  shutdown equipment (only for selected fire areas).  
  D.3 Administrative or configuration control procedures that govern fuse replacement (e.g.,
  D.3 Administrative or configuration control procedures that govern fuse replacement (e.g., fuse control procedures).  
fuse control procedures).  
  D.4 Maintenance procedures that verify breaker over-current trip settings to ensure
  D.4 Maintenance procedures that verify breaker over-current trip settings to ensure
  coordination remains functional, for post-fire safe shutdown or alternative shutdown
  coordination remains functional, for post-fire safe shutdown or alternative shutdown
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  D.8 Cable routing for components and equipment credited for post-fire safe shutdown or
  D.8 Cable routing for components and equipment credited for post-fire safe shutdown or
  alternative shutdown (only for selected fire areas).  
  alternative shutdown (only for selected fire areas).  
  D.9 LIST of post-fire safe shutdown or alternative shutdown design changes completed,
  D.9 LIST of post-fire safe shutdown or alternative shutdown design changes completed, since the last inspection.  
since the last inspection.  
  E. SPURIOUS FIRE INDUCED CIRCUIT FAULTS  
  E. SPURIOUS FIRE INDUCED CIRCUIT FAULTS  
  E.1 LIST of identified fire induced circuit failure configurations (only for selected fire
  E.1 LIST of identified fire induced circuit failure configurations (only for selected fire
Line 303: Line 290:
  F.10 LIST of procedures that implement Cold Shutdown Repairs.  
  F.10 LIST of procedures that implement Cold Shutdown Repairs.  
  F.11 For Cold Shutdown Repairs, provide the following:  
  F.11 For Cold Shutdown Repairs, provide the following:  
  * Procedure for inventory and inspection (i
  * Procedure for inventory and inspection (i.e., needed tools, material, etc.); and  
.e., needed tools, material, etc.); and  
* Most recent inspection and inventory results.   
* Most recent inspection and inventory results.   
7  .  F.12 Calculation or analysis that demonstrates pressurizer level will remain within the
7  .  F.12 Calculation or analysis that demonstrates pressurizer level will remain within the
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  G.7 LIST of condition reports for post-fire safe shutdown (SSD) or alternative shutdown
  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
  (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,
  analysis, fire hazards analysis, SSD or ASD operating procedures and/or training, timeline evaluations for operator actions, and supporting engi
timeline evaluations for operator actions, and supporting engi
neering evaluations, analysis, or calculations.  
neering evaluations,
analysis, or calculations.  
  G.8 LIST of all Generic Letter 86 - 10 evaluations.  
  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.9 Copy of all Generic Letter 86 - 10 evaluations performed in the last three years.  
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the mitigating strategies. These could be extensive damage mitigation guidelines
the mitigating strategies. These could be extensive damage mitigation guidelines
  (EDMGs), severe accident management guidelines (SAMGs), emergency  
  (EDMGs), severe accident management guidelines (SAMGs), emergency  
operating
operating procedures (EOPs), abnormal operating procedures (AOPs), etc.  
procedures (EOPs), abnormal operating procedures (AOPs), etc.  
  H.3 A matrix that shows the correlation between the mitigation strategies identified in
  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  
  Nuclear Energy Institute 06-12, Revision 2, "B.5.b Phase 2 & 3 Submittal  


Guideline,"
Guideline," issued December 2006, and the site-specific procedures or guidelines that are used
issued December 2006, and the site-specific procedures or guidelines that are used
  to implement each strategy.  
  to implement each strategy.  
  H.4 LIST of engineering evaluations or calculations that were used to verify  
  H.4 LIST of engineering evaluations or calculations that were used to verify  
Line 367: Line 349:
and tools needed to implement 10 CFR 50.54(hh)(2) strategies.  
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)  
  H.8 For equipment and tools needed to implement 10 CFR 50.54(hh)(2)  
strategies,
strategies, provide the following:  
provide the following:  
  * Procedures for inventory, testing, and inspection; and  
  * Procedures for inventory, testing, and inspection; and  
* Most recent inspection, inventory, and testing results.  
* Most recent inspection, inventory, and testing results.  
Line 384: Line 365:
  required to implement any mitigating strategies.  
  required to implement any mitigating strategies.  
  H.13 Docketed correspondence for 10 CFR 50.54(hh) to include license amendment
  H.13 Docketed correspondence for 10 CFR 50.54(hh) to include license amendment
  requests (LARS); Safety Evaluation Reports (SER); Request for Information  
  requests (LARS); Safety Evaluation Reports (SER); Request for Information (RFI) and associated responses; and other pertinent documents.
(RFI) and associated responses; and other pertinent documents.
}}
}}

Revision as of 14:30, 8 July 2018

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)
ML16054A073
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 02/18/2016
From: Shaeffer S M
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 NRC s 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, 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;

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);
  • 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.

(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 engi

neering 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.