Text

Notification of Conduct of a Triennial Fire Protection Baseline Inspection 2016007
	ML16074A256
Person / Time
Site:	Millstone
Issue date:	03/14/2016
From:	Rogge J; Engineering Region 1 Branch 3
To:	Heacock D; Dominion Resources
	Rogge J
References
	Download: ML16074A256 (12)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 March 14, 2016 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION UNITS 2 AND 3 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Heacock:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commissions (NRC) staff will conduct a triennial fire protection baseline inspection at Millstone Power Station, Units 2 and 3, beginning in July, 2016. The inspection team will be led by Keith Young from the Region I Office. The team will be composed of personnel from the NRC Region I Office. The inspection will be conducted in accordance with Inspection Procedure 71111.05T, the NRC's baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

Information Gathering Visit - Week of July 11, 2016

On-Site Inspection - Weeks of July 25, 2016 and August 7, 2016 The purpose of the information gathering visit is to obtain information and documentation needed to support the inspection, to become familiar with the stations fire protection programs, 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.

The Initial lists of documents that the team will review during the conduct of the inspection are included 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 such as: Office space size and location; specific documents requested to be made available to the team in their office spaces; arrangements for reactor site access; and the availability of knowledgeable plant staff and licensing organization personnel to serve as points of contact during the inspection.

D. Heacock We request that during the on-site inspection weeks, you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents which establish that your fire protection program satisfies NRCs regulatory requirements and that it 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 who are knowledgeable regarding those 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.

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 Keith Young, the team leader, in the Region I Office at 610-337-5293.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosures:

1. Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation cc: Distribution via ListServ

D. Heacock We request that during the on-site inspection weeks, you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents which establish that your fire protection program satisfies NRCs 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 who are knowledgeable regarding those 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.

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 Keith Young, the Team Leader, in the Region I Office at 610-337-5293.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosures:

1. Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation cc: Distribution via ListServ Distribution: (See Next Page)

ML16074A256 SUNSI Review Non-Sensitive Publicly Available OFFICE RI/DRS RI/DRS NAME KYoung/KY JFRogge/JFR DATE 03/11/2016 03/14/2016 ENCLOSURE 1 Fire Protection Program 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 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 of course always 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)

Fire Probabilistic Risk Assessment (PRA) Summary Document (request A.4)

Based on review of the above four documents, team leader should 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 Probabilistic Risk Assessment (PRA) Summary Document (if available).

A.5 Fire Protection Program and/or Fire Protection Plan.

A.6 LIST of post-fire safe shutdown or alternative shutdown systems (i.e., safe shutdown equipment list).

A.7 Fire Protection System Design Basis Document.

A.8 Post-fire Safe Shutdown or Alternative Shutdown Design Basis Document.

2 A.9 LIST of applicable NFPA codes and standards (i.e., codes of record).

A.10 LIST of deviations from NFPA codes of record.

A.11 NFPA Compliance Review Report (if available).

A.12 Report or evaluation that compares the fire protection program to the NRC Branch Technical Position (BTP) 9.5-1 Appendix A.

A.13 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.14 COPY of NRC Safety Evaluation Reports for fire protection program and post-fire safe shutdown or alternative shutdown features.

A.15 COPY of NRC approved exemptions for plant fire protection and post-fire safe shutdown or alternative shutdown features.

A.16 COPY of exemption requests submitted but not yet approved for plant fire protection and post-fire safe shutdown or alternative shutdown features.

A.17 Facility Operating License.

A.18 Technical Specifications (electronic format only).

A.19 Technical Requirements Manual (electronic format only).

A.20 Updated Final Safety Analysis Report (electronic format only).

B. GENERAL PLANT DESIGN DOCUMENTS B.1 Piping and instrumentation diagrams (P&IDs) for post-fire safe shutdown or alternative shutdown systems (C-size paper drawings).

B.2 P&IDs for fire protection systems, including fire water supply, water suppression sprinklers &

deluge, and CO2 and Halon systems (C-size paper drawings).

B.3 Yard layout drawings for underground fire protection buried piping (C-size paper drawings).

B.4 Layout or arrangement drawings of reactor coolant pump lube oil system leakage points and associated lube oil collection systems (C-size paper drawings) (PWRs only).

B.5 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).

B.6 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).

B.7 Equipment location drawings which identify the physical plant locations of post-fire safe shutdown or alternative shutdown equipment (C-size paper drawings).

3 B.8 Plant layout drawings which identify: (C-size paper drawings)

Plant fire area boundaries;

Combustible control zone drawings (if available);

Areas protected by automatic fire suppression and detection; and

Locations of fire protection equipment.

C. CLASSIC FIRE PROTECTION C.1 COPY of 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.

C.4 Last two completed surveillance's 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).

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

Last five fire brigade drill critiques;

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

Last unannounced drill critique;

Last back-shift drill critique;

Dates, shifts, and locations of unannounced drills for last three years;

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

4 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 Qualifications, including self-contained breathing apparatus (SCBA) and training lesson plans.

C.15 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.

C.16 Pre-fire plans for all fire areas.

C.17 For Emergency Lighting Units (ELU), provide the following:

LIST of Preventive Maintenance tasks and frequencies;

Most recently performed monthly or quarterly functional test;

Most recently performed battery discharge performance test;

ELU battery loading analysis;

vendor manual(s) for on-site inspector use; and

results of black-out testing (if performed).

C.18 Impairment Log (at start of inspection), for fire protection features that are out of service.

C.19 Three Fire Protection screening reviews for recent design changes, modifications, or temporary modifications (e.g., a Generic Letter 86-10 review that screened out).

C.20 LIST of penetration seal work, re-work, or installation activities, in the last three years.

C.21 LIST of fire wrap work, re-work, or installation activities, in the last three years.

C.22 Fire protection system health reports for the two most recent quarters.

C.23 Fire protection program health report for the two most recent quarters.

C.24 Emergency lighting system health reports for the two most recent quarters.

C.25 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.26 Licensee evaluation of industry operating experience, (Specific items to be selected by the inspector) such as:

NRC IN 2013-02, Issues Potentially Affecting Nuclear Facility Fire Safety;

NRC IN 2013-06, Corrosion in Fire Protection Piping Due to Air and Water Interface;

NRC IN 2013-09, Compressed Flammable Gas Cylinders and Associated Hazards;

NRC IN 2014-10, Potential Circuit Failure-Induced Secondary Fires or Equipment Damage;

NRC IN 2014-15, Inadequate Controls of Respiratory Protection Accessibility, Training, and Maintenance; and

NRC IN 2015-02, Antifreeze Agents in Fire Water Sprinkler Systems C.27 COPY of any test, surveillance, or maintenance procedure (current revision), including any associated data forms, for any requested "last performed" test, surveillance, or maintenance.

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 quarters.

D.6 Last surveillance demonstrating operability of those components operated from the safe shutdown or alternative shutdown panel.

D.7 Schematic or elementary diagrams for circuits to be reviewed (C-size paper drawings).

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, in the last three years.

E. SPURIOUS FIRE INDUCED CIRCUIT FAULT 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 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 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 (if available);

Operator Time Critical Action Program (if available);

Time lines for time-critical OMAs; and

Time line validations.

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.

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.

7 F.13 For Radio communications, provide the following:

Communications Plan for firefighting 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 COPY of NRC approved exemption requests for operator manual actions for 10 CFR 50 Appendix R III.G.2 fire areas.

F.15 COPY of exemption requests submitted but not yet approved, for operator manual actions for 10 CFR 50 Appendix R III.G.2 fire areas.

F.16 Environmental and habitability evaluations for post-fire operator manual actions (temperature, smoke, humidity, SCBAs, etc.).

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 Self assessments, peer assessments, and audits of fire protection activities for the last three years.

G.4 Self assessments, peer assessments, and audits of post-fire safe shutdown or alternative shutdown capabilities for the last three years.

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

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

G.7 LIST of open and closed 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.

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) or simplified flow diagrams for systems relied upon in the mitigating strategies. These could be the type used for training (C-size paper drawings).

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 and inspection; and

Most recent inspection and inventory results.

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).

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

H.12 Copies of memoranda of understanding (MOU) (e.g., with local fire departments) required to implement any mitigating strategies.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 March 14, 2016 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION UNITS 2 AND 3 - NOTIFICATION OF CONDUCT OF A TRIENNIAL FIRE PROTECTION BASELINE INSPECTION

Dear Mr. Heacock:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commissions (NRC) staff will conduct a triennial fire protection baseline inspection at Millstone Power Station, Units 2 and 3, beginning in July, 2016. The inspection team will be led by Keith Young from the Region I Office. The team will be composed of personnel from the NRC Region I Office. The inspection will be conducted in accordance with Inspection Procedure 71111.05T, the NRC's baseline fire protection inspection procedure.

The schedule for the inspection is as follows:

Information Gathering Visit - Week of July 11, 2016

On-Site Inspection - Weeks of July 25, 2016 and August 7, 2016 The purpose of the information gathering visit is to obtain information and documentation needed to support the inspection, to become familiar with the stations fire protection programs, 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.

The Initial lists of documents that the team will review during the conduct of the inspection are included 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 such as: Office space size and location; specific documents requested to be made available to the team in their office spaces; arrangements for reactor site access; and the availability of knowledgeable plant staff and licensing organization personnel to serve as points of contact during the inspection.

D. Heacock We request that during the on-site inspection weeks, you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents which establish that your fire protection program satisfies NRCs regulatory requirements and that it 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 who are knowledgeable regarding those 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.

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 Keith Young, the team leader, in the Region I Office at 610-337-5293.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosures:

1. Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation cc: Distribution via ListServ

D. Heacock We request that during the on-site inspection weeks, you ensure that copies of analyses, evaluations or documentation regarding the implementation and maintenance of the station fire protection program, including post-fire safe shutdown capability, be readily accessible to the team for their review. Of specific interest for the fire protection portion of the inspection are those documents which establish that your fire protection program satisfies NRCs 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 who are knowledgeable regarding those 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.

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 Keith Young, the Team Leader, in the Region I Office at 610-337-5293.

Sincerely,

/RA/

John F. Rogge, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-336 and 50-423 License Nos. DPR-65 and NPF-49

Enclosures:

1. Fire Protection Program Supporting Documentation

2. Mitigating Strategies Supporting Documentation cc: Distribution via ListServ Distribution: (See Next Page)

ML16074A256 SUNSI Review Non-Sensitive Publicly Available OFFICE RI/DRS RI/DRS NAME KYoung/KY JFRogge/JFR DATE 03/11/2016 03/14/2016 ENCLOSURE 1 Fire Protection Program 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 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 of course always 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)

Fire Probabilistic Risk Assessment (PRA) Summary Document (request A.4)

Based on review of the above four documents, team leader should 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 Probabilistic Risk Assessment (PRA) Summary Document (if available).

A.5 Fire Protection Program and/or Fire Protection Plan.

A.6 LIST of post-fire safe shutdown or alternative shutdown systems (i.e., safe shutdown equipment list).

A.7 Fire Protection System Design Basis Document.

A.8 Post-fire Safe Shutdown or Alternative Shutdown Design Basis Document.

2 A.9 LIST of applicable NFPA codes and standards (i.e., codes of record).

A.10 LIST of deviations from NFPA codes of record.

A.11 NFPA Compliance Review Report (if available).

A.12 Report or evaluation that compares the fire protection program to the NRC Branch Technical Position (BTP) 9.5-1 Appendix A.

A.13 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.14 COPY of NRC Safety Evaluation Reports for fire protection program and post-fire safe shutdown or alternative shutdown features.

A.15 COPY of NRC approved exemptions for plant fire protection and post-fire safe shutdown or alternative shutdown features.

A.16 COPY of exemption requests submitted but not yet approved for plant fire protection and post-fire safe shutdown or alternative shutdown features.

A.17 Facility Operating License.

A.18 Technical Specifications (electronic format only).

A.19 Technical Requirements Manual (electronic format only).

A.20 Updated Final Safety Analysis Report (electronic format only).

B. GENERAL PLANT DESIGN DOCUMENTS B.1 Piping and instrumentation diagrams (P&IDs) for post-fire safe shutdown or alternative shutdown systems (C-size paper drawings).

B.2 P&IDs for fire protection systems, including fire water supply, water suppression sprinklers &

deluge, and CO2 and Halon systems (C-size paper drawings).

B.3 Yard layout drawings for underground fire protection buried piping (C-size paper drawings).

B.4 Layout or arrangement drawings of reactor coolant pump lube oil system leakage points and associated lube oil collection systems (C-size paper drawings) (PWRs only).

B.5 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).

B.6 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).

B.7 Equipment location drawings which identify the physical plant locations of post-fire safe shutdown or alternative shutdown equipment (C-size paper drawings).

3 B.8 Plant layout drawings which identify: (C-size paper drawings)

Plant fire area boundaries;

Combustible control zone drawings (if available);

Areas protected by automatic fire suppression and detection; and

Locations of fire protection equipment.