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Regulations, Guidance, and Communications

NRC Regulations, Guidance and Communications.
NRC Regulations, Guidance, and Communications for Fire Protection Programs in Nuclear Reactors

The Commission's requirements for nuclear plant fire protection programs are promulgated in a number of regulations and supporting guidelines, including Regulatory Guides, NUREG-series publications, standards.

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Regulations

NRC's regulations are found in Chapter I of Title 10, "Energy," of the Code of Federal Regulations (CFR). Chapter I is divided into Parts 1 through 199. The following are the principal parts and sections governing fire protection at nuclear reactors:

See also our Operating Reactors Regulations, Guidance, and Communications page. The NRC Regulatory Agenda (NUREG-0936) is a semiannual compilation of brief descriptions of all rulemaking actions.

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Guidance

Regulatory guides are issued in 10 divisions and are intended to aid licensees in implementing regulations. The regulatory guides listed below apply to fire protection at nuclear reactors.

REGULATORY GUIDES
Number Title
RG 1.75,
Rev. 2
Physical Independence of Electric Systems, dated September 1978
RG 1.174 An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, dated July 1998
RG 1.175 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing, dated August 1998 RS809-5 Qualification Test for Cable Penetration Fire Stops for Use in Nuclear Power Plants, dated September 1979
RG 1.189,
Rev. 1
Fire Protection for Nuclear Power Plants
RG 1.191 Nuclear Power Plants During Decommissioning and Permanent Shutdown
RG 1.205 Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
DG-1218 Final Draft Revision 1 of RG 1.205, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
DG-1214 Draft Revision 2 of RG 1.189. “ Fire Protection for Nuclear Power Plants”
RG 1.189 Rev.2 Fire Protection for Nuclear Power Plants
RG 1.205, Rev.1 Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants

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The NUREG sections listed below apply to fire protection at nuclear reactors.

NUREG-SERIES PUBLICATIONS
Designator Title
NUREG-0800,
Sec. 9.5.1, Rev. 5
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants Fire Protection Program
NUREG-0800,
Sec. 19.0
Use of Probabilistic Risk Assessment in Plant-Specific, Risk-Informed Decisionmaking: General Guidance
NUREG-0933 A Prioritization of Generic Safety Issues, dated April 1999
NUREG-1022,
Rev. 1
Event Reporting Guidelines: 10 CFR 50.72 and 50.73, dated January 1998
NUREG-1552 Fire Barrier Penetration Seals in Nuclear Power Plants, dated July 1, 1996
NUREG-1552,
Supp. 1
Fire Barrier Penetration Seals in Nuclear Power Plants, dated January 1999

NUREG-1742,
Volumes 1 & 2

Perspectives Gained from the IPEEE Program, Volumes 1 & 2

NUREG-1805

Fire Dynamics Tools (FDTs) Quantitative Fire Hazard Analysis Methods for the U. S. Nuclear Regulatory Commission Fire Protection Inspection Program

NUREG-1824,
Volume 1, DFC

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 1: Main Report; Draft for Comment

NUREG-1824,
Volume 2, DFC

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 2: Fire Dynamics Tools (FDTs); Draft for Comment
NUREG-1824,
Volume 3, DFC

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 3: Fire Induced Vulnerability Evaluation (FIVE-Rev 1); Draft for Comment

NUREG-1824,
Volume 4, DFC
Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 4: Consolidated Fire Growth and Smoke Transport Model (CFAST); Draft for Comment
NUREG-1824,
Volume 5, DFC

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 5: MAGIC; Draft for Comment

NUREG-1824,
Volume 6, DFC

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 6: Fire Dynamics Simulator (FDS); Draft for Comment

NUREG-1824,
Volume 7, DFC

Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications, Volume 7: Experimental Uncertainty; Draft for Comment

NUREG/CR-6850,
Volume 1

EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 1: Summary & Overview

NUREG/CR-6850,
Volume 2

EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 2: Detailed Methodology

NUREG-1852 NRC-RES Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire - Final Report
NUREG-0800, Section 9.5.1.2
Rev. 0
Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants Fire Protection Program, Section 9.5.1.2, “Risk-Informed, Performance-Based Fire Protection Program”
NUREG-1924
Electric Raceway Fire Barrier Systems in U.S. Nuclear Power Plants

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Communications

Generic Communications are NRC's primary method of sending information to specific classes of licensees. The several types are Bulletins (BLs), Generic Letters (GLs), Regulatory Issue Summaries (RIS), Information Notices (INs), and Administrative Letters (ALs).

ADMINISTRATIVE LETTERS
Number Title
AL-94-03 Announcing an NRC Inspection Procedure on Licensee Self Assessment Programs for NRC Area-of-Emphasis Inspection
AL-94-03,
Att. 1
Inspection Procedure 40501: Licensee Self-Assessments Related to Area-of-Emphasis Inspections
AL-94-07 Distribution of Site Specific and State Emergency Planning Information
AL-95-06 Relocation of Technical Specification Administrative Controls Related to Quality Assurance
AL-96-04 Efficient Adoption of Improved Standard Technical Specifications
AL-98-02 Revisions to Event Reporting Guidelines for Power Reactors
AL-98-09 Priority for NRR Review of Risk Informed Licensing Actions
AL-98-10 Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety

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BULLETINS
Number Title
BL-75-04 Cable Fire at Browns Ferry Nuclear Power Station
BL-75-04A Cable Fire at Browns Ferry Nuclear Power Station
BL-75-04B Cable Fire at Browns Ferry Nuclear Power Station
BL-77-08 Assurance of Safety and Safeguards During an Emergency - Locking Systems, dated December 28, 1977
BL-78-01 Flammable Contact-Arm Retainers in G.E. CR120A Relays
BL-78-03 Potential Explosive Gas Mixture Accumulation Associated with BWR Offgas System Operations
BL-81-03 Flow Blockage of Cooling Water to Safety System Components by Corbicula sp. (Asiatic Clam) and Mytilus sp. (Mussel), dated April 10, 1981
BL-92-01 Failure of Thermo-Lag 330 Fire Barrier System to Maintain Cabling in Wide Cable Trays and Small Conduits Free from Damage, dated June 24, 1992
BL-92-01,
Supp. 1
Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function, dated August 28, 1992

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CIRCULARS
Number Title
CIR-77-03 Fire Inside a Motor Control Center
CIR-78-04 Installation Error that Could Prevent Closing of Fire Doors
CIR-78-18 UL Fire Test
CIR-79-13 Replacement of Diesel Fire Pump Starting Contactors

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GENERIC LETTERS
Number Title
GL-77-02 Fire Protection Functional Responsibilities, Administrative Control and Quality Assurance
GL-80-45 Fire Protection Rule
GL-80-48 Revision To 5/19/80 Letter on Fire Protection
GL-80-56 Commission Memorandum and Order on Equipment Qualification
GL-80-96 Fire Protection
GL-80-100 Appendix R to 10 CFR 50 Regarding Fire Protection - Federal Register Notice, dated November 24, 1980
GL-80-103 Fire Protection - Revised Federal Register Notice, dated November 25, 1980
GL-81-12 Fire Protection Rule (45 FR 76602, 11/19/80), dated February 20, 1981
GL-81-12
Clarification
Clarification Letter to Generic Letter 1981-012
GL-85-01 Fire Protection Policy Steering Committee Report
GL-85-01,
Enc. 1
Recommended Fire Protection Policy and Program Actions
GL-82-21 Technical Specifications for Fire Protection Audits, dated October 6, 1982
GL-83-33 NRC Positions on Certain Requirements of Appendix R to 10 CFR 50, dated October 19, 1983
GL-85-01 Fire Protection Policy Steering Committee Report, dated January 9, 1985
GL-86-10 Implementation of Fire Protection Requirements, dated April 24, 1986
GL-86-10,
Supp. 1
Fire Endurance Test Acceptance Criteria for Fire Barrier Systems used to Separate Redundant Safe Shutdown Trains within the Same Fire Area, dated March 25, 1994
GL-88-12 Removal of Fire Protection Requirements from Technical Specifications
GL-88-20 Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54(f), dated November 23, 1988
GL-88-20,
Supp. 1
Initiation of the Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54(f), dated August 29, 1989
GL-88-20,
Supp. 2
Accident Management Strategies for Consideration in the Individual Plant Examination Process, dated April 4, 1990
GL-88-20,
Supp. 4
Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities, dated June 28, 1991
GL-88-20,
Supp. 5
Individual Plant Examination of External Events for Severe Accident Vulnerabilities, dated September 8, 1995
GL-89-13,
Service Water System Problems Affecting Safety-Related Equipment, dated July 18, 1989
GL-89-13,
Supp. 1
Service Water System Problems Affecting Safety-Related Equipment
GL-91-18 Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and Operability
GL-91-18,
Rev. 1
Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions, dated October 8, 1997
GL-91-18,
Rev. 1, Att. 1
NRC Inspection Manual, Part 9900: Technical Guidance: Resolution of Degraded and Nonconforming Conditions
GL-92-08 Thermo-Lag 330-1 Fire Barriers, dated December 17, 1992
GL-93-03 Verification of Plant Records, dated October 20, 1995
GL-93-06 Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas", dated October 25, 1993
GL-93-06,
Enc. 1
NUREG-1364: Regulatory Analysis for the Resolution of Generic Safety Issue 106: Piping and the Use of Highly Combustible Gasses in Vital Areas
GL-95-01 NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities
GL-03-01 Control Room Habitability
GL-06-03 Potentially Nonconforming Hemyc and MT Fire Barrier Configurations

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REGULATORY ISSUE SUMMARIES
Number Title
RIS-99-02 Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes
RIS-01-09 Control of Hazard Barriers
RIS-04-03 Risk-Informed Approach for Post-Fire Safe-Shutdown Circuit Inspections
RIS-04-03,
Rev. 1
Risk-Informed Approach for Post-Fire Safe-Shutdown Circuit Inspections, Revision 1
RIS-05-07 Compensatory Measures to Satisfy the Fire Protection Program Requirements
RIS-05-20 Revision to Guidance Formerly Contained in NRC Generic Letter 91-18, "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability"
RIS-05-20,
Att. 1
NRC Inspection Manual Part 9900: Technical Guidance Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety

RIS-05-30

Clarification of Post-Fire Safe-Shutdown Circuit Regulatory Requirements

RIS-06-10 Regulatory Expectations with Appendix R Paragraph III.G.2, Operators Manual Actions
RIS-07-06 Regulatory Guide 1.200 Implementation
RIS-07-19 Process for Communicating Clarification of Staff Positions Provided in Regulatory Guide 1.205 Concerning Issues Identified During the Pilot Application of National Fire Protection Association Standard 805

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INFORMATION NOTICES
Number Title
IN-79-32 Separation of Electrical Cables for HPCI and ADS
IN-80-11 Generic Problems with ASCO Valves in Nuclear Applications Including Fire Protection Systems
IN-81-27 Flammable Gas Mixtures in the Waste Gas Decay Tanks in PWR Plants
IN-82-28 Hydrogen Explosion While Grinding in the Vicinity of Drained and Open Reactor Coolant System
IN-82-53 Main Transformer Failures at the North Anna Nuclear Power Station
IN-83-41 Actuation of Fire Suppression System Causing Inoperability of Safety-Related Equipment, dated June 22, 1983
IN-83-69 Improperly Installed Fire Dampers at Nuclear Power Plants, dated October 21, 1983
IN-83-83 Use of Portable Radio Transmitters Inside Nuclear Power Plants
IN-84-09 Lessons Learned from NRC Inspections of Fire Protection Safe Shutdown Systems (10 CFR 50, Appendix R), dated February 13, 1984
IN-84-09,
Rev. 1
Lessons Learned from NRC Inspections of Fire Protection Safe Shutdown Systems (10 CFR 50, Appendix R), dated March 7, 1984
IN-84-16 Failure of Automatic Sprinkler System Valves to Operate, dated March 2, 1984
IN-84-42 Equipment Availability for Conditions During Outages not Covered by Technical Specifications
IN-84-92 Cracking of Flywheels on Cummins Fire Pump Diesel Engines
IN-85-09 Isolation Transfer Switches and Post-Fire Shutdown Capability, dated January 31, 1985
IN-85-30 Microbiologically Induced Corrosion of Containment Service Water System
IN-85-85 Systems Interaction Event Resulting in Reactor System Safety Relief Valve Opening Following a Fire Protection Deluge System Malfunction
IN-86-13 Standby Liquid Control System Squib Valves Failure to Fire
IN-86-13,
Supp. 1
Standby Liquid Control System Squib Valves Failure to Fire
IN-86-17 Update of Failure of Automatic Sprinkler System Valves to Operate
IN-86-106 Feedwater Line Break
IN-86-106, Supp. 1 Feedwater Line Break
IN-86-106, Supp. 2 Feedwater Line Break
IN-86-106, Supp. 3 Feedwater Line Break
IN-86-35 Fire in Compressible Material at Dresden Unit 3, dated May 15, 1986
IN-87-14 Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment, dated March 23, 1987
IN-87-20 Hydrogen Leak in Auxiliary Building
IN-87-50 Potential LOCA at High- and Low-Pressure Interfaces from Fire Damage
IN-88-04 Inadequate Qualification and Documentation of Fire Barrier Penetration Seals, dated February 5, 1988
IN-88-05 Fire in Annunciator Control Cabinets
IN-88-04,
Supp. 1
Inadequate Qualification and Documentation of Fire Barrier Penetration Seals, dated August 9, 1988
IN-88-45 Problems in Protective Relay and Circuit Breaker Coordination, dated July 7, 1988
IN-88-56 Potential Problems With Silicone Foam Fire Barrier Penetration Seals, dated August 4, 1988
IN-88-60 Inadequate Design and Installation of Watertight Penetration Seals
IN-88-61 Control Room Habitability - Recent Reviews of Operating Experience
IN-88-64 Reporting Fires in Nuclear Process Systems at Nuclear Power Plants
IN-89-44 Hydrogen Storage on the Roof of the Control Room
IN-89-52 Potential Fire Damper Operational Problems, dated June 8, 1989
IN-90-70 Pump Explosions Involving Ammonium Nitrate
IN-91-17 Fire Safety of Temporary Installations or Services, dated March 11, 1991
IN-91-20 Electrical Wire Insulation Degradation Caused Failure in a Safety-Related Motor Control Center
IN-91-37 Compressed Gas Cylinder Missile Hazards
IN-91-63 Natural Gas Hazards at Fort St. Vrain Nuclear Generating Station
IN-91-47 Failure of Thermo-Lag Fire Barrier Material to Pass Fire Endurance Test, dated August 6, 1991
IN-91-53 Failure of Remote Shutdown System Instrumentation Because of Incorrectly Installed Components
IN-91-77 Shift Staffing at Nuclear Power Plants, dated November 26, 1991
IN-91-79 Deficiencies in the Procedures for Installing Thermo-Lag Fire Barrier Materials, dated December 6, 1991
IN-91-79,
Supp. 1
Deficiencies in the Procedures for Installing Thermo-Lag Fire Barrier Materials, dated August 4, 1994
IN-92-14 Uranium Oxide Fires at Fuel Cycle Facilities
IN-92-18 Potential for Loss of Remote Shutdown Capability During a Control Room Fire, dated February 28, 1992
IN-92-28 Inadequate Fire Suppression System Testing, dated April 8, 1992
IN-92-46 Thermo-Lag Fire Barrier Material Special Review Team Final Report Findings, Current Fire Endurance Tests, and Ampacity Calculation Errors, dated June 23, 1992
IN-92-46,
Att. 1
Final Report of the Special Review Team for the Review of Thermo-Lag Fire Barrier Performance
IN-92-55 Current Fire Endurance Test Results for Thermo-Lag Fire Barrier Material, dated July 27, 1992
IN-92-82 Results of Thermo-Lag 330-1 Combustibility Testing, dated December 15, 1992.
IN-93-33 Potential Deficiency of Certain Class 1E Instrumentation and Control Cables, dated April 28, 1993
IN-93-40 Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material, dated May 26, 1993
IN-93-41 One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems, dated May 28, 1993
IN-93-71 Fire at Chernobyl Unit 2
IN-94-12 Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment, dated February 9, 1994
IN-94-22 Fire Endurance and Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers, dated March 16, 1994
IN-94-26 Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor
IN-94-28 Potential Problems with Fire Barrier Penetration Seals
IN-94-31 Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles
IN-94-34 Thermo-Lag 330-660 Flexi-Blanket Ampacity Derating Concerns, dated May 13, 1994.
IN-94-53 Hydrogen Gas Burn Inside Pressurizer During Welding
IN-94-58 Reactor Coolant Pump Lube Oil Fire, dated August 16, 1994
IN-94-86 Legal Actions Against Thermal Science, Inc., Manufacturer of Thermo-Lag, dated December 22, 1994
IN-94-86,
Supp. 1
Legal Actions Against Thermal Science, Inc., Manufacturer of Thermo-Lag, dated November 15, 1995
IN-95-27 NRC Review of Nuclear Energy Institute, "Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide", dated May 31, 1995
IN-95-32 Thermo-Lag 330-1 Flame Spread Test Results, dated August 10, 1995
IN-95-33 Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3, dated August 23, 1995
IN-95-36 Potential Problems with Post-Fire Emergency Lighting, dated August 29, 1995
IN-95-36,
Supp. 1
Potential Problem with Post-Fire Emergency Lighting, dated June 10, 1997
IN-95-48 Results of Shift Staffing Study, dated October 10, 1995
IN-95-49 Seismic Adequacy of Thermo-Lag Panels, dated October 27, 1995
IN-95-49,
Supp. 1
Seismic Adequacy of Thermo-Lag Panels, dated December 10, 1997
IN-95-52 Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials, dated November 14, 1995
IN-95-52,
Supp. 1
Fire Endurance Test Results for Electrical Raceway Fire Barrier Systems Constructed from 3M Company Interam Fire Barrier Materials, dated March 17, 1998
IN-96-23 Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing
IN-96-33 Erroneous Data from Defective Thermocouple Results in a Fire
IN-96-34 Hydrogen Gas Ignition During Closure Welding of a VSC 24 Multi Assembly Sealed Basket
IN-97-01 Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room, dated January 8, 1997
IN-97-23 Evaluation and Reporting of Fires and Unplanned Chemical Reactor Events at Fuel Cycle Facilities
IN-97-37 Main Transformer Fault with Ensuring Oil Spill into Turbine Building
IN-97-48 Inadequate or Inappropriate Interim Fire Protection Compensatory Measures, dated July 9, 1997
IN-97-59 Fire Endurance Test Results of Versawrap Fire Barriers, dated August 1, 1997
IN-97-70 Potential Problems with Fire Barrier Penetration Seals, dated September 19, 1997
IN-97-72 Potential for Failure of the Omega Series Sprinkler Heads
IN-97-73 Fire Hazard in the Use of a Leak Sealant, dated September 23, 1997
IN-97-82 Inadvertent Control Room Halon Actuation Due to a Camera Flash
IN-98-31 Fire Protection System Design Deficiencies and Common-Mode Flooding of Emergency Core Cooling System Rooms at Washington Nuclear Project Unit 2, dated August 18, 1998
IN-99-03 Exothermic Reactions Involving Dried Uranium Oxide Powder (Yellowcake)
IN-99-05 Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration, dated March 8, 1999
IN-99-07 Failed Fire Protection Deluge Valves and Potential Testing Deficiencies in Preaction Sprinkler Systems, dated March 22, 1999
IN-99-17 Problems Associated with Post-Fire Safe-Shutdown Circuit Analyses, dated June 3, 1999
IN-99-28 Recall of Star Brand Fire Protection Sprinkler Heads
IN-99-28,
Supp. 1
Recall of Star Brand Fire Protection Sprinkler Heads
IN-99-34 Potential Fire Hazard in the Use of Polyalphaolefin in Testing of Air Filters
IN-00-12 Potential Degradation of Firefighter Primary Protective Garments, dated September 21, 2000.
IN-00-14 Non-Vital Bus Fault Leads to Fire and Loss of Offsite Power, dated September 27, 2000
IN-01-04 Neglected Fire Extinguisher Maintenance Causes Fatality, dated April 11, 2001
IN-01-10 Failure of Central Sprinkler Company Model GB Series Fire Sprinkler Head, dated June 28, 2001
IN-01-12 Hydrogen Fire at Nuclear Power Station, dated July 13, 2001
IN-01-12
(Errata)
Hydrogen Fire at Nuclear Power Station, dated August 8, 2001
IN-02-01 Metalclad Switchgear Failures and Consequent Losses of Offsite Power, dated January 8, 2002
IN-02-04 Wire Degradation at Breaker Cubicle Door Hinges, dated January 10, 2002.
IN-02-07 Use of Sodium Hypochlorite for Cleaning Diesel Fuel Oil Supply Tanks, dated January 28, 2002
IN-02-15 Hydrogen Combustion Events in Foreign BWR Piping, dated April 12, 2002
IN-02-15,
Supp. 1
Potential Hydrogen Combustion Events in BWR Piping
IN-02-24 Potential Problems with Heat Collectors on Fire Protection Sprinklers, dated August 19, 2002
IN-02-27 Recent Fires at Commercial Nuclear Power Plants in the United States, dated September 2, 2002
IN-03-19 Unanalyzed Condition of Reactor Coolant Pump Seal Leakoff Line During Postulated Fire Scenarios or Station Blackout
IN-04-19 Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment
IN-05-01 Halon Fire-Extinguishing System Piping Incorrectly Connected
IN-05-03 Inadequate Design and Installation of Seismic-Gap Fire Barriers
IN-05-04 Single-Failure and Fire Vulnerability of Redundant Electrical Safety Buses
IN-05-07 Results of Hemyc Electrical Raceway Fire Barrier System Full Scale Fire Testing
IN-05-14 Fire Protection Findings on Loss of Seal Cooling to Westinghouse Reactor Coolant Pumps
IN-05-20 Electrical Distribution System Failures Affecting Security Equipment
IN-05-32 Product Alert for Fire Hydrants
IN-06-02 Use of Galvanized Supports and Cable Trays with Meggitt Si 2400 Stainless-Steel-Jacketed Electrical Cables
IN-06-31 Inadequate Fault Interrupting Rating of Breakers
IN-07-07 Potential Failure of All Control Rod Groups to Insert in a Boiling Water Reactor Due to a Fire
IN-07-12 Tactical Communications Interoperability Between Nuclear Power Reactor Licensees and First Responders
IN-07-17 Fire at Nuclear Power Plants involving Inadequate Fire Protection Administrative and Design Control
IN-07-19 Fire Protection Recalls and Design Notices
IN-07-23 Inadvertent Discharge of Halon 1301 Fire Suppression System from Incorrect and/or Out-of-date Procedures
IN-07-26 Combustibility of Epoxy Floor Coatings at Commercial Nuclear Power Plants
IN-07-27 Recurring Events Involving Emergency Diesel Generator Operability
IN-08-05 Fire Involving Emergency Diesel Generator Exhaust Manifolds
IN-09-29 Potential Failure of Fire Water Supply Pumps to Automatically Start Due to a Fire
IN-10-09 Importance of Understanding Circuit Breaker Control Panel Indications

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INSPECTION DOCUMENTS
Number Title
71111.05XT Attachment 71111.05XT – Fire Protection – NFPA 805 (Triennial)
EA-09-307 Browns Ferry Nuclear Plant - NRC Triennial Fire Protection Inspection Report
71111.05AQ Fire Protection Annual/Quarterly
71111.05T Fire Protection [Triennial]
71111.05TTP Fire Protection – NFPA 805 Transition Period (Triennial)
Inspection Manual
Chapter 0609F
Fire Protection Significance Determination Process

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Additional Information

  • An August 29, 1977, memorandum to Toledo Edison also transmitted fire protection guidance.
  • Office Letter 803, Revision 3, License Amendment Review Procedures, is applicable to fire protection.
  • One regulatory issue summary, 99-02, Relaxation of the Technical Specification Requirements for Porc Review of Fire Protection Program Changes, dated October 13, 1999, is applicable to fire protection.
  • One Branch Technical Position provide guidance, Appendix A to Branch Technical Position APCSB 9.5-1, Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976 (August 23, 1976).

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Page Last Reviewed/Updated Tuesday, February 25, 2014