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Regulations, Guidance, and Communications
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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,
generic communications, branch technical positions, and industry consensus
standards.
On this page:
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 |
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 |
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 |
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 |
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 |
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 |
REGULATORY ISSUE SUMMARIES |
Number |
Title |
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 |
RIS-07-06 |
Regulatory Guide 1.200 Implementation |
RIS-06-10 |
Regulatory Expectations with Appendix R Paragraph III.G.2, Operators
Manual Actions |
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 |
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-80-25 |
Transportation of Pyrophoric Uranium |
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-91-47 |
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-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-05-32 |
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-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 |
Other Related Documents:
- 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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