ML15259A031
| ML15259A031 | |
| Person / Time | |
|---|---|
| Issue date: | 09/16/2015 |
| From: | Barrett H, Giitter J, Js Hyslop, Markhenry Salley NRC/NRR/DRA, NRC/RES/DRA |
| To: | Nuclear Energy Institute |
| Frumkin D | |
| References | |
| Download: ML15259A031 (69) | |
Text
The Journey to a More Predictable Regulatory Framework for Fire Safety Joseph Giitter, Director Division of Risk Assessment Office of Nuclear Reactor Regulation g
U.S. Nuclear Regulatory Commission NEI Fire Protection Information Forum September 2015
NFPA 805 2
NFPA 805 Status 2
LA Issued 3
LA Finalization 14 Application pp Under Review,, 2nd Round of RAIs 8 Review Complete, Licensee Initiated Changes Scheduled to be submitted 0 2 3
NFPA 805 Communications
- Over the past year
- Approximately 100 bi-monthly status calls with site VPs
- Approximately a dozen Frequently Asked Questions g
calls/meetings
- Periodic public senior management meetings
- Several topic specific meetings 5
NFPA 805 Implementation
- Major efforts by licensees to complete transition and implementation
- Greater focus on inspections
- NRC staff have been providing training to Regional Inspectors and support the NFPA 805 triennial inspections
- Inspection results have been low level findings of green significance.
6
Lessons Learned Significant safety improvements Licensing basis clarity Continual engagement and communication between NRC and industry Challenges resulting from the use of unapproved methods and emergent issues New approaches to address PRA suitability (scope, level of detail, and technical adequacy) are needed 7
PRA Technical Adequacy Working Group Objectives j
- Develop a suitable process for making new PRA methods available for risk-informed regulatory applications.
- Improve process for closure of peer review Facts and Observations (F&Os).
- Evaluate gaps in current peer review process.
Path Forward
- NRC WG is reviewing the final whitepaper whitepaper.
- Future work will be addressed by the appropriate line organizations.
Alternative PRA Certification Certification Concept
- More in-depth than peer review
- Performed by an independent body that would include NRC participation
- Outcome:
- a certified PRA model that a licensee could use to make licensing decisions with ith m muchch less NRC re review ie than at present
- Comparable risk numbers across plants (i.e., risk would be less dependent upon analyst analystss assumptions or choice of methods)
- No outstanding F&Os (must be fixed and re-reviewed before the Authority certifies the model) 9
Fire Research
- Refining And Characterizing Heat Release Rates From Electrical E l Enclosures D During i FiFire (RACHELLE-FIRE) - (NUREG-2178, Volume 1, EPRI 3002005578)
- Heat Release Rates of Electrical Enclosure Fires (HELEN-FIRE) -(NUREG/CR-7197)
- g Nuclear Power Plant Fire Ignition Frequency q y and Non-Suppression pp Probability Estimation Using the Updated Fire Events Database: United States Fire Event Experience Through 2009 (NUREG-2169, EPRI 3002002936)
- Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities
(
(DELORES-VEWFIRE)-(NUREG-2180)
)( )
Outside of NFPA 805
- Watts Bar 2
- License Amendment Request Reviews
- Public Release of Fire Protection Documents
Conclusion
- Risk-informed, Risk informed, performance based alternatives to prescriptive, deterministic g
regulations can be successfully y implemented
- Lessons learned from NFPA 805 and g g research are continuing ongoing g to enhance the regulatory framework for fire safety for all nuclear plants in the U.S.
12
Fire PRA Technical Adequacy f Risk-Informed for Ri k I f d Applications A li ti J.S. Hyslop Sr. Reliability and Risk Engineer PRA Licensing Li i B Branch,h US NRC/NRR Presented to NEI Fire Protection Information Forum,,
Phoenix, 9/2015
Background
g
- Integrated leak rate testing (ILRT)
- S Surveillance ill ffrequency (TSTF (TSTF-425) 425)
- Risk-informed completion time (TSTF-505)
- Limited technical specification change
- Categorization of SSCs as safety significant vs. safety related (10CFR 50.69)
- N No fi fire assessmentt needed d d ffor Ri Risk-Informed kI f d Inservice Inspection (RI ISI); and thus no requirement for quality for fire
Phased Approach to PRA Quality
- Phase 3 of p phased PRA q qualityy achieved
- Guidance for phase 3 completed with issuance of RG 1.200 Rev.2 (SECY-10-0143)
- All significant g modes and initiators that could change g the decision substantially should be quantified, and include an uncertainty analysis
- Other modes and initiators allow less robust quality
- Significant modes and initiators must have peer review done on respective PRA
- Phase 2 applications still allowed
- Quality of PRA must be compatible with safety implications of proposed change and the role PRA plays in justifying the change (RG 1.174)
Risk Informed Completion Time Applications
- Plant-wide application
- Can extend out of service time to 30 days
- Requires a fire PRA peer review; fire and internal events to be treated comparably for quality and need CCII PRA
- More limited tech spec change can vary with respect to fire importance p
- SE for TSTF 505 states that when key assumptions introduce a source of uncertainty to the risk calculations, TR NEI 06-09, Revision 0, requires analysis of the assumptions and an accounting for their impact on the calculated risk informed completion times.
Approaches Used for Other Applications
- Fire generally treated differently for applications other than TSTF-505.
- Other applications are ILRT ILRT, TSTF-425 TSTF 425, or 10CFR 50.69
- Fire PRA contribution to total risk can exceed internal events
- Quality requirements distinguish between fire and internal events
- For these other applications, applications IPEEEs continued to be allowed to address fire
- Staff moving steadily toward use of fire PRA, if available in most cases available,
Concluding g Observations
- More rigorous fire requirements for quality where fire is clearly substantial to the decision - need for a fire PRA
- For other applications, analyses less robust than fire PRA allowed
- Staff moving steadily to using fire PRA, if available.
available
- Phase 4 of phased approach to PRA (full quantification) tifi ti ) would ld raise i b bar
Backup Slide - ILRT
- SE references EPRI 1009325 Rev 2: Risk impact to extend surveillance interval to 15 years is small small, but due to the possibility of an outlying plant, a confirmatory risk impact assessment is prudent.
- SE: Capability category I for IE
- EPRI 1009325, Rev 2A: Where possible, should have a quantitative evaluation of fire. fire Must be of sufficient quality or detail.
- Staff moving g steadily y towards use of fire PRA,, if available
Backup Slide - Surveillance Frequency
- SE: CCII for Internal events PRA
- Where quantitative q antitati e fire risk models are unavailable, the staff continues to allow IPEEEs
- Staff moving steadily towards use of fire PRA, if available
- SE: Qualitative evaluations are acceptable t show to h negligible li ibl or zero fifire risk i k iimpactt
Backup Slide - Categorization of SSCs
- RG 1.201 Rev 1: Apply fire PRA which meets RG 1 200 if it is used for categorization 1.200, categorization.
- Staff is still allowing a conservative treatment for fire to categorize SSCs
- NEI 00-04 00 04 identifies id tifi allll system t ffunctions ti andd associated SSCs that are involved in the mitigation of any unscreened fire scenario (i.e., retained in the FIVE analysis) as safety significant.
significant
- In addition, all screened scenarios are reviewed to identify any system functions and associated SSCs that would result in a scenario being unscreened, unscreened if that system function was not credited
Backup Slide - Tech Spec Change
- RG 1.177 Rev 1: PRA that meets RG 1.200 for IE and for fire. CCII necessary for majority of applications.
- According to RG 1.174 Rev 1, should fire not affect ff t the th decision d i i b being i made, d lless robust b t analysis is acceptable
- Staff experience consists of acceptable fire bounding analysis, and detailed fire PRA review when top 10 cutsets were from fire PRA
MSO and Licensing Basis Harry Barrett, PE Senior Fire Protection Engineer US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Risk Assessment
Topics for Discussion
- Current Status
- New Information
- R Regulatory l t F Footprint t i t
- Final Endorsement 9/16/2015 NEI Fire Protection Information Forum 2015 24
Current Status
- Plants must meet their individual Fire Protection licensing basis
- TIA 20132013-02 02 (Braidwood/Byron Single Spurious) did not change this NEI Fire Protection Information Forum 9/16/2015 25 2015
New Information
- NUREG\CR NUREG\CR-7150, 7150, JACQUE JACQUE-FIRE FIRE Volume 3
- Revisions to Main Body of NEI 00-01 to address MSO guidance
- New Appendix I, Application of PIRT Results
- New Appendix J, Guidance on Shorting Switches
- New guidance on Proper Polarity Short Circuit Conditions
- New g guidance on hot short duration for DC circuits
- Open Circuited CT testing NEI Fire Protection Information Forum 9/16/2015 26 2015
Regulatory Footprint
- Similar to the process used for NUREG\CR- NUREG\CR 7150, JACQUE-FIRE Vol. 2
- When JACQUE-FIRE JACQUE FIRE Vol. 3 is in its final pre- pre publication form, NRC RES will draft an internal memorandum to NRR\DRA informing the technical h i l review i b branches h that h the h guidance id iis ready and available for use
- NRC NRR\DRA plans to send NEI a letter stating if or when the guidance may be used in regulated applications pp ((both risk informed and deterministic))
NEI Fire Protection Information Forum 9/16/2015 27 2015
Final Endorsement
- In parallel, NEI could publish new revision of NEI 00-01 with the new information
- Once JACQUE JACQUE-FIRE FIRE Vol Vol. 3 and NEI 00-01 00 01 have been issued:
- NRC will consider endorsing NEI 00-01 in applicable Regulatory Guides
- For non-NFPA 805 plants, RG 1.189 NEI Fire Protection Information Forum 9/16/2015 28 2015
QUESTIONS?
NEI Fire Protection Information Forum 9/16/2015 29 2015
NFPA 805 I
Inspection i E Experiencei Harry Barrett, PE Senior Fire Protection Engineer US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Risk Assessment
Topics for Discussion
- NFPA 805 Triennial Fire Protection Inspections
- NFPA 805 Inspector Training
- Findings
- Lessons Learned
- Summary y NEI Fire Protection Information Forum 9/16/2015 31 2015
NFPA 805 Triennial Fire Protection Inspections
- Pilots
- Shearon Harris
- 1st August/September 2011
- 2nd April/May 2014
- Oconee - July/August 2013
- Non-Pilots Non Pilots
- Duane Arnold - January/February 2015
- Callaway - April/May 2015
- Palisades - March/April 2015
- Nine Mile Point - June/July y 2015 NEI Fire Protection Information Forum 9/16/2015 32 2015
NFPA 805 Inspector p Training g
- Face to Face training performed
- Region II - prior to Pilot inspections
- Region III - prior to Duane Arnold
- Future training planned in Regions I and IV NEI Fire Protection Information Forum 9/16/2015 33 2015
NFPA 805 Inspection Findings
- Failure to evaluate all potentially risk significant fire scenarios (missed ignition source)
- Failure to evaluate all potentially risk significant fire scenarios (missed targets)
- Failure to model the as-built, as-operated and d maintained i t i d plant l t ((sprinkler i kl obstructions not modeled) 9/16/2015 NEI Fire Protection Information Forum 34
Lessons Learned
- NRC
- Large volume of documents to be reviewed
- Licensees could help p with roadmap p
- Helps to have SRA on team
- NRR support helped
- Some inspection teams were large
- Need to communicate with licensee (some observers inspectors in training observers, training, etc etc.))
- NRC will consider addressing the minor/more than minor threshold for NFPA 805 findings g NEI Fire Protection Information Forum 9/16/2015 35 2015
Lessons Learned - continued
- NRC
- NFPA 805 Triennial Inspection Procedure has been used numerous times now
- Does not appear to be any show stoppers
- We have some minor changes g we recommend
- Industry feedback on TFPI procedure?
NEI Fire Protection Information Forum 9/16/2015 36 2015
Lessons Learned - continued
- Industry
- Navigation through numerous analyses, calcs and other documents is very time consuming
- Providing the inspection team with a roadmap to explain the site-specific document structure would help
- Watch out for operational activities that may place system/component operations outside the PRA assumptions
- Monitoring Program must be vigilant with respect to system tagouts and pre-outage pre outage preparations NEI Fire Protection Information Forum 9/16/2015 37 2015
Lessons Learned - continued
- Industry - continued
- Try to risk-inform your fire brigade drills - be sure that your most risk risk-significant significant areas have been addressed in fire drills
- Verify that you have properly dispositioned MSO scenarios that result in vessel/SG overfeed NEI Fire Protection Information Forum 9/16/2015 38 2015
Summary
- Some of the early NFPA 805 plants have been inspected under the NFPA 805 Triennial Inspection procedure
- Violations of low safety significance have been identified
- Lessons Learned have been identified for b th NRC and both d IIndustry d t NEI Fire Protection Information Forum 9/16/2015 39 2015
QUESTIONS?
NEI Fire Protection Information Forum 9/16/2015 40 2015
NRC FIRE RESEARCH CURRENT RESEARCH ACTIVITIES Mark Henry Salley P.E.
Chief, Fire Research Branch U.S. Nuclear Regulatory Commission September 16 - 18, 18 2015 Phoenix, Phoenix AZ AZ.
September 16 - 18, 2015, Phoenix, Arizona 42 Goal of this Presentation
- Provide a High Level Overview of NRC Office of Nuclear Regulatory Research (RES) Fire Research Activities
- Updates on Long Term Projects
- Future Projects under Consideration
- Detailed Presentations on Specific Research Topics will be covered in other Plenary's
- Ashley and I will try to minimize duplication on joint NRC-RES/EPRI projects
September 16 - 18, 2015, Phoenix, Arizona 43 A word about Partnerships &
Collaborations Coming g together g is a beginning.
g g Keeping together is progress.
Working together is success. success "
--Henry y Ford
September 16 - 18, 2015, Phoenix, Arizona 44 Partnerships & Collaborations
- Fire Addendum for Fire Risk Research
- Oldest and Longest Running Addendum under the MOU
- National Institute Standards and Technology (NIST)
- Department of Energy (DOE) National Laboratories
- Sandia National Laboratories
- Brookhaven National Laboratories
- International Partnerships p
- The Organization for Economic Co-operation and Development (OECD)
- Committee on the Safety of Nuclear Installations
- Japan Nuclear Regulatory Authority (JNRA)
- Agreement g implemented p in 2012 between USNRC-RES and JNES
- JNES is now a part of Japan Nuclear Regulatory Authority
- Academia
- University of Maryland
September 16 - 18, 2015, Phoenix, Arizona 45 Fire Modeling - V&V
- NUREG-1824 Supplement 1 (EPRI 3002002182)
- Expands Number of Experiments
- Test Series: from 5 to 18
- Individual: from 26 to 340
- Uses Latest Versions of the Fire Models
- FDTs: 1805.0 to 1805.2
- FIVE: Rev. 1 to Rev. 2
- CFAST: Ver. 5 to Ver. 7
- MAGIC: Ver. 4.1.1 to Ver. 4.1.3
- FDS: Ver. 4 to Ver. 6
September 16 - 18, 2015, Phoenix, Arizona 46 Fire Modeling - V&V
- NUREG-1824 Supplement 1 (EPRI 3002002182)
- Improvements:
- Adds More Model Output Quantities
- Sprinkler/Smoke Detector Activation
- Electrical Cable Failure Time (THIEF)
- More Quantifiable Assessment of Model Accuracy
- Superseded Color Code V&V Table 3-1 NUREG-1824 Vol.1
- Complements NUREG-1934 (EPRI 1023259) Fire Model Application pp ca o Gu Guide de ((FMAG) G)
- Public Comment Period Closed - March 31, 2015
- Final Publication - Late 2015
September 16 - 18, 2015, Phoenix, Arizona 47 Fire Modeling - Continued
- NUREG-2164 Consolidation of the 1985 Sandia National Laboratories/Factory L b t i /F t Mutual M t l Main M i Control C t lR Room andd Electrical Cabinet Fire Test Data,
- Published: May, y 2015
- Greater use of Fire Modeling in other Projects:
- Obstructed Ob t t d Plume Pl Models M d l NUREG-2178 NUREG 2178 Vol.
V l 1 RACHELLE-FIRE RACHELLE FIRE
September 16 - 18, 2015, Phoenix, Arizona 48 Fire Detection
- Determining the Effectiveness, Limitations, and Operator Response ffor Very R V Early E l W Warning i FiFire D Detection t ti S Systemst in Nuclear Facilities (DELORES-VEWFIRE) NUREG-2180
- Issued 60-day Public Comment period closed September 8, 2015
- Received approximately 100 comments
- NRC and NIST staff members are working on addressing/resolving comments
- Final report should be back in publication process by end of year.
- One O Utility Utilit hash proposed d using i the th draft d ft version i tto supportt th their i
September 16 - 18, 2015, Phoenix, Arizona 49 Fire Detection Data, Method, Tools
- Draft NUREG-2180
- Provides Data and Method (risk scoping study) to support fire PRA
- Smoke Detection PRA Application tool being developed to support the final NUREG:
- Solves S l b th NUREG both NUREG-2180 2180 eventt ttree and d NUREG/CR NUREG/CR-6850 6850 detection/suppression event tree
- Similar format to NUREG-1805 FDTs
- Will be included on CD (and website) with final NUREG NUREG-report report
- Several errors/oversights in draft NUREG-2180 were identified via development of the Smoke Detection PRA Application Tool
- Public P bli comments t have h also l identified id tifi d ththese errors/oversights
/ i ht
- Errors/oversights will be corrected before the final NUREG is published
September 16 - 18, 2015, Phoenix, Arizona 50 Screen Shot of NUREG-2180 Smoke Detection PRA Application Tool
September 16 - 18, 2015, Phoenix, Arizona 51 NUREG 2178 Vol 1 (EPRI 3002005578)
- NUREG-2178 Vol 1 ((EPRI 3002005578)Refining ) g And Characterizing Heat Release Rates From Electrical Enclosures During Fire (RACHELLE-FIRE)
- Ashley Lindeman will provide a detailed discussion
- Final Report in process
- Follow-on Activities starting
- EPRI Fire Modeling
- RES/NIST Wall and Corner Effects Testing
- Draft Test Plan for Public Comment
- NUREG/CR-7197 Heat Release Rate of Electrical Enclosure Fires (HELEN-FIRE)
- Final Report in process with NIST
September 16 - 18, 2015, Phoenix, Arizona 52 Joint Analysis of ARC Faults (JOAN of ARC)
- OECD/NEA International Project j to Examine High g Energy gy Arcing Faults (HEAF) Fire Events
- OECD Fire Project-Topical Report No. 1 Analysis of High Energy Arcing Fault (HEAF) Fire Events. June 2013
- First Phase Testing Complete Fall 2014
- Final Phase Testing Scheduled for October 2015
- All Testing gp performed at KEMA Test Facility y in PA.
September 16 - 18, 2015, Phoenix, Arizona 53 Goal of the International HEAF Expert Panel
- OECD/NEA International Project j to Examine High g Energy gy Arcing Faults (HEAF) Fire Events (Continued)
- After Completion of Testing, form an International HEAF E
Expert t Panel:
P l
- NUREG/CR-6850 Appendix M
- Topical Report No. 1 (International HEAF Operating Experience
- Goal of International Project
- Using these 4 Key Reports Develop an Improved, International HEAF PRA Model (NUREG/CR-6850 Appendix M)
September 16 - 18, 2015, Phoenix, Arizona 54 Electrical Cable Fire Hazards
- Cable Heat Release Ignition, g , and Spread p in Trayy Installations during Fire (CHRISTIFIRE) NUREG/CR-7010
- Volume 1: Horizontal Trays, July 2012
- Volume 2: Vertical Shafts and Corridors , December 2013
- Volume 3 : Focus on Cable Ignition,
- Work currently on going
- Delayed because off higher priority work
September 16 - 18, 2015, Phoenix, Arizona 55 Electrical Circuit Performance
- Joint J i t Assessment A t off Cable C bl DDamage and d Quantification Q tifi ti off Effects from Fire (JACQUE-FIRE) NUREG/CR-7150 EPRI 1026424, 3002001998
- Volume Vol me 1 Phenomena Identification and Ranking Table (PIRT), October 2012
- Volume 2 Expert Elicitation Exercise, May 2014
- Volume 3
- Joint Project with EPRI
- Project j nearing g completion p
- Detailed Presentation in another plenary by Andy Ratchford
September 16 - 18, 2015, Phoenix, Arizona 56 Electrical Cable Coating Performance
- Response Bias of Electrical Cable Coatings at Fire Conditions (REBECCA (REBECCA-FIRE) NUREG-XXXX,
- Expanded Scope to 3 Volumes:
- Volume 1: History of the application, regulation and research of cable coatings materials
- Volume 2: Cable thermal response and electrical integrity performance
- ML15139A512 (NUREG/CR-6850 Appendix Q guidance)
- Volume 3: Flammability properties of the cable coatings
- Currently performing small scale flammability tests at NIST. These tests have focused on determining ignition temperature.
- Preliminary tests data show that coatings applied on thermoplastic cables tend to show small increases in the ignition temperature from those compared to the bare cable. Cable coatings applied on thermoset cables have shown no benefit.
- Future tests include intermediate scale tray tests. It is expected that a test plan will be sent out for public p comment in earlyy 2016.
September 16 - 18, 2015, Phoenix, Arizona 57 Compensatory Measures
- NUREG/CR-7135 NUREG/CR 7135 Compensatory Compensatory and Alternative Regulatory MEasures in Nuclear Power Plant FIRE Protection (CARMEN-FIRE) published August, 2015
- Documents the history of fire protection compensatory measures and the NRCs regulatory framework related to fire safety compensatory measures.
- Discuss new technologies such as video-based detection systems, temporary penetration seals, and portable suppression systems systems, that under certain conditions conditions, may offer an effective alternative to the measures specified in a plants approved fire protection program.
September 16 - 18, 2015, Phoenix, Arizona 58 Fire PRA Training
- Five Class Modules:
- Each Module will only be offered one week per year during different weeks
- EPRI provides Professional Development Credits
- Professional Engineer (PE) License Requirements in many states
- NRC Hosting at White Flint Headquarters
- Electrical Analysis, Fire Analysis, Advanced Fire Modeling
- Methods for Applying Risk Analysis to Fire Scenarios (MARIAFIRES) 2012 Draft report under development
- NRC and EPRI currently y discussing g how to p present annual updates p of material.
- Separate Training?
- Tied to NEI Fire Protection Forum?
September 16 - 18, 2015, Phoenix, Arizona 59 Knowledge Management
- Three Mile Island Accident of 1979 Knowledge Management Digest NUREG/KM-0001, NUREG/KM 0001, December 2012
- Revision currently in progress
- New Interface
- Greatly Expanded to Four DVDs
- The Browns Ferry Nuclear Plant Fire of 1975 Knowledge Management Digest NUREG/KM-0002, May 2013
- Fire Protection and Fire Research Knowledge Kno ledge Management Digest NUREG/KM-0003, January 2014
- Scheduled for update after end 2015
- Other NUREG/KMs currently under development:
- Hydrogen Knowledge Management Digest NUREG/KM
- Chernobyl Accident of 1986 Knowledge Management Digest NUREG/KM
September 16 - 18, 2015, Phoenix, Arizona 60 In Memory of Dr. John L. Bryan Born November B N b 1515, 1926 Died October 13, 2014
- Prof Bryan was a Leader in the Fire Protection Community. Founder and Chair of the University of Maryland Department of Fire Protection Engineering 1956 to 1993 many of the Fire Protection Engineers in the Nuclear Industry and at the Nuclear Regulator owe their start to Prof. Thank You Prof.
NRC FIRE RESEARCH INSIGHTS FROM TESTING Mark Henry Salley P.E.
Chief, Fire Research Branch U.S. Nuclear Regulatory Commission September 16 - 18, 18 2015 Phoenix, Phoenix AZ AZ.
September 16 - 18, 2015, Phoenix, Arizona 62 Goal of this Presentation
- Provide High Level Preliminary Insights to recent Overview O i off NRC Offi Office off Nuclear N l R Regulatory l t R Research h (RES) Fire Testing Activities
- Additional Details will be covered in other Plenary's y
- Focus on three Test Programs
- NUREG/CR-7197 Heat Release Rate of Electrical Enclosure Fires
((HELEN-FIRE))
September 16 - 18, 2015, Phoenix, Arizona 63 HELEN-FIRE- Key Insights Importance of Ventilation
- HELEN Fire tests 68 and 83 illustrate the importance of enclosure ventilation characteristics
- Test 68- Enclosure door closed, limited ventilation openings
- Peak HRR- 216 kW
- Test 83- Enclosure door open
- Peak HRR HRR- 577 kW Test 68 Test 83
September 16 - 18, 2015, Phoenix, Arizona 64 HELEN-FIRE- Key Insights Importance of Combustible Configuration
- HELEN Fire tests 71 and 79 illustrate the importance of configuration g of the combustibles within the enclosure
- Test 71-Cables were strewn within the enclosure without bundling,
- Peak HRR- 138 kW (while door closed)
- Test 79- Cables were loosely bundled together at the top of the enclosure
- Peak HRR HRR- 40 kW (while door closed)
Test 71 Test 79
September 16 - 18, 2015, Phoenix, Arizona 65 HELEN-FIRE- Key Insights -
Role of the Jacket Importance
- HELEN Fire tests 71 and 79 illustrate the importance of configuration g of the combustibles within the cabinet
- Test 37- TP Cable #807 with intact Jacket, 5.41 kg of combustible material
- Peak HRR- 35 kW
- Test 52- TP Cable #807 with stripped Jacket, 2.17 kg of combustible material
- Peak HRR HRR- 122 kW Test 37 Test 52
September 16 - 18, 2015, Phoenix, Arizona 66 JOAN of ARC- Key Insights: Voltage Level Important; Low 480 V
- Extensive internal damage
- Limited external damage
- No propagation to external targets (preliminary)
- Bus bar separation and clearance has a significant effect on arc hold times
September 16 - 18, 2015, Phoenix, Arizona 67 JOAN of ARC - Key Insights Voltage Level Important; Medium 6.9kV 6 9kV
- Extensive internal damage
- Extensive external damage
- (Right picture) Test Instrumentation stand damage; 3ft from rear of enclosure
- Extensive Enclosure Damage; enclosure deformation and burn through
September 16 - 18, 2015, Phoenix, Arizona 68 JOAN of ARC- Key Insights Value of Thermal Imaging
September 16 - 18, 2015, Phoenix, Arizona 69 JNRA/NRC Key Insights Aluminum vs. vs Copper
- Initial Bus Bar test results indicate a difference in total energy release depending on the bus bar material (Al. vs.
Cu.)
- The Zone of Influence (ZOI) f aluminum for l i b bus bbars appears to be greater than similar bus bars made of copper
- Energy released from the burning aluminum adds to the energy of the electrical arc
- More testing currently being planned