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| issue date = 04/23/2014
| issue date = 04/23/2014
| title = Supplemental Interim Technical Guidance on Fire-Induced Circuit Failre Mode Likelihood Analysis
| title = Supplemental Interim Technical Guidance on Fire-Induced Circuit Failre Mode Likelihood Analysis
| author name = Giitter J G
| author name = Giitter J
| author affiliation = NRC/NRR/DRA
| author affiliation = NRC/NRR/DRA
| addressee name = Tschiltz M D
| addressee name = Tschiltz M
| addressee affiliation = Nuclear Energy Institute (NEI)
| addressee affiliation = Nuclear Energy Institute (NEI)
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Gallucci R H, NRR/DRA, 415-1255
| contact person = Gallucci R, NRR/DRA, 415-1255
| package number = ML14111A366
| package number = ML14111A366
| document type = Letter
| document type = Letter
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=Text=
=Text=
{{#Wiki_filter:April 23, 2014  
{{#Wiki_filter:April 23, 2014 Mr. Michael D. Tschiltz Director, Risk Assessment Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218
 
Mr. Michael D. Tschiltz Director, Risk Assessment  
 
Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218  


==SUBJECT:==
==SUBJECT:==
SUPPLEMENTAL INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS  
SUPPLEMENTAL INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS


==Dear Mr. Tschiltz:==
==Dear Mr. Tschiltz:==


The Office of Nuclear Regulatory Research (RES) completed supplemental interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in February 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14017A084), which supersedes an earlier issuance of similar guidance from December 2013 (ADAMS Accession No. ML13346A092). Enclosed is a copy of this  
The Office of Nuclear Regulatory Research (RES) completed supplemental interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in February 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14017A084), which supersedes an earlier issuance of similar guidance from December 2013 (ADAMS Accession No. ML13346A092). Enclosed is a copy of this supplemental interim guidance (ADAMS Accession No. ML14017A135).
 
This document supersedes the previous interim technical guidance in a manner similar to that in NUREG/CR-6850, EPRI/NRC Fire PRA Methodology for Nuclear Power Facilities, for the treatment of circuit failure mode probability estimates. This supplemental interim guidance is based on the completed work of the U.S. Nuclear Regulatory Commission (NRC) and Electric Power Research Institute Fire Probabilistic Risk Analysis (PRA) Expert Elicitation panel.
supplemental interim guidance (ADAMS Accession No. ML14017A135).  
 
This document supersedes the previous interim technical guidance in a manner similar to that in NUREG/CR-6850, "EPRI/NRC Fire PRA Methodology for Nuclear Power Facilities," for the treatment of circuit failure mode probability estimates. This supplemental interim guidance is based on the completed work of the U.S. Nuclear Regulatory Commission (NRC) and Electric Power Research Institute Fire Probabilistic Risk Analysis (PRA) Expert Elicitation panel.
Several representatives from the nuclear industry were co-members of this panel.
Several representatives from the nuclear industry were co-members of this panel.
The previous interim guidance was issued when only a fraction of the cases evaluated by the experts had been calculated and reviewed. Therefore, that guidance addressed only solenoid operating valve (SOV) spurious operation probabilities, with only bounding cases for other circuit types. This updated guidance not only repeats that from the previous, but also includes the following: (1) hot short-induced spurious operation conditional likelihood estimates for motor operated valves (MOVs) and power circuit breaker control circuits; (2) method to calculate the probabilities for exceeding specific durations of hot-short induced spurious operations for both AC and DC control circuits.  
The previous interim guidance was issued when only a fraction of the cases evaluated by the experts had been calculated and reviewed. Therefore, that guidance addressed only solenoid operating valve (SOV) spurious operation probabilities, with only bounding cases for other circuit types. This updated guidance not only repeats that from the previous, but also includes the following: (1) hot short-induced spurious operation conditional likelihood estimates for motor operated valves (MOVs) and power circuit breaker control circuits; (2) method to calculate the probabilities for exceeding specific durations of hot-short induced spurious operations for both AC and DC control circuits.
The final results of the PRA Expert Elicitation project will be published in Volume 2 of NUREG/CR-7150 later this year, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this supplemental interim guidance, which is based on the completed work of the expert panel and is not expected to change. Volume 2 of the report will provide additional refinement to the methods for quantifying fire-induced cable damage. This Supplemental Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed.


The final results of the PRA Expert Elicitation project will be published in Volume 2 of NUREG/CR-7150 later this year, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be c onsistent with this supplemental interim guidance, which is based on the completed work of the expert panel and is not expected to change. Volume 2 of the report will provide additional refinement to the methods for quantifying fire-induced cable damage. This Supplemental In terim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed.
M. Tschiltz                                   We welcome further dialogue to enhance analytical methods for use in fire PRA regulatory applications. If you have any questions, please feel free to contact Hossein Hamzehee at (301) 415-0562.
 
Sincerely, Joseph G. Giitter, Director     /RA/
M. Tschiltz
Division of Risk Assessment Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
 
We welcome further dialogue to enhance analytical methods for use in fire PRA regulatory applications. If you have any questions, please feel free to contact Hossein Hamzehee at (301) 415-0562.  
 
Sincerely,  
 
Joseph G. Giitter, Director  
/RA/ Division of Risk Assessment Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission  


==Enclosure:==
==Enclosure:==


Supplemental Interim Technical
Supplemental Interim Technical Guidance
 
Guidance M. Tschiltz
 
We welcome further dialogue to enhance analytical methods for use in fire PRA regulatory applications. If you have any questions, please feel free to contact Hossein Hamzehee at (301) 415-0562.
 
Sincerely,


Joseph G. Giitter, Director  
M. Tschiltz                                    We welcome further dialogue to enhance analytical methods for use in fire PRA regulatory applications. If you have any questions, please feel free to contact Hossein Hamzehee at (301) 415-0562.
/RA/ Division of Risk Assessment Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission  
Sincerely, Joseph G. Giitter, Director     /RA/
Division of Risk Assessment Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission


==Enclosure:==
==Enclosure:==


Supplemental Interim Technical  
Supplemental Interim Technical Guidance DISTRIBUTION:
 
RGallucci       JSHyslop     HBarrett       PLain DONeal         MSalley       GTaylor       NMelly RidsNrrDra     RidsNrrDraApla Accession Number: Pkg: ML14111A366 Memo: ML14086A165 Encl: ML14017A135 OFFICE           NRR/DRA       NRR/DRA           NRR/DRA         NRR/DRA       DD: NRR/DRA NAME             RGallucci     AKlein           HHamzehee       SLee           JGiitter DATE             03/27/2014   04/04/2014         04/07/2014     04/07/2014     04/ 23 /2014 OFFICIAL RECORD COPY}}
Guidance  
 
DISTRIBUTION
: RGallucci JSHyslop HBarrett PLain DONeal MSalley GTaylor NMelly RidsNrrDra RidsNrrDraApla Accession Number: Pkg: ML14111A366 Memo: ML14086A165   Encl: ML14017A135 OFFICE NRR/DRA NRR/DRA NRR/DRA NRR/DRA DD: NRR/DRA NAME RGallucci AKlein HHamzehee SLee JGiitter DATE 03/27/2014 04/04/2014 04/07/2014 04/07/2014 04/ 23 /2014 OFFICIAL RECORD COPY}}

Latest revision as of 06:27, 4 November 2019

Supplemental Interim Technical Guidance on Fire-Induced Circuit Failre Mode Likelihood Analysis
ML14086A165
Person / Time
Issue date: 04/23/2014
From: Giitter J
NRC/NRR/DRA
To: Tschiltz M
Nuclear Energy Institute
Gallucci R, NRR/DRA, 415-1255
Shared Package
ML14111A366 List:
References
Download: ML14086A165 (3)
v • d • e


Text

April 23, 2014 Mr. Michael D. Tschiltz Director, Risk Assessment Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218

SUBJECT:

SUPPLEMENTAL INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS

Dear Mr. Tschiltz:

The Office of Nuclear Regulatory Research (RES) completed supplemental interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in February 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14017A084), which supersedes an earlier issuance of similar guidance from December 2013 (ADAMS Accession No. ML13346A092). Enclosed is a copy of this supplemental interim guidance (ADAMS Accession No. ML14017A135).

This document supersedes the previous interim technical guidance in a manner similar to that in NUREG/CR-6850, EPRI/NRC Fire PRA Methodology for Nuclear Power Facilities, for the treatment of circuit failure mode probability estimates. This supplemental interim guidance is based on the completed work of the U.S. Nuclear Regulatory Commission (NRC) and Electric Power Research Institute Fire Probabilistic Risk Analysis (PRA) Expert Elicitation panel.

Several representatives from the nuclear industry were co-members of this panel.

The previous interim guidance was issued when only a fraction of the cases evaluated by the experts had been calculated and reviewed. Therefore, that guidance addressed only solenoid operating valve (SOV) spurious operation probabilities, with only bounding cases for other circuit types. This updated guidance not only repeats that from the previous, but also includes the following: (1) hot short-induced spurious operation conditional likelihood estimates for motor operated valves (MOVs) and power circuit breaker control circuits; (2) method to calculate the probabilities for exceeding specific durations of hot-short induced spurious operations for both AC and DC control circuits.

The final results of the PRA Expert Elicitation project will be published in Volume 2 of NUREG/CR-7150 later this year, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this supplemental interim guidance, which is based on the completed work of the expert panel and is not expected to change. Volume 2 of the report will provide additional refinement to the methods for quantifying fire-induced cable damage. This Supplemental Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed.

M. Tschiltz We welcome further dialogue to enhance analytical methods for use in fire PRA regulatory applications. If you have any questions, please feel free to contact Hossein Hamzehee at (301) 415-0562.

Sincerely, Joseph G. Giitter, Director /RA/

Division of Risk Assessment Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission

Enclosure:

Supplemental Interim Technical Guidance

M. Tschiltz We welcome further dialogue to enhance analytical methods for use in fire PRA regulatory applications. If you have any questions, please feel free to contact Hossein Hamzehee at (301) 415-0562.

Sincerely, Joseph G. Giitter, Director /RA/

Division of Risk Assessment Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission

Enclosure:

Supplemental Interim Technical Guidance DISTRIBUTION:

RGallucci JSHyslop HBarrett PLain DONeal MSalley GTaylor NMelly RidsNrrDra RidsNrrDraApla Accession Number: Pkg: ML14111A366 Memo: ML14086A165 Encl: ML14017A135 OFFICE NRR/DRA NRR/DRA NRR/DRA NRR/DRA DD: NRR/DRA NAME RGallucci AKlein HHamzehee SLee JGiitter DATE 03/27/2014 04/04/2014 04/07/2014 04/07/2014 04/ 23 /2014 OFFICIAL RECORD COPY

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