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| issue date = 12/16/2013 | | issue date = 12/16/2013 | ||
| title = Interim Technical Guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis | | title = Interim Technical Guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis | ||
| author name = Giitter J | | author name = Giitter J | ||
| author affiliation = NRC/NRR/DRA | | author affiliation = NRC/NRR/DRA | ||
| addressee name = Bradley B | | addressee name = Bradley B | ||
| Line 9: | Line 9: | ||
| docket = | | docket = | ||
| license number = | | license number = | ||
| contact person = Gallucci R | | contact person = Gallucci R, NRR/DRA/APLA, 415-1255 | ||
| document type = Letter | | document type = Letter | ||
| page count = 3 | | page count = 3 | ||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:December 16, 2013 | {{#Wiki_filter:December 16, 2013 Mr. Biff Bradley Director, Risk Assessment Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218 | ||
Mr. Biff Bradley Director, Risk Assessment | |||
Nuclear Energy Institute | |||
1201 F St., NW, Suite 1100 Washington, DC 20004-1218 | |||
==SUBJECT:== | ==SUBJECT:== | ||
INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS | INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS | ||
==Dear Mr. Bradley:== | ==Dear Mr. Bradley:== | ||
The Office of Nuclear Regulatory Research (RES) completed an interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in June 2013 (Agencywide Documents Access and Management System Accession Number ML13165A209). Enclosed is a copy of this interim guidance (ADAMS Accession No. ML13165A214). This document provides interim technical guidance, in a manner similar to that in NUREG/CR-6850, | The Office of Nuclear Regulatory Research (RES) completed an interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in June 2013 (Agencywide Documents Access and Management System Accession Number ML13165A209). Enclosed is a copy of this interim guidance (ADAMS Accession No. ML13165A214). This document provides 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 interim guidance is based on the recent work of the 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 interim guidance is based on the latest information developed by the expert panel and is not expected to change when finalized. | ||
The final results of the PRA Expert Elicitation project are expected to be published in Volume 2 of NUREG/CR-7150 in 2014, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this interim guidance. | |||
The final results of the PRA Expert Elicitation project are expected to be published in Volume 2 of NUREG/CR-7150 in 2014, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this interim guidance. However, Volume 2 of the report is expected to provide additional refinement to the methods for quantifying fire-induced cable damage. This Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed. | However, Volume 2 of the report is expected to provide additional refinement to the methods for quantifying fire-induced cable damage. This Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed. | ||
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. | |||
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 | Sincerely, | ||
/RA/ | |||
(301) 415-0562. | Joseph G. Giitter, Director Division of Risk Assessment Office of Nuclear Reactor Regulation | ||
Sincerely, | |||
==Enclosure:== | ==Enclosure:== | ||
As stated | As stated | ||
1201 F St., NW, Suite 1100 Washington, DC 20004-1218 | December 16, 2013 Mr. Biff Bradley Director, Risk Assessment Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218 | ||
==SUBJECT:== | ==SUBJECT:== | ||
INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS | INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS | ||
==Dear Mr. Bradley:== | ==Dear Mr. Bradley:== | ||
The Office of Nuclear Regulatory Research (RES) completed an interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in June 2013 (Agencywide Documents Access and Management System Accession Number ML13165A209). Enclosed is a copy of this interim guidance (ADAMS Accession No. ML13165A214). This document provides interim technical guidance, in a manner similar to that in NUREG/CR-6850, | The Office of Nuclear Regulatory Research (RES) completed an interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in June 2013 (Agencywide Documents Access and Management System Accession Number ML13165A209). Enclosed is a copy of this interim guidance (ADAMS Accession No. ML13165A214). This document provides 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 interim guidance is based on the recent work of the 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 interim guidance is based on the latest information developed by the expert panel and is not expected to change when finalized. | ||
The final results of the PRA Expert Elicitation project are expected to be published in Volume 2 of NUREG/CR-7150 in 2014, and will support a future update to the methodology in | The final results of the PRA Expert Elicitation project are expected to be published in Volume 2 of NUREG/CR-7150 in 2014, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this interim guidance. | ||
However, Volume 2 of the report is expected to provide additional refinement to the methods for quantifying fire-induced cable damage. This Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed. | |||
NUREG/CR-6850. The results are expected to be consistent with this interim guidance. | 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. | ||
However, Volume 2 of the report is expected to provide additional refinement to the methods for quantifying fire-induced cable damage. This Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed. | Sincerely, | ||
/RA/ | |||
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. | Joseph Giitter, Director Division of Risk Assessment Office of Nuclear Reactor Regulation DISTRIBUTION: | ||
RGallucci JSHyslop HBarrett Plain DONeal MSalley GTaylor NMelly RidsNrrDRA RidsNrrDRAApla Accession Number: Pkg No.: ML13346A092, Memo: ML13238A280, Encl: ML13165A214, Transmit memo: ML13165A209 Office NRR/DRA NRR/DRA NRR/DRA NRR/DRA NRR/DRA Name R. Gallucci A. Klein H. Hamzehee S. Lee J. Giitter Date 8/26/2013 9/6/2013 9/6/2013 12/12/2013 12/16/13 Official Record Copy | |||
Sincerely, | |||
RGallucci | |||
ENCLOSURE INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS AGENCYWIDE DOCUMENT ACCESS AND MANAGEMENT SYSTEM (ADAMS) ACCESSION NO. ML13165A214}} | ENCLOSURE INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS AGENCYWIDE DOCUMENT ACCESS AND MANAGEMENT SYSTEM (ADAMS) ACCESSION NO. ML13165A214}} | ||
Latest revision as of 14:16, 4 November 2019
| ML13238A280 | |
| Person / Time | |
|---|---|
| Issue date: | 12/16/2013 |
| From: | Giitter J NRC/NRR/DRA |
| To: | Bradley B Nuclear Energy Institute |
| Gallucci R, NRR/DRA/APLA, 415-1255 | |
| References | |
| Download: ML13238A280 (3) | |
Text
December 16, 2013 Mr. Biff Bradley Director, Risk Assessment Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218
SUBJECT:
INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS
Dear Mr. Bradley:
The Office of Nuclear Regulatory Research (RES) completed an interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in June 2013 (Agencywide Documents Access and Management System Accession Number ML13165A209). Enclosed is a copy of this interim guidance (ADAMS Accession No. ML13165A214). This document provides 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 interim guidance is based on the recent work of the 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 interim guidance is based on the latest information developed by the expert panel and is not expected to change when finalized.
The final results of the PRA Expert Elicitation project are expected to be published in Volume 2 of NUREG/CR-7150 in 2014, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this interim guidance.
However, Volume 2 of the report is expected to provide additional refinement to the methods for quantifying fire-induced cable damage. This Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed.
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,
/RA/
Joseph G. Giitter, Director Division of Risk Assessment Office of Nuclear Reactor Regulation
Enclosure:
As stated
December 16, 2013 Mr. Biff Bradley Director, Risk Assessment Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218
SUBJECT:
INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS
Dear Mr. Bradley:
The Office of Nuclear Regulatory Research (RES) completed an interim technical guidance on Fire-Induced Circuit Failure Mode Likelihood Analysis in June 2013 (Agencywide Documents Access and Management System Accession Number ML13165A209). Enclosed is a copy of this interim guidance (ADAMS Accession No. ML13165A214). This document provides 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 interim guidance is based on the recent work of the 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 interim guidance is based on the latest information developed by the expert panel and is not expected to change when finalized.
The final results of the PRA Expert Elicitation project are expected to be published in Volume 2 of NUREG/CR-7150 in 2014, and will support a future update to the methodology in NUREG/CR-6850. The results are expected to be consistent with this interim guidance.
However, Volume 2 of the report is expected to provide additional refinement to the methods for quantifying fire-induced cable damage. This Interim Technical Guidance serves as an NRC staff position on fire-induced circuit failure mode likelihood analysis until Volume 2 is published and endorsed.
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,
/RA/
Joseph Giitter, Director Division of Risk Assessment Office of Nuclear Reactor Regulation DISTRIBUTION:
RGallucci JSHyslop HBarrett Plain DONeal MSalley GTaylor NMelly RidsNrrDRA RidsNrrDRAApla Accession Number: Pkg No.: ML13346A092, Memo: ML13238A280, Encl: ML13165A214, Transmit memo: ML13165A209 Office NRR/DRA NRR/DRA NRR/DRA NRR/DRA NRR/DRA Name R. Gallucci A. Klein H. Hamzehee S. Lee J. Giitter Date 8/26/2013 9/6/2013 9/6/2013 12/12/2013 12/16/13 Official Record Copy
ENCLOSURE INTERIM TECHNICAL GUIDANCE ON FIRE-INDUCED CIRCUIT FAILURE MODE LIKELIHOOD ANALYSIS AGENCYWIDE DOCUMENT ACCESS AND MANAGEMENT SYSTEM (ADAMS) ACCESSION NO. ML13165A214