View source for NUREG-1547, Informs That DOE & Fmrc Repts Not Applicable to NRR Work Associated W/Fire Modeling & Fire Barrier Qualification. Staff Rept Re Study of Alternative time-temperature Curves to Be Published as NUREG-1547 & Available in Sept 1996

{{Adams
| number = ML20141M640
| issue date = 08/29/1996
| title = Informs That DOE & Fmrc Repts Not Applicable to NRR Work Associated W/Fire Modeling & Fire Barrier Qualification. Staff Rept Re Study of Alternative time-temperature Curves to Be Published as NUREG-1547 & Available in Sept 1996
| author name = Marsh L
| author affiliation = NRC (Affiliation Not Assigned)
| addressee name = Duraiswamy S
| addressee affiliation = NRC ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS)
| docket = 
| license number = 
| contact person = 
| case reference number = RTR-NUREG-1547
| document report number = ACRS-3027, NUDOCS 9609090058
| package number = ML20140H218
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| page count = 2
}}

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j                        MEMORAIEMI T0:          Sam Duraiswamy, Chief i                                                Nuclear Reactors Branch
{                                               Advisory Coenittee on Reactor Safeguards                 ,
4 FROM:                  Ledyard B. Marsh, Chief Plant Systems Branch           fk A
i                                               Division of Systems Safety and Analysis                    i i                                               Office of Nuclear Reactor Regulation
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==SUBJECT:==
F0LLOWUP TO THE 429TH MEETING 0F THE ADVIS0RY
;                                                                                                         I Copei!TTEE ON REACTOR SAFEGUARDS l                                                                                                         l l                         In its letter to the Chairman dated March 15, 1996, the Advisory Committee on i                        Reactor Safeguards (ACRS) stated that a large number of fire models exist,        1 i                         some of which are being evaluated by the Department of Energy (00E), the need i                         for new fire models was not clear, and questioned the staff efforts related to l                         the development of alternative time-temperature curves, since the ACRS had been told that alternative time-temperature curves had been produced by the j                         insurance industry. Subsequently by mescranda of June 26, 1996, and i                        August 12, 1996, the ACRS staff provided the draft report of the Accident j                         Phenomenology and Consequence (APAC) Methodology Evaluation developed by i
Sandia National Laboratory for the Department of Energy, and "MFL Wall Fire Resistant Ratings," prepared by Factory Mutual Research Corporation (FMRC).
The Fire Protection Engineering Section has reviewed the DDE and FMRC reports
;                         and has concluded that these efforts are not applicable to the Office of j                        Huclear Reactor Regulation (NRR) work associated with fire modeling and fire barrier qualification.
i i                        The objective of the 00E effort was to evaluate 5 computer codes for application in the performance of safety analysis at DOE facilities as required by 00E orders. The scope of the study was limited to source term analysis (fire involving radioactive material), in-facility transport of radioactive materials by the fire gases, and the transport of chemical and       ;
.                         radioactive materials external to the facility. This is significantly l                        different from the scope of the NRR staff sponsored project, which was to i                         evaluate the performance of fire barriers protectinti cables and equipment      ;
j                         necessary to achieve and maintain safe shutdown fol' owing a fire, i
i                         The scope of the FMRC proposal is limited to developing a methodology for       ,
selecting the appropriate fire rating, based on the ASTM E-119 time-i                         temperature curve, for fire walls to prevent fire propagation between adjacent i                         compartments, whereas the NRR staff effort was related to the development of i                        nuclear power plant specific time-temperature curves to be used as an
]                         alternative to the ASTM E-119 curve. The appropriate fire rating for barriers 4                         separating redundant safe shutdown components in the same fire area is I                         specified in Section III.G.2 of 63pendix R to 10 CFR 50. The FMRC report is l                        attached, please return it to your point of contact at FMRC.
i CONTACT:     Edward A. Connell, NRR/SPLB                                         i 301-415-2838
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;                        San Duraismesy                                2-i.
I The staff has completed its work related to the feasibility study regarding       <
i alternative time-temperature curves. This was reported to the Cosmission in       I
!                        SECY-96-162, dated July 19, 1996. A copy of the study was also provided to j                        the Nuclear Energy Institute in a {{letter dated|date=July 29, 1996|text=letter dated July 29, 1996}}. The staff report titled " Methodology for Developing and Implementing Alternative
!                        Temperature-Time Curves for Testing the Fire Resistance Barriers for Nuclear Power Plants," is being published as NUREG-1547. We expect the report to be l
available in September 1996. The ACRS staff is on the distribution for the report.
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