ML20126M702
| ML20126M702 | |
| Person / Time | |
|---|---|
| Issue date: | 10/13/1979 |
| From: | Harrison G Office of Nuclear Reactor Regulation |
| To: | Moore V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19250G967 | List:
|
| References | |
| FOIA-81-201 NUDOCS 8106190364 | |
| Download: ML20126M702 (3) | |
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SAi!0IA F.EFORT Ci! FUCLE.'*3 PS'!!R PU Ni FIRE F.',0TECTION "ENTILATICH - NUREG/CP.-0633; C.Ud] M'.'ST,1379 a3 cu'::c-ct repet i:1s peapred by Sandia Lt.'.:catacles '. tith the objective
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..s dominant fire control parameters are the fire area barriers and the fire suppression systems.
This fact should have been stressed in
-the report because it would have been realized that fire dampers in the ventilation ducts would automatically close.
Hence, the fire protaction design objective is contain:ent rather than te r;orature control by the HVAC.
- 3 It is stated in the report that Ccaft Teg. Guide 1.120 lacks specific acd sufficient guidance with ripeds to vcntilation s;.sti s.
o.30 Guide 1.120 gives explicit trea tant
.~c,e a nu..':ar of pis.nt :rcas such as the control roca (C,6.b), cable s raading roca (C.G.c), switchg3ar (C.6.e), and battery rooms (C.6.9), etc.
4 Cn'page 14 of the reprt, a discussion is presanted which completely ove:csights the existance of cutcclatic fire su;pression syste r.s and, to one.ith firefighting exprisnce, does not prcperly ccesider the real life as. tacts of cantal. fire extinguishment.
5 The first rac:c=ndaticn containad en page 35 is presentad '..ith dis-recard ior the fact that many fadacal and state ccde taking groups
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".r.e ai raady acccr ;1 t s hid this reccrenda tion.
~his is '..hy the fire protecti:n philc cphy = fc;'i'. :ni::.rusi T in this country cuar the put 50 years is that of c cta' 20t and su;?ression, Qich s
'iy us have fire barriars, fli, as;,m.d ii.itatWis, n','AC fire dacra cs,'
and fire departcants.
Tha coly.'xceptica to this shiloso;hy,wl i be in en extensive tu-el systr usid 'or tears :irtati:n.
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In sunary, I do not agree with the thrus,t'of this report nor do I concur with any.o f the recommendations.
Finally, 'the report will not assist our licensing review process.
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Gregn y A. Marrisen, P.E.
Fire Prot'ection Engineer cc:
T. Iucley V. Stello R. itattson G. Arlotto S. Hanauer V. 3anaraya R. '.'ol l ma r R. Satterfield C. Long P. !btthaus D. Fischer R. Ferguson G. 3ennett R. Feit D. i;otley E. Sylvestar A. Hintze G. Lain 2s W..'Orrison E. '..'anziacar e
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NU' I L AR I,t liUL A IC;RY CO'.*f.HSSION g
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tiOV 181930 MEM0?.AHOUM FOR: Frank Schroeder, Assistant Director
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for Generic Projectsr Division of Safety Technology FROM:
Vincent S. i'oonan, Assistant Director l
for Materials & Qualifications Engineering I
Division of Engineering
SUBJECT:
DRAFT REGULATORY GUIDE RS309-5 DATED JULY,1979, "QUAllFICATION TEST FOR CABLE PENETRATION FIRE STOPS FOR USE IN NUCLEAR POWER PLANTS" Per your request, we have reviewed the subject document.
Our fire protection review guidelines contained in B.TP ASB 9.5-1 (and Appendix "A" thereto) specify that fire stops must have.a fire rating verified by the ASTM E-119 fire test method or its equivalent. To date, we have had no problem in having the industry conform to this. On the contrary, this requirement for fire testing fire barriers and fire stops is one of the more " cut-and-dried" engineering specifics of the fire pro-tection profession.
Fire barriers and fire stops have been tested and The successfully used in the industrial community for over fifty years.
fire loss record in this regard is that fire s'to'ps tested to the ASTM E-119 Therefore, since nucicer method do perform their design objective well.
plant fire stop cesigns have been and are being verified by full scale fire tests conducted at independent, nationally recognized testing laboratories using the ASTM, ANSI, or NFPA fire test method, then,we do not see a tech-nology gap that needs to be filled by the subjec: Reg. Guide. Hence, we recom,end that Reg. Guide RS809-5 not be issted.
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f1p Jancd,I h _lLdnan,' Assistant Director for Materials & Qualifications Engineering
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Division of Engineering l
Centact:
G. Harrison X27877 cc:
R. Vollmer
- 0. Notley G. Arlotto G. Harrison V,
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W. Morrison G. Knighton
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V. Senaroya R. Silver
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E. Wenzinger H. l.evin A
W. Farmer S. Hudson R. Ferguson a
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JM 121991 MEMORAllDUM FOR: Guy Arlotto, Director Division of Engineering Standards Office of Standards Develorcent FROM:
Thomas E flurley, Director Division of Safety Technology Office of Nuclear Reactor Regulation
SUBJECT:
REGULATORY GUIDE RS 809-5, QUALIFICATION TEST FOR CABLE PE!!ETRATION FIRE STOPS FOR USE IN NUCLEAR POWER PLANTS We have completed our review of the subject guide transmitted by route slip dated September 2,1980. Our review involved several n'ee' tings and a number of discus-sions with members of your staff. Based on these discussions we are returning the guide to you for your further evaluation of the requirement for positive pressure on the exposed side of the penetration during the test (Section C.2.b) and for several revisions listed below.
With satisfactory resolutfoa of the pres-sure differential issue and the listed revisions, we will have no objections to the issuance of this guide.
Comments:
1.
Based on review of published research and of tests performed by licensees, we do not see the need to specify a positive pressure on the exposed side of the penetration during the test (section C.2.b).
Our experience indi-cates that the passing of the ASill E-119 test provides acceptable assur-ance that the fire stop would remain effective if exposed to a positive i
l pressure differential in a fire.
2.
It is our understanding that you will delete Section C.4 regarding the protrusion of cable on the exposed side.
3.
Paragraph 3.2 Value/ Impact of Procedural Alternatives and paragraph 5 l
Relationship to other Existing Proposed Regulations or Policies in your value/ impact statement should address the relationship of this guide to paragraph 50.48 and Appendix R to 10 CFR Part 50.
Pa ra gra ph II. M. o f Appendix R addresses the regulatory requirement with respect to fire I
barrier penetration seals.
4 The implementation section of the regulatory guide states that with respect to operating plants and plants under construction " implementation schedules will be determined on a case-by-case basis"for these facilities by the Office o H r 'e c tor R gula tior.,-
{y memorandum fmm Harold R. Denton to 1bh
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Guy Arlotto - 'JAN 121931 7-
' Robert !!inogue dated July 3,1980 regarding concurrence on Regulatory..
Gui,de 1~.141 we state our position on implementation requirements for all
' future r'egulatory guides.
Specifically, we stated that "we should.. avoid designating that implementation should,bc decided on a case-by-case basis."
l This statement applies not only to the' extent of application for.different categories of reactors but also to the implementation schedules. The imple-
- mentation section should exclude cable penetration fire stops which have i
been or will be. installed in accordance with an f!RC approved fire ' protection program.or plants licensed before: January 1,1979. ~ These fire stops which
~
have been reviewed and found.. acceptable by the NRC meet the requirements of-
, Paragraph.III. II of Appendix R.
Orig'nd signed by
- 7. E'.1,tudey Thomas E. Murley. Director Division of Safety Technology Office of fluclear Reactor Regulation
Enclosure:
Regulatory Guide RS 809-5 l
' cc:.V.'Benaraya^'
l L, Re-f'erguson Distribution Copies:
' ' Central File RSCB s/f TEPA PDR Tschul tze DST '80-103 Jltull in -
FSchroeder
' Tifurl ey RSilver GKnighton Note previous concurrence sheet for add'1 concurrences.*
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