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| {{#Wiki_filter:REGULATO INFORMATION DISTRIBUTION TEM ('RI DS)'ACCESSION NBR!8311110135 DOC~DATES 83/11/04 NOTARIZED'NO.FACIL:50 3i5 Donal.d'.6 | | {{#Wiki_filter:}} |
| ~'Cook>>Nuclear>>Power-.->>Plantg
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| ',Uni,t'i Indiana 8"'.50 316 Donald O~">>Cook'uclear Power.Planti'Uni,t 2i Indiana 8 AUTH;NAME'AUTHOR AFFILIATION ALEXICH~M,P,-Indiana 8'Mjchigan=-Electr ic,Co,'REOIP NAMEi RECIPIKNT AFFILIATION
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| :-DENTONgH,Rs..
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| Of fice>>of Nucl'ear tReactor I Regul ation'ir ector>>.-SUBJECT;=-)Provides addi info re>>.ut)1 8308224 submittal"L 834021 tel con r e" 34 h-f ire pr otection-of>>embedded cabl es'Two embedded'ables found w/o sufficient"fire barrier~to:provide" 3 h r at ing, Addi insu1 a t i on~w i l l"be;pr ov i ded..DISTRIBUTION iCODE>>'AOOSS iCOPIES'RECEIVED:LTR,J,'NCL:,P'SIZE:."'TITLE>, OR'Submittal:
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| Fir e>>iProtection.NOTES!DOCKET¹0500031'5 05000316 RECIPIENT>>
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| ID CODE/NAME, NRR" ORB1>>BC'1.*INTERNALR ELD/HDS3 IE'i'WHITNEY g L NRR=WAMBACH.NRR'/DL-"'DIR RGN3>>COPIES I;TTR"ENCL>>
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| 434 1=1 ,i..1 RECIPIENT ID CODE/NAME, IE:;F ILE>>06 NRRFIORAVANT07 DE/CEB 09 RK L 04>>COPIES LTTR ENCL 1 2 2 1 EXT'ERNAL~ACRS.NRC>>PDR NTIS 11 02 534 1>>LPDR NSIC, 03'2 05 1)TOTAL NUMBER OF:COPIES REQUIRED!LTTR 22 ENCL.
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| i F M lii II)i Fi s>>T ocit>)n e"i inn r 0).f<:c)y><<I<<P'l)i i)~<<.'c'ii)~'0 f ikey~A'0L)l y'O'>>I''i" Oily AOV Il~<>I~~~I>rRq~i r a 4>i f)l no>>)e<<>r~'<<'1J r)I jr 3 3i<l',g Icy o<)9:l6)'l ir)'i f 9giy" tv f'l)), rgy61, i r Ail I r jy<r 0 II c'Fyf'f r<~cliPP%4c~'IF'I F'f ii'i'1 v~0 F fili)l>rq Pn','i r vn'1 i l)i">nR Q n))k~g)n r'F i)july>l~c) l;8" p lip f'f Jgpggep 0 I r f il r'iirvnacr nP~yira iF-l a~r>4C<irar0tua O<<~y.nu~f ,t"9t'rhea<<
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| i~r f I'y c>nrem iy fi)~<>r fl~",;)~r 0>>~."-fh Ic..lI f: 5)F I g'))il P<I~<<lu~gyfl(yh: 9 l.>>)a)r I xt.,<f c,'I)or>r 9qaw~a<~i r 3;f t.e 9 r",jets>>..rli>:>j f I t INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O.BOX 16631 COLUMBUS, OHIO 43216 November 4, 1983 AEP:NRC:0692I Donald C.Cook Nuclear Plant, Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 FIRE PROTECTION FOR EMBEDDED CABLES Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
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| ==Dear Mr.Denton:==
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| The purposes of this letter are (1)to provide additional information related to our previous submittal (AEP:NRC:0692H) dated August 22, 1983 and (2)to confirm the telephone conversation we had with your staff on Friday, October 21, 1983 concerning three-hour fire protection of embedded cables at the Donald C.Cook Nuclear Plant.The previous submittal transmitted a report, dated March 1983, which was prepared by our consultants, Engineering Planning Management Incorporated (EPM).That report was titled"Supplemental Information Safe Shutdown Capability Assessment and Proposed Modifications, 10 CFR 50, Appendix R, Section III G." Section 2 of the Supplemental Report stated, in part, that the additional barrier mass between the embedded cables and the cold side (of the wall)will function as a heat sink, lowering the actual in-wall temperature at the embedded cable to a number substantially lower.than the 322 F used for the standard NFPA barrier rating.At our request, EPM reviewed the bases employed in the Supplemental Report.We received a letter from EPM, dated September 28, 1983, concerning the additional reviews.The information attached to the EPM letter stated that the critical temperatures at a four inch depth reached between 500 F and 600 F after three hours.As discussed during the telephone conversation, we have traced all safety related cables in fire zones to determine which zones included more than one Essential Safety Features (ESF)train.As a result, we found two cases in which embedded cables did not have a sufficient fire barrier to provide a three-hour zating.In both of these cases, the cables were in concrete pilasters, which are not part of the structural wall.The affected pilasters are located in Fire Zone 15 in Unit 1 (i.e., the red ESF divisional diesel generator room)and Fire Zone 19 in Unit 2 (i.e., the green ESF divisional diesel generator room).In both cases, we will add sufficient insulation to provide a three-hour 8311110135 831104 PDR ADOCK 05000315 F PDR 0 t"0;f F t, h P~)Jrhf~=)>>I II ,h'I 0 P 0 I'~r h I'h f')0, , f.h'.0'), E I'ff" r'I I t f f I R rFj I'rf, Hr<<fr)')h~r)Ef 1t'"'FI'*'>>qr)~~0'f~hj.fC>><<f I 0 E It E=h~~h fbi I'h W~--I I (h R Hf rt~I~0 pl h",'"ht h<<f A I~jl 0<<tf'h E)",0'" r),IIR E 0 hjrt h 0>>I''jhf')jlht
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| .)-~>>y<<,.'h'tl 0 I'E;r~I>>)'l>>tjr)l)T E>>$0>>P)$f*''I",E R'f E f>>h;0"))>>htrgrl wir I f'>>P j~,0 r h f F 0 rt f 0'>>lt t I g)'Hr Hf~'.>>rv F f ,""),f f~
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| Mr.'Harold R.on AEPsNRC:0692I barrier, without any reliance on the insulation properties of the concrete.The insulation modification will not rely on any conditions addressed in the Supplemental Report.This information should be factored into the data-base for your Safety Evaluation Report on fire protection which, we understand we will be receiving shortly.This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
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| Very truly yours,~i M.Al ich Vice Pre ident MPA/pb cc: John E.Dolan W.G.Smith, Jr.-Bridgman R.C.Callen G.Charnoff E.R.Swanson, NRC Resident Inspector-Bridgman 0~-P1")F a~~}}
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