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=Text=
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{{#Wiki_filter:3]STKBUTION
{{#Wiki_filter:3]STKBUTION 'EMONSTRk TIOYi                     SYSTEM REGULATOIINFORMATION DISTRIBUTION'STEM               (RIDE)
'EMONSTRk TIOYi SYSTEM REGULATOIINFORMATION DISTRIBUTION'STEM (RIDE)I~~'CCESSION NBR:8910160287 DOC.DATE: 89/10/05 NOTARIZED:
I~         ~
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
              'CCESSION NBR:8910160287         DOC.DATE:   89/10/05     NOTARIZED: NO         DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana                           6 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana                           6 05000316 AUTH. NAME                     AUTHOR AFFILIATION ALEXICH,M.P.                   Indiana Michigan Power Co. (formerly. Indiana         6 Michigan Ele RECIP.NAME                     RECIPIENT AFFILIATION Document Control Branch (Document         Control Desk)
Indiana Michigan Power Co.(formerly.
Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Forwards addi info re radiation monitoring sys per Staff request.DISTRIBUTION CODE: AOOSD COPIES RECEIVED:LTR J ENCL L SIZE: TITLE: OR/Licensing Submittal:
Forwards               addi info re radiation monitoring sys per Staff request.
Appendix I NOTES: RECIPIENT ID CODE/NAME PD3-1 LA GIITTER,J.
DISTRIBUTION CODE: AOOSD TITLE: OR/Licensing Submittal: Appendix COPIES RECEIVED:LTR I      J   ENCL L   SIZE:
INTERNAL: NRR/DREP DIR10E NUDOCS-ABSTRACT OGC/HDS1.RGN3 DRSS/RPB EXTERNAL: EGGG SIMPSON,F NRC PDR COPIES LTTR ENCL 1'1 1 1 0-1 1 1 0 1 1 2 2 1 1 I.RECIPIENT ID CODE/NAME PD3-1 PD NRR/DREP/RPB 10 OC/LFMB ILE 0 LPDR COPIES LTTR ENCL 5 5 2 2 1 0 1 1 1 1 h D R D S h NCTE'IO ALL'KIDS" R!KIPIHGS:
NOTES:
PIZASE HELP US TO REDUCE TASTE!CCkKACZ'IHE DOCXJMEÃl'XÃIBOL DESK, KXM Pl-37 (EXT.20079)XO ElZHZHAXE YOUR 5AMB PBCM DIPIVGBVTION LISTS FOR~IMENIS YOU DGNFT NEED!I TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 15 Indiana Michigan Power Company P.O.Box$6631 Coiumbus, OH 43216 8 AEP:NRC:0856X Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 NUREG 0737, SECTION II.F.1-2 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 ATTN: T.E.Murley October 5, 1989
I RECIPIENT           COPIES            .RECIPIENT          COPIES ID CODE/NAME         LTTR ENCL ID CODE/NAME        LTTR ENCL h
PD3-1 LA                   1            PD3-1 PD                5    5 GIITTER,J.                 1    1 D
INTERNAL: NRR/DREP DIR10E                         1    0-      NRR/DREP/RPB 10        2    2 NUDOCS-ABSTRACT           1    1      OC/LFMB                1    0 OGC/HDS1                   1    0            ILE      0      1    1 RGN3       DRSS/RPB       1    1 EXTERNAL: EGGG SIMPSON,F                         2     2       LPDR                   1     1 NRC PDR                    1     1 R
D S
h NCTE 'IO ALL 'KIDS" R!KIPIHGS:
PIZASE HELP US TO REDUCE TASTE! CCkKACZ 'IHE DOCXJMEÃl'XÃIBOLDESK, KXM Pl-37 (EXT. 20079)   XO ElZHZHAXE YOUR 5AMB PBCM DIPIVGBVTION LISTS FOR   ~IMENIS YOU   DGNFT NEED!
I TOTAL NUMBER OF COPIES REQUIRED: LTTR                       19   ENCL     15


==Dear Dr.Murley:==
Indiana Michigan Power Company P.O. Box $ 6631 Coiumbus, OH 43216 8
This letter provides additional information regarding radiation monitoring systems as requested by a member of your staff.The information supports our previous submittal AEP:NRC:0678Y, dated July 23, 1986, and is provided on the two attachments.
AEP:NRC:0856X Donald C. Cook Nuclear Plant Unit Nos. 1 and          2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG 0737, SECTION II.F.1-2 U.S. Nuclear Regulatory Commission ATTN:        Document  Control Desk Washington, D.C.          20555 ATTN:        T. E. Murley October 5, 1989
Attachment 1 is a description of how the gaseous radioactive effluent monitor readings are corrected for decay for the purpose of off-site dose calculation.
 
Attachment 2 is a copy of an internal calculation to determine if the radiation monitor could survive in a post accident environment per IE Information Notice 86-30.This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
==Dear Dr. Murley:==
Very truly yours, M..Al xich Vice President edg Attachments cc: D.H.Williams, Jr.A.A.Blind-Bridgman R.C.Callen NFEM Section Chief G.Charnoff NRC Resident Inspector-Bridgman A.B.Davis-Region III 8910160287 891005 PDR ADQCK 05000315 P PNU ATTACHMENT 1 AEP:NRC:0856X Attachment 1 to AEP:NRC:0856X Page 1 The response of the Eberline SPING gaseous effluent radiation monitor (low-, mid-, and high-range channels)was calculated as a function of time for a postulated accident.The response of the detectors to the post-accident gas mixture was determined by utilizing the primary calibration efficiencies of each detector type.The result of the analysis provided tables of post-accident decay correction factors which can be applied to the radiation monitoring channels.These correction factors had been inserted into and made part of our off site dose assessment computer code (DAP).DAP estimates off site doses to the whole body and thyroid resulting from plant releases.The user is prompted to input the following information:
 
meteorological data, radiation monitor reading, time of reactor shutdown, duration of release, effluent flow rates, and the type of the accident that would be considered.
This letter provides additional information regarding radiation monitoring systems as requested by a member of your staff.
During the process of calculating the estimated doses, the computer code automatically retrieves the gas mixture decay factor, which is a dimensionless multiplier, for the appropriate monitor reading.
The   information supports our previous submittal AEP:NRC:0678Y, dated July 23, 1986, and is provided on the two attachments.
s r a lONI'IIMC'll AME I RICAN EI.ECTRIC POIER SERVICE CORPORATION R>$$Q RADIOLOGICAL SUPPORT SECTION CALCULATION COYER SHEET FLE NO.SUBJECT 4 FILE LOCATION UNIT PLANT Co DATE CALCUlATED BY~.W gC VERIFIED/CHECKED APPROVED BY t PRDBLRR DHCRIPTIDR:
Attachment 1 is a description of how the gaseous radioactive effluent monitor readings are corrected for decay for the purpose of off-site dose calculation. Attachment 2 is a copy of an internal calculation to determine         if the radiation monitor could survive in a post accident environment per IE Information Notice 86-30.
2.~~~~Spis~Qg.g(.3aa~~4~P"+><'~<P~5~~Ar dM c~(t~ly Vis ck~(8~~ss d~s 4 pal~g~g/),sr 4Pf 4 cc id~DESIGN BASIS OR  
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Very     truly yours, M.     . Al xich Vice President edg Attachments cc: D. H. Williams,         Jr.
A. A. Blind - Bridgman R. C. Callen NFEM Section Chief G. Charnoff NRC Resident Inspector     - Bridgman A. B. Davis - Region     III 8910160287 891005 PDR ADQCK 05000315 P                       PNU
 
ATTACHMENT 1 AEP:NRC:0856X to AEP:NRC:0856X                                   Page 1 The response   of the Eberline SPING gaseous effluent radiation monitor (low-, mid-, and high-range channels) was calculated as a function of time for a postulated accident. The response of the detectors to the post-accident gas mixture was determined by utilizing the primary calibration efficiencies of each detector type. The result of the analysis provided tables of post-accident decay correction factors which can be applied to the radiation monitoring channels.
These correction factors had been inserted into   and made part of our off site dose assessment computer code (DAP). DAP estimates off site doses to the whole body and thyroid resulting from plant releases.
The user is prompted to input the following information:
meteorological data, radiation monitor reading, time of reactor shutdown, duration of release, effluent flow rates, and the type of the accident that would be considered. During the process of calculating the estimated doses, the computer code automatically retrieves the gas mixture decay factor, which is a dimensionless multiplier, for the appropriate monitor reading.
 
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                                                                                ~.W       gC CALCUlATED BY VERIFIED/CHECKED FILE LOCATION                                        APPROVED BY                               t PRDBLRR DHCRIPTIDR:     2. ~ ~~~Spis~ Qg.                     g( .3aa   ~~ 4
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DESIGN BASIS OR  


==REFERENCES:==
==REFERENCES:==


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output&#xb9;1 using"<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"20CI1";
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output&#xb9;1 using"<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"40CN";
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output&#xb9;1 using"<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"60CN";
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output&#xb9;1 using"<%&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"30Ct)";
ENGINEERING 1 RIVERSIDE PLAZA COLUMBUS, OHIO 4'<>i       4S DEI AMERICAN ELECTRIC POWER SERVICE CORP.
output&#xb9;1 using"<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"100CH" for X=0 to 5 step.5 let CONC=10"X4.000001 let E=i print'ONC; output&#xb9;1 using"A,&#xb9;~&#xb9;""":CONC/.000&)i output&#xb9;1:" for I I=0 to 1{iv step 20 print"II=" II;if II=0 then let I=l else let I=II print R(CONC, I,E);output&#xb9;1 using"&#xb9;.&#xb9;&#xb9;&#xb9;'""":R(CONC, IE);outpu"&#xb9;1: " next I I print output&#xb9;':" nex~X close&#xb9;1 cli"TV output.GR" de f R (COt<C~Hs E)1et R=75179.SiCGNC~ElH end def end.
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                                                                                                                                                          'k ct'<<C.h.J    saaAs                                                self Aksar!aa+>>I 7s!c q]aacha<s        4.   -Ka.    !ors>4 ., ~m ac& u..!o es                  AIM.<<:
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a            4 I                                  I      I aaooceagm          e.>>oa>>I        mcs
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cIssaa>> cJ...          W ..sac.'I,IhcV, (c          'v~     c, aaau~bw
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                                                          ... al(  rc        77vf  CK 0 RIVERSIOE PLAZA                      COMPANY                      Q.O.
COLUMBUS. OHIO                        PLAN
                                                            'I SUBJECT I       I I   (      I
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        '. AMERfCANELECTRtC POWER SERVICE CORP.                       OAT                            cc 1 RlVERSlOE PLAZA                                 COMPANY                          O.O.
COLUMBUS, OHIO                                   PLAN SUBJECT                                     4     }II   5
                                      /Irsu/g       ~e}IE8     code/FAINTED   4   4IFE& accFcfa~4.
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C/opec Ac        8f o 40FI       Cd y     /Cc     c/d 5 Els.:
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W/g =       3   }6 }A.<
D = 7/d'/}E         4       2krS
 
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foaw~aIa<OI     ENGINEERING DEPT.                                           SHEET    5    OF
      'AMERICANELECTRIC PONER SERVICE CORP.
0 RIVERSIOE PLA2A COLUMBUS, OHIO COMPANY PLANT
                                                                            '            OK a.a.
SUB JEGT                               Z>asE     A
                      ///.     QdaaI       (st Vj4           o+IC     II'& Hl/44I   44 S~lt PLEA         is     M Oo'a C(=W.                                   CN)
                      ~(ooo       c.s-nn = I VI'ro       cay~ N
                                    $ Z(L (4'.+P~
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                .0.6$ pQ./cc.       -   D SSE(4         +/cc Ii=.f(.i (a.ZZ~(o             )(D.SS       (G   )C.Ee)(~   )/~~
4<     IGOID   ~
 
                                            ~ (~wee+ ~     L ~
  ) tys ping.txt 00100 create "OUTPUT" replace
,00110 open &#xb9;1:"OUTPUT" 00120 output &#xb9;1:"DOSE FOR LINE SOURCE" 001 i0 output &#xb9;1:"CONCENTRATION VS DOSE" 00140       output &#xb9;1 using "<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"
00150      output &#xb9;1 using "<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"iCt)";
00160      output &#xb9;1 using "<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"20CI1";
'00170 output &#xb9;1 using "<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"40CN";
00180 output &#xb9;1 using "<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"60CN";
00190 output &#xb9;1 using "<%&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"30Ct)";
00200 output &#xb9;1 using "<&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;&#xb9;":"100CH" 00260 for X=0 to 5 step .5 00270          let     CONC=10"X4.000001 002a0          let     E=i 00290          print'ONC; 00i00          output &#xb9;1 using "A,&#xb9;~&#xb9; "":CONC/.000&)i 00310          output &#xb9;1:"
00i20        for I I=0 to 1{iv step 20 00i21              print "II=" II; 003 i0            if II=0 then let I=l else let I=II 00~40              print R(CONC, I,E);
output &#xb9;1 using "&#xb9;.&#xb9;&#xb9;&#xb9;'""":R(CONC, IE);
00 ~60            outpu" &#xb9;1: "
00 i70        next I I 00 i71        print Vuat          output     &#xb9;':"
      '0380 nex ~   X 00 i90      close &#xb9;1 00400      cli   "TV output.GR" 00410      de f   R (COt<C~ Hs E) 00420          1et R=75179.SiCGNC~ElH 004.0 end def 00440 end.
 
ty output DOSE FOR LIi'JE SOURCE CONCENTRATION VS DOSE iCM       20CN     40CH    enc>>    Snci1    100CN 1.000E+0 7.51SE-2     3.759E-3 1.879E-3 1.253E-3  9. 397E-4 7. 51SE-4
: 3. 162E+0 2. 377E-1   1. 189E-2 5.943E-3 '.962E-3 2r 9/2t 3 Zo 377E 1.000E+1 7.51SE-1     3.759E-2 ~r-,~g  &253E-2  9.397E-3 7.518E-3
<<,162E+1 2.377&0     1.189E-i 5.94 E-2 3.96 E-2  2.972E-2 2. <<77E-2 1 . OOOE+2 ~7~+<8. 759E-1 1.879E-1 l. 253E-1    9. <<97E-2 7. 51SE-2
:. 162E+2 2. 77E+1 1. 189E+0 5. 943E-1 3.962E-1   =. 972E-1 2. 377E-1
: l. OOOE+3 7. 518E+1 3. 759E+0 i. 879E+0 '.253E+0 9. <<97E-1 7.518E-1 3<<. 162E+3 2. <<77E+2 1.189E+1 5 94~E+0 3 '62E+0 .97'E+0 . ~77E+0 1.000E+4 7.51SE+2 3.759E+1 1.879E+1 1 . 25 <<E+1 9. <<97E+0 7.518E+0
  .162E+4 2.377E+3 1.189E+2 5 94<<E+1 <<.962E+1 2~97 ~+    X  :77E+1 1.00OE+5 7.51SE+3 3.759E+2 1. 8798+2 1.253E+2 9. 97E+1 7.518E+1 Q WOcn~
 
33SE                                              FC3R                                      LIIE                                          .0LJR.,'E I:ONt;ENTRRTtON                                                                                                'LJS                  DOSE IQOQO                                                                                                                                                                                                                                                                                    o
                                                                                                                                                                                                                                                                                    ~I 3i- tori~e IIIQO
          ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
I I ~ ~ ~ ~ ~ f ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Qe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ Q II ~ ~ ~ ~ ~ ~ ~ ~ ~
I
                                                                                                                                                                                                          ~ ~ ~ ~ ~ ~~ ~ ~ ~ ~ ~ ~ ~
                                                                                                                                                                                                                                          ~
                                                                                                                                                                                                                                        ~ ef f
ol~
I ~ e I4IJT I I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I I ~
pl fe
                                                                                                                                                                                                                                                                                        ~ ~ ~ ~
                                                                                                                                                                                                                                                                                            ~
                                                                                                                                                                                                                                                                                              ~
I ilt)
                                                                                                                                                                                                                                                                        ~I
                                                                                                                                                                                  ~             o I ~ ~ I I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ I ~ ~ ~ I ~ I ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ oe qeoh I ~ ~ ~ ~                                       le ~ ~ ~ ~ ~ ~ ~ ~ I pCI
                                                                                                                                                                                                                                                                    ~1 I g dCgge
                                                                                                                                                                                                                                                                                                  ---'20~'. ll
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IOO                                                                                                                                                                        ~ P' 30CII I
I ~ I ~ I I ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 11 ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~
                                                                                                                                                                                                                ~
ee f r" Vf
                                                                                                                                                                                                                            << g<<h +ors H'                                              'FOCH olpleh            I ~ ~ ~ ~ ~ ~ ~ I ~ I ~ ~ ~ I~ ~ ~ I ~II ~ ~ ~ II ~ ~
                                                                                                                                                                                                        ))<<
            ~~~                                                                                               ~ ~ ~ ~ ~               ~ ~                                                           ~         I ~ ~ ~ If                            ~ ~ ~ ~ ~ I~~ ~ ~ I~ ~I~~ ~ ~I~ ~ I 0      IP I
r- 4e <<<<el
                                                                                                  ~ er'                                                                    of    ~       o          ee    ~   1'
                                                                                                                                                                                                                                                                                                  --80CH
          ~~~~~~~~~~~           Il I II
                                    ~   ~     ~ ~ ~ ~ II  ~ ~ ~ II  ~l          ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~~ ~ ~ ~ ~ f
                                                                                                                        ~
                                                                                                                          ~ ~ ~ ~ I ~ ~ ~ I g feh ~ I IIMefl f f8 (<<7>>
                                                                                                                                  ~"eel                  I <<>>de>>el e<<eee          ~  <<I    I ~
fI  ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~~ ~ ~ ~ ~   I~ Ill he s     ~ ~~ ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I~~ e   ~ ~ ~ ~ s
                                                                                                                                                                                                                                                                                                  ---IOOCH f ~~                  I     ~e            <<<<           ~
I
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Latest revision as of 00:52, 4 February 2020

Forwards Addl Info Re Radiation Monitoring Sys Per NRC Request.Description of How Gaseous Radioactive Monitor Readings Corrected & Calculation to Determine If Monitor Can Survive post-accident Environ,Per Info Notice 86-030,encl
ML17328A190
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/05/1989
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737 AEP:NRC:0856X, AEP:NRC:856X, IEIN-86-030, IEIN-86-30, NUDOCS 8910160287
Download: ML17328A190 (12)
v • d • e


Text

3]STKBUTION 'EMONSTRk TIOYi SYSTEM REGULATOIINFORMATION DISTRIBUTION'STEM (RIDE)

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'CCESSION NBR:8910160287 DOC.DATE: 89/10/05 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana 6 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly. Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards addi info re radiation monitoring sys per Staff request.

DISTRIBUTION CODE: AOOSD TITLE: OR/Licensing Submittal: Appendix COPIES RECEIVED:LTR I J ENCL L SIZE:

NOTES:

I RECIPIENT COPIES .RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL h

PD3-1 LA 1 PD3-1 PD 5 5 GIITTER,J. 1 1 D

INTERNAL: NRR/DREP DIR10E 1 0- NRR/DREP/RPB 10 2 2 NUDOCS-ABSTRACT 1 1 OC/LFMB 1 0 OGC/HDS1 1 0 ILE 0 1 1 RGN3 DRSS/RPB 1 1 EXTERNAL: EGGG SIMPSON,F 2 2 LPDR 1 1 NRC PDR 1 1 R

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PIZASE HELP US TO REDUCE TASTE! CCkKACZ 'IHE DOCXJMEÃl'XÃIBOLDESK, KXM Pl-37 (EXT. 20079) XO ElZHZHAXE YOUR 5AMB PBCM DIPIVGBVTION LISTS FOR ~IMENIS YOU DGNFT NEED!

I TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 15

Indiana Michigan Power Company P.O. Box $ 6631 Coiumbus, OH 43216 8

AEP:NRC:0856X Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG 0737, SECTION II.F.1-2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 ATTN: T. E. Murley October 5, 1989

Dear Dr. Murley:

This letter provides additional information regarding radiation monitoring systems as requested by a member of your staff.

The information supports our previous submittal AEP:NRC:0678Y, dated July 23, 1986, and is provided on the two attachments.

Attachment 1 is a description of how the gaseous radioactive effluent monitor readings are corrected for decay for the purpose of off-site dose calculation. Attachment 2 is a copy of an internal calculation to determine if the radiation monitor could survive in a post accident environment per IE Information Notice 86-30.

This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, M. . Al xich Vice President edg Attachments cc: D. H. Williams, Jr.

A. A. Blind - Bridgman R. C. Callen NFEM Section Chief G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III 8910160287 891005 PDR ADQCK 05000315 P PNU

ATTACHMENT 1 AEP:NRC:0856X to AEP:NRC:0856X Page 1 The response of the Eberline SPING gaseous effluent radiation monitor (low-, mid-, and high-range channels) was calculated as a function of time for a postulated accident. The response of the detectors to the post-accident gas mixture was determined by utilizing the primary calibration efficiencies of each detector type. The result of the analysis provided tables of post-accident decay correction factors which can be applied to the radiation monitoring channels.

These correction factors had been inserted into and made part of our off site dose assessment computer code (DAP). DAP estimates off site doses to the whole body and thyroid resulting from plant releases.

The user is prompted to input the following information:

meteorological data, radiation monitor reading, time of reactor shutdown, duration of release, effluent flow rates, and the type of the accident that would be considered. During the process of calculating the estimated doses, the computer code automatically retrieves the gas mixture decay factor, which is a dimensionless multiplier, for the appropriate monitor reading.

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