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| issue date = 10/05/1989 | | issue date = 10/05/1989 | ||
| title = 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 | | title = 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 | ||
| author name = | | author name = Alexich M | ||
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | ||
| addressee name = | | addressee name = Murley T | ||
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | ||
| docket = 05000315, 05000316 | | docket = 05000315, 05000316 | ||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#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: | 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: | |||
INTERNAL: NRR/DREP DIR10E NUDOCS-ABSTRACT OGC/HDS1 | NOTES: | ||
PIZASE HELP US TO REDUCE TASTE!CCkKACZ'IHE DOCXJMEÃl'XÃ | 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 | |||
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 | 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. | |||
a s r R>$ $Q I | |||
lONI'IIMC 'll AMERICAN EI.ECTRIC POIER SERVICE CORPORATION RADIOLOGICAL SUPPORT SECTION CALCULATION COYER SHEET FLE NO. PLANT Co UNIT SUBJECT 4 DATE | |||
~.W gC CALCUlATED BY VERIFIED/CHECKED FILE LOCATION APPROVED BY t PRDBLRR DHCRIPTIDR: 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 | |||
==REFERENCES:== | ==REFERENCES:== | ||
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+EkllC<L ~g4,( 4r SPPQ 3/>I t44tt REVISIONS CA LCULATED CHECKED APPROVED, NO. DATK CHANGK BY BY DATE BY DATE SUPERSEDED BY REVlSION NO. DATED REASON'IGURE RS -I | |||
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8,0CA~a~g~4v"~ubz IZ~p~~l h45iY | ~ Da | ||
~~foaw~aIa<OI ENGINEERING DEPT.' | |||
~(~wee+~L~)tys 00100 ,00110 00120 001 i0 00140 | a | ||
output¹1 using"<¹¹¹¹¹¹¹¹":"20CI1"; | ~ | ||
output¹1 using"<¹¹¹¹¹¹¹¹":"40CN"; | acaaaaaIccs SUBJECT | ||
output¹1 using"<¹¹¹¹¹¹¹¹":"60CN"; | ~ | ||
output¹1 using"<%¹¹¹¹¹¹¹":"30Ct)"; | ENGINEERING 1 RIVERSIDE PLAZA COLUMBUS, OHIO 4'<>i 4S DEI AMERICAN ELECTRIC POWER SERVICE CORP. | ||
output¹1 using"<¹¹¹¹¹¹¹¹":"100CH" for X=0 to 5 step.5 let CONC=10"X4.000001 let E=i print'ONC; output¹1 using"A,¹~¹ | t L)OSC 4 S 4'M COMPANY PLA C~k ia ~ | ||
ty output DOSE FOR LIi'JE SOURCE CONCENTRATION VS DOSE iCM 20CN 1.000E+0 7.51SE-2 3.759E-3 3.162E+0 2.377E-1 1.189E-2 1.000E+1 7.51SE-1 3.759E-2 | SHEET OF~ | ||
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4< IGOID ~ | |||
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) tys ping.txt 00100 create "OUTPUT" replace | |||
,00110 open ¹1:"OUTPUT" 00120 output ¹1:"DOSE FOR LINE SOURCE" 001 i0 output ¹1:"CONCENTRATION VS DOSE" 00140 output ¹1 using "<¹¹¹¹¹¹¹¹":" | |||
00150 output ¹1 using "<¹¹¹¹¹¹¹¹":"iCt)"; | |||
00160 output ¹1 using "<¹¹¹¹¹¹¹¹":"20CI1"; | |||
'00170 output ¹1 using "<¹¹¹¹¹¹¹¹":"40CN"; | |||
00180 output ¹1 using "<¹¹¹¹¹¹¹¹":"60CN"; | |||
00190 output ¹1 using "<%¹¹¹¹¹¹¹":"30Ct)"; | |||
00200 output ¹1 using "<¹¹¹¹¹¹¹¹":"100CH" 00260 for X=0 to 5 step .5 00270 let CONC=10"X4.000001 002a0 let E=i 00290 print'ONC; 00i00 output ¹1 using "A,¹~¹ "":CONC/.000&)i 00310 output ¹1:" | |||
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 ¹1 using "¹.¹¹¹'""":R(CONC, IE); | |||
00 ~60 outpu" ¹1: " | |||
00 i70 next I I 00 i71 print Vuat output ¹':" | |||
'0380 nex ~ X 00 i90 close ¹1 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 | |||
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Latest revision as of 01:52, 4 February 2020
ML17328A190 | |
Person / Time | |
---|---|
Site: | Cook ![]() |
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) | |
Text
3]STKBUTION 'EMONSTRk TIOYi SYSTEM REGULATOIINFORMATION DISTRIBUTION'STEM (RIDE)
I~ ~
'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
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
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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,00110 open ¹1:"OUTPUT" 00120 output ¹1:"DOSE FOR LINE SOURCE" 001 i0 output ¹1:"CONCENTRATION VS DOSE" 00140 output ¹1 using "<¹¹¹¹¹¹¹¹":" 00150 output ¹1 using "<¹¹¹¹¹¹¹¹":"iCt)"; 00160 output ¹1 using "<¹¹¹¹¹¹¹¹":"20CI1"; '00170 output ¹1 using "<¹¹¹¹¹¹¹¹":"40CN"; 00180 output ¹1 using "<¹¹¹¹¹¹¹¹":"60CN"; 00190 output ¹1 using "<%¹¹¹¹¹¹¹":"30Ct)"; 00200 output ¹1 using "<¹¹¹¹¹¹¹¹":"100CH" 00260 for X=0 to 5 step .5 00270 let CONC=10"X4.000001 002a0 let E=i 00290 print'ONC; 00i00 output ¹1 using "A,¹~¹ "":CONC/.000&)i 00310 output ¹1:" 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 ¹1 using "¹.¹¹¹'""":R(CONC, IE); 00 ~60 outpu" ¹1: " 00 i70 next I I 00 i71 print Vuat output ¹':"
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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
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