ML20107A703

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Rev 7 to Offsite Dose Calculation Manual
ML20107A703
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/31/1984
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20107A679 List:
References
PROC-841031, NUDOCS 8502200082
Download: ML20107A703 (8)
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Text

.

OFFSITE DOSE CAIftIATION MANIAL FOR SOUIH CAROLINA ELECIRIC AND GAS COMPANI VIRGIL C. SGCER NUCLEAR STATION PEVISION 7 October 1984 hiVl' d

d7WED '3Y 74 -

'e/'o/e+

- MGij PSRC 8502200082 850130 PDR ADOCK 05000395 R pop Revision 7 -

LIST OF EFFECTIVE P7GES Page Revision Page Revision i 7 1.0-1 5 11 7 1.0-2 5 iii 7 1.0-3 5 -

iv 5 1.0-4 5 v 5 1.0-5 5 vi 5 1.0-6 5 vii 3 1.0-7 5 viii 5 1.0-8 5 1.0-9 5 1.0-10 5 1.0-11 5 1.0-12 5 1.0-13 7 1.0-14 5 1.0-15 5 1.0-16 5 1.0-17 5 1.0-18 5 1.0-19 5 1.0-20 5 1.0-21 5 1.0-22 5 1.0-23 5 1.0-24 5 1.0-25 5 1.0-26 5 1.0-27 5 l 1.0-28 5 1.0-29 5' ,

1.0-30 5 1.0-31 5 1.0-32 5 1.0-33 5 1.0-34 5 I

1.0-35 5 l 1.0-36 5 l 1.0-37 5 1.0-38 5

'l.0-39 5 .

1.0-40 6 i

0D3, V.C. Stmner/SCEandG: Revision 7 (October 1984) i

~

I l

LISP CF"EIT!!ETIW TJGIS (02ntinued) ,

l Page Revision ^ Page Revision

2.0-1 5 2.0-46 5 2.0-2 5 2.0-47 5 2.0-3 5 2.0-48 5 2.0-4 5 2.0-49 5 2.0-5 5 2.0-50 5 2.0-6 5 2.0-51 6 2.0-7 5 2.0-8 5 2.0-9 5 3.0-1 5 2.0-10 5 3.0-2 5 2.0-11 7 3.0-3 5 2.0-12 5 3.0-4 5 2.0-13 5 3.0-5 5 4

2.0-14 5 3.0-6 5 2.0-15 5 3.0-7 5 2.0-16 5 3.0-8 ~5 l 2.0-17 5 3.0-9 5 2.0-18 5 3.0-10 5 2.0-19 5 3.0-11 5 2.0-20 5 3.0-12 5 2.0-21 5 3.0-13 5 2.0-22 5 2.0-23 5 2.0-24 5 2.0-25 5 2.0-26 5

-2.0-27 5 2.0-28 7 2.0-29 5 2.0-30 5 2.0-31 5 2.0-32 5 l 2.0-33 5 I 2.0-34 7 2.0-35 5 l

l 2.0-36 5 2.0-37 5 2.0-37a 5 1

2.0-38 5 l 2.0-39 5 l 2.0-40 5 2.0-41 5 2.0-42 5 2.0-43 5 2.0-44 5 2.0-45 5 0001, V.C. Summer /SCELG: Revision 7 (October 1984) 11

CDNTROLLED COPY DISTRIBUTION Person Cooy 4 Director, Nuclear Plant Operations 1 Manager, GP&EP 2 Manager, Nuclear Licensing 3 Associate Manager, Health Physics 4 Sr. Staff Health Physicist 5 i

Supervisor, Radiological Envirortnental. 6

~i Supervisor, Count Rocm 7 Manager, Support Services 8 Manager, Operations 9 Assoc. Manager Regulatory Conpliance 10 V. C. Summer Document Section 11 Manager ISEG 12 Associate Manager, Quality Assurance 13 Supervisor, Non-Radiological Envirormental Prograns 14 l

l l

ODC1, V.C. Sumer/SCEandG: Revision 7 (October 1984) 111 l

4 4

  • The Steam Generator Blowdown Effluent may be released to the Circulating mter either directly in the (bndenser outflow or via the ponds and sunps of the Industrial and Sanitary Waste Systen; the latter path is preferred for chemical reasons in the first hours following startup. The Turbine Building Sunp and Condensate j Denineralizer Backwash Effluents enter the Circulating Water through- l the Industrial and Sanitary System.

For the sake of clarity, two mutually exclusive setpoint calculation processes are outlined below. Section 1.1.3.1 is to be used whenever Steam Generator Blow @wn in bel'ng released directly to j the Circulating Water in the Condenser outflow, which is the normal P mode. Section 1.1.3.2 is to be used whenever Steam Generator Blowdown is being released to the Industrial and Sanitary este System, or diverted to the Nuclear Blowdown Processing System, both of which are alternate modes. Each section covers all four monitors (RM-L3, RM-L8, RM-L10 and % Lil).

j- NOTE: When Circulating Water is unavailable for effluent dilution, releases containing activity above LID should be discouraged via pathways which lead to it. Steam Generator Blowdown i should be diverted to the Nuclear Blowdown Processing System.

Condensate Demineralizer Backwash may be diverted to.the

. Turbine Building Sunp or not released. Turbine Building Sump effluent should be diverted to the Excess Liquid Waste Proces-

! sing System. (These steps are to keep the calculated dose to individuals as low as reasonably achievable.) Furthermore, l

sampling and analysis of the Industrial and Sanitary este

! System is to be initiated and the measured concentrations used in the dose calculations of Section 1.2.

l l

0004, V. C. Sumter, SGand3: Revision 7 (October 1984) 1.0-13

_ , , . . . , , . < - -. ,, . --_.,y- . . _,,

l 1.2 Dose Calculation For Liquid Effluents The method of this section is to be used in all cases for calcu-lating doses to individuals from routine liquid effluents. Four notes at the end of the section confirm the values which certain parameters are to be assigned in see special cases.

The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expression:

m.

D7= A17 bt1 Cil F1 i, l=1 ,

(31) where:

D7 = the cumulative dose ccanitment to the total body gr any organ,7 e frczn the liquid effluents for the total time period t i,-

in mrem (Reference 1 ). 1-1 dt1 = the length of the lth time period over which Cil and F1 are averaged for all liquid releases, in hours.

Cil = the average concentration of radionuclide, i, in undiluted liquid effluent during time period 8t1 frczn any liquid release, in tci/ml.

A17= the site related ingestion dose ecmnitment factor to the tota'.

i body or any organ 7for each identified principal gama and beta

' snitter listed in Table 1.2-3 in mren-ml per hr-uci.

A17 = Ko ( (Uw/Dw) + UFBFi) DFi (32)

F1 = the near field average dilution factor for Cil during any liquid effluent' release. Defined as the ratio of the maximun undiluted liquid waste flow during release to the product of the average flow from the discharge structure to unrestricted receiving water times Z.

003, V. C. Summer, SCEand3: Revision 7 (October 1984) 1.0-28

l TAM.I 1.2

  • SITE RELATED INGESTION DOSE CDMMITtfNT FACTOR, Ah (mrem /hr per uCi/mi)
mvCLICC: 90=C . L!vCe . 7,30pv . Tnve0!D: E!DMCv : - LUNO . 08 ((1 !

4 M-3 ;8 ecC*CC*t.96C+00'O.9&C+00's.9EC*ee's.96C+00's.96C+04:8.96C*et:

C-te :3.15C*ed: 6.3CC+03-6.30C 03:6.30C+03'6.33C+03:6.38C+03:6.30C+03:

NS-24 :5.deC*CI.5.4SC+02:5.40C+C2.5.40C+02:5.deC*s2:5.deC+02*S.40C+02:

. P-32  : 4. 6 2 C *O*; 2. S *C

  • 06 : 3.7 9C e C6 : 9. 80C *es . e. 00C+39 : 3. e0C + 00 : 5. 20C + 06 :

Cr-ft  : 8. 00C+00 C.00C*e0. t . 49C+CO. 6.94C *e t : 3. 29C-01:1. 99C+9e

  • 3.76C +02 :

Ms-34 :0.OCC*CO:4. ?6 C + C 3 ! 9. 0eC + CZ : 0. eeC + 00 : 1. 4 2C

  • e 3 : 0. eaC + 08 : 3.46C + ed :
Paa!6 :8.0CC*CC't.20C*C2:2.82C*01:0.00C+09:1.52C+02:3.geC+0e!3.82C+03:

re-tS  : 9. 0 ?C

  • C * ' 6.13C
  • C2
  • 1. 4 3C *02 : 3. 00C + 00 : 8. 00C *90 : 3. 4 2C + 02 : 3.52C + 82 :

re-19 :1 40C*C3:3.29C+03rt.26C+03:e.e2C+00:0. SCC +39:9.19C*e2:1.80C+ed:

! Co-79 :9.eJC*d3't.5tC*02:3.39C+C2;S.00C+00:8.SeC+00:8.00C+es:3.06C*03:

Co-69 0.08C+e0'4.38C+02:9.50C*C2:3. esc +0e 8.90C+09:8.00C+te:3.16C+03:

Ms-63  ; d .19C + 04 ' 2. 91 C + 0 3
  • t . 4 t t
  • 0 3 :8.00C*st*s.00C+00*S.00C*S8:6.97C+02:

ha-65 ft.7dC+02:2.2tC*0t*1.etC*st:0.00C+09:0.9CC+te:3.00C*S8:5.6tt+32:

Cu*64 i s . SCC

  • C 3.1. 6 9 C + 01 : 7. 9 3 C + 02 : e . 80C + 80 : d . 26 C + 01 : 9. 00 C + 80 : 1. 44 C + 03 :

! 2n-6? :2.36C+94:7.5CC+C4:3.39t+08:8.0CC+88:5.92C+04:8.00C+00:4.73C+S4:

4 2n*6P :5.02C+ 1 9.6CC*C1:6.67C+00:8.08C+00:6.24C+01:8.08C+80:1.edC+01:

. .r..  :.. SOC *e..e.eeC+ee 4.3.C. 1 0.0.C+0e:....C.08:0...C+00:6.3.C+.iq:

. 0*-04 l0.00C+00:8.0CC+CO:5.67C+01:0. ESC *84 0.00C+e8:8.SeC+99:4.45C-84

  • p*-e! 8.CCC*CC:0.CCC+00:2.23C+0C:8.00C+CO:0.00C*ee!e.00C+8e:1.09C-15:
  1. e*06 :8.00C+00*1.03C CS:4.79C+84:e.SeC+0s;e.84C+00:8.80C+00:2.03C+84:

20*8# :0.eCC*CC'2.95C+02:1.?6C+02:9.88C+08:3.00C+00:8.geteet*4.87C-09:

sc e9 :0.CCC+cc 1.9tC+02:3.37C*02:9.98C+00:8.00C+es:8.SeC+39:1.13C-t**

5**f9 24.feC*C4:C . D C C *C C : 1. 37 C + 0 3 : 8. e e C +.0 : 8. 00C + 08 : 0. 00C + 00 : 7*. 66C + 0 3 :

SP-90 :1.teC*C&'C.ect*ce:2.SeC*CT:8.SeC+00:8.0CC+et:9.seC*Se:3.4eC+04:

SP-9:  : 8 *9C +C ' C. 80C*CC ' 3.* 5C + 01 : 0. CCC *CO : C.80C+00 : 8. 00C+eS 4.19C+03 5*-92 .3.33C*C2'C. cec'e0 1. 4C*es;e.e0C*ee:. 80C+00:8..eC+.0:6.60C+03:

v-90 :3.3&C*ec'O.eCC+00.3.69C-02:3.00C+00:e.00Cese:8.30C+00:1.46C+S4:

v-9tp :1.3CC-C2'O.00C*CC'T.04C+04:9.8eC+00:0.00C*e0:8.ett*99:3.02C-02:

v-91 :2.e2C*01.C.CCE*CD'5.39C-et:8.eeC+08:0.edC*ee:e.90C+08:t.11C*se!

v-92  : 1. 2 tt

  • 01: 8.CCC *CC 3.* 3C-C3 : 8. 02C+00 : e. 80C+00: 8.00C *ee: 2.12C +0 3:

v-93  : 3. 6 3C+Ct .c. 0CC a ec . t . 96C-02 's. eCC+et . e. 90C+08 : 0. 00C +08 !!.22C+34 :

2*-9?  ; 2.77C

  • CO . D. e f t-81 ! 6.ett -81 : 8.COC +C2 : 1.39t+C4 : 8.eaC+es : 2.82C+s 3:

2P-9* 3.?3C-C1 3.C5C-C2.1.4tC-C*'t.82C*C2:4.6*C-e2.0.8eC*CO:9.57C+03:

MS-97 4.4?C+02'2.dSC*CZ t.34C*02:0.92C+00:2.46C+02:2.88C+38:1.51C*S6:

. M0-99 :0.00C*CC 4. 61C

  • C2 : e .79C + 01 : C. 8 2C
  • CC : 1. e5 C + 0 3 : 8. 00C + 0 0 : 1. 07C +0 3 :

Ts-99+ :2.94C-02's.32C=C2!1.04C*CO:9.00C+00:1.26t*02*4.97C-82:4.92C+05:

Tc-st! :3.03C-C:.4.3dC.c2:4. 2 6 C -C 1 : 0. CCC + C O : 7. 85C -21:2.23C-42:1.3tCat3:

Dw-103 :1.99C+08:9 CCC*dC G.54C*CC.C. cec +08:7.57C*et;e.ecC+08.2.3tC*e3*

R*-105 :t.6TC*CO:C.02C-CC'6.52C-01 0.eCC+e8:2.13C+31:0.00C+00:1.e C+03:

e .t ee : 2. 9'C +CI .e.82C+CC . 3.* 3C+0 t t 8.eeC* e0 :5.69C+02 :8.00C+88:1.9tC*B4:

. aq*110**1 42C*Ct!!.3tC*C1: 7.9CC +0C 8.eeC+00:2. 50C *et !S.eeC+00:5.36t*E3 *l

, 7p .125m.2 7%C*e 3 1.e tt *0 3 : 3.74C+d2 :8.39C+02:1.13C+04:8.88C+98:1. tlc +04:

Ts.12*e.7.CTC*C3:2.52C*C3 0.!9C+82:1.08C+83:2.06C+04.8.00C+03:2.36C*ed:

ff=12* *1,14C*C :4.11C+01;2.49C+01:9.40C+Ct.d.6&C+02*e.00C+08:9.83C*S3:

. fe-129+.t.2tC+04:4.47C 03:1.09C*e3'4.stC*e3:5.00C+C4:8.00C+08:6.83C+0d!

Te-129 :3.27C+01:1.23C*0117.96C+0C'2.33C+01:1.37C+82*e.80C+98:2.4?C+S8:

Te-13ta:1.0CC*e3.9.StC*C2.7.34C*02:1.39C*e3:0.92C+83:0.88C*ee:8.74C+04:

7t-131 :2.CTC*Ct'e.!'C*CC:6.47t+C3: 4.69C+01:8.99C+01:8.02C+00:2.90C+88:

Te-132 :2.62C*C3:1.?CC*C2't !9C*a3:1.8?C+83:1.63C+04:8.00C*ee:8.82C*ed:

t-132 :9.ett*01:2.6dC+02:1.8?t*0!'2.25C*ed!4.t!C+02:8.90C*99:2.29C+02:

6 1-131  ; 4. 94C *e2 : ?. CPC +CZ i e. 06C+e2 2. 32C+ef : 1. 22C+0 3 : 8. 00C+08 : 1.0?C +er :

!*t32 :2.42C*C1'6.4*C*Ct:2.26f+01:2.26C*e3:1.93C*02 9.83C+00:1.22C+01:

. 1-133 :1.65C*C2:2.94Cae2:6.97C+Ct:4.32C*C4'5.83C+92:9.02C+09:2.6eC+02*

1 !=334 :3.26C+Ct:3.43C*et:1.23C+08:5.9aC*e!:5.46C*et:8.00C+80:2.99C-92:

1 135 5.20C+Cl;t.3tC+02:1.10C+88:9.ItC*e3:2.22C+02:9.00C+e8:1.56C+02*

! Cs-334 ;3.83C* eft *.2tt*0?:5.tSteet:e.eeC+08:2.33C+05:7.75C*se:1.26r+ed:

Cs-136 :3.t?C+24:1.25C*d?'9.01C*ed:9.eeC*et:6.9tC*84*9.5SC+83:1.42C+08:

Cs-93? 13 8tC

  • Cf . 3 t C *ct : 3. 4 0C *C5. e. e@C*e0 : 1.00C+ 85 : 5. 9 9t *84 :1.43C+04:

Cs-103 :2.69C*bl.5.3tC+02:2.63C+0* 8.47C*ee!3.90C+02:3.05C+81'2.7?C-e7:

Ba-t39 :9.0CC+CC.6.alC*C3.2.64F*e;;d.00t*et:5.99C-8J:3.c4C 01:1.62C+951 04 148 : 1. 0 6C

  • C 3 ' 2. 37 C + 00.1. 2 3L
  • 0 2 : 9. 00C+ 00 's .e5C-O t
  • 1. 33C+ 0 d ' 3. S oC
  • C * :

84-141 : 4. 3* C

  • PC : 3. 30C -0 3 : 1. e OC + 81 ! 8. 0 3 C
  • e 2. 3. 87 C + 9 3 : 1. e ? C' e 3 ; 2. e6C-0 9 :

34-842 f t 90C*CO : 2.0 3C 03:1.24C-9 8 : e.eeC+Po: 1.72C-e 3 : 1. t SC-8 3:2. 74C-10 :

La-tec :3.!6C*Ct:1.82C*Ct.4.76C-e!:0.eCC+00:0.00C+00:e.20C+00:1.32C+88:

Le=t42 ft.83C-C2's.33C.C3:2.9?C*83:8.e0C*ee e.04C+CO:8.e@C+03:6.SeC+81:

Ce*Iot  ; 8. e t C*C1 ' 5. 4 2C 8 t ? 6. t SC *02 : 0. 03C + 80 : 2.52C-S t : 8. stt

  • 02 : 2.0 FC +0 3
  • Ct-te3 :3.41C'et:1.94C+0!!1.16C-02:8.00C.C3:4.60C+02*8.00C*es:3.99C*e3:

. Ctande 24.10C*01:1.7!C+01:2.24f*@e*0.08C+00:1.GeC*st:8.94C+00:1.4tC*04:

. Pe-143 :1.32C+C2 1.29C Ol'6.52L 02:8.02C*ea:3.05C+01:8.SeC*ea:5.77C+e3:

Pe-144 :4.3tt 03.8.79C=C3:2.19C-04:9. 00C +00 ; t . e C-0 3 : e 00C + 09 : 6.19C-t e:

No-147 :9.00C*CI:3. eat *CO'6.22C-82's.02C*00:6.00C*et:0.88C+00:4.99C+03:

w*te? :3.94Ce02:2.!! cec 2.8.9CC*et.0.02C*e0'8.00C*e0:9.eeC*es:8.3aC+04:

[ . Ns=239 :1.26C*C1 1.25C+02:6.91L*S3.0.00C+00.3. Sit-92:9.88C+08:2.5*C*03:

I l -

  • Calculated using eqtution (32 ) and Tables 1.2-1 and 1+2-2
  • l 1.,o_34 0004, V.C. Sxmr, SCEandG: Revision 7 (October 1984)

Dj

= air due to beta emissions frca noble gas radionuclide i (mrad),

i

= 3.17x10-8[ nix /QQi, (17) i F

where:

Ni = air dose factor due to beta emissions from noble gas radionuclide 1 (mrad /yr per uCi/m3) from Table 2.1-1 2.2.2.b Dose to an individual from radiolodines and radioactive materials in particulate form and radionuclides (other than noble gases), with half-lives greater than eight (8) days will be 4

calculated for the purpose of irrplementation of section 3.11.2.3 of f the Technimi Specifistions as follows:

i Dp = dose to an individual frcm radioiodines and radionuclides in particulate form, with half-lives greater than eight days (mren) j = 3.17x10-8[Rij Wij' Qi', (18) ij where:

Wi j' = relative concentration or relative deposition for the maximum exposed indivudual, as appropriate for exposure pathway j and radionuclide i.

X/Q' for inhalation and all tritium pathways.

= 3.5 x 10-6 sec/m3 l

I D/Q' for other pathways and non-trititan radionuclides

= 1.0 x 10-8 m-2 I

(See the notes to Table 2.2-7 and 2.2-8 for the origin of these factors.)

ODm, V.C. Suntner, SCEnnd', Revision 7 (October 1984) 2.0-11

- . . , _ - - - - - - _ - _-. --

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