ML20082L360
| ML20082L360 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/30/1991 |
| From: | Joshua Wilson TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| NUDOCS 9109040076 | |
| Download: ML20082L360 (192) | |
Text
-
I o
l i
k 1
,a August 29, 1991 U.5. Nuclear Regul atory Cornmission Arlhi Document Control Desk Washington, D.C.
29%$
Ge n t 1.eme n !
In the % Lter of
)
Docket Nos. 50-327 Tenneuee Valley Authority
)
50-323 SEQUOYAll NUC1 EAR PLANT (SQN) - SEMIANNUAL RAD 10 ACTIVE ETF1.UENT RELEASE l
REl>CRT Enclosed is the Semiannual Radioactive Efiluent Release Report for the perled of January 1 to June 30, 1941, which is being s'atmitted in l
accordance with SQN Technical Specifications (TS) 6.0.1.8.
In accordance I
with TS 6.14.1.3, Revision 25 to the Ofisite Dose Calculation Manual is inc.uded in Att.ichment 1 to the encloare.
Please direct questions concerning this issue to W. C. Ludwig at (61$) 5:.3-7!40.
(
Very truly ycurs, l
TENNE 3 BEE VA1.1.EY AUTHOR!rY
{0 3H%
J
- 5.. kilson Enclosure cet See page 2 l
^
t l
f^PDR9164Cf40076 910630 t
l ADOCK 05000327 j \\
R PDR
l o
2 U.S. Nuc l ea r Regul a t ot y Conuni u. lon August 29 1991 cc ( Etie l o v.u t e ) :
Mr. D.
E.
1 a !'.a i ro. Project Manager U.S. Nuclear Regulator y Conenin61on One White llint, 'iotth 115% Hockville Pike f(ockville. Matyland 20 % 2 NRC hes. lilent Inspectos bequoyah Nuc lear l'latit 2600 Igou l'etry Road Sodily Dair.y. Tenneasce 37379 Mr.
- h. A. Wilson. Project Chief U.S. Nuclear Regulator y Conunission It e g i on !!
101 Morletta Street. NW, Suite 2900 Atlanta. Georgia 30323
l 1 NC L0bl.'R l;
!;f QUOYA!! NtT!. l AR Pl. ANT l'FF1.UENT AND kAsil ()ist'es Al SF.M1 ANNUAL kl.I' ORT JANUARY l TO JU!.l~ 30, 1991 i
I I
i l
0 o
KFFLUENT AND WASTE DISI'OSAL SKHI ANNUAL f(El'Ol(T SUFI'LEHENTAL INF0ltMAT10N lot ilALP 1991 1.
l(EGULAT01(Y L1 HITS A.
Caccouc Effluento 1.
Doco rates due to radioactivity rolesced in cancoup offluento from the oito to areas at and beyond the oito boundary shall be limited to tho followingt a.
Noble gasoot-Loco than or equal to 500 enrom/your to the total
- body,
- Leon than or equal to 3000 incom/ year to the skin.
b.
Ioditu.-131, icdino-133, tellium, and all radionuclidos in particulato form with half-livos croator than 8 dayan
- Leno than or equal to 1500 incom/yoar to any orgall.
2.
Air dono due to nobio gason roloaced in gaceous offluento to areno at and beyond the oito boundary shall bo limited to the followingt
- a.
Loco than or equal 5 inrad for gamma radiation and loon than or equal to 10 mrad for bota radiation during any calendar quarter.
b.
Loon than or equal to 10 mrad f or ga:wa radiation and loan than or equal to 20 mrad for bota radiation during any j
calendar year.
3.
Dopo to a inomber of the public f rom todino-131, lodino-133, tritium, and all radionuclideo in particulato form with half-liven greator than night days in geneoub offluento rolosood to arono at and beyond the oito boundary shall be limited to the following:
- a.
Loco than or equal to 7.5 mrom to any organ during any I
calendar quarter.
1 I
b.
Loco than or equal to 15 turem to any organ during any calendar year.
B.
Liquid Effluento l
1.
Tho concentration of radioactivity rolonced in 11guld offluento to unrestricted areno chall bo limited to the concentrations specified in l
Title 10 of the Code of Podoral Hogulations, part. 20 (Standardo for protect.Lon Against Radiation), Appendix B. Tablo II, Column 2 for radionuclideo other 1.han diosolved or entrained noblo gason.
Frr dissolved or entrained nobio gacon, the concentration shall bo limited to 2.0E-04 microcurio/ milliliter (uct/ml) total activity.
- Thoso valuco aro used as appilcablo limito for gacoous roloat.oc...
__m.
6 o
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL HEPORT SUPPLEHENTAL INF0HMATION 18kilAlF 1991 2.
The doco or dose commitment to a member of the public from radioactivity in liquid offluento releaped to unrestricted arono shall be limited to
- a.
Leno than or equal to 1.5 mrem to tho total body and leco than or equal to 5 inrem to any organ during any calendar quarter, b.
Loup than or equal to 3 turem to tho total body and Icco than or equal to 10 mrom to any organ during any ce'endar year.
2.
HAX1 HUM PEHHISSlHLE CONENTHATION A.
Liquido 1.
The maximum pormlunible concentrations (HPC) for liquid
.to thone listed in 10 CFR 20. Appendix 11, Table 11, Column 2, with the most l
routrictivo HPC being used in all casos.
For dissolved and entrained gaces the HPC of 2,0E-04 uC1/mi 10 upplied. Thiu HPC in based on tho Xo-135 HPC in alt (uubmerolon done) converted to an equivalent concentration in water no discunced in the international Comminolon on RadioloSical Protection (ICHP),
publication 2.
l 11 Caucoua 1.
The maximum perminalble dooo raten for gaceouu releacon are defined in plant Offolto Doue Calculation Manual.
a.
Noble gun dopo rato at the utto boundaryt
- Loan than or equal to $00 mrem /your to the total body,
- Leon than or equal to 3000 mrom/yoar to skin, b.
lodino-131, iodino-133, tritium, and particulates with half-11vou greator than eight days dono rato at the oito boundary:
- Loco than or equal to 1500 mrem / year to any organ.
3.
AVKHACK ENKHGY Sequoyah's Technical Specifications limit the dose equivalent ratou due to the rolcano of finolon and activation productu to lose than or equal to 500 mrom/your to the total body and loup than or equal to 3000 mrom/ year to the akin. Thereforo, the average beta and gamma energies (E) for gaseous offluento ao described in Regulatory Guido 1.21. " Honouring, Evaluation, and Hoporting Radioactivity in Solid Wasten and Holonoco of Hadlonctivo Materialu in Liquid and Caseous Effluento from Light-Water Cooled Nucinar power plants," are not appitcable.
- Thoso valuou are used no applicable limits for liquid effluento.
1 _ _ _ _ _ _ _ _ - - -
4 e
EFFl.UENT AND WASTE Dl!;por.Al,f;EHIANNUAl. hep 0RT
!;llppLEMENTAL lHF0kHAT10N ltiJAW l99.1 4.
Houcurementu and Approximationu of Total Radioact tvity NOTE Evory effort tu mudo to enuuro that all offluents from Sequoyah are corjucted cuch that all Of f atto Dopo calculation Manual (ODCH)
Lower Limits of Dotection (i.LDu) are mot.
Whenever an analyalu doep not identify a radioluotopo, n "0.00E-01 Cl" la recorded for the relonuo.
Thiu does not nocoonnelly mean that. no activity won relenned for that particulne radionuclido, but that the concentration wan below tho ODCH and unalyulu 1.LDn.
Hof or to Tablen A und U for cottmnton of thoue typical LLD valuon.
a.
Finnion und Activation Canos Airborno offluont gnuooup uctivity in continuounty monitored und recorded.
Additionni grab unmplos from the chiold building, auxiliary building, uorvice building, and condennor vacuum exhaupta are taken and analyzed at lonut monthly to deto 1nino the quantity of noblo gun nettvity rolonned for the month based on the uvorano vent flowratou recorded (or the unmplo porlod.
Also, noblo gnu unmploo are collected and ovaluated f or t he uhtold and aux 111ary buildingo followinr, startup, uhutdown, or rated thetinni power chango exceeding 15 percent within one hour (numpling only required if dono equivalent 1-131 concentration in the primary coolant has incroauod moro than a factor of 3 and the noblo suo activity monitor shown that the containment activity han incronned more than a f actor of 3).
The quantity of noblo gunoo rotonood through the uhloid and auxillary building exhaupto duo to purging or venting of containment and l
relennon of wanto gao docuy tanks aro also dotot1nined.
Tho tolat noblo gas activity rolenood for the month to then dolorininod by unnuning all of the activity rolonood from each vont for all samplinr. periods, the activity roloauod f rom purging or venting of containment, and the activity roloaned from wanto gan docuy tank (n),
b.
lodinou and particulatou lodino and particulato activity in continuoucly cumpled.
Charcoal and particolato cumplos are taken from the uhtold and auxiliary building oxhauuta and analyzed at lonat wookly to dolormino the total activity roloused f rom the plant based on the average vont flowraton recorded for nampling porlod.
Also, particulato and charconi unmples are taken from the auxiliary and chloid building exhaupto once por 24 houro for 2 days followinr.
startup, rhutdown, or a rated thetinal power chnnr,o exceedlnr 15 porcent within ono hour.
The quantity of iodino and particulato rolonsed from each vont during onch sampling period to then detotmined uutnt, tho averano vont ilowratoo recorded ior the pumplinr, period and activity concentration.
The total particulato and lodino act tvity reloaped for the inonth in then detonninod by pununing all of the activity rolonood f rom the uhtold and auxiliury butiding oxhausto for all sampling, porlodo.
4 g
EFFLUENT AND WASTX DISPOSAL SEMIANNUAL hep 0HT SUp!'LEMENTAL INFORMATION lul_l!A_lg 1991 4.
Measuromento and Approximation of Total Radioactivity (continued) c.
L*. quid Effluento (1) Hap )} (Radwanto and condenuato regeneranto to cooling tower blowdown)
Total ganuna isotopic activity concentrations are dotetsnined on each batch of 11guld offluent prior to relonso. The total activity of a tolonoed batch to dolormlned by numming each nuclide's concentration and nuitiplying by the total volumo discharged.
The total activity rolonced during a month to then determined by pununing the activity content of each batch discharged during the month.
(2) Continuous Releases and l'orlodic Continuous Rolonnes (Condenanto regeneranto, turbino building nump and otoam generator blowdown)
Total gamma f ootopic activity concentration in doteiinined daily on a composito saniple f rom the condonnuto pystem and turbino building ournp and weekly for otoam generator blowdown.
The total activity of the continuous roloano in dolormlned by nunaning each nucildo's concentration and multiplying by tho total volumo discharged. The total activity relenood during the mo th in than determined by uununing the activity content of each daily at., weekly compootto for the month.
5.
llatch Valuo.
Uptts guartor quart o_r, tot 2nd u.
Liquid 1.
Number of batches roloused (Radwasto only) 101 128 Each 2.
Total timo porlod for batch relenoco 14,851 18,321 Hinuton 3.
Maxinum timo period for a batch colonso 191 200 Minutoo 4.
Averato timo period for batch coloasco 139 143 Minutoo S.
Mininum utream flow during porlods of offluent into a flowing stream:
N/A N/A b.
Gaseous 1.
Number of batches colonged 187 216 Each 2.
Total timo period for batch reloacos 14,287 9.452 Minutes 3.
Maxinum timo period for a batch releaso 480 372 Hinuten 4.
Average Limo period for batch relonens 76 44 Minuten 5.
Minimum timo portod for a batch rotonsa 14 13 Hinutoo -.
t e
EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL hep 0HT Suppl.1:HENTAl INFORMATION lut IIAI,F J921 6.
Abno1nel Helencon Valuet _
tJn{1s Quatter Quagtp
...J n1_.
Pnd a.
1.lquid (1) Number of Holoacou O
O (2) Total Activity Helenced 0.00E._01 O_t00thQ1 Cl b.
Caccoon (1) Number of Holeanoo 0
0 (2) Total Activity Holonned 0,,,00 t:- Q 1 0 00_E Q1, Ci 1
1 1.
Of fuito Douo Calculation Manual (ODCH)
Woro any channon mudo to tho UDCH during the reporting porlod?
_.J__ Yus
, No.
Soo Attachment 1.0.
IN0pKHAHIS 1HSTRUMENTAT10N Pursuant to ODCH Section 1.3.1, tho followl.nc inf ot1 nation in provided concerning radioactivo of fluont monitoring inotrutnentation which was inoperable for greator than 30 conuncutivo dayn during the porlod January 1, 1991 t.hrough Juno 30, 1991.
Flow Indicator 1-F1-30-242, which moanurou air flow rate through Unit 1 Shlold Building Exhaust, was dociared inoperablo on October 31, 1907, for oxhaunt flow rateu of luno than 8000 cubic foot por minuto.
2-F1-30-242, which moanuron air flow rato through Unit 2 Shlold Building Exhaupt, was declarod inoperable for exhaunt flow raten of leno than 8000 cubic foot. Per minuto un November 25, 1987. Theco inntrumento were not roturned to an operable utatus within 30 daya duo to the timo f rame roquired to install the noconnary plant modiflentions to onouro compliance with Hogulatory Culdo 1.97 (HO-1.97).
Flow l
ludicators 1,2-F1-90-400 have been inntalled and woro declared operable on i
1/31/91.
Detalla concernine, this upgraue have boon provided in s memo from TVA to NRC dated June 11,1991 on HG-1.97 - Dovlation 29 - Minimum Flow f or SQN'n Shlold building (SD) Stack inot rumentation.
_S.
n-... _ -. - _ _ -.. - -. -.
e-e EFFl.UENT AND WASTE DISPOSAL SEM1 ANNUAL REP 0fd
)pt HAI_.F 1991 L1 QUID EFFLUENTS - SUMMATION OF ALL HELEA9ES l
. lH.L hltl A.
Eiss199_antAttintion v lt
.mr_
Mer9.c
..ato Etr.9r a
o l'rs.Lc.in 1.
Total Rolcased Curlos 1.88E-01 11.81H01 2,551401 11.88+01 2.
Avorugo Diluted Conc.
During Period of All Identiflod lootopen uC1/ml 1.19E-07 1.35R-0T 3.
Percent of Applicable Limit (Total Body Dono) 2.13E-01 6.40E-01 D+
Irltlu3 1.
Total Holeased Curles 3.81E+02 11.8E401 4.33E602 11.8E+01 2.
Averato Diluted uCL/ml 2.40E404<
2.29E-04 Conc. During Porlod 3.
Porcent of Applicable Limit (3.0E-03 uCL/ml) 0.00E+00 7.64E400 C.
pjgsgly3ttyn Lf.et rained Cas_es t
1.
Total Released Curlon 1.38E-01 13.9E+01 9.32E-01 13.9E+01 2.
Averago D11uted uCi/mi 8.71E-08 4.94E-07 Conc. During Period 3.
Porcent of Applicable Limit (2.0E-04 uCL/ml) 4.35E-02 2.47E-01 D.
Crogs,___ Alpha _ Radigac t ivity 1.
Total Roloaned Curles
- 0. 00E- 01 12.0E+01 0.00E-01 12.0E+01 E.
Volumn of Wayte Rotenced (Ucfore Dilution)
Liters 3.28E+07 14.0E+00 2.88E+07 14.0E+00 F.
yolume of_Diluttgn Litors 1.55E409 11.1E+01 1.86E+09 11.1E+01 Weier_lerJatioA 1
I O
O m.
e e
KFFl.UENT AND WA!!TK 1)llil'OSAl, UKHI ANNUAL. ItEl'0HT J p Lil At El',19]
l.1',101 D KFl't.UENTS -
TOTAL l'I. ANT lilUcIlAltGK 0.
J p dogm.,Uinima ry (Notes linf or to Tablo A f or valuun regiorlod nu 0.00K 01) llequired by ODcH/0 thera Vlnulon and Act tynt ton l'roduclu CofillUtM'tlo_Hodg 1)ntfA hode nulldo unit Qvuttor 99 utter quurA er 09arter 19L
._.7IHE,
._l.f! L
_2!UL, t.
ntcont lum n9 ci 0,00EQ1 9a0Egt q1ogLRt pagEg1 7.
at runt lum 90 ci naplept 9,0gE01 g,ppkO1 0,00lt01 3.
Iron-55 ci pappE01 g,90E01 222!'E9?
h.;l!'E92 4.
Hunr,anono $4 ci popqEQ1 QdOE01 idHMJ3 h19KJ1 S.
cobalt 58 ci h1SE91>
9t99EP1 M1 EOR 9 ti1E9R 6.
Iron-59 ci paqlE01 p.aqE91 Id3kOA 9d9E91 1.
cobalt-60 ct
- l D E 04 M1E01 LMKJi' MislE92 t
H.
Ilnc-6s 01 0 0kMal Qa0E01 PAGE01 LAllEQk x
9.
Holybdonum-99 ct RtQg(01 qdOEQ1 QJpE01 ia} Epi 10.
lodino~131 ci
!1R?y,- 0 7 0.,0ghp1 1,9 Midi MiEQ1 11.
coutum-134 ci h44EO) 2AtEgh LME01 h92E9.Z 12, coutum-131 ci hplk91 FEERh 2dAE01 hM' EOR 13, cor t um-141 ci p20pkO1 9390k91 9 DOE 91 EdOE91 l
14, corium-144 cl 0 &QE9]
.Q300E0.1 paQEQ1 ga.' 4ll7_pi L
t 15.
Ant imosty-125 ci buqE01 Q10gE01 L.QSEgg
,4 Jkg-pg i
a l
l 16.
coba1t 51 ei k,12E91 pdOE01 h19ER4 L.11th01 17.
chromium-51 ci 9 DOE 01 249E01 M 3?E91 6A3 ERA 18.
Niobium-9s cl QtgqEQ1 O 00E0{
2.tg9EQ3 M]Ihq4, a
r-
~ _ _ _ _.. _ _., _.. _ _ _ _ _ _.
.. _. _. ~ _
. _ -. _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ -.... _ - ~ ~. _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _
I e
o I<FFl.tlENT AND WAfiTH DIGl'USAl. tiKHI ANNtlAt. ItKl'OltT InLI!ML1991 1.1QlllD KFFIAlENTS - TOTAL l't. ANT DilsCI(Al(GH (CONT 1NUKU) l continunp_Mn Imtdtngon Nuclido unit guarter quatter gun _ttet gunctxt
._1 (81_
- ltid_
._] 81_.
.__2D4, _
19.
todino-133 ci pa0E;01 EdoE01 bal!Eqh L Dih91 l
20.
Zirconium 95 ct 9 DOE 91 9ARERI 11A1Ls h191EM 21.
Toe tinot t um-99m et c ppE91 9d9thol RdRM-91 L911)E91 u
22.
leuthentum 103 ct L9EERt 9aD9E91 h4fFc_0k h))LQ(,
1 23.
Totturium 132 ci gtqQlEQ1 9300lkOl
- 6. JOE 0?!
QdOI,hQL 24.
Antimony.124 ct applEq1 p,90Ep1 pu0 m 03 9,21K-91 25.
i.unthunum 140 ct 0 00 Eg1 OdOE01 AtlAE9h Ad9fc.DA 1
26.
centum 136 ci p200E01 h00K- 01 9 a 0 E iL1 la0E91 27.
nodium 24 ct 9dRL91 L99 EPA 11.24 Fc_01 L91ERh 2a.
todino las ct 9199E91 949 ERA 2dikSit L UJk9A l
29.
ntronu um 92 ct naarc01 gaqEnt up.ent 3,3nd3.
30.
Yttrlum-91 ci 0 9php]
pdQJE01 1,Jlkp]
h0Q]h01 1
31 lodino 132 ct 9dQE01 9dQ.lF 91 -
R&9h21 h A !E d k l
l 32-Etuc 69H ct QtQQLQ1 Q 001 Q1 91 phQJ la41EQ}
0 33 cortum-143 ct gdOEql gaqE01 b]3E04 gag 0Egl l
Total for l'ortod ci 2 dBE-9_4 ii.4lE9A idlX11 h#1>E01 0
i l
l
-a-
~-_ _. _
e e
S EFFLUENT AND WACTE DISPOSAL SEM1 ANNUAL HEP 0HT l!!1_.EA.I E.1991 f
LIQUID EFFLUENTS - TOTAL PLANT DISCilARCH (CONTINUED)
C.
l!!91ol'E SJ!?Enty (NOTE:
Hofo to Table A for valuce reported au 0.00E-01)
Required by ODCH/Others Dlocolved and Entrained Noble Casos E9D110,upng_Mgle hu_idLMgdg Nucildo Unit Qu_oylel Quarler Qu_ni o_r Quayter t
_ 2L 18L
- lui_
_.1PL 9
1.
Krypton-81 Cl 1 9.90}',,01 0.00E-01,
- f.,12 E- 06 0 pp0);-0J 1
2.
Krypton-88 Ci 0 00E-ql b_00E_0_1 p,00lbot, 2 801i_Q5 0 903-01
,1 33E-01 p.94E-01 3.
Xenon-133 Cl 7.93E-0j 1
4.
Konon-133m Cl 0.00E-01 QuQpfc_01 8.92E-04
_1.15 E-9 2, 5.
Xenon-135 Ci p_t99,J?- 01 QiO0E-01 1.15E-03 1 86E-02 6.
Xenon-138 Cl 0 00E -0J Q.00E-01 0.00E-01 0.003 3 2
1.
Krypton-85m Ci 0.00E-01 O 00E-01 1.41E-05 1.15E-05 a
8.
Xenon 131m Ci 0.00E_Q1 Q190E-0_1 1.41E-03 1.36E-03 9.
Xenon-135m Ci 9 00E-01 9200E-01 2 96E-Oi 1.28E-04 Total for l'eriod Cl J.93E-05 h00E-01 1.37E-01 9.32E-01 l
l l
l l
1 9-
___m e
o itFFLUENT AND WASTE DISI'OSAL fiEHI ANNUAL HEl' ORT InULAJJU1.1 9
TABLE A LIQUID "TYl'1 CAL Lt.D" EVALUATION (1)
At(2)
Nuclido ongyML.JEm l.a._.
_3_0 JEltL-
- Lhr__
2 ht-_
Heinr,aneso - 54 hpE,ql
- 9. lgE,09 2.JJ2 Epi 1 1?E-9]
h))fE-09 cobalt-so LREQI 8d13 -09 n.21E-09 E lt_r,-p3 0.718-02 t ron-59 1 0E-01.
J_. 6ffi-Og 1,62E-00 1.67E-On id??_E-Og cobalt.60 LO&p1 t aaH-08 hqpt-OR hPfkpa h9aE9h zine-65 AaE01 Pu14E98 Zd4 E-08 22 14E-08 hiiE9a Holybdenum-99 p AE01 h24En08 hylyde
- dph-Og
}J4H-Og co n tum-134 10h01 1, g7fi-pq.9 9,u2E09 9 affi-Og
,9 q?fcqq t
g t
conlum 137 5,pi ql 1.llE99 id3fc99 9,31E-09 9 11E-09 corium--141 h9E9.1 LO6E-08 hg6fE9a holERR h0 ? E- 08 certum-144 hgE- 06 AapjE-08 4 03f:2QU 4 9)fdg 4_. 0_3fc0g Q
1 lodino.131 1 OE-06
- 7. 78 E09
_7, 7 8 E- 09 7.30E-09 7.32E-09 Krypton-01 j dE.O.h it!t2H-08 h85E-06 Zd3E-on itg,0E-Og Krypton-HB IdH.Rfi
/ 11p 08 J,21E-08 23 568-08 h2]fdg
(
Konon-133 1,0E-05 21lEgg 2.t04 E-_08 2,04E-08 2,0$E-08 0
i Xonon-133m h9fc0J
_}.05E-Og 5,07 Fc9_g 5,10E08 1,17E-06 Kenon-135 1,0E-Oh
}16qF09 5.10E-0g
},93E-09 6,40E-09 Kenon-138 inQEQ5_
fag 119J1 h, 8 ?J-q8, LS}M-07 4.79E-06 i
I l
{
4 o
EFPLUhNT AND WASTH DISP 00AL SEHtANNUAL REP 0HT 181)LAMJi91 TAllLK A t,1 QUID "TYp1 CAL LLD" EVALUATION (1)
(Continued) linlide 9KtLkW Tynisal I.Lu 7ettium lar,@
IJE-06 Group Alpha AJt;-01
? 0E-08 Strontium-89
)JJi,0_8 JJKJj IJF 01 fit s ont lum-90 kJR-08 n
1ron-55 JAK- 06 3.0H-01 110TK;il (1) 1.1,0 valuen arn in uct/ml.
Samplo analycon are performed to onoure that ODCH Lt.D limits are mot.
Those are typical LLD valuun.
(2)
At in the timo between onmple collection and countint, timo, i
l l
1 I
t EFF1.tlENT AND L'ASTE DISPODAL SEMI ANNUAL REl' ORT let ilALP 1991 CASEOUS EFFLUENTS-SUMMATION OF ALL REl. EASES (GROUND LEVEL RELEASES)
. La L
.J.nt.
gu199LlILtLHl_AJJ__ILolgtsfin Unli
,3(r_,
M rtpot
,.,Q(r_
Mrtgr A.
Nohle Canes 1.
Total Roloaned C1 2.83E402 11.1E401 2.18E+02 11.1E401 2.
Aver.ico kolcoco Rate of Portod uC1/soe 3.64E401 3.58E601 3.
Porcent of Appitcublo 3.00E-01 5.20E 01 Limit (Cavuna)
II.
I9illina 1.
Total lodino-131 Ci 0.00E-01 11.3E401 0.00E-01 11.3E+01 2.
Average Holoaco Rato for Porlod uct/coe 0.00E 01
- 0. 00E- 01 C.
l'gilquJnics 1,
Particulatoo with Ci 2.01E-06 11.68401
- 0. 00E- 01 11.6Ef01 half-livon >8 days 2.
Average kolcace Rato for Period uC1/poc 2.58E-01
- 0. 00E- 01 3.
Group Alpha Radio-Ci 0.00E-01 f2.1E401 0.00E-01 12.1Ef01 activity D.
TIllit!!g l
1.
Total Rolcano 01 9.00E-01 11.5E401 5.82E400-11.5E+01 l
2.
Average Releaso Rato for l'ortod uct/coe 1.16E-01 7.48Pr01 E.
3-131 ul-132 di-3__and
[a.ttistulates with ha,JL
,lifen >B dayg 1.
Porcent of appilcable 6.67E-03 5.33E-02 Limit.
(Max Organ-Child Livor) _.
4 o
EFFLUhNT AND CASTE DISPODAL SEM1 ANNUAL HEP 0HT ltLIME.119.1 CASE 0VS EFFLUENTS-SUMMA't!ON OF ALL REl. EASES (CROUND LEVEL REl. EASES) 09ttLlmtqug_tiojp pq(sh,tigde unit Marter Wer_Let Marler War.ter
. 18t
.- 2 011 _
l!.L.-
Uld---
F.
Noble Cacent Roquired by ODCH/Othere i
i 1.
Ky plon-- 8 7 C1 2 t.12fc03 h,4,2L-Q4 p.00E-01
.t. 24 E-04 2.
Krypton-88 Cl
}.15E-pl 11.19[-04 8.77E-02
).93E-Q2 3.
Xenon-133 Ci 1&Etpl it19.E-01 9.36E401 h!!itiLQ1 4.
Xenon-133m Ci dt.Q,0fM 9300E-01 1.19E400 2.731000 5.
Xenun+135 Cl idi)f _.03
_2.29E-01
- 1. 65 EJ o_0 3.68E+00 0
6.
Xenon-138 Cl 91Qpj;01 0.00E-01 0.00E-01 0.00E-01 1.
Krypton-85 Cl 9 00E-01 p.00:-01 1.01Etqq 2.28E490 8.
Argon-41 Ci Q.00Fe.91 Qtpp!:;0_1 p.69E,01 6.60E-01 9.
Krypton-85m CL k.19 E- 03 9.66E-05 B.43E-02 1.73E-01 10.
Xenon-131m Cl O 00E-01 0. 00 E-0_1, 1 44E+0_0 2,14E+00 a
11.
Xenon-135m Cl 1.93E-02 3.02E-04 9200E-01 0.00E-01 Total for Period Cl
_1. 8 3 E +0_2 9.40E-01 9.98E+01.
g 77E402 0.
Iodinos 1.
lodino-131 gl 0.00E-01 0.00E-01 2.
Jodine-13),
91 p.00E-01
^ 00E-01 3.
_ lodine-135 Qi O.00E-01 0.00E-01 Total for Porlod Ci 0,00E-01 0.00E-01 NOTE: Refer to Table B for values reported no 0.00E-01.
e EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT ILLlt% LIM 1 CA30008 EFFLUENTS SUMMATION OF ALL RELEASES (CHOUND IEVEL RELEASES) 11.
l'atusulates Hoquired by ODCH/Othero uucildo Unit Condnuoup_H_o,40 Qu_alttitt Wurtet lpL__
__. 2nd 1.
Strontium-89 Ci QA0E _Q1 2100E-01 2.
Strontium-90 Ci 0.008-01 0.00E-01 3.
Iron-59 Ci 0.00E-01 0.00E-01 4.
Cobalt-60 Ci Q100E-0J O_.00E-01 5.
Zinc-65 Ci 0.00E-01 0.00E-01 6.
Manganoso-54 Ci 0.00E-01 0.00E-01 1.
Cobalt-58 Ci 2,011_p1 0.00E-01 8.
Molybdenum-99 Ci 0 006-01 0.00E-01 9.
Conium-134 Cl 0.00E-01 pdOE 0),
10.
Cesium-131 Ci 0.00E-01 0.00E 01 11.
Corium-141 Ci 0.00E-01 0.00E-01
(
l 12.
Cerium-144 Ci 0,00E-01 0.00E-01
(
Others (Specify) l Total for l'ortod Cl 2 01E-06 0_.00E-01 i
l NOTKt Refer to Tablo li for values reported as 0.00E-01, t
l 1 -
o EFFLUENT AND WASTE DISPOSAL SEH1 ANNUAL ltEPORT lult!Altr_ll9.1 TABLE D CASEOUS "TYl'1 CAL" LLD EVALUATION (I)
N0ltip_ Gag 3((2)
~
Hutt.119 ODCL!M
.__1 hr
,_L 5 h r_.
Krypton-H1 A dE-94 h19E-06 2 19fcQt Keyplon-IIB I g ;QA 1 22E-Oh L]iydk Xenon-133
,1,0E 04 Lig-01 k,56E-01 Kenon-133m i g -01 L19,li,01 31,02E-06 Xenon-135 AdE _Q4 2d9F-Q2 RJ0E-07 Xenon-138 hqE_01 LilflE-05 H.55E-05 l'.ar11mla.to Somnia
- 1207Ja, 2,79 d4_
L 79 tja_
Hant,annon-54
} OE,,J,Q h8_3g _-Q L 65E-11 blog:M Cobalt-58 hgE-1Q in,Qli-j,2 b]9E-14 9,19E-15 6
1ron-59 LOR-10 h2111-M
- 1. 36 Fcu 7 033_11 cobalt.-60 1.0E-LQ Ll1E-12 14M:M 1,07ti:M 7.I ne-65
l M lybdenum-99
},08-10 gJflE--12 1,05E-13_
3,18E-14 Co: lum-134 hqFcl_q 2 d 3J1-J 2 D M S)) M 1.21E-14 I
r'oa lum-131 hQE-1Q Ljl5E-12 J 4 71 M-M.
1 10E-1A l
Cerium-141 L OE-10 Rd2fc_1g 9,828-14 1,50E-14 I
i corium-144 laulq LOR:12 h2fE.:n bl6?cB lodif 'o-ib 1 0E-10 L 8R -12 LZgE-14 1,1?I H Gharsul?_.mnh 4
,_2.0 da_
.2,5 da 5. 5_ d a_
lodine-131 LOE-11 2.53E-Q L 10ft-13 2.00E-1_4 -
t e
EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT 1s1 IIALF 1991 TABLE D GASEOUS " TYPICAL" LLD EVALUATION (1)
(continued)
]Luq11do ODCH_L1_.D Iypical_LLD Tritium 1.0E-06
- 1. 0E-11 Group Alpha 1.0E-11 1.5E-14 Strontium-89 1.0E-11 1.0E-14 Strontium-90 1.0E-11 1.0E-15 N0_ItEh (1) LLD valuco are in uCi/cc.
(2) At f or noble Ensos le the time f rom sampling to analynto.
At for charcoal and particulato comples is the midpoint. of sampling to analysic..
t e
EFFLUENT AND WAUTE DISP 0SAb SEMI ANNUAb EEp0RT lot HALF 1991 SOLID WASTE (FAD 10 ACTIVE SHipHENTS)
A.
Solid Wanto Shipped Offatto for Durial or Disposal (tiot Irradiated Fuel) 1.
Iypo..g[_Wanto
,thdi l'cE} g.t11 6Jio
.E o t. 19.12 od KrroM a.
Spent roolna, fliter sludges, m3 3.49Et1 11.00E-1 ovaporator bottoms, etc.
C1 1.11Et3 11.50E+1 b.
Dry Active Wasto, Comproculble Woote m3 2.44E+1 11.00E-1 Contuminated Equipment, etc.
C1 4.38E40 11.50E+1 3
Irradleted Componento, m
Notio N/A Control Rodo, etc.
Ci None N/A d.
Other: Mechanical Filters mI 3.41E40 N/A Ci 6.64E10 N/A 2.
Estimate of_Mahr_ Nucl_ido Copp,q.tdl,Lo_gjl)y,_t_ype of Woolol a.
Spent resin, filter sludgeo, ovaporator bottoms, etc.
(nuclideo determined by monourement)
WC33"o l'EE9ettt 1.
Mangancou-54 1.4HE41 1.34Et0 2.
Iron-SS 1.35Ee2 1.22E+1 3.
Cobalt-58 4.10Et2 4.24Ett 4.
Coba lt-60 1.21Et2 1.09E+1 F.
Nickol-63 1.95E42 1.76E+1 6.
Ceo lum-134 6.95k41 6.26E40 7.
Cen tum-13 7 7.92E+1 7.13E40 8.
N8.;*61 59 1.61Et1 1.45Et0 b.
9ty active wasto, comprescible wanto, contaminated equipment etc.
(m elldes determined by estimato) 1.
Chromium-51 4.97E-1 1.14Et1 2.
Iron-55 1.06E60 2.43E+1 3.
Cobalt-58 2.03E40 4.64E41 4.
Cobalt-60 3.86E-1 8.00E40 5.
Nickel-63 1.75E,1 A. t'0E 40 6.
Niobium 95 1.28E-1 2.92E40 7.
Zirconium-95 5.41E-2 1.24E40 c.
1tradiated Componento N/A N/A d.
Other: Mechanical Filtero
@rjgs percerlt 1.
Hanagancoo-54 1.33E-1 2.00E60 2.
Iron-55 3.27E&O 4.92Et1 3.
Cobalt-50 5.15E-1 7.76E40 4.
Cobalt-60 1.83Et0 2.75Et1 5.
Nickol-63 t,87E-1 1.34E+1 0419a
- I 'l-
/
1 PFFl.llENT AND WARTE lill;l'OSA1, !!EHI ANNUAL, i<EI' ORT lui llAl.F 1991 l
Col.lD WASTE (HAD10 ACTIVE Silli'HENTU) 3.
.tigljil WautitjllppoolM9!)
Nyty.bor of_,plilpesjt)lR Tyt?Ja.ptttily Kgdat.9LTrjttusport aljpg prediluttip!)
u) Spont ronin, fittor ciudges, ovuporator bottomo, etc.
76 A-l.!: A Hotor Prolght lluenwoll, SC 3
Il-LSA Hotor Froltht llarnwell, SC p utnti.c p o L t;}tt. lyn.ein t o Tyj? A ug)(1(y NgthngLT.tn_ tit!por[a1{gg
[ht!!.(.ltin1{p!)
b) Dry activo wanto, comprountblo wanto, contaminolod equipnient, etc.
46 A-l.!! A Hotor Prolght llarnwoll, I:C N_unilmp_nLJhlpingttt;v1 Tyly,Ryutt1(y M9jhtyLTI:enppgrt a(1o!)
Enjillug(inti c)
Irradiated componento, control rodu, etc.
Nono Run3tiot_g[Jhlpeg tit:1 Tyt!t,Qyall.t1(y M9jhty!L'Ogpptt9tig(jpn prn[)ttittjon d) Othor: Hochanicul ilitorn.
1 A-1.SA Hotor Frolght llarnwell, !!C 4.
J pte d i g (ed.,fite 1_ !;)11 ppp!1(o ( D 1 u po s 1 t i on )
Holnl e.r PLGll)pinott{g Ty3yLQuitn{Jiy MgibtgLTreytoportaljpg pyjt(Jtitt(lpit l
Hono N/A N/A N/A 891 AJilll.cujjprLo.LWald!!
l Was colidification performod?
No If you, colidifleation modlat tiLA_
6.
Wero uny channon made to the proccup control program?
_You
_ l,_No if you, udd up an attachment at the end of report in accordance with l'rocoon Control l'rogram Soction 9.0.
1.
Woro any major changou mado to the radioactlvo wanto ayutoma (llquid, gavooun or solid)?
You _ K No.
If yes, add an uttachment at the end of report in accordance with Technical Specification Administration Control 6.15.
0419a..
-- - - -~-.~. _ _,____._
Attachmont 1.0 l
/
e n
y n..
,n n - --
,.c... --.m c...,,,,.. -,
-,.a
i SEQUOYAH NUCLEAR PLANT OFFS TE DOSE CALCULATION MANUAL TDNESSEE VALLEY ALITHORITY
\\
l l
l
.rew-----*wwee-
,y erso--,.m-n4=--wv--e.--qt..-.w--w er
..--e<<
-r w. y w y,
s-cr-3,-
---w,.e,-w e3--.,
ree.--eeyme.-.-
e, o
ST000YMLRUCLI AILPLMit DITSITLP05LCMCULATiflLMMfUAL DATES _DL PEYI510liS Original ODCM 01/29/801 Revision 20A 12/14/868 kevlalon 1 04/lb/80i Revision 21 02/1L/092 kevision 2 10/07/U0#
Revision 22 06/01/898 kevision 3 11/03/80, 02/10/81 kevision 22 06/01/892 04/08/81, 06/04/81F Revision 23 06/28/89, 09/10/898 Hevision 4 11/22/82 10/2?/01, Revision 24 02/15/908 11/28/81, 04/29/828 Hevision 26 11/02/90, 04/24/91 2 Fevision $
10 / 21/ ft 2i kevision 6 01/20/838 Hevision 7 03/23/038 Levision 8 12/16/832 Revision 9 03/07/84 8 kevision 10 04/24/84 8 Novlsion 11 08/21/84 8 Reviniors 12 02/19/858 kevlalon 13 12/02/868 Revisloc 14 04/14/868 Revision IL 11/05/868 Revislen 16 01/16/078 Nevision 17 10/28/078 Revision 10 01/Ob/882 Revlalon 19 03/30/882
)
Revision 20 07/19/888 Approved by
. f,um Date j
rah C alt k
Approved b k1 Q Date a
i Manager, Chemistry 1
and kadlological Services l
l l
1 how Powe r license f or Sequoyah 11 nit 1 2 RARC Meeting dato 8 Dats approved by RARC Chairman l
d Revi alon 23 Arnp3 ement.s the Nuclear Data Ef fluent Mansigement
- Software, This ODCM revision and the software will be implemented concare er.tly on October 9, 1989.
Heleanos made dur 'ng the rnonth of October prior to the sof tware 1:rplementation will be backfitted to comply wlub this revision.
i
)
0010v
<__m A
O I
SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING Revision 25 Page(s)
Rev3sion TOC-1 Revision 25 TOC-4 Revision 25 Listing of Dates and Revisions Revision 25 1-2, 9-11, 35, 48-50, 74, 91, 98, 100, 102, 104, 106, 111 Revision 25 113, 115, 11'/, 119, 122-123, 130, 138-143, 145-146, 154 l
"*IOh t
l EPL-1 h
0010v
e, e
e i
SEQUOYAH NUCLEAR PLANT
~
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS
~~ Revision 25 page 1.0 CArCOUS EFFLUENTS 1
1.1 RELTASE POINTS DESCRIPTION 1
1.2 D6SE RATE.
3 1.2.1 REQUIRFMENTS 3
1.2.2 REPORTING LIMITS 4
1.2.3 NOBLE CAS DOSE RATES 4
1.2.3.1 Total Body Dose Rate 4
1.2.3.2 Skin Dose Rate 5
1.2.4 1-131. 1-133 TRITIUM AND ALL RADIONUCLIDES IN PARTICt' LATE 2
FORM WITH HALF-LIVES OF CREATER THAN 8 DAYS - ORcAN DQSE RATE 6
, /
1.3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 7
1.3.1 REQUIREMENT 7
1.3.2 RELEASE SAMPLING, 8
1.3.3 INSTRUMENT SETPOINTS 9
1.3.3.1 Release Point Monitor Setpoints.
9 1.3.3.1.1 Containment Purr.e Effluent Monitors 9
1.3.3.1.2 Waste Gas Decay Tank Effluent Monitors 10 1.3.3.2 Discharge Point Monitor Setpoints 11 1.3.3.3 Dir. charge _ Point Effluent Monitor Default Setpoints 11 1.4 DOSE - NOBLE CASES 12 1.4.1 REQUIREMENTS 12 TOC-1
)
0010v
e e
i 4
SE000YAH WUCLEAR PLANT I
0FFSITE DOSE CALCULATION MANUAL I
TABLE OF CONTENTS Revision 24 page 1.4.2 CUMULATTVE DOSE CALCULATIONS - WCBLE CASES 13
- 1. 4. 2.1 g_ansne dose t o al -
13 1.4.2.2 Beta dose to air 14 1.4.2.3 Cumuistive Dose - Wohle_Cas 14 1.4.2.4 Comparison to Limits 14 1.5 CUMUtdTIVE DOSE - I-131. T-133. TRTTIUM AND RADIONUCLTDES IN PARTICUI. ATE FORM 15 1.5.1 REOUIREMENTS 15-1.5.2 DOSE DUE TO T-131. I-133. TRITIUM AND ALL RADIONUCLTDES IN PARTICULATE FORM WITH NALF-LIVES OF CREATER THAN 8 DAYS 17 1.5.2.1 Otran dose calculation 17 1.5.2.2 Cumulative Doses 18 l
W 1.5.2.3 Comparison to Limits 18 l
1.6 CASEOUS RADWASTE TREATMENT 19 1.6.1 REOUIREMENTS 19 1.6.2 DOSE PROJECTIONS 20 1.6.3 CASEOUS RADWASTE TREATMFNT SYS' TEM DESCRIPTION 20 1.7 OUARTERLY DOSE CALCULATIONS 21 1.7.1 N0BLE CAS - CAMMA AIR DOSE 21 1.7.2 NOBLE CAS - BETA AIR DOSE
'21 1.7.3 RADIOTODINE. PARTICULATE AND TRITIUM - MAXIMUM ORGAN DOSE _
22 TOC-2
')
00101 Nef '
1 4
.{f..
I T5 4
6,[h.,
,[
h'-
,n,,
v
> t?
_ _,.,j d D?
- * * * + ' *
~ -
e-SFOUoYAH NUCLEAR PLANT 3
OFFSITE DOSE CALCULATION MANUAL
, TABLE OF CONTENTS Revision 24 P888 1.7.4 POPULATION DOSES 23 1.7.5 REPORTING OF DOSEC 25 i
1.8 CASE (i.' RELEASES - Dose Factors 26-l 1.8.1 PASTURE CRASS-COW /00AT-MTLK INCESTION DOSE FACTORS - Rgpi 26 1.8.2 STOREt, FEED-COW / COAT-MILK TNCESTION DOSE FACTORS - RCSi 27 1.B.3 PASTURE CRASS-BEEF TNCESTION DOSE FACTORS - R pt 28 g
1.8.4 STORED FEED-BEEF INCESTION DOSE FACTORS - Rgst 29 1.8.5 FRESH LEAFY VECETABLE TNCESTION DOSE FACTORS - Rypt 30 1.8.6 STORED VECETABLE TNCESTION DOSE FACTORS - Rygt 31 1.8.7 TRTTIUM-PASTURE CRASS-COW / COAT-MILK DOSE FACTOR - RCTP 32
- w+
1.8.8 TRTTIUM-STORED FEED-COW / COAT-MILK DOSE FACTOR - RCTS 33 1.8.9 TRITIUM-PASTURE CRASS-BEEF DOSE FACTOR - RMT 34 1.8.10 TRITIUM-STORED FEED-BEEP DOSE FACTOR - RMTS 35 1.8.11 TRITTUM-FRESH LEAFY VECETABLES DOSE FACTOR - RVTF 36 1.8.12 TRITIUM-STORED VECJTABLES DOSE FACTOR - RVTS
'37 l
1.8.13 INHALATION DOSE FACTORS-Ryg 38 1
l 1.8.14 CROUND FLANE DOSE FACTORS - C*gg 38 l
1.9 DISPERSTON METHODOLOGY 39 1.9.1 ATR CONCENTRATION - 1 (pC1/m8) 39 1.9.2 RELATIVE CONCENTRATION - r/0 (sec/m')
40 TOC-3 hf
)
00101 i!
- c k,' l; a br M hbff)
'w
$.~
- kN{!-W!. %***NisM f
E G M ?i'
- -. ~..
~
e, e
}
SE_QUOYAll NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Revision 25 Page 1.9.3 RELATIVE DEPOSITIOK-D/Q (m-2 )
41 2.0 L10UID EFFLUENTS 42 2.1 RELEASE POINTS 42 2.2 CONCENTRATION 44 2.2.1 REQUIREMENTS 44 2.2.2 MPC-SUM OF THE RATIOS 45 2.3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 46 2.3.1 REQUIREMENTS 46 2.3.2 RELEASE SAMPLING 47 2.3.3 INSTRUMENT SETPOINTS 48 2.3.3.1 Discharge Point Monitor Setpoints 48 2.3.3.2 Release Point Monitor Setgoints 48 2.3.3.3 Release Point Monitor Setpoint 50 2.3.4 Post-Release Analysis 51 2.4 DOSE 52 2.4.1 REQUIREMENTS 52 2.4.2 CUMULATIVE LIQUID EFFLUENT DOSE CALCULATIONS 54 2.4.2.2 Monthly Dose Calculations 55 2.4.2.3 Cumulative Doses 55 10C-4
-]
d 0010v
_.. _.. _... - _.. _ _. ~.... _ _ _ _
e SE000YAH NUCLEAR PLANT OFFSITE DOSE CALCULATION _ MANUAL I
TABLE OF CONTENTS Revision 24 Pete 2.4.2.4 Comnarison to Limits 55 2.5 LTOUID WASTE TREATMENT 56 2.5.1 ETEgy,IREMFWT 56 2.5.2 LIOlIO RADWASTE TREATMENT SYSTEM 57 2.5.3 DOSE PROJECTIONS 57 2.6 OUARTERLY DOSE CALCULATIONS 58 2.6.1 WATER INGESTION 53 2.6.2 FISH TNGESTION 59 2.6.3 SHORELINE RECREATION 59 2.6.4 TOTAL MAXIMUM TNDTVIDUAL DOSE 60 2.6.5 POPULATION DOSEE 61 2.7 LTOUTD DOSE FACTOR EQUATIONS 63 2.7.1 WATER INGESTION - A it (arem/hr per pCi/ml)
W 63 2.7.2 FISH INGESTION - Arit (area /hr per pCi/ml) 63 i
2.7.3 SHORELINE RECREATION - ARit (mrom/hr per pC1/ml).
_63 3.0 Fadiological Environmental Monitorint-65 l
3.1 MTNTMUM REOUTRED MONITORING PROGRAM 65 i
l 3.1.1 REOUTREMTNT 65 3.1.2 MONITORING PROGRAM 66 3.1.3 DETECTION CAPABTLTTTES 67 TOC-5
.b 4 00101 a
g fi0.y...
L.y lh*;g6J,5l.JW
. ;f' -:'vW
$Er
-.ns, - -?Y'
g
.j.
l SEQUOYAH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL i
TABLE OF CONTENTS Revision 24 Page 3.2 LAND USE CENSUS 68 3.2.1 REOUIREMENT 68 3.2.2 IAND USE CENSUS 69 3.3 INTERLABORATORY C0KPARISON PROGRAM 70 3.3.1 SEOUIREMENT 70 3.3.2 INTERLABORATORY COMPARISON PROGRAM 70 4.0 TOTAL DOSE 71 4.1 REOUIREMENT 71 4.2 ANNUAL MAXIMUM INDIVIDUAL DOSES - TOTAL REPORTED DOSE 72 5.0 REPORTING REOUIREMENTS 73 Q
5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 73-5.2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 73 6.0 DEFINITIONS 75 6.1 CHANNEL CALIBRATION 73 6.2 CHANNEL CHECK 75 6.3 CHANNEL FUNCTIONAL TEST 75 i
6.4 GASEOUS RADWASTE TREATMENT SYSTEM 75-6.5 DOSE EQUIVALENT T-131 76 6.6 NEMBER(S) 0F THE PUBLIC 76 6.6 OPERABLE - OPERABILITY 76 TOC-6
..c a'
D0101
&as..w. @ yi':.'
b.theK
.- ~d:ttt se+&~i. n - ~i b
J.
a e
s
.-,4 0
0 SE000YAH NUCLEAR PLAhT OFFSITE DOSE CALCU QTION MANUAL TABLE OF CONTENTS Revision 24 page 6.B tippj
?6 6.9 PURCE - PURCTNG 76 6.10 RATED THERMAL POWER 77 6.11 JJTE BOUNDARY 77 6.12 povRcE CHECx 77 6,13 UNRESTRICTED AREA 77 6.14 VENTit.ATION EKRAUST TREATMENT SYSTEM 77 6.15 VENTING 77 9
l l
TOC - 7
%c
.I 00101 i
i'n
-jyk '..
L ' [ *e,
p '.'$ '{ ?' -
d i
~~6--
,a
,, ~ - - + " ~.
Q-
+,
,tv
e o
SEOUOYAH NUCLtAR PLANT OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES Revision 24 page 1.1 RADIOACTIVE GASEOUS WASTE MONITORING SAMPLING AND ANALYSIS PROGRAM 78 1.2 JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES 82 1.3 SQN - 0FFSITE RECEPTOR LOCATION DATA 89 1.4 DOSE FACTORS FOR SUBMERSION IN NOBLE CASES 90 1.5 RADIDACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION 91 1.6 RADICACTIVE CASEOUS EFFLUENT MONITORING INSTRUMENTATION SUEVEILLANCE REQUIREMENTS 93 1.7 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES 95 1.8 POPULATION WITHIN EACH SECTOR ELEMENT 96 1.9 INCESTION DOSE FACTORS k
98 1.10 RADIONUCLIDE DECAY AN'D STABLE ELEMENT TRANSFER DATA 105 1.11 DOSE CALCULATION FACTORS 108 1.12 IMHALATION DOSE FACTORS 110 1.13 EKTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED CROUND 118 2.1 RADI0 ACTIVE LIQUI.D WASTE SAMPLING AND ANALYSIS PROGRAM 120 2.2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 124 2.3 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 127 2.' 4 RECEPTORS FOR LIQUID DOSE CALCULATIONS 129 2.5 BIOACCUMULATION FACTORS FOR FRESHWATER FISH 130 TOC-8
'_y:
a g
.. am.
.. =
3
- y n
~
. ~..
s a
SEQUOYAH NUCLtkR f16TJ, g
OFFSITE DOSE CALCUL& TION MANUAL LIST 0F-TABLE-Revision 24 Page 3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 131 3.2 MAXIMUM VALUE!, FOR THE LOWER LIMITS OF DETECTION (LLD) 134 3.3 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 136 3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 137 3.5 SEQUOYAH h"JCLEAR PLANT - ENVIRONMENTAL RADIOLOCICAL MONITORING PROGRAM - SAMPLING LOCATIONS 141 3.6 SEQUOYAH NUCLEAP PLANT - THERM 0 LUMINESCENT DOSIMETRY LOCATIONS 143 TOC-9
^e l
)
.00101 1
(
.lN
- t i
y4,.g' 4a -
t*
- fl
'f L.L
~~' "~~
~~'
o SE000YAH NUCLEAR PLANT I
0FFSITE DOSE _ CALCULATION MANUAL LIST OF FIGURES Revision 24-page 1.1 CASEOUS EFFLUENT RELEASE POINTS 145 1.2 AUKILIARY AND SHIELD BUILDING VENTS (DETAIL)
-146 1.3 SQN LAND SITE BOUNDARY 147 1.4 CASEOUS RADWASTE TREATMENT SYSTEM 148 1.5 PLUME DEPLETION EFFECT FOR CROUND LEVEL RELEASES 149 1.6 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 150 1.7 RELATIVE DEPOSITION FOR CROUND LEVEL RELEASES 151 2.1 LIQUID EFFLUENT RELEASE POINTS 152 2.2 LIQUID RADWASTE SYSTEM 153 3.1 RADIOLOGICAL-ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN 1 MILE OF PLANT 154 3.2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS - WITHIN 1 TO 5 MILES OF PLANT 155 3.3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS -
GREATER TRAN 5 MILES OF PLANT 156 TOC-10 x
00101 9
I Ad % : #.n;jkipC % % ~ -
%, :< +:& G -
~@v MA 1
~$
V
l t
4 a
SON ODCM Revision 25 Page 1 of 156 i
1.0 GASEDUS_EfI wENTS 1.1 RELEASE _EQ1HIS.DESCRH110H There are six exhausts at Sequoyah Nuclear Plant that are monitored for airborno effluents.
These ares a Condenser Vacuum Exhaust for each unit, a Service Building Exhaust, an Auxiliary Building Exhaust and a Shield Building Exhaust for each unit.
Figure 1.1 provides an outline of the airborne effluent release and discharge points with associated radiation monitor identifications.
CDAdcD11tL_YAC3LRm._Ixhautt The Condenser Vacuum Exhausts (CVEs) are located in the turbine building. They exhaust at a maximum design flow rate of 45 cubic feet per minute.
They are monitored by radiation monitors (1)- and (2)-RM-90-99, -119.
Serxlsztatildino Vent various low-level sources exhaust to the Service Building Vent.
This R25 exhausts at approximately 14,950 cfm and is monitored by radiation monitor 0-RM-90-132.
Auxiliar.y_DuilIllRS lKhaust (see Figure 1.2 for detail) 5hkd The annulus vacuum priming system exhausts through the con'.ument vent to the Auxiliary Building. The Auxi.11ery Building er.ust mixes with the General Exhaust System and they cumulatively exhaust at a maximum design flow of 228,000 cim.
The exhaust is monitored by radiation monitor 0-RM-90-101.
Ehle1d B_uildino Vent (see Figure 1.2 for detail)
The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building and exhausts to the waste gas header.
There are nine Waste Gas Decay Tanks (WGDTs) that also empty into this header.
Either ABGTS or the Emergency Gas Treatment System (EGTS) is run to release a WGDT.
Each WGDT has a design capacity of 600 cubic feet and a design release rate of 22.5 cfm.
Both the Containment Purge and the Incore Instrument Room Purge from each unit tie into the waste gas header. The Containment Purge exhausts at a maximum of 28,000 cfm and is monitored by radiation monitors (1)- (2)-RM-90-130, -131.
If the Incore Instrument Room Purge is operating exclusively, it exhausts at 800 cfm.
Under emergency conditions, and sometimes during normal l
operation, the ECTS is used to draw a vacuum in the annulus and exhaust to the Shield Building Vent.
Auxiliary Building Isolation starts both the ABGTS and ECTS.
The common header exhausts to the 0144v
4 SON ODCM Revision 25 Page 2 of 156
)
Shield Building Exhaust.
There is or.e exhaust for each unit.
This exhausts at a maximum design flow of 28,000 cfm and is monitored by radiation monitors (1)- (2)-i<M-90-400.
R25 i
"W W 0144v L
{
SQN ODCM R3 vision 24 Page 3 of 156 1.2 DOSE RATE
)
1.2.1 PEOUIREMENTS The dose rate due to radioactive materials released in gaseous affluants to areas at or beyond the SITE DOUNDARY (UWRESTRICTED AREA)
R24 (see rigure 1.3) shall be limited to the followings a.
For noble gases:
Less than or equal to 500 mram/yr to the total body and less than or equal to 3000 mrom/yr to the skin, and b.
For Iodine-1J1, Iodine-133. Tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
Less than or equal to 1500 arsa/yr to any organ.
This requirament is applicable at all times.
This requirement is provided to ensure that the dose at any time at the SITE BOUNDARY from gaseous effluents from all units on the site R24 will be within the annual dose limits of 10 CFE Part 20.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Colunn 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous ef fluents will not result in the exposure of a MEMBER OF THE PUBLIC, R24 either within or outside the SITE BOUNDARY, to annual average R24 concentrations exceeding the limits specified in Appendix B. Table II of 10 CFR part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC R24
$$$$l who m1y at times be within the SITE BOUNDARY, the oacupancy of the R24 individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
R24 The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the SITE BOUNDARY to less than or equal to R24 500 mrem /yr to the total body or to less than or equal to 3000 mrem /yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose-rate above backstound to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /yr for the nearest cow to the plant.
This requirement applies to the release of gaseous effluents from all reactors at the site.
For units with shared radwaste treatment systems, the gaseous affluents from the shared svstems are proportioned among the units sharing that system.
If this requirement is not met, the following action will be performed:
With dose rate (s) exceeding the above limits, without delay restore the release rete to within the above limit (s).
- 1. c a-01441 Q
p
, t;-
7
+1 5
2
~,
SQN ODCM R3 vision 24 page 4 of 156 To ensure that this requirement is met
)
The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 1.2.3, and The dose rate due to 1-131, 1-133 Tritium, and for all radionuelides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 1.2.4 and by obtaining representative samples and performing analyses in accordance with the sampling and analysis progrka specified in Table 1.1.
1.2.2 REPORTING LIMITS i
10 CFR 50.73 requires that any airborne radioactivity release that exceeds 2 times the applicable concentrations of the limits specified in Appendix B. Table II of 10 CFR 20 in UFRESTRICTED AREAS when R24 averaged over a period of one hour be reported to the NRC within 30 days. For the purposes of meeting this requirement, it is assumed that the dose rate limits stated above are the result of offsite concentrations equal to those listed in Appendix B, Table II of 10 CFR 20, 1.2.3 NOBLE CAS DOSE RATES k
Dose rate 6 are calculated for total body and skin due to submersion within a cloud of noble gases using a semi-infinite cloud model.
1.2.3.1 Total Body Dose Rate The dose rate to the total body DRTB in mrem / year, is calculated i
using the following equation:
DRyg = (K/Q) F 1 Ci DFBi (1.1) i where K/Q relative concentration, s/m.
Relative air s
=
concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 siven in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site _ boundary locations is used.
5.12E-06 s/m' (from Table 1.3).
=
F
= flowrate of effluent stream, ce/s.
concentration of noble gas nuclide i,in_ effluent stream,
- Ci a
yCi/cc.
- ~ * ~
DFBi total body dose factor due to gamma radiation for noble gas
=
nuclide 1, mram/y per yci/m8 (Table 1.4).
i J
01441 O
53 if4)k J ~. #@tp&*M.
- e n -+.~
sw M
SQN ODCM Revision 24 Page 5 of 156 1.2.3.2 Skin Dose Rate The dose rate to the skin, DR, in mrem / year, is calculated using the following equation:
(X/Q) F 1 C (DFsi + 1.11 Dr i)
(1,2)
DR a
1 y
s i
where
+
X/Q
= relative concentration, s/m'.
Relative air concentrations are calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dnse rate calculations, the highest value f rom the sixteen Innd-site boundary locations is used.
= 5.12E-06 s/m' (from Table 1.3).
F
= flowrate of effluent stream, cc/s.
Ci
= concentration of noble gas nuclide i in effluent stream, uci/ce.
DTSi
= skin dose factor due to beta radiation for noble gas nuclide i, mram/y per pCi/m* (Table 1.4).
1.11
= the average ratio of tissue to air energy absorption coefficients, mrem / mrad.
DFyi
= dose conversion f actor for external ganum for noble gas nuclide i, mead / year per uCi/m' (Table 1.4).
W l
l l
=c Reformatting / Repagination changes only I
J 01441
[I h55h5
- bfdhkW$iAY&bO -
mz
.4 -
@~N2 %~ -"- $ C EN
SQN ODCM R3 vision 24 Page 6 of 156 1.2.4 1-131. 1-133. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORN WITH HALT-LIVES OF CREATER THAN 8 DAYS - ORGAN DOSE RATE organ dose rates due to I-131. I-133. Tritium and all radionuclides in particulate form with half-lives of greater than 8 days, DR In org arem/ year, are calculated for all age groups (adult, teen, child, and infant) and all organs (bone, liver, total body, thyroid, kidney, lung, and CI Tract) using the following equation:
DRors= Fl C (X/Q)(RIT+RCTP)+{C [(X/Q)Rgt+(D q)[gCPi+ Rat)))
(1.3) R24 i
/
T i
where:
F flovrate of effluent stream, cc/s.
=
CT concentration of tritium in effluent stream, pCi/cc.
=
1/Q relative concentration, s/m8 Relative air
=
concentrations are calculsted for the land-site boundary in each of the sixteen sectors as described in Section 1.9.2 using the historical meteorological data for the period 1972-1975 given in Table 1.2.
For dose rate calculations, the highest value from the sixteen land-site boundary locations is used.
5.12E-06 s/m8 (from Table 1.3).
=
RIT inha tion dose f actor f or tritium, mrem / year per
=
pCi/m8 Dose factor is calculated as described in 8
Section 1.8.13.
RCTP Grass-cow-milk dose factor for tritium, mrem / year per
=
pCi/m8 Dose factor is calculated as described in U
Section 1.8.7.
Ci concentration of r.uclide i in effluent stream, pCi/ce.
=
RIi inhalation dose factor for each identified nuclide i,
=
mram/ year per pC1/m8 Lose factors are calculated as described in Section 1.8.3 3.
D/Q relative deposition, 1/m8 Relative deposition is
=
calculated for the land-site boundary in each of the sixteen sectors as described in Section 1.9.3 using the historical meteorological data for the, period 1972-1975 given in Table 1.2.
For dose' rate calculations,'the highest value from the sixteen land-site boundary locations is used
= 1.29E-08 1/m3 (from Table 1.3).
R Crass-cow-milk dose factor for each identified nuclide 1, cpi a
m8-mrem / year per pCi/s. Does factors are calculated as described in Section 1.8.1.
RCi
- ground plane dose factor for each identified nuclide i, m8-mram/ year per pCi/s. Dose factors are calculated as described in Section 1.8.14.
The maximum organ dose rate is selected from among the dose rates calculated for all the organs and all age groups.
.% c
. a..
01441 a'
G.$ ;
O 55A
- A5 A}
?!"! ' e I Y
<,Y.
SQN ODCH Ravision 24 page 7 of 156 1.3 RADI0 ACTIVE CASE 003 EFFLUERT MONITORINC INSTRUMENTATION i
1.3.1 REOUIREMENT The radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.5 shall be OPERABLE with their alarm / trip setpoints R24 set to ensure that the limits of section 1.2 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in Section 1.3.3.
This requirement is applicable as shown in Table 1.5.
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alanm/ trip setpoints for these instruments shall be calculated in accordance with the procedures in Section 1.3.3 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instrumentation is R24 consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR part 50.
If this requirement is not met, the appropriate following action (s) will be performed:
With a radioactive gaseous affluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than required above, 19N$$
without delay rurpend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint so it is acceptably conservativa._
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the action shown R24 in Table 1.5~.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, axplain in R24 the next semi-Annual Effluent Report why the inoperability could not be corrected within 30 days '
To ensure that this requirement is met:
Each radioactive gaseous affluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the R24 CHANNEL CHECK. SOURCF. CHECK, CHANNEL CALIBRATION, and CHANNEL R24 FUNCTIONAL TEST operations at the frequencies shown in Table 1.6.
R24
,% c g.
j 01441
)
difi.h SE 3.,g:01,. ; %"p
?1 f t y..
3:,. w :
.gg,.S{
_J
SQN ODCN R3 vision 24 1.3..? REiEASE_SAMPLTNC 3
prior to each release (excludint, an Incore Instrument Room Purge),
a grab sample is taken and analyzed to determine the concentration.
pCi/ce, of each noble gas nuclide.
On at least a weekly basis, filters are analyzed to detemine the amount of iodines and particulates released. Composite samples are maintained (as required by Table 1.1) to determine the concentration of certain nuclides (Sr-89. Sr-90 and alpha emitters).
For those nuclides whose activities are determined from composite-samples the concentrations for the previous comoosite period will be assumed as the concentration for the next period to perform the calculations in Sections 1.2, 1.4, 1.5 and 1.6.
The actual measured concentrations will be used for the dose calculations described in Section 1.7.
N l
l l
l
. ~x.
-)
Reformatting / Repagination changes only 01441
)
i dk
_' s..
?.'} : ?, '.
~ ~.. ',. ~
si" e ss
" ?
gas ~<~ ~ n ;,;, 13.g.3.,
s 4,,
,,.9
,,. ;y ; -
,g
,.a..
4
SON ODCM Revision 25 page 9 of 156 i
1.3.3 1HEIRUMENT SETPOINIS Airborne effluent monitor setpoints are determined to ensure that the dose rate at the SITE BOUNDARY does not exceed the dose rate limits given in ODCM Section 1.2.1 and to identify any unexpected releases.
1.3.3.1 Relgnae Point Monitor Setpointm S _,2-RM-90-130,-1 R 0-EM-9A:11El
- 1. 3. 3.1.1 Contai nment Purge _EL(lygnt Monlinrs (1. 2-RM-90-130, -131)
These monitors are set at a epm value equal to a percentage of the Technical Specification Limit of 8.5x10-8 pCi/cc of Xe-133 (Technical Specification 3.3.2.1, Table 3.3-4).
1.3.3.1.2 Waste Ga5_P_cIAY._Iank Effluent Monitor __(0-RM-90-118)
For each release from a waste gas decay tank, two setpoints are calculated for the monitors one based on the expected response of the monitor to the radioactivity in the ef fluent streams and a calculated maximum setpoint which corresponds to the most restrictive dose rate limit given in ODCP Section 1.2.1.
The expected monitor response is calculated as described below in Equation 1.4.
The maximum calculated setpoint is calculated as described below in Equation 1.5.
A kOOE comparison is made between these two calculated setpoints to determine m.J which is used.
The actual monitor setpoirt for the release is set equal to X times the expected monitor response, or to the maximum calculated setpoint, whichever is less.
X la an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions).
The X times expected response setpoint allows for the identification of any release of l
radioactivity above the expected amount.
The maximum calculated l
setpoint ensures that the release will be stopped if it exceeds the 10 CPR 20 dose rate limits after dilution.
RKreeted Mo111tpdgsppj1gg R=
B+ I effi C1 (1.4) 1 where B
= monitor background, cpm.
effi
= efficiency factor for the monitor for nuclide i, cpm per pCi/cc.
Ci
= measured concentration of nuclide 1, pCi/cc.
]
Entire Page Changed 0144v
S9N ODCM Revlalon 25 Page 10 of 156 i
falcu1Aled.11aKitagm__Ee_traint The calculated maximum setpoint, S in cpm, corresponding to the ma:
dose rate limit is' determined using the following equation:
DR11m Smax * ( A SF
(
(R - B)))
,D (1.5)
DR where A
= dose rate allocation factor for the release point, dimensionless. The dose rate allocation factors for release points are defined in approved plant procedures.
SF
= safety factor for the monitor, dimensionless.
Safety factors for each monitor are defined in approved plant procedures.
i DR11m the dose rate limit, mrem / year.
a 500 mrem / year to the total body for noble gases,
=
3000 mrem / year to the skin for noble gases, and
=
= 1500 mrom/ year to the maximum organ for lodines and particulates.
DR
= the calculated dose rate for the release, mrem / year.
= DRTB for total body (as described in Section 1.2.3.I'
= DRs for skin (as described in Section 1.2.3.2), and
= DR for maximum organ (as described in or Sect $on1.2.4).
R
= expected monitor response (as calculated in
.4 Equation 1.4), cpm.
MCP9#
h
= the monitor background, cpm.
l l
1.3.3.2 Eingharge Point lignitor Setpoints (1.2-RM-93-4A(L i
0-RM-90-101. 0-RM-90-132. 0-RM-90-99.-119)
A normal default setpoint is determined for each discharge point monitor as described in Section 1.3.3.3.
These setpoints on the discharge monitors will routinely be set equal to the default setpoints.
When release permits are generated, the expected response and maximum calculated setpoints are calculated for the appropriate discharge monitor as described in Section 1.3.3.1 A comparison is made between the three setpoints as described below to choose the appropriate setpoint for the monitor during the release (after the release, the monitor should be returned to the default setpoint).
For almost all releases, the setpoint for the discharge monitor will be the default setpoint, l
l IP
- 1 times the expected monitor responseEis less than the J
l calculated maximum setpoint:
I a.
IF X1 times the expected monitor response is less than 1 X is an administrative factor designed to account for expected variations in monitor response.
It will be defined in-approved
)
plant instructions.
./
Entire Page Changed 0144v l, _ - _ _ _
o o
S9N ODCM Revision 25 Page 11 of 156 the normal default setpoint, AND the default setpoint is less than the maximum calculated setpoint, THEN the setpoint shall be set equal to the normal default
- setpoint, b.
OTHERWISE the setpoint shall be cet equal to XI times the expected rnonitor response.
1 X is an administrative factor designed to account for expected variations in monitor response.
It will be defined in approved I
plant instructions.
NOTE For the shield building exhaust anonitors (1,2-RM-90 400), the above calculations and comparisons are performed in epm, then the final resulting setpoint is converted to units of pC1/sec.
1.3.3.3 Discharoe Point Effluent Monitor Default Setp.cinta Shigld Buildino Vents (1. 2-RM-90-400), Auxiliary Fulldino Vent (0-RM-90-1011A and-Service Buildina Vent (0-RM-90-132)
These discharge point effluent monitors are set to ensure crmrAlanua with ODCM Section 1.2.1.
The default setpoints are defined as the maximum calculated setpoint described by Equation 1.5, calculated for
.,, s Xe-133.
The default setpoints for the shield building monitors are calculated in units of cpm, then converted to pCi/sec for use on the monitor.
Condenser Vacuum Exhnust Vent (0-RM-90-99 and -119)
This discharge point effluent monitor is set to ensure compliance with ODCM Section 1.2.1 and to identify the presence of primary to secondary leakage of radioactivity.
The default setpoint is-determined by calculating the maximum calculated setpoint described by Equation 1.5 for Xe-133, and then taking 10% of this value as.the setpoint.
Once a primary to secondary leak is identified, the setpoint on this monitor may be adjusted upward to enable it to be used to identify any further increases in the leak rate.
l Deleted by Revision 25 (1.6)
Deleted by Revision 25 (1.7)
)
Entire Page Changed 0144v
SQN ODCM R3 vision 24 Page 12 of 156 1.4 DOSE - NOBLE CASES 1.4.1 REOUIREMENTS The air dose due to noble gases released in gaseous effluente from each reactor unit to areas at or beyond the SITE BOUNDARY (see R24 Figure 1.3) shall be limited to the followingt a.
During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal tn 10 mrad for beta radiation and b.
During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
This requirement is applicable at all times.
This requirement is provided to implement the requirements of Sections II.B.III. A and IV. A of Appendix 1,10 CFR Part 50.
The requirement inglements the guides set forth in Section II.B of Appendix I.
The action to be taken provide the required operating flexibility and at the same time implements the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low a reasonably achievable." The surveillance implements the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by gygrgp calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately modeled R24 pathways is unlikely to be substantially underestimated. The dose calculations established in Section 1.4.2 for calculating the dosos due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50. Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases.from Light-Water Cooled Reactors," Revision 1, July 1977.
The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the R24 h.!stcrical average atmospheric conditions.
If Ric requirement is not met, the following action will be
. verforbeda Q1th the estmalated air dose from radioactive noble gases in gaseoJ@ offluenta axeeeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technien1 Specification 6.9.2, a Special Report which identifies the 01441
)
.,.]
9.
4 N-ovg
'M
.j ( % ( * '?. g
[
,4
_, j ;;_
m SQN CDCM R3 vision 24-Pcto 13 of 156 cause(s) for axcoading the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
To ensure that this requirement is mett l
cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in section 1.4.2 at least once per 31 days.
l l
1.4.2 CUMUtATIVE DOSE CI,tCUt.ATIONS - WOBtt CASES Doses to be calculated are-smsu and beta air doses due to exposure to an infinite cloud of noble gases. These doses will be calculated at the land-site boundary location with the highest annual-average K/Q based on 1972-1975 meteorological data (Table 1.2).
This location is chosen from the SITE BOUNDARY locations listed in R24 Table 1.3.
Dispersion factors are calculated using the methodology described in Section 1.9.2.
No credit is taken for radioactive decay.
1.4.2.1 Camma dose to air The ganma air dose, D in mrad, is calculated for each releaso i
y l
ggggg using the following equation:
Dy = 1.9E-06 (K/Q) I Qi DF71 T (1.8) i where:
1.9E-06 conversion factor, years per minute.
=
A/Q highest land-site boundary annual-average relative
=
concentration, 5.12x10** s/m3 (from' Table 1.3).
release rate for nuclide i, vCi/s.
Qi.
=
DFy1 dose conversion factor for external samma for nuclide 1
=
(Table 1.4), mead / year per pCi/m*.
duration of release, minutes.
t
=
The samma-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 1.4.2.3.
{
M a-01441
}
i
- The
- b. k j b ' M
}.l N.f.
^$u
_Qq
.s g;4 g,,,
7y
s e
SQN ODCM R3 vision 24 Page 14 of 156 1.4.2.2 Deta dose to air The beta air dose, D3 in mrad, is calculated for each relenJe using the following equation:
De = 1.9E-06 (X/Q) I Qi Drgi T (1.9) where:
1.9E-06 a conversion f setor, years per minute.
highest land-site boundary annual-average relative 1/Q
=
concentration, 5.12x10** s/m* (from Table 1.3).
release rate for nuclide 1, pCi/s.
Q1
=
dose conversion factor for external beta for nuclide i, Dr i e
=
mead /yese per pCi/m* (from Table 1.4).
duration of release, minutes.
T 4
The beta-air dose calculated by this method will be used in the cumulative dose calculations discussed in Section 1.4.2.3, 1.4.2.3 Cumulative Doce - Noble Cae Quarterly and annual sums of all doses are calculated for etch celease as described below to compare to the limits lirted in Sectier.1.a.1.
For noble gases, cumulative doses are calculated for garama r!d beta air doses.
Doses due to each release are summed with t.he doses for all previous release in the quarter or year to obt.ain eunulst.5v3 quarterly and annual doses.
1.4.2.4 comparison to Limits l
The cumulative calendar quarter and calendar year dosos are compared t
to their respective limits once per 31 days to determitva compliar.cc.
l l
S 1
l l
l
.~ a :
a-j Reformatting / Repagination changes only
_/
01441 2
'.w.+
~ abk 9K:e 2 m.i,yi: m:.ipf?
v.
SQN ODCH R0 Vision 24 p:go 15 of 156 1.5 CUMULATIVE DOSE - I-131. I-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM 1.5.1 REOUIREMENTS The dose to a MEMBER OF THE PUBLIC from I-131. I-133. Tritium and all R24 radionuclides in particulate form with half-lives greater than 8 days in gaseous affluents released to areas at or beyond the SITE DOUNDARY R24 (see Figure 1.3) shall be 1Laited to the '91:, 'ing from each reactor unit:
s.
During any calendar quarter Less than or equal to 7.5 mram to any organ and, b.
During any calendar year Less than or equal to 15 mram to any organ.
This requirement is applicable at all times.
This requirement is provided to implement the requirements of Sections II.C.III.A and IV.A of Appendix I, 10 CFR part 50.
The requirement implements the guides set forth in Section II.C of Appendix I.
The action to be taken provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable."
Section 1.5.2 calculational methods implement the requirements in gjy;Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through R24 appropriately modeled pathways is unlikely to be substantially underestimated.
Section 1.5.2 calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004 "A
l Statirtical Analysis of Selected parameters for Predicting Food Chain l
Transport-and Internal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, " Calculation of Annual Doses to Man from i
Routine Releases of Reactor Effluents for the Purposes of Evaluating l
Compliance with 10 CFR part 50, Appendix I," Revision 1, October 1977 l
and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of caseous Effluents in Routine. Releases from Light-Water Cooled Reactors," Revision 1 July 1977. These equations also provide for determining the actual doses based.upon the historical average atmospheric conditions. The release rate specifications for I-131, I-133 tritium and all radionuclides in particulate form with half-lives greater than 8 days are dependent on the existing radionuclide pathways to man, beyond the SITE BOUNDARY.
R24 The pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides,
.W 01441 h
t
+A[
h-or h
y,'
,a
'Y N
t kfh i {
l e
SQW ODCM R3 vision 24 page 16 of 156
- 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto' grassy areas where milk animals and meat producing animals grate with consumption of the alik and meat by man, and t.) deposition on the ground with subsequent exposure of man.
If this requirament is not met, perform the fol'owing setion:
With the calculated dose from the release 3; 4-121. I-133 tritium and all radionuclides in particulate form with 1 lf-lives exceeding B days, in gaseous affluents exceeding any of the above limits, prepara and submit to the Commission within 30 days, pursuant to Technical Specification.6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
To ensure that this requirement is met Cumulative dose contributions for the current calendar quarter and current calendar year for I-131, 1-133 tritium and all radionuclides in particulate form with half-lives exceeding a days shall be determined in accordance with the methodology and parameters in Section 1.5.2 at least once per 31 days.
..~.%
Wfi%V
/
I Lc a-Reformatting / Repagination changes only s
)
01441 a
f i
ha:
,l gl$
- A i.-+w b h! e* * *
$ $ $l. '%
% " ~' '
~ _ _.
e SQN ODCH R3 vision 24 page 17 of 156 1.5.2 DOSE DU(,70 1-111. 1-13 3. TRITIUM AND ALL RADIONUCLIDES IN PARTICULATE FORM.WITH HALF-LIVES OF CRFATER THAN 8 DAYS
\\
1.5.2.1 Orten dose calculation Organ doses due to I-131.1-133, tritium and all radionuclides in particulate form with half-lives of greater than 8 days are calculated for each release for the critical receptor. The critical receptor is defined as the land-site boundary in the sector with the highest annual average X/Q. The annual average K/Q and D/Q are calculated using the methodology in Sections 1.9.2 and 1.9.3 using the historical 1972-1975 meteorological data (Table 1.2).
Pathways considered to exist at this location a e inhalation, ground plane exposure, grass-cow-milk ingestion, grass-cow-beef ingestion and fresh leafy and stored vegetable ingestion. All age groups are considered (adult, teen, child and infant).
Dose factors for these age groups and pathways are calculated as described in Section 1.8.
For the ground exposure pathway, which has no age or organ specific dose f actors, the total body dose will be added to the internal organ doses for all age groups. Wo credit is taken for radioactive decay.
The general equation for the calculation of organ dose is:
Dors = 3.17E-08 7 [ [ Rpt [ Wp Qt ]
(1.10) ip where:
$$$@P 3.17E-08 = conversion factor, year /second T
= duration of release, seconds.
Rpg
= dose f actor for pathway P for each identified nuclide i, 8
2 -mrem / year per pCi/s for ground plane, grass-cow-milk, grass-cow-ment, and vegetation pathways, and arem/ year per pCi/m' for inhalation and tritium ingestion pathways.
Equations for calculating these dose factors are given in Section 1.8.
Wp
. dispersion factor for the location and pathway,
= K/Q for the inhalation ahd tritium ingestion l
- pathways, 8
5.12E-06 a/m.
.D/Q for the food and ground plane pathways,
= 1.20E-08 m-8 Qg r<, lease rate for radionuclide i, pci/s From the four att groups considered, the maximum is determined by comparing all otgan doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The organ doses for the critical age group will be used in the cumulative doses discussed in section 1.5.2.2.
L. c
=
8eformatting/ Repagination changes only
)
01441 N
w M
- a.
.wsA w
...w.
~w
SQW ODCK R3 vision 24 "I"
II' 1.$.2.2 Cumlative Doses Quarterly and annual sums of all doses are calculated for each release i
as described below to compare to the limits listed in section 1.5.1.
For maximam organ dose, cumulative quartarly and annual doses are j
j maintained for each of the elskt orger6 considered.
The cumulative dose is obtained by suming the doses for each organ of the critical age group (as calculated in section 1.5.2.1) as determined for each release with the organ doses for all previous releases in the quarter or year to obtain the cumulative quarterly and annu21 doses. Thus.
tne cumulative organ doses will b6 conservative values, consisting of i
doses belonging to various aga groups depending on the mix of radion9clides. The highest of these cumulative organ doses is ut,ed l
for the com,,srison to tha limit.s described in section 1.5.1.
1.5.2.3 EEterigen t o 1,itnits The cumulative calendar quarter and calendar year doses are compared to their respective limits once per 31 days to determine compliance, i
j l
l 1
,%.~
1 m-l Reforr.atting/ Repagination changes only l
.j 01441 3
p.g ya.ww:zg..
. 4. -. a. s. g 4,w.c.,,,,.g,+
e e
s0W ODCH R3 vision 24 page 19 of 156 1.6 CASE 0VS RADWACTE TREATMENT 1.6.1 FEOUIREMENTS The CASE 0VS RADWASTE TREAmENT SYSTEN and the VENT!LATIDW REMAUST R24 TREAMENT SYSTEN shall be used to reduce radioactive materials in R24
- sseous weste prior to their discharge when the projected gaseous effluent doses due to gaseous effluent releases to areas at or beyond The SITE DOUNDARY (see rigure 1.3), when averaged over 31 days, would R24 exceed 0.2 mead per unit for gamsu radiation, and 0.4 mrod per unit for beta radiation. The appropriate portions of the VENTILATION R24 EIRAVCT TREA m EWT SYSTEN shall be used to reduce radioactive meterials R24 in gaseous waste prior to their discharge when the projected dosso due to gaseous affluents to areas at or beyond the Wits 40VWDt h (See R24 ylgure 1.3) when averaged over 31 days would exceed 0.3 mrom per unit to any organ.
This requirement is applicable at all times.
This requirement that the appropriate portions of these systems be used, when specified, provides rehsonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This requirement implements the requirements of 10 CTR part 50.36a, General Design Criteria 60 of Appendix A to 10 CTR part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50.
The specifled limits governing the use
- g of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.D and II.C of Appendix I,10 CTR part 50, for gessous af fluents.
If this requirement is not mat, perfotin the following action With the gaseous waste being discharged without treabnet '; for more t.han 31 days and in excess of the above limits, prepare and submit to the commission within 30 days, pursuant to Technical Spot.ification 6.9.2, a special Report which includes the following l
intorinations 1.
Identification of the inoperable equipment or subsystems and the reason for inoperability.
2.
Action (s) taken to restore the inoperable Squ!pment to OpKRABLE status, and R24 3.
Summary description of action (s) taken to prevent a recurrence.
To ensure that this requirement is met?
Doses due to gaseous releases from the site shall be projected at parameters $nsection1.6.2.er 31 days, in accordance with the methodology and least once ca 1
)
01441
/
9 j;~
nM Y
$ k f Y 4.~
jh tf $,flhk.~
. f..f ;. g,e sgyg 3 g y[.,f hllg
e o
SQW ODCM Revision 24 1.6.2 DOSE pp0JrCT10Ng in accordance with Section 1.6.1. dose projections will be performed.
This will be done by maintaining running 31-day totals for the gamma dose the beta dose and the maximam organ dose. Once per 31 days.
these 3). day running tottic will be compared to the limits given in section 1.6.1 to determine cowpliance.
If the projected doses exceed any of these limits the CASEOUS R24 RADWASTE TREATMENT SYSTEM and the VERTILtTION EKHAUST TRF.ATHEWT SYSTEN R24 shall be used to reduce radioactive matoris.ts in gaseous effluents to areas ht or beyond the SITE BOUNDARY.
R24 1.6.3 9,MI,QJff FADWADTE TREATMENT SYSTDI DESCRIPTIOW The CASEOUS RADWASTE TREA1NENT SYSTEM (CRTS) described below b5411 be R24 meintained and operated to keep releases ALARA.
A flow diagram for the CRTS is given in Figure 1.4.
The system consists of two weste-gas compressor packages, nine gas decay tanks, and the associated piping, valves, and instrumentation. Caseous wastes are received from the followings degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown, displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header, and boron recycle process operation.
't
}
01441 4
1 Yl}MRha.i;;$fi:FaQ.
40lll-4q, e.;.yp3.x&
S SQW ODCH R3visten 24 page 21 of 156 1.7 fAfARTERLY Dost CALCULATIONS
(
A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as i
required in Section $.2.
Methodology for this analysis ja that which is described in this section using the quarterly release values reported by the plant personne).
All real pathways and receptor locations identified by the most recent land use survey are
{
considered. In addition, actual meteorological data representative of l
a ground level release for each corresponding calender quarter will be used. For todine re' eases, it is assumed that half the iodine i
released is in organic form. Organic todine causes a dose only by inhalation. For cow-milk and beef ingestion doses, the fraction of the time the animals are on stored feed (identified in the survey) is I
used in the calculation.
The highest organ dose for a real receptor is determined by suming the dose contribution frem all identified pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for 7
identified garden locations), cow and/or goat milk ingestiot, Mf a cow or g st is identified for the location), beef ingestion (the beef inteu ton dose for the location of highest beef dose for all receptors will to considered the but dose for all receptors).
1.7.1 FABLt CAS - CAMMA AIR DOSE Cama air doses due to exposure to noble gases, D in aren, are y
calculated using the following equationt thW4 Dy = Xin Dr g (1.11) y where Kim
concentration of nuclide i at location m, pC1/m8 Air concentrations are calculated as described by l
Equation 1.16.
Dr g
= dose conversion factor for external samma for nuclide 1 y
mrad / year per pC1/m* (Table 1.4).
1.7.2 N0Btt CAS - BETA AIR DOSE Beta air doses due to exposure to noble gases, D3 in arem, are calculated using the following equationt l
D '" Kim DF 1 (1.12) 8 8
where gg,
= concentration of nuclide i at location n, pC1/m'.
Air concentrations are calculated ac described by Equation 1.16.
DFgg
. dose conversion factor for external beta for nuclide 1, atad/ year per pCi/ms (Table 1.4).
f Refomatting/ Repagination changes only
..e k
"
- Q '; cj 1,
Y '*
- M 1
'h Q A5 h
qe
- Th*MN
- o e
e SQW ODCH R3 vision 24 j
page 22 of 156 1.7.3 JLA.01010DTWE. PARTICtfLATE ANQ TRIT!tfM - MAKINVH ORC &W DOSE Organ doses due to radiolodine, particulate and tritium releases.
D in arem are calculated using the f011owing equation:
org 1
Dorg
- 3.17E-08((X/Q)IRptQt11(D g){g p(D/Q)Rog+(A/Q)Rgg)Qt)
(1.13) R24 f
p i
p i
p 1
where 3.17E-08 e convergien factor, year /second.
l 1/Q Relative concentration for location under consideration,
=
s/m8 Relative concentrations are calculated as described by Equation 1.17.
I Rpy ingestion dose factor for pathway p for tritium,
=
as-mrom/ year per pCi/s.
Ingestion pathways available for consideration are the same as those listed 1
above for Hpg.
squations for calculating ingestion dose fenora for tritium are given in Sections 1.8.7 through i
1.6.12.
adjusted release rate for tritium for location under Qy
=
consideration, VC1/s.
Calculated in the same manner as Qt above.
ingestion dose factor for pathway p for each identified Rpg
=
nuclide 1 (except tritium), w8-mrem / year per pCi/s.
Ingestion pcthways available for consideration includes pasture grass-cow-milk ingestion stored feed-cow-milk ingestion hik....
I pasture grass-goat-milk ingestion stored feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion Equations for calculating these ingestion dose factors are given in Sections 1.8.1 through 1.8.6.
D/Q Relative deposition for location under consideration,
=
a-a.
Relative deposition'is calculated as described in Equation 1.18.
RGi Dose factor for standing on contaminated ground,
=
a8-mrom/ year per pCi/s. The equation for calculating the ground plano dose factor is given in Section 1.8.14.
Inhalation dose factor, arem/ year per WC1/m8 The Ryg
=
equation for calculating the inhalation dose factor is given in Section 1.8.13.
I e
e 01441 s
Y S
U
$ $ h iNE h h$h$h; N N Y = -
AWkNB&O-MIEwdS
o e
SQN ODCH Revision 24 page 23 of 156 Qg
= adjusted release rate for nuclide i for location under consideration, pCL/s.
The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector. Hence, the adjusted release rate is equal to the actual release rate decayed for en avertto travel time during the period.
9 Qin I fj ervi-Ki x/uj)
(1.14)
$=1 where Qto
= initial aversie releaso rate for nuc1'.Je i over the period, uci'0.
fj
= joint relative frequency of occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a f raction.
At
= radiological decay constant for nuclide i, s*l.
x
= downwind distsnce, meters.
uj
= midpoint value of wind speed class interval j, m/s.
1.7.4 POPtfLATION D0FtS For determining population doses to the 50-mile population around the g{gg$
plant, each compass sector is broken down into elements.
These elements are defined in Table 1.7.
For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element. Dispersion factors are calculated for the midpoint of each sector element (see Table 1.7).
For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.
The general equation used for calculating the population dose in a given sector element is pop = P{ RATIOp a popN
- 0.001
- DOSEp (1.15)
Dost where RATI0p
= ratio of average to maxh.2m dose for pathway p.
(Average ingestion rates are obtained from Regulatory culde 1.109, Table E-4.)
= 0.5 for submersion and ground exposure pathways, a shielding / occupancy tactor.
.~x
.c Reformatting / Repagination changes only 01441
/
Ws: k k A.;;ik p a g h v
+
b
...s.r.... ns+
meh
e SQN ODCH R3 vision 24 page 24 of 156
= 1.0 for the inhalation pathway.
= 0.515, 0.515, 0.5, and 0.355'for milk, for infant, child, toen and adult, respectively.
(It is assumed that the ratio of average to maximum infant allk ingestion rates is the same as that for child.)
= 1.0, 0.90, 0.91, 0.86 f or beef ingestion, for infant, child, teen and adult, respectively.
l
= 1.0, 0.38, 0.38, 0.37 for vegetable ingestion, for infant, I
child, teen and adult, respectively.
(It is assumed that the average individual eats no fresh leafy vegetables, only stored vegetables.)
t POPN
= the population of the sector element, persons (Table 1.8).
AGE
- fraction of the population belonging to each age group.
= 0.015, 0.168, 0.153, 0.665 for infant, child, teen and adult, respectively (f ractions taken from WREC/CR-1004, Table 3.39).
0.001
= conversion from arem to rem.
DOSEp
= the dose for pathway P to the maximum individual at the location under consideration, mrem.
For ingestion pathways, this dose is multiplied by an average decay correction to account for decay as the food is moved through the food distribution cycle. This average decay correction, ADC, is defined as follows:
For milk and vegetables, ADC = exp(-Kit) where Kg
= decay constant for nuclide i, seconds.
t
= distribution time for food product under consideration l
(values from Regulatory Guide 1.109 Table D-1).
= 1.21E+06 seconds (14 days) for vegetables, j
= 3.46E+05 seconds (4 days) for milk.
exp(-K t) k teb i
i For meat. ADC
=
1 - exp(-K tcb) i where Kg
= decay constant for nuclide 1, seconds, t
= additional distribution time for meat, over and above the time for slaughter to consumption described in Section 1.8.3, 7 days, ted
= time to consume a whole beef, as described in Section 1.B.3.
For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period curing which a whole beef is consumed, for the calculation of population dose. In other words, this assumes that the maximum individual freezes and eats l
a whole beef, while the average individual buys smaller portions at a j
time.
.~.:.
.r Reformatting / Repagination changes only OW1
)
g
,.;W ^ ;..%
&r.Anw+
ak
l 1
SQW ODCM -
Revision 24 i
page 25 of 156 I
population doses are sunused over all sector elements to obtain a total population dose for the 50-mile population.
I i
1.7.5 REPOETIWC or Dosts The calculated quarterly doses and calculated population doses described in this section are reported in the Semi-Annual Effluent Release Jeport submitted to the NRC for the period ending Decembet* 31 of each year.
I l
I I
I r
s-N I
t 1
1
,'e.:.
Refomatting/ Repagination changes only..
01441
-)
N
,L w3.e.#ws.1
. mm,a.a.m..
... og
_ _ _ _ _ _ _ _ _. _. _ ~
O g
SQW ODCH Revision 24 l
1.8 CASr0VS RELEASES - Dose rectors l
1.8.1 pASTUPE CRASS-COW /0047 'At!.K INGESTION DOSE FACTORS - R pl C
(m8-arem/ year per microcuries/second)
I ~"*PI~I lepII I vII**"p(*1 L )) )
l 1b E
R pi
- 10'DFLgeo,p agQgerp(-kgtg,)f {
C U r p
Ip Ag F Ag where 10'
= conversion factor, picoeurle/ microcurie.
DrLiao ingestion dose conversion factor for nuclide 1 a
age group a organ o mrom/picoeurie (Table 1.9).
V,p milk ingestion rate for age group a. Liters / year.
=
ri transfer factor for nuclide 1 from animal's feed to milk.
m
=
days / liter (Table 1.10).
Og enimal's consumption rate, kg/ day.
=
kg decay constant for nuclide 1. seconds-a (Table 1.10).
=
tm transport time from allking to receptor, seconds.
f f
=
p f rection of time animal opends on pasture, dimensionless, fraction of activity retained on pasture grass, r
a dimensionless.
kg
= the effective decay constant, due to radioactive decay and weathering, seconds-a equal to kg + Kw.
k
= weathering decay constant for leaf and plant surfaces, w
seconds *8 t,p
= time pasture is exposed to deposition, seconds.
(
Y
= agricultural productivity by unit area of pasture grass, p
kg/m8 By
= transfer factor for nuclide i from soll to vegetation, i
picoeuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil),
tb
= time period over which accunulation on the ground is evaluated, seconds.
p
= effective surface density of soll, kg/n.
8 NOTE: Factors defined above which do not reference a table,for their numerical values are given in Table 1.11.
- x Reformatting / Repagination changes only 01441 u..?
l e.?
~ -, (
hg
/.
> a c4 -es
6
' f.I. ' te s so sa q e a
-*5 ga jq ~
l
e SQW ODCM Revision 24 page 27 of 156 1.8.2 STORED FEED-COW / GOAT-MILK INOESTION Dost FACTOPS
- RCSi (m8-arem/ year per microcuries/second)
(1-exp(-k ti esfU RcSi = 106 DrL e, U,p Fal Of fs exp(-A tgn) i t
( r(1-exp(-k test E
U 8 vil***PI*k t ))
1 ib
+
1 Tsf IE p kg where:
108
= conversion factor, picoeurie/ microcurie.
OTLg.,
= ingestion dose conversion isetor for nuclide i, age group s, organ o, mrom/picoeurie (Table 1.9).
U,p
= milk ingestion rate for age group a, liters / year, ri
= transfer factor for nuclide i from animal's feed to milk, m
days / liter (Table 1.10).
Og
= animal's consumption rate, kg/ day.
f,
= fraction of time animal spends on stored feed, dimensionless.
kg
= decay constant for nuclide 1 seconds *8 (Table 1.10).
tfm
= transport time from milking to receptor, seconds, t,g
= time between harvest of stored feed and consumption by e
animal, seconds,
= fraction of activity retained on pasture grass, r
dimensionless, kg
= the effective decay constant, due to radioactive decay and
-"N weethering, seconds-8, equal to Ag + A.
i w
kw
= weathering decay constant for leaf and plant surfaces, seconds-4 tesf
= time stored feed is exposed to deposition, seconds.
Ygg
= agricultural productivity by unit area of stored, feed, kg/m8 Bgy
= transfer f actor for nuclide i from soil to vegetation, picocuries/kg (wet weight of vegetation) per picoeuries/kg (dry soil).
tb o time period over which, accumulation on'the ground is evaluated, seconds.
p
= effective surface density of soil, kg/m*.
POTE: Factors d1 fined above which do not reference a table for their numerical values are given in Table l.11.
. Reformatting / Repagination changes only If 01441 l
d
..J 542 t s,lbh
,9 QS-h
?*I$!N "V *^
" 4 N l
l e
SQW ODCM Revision 24 page 28 of 156 1.8.3 pASTtfRE CRASS-BJ,U_1WCESTION DOSE FACTORS - Rgpg (m8-area / year per microcuries/second)
(1-exp(-k teb))
i IMPi = 10' DTL ao Dam Ifi 9f
- Kp(*l ts) i i
qg f ( r(1-exp(-kgtep))
sty (1-exp( kit ))
d
+
)
p I AE F Ai p
where 108 conversion f actor, picoeurie/ microcurie.
e DFL ao
- ingestion dose conversion factor for nuclide 1 i
age group a, organ o, mram/picoeurie (Table 1.9).
U,,
= most ingestion rate for ese group a kg/ year, rti
= transfer factor for nuclide i from cow's feed to meat.
days /kg (Table 1.10).
Of cow's consuropticn rate, kg/ day.
=
kg
= decay constant for nuclide i, seconds-a (Table 1.10).
teb time for receptor to consume a whole beef, seconds.
=
r tg transport time from slaughter to consumer, seconds,
=
f p fraction of time cow spends on pastura, dimensionless.
=
fraction of activity retained on pasture grass, t
=
dimensionless.
KE the effective decay constante due to r&Qicactive decay and
=
weathering, seconds-8 equal to 14+K.
w L,
weathering decay constant for leaf and plant surfaces,
=
seconds-8 time pasture is exposed to deposition, seconds.
N t,p
=
Y
=
p agricultural productivity by unit area of pasture grass.
kg/m8 By transfer factor for nuclide i from soil to vegetation, i
=
picoeuries/kg (wat weight of vegetation) per picoeuries/kg (dry soil).
time over which accumulation on the ground is evaluated, tb
=
seconds.
p
= effective surface density of soil, kg/m8 Factors defined above which d' not reference a table for their NOTE:
o numerical values are given in Table 1.11.
l Reformatting / Repagination changes only C
OW f
-. -.u. n : w w -+:s+ d.
gngw n.t.:.sen
o SQW ODCH Revision 24 page 29 of 156 1.8.4 STOPED FEED-PEff YWGESTION DOSE FACTORS - Rggi (a -arem/ year per microcuries/second) s (1-exP(-k teb))
i 8 s1 = 10' DrL., U., rft Qf erp* kgt.)
M t
,, gg f' I ~'"PI'l ic8f))
T(1**"P("I tesf))
- biv(1***P(*k t ))I l
t ib Ai test Tsf Ag r Ag
- ~
where:
10'
= conversion f actor, ricoeurle/ microcurie.
DFLg,o
= ingestion dose conversion factor for nuclide 1 age group a, organ o, mrom/picoeurie (Table 1.9).
U a meat ingestion rate for age group a, kg/ year.
se Pgi
= transf er f actor for nuclide i from cow's feed to meet, days /kg (Table 1.10).
Qf a cow's consumft. ion rate, kg/ day.
~
11
= decay constant for nuclide 1, seconds-a (Table 1.10).
tcd
= time for receptor to consume a whole beef, seconds.
ts transport time from slaughter to consumer, seconds, a
f, fraction of time cow spends on stored feed, dimensionless,
=
tear
= time between harvest of stored feed and consumption by cow, seconds, r
= fraction of activity retained on pasture grass, dimensionless, t,,(
= time stored feed is orposed to deposition, seconds.
M Yst
= agricultural productivity by unit area of stored feed.
y kg/m*.
i g
= the ef f ective decay constant, due to radioactive decay and weathering, seconds *8, equal to kg + kw.
K
= weathering decay constant for leaf and plant surfaces, w
seconds-8 Biy
= transfer f actor for nuclide i from soil to vegetation.
picoeuries/kg (wet weight nf vegetation) per picoeuries/kg (dry soil).
tb e time over which accumulation on the ground is evaluated, seconds.
P
= effective surface density of soil, kg/m,
s NOTE: rectors defined above which to not reference a table for their numerical values are given in Table 1.11.
1 Reformatting / Repagination changes only 01441 d
D
'tN
- % I h 2_4*I Ly '
y.
4
. f _.
?e f.
i,'
8
o SQW ODCH Revision 24 page 30 of 156 1.8.5 [EFSH LF.AFY VEGtTABJQCJ$lig,Jpf t FAMPJ - Ryrg (m8-mrem / year per microcuries/second)
Ryy1 a 108 DFLiao *(*k t e) UTLef I (1-e(*kgt,))
Biy(1-e(-k t ))l r
ib ih L
+
yg wg r At where 10' conversion factor, picoeurie/mierocurie.
DrLg,
ingestion dose conversion f actor for nue11de i, age group a, organ o, mrom/picoeurie (Table 1.9).
Kg decay constant for nuclide 1, seconds *8 (Table 1.10).
=
sverage time between harvest of vegetables and their te h
=
consumption and/or storage, seconds.
UrLa consumption rate of fresh leafy vegetables by the receptor
=
in age group a, kg/ year.
ft fraction of fresh leafy vegetables grown locally, a
dimensionless, fraction of deposited activity retained on vegetables.
I r
a dimensionless.
ig the effective decay constant, due to radioactive decay and
=
weathering, seconds-a, a11+tw k
a w
decay constant for removal of activity on leaf and plant surfaces by weathering, seconds-a, t,
orposure time in garden for f resh leafy and/or stored
=
vegetables, seconds.
lpp$$
Yg agricultural yield for fresh leafy vegetables, kg/m8 Bv transfer factor for nuclide i from soil to vegetables, i
=
picoeuries/kg (wet weight of vegetation) per picocuries/kg (dry soil),
time period over which accumulation on the ground is tb o
evaluated, seconds, p
effective surface density of soil, kg/m8
=
NOTE: rectors defined above which do not referance a table for their numerical values are given in' Table 1.11.
l i
Reformatting / Repagination changes only-
"' E 01441
~
?
/
4 e
. h',
,T
$+
5 e
a
' *k! 4.
- 4 M
h~
--4 dk.
a.* i"
'".#*dh [,l h /
k.
e SQW ODCM Revision 24 page 31 of 156 1.B.6 E1MQ_Ugf1RLf_.]WRJILOW t@UAgInM - Rggi m8+arem/ year per microcuries/second)
(1-o(~k t v))
i s kyst = 10' DrLg, exp(-Agt e) Usaft y t,y h
(r(1-e(-A te)) + D v(1-o(-k t )))
t i
ib Yav KE Pki where:
10'
= conversion f actor, picoeurie/ microcurie.
- DrLie,
= ingestion dose conversion f actor f or nuclide 1, age group a, organ o, arem/picoeurie (Table 1.9).
Ki decay constant for nuclide 1, seconds-8 (Table 1.10).
e average time between harvest of vegetables and their the consurrption and/or storage, seconds.
Ug,,
consuntption rate of stored vegetables by the receptor in a
age group a, kr,/ year.
fraction of stored vegetables grown locally, dimensionless.
f
=
g gy time between storage of vegetables and their consumption, t
a
- seconds, fraction of deposited activity retained on vegetables, r
=
dimensionless.
KE
" the effective decay constant, due to radioactive decay and weathering, seconds-2 kg + L,
=
@lIh decay constant for remnval of activity en leaf and plant
=
surf aces by weathering, seconds-a.
t, esposure time in garden for fresh lesfy and/or stored
=
vegetables, seconds, s
Y,y agricultural yleid for stored vegetables, kg/m8
=
By transfer factor for nuclide i from soil to vegetables, i
=
picoeuries/kg (wet weight of vegetation) per picocuries/kg (dry soil),
time period over which accunulation on the ground is tb
=
l evaluated, seconds.
I p
effective surface density of soil, kg/m'.
=
WOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
Refornatting/ Repagination changes only 01441 Y
il
.~.s;n ;;;:@g;mu
,.. a w._..,.,..,
. A
e i
SQW ODCM l
Revision 24 Page 32 of 166 i
1.B.7 TFITilfM-PASTURE _ CRASS-COW /C0AT-MILK t>0st FACTOR - RCTp
)
(area / year per microcuries/n )
e Reyp.108 10* Drby., r y gg U,p [0.75(0.5/H)) fp exp(-1 t m) i e
7i wheret 10' conversion factor, grams /kg.
=
106 conversjen f actor, picoeuries/sicrocuries.
e Drt
= ingestion dose conversion factor for tritius for age group a, organ o, mren/picoeurie (Table 1.9).
Fat
= transfer factor for tritium from animal's feed to allk, days / liter (Table 1.10).
Qt
= animal's consumption rate, kg/ day.
U$5
= milk ingestion rate for age group a, liters / year.
0.
= the fraction of total feed that is water.
0.5
= the ratio of the specific activity of the food grass water to the atmospheric water.
H
= absolute humidity of the atmosphere, s/m'..
f
. fraction of time animal spends on pasture, dimensionless.
p 17
. decay constant for tritium, seconds *8 (Table 1 10).
tm
- transport time from milking to receptor, seconds.
f NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
I h0NhN l
Reformatting / Repagination changes only I~a a s-01441
)
I gg.s;sa.gggg=
~ swn
?
?
r
,-,.--. =..-- -- - - ------ - -
g n = w y
SQW ODCH Revision 24 page 33 of 156 1.8.8 TPITitfM-STORFD FtrD-COW /,91AT-MILY Dost FACTOR - RCTS (arem/ year per nicrocuries/me)
(1-exp(~k test))
y RCTS
- 108 10' DFL., rgy Qt U,p 10.7$(0.5/11)) is t
p(*k t n)
Ti AT Lest where los e conversion factor, grams /kg.
106
. conversion f actor, picoeuries/microcuries.
DFigao ingestion dose conversion factor for tritium for
=
age group a. organ o, aren/picoeurie (Table 1.9).
Tmf transfer factor for tritium from animal's feed to milk.
days / liter (Table 1.10).
Qg
. animal's consumption rate, kg/ day.
U$5
. milk ingestion rate for age group a, liters / year.
0.
= the fraction of total feed that is water.
0.5
= the ratio of the specific activity of the feed grass water to the atmospheric water.
H e absolute humidity of the atmosphere, s/m.
s f.
fraction of time animal spends-on stored feed, e
dimensionless, 17
= decay constant for tritium, seconds-a (Table 1.10).
tegg
= time betwoon harvest of stored feed and consumption by animal, seconds, ifm
- transport time from nilking to receptor, seconds.
M WOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
Reformatting /Hepagination changes only
".M 01441
)
J l
4-
- . i.
%.wmica -
- m a. n e % # #
o SQW ODCM Revision 24 page 34 of 1$6 1.8.9 IffT!UM-PASTURE GRMjL-AECT DOSE FACTOR - Egy (mrem / year per microcuries/m')
RMTp
- 108 10' DFL ao If7 Of Una 10.75(0.$/H)) fp exp(-tyte)
T (1-exp(-k iT er))
(I**"P(*1 icb))
T where T I hT ted ep 10' conversion f actor, grams /kg.
=
10' conversion f actor, picoeuries/picrocuries.
Drbran Ingestion dose conversion factor for H-3 for age group a, organ o, mrom/picoeurie (Table 1.9).
Fgy transfer f actor for H-3 from cow's feed to meat, days /kg a
(Table 1.10).
Qg cow's consumption rate, kg/ day.
a Um meat ingestion rate for age group a, kg/ year.
a 0.75 e the fraction of total feed th6L is water.
0.5 the ratio of the specific activity of the feed grass water
=
to the atmospheric water.
H absolute humidity of the atmosphere, g/m'.
=
fp fraction of tLae cow spends on pasture, dinensionless.
ty decay constant for tritium, seconds-8 (Table 1.10).
a ts
- transport tine frDa slauShter to consumer, seconds.
t
= time pasture is exposed to deposition, seconde.
op teb
- time for receptor to consume a whole beef, seconds.
NOTE: <<rtors defined above which do not reference a table for their svaerical values are given in Table 1.11.
1 l
+
Reformatting / Repagination changes only
..* c 01441 a-
./
- c v,
- 4
?
(
4 r
s
e SON ODCM Revision 25 Page 3b of 156 1.8.10 IRIIJ1&i:fLIDRED_ REED-131;%LDOSLTACT.08 - kg7s (mrem / year per microcurles/m8)
Rg7s = los 10' DrLTao If7 Of Unm (0.75(0.5/11)) f, exp(-% t,)
7 (1-exp(-A tep))
(1-exp(-K lT eb))
T t st AT tcb R26 where T
e 108 conversion factor, grams /kg.
=
10' conversion factor, picoeurles/microcurles.
e DrLTao Ingestion dose conversion f actor for 11-3 for age group a, organ o, mrom/picocurle (Table 1.9).
rgy transfer factor for 11-3 from cow's feed to meat, days /kg a
(Table 1.10).
Of a cow's consumption rate, kg/ day.
U meat ingestion rate for age group a, kg/ year.
am a
0.75
= the fraction of total feed that is water.
0.L the ratlo of the speeltic activity of the feed grass water
=
to the almospheric water.
11
= absolute humidity of the atmosphere, g/m,
s i
fraction of time cow spends on stored feed, dimensionless.
s A
decay constant for tritium, seconds *1 (Table 1.10).
T ts
- transport time from slaughter to consumer, seconds.
tear e time to consume stored feed, seconds.
R2L tch
= time for receptor to consumo a whole beef, seconds.
NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 1.11.
0144v
/
~ _... _ _
SQW ODCH kovision 24 page 36 of 156 1.8.11 ItunH-rPrSILLMry vrcriptrs pov rAerpt - Hvir (mrem / year per microcuries/me) t kyyy = 108 10' Drby., lo.15(0.$/H)) Urt (g, exp(-kythe) where 10' conversion factor grams /kf,.
=
10' conversion factore pleocuries/microcuries.
=
I Dity.o ingestion dose conversion f actor for tritlute for
=
ese group a. organ o. sures/picoeurie (Table 1.9).
0.75 the fraction of total vegetation that is water.
=
0.5 the ratio of the epocific activity of the vegetables water
=
to the atmospheric water.
H absolute humidity of the atmosphere, g/n'.
=
Ur!.s consumption rate of fresh leafy vegetables by the receptor in af.e f.roup a. kg/ year.
f, fraction of fresh leafy vegetables grown locally.
t a
dimensionless.
ky
= decay constant for tritium, seconds-a (fable 1.10).
te
- time between harvest of vegetables and their consumption h
and/or storego. seconds.
W0tt's rectors defined above which do not reference a table for their numerical values are given in Table 1.11.
1 Wk I
.~ e :
R* formatting /kepagination changes only 01441
> Q.%u K 4 l ki b t;r."?yidn-
. svJ~hi.n5% nv+% k,Si>l
~.
e 80W ODen Revision 24 page 37 of 156
)
1.8.12 TPIT!UM-CT0krD VECUTAPt.t3 DOSF FACTOR - Ryrg (aram/ year per microcuries/n8)
(1-exp(-k t v))
ta Rygg = 108 10' DFL., 10.7$(0.$/H)) Usafg wy t,y t
'"P(*k t e)
Th where:
10' conversion factor, grams /kg.
=
- 10' conversion f actor, picoeuries/microcuries.
e DTL.,
e ingestion dose conversion f actor for tritium for t
age group a, organ o, mrom/picoeurie (Table 1.9).
0.75
= the fraction of total vegetation that is water.
0.5 e the retto of the specific activity of the vegetation water to the atmospheric water.
H
= absolute humidity of the atmosphere, g/m'.
U consumption rate of stored vegetables by the receptor in sa e
age group a. $ 1'yaar.
f fracti n of 6 ired vtgetables grown locally, dimensionless, a
g ky decay constan f r~ - tritium, seconds-1 (Table 1.10).
e tsy time between rr b *t of stored vegetables and their a
consunt, an anos t e,torage, seconds.
the
- tiae Netween harvest of vegetables and their storage, seco< A.
NOTE: Fac'.t 1 defined above which do not reference a table for their num6r>eal values are given in Table 1.11.
M Reformatting /RepaginaLion chsnges only 01441
)
J
. ye
]
$ M id Y
.5 &;Ct 3 0H $ a G d=
m~ ? -+4 W N.4 % ' M 5 N S
i t
sQW ODCN Revision 24 page 38 of 156 1.8.13 ImtA1.ATION DOSE FACTORS-Ryg l
l (arem/ year per microcuries/n')
e Nq - cRt o BR6 10' 4
I v.mses D.44
< 4M44ation dose conversion f actor for nuclide 1
% 4 grrty a and orgon o, area /pleocurie (Table 1.12).
BRg
. breathk.it rate for age group a. 2 / year (Table 1.11).
8 20*
= conversion factor, picocurie / microcurie.
[
1.8.14 GROWD PLAWE D05i FACTORS - Rag (2 -mrem / year per microcuries/second) 8 Rag. Drago 1/kg 20' 8760 11 - exp(-Agt ))
b i
i where DFCio
- dose conversion factor for standing on contaminated ground t
for nuclide i and organ o (total body and skin), mrem /hr per picoeurio/a8 (Table 1.13).
kg
. decay constant of nt:11de 1. seconds *8 (Table 1.10).
10'
. conversion factor, picoeurie/ microcurie.
8760
. conversion-factor, hours / year.
tb
- time period over which the ground occunnalation is evaluated, seconda (Table 1.11).
Y8NW i
i l
iF Reformatting / Repagination changes only
~4 01441 4
6 g
y4
,,y 4
I
' *4 i.
p*
hNit.' $$' h r
f h"hWr'l,
- -Q ~ j,..
G-
- yf
{,*h'_{ghlll{$&.tIyy,;&
2
1 S W ODCH Revision 24 i
page 39 of 156 1.9 DIdPER510N MOTH 0tcl.0GY Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data consisting of vind speed and direction measurenents at 10m and temperature measurements at 9m and 46m.
A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considers plume depletion (using information from ylgure 1.5), and building wake effects.
Terrain effects on dispersion are not considered.
t Hourly everage meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction. and atmospheric-stability. The joint-frequency distribution which represents the historical meteorological data for the period January 1972 to e
December 197$ is given in Table 1.2.
The wind speed classes that are used are as follows:
Number Rant.e (m/s)
Midreint (m/s) 1
<0.3 0.13 2
0.3-0.6 0.4$
3 0.7-1.5 1.10 4
4 1.6-2.4 1.99 2.5-3.3 2.88 6
3.4-5.5 4.45 j
g 7
$.6-8.2 6.91 8
8.3-10.9 9.39 9
>10.9 10.95 The stability classes that will be used are the standard A through C classifications. The stability classes 1-7 will correspond to i
A=1 Bek..... Ge7.
l 1.9.1 AIR C0 Wen'TRATION - 1 ( uci/n',)
Air concentrations of nuclides at downwind locations are calculated using the following equation 9
7 l
A g s. I I (2/v)t/s fjk Qi P orp(.kt x/uj)
(1.16) j=l kal Igg uj (2rx/n) where fjk
- joint relative frequency of occurrence of winds in windspeed class j. stability class k. blowing toward this exposure point, orpressed as a fraction.
1
.~ s a Rafotratting/Repasination changes only oggg
)
A2 8
a f
j e
SQW ODCH Revision 24 page 40 of 156 3
Qg
. sverage annual release rate of radionue11de 1, pci/s.
p
. fraction of radionuclide remaining in plume (riture 1.$).
1,g
. vertical dispersion coefficient for stability class k which includes a building wake adjustaient,
.(ejk+cA/v)s/s, or
/3 o k, whichever is emailer.
s where egg is the vertical dispersion coefficient for stability class k (m) (ylgure 1,6),
e is a building shape factor (c 0.5).
A is the mininum building cross-sectional area (1800 m8).
uj
. midpoint value of wind speed class intervat j, m/s.
x e downwind distance, n.
j n
. number of sectors, 16.
i At
. radioactive decay coefficient of-radionuclide 1 s**
2rx/n
= sector width at point of interest, n.
1.9.2 RELATIVE CONCENTRAff0N - 1/0 (sec/m )-_
s Relative concentrations of nuclides at downwind locations are calculated using the following equation 9
7
. Il k.1I (2/v)a/s D
t/0 (1,17) i j
tak uj (25x/n) where fjk
- joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction, Izk
- vertical dispersion coefficient for stability-class k which includes.a building wake adjustment,-
. (ejk + cA/,)a/s, or. (3 e k, whichever is smaller.
s where ok is the vertical dispe,rsion coefficient for stability c
class k (m) (Figure 1.6),
c is a building shape factor (c.0.5).
A is the minimum building cross-sectional area (1800 m8),
uj
. midpoint value of wind speed elsse interval j, m/s, x
. downwind distance, m.-
n
. number of sectors, 16.
sector width at point of interest, m, 2rx/n a
i l
Reformatting / Repagination changes only i
l 01441 i
4 r
a 4
$M%1W&$A391NM4:
+
&$Ek;M%e Awd4
__._... _. _, _ _ _ _. _ _ _ ~ _ _..
._=. _ -
i 4
e o
a
.i SQW ODOM I
Revision 24 1.9.3 Rf*t,ATIVE DTP05f710N-D/0 (m-8)
Relative deposition of nuclides at downwind locations is calculated using the following equations i
9 7
fjk DR D/0 *j 1 k 1 O.18)
(2rx/n) where I
i (k
a joint relative frequency of occurrence of winds in windspeed class j and stability class k. blowing toward this exposure pointe expressed as a fraction.
DR
= relative deposition rate. 2-1 (from Figure 1.7).
x
. downwind distance, m.
n
. nunper of sectors. 16, 2rx/n
= sector width at point of interest, m.
9 M
l 1
i F
h
- . s :.
Reformatting / Repagination changes only 01441
}
j
}.
u aii MMRQiyN4lrMWgr$t@:n +.,
+;gg,g;;jhf@gjn:g;c..,.,sgy$
,.j..m
o SQN ODCH Revision 24 Page 42 of 156 2.0 L10VID EFFLUFNTS 2.1 PELEACE P01EIE There are four systems f rom which liquid ef fluents are released to the environment. These are the Liquid Radweste System, the Condensate Demineraliter System, the Turbine Building Sump, and the Units 1 and 2 Steam Cenerator Blowdown, rigure 2.1 provides an outline of the liqui' selease paths and discharge points with associated flow rates and r.tdistion monitors.
All liquid effluents are ultimately discharged to the Diffuser Pond which releases to the Tennessee River. The Essential Raw Cooling Water (gRCW) provides dilution for 11guld affluents at a mf nissum flow rate of 15,000 gpm. ERCW flow is monitored by radiation smonitort 0-RM-133. -134. -140. -141.
The inlet of the Diffuser Pond is monitored by radiation nonitor 0-RM-90-211.
Lieuld Padwaste System The Liquid Radwaste System processes liquid from the Reactor Buildint and Auxiliary Building Floor Drains and the laundry / hot shower and chemical drain tanks. Figure 2.2 provides a schematic of the 1,1 quid Redwaste System, showing the liquid pathways, flow rate and radiation monitors. The normal release points for liquid radtaste are the Monitor Tank and the cask Decontamination Collector Tank (CDCT). The Monitor Tank has a capacity of 22,000 gal and is released routinely at m -
a flow rate of 125 spm. The CDCT has a capacity of 15,000 gal and is also released routinely at a flow rate of 125 spm. The Monitor Tenk and CDCT dischat ge to the Cooling Tower Blowdown (CTBD) line as a batch release and are monitored by radia. tion monitor 0-RM-90-122.
Condensate Demineraliter Systen The Condensate Domineralizer System processes liquid wastes coming -
from the High Crud Tanks (HCT-1 and -2), the Woutraliastion Tank, and the Non Reclaimable Weste Tank (WhWT). The HCTs have a capacity of 20,000 gal and a maximum discharge ' flow rate of 245 spm. The Neutralization tank has a capacity of 19.000 gal and a maxinum discharge flow rate of 245 gym. The NRVT has a capacity of 11,000 gal and a maximum discharge flow rate of 245 gra. The Condensate Domineralizer System is routinely released to the CTbD line and is monitored by radiation monitor 0-RM-90-225.
Turbine. build inst Sump The Turbine Building Suntp (TBS) normally rsleases to the 1,ow Volume Weste Treatment Pond (LWTP) but can be released to the Yard Pond.
7.* p Reformatting /Repa$1 nation changes only j
n.p..:;.yAQ%w4:~
w& :4j.m+./
amn
+
v
7 t
g SQW ODCH Revision 24 page 43 of 156 The TBS has a capacity of 30,000 gal atid a design discharge release rate of 1.150 gpm per pump. TBS releases are monitored by radiation monitor 0-RM-90-212.
litam Ge.nrretor B1owdown The stean Generator Blowdom (SGBD) is processed in the Steam Generator Draindown riash Tanks or SGBD Heat Exchangers. The SGBD discharge has a maximum flow rate of 80 gra per steam generator. SCDD dischart,os to the CTBD line are continuous and are monitored by radiation monitors (1) (2)-RM-90-120. -121.
l
$lMih 1
I l
l
.b c Reformatting /Repaginata.on c.hanges only 01441 I
s Qj o
h~e d'
4e4 g'+-- ' E i ;9d is' r.VL g
/ ?(Ml*,p *,
- A
- 7e, h (U
- g
O SQN ODCM Revision 24 page 44 of 156 2.2 ffECITTPATION 2.2.1 naunTm l
The concentration of radioactive material released to WRESTRICTED R24 i
AREAS (see Figure 1.3) shall be limited to the concentretions R24 I
epecified in 10 CrA part 20 Appendix 3. Tablo II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gasek, the concentration shall be limited to 2110-* nigrocuries/mi total activity.
4 This requirement is applicable at all times.
This requirement is provided to onoure that the concentration of radioactive materials released in 11guld waste effluents to WREStr,2CTED ARFAS will be less than the concentration levelt R24 specifled in 10 CFR part 20. Appendix 3, Table !!. Column 2.
This limitation provides adJitional assurance that the levels of radioactive materiale in bodies of Water in WRESTRICTED AREAS will R24 result in exposures withio (1) the Section !!.A design objectives of Appendix I,10 CTM $0, to a MLMBER OF THE pF8L.1C and (2) the limits of R24 10 CTR 20.106(e) to the population. The concentration ilmit for dissolved or entrained noble gases is based upon the assumption that Re 135 is the controlling radioisotope and its Mpc in air (submersien) was converted to an equivalent concentration.n water using the methods described in International Commission of Radiological protection (ICRP) Publication 2.
j g
If this requirement is net met, the following action will bo i
performed i-With the concentration of radioactive material released to WRESTRICTED AREAS exceeding the above limits, without delay.
R24 restore the concentration to within the above limits.
To oneure that this requirener.t is met:
Radioactive liquid westes shall be esmpled and analysed according to the sampling and analysis pr'ogram of Table 2.1 and The results of the radioactivity analysis shall be used in accordance with the methods in section 2.2.2 to assure that the concentration at the point of release is maintained within the limits stated above.
l l
- a d'
j 01441
)
d n
5;$&l,,l$.',4h'hh b,0$W.\\.
Mn j
&DN f,%.. ;&f!b4bEk:
i e
o SQW ODCM J
Revision 24 Page 45 of 156 I
2.2.2 MPC-nm or THE RAT!01 i
The sum of the ratios (R ) for each release point will be calculated J
1 i
by the following relationship, i
CL RJ=
(2.1) where R3 the sum of the ratios for release point j.
=
i KPCg the MPC of radionuclide i, as specified in section 2.2.1,
=
wC1/mt..
Ci e concentration of radionuclide 1, wCi/mL.
l The sum of the MPC ratios must be s 1 due to the releases from any or all of the rolesse points described above.
The following relationship is used to ensure that this_ criterion is
-i mets i
t fgR3+fR22*fR33+fR44 (2.2)
[
RTBS +
i
- 1. 0
~
F i
where
~ * +
- RTBS eum of the ration of the turbine building sump as M
4 determined by equation 3.1.
fg f *f *fe = effluent flow rate for radweste, condensate 2 3 demineraliser system and each of the steem generators, respectively,'spm.
Rg,R *R *R4 " sum of ratics for redweste, condensate 2 3 domineralizer system and each of the steam generators, respectively, as determined by equation 2.1.
F
= minimum dilution flow rate for CTBD, 15,000 spm.
4 I
l l
l l
Reformatting / Repagination changes only g..
01441__
l i
- h 1$
i
.. c i* E
- ~
4
}
?
4 4
SQW ODCM Revision 24 page 46 of 156 2.? RADI0 ACTIVE L10UID EFFLUEWT HONITORINC INTTRUME*lTATION 2.3.1 EIOUIREMENTS The radioactiva liquid effluent monitoring instrumentation channels shown in Table 2.2 shall be OPERABLE with their alarm / trip setpoints R24 set to enrure that the limits of section 2.2.1 are not exceeded. The
- alarm / trip setpoints of these channels shall be determined in accordance with the methodology and parameters in Section 2.3.3.
This requirement is applicable during all releases via these pathways.
The radioactive liquid af fluA. instrumentation is provided to monitor and control, as applicable, ths releases of radioactive materials in liquid affluents during actual or potential releases of liquid ef flu"'
s.
The alarm / trip setpoints for these instruments shall be cale '? ed in accordance with the procedures in Section 2.3.3 to ensu - hat the alarm / trip will occur prior to exceeding the limits of 10 C '
art 20.
The OPERABILITY and use of this instrumentation is R24 cons' isnt with the requirements of General Design Criteria 60, 63 knd 64 of Appendix A to 10 CFR part 50.
If this requirement is not met, the appropriate following action (s) will be performed; With a radioactive liquid effluent monitoring instrumentation a.
channel alarm / trip setpoint less conservative than required abSve, without delay purpend the release of radioactive liquid effluents 9thyg monitored by the affected channel or declare the channel inoperable, or change the setpoint so that it is acceptably consorystive, b.
With less than the mininun number of radioactive liquid affluent monitoring instrumentation channels OPERABLE. take the action R24 shown in Table 2.2.
Exert best effort to return the instruments to CPERABLE status within 30 days a74, if unsuccessful, explain in R24 the next Scmi-Annual Effluent Release u&part why the inoperability could not be corr,ected within 30 days.
To ensure that this requirement is met:
Each radioactive liquid affluent monituring channel shall be demonstrated OpKRABLE by perfocmance of the CHANNEL CHECE, CRANNEL R24 cal'BRATION, and CHANNEL FUNCTIONAL TEST operations at tne R24 frequencies shown in Table 2.3.
a-01441 g/
- J
- (j Qy
,/- Q$
,3.pp,Q g
...,,.ggQh
a 4
SQW ODCH Revision 24 Page 47 of 156 3
2.3.2 ELLEAtt SAMPi,1NG Radweste tanks will be recirculated through two volume changes prior to sampling to,tnsure that a representative sample is obtained. The condensate demit,eraliter waste evaporator blowdown tanks cannot be recirculated. However, the contents will be transferred to the waste distillate tanks prior to release.
Condensate demineralizer tanks are routinely continuously released" and utilize a composite sampler to obtain a representative sample while being discharged. In the event of an inoperable effluent radiation monitor or composite sampler, a two volume recirculation and two independent samples and analyses will be performed. Releases from the steam generator b1;wdown and turbine building sumps,;.
considered continuous and grab-sampled daily.
Prior to a batch release, a grab sample will be taken and analyzed to determine the concentration, pCi/m1, of each gamma-emitting nuclide. For continuous releases, daily grab or composite simples will be taken and analyzed to determine the concentration, teci/m1, of each gamma-emittinF nuclide nuclide. Composite samples are maintained (as required by Table 2.1) to determine the concentration of certain nuclides (n-3, Fe-55 Sr-89, Sr-90, and alpha emitters).
For those nuclides whose activities are determined from composite samples (i.e. Wr-89, Sr-90, Fe-55 and H-3) the concentrations for the previous composite period will be assumed as the concentration for the i
next period to perform the calculations in Sections 2.2, 2.3, 2. A and
,,,hh 2.5.
The actual measured concentrations will ce used for the dose
$$d calculations described in Section 2.6 t
a sampling requirements for these release points are applicable only duries periods of primary to secondary leakage or t!.a release of radioactivity as detected by the affluent radiation monitor provided the radiation monitor setpoint is at a LLD of i IE-06 pCL/ml an allowing for_ background radiation during periods when primary to secondary leakage is occurring.
i
~
's c
' Reformatting / Repagination changes only 01441 h
. lll wu u 6....
,. fig.;;&, ff t;v,,;.7 %iffhQfy
.s.
- m. 4 b,. -bW ~ h:gy.Q3LhhKa QAfa {%
., a
SON ODCM Revision 25 Page 48 of 156 2.3.3 11?SIEUMENT SETPOIlil$
Liquid effluent monitor setpoints are determined to ensure that the concentration of iloactive material released at any time from the site to UNRESTRIClu. AREAS does not exceed the MPC limits referenced in ODCM Section 2.2.1 and to identify any unexpected releases.
2.3.3.1 D15dB192221RLManitor Setpoints (0-RE-90-2 1 Q-FE-90-123 -134,-140,-141)
The setpoints for the diccharge point monitor, RE-90-211, an0 for ERCW monitors (RE-90-133, -134, -140, and -143) are set to ensure that the concentr4 tion of radioactive materials released at any t!.me from the site do not exceed the limits given in ODCM Section 2.2.1.
The setpoints for these monitors will be set to alarm if the activity in the stream exceeds a value of 1E-06 pC1/ml.
2.3.3.2 Release Point _ Monitor Setpoints (0-RM~90-1222_Q-BM-90-225; 0-RM-90-2 U1_,LQs t 21 -RM-90-12 0, -12H There are five release point effluent monitors the Liquid Radwaste System radiation monitor 0-RM-90-122; the Condensate Domineralizer System radiation monitor 0-RM-90-225; the Turbine Building Sump radiation monitor 0-RM-90-212; and the Steam Generator Blowdown (SGBD) ggg-&
radiation monitors (1) (2).RM-90-120, -121.
The batch release points, the Liquid Radwaste System and the Condensate Demineralizer System (if being released in a batch mode),
are looking at an undiluted waste stream as it comes out of a tank.
The purpose of the monitor setpoints for these batch releases is to identify any release that is larger than expected and would have the potential to exceed the 10 CFR 20 limits after dilution. Setpoints are calculated as described in Section 2.3.3.3.
The continuous release points, the Condensate Demineralizer System, the Steam Generator Blowdowns and Turbine Building Sump, will not be releasing radioactivity unless there is a primary to secondary leak.
When there is no identified primary to secondary leakage, these release points are monitored to indicate che presence of elevated activity levels in these systems.
In accordance with the requirements of ODCM Table 2.1 footnote h, the setpoints for these monitors will be set to alarm if the activity in the stream. exceeds a value of lx10-' pC1/ml.
When there is identified primary to secondary leakage, the continuous release pointu are monitored to identify any release that is larger than expected and would have the potential to exceed the 10 CFR 20 limits after dilution.
The monitor setpoints are calculated in the
)
Entire Page Changed 01441
n i
S9N ODCM Revision 25 Page 49 of 156 same manner as the batch release point monitor setpoints, described in Section 2.3.3.3, when this is the case.
When these release points are being treated in this manner, a single batch release is defined as all effluent released through this point on a continuous bases for a period of time (usually one week).
2. 3. 3. 3 ReleAte_Ecint_tiontto1Jrips_ int For each release from a release point, two setpoints are calculated one based on the monitor response to the contents of the effluent s tre am; and another based on the predicted teeponse of the monitor to the activity in the release stream if it were large enough to exceed the 10 CFR 20 limits after dilution. The expected monitor response, R in epm, is calculated using equation 6.3 below. The maximum calculated setpoint, S is calculated using Equation 6.4 below.
m ax,
A comparison is made between these two calculated setpoints to determine which is used.
The actual monitor setpoint for the release is set equal to X times the expected monitor response, or to the maximum calculated setpoint, whichever is less. X is an administrative factor designed to account for expected variations in monitor response (it will be defined in approved plant instructions).
The X times expected response setpoint allows for the identification of any release of radioactivity above the expected amount.
The maximum calculated setpoint ensures that the release will be stopped if it exceeds the 10 CFR 20 concentration limits after dilution.
N EErgeted respanag R = B + I Eff3*C1 (2.3) where B
= monitor background, cpm.
Effi
= monitor efficiency for nuclide 1, cpm per pCi/cc.
Ci
= tank concentration of nuclide 1, pCi/cc.
Cnisulated Maximw!LEenitor Selenint SF (Fw+ (A*Fdil))
S
=
max (R - B)
+B (2.4)
Fw R3 where SF
= safety factor for the monitor.
F
= flow of waste stream, gpm.
w Fdil
= flow of the dilution stream, gpm.
A
= f raction of dilution flow allocated to this release point.
For the TBS, this fraction is zero.
The fractions for the remaining 4 release points are defined as the ratio of the Entire Page Changed l
0144v
)
i SOM ODCM Revision 25 Page 50 of 156 allocated minimum CT!!D flow for that release point to the i
tot.a1 minimum CTBD flow.
The mlnlmum CTDD flow allocation for these release points is as follows; Radwaste 9000 gpm Condensate domineraliser 3000 gpm Steam Generator Dlowdown (U1) 1500 gpm Steam Generator Blowdown (U2) 1500 gpm NOTE: These allocation factors may be adjusted for a particular release if it is known that there are no releases being made through other release points Anto the CTBD.
l'or euraple, if t.here are no releases being made through the Conde.+5 ate Domineralizer or either Steam Generator h.owdown, the allocation f actor f or the Radwaste Systd;t may be calculsted I
using the entire 15,000 gpm flow rate.
In addition, if the CTilD flow rate is greater than 1$,000 gpm, the additional flow rate may be used in the calculation of the allocation factors.
Ej sum of the MPC ratios for release point j as calculated in
=
Section 2.2.2.
R
= expected monitor response, cpm, as calculated above.
B
= background, cpm.
.. ma NM4N' r
Deleted by Revision 25 (2.5)
Deleted by Revision 25 (2.6) l l
t Entire Page Changed 0144v l
4 t
SQN ODCM Revision 24 2.3.4 Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 2.2.1 were not exceeded.
A composite list of concentrations (C ), by isotope, will be used t
with the actual waste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.2 to demonstrate compliance with the limits in Section 2.2.1.
This data and setpoints will be recorded in auditable records by plant personnel.
l M
Reformatting / Repagination changes only-
.M 01441 f
+
J
.. n l
}
v
a'*
- , "[-( A
e g$p 6i + r,,4 mi
,.g" $ 4 * ;'t.
- ->a.g*
fM.6
- f 4,
. -. ~..
.. ~.
SQN ODCH Revision 24 l
page 52 of 156 2.4 QQ1%
l 2.4.1 EEOUIREMENTS l
i The dose or dose commitment to a MEMBER OF THE PUBLIC from R24 l
radioactive materials in liquid affluents released to UWRESTRICTED R24 AREAS shall be limited from each reactor units-R24 s.
During any calendar quarter t; less than or equal to 1.5 mrom to the total body and to less than or equal to 5 arom to any organ, and b.
During any calendar year to less than or equal to 3 mrom to the total body and to less than or equal to lo trem to any organ.
This requirament is applicable at all times.
This requirement is provided to implement the requirements of Sections II.A, III.A. and IV.A of Appendix I, 10 CFR part 50 The requirement implements the guide set forth in Section II.A of Appendix I.
The action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in liquid effluents will be kept "as low as reasonable achievable."
Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in h5hhh radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.
The dose calculations in this Section implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriately R24 modeled pathways-is unlikely to substantially underestimated. The equations specified in this section for calculating the doses due to the actual release rates cf radioactive materials in liquid effluents are consistent with the methodology, provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR part $0, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.133, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1 " April 1977.
This requirement applies to the release of liquid effluonts from nach reactor at the site. For units with shared radweste treatment systems, the 1Lguld effluents from the shared systems are proportioned among the units shcring that system.
N
~ ~ "
01441
)
l l
o g
- e. 4 -o
+
i'
- W A & % 'I l
a.
_ {. lk, (m.... : 1
-5l, s
es
- s..
s
SQN ODCM Revision 24 page 53 of 156 If this requirement is not met, the following action will be performed:
With the calculated debe from the release of radioactive materials in liquid effluents exceeding any of the above limits. Prepare and submit to the Conaission within 30 days, pursuant to Technical Specification 6.9.2 a special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in coti.11ance with the above limits. This special Report shall also include (1) the results of radiological l
analyses of the drinking water source and (2) the radiological
% pact on finished drinking water supplies with r* gard to the requirements of 40 CyR 141 (applicable only if drinking water supply is taken from the receiving water body within three miles downstream of the plant discharge).
To ensure that this requirement is mets cumulative dose contributions from liquid affluents for the current calendar quarter and t.urrent calendar year shall be determined in accordance with the methodology and parameters in Section 2.4.2 at least once per 31 days.
M
?
f Reformatting /Repesination changes only 01441
.b ih w.
z_
- *+Yk k' E N; t'ghg
[
i e ke
..w P
U --. # p %/ : '
4.
SQN ODCM Revision 24 Page $4 of 156 2.4.2 CUKULATIVE LTOUID EFFLUENT DOSE CALCULATIONS Doses due to liquid effluents are calculated for each release for all age groups (cdult, teen, child and infant) and organs (bone liver, total body, thyroid, skin, kidney, lung and CI tract). Pathways considered are ingestion of drinking water, fish conrumption and recreation-shoreline. The maximum individual dose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser (see Table 1.1).
The maximum individual dose from fish ingestion is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the first downstream dam (Chickamauga Dam). The maximum potential recreation dose is calculated for a location immediately downstream of the plant outfall. Dose factors for these age groups and pathwaye are calculated as described in Section 2.7.
For pathways with no age or organ specific dose factors (i.e. shoreline recreation), the total body dose will be added to the internal organ doses for all age groups.
The general equation for the dose calculations ist Dose = 1 Ait TCi D (2.7) i where:
Ait
= the total dose factor to the total body or any organ t for nuclide i, mrem /hr per pCi/ml. The total dose factor is the sum of the dose factors for water ingestion, fish' ingestion, and shoreline recreation, as defined in Section 2.7.
ggggg T
= the length of time period over which the concentrations and the flows are averaged for the liquid release, hours.
Ci
= the average concentration of radionuclide i, in undiluted liquid ef fluent during the time period T from any liquid release, pCi/ml.
D
= the near field average dilution factor for C t during any effluent release. -D is caleuinted by the following equation:
FLOWw D=
0.50 RF where
- FLOW, maximum undiluted liquid waste flow during the release, cfs, For TBS releases, this term is the diluted waste flow into the pond.
0.60
= mixing factor of affluent in river, defined as the percentage of the riverflow which is available for dilution of the release.
RF
= default riverflow, cfs. For each release, this value is set to 7900 cfs (the lowest everage quarterly riverflow recorded from the period 1978-1988).
Reformatting / Repagination changes only "i
01441
)
j aA
., e b
9 3P
.4 I 4.&
f g
-g
... ~ ~
~-.
SQW ODCM-Rsvision 24 -
page 55 of 156 From the four age groups considered, the maximum is determined by comparing all organ doses for all age groups. The age group with the highest single organ dose is selected as the critical age group. The total body and maximum organ doses for the critical age group are used in the calculation of the monthly dose described in Section 2.4.2.2.
2.4.2.2 Monthly Dose Calculations-At the end of each month, the actual average riverflow for the month is used to recalculate the liquid doses. The monthly cumulative dose is defined as the rum of.the doses for the critical age group for each release during the month. Thus, the monthly cumulative dose will be a conservative value, consisting' of doses belonging to various age groups depending -on the mix of radionuclides. : These doses are multiplied by the ratio of the default riverflow (1900 cfs) to the actual monthly average riverflow to obtain the monthly dose. The total body and maximum organ doses determined in this manner are then used to determine the cumulative quarterly and annual' doses described in Section 2.4.2.3, and for the dose projections described in Section 2.5.3.
2.4.2.3 Cumulative Doses Quarterly and annual sums of all doses are-determined at the end of-each month to compare to the limits given in'Section 2.4.1.
These quarterly and annual sums will be the sum of the monthly cumulative doses described in Section 2.4.2.2 for the appropriate months in the quarter or year. These doses will be used in the comparison to the-limi ts.
@$UI@
2.4.2.4 Comparison to Limits The cumulative calendar quarter and calendar year' doses are compared-to the limits in Section 2.4.1 once per 31 days to determine '
compliance.
Reformatting / Repagination changes only -
.01441
,a
~ av S*,
1 5h
,', a.
.Y.
, J!
f f
fh}-*(? j'b. &
(.A
'.{ l llk'?$* ~
'* 'k?$ V l
s~
~
r-
SQN ODCM Revision 24 Page 56 of 156 2.5 LIOUID WASTE TRF.ATMENT 2.5.1 REOUIREMENT The liquid radweste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent to UNRESTRICTED AREAS R24 (see Figure 1.3) would axceed 0.06 arem per reactor unit to the total body or 0.2 meem per reactor unit to any organ in a 31-day period.
This requirement is applicable at all times.
The requirement that the appropriate portions of this systam be used when specified provides assurance that the releases of radioactive materimis in liquid effluents will be kept "as low or reasonable achievable." This requirement implements the reqw! taents of 10 CFR part 50.36a, General Design Criteria 60 of Appendix A to 10 CFR Tart 50 and the design objective given in Section II.D of Appendix 1 to 10 CFR part 50.
The specified limits governing the use of appropriate portions of the liquid redwaste system were specified as a suitable fraction of the dose design objectives set forth in Section II. A of Appendix I,10 CFR part 50, for liquid effluents.
If this requirement is not met, the following action will be performed:
With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepara and submit to the psWNy Commission within 30 days pursuaC. co Technical specification 6.9.2, a special Report which includes the following information:
1.
Identification of the inoperable equipment or subsystamm and the reason for inoperability, l
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and R24 i
3.
Summary description of action (s) taken to prevent a recurrence.
To ensure that this requirement is met:
Doses due to liquid releases shall be projected et least once per 31 days, in accordance with the methodology sud parameters in Section 2.5.3.
.b c 014=1 d
'ts
,f y
- O,*
^g I
.?*"*
~~W
_ [.
?_ '$
t l
SQR ODCK Revision 24 page 57 of 156 2.5.2 LTOUID RADWASTE TREATMENT SYSTEM The liquid radwawte treatment system described below shall be maintained and operated to keep releases ALARA.
A flow diagram for the LRTS is given in Figure 2.2. The system consists of one reactor coolant drain tank with two pumps and a floor and equipment drain rump inside the containment of each unit and the following shared equipment inside the auxiliary buildings one sump tank and pumps, one tritiated drain collector tank with two punps and one filter, one floor drain collector tank with two pumps and one filter, a waste condensate tank filter, three waste condensate tanks and two pumps, a chemical drain tank and pump, two laundry and hot shower tanks and pump, a spent resin storage tank, a cask decontamination tank with two pumps and two filters. Auxiliary Building floor end equipment drain sump and pumps, and evaporator with two distillate tanks, a Mobile Waste Domineralizer System (if needed) and the associated piping, valves and instrumentation.
2.5.3 DOSE PROJECTIONS In accordance with Section 2.5.1, dose projections will be performed by averaging the two previous month's doses as determined in Section 2.4.2.2.
To determine compliance with the limits, these averages are assigned as the dose projections for the upcoming month.
The projected doses are compared to the limits of Section 2.5.1.
If the projected doses exceed either of these limits, the liquid radwaste
- ~ + -
"MNd*
treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge to UNRESTRICTED AREAS.
R24 M
a-01441 J
a
$'2[ ntd[
vh($@" 'N0L 27,p%..W.-@,68,2, pgh.
. ~ _ _.- _
0 SQN ODCM Revision 24 page 58 of 156 2.6 OtfARTERLY DOSE CALCVLATIONJ A complete dose analysis utilicing the total estimated laquid releases for each calendar quarter will be performed and reported as required 1
in Section 5.2.
Methodolof.y for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assir.ned, for this calculation, to be continuous over the 90 day Period.
The average dilution f actor, D, used for the quat terly calculations ist l
1 l
D=
(for receptors upstream (2.7)
- 0.60 of Chickamauga Dam) and.
D=
(for receptors downstream (2.8)
RF of Chickamauga Dam) where RT
= the average actual riverflow for the location at which the dose is being determined, cfs.
0.60 = the fraction of the riverflow available for dilution in the near field, dimensionless.
2.6.1 WATER INGCSTION Water ing,estion doses are calculated for each-water supply identified within a 50 mile radius downstream of SQN (Table 2.4).
Water NWM ingestion doses are calculated for the= total body and each internal organ as described below Dorg = 10* 9.80E-09 Awig Qi D exp(-8.64E+04 ki t)
(2.9) d where 10'
= conversion factor, pCi/Ci.
9.60E-09 = conversion factor,-cfs per al/ hour.
1 Agit
= Dose factor for water ingestion for nuclide 1, age group I
t, mrem / hour per yC1/m1, as calculated in Section 2.7.1.
gg
= Quantity of nuclide i released during the quarter, curies.
l D
= dilution factor, as described above, cis-1 kg
= radiological decay constant of nuclide i, seconds **
l (Table 1.10).
l l
Reformatting / Repagination changes only 01441
)
id
,0f. ; [ -
.;s Qbk:s -Q,'ffdh& a
~.
.~'
' f D "" % "NS~
Ci SYs
e SQW ODCM Revision 24 page 59 of 156 td decay time for water ingestion, equal to the travel time
=
from the plant to the water supply plus one day to account for the time of processing at the water supply (per Regulatory cuide 1.109), days.
8.64E+04 conversion factor, seconds per day.
=
2.6.2 FIEH INGESTI,9E Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of SQN (Table 2.4).
Individual fish ingestion doses are calculated for the total body and each internal organ as described below Dors = 10' 9.80E-09 0.25 Ayit Qi D arp(-8.64E&O4 it t)
(2.10) d where 10' conversion factor, pCL/C1.
9.SOE-09 e conversion factor, cfs per ml/ hour.
0.25 fraction of the yearly fish consumption eaten in one a
quarter, dimens.onless.
Apit Dose factor for fish ingestion for nuclide i, age group t,
=
mrem / hour per pCi/ml, as calculated in Section 2.7.2.
Qg Quantity of nuclide i released during the quarter, Curies.
=
D dilution factor, as described above, cfs-4
=
At radiological decay constant of nuclide i, seconds-2
=
(lable 1.10).
$$$%g td
. decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days.
B.64E+04 conversion factor, seconds per day.
e 2.6.3 SHORELINE RECREATION Recreation doses are calcultted for each identified reach within a 50 mile radius downstream of SQN (Table 2.4)..It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline at a location immediately downstream from the diffusers, Individual e
recreation shoreline doses are calculated for the total body and skin as described below:
Dors = 108 9.80E-09 rf ARit Qi D exp(-8.64E+04 Ki t)
-(2*11) d where 10' conversion factor, pCi/CL.
=
conversion factor, cfs per al/ hour.
9.80E-09 a
Nc a-Reformatting / Repagination changes only
.01441 i
ja 6.)
b ~ N N<
+
v i + ;hi,
'f a 2 N7h E'*t
- i
'? -
N b E'
i P
a e
SON ODCM Revision 24 page 60 of 156 rf recreation factor, used to account for the fact that the a
same amount of time will not be spen; at a recreation site during each quarter. - Recreation f ac tors used are:
1st quarter - 0.1 2nd quarter - 0.3 35d quarter - 0.4 4th quarter - 0.2.
ARit
= Dose factor for shoreline recreat'.on for nuclide i, age group t, mram/ hour per vC1/m1, as calculated in Section 2.7.3.
Q1
= quantity of nuclide i released during the quarter, curies.
D
= dilution factor, as described above, cfs**.
11
= radiological decay constant of nuellde i, seconds-1 (Table 1.10),
td
- decay time for recreation, equal to the travel tima from the plant to the center of the reach, days.
8.64E+04
= conversion factor, seconds per day, 2.6.4 TOTAt MAX 7 MUM TNDIVIDUAt DOSE 7.ht tetal_maxip m individual total. body._ dose _is_obtained.by summing the fallowing _for_sach_ age _gecupa_the highest _ total _ body _wate.r inge s tiorLdo s t_f rontamong_sil_the._ pub lic._ya t ensuppJ i_e s t_the_ hi ghe s t total _ body.. fish _ ingestion dose from.among_all the reaches; and the total _ body _ maximum shoreline. recreation _ dose. The total maximum individual organ dose is obtained by summing the following for each Q
organ and each age groups that organ's highest water ingestion dose from among all the public water supplies; that organ's highest-fish ingestion dose from among all-the reaches; and the total body maximum shoreline recreation doso. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.
2.6.5 EOPUtATION DOSES For determining population doses to, the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.
For water ingestion, the general equation used for calculating-the population doses, PopWTR, in man-rom for a given PW3 is:
5 4
popWTRg = 10-s { pop, [ P0pa ATHW, TVDOSamt (2.12) n.1 a=1 where:
water ingestion population dose to organ - t, man-rem.
PopWTRg a
"e:
Reformatting / Repagination changes only 0141
)
J a
m%
- 7
.i, Q _,
.r
~ M*h.
nt,
- i 4" *
.d.
i-
- 0
' E' 2'.%
I ~,:'.
.$$I,*
.y
l SQN ODCM Revision 24 Page 61 of 156 POP
- fraction of population in each age group a (from a
WUREO CR-1004, table 3.39).
Adult 0.665
=
Child 0.168
=
infant = 0.015 Toen 0.153
=
POP
- population at PWS m.
The 4 PWSs and their populations m
are listed in Table 2.4 ATMW
= ratio of everage to maximum water ingestion rates for a
each age group a.
Maximum water ingestion rates are given in Table 1.11.
Average water ingestion rates, in L/ year (from R.C. 1.109 Table E-4) are Adult 370 Child
= 260 Infant = 260 Teen 260
=
TVDOSamt
= total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 2.6.1, mrem.
10**
= conversion factor for rem /mrom.
For population doses resulting from fish ingestion the calculation assumes that all fish caught withits a 50-mile radius downstream of SQN are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses POPF, in man-rem from fish ingestion.
j;yyy of all fish caught within a 50-mile radius drwnstream is:
453.6 KVST APR 4
3 TFDOSart POPa POPFt=
1 1
(2 13) los 108 r=1 a=1 FISH, POPs where:
POPFt
= total fish. ingestion population dose to organ t, man-rem.
HVST
= fish harvest for the, Tennessee River, 3.04 lbs/ acre / year.
APR
= size of reach, acres (Table 2.4).
TFDOSart
' total fish ingestion dose to organ t for reach r,'
for the age group a, as described in Section 2.6.2, mrom.
- POP,
= fraction of population in each age group a, as given above.
FISH
= amount of fish ingested by each age group a, kg/ year.
a Average fish ingestion rates (R.C. 1.109 Table E-4) are:
Adult 6.9
=
Child 2.2
=
Teen 5.2
=
453.6
= conversion factor, g/lb.
10'
= conversion factor, aram/ rem.
108
= conversion factor, g/kg.
Reformatting / Repagination chanaes only 01441
)
_s
, :,.x
- l..
ab lAQ
)
40$M$$$$%% ^
"' - ~~+S5 ti%iW&dbO$$
i SQN ODCH Revision 24 i
Page 62 of 156
.For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem ist REQTRA 4
POPRt=
1 TSHDOSrt 8NVI8 HRSVIS (2.14) r p
108 8760 r=1 where:
POPRt a total recreation population dose for all reaches to organ t, man-rem.
REQFRA fraction of yearly recreation which occurs in that
-a quarter, as given in Section 2.6.3.
TSHDOSrt total shoreline dose rate for organ t, in reach r, a
mrem /h.
SHVIsr shoreline visits per year at each reach r, (Table 2.4).
a MRSVISp length of shoreline recreation visit at reach r. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
a los conversion factor, prem/ rem.
a 8760 conversion factor, hours / year.
=
-w i
l t
l l
l I
Reformatting / Repagination changes only 01441
]
J*
- +
.g E-a, 6.- tw-
".-+s I Y
! W Y + ~'i-*:'ebf*:
'. 'N bd$ k. -., - -.. - -
hY b
5 kkA%ib $hvi h5 Sib
e SQN ODCH Revision 24 2.7 LIOUID DOSE FACTOR EQUATIONS 2.7.1 WATER INCESTION - AWit (arem/hr per pCi/ml)
DFList U 108 108 wa 8760
'where:
DFList
= ingestion dose conversion factor for nuclide i, age group a, organ t, arem/pci, (Table 1.9).
U
= water consumption rate for age group a. L/ year,--
we (Table 1.11).
10'
= conversion factor, PCi/pci.
10'
= conversion factor, al/L.
8760
= conversion factor, hours per year.
2.7.2 TISH INCESTICH - Aptt (mrem /hr per pCi/ml)
DTLinkUfa Bi 10' los 8760 where!
DF iat
= ingestion dose conversion factor for nuclide i, age group L
a, organ t, mrem /pci, (Table 1.9).
Uga
= firh consumption rate for age group a, kg/ year.
--W (Table 1.11).
Bt
= bioaccumulation factor for nuclido i, pCi/kg per pCi/L, (Table 2.5).
10'
= conversion factor, pCL/pci.
10'
= conversion factor, ml/L.
8760
= conversion factor, hours per year.
2.7.3 SHORELINE RECRF.ATION - ARit (arem/hr per WCi/ml).
DFCit Ke M W 108 10* U ARit
- Il-exp(-1 t )l 1b where:
DFCit
= dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), arem/hr per pCi/mt, (Table 1.13).
K
= transfer coefficient from water to shoreline sediment.
e L/kg-hr, (Table'1.11).
M
= mass density of sadiment, kg/m8. Table 1.11).
(
Reformatting / Repagination changes only 01441
)
I
=
A lU.
..u :
- in 5 2,h 4
- 6jbSs.h, Q,74.:
...r.;,; gg.gh* -
- 44
- Q 4,,.;,,
,g y.
.4 SQW ODCH Revision 24 Page 64 of 156
_.t K
= transfer coefficient from water to shoreline sediment, e
L/kg-br, (Table 1.11),
M
. mass density of sediment, kg/m, (Table 1.11).
8 W
. shoreline width factor, dlmensionless, (Table 1.11).
10'
. conversion factor, al/L.
10'
. conversion factor, PC1/pci.
3600
. conversion factor, seconds / hour.
11
= decay constant for nuclide i, seconds-a, (Table 1.10).
tb
. time shoreline is exposed to the concentration on the water, seconds, (Table 1.11).
U
. usage f actor, 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> / year.
8760
. conversion-factor, hours / year.
l l
4 Refonnatting/ Repagination changes only 01441
)
s
~
44, g
i u.
s.",
. c.
Et:e,
N
... #... a.
m.s N
I, E
E*
'* l
t l
IO,,,.7.N 5
,., -'
- k '". " '. * " - - - - - - -
-~~~-~~*---v~--
~
~ "
v
SQN ODCH Revision 24 page 65 of 156 3.0 Radiolotical Environmentel Monitorint 3.1 MINIMUM REQUIRED MONITORING PROCRA){
3.1.1 REOUIREME E The radiological environmental monitoring program shall be Conducted sa specified in Table 3.1.
This requirement is applicable at all times.
The radiological environmental monitoring program required by this section provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring progrr.m by verifying that the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the firrt three years of comercial operation.- Following this period, prcgram changes may be initiated based on operational experience.
The LLDs required by Table 3.2 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a prlgri (before the fact) limit representing the capability of a measurement system and not as a N
posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidatly small sample stres, the presence of interf aring nuclides, or other uncontrollable circumstances may render these LLDs unschievable. In such cases, the contributing circumstances will be identified and described in the Annual Radiological Environmental Operating Report.
If this requirement is not met, the appropriate following action (s) will be perfomed:
With the radiological environmental monitoring program not being a.
conducted as specified in Table 3.1, prepare and submit to the consnission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b.
With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.3 when averaged over any calendar quarter, prepare and submit to the Comunission within 30 days from the end of the affected quarter, pursuant to Refomatting/ Repagination changes only 01441
)
W
- h&
m
.sur'
?
1 N M C $ddd M 3 $j@ #. 6 4 prb.4 %. as6MS$1A%Fl@6d@d5i !
+
SQN ODCH Revlaion 24 i
page 66 of 156
~
Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents se that the potential annual dose to a member of the public is less than the calendar year limits of Sections 1.4.1. 1.5.1 and 2.4.1, When one or more of the radionuclides in Table 3.3 is detected in the sampling medium, this report shall be submitted ift concentration (1) concentration (2)
+
+..
3,1.0 limit level (1) limit level (2)
When radionuclides other than those in Table 3.3 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to R24 or greater than the calender year limits of Sections 1.4.1, 1.5.1 and 2.4.1.
This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event., the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
c.
With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specified locations from which sampler were unavailable may then.
l M
be deleted from the monitoring program. Pursuant to Section 5.1, I
identify the new locations for obtaining replacement samples in j
the Annual Radiological Environmental Operating Report. A revised figure (s) and table (s) for the ODCH ref1seting the new location (s) shall be included in the next Semi-Annual Effluent Release Report pursuant to Section 5.2.
l To ensure that this requirement is met:
The radiological environnental. monitoring samples shall be collected pursuant-to Table 3.1 from the, locations given in the tables and figures listed below and shall be analyzed pursuant to the requirements of Table 3.1 and the detection capabilities required by Table 3.2.
3.1.2 NOVITORING PROGRAM An environmental radiological monitoring program shall be conducted in accordance with the above requirement. The monitoring program described in Tables 3.4, 3.5, and 3.6, and in Figures 3.1, 3.2 and 3.3 shall'be conducted. Reruits of this program shall be reported in 01441 I
f.,
d2 M
- ,h.
kh g% +f'.'-+-.
.Qh _fy+3 _ _ _ _.
-p 6
4
SQN ODCM Revision 24 page 67 of 156 accordance with Section 5.1.
The atmospheric environmental radiological monitoring program shall consist of monitoring stations from which samples of air particulstes and atmospheric radiciodine shall be collected.
The terrestrial monitoring program shall consist of the collection of allk, soil, ground water, drinking water, and food crops. In addition, direct gansna radiation levels will be measured in the vicinity of the plant.
The reservol.r sampling program shall consist of the collection of samples of surface water, sediment, clams, and fish.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavailability, or to malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.
3.1.3 DETECTION CAPABILITIES Analytical techniques shall be such that the detection capabilities listed in Table 3.2 are achieved.
l l
Reformatting /Repag;ination changes only l
I g
(,. N l[j d+. <
v y,[td3h.
, Ygyd w
y
~ -
a i
SQN ODCH Revision 24 page 68 of 156 3.2 LAND USE CENSUS 3.2.1 PEOUTREMENI A Land Use Conrus shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest allk animal, the nearest residence, and the nearest garden
- of greater then 50 38 (500 f t8) producing f resh leafy vegetables.
This requirement is applicable at all times.
This requirement is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of that census. The best survey information from the door-to-door, serial, or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Peat 50.
Restricting the census to gardens of greater than 500 f t' provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a scrden of this size is the mininum required to provide the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this mininum garden size, the following assumptions were used 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m.
8
(
ggggg The results obtained in the Land Use Census will be evaluated in t
accordance with the following appecpriate actions:
i l
a.
With a Land Use Census identifying a location (s) that yields a l
calculated dose or dose commitment 20% greater than the values l
currently being calculated in Sections 1.4 and 1.5, identify the l
new location (s) in the next Sami-Annual Effluent Release Report pursuant to Section 5.2.
b.
With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same pathway) 20%
greater than at a location from which samples are currently being obtained in accordance with the requirements of Section 3.1.1, add the new location (s) within 30 days to the radiological environmental monitoring program given in section 3.1.2, if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose conunitment(s), via the same exposure pathway, may be deleted from this monitoring program af ter october 31 of the year in which this Land Use Census was conducted. pursuant to Technical Specification 6.14, submit in the next Semi-Annual Effluent Reformatting / Repagination changes only 71.c l
a-01441 l
'M w
y
- EE 5 ' ' '
c- *
.h ekfkk 54 s,n
..p-y,n,e
&Y*4?NJ se
+$ -
lte
$$yK*hh y'
A*
~ v"
i SQN CDCH Revision 24 page 69 of 156 Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with the information supporting the changu in sampling locations.
To ensure that this requirement is met:
j The Land Use Census shall be conducted during the growing season l
at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, mail survey, telephone survey, serial survey, or by consulting local agricultural authorities. The results of the Land Use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Section 5.1.
i 3.2.2 LM'D USE CENSUS A land use survey shall be conducted in accordance with the requirements above. The results of the survey shall be reported in the Annual Radiological Environmental Operating Report.
i
...,e v4Wei4p l
l Brc 1 leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two-R24 different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.1.4c shall be followed, including analysis of control samples.
,% c
(
. a.-
01441 i
../
N
\\
e
~
ao ' yp i
);' **
Et
,, f h ** '* "
'h51-$ '
M.* ' "5 -
- ef
'4
-r
i SQN ODCH Revision 24 page 70 of 156 3.3 INTERLABORATORY COMPARTSON PROCRAM 3.3.1 REQUIREMENT Analyses shall be performed on radioactive materials eupplied as part of an Interlaboratory Comparison program which has been approved by the Cossalssion.
This requirement is applicable at all times.
The requirement for participation in an Interlaboratory Comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
If this requirement is not met, the following action will be performed:
With analyses not being perforined as required above, report the corrective actions being taken to prevent a recurrence to the Comission in the Annual Radiological Envirotunental Operating Report.
To ensure that this requirement is met:
A numnary of the results obtained as a part of the above required N
Interlaboratory Comparison program and in accordance with the guidance below shall be includod in the Annual Radiological Environmental Operating Report.
3.3.2 IFIERLABORATORY COMPARISON PROCRAM Analyses shall be perfot1ned on radioactive materials rapplied as part of an Interlaboratory Comparison program which has been approved by the NRC. A summary of the results bbtained in the intercomparison shall be included in the Annual Radiological Environmental Operating-Report (or the EPA program code designation may be provided).
If analyses are not performed as required corrective actions taken to prevent a recurrence shall be reported.in the Annual Radiological Environmental Operating Report.
Reformatting / Repagination changes only l
01441
/
I e
?
7,'
. vsf
- ..E M,
h k
d5i hks$$f[9?" NN " - **NNE,
i'
?
I k
o SQN ODCM Revision 24 page 71 of 156 4.0 IoIAL DOSE 4.1 REOUTPrMENT The annual (calendar year) dose or dose cossnitment to any KEMBER OF THE R24 PUBLIC, due to rolesses of radioactivity f rom uranium fuel cycle R24 sources, shall be limited to less than or equal to 25 mraa to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mesa).
This requirement is applicable at all times.
This requirement is provided to meet the dose limitations of 40 CFR 190. The action requires the preparation and submittal of a special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.
For sites containing up to 4 reactors, it is highly unlikely that the rerultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits R24 of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The special Report will describe a course of action which should result in the limitation of dose to a MEMBER OF R24 THE PUBLIC for 12 consecutive months to within the 40 CTR 190 limits.
R24 For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel R24 cycle sources is negligible, with the exception that dose contributions.from other nuclear fuel cycle facilitie: at the same site or within a radius of 5 miles must be considered.
ggggp If*this requirement is not met, the following action will be performed:
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of section 1.4.1. 1.5.1, or 2.4.1, calculations should be made to determine if the above limits have been violated. If such is the case, prepare and submit a special Report to the Director, Nuclear Reactor Regulation U.S. Regulatory Commission, Washington D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits above. This Special Report, as defined in 10 CTR part 20.405c, R24 shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources R24 (including all effluent pathways and direct radiation) for a calendar year that includes the release (s) covered by this report. If the estimated dese(s) exceeds the above limits, and if the release 4
condition resulting in violation of 40 CFR 190 has not already been corrected,- the special Report shall include a request for a, variance in accordance with the provisions of 40 CFR 190 and including the specified information of section 190.11(b). Rubmittal of the report M
01441 w
1
'W h55 k
h
${hhi4. ~ f 7
- =.$;
h
',5k 3,5.
4
__._._m SQW ODCH Revision 24 Page 72 of 156 is considered a t1 Rely request, and a variance is granted until the staff action on the request is completed.
R24 To ensure that thit; requirement is mett Cunn41stive dose contributions from liquid and gaseous efflusnts shall be determined in accordance with the methodology and parameters in Sections 1.4.2, 1.5.2, and 2.4.2.
4.2 LNNUAL MAXIMUN INJLUIDUAL DOSES - TOTAL REPORTED DOSE To determine compilance with 40 CFR 190 as required in Section 5.2, the annus1 done contributions to the maximum individual-from SQW radioactive ef fluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by first, summing the quarterly total body air submersion dose, the quarterly critical organ dose from gaseous effluents, the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the direct radiation monitoring program, and then taking the sum for each quarter and summing cvsr the four quarters.
N l
l 3 % C.
01441
.A 3
pE a
W%4#h2W @ #M W.,,hishh M M 4;& #;# W W WE DE @ gs'g@
0 i
SQN ODCH Revision 24 page 13 of 15f, 5.0 E[ PORTING REOULREMEh'Jf$,
5.1 $NWUAL RADiotocIcAL_rNVIRONMENTAL OF RATING REPORT The annual radiolor,ical environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Section 3.2 and a listing of the new locations for dose calculations and/or environmental monitoring identified by the land use census. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include summarized and tabulated results in the f or1nat of Negulatory Guide 4.8 December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
$lififf The reports shall also include the followings a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensee participation in the Interlaboratory Coc:parison Program required by Section 3.3.
i 5.2 STMT-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE rep 0R_I Semiannual radioactive release reports shall include a summary of the cuantities of radioactive liquid and gaseous effluents and solid waste l
released from the unit as outlined in Regulatory Guide 1.21 j
- Measuring Evaluating, and Repori.ing Radioactivity in Solid Wastes I
and Releases of Radioactive Materials in Liquid and Caseous Effluents from Light-Water-Cooled Nuclear power plants," Revision 1. June 1974, with data summarized on a quarterly basis following the forv.at of Appendix B thereof.
The semiannual radioactive release repor' shall include unplanned releases from the site to unrestricted areas on a quarterly basis and shall also include any changes made to the ODCM pursuant to Technical Specification 6.14.
.f Reformatting / Repagination changes only 01441
)
1
,t e
fEsMi&dfdsMk.u,: w;.
m uMMMWMUdswandig"
S9N ODCM Revision 25 Page 74 of 156 i
The semiannual radioactive release report shall inciwne informstlon for solid waste as outilned An the Process Control program, ar.$ shall also include any changes made to the PCP during the reporting period.
The semi-annual radioactive release report shall include a discuss!on R2$
of any licensee faltlated major changes to the radwaste systems as R25 required by SON Technical Specification 6.15.1.1.
R2L The annual s5dioactive effluent release report (Radiological Impact) to be submitted 60 days after January 1 of each year shall include an 1
annual summary of hourly meteorological data collected over the
)
previous year. This annual summary may be either in the form of an i
hour by hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the a
form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
In lieu of submission with the annual radloactive effluent release report, this summary of required meteorolcgical data may be retained in site in a file thet shall be provided to WRC uprn request).
Th!s same report shall include an assessment r* the radiation doses due to radlohetive 11guld and gaseous off usnts released from the un!t or station during the previous calendar year. This same report shall also include an tesessment of the radiation doses from radloactive 11guld and gaseous tiluents to MEMBERS Of THE PUBLIC due to their activities inside the tit BOUNDARY (rigure 1.3) during the report period.
All assumptions sed 11. making these assessments (l.e., specific activity, exposure time, and location) sns11 he included in these reports.
The
- v..u, meteorological conditions concurrent with the time of release of radioactive materl Als in gaseous ef fluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in accordance with Sections 1.7 and 2.6.
The annual radioactive effluent release report to be submitted after January 1 of aach year shall also include an assessment of radiation dnpos to th6 Ilkely most exposed MEMDERS OF THE PUBLIC from reactor talenbes and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation, in accordance with Section 4.2.
Acceptable methods for calculating the dose contribution from 11guld and gaseous effluents are given in Regulatory Guide 1.109, Revis!on 1.
l 0144v l
l.
l 5
e
.-ne,,..
nn.
-,s.,-+--,-n
.---m,--
,,w--,.
,,y aw.x,.
,w.n.-n,
- - y w--,-,---e
- ~~ n
. -~< - ~,
-,.,--rsv---
l SQW ODCH Revision 24 page FS of 156 6.0 EEFINITIONS The defined terms in this section appear in capitalized type in the text and are applicable throughout this ODCH.
6.1 CMENEL CALIBRATION A CHANWEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANWEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHAyVEL rirWCTIONAL TEST. The CHAWNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
6.1 CHANNEL CHECK A channel check shall be the qualitative assessement of channel behavior during operation by observation. This deternination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
6.3 CHANNEL TUNCTIONAL TEST A CRANNEL TUNCTIONAL TEST shall bet Analog channels - the injection of a simulated signal into the a.
channel as close to the sensor as practicable to verify OPERABILITF including alarm and/or trip functions.
b.
Distable channel - the injection of a simuisted siti 41 it.Lo the sensor to verify OPERABILITY including alarm and/or trip function.
6.4 CASEOUS RADWASTE TREATMENT SYST'EM A CASE 0VS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluance by collecting primary coolant system offgedes from the primary system and providing f or detr* or holdup for the purpose of reducing the total radioactivity prior to release to the environenant.
Page Added N.:.
01441
/
,s
- 8
'r I
ETsiG6k Mk N)MM i 'l*
E-hfNt6bbN10ISMWN h bb
I A
e sQW ODcM Revision 24 page 76 of 156 6.5 DOSE EQUIVALEWT 1-131 DOSE tQUIVA1.ENT 1-131 shall be that concentration of 1-131 (pC1/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131. 1-132. 1-133. 1-134 and 1-135 attually present. The thyroid dose conversion f actors used for this calculation shall be those listed in Table III of 71D-14844, " Calculation of Distence rectors for power and Test Reactor Sites."
6.6 MEMBER (8) Or THE PUBLIC MtKBER(5) OP THE PUBLIC shall include all individuals who are not occupationally associsted with the plant. This category shall include non-employees of the licensee who are pomitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category does not include non employees such as vending nachine servicemen or postenen who, as part of their formal job function, occasionally enter an area that is controlled by the licensee for purposes of protection of individuals f rca exposure to radiation-and radioactive materials.
6.7 OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE oc have OPERADILITY when it is capable of perfoming its specified f uMtion(s), and when all necessary attendant instrumaettation.
controls, a normal and an emergent,y electrien1 power source.
N,,,
ewlint, or seal water. lubrication or other auxiliary equipment that tre required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing, that ? related support function.
6.8 HODE A HDDE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 4.1 of-the SQW Technical Specifications.
6.9 PURCE - pURCIWO PURCE or pURG1WG is the controlled process of discharging air or gas from a confinement to maintain temperature. Pressure, humudity, concentration or other operating condition. in such a manntr that replacement air or gas is required to purify the eonfinoment.
page Added
[
01a41
)
1 l'
,/'
Q
'.h M$?kbt0%&#$bs 99e c me,:yd$Ql., q}]piQjk%+;4&$Q&
SQN ODCH Revision 24 page 77 of 156 6D RATED '!HEPN.L PWER RATED Tilt'KRAL POWQ shall be a total reactor core heat t ransfer rate to the reactor coolant of 3411 NWL.
6.11 SITE BOVHDARY The SITE BOVWDARY shall be that line beyond which the land is not owned leaseo, or otherwise controlled by the licensee (sce Figure 1.3) 6.11 SOURCE CHECE A SOURCE CHECK shall be the qualitative assestment of channel response when the channel sensor is orposed to a radioactive source.
6.13 UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area, at or beyond the SITE BOUNDARY to which accoas is not controlled by the licensee for purposed of protection of individuals frum exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.
6.14 VENTILATION EKMAUST TREATMENT SYSTEM khhkf A VENTILATION EKRAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate fers in af fluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION EIMAUST TREATMENT SYSTEM components.
6.15 VENTINC VENT 1WO is the controlled process of discharging air or gas from a confinament to maintain temperature, pressure, humidity, concentration, or other operating condition. in such a manner that replecament alc gas is not provided or required during VEYTINC.
V6nt, used in system names, does not imply a VtVTING process.
page Added
,% 4 01441
)
St. f.hp
- -cmadpy g M M&... elm {Q fqwQdiWMQ@mkri a
~ -
_4 4
-a r *.
_______.J._.
-+w 1s
,w-r s
a_
o SQN ODCM Revision 24 Page 78 of 156 Table 1.1 (Page 1 of 4)
RADIDACTIVE CASEOU$ WASTE MONITORING SAMFLING AND ANALYSIS PROGkAM Gaseous Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD)
Type Frequency Frequency Analysis (pC1/ml)'
A. Waste Gas P
P
~
Storage P.ach Tank Each Tank Principal lx10**
Tank Crab Camma faitters8 L. Containment
- 1. PUkGE P'
D' Principal lx10**
R24 Each PURCE Each PURCE Cazena R24 Grab faitters8 Sample 11 - 3 lx10*'
DJ DJ Principal lx10**
- 2. Vent Each Day Each D6y Gamma Crab Emitters 8 Sample H-3 lx10**
E Noble Gases and M
M Principal lx10-*
Tritium Grab Camma Sample reitters8
- 1. Condenser i~~~
Vacuum H-3 lx10*'
.b Exhaust"
- 2. Auxiliary Building
Exhaust
- 3. Service Bldg.
Lxhaust I
l
- 4. Shield Bldg.
Exhaust'"
Lc Reformatting / Repagination changes only 01461
~~
l i
1 c
_.'e f ' 4.1$
w.w%MWer
.. g.sqfs p&c% mAdsd
o SQN 09CM Rovision 74 Fate 79 of 156 Table 1.1 (Page 2 of 4)
RADICACTIVE CASIOUS WASTE MONITORING SA"JLING Ah'D ANALYSIS PROGRAM Caseous Minimum Type of Lower Limit of Release Sanpling Analysis Activity Detection -LLD Type frequency Trequency Analysis (pC1/ml)*
D. Zodine and W'
1-131 1x10
Farticulates Continuous' Charcoal Sanpler Sample
- 1. Auxiliary W'
Principal 1x10*
Building Continuous' Particulate Canrna 1.xha us t Sampler Sample Emitters 8 (I-131
- 2. Shiald Others)
Building Lxhaust M
Gross Alpha 1x10"
Continuous' Coreposite Sampler Particulate Sanple Q
St-89 lx10
Continuous' Composite
$r-90 Sampler Particulate Sarople T. Noble Cases Continuous' Noble cas Noble cases 1x10
$M all Release Monitor Monitor Gross Beta types as or Camma listed in C l
l Refortnatting/ Repagination changes only D1461
)
'J e
.(
Dl.-l$Q ~h h0lh.h?Q;.
...Q L x Ju k ff$) "',f l i. W : p Qi&h H:
e SQN ODCM Revision 26 l' age 80 of 156 Table '.1 (Page 3 of 4) kAD!0 ACTIVE CASLOUS WASTE MONGOP.!N;, SAMPLING AND ANALYSIS PROGAAM TABLE NOTATION P = Completed prior to each release.
D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = At least once per 31 days W = At least once per 7 days Q = At least once per 92 days a The LLD is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count above system background that will be detected with 95% probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical R24 separation):
4.66s.
LLD =
E V
2.22x10' Y
exp (-K At)
We re t LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume,
- s. is the standard deviation of the background counting rate or of the counting rate of a blank saniple as appropriate (as counts per g
minute),
E is the counting efficiency as counts per disintegration, V is the sample sise in units of mass or volume, 2.22x10' is tha nustber of disinterrations per minute per microcurie, Y is the tractional radiochemical yield (when applicable),
K is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and-time of counting (aldpoint).
It should be noted that the LLD is defined as an a priori (before the f act) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement.
b Sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 15% of RATED THERMAL R24 P0kT.R within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unless (1) analysis shows that the DOSE R24 EQU1 VALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3 and (2) the containment noble gas R24 activity monitor (RE-90-106 or RE-90-112) shows that the radioactivity has not increased by more than a factor of 3.
. i,s..:.
keformatting/ Repagination changes only
)
01461 a
a MhNk b
ihlb
-';
- M Y Je b ' + 6-
$"* 4 M hU4 I
E@
/
SQN ODCM Revision 24 Page 81 of 156 Table 1.1 (Page 4 of 4)
RAb!0 ACTIVE CASE 0VS WASTE MONITORING SAMPLING AND ANA1.YSIS PROGRAM TABLE NOTAtl0N c Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
4 Samples shall be changed at least once per 7 days and ana!.yses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> af ter changing (or af ter removal f rom sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 2 days following each shutdown from 115% RATED R24 THERMAL POWER. startup of 115% RATED THERMAL POWER or THERMAL POWER R24 change exceeding 15% of RATED THERMAL POWER in one hour and analyses R24 shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analysed, the corresponding LLD's may be increased by a factor of 10.
e Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
f The ratio of the sarnple flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 1.2,1.4, and 1.5.
g The principal ganrna emitters for which the LLD specification applies exclusively are the following radionuclides Kr-87. Kr-88, Xe-133 Xe-133m. Xe-135, and Xe-138 f or noble gases and Mn-54, re-59,1-131 Co-58. Co-60. In-65. Mo-99, Cs-134, Cs-137. Ce-141 and Ce-144 for particulate principal gasena emitters. This list does not mean that only these nuclides are to be detected and reported. Other ganrr.a peaks which are measurable and identifiable, together with the above nuclides, shall also be analysed and reported in the Semi-annual Radioactive Ef fluent Release Report pursuant to Section 5.2.
h During releases via this exhaust system.
1 PURGING - Applicable in MODES 1, 2, 3 and 4. the upper and lower R24 compartments of the containment shall be sampled prior to PURGING.
R24 Prior to breaking containment ihtegrity in MODE 5 or 6 the upper R24 and lower compartments of the containment shall be sampled. The incore instrument room purge sample shall be obtained at the shield building exhaust between 20 and 25 minutes following initiation of the incore instrument room PURGE.
R24 j VENTING - Applicable in MODES 1, 2, 3, and 41 the containment will R24 be VENTED to the containment annulus and then to the auxiliary R24 building via containment annulus fans. The lower containment compartment shall be sampled daily when VENTING-is to occur to R24 account for the radioactivity being discharged from the VENTING R24 proceas.
,~.:-
Reformatting / Repagination changes only 01461 l
)
s t
- W hhh Mh Yk ' ;< i V '". <
~O L $ hY.
h*y$
?'*.
SQN ODCM Revision 24 Page 82 of 156 Table 1.2 (1 of ?)
JOINT PERCf.NTAGE IREQtlENCIES OF WIND DIRECTION AND WIND SPEED TOR DIFFERENT STABil.17Y C1. ASSES
- Sequoyah Nuclear Plant Meteorological Tacility*
Jan. 1. 72 - Dec. 31. 75 Stability Class A Delta T1-1.9 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm
_1.4
_ 3. 4 5.4 7.4 12.4 18.4 24.6 124.5 Total N
0.01 0.01 0.01 0.03 0.04 0.04 0.0 0.0 0.0 0.13 NNE 0.0 0.0 0.04 0.19 0.20 0.16 0.01 0.0 0.0 0.60 NE 0.0 0.0 0.08 0.20 0.15 0.13 0.0 0.0 0.0 0.56 LNE 0.0 0.0 0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.07 E
0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.0 0.0 0.03 SE 0.0 0.0 0.01 0.02 0.0 0.0 0.0 0.0 0.0 0.03 SSE 0.0 0.0 0.01 0.03 0.02 0.02 0.01 0.0 0.0 0.09 5
0.0 0.0 0.01 0.04 0.06 0.05 0.01 0.0 0.0 0.17 SSW 0.0 0.0 0.01 0.09 0.18 0.16 0.01 0.0 0.0 0.45 SW 0.0 0.0 0.04 0.12 0.10 0.09 0.02' O.0 0.0 0.37 WSW 0.0 0.0 0.02 0.03 0.03 0.02 0.02
'0.0 0.0 0.12 W
0.0 0.0 0.01 0.0 0.01 0.02 0.0 0.0 0.0 0.04 WIN 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.02 NW 0.0 0.0 0.01 0.01 0.01 0.05 0.01 0.0 0.0 0.09 M,.. a N!N 0.0 0.0 0.01 0.0 0.02 0.08 0.01 0.0 0.0 0.12 Sub-total 0.01 0.01 0.31 0.80 0.83 0.83 0.12 0.0 0.0 2.90
-958-stab 111ty class A occurrences out of total 32723 valid temperature difference readings.
934 valid wind direction /vind speed readings out of total 958 stability class A occurrences.
All columns and calm total 100 percent of net valid readings
- Meteorological Facility located 0.74 miles SW of Sequoyah Nuclesr Plant.
Temperature Instrweents 33 and 150 feet above ground.:
Wind instruments 33 ieet above ground.
},.:.
Reformatting / Repagination changes only 01461 y... ::
$N $b % 2 5,$ W h(A,%%
.a
+~
s%:r n&Mht&$$h8%k!V@kWfN$
c:
SQN ODCM Revision 24 Page 83 of 156 Table 1.2 (2 of 7)
JOINT PERCENTACE TREQUENCIES OF WIND DikECTION AND WIND SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological racility*
Jan. 1, 72 - Dec. 31, 75 Stability Class B
-1.9 < delta 71-1.7 deg. C/100m Wind Speed (eph) 0.6-1.5-3.5-
- 1. *-
7.$-
12.5-18.5-Calm 1.4 3.4
- 5.4
_7..
12.4 18.4 24.4
>26.5 Total N
0.0 0.0 0.01 0.01 0.02 0.03 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.23 0.20 0.18 0.01 0.0 0.0 0.67 NE 0.01 0.0 0.08 0.29 0.09 0.06 0.0 0.0 0.0 0.52 ENE 0.0
' 0. 0 0.03 0.03 0.01 0.0 0.0 0.0 0.0-0.07 E
0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.03 ESE 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 SE 0.0 0.0 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.0L SSE 0.0 0.0 0.01 0.03 0.0 0.02 0.0 0.0 0.0 0.06 5
0.0 0.0 0.03 0.03 0.07 0.04 0.01 0.0 0.0 0.18 SSW 0.0 0.0 0.04
-0.09 0.20 0.20 0.03 0.0 0.0 0.56 SW 0.0 0.0 0.03 0.11 0.14 0.10 0.02 0.0 0.0 0.40 WSW 0.0 0.0 0.01 0.01 0.03 0.02 0.01 0.01 0.0 0.09 W
0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.02 VNW 0.0 0.0 0.0 0.01 0.01-0.03 0.0 0.0 0.0 -
0.05 NW 0.0 0.0 0.0 0.0 0.01 0.05 0.0 0.0 0.0 0.06 NNW 0.0 0.0 0.01 0.02 0.02 0.06 0.01 0.0 0.0 0.12 Q
Sub-TOTAL 0.01 0.0 0.33 0.90 0.81 0.81 0.09 0.01 0.0 2.95 969 stability class B occurrences out of total 32723 valid temperature difference _ readings.
953 valid wind direction / wind speed readings out of total 969 stability class B occurrences.
4 All columns and calm total'100 percent of not valid readings.
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
Reformatting / Repagination changes only (y0 01461
-]
s
[R Ie g;jnSik '
n.
W a W W M;$ @M M1 % ea m w m *- w d E@NNhU $ W f N '
SQN ODOM Revision 24 Page 84 of 156 Table 1.2 (3 of 7)
J0!NT PERCENTACE TREQUENCIES OF WIND If!RECTION AND WIhT SPEED TOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological Facility
- Jan.1, 72 - Dec. 31, 75 Stability Class C
-1.7 < delta T1-1.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm
.1.4 3.4 5.4 7.4 12.4 18.4, 24.4
> 24. 5 _ Total N
0.0 0.0 0.01 0.02 0.02 0.02 0.0 0.0 0.0 0.07 NNE 0.0 0.0 0.05 0.12 0.11 0.11 0.0 0.0 0.0 0.39 NE 0.0 0.0 0.05 0.14 0.05 0.03 0.0 0.0 0.0 0.27 ENE 0.0 0.0 0.03 0.02 0.0 0.0 0.0 0.0 0.0 0.05 T
0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0
- 0.02 ESE 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.02 SE 0.0 0.0 0.01 0.01 0.0-0.0-0.0 0.0-0.0 0.02 SSE 0.0 0.0 0.01 0.02 0.0 0.02 0.0 0.0 0.0 0.05 5-0.0 0.0 0.03 0.04 0.06 0.05 0.0 0.0 0.0 0.18 SSW 0.0 0.0 0.01 0.11 0.14 0.13 0.02 0.0 0.0 0.41 SW 0.0 0.0 0.03 0.08 0.12 0.07 0.01 0.0 0.0 0.31 WSW 0.0 0.0 0.01 0.02 0.03 0.02 0.0 0.01 0.0 0.08 W
0.0 0.0 0.0 0.01 0.0 0.01 0.01 0.0 0.0 0.03 WNW 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 0.0 0.03 NW 0.0 0.0 0.0 0.0 0.02 0.03 0.01 0.0 0.0 0.06 999P1 NNW 0.0 0.0 0.0 0.02 0.02 0.05 0.0 0.0 0.0 0.09 SUB-TOTAL 0.0 0.0 0.26 0.64 0.58 0.55 0.05 0.0 0.0 2.0B N
684 stability class C occurrences out of total 32723 valid temperature di!!erence readings.
672 valid wind direction / wind speed readings out of total 684 stability class C occurrences.
All columns and calm total 100 percent of net valid readings.
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 100 feet above ground.
Wind instruments 33 feet above ground.
.'M Reformatting / Repagination changes only 01461 ll S
cg M
S q
N@y3fdddN M M M h& mc.d $3Mw:NMsh hhd[$ M 1$$$Mi 4
i SQN ODCH Revision 24 Page 85 of 156 Table 1.2 (4 of 7)
JOINT PERCENTA':.E TREQUf,NCIES OF WIND DIRECTION AND WIND SPEED FOR DITTERENT STABILITY CLASSES
- Sequoyah Nuclear Plant Meteorological racility*
Jan.1, 72 - Dec. 31, 75 stability Class D l
-1.5 < delta Ti-0.5 deg. C/100m Wind Speed (sph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4 12.4 18.4 24.4
>24.5 Iotal N
0.003 0.01 0.24 0.22 0.16 0.17 0.0 0.0 0.0 0.80 NNE 0.017 0.06 0.73 1.03 0.84 0.78 0.07 0.0-0.0 3.51 NE 0.006 0.02 0.76 0.88 0.42 0.42 0.05 0.0 0.0 2.55 ENE 0.003 0.01 0.21 0.11 0.03 0.0 0.0 0.0 0.0 0.36 E
0.003 0.01 0.12 0.03 0.02 0.01 0.0 0.0 0.0 0.19 ESE 0.003 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.0 0.09 SE 0.0 0.0 0.12 0.08 0.0 0.0 0.0 0.0 0.0 0.20 SSE 0.0 0.0 0.15 0.15 0.05 0.06 0.01 0.01 0.0 0.43 S
0.003 0.01 0.31 0.53 0.38 0.25 0.02 0.0 0.0 1.50 SSW 0.003 0.01 0.44 1.25 0.95 0.70 0.07 0.0 0.0 3.42 SW 0.003 0.01 0.47 1.17 1.03 0.52 0.03 0.01 0.0 3.24 WSW 0.0 0.0 0.22 0.34 0.18 0.21 0.07 0.01 0.0 1.03 W
0.003 0.01 0.06 0.08 0.10 0.19 0.02 0.01 0.0 0.47 WNW 0.003 0.01 0.06 0.05 0.11 0.18 0.01 0.0 0.0 0.42 NW 0.0 0.0 0.08 0.08 0.22 0.31 0.03 0.0 0.0 0.72 ggggy NNW 0.003 0.01 0.15 0.14 0.25 0.36 0.02 0.0 0.0 0.93 TOT ' '. 0.05 0.18 4.18 6.16 4.74 4.16 0.40 0.04 0.0 19.86 6567 stability class D occurrences out of total 32723 valid temperature P
difference readings.
6345 valid wind direction / wind speed readings out of total 6567 stability class D occurrences.
All columns and calm total 100 percent of net valid readings. =
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.
Wind instruments 33 feet above ground.
,t
. Reformatting / Repagination changes only 01461 f
y 7
s' n-dNb.%)
M. M N # 5
'F [id 50NkldhIm MyIdMMNkY)fkh$k Mi%dic3.o 9
5
~ _ _
~ _ _ _. _
SQN ODCol Revision 24 Page Bb of 156 Table 1.2 (5 of 7)
JOINT PERCENTACE TREQUENCIES nr WIND DIRECTION AND WIND SPEED FOR DITTERENT STAB 11,lTY C1. ASSES
- Sequoyah Nucleat Plant Meteorological Facility
- 4 Jan. 1. 72 - Dec. 31, 75 i
Stability Class E
-0.5 < delta T1 1.5 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-7.5-12.5-18.5-Eatm.
- 1. 4_
3.4
.}.4 7.4 12.4 18.4 24.4
>24.5_
Iotal s
N 0.017 0.23 1.26 0.83 0.39 0.27 0.0 0.0 0.0 2.98 NNE 0.023 0.31 2.83 2.46-1.07 0.92 0.03 0.0 0.0 7.62 NE 0.011 0.15 1.03 0.71 0.31 0.18 0.01 0.0 0.0 2.39 ENE 0.009 0.12 0.48 0.16 0.04 0.0 0.0 0.0 0.0 0.80 E
0.010 0.14 0.24 0.05 0.01 0.01 0.0 0.0 0.0 0.45 ESE 0.007 0.09-0.11 0.01 0.01 0.01 0.01 0.0 0.0 0.24 SE 0.007 0.10 0.37 0.06 0.01 0.01 0.0 0.0 0.0 0.55 6SE 0.008 0.11 0.58 0.24 0.13 0.23 0.04 0.02 0.0 1.35 6
0.013 0.17 1.33 1.49 0.91 1.05 0.08 0.0 0.0 5.03 S$W 0.007 0.10 1.67 2.32 1.67 1.45 0.11 0.0 0.0 7.32 SW 0.013 0.17 1.59 2.07 1.30 0.99 0.10 0.0 0.0 6.22 WSW 0.010 0.13 0.87 0.55 0.35 0.40 0.06 0.0 0.0 2.36 W
0.007 0.10 0.42 0.28 0.21 0.22 0.03 0.0 0.0 1.26 WNW 0.010 0.14 0.37 0.22 0.19 0.2?
0.02 0.0 0.0 1.21 gl WW 0.007 0.10 0.50 0.37 0.43 0.38 0.02 0.0 0.0 1.80 NNW 0.011 0.15 0.80 0.68 0.57 0.40 0.01 0.0 0.0 2.61 Sub-total 0.17 2.31 14.45. 12.50 7.60 6.79 0.52 0.02 0.0 44.19 l
14624 stability class E occurrences out of total 32723 valid temperature difference readings.
1414b valid wind direction / wind speed readings out of total 14624 stability class E occurrences.
All columns and calm total 100 percent of net valid readings.
- Meteorological facility located 0.74 alles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 knd 150 feet al.ove ground.
Wind instruments 33 feet above ground.
Reformatting / Repagination changes only 01461
)
s I.
x =: ; @p i c,
a hW NINh?/C N Nihkih7)/NM'bk M M 'bNP"bM$
NNbh
$iN
O O
SQN ODCM Revision 24 Page 87 of 156 Table 1.2 (6 of *)
JOINT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND WIND SPEED TOR DITTERENT STABILITY CALSSES*
Sequoyah Nuclear Plant Meteorological Facilitv*
Jan. 1, 12 - Dec. 31, 75 Stability Class T 1.5 < detta 71 4.0 deg. C/100m Wind Speed (mph) 0.6-1.5-3.5-5.5-1.5-12.5-18.5-Cale
. 1. 4
_3.4
__ 5. 4 7.4 12.4 18.4 24.4 - 124.5_ Total N
0.011 0.21 1.37 0.44 0.04 0.0-0.0 0.0 0.0 2.06 NNE 0.018 0.35 3.61 0.84 0.05 0.0 0.0 0.0 0.0 4.85 NE 0.011' O.21 1.15 0.28 0.01 0.0 0.0 0.0 0.0 1.65 ENE 0.006 0.16 0.39 0.03 0.0 0.0 0.0 0.0 0.0 0.58 E
0.010 0.20 0.22 0.0 0.0 0.0 0.0 0.0 0.0 0.42 ESE 0.007 0.13 0.18 0.02 0.0 0.0 0.0 0.0 0.0 0.33 SE 0.007 0.14 0.23 0.02 0.0 0.0 0.0 0.0 0.0 0.39 SSE 0.008 0.15 0.37 0.07 0.03 0.01 0.0 0.0 0.0 0.63 S
0.009 0.17 0.77 0.30 0.10 0.06 0.0 0.0
-0.0 1.40 SSV 0.006 0.12 1.13 0.71 0.26 0.11 0.0 0.0 0.0 2.33 SW 0.005 0.10 0.99 0.86 0.27 0.13 0.0 0.0 0.0 2<35
^^
WSW 0.005 0.09 0.46 0.19 0.04 0.01 0.0 0.0 0.0 0.79 W
0.004 0.07 0.20 0.07 0.01 0.0 0.0 0.0 0.0 0.35 WNW 0.005 0.10 0.24 0.07 0.01 0.0 0.0 0.0 0.0 0.42 NW 0.003 0.05 0.29 0.15 0.05 0.01 0.0 0.0 0.0 0.55 W
NNW 0.005 0.09 0.52 0.34 0.05 0.01 0.0 0.0 0.0 1.01 SM-TOTAL 0.12 2.34 12.12 4.39 0.92 0.34 0.0 0.0 0.0 20.11 6542 stability class T occurrences out of total 32723 valid temperature difference readings.
6461 valid wind direction / wind speed readings out of total 6542 stability class T occurrences.
All columns and calm total 100 percent of not valid readings.
- Meteorological facility located 0.74 miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and 150 feet above ground.-
Wind instruments 33 feet above ground.
.M Reformatting / Repagination changes only 01461 4
4
,8
- 'k
-Q
_l 6
hiM $ &$, & 5;N.$ffffOkn#5:4.;;&yqwyh5L& Q Qk & hiQG$45'
,g_
g
$QN ODCM Revision 24 I
Table 1.2 (7 of 7)
JOINT PERCENTAGE TREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFTERENT STAB 11,ITY CLASSES
- Sequoyah Nuclear Plant Meteorological Facility
- l Jan. 1, 72 - Dec. 31, 75 Stability Class C Delta 7 > 4.0 deg. C/100m Wind Speed (mph)
O.6-1.5-3.5-5.5-7.5-12.5-18.5-Calm 1.4 3.4 5.4 7.4-12.4 18.4 24.4 f,24.5 Total N
0.003 0.06 0.33 0.09 0.0 0.0 0.0 0.0 0.0 0.48 NNE 0.005 0.10 1.03 0.20 0.0 0.0 0.0 0.0 0.0 1.33 NE 0.005 0.09 0.74 0.12 0.0 0.0 0.0 0.0 0.0 0.95 LNE 0.007 0.13 0.42 0.02 0.0 0.0 0.0 0.0 0.0 0.57 E
0.007 0.14 0.18 0.01 0.0 0.0 0.0 0.0 0.0 0.33 ESE 0.006 0.11 0.08 0.01 0.0' O.0 0.0 0.0 0.0 0.20 SE 0.005 0.09 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.17 SSE 0.008 0.16 0.21 0.0 0.01 0.0 0.0 0.0 0.0 0.37 5
0.006 0.11 0.39 0.04 0.02
-0.0 0.0 0.0 0.0 0.55
$$W 0.003 0.06 0.48 0.32 0.06 0.01 0.0 0.0 0.0 0.89
$W 0.002 0.03 0.44 0.42 0.0 0.0 0.0 0.0 0.0 0.95 WSW 0.001 0.01 0.11 0.07 0.0 0.0 0.0 0.0 0.0 0.19 W
0.002 0.03 0.08 0.02 0.0 0.0 0.0 0.0 0.0 0.13 WNW 0.001 0.01 0.03 0.01 0.0 0.01 0.0 0.0 0.0 0.06 NW 0.001 0.02 0.06 0.03 0.0 0.0 0.0 0.0 0.0 0.11
'Q NNW 0.001 0.02 0.08 0.03 0.0 0.0 0.0 0.0 0.0 0.13 SUB-TOTAL 0.06 1.17 4.74 1.39 0.09 0.2.
- 0. 0 -
0.0 0.0 7.41 2379 stability class C occurrences out of total 32723 valid temperature di!Icrence readings.
l 2378 valid wind direction / wind speed readings out of total 2379 stability class C occurrences.
f All colunos and calm total 100 percent of net valid readings.
- Meteorological f acility located 0.74 Miles SW of Sequoyah Nuclear Plant.
Temperature instruments 33 and.150 fe'et above ground.
Wind instruments 33 feet above ground.
M L
Reformatting / Repagination changes only 01461 l
E F
k _
,3-
,q',_
SQN ODCM Revision 24 Page 89 of 156 Table 1.3 SQN - OTTSITE RECEPTOR LOCATION DATA DISTANCE X/Q D/Q P01NT from plant (s/m')
(1/m )
8 (m)
Site Boundary N
950 5.12E-06 1.29E-08 Site Boundary NNE 2260 1.93E-06 5.2BE-09 Site boundary NE 1910
- 2. 32E-06 6.33E-09 Site boundary ENE 1680 1.12E-06 2.64E-09 Site Boundary E
1570 7.10E-07 1.46E-09 Site Boundary ESE 1460 7.91E-07 1.5BE-09 Site boundary St
'460 9.14E-07 2.41E-09 Site Boundary SSE 1550 1.34E-06 3.23E-09 Site boundary 5
1570 2.37E-06 4.18E-09 Site Boundary SSW 1840 4.51E-06 9.26E-09 Site Boundary SW 2470 1.3BE-06 2.63E-09 Site Boundary WSW 910 2.93E-06 3.86E-09 Site boundary W
670 3.63E-06 3.74E-09 Site Boundary WNW 660 2.49E-06 2.44E-09 Site boundary NW 660 2.85E-06 3.67E-09 Site Boundary NNW 730 3.95E-06 6.59E-09 Liquid Discharge S
870 N/A N/A NOTE For quarterly airborne dose calculations, doses will also be calculated f or all locationa identified in the most recent land use census, and for any additional points deemed necessary.
itMy
~*
Reformatting / Repagination changes only 01461 p
w.,
- ~~'g^, )
h2I[
d(
". a.k
.hh0N N
- # *e
. U ft
/
l Irk
SQN ODCM Revision 24 Page 90 of 156 Table 1.4 DOSE TACTORS FOR SUBKEPSION IN NOBLE CATES Submersion dose Air dose aremlyr per pci/m' arad/y per pC1/m' DFBi DFB.
DFyi DTai Kr-83m 7.56E-02 1.93E+01 2.8BE+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06t+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01-4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.96t+02 3.06E+02 3.53E+02 1.0$E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03
.- m M
Xe-137 1.42E+03 1.22E+04 1.51E+03
-1.27E+04 Xe-138' 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.8LE+03 2.69E+03 9.30E+03 3.28E+03
Reference:
Regulatory Guide 1.109. Table B 1.
. {s :.
Reformatting / Repagination changes only sc 01461 g,'
yt 9 7, ;- -
gE s..~
Ah $, 44 6 M",12 j;j 's_ ** *b{hb.f c
h V
Sk $t.',N7WEM A @#U5h4dd Nr b
SON ODCM Hovlalon 25 Page 91 of 156 Table 1.5 (Page 1 of 2)
RADICACTIVF GASICOUS ErrLUENT MONITORING IllSTRUMENTATIOtt Minimum Channela Applic-Instrwnent OPEl%1%E p.bility Action 1.
WASTI: CAS DISPOSAL SYSTEM a.
Noble Gan Activity Monitor 1
40 b.
1:1 fluent System TJow Rate Monsuring Devico 1
41 2.
CONDENSER VACITUM EXIIAUST SYSTEM Noble Gas Activity Monitor 1
42 n.
b.
Flow Hate Monitor 1
41 3.
SilII:LD BUILDING EXIIAUST SYSTEM e
a.
Hoble Gas Activity Monitor 1
42 b.
lodine Sampler 1
44 c.
Particulate Sampler 1
44 d.
Flow kato Monitor 1
41 e.
Sampler flow kate Monitor 1
41 4.
AUXILIARY llUILDING VENTILATION SYSTEM a.
Noble Gas Activity Monitor 1
42 b.
Iodine Sampler 1
44 Particulate Sampler c.
1 44 d.
Flow Rate Monitor 1
41 e.
Sampler Flow Rato Monitor 1
41 5.
SEkVICE DUILDING VT:NTILATION SYST!:M R25 n.
Hoble Gas Activity Monitor 1
42 h.
Flow Rate Monitor 1
41 01461 1
4
o SQN ODCM Revision 24 Page 92 of 15$
Table 1.5 (Page 2 of 2)
RADICACTIVE CASEOUS ETTLUENT MONITORING INSTRUMLNTATION TABLE NOTATION R24 At all times.
R24 During shield building exhaust system operation.
ACTION 40 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, the contents of R24 the tank (s) may be released to the environment provided that prior to initiatirg the releases
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 41 - With the number of _ channels OPERABLE less than required by R24 the Minircum Channels OPERABLE requirement, elfluent R24 releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 42 - With the number of channels OPERABLE less than required by R24
.M,,
the Minimum Channels OPERABLE requirement, offluent R24 releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analysed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 44 - With the number of channels OPERABLE less than required by R24 the Minimum Channels OPERABLE requirement, effluent R24 releases via the affected pathway may continue provided that within a hours after the channel has been declared inoperable samples arie continuously collected with auxiliary sampling equipment as required in Table 1.1.
.~.:.
Reformatting / Repagination changes only 014g,1
)
- m. sW :g:, ?
+~{ % f
. ~..
FN @ M M NM, N k M M w P % l% C % e M @ E M M M k M $nkhNh1
1 l
j SQH ODCM Revision 24 i
Pase 93 of 156 4
Table 1.6 (Page 1 of 2)
RADIDACTIVE CASEOUS EFTLUENT MONITORING INSTRUMENTATION SURVE!*. LANCE RtQUIREMENTS MODES CHANNEL in which CHANNLL n~NC-surveil.
1 CRANNEL SOURCE CALIBRA-TIONAL lance Instrument EHECK CHECK T!ON TEST Required i
- 1. WASTE CAS DISPOSAL SYSTEM
- a. Noble ces Activity Monitor P
P R(3)
Q(1)
- b. Tiow Rate Monitor D
N.A.
R Q
- 2. CONDENSER VACUUM EXHAUST SYSTEM l
- a. Noble cas Activity Monitor D
M R(3)
Q(2)
- b. Flow Rate Monitor D
N.A.
R Q
a
- 3. SHIELD BUILDING EXHAUST SYSTEM
- a. Noble Gas Activity Monitor D
M.
R(3)
Q(2)
- b. todine Sampler W
N.A.
N. A. -
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. T)ow Rate Monitor D
N.A.
R Q
- e. Sarnpler Flow Rate Monitor D
N.A.
R Q
- 4. AUXILIARY BUILDING VENTILATION SYSTEM
- a. Noble Gas Activity Monitor D
M R(3)
Q(2)
- b. lodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler _
W W.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q.
- 5. SERVICE BUILDING VENTILATION SYSTEM i-
- a. Noble cas Activity Monitor. D M
R(3)
.Q(2)
- b. Flow Rate Monitor '
D N.A.
R Q
~)
r 1
.% 4 Reformatting / Repagination changes only 01461-
,?
e.
=o;
'f'
- Eff V-O r E ':
N t'N 6
+
?
T
- SON ODCM Revision 24 Page 94 of 156 I
Table 1.6 (Fage 2 of 2)
RADIDACTIVE CASEOUS ETTLUENT HONITORING INSTRUMENTATION SURVE1LLANCE REQUIREMENTS TABLE NOTATION l
l P = Completed prior to each release R = At least once per 18 months Q = At lease once per 92 days D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per 31 days At all times.
R24 During shield building exhaust system operation.
During waste gas releases.
(1) The CHANNEL TUNCT10NAL TEST shall also demonstrate that automatic R24 isolation of this pathway and control room alarm ant.unciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(2) The CHAVNEL TUNCTION TEST shall also demonstrate that control room R24 alarm annunciation occurs if any of the following conditions 1xists:
- 1. Instrument indicates measured levels above the alarm setpoint.
M
- 2. Circuit failure.
i
- 3. Downseale failure.
l Tor the auxiliary building ventilation system, at least once every 18 months, the CHANNEL FUNCTIONAL TEST shall also demonstrate R24 automatic isolation of this pathway if the following condition exists:
Instrument indicates measured levels above the alarm / trip setpoint.
(3) The initial CHANNEL CALIBRATION shall be performed using one or R24 more of the reference standards certified by the National Bureau of Standards or using standards that have,been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CRANNEL CALIBRATION, sources that have been related to R24 the initial calibration shall be used.
R24 l
R24 R24 R24
%?
Pefornatting/ Repagination changes only 01461 m
- l %,
N5 neb 550'k hhh6
' C, 4 y iM e W@Nd.
[$NNO4 m4,..h*
4
O SQN ODCM Revision 24 Page 95 of 156 Table 1.7 SECTOR ELEMEhTS CONSIDERED TOR FOPU11. TION DOSES Range of Midpoint of Sector Element Sector Element Site boundary - 1 mile 0.8 mile 1-2 alles 1.5 miles 2-3 miles 2.5 miles 3-4 miles 3.5 miles 4-5 miles 4.5 miles 5 - 10 miles 7.5 miles 10 - 20 miles 15 miles 20 - 30 miles 25 miles 30 - 40 miles 35 miles 40 - 50 miles 45 miles Y@W I
1 l
l i
i
(
.e Reformatting / Repagination changes only 01461 l
t I /1
[
66 l', N. ),0 -
[d[$,([ [d9$$k d*,h,h,kl.N.,: e ". '.." ", g4,4. ' '$.. ' j.y(p pitef th,.' )
$xh.~/fg?,h,t f _
~
SQN ODCM Revision 24 Page 96 of 156 Table 1.8 POPULATION WITHIN EACH SECTOR ELEP.ENT Sector Midpoint (miles) 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N
20 41 213 129 66 1784 5453 3470 2610 11145 NNE O
30 123 182 62 600 10628 4910 8250 1062$
NE O
O 67 67 94 581 2884 6998 7047 18080 IJ4E O
11 24 222 300 773 4707 5747 29477 18679 E
O 70 11 191 137 918 17440 6808 5072 4129 ESE O
118 113 194 137 1849 46521 5044 1896 13624 SE O
179 322 168 205 1507 6005 5461 15641 3417
$$E O
125
,,0 750 601 2347 13242 8596 34279 11648 5
0 67 143 229 811 3930 28008 26690 19642 11622 55W 0
82 140 400 170 8927 96966 55597 21349 11978 SW 0
10 306 634 194 9787 94225 23455 11641 11109 VSW 20 190 642 1124 1669 19089 28405 4106 15081 9548 W
10 20 233 657 657 5225 1580 6350 5699 7707 WNW 10 30 365 598 598 2622 6540 4920 6699 2450 l
NW 50 80 292 569 336 2696 1410 1750 1217 15856 NNW 10 263 80 75, 213 1610 471 3130 2835 5719 l
l
. ~=e Reformatting / Repagination changes only 01461 w
4s :;f
$$$hb$55.Y$h kk&$*? : &G'*-[%.?.m :'nW~$Y'E E $$
S$$' BYE $
1:
SQN ODvM Revision 24 Page 97 of 156 Table 1.9 (1 of 8)
INCESTION DOSE EACTORS (arem/pCi ingested)
ADULT l
bone liver t body
' thyroid kidney lung gi-111 I
H-3 1.05E-07 i.05E-07 1.05E-07 1.0$E-07 1.0$E-07 1.05E-07 1.0$t-07 C-14 2.84E-06 3.68E-07 l 5.6BE-07 5.6BE-07 5.6BE-07 5 6BE-07 5.68E-07 3
Na-24 1.70E-06 fl.70E-06 l 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04l1.20E-05 7.46E-06 0.00E 00 0.00L+00 0.00E+00 2.17E-05 0.00t+0010.00E+00{8.72E-07 Cr-51 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 0.00E+00 l4.57E 0.00E+00 1.36E-06 0.00E+00 1.40E-05 Hn-54 Mn-56 0.00E+00 i 1.15E-07 2.04E-08,0.00E+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 ' 1.90E-06 ; 4.43E-07 ' O.00E+00 0.00E+00 1.06E-06 1.09E-06 re-59 4.34E-06 ; 1.02E-05 ; 3.91E-06 0.00E+00 0.00E+00 2.BSE-06 3.40E-05 Co-57 0.00E+00i1.75E-07\\2.91E-07 0.00E+00 0.00E+00 0.00E400 4.44E-06 Co-58 0.00E+00 - 7.450-07 l1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 Co-60 0.00E400 2.14E-06_j a.12E-06 l 4.00E*00 0.00E+00 0.00E+00 4.02E-05 N1-63' ~~ 1.30E-04 9.01E-06 4.36E-06
. +00 0.00E400 0.00E+00 1.8BE-06 Ni-65 5.2BE-07 6.86E-08 5.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 Co-64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84t-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 In-69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-08 0.00E+00 2.47E-07 0.00E+00 2.49E-05 Er-82 0.00E+00 0.00E+00 2.26E-06 0.00E+00 0.00E+00 0.00E+00 2.59E-06 Br-83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 Br-84 0.00E+00 0.00E+00 a.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 Br-85 0.00E*00 0.00E+00 2.14E-09 0.00E+00 0.00E*00 0.00E+00 0.00E+00 gp3q*q Rb-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 Rb-89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E*00 2.33E-21
$r-89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04
$r-91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y-90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91n 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.7'7E-09 0.00E+00 0.00E+03 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.6BE-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E400 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 0.00E+00 1.54E-11 0.00E400 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 0.00E+00 7.97E-08 0.00E+00 7.06E-07 0.00E+00 2.16E-05 Ru-105 1.54E-08 0.00E+00 6.0BE-09 0.00E+00 1.99E-07 0.00E+00 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 0.00E+00 6.04E-05
..Sb-124 2.80E-06 5.29E-08 1.11E-06 6.798-09 0.00E-00 2.18E-06 7.95E-05 Ref ormatting/ Repagination changes only 01461
- [
..),
/'.
w s 4 M M g2W M W -.
q a d L $ n'## n w h M A i
..m_.___
._ _ __ ~ _ _
e SON ODCM Revision 25 Page 98 of 156 Table 1.9 (2 of B) i INGESTION DOSE FACTORS (mren/pC1 Angested)
ADULT bone liver t body thyrold kidney lung 1
9 -111 Sh-125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.008-00 1.38E-06 1.97E-05 Sn-125 8.33E-06 1.68E-07 3.7bE-07 1.39E-07 0.00E-00 0 00E-00 1.04E-04 E25 7c-125m 2.68E-06 9.71E-07 3.59t-07 0.06E-07 1.09E-05 0.00t+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.00E400 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.40E-07 0.00C+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.00E-05 0,00E400 5.79E-05 70-129 3.14E-08 1.18E-0D 7.65E-09 2.41E-08 1.32E-07 0.00t+00 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-00 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.225-09 1.62E-08 8.63E-00 0.00E400 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E400 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 1-131 4.16E-06 b.95r-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57,0 06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.55E-07 0.00E+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.00E400 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-10 I-135 4.43E-07 1.16E-06 4.2BE-07 7.65E-05 1.86E-06 0.00E400 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 0.00E+00 4.79E-05 1.59E.05 2.59E-06 Ca-136 6.51E-06 2.57E-05 1.85E-05 0.00E400 1.43E-05 1.90E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.01E-08 7.91E-09 4.65E-13 i
gr.
Ba-139 9.70E-08 6.91E 11 2.84E-09 0.00E+00 6.46E-11 3.9"E-11 1.72E-07 Da-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4,18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 0.00E*C0 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E 1.34E-09 0.00E400 1.85E-11 1.24E-11 3.00E-26 La-140 t.50E-09 1.26E-09 3.33E-10 0.00E+00 0.00E+00 0.00E+00 9.25E-05 La-142. 28E-10 5.82E-11 1.45E-11 0.00E+00 0.00t+00 0.00E+00 4.25E-07 Ce-141 9 36E-09 6.33E-09 7.18E-10 0.00E+00 2.94E-09 0.00E400 2.42E-05 Co-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Co-144 4.88E-07 2.04E-07 2.62E-08 0.00E+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 0.00E+00 2.13E-09 0.00E+00' 4.03E-05 Pr-144 3.01E-11. 1.25E-11 1.53E-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 0.00E400 4.25E-09 0.00E400 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 0.00E+00 2.40E-05 Referencer.t Regulatory Guide 1.109,-Table E-11.
Dose Factors for Co-57. Zn-69m. Br-82, Nb-97, Sn-125. Sb-124 and R25 Sb-125 are f rom NUREG-0172 k2LSD.tA1.LiR Endiation Dose CommitrotnL.
EAC191LinL2._OntltALChLan i c I n t ak et, November, 1977, 7able 4..
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
01461
8
+
SQN ObCM Revision 24 Fage 99 of 156 l
Table 1.9 (3 of 8)
INCEST 10N ICSE EACTORE (arem/pCl ingested) 3 TEEN bone liver t body thyroid kidney lung 81-111 H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12t-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 F-32 2.76E 1. 71E45 1.0?E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 Cr-51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14Ec09 6.05t-07 Mn-54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-46 0.00E+00 1.21E-05 Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 Ee-55 3.78E-06 2.68E-06 6.25E-07 0.00E40 0.00E+00 1.70E-06 1.16t-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00t+00 4.32E-06 3.24t-05 i
Co-57 0.00E400 2.38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00t+00 3.66E-05 N1-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00- 0.00E+00 -0.00E+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00Ec00 5.19E-06 Cu-64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 2n-65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 In-69 1.47E-08 2.80E-08 1.96E-09 0.00E+00- 1.83E-08 0.00E+00 5 16E-08 In-69m 2.40E-07 5.66E-07 5.19E-08 0.00E400 3.44E-07 0.00E+00 3.11E-05 Br-82 0.00E+00 0.00E+00 3.04E-06 0.00E+00 0.00E+00- 0.00E+00 0.J0E+00 Br-83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B r-tie 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00L+00 0.00E+00 l
M.~.
Rb-86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 kb-88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-08 0.00E +00 0.00E+00 0.00E+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 3.24E-05
$r-90 8.30E-03 0.00E+00 7.05E-03 0.00E+00 0.00E+00 0.00E+00 '2.33E-04 Sr-91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E400 3.66E-05
$r-92 3.05E-06 0.00E+00 1.30E47 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y-90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 _0.00E+00 0.00E+00 8.24E-05
- Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E 08 0.00E+00 3.00E-05 2.r-9 7 2.3?E-09 4.690-10 2.16E-10 0.00r+00 7.11E-10 0.00E+00 1.27E-04 l
Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.3?E-11 1.83E-11 6.68E-12 0.00E+00 2.14E-11 0.00E+00 -4.37E-07 Mo-99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00. 1.08E-05 Te-99m 3.32E-10 9.26E-10 1.20E4R 0.00E+00- 1.38E-08' 5.14E-10 6.08E-07 l
Tc-101'
, 3.60E-10' 5.12E-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17~
ku-103 2.55E-07 0.00E+00.1.09E-07 0.00E+00 8.99E-07 0.00E+00- 2.13E-05 Ru-10$'
2.18E48' O.00E+00 - 8.46E-09 0.00E+00 2.75E47 0.00 b00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 0.00E+00 7.56E-06 0.00b00 1.88E-04 Ag-110m 2.05 E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.0M+00 5.45E-05
$b-124 3.87E-06 7.13E-08 1.51E-06 8.78J-09 0.00E-00 3.38E-06 7.80E-05
- Reformatting / Repagination changes only 01461 a
s e
r.
9
-3, d-A i,
Gnaw @;axi&%W.e w n swm46WsMwdMxy' ?d
.- _ _ _ _ _ ~. _. _ _ _ _ _
O SON ODCH Fevision 25 l'ago 100 of 156 Table 1.9 (4 of 8)
XHOESTION DOSE FACT 0106 1.15E-06 2.100-06 3.92E OL 0.00E+00 2.41E-05 70-127 1.5BE-07 L.601:-08 3.400-08 1.09E-07 6.40E-07 0.00E400 1.22E-05 Te-129m 1.63E-OL 6.05E-06 2.5BE-06 L.26E-06 6.822-0$ 0.00E+00 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.880-07 0.00E+00 2.4LE-07 Te-131m 2.440-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.00E+00 9.39E-05 Te-131 2.79E-08 1.1LE-08 8.72E-09 2.15E-08 1.22E-07 0.00E+00 2.29E-04 Te-132 3.49E-06 2.21E-06 2.00E-06 2.33E-06 2.12E-OL 0.00E+00 7.00E-05 1-130 1.03E-06 2.90E-06 1.19E-06 2.43E-04 4.59E-06 0.00E400 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.390-03 1.410-05 0.00E.00 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.1LC-06 0.00E400 3.18E-07 1-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 L.08E-06 0.00E400 2.L8E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.4LE-06 6.10E-07 0.00t+00 5.10E-09 I-135 6.10E-07 1.570 06 5.82E-07 1.01E-04 2.480 06 0.00E+00 1.74E-06 Cs-134 8.37E-Ob 1.97E-04 9.14E-05 0.00E400 6.26E-OL 2.39E-05 2.45E-06 Co-136 8.59E-06 3.38E-05 2.27E-05 0.00E400 1.84E-05 2.900-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E 00 5.07E-05 1.97E-05 2.12E-06 ts-138 7.76E-08 1.49E-07 7.45E-00 0.00E+00 1.10E-07 1.28E-08 6.76E-11
$wW Un-139 1.39E-07 9.78E-11 4.0bE-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 Ha-140 2.84E-05 3.48E-08 1.83E-06 0.000 00 1.18E-08 2.34E-08 4.380 05 ha-141 6.71E-08 5.01E-11 2.24E-09 0.00E400 4.65E-11 3.43E-11 1.43E-13 nn-142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99t-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 0.000 00 0.00E+00 0.00E400 9.82E-05 La-142 1.79E-10 7.95E-11 1.980-11 0.00E+00 0.00E+00 0.000+00 2.42E-06 Co-141 1.33E-08 8.880 09 1.02E-09 0.00E+00 4.18E-09 0.00E.00 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 0.00E+00 $.14E-05 Co-144 6.96E-07 2.88E-07 3.74E-08 0.00E400 1.72E-07 0.00E+00 1.75E-04 i
Pr-143 1.31E-08 5.230-09 6.52E-10 0.00E+00 3.04E 09 0.000+00 4.31E-05 Pr-144 4.300-11 1.76E-11 2.18E-12 0.00E+00 1.01E 11 0.00E400 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 0.00E400 5.99E-09 0.00E 00 3.68E-05 W-187 1.460-07 1.19E-07 4.17E-08 0.00E400 0.00E.00 0.00E+00 3.22E-05 Hp-239 1.76E-09 1.66E-10 9.22E-11 0.00E400 5.21E-10 0.00E+00 2.67E-05 Roferencest Regulatory Guido 1.109, Table E-12.
Doso rectors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are irom NUREG-0172 Age. Specific _RadlaucltlenLCormincA FACLQIA,.LQLA DDLIEDLChtOnlc lutakto November, 1977, Table 4.
NOTE: The tritium dose factor for bono is assumed to be equal to the total body dose iactor.
01461 I
b SQN ODCM Revision 24 Page 101 of 156 Table 1.9 (5 of 8)
INGESTION DOSE FACTORS (mrem /pCl ingested)
CHILD bone liver t body thyroid kidney lung gi-111 8-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Or-51 0.00E+00 0.00E+00 B.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 tb-54 0.00E+00 1.07E-05 2.85E-06 0.00E400 3.00E-06 0.00E+00 8.98E-06 Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.04E-07 0.00E+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1.13E-06 Te-59 1.65E-05 2 27E-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.93E-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.515-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co-60 0.00E+00 5.29E-06 1.56E-05 0.00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 0.00E400 0.00E+00 0.00E+00 1.94E-06 N1-65 2.22E-06 2.09E-07 1.22E-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.00E+00 2.45E-07 1.48E-07 0.00E+00 5.92E-07 0.00E400 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 0.00E+00 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 0.00T+00 3.84E-08 0.00E+00 3.99E-06 In-6C$
7.10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 0.00E+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.71E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-54 0.00E+00 0.00E+00 1.98E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 9.12E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 thNir Rb-86 0.00E400 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00
- 4. 31 E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 0.00E+00 0.00E+00 0.00E+00 9.32E-09 kb-89 0.00E+00 1.17E-07 1.04E-07 0.00E+00 0.00E+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 0.00E*00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29E-04
$r-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E400 5.30E-05 Er-92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E400 0.00E*00 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y-91m 3.82E-10 0.00E+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.&lE-08 0.00E+00 0.00E+00 0.00E+0D 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E 0.00E+00 0.00E+00 '0.00E+00 1.04E Y-93 1.14F-08 0.00E+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+0C 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97 2.17E-10 3.92E-11 1.83E-11 0.00E+00 4.35E-11 0.00E+00 1.21E-05 ho-99 0.00E+00 1.33E-05
- 3. 29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 Te-99m 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 ku-103 7.31E-07 0.00E +00 2.81E-07 0.00E+00 1.84E-06 0.00E+00 1.89E-05 Ru-105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.00E+00 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04 i
Ag-110m 5.39E-07
- 3. 64E-07 2.91E-07 -0.00E+00 6.78E-07 0,00E+00 4.33E-05 Sb-124 1.11E-05 1.44E-07 3.89E-06 2.45j-on n,00E+00 6.16E-06 6.94E-05
' Reformatting / Repagination changes only 01461 q)d@
C.YMlY5?Y&h,&$th,
~WG A
kbWTG3A h
M-.
~
+
SON ODCM hevision 25 Page 102 of 156 7able 1.9 (6 of 8)
INGESTION DOSE EACTORS (mrem /pci ingested)
CHILD bone liver t body Myroid kidney lung g1-111 Sb-125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05 Sn-125 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0.00E+00 0.00E+00 1.10E-05 R25 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.00E+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.44E-05 Te-129 1.24E-07 3.749-08 3.18E-08 9.56E-08 3.92E-07 0.00E400 B.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+0D 1.36E-07 Te-132 1.01E-05 4.47E-06 5.40E.06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 I-130
.?.92E-06 5.909-06 3.04E-06 6.50E-04 0.82E-06 0.00E+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-C3 2.84E-05 0.00E+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.0JE+00. 2.95E-06 1-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E 0.00E+00 5.16E-07 I-135 1.75E-0(
3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2. 3 r>E-0 5 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-05 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.52E-05 f.00E+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.012-07 0.00E+00 2.23E-07 2.$0E-08 1.46E-07
%WMFW Ba-139 4.14E-07 2.21E-10 1.20E-08 0.00E400 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 0.00E+00 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 ba-142 8.74E-08 6.29E-11 4,SBE-09 0.00 >00 5.09E-11 3.70E-11 1.14E-09 La-140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 -0.00E+00 0.00E+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23Eell 0.00E+00 0.00E+00 0.00E+00 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-(0 0.00E+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 0.00E+00.1.59E-09 0.00E+00 5.55E-05 Ce-144 2.08E-06 6.52E 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-09. 0.00E+00 6.39E-09 0.00E+00 4.24E-05 i
Pr-144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 i
Nd-147 2.79E-08 2.26E-08 1.75E-09 0.00E+00.1.24E-08 0.00E+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 _0.00E+00 0.00E+00 3.57E-05 Np-239 5.2SE-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 1
Referencess Regulatory Guide 1.109, Table E-13.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 l
Sb-125 are from NUREG-0172 Ag.e Specific Radiation Dolf Commitment _
Eastors for a One Year Chronic Intake,, November, 1977, Table 4.
NOTE: The tritium dose factor for bone is assumed to bc equal to the total body dose facter.
01461
~
SQN ODCM Revision 2h Page 103 of 156 Table 1.9 (7 of 8)
INGESTION DOSE FACTORS (arem/pci ingested)
INFANT bone liver t body thyroid kidney lung gi-111 B-3 3.0BE-07 3.08E-07 3.0SE-07 3.08E-07 3.0BE-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-05 5.06E-06 5.06 E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.bOE+00 0.00E+00 2.30E-05 Cr-51 C'.00E+00 0.00E+00 1.41E-08 9.20E-09 2.015-09 1.79E-0E 4.11E-07 Mn-54 0.s0E+00 1.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.1BE-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Ee-59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.0BE-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.0$E-05 Cu-64 0.00E+00 6.09E-07
- 2. 8 2E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 In-65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 2n-69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-OS 0.00E+00 1.37E-05 2n-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1.24E-06 0.00E+00 4.24E-05 Br-82 0.00E+00 0.00E+00 1.27E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 m,,,,
WaW99 Br-85 0.00E+00 0.00E+00 1.94E-08 0.00Ev00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 Rb-BB 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 Sr-89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00- 0.00E+00 t.16E-05 Sr-90 1.85E-02 0.00E+00
- 4. 71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 Sr-92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y-90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91m 8.10E-10 0.00E+00 2.76E-11.0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05.
Y-92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 Zr-97 1.4BE-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-03 0.00E+00 1.46E-05 Nb-97
-4.59E-10 9.79E-11 3.53E-11 0.00E+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 0.00E+00 3.08E-06 0.00E+00 1.80E-05 Re-105 1.36E-07 0.00E+00 4.58E-08 0.00E+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 0.00E+00 3.01E-06 0.00E+00 2.85E-05 0.00E+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 0.00E+00 1.04E-06 0.00E+00 3.77E-05 Sb-124 2.14E-05 3.15E-07 6.63E-06
- 5. 6B E'-08 0.00E+00 1.34E-05 6.60E-05 Esformatting/ Repagination changes only 01461
.i ru
%%s4hb N#$W
~ "
SEGd%&emW%
-t-j
s SON ODCM Revision 25 Page 104 of 156 Table 1.9 (8 of 8)
INGESTION DOEE FACTORS (mrem /pCi ingested)
IbrANT bone liver t body thyroid kidney lung gi-111 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72E-06 1.64E-05 Sn-125 7.41E-05 1.3BE-06 3.29E-06 1.36E-06 0.00E+00 0.00E400 1.11E-04 R25 Te-125m 2.33E-05 7.790-06 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1.11E-05 Te-127m 5.B5E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.00E+00 2.36E-05 Te-127 3.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.00E+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.00E+(J 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.00E+00 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0.00E+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.00E+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.00E+00 1.51E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.00E+00 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.00E+00 1.84E-06 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0.00E+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.101-05 0.00E+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 0.00E+00 5.38E-05 1.10E-05 2.05E-06 Ca-137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-05 Ca-138 4.81E-07 7.82E-07 3.79E-07 0.00E400 3.90E-07 6.09E-08 1.25E-Ob MWsF Ba-139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.5BE-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4,25E-07 2.91E-10 1.34E-08 0.00E+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.148-09 0.00E+00 0.00E+00 0.00E+00 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 Co-141 7.87E-0B 4.80E-03 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09.0.00E+00 5.73E-05 Co-144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E400 1.71E-04 Pr-143 8.13E-08 3.04E-0E f 03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 Nd-147 5.53E-08 5.6BE-08 3.?*E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 H-187 9.03E-07 6.2BE-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05 Referencest Regulatory Guide 1.109, Table E-14.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 R25 and SD-125 are from NUREG-0172 boe Specific Radiation Dose Commitment Factors for a One Year chronic Intah21, November, 1977, Table 4 NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
01461 j
e SQN ODCM Revision 24 Page 105 of 156 Table 1.10 (1 of 3)
RADIONUCEIDE DECAY AND STABLE ELEMENT TRANSTER DATA Half-Life K
Biv Fi Fi Fri (minutes) (1/s)
(cow)
(goat)
(beef)
E-3 6.46E+06
- 1. 79E-09 4.80E+00 1.00E-02
?.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04
- 2. 57E-08 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Mn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00F-03 1.30E-02 Co-5B 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03
- 6. 70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-01 1.40E-02 1.30E-02 9.70E-04 In-65 3.52E+05 3.2BE-0B 4.00E-01 3.90E-02 3.90E-02 3.00E-02 In-69m B.26E+02 1.40E-05 4.00E-01 3.90E-02 3.90E-02 3.00E-02 In-69 5.56E+01 2.0BE-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-B2 2.12E+03 5.45t-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E,02 6.GBE-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.1BE+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-B6 2.69E+04 4.29E-07 1.30E-01 3.00E-02 3.00E-02 3.10E-02
---~+
Rb-BB 1.76E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 TY"dI Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.2BE+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 St-90 1.50E+07 7.10E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5.70E+02 2.vJE-05 1.70E-02
-1.40E-03 1.40E-02 6.00E-04 St-92 1.63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-Ob 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.GOE-03 Y-91 B.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E 1.00E-05 1.00E-05
-4.60E-03 Zr-95 9.22E+04 1.25E-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Ir-97 1.01E+03 1.14E-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E Nb-97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Mo-99 3.96E+03 2.92E-06 1.20E-01
.7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 1.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 1.50E-02 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-105 2.66E+02 4.34E-05 5.00E-02 1.00E-06
-1.00E-06.
4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 -1.00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02
.~ s :.
a-Reformatting / Repagination changes only 01461 j
e
(
$5$E5 YOh$b
$i W ?.b:ik:
w J-e: N$$hl E1k$+$
'b
\\
q SON ODCM Revision 25 Page 106 of 156 Table 1.10 (2 of 3)
RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSTER DATA Half-Life A
Biv Tmi Fmi If1 (minutes)
(1/s)
(cow)
(goat)
(beef)
Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 N/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 N/A Sn-125 1.39E+04 8.32E-07 N/A N/A N/A N/A R25 Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Tu-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 I-130 7.42E+02 1.56E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-131 1.16E+04 9.96E-07 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 1-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 Cs-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-137 1.59E+07 7.26E-10 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+01 1.39E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 kbhF Ba-140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Co-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-08 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Pr-144 1.73E+01 6.68E-04 2.50E-03 5.00E-06 5.00E-06 4.70E-03 Nd-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E-04 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A N/A N/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A N/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A N/A Kr-88 1.70E+02 6.79E-05 N/A N/A N/A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A N/A N/A Xe-13hn 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15E+03 3.67E-06 N/A N/A N/A N/A 01461
e SQN ODCM Revision 24 Page 107 of 156 Table 1.10 (3 of 3)
RADIONUCL1DE DECAY AND STABLE ELEMENT TRANSFER DATA Half-Life A
B, T.,
T.i Tri (minutes)
(1/s)
(cow)
(goat)
(beef)
Ke-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+01 7.50E-04 N/A N/A N/A N/A Xe-135 5.47E+02 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+01 8.19E-04 N/A N/A N/A N/A References Half-lives for all nuclides DOE-TIO-11026. " Radioactive Decay Data Tabirs - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment " D. C. Kocher, 1981.
Transf er f actors for Sb-isotopes are f rom ORNL 4992, "Hethodology for Calculsting Radiation Doses from Radioactivity Released to the Environment," Mare.h 1976. Table 2-7.
Cow-milk transfer factors for Iodine Strontium, and Cesium nuclides are from NUREC/CR-1004 Table 3.17.
Coat-milk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.
Beef transfer factors for Iron Copper Molybdenum, and Cesium
...w nuclides are irom NUREC/CR-1004, Table 3.18.
All other nuclides' transfer factors are from Regulatory Guide 1.109 Tables E-1 and E-2.
r
.% c Reformatting / Repagination changes only 01461 A
- ixi@bkTs$kWk@wni.&
n
-ans%'h%&n,.ndgA$
SQN ODCM Revision 24 Page 108 of 156 Table 1.11 (1 of 2)
DOSE CALCULATION PACTORS ractor Value Units Reference BR. (infant) 1400 m*/ year ICRP 23 BR. (child) 5500 m*/ year ICRP 23 BR. (teen) 8000 m'/ year ICRP 23 BR. (adult) 8100 m*/ year ICRP 23 f.
1 WA Assumption f(
1 R. C. 1.109 (Table E-15)
(,
1 WA Assumption f.
O TVA Assumption B
9 g/m*
TVA Value K.
0.072 i
L/kg'hr R. C.1.109 (Section 2.C. )
M 40 kg/m R. C.1.109 (Section 2.C. )
P 240 kg/m' R. G. 1.109 (Table E-15)
Q, (cow) 64 kg/ day NUREC/CR-1004 (Sect. 3.4 )
Qr (goat) 08 kg/ day NUREC/CR-1004 (Sect. 3.4) r 0.47 NUREG/CR-1004 (Sect. 3.2) t.
4.73E+08 seconds R. C. 1.109 (Table E-15)
(15 years) t, 7.78E+06 seconds SQN FSAR Section 11.3.9.1 (90 days) t..,
1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180-days) t.
5.18E+06 seconds R. C. 1.109 (Table E-15)
(60 days) t.,
2.59E+06 seconds R. C.1.109 (Table E-15) g-(30 days) t..e 7.78E+06 seconds R. C.1.109 (Table E-15)
(90 days)-
tr.
8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) tn.
8.64E+04 seconds NUREC/CR-1004. Table 3.40 (1 day) t.
1.12E+06 seconds NUREC/CR-1004. Table 3.40 (13 days) tv 2.38E+07 seconds SQN FSAR Section 11.3.9.1 i
(275 days)
U.. (infant) 0 kg/ year R. C. 1.109 (Table E-5)
U.. (child) 41 kg/ year R. C. 1.109 (Table E-5)
U.. (teen)-
65 kg/ year R. C. 1.109-(Table E-5)
U.. (adult) 110 kg/ year R. C. 1.109 (Table E-5)
U.,(infant) 330 L/ year R. C. 1.109 (Table'E-5)
U., (child) 330 L/ year R. C. 1.109 (Table E-5)
U.,(teen) 400 L/ year R. C. 1.109 (Table E-5)
U.,(adult) 310
-L/ year-R. C. 1.109 (Table E-5)-
~ e Reformatting / Repagination changes only
~"
01461
$2& h &dM4;td&n%;u.+
=
0 M,8
- ' "-iShM6 dM=&L NMM
. -. -. - -. -. - - - -.. - -. -. ~. - -.. - - -- -
a SQN OCCt1 Revision 24 Page 109 of 156 Table-1.11 (2 of 2)
DOSE CALCULATION FACTORS Factor Value Units Reference Ur.(infant) 0 kg/ year R. C. 1.109 (Table E-5)
Ur.(child) 6.9 kg/ year R. C. 1.109 (Table E-5)
Ur.(teen) 16 kg/ year R. C.1.109 (Table E-5)
Ur.(adult) 21 kg/ year R. C. 1.109 (Table E-5)-
Urt. (infant) 0 kg/ year R. C. 1.109 (Table E-5)
Urt. (child) 26 kg/ year R. C. 1.109 (Table E-5)
Urt. (teen) 42 kg/ year R. C.1.109 (Table E-5 )
UrL. (adult)
-64 kg/ year R. C. 1.109 (Table I-5)
Us. (infant) 0 kg/ year R. C. l.109_(Table-E-5)
Us. (child) 520 kg/ year R. C.1.109 (Table E-5).
Us. (teen) 630 kg/ year R. C. 1.109 (Table _ E-5 )
Us. (adult) 520 kg/ year R. C. 1.109 (Table E-5)
U..(infant) 330 L/ year R. C.1.109 (Table E-5)
U..(child) 510 L/ year R. r;.1.109 (Table E-5)
U..(teen) 510 L/ year E. - C.1.109 (Table E-5)
U..(adult) 730 L/ year R. C. 1.109 (Table E-5)
W 0.3 none R. C.-l.109 (Table A-2)
Yr 1.85 kg/m' NUREC/CR-1004 (Table-3.4)-
Y, 1.18 kg/m' NUREC/CR-1004 (Table 3.3)
-Y r 0.64
'kg/m' NUREC/CR-1004.(Table 3.3)
Y.,
0.57 kg/m' NUREC/CR-1004 (Table 3.4)
(value selected is for non-leafy vegetables)
- 1. (iodines) 7.71E-07 sec~'
NUREC/CR-1004 (Table 3.10)~
(10.4 d hall-life)
'R24
-~~W
- 1. (particulates)-
5.21E-07 sec '
NUREC/CR 1004 (Table:3.10)
~
(15.4 d-half-life)
R24.
Reformatting / Repagination changes only 01461 J
a y,4 gg
-N#EMd;FNM$ff,{hiME,iMffer
. A ds.,$ @ % f S pidi s $: sg M}g d ijl 25 wc
SQN ODCM Revision 24 Page 110 of 156 Table 1.12 (1 of 8)
INHA1.ATION DOSE EACTORS (mrem /pCi inhaled)
ADULT bone liver t body thyroid kidney lung ri-111 E-3
- 1. 28 E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 0.00E+00 0.00E+00 0.00E+00 1.08E-05 Cr-51 0.00E+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E +00 4.95E-06 7.87E-07 0.00E+00 1.23E-06 1.75E-04 9.67E-06 Mn-56 0.00E+00 1.55E-10 2.29E-11 0.00E+00 1.63E-10 1.18E-06 2.53E-06 Te-55 3.07E-06 2.12E-06 4.93E-07 0.00E+00 0.00E+00 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 0.00E+00 0.00E+00 1.27E-04 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.93E-06 Co-58 0.00E+00 1.98E-07 2.59E-07 0.00E+00 0.00E+00 1.16E-04 1.33E-05 Co-60 0.00E+00 1.44E-06 1.85E-06 0.00E+00 0.00E+00 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 0.00E+00 0.00E+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 0.00E+00 5.78E-10 8.4BE-07 6.12E-06 2n-65 4.05E-06 1.29E-05 5.82E-06 0.00E+00 8.62E-06 1.08E-04 6.6BE-06 2n-69 4.23E-12 8.14E-12 5.65E-13 0.00E+00 5.27E-12 1.15E-07 2.04E-09 2n-69m 1.02E-09 2.45E-09 2.24E-10 0.00E+00 1.48E-09 2.3BE-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1.69E-06 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Br-83 0.00E+00 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.90E-08 Br-84 0.00E+00 0.00E+00 3.91E-08 0.00E+00 0.00E+00 0.00E+00 2.05E-13 Br-85 0.00E+00 0.00E+00 1.60E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 k@E55 Rb-86 0.00E+00 1.69E-05 7.37E-06 0.00E+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 0.00E+00 4.84E-08 2.41E-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.20E-08 2.12E-08 0.00E+00 0.00E+00 0.00E+00 1.16E-21 Sr-89 3.80E-05 0.00E+00 1.09E-06 0.00E+00 0.00E+00 1.75E-04 4.37E-05 Sr-90 1.24E 02 0.00E+00 7.62E-04 0.00E+00 0.00E+00 1.20E-03 9.02E-05 Sr-91 7.74E.19 0.00E+00 3.13E-10 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 0.00E+00 3.64E-11 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 0.00E+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 0.00E+00 1.27E-12 0.00E+00 0.00E+00 2.40E-07 1.66E-10 m
u Y-91 5.78E-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.81E-05 Y-92 1.29E-09 0.00E+00 3.77E-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1.18E-08 0.00E+00 3.26E-10 0.00E+00 0.00E+00 6.06E-06 5.27E-05 Et-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00
-Mo-99 0.00E+00 1.51E-08 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 0.00E+00 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.23E-08 0.00E+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.BBE-11 0.00E+00 3.89E-11 0.00E+00 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 0.00E+00 1.09E-06 0.00E+00 1.67E-05 1.17E-03 1.14E-04 Ag-110m 1.35E-06 1.25E-06 7.43E-07 0.00E +00 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0.00E+00 3.10E-04 5.08E-05 Reformatting / Repagination changes only 01461
)
.E
~,
Y x $ M & # M W s k t :. w + % m & M N b M c s k W E5
e SON ODCM Revision 25 Page 111 of 156 Table 1.12 (2 of 8)
INH?LATION DOSE FACTORS (mrem /pCl inhaled)
ADULT bone liver t body thyroid kidney lung g1-111 Sb-125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81E-05 R25 Tv ~25m 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E 6.37E-10 8.14E-07 7.17E-06 Te-129m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6,88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 f.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0.00E+00 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0.00E+00 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 0.00E+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 0.00E+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 0.00E+00 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 ww--
hN*N#
Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 -4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 0.00E+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 0.00E+00 8.75E 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 0.00E+00 7.83E-07 4.52E-05 1.50E-05 i
Ce-143 2.33E-08 1.72E-08 1.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2.69E-18
-Hd-147 6.59E-07 7.62E-07 4.56E-08 0.00E+00- 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 0.00E+00 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05
Reference:
Regulatory Guide 1.109, Table E-7.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are-from NUREG-0172 Ace Specific Radiation Dose Commitment Emeters for a One Year Chtonic Intake, November 1977, Table 8.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
014b1
e SQN ODCM Revision 24 Page 112 of 156 Table 1.12 (3 of 8)
INHA1.ATION DOSE FACTORS (arem/pCi inhaled)
TEEN bone liver t body thyroid kidnay lung gi-ill H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1.16E-05 Cr-51 0.00E+00 0.00E+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 0.00E+00 6.39E-06 1.0$ E-06 0.00E+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 0.00E+00 2.12E-10 3.15E-11 0.00E+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.9BE-06 6.93E-07 0.00E+00 0.00E+00 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-04 2.23E-05 Co-57 0.00E+00 1.18E-07 1.15E-07 0.00E+00 0.00E+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 0.00E+00 1.6BE-04 1.19E-05 Co-60 0.00E+00 1.89E-06 2.4BE-06 0.00E+00 0.00E+00 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.54E-10 1.06E-10 0.00E+00 8.01E-10 1.39E-06 7.6 8 E-06 2n-65 4.82E-06 1.67E-05 7.80E-06 0.00E+00 1.08E-05 1.55E-04 5.83E-04 2n-63 6.04E-12 1.15E-11 8 07E-13 0.00E+00 7.53E-12 1.9BE-07 3.56E-08 2n-69m 1.44E-09 3.39E-09 3.11E-10 0.00E+00 2.06E-09 3.92E-06 2.14E-05 Br-82 0.00E+00 0.00E+00 2.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E400 0.00E+00 5.41E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 n
Br-85 0.00E+00 0.00E+00 2.29E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 enz@Y NN*
Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82E-06 3.40E-08 0.00E+00 0.00E+00 0.00E+00 3.65E-15 Rb-89 0.00E+00 4.40E-08 2.91E-08 0.00E+00 0.00E+00 0.00E+00 4.22E-17 Sr-89 5.43E-05 0.00E+00 1.56E-06 0.00E+00 0.00E+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 B.35E-04 0.00E+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-0B 0.00E+00 4.39F-10 0.00E+00 0.00E+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.0BE-11 0.00E+00 0.00E+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.90E-05 Y-91m 4.63E-11 0.00E+00 1.77E-12 0.00E+00 0.00E+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.2IE-06 0.00E+00.0.00E+00 3.67E-04 5.11E-05 Y-92 1.84E-09 0.00E+00 5.36E-11 0.00E+00 ~ 0.00E+00 3 '. 35 E-06 2.06E-05 Y-93 1.69E-08 0.00E+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24E-05 Ir-95 1.82E-05 5.73E-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.86E-05 ir-97 1.72E-nB 3.40E-09 1.57E-09 0.00E+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-v6 1.29E-06 7.08E-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Hb-97 3.92E-11 9.72E-12 3.55E-12 0.00E+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 0.00E+00 2.11E-08 4.03E-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 0.00E+00 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 0.00E+00 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 0.00E+00 5.42E-11 0.00E+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 0.00E+0C 2.38E-05 2.01E-03 1.20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 Sb-124 5.38E-06 9.92E-08 2.10E-06 1.22Er08 0.00E+00 4.81E-04 4.98E-05 Reformatting / Repagination changes only 01461 j
3p65dEkM$%;@M2hb
@hFMV4We%dMMkhl)
W:5-u-
l %
s SON ODCM Revision 25 Page 113 of 156 Table 1.12 (4 of 8)
INHALATION DOSE FACTORS (mrem /pci inhaled)
TEEN bone liver t body thyroid kidney lung gi-Ili Sa-125 9.23E-06 1.03E-07 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0.00E+00 1.26E-04 7.29E-05 R25 Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0.00E+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 0.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.57E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-09 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0.00E+00 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0.00E+00 1.29E-06 1-134 1.?1E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.2BE-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 0.00E+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 0.00E+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.3BE-11 5bhk Ba-139 1.67E-10 1.18E-13 4.87E-12 0.00E+00 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 0.00E+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Co-143 3.32E-08 2.42E-08 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 0.00E+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 0.00E+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 0.00E400 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 0.00E+00 1.25E-08 8.11E-06 1.65E-05 Reference Regulatory Guide 1.109, Table E-8 Dose Factors for Co-57, Zn-69m, Br-P2, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are from NUREG-0172 Ace Specific Radiation-Dore Commitment Factorr for a One Year chi 2pic Intake. November 1977, Table 8.
l
?
NOTE: The tritium dose factor for bone is assumed to be equal to the i
total body dose factor.
i 01461
)
SQN ODCM R3 vision 24 Page 114 of 156 Table 1.12 (5 of 8)
INHALATION DOSE TACTORS (mrem /pCi inhaled)
CHILD bone liver t body thyroid kidney lung gi-111 E-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06
- 4. 35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06
- 4. 35 E-06 P-32 7.04E-04 3.09E-05 2.67E-05 0.00E+00 0.00E+00 0.00E+00 1.14E-05 Cr-51 0.00E+00 0.00E+00 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.57E-06 0.00E+00 2.71E-06 4.26E-04 6.19E-06 Hn-56 0.00E+00 4.48E-10 8.43E-11 0.00E+00 4.52E-10
- 9. 2 9 E-06 Co-60 0.00E+00 3.55E-06 6.12E-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 0.00E+00 0.00E+00 2.21E-06 2.27E-05 Cu-64 0.00E+00 5.39E-10 E.00E-10 0.00E+00 1.63E-09 2.59E-06 9 92E-06 In-65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-11 2.41E-12 0.00E+00 1.58E-11 3.84E-07 2.75E-06 2n-69m 4.26E-09 7.28E-09 8.59E-10 0.00E+00 4.22E-09 7.36E-06 2.71E-05 Br-82 0.00E+00 0.00E+00 5.66E-06 0.00E+00 J.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.28E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.4BE-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 6.84E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00
---wa Rb-86 0.00E+00 5.36E-05 3.09E-05 0.00E+00 0.00E+00 0.00E+00 2.16E-06 Idiid Rb-8E 0.00E+00 1.52E-07 9.90E-08 0.00E+00 0.00E+00 0.00E+00 4.66E-09 Rb-89 0.00E+00 9.33E-08 7.83E-08 0.00E+00 3.00E+00 0.00E+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 0.00E+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3.28E-08 0.00E+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 0.00E+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-08 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m 1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.47E-04 0.00E+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 0.00E+00 0.00E+00.6.46E-06 6.46E-05 Y-93 5,04E-08 0.00E+00 1.38E-09 0.00E+00' O.00E+00 2.01E-05 1.05E-04 2r-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.4BE-06 1.77E-06 0.00r&OO 2.33E-06 1.66E-04 1.00E-05 Nb-97 1.16E-10 2.0SE-11 9.74E-12 0.00E+00 2.31E-11 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.15E-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 0.00E+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.6BE-05 0.00E+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1.16E-04 As-110m 4.56E-06 3.08E-06 2.47E-06 0.00E+00 5.74E-06 1.48E-03 2.71E-05 Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-08 0.00E+00 8.76E-04 4.43E-05 l
Reformattieg/ Repagination changes only
~
01461 1
3 gu$
% Yg h % % 5.Y!ki.S $ b k W m ~ ' : -
x &nsnkSK;n=ad$ &
SQN ODCM Revision 25 Page 115 of 156 Table 1.12 (6 of 8)
INHALATION DOSE TACTORS (mrem /pC1 inhaled)
CHILD bone liver t body thyroid kidney lung g1-111 Sb-125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0.00E+00 6.27E-04 1.09E-05 Sn-125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0.00E+00 2.43E-04 7.17E-05 R25 Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0.00E400 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 1.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63C-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.5BE-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0.00E+00 7.6BE-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0.00E+00 8.65E-07 1-133 4.48E-C6 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0.00E+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E 07 1.37E-05 8.92E-07 0.00E+00 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0.00E+00 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 0.00E400 1.68E-07 1.84E-08 7.29E-08 om.,
%sW6f Ba-139 4.98E-10 2.66E-13 1.45E-11 0.00E+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 0.00E+00 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 0.00E+00 2.5cE-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 0.00E+00 0.00E+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.'9E '1 0.00E+00 0.00E+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Co-143 9.89E-08 5.37E-08 7.77E-00 0.00E+00 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 0.00E+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.o*E-12 8.10E-13 0.00E+00 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 0.00E+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 0.00E+00 0.00E+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.57E-05 1.73E-05 References Regulatory Guide 1.109, Table E-9.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are from NUREG-0172 Ace Specific Radiation Dose Commitment _
Factors for a One Year _ Chronic Intake, November 1977, Table 8.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
01461 J
SQN ODCM Revision 24 Page 116 of 156 Table 1.12 (7 of 8)
INHALATION COSE FACTORS (mrem /pci inhaled)
INFANT bone liver t body thyroid kidney lung gi-lli H-3 L.62E-07 4.62E-07
- 4. 6 2E-0 7 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 0.00E+00 0.00E+00 0.00E+00 1.15E-05 Cr-51 0.00E*00 0.00E+00 6.39E-08 4.11E-08 9.45E-09 9.11E-06 2.55E-07 Mn-54 0.00E+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 0.00E+00 1.10E-09 1.5BE-10 0.00E+00 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21E-05 7.82E-07 Fe-59
- 9. 6 9 E-06 1.68E-05 6.77E-06 0.00E+00 0.00E+00 7.25E-04 1.77E-05 Co-57 0.00E+00 4.65E-07 4.58E-07 0.00E+00 0.00E+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 0.00E+00 0.00E+00 5.550-04 7.95E-06 Co-60 0.00E+00 5.73E-06 8.41E-06 0.00E+00 0.00E+00 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 0.00E+00 0.00E+00 1.49E-04 1.73E-06 N1-65 1.71E-09 2.03E-10 8,79E-11 0.00E+00 0.00E+00 5.80E-06 3.5BE-05 Cu-64 0.00E+00 1.34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 In-65 1.38E-05 4.47E-05 2.22E-05 0.00E+00 2.32E-05 4.62E-04 3.67E-05 In-69 3.85E-11 6.91E-11 5.13E-12 0.00E+00 2.87E-11 1.05E-06 9.44E-06 In-69m 8.98E-09 1.84E-08 1.67E-09 0.00E+00 7.45E-09 1.91E-05 2.92E-05 Br-82 0.00E+00 0.00E+00 9.49E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 2.72E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.46E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 yte+w Kb-86 0.00E+00 1.36E-04 6.30E-05 0.00 E +00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3.9BE-07 2.05E-07 0.00E400 0.00E+00 0.00E+00 2.42E-07 Rb-89 0.00E+00 2.29E-07 1.47E-07 0.00E+00 0.00E+00 0.00E+00 4.87E-08 Sr-89
- 2. 84 E-04 0.00E+00 8.15E-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 Sr-90 2.92E-02 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36E-05 Sr-91 6.83E-08 0.00E+00 2.47E-09 0.00E+00 0.00E+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 0.00E+00 6.30E-08 0.00E+00 0.00E+00 1.92E-04 7.43E-05 Y-91m 2.91*-10 0.00E+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.20E-04 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-0B 0.00E+00 3.29E-10 0.00E+00 0.00E+00 1.75E-05 9.04E-05 Y-93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Ir-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 0.00E+00 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 0.00E+00 3.37E-06 3.42E-04 9.0$E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 0.00E+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 0.00E+00 1.18E-07 2.31E-08 0.00E+00
- 1. 89E-0 7 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-04 5.80E-13 0.00E+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.77E-06 0.00E+00 7.61E-05 8.26E-03 1.17E-04 Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2.62E-03 2.36E-05 Sb-124
- 2. 71E-05 3.97E-07 8.56E-06 7.18E,,08 0.00E+00 1.89E-03 4.22E-05 Reforvatting/ Repagination changes only 01461 4
l Q
I.
mnemqqn
~ +MMMMeMh*
s SON ODCM Revision 25 Page 117 of 156 Table 1.12 (8 of 8)
INHALATION DOSE FACTORS (mrem /pci inhaled)
INFANT bone liver t body thyroid kidney lung q1-111 Sb-125 3.69E-05 3.41E-07 7.73E-06 4.45E-08 0.00E+00 1.17E-03 1.05E-05 Sn-125 1.01E-05 2.51E-07 6.005-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 R25 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 To-127m 1.19E-05 4.93E-06 1.4LE-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.40E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.LSE-11 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00F+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 0.00E*00 1.36E-04 5.69E-05 9.53E-07 Cs-l'36 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 0.00E+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 0.00E+00 2.93E-07 4.67E-08 6.26E-07 W*TW Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 0.00E+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 0.00E+00 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.2SE-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 0.00E+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00B+00 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Hp-239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05
Reference:
Regulatory Guide 1.109, Table E-10.
Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sn-125, Sb-124 and R25 Sb-125 are from NUREG-0172 Age Specific Radiation Dose Commitatat_
Factors _for a One Year Chronic Intake. November 1977, Table 8.
NOTEt The tritium dose factor for bone is assumed to be equal to the total body dose factor.
01461
c.
o SQN OBCM Revision 24 Page 118 of 156 Table 1.13 (1 of 2)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED CR0ttG (arem/h per pCi/m')
Nac11de Total Body Skin B-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54
$.80E-09 6.80E-09 Hn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 2n-65 4.00E-09 4.60E-09 2n-69 0.0 0.0 2n-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 ggggy Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 2r-95 5.00E-09 5.80E-09 2r-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Nb-97 8.11E-09 1.00E-08 Mo-99 1.90E-09 2.20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E.09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-08 2.10E 08 Sb-124 2.17E-08 2.57E-08
.% c Reformatting / Repagination changes only 01661 Y
+.
r5 NigS9.;p.aq$$..ig.@...~ca G.., _. --
.. d ;; @ w.J e + J Sx-4:4
~
9 SON ODCM Revision 25 Page 119 of 156 Table 1.13 (2 of 2)
EXTEENAL DOSE FACTORS FOR ST/,NDING ON CONTAMINATED GROUND (mrem /h per pC1/m?)
Huclide Total Body Skin Sb-125 5.48E-09 6.80E-09 Sn-125 3.58E-09 4.51E-09 R25 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 1-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.2]E-08 1.40E-08 Ce-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09
References:
Regulatory Culde 1.109, Table E-6.
9 Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sn-125, Sb-124 and Sb-125 R25 are from RosceRAte Conversion Factors for External Ernosure to Pho(o m d Electron _ Rdin. tion f rom Radionuclides occurrina in Routine _ ReleaseLLtgr3 lblC1tAL fR1 Cvele Fac111 tim D. C. Kocher, lies 1th Physics Volume 38, April 1980 01461
. ~_... _ -... - - - - -. -..
SQN ODCM Revision 24 Page 120 of 156 Table 2.1 (Page 1 of 4)
RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Minimum Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD)
Type Frequency
' Frequency Analysis (pCi/ml)*
A. Batch Waste P
P kelease Each Batch Each m rch Principal 5x10*'
e Tank.'
Camma Emitters'
- 1. Waste Con-densate I-131 1X10
Tanks (3)
- 2. Cask Deron-P M
Dissolved /
1x10*'
tamination One Batch /M Entrained Tank Cases (Camma Emitters)
- 3. Laundry Tanks (2)
P M
H-3 1x10
Each Batch Composite'
- 4. Chemical Cross 1x10
Drain Tank Alpha
- 5. Monitor Tank
- 6. Distillate Tanks (2)
P Q
- 7. Condensate Each Batch Composite
- Sr-89, 5x10
Demineraliser Sr-90 Weste Evaporator Fe-55 1x10" Blowdown Tank (1)
B. Continuous D
W Principal 5x10-'
Releases
- Crab Sample Composite' Caama Emitters'
- 1. Steam Generator" I-131 1x10**
Blowdown M
M Dissolved /
1x10-*
- 7. Turbine Crab Sample Entrained Cases (Camma Building" Emitters)
Sump D
M H-3 1x10
Grab Sample Composite'-
Cross Alpha 1x10
D Q
Sr-89, 5x10" Grab Sample Composite'.f Sr-90
?
Fe-55 1x10
Reformatting / Repagination changes only 01461
.t s
.v,_ 's % &s h
,gst f, st,
$ t.$$
be N
hkWWfkf{ 10%
BYE-Y M
~
_.. _ _. _ _ _...._._. _ __.._,..-._ _. ___ _.._ _._.. _ _ _..._-_._....-_... _ _ ~._. _ __. _ _
e.
SQN ODCM R3 vision 24 Page 121 of 156
)
Table 2.1 (Page 2 of 4)
. i RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS TROGRAM
~
Liquid Minimum.
Type of Lower Limit of Release Sampling Analysis Activity Detection (LLD)
Type Frequency Frequency Analysis (pCi/ml)*
C. Periodie W
Principal 5x10
Continuous-Continuous 8 Composite
- Gamma Releases
Emitters' I-131 1x10
- 1. Non-Reclains able Waste M8 M
Dissolved 1x10**
Tank Crab Sauple and Entrained Cases
- 2. Eigh Crud (Cansna -
Tanks (2)
Emitters)
M H-3 1x10
- 3. Neutralizer Continueus:
Composite' Tank Gross 1x10-'
Alpha Q
St-89 5x10
Continuous
- Composite
- Sr-90 i
""~
%BMW Fe-55 1x10 "
l l
.b 4 Reformatting / Repagination changes only 01461 I
l I
-)
r i
l 8
[k.s.,,.bh!N' t,
a q
.W
+4$
try. -
.y n.
4
!, r 4'
,yJ,-
a
. ' N. ~.,7.].a
- % gr ' -
' T ao w
,t 1
a..
.mes...
a'
0 SON ODCM Revision 25 Page 122 of 156 Table 2.1 (Page 3 of 4)
RADI0 ACTIVE LIQUID HASTE SAMPL1HG AND ANALYSIS PROGRAM TABLE NOTATION Pe Completed prior to each release 0 = At Icast once per 92 days D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A.
= Not Applicable M = At least once per 31 days a The LLD la defined for the purpose of these specifications as the smallest concentration of radioactive material in a sample that will yield a not count above system background that will be detected with 95\\ probability with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66sb bbD * ~
E v
2.22x10' Y
exp (-Aht)
Where LLD is the "a priori" lower limit of detection as defined above in microcurie per unit mass or volume, ob is the standard deviation of the onckground counting rate ypf* ;[
or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency as counts per disintegration, V is the sample size in units of mass or volume, 2.22x106 1s the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between midpoint R25 of sample collection and time of counting (midpoint).
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an A_ppsterloti (after the fact) limit for a particulate measurement, b
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and.in which the method.of sampling employed results in a specimen which is representative of the ligulds released.
01461 l
0 S9N ODCM Revision 25 Page 123 of 156 Table 2.1 (Page 4 of 4)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION c Prior to analyses, all samples taken for the composite shall be throughly mixed in order for the composite sample to be representative of the effluent release, d A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by the method described in Section 2.3.2, to assure representative sampling.
e A continuous release is the discharge of liquid wastes of e nondiscrete volume; e.g., from a volume or system that has an input R25 flow during the continuous release.
f The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141.
Co-144 shall also be measured with an LLD of 5x10-6 This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identif,lable, together with the above nuclides, shall also be identified and reported.
g Releases from these tanks are continuously composited during releases.
YN49#
With the composite sampler or the sampler flow. monitor inoperable, the sampling frequency shall be changed to require representative batch samples from each tank to be released to be taken prior to release and manually composite for these analyses.
h Applicable only during periods of primary to secondary leakage or the release of radioactivity as detected by the effluent radiation monitor provided the radiation monitor setpoint is at a LLD of 11x10-6 pCi/ml and allowing for background radiation during periods when primary to secondary leakage is not occurring.
01461
SQN ODCM Revision 24 Table 2.2 (Page 1 of 3)
Page 124 of 156
{
FADI0 ACTIVE LIQUID EFTLUENT MONITORING INSTRUMENT l
Minimum Ins t rumen t Channels OPERABLE Action 1.
CROSS RADI0 ACTIVITY MONITORS PROVIDINC AUTOMATIC TERMINATION OF RELEASE Liquid Radwaste Effluent Line a.
b.
Steam Generator Blowdown Effluent Line 1
30 Condensate Demineraliser Effluent Line c.
1 31 1
30 2.
CROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE Essential Raw Cooling Water Effluent a.
Header **
1 32 b.
Turbine Building Sump Eifluent Line 1
32 3.
FLOW RATE MEASUREMENT DEVICES Liquid Radwaste Effluent Line a.
b.
Condensate Demineralizer Effluent Line 1
33 Steam Generator Blowdown Effluent Line c.
1 33 d.
Cooling Tower Blowdown Effluent Line 1
33 1
33 4
TANK LEVEL INDICATING DEVICES yp]E$
Condensate Storage Tank a.
b.
Steam Generator Layup Tank
- 1 34 1
34 5.
CONTINUOUS CCMPOSITE SAMPLER AND SAMPLE FLOW MONITOR Condensate Demineralizer Regenerant Effluent Line a.
1 35
- Required when connected to the secondary system
i asnommww
.w e
(-
+ "~
m.__..
i o
-Rsvision 24-Page 124 of 156--
Table 2.2 (Page 1 of 3)
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum.
Channels e
Instrument OPERABLE Action 1.
CROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line 1
30 b.
Steam Generator Blowdown Effluent Line-1 31 c.
Condensate Demineralizer Effluent Line 1
30 2.
CROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC--
TERMINATION OF RELEASE a.
Essential Raw Cooling Wate.- Effluent Header **
1 32 b.
Turbine Building Sump Effluent Line-1
.32 3.
FLOW RATE MEASUREMENT DEVICES a.
Liquid Radwaste Effluent Line 1
33 b.
Condensate Demineralizer Effluent Line 1
33 c.
Steam Generator Blowdown Effluent Line 1
33-d.
Cooling Tower Blowdown Effluent-Line 1
33 4.
TANK LEVEL INDICATING DEVICES a.
Condensate Storage Tank 1
34 b.
Steam Generator layup Tank
- 1 34 5.
CONTINU0US COMPOSITE SAMPLER AND SAMPLE' FLOW MONITOR a.- Condensate Demineralizer Regenerant Effluent Line 1
35 l
- Required when connected to the secondary system
- Requires minimum of 1 Channel / Header:to be OPERABLE.-
l Reformatting / Repagination changes only 01461 J
h f'Yi { {
[4N h
'ih
~
+
. ~ _
SQN ODCM Revision 24 Page 125 of 156 Table 2.2 (Page 2 of 3)
RADI0 ACTIVE LIQUID EyyLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a releaser
- a. At least two independent saniples are analyzed in accordance with Section 2.3.2, and
- b. At least two technically qualified members of the yacility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity gamma at a limit of 6etection of at least 10" microcuries/ grams
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131,
- b. At least once per 24 hourt when the specific activity g
of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity gamma at a limit of detection of at least 10" nicrocuries/ml.
j ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continued provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
Reformatting / Repagination changes only 01461 e
+
k JV gi
,A, a '.
e a
(
fih $ $ jh & h $ $ & T W k $ c a & a
%%Yh bkNYMMY$
o SQN ODCM Revision 24 Page 126 of 156 Tabic 2.2 (Lage 3 nf 3)
RADICACIf VE LIQUID EITLUENT MONITORING INSTRUMENTATION TABLE NOTATION ACTION 34 With the number of ct.annels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank saay continued provided the tank liquid level is estimated during all liquid additions to the tank.
ACTION 35 With the nu.uber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue provided representative batch samples of each tank to be released are taken prior to release and composited for analysis according to Table 2.1, footnote g.
Nh5Ikb i
l i
l I
. '-,4 c l
Reformatting / Repagination changes only 0146,4 l
i Ug M
r* _
t.
f1 Q.'y,
r --
_t s
)
i SQN ODCM i-Revision 24 Page 127 of 156 Table 2.3 (Page 1 of 2)
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMEhTS CHANNEL CHANNEL SOURCE CHAVNEL TUNCTIONAL Instrument CHECK CHECK. CALIBRATION TEST 1.
CROSS BETA OR GAMMA RADIDACTIVITi MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluents Line
-D P
R(3)
Q(1) b.
Steam Generator Blowdown Effluent Line D
M R(3)
Q(5) c, Condensate Demineralizer Effluent Line D
M R(3).
Q(5) 2.
CROSS BETA OR CAMMA RADIDACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE Essential Raw Cooling Water-a.
Effluent Line D
M R(3)
Q(2) b.
Turbine Building Sump Elfluent Line D
M R(3)
Q(2) 3.
FLOW RATE MEASUREMENT DEVICES
)
a.
Liquid Radwaste Effluent Line D(4)
N.A.
R Q
- b. -Stean Generator Blowdown
~
Effluent Line D(4)-
N.A.
R Q
c.
Condensate Demineralizer Effluent Line D(4)
N.A.
.R Q
d.
Cooling Tower Blowdown Effluent Line
-D(4)
N.A.-
R Q
4 TANK LEVEL INDICATING DEVICES, a.
Condensate Storage Tank D*'
N.A.
R '.
Q.
b.
Steam Generator Layup Tank D*
-N.A.
R N.A.
l.
l 5.
CONTINUOUS COMPOSITE SAMPLER
{
AND SAMPLE FLOW MONITOR a.
Condensate Domineralizer Regenerant Effluent Line
'P N.A.
R N.A.
Reformatting / Repagination changes only 01461 0
l
- q,, i ~ +
}%lbh
$d#6ddf IS'M.$ NlihN'M244Wce/?"
wiv WMUk$dfitidshiNN!fj$mirGkksMM
..- ~ -
e SQN ODCM Revision 24 Page 128 of 156 Table 2.3 (Page 2 of 2)
RADIDACTIVE LIQUID ETFLUENT MONITORING INSTRUMENTA*i!ON SURVEILLANCE REQUIREMENTS TA3LE NOTATION P = Completed prior to each release R = At least once per 18 months Q = At least once per 92 days D = At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N.A. = Not Applicable M = At least once per 31 days During liquid additions to the tank.
(1) The CRANNEL FUNCTIONAL TEST shall also democstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(2) The CHANNEL WNCTIONAL TEST shall also demonstrate that control room alara annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Burca.
of Standards or using standards that have been obtained from
.- e suppliers that participate in measurement assurance activities with NES. These standard = shall permit calibrating the system over its intended range of energy and measurement range. For subs't ent CHANNEL CALIERATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CPECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous periodic, or batch releases are made.
($) 'Ihe CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annut.ciation occurs if any of the following conditions, occurs
- 1. Instrument indicates measured levels above the alarm / trip setpoint..
- 2. Circuit failure.
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room annunciation occurs if the following condition occurs:
- 1. Downscale fmilure.
Reformatting / Repagination changes only 01461 l
J
$h s h.Y$h{!
7 T.* : e " Wh ! '
- rSS o
l
~. - _.
O e
SQN OICM Revision 24 Page 129 of 156 Table 2.4 RECEPTORS FOR LIQUID DOCE CALCULATIONS 1ennessee River Reaches Within 50 Mile Radius Downstream of SQN Name Beginning Ending Site Recreation TRM TRM (acres) visits / year Chickatsuga lake 484.0 471.0 9939 5,226.700 below SQN Nickajack take 471.0 435.0 5604 240,700 (Part 1) fHekajack Lake 435.0 425.0 5326 607,600
'* rt 2) ersville Lake 425.0 400.0 6766 104.000 Putilic Water Supplies Within 50 Mile Radius Downstream of SQN Name
'rRM Population E. I. DuPont 469.9 1.400 Chattanooga, TN 465.3 224,000 South Pittsburg, TN 418.0 4.898 Bridgeport, AL 413.6 4,650 Q.:.
Reforrr.stting/ Repagination changes only 01461
' f t '*.h f
d@h$ des 23fli4lihWin?)#h<W7 777 Em ";s9NMk N O M M6N k ?NIS
O CON ODCM Revision 25 Page 130 of 156 Table 2.5 BIOACCUMULATION FACTORS FOR TRESi! WATER FISH (pCi/kg per pC1/ml)
N-3 9.0E-01 Tc-99m 1.5E+01 C-14 4.6E+03 2c-102 1.5E401 i
Na-24 1.0E 02 Ru-303 1.0E401 P-32 1.0E405 Ru-105 1.0E401 Cr-51 2.0E402 Ru-106 1.0E401 Mn-54 4.0E+02 Ag-110m 2.31E+00 R25 Mn-56 4.0E402 Sb-124 1.0E+00 ie-55 1.0E+02 Sb-125 1.0E400 fe-59 1.0E402 Sn-125 3.0E+03 R25 Co-57 5.0E+01 Te-125m 4.0E+02 Co-58 5.0E+01 Te-127m 4.0E+02 Co-60 5.0E401 Te-127 4.0E*02 Ni-63 1.0C+02 Te-129m 4.0E+02 Ni-65 1.0E402 7c-129 4.0E402 Cu-64 5.0E+01 Te-131m 4.0E+02 Zn.65 2.0E+03 70-131 4.0E402 Zn-69 2.0E403 Te-132 4.0E+02 Zn-60m 2.0E+03 I-130 4.0E401 Br-82 4.2E+02 I-131 4.0E401 Br-83 4.2E+02 I-132 4.0E+01 Dr-84 4.2E+02 I-133 4.0E+01 br-85 4.2E+02 1-134 4.0E+01 Rb-86 2.0E+03 N,.,.4,.
1-135 4.0E+01 Rb-88 1.0E+03 Cs-134 1.9E+03 Rb-89 2.0E+03 Cs-136 1.9E403 Sr-89 5.6E+01 Cs-137 1.9E403 Sr-90 5.6E+01 Cs-138 1.9E+03 Sr-91 5.6E+01 Da-139 4.0E+00-Sr-92 5.6E+01 Ba-140 4.0E+00 Y-90 2.5E+01 Da-141 4.0E+00 Y-91m 2.5L+01 Da-142 4.0E400 Y-91 2.5E+01 La-140 2.5E+01 Y-92 2.5E+01 La-144 2.LE401 Y-93 2.5E+01 Ce-141 1.0E+00 Zr-95 3.3E400 Co-143
- 2. 0E+00 Zr-97 3.3E+00 Ce-144 1.0E+00 Nb-95 3.0E+04 Pr-144 2.5E401 Nb-97 3.0E+04 Pr-143 2.5E+01 Mo-99 1.0E+01 Nd-147 2.5E+01 W-187 1.2E+03 Np-239 1.0E+01
References:
Bloaccumulation factors for Ag-110m, Sb-124, Sb-125 and Sn-125 are from R25 I
ORNL-4992, "A Methodology for Calculating Radiation Doses from Radio-i activity Released to the Environment, March 1976, Table 4.12A.
Bioaccumulation factors for Iodine, Cesium, and Strontium nelides are from NUREG/CR-1004, Table 3.2.4.
All other nuclides' bloacc?unulation f actors are f rom Regulatory Guide 1.109, Table A-1.
01461
.s.
a SQN ODCH Revision 24 Pese 131 of 156 Table 3.1 (Page 1 of 3) minim M REQUIRED RADIOLOGICAL LNVIR0hMENTAL MONITORING PROGPAM Exposure Pathway Number of Samples and/or and Sampling and Type and Trequency Saerle Sample Locations ** Collection Frequency of Analysis
- 1. AIRB0kNE Radiciodine end minimurs of 5
. Continuous operation Radiciodine canister Particulates locations of sampler with Analyse at least once sample collection as per 7 days for 1-131.
required by dust loading but at least Particulate sampler once per 7 days.
Analyse for gross beta radioactivity 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> iollowing filter change.
Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mekn of control samples.
Perform gansna isotopic analysis on Q
composite (by location) sample at least once per 92 days.
- 2. DIRECT 35 to 40 At least once per Camma Dose.. At least RADIATION locations with 92 days, once per 92 days.
1 2 dosimeters for continuously measuring and recording dose rate at each location.
- sample locatior: are given in Table 3.4 L.:.
Reformatting / Repagination changes only 01461
/[lC *.
1'?i,,
Y"[$h Ih u,
., j y.
.w
+
a ifkMM$5hdMidhk@MM((#htbaGMh#hMhN/Mf54EdIJthhk!
f f.
J
e l
SQN OICH l
Revision 24 Page 132 of 1%
Table 3.1 (Page 2 of 3)
MINIMUM REQUIRED RADIOLOGICAL LNVikONMENTAL MON 170 RING PROGRAM Luposure fathway Number of Samples and/or and Sampling and Type and frequency pample Sample tocations** Colle nipn Frequency of Analysis
- 3. WATLRBORNE
- a. Surface 3 locations Composite
- sample Canrna isotopic collected over a analysis of each period of 1 31 days. composite sample.
Tritium analysis of l
composite sample at i
least once per 92 days.
- b. Ground 2 locations At least once per Camma isotopic and 92 days.-
tritium analyses of each sample,
- c. Drinking Minlanum ot 1 Composite
- sample Cross beta and gansna location collected over a isotopic analysis of period of 1 31 days. each composite sample.
2 locations Monthly single Tritium analysis of sample.
composite sample at Q
1 east once per 92
- days,
- d. Sediment Minimum of 2 At least once per Gangna isotopic from locations.
184 days
__ analysis.
l Shoreline of each sample, locations 7 Composite samples shall be collected by collecting an aliquot c.t intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
- Sample locations are given In Table 3.4.
l Reformatting / Repagination changes only 01461 I
4
,$1: ::h If hk)$'$d.
.. khh%OMi h
Y 'I El Y i l" 5.
/
_ _ _ _ _ _ _ ~. __ _--
SQN ODCM Revision 24 Page 133 of 156 Table 3.1 (Page 3 of 3)
MINIMUM F.EQUlkED RADIOLOGICAL ENVIRONMENTAL MON 170k1NG PROGRAM Exposure Pathway Number of Samples and/or and Sampling and Type and Frequency La,mrie Sample Locations ** Collection Frequency of Analysis 4.INGT.ST!0N
- a. Milk 3 locations At least once per 15 Canrna isotopic and Samples of broad days when animals 1-131 analysis i
leaf vegetation are on pastutet of each sample.
at offAlte at least once per location of 31 days at other highest D/Q if times.
milk sample is not available.
b.Tish and 3 locations one sample in Gamma 1:otopic Invertebrates season, or at least analysis on edible once per 184 days portions.
if not seasonal.
One sample of each of the following species:
1.
Channel Catiish 2.
White Crappie 3.
Smallmouth Buffalo N
- e. rood Products Minimum of 2 At time of harvest.
Canana isotopic locations one sample of each analysis on edible of the following portion.
classes of food products.
1.
14ttuce and/or cabbage 2.
Corn 3.
Beans
, 4.
Tomatoes
- Sample locations are given in Table 3.4.
1 f
i
.M /
.?
Reformatting / Repagination changes only 01461 Y
di
'S f.
4-f,
^
CiW @ s & M %A M ti M U ski? % M e h %. A +wSNdA9dd$ir$2 fids's'delNMM,'
w
0 SQN ODCN Revision 24 Page 134 of 156 Table 3.2 (Page 1 of 2)
MAX 1tCM VAlt'E5 TOR THE LOWER LIMITS Or CETECTION (LLD)
Airborne Particulate Water or Cases Fish Milk Tood Products Sediment Analysis
{pCi/L) jpCi/m'l,(pCi/KR we t ) (pCl/L)
(pCi/Ky. wet ) jpCi /Kr. dry) gross beta 4
1x10*'
N.A.
N.A N.A.
N.A.
B-3 2000*
N.A N.A N.A N.A.
N.A.
Mn-54 15 N.A.
130 N.A.
N.A.
N.A.
Te-59 30 N.A.
260 N.A.
N.A.
N.A.
Co-58,60 15 N.A.
130 N.A.
N.A.
N.A.
2n-65 30 N.A.
260 N.A.
N.A.
N.A.
Ir-95 30 N.A.
N.A.
N.A.
N.A.
N.A.
Nb-95 15 N.A.
N.A.
N.A.
N.A.
N.A.
1-131 1**
7x10
N.A.
1 60 N.A.
Cs -134 15 5x10
130 15 60 150 Cs-137 18 6x10*#
150 18 80 180 W$$
ta-140 60 N.A.
N.A.
60 N.A.
N.A.
La-140 15 N.A.
N.A.
15 N.A.
N.A.
- If no drinking water pathway exists, a value of 3000 pCi/L may be used.
- If no drinking water pathway exists, a value of 15 pCi/L may be used.
Reformatting / Repagination changea on!y 01461 s
- *;, ;N !s 1
- n. <:u
,..\\
V e
e.Y.* A l*h '," es
- "_h,
.,O
)
w (
- r??
?
sA s
s SON ODCM Revision 24 Page 135 of 156 Table 3.2 (Page 2 of 2)
MAX 1 MUM VALUES FOR THE LOWER LIMITS OT DETECTION (LLD)
TABLt NOTATION a The LLD is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sarrple that will i
yield a net count above system background that will be detected with 95% probsbility with only a $1 probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66s.
LLD =
E V
2.22 Y
exp(-ut) i Vheres LLD is the "a priori" lower limit of detection as defined above in picoeurie per unit mass or volume,
- s. is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).
E is the counting efficiency as counts per disintegration.
V is the sample site in units of mass or volume, 2.22 is the number of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),
l K is the radioactive decay constant-for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
It should be recogniced that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not an a posteriori (after the fact) limit for a particular measurement. Analys'is will be performed in such a manner that the stated LLDs will be achieved under routine conditions.
b Other peaks which are measurable and-identifiable, together with the radionuclides in Table 3.2, shall be identified and reported.
N Reformatti.g! Repagination changes only 01461 s
a:
k k u nk n $ $ @ m u s w w a. a. m s g k w w w i k iin e
'?-?C,
- ?
~
. ~.. __ -._ _
Revision 24 i
Page 136 of 156 i
Table 3.3 l
P.tPORT!NC LEVELS TOR RADIDACTIVITY CONCINTMTIONS IN LhTIRONMENTAL $AMPLES l
Airbcrne Particulate Water or cens Fish Milk Toou Products Analysis IPCi/L)
(PCI /m'L.(201/Kr. wet )
(PCI/L)
(901/km. wet)
H-3 2 x 10**
N.A N.A N.A.
N.A.
Mn-54 1 x 10' N.A.
3 x 10' N.A.
N.A.
re-59 4 x 10' N.A.
1 x 10' N.A.
N.A.
Co-$8 1 x 10' N.A.
3 x 10' N.A.
N.A.
Co-60 3 x 10' N.A.
1 x 10' N.A.
N.A.
In-65 3 x 10' N.A.
2 x 10' N.A.
N.A.
tr Nb-95 4 x 10' N.A.
N.A.
N.A.
N.A.
1-131 2
O.9 N.A.
3 1 x 10 8
Cs-134 30 10 1 x 10' 60 1 x 10' Cs-137 50 20 2 x 10' 70 2 x 10' l
Ba-La-140 2 x 10' N.A.
N.A.
3 x 10' N.A.
l l
l (a) for drinking water samples. This is 40 CTR Part 141 value.
If no drinking water pathway exists, a value of 30,000 pC1/L stay be used.
(b) If no drinking water pathway exists, a value of 20 pCi/L may be used.
- ,eL
.. ~
Reformatting / Repagination changes only 01461 i
t
~!
s.
't BW5i&$bhCN5$0AUf%u&WwY SsM 5k$hi$1NS$$5'N'AA
$hbY
e l
SQN ODCM Revision 26 Page 137 of 156 Table 3.4 (Sheet 1 of 4)
RADIOLOGICAL ENVIR0hMENTAL MONITORING PROCPJJi Exposure Pathway Saepling and Type and Frequency
_and/or Sarnple Sample Locations
- Collection Frequency of Analysis l
l AIRBOLNE Particulates 4 samples from loca-Continuous sampler Analyse for gross tions (in different operation with beta rsdioactivity r
sectors) at or near sample collection
,1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> follow-the site boundary once per 7 days ing filter. change.
(1ti-2,3,4.and 5)
(more frequently Perform samma iso-if required by dust topic analysis on 4 samples from com-loading) each sample if-munities approx-gross beta > 10 imately 6-10 miles tiaes yearly mean distance from the of control sample.
plant. (PM-2,3.8 and 9)
Composite at least once per 31 days (by location for gamma scan).
4 samples from control locations greater than 10 miles from the plant (AM-1.2.3.and 4)
Radiolodine Samples from same Continuous sampler I-131 at least location as air operation with fil-once per 7 days particulates.
ter collection once i
W per 7 days Soil Samples from same Once per year Cama scan St-89, locations as air Sr-90 once per particulates year DIRECT 2 or more dosimeters Once per 92 days Cann.a dose at RADIATION placed at locations least once per (in different sectors 92 days i
i at or near the site boundary in each of the 16 sectors.
2 or more dosimeters j
placed at' stations l
located >5 miles from the i
plant in each of the 16 sectors i
I Sample locations are listed in Tables 3.5 and 3.6 and shown on l'isures 3.1, 3.2 and 3.3 Reformatting / Repagination changes only 01461 1
s g*
J e v
- g
,g p
P*
?O
. p.[M IhhdONk$
hN,Eh}lhWS_W,@b$%,u/Msdha___ b.O_
5 k Nib b
- ~
0 SON ODCM Revision 25 Page 138 of 156 l
Table 3.4 (Sheet 2 of 4)
RADIOLOGICAL ENVIROliMEliTAL MONITORING PROGRAM Exposure Tathway Sampling and Type and Faequency i
_.nndlar_SMPle SMric.10 Call 0_us
- Col]ErlionlIrunacy of Anhiy115 j
DIPECT 2 or more dosimeters RADIATION in at least 8 additional I
(continued) locations of special interest.
WATERBORNE Surface TRM 497.0 Collected by auto-Gamma scan of each TRM 483.4 matic sequential-composite sample.
TRM 473.2 type sampler ** with Composite for H-3 composite samples analysis at least collected at least once per 92 days once per 31 days Ground I sample adjacent to At least once per Gross beta and plant (location W-6) 92 days gamma scan, Sr-89 Sr-90 and H-3 an-1 sample from ground snalysis at least water source up-once per 92 days gradient Drinking 1 sample at the Collected by auto-Gross beta and first potable matic sequential gamma scan of
a surface water supply type sampler ** with each composite R25 downstream from the composite sample sample. Composite plant (TRM 473.0) collected at 1 cast for H-3, Sr-69, once per 31 days Sr-90 at least I sample at the next Grab sample once 2 downstream potable per 31 days surface water sup-pliers (greater than 10 miles downstream)
(TRM 470.5 and 465.3) 2 samples at control Samples collected by l
locations (TRM 497.0 automatic sequential and 503.8)***
type sampler ** with R25 composite sample l
collected at least once per 31 days.
- Sample locations are listed An Tables 3.5 and 3.6 and shown on Figures-3.1, 3.2 and 3.3
- Samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
l
- The surface water sample collected at TRM 497.0 is considered a control for the raw drinking water sample.
01461
0 e
59N ODCM Revision 25 Page 139 of 156 Table 3.4 (Sheet 3 of 4)
RADIOLOGICAL FNVIkONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and frequency and/or_Saule Smric_Lacationn*..fo1lert.Lon_.freguency oLAnalytin WATEkbORNE (continued)
Sedirnent TEM 496.5, TRM 483.4 At least once per Gamma scan of each TRM 480.8, TRM 472.8 184 days sample.
Shorellne TRM 485, TRM 47f At least once per Gamma scen of each TRM 477 184 days sample.
INGESTION Milk 1 sample from milk At least once por Gamma lootopic and producing animals In 15 days I-131 analysis of each of I-3 areas in-each sample. Sr-89 dicated by the cow St-90 once per census where doseh are quarter calculated to be highest.
If samples are not avall-able from a mlli anlmal i
location, doses to that area wl11 be estimated by psojecting the doses from concentrations detected In mllk from other sectors or N
samples of vegetation wlll be taken monthly where milk is not aval*able R25 At least I sample from a control location Fish 1 sample cach irom At least once per Gamma scan on Nickajack, Chicka-184 days.
One sam-edible portion mauga, and Watts ple of each of the-13ar Reservoirs following species:
Channel Catfish Crapple Smallmouth ButIalo
- Sample locations are listed In Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3 i
01461
S9N ODCM Revision 25 Page 140 of 156 Table 3.4 (Sheet 4 of 4)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sampling and Type and Frequency
_cAdLQL SONPlc sat?P1S3 0 CAL 19nt*
CQllettl0JLfteque.ncy oL ADAlIAis INGESTION (continued)
Invertebrates 2 samples downstream At least once per Gamma scan on (Asiatic Clams) from plant dischargo**
184 days edible portion I sample upstream from the plant **
Food I sample each of At least once per Gamma scan on Products principal food 365 days at time of edible portion products grown at harvest.
The types private gardens of foods available for and/or farms in the sampling will vary, immediate vicinity Following is a list of of the plant typical foods which may be available:
Cabbage and/or Lettuce Corn Green Beans Potatoes Tomatoes m.N Vegetation Samples from farms At least once per 1-131 and gamma producing milk 31 days scan at lea,st but not providing once per 31 days.
a milk sample Sr-89, Sr-90 (Farm Em) analysis at least once por 92 days.
Contrel sample from R25 one control dairy R25 farm (Farm S)
R25 i
- Sample locations are listed in Tables 3.5 and 3.6 and shown on Figures 3.1, 3.2 and 3.3
- Ho permanent stations established.
Locations depend on availability of:
clams.
01461
l 0
j S9N ODCM j
Revision 35 Page 141 of 156 Table 3.5 (1 of 2..
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS i
Map Approximate Indicator (I)
Location Distance or Samples
.Jhunktt 8 5tn11nn Seclet __.01112.5 )
._CDAt1ol iC)
C011Rcit4b 2
LM-2 N
0.8 I
LM-3 SSW 1.2 I
LM-4 NE 1.5 I
LM-5 NNE 1.8 I
PM-2 SH 3.8 I
PM-3 W
5.6 I
PM-8 SSW 8.7 1
-C AP, CT, S 13 RM-3 ESE 11.3 C
H 16 Farm C NE 16.0 C
H 17 Parm S HNE 12.0 C
M, V R25 18 Farm J WNW 1.1 I
M 19 Farm NW NW 1.2 I
M, WC 20 Farm EM N
2.6 I
V 24 Hell No. 6 HNE 0.15 I
W W
31 TRMd 473.0 11.58 I
PW (C. F. Industries) 32 TRM 470.5 14.0e I
pw (E. I. DuPont) 33 TRM 465.3 19.2e y
pw (Chattanooga) 34 TRM 497.0 12.5' Cf SH 35 TRM 503.8 19.3' C
PW (Dayton) 36 TRM 496.5 12.08 C
gw 42 TRM 472.8 11.7e I
01461 t
I I
l l
n.-.-
-,c..
___-___m.___________
e SON ODCM Revision 25 Page 142 of 156 1
Table 3.$ (2 of 2)
ElIVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Map Approximate Indicator (I)
Location Distance or Samples Rwnber
- Elation Sentor ___(B11ca L_.
fomtI.nl (C)_
CallatLedb 45 TRM 425-471 I
T (Nickajack)
Reservoir) 46 TRM 471-530 1/C T, CL R25 (Chickamauga Reservoir) 47 TRM $30-602 C
T (Watts Bar Reservoir) 48 Farm H HE 4.2 I
M a See figures 3.1, 3.2, and 3.3 b ggpt,cogen AP = Air particulate filter CT = Charcoal filter CL = Clams T =
Tish W
M =
Milk PW = Public water R =
Rainwater Soll S =
SD = Sediment SS = Shoreline sediment SW = Surface water V =
Vegetation W = Well water c A control for well water, d TRM = Tennessee River Mile.
o Distance from plant discharge (IRM 484.5) f Surface water-sample also used as a control for public water.
01461
S9N ODCM Revision 35 Page 143 of 156 Tab 3e 3.6 (1 of 2)
TilEkM0 LUMINESCENT DOSIMETRY LOCATIONS Map Approximate Onsite (On)a Location Distance or
_liebcI_
S.tation Str.Ltor IMilits )
Quattr-.IDLL1 3
SSW-2A SSW 1.2 On 4
NE-1A NE 1.5 On 5
NNE-1 NNE 1.8 On 7
SW-2 SH 3.8 Off 8
W-3 W
5.6 Off 9
SSW-3 SSW 8.7 Off 10 WSW-2A WSW 2.6 Off 11 SW-3 SW 16.7 Off 12 NNE-4 NNE 17.8 Off 13 ESE-3 ESE 11.3 Off 14 WNW-3 WNW 18.9 Off 49 N-1 N
0.6 On 50 N-2 N
2.1 Off 51 N-3 N
5.2 Off
$2 N-4 N
10.0 Off 53 NNE-2 NNE 4.5 Off 54 NNE-3 NNE 12.1 Off 55 NE-1 NE 2.4 Off 56 NE-2 NE 4.1 Off W
57 ENE-1 ENE 0.4 On
$8 ENE-2 ENE 5.1 Off 59 E-1 E
1.2 On 60 E-2 E
5.2 Off 61 ESE-A ESE 0.3 On R25 62 ESE-1 ESE 1.2 On 63 ESE-2 ESE 4.9 Off 64 SE-A SE 0.4 On 65 E-A E
0.3 On R25 66 SE-1 SE 1.4 On 67 SE-2 SE 1.0 On 68 SE-4 SE 5.2 Off 69 SSE-1 SSE 1.6 On 70 SSE-2 SSE 4.6 Off 71 S-1 S
1.5 On 72 S-2 S
4.7 Off 73 SSW-1 SSW 0.6 On 74 SSW-2 SSW 4.0 Off 75 SW-1 SW 0.9 On 76 WSH-1 WSW 0.9 On 01461 L
r,..
.,-m
.,-,-..v-..
,,..e.
---,-m..
,, -., - -... ~,..,., ~ -
_.~_.________._;
I SQW DDOM tevision 24 l' age 166 of 166 i
Table 3.6 (2 of 2) 1E kMOLUMINESCLN7 DOSIMITRY LOCATIONS Map Approxianste Onsite (On)'
Location Distance or Number S_tation Sector (Miles)
Off6fte (Off) 77 WSW-2 WSW 2.$
Off 78 WSW-3 WSW 3.7 Off 79 WSW-4 WSW 7,8 Off 80 WSW-5 WSW 10.1 Off 81 W-1 W
0.8 On 82 W-2 W
4.3 Off 83 WNW-1 WW 0.4 on 84 WNW-2 WNW 3.3 Off 85 NW-1 NW 0.6 On 86 NW-2 NW 5.2 Off-87
- NNW-1 NNW 0.6 on 88 NNW-2 NNW 1.7 On 89 NNW-3 NNW
$.3 Off i
W 1
a a
a.
TLDs designated cnsite are those located two alles or less f rom the plant.
TLDs designated offsite are those located more than two miles from the plant.-
. % 4.
.e Reformatting / Repagination changes only 01461
)
I p
2 0
'1-~.
V4M s4% % W h & gt h M 6 % @ W 6xan k k % _!h M Gia % %ka
_ ~
~
- ~
SON CDCH Havision 2$
Page 145 of 156 Figure 3.1 GASEOUS ErrLUENT RELEASE POIITTS Condenser Vacuum Exhaust' Shleid Building Vent (one per unti)
I (one per unit) j k l
(.wde. *)
j O 1,2-RE40-s ts.ts
'N'
'.2-RW-M-m U 1f T-~
TummMc Lij~g" y
McM TANKsp Y
CCWTAIHWINT gg i
m,,7, "O
I nooW Punet
~~
CONDENSER 0-Rt-to-tis g U t.2-RW-M-tao,13
....................u..........q y
y Service Building Vent I
A Avanne tsa.
d l wonoo.cf au Tucum t
YSTEW (ADM) au TREATWINT a o-at-so-tu r-j gy A
4
! " S(**)
Auxillary Building Vent h
% i.u.
mmy cum,.
yo-ar-,o-iot
,e 9.
CoNTANWENT AUXUARY vgyr I k soev..eenween ANNLUR5 VACUUW PRMNO FANS j
4 ANNLul$
t.
(2 Psn uMw)
$cmt t 1
01401 1
SQll ODCH Revision 25 Page 146 of 156 Figure 1.2 AUXILI ARY AlfD S!!! ELD !!UILDING VE!TTS (DETAIL)
Shield Butiding v.nt t,3-w-to-4oo g
r"- -- - i finerum.nt n
-H,f LN f ---- ---,"N h**d- --- _J J
-- J F
4 g,,44 4
l*'J cf _cw_ _.enm.nty 4
. H
._. H r..._._.___,
J d%.h'_"dJ j
- _ -.J' b
L.WNJ g,
i F. 7
- i y........-_....
8 4.jas.aen elj an.,.,,,.e,
f._.~._:An,m (o.so ml j k t
WW finn w l
"*"**)
i r>i J
~'
i l LS f
0" (""*b E
L_m.I i
m I
.]
m t.s q-N 4 A N I
l f
8
- We Auxillary i
pullding i
I m._.
I i
Vent l
Le!- i 4 L._.......__.
J g
v FJ F-I
. en 4 Awrs o-Rw-po-io10
! _ m-= j L_ _J
~
dl
.~.q Auxillory h*NJ
~N M
N
-- - - J Building *
-Nj i ***= =$3 b
~=
p j,.
.J
- ""*__J oWcrn tt 01461
.. ~. -. - _.
_ - - - - - -. -. ~
t i
1 SQW ODCN kovision 24 t
Page 147 of 156 Figure 1.3 SQW t.AND SITE. Bot /WDARY
/
\\
,o f
.J.
, l' u){%
,t
^'
% :i n
r c
/
iw.. h
[. /
J
\\,
..},
$ql
t
- t y
/ F-n/.
_4 i
l
/
s f,f pg
'r
./ef..
's, y
j W,..,
v
~
\\
kj
,,,, ~ p s4 e
4n t',,o*Y
_f'
/
-(
go 4%-
ikh hI S
\\
4
- 'W 7(/
.(
9 - Q, a
k).s 8
\\
\\
W d
8
.s u,c wL k4.J seu f.,
l,
,l.g d e @ w.afJ
/,
M weerp
,e "
... 6 **ubs si 6ru 4ee e
we.44 w g,,
,[
7
. Ylead A W$
Reformatting /Repaginetton changes only 01461 m a n u - u(- - a u s e a*
.)ye 4-n
.f
~
3 g -
i I
i 80W ODcN j
Revision 24 i
Page 148 of 156 I
rigure 1.4 CASEOUS RADWASTE TREAntCET SYSTEM CVCSVCT\\
Unit 1 /
~
Unit 2 /
CVCS HT WC5 RCOT \\
Unit 1
/
WCS HCDT \\
Unit 2 /
l l
1 e
Weste Cos Compressor h
Package Vent (typlcol of 2)
CVCLCVAPA o
immer Units 1&2/
r' CVCS HT l '
/
n Ml y
I E
M g-u J L f%
r%
f%
Wosts Cos Woote Goa Weste Goo Decoy Tonk Decoy Tonk Decoy innh M 1 f**8)
Me)
Mee)
(W of 7)
W
%.d v
- Reformatting / Repagination changes only 01461
. o..,
.J
. % 5;P-3,7;[i.:T4/h 55MOl%%k%dkNI&,$'k%A;55Rhuww%ssu+wsiiil$'n'ANtNM$50/N 4
s
-n
-..,,,n,....,n--..
.,,.,.--e,,~
d
e SQW ObCH Revision 24 Page 149 of 156 Figure 1.5 PLVME DEPLETION EFTECT FOR CROUND LEVEL RELEASES (All Stability Classes) 4 2
ag I
l' l
/
0
/
/
g 1
e}<
/
t 3
I I
E
/
/
r
]
l a
g x
I3 9
I I
I
/
l
/
c L
I i
o" q
m h
9 4
w M
N a
d W
o o
Wsc e o
d SWMd NI DNINIVWIW Noll3YW4 r
Refot1natting/ Repagination changes' only 01M1 i
b T
' i k
' '4%g -'
Q "f,4 4
I OE b
n F
5 NAk'k YY" NI A'd?'h*
>I.
s p
4 i
SQW ODCH Revision 24 Page 150 of 156 Figure 1.6 VERTICAL STAFDARD DEVIATION OF MATERIAL IW A PLUME 1000
/
/
3 I
A
/
/
/
/
/
/
/
I
/
/
r r
i r
s J
)
/
/
7 f
/
/
/
/
/
y
/
/
/
/
A 100
/
/
/
/
/
/
/
f nr a
1' D
/
/
./"
A
/
,F
,F
/"
2" d
/
/
/
/
/
/
g
/
?
/
J
-/
^
/ / /
CL//
f
/
f
/
,.A U
/
F
/
0 10 l
1
/
/
f
/
/
-P
/
/
/
/
l
/
/
/
/
/
/
/
' /
/
/
/
i
/
/
1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) i l
l l
{
.~.:.
Reformatting / Repagination changes only 01461 l
1 e
4k j
4
",,e.
- [.,
~
- s
$Yh'Y$ YNkke bkkb 'NH! $N l>
' 'IAN' '%Y$*l$ t $,! I $$: h h t*A I$$* U $
t
.,,.m. -.,
-.--m
e SQN ODCH Revision 24 Page 151 of 156 Figure 1.7 RELATIVE DEP051 TION FOR Ch'0VND LEVEL RELEASE 5 (All stability 71 asses) 1N t
w 1H
\\
N.
4 g
x, w
6 i
g
' u i
z N
l w
w w
T w
\\
E T
e
% g
$ 10-6
% (
A X
n
- - s E
A w
N o
N
\\
n s
5
\\
l e
104 N
10-7 0.1 1A
'10.0 100A 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
.~ e.:.
a-Reformatting /Repaginetton changes only 1
01461 a
60' f
f 4 k
%&5FS%"$Xi$i!$k:$WR$5Ein 4.:6%>.
'Lv " Mi4:H $$:5 t b 5 M & % ! N 5 5Y $
i
sim.
M,,j -
gW K:
o.
h-s.
Condensate j
Demineralizer:
Steam Generator Blowdown iTurbine Building vet
.c.
S System Unit 1 Unit 2 Sump 1
s/c s/c s/c s/c s/c s/c s/c s/c :
q n;,,, w see r r
W C
ro,,w
+
- 1: 12 73 74, Ii 12 EJ f4 :
Turbine eu:id;ng c -
S (2__0000 gol) l T
- surri, s
,E 5
l f fl f l f l f I f l f' U""' 9-_
t y;,p, g f
{
e=
e-au-m- :: []
s Temk 2 J2. -)
(20000 gof) a
=.
"") f 1
E 3
! ** " ) f I
ise -
'I~
Y:
22 1;4 g
Neutru4 rats.ee j
S/c Dreb= deem S/c h sc8D.!
II
~
Tonk e
n,,g y,4 sCBD s
g n,,g y,4 "f..
g (19000 got) l H/X H/X
{ f] f y
y n
I l
c.-
I l.cw Volume 5"5 non-n.eeim w. m e' 1f l f lf :'
4 we,i. ranu.
Yard weste g,
,c (isooo g i
-=-se-ini 3 []
-*=-*-inizi []
l Pond Treatment W
Pond E
e-h[
.[ compe it. *af " l M
l t-L_______
M
*-"-* 9 :
S k,.
=
g M
Radwaste O
0-Rnt-90-122 j
e.
g.
System j
I f
{_
- e
(*. n ure 2.2) e g
ya Diffuser
, m,
'h
- e
+
Tower pong R.iver re
'RCW coonng l fl f l fl r c
}
+
~ =g g
Q flOW glowdown klinimum 15000 gpm
+ '..
for dilution R2 N*.
$.g.%. y
^
hA ~'s.
t
SQW ODCM Revision 24 Page 153 of 156 Figure 2.2 1,IQUID RADWASTE SYSTEM Reccior Bubding M*E87 BdD#'h9 Droln Drolna t
l U
Trttjoted Droin Collector Tonk N*
noor Droin Collector Tonk (occasional use) i Chemical Droin 20 som I
Tonk 7
(600 goo Vendor Rodweste Dominerellter Weste System Evoporotor Lownery and
}
l I l
Hot Shower Tonks A & B e
20 gpm (600 gol) 1f 1I Weste Disilliste Tonks Cook Decon (8500 got)
Wonitor Tank Collector Tonk (22000 gol)
(IS000 gol) j f 125 9pm 125 gpm if
<rouun.r.aos.poth) 1 T l
(occoslonel releone poth)
I Pg D-RM-go-122 Il yTO C0QpNG TOWER BLOWDOWN Refotvatting/ Repagination changes only 4 61
+
8 y
(MRNNd5}$2hyNIfIidiiihk9 9k,EI9 4 "<>i'd*4'N bf Nb d M!Nb i
SON ODCM R3 vision 25 l' age 154 of 3 50 rigure 3.1 Environmontal RadioloDical Sampling Locations Within 1 Milo of Plant 348.76 N
11.26 NNW is L6 NNE 320. S 33.76 p
N
/
2 NE i
56.25 303.75 g
__' \\
87
\\
eNe WNW M81.25 ~~j/ n.1 e
3 QUOY Ar:
-Q
-E W-
- 5N gn
- NT.
- 6' n j s
^
266.75
,,s 101.26 76
'ki 64 WSW
'/.
O~
ESE YS 23e.2s' 0 96B
/
73
% /
)
g\\
s SW v#
gs SE s
1 e 8.7 5 ic i.2 s 3
-.- _. ? c ?_ __
l
O v
SQW ODCN Revision 24 Page 155 of 156 Figura 3.2 Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant 34a7s N
11.r s NNW NNE 8
an.7s see. s NW
[
8 NE 303.7s 86.26 20 48 p
56 WNW ENE e55 5,
k (4*
koIp@ peps as t.as 7 a.7 s 5
3 gg
~
W-1 i
-E 59 10 2
tsa.7s 77 86 1D t.2 s 8
69 l
I i
WuW 63 'ESE s
238.2s e
173.7s 3
'46 a7o l
s tacts s
188.78 scAtt
.6 1
2 MILES
'.+:
a-Reformatting / Repagination changes only 01461 b
.;g;g(pw'j[
F.
roi@sMsylfggfif(MN&,:qu@w m n..-;g-9pgjMlhyi@h.p$udfA%hd
o, SQW ODCM Revision 24 Page 156 of 156 rigure 3.3 i
Environmental Radiologica'l Sampling Locations l
l Greater Than 5 Miles From The Plant i
satte
?
.a.
Itse
~ ~>
asus as ts 9'
ry
- u.
303fs b
gg MJs e.n,1.n.
4 4
i
' em.
9 ~,,
S
.r.*-+
si. s W
4 e o=.-
ra.ta f
^
===-~ 9.
e.
r Y
J oo l
b.
e 3
f vm4=
'd 1
o I
(
tot t*
/@ *
-i N
{
.l
/
,, e =,\\ w, ew amosa
- 2 6 setts s om<
i
/
1 g
J attra iaeas Dow l
1882s gos.ts
.eu.
.,t Refonnatting/ Repagination changes only OM h
Y
,, l'
' d!b
,+
phMG2%lhishtMhWd%kmiy&5' +aezn$$$$UhOkWNS$