ML20090B664
| ML20090B664 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1991 |
| From: | Tremblay L VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-92-25, NUDOCS 9203040019 | |
| Download: ML20090B664 (133) | |
Text
- - ._ - . - _ _ - - _= _ - ._- - ___
VERMONT YANKEE ,
NUCLEAR POWER COllPORATION l Ferry Road. Biattleboro, VT 05301 7002
( l , ENGINE RING OrriCE
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E101 TCW V A Pi r.10 em "w e n February 28,1992 IIVY 92 25 United States Nuclear Regulatoly Commission A'ITN: Document Control Desk Washington, DC 20555
References:
- a. License No. DPR 28 (Docket No. 50-271)
Subject:
Vermont Yankee Effluent and Waste Disposal Semiannual Report for the Third and Founh Quaners,1991
Dear Sir:
Enclosed herewith please find one copy of the Vermont Yankee Nuclearrower Corporation subject te x>rt. This report covers the penod beginning July 1,1991 and ending December 31, 1991 anc; is submitted in accordance with our Tecfinical Specification 6.7.C.1 and 10CFR50.36a(a)(2). The annual dose summary to man for 1991 will be submitted in a supplemental report in accordance with Technical SpeciGeation 6.7.C. l.b.
We trust that the enclosed information is satisfactory; however, should you have any questions, please contact this office.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION (Y@V\ @ O . /.
Leonard A. Tremblay, Jr. '
Senior Liceitsing Engineer cc: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS 020163 ,
9 3 9203040019 911231 PDR ADOCK 05000271 (gl.
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EFFLUENT AND WASTE DISPOSAL .
SEMIANNUAL REPORT .!
FOR THIRD AND FOURTH QUARTERS, 1991-5 h
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Verinout Yankee Nuclear Power Station r'
8792R E
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ERRATA fn the Vermont Yankee Effluent and Waste Disposal Semiannual Report covering the third and fourth quarters of 1991, the following corrections should be L made
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None.
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.a. . . . _ _ _ _ _ . , _ - . _ _ _ , _ _ , _ - , _ . _ - - , , - - . _ . - . _ , _ , _ _ _ , _ , . _ , . . , . , , . _ - - .
IABLE_1A VermonLJ ankee Ef tluentand _W asic _ Dis pos aLSemi annuaLRepor t Third andlouritLQuarters,_1991 Gascona_.EL11uentn _Ewamation_oLA1LAcleases
__ Unit Quarter Quarter Est. Total 3 4 Errorm_1__
A. Fission and Activation Gases
~
I ulo.ta ltelenae ci 2.lb E10 2 .... . 1,18EiD3 :1.00EiDZ___
- 2. Averagc_rclease rate for period _.__.uC1/ set 3131E+01 1. 4flEiDL
__.32 d er.cen tsf_Ie. chi _Speci_11 mil % _.___ .
/
B. Iodines
__.l Jotallodine:131 Ci 1.53Er02 3 Q M .0Z__._:h 00Et01._
- 2. Ay.rIngt release rate for perind__.utilsec 1.95E-03 3 JJE-Q3__.
- 3. Perrenknf._Icchi_ Spec 2_lipit 1 C. Particulates
__1,J.aI11tulatts_xitiLI-1/ 2 > 8 days C1 3.42E-03. LDSE-02 15,00Et01_
- 2. Average release _ratn_ int _.feriod uCi/sec 4.31E 04 12 121_03_.
3,Je r. cent.oLInch,_ Spec 1_ limit _J _ __
4m Gross _nipha_. radioactivity Ci L16E 0h 3.15E-00__
D. Tritium
_ 1._.lota Lrelease c1 1,8AEt01 1.15EiOL - th00E10L._
_.__2.i_Ay e r n g e r e l.e a s e raic__ Lor _pntigd uCi/sec 2.34E+00 12AhE10D
_32._l' erc en t_o f._ Itch.uSp e c1_ limit 1 4
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8792R
IMLE_1B VermonLYankee Ef fluent _and _Was t e _Dispas aLSenilannua LReport Third._and_EcuttitQuulera,_1911 Gascous_Efiluenta ___ Elevated _Reicase (1)
Continuourdiode Batsidiode NuclidCA._Relcased UniL Quarter Quarter Quarter Quarter 3 4 3 4 I
1.s_EiEE #p.1_GASss Kryp(Un-85 Ci ND ND Kryplon-85tn ci 1.BQEiD0 lii9.9Ed.00
___ Krypton-32 C1 8.93Et0.0 2,93Et01 Y,rJSton-83 Ci 5.49.QE10Q 1 RlfiG1 Xenon-133 C1 1.59E400 4.Q_4E100 Xenon-135 Ci 8.29Ei,QO 2.61E101
___ Xenon-135m C1 4 4%EiO1 1.,lDEtQ2 .
Xenon-US_ C1 2t05Et02 _ _ _l,81EtQ2 Uniden.t.111sd Ci Tota 1 JDI_2crind_ Ci 2,26EiD2. 1_Q43103 _
2,_lodines Indin.e-131 C1 1.53E-02 2 14E-02 ladins-133 Ci 5 't9E-02 9.,D2E-0 2 Iodine-13S Ci 9.62E _Q2 1.28E-01 - __
Tntal_.f.oI_ period Ci- 1,06E 01 2m401-01 . . _ _
- 3. Particulates
. St ront iwn-89 Ci 9 6BE-04 1.74E-03 d irontium-90 Ci 5.76E-06 1,82E-05 Cesium-134_ Ci ED_ _ - 4.06E.:06 .
Cesium-137 C1 1.91h Q5_ 4.23E-05
___larimn-Lanthnaum:1!to Ci 1 42E-03' 5.65E-03 Ceriwn-141 Li 1.33E-Q3 1.98E-04 - - _
(1) There were nc batch mode gaseous rele:cce fer tM e reporting parind.
ND - Not detected at the plant stack.
8792R t
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! IABLLIC i
VermonLYankee EUluent_an d_W aate_ Dis po s a LEemiannuaLRe por t Ibird and_ Fourth Quarters _1991 Gasenus Ef fluents - Ground _LeyrLReleases (1)
Continuous _. Mode EatcitMode __
_NuclideE_ Released UniL Quarter Quarter Quarter Quarter 3 4 3 4 --
L._Eission_9as.es
.__ Krypton-85 C1. NIL Krypton-85m Ci 6.62E-01 Krypton-87 C1 3,22E+00 '(-
Krypton _BB C1 2,10E+00 \
__ Xenon-133 C1. 5t 34h0L____ -__
___ Xenon-135 C1 3dBEt0D _
____ Xenon-135m C1 2.13EiD1
__ Xenon-138 C1 .LQ3E+02 Unidentified Ci
____IntnLisr_ period _Ci__ 1.3hE102 L_.Indines Indine-131 CJ 9210E-03 _
___ lodine-133 Ci b11E-0.2 _ . -
Iodine-L35. Ci L33E-02__
1.21E-01 Total for pcgipd_._ _.____.C1.
1.__l'Ar_titulate s
_!it rontium-89 C1 1 ale-03
___Etrontium-90 C1 1.42E-05
_ _Cggium-134 Ci ND Cesium-137 Ci _ND _ . _ _ _
_ Earium-Lanthanum-1kQ Ci Z,DHE-03 _
Ceriurit-L41. Ci 8. 9 2E-0.5 (1) There were no batch mode gaseous releases for this reporting period. -
ND - Not detected at the turbine roof.
2792R
l IAELE_1D V.crmont_ Yankee Ef fluent _ and_Was te._DisposaLSemiannuaLRepor.t 1
IhirLanLfourth_ Quarters _1991 Gasecua_ Effluents - Montaut_ine Releases 2nese were no nonioutine or cecidental gaseous releases during the third or fourth quarters of 1991.
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IADLL2A VermonLJankee EtLluentand_Was t e_ Dis po s a LS emiannua LRepo r t Third and FourilLQuaricIs_1291 Liquid Ef fluents - Summati.on of All Re.ltanca There were no liquid releases during the third or fourth quarters of 1991.
y 8792R
IABLL2B YermonLYankec ELLluen Land _Wa ale _ Dis po s aLSemiannua LRepor t
'1hirLanLEcutth_QuaricIn__12.21 LiquiLEilluents. - MonInulint_.Releas_ eft There were, no nonroutine or accidental releases during the third or fourth quarters of 1991.
3 8792R
IAllLE_3 VarmonLYankee E U l uen tan LWa s t e_ Dis po s al_S emiannuaL Ae port Ihirsland Fourth OnattarS4_l H1 SolisLWante and IrradiatrLEucl_Shimesta A. Solid Waste Shipped Of f-Site for Burial ur D3 sposal ( 4c; 7 radiated Fuel):
__3nik._. 6-Month Est. Total
___l'ariosi ErLOL,l _
- 1. Type of Waste
- a. Spent resins, filter sludges, evaporator m3 2.90E+01 hoitoma, etc. 1,33EtD 2 Cg_
- b. Dry compressible waste, contaminated m 4.89E+01 eouiDment. etc. Ci 3.51E 01
- c. Irradiated components, control rods, m3 8.13E+00 el.c . Ci 1.8DEtDS
- 2. Estimate of Major Nuclide Composition (By Type of Waste):
- a. Cohalt-60 % 1.76I 01 Cealum-137 % 4.00E+00 linc-65 7,.__Ll0Et0L Cesiunt_13ft_3_LAQEtDD_
Cesium-137 % 1.54E+01 Nickel-63 % 8.0DE-DL_
Iron-T % 1,20E+01 c. Sobalt-hD % 9.32E+01 Iodine-131 % LD3ItQ1 Iron-55 L i,10E QQ._
_ Xenon-131m % _R,3DEt00 Nickel-63 7e_A,001-QL_
Cesium-134 % 6.70E+00 %
Bariam-140 % 5. 20Et00 %
Lanthanum-LIL QJ 5.20E+00 %
Nickel-63 % 2.30Etq0 %
- b. Iron-55 % 5,16Ed.01 %
Pobalt-60 % 1.76E+01 %
Zine-65 % L AQE+00 J Manganese-54 % 4.80X QQ %
- 3. Solid Waste Dieposition:
Number of Shipments tiode of TranERQLtation Deitination 13 Truck Barnwell, SC 1 Truck Richland, WA B. Irradiated Fuel Shipments (Disposition): None C. Supplemental information
- 1) Class of solid waste containers shipped: 46 A (unstable), 2A, AB, SC
- 2) Types of containers used: 46 Strong-tight Containers, 6 Type A, 5 Type B
- 3) Solidification agent or absorbent: None 8792R
IABLE SA VERHONT YANKEE JAN91-0EC91 METEOPOLOGICAL DATA JOINT FREQUfkCY DISTRIBUI!ON 297.0 FT WINO DAT A STABILITY CLASS A " LASS TREQUEhCV (PERCENT) s .14 WIND OIRECTION FROM SPEED (MPH) N NNE NE ENE E ESE SE SSE S SSW SW VSW W WNW NW NNW VRBL TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM 0
.00 .0a .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (1)
(2) .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 C-3 1
.00 .00 .00 B.33 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 B.33 (1)
(2) .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 47 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 (1) 8.33 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 8.33 (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 0 0 0 0 0 0 0 0 0 0 0 3 0 3 8 12 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 25.00 .00 25.00
.00 .00 .00 .00 .00 .00 .00 .00 .09 .00 .00 .00 .00 .00 .00 .04 .00 .04 (2) 13 18 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 25.00 .00 25.00 (2) .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .04 .00 .04 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 2 0 3 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 8.33 .00 16.67 .00 25.00
.00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .01 ,00 .02 .00 .04 (2)
GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 8.33 .00 B.33 (2) .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 01 .00 .01 ALL SPEEDS 1 0 0 1 0 0 0 0 0 0 0 0 0 1 0 9 0 12 (1) 8.33 .00 .00 8.33 .00 .00 .00 .00 .00 .00 ,00 .00 .00 B.33 .00 75.00 .00 100.00 (2) .01 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .11 .00 .14 (1)= PERCENT OF ALL C000 OBSERVATIONS FOR THIS PACE (2)= PERCENT Of ALL GOOD OBSERVATIDNS FOR THIS PER100 C= CALM -(WIND SPEED LESS THAN OR fouAL 10 .95 MPH)
TABLF SB VERMONT YANKEE JAW 91-DEC91 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUT10N 297.0 FT WikL DATA STABILITY CLAS' B CLASS FREQUENCY (PERCENT) = .70 WIND OlRECTION FROM SPEE0(MPH) N NNE WE ENE E ESE SE SSE S SSW SW WSW W WNW NV NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C3 0 1 1 0 0 1 1 0 0 0 0 0 0 0 0 0 0 4 (1) .00 1,69 1.69 .00 .00 1.69 1.69 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6.78 (2) .00 .01 .01 .00 .00 ,01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 47 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 0 4 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6.78 .00 6.78 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .00 .05 8 12 2 0 0 0 0 0 2 2 0 0 0 0 1 0 0 1B 0 25 (1) 3.39 .00 .00 .00 . 0') .00 3.39 3.39 .00 .00 .00 .00 1,69 .00 .00 30.51 .00 42.37 (2) .02 .00 .00 .00 .00 .00 .02 .02 .00 .00 .00 .00 .01 .00 .00 .21 .00 .30 13-18 0 0 0 0 0 0 0 1 0 0 0 0 0 0 1 6 0 8 (1) .00 .00 .00 .00 .00 .00 .00 1.69 .00 .00 .00 .00 .00 .00 1.69 10.17 .00 13.56 (2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .01 .07 .00 .10 19 24 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10 0 14 (1) 6.78 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 16.95 .00 23.73 (2) .05 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 12 .00 .17 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 3 0 4 (1) .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 1.69 .00 5.08 .00 6.78 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 ,04 .00 .05 ALL SPEEDS 6 1 1 0 0 1 3 3 0 0 0 0 1 1 1 41 0 59-(1) 10.17 1.69 1.69 .00 .00 1.69 5.08 5.03 .00 .00 .00 .00 1.69 1,69 1.69 69.49 .00 100.00 (2) .07 .01 .01 .00 .00 .01 ,04 .04 .00 .00 .00 .00 .01 .01 .01 49 .00 .- 70 (1)* PERCENT OF ALL GOOO OBSERVATIONS FOR THis PAGE (2)= PERCENT OF ALL GOOO OBSERVATIONS FOR THIS PER100 C= CALM (WIND SFEED LESS THAN OR EQUAL TO .95 MPH)
l l
TABLE SC VERMONT YAkKEE JAN91 DEC91 METEOROLOGICAL DATA JolNT FREQUENCY DISTRIBuil0N 297.0 FT WIND DATA $1 ABILIFY CLASS C CLAS$ FREQUENCY (PERCEkt) = 2.20 WIND DIRECTION FROM N NNE NE ENE E ESE SE SSE $ SSW SW WSW W WNW WW kNW VRBL TOTAL SPEE0(MPH) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM 0
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (1) .00
.00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .D0 . A .' .00 .00 .00 .00 .00 0 0 0 0 0 0 0 0 0 5 C3 0 1 0 2 0 0 1 1 (1) .00 .54 00 1.08 .00 .00 .54 .54 .00 00 .00 .00 .00 .00 .00 .00 .00 2.70
.00 .00 .02 .00 .00 .01 .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 .06 (2) .01
- 27 4-7 4 1 1 1 0 1 1 0 1 0 0 0 1 0 3 13 0 (1) 2.16 .54 .54 .54 .00 .54 .54 .00 .54 .00 .00 .00 .54 .00 1.62 7.03 .00 14.59
.00 .01 .01 .00 .01 .00 .00 .00 .01 .00 .04 .15 .00 .32 (2) .05 .01 .01 .01 0 5 2 13 6 0 0 1 1 3 5 20 0 69 8-12 8 3 1 1 (1) 4.32 1,62 .00 .54 .54 2.70 1.08 7.03 3.24 .00 .00 .54 .54 1.62 2.70 10.81 .00 37.30 (2) .10 .04 .00 .01 .01 .06 .02 .15 .07 .00 00 .01 .01 .04 .06 .24 .00 .82 13-18 7 1 0 0 0 0 0 2 3 0 0 0 1 3 7 28 0 52 (1) 3.78 .54 .00 .00 .00 .00 .00 1.08 1.62 .00 .00 .00 .54 1.62 3.78 1%.14 00 28.11 (2) .08 .01 .00 .00 .00 .00 .00 .02 .04 .00 .00 .00 .01 .04 .08 .33 .00 .62 0 0 0 0 0 0 0 0 0 1 2 0 21 0 27 19 24 2 0 1 (1) 1.03 00 .00 00 .00 .00 .00 .00 .00 .54 .00 .00 .54 1.08 .00 11.35 .00 14.59
.00 .00 .00 .00 .00 .00 .01 .00 .00 .01 .02 .00 .25 .00 .32 (2) .02 .00 .00 0 0 0 0 0 0 0 0 0 0 0 0 1 0 3 0 5 GT 24 1 (1) .54 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .54 .00 1,62 .00 2.70 (2) .01 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .01 .00 .04 .00 .06 6 4 6 4 16 10 1 0 1 4 9 15 85 0 185 ALL SPEEDS 22 1 1 (1) 11.89 3.24 .54 2.16 .54 3.24 2.16 8.65 5.41 .54 .00 .54 2.16 4.86 8.11 45.95 .00 100.00 (2) .26 .07 .01 .05 .01 .07 .05 .19 .12 .01 .00 .01 .05 .11 .18 1.01 .00 2.20 (1)= PERCENT OF ALL GOOD 08 SERVAT 10NS FOR THIS PACE (2)sPERCENT OF ALL C000 OBSERVA110NS FOR THIS PERICO C= CALM (WIND SPEE0 _ESS THAN OR EQUAL TO .95 MPH)
- - - - ~ ~ "
'" - - ~ ._ _____
TABLE 5D VERMONT YANKEE JAN910EC91 METEOROLOGICAL DATA J0thi FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS D CLASS FREQUENCY (PERCENT) = 47.39 WIND OIRECTION FROM N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL SPEED (MPH) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM 0 0 0
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (1) .00
.00 .00 .00
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) 36 27 12 9 12 12 11 31 44 0 455 C3 50 33 28 19 34 38 59 (1) 1.26 .B3 .70 48 .85 .95 1.48 .90 .68 .30 .23 .30 .30 .28 .78 1.10 .00 11.42
.39 .33 .23 .40 .45 .70 .43 .32 14 .11 14 .14 .13 .37 .52 .00 5.41 (2) .59 73 145 140 77 31 18 11 22 26 45 170 0 989 4-7 101 38 24 27 41 (1) 2.54 .95 .60 .68 1.03 1.83 3.64 3.51 1.93 .78 45 .28 .55 .65 1.13 4.27 .00 24.82 (2) 1.20 45 .29 .32 49 .87 1,72 1.67 .92 .37 .21 .13 .26 .31 .54 2.02 .00 11.77 8 12 132 30 9 9 20 41 79 129 194 37 38 37 70 113 60 193 0 1191 (1) 3.31 .75 .23 .23 .50 1.03 1.98 3.24 4.87 .93 .95 .93 1.76 2.84 1.51 4.84 .00 29.89 (2) 1=57 .36 11 11 .24 49 .94 1,53 2.31 .44 45 44 .83 1.34 .71 2.30 .00 14.17 13 1* tS9 39 8 2 5 8 5 10 71 25 12 16 85 156 108 229 0 948
- f. ) 4.24 .98 .20 .05 .13 .20 .13 .25 1.78 .63 .30 40 2.13 3.92 2.71 5.75 .00 23.80 (2) 2.01 .46 .10 .02 .06 .10 .06 .12 .84 .30 .14 .19 1.01 1.86 1.28 2.72 .00 11.28 0 0 0 3 2 12 3 0 0 29 50 46 91 0 302 19 24 63 2 1 (1) 1.58 .05 .03 .00 .00 .00 .08 .05 .30 .08 .00 00 .73 1.26 1.15 2.28 .00 7.58 (2) .75 .02 .01 .00 .00 .00 .04 .02 .14 .04 .00 .00 .34 .59 .55 1.08 .00 3.59 0 0 0 0 0 0 0 0 0 0 0 5 12 16 45 0 99 GT 24 21 (1) .53 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 13 .30 40 1.13 .00 2.48
.25 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 00 .06 .14 19 .54 .00 1.18 (2) 76 223 368 306 772 0 3984 ALL SPEEDS 536 142 70 57 100 160 291 317 381 108 77 (1) 13.45 3.56 1.76 1.43 2.51 4.02 7.30 7.96 9.56 2.71 1.93
- 91 5.60 9.24 7.68 19,38 . .00 100.00 (2) 6.38 1.69 .83 .68 1.19 1.90 3.46 3.77 4.53 1.28 .92 90 2.65 4.38 3.64 9.18 .00 47.39 (1) PERCENT OF AR GOOD OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL C000 OBSERVATIONS f 0R THis K (100 C= CALM (WIND SPEED LESS THAN OR EQUAL 10 .95 MPH)
TABLE SE VERMONT YANKEE JAN91-DEC91 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WINO DATA STABillTY CLASS E CLASS FREQUENCY (PERCENT) = 33.21 WIND OIREC110N FROM N NNE NE ENE E ESE SE SSE $ S$W SW WSW W WNW NW kNW VRBL TOTAL SPEED (MPH) 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1 0 2 CALM
.00 .00 .00 .00 .00 .30 .00 .04 .00 .00 .00 .00 .00 .00 .00 .04 .00 .07 (1)
(2) .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .01 .00 .02 44 15 6 9 16 18 34 72 0 665 C3 87 52 50 43 54 69 74 22 (1) 3.12 1.86 1.79 1,54 1.93 2.47 2.65 1.58 .79 .54 .21 .32 .57 .64 1.22 2.58 .00 23.82 (2) 1.03 .62 .59 51 .64 .82 .88 .52 .26 .18 .07 .11 .19 .21 40 .86 .00 7.91 47 180 19 8 15 19 40 140 143 70 24 16 19 19 21 51 243 0 1027 (1) 6.45 .68 .29 .54 .68 1.43 5.01 5.12 2.51 .86 .57 .68 .68 .75 1.83 8.70 .00 36.78 (2) 2.14 .23 .10 .18 .23 48 1.67 1.70 .83 .29 .19 .23 .23 .25 61 2.89 .00 52.22 8 12 70 6 2 1 1 8 36 98 BS 36 15 16 40 54 45 209 0 725 (1) 2.51 .21 .07 .04 .04 .29 1.29 3.51 3.15 1,29 .54 .57 1.43 1.93 1.51 7.49 .00 25.97 (2) .83 .07 .02 .01 .01 10 43 1.17 1.05 .43 18 .19 48 .64 .54 2.*9 SO 8.62 15-18 31 1 0 1 0 0 3 25 37 18 3 4 24 39 .2 111 0 324 (1) 1.11 .04 .00 .04 .00 .00 .11 .90 1.33 .64 11 .14 1.00 1.40 .82 3.98 .00 11.60 (2) .37 .01 .00 .01 .00 .00 .04 .30 44 .21 .04 .05 .33 .46 .27 1.32 .00 3.85 0 0 0 0 8 0 2 2 6 5 13 0 44 19 24 5 0 1 1 1 (1) .18 .00 .00 .00 .00 90 .04 .04 .29 .04 .00 .07 .07 .21 .18 .47 .00 1.58 (2) .06 00 .00 .00 .00 .00 .01 .01 .10 .01 .00 .02 .02 .07 .06 .15 .00 .52 OT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 L 0 5 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .04 .04 .11 .00 18 (2) .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .01 .04 .00 06 A(L SPEEDS 3/3 78 60 60 7 117 254 312 225 94 40 50 105 139 159 652 0 2792 (1) 13.36 2.79 2.15 2.15 2.65 4.19 9.10 11.17 8.06 3.37 1.43 1.79 3.76 4.98 5.69 23.35 .00 100.00 (2) 4.44 .93 .71 .71 . 8s 1.39 3,02 3.71 2.68 1.12 48 .59 1.25 1.65 1.89 7.76 .00 33.21 (1)= PERCENT Of ALL GOOD OBSERVAll0NS FOR THIS PAGE (2)= PERCENT OF ALL GOOD 08SERVAfl0NS FOR THIS PERIOD Cs CALM (WINO SPEED gESS THAN OR EQUAL 10 .95 MPH)
F IAP,LE 5F VERMONT YANKEE JAN91 DEC91 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WINO DATA STABILITY CLASS F CLASS FREQUENCY (PERCENT) = 14,04 WINO DIRECil0N FROM SPEED (MPN) N NNE WE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL CALM 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .08 00 .00 .00 .08 (2) .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .01 .00 .00 .00 .01 C-3 42 42 25 25 38 36 47 37 27 19 10 8 12 14 22 37 0 441 (1) 3.56 3.56 2.12 2,12 3.22 3,05 3.98 3,14 2.29 1.61 85 .68 1.02 1.19 1.86 3.14 .00 37.37 -
(2) .50 .50 .30 .30 .45 43 .56 .44 .32 .23 .12 .10 .14 .17 .26 .44 .00 5.25 47 54 11 5 4 12 40 101 94 39 16 11 9 13 14 29 B4 0 536 (1) 4.58 .93 42 .34 1.02 3.39 8.56 7.97 3.31 1.36 93 .76 1.10 1.19 2.46 7.12 .00 45.42 (2) .64 .13 .06 .05 .14 48 1.20 1.12 46 .19 .13 .11 15 .17 .34 1.00 .00 6.38 8 12 11 1 0 0 0 1 14 30 23 5 8 3 9 17 14 44 0 180 (1) .93 .08 .00 .00 .00 .08 1.19 2.54 1.95 .42 68 .25 .76 1.44 1.19 3.73 .00 15.25 (2) .13 .01 .00 .00 .00 .01 .17 .36 .27 .06 10 .04 .11 .20 .17 .52 00 2.14 13 18 1 0 0 0 0 0 0 0 4 1 1 0 2 3 3 6 0 21 (1) .08 .00 .00 .00 .00 .00 .00 .00 .34 .08 08 .00 .17 .25 .25 .51 .00 1.78 (2) .01 .00 .00 .00 .00 .00 .00 .00 .05 .01 .01 .00 .02 .04 04 .07 .00 .25 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .00 .08 00 .00 .00 .08 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 108 54 30 29 50 77 162 161 93 41 30 20 36 50 68 171 0 1180 (1) 9.15 4.58 2.*4 2.46 4.24 6.53 13.73 13.64 7.B3 3.47 2.54 1.69 3.05 4.24 5.76 14.49 .00 100.00 (2) 1.28 .64 .36 .34 .59 .92 1,93 1.92 1.11 .49 .36 .24 .43 .59 .81 2.03 .00 14.04 (1)= PERCENT OF ALL C000 OBSERVATIONS FOR THIS PACE (2)= PERCENT OF ALL G000 OBSERVATIONS FOR THIS PER100 C= CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MAH)
IARE 50 %
/
VERMONT YANKEE JAN91 DEC91 METEOROLOGICAL DATA JClNT FREQUENCY DISTRIOUTION 297.0 FT WIND DAT A STABILITY CLASS C CLASS FREQUENCY (PERCEN1) = 2.31 WIND DIRECTIDN FROM SPEED (MPH) N NNE ht ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 CALM 0 0 0
.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (1) .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 8 4 2 3 0 0 54 C3 4 3 2 4 1 3 1 8 5 5 1 (1) 2.06 1.55 1.03 2,06 .52 1.55 .52 4.12 2.58 4.12 2,06 2.58 1.03 1.55 .00 .52 .00 27.84 (2) .35 .04 .02 .05 .01 .04 .01 .10 .06 10 .05 .06 .02 .04 .00 .01 .00 .64 4-7 2 1 1 5 11 16 8 6 6 3 7 10 5 4 0 91 5 1 (1) 2.58 1.03 .52 .52 .52 2.58 5.67 8.25 4.12 3.09 3.09 1.55 3.61 5.15 2.58 2.06 .00 46.91 (2) .06 .02 .01 .01 .01 .06 13 .19 .10 .07 .07 .04 .08 .12 .06 .05 .00 1.08 8-12 4 0 0 0 0 0 2 12 2 4 1 4 2 6 0 5 0 42 (1) 2.06 .00 .00 .00 .00 .00 1.03 6.19 1.03 2,06 .52 2.06 1.03 3.09 .00 2.58 .00 21.65 (2) .05 .00 .00 .00 .00 .00 .02 .14 .02 .05 .01 .05 .02 .07 .00 .06 .00 .50 0 0 0 0 0 0 0 0 0 1 2 2 0 6 13-18 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .52 .00 .00 .00 .52 1.03 1,03 .00 3.09 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .01 .00 .00 .00 .01 .02 .02 .00 .07 19 24 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 1 (1) .00 .00 .00 .00 .00 .00 .00 .00 .52 .00 .00 .00 .00 .00 .00 .00 .00 .52 (2) .00 .00 .00 .00 ,00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .00 .00 .00 .01 GT 24 0 0 0 0 0 0 0 0 0 0 L 0 0 0 0 0 0 0 (1) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 (2) .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ALL SPEEDS 13 5 3 5 2 8 14 36 16 19 11 12 11 20 7 12 0 194 (1) 6.70 2.58 1.55 2.58 1.03 4.12 7.22 18.56 8.25 9.79 5.67 6.19 5.67 10.31 3.61 6.19 .00 100.00 (2) .15 .06 .04 .06 .02 .10 .17 43 .19 .23 .13 .14 .13 .24 .08 .14 .00 2.31 (1)= PERCENT OF ALL G000 OBSERVATIONS FOR THIS PAGE (2)= PERCENT OF ALL C000 OBSERVATIONS FOR THIS PER100 Ca CALM (WIND SPEED LESS THAN OR EQUAL TO .95 MPH)
l TABLE SH VERMONT YANKEE JAN91-DEC91 METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION 297.0 FT WIND DATA STABILITY CLASS ALL CLASS FREQUENCY (PERCENT) = 100.00 WIND DIREC110N FROM N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW VRBL TOTAL SPEED (MPH) 0 0 0. 0 0 0 0 0 1 0 1 0 3 CALM 0 0 0 0 1
.00 .00 .00 .01 .00 .00 .00 .00 .00 .01 .00 .01 .00 .04 (1) .00 .00 .00 .00
.00 .00 .00 .00 .01 .00 .00 .00 .00 .00 .01 .00 .01 .00 .04 (2) .00 .00 .00 C3 183 132 106 94 127 147 183 126 81 54 29 34 42 46 87 154 0 1625 (1) 2.18 1.57 1.26 1.12 1,51 1 . 75 2.18 1.50 .96 .64 .34 .40 .50 .55 1.03 1.83 .00 19.33 (2) 2.18 1.57 1.26 1.12 1.51 1.75 2.18 1.50 96 . 64 .34 .40 .50 .55 1.03 1.83 .00 19.33 4-7 345 71 39 48 73 159 398 393 195 77 51 42 62 71 133 518 0 2675 (1) 4.10 .84 .46 .57 .87 1.89 4.73 4.68 2.32 .92 .61 .50 .74 .84 1.58 6.16 .00 31.82 (2) 4.10 .84 .46 .57 .87 1.89 4.73 4.68 2.32 .92 .61 .50 .74 . 84 1.58 6.16 .00 31.82 40 22 55 135 2 84 313 82 62 61 123 193 124 492 0 2235 6 12 227 11 11 2.70 .48 .13 .13 .26 .65 1.61 3.35 3.72 .98 .74 .73 1,46 2.30 1,48 5.85 .00 26.59 (1) .00 26.59 (2) 2.70 .48 .13 .13 .26 .65 1.61 3.38 3.72 08 .74 . 73 1,46 2.30 1.48 5.85 3 5 8 8 38 115 45 16 20 116 202 144 385 0 1362 13 18 208 41 8 2.47 49 .04 .06 .10 .10 45 1.37 .54 19 .24 1.38 2,40 1.71 4.58 .00 16.20 (1) 10 (2) 2.47 49 .10 .04 .06 .10 .10 45 1.37 .54 19 .24 1.38 2.40 1.71 4.58 .00 16.20 0 0 0 4 3 21 5 0 2 32 60 51 137 0 392 19-24 74 2 1
.88 .01 .00 .00 .00 .05 .04 .25 .06 .00 .02 .38 71 .61 1.63 .00 4.66 (1) .02
.61 1,63 00 4.66 (2) .88 .02 .01 .00 .00 .00 .05 .04 .25 .06 .00 02 .38 71 _
0 0 0 0 0 0 0 0 0 0 5 15 17 55 0 114 07 24 22 0
.26 .00 00 .00 00 .00 .00 .00 .00 .00 .00 .00 .D6 18 .20 .65 .00 1.36 (1) .00 1.36 (2) .26 .00 .00 .00 .00 .00 .00 00 .00 .00 00 .00 .06 .18 .20 .65 ALL SPEEDS 1059 286 165 156 227 369 728 845 725 203 158 159 380 588 556 1742 0 00 100.00 8406 (1) 12.60 3.40 1.96 1.86 2.70 4.39 8.66 10.05 8.62 3.13 1.88 1.89 4.52 7.00 6.61 20.72 .00 100.00 (2) 12,60 3.40 1.96 1.86 2.70 4.39 8.66 10.05 8.62 3.13 1.88 1.89 4.52 7.00 6.61 20.72 (1)= PERCENT OF ALL 0000 DBSERVATIONS FOR THIS PACE (2)= PERCENT OF ALL 0000 OBSERVATIDNS FOR THIS PERIOD C3 CALM (WIND SPEED LESS THAN OR EQUAL 70 .95 MPH)
LPPENDIX A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT iupplemental Information Third and Fourth Quarters, 1991 Facility: Vermont._Yankec_Rualcar_fnEeLStation . .
Licensee: V.e rmont_Yanken_liuc le ar_Env er_Corpo r ation 1A. Technical Specification Limits - Dose and Dose Rate Ienhnic aLSpe cificatioitand_C ategory Limit
- a. Enble_Ganes 3.8.E.1 Total body dose rate 500 mrem /yr 3.8.E.1 Skin dose rate 3000 mrem /yr 3.8.F.1 Gamma air dose 5 mrad in a quarter . .
3.8.F.1 Gamma air dose 10 mrad in a year 3.8.F.1 Beta air dose 10 mrad in a quarter 3.8.F.1 Beta air dose 20 mrad in a year
- b. lodine-131 ulodine-133, Tritiua_and Radionuclides in Particulate Form With Half-Llyga ..
Gre.akcLIhaILS _ Days . . .
3.8.E.1 Organ dose rate 1500 mrem /yr 3.8.G.1 Organ dose 7.5 mrem in a quarter 3.8.G.1 Organ dose 15 mrem in a year
- c. Liquids 3.8.B.1 Total body dose 1.5 mrem in a quarter 3.8.B.1 Total body dose 3 mrem in a year 3.8.B.1 Organ dose 5 mrem in a quarter 3.8.B.1 Organ dose 10 mrem in a year A-1 8792R
"-"-- ~ - - - ~ - - - - - . - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ __
2A, Technical Specification Limits - Concentration IechnicaLSpe c i f i s ation_and_Catego ry LimLt
- a. Rohle_ Gates No MPC limits
- b. Indine-llL.ladine-131 mTritium_and Radionuclid e a_in_f a tticul at t_Intm_With Half-Lives Greater Than 8 D.ays: No MPC limits
- c. Liquids 3.8.A.1 Total fraction of MPC excluding noble gases (10CFR20, Appendix B.
Table II, Column 2): 11.0 3.8.A.1 Total noble gas concentration: 12E-04 uCi/cc
- 3. Average Energy Providedbelowaretheaverageenergy(5)oftheradionuclidemixturein releases of fission and activation gases, if applicable,
- a. Average gamma energy: 3rd Quarter 1.11E+00 MeV/ dis 4th Quarter 1.12E+00 MeV/ dis
- b. Average beta energy: Not Applicable
- 4. Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
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- a. Fission and Activation Gases Continuous stack monitors monitor gross Noble Gas radioactivity released from the plant stack. Total Noble Gas release rates are calculated using this monitor. On days the monitor shows less tha1 detectable release of fission gases, a zero release is considered.
To determine the isotopic breakdown of the release, samples are taken of the Steam Jet Air Ejector, which is the source gas for the releases. These samples are analyzed by gamma spectroscopy to determine the isotopic composition. The isotopic composition is then proportioned to the gross releases determined f rom the stack monitor to quantify the individu 1 isotopic releases. These are indicated in Table IB and the .als of Table 1A.
Beginning in the fourth quarter of 1991, grab samples were obtained from the Turbine Building roof vents. Only Xe-135 was detected in these samples. The remainder of the gases indicated were calculated by ratioing the indicated Xe-135 to t'e other gases using the Steam Jet Air Ejector samples as mentioned above. These results are indicated in Table 1C and the tatals of Table 1A.
The error involved in these steps may be approximately t100 percent,
- b. Iodines Continueus isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. Beginning in the fourth quarter of 1991, continuous particulate and charcoal samples were also taken at the Turbine Building roof vents. The filters and cartridges are normally removed weekly and are analyzed for Iodine-131, 132, 133, 134, and 135. The error involved in these steps may be approximately 150 percent.
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- c. Particulates The particulate filters described in b above are also counted for particulate radioactivity. The error involved in this sample is also approximately 150 percent.
- d. Liquid Effluents Radioactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liquid effluents released. For each batch, station records are retained of the total activity (mci) released, concentration (uCi/ml) of gross radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River.
Each batch of radioactive liquid effluent released is analyzed for gross gamma and gamma isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is also analyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition to gamma spectroscopy.
There were no liquid releases during the reporting period.
- 5. Batch Releases
- a. Liquid There were no routine liquid batch releases during the reporting period.
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- b. Gaseous There were no routine gaseous batch releases during the reporting period.
- 6. Abnormal Releases
- a. Liquid i
There were no nonroutine liquid releases during the reporting period.
- b. Gaseous There were no nonroutine gaseous releases during the reporting period.
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APPENDIX B i
LIQUID 110LDUP TANKS Requirement: Technical Specification 3.8.D.1 limits the quantity of radioactive material contained in any outside tank. With the quantity of radioactive material in any outside tank exceeding the limits of Technical Specification 3.8.D.1, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report per Technical Specification 6.7,C.1.
Respanne: The limits of Technical Specification 3.8.D.1 were not exceeded during this reporting period.
)
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APPENDIX C RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification Table 3.9.1. If an inoperable radioactive liquid effluent monitoring instrument is not returned to operable status prior to a release pursuant to Note 4 of Table 3.9.1, an explanation in the next Semiannual Effluent Release Report of the reason (s) for delay in correcting the inoperability are required per Technical Specification 6.7.C.1.
Reaponse: Since the requirements of Technical 'q,ecification Table 3.9.1 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required. .
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APPENDIX D RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Rc_quirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Tecnnical Specification Table 3.9.2. If inoperable gaseous effluent monitoring instrumentation is not returned to operable status within 30 days pursuant to Note 5 of Table 3.9.2, an explanation in the next Semiannual Effluent Release Report of the reason (s) for the delay in correcting the inoperability is required per Technical Specification 6.7.C.l.
Reappnae: Since the requirements of Technical Specification Table 3.9.2 governing the operability of radioactive gaseous ef fluent a monitoring instrumentation were met for this reporting period, no response is required.
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APPENDIX E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Bequirement: The radiological environmental monitoring program is conducted in accordance with lechnical Specification 3.9.C. With milk sampics no longer available from one or more of the sample locations required by Technical Specification Table 3.9.3 Technical Specification 6.7.C.1 requires the following to be included in the next Semiannual Effluent Release Report:
(1) identify the cause(s) of the sample (s) no longer being .
available, (2) identify the new location (s) for obtaining available replacement samples and (3) include revised ODCM figure (s) and table (s) reflecting the new location (s).
Resitonse: The dairy f am at Station TM-16/TC-16 went out of business and was sold at auction in July of 1991. A substitute location was chosen to replace it, and the first samples were collected there in July of 1991. The new milk and cattle feed sampling location is designated TM-15 and TC-15 (for milk and cattle feed, respectively). These changes were made to the ODCM as Revision 11. The changed ODCM pages are attached to Appendix 11.
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s____ .
APPENDIX F i 1AND USE CENSUS Requirement: A land use census is conducted in accordance with Technical Specification 3.9.D. With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.8.G.1, Technical Specification 6.7.C.1 requires the identification of the new location (s) in the next Semiannual Effluent Release Report.
BCEponse: No locations were identified by the 1991 land use census that '
would yield at least a 20 percent greater dose or dose commitment than the values currently being calculated pursuant to Technical Specification 4.8.G.I.
1 w
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APPIWDIX G
! PROCESS CONTROL PROGRAM Requirement: Technical Specification 6.12.A.1 requires that licenseo initiated changes to the Process Control Program (PCP) be submitted to the Commission in the Semiannual Radioact ive Effluent Release Report for the period in which the crange(s) was made.
Response: The Process Control Program was revised to include the following paragraph at the end of Section 3.0 during this reposting period:
" Vendor supplied or temporary methods of processing resins may be used in lieu of the above process provided that the vendor or temporary process meets the requirements of quality described above and does not conflict with accepted burial criteria or safety requirements. Such methods will be reviewed ani approved by the Plant llealth Physicist and the Radiation Protect.lon Supervisor prior to implementation."
This change did not reduce the overall conformance of the dewatered spent resins / filter media vaste product to existing criteria for solid waste shipments and disposal. It allows the use of qualified vendor supp'.ied or temporary methods of processing resins.
The revised PCP is attached.
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I D
VERMONT YANKEE NUCLEAR POWER CORPORATION PROCESS CONTROL PROGRAM REV 2 09/18/91 Submitted d 66 ~
- //
Radiation Protection Supervisor mmd Approved M PORC.
Approved b Plant Manager Approved y cy & ON
! Sr. Vice Pres [ddnt, Operations l
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MhDikieDMM(RIM % RUM @
Page 1 of 4 VERMONT YANKEE NUCLEAR POWER CORPORATION PROCESS CONTROL PkOGRAM
==
Introduction:==
describes The Vermont Yankee Nuclear Power Corporation Process Control Program (PCP) the administrative and technical controls on the radioactive waste systems which provide aseurances that Vermont Yankee meets federal shipping and burial site requirements.
The PCP describes process parameters, controls, and sampling to ensure compliance with 10 CFR Part 71, 10 CFR Part 61, Department of Transportation, state, and burial site regulation requirements.
1.0 Solidification Vermont Yankee Nuclear Power Corporation does not routinely solidify liquid waste.
If the use of solidification to dispose of any liquid waste is required, it will be done by an outside vendor under the vendor's PCP. This PCP will be reviewed and approved by the plant Health Physicist, and the Radiation Protection Supervisor prior to implementation. This review is to identify that there is sufficient supporting documentation of the vendor's PCP to give assurance that the final product will meet all requirements for transport and burial, and that sufficient procedural c6ntrols exist to assure safe operations.
2.0 Cartridae Filter Elements Filters Cartridge filter elements will be air dried and compacted as dry active waste.
that are too radioactive to be disposed of in this manner will be placed in spent resin liners for disposal.
3.0 Resins Vermont Yankee for many years has produced radioactive waste in the form of dewatered resins. The method employed for dewatering is a Bird centrifuge. The resin is then discharged via a hopper into a burial container formed to fit into an approved shipping cask.
Commercial ion exchange resins have a certain moisture content in the form of bound Beyond this, ion water resulting from the hygroscopic properties of the resin.
exchange resins can take up free water or surface water which can be removed by centrifuging. The resulting moisture content is expressed in percent of moisture per weight of dry resin.
A number of methods can be used to determine the bound water in ion exchange resins.
Oven drying or azeotropic distillation are techniques which are generally used for high polymers. Vermont Yankee used oven drying to determine moisture content in the radioactive spent resins. Graver Water conditioning Company technical manuals were consulted for the moisture content of unused ion exchange resins.
._ _ _ _ .- ~- _ _ _ _ _ _-.__._ __ _
- Pago 2 of 4 t
Af ter centrifuging and discharge to the cask liner, a spent resin sample was obtained.
- The sample was immediately weighed, then oven dried for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and re-weighed. The moisture content of the centrifuged spent resin was calculated to be 59.6%.- The l
~
r.o teturo ccetent Y t2 e uwrid r.D,t ar n of r M ine to betwie s M c n( Mn
~
': M s rJ W the si5ent risihe a're" daw'aGNd 'shchthat ohly bouhd tiat~e t remains.
^
j l A second method was used to determine if vibration would leach water from the unused
- resin. A lab centrifuge was sat up with resin and resin plus filter aid mixtures.
l The centrifuge was set for 700 RPM for 30 minutes. No free water was observed in any
- of the mixtures.
t The results of theue tests showed that the moisture content of centrifuge processed I. resins was less than or equal to mixtures of unused commercial grade ion exchange
. resins. At these moisture contents, all the water remains bound even after severe i vibration in a centrifuge, therefore it is concluded that Vermont Yankee's centrifuged i spent resins do not include any free-standing liquids.
4 To comply with the statement, " Any liquida present in waste packages shall be non-corrosive with respect to the container", Vermont Yankee tested the pH of various resin j
i mixtures used by the plant in solution with water. The range was found to be 4.2 -
l 8.4. A solution is not considered corrosive to iron if the pH is greater than 4.0.
A resin sample is taken from each liner prior to shipment. The sample is counted to determine the activity and waste classification. The majority of the resins generated are Class A w&sta. All Class B or C resins will be disposed of in an apprwved High Integrity Container (HIC).
$ Vendor supplied or temporary methods of processing resina may be used in lieu of the j above process provided that the vendor or temporary process meets the requirements of 1 quality described above and does not conflict with accepted burial criteria or safety
] requirements. Such methods will be reviewed and approved by the Plant Health Physicist
}
and.the Radiation Protection Supervisor prior to implementation.
4.0 Filter Liners During refueling outages and normal operation, liquid radwaste processing may muire use of a decanting filter on the condensate phase separators. A floating suction is used to decant the water and resin into a filter liner. Filtered water is pumped form the liner. When use of the liner is completed, a vacuum pump is attached to dewater the rc. n in the liner. The liner is dewatered for a minimum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and until no more water is viewed from the pump discharge. A resin sample is taken from the liner and counted to determine the activity and waste classification.
5.0- Drv Active Waste (DAW)
All DAW is examined before being compacted. Any liquids or items found that would compromise the integrity of the package are removed and separated as specified by procedure. All waste is compacted into boxes using a box compactor. Containers used for DAW shipments moet the criteria of 49 CFR 173.425a. or - b. "No leakage of radioactive material" as specified in 49 CFR 173.425.b.1 will be met provided that no radioactive materials in quantities equal to or exceeding those specified in 49 CFR 173.443 are detected on the external surfaces of the package at any time during shipment.
1)3 Sw T11 cc s (: o 3 g: ;>, .
3
,7 m _
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Page 3 of 4 5.0 chalating lugnte Tr r de e t > :emW y wiD ll D ' F l '. - Hitting McP a are N rolled ny tium pla .t chemistry department using procedure Ap 0520 7.0 Exelosive Waste i
No waste capable of detonation or of explosive decomposition or reaction will be disposed as per 10 CFR 61.56(a)(4).
8.0 Toxie Waste No waste capable of generating toxic gases, vapore, or fumes will be disposed as per 10 CFR 61.56(a)(5).
i 9.0 Pyrochoric Waste No waste that is pyrophoric will be disposed as per 10 CFR 61.56(a)(6).
10.0 Mich Intecrity Containers ,
Vermont Yankee Nuclear Power Corporation has contracted with various suppliers of approved HICs. South Carolina has approved PCPs for HICs used by Vermont Yankee.
Any HIC Vermont Yankee may choose to use at some future time, will meet all applicable requirements.
11.0 Waste class Determination Vermont Yankee periodically performs laboratory analysis on all waste streams to determine the activity of radionuclides listed in Tables 1 and 2 of 10 CFR 61.
Correlation analysis shows that the relative concentration of each radionuclide, with respect to the overall activity in a given Vermont Yankee waste stream, remains constant over time. A set of scaling f actors is determined which allows the activity of 10 CFR 61 radionuclides to be estimated using the results of gamma spectrometric analysis or direct gamma dose rate measurements. -
For resin wastes, analysis is performed on samples of each source of resin comprising the contents of a burial container. Scaling factors are applied to the activity of radionuclides identified by gamma spectrometry analysis to determine the activity of those radionuclides which are not detected in the gamma spectrum.
For DAW, dose rate-to-curie conversion calculations are performed to determine the total activity present in a container. Scaling f actors are applied to the container's total curie content to determine the activity of individual radionuclides.
Once the activity of each radionuclide in a burial container is estimated, the waste classification is derived using methods required by 10 CFR 61.
Specific procedures for waste class determination are contained in AP 0504, " Shipping and Receiving of Radioactive Material".
Pags 4 of 4 PROC:::*.,:t:0 "!CM TMPLEMENT THE PCP 1). . 'AP O.E04 Shipment and Receipt of Radioactive hatettais 'l
- 2. OP 2511 Radwaste Cask, Drum and Box Handling
- 3. AP 0021 Maintenance Requests
- 4. OP'2151 Liquid Radwaste
- 5. OP 2153 Solid Radwaste
- 6. AP 0620 chemical Material control
APPENDIX H OFF-SITE DOSE CALCULATION MANUAL i
Reguir.cment : Technical Specification 6.13.A.1 requires that licensee ;
3 Initiated change; to the Off-Site Dose Calculation Manual (ODCM) be submitted to the CommiAsion in the Semiannual Radioactive a
', Effluent Release Report for the period in which the change (s) was made effective.
i Enannnan: There were two revisions to the Off-Site Dose Calculation Manual during this reporting period:
l j
l 1. The dairy farm at Station TM-16/TC-16 went out of business L and was sold at auction in July of 1991. A substitute location was chosen to replace it, and the first samples i
! were collected there in July of 1991. The new milk and
! cattle feed sampling location is designated TM-15 and TC-15 (for milk and cattle feed, respectively). Theec changes l 1 i
were made to the ODCM as Revision 11. They will not reduce the accuracy or reliability of dose calculations or setpoint determination. The changed ODCM pages are attached.
- 2. .The-Off-Site Dose Calculation Manual was amended to include i Method I off-site dose calculations for a ground level release f rom the Turbine Building roof vents. Method I dose model assumptions are conservative. They assume a ground level release receptor point at the site. boundary with the
-maximum atmospheric dispersion factors. At this location all possible-pathways are assumed to exist (e.g., ground plane, inhalation, garden, milk, and meat). These changes were made to the ODCM as Revision 12. This revision provides a method for integrating the measured releases from j the Turbine Building through the roof vents into the total I
(
release calculation for the plant. It will not reduce the l
accuracy or reliability of dose calculations or setpoint'
[
l- determinations. The changed ODCM pages are attached.
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VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULATION MANUAL REVISION ll 11
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Reviewed h 9/-$3 Plant' ' perations Review
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D&te ommittee Approved Plant"Mana er
\ / ?Date kSM Approved M I W"#/ /[/Date
- N Senior Vice President, Operations l
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Table 4.1 Radiological Environmental Monitoring Stations (l) ;
Exposure Pathway Sample Location Distance -
and/or Sample and Designated Code (2) (km)(61 Direction (6)
- 1. AIRBORNE (Radiolodine and Particulate) l AP/CF-il River Station 1.9 SSE No. 3.3 AP/CF-12 N. Hinsdale, NH 3.6 NNH AP/CF-13 Hinsdale Substation 3.1 E i AP/CF-14 Northfield, MA 11.3 SSE AP/CF-15 Tyler Hill Road (4) 3.2 HNW AP/CF-21 Spofford Lake 16.1 NNE
- 2. HATERBORNE
- a. Surface HR-11 River Station 1.9 Downriver No. 3.3 HR-21 Rt. 9 Bridge 12.8 Upriver
- b. Ground HG-11 Plant Hell --
On.31te
- WG-12 Vernon Nursing Well 2.0 SSC HG-22 Skibntowsky Hell 14.3 N
- c. Sediment SE-Il Shoreline Downriver 0.8 On-Site from SE-12 North Storm 0.15 On-Site Shoreline Drain Outfall(3)
- 3. INGESTION
- a. Milk TM-ll Miller Farm (4) 0.8 HHH TM-12 Dominick (5) 5.2 E TM-13 Newton Farm 5.1 SSE TM-14 Brown Farm 2.6 S TM-15 Gayland Farm 4.7 ugg/nw 1 TM-24 County Farm 22.5 N
- b. Mixed TG-l' River Station 1.9 SSE Crasses No. 3.3 TG-12 N. Hinsdale NH 3.6 NNE TG Hinsdale Substation 3.1 E .
TG-14 Northfield, MA 11.3 SSE TG-15 Tyler Hill Rd.(4) 3.2 HNH TG-21 Spofford Lake 16.1 NNE Revision 11 Date 7 /27/91 4-2 5713R/20.74
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Table 4.1 (continued)
Radiological Environmental Monitoring Stations (l) l Exposure Pathway Sample Location Olstance and/or Sample _ and Designated _ Code (2) (km)(6) Direction (6) j
- c. Silage ~
, .1 1 Miller farm (4) 0.8 WNW 12 Dominick (5) 5.2 E ,
TC-13 Newton farm 5.1 SSE TC-14 Brown farm 2.6 S TC-15 Gayland Farm 4.7 WNW/NW l TC-24 County farm 22.5 N
- d. Fish rH-11 Vernon Pond --
On-Site FH-21 Rt. 9 Bridge 12.8 Upriver
- 4. DIRECT RADIATION DR-1 River Station 1.6 SSE No. 3.3 ,
DR-2 N. Hinsdale, NH 3.9 f4NH DR-3 Hinsdale Substation 3.0 E DR-4 Northfleid, MA 11.0 SSE DR-5 Spofford Lake 16.3 NNE -
, DR-6 Vernon School 0.46 HSW OR-7 Site Boundary 0.27 W OR-8 Site Boundary 0.25 SH OR-9 Inner Ring 2.1 N OR-10 Outer Ring 4.6 N OR-11 Inner Ring 2.0 flNE DR-12 Outer Ring 3.6 NNE OR-13 Inner Ring 1.4 NE DR-14 Outer Ring 4.3 NE OR-15 Inner Ring 1.4 ENE DR-16 Outer Ring 2.9 ENE ,
DR-17 Inner Ring 1.2 E DR-18 Outer Ring 3.0 E OR-19 Inner Ring 3.5 ESE OR-20 Outer Ring 5.3 ESE DR-21 -Inner Rtng 1.8 SE DR-22 Outer Ring 3.2 SE DR-23 Inner Ring 1.8 SSE DR-24 Outer Ring 3.9 SSE ,
DR-25 Inner Ring- 2.0 5 Revislon 11 Date 7/27 /91 4-2a
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TG 12 AP/CF*12 s0 Hlf4SDALE , fl.H. A b
TC-15 TM-1$
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4 Apftp.11 i , A AP/CF 13 1
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I i m uwwaararau .1 8 vtFJCN CAM i t_______ _
IC'1' A AP/CF 11 VERilCft , V.I. wc 12 ','
1C 13 d TM 13 0
LILV P M K! LCM (TER$
Figure 4-2 Environmental Sa=pling Locations Vithin 5 k:n of Plant Revisioa _11_ Date 7/ 2791 L. 5
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VERMONT YANKEE NUCLEAR POWER STATION OFF-SITE DOSE CALCULAit^4 MANUAL REVISION NO 12 Reviewed T/ ?6 ['5! / -
Plant cJyrations Review Committee Da t e' Approved AMW '
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Date, PiggManager Approved 8t+1 ) f/#$h [
_/0 ate Sent ' f cif Pr nt, Operations
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Revision 12 Date 10/01/91
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e TABLE OF CONTENTS Page 111 LIST OF AFFECTED PAGES...........................................
DI SC LAI ME R OF R ES PONSI B I LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv r
ABSTRACT.................................................. ...... v -
viii LIST OF TABLES...................................................
x ,
LIST OF FIGURES..................................................
1.0 INTRODUCTION
..................................................... 1-1 1.1 Summary of Methods, Dose Factors, limits, Constants, Variables, and Definitions................................. 1-2 i 2.0 METHOD TO CALCULATE OFF-SITE LIQUID CONCENTRATIONS............... 2-1 E NG . -l 2.1 Method to Determine and F)NGC3 ............................
o 2.2 Method to Determine Radionuclide Concentration for Each Liquid Efflu'.nt Pathway........................... 22 ,
2.2.1 Sample Tanks Pathway............................... 2-2 l 2.2.2 Service Water Pathway................... .......... 2-3 2.2.3 Circulating Water Pathway................. ........ 2-3 3.0 0FF-SITE DOSE CALCULATION METH0DS................................ 3-1 3 .1. Introductory Concepts...................................... 3-2 3.2 Method to Calculate Total Body Dose from Liquid Releases................................................... 3-5
. 3.3 Method to Calculate Maximum Organ Dose from Liquid Releases................................................... 3-11 3.4 Method to Calculate the Total Body Dose Rate from Noble Gases................................................ 3-14 3.5 Method to Calculate the Skin Dose Rate from Noble Gases.... 3-20 3.6 Method to Calculate the Critical Organ Dose Rate from Iodhles, Tritium, and Particulates with T]/2 Greater Than 8 Days................................................ 3-26 3.7 ' Method to Calculatt the Gamma Air Dose from Noble Gases.... 3-30 3.8 Method to Calculato the Beta Air Dose from Noble Gases..... 3-34 3.9 Method to Calculat9 the Critical Organ Dose from Tritium.
Iodines and Particulates................................... 3-38 3.10 Receptor Points and Annual Average Atmospheric 3-44
- Dispersion Factors for Important Exposure Pathways.........
3.11 Method to Calculate Direct Dose from Plant Operation....... 48 3-56 3.12 Cumulative Doses...........................................
Revision 12 Date 10/01/91
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, TABLE OF CONTENTS (Continued)
Page 4.0 ENVIRONMENTAL MONITORING PR0 GRAM................................. 4-1 5.0 SETPOINT DETERMINATIONS.......................................... 5-1 5.1 Liquid Effluent Instrumentation Setpo1nts.................. 5-2 5.2 Gaseous , Effluent Instrumentation Setpoints................. 5-9 6.0 LIQUID AND GASEOUS EFFLUENT STREAMS, RADIATION MONITORS AND RADHASTE TREATHENT SYSTEMS................................... 6-1 6.1 In-Plant Liquid Effluent Pathways.......................... 6-1 6.2 In-Plant Gaseous Effluent Pathways. . .. .................. 6-3 REFERENCES....................................................... R-1 APPENDIX A: Method I Example Calculations....................... A-1 APPENDIX B: Approval of Criteria for Disposal of Slightly Contaminated Septic Waste On-Site a' Vermont Yankee............................. ................ B-1 APPENDIX C: Response to NRC/EGGG Evaluation of ODCM Update Through Rctision 4................... .............. C-1 Revision 12 Date10/01/91
-vil-8855R
. - . - - . = - . . . .
LIST OF TABLES ,
i Number Title Page 1.1-1 Summary of Radiological Effluent Technical Specifications and Implementing Equations 1-3 t 1.1-2 Summary of Methods to Calculate Unrestricted Area Liquid Concentrations 1-6 1.1-3 Summary of Methods to Calculate Off-Site Doses from Liquid Releases 1-7 1.1-4 Summary of Methods to Calculate Dose Rates 1-8 1.1-5 Summary of Methods to Calculate Doses to Air from Noble Gases 1-9 1.1-6 Summary of Methods to Calculate Oose to an Individual '
from Tritium, Iodine and Particulates 1 Suneary of Methods for Setpoint Determinations 1-11 l 1.1-7 Summary of Variables 1-12 1.1-8 Definition of Terms 1-16 1.1-9 l
1.1-10 Dose Factors Specific for Vermont Yankee for Noble Gas Releases 1-19 1.1-10A Combined Skin Oose Factors Specific for Vermont Yankee i Ground Level Noble Gas Release 1-20 1.1-11 Dose Factors. Specific for Vermont Yankee for Liquid Releases 1-21 1,1-12 Dose and Dose Rate Factors Specific for Vermont Yankee for Tritium, Iodine and Particulate Releases 1-22 ,
3.2-1 Environmental Parameters for Liquid Effluents at i Vermont Yankee 3-9 3.2-2 Usage Factors for Various Liquid-Pathways at Vermont Yankee 3-10 3.9-1 Environmental Parameters for Gaseous Effluents at Vermont Yankee 3-42 3.9-2 Usage factors for Various Gaseous Pathways at Vermont-Yankee 3-43 Revision 12 Date 10/01/91
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- .- - - ~
LIST OF TABLES Title Page Number l Vermont Yankee Dilution Factors 3 47 3.10-1 Radiological Environmental Monitoring Stations 4-2 4.1 ,
5.2-1 Relative fractions of Core Inventory Noble Gases After Shutdown 5-20 t
4 i
I i
i I
i l
l l
Revision 12 Date 10/01/91 I
-ix- l
- ~ ]
8855R .
5
LIST OF FIGURES Number Title Page 4 Environmental Simp 1tng Locations in Close Proximity to Plant 4-4 4-2 Environmental Sampling Locations Within 5 km of Plant 4-5 3 Environmental. Sampling Locations Greather Than 5 km from Plant 4-6 4-4 TLD Locations in Close Proximity to Plant 4-7 4 TLD Locations Within 5 km of Plant 4-8 1
4-6 TLD Locations Greater Than 5 km from Plant 4-9 i 1
6-1: Liquid Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Vermont Yankee 6-9 6-2 Gaseous Effluent Streams, Radiation Monitors, and Radwaste Treatment System at Vermont Yankee _ 6-10 Date 10/o1/91 12 Revision
-x-
- 8855R
Table 1.1-4 Summary of Methods to Calculate Dose Rates Reference Equation Equation Section 1 Number _ Category
_ Total Body Dose Rate j tbs gmrem) = 0.70 3'4'I 3-5 h1 DFB from Noble Gases yr 3 1
Released from Stack Total Body Dose Rate j tbg gmrem) 3'4*I 3-39 4.0 hi DFB from Noble Gases yr g 1
Released from Ground ST 3-7 Skin Dose Rate j skins g mrem y, yr {( gi OF,si 3.5.1 from Noble Gases Released from Stack Cl 3-38 Skin' Dose. Rate from Noble Gases j sking zmrem) yr
- [h 3
1 DF,gI 3.5.1 ,
Released from Ground l
Critical-Organ Dose .STP 3.6.1 3-16 .
Rate from Stack R cos r i Sico Release of Iodines, i Tritium, and Particulates with 7 1/2 Greater Than Eight Days 3.6,1 ,
Critical Organ Dose .GLP 3-40 .
DFG Rate from Ground R " 01 gggg cog r i Level Release of Iodines; Tritium, '
and Particulates with i 1/2 Greater Than Eight Days Reviston 12 Date lo/01/91 ,
1-8
-8855R
.- - . - - - - ..- - .. - .- .--~.. _
l Table 1.1-5 Summary of Methods to Calculate Doses to Air from Noble Gases Equation Reference Number Category Equation Section 3-21 Gamma Dose to Air ST 3*7'I DY Q1 DFY i
from Noble Gases airs (mrad) = 0.022 i Released from Stack Gamma Dose to Air 0 3'I'I 3-41 DYairg (mrad) = 0.13 0 i ' DF Yi '
from Noble Gases 3 Released from Turbine Building (Ground Level Release) 3-23 Beta Dose to Air O ST B 3.8.1.
- Q DF from-Noble Gases Dairs (mrad) . 0.019 -1 1 I
Released from Stack 3-43 Beta Dose to Air 0 3'0*I from Noble Gases Dalrg (mrad) i 0.55 g 0 i ' DF0i Released from Turbine Building (Ground Level Release)
{
i 12 10/01/91 Revision _ Date 1-9 8855R
,, ,, w ,+m+ -..sm,. .,ve-,,,-,,.en.,,,,,,v,-,- ,.m., ,-,,-r. e,. re-r,..,,., ,,,-,,-,--,,-nc--,, w-~, vnv,.,--n.,- we,--,,a--,.--mn- - - - - n,
Table 1.1-6 Summary of Methods to Calculate Dose to an Individual from Tritium, Iodine, and Particulates in Gas Releases and Direct Radiation Equation Reference Category Equation Section Number _
Dose to Critical E STP 3.9.1 3-25 DFG 3gg, Organ from Stack Dgg, (mrem) - Qg Release of Iodines, Tritium, and Particulates 3-44 Dose to Critical GLP DFG 3'9'I Organ from Ground D cog (mrem) = Q 1 gico 3
Level Release of Iodines, Tritium, and Particulates Direct Dose Turbine Building 3.11.1 3-27 Dd (*#'*) " K @ (L) *E North Warehouse 3.11.2 3-29 Shielded End D 3-0.25xk g 3.11.2 3-30 Unshielded End D U=0.53xk u LLW Storage Pad Direct Line (Module 3.11.3 3-31 Short Side Out)
D dE - 0.28 xd k
- Id Direct Line (Module 3.11.3 3-32 Long Side Out)
D dS - 0.39 xd k
- dI Skyshine (Resin 3.11.3 3-33 xf gg Liners)
D SKR=0.016xk ggg 3*II'3 3-34 Skyshine (DAW) D SKD-0.015xkSKD * #SK Resin Liner Trans- 3.11.3 3-35 xT Tran fer (Unshielded)
O Tran.0.0025xkTran Intermodular Gap x A RL
- I Gap 3.11.3 3-36 DGap - 2.44E-2 x Hg ,p Dose 0#0101 Revision [ Date 1-10 8855R
Table 1.1-8 Summary of Variables Variable Definition Units _
A 'q = Total gamma activity contained in a resin Cl liner in storage directly in line with a gap between adjacent storage modules ,
- Concentration at point of discharge of pC1/mi Ch dissolved and entrained noble gas "1" in liquid pathways from all station sources ,
- Total activity of all dissolved and entrained pCi Cf noble gases in 11guld pathwap from all T m
station sources ,
C d1
- Concentration of radionuclide "1" at the koint gQt of liquid discharge ml Cj - Concentration of radionuclide "i" gC1 CC C - Concentration, exclusive of noble gases, of p.Ci pj radionuclide "1" from tank "p" at point of ml discharge C
ml
- Concentration of radionuclide "1" in mixture gC i,
~at the monitor ml
- Beta dose to air from stack release mrad l Dfrs a
Dfrg - Beta dose to air from ground level release mrad a
- Gamma dose to air from stack release mrad Dfrs a
D,hg - Gamma dose to air from ground level release mrad D eg3 - Dose to the critical organ from stack release mrem D - Dose to the critical organ from ground level mrem egg- release D - Direct dose (Turbine Building) mrem d
l Revision 12 Date10/01/91 1-12 8855R l
XahAe_i d .B ;
(continued)
Summary of Variables Variable __
Definit 1on Units _
ma R = se ra e at r m un bst meted side of d storage module facing site boundary hr D = rec se a si e undary per unobstmeted E ,
dE storage module (short end) yr-module D = Direct dose at site boundary per unobstructed mrem _
dS storage module (long side) yr-module Y
D ggggg, = camma dose to air, corrected for finite cloud mrad M8 !
D = Intermodular tap dose projected to the 7#
0*E maximum site beundary location from resin waste not direc*.ly shielded by DAW modules.
= Dose to the maxinum organ mrem D,,
= Dose to skin from beta and gamma mrem D
Rg = Dose rate at 1 meter froe source in shielded stem end of North Warehouse hr Dg = Annual dose at site boundary from M ed sources mm in shielded end of North Warehouse yr R gg = Maximum dose rate at 3' aver top of DAW mrem in a storage module hr ,
R = Maximun, f ame re
- at 3' over top of each mr.cm 0 resin liner in a storage module hr
= Skyshine dose at the site boundary from DAW mrem D gg in storage modules (unobstructed top surfaces) yr-module
= Skyshine dose at the site boundary from resin mrem D gg liners in storage modules (unobstructed top yr-liner surfaces)-
Revision Date 1-13 8855R
.r..., - - . . - . _ . . . -. . . . . . ,-r _ . = . . _ _ , , . , _ . _ . . . _ _ . . - , _ . , , , . . , _ .- .m.. .._.
Trble 1.1-8
) (continued)
Summary of Variables Verlable DeLinition Un[t s .. ._
= Dose to the total body mrem D
T = e direct dose conversion factor for N-16 W/6 scatter from the turbine hall to Location (L) e R = Dose rate at contact from the unshielded top R_
Tm surface of resin liner hr ,
D = Dose at the site boundary f rom unshielded mrem I#"" movement of resin liner between transfer cask and storage module a
= Dose rate at 1 meter from source in unshielded mr.em Rg end of North Warehouse hr Dg = The annual dose at site boundary f rom fixed Etem yr sources in the unshielded end of North Warehouse ratio DF = Dilution factor ratio DF = Minimum all wable dilution factor min
= Composite skin dose factor mrem-Erc DF' pCi-yr c
DFB = Total body gamma dose factor for nuclide "i" f
DFB = Composite total body dose factor p DFL gty = Site-specWc, tots 1 body dose f actor for a mm liquid release of nuclide "i" Ci
.DFL g = Site-specific, maximum organ dose factor for a Mr.em liquid release of nuclide "i" Ci DFG = Site-specific, critical organ dose factor for a mram sie stack gaseous release of nuclide "i" Ci Revision Date 1-14 8855R 1
.,-w , , - _ . . . . . _ _ . _ . _ .
.,_-.---.~,,.,_.-,,y,cs,,, . . , - . _,m_,,.. . - _,- , , , . . .. - , , - . . - - - - - .
_. . _ . _. . _ . _ . _ - _ _ _ = _ . _ _ . _ . , _ . . _ _ _ - _ _ _ . -
. _ = _ . _ . _ . _ . _
S 4
Table 1.1-8 (continued)
Summary of Variables Variable Definition Units
= Site-specific, critical organ dose rate factor mrem-see DFG'ie s for a stack gaseous release of nuclide "1" pCi-yr DFG = Site-specific, critical organ dose factor for mrem 8C I a ground level gaseous release of nuclide "i" Ci
= Site-specific, critical organ dose rate factor mrem-sec DFG'IC" 8 for a ground level gaseous release of nuclide "i" pCi-yr 3
- '**~*
DFS i
= Beta skin dose factor for nuclide "i" pCi-yr i
- ""~"*
DF' = Combined skin dose factor for nuclide "i" Y II is from a stack release
- "*~"
DF' = Combined skin dose factor for nuclide "i" Y '~7# '
8 from a ground level release '
i 3
"'8
- DF = Camna air dose factor for nuclide "i" pCi-yr i
- DF g = Beta air dose factor for nuclide "i" ,
- "* I k- = Critical organ dose rate due to iodines 7#
"" and particulates released from stack l4 i
k = Critical organ dose rate due to iodines 7# '
- 8 and particulates released from ground k = Skin dose rate due to stack release of ##
sHns noble gases l R = Skin dose rate due to ground release of t skig noble gases Revision _l]_, DateIO/01/91 1-15 8855R i
I ,
,,..~,n.v. n,.---.-,,--,v- - - , . ,.- - -,- ,--.,,---n-,.,,,~n.,n.rn~,. , -,n-,--r.m,-,,,,a,,,,ci
Table 1.1-8 (continued) l Summary of Variables Definition Units Variable _
i
- '* I R - Total body dose rate due to noble gases yr l tbs from stack release l
R - Total body dose rate due to noble gases yr tbg from ground level release ,
D/0 - Deposition factor for dry deposition of 12 elemental radiciodines and other particulates m E
- Gross electric output over the period of MW'h interest f - Fraction of a year that a storage module is fraction d in use with an unobstructed side oriented toward west site boundary f - Fraction of a year that the intermodular gap fraction gap is not shielded f - Fraction of a year that a storage module is fraction gg in use with an unobstructed top surface F
- Flow rate out of discharge canal gpm d
Flow rate past liquid radwaste monitor gpm F
m F
- Flow rate past gaseous radwaste monitor ci set 0 - Total fraction of MPC in liquid pathways fraction F
(excluding noble gases)
- Maximum permissible concentration for gC1 MPC g cc radionuclide "i" (10CFR20, Appendix B, Table 2, Column 2)
- Release for radionuclide "1" from the curies Og point of interest Revision 12 Date 10/01/91 1-16 8855R
Table 1.1-8 (continued)
Summary of Variables i
Definition Units Variab2
- Release rate for radionuclide "1" pcuries Q,
at the point of interest sec i
.ST Q,
- The noble gas radionuclide "1" release gCi l rate at the plant stack sec l
.GL Qg
- The' noble gas radionuclide "1" release p.Ci rate from the Turbine Building (ground sec level release)
.SJAE - The noble gas radionuclide "1" release $
5'C 01 rate at the steam jet air ejector
.A0G Q-g The noble gas radionuclide "1" release rate aCl at the exhaust of the augmented Off-Gas System sec
.STP Qg The iodine, tr' tium, and particulate gC1 sec radionuclide "i" release rate from the plant stack
.GLP Qg
- The iodine, tritium, and particulate gCi radionuclide "1" release rate from the sec Turbine Building (ground level release)
- The release of noble gas radionuclide curies ST gi "1" from the plant stack i
- The release of noble gas radionuclide "1" from curles g GL the Turbine Building-(ground level release) i curies Q
P - The release of iodine, tritium, and particulate radionuclide "1" from the plant stack curies Q
- The release of lodine, tritium, and particulate -
radionuclide "1" from the Turcine Building (ground level-release) ,
i
= Liquid monitor response for the limiting cps
-R pt concentration at the point of discharge i
Revision 12 Date 10/01/91 1-17
. 8855R l
Iable _1.1-8 (continued)
Summary of Variables Variable Driinit.ica _1! nits _ _
" = Response of the noble gas monitor at the epm R'sp t limiting skin dose rate
= Response of the noble gas monitor to cpm R
spt limiting total body dose rate
= Shielding factor Ratio S
F S
= Detector counting ef ficiency f rom the most _ cpm _ # mRIhr_
3 recent gas monitor calibration pCi/cc pCi/cc S = Detector counting efficiency for noble _c pnL_ # mR/h _
E gas "i" pCi/cc pCi/cc S
= Detector counting efficiency from the most _cp t._
1 recent liquid monitor calibration pCi/ml
= Detector counting efficiency for _sps S
gg radionuclide "i" pCi/ml
= Time that an unshielded resin liner is hours T
Tran exposed in the storage pad area W = Intermodule gap width between adjacent DAW inches ap storage modules which shield resin liner storage modules from the west site boundary X/Q,
= Annual or long-tem average undepleted atmospheric dispersion factor for stack release m IEE X/Q = Annual or long-term average undepleted E atmospheric dispersion factor for ground level m release I#E
[X/Q} = Ef f ective annual or long-term average enna atmospheric dispersion factor m for stack release I#E
= Effective annual or long-term average 3
[X/Q}8 ganna atmospheric dispersion f actor m for a ground icvel release Revision 12 Date 10/01/91 1-18
. 885$R
I Table 1.1-10 Dose factors Specific for Vermont Yankee for Noble Gas Releases Ganna Combined Skin Total Body Beta Skin Dose factor Beta Air Gamma Air Dose factor Dose Factor (Stack Release) Dose Factor Dose factor 3 3 3 3
I Radionuclide DFB g (mrem-m pci-yr )0FS g (mrem-m pci-yr ) DFg g(mrem-sec) pCi-yr DF0 3 (mrad-m ) DFJ(mrad-m pCl-yr pCi-yr 8.84E-03* 2.69E-03 8.81E-03 3.28E-03 9.30E-03
'Ar-41 7.56E-08 ----- 1.49E-05 2.88E-04 1.93E-05 Kr-83m 1.17E-03 1.46E-03 1.83E-03 1.97E-03 1.23E-03 Kr-85m 1.61E-05 1.34E-03 8.16E-04 1.95E-03 1.72E-05 Kr-85
-Kr-87 5.92E-03 9.73E-03 1.06E-02 1.03E-02 6.17E-03 1.47E-02 2.372-03 1.32E-02 2.93E-03 1.52E-02 Kr-88 1.66E-02 1.01E-02 1.94E-02 1.06E-02 1.73E-02 Kr-89 1.56E-02 7.29E-03 1.70E-02 7.83E-03 1.63E-02 Kr-90 9.15E-05 4.76E-04 4.06E-04 1.11E-03 1.56E-04 Xe-131m 2.51E-04 9.94E-04 8.49E-04 1.48E-03 3.27E-04 Xe-133m 2.94E-04 3.06E-04 4.57E-04 1.05E-03 3.53E-04 Xe-133 3.12E-03 7.11E-04 3.03E-03 7.39E-04 3.36E-03 Xe-135m 1.81E-03 1.86E-03 2.60E-03 2.46E-03 1.92E-03 Xe-135 1.42E-03 1.22E-02 8.48E-03 1.27E-02 1.51E-03
-Xe-137 8.83E-03 4.13E-03 9.60E-03 4.75E-03 9.21E-03 Xe-138
- 8.84E-03 = 8.84 x 10-3 12 IO 0191 Revision Date 4 1-19 8855R ,
H l
1
- - . - . . = . - . . , , , - . , . _ _ . . _ - - _ . ~ _ . - _ . . , . -_ - . _ . . . - - - . . - . . , _ . . . . . .- - - . - ~ . . . - - - - _ . . _ . . _ _ _ _ . . - - . - - . _ . - - . .
1 Table 1.1-10A l l
Combined Skin Dose Factors Specific for Vermont Yankee Ground Level Noble Gas Releases
^$'
Radionuclide )
Of{a( v AR-41 8.75E-02 KR-83M 8.45E-05 KR-85M 3.08E-02 KR-85 2.34E-02 KR-87 1.96E-01 KR-88 1.08E-01 KR-89 2.52E-01 KR-90 1.98E-01 XE-131H 8.97E-03 XE-133M 1.87E-02 XE-133 6.87E-03 XE-135M 2.71E-02 XE-135 4.08E-02 XE-137 2.19E-01 XE-138 1.12E-01 l l
l Revision 12 Date 10/01/91 1-20 8855R e e-, - - -- ,
Table 1.1 11 Dose Factors Specific for Vermont Yankee for Liquid-Releases Total Body Maximum Organ Dose Factor Dose factor DFl DFL,,,(mrem}Ci Radionuclide itb ' mrem)
Ci 2.06E-04 2.06E-04 H-3 3.38E-02 3.38E-02 Na-24 6.96E-02 Cr-51 3.10E-04 l 2.08E-01 3.00E+00 Mn-54 8.53E-06 5.29E-03 -1 Hn-56-- '
2.49E-01 1. 84 E+ 00 Fe-59 5.97E 4.34E-01 Co-58 2.13E-01 1.28E+00 Co-60 1.64E+01 Zn-65 8.06E+00 2.55E-01 8.91E+00 Sr-89 1.67E+02 Sr-90 4.23E+01-4.21E-04 1.36E-01 Zr-95 4.51E-02 Mo-99 4.79E-03
- 5.04E-06 2.33E-04 Tc-99m 8.44E-03 2.22E-01 Sb-124 1.47E+01 I-131 2.57E-02 3.10E-06 1.29E-04 1-132 1.63E+00 I-133 3.31E-03 3.16E-04 5.90E-02 I-135 1.60E+02
'Cs-134 -1.28E+02 7.58E+01 1.21E+02 Cs-137 4.08E-03 9.72E-02 Ba-140 4.10E-02
-Ce-141 2.31E-05 1.18E-02 8.90E+00.
W-187-i i
Revision 12- Date 10/01/91 1-21 8855R l
Table 1.1-12 Dose and Dose Rate factors Specific for Vermont Yankee for Iodines, Tritium and Particulate Releases Stack Release Ground Level Release Critical Organ Critical Organ Critical Organ Critical Organ Dose factor Dose Rate factor Dose factor Dose Rate factor
- '*~5'C DFG gico(mrem-sec)
DFG OfG sico (*yr-pCi ) DFG gico (mrem)
Ci yr-pCi Radionuclide sito (mrem) Ci 1.81E-04 5.70E-03 5.23E-03 1.65E-01 H-3 1.10E-01 3.47E+00 3.17E+00 1.00E+02 C-14 3.80E-03 1.32E-01 5.63E-02 2.54E+00 Cr-51
- 4. 36E- 01 1.72E+01- 1.66E+01 7.47E+02 Mn-54 4.35E-01 1.44E+01 4.89E,00 1.62E+02 ,
Fe-59 2.26E-01 8.07E+00 4.55E+00 2.05E+02 Co-58 4.76E+00 2.12E+02 2.59E+02 1.17E+04 Co-60 2.32E+00 7.51E+01 2.57E+01 8.33E+02 Zn-65 7.08E+00 2.23E+02 7.88E+01 2.49E+03 Sr-89 2.69E+02 8.48E+03 3.01E+03 9.49E+04 Sr-90 4.31E-01 1.42E+01 4.83E+00 1.59E+02 Zr-95 7.86E-01 2.63E+01 8.86E+00 3.19E+02 Sb-124 1.51E+03 5.38E+02 1.?OE+04 I-131 4.80E+01 '
1.61E+01 6.81E+00 2.15E+02 I-133 5.12E-01 3.28E+02 1.1E+02 3.69E+03 Cs-134 9.88E+00 1.01E+01 3.44E+02 1.23E+02 5.55E+03 Cs-137 7.02E-02 3.27E+00 1.11E+00 3.56E+01 8a-140 3.37E+00 1.22E+00- 3.88E+01 Ce-141 1.06E-01 7.60E+01 2.69E+01 8.52E+02 Ce-144 -2.40E+00 l
12 10/0l!91 Revision Date 1-22 8855R
__ _ = - _ ___. _ __---___ _ _. . _ _ _ . . _ _ _ _ _ - . _ - _ . . _ _
time duration, this approach of limiting dose rates equivalent to the annual dose limits then assures that 10CFR20.106 limits on an annual average air concentration in unrestricted areas will be met.
Each of the methods to calculate dose or dose rate are presented in separate sections of Chapter 3, and are summarized in Tables 1.1-1 to 1.1-7.
Each method has two levels of complexity and conservative margin and are called Method I and Method II. Method I has the greatest margin and is the simplest; generally a linear equation. Method 11 is a more detailed analysis chich allows for use of site-specific factors and variable parameters to be selected to best fit the actual release. Guidance is provided but the <
appropriate margin and depth of analysis are determined in each instance at the.' time of analysis under Method II.
The plant has two gaseous release points: the main vent stack (elevated release) and the Turbine Building roof vents (ground level release). Therefore, total dose calculations for skin, whole body, and the critical organ-from gaseous releases will be the sum of the elevated and i
ground level doses.
I l
1 l
Date 10/01/9 12 Revision 34 8855R l
4 b----= - ... . .,._ ,, .. _ , ,. , , _ _ . _ . _ , _ _ _ _ ,
-3.4 Method to Calculate the Total Body Dose Rate from Noble Gases l Technical Specification 3.8.E.1 limits the dose rate at any time to the ,
total body from noble gases at any location at or beyond the site boundary equal to or less than 500 mrem / year. By limiting the maximum Rtb to a i
rate equivalent to no more than 500 mrem / year, assurance is provided that the total body dose accrued in any one year by any member of the general public cf eill be less than 500 mrem in accordance with the annual dose limits of 10CFR Part 20. to unrc4tricted areas.
Use Method I first to calculate the Total Body Dose Rate from the peak release rate via the plant stack and Turbine Building roof vent. Method I applies at all release rates.
Use Method II if Method I predicts a dose rate greater than the Technical Specification limit (i.e., use of actual meteorology over the- period of interest) to determine if, in fact, Technical Specification 3.8 E.1 had actually been exceeded during a short time interval.
_ Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant stack noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint
.is based on a value which corresponds to the off-site dose rate limit of Technical Specification 3.8.E.1, or a value below it.
Determinations of dose rates for compliance with Technical Specifications (3.8.E.1) are performed when the effluent monitor alarm '
setpoint is exceeded and the corrective action required by Specification 3.8 E.2 is unsuccessful, or as required by the notations to Technical Specification Table 3.9.2 when the stack noble gas monitor is ,
Revision 12 Date 10/01/91 3 14 8855R ,
-3.4.1 Method I The Total Body Dose Rate due to noble gases can be determined by multiplying the individual radionuclide release rates by their respective dose factors, summing all the products together, and then multiplying this total by a conversion constant (0.70), as seen in the following Equation 3-5 (an
, ' example calculation is provided in Appendix A):
it - 0.70 h3 DFB g (3-5) tbs 1 3
mrem pCi-ac pCl) mrem-m I I pCi-yr yr Cl-m 3 sec obere:
hf - In the case of noble gases, the release rate from the plant stack (pC1/sec) for each radionuclide, "i", identified. The release rate at the plant stack is based on the measuru radionuclide distribution in the off-gas at the Steam 4. Air Ejector (SJAE) during plant operation wnen the activity at the stack is below detectable levels, and the recorded total gas effluent count rate from the Stack Gas Monitor I or II. The release rate at the stack can also be stated as follows:
'SJAE S g L F (3-28) hST i
39 JAE i
pCl - (cpm) (pC1/cc) cpm (O
sec sec M - Plant Stack Gas Monitor I or II count rate (cpm).
Revision 12 Date 10/01/91 3-15 8855R
. - . . - . . - - - . ~ . - _ . - . - . - - .. - _ ~
i 1
S g. - Appropriate or conservative plant stack monitor detector counting efficiency for the given nuclide l mix (cpm /(pC1/cc)). l F - Stack flow rate (cc/sec).
hyJAE - The last measured release rate at the steam jet air ejector of noble gas i (pC1/sec). .
DFBj - Total body gamma dose factor (see Table 1.1-10).
For ground level noble gas releases, the tota _1 body dose rate is calculated as follows:
(3-39)
R tbg
- 4.0 hf DFB j 3
(p,CJ) (mrem-m ,
sec pC1-yr where: ,
hf - Ground level release rate (pC1/sec) of noble gas from Turbine Building.
During periods (beyond the first five days) when the plant is shutdawn and no. radioactivity release rates can be measured at the SJAE, Xe-i33 may be used in place of the last SJAE measured mix as the referenced radionuclide to determine off-site dose rate and monitor setpoints. In this case, the ratio of in Equation 3-28 above is assumed to eachhfAE tothesumofallhSJAE reduce to a value of 1, and the total body gamma dose factor DFB; for Xe-133 3
(2.94 E-04 mrem-m /pC)-yr) is used-in Equations 3-5 and 3-39. Alternately,
- a relative radionuclide "i" mix fraction (f,) may_ be taken from Table 5.2-1 as a
. function of time after shutdown, and substituted _in place of the ratio of hfAE tothesumofallh5JAE in Equation (3-28) above to determine the relative fraction of each noble gas potentially available for release to the
-.totP1 (example' calculations can be found in Appendix A). Just prior to plant startup before a SJAE sample can be-taken and analyzed, the monitor alarm Revision 12 Date 10/01/91 3-16 8855R f' .e-3 r-y-- --se-. 9 -=-tr yr y r-rr T1=e= V y -- e- 4- - =-e- -w
--- ~.----.. - _ __ __ _ _
l 1
l setpoints should be based-on Xe-138 as representing the most prevalent high dose factor noble gas expected to be present shortly after the plant returns to power. Monitor alarm setpoir ts which have _been determined to be conservative under any plant conditions may be utilized at any time in lieu of the above assumptions.
Equations 3-5 and 3-39 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event). and 2, Noble. gas releases via the plant stack,and Turbine Building roof vents to the atmosphere.
3.4.2 Basis for Method I Method I may be used to show that the Technical Specification which limits total body dose rate from noble gases released to the atmosphere '
(Technical Specification 3.8.E.1) has been met for the peak noble gas release rate.
Method I was derived from Regulatory Guide 1.109 as follows:
(3-6)
R tbs
= lE+06 5 7 [X/QF i
hf DFB g 3
mrem (pCi} ) I sec' <pCi' ' mrem-m }
- yr ' pCi m 3 sec pCl-yr ehere:
S - Shielding factor - 1.0 for dose rate determination.
F
[X/Q]{ = Maximum annual average gamma atmospheric dispersion factor for stack releases 3
- 6.98E-07 (sec/m )
Revision 12 Date)0/01/91 3-17 8855R
o Release rate from the plant stack of noble gas "i" (pC1/sec).
hf =
3 DFB - Gamma total body dose factor, ( ). See Table 1.1-10. l 3
Equation 3-6 reduces to:
tbs
= 0.70 hf DFB i (3-5) 3 (pCl-sec) i (mrem-m )
ggCl,)
(mrem) yr 3 set pCi-yr Cl-m For ground level releases, the ground level maximum annual average gamma 3
atmospheric dispersion factor = 3.95E-06 sec/m , thus leading to:
R tbg
- 1 +06
- 3.9H-06 hf DFB 9
(3-39)
'R tbg - 4.0 hf DFB g The selection of critical _ receptor, outlined in Section 3.10, is inherent in Method I, as are the maximum expected off-site annual or long-term average atmospheric dispersion factor!. Due to the holdup and decay of gases allowed in the A0G, off-gas concentrations at the plant stack during routine plant
_ operations are usually too low for determination of the radionuclide mix at the plant stack. It is then conservatively assumed that most of the noble gas activity at the plant stack is the result of in-plant steam leaks which are removed to the plant stack by building ventilation air flow, and that this air '
flow his an isotopic distribution consistent with that routinely measured at
,the SJAE.
Regarding the calculation of ground level release doses from the Turbine Building Roof Vent, the ground level atmospheric dispersion factors are based on the same methodologies as used for the stack dispersion factors Revisicn 12 Date 10/01/91 3-18 8855R
(same noble gas mix, meteorological history (1981-1985), and meteorological models), and are for the site boundary location that will have the highest dose.
In the case of noble gas dose rates, Method 11 cannot provide much extra lealism because R tbs and R tbg are already based on several factors which make use of current plant parameters However, should it be needed, the dose rate analysis for critical receptor can be performed making use of currer.t meteorology during the time interval of recorded peak release rate in place cf the default atmospheric dispersion factor used in Method I.
3.4.3 Method II If Method I cannot be applied, or if the Methot I dose exceeds the limit, then Method 11 may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 IReference A), except where site-specific models, data or assumptions are more applicable. The base ,
case analysis, documented above, is a good example of the use of Method II.
It is an acceptable starting point for a Method II analysis. Analyses requiring Method 11 calculations should be referred to YNSD to be performed and documented.
Revision 12 Date 10/01/91 3-19 8855R
- - - - ~ - - - _ _ , _ _
3.5 Method to Calculate the Skin Dose Rate from Noble Gases Technical Specification 3.8.E.1 limits the dose rate at any time to the skin from noble gases at any location at or beyond the site boundary to 3,000 3 mrem / year. By limiting the maximum R skin to a rate equivalent to no more than 3,000 mrem / year, assurance is provided that the skin dose accrued in any one year by any member of the general public is much less than 3,000 mrem.
Use Method I first to calculate the Skin Dose Rate from the peak
] release rate via the plant vent stack and Turbine Building roof vent Method
] I epplies at all release rates, j Use Method II if Method I predicts a dose rate greater than the Technical Specification limits (i.e., use of actual meteorology over the period of interest) to determine if, in fact, Technical Specification 3.8.E.1 had actually been exceeded during a short time interval.
Compliance with the dose rate limits for noble gases are continuously demonstrated when effluent release rates are below the plant Stack noble gas activity monitor alarm setpoint by virtue of the fact that the alarm setpoint is based on a value which corresponds to the off-site Technical Specification dose rate limit, or a value below it.
l Determinations of dose rate for compliance with Technical Specificaticns (3.8.E.1) are performed when the effluent monitor alarm setpoint is exceeded and the corrective action required by Specification 3.8.E.2 is unsuccessful, or as required by the notations to Technical Specification Table 3.9.2 when the stack noble gas monitor is inoperable.
Revision 12 Date 13/01/91 3-20 8855R l
l
3.5.1 Method I The skin dose rate due to noble gases is determined by multiplying the individual radionuclide. release rates by their respective dose factors, and summing all the products-together as seen in the following Equation 3-7 (an .l example calculation is provided in Appendix A):
. .ST R 01 0Fj (3-7) skins * ' \
(,my) gpCi) gmrem-sec) pCi-yr yr sec where:
hyT, .In the case of noble gases, the noble gas release rate from the plant stack (pC1/sec) for each radionuclide, "i", identified.
The release rate at the plant stack is based on the measured radionuclide distribution in the off-gas at the Steam Jet Air Ejector (SJAE) during plant operation when the activity at the e
stack is below detectable levels, and the recorded total gas effluent count rate from the Stack Gas Monitor I or II. The release rate at-the stack can also be stated as follows:
'SJAE Oi b (3-28) gST , M F I 59 JAE i
p2 ,
(cpm) (pCi/cc) (cc )
sec cpm sec 1
M = Plant stack gas monitor I or II count rate (cpm).
Sg - Appropriate or conservative plant stack monitor detector counting efficiency for the given nuclide mix (cpm /(pC1/cc)).
F = ' Stack flow rate (cc/sec).
hyJAE = The last measured release rate-at-the steam jet air ejector of noble gas I (pC1/sec).
0F's1
= combined skin dose factor (see Table 1.1-10).
for-stack release.
l For Turbine Building roof vent releases, the skin dose rate from noble gases is calculated by Equation 3-38:
l l Revision 12 Date10/ol/91 3-21
. 8855R l
~ _ . _ _ _ _ m_. . _ . . . . __ _____ _. _ . _ --
'GL '
sking." 0F' (3-38)
I ig ehere:
hf . The noble gas release rate from the Turbine Building (pCl/sec) for each radionuclide "1" identified.
1 Of j9 Combined skin dose factor for a ground level release (Turbine Building) (see Tacle 1.1-10A).
During periods (beyond the first five days) when the plant is shutocwn and no radioactivity release rates can be measured at the SJAF, Xe-133 may te used in place of the last SJAE measured mix as the referenced radionuclide to determine off-site dose rate and monitor setpoints. In this case, the ratio ofeachh tothesumofallh5]AE in Equation 3-28 above is assumed to ;
reduce to a value of 1, anc the ccmbined skin dose factor DF'g for Xe-i33 (4.57 E-04 mrem-sec/pCl-year) is used in Equations 3-7 and 3-38. Alternately,
-a relative radionuclide "1" mix fraction (f g ) may be taken from Table 5.2-1 as a function of time af ter shutdown, and substituted in place of the ratio of each h AE tothesumofallh in Equation 3-28 above to determine the relative fraction of each noble gas potentially availaole for release to t.9e 4
total (example calculattens can be found in Appendix A). Just prior to plant startup before a SJAE samole can be taken and analyzec, the monitor alarm setpoints should be based on Xe-138 as representing the most prevalent high dose factor noble gas expected to be present shortly after the plant returns to power. Monitor alarm setpoints which have.been determined to be conservative-under any plant conditions may be utilized at any time in lieu of the above assumptions.
Equations 3-7 and 3-38 can be applied under the following conditions i (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency _ event). anc
- 2. Noble gas releases via the plant stack and Turbine Building roof :
-vents to the atmosphere- .
Revision 12 Date 10/01/91 3-22 8855R T.
)
3.5.2 Basis For Method I The methods to calculate _ skin dose rate parallel the total body dose
- rate methods in Section 3.4.3. Only the differences are presented here.
Method I may be used to show that the Technical Specification which limits skin dose rate from noble gases released to the atmosphere (Technical Specification 3.8.E.1) has been met for the peak noble gas release rate.
Method I'was derived from Regulatory Guide 1.109 as follows:
D S
- 1.11 S F 0 i r, + 3.1?E+04 05 [X/Q)g DFS g (3-8) l 1
3 IpCi-yr) Ci (mrem}
yr
- (mrem) mrad
( ) (mrad) yr Ci-sec yr (sec}
m 3
mrem-m pCi-yr
)
where:
1.11 - Average ratio of tissue to air absorption coefficients will convert mrad in air to mrem in tissue.
- 3.17E+04 Og DFgY (3-9)
D tr [X/Q]s 1
pCi-yr (mrad) (Cl) yr (sec) mrad-m p -yr yr (Ci-sec) m 3
/ (3-10) now Dhnite" O air [X/Q]3 [X/Q)3 3
gmrad) (sec)
(mrad) yr- yr g3 (msec) l
( 3-11')
and Qg
- 31.54 Of (C_1) (Cl-sec) (pC_1 )
yr pCl-yr sec Revision 12 Date 10/01/91 3-23 8855R l
~ - , < , .
~
so kskins " I' F +06NQ){ f DF{ (3-12) 3 g
mrem ygmrem) <) (pCi) (sec) (pCl) gmrad-m )
yr mrad pC) 3 sec pCi-yr m
P.
+ 1E+06 X/0 3 i
L Of 9 3
Ci pCl, sec pCi (mrem-m )
(C1 ) ,3 sec pCi-yr substituting (X/Q)Y - 6.98E-07 sec/m3 X/Q - 5.99E-07 sec/m3 Sp - Shielding factor - 1.0 for dose rate determinations gl've s k skins - 0.77 i
f DF{
+ 0.60 i
(DB g (3-13) 3 3 (pCi-sec-mrem) (g) gmrad-m ) (DC1-sec) (pC1) (m_ rem-m )
gmrem) pC1-yr Yr 3 sec pCl-yr Ci-m 3 sec pC1-m -mrad
- h [0.77 DFj + 0.60 DFS g3 (3-14) i define (3-15)
DFj,-0.77DF{+0.60DFS j then k DFj, (3-7) skins -
(mrem)- gg) (mrem-sec) yr sec pC1-yr For determining combined skin doses for ground level releases (Turbine-3 Building), a YX/Q - 3.95E-06 sec/m and an undepleted X/Q g 3 g 1.74E-05 sec/m have been substituted into Equation-3-12 to give:
. Revision 12 Date 10 /01/91 3-24 8855R ,
- - ,.e ,
1 R
sking = l(4.38DF{+17.40FS) 3 then DF - (3-37) g 4.38DF{+17.4DFS $
and R DF (3-38) sking - g tshere :-
hf - The noble gas release rate from the Turbine Building (pC1/sec) for each radionuclide "1" identified.
f 0F,9
- Combined skin dose factor for a ground level release (Turbine Building) (see Table 1.1-10A].
The selection of critical receptor, as outlined in Section 3.10 is inherent in Method I, as it determined the ma'ximum expected off-site atmospheric dispersion factors based on past long-term site-specific meteorology.
Regarding the calculation of ground level release doses from the Turbine
- Building roof vent, the grou'nd level atmospheric dispersion factors are based on the same methodologies as used for the stack dispersion factors (same noble gas mix, meteorological history [1981-1985), and meteorological models), and are for the site boundary location that will have the highest dose.
3.5.3 Method II
~
If Meth.od I cannot be applied, or if the Method I dose exceeds the limit, then Method II may be applied. . Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The base case analysis, documented above, is a good example of the use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Method II
-calculations should be referred to YNSD to be performed and documented.
L l
i L Revision 12 Date 10/01/91 3-25 8855R
. - . .%....- -m.#.__ . . - - . . s .~.,
3.6 Method to Calculate the Critical Organ Dose Rate from lodines, Tritium and j Particulates with T l/2 Greater Than 8 Days f Technical Specification 3.8.E.1.b limits the dose rate to any organ, denoted R cg, from I-131, I-133, 3H, and radionuclides in particulate form with half lives greater than 8 days to 1500 mrem / year to any organ. The peak release _ rate averaging time in the case of iodines and particulates is commensurate with the time the iodine and particulate samplers are in service between changeouts (typically a week). By limiting the maximum k to a rate equivalent to no more than 1500 mrem / year, assurance is co provided that the critical organ dose accrued in any one year by any member of the general public will be less than 1500 mrem.
i Use Method I first to calculate the cit; cal vgan dose rate from the peak release rate via the plant vent stack and Turbine Buildi7 roof vent. l Method I applies at all release rates. 4 i
Use Method II if Method I predicts a dose rate greater than the Technical Specification limits (i.e., use of actual meteorology over tne period of interest) to determine if, in fact, Technical Specification 3.8.E.1.b had actually been exceeded during the sampling period.
3.6.1 Method I The critical organ dose rate from stack releases can be determined by multiplying the individual radionuclide stack release rates by their respective dose factors and summing all their products together, as seen in the following Equation 3-16 (an example calculation is provided in Appendix A_):
k eg3 =
[ DM sgcg (3- W (mrem) (pCI)_(mrem-sec) yr sec pC1-yr Revision 12 Date 10/01/91 3-26 8855R e--, . -.
where:
hSTP - Stack activity release rate determination of radionuclide "1" (Iodine-131, Iodine-133, particulates with half-lives greater than 8 days, and tritium), in pC1/sec. For 1 - Sr89, Sr90 or tritium, use the best estimates (such as most recent measurements).
DFG sico-Sitespecificcriticalorgandoseratefactor(*[~C) for a stack gaseous release. See Table 1.1-12.
For ground releases (Turbine Building) the critical organ dose rate
' from Iodine Tritium, and Particulates with T 1/2 greater than 8 days is calculated as follows:
L R
egg
=
[D gco (3 40) where:
h f - Ground-activity release rate determination of radionuclide "i" (Iodine-131. Iodine-133, particulates with half-lives greater than 8 days, and tritium), in pCi/sec. For 1 - Sr89, Sr90 or tritium, use the best estimates (such as most recent measurements).
DFG gg
- Site specific critical organ dose rate factor (* 'C r ) for a ground level gaseous release. See Table 1.1-12.
Equations 3-16 and 3-40 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Tritium, lodine, and particulate releases via the plant stack and Turbine Building vent to the atmosphere.
l i Revision 12 Date 10 /01/91 3-27 8855R l
3.6.2 Basis for Method I The methods to calculate critical organ dose rate para!1el the total body dose rate methods in Section 3.4. Only the differences are presented here.
Method I may be used to show that the Technical Specification which limits organ dose rate from iodines, tritium and radionuclides in particulate form with half lives greater than 8 days (hereafter called Iodines and Particulates or "I+P") released to the atmosphere (Technical Specification 3.8.E.1.b) has been met for the peak I + P release rates.
The equation for Rgg, and Regg is derived by modifying Equation 3-25 from Section 3.9 as follows:
D - Q3 DFG 33co (3- m co, 1
(mrem) (C1) ( *]*)
applying the conversion factor, 31.54 (Cl-sec/pC1-yr) and converting Q to Q in pCi/sec as it applies to the plant stack yields:
STP 3-18)
- 31.54 Q OFG sico cos 4
(Cl-secy C (p_CJ) (mrem)
_(mrem) yr pCl-yr sec C1 Eq. 3-18 is rewritten in the form:
R - 0FG ' - 9' cos sico l (mremy guC1) (mrem-sec) yr sec pCi-yr incorporates L OFG'sico and DFG'gico (for Turbine Building vent releases) the conversion constant of 31.54 and has assumed that the shielding factor Reviston 12 Date 10/01/91 3-28 8855R e
l l
(5 ) Applied to the direct e>posure pathway.from radionuclides deposited on 7
the ground plane is equal to 1.0 in place of the SF value of 0.7 assumed in the determination of DFG39c,and DFG g for integrated doses over time.
g gg The selection of a critical r:cepive (based on the combinatio1 of exposure pathways which include direct dose from the ground plane, inhalation, and ingestion of vegetables, meat, and milk) which is outlined in Section 3.10 is inherent in Method I, as are the maximum expected off-site atmospheric dispersion factors based on past long-term site-specific meteorology.
Regarding the calculation of ground level release doses from the Turbine Building roof vent, the selection of a critical eceptor is based on the site boundary with the highest ground level atmospheric dispersion factor (based on same meteorological history and models as used in the stack) and the assumption that all of the exoosure pathways used for the stack release occur at this site boundary.
Should Method II be needed, the analysis for critical receptor critical pathway (s) and atmospheric dispersion factors may be performed with actual meteorologic and latest land use census data to identify the location of those pathways which are most impacted by these type of releases.
3.6.3 Method II If Method I cannot be acplied, or if the Method I dose exceeds the limit, then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A), except where site-specific models, data or assumptions are more applicable. The base case analysis, documented above, is a good example of the uss of Method II.
It is an acceptable starting point for a Method II analysis. Analyses requiring Method II calculations should be referred to YNSD to be performed and documented.
Revision 12 Date 10/01/91 3-29 8855R ,
l 3,7-' Method to Calculate the Gamma Air Dose from Noble Gases Technichl Specification 3.8 F.1 limits the gamma dose to air from noble
-. gases at any location at or beyond the site boundary to 5 mrad in any quarter and'10 mrad in any year. Dose evaluation is required at least once per month.
Use Method I first to calculate the gamma air dose for the plant stack and Turbine Building roof vent releases during the period. Method I applies at all dose levels.
Use Method II if a more accurate calculation is needed.
3.7.1 Method I The gamma air dose from plant stack releases is:
(3-21) 0,jrs-0.022 1 Qf DFj (mrad) (pC1-w) (Cl) (*#8d-* )
3 Ci-m pCl-yr whcre:
Qf-totalnoblegasactivity(Curies) released to the atmosphere via "1" during the period of the plant stack of each radionuclide interest.
DFJ-gammadosefactortoairforradionuclide"i". See Table 1.1-10 For ground level noble gas releases from the Turbine Building, the
_ gamma air _ dose is calculated as follows:
D 0.13 Qi DFY (3-41) wirg = i j
Revision 12 Date 10/01/91 3-30 8855R
.-w.- - . . - - - - - y- y ,_,y- , - ~ ,
there:_
i Total noble gas activity (curies) released to the atmosphere Qf via the Turbine Building of each radionuclide, "i", during the period of interest Equations 3-21 and 3-41 can be applied under the following conditions (otherwise justify Method I or consider Method II): ;
- 1. Normal operations (not emergency event), and
- 2. Noble gas releases via the plant stack ar.d Turbine Building vent to the atmosphere.
3.7.2 Basis for Method I Method I may be used to show that the Technical Specification which limits off-site gamma air dose from gaseous effluents (3.8.F.1) has been met for_ releases over appropriate periods. This Technical Specification is based on the Objective in 10CFR50, Appendix I, Subsection 8.1, which limits the estimated annual gamma air dose at unrestricted area locations.
Exceeding the Objective does not immediately limi.t plant operation but requires a report to the NRC.
For any noble gas release, in any period, the dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109 with the added assumption that O finite-DD/QF/U/Q]:
(3-22) 0,jrs-3.17E+04(X/Q]{ i Qf DFJ (mrad) (
e
) (sec/m3) (C1) ( )
where:
[X/Q]{=maximumannualaveragegammaatmosphericdispersionfactor for a stack release 3
- 6.98E-07 (sec/m )-
Reviston 2 Date 10/01/91 3-31 8855R
= number of curies of noble gas "1" released from the plant stack Of )
ohich leads to:
0,022 (3-21)
D a rs 1
Qf DF{
(mrad)~ (pC1- ) (C1) ( ,
)
Cl-m for the ground level release:
(3-42)
D,Jrg-3.17E+04[X/Q][ Qf DF{
obere:
(X/Q)Y - Maximum annual average gamma atmospheric dispersion factor 9 for a ground level release
- 3.95E-06 sec/m3 leading to:
(3-41)
D a rg = 0.13 Of DFj Regarding the calculation of ground level release doses from the Turbine Building roof vent, the ground level atmospheric dispersion factors are based on the same methodologies as used for the stack dispersion factors
.(same noble gas mix, meteorological history (1981-1985: and meteorological models), and are for the site boundary location that will have the highest dose.
The main difference between Method I and Method II is that Method II would allow the use of actual meteorology to determine [X/Q)Y rather than use the maximum long-term average value obtained for the years 1981 to 1985.
Revision 1 ate D 10/01/o1 3-32 8855R.
,- , ,y.- . _ - _ -. - .
3.7.3 Method'Il If the Method I dose determination indicates that the Technical Specification limit may be exceeded, or if a more exact calculation is required. then Method II may be applied. Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rev. 1 (Reference A),
except where site-specific models, data or aanmptions are more applicable.
Analyses requiring Method II calculations should be referred to YNSD to be performed and documented.
Revision 12 Date 10/01/91 3-33 8855R
3.8 Method to Calculate the Beta Air Dose from Noble Gases Technical Specification 3.8.F.1 limits the beta dose to air from noble gases at any location at or beyond the site boundary to 10 mrad in any quarter and 20 mrad in any year. Dose evaluation is required at least once per month.
Use Method I first to calculate the beta air dose for the plant stack and Turbine Building roof vent releases during the period. Method I applies at all dose levels.
Use Mathod II if a more accurate calculation is needed or if Method I cannot be applied. _
3.8.1 Method I The beta air dose from plant vent stack releases is:
0 0
airs
- 0.0M fD (3-23)
(mrad) (C1) (mra _y )
(P Cl- ']m ")
p where:
DF = beta dose factor to air for radionuclide "i". See Table 1.!-10.
Qf=totalnoblegaseti'.vity(Curies) released to the atmosphere via the plant stack of each radionuclide "i" during the period of interest.
For ground level noble gas releases from the Turbine Building, the beta air dose is calculated as follows:
= 0.55 DF (3 43) 0 Qf Revision 12 Date10/01/91 3-34 8855R
- =
where:
. Total noble gas activity (curies) released to the atmosphere Qf via the Turbine Building of each radionuclide "i" during the period of interest.
Equations 3-23 and 3-43 can be applied under the following conditions (otherwise justify Method I or consider Method II):
- 1. Normal operations (not emergency event), and
- 2. Noble gas releases via the plant stack and Turbine Building vent to the atmosphere.
3.8.2 Basis for Method I This section serves three purposes: (1) to document that Method I complies with appropriate NRC regulations, (2) to provide background and training information to Method I users, and (3) to provide an introductory user's guide to Method II. The methods to calculate beta air dose parallel the gamma air dose methods in Section 3.7.3. Only the differences are presented here.
Method I may be used to show that the Technical Specification which limits off-site beta air dose from gaseous effluents (3.8. A.1) has been met for releases over appropriate periods. This Technical Specification is based on the Objective in 10CFR50, Appendix I, Subsection B.1, which limits the estimated annual beta air dose at unrestricted area locations.
Exceeding the.0bjective'does not immediately limit plant operation but requires a report to the NRC within 30 days.
f
- For any noble gas release, in any period, the dose is taken from Equations B-4 and B-5 of Regulatory Guide 1.109:
(3-24)
D 1rs - 3.17E+04 X/Q s Q DFf Revision 12 Date 10/01/91 3-35 8855R
3 sec mrad-m (mrad) (pCi-yr pCl-yr Cl-sec ,3 substituting:
X/Q - Maximum annual average undepleted atmospheric s
dispersion factor for a stack release.
- 5.99E-07 sec/m3 We have 0.019 DF 0 (3-23)
D a rs
=
Qf (mrad) (pC1- ) (C1) ( )
Cl-m For the ground level release:
0 (3 44)
D rg - 3.17E+04 (X/Q) Qf DF there:
- Maximum annual average undepleted atmospheric dispersion (X/Q)9 factor for a ground level release (Turbine Building)
- 1.74E-05 sec/m3 leading to:
0
= 0.55 DF 0 (3-43)
D rg Of -
Regarding the calculation of ground level release doses from the Turbine Building roof vent, the ground level atmospheric dispersion factors are based on the .ame methodologies as used for the stack dispersion factors (same noble g'as mix, meteorological history (1981-1985), and meteorological models), and are for the site boundary location that will have the highest dose.
Revision 12 Date 10/01/91 3-36 8855R
3 8.3 Method II If Method I cannot be applied, or-if the Method I dose determination
-indicates that the Technical Specification limit may be exceeded, or if a more exact calculation is required, then Method II may be applied, Method II consists of the models, input data and assumptions in Regulatory Guide 1.109, Rey, I (Peference A), except_where site-specific models, data or assumptions are more applicable. Analyses requiring Method Il calculations should be referred to YNSD to be performed and documented.
i l
l
, Revision 12 Date 10/01/91-3-37 8855R
3.9 Method to Calculate the Critical Organ Dose from Iodines, Tritium and Particulates l Technical Specification 3.8.G.1 limits the critical organ dose to a Member of the Public from radioactive lodines, Tritium, and particulates with half-lives greater than 8 days (hereafter called "I+P") in gaseous effluents to 7.5 mrem per quarter and 15 mrem per year. Technical Specification 3.8.M.1
' limits the total body and organ dose to any real member of the public from all station sources (including gaseous effluents) to 25 mrem in a year except for the thyroid, which is limited to 75 mrem in a year.
Use Method I first to calculate the critical organ dose from a vent stack and Turbine Building roof vent release as it is simpler to execute and more conservative than Method II. Method I is conservative for total body, critical organ,- and thyroid dose greater than 0.1 mrem.
Use Method II if a more accurate calculation of critical organ dose is needed (i.e., Method I indicates the dose is greater than the limit), or if Method I cannot be applied, or if the majority of the release is Iodine and the 75 mrem limit for Specification 3.8.L.1 needs to be evaluated.
3.9.1 Method I D - DFG (3-25) cos. sico (mrem) (C1) ( *]* ) -
Q = Total iodine, tritium, and particulate activity (Ci) released from the stack to the atmosphere of radionuclide "1" during the period of interest. For strontiums, use the most recent measurement.
DFG .. Site-specific critical organ dose factor for a stark gaseous 33C release of radionuclide "1" (mrem /C1). For each radionuclide it is the age group and organ with the largest dose factor. See Table 1.1-12.
Revision 2 Date 10/01/91 3-38 8855R
The critical organ dose is calculated for ground level releases as
.follows:
l O - OFG (3-44) cog _Q gico (mrem) (C1)
(*]*)
Q - Total lodine, tritium, and particulate activity (Ci) released from the Turbine Building to the atmosphere of radionuclide "1" during the period of interest. For strontiums, use the most recent measurement.
DFG - Site-specific critical organ dose factor for a ground level 9 ICO release (Turbine Building) of nuclide "1" (mrem /Cl). For each radionuclide it is the age group and organ with the largest dose factor. See Table 1.1-12.
Equations 3-25 and 3-44 can be applied under the following conditions (otherwise, justify Method I or consider Method II):
- 1. Normal operations (not emergency event),
- 2. I+P releases via the plant stack and Turbine Building to the atmosphere, and
- 3. Any continuous or batch release over any time period.
3.9.2 Basis for Method I This section serves three purposes: (1) to document that Method I complies with appropriate NRC regulations, (2) to provide background and training information to Method I users, and (3) to provide an introductory user's guide to Method II.
Method I may be used to show that the Technical Specifications which limit off-site organ dose from gases (3.8.G.1 and 3.8.L.1) have been met for releases over the appropriate periods. These Technical Specifications are based on Objectives and Standards in 10CFR and 40CFR. Technical Specification 3.8.G.1 is based on the ALARA Objectives in 10CFR50, Appendix I, Revision 12 - Date 10/01/91 3-39
. 8855R
l Subsection II C. Technica' Specification 3,8.M.1 is based on Environmental
' Standards for Uranium fuel Cycle in 40CFR190 (hereafter called the Standard) tshich applies to direct radiation as well as liquid and gaseous effluents.
These methods apply only to I+P in gaseous effluents contribution.
Exceeding the Objective or the Standard does not immediately limit plant operation but requires a report to the NRC within 30 days. In addition, a waiver may be required.
Method I was developed such that "the actual exposure of an individual ... is unlikely to be substantially underestimated" (10CFR50, Appendix I). The use below of a-single " critical receptor" provides part of the conservative margin to t'he calculation cif critical organ dose in Method I. Method II. allows that actual-individuals, with real behaviors, be taken into account for any given release. In fact, Method I was based on a Method II analysis of the critical receptor for the annual average conditions. For purposes of complying with the Technical Specifications 3.8.G.2 maximum long term (five years) average atmospheric dispersion factors are appropriate for batch and continuous releases. That analysis was called the " base case"; it was then reduced to form Method I.
The base case, the method of reduction, and the assumptions and data used are presented below.
The steps performed in the Method I derivation follow. First, in the base case, the dose impact to the critical receptor in the form of dose factors (mrem /Cl) of I curie release of each I+P radionuclide to gaseous effluents was derived. Then Method I was determined using simplifying and further conservative assumptions. The base case analysis uses the methods, data and assumptions in Regulatory Guide 1.109 (Equations C-2. C-4 and C-13 in Reference A). Tables 3.9-1 and 3.9-2 outline human consumption and environmental parameters used in the analysis. It is conservatively assumed that the critical receptor lives at the " maximum off-site atmospheric dispersion factor location" as defined in Section 3.10. However, he is exposed, conservatively, to all pathways (see Section 3.10). The resulting site-specific dose factors are for the maximum organ and the age group with Revision 12 Date 10/01/91 3-40
, 8855R
the highest dose. factor for that organ. These critical organ, critical age dose factors are given in Table 1.1-12.
For any gas release, during any period, the increment in annual average dose from radionuclide "1" is:
(3-26)
ADjco = OgDFG gco there OFG gen is the critical dose factor for radionuclide "1" and Qg is the activity of radionuclide "1" released in curies.
Method I is more conservative than Method II in the region of the Technical Specification limits because it is based on the following reduction of the base case. The dose factors DFGg,,g used in Method I were chosen from the base case to be the highest of the set for that radionuclide. In effect
.each radionuclide is. conservatively represented by its own critical age group and critical organ.
Because of the assumptions about receptors, environment, and radionuclides and because of the low Objective and Standard, the lack of
-immediate restriction on plant operation, and the adherence to 10CFR20 concentrations (which limit public health consequences) a failure of Method I (i.e , the exposure of a real individual being underestimated) is improbable and the consequences of a failure are minimal.
3.9.3 METH00 II If Method I cannot be applied, or if the Method I dose exceeds the limit or if a-more exact calculation is required, then Method II should be applied. Method II consists of the models,-input data and assumptions in Regulatory Guide 1.109, Rev.1 (Reference A), except where site-specific models, data or assumptions are more applicable. The base case analysis, documented above, is a good example of the use of Method II. It is an acceptable starting point for a Method II analysis. Analyses requiring Method II calculations should be referred to YNSO to be perforced and documented.
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. 3-41 l 8855R
Environmental Parameters for Gaseous Effluents at Vermont Yankee (Derived from Reference A)
Vegetables Cow Hilk Goat Milk Heat Variable Stored Leafy Pasture Stored Pasture Stored Pasture Stored (V Agricultural (Kg/M2 ) 2. 2. 0.70 2. 0.70 2. 0.70 .2.
Productivity Soil Surface (KG/M2 ) 240. 21 0 . 240. 240. 240. 240. 240. '240.
Density I Transport Time ' .( H RS ) 48. 48. 48. 48. 480. 480.
to User IB Soll Exposure (HRS) 131400. IJ1400. 131400. 131400. 131400. 131400. 131400. 131400.
Time If Crop Exposure (HRS) 1440. 1440. 720. 1440. 720. 1440. 720. 1440.
Time to Plume TH Holdup After (HRS) 1440. 24. O. '160. O. 2160. O. 2160.
Harvest Animals Daily (KG/ DAY) 50. 50. 6. 6. 50. 50.
-)F Feed FP Fraction of Year 0.50 0.50 0.50 on Pasture
- 1. 1. 1.
FS Fraction Pasture when on Pasture FG Fraction of Stored 0.76 Veg. Grown in Garden FL Fraction of Leafy 0.50 Veg. Grown in Garden FI Fraction Elemental.
lodine = 0.5 11 Absolute Humidity = 5.6 (gm/M3 )
Revision 12 Date 10/01/91 3-42
- r" _ _ _ _ _ __
- - . . - - . - - - - ~ . - . .-. - . ..-. - - . - . - . . _ . -
Table 23)-2 Usage factors for Various Gaseous Pathways at Vermont Yankee l (from Regulatory Guide 1.109, Table E-5)
Age Leafy '
Group Vegetables Vegetables Milk Meat Inhalation (kg/yr) (kglyr) (1/yr) (kg/yr) (m3 /3r) :
Adult 520.00 64.00 310.00 110.00 8000.00 i
Teen 630.00 42.00 400.00 65.00 8000.00 Child 520.00 26.00 330.00 41.00 3700.00 Infant 0.00 0.00 330.00 0.00 1400.00 i
i Y
t t
i-Revision 12 Date 10/0; j' 3-43 8855R e
r----rgrmm te rw-r,ti m r r -- r *mm-r s v r-*m-----tr-*e're r v~-w--- - . -,-_, , ..wn,.e- ee-w., .,--,..~,.;-,,%., ,:,: e- , rr y ,- - e-.m.,,we,w% r a.
3.10 Receptor Points and Annual Average _ Atmospheric Dispersion factors for Important Exposure Pathways The gaseous effluent dose methods have been simpilffed by assuming an individual whose behavior and living habits inevitably lead to a higher dose than anyone else. The following exposure pathways to gaseous effluents listed in Regulatory Guide 1.109 (Reference A) have been considered:
- 1. Direct exposure to contaminated air;
- 2. Direct exposure to contaminated ground;
- 3. Inhalation of air; 4 Ingestion of vegetables;
- 5. Ingestion of cow's milk; and
- 6. Ingntion of rneat.
Section 3.10.1 details the selection of important off-site locations and receptors. Sectior. 3.10.2 describes the atmospheric model used to convert meteorologic data into atmospheric dispersion factors. Section 3.10.3 presents the maximum atmospheric dispersion factors calculated at 9ach of the off-site receptor locations.
3.10.1 Receptor locations
! Three important receptor locations are considered in the dose and dose rate equations for gaseous radioactive effluents. They are:
f
- 1. The point of maximum gamma exposure from an overhead noble gas cloud; Revision 12 Date 10/01/91 3-44
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- 2. The point of maximum ground level air concentration and deposition of radionuclides. f The point of maximum gamma exposure ($ sector, 400 meters) was determined by finding the maximum five-year average gamma X/Q at an.v off-site location. The location of the maximum ground level air concentration and deposition of radionuclides (NW sector, 2900 meters) was determined by finding the maximum five-year average depleted X/Q and 0/Q at any off-site location. ,
for the purposes of determining the Method I dose factors for iodines, tritium, and particulates, a milk animal was assumed to exist at the location ,
of highest calculated ground level air concentration and deposition as noted above. This location then conservatively bounds the deposition of radionuclides at all real milk animal locatiens.
Regarding the calculation of ground level release doses from the Turbine Building roof vent, the selection of a critical receptor is based on the site boundary with the highest ground level atmospheric dispersion factor (based on same meteorological history and models as used in the stack) and the assumption ti,at all of the exposure pathways used for the stack release occur at this site boundary. .
3.10.2 Vermont Yankee Atmosp_heric Dispersion Model The annual average atmospheric dispersion factors are computed for routine (long-term) releases using Yankee Atomic Electric Company's (YAEC)
AEOLUS Computer Code (Reference B). AEOLUS is based, in part, on the straight-line airflow model discussed in Regulatory Guide 1.111 (Reference C). The valley in which the plant is located is considered by the model.
AE0LUS produces the following annual average atmospheric dispersion factors for each location:
- 1. . Undepleted X/Q dispersion factors for evaluating ground level concentrations; Revision 12 Date 10/01/91 g
8855R
-,,,,,,.,~,-m__
- 2. Depleted X/Q dispersion factors for evaluating ground level concentrations;
- 3. Gamma X/Q dispersion factors for evaluating gamma dose rates from a sector averaged finite cloud (multiple energy undepleted source);
and 4 D/Q deposition factors for evaluating dry deposition of elemental radiolodines and other particulates.
The deposition velocity concept presented in "Heteorology and Atomic Energy - 1968" (Reference E, Section S-3.2) is used to determine the depleted X/Q and D/Q factors, assuming a constant deposition velocity of I cm/sec.
L Gamma dose rate is calculated throughout this 00CH using the finite cloud model presented in "Neteorology and Atomic Energy - 1968" (Reference E.
Section 7-5.2.5). That model is implemented through the definition of an effef.tive gamma atmospheric dispersion factor, (X/QY ) (Reference B. Section 6), and the replacement of X/Q in infinite cloud dose equations by the (X/QT ).
3.10.3 Annual Average Atmospheric Dispersion factors for Receptors Actual measured meteorological data for the five-year period, 1981 through 1985, were analyzed to determine all the values and locations of the l
maximum off-site annual average atmospheric dispersion factors. Each dose and dose rate cal:ulation incorporates the maximum applicable off-site annual average atmospheric dispersion factor. The values used and their locations are summarized in Table 3.10-1. Table 3.10-1 also indicates which atmospheric dispersion factors are used to calculate the various doses or dose rates of interest.
Revision 12 Date10/01/91 3-46 8855R
.. ,.-.__._..,.-.s . - - , , . .% . ., ,. - - . . ..,__w.. .,-..w., . ,, _c -.__ ,. . . - - -
Table 3.10-1 .
Vermont Yankee Dilution Factors Dose Rate to Individual Dose to Air Total Body Skin Crttical Organ Gamma Beta I
X/Q depleted ( ) - -
5.85E-07 )
m (1.65E-05)
S.99E-07 - 5.99E-07 X/Qundepleted(y) )
) (1.74E-05)
(1.74E-05) m
- - 5.85E-09 )
D/Q(h)m (6.50E-08) 6.98E-07( 6.98E-07 - 6.98E-07( -
X/0Y (Sy) )
(3.95E-06)
) (3.95E-06)g 3 m (3.95E-06)
(1) Maximum gamma exposure point: S sector, 400 meters (0.25 miles), for stack release.
(2) Maximum ground level concentration: NW sector. 2900 meters (1.80 miles). for stack release.
(3) Turbine Building (ground level release) maximum dilution factors: 5 Sector. 366 meters (0.23 miles).
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3_47 8855R
i l
l 3.11 Method to Calculate Dose From Plant Operation l l
Technical Specification 3.8.H.1 restricts the dose to the whole body or any organ to any member of the public from all station sources (including direct radiation from fixed sources on-site) to 25 mrem in a calendar year (except the thyrold, which is limited to 75 mrem).
3.11.1 Turbine Building ,
The maximum contribution of direct dose to the whole body or to any organ due to N-16 decay from the turbine is:
D " (3-27) d KN16(L)
- E (mrem) (mrem) (MW,h)
MH,h where:
D - The dose contribution from N-16 decay at either the site d
boundary off maximum impact (west site boundary) or closest off-site residence - (mrem).
E = Gross electric output over the period of interest <
(HW,h).
= The N-16 dose conversion factor for (L) equal to either:
KN16(L)
(1) 3.23E-06 for the maximum west site boundary; or (2)-1.29E-06 for the closest residence (mrem /MW,h).
3.11.2 North Warehouse Radioactive materials and low level waste can be stored in the north oarehouse. The maximum annual dose contributions to off-site receptors (west site boundary line) from sources in the shielded (east) end and the unshielded (oest) end of the north warehouse are:
- 12 i Revision Date 10/01/91 !
3-48 S355R
y . ee n's1'v- *yvy g e-- 9 sg>+y +*N-da-a'>gea% rwgw+-.T ---r-'-vg - - -w,--r-w---m---v-
D - 0.25 x kgfor the shielded end (3-28)
S gmrem) g mrem /yr gmrem) l yr mrem /hr) hr and i
l D . 0.53 x RU for the unshielded end (3-29)
U g
mrem y zmrem/yr) gmrem) yr mrem /hr hr ,
where:
Dg = The annual dose contribution at the maximum site boundary ,
location from fixed sources of radiation stored in the shielded east end of the North Warehouse (mrem), yr D - The annual dose contribution at the maximum site boundary U
location from fixed sources of radiation stored in the .
unshielded west end of the North Warehouse (* **). !
Rg - Dose rate measured at 1 meter from the source in the shielded end of the north warehouse (* 'r }'
Rg . Dose rate measured at 1 meter from the source in the unshieldedendoft,henorthwarehouse(*['r I' 0.25 - Dose rate to dose conversion factor which relates mrem /yr at l
the west site boundary per mrem /yr measured at 1 meter from the source in the shielded end of the warehouse assuming it is full to capacity for one year ( () .
i i Revision 12 Date 10/01/91 3-49 8855R ,
1 n r,-, - , , , , , , - ,v.e ..n- . , , - . ,..n,-.,,- ., .- ,.,...+,.n , n.,, p , -,,.vn-n,, - ~ -,,,-,,-x.,,r-
0.53 = Dose rate to dose conversion factor which relates mrem /yr at the west site boundary per mrem /yr measured at I meter from the source in the unshielded end of the warehouse assuming it is full to capacity for one year ( f{),
3.11.3 Low Level Waste Storage Pad Interim storage of packaged Dry Active Haste (DAH) and spent ion exchange and filter media is permitted in modular concrete storage overpacks on the LLW storage pad facility adjacent to the north warehouse. The arrangement of the storage modules is such that DAH is placed in modules which shield higher activity lon exchange media from the west site boundary. The 1ose at the maximum site boundary receptor from both direct radiation and s;yshine scatter can be calculated as follows:
(a) Direct Dose (line of sight)
= 0.28 x k *I d (3-30)
D d dE gmrem/yr) gmrem) g,y_r mremmodule) mrem /hr hr or D " *9 * * (~ '
d d d5 g
mrem gmrem/yr) gmrem) yr-module) mrem /hr nr i where:
l l
D = The annual direct dose contribution at the maximum site l dE boundary from a single rectangular storage module which has an unobstructed short end surface (not shielded by other modules) orientated toward the west site boundary mrem
'yr-motu)e)*
3 Revision 12 Date 10/01/91 '
. 3-50 8855R L
n .~ . ._
D - The annual direct dose contribution at the maximum site dS boundary from a single rectangular storage module which has an unobstructed long side surface (not shielded by other modules) orientated toward the west site boundary mrem yr-module
- R Maximum dose rate measured at 3' from the side of the d
storage module whose unobstructed face (i.e., a side or end surface which is not shielded by other waste modules) is toward the west site boundary.
f - The fraction of a year that a storage module is in use d
on the storage pad.
0.28 Dose rate to dose conversion factor which relates mrem /yr at the west site boundary per mrem /hr measured at 3' from the narrow end of the rectangular storage module when that face is orientated toward the west boundary.
0.39 - Dose rate to dose conversion factor which relates mrem /yr at the west site boundary per mrem /hr measured at 3' from the long side of the rectangular storage module when that face is orientated toward the west boundary.
(b) Scatter From Skyshine
= 0.0M x (3-32) i D
SKR kSKR
- ISK mrem gmrem/yr) gyr-liner) (mrem) hr mrem /hr and Revision 12 Datelo/01/91 3-51 8855R l
l
D - 0.015 x k gag xf gg (3-33)
SKD mrem (mrem /yr) gmrem)
<yr-module) mrem /hr hr where:
R - The annual skyshine scatter contribution to the dose at the SKR maximum site boundary from a single spent ion exchange media liner in a storage module whose top surface is not -
obstructed due to stacking of modules I.yr er}'
R The annual skyshine scatter contribution to the dose at the SKD maximum site boundary from a rectangular storage module containing DAW whose top surface is not obstructed due to stacking of modules (yr ule}'
k - For Resins, the maximum dose rate measured at 3' over the SKR top of each liner in a storage module (mrem /hr).
k - For DAW the maximum dose rate measured at 3' over the top SKD surface of a storage module with DAW (mrem /hr).
f - The fraction of a year that a storage module is in use SK on the storage pad.
0.016 - Dose rate to dose conversion factor for the scatter dose from each resin liner source in storage which relates mrem /yr at the west site boundary per mrem / hour at 3' from the top of the module.
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0.015 - Dose rate to dose conversion factor for the scatter dose from DAH boxes in storage which relates mrem /yr at the west site boundary per mrem /hr at 3' from the top of the module.
(c) Dose From Resin Liners During Transfer During the movement of resin liners from transfer casks to the storage modules, the liners will be unshielded in the storage oad area for a short period of time. The maximum dose contribution at the site boundary during the unshielded movement of resin liners can be calculated from:
0.0025 x k x T (3-30 D
trans - tran trans (mrem) (mrem /hr) ( ) (br>
R/hr where:
D trans - The dose contribution to maximum site boundary resulting from the unshielded movement of resin liners between a a transfer cask and a storage module (mrem).
R trans - Dose rate measured at contact (2") from the unshielded top sur face of the resin liner in R/hr.
T The time (in hours) that an unshielded resin liner tran is exposed in the storage pad area.
0.0025 - The dose rate to dose conversion factor for an unshielded resin liner which relates mrem / hour at the west site boundary per R/hr at contact (2") from the unshielded surface of the liner.
Revision 12 Date 10/01/91 3-53 8855R 1
(d) Intermodular Gap Dose In addition to the above methods for determining doses at the west site boundary from the LLW storage pad, another dose assessment model has been included to address the possible condition of spaces or gaps existing between the placement of the OAW storage modules situated along the west facing side of the pad. This could result in a radiation streaming condition existing if ion exchange resin liners were placed in storage directly behind the gap. The direct dose equations (3-30 and 3-31) consider that the storage modules situated on the outside of the pad area provide a uniform shield to storage modules placed behind them. The inMrmodular gap dose equation (3-35) accounts for any physical spacing between the outside storage modules which have not been covered by additional external shielding.
- 2.44E-2 x W x A I (3-30 Og ,p Gap RL
- Gap
( *y"r*)(yr* "in-Ci) (in) (Cl) where:
- The annual dose contribution at the maximum site boundary Og ,p '
(west) from radiation streaming through the intermodular gap between DAW storage modules used to shield resin I modules from direct radiation (mrem /yr).
W - The intermodular gap width (inches) between adjacent DAW Gap
' storage modules facing the west site boundary.
A gg
- The total gamma activity contained in a condensate resin liner stored directly in line with the intermodular gap adjacent DAW modules ( C1).
Revision 12 Date 1o/01/91 ,
t 3-54 8855R I
. l u
f gp - The fraction of a year that the intermodular gap is not i shielded.
2.44E-2 = The activity to site boundary dosa conversion factor for
""* ).
a one-inch wide intermodular gap (
yr-in-Ci The site boundary dose from waste materials placed into storage on the Low Level Waste Storage Pad facility is determined by combining the dose contribution due to direct radiation (line of sight) from Part (a) above with the skyshine scatter dose from Part (b), resin liner transfer dose from Part (c), and any intermodular gap dose from Part (d).
3.11.4 Total Direct Dose Summary The dose contributions from the N-16 source in the Turbine Building, fixed sources in the north warehouse, and fixed sources on the Low Level Haste '
Storage Pad facility, shall be combined to obtain the estimate of total off-site dose to any member of the public from all fixed sources of radiation located on-site.
Revision 12 Date 10/01/o1 '
3-55 8855R 1
O 3.12 Cumulative Doses Cumulative Doses for a calendar quarter and a calender year must be maintained to meet Technical Specifications 3.8.B.I. 3.8.F.1 and 3.8.G.I. In addition, if the requirements of Technical Specification 3.8.M.2 dictate, cumulative doses over a calendar year must be determined for Technical Specification 3.8.M.l. To ensure the limits are not exceeded, a running total ,'
must be kept for each release.
nendatt Revision _la_ Date 'n/n,221 3- 5 v, 8855R
gas. The nominal plant stack flow is 7.5E+07 cc/sec ((160,000 cfm x 28,300 3
cc/ft )/60 sec/ min).
When monitor responses indicate that activity levels are below the i
LL0s at the stack (or A0G) monitors, the relative contribution of each noble gas radionuclide can conservatively be approximated by analysis of a sample of off-gas obtained during plant operations at the steam jet air ejec. ir (SJAE). This setpoint example is based on the following data (see Table 1.1-10 for DFB g andDFj):
OFB g QfAE 0F{
( p,C_1,) gmrem-m ) gmrem-sec) i sec pCi-yr pCi-yr Xe-138 1.03E+04 8.83E-03 9.60E-03 Kr-87 4.73E+02 5.92E-03 1.06E-02
. Kr-88 2.57E+02 1.47E-02 1.32E-02 Kr-85m 1.20E+02 1.17E-03 1.83E-03 Xe-135 3.70E+02 1.81E-03 2.60E-03 Xe-133 1.97E+01 2.94E-04 4.57E-04 7 5]AE L. Q, DF Bg 0FB =
(5-11)
.SJAE Qg i
7 .SJAE L Og 0FBg - (1.03E+04)(8.83E-03) + (4.73E+02)(5.92E-03)
+ (2.57E+02)(1.47E-02) + (1.20E+02)(1.17E-03)
+ (3.70E+02)(1.81E-03) + (1.97E+01)(2.94E-04) 3
- 9.83E+01 (pCi-mrem-m / set-pCi-yr)
Revision 12 Date 10/01/91 5-12 8855R
SJAE Q - 1.03E+04 + 4.73E+02 + 2.57E+02 1
i + 1.20E+02 + 3.70E+02 + 1.97E+01 1
- 1.15E+04 pC1/sec 9.83E+01 DFB c = 1.15E+04
- 8.52E-03 (mrem-m3 /pC1-yr)
R t - 716 S ghDFB '
c 1 1
- (716) (1E+08) (7.5E+07) (8.52E-03) 112,050 cpm Next:
7 .SJAE L.
O gDF{
i 7 .SJAE L. Qg 0Fj-(1.03E+04)(9.60E-03) + (4.73E+02)(1.06E-03)
+ (2.57E+02)(1.32E-02) + (1.20E+02)(1.83E-03)
+ (3.70E+02)(2.60E-03) + (1.97E+01)(4.57E-04)
- 1.04E+02 (pCi-mrem-sec/sec-pCl-yr) 0F, 1.04E402 e 1.15E+04 Revision 12 Date 10/01/91 5-13 8855R ;
I
- 9.04E-03 (mrem-sec/pC'-yr) l SI (5-10)
R[pt - 3,000 S gh
- (3,000) (lE+08) (7.5 07) (9.04E-03)
- 442,478 cpm The setpoint, Rspt, is the lesser of tb p
and R 5 ".
3 For the noble gas mixture in this example Rspt is less than R t , indicating that the total body dose rate is more restrictive.
Therefore, in this example the " Stack Ga' .* and " Stack Gas II" noble gas activity monitors should each be set at 112,050 cpm above background or at some conservative value below this (such as that which might be based on controlling release rates from the plant in order to maintain off-site air concentrations below 2 x MPC when averaged over an hour), or to account for other minor releases from the Turbine Building roof vents. For example, if an administrative limit of 70 percent of the Technical Specification whole body dose limit 500 mrem /yr (112,050 cpm) is chosen, then the noble gas monitor alarms should te set at 78,435 cpm above background (0.7 x 112.050 78,435).
5.2.1.3 Basis for the Plant Stack and A0G System Noble Gas Activity Monitor Setpoints The setpoints of the plant stack and A0G system noble gas activity monitors must ensure that Technical Specification 3.8.E.1.a is not exceeded.
Sections 3.4 and 3.5 show that Equations 3-5 and 3-7 are acceptable methods for determining compliance with that Technical Specification. Which equation (i.e., dose to total body or skin) is more limiting depends on the noble gas Therefore, each equation must be considered separately. The mixture.
derivatio.is of Equations 5-9 and 5 10 begin with the general equation for the response R of a radiation monitor:
12 Date 10/01/91 Revision 5-14 8855R
R - S C,g (5-13) gg (cpm) (CE*- }( )
C cm where:
R - Response of the instrument (cpm) 3 S
9 9 - Detector counting efficiency for noble gas "i" (cpm /(pC1/cm ))
C,g'. Activity concentration of noble gas3 "1" in the mixture at the noble gas activity monitor (pC1/cm )
The relative release rate of each noble gas, h g (pC1/sec), in the total release rate is normally determined by analysis of a sample of off-gas obtained at the Steam Jet Air Ejector (SJAE). Noble gas release rates at the plant stack and the A0G discharge are usually so low that the activity concentration is below the Lower Limit of Detection (LLD) for sample analysis. As a result, the release rate mix ratios measured at the SJAE are used to present any radioactivity being discharged from the stack, such as may have resulted from plant steam leaks that have been collected by building ventilation. For the A0G monitor downstream of the charcoal delay beds, this leads to a conservative setpoint since several short-lived (high dose factor) noble gas radionuclides are then assumed to be present at the monitor, which in reality, would not be expected to be present in the system at that point.
During periods when the plant is shutdown (after five days), and no radioactivity release rates can be messured at the SJAE, Xe-133 is the dominant long-lived noble gas and may be used as the referenced radionuclide to determine off-site dose rates and monitor setpoints. Alternately, a relative radioauclide, "i", mix fraction, (f ), may g be taken from Table 5.2-1 as a function of time after shutdown (including periods shorter than five days) to determine the relative fraction of each noble gas potentially available for release to the total. However, prior to plant startup before a SJAE sample can be taken and analyzed, the monitor alarm setpoints should be based on Xe-138 as representing the most prevalent high dose factor noble gas Revision 12 Date 10/01/91 5-15 8855R
expected to be present shortly after the plant returns to power. Monitor I
alarm setpoints which have been determined to be conservative under any plant conditions may be utilized at any time in lieu of the above assumptions.
C,g the activity concentration of noble gas "1" at the noble gas activity monitor, may be expressed in terms of Qg by dividing by f, the appropriate flow rate. In the case of the plant stack noble gas activity monitors the appropriate flow rate is the plant stack flow rate and for the A0G noble gas activity monitors the appropriate flow rate is the A0G system flow rate.
(5-14)
C mi 1
($) ($)
3 sec (E) cm 3
cm where:
Q, . The release rate of noble gas "i" in the mixture for each noble gas identified. .
F - Appropriate flow rate (cm /sec)
Substituting the right half of Equation 5-14 into Equation 5-13 for Cmi YI 'Id5 (5-15)
R - S gg hg h 3
(cpm) (cp m) ( ) ggy j Cm The detector calibration procedure establishes a counting efficiency for a given mix of nuclides seen by the detector. Therefore, in Equation 5-15 one may substitute gS for Sg ), where Sg represents the counting efficiency determined for the current mix of nuclides. If the mix of nuclides changes significantly, a new counting efficiency should be determined for calculating the setpoint.
Revision 12 Date 10 /31/91 5-16 8855R
(5-16)
R - S g h bg (cpm) (CE*~ } ( ) ( )
C Cm The total body dose rate due to noble gases is determined with Equation 3-5:
. T .
DFB g (3-5)
R . 0.70 L, Qg tbs 3
(pC1) (mrem-m (mrem) yr (pC1-secy 3 set pCi-yr )
C1-m where:
R total body dose rate (mrem /yr) due to noble gases from tbs stack release 3
0.70 - (1.0E+06) x (6.98E-07) (pCi-sec/pC1-m )
lE + 06 - number of pC) per pCi (pCi/pCl) 6.98E [X/Q)Y, maximum annual average gamma atmospheric 3
dispersion factor (sec/m )
the release rate of noble gas "i" in the mixture for each Og noble gas identified (pCi/sec) (Equivalent to
.ST Q,
for noble gases released at the plant stack.)
DFB;
= total body dose factor (see Table 1.1-10) 3 (mrem-m /pCi-yr)
Revision 12 Date 10/01/91
- 5-17 8855R E
?
a
-i
.5]AE OfB l Q, i
3 i (UCi/sec) (mrem-m /pCi-yr)
Xe-138 5.15 E+03 8.83 E-03 Kr-87 2.37 E+02 5.92 E-03 Kr-88 1.29 E402 1.47 E-02 Xe-135 1.85 E+02 1.81 E-03 Calculation The dose rate is calculated from Equations (3-5) and (3-28):
(3-5)
R 0.70 h DFB tbs - i g
3 Imrem) g pCl-sec' IuC)' mrem-m '
yr 3 ec pCl-yr uCi-m and where the stack release rate is determined from:
5 (3-28)
.5T h,]AE 3 i SJAE Sg~
i (cpm) (c1 )
j (uC1/cc) set com (sec)
.SJAE First, determine the sum ( ) of all Q 3 and the fraction that each noble gas i repretents in the total gas mix.
.SJAE
- (5.15 E+03) + (2.37 E+02) + (1.29 E+02) + (1.85 E+02)
Q3
- 5.70 E+03 uC1/sec and the relative fraction of each noble gas:
Reviston 12 Date 10/01/91 ,
A-4 8855R
- -' ~ - - - - - - - - - - . _ . _ _ _ _ . __ __ _. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
f Rela action g
h /5.70 E+03 o i Xe-138 5.15 E+03/5.70 E+03 - 0.904 i Kr-87 2.37 E+02/5.70 E+03 - 0.042
=
Kr-88 1.29 E+02/5.70 E+03 - 0.023 Xe-135 1.85 E+02/5.70 E+03 - 0.032 Next, the stack release rate of each noble gas i from Equation (3-28) can be substituted into Equation (3-5) to give the dose rate as:
I ktbs = 0.70 M g F g
f 3
DFB 3
0.70 80,000 1/1E408 7.55 E+07 g fg DFB g
+
4.23 E+04 [(0.904)(8.83 E-03) + (0.042)(5.92 E-03)
(0.023)(1.47 E-02) + (0.032)(1.81 E-03)) -
Answer ktbs 365 mrem / year noble gas total body dose rate.
2 00 91 Revision Date A-5 8855R
f g (32 day)" 0FBg **
g Kr-85 0.152 1.61 E-05 l 9.15 E-05 I Xe-131m C.070 Xe-133 0.777 2.94 E-04
- Fraction of nuclide in mix as function of time (see Table 5.2-1).
- 0ose factors from Table 1.1-10.
Calculation The dose rate is calculated from Equations (3-5) and (3-28):
(3-5) k 0.70 h DFB g tbs = i 3
UCi Imrem} (pCi-sec' (mrem-m pCl-yr yr uC)-m 3 Tec' and where the stack release rate is determined from:
.5]AE (3-28)
" M F JAE i
(cpm) (cc )
g 2) u (uC1/cc):pm sec sec
.SJAE However, for a time (t) after shutdown, the ratio of Qg to the sum release rate of all noble gases can be replaced in Equation (3-28) by the relative fraction [f (t)) g of each noble gas available in the system; therefore, Equation (3-28) can be written:
Revision 12 Date 10/01/?1 A-7 8855k
i
.ST 1
~
- f (t) M F I Q l i i Sg Therefore, using the above data for a time period 32 days after shutdown, the dose rate equation can also be written as:
1 0.70 M F f g (t) DFB ktbs gg g $
- 0.70 80,000 1/1E+08 7.55 E+07 [(0.152)(1.61 E-05) +
(0.070)(9.15 E-05) + (0.777)(2.94 E-04)) -
Answer ktbs = 10.0 mrem / year noble gas total body dose rates at 32 days after shutdown. ,.gy fh$,?f-a-
Revision 12 Date 13/01/91 A-8 8855R
.5]AE DF{3 01 (mrem-sec) uC1/ year i (uC)/sec) j Xe-138 5.15 E+03 9.60 E-08 l 1.06 E-02 Kr-87 2.37 E+02 Kr-88 1.29 E+02 1.32 E-02 Xe-135 1.85 E+02 2.60 E-03 Calculation The skin dose rate is calculated from Ecuations (3-7) and (3-28);
.ST (3_7)
R 91 DF{s skins " i gmrem) uC))
, gmrem-sec) yr sec UCi-yr and where the stack release rate is determined from:
.SJAE (3-28)
.ST Q, )
Qi =
.S]AE M
W f 01 (cpm) 3 (uCi/cc) cpm (1) set
( )
.SJAE First, determine the sum ( ) of all Q g and the fraction that each noble gas i represents in the total gas mix.
T L.,
.5]AE
- (5.15 E+03) + (2.37 E+02) + (1.29 E+02) + (1.85 E+02)
Qj
- 5.70 E+03 uCi/sec.
and the relative fraction of each noble gas:
Revision 12 Date 10/31/91 A-10 8855R
Rela e raction t ,
b /5.70 E+03 5.15 E+03/5.70 E+03 - 0.904 Xe-138 2.37 E+02/5.70 E+03 - 0.042 Kr-87 1.29 E+02/5.70 E+03 - 0.023 Kr-88 1.85 E+02/5.70 E+03 - 0.032 Xe-135 Next, the stack release rate of each noble gas i from Equation (3-28) can be substituted into Equation (3-5) to give the skin dose rate as:
1 F f DFj skins
- N W g g
+
- 80,000 1/1E+08 7.55 E+07 [(0.904)(9.60 E-03)
(0.042)(i.06 E-02) + (0.023)(1.32 E-02) + (0.032)(2.60 E-03)]
= 6.04 E+04 (8.68 E-03 + 4.45 E-04 + 3.04 E-04 + 8.32 E-05) 6.04 E+04 (9.51 E-03)
Answer kskins - 574 mrem / year noble gas skin dose rate.
12 Date 10/01/91 Revision A-11 8855R
DIis
*~S'C f i (t >5 days) (*Ci-year) u i
- 1. 4.57 E-04 Xe-133 Calculation The skin dose rate is calculated from Eauations (3-7) and (3-28):
ht 0Fj3 skins - i J
(mrem) (fCl) (mrem-sec) uCi-yr .!(e yr sec and, the stack release rate is determined from:
.SJAE (3-28)
.ST Qg )
Oi * " 'ST I
.SJAE Oi g
However, for times greater than five days after shutdown, Xe-133 may be used Therefore, in Equation (3-28) the ratio as the referenced radionuclide alone.
.SJAE .SJAE to the sum of all Q g can be replaced by a value of I which of Qg indicates that all the contribution to the release is from Xe-133.
Therefore:
.ST Q Xe-133 1.0 x 120,000 x 1/1E+08 x 7.55 E+07 (cpm) (cc/sec)
(UCi/cc) cpm
.ST Q Xe-133 - 90,600 uCi/sec.
Revision 12 Date 10/01/01 A-13 8855R
' ~ ---------.u.___,___.__
.5T Therefore, replacing this value of Og into Eauation (3-7) we find the skin dose rate as:
kW ns - 90,600 x 4.57 E-04 (mrem} (UC1} (mrem-sec) yr iec uCi-yr Answer k . 41.4 mrem / year.
I 0 01 'l Revision Date A-14 8855R
EXAMPLE PROBLEM NO._ 6
- l.IIRe Critical _ Organ Dose Rate From Iodine, Tritium, and Particulates References
=- a ) OOCH Section 3.6 (Method I).
, 'b) Technical Specification 3.8.E.1.b.
Problem Calculate the critical organ dose rate due to measured effluent data taken from the plant . tack for a seven-day sample collection period.
Plant Data-a)' Stack particulate analysis for the seven-day period of interest.
(I'
.STP 0; .
Activity Q mre c i
i (uCl/sec) g yr-uCi )
'Sr-89*
1.42 E-04* 2.23 E+02 Sr-90* 3.50 E-03* 8.48 E+03 Co-60 -4.89 E-02 2.12 E+02 Cs-137 3.90 E-03 3.44 E+02 Zn-65 1.01 E-02 7.51 E+01 Na-24** 2.76 E-03** --
Mn-54+ <2.87 E-06+ 1.72 E+01 (II- ~DFG i co' dose rate-facter for each radionuclide is taken from
-Table 1.1-12.
' Revision 12 Date 10/01/91 A-15
(qty .
- For Sr-89/90, use the most recent available measurement from quarters composite analysis.
- Na-24 has a half. life of less than 8-1/2 days, and therefore is not included in the dose analysis per requirement; of Technical Specification 3.8.E.1.b even though it was detected.
+Hn-54 is not included in the dose analysis since it was not detected as .
being present above'the LLO.
b) Steck iodine (charcoal and particulate activities combined for the seven-day period of interest):
t
1 (uCi/sec) fvr-uC1 I-131 1.16 E-03 1.51 E+03 I-133* <6.35 E-05* 1.61 E+01 I-135** 7.21 E-03** 5.i4 E-01 and H-3+- 3.17 E-02 5.70 E-03 Notes
- I-133 is not included in the dose analysis for this case since it was not detected is being present in the stack analysis.
- I-135 is not included in the dose analysis because it has a half life less than 8-1/2-for particulates, and is not included as a required iodine in Technical Specification 3.8.E.1.b.
F
+ Tritium value based as latest available stack grab sample.
Revision 12 Date10/01/91 A-16 8855R l
= Calculation i
LThe Jose rate is calculated from Equation (3-16):
.5TP (3-16) 01 DFG,ico cos " 1 s zmrem) guC1) (mrem-sec) uC1-yr yr set The dose rate factors (DFGsico) for each of the radionutildes detected in
'the plant stack charcoal and particulate filter sample (plus tritium) is taken t' rom Table 1.1-12 of the 00CM.
Therefore:
k - (1.42 E-04)(2.23 E+02) + (3.50 E-03)(8.48 E+03) +-(4.89 E-02) cos *
(2.12 E+02) + (3.90 E-03)(3.44 E+02)
+ (1.01 E-02)(7.51 E+01)
+ (1.16 E-03)(1.51 E+03) + (3.17 E-02)(5.70 E-03)'-
Answer L - '
R egg
-33.6 mrem / year critical organ dose rate from iodine, tritium, and j particulate.
I Revi s ion - 12 Date lo /c1/01 l:-
L A 17 8855R
EXAMPLE PROBLEM NO. 7.
1121 i ,
Gcmma Air Dose From Noble Gases released from stack References a) '00CM Section 3.7 (Method I).
b) . Technical Specification 3.8.F.1.
Problem Calculate the maximum gamma air dose re ;1 ting from noble gases released from the plant stack over a calendar month.
Plant Data
. Based on the daily off-gae, analysis, the total activity released during the month of interest is:
DF{*
- . Activity Qf 3 I mrad-m nCi-yr
}
- i (C1)
Kr-88 '3.55 E-01 1.52 E-02 Kr-85m 4.71 E+00 1.23 E-03
-Xe-138 12.75 E+00 9.21 E-03
-Xe-135' 3.51'E+01 1.92 E-03 ,
.Xe-133 9.42 E401 3.53 E-04
- Gamma air dose factors taken from Table 1.1-10.
Revision 12 ~ Date 10/01/91 A-18 8855R
' Calculation-
- The maximum gamma air dose off-site is calculated from Equation (3-21):
'3-21)
'Dfirs-0.022 QfT DFf _
3 (mrad) (pp ,yr) (C1)
(mrad-m pC1-yr )
3 C1-m Therefore:
+ (4.71 E+00)(1.23 E-03)
Ofirs - 0.0?.2 [:3.55 E-01)(1.52 E-02)
+ (2.75 E+00)(9.21 E-03) + (3.51 E+01)(1.92 E-03) +
(9.42 E+01)(3.52 E-04)]
- 0.022 (5,40 E-03 + 5.79 E-03 + 2.53 E-02 + 6.74 E-02 +
3.31 E-02)
Answer
-Ofirs-3.01E-03mradgammaairdoseduringthemonth.
i Revision 12 Date lo /01/91 !
I' A-19 8855R m ----
.. ~ .. . -- ~ . . - . _ , . . .= . ..
1 EXAMPLE C,.LCULATION NO. 8- l Tm
-Beta' Air Dose from Ncble Gases released from stack References a) 00CM Section 3.8 (Method I).
b)' Technical Specification-3.8.F.I.
-Problem LCalculate the maximum beta air dose resulting from the same noble gas releases given in Example Calculation No. 7.
Plant' Data from Example No. 7, the total activity determined to be released during the month is:
OFf*
b 3 Activity Q (mrad-m
,pC1-yr )
'l (Ci)
Kr-88 3.55 E-01 2.93 E-03 Kr-85m 4.71 E+00. 1.97 E-03 Xe-138 2.75 E+00 4.75 E-03 Xe-135 3.51 E+01 2.46 E-03 Xe-133 9.42 E+01 1.05 E-03
'*Beta air dose factors taken from Table 1.1-10.
Revision 12 Date 10/01/91 A-20 8855R
Calculation
.The maximum beta air dose offL. site is alculated from Equation (3-23):
Offrs-0.019 fD (3-23) 3 (mrad) (pCl-yr) (Cl) (mrad-m )
3 pCl-yr Cl-m Therefore:
6 0, 7 - 0.019 [(3.55 E-01)(2.93 E-03) + (4.71 E+00)(1.97 E-03)
+ (2.75 E+00)(4.75 E-03) + (3.51 E+01)(2.46 E-03) +
(9.42 E+01)(1.05 E-03)]
= 0.019 (1.04 E-03 + 9.28 E-03 + 1.31 E-02 + 8.63 E-02 +
9.89 E-02)'
Answer 0
0 lrs - 3.96 E-03 mrad beta. air dose during the month.
Revision 12 Date 10/01/91 A-21 8855R
--m _ w -m -
-r e -, - - - + , ,
EXAMPLE PROBLEM-NO. 9- .
- hte Critical. Organ Dose from Iodine, Tritium, and Particulates References a) 00CM Sectior 3.9 (Method I).
b) Technical Specification 3.8.G.I.
Problem Calculate the critical organ dose due to the total activity recorded as being released from the plant stack during a calendar month.
Plant Data a) From the combined stack analyses during the month, the following acthity released is.
1 DFG q STP sico 1
(mrem) i (Ci) C1 Sr-89* 5.42 E-04* 7.08 E+00 Sr-90* 1.10 E-02* 2.69 E+02 Co-60 2.30 E-01 4.76 E+00 1.15 E-02 1.01-E+01
.Cs-137.
Zn-65 2.60 E-02 '2'.32 E+00 Na-24** 7.11 E-03** --
Mn-54 <2.76 E-06+ 4.36 E-01 l
1 Revi'ston 1 Date,o/m /ci A-22 8855R
APPENDIX J ON-SITE DISPOSAL OF SEPTIC WASTE Re.quir.ement: Off-Site Dose Calculational Manual, Appendix B requires that the dose impact due to on-site disposal of septic waste during the-reporting year and from previous years be reported to the Commission in the Semiannual Radioactive Effluent Report filed after January 1 if disposals occur during the reporting year.
-Response: There were no on-site disposals of septic waste during the reporting year.
l l
l J-1 8792R l
i'
.*--. _ _ _ __ .-m --.-- ..g e F
- 9 .,c . , ~ . ..-.zq.pp..p.e i.n g 3 y p w g e
Notes for Plant Data a) Above (1) Critical organ dose factor taken from Table 1.1-12.
- For Sr-89/90, use the most recent available measurement from the quarterly composite _ analysis.
- Na-24 has a half life of lecs than 8-1/2 days, and therefore is not included in accordance with Techitical Specification 3.8.G.I.
+Mn-54 is not included in the dose analysis since it was not detected as being present above the required LLD.
b) Total iodine release for the month based on the combined charcoal and ;
particulate filter samples taken during the month:
' OIO STP sico 01 (mrem) i (Ci) Ci I-131 4.30 E-03 4.80 E+01 -
I.133 1.12 E-04* 5.12 E-01 1-135** 2.01 E-02**
and H-3+ 0.15 1.81 E-04 Calculation The dose is calculated from Equation (3-25):
G-29 O
ggg
=
O f DFG3gcg (mrem) (C1) (mrem /C1) 1# 10/01!91 Revision Date
, A-23 8855R
Notes for Plant Data b) Above
- In this case 1-133 was found in one of the weekly stack sa': pies to be present,'and therefore based on that value is included-in the dose analysis.
- I-135 is not included in the dose analysis because it has a half life less than 8-1/2 days for particulates~and is not included as a required iodine in Technical Specification 3.8.B.I.
+ Tritium value based on the monthly stack grab sample.
The dose factor-(DFGsico) for each radionuclide detected in the plant stack charcoal and particulate-filter sample (plus tritium) is taken from Table 1.1-12 of the 00CM.
I Therefore:
O cg3 - (5.42 E-04)(7.08 E+00) + (1.10 E-02)(2.69 E+02) +
(2.30 E-01)(4.76 E+00) + (1.15 E-02)(1.01 E+01) +
- (2.60 E-02)(2.32 E+00) + (4.30 E-03)(4.80 E+01) +
(1.12 E-04)(5.12 E-01) + (0.15)(1.81 E-04) -
Answer.
D = 4.44 mrem maximum organ dose for the month.
cg3 5
Revision 12 Date 10/01/91 A-24 8855R
l APPENDIX I RADIOACTIVE LIQUID, CASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Eqquiremani: Technical Specification 6.14.A requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evalustion was reviewed by the Plant Operation Review Committee.
Re.aponse: There were no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting period.
5 I-1 8792R
.