ML20090C502
| ML20090C502 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/31/1991 |
| From: | Fey F NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20090C496 | List: |
| References | |
| NUDOCS 9203050062 | |
| Download: ML20090C502 (14) | |
Text
-_ -
6 TRANSMITTAL MANIFEST liCRTilERN STATES POWER COMPANY NPJLEAR GENERATION DEPARTMEllT liMIIC.ERO.JN.CLEAILEERERAlllLG_EhllT Effluent and Waste Dinposal Semiannual Report LQr Ju1y L_3.22 L_throuall_D.ec9nbsr_2L._.ME MANIFEFT DATE: FEBRUARY 27, 1992 USNRC 4
ANI Library 1
- Regional Admin III General Electric 2
- NRR Project Manager San Jose Cust. Serv.
- DCD San Jose Fuel Proj. Mgr
- Resident Inspector Shaw Pittman Potts &
Trowbridge 1
F M Bendell 1
J Silberg K P Jepson 1
Safety Audit Committee 10 P H Kamman 1
- F. J Albrecht J E Windschill 1
- A B Cutter P I Plant Manager 1
- R L Hannen Monti Site Gen Manager 1
- W J 11111 ERAD Department 1
- D D Lanning Attn: Records Clerk
- D M Musolf Communications Department 1
- G H Neils
- NRS File 1
- T M Parker
- NSS File 1
- J A Thie
- MDH 1
- Secretary Attn: Comm. of Health Manifest File
__.m.
_,.m NORTilER?! STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 i
EFFLt!ENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 Supplemental Information
- 11. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A. Noble Gases 5 mrad / quarter gamme radiation
-10 mrad / quarter beta radiation B.
Long. Lived Iodines, Particulates, and Tritium :
7.5 mrem / quarter dose to any organ C.
Liquid Effluents :
1.5 mrem / quarter dose to the total body S.0 mrem / quarter dose to any organ
- 2. Maximum Permissible Concentrations A. Noble Gases :
10 CFR Part 20, Appendix B, Table II, Column 1 B.
Long Lived-Iodines,-Particulates, and Tritium :
-10 CFR Part 20, AppendixRB, Table II, Column 1 i
C.fLiquid Effluents :
10 CFR Part 20,' Appendix B, Table II, Column 2 2.0 E-4 uci/ml_for dissolved and entrained gases
'3.
Average Energy l
(Not Applicable)
_, - - - -. ~
_ ~,.
- ~.
.. -. - - -. -. ~. _ _
. ~.. -. - _ -. -. -. - -
Page 2
y 2
EFFLUENT AND WASTE-DISPOSAL SEMIANNUAL REPORT Perloo : Jul - Dec 1991 Suppl'emental Informacion (continued)
- 4. Measurements and Approximations of Total Radioactivty-4 A., Noble Gases t Continuous--gross activity monitors in Reactor Building Vent and Plant Stack exhaust streams, n'eekly isotopic analysis of exhaust streams.
B.
Iodines in Gaseous Effluent :
Continuous monitoring with charcoal cartridges in Reactor Building
-Vent and Plant. Stack exhaust streams with weekly analysis.
C. Particulates in Gasecos Effluent :
Continuous monitoring with particulate filters in Reactor. Building Vent and Plant Stack exhaust r-treamn with weekly analys?.c.
-D.
Tritium in Gaseous Efflue.nt :
Continous monitoring with silica gel cartridges in Reactor Building
' Vent and Plant Stack exhaust streams with' weekly analysis.
E.
Liquid Effluents :
-Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during planned release.
5 Batch Releases A. Liquid :
1.. Number of Batch Releases 0
'2. Total Time Period for' Batch Releases NA min
- 3. Maximum Time Period.for a Batch Release NA min 4.l Average Time Period for a Batch Release NA min
- 5. Minimum Time Period for a Datch Relense NA min
- 6. Average River Flow During Release NA cf/see B.
Gaseous::.
- 1. Number of. Batch Releases.
2
- 2. Total-Time Period for Batch Releases 4630.0 min
- 3. Maximum Time Period for a Batch Release 4030.0 min
- 4. Average Time Period for a Batch Release 2315.0-min
- 5. Minimum Time Period for a Batch Release 600.0 min I
l-
~...
, ~...
~
. _ _. _. _ _-.._... - ~.. _..
__.__._.e_._
Page 3-
-l
)
l
_ EFFLUENT.AND WASTE DISPOSAL SEtt1 ANNUAL REPORT Period : Jul - Dec 1991-1 supplemental Information__(continued) r6.-Abnormal neleases A.
Liquid :
T. Number of Releases 0
- 2. Total Activity Released NA Ci
-B.
Gaseous _:
- 1. Number of Releases 0
- 2. Total _ Activity Released 0.0 Ci 4
I I
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I l
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Page-4 a
EFPLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 i
Table 1A Gaseous Effluents - Summation of all Releases i
~
i Un7 ts l 3iW~Dtr
[~TtTi 6Er
[Est. Totar e
_l
[___
L l Error, %
i A.;: Fission & Activation gases 1-~~To L a 1-11e 1 e a s e cT 533ETF2
~4~61E+02 l 2~~0Tf70T-l l~~1. Av e r aJ'e Re Te a s e Ra t e uciLsec 6 6DETOT 5.87ETUT l
- 3. Percent Tec) Spec Otrly l
l l
- Reporting Level
! 1.26E+00 6.88E-01 l Gamma Radiation l
_ Beta Radiation J
't l 4.18 E- 01 1.50E-01 j D.
~ 1.
ToEaT~I-TTI~ Tete a s e C~
1.17 6f- 0 2
- 7. DIE-03
- 1. UFfTUl~ l
~
'~
- 2. Average ITf3T Release-nate uci/see 1.T7E-03
- 8. 8.TE 0 4 C,-Particulates
~l~ 1.. Total ParticulAles*
Ci 1.6FE-03 9.7FE-04 3.000+01'l
~
~
~
T. IE-04 1.2TE0'4 T
- 2. Average Release RTte ucI/sec
],~.~ Gross Alpha Radlong ivity
_ CT 6 GE-06 4 lTE-03,]
D.
Tritium T. 6ETDT~I~FTETDT 1.0OU UT-l
~1.
TotaT'Re1 ease cr~
T
- ~~2 Average _ Release Rate, Eci/sec
~1.83E+00 2 ~. 47E + 0 0
'E.
Percent Orrly Tech Spec Reporting Levels
~~
?)
l'~1odines, Particulates, I
l l_
and Tritium J
't l 2.97E+00 1.99E+00 i t
e 1
4 3
l w
w-wwy r
t me -
ww e-i-wi g-s er e
m
=
r-+--
l Page 5
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 Table la Gaseous Effluents - Elevated Releases
]
l l
Continuous Moide l
D'atch Mode l
~
l Nuclides Released
[ Unit j 3rd Qtr j 4th Otr l 3rd Otr l 4th Ott l
1.
Fission Gases 0.00 U03 1 0.0Tc+00 i
KR-85F C I 570 E +T6-~ ~~5 Y B E + 0 0
- 0. 0TG6D ' DTDTETOT-l KR-17 Cl F.TT&TO-lT6TsT6D DTOTE+TO~ 'O.0TYTDFlI
~
KR-8T~
Cl I~T6YTOT- ~2TT7tTWO-KR-IS Ci B 6FETO~0 2~T6YT00 0.065T00 0. 0 0 E + 0 0- l
~
xE-l!3 CI-
~F.70t7T2 9.57E+01 4~T6E-03 0.00E+00 l
~
- 0. 0TU60 0.00E+00 xC-l'37M Ci 2.2FE400 2.Tff70D 7~TTE UT O' FDRTGU~ll T
XE-1B Ci
~5 T6TTOI -6.36E+01-l XE-~B5E CE T.75YTOT 7 3BYTOT UTo~0 E+ 0 0
~6 TOYT60--l l
X E-TT7 CT T.75YT6T~~T 7FGD 2 0.00E+66
- 0. 0 0 E+ 0F l
~
0 30E+00 l
XE-136~
Ci
- 6. 5B E:T61 6.58E+11 0.0TE+00 070TTOT~ 1 l
AR-41
~~Ci 1.97Y 0T 0.0DE+00 3.50E l
~
i I
l Total for Period
~dI 4~2TE+12 3 F6 E + 0T~
- 1. 25Y~~07
- 0. 0 0 E + 0T l 2.
Iodines I-T33 C I'
- 3. 3 5F03 l T~TDE~T4 0.03t+00 0.DlE+0T'l I-T3'l Ci-2.TfC DT '~3.48E-03 0.00E+00 0.00E+66~l
~
Ci 2. 7 8 E-OT~I~71 TDT o.00E+60~TDTt7DF l I-13F l
l Total for Perio3 Ci L 5.15 E-T2~ ~T~0Ts~~0 3 0.00E+06 0.00E+00 1
- 3. Particulates 0.00E+00 CR-51 C1 2.11E-06 0.WD8700 6 DOE +00
~T.TUYTDT ll MN-54 Ci 1.13E-06 1.72E-DT-~~T.~0 D E + 0 0 CO-60 Ci 8.f9E-06 23 3E-06 T T TETO~8 0. 0 0 E + 0 0~~ l ZN-55 Ci 1.4FE-06
- 4. 8 4 E- 07 0.00C+00 0.F6E+00 1 ZR-95 CI' 2.28E-5T~
6 TOTE +00 0.0DE+00
- 0. 0 DYTDF l
~
C5-137 Ci 1.75T~T5~
9.84E-06 0.00E+00 0 6DE+00 BA-14'D -
CI 3.28E-Of 3.97'E-04 0.00YT00 0.00E+00-SR-89 Ci 6.08E-04 DT60TT6D 0.0TETOT 0.00E+00 ST-lF Ci
- 5. 7F5~57 0.0lE+00 0.00YTED OTDTE+00 l
Total for Period Ci 9.67E-04 4.10T~T4 1.82E-08 0.00E+TO' Analysis of St-89 & 90 for the 4th Qtr war not complete 1 in time for this report, results will be included with the next semiannual report.
i
.. _ _ _ _ _ _ _ _ _... _. _....... _. ~. _ _, _. ~. _ _ _ _ _ _ _. _. ~ _ _... _ _.
Page 6
-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 I
Table 1C Gaseous Effluents - Building Vent Releases
~~
l Cont'inuous Mode Datch Mode l
Nuclides Released l Unit 3rd Otr 1 4th Qtr 3rd Otr l 4th Otr l
1.
Fission Gases 1
KR-88 61 4.57E-01 2.7Tt+00 0.00E+00 0.00E+00 KR-89 Ci
1.1fE+01 0.00ERT-0 6DE+00
=0 TOT UTO~
~
XE-133 C i ~~
1.12E+01 1.8FE-01 0.00E+00 3.1TE~0T i XE-IT5 Ci ET6DTI 2.07ET01 0.00ETD0 3. 4 3 E-5T XE-135M Ci-3.23E401 4.04E+01 0.00E+00 0.00E+00 XE-138 Ci 0.0VE+00 1.14E+0V U.00E+00 0.0FE+00 Total for Period i Ci 9. 73 E + 0T~ T T1E+01 0.00E+00 6.57E-03'
~
- 3. Iodines.
I-131 Ci 8.35E-03 6.20E-03 0.00E+00 0.00E+00 1-133 Ci 7.31Ea02
- 5. 2 fE- 0 2 0 TD~ET0F 0.00E+00 1-135 Ci
- 9. 3 5 E- 0 2
~8.84E-02 0.60E+00 0.0TE70F-Total for Period Ci G E-01
~1.47E-61 0.00E+00 0.00E+00~
- 3. Particulates-1 MN-54 Ci 1.48E-05 7.10E-06 0.00E+F0 0.00E+00 CO-60 C1 2.58E-04 1.1TE-04 0.00E+00 0.00E+00 Zh-65 C1 4.lBE-05
- 1. 0 3 E-64 0.00E+00 0.00E+00 1
CS-137 C1 4.31E-05 9.Tik-06 0.00E+00 0.00E+00 BA-140 Ci 3.T E-04 3. l fE- 0 4 0.06E+00 0.00E+0F CE-141 Ci 3.06E-05 2.34E-0T~
0.00E+00 0.0VE+0D
SR-89 C1 3.84E-06
--F 00E+00_
0.0'UE+00 0.00E+00
~~
Total for Period Ci 7.08E-04 5.69E 0.00E+00 0.00E+00~'
Analysis'of Sr-89 & 90 for the 4th Qtr was not completed in time for this report, results will be. included with the next semiannual report.
I i-i.
- j..
I-
Page T
~
EFFLUENT AND-WASTE DISPOSAL SEMIAN!1UAL REPORT Period Jul - Dec 1991 Table 2A Llould Effluents - Summation of all Releaces l
Onits
[~ITd Qtr l 4Ih7E r list. Total l
1 l
__1 Error,j_
'A.. Fission & Activation products 1
I l
~
~
~ 1._ Total Release (not includingT--
Ci 0.00E+00
-0.00E+00 0.00E+00 l
-tritium ases, alpha) e
- 2. Avg DT u eT Concentrati'on u cT7iU ~~~0700ET60 6760Y70V B.
- 1. Total Release di~~
~0TOTsTO~6 OT00ET60 0 60f70Fl
-- l ~~~2. Av g Diluted ConcentTation uci/mI 0.00E+00
- 0. 60YTOE l
C. Dissolved and Entrained Gases.
- 1. Total Release
~'~Ci
-0.60E+0F 0.06t+00 0.0DE+00~l
~7._ Avg DT1ut_ed Concentration uci/ml
-~DT60T760 0. 6FETUD-v D. Percent-Qttly Tech Spec 1 Reporting Level
- 1. hhole Body Dose t
- 0. 66tT00 U~66tT5U-l 2.
Organ Dose
~T~
,37F0E+00 0.6DET66~l E. Gross' Alpha Radioactivity l
l;
}
- 1. Total Release l
Ci l 0.00E+00 i ~0TDTE+00 I 0~. 0~0ET60 1
]F. Volume-of Waste Released'~ _
-l Liters l 0. UTETU O l 0.60E+00 i 0.0DETOTl lT.. Volume of Dilution Water Used i Liters'l 0.00E+00 I T~5Ft_TO'5 ;I - 6 TOTTOT~l Table 2D Liquid Effluents l
l l
ConU nuous Mode Ba tch tiode l
i
. Nuclides Releaspd l Unit 1 3rd Otr.
.l ith Qtr 3rd,Otr i 4th Otr l
l.
None Heleased This Period I
a i_.
.. ~. - - ~. ~.. ~. ~.
. - -. - -.. -.... ~ -. - -. - -.
... - -. - -- _.~.
Page 8
i ErrLUENT /.ND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 i
Table 3 Solid Waste and Irradiated ruel Shipments
-- A. Solid Waste Shipped offsite for Burial or Disposal (not irradiated fuel)
)-
~
I
~~I~.~~T W ~o~f Waste Units 6-month-Est. Total l Period Ettor,-%
- a. Spent-resTEs, filter ciudges, Cu. Meter 7.34E+31 evap, orator bottoms, etc.
Ci 9.95E402 3.70E+01 b.-Dry compressTble waste,-~~
Cu? Meter 6. 8TETU T~
[
contaminated-equipment, etc.
Ci 4.26E401 3.50E+01
[
c.'Trradiated components, Cu. Meter 0.00EfD0 etc.
Ci 0.00E+00 0.00E+01 con t r ol - rods,Fe )
__d. _0 t h e r~(T6scri Cu. Meter GTO GETO~O 4
l.,__ C i 1 0.00E+00
_0.00E+01 7 7 jistimate of major nuclide
{
Nuc11~de lTPercent l
i-l composition (by-type of waste)
L I
_1 I-A l
l_
]
Cr-51 2.00E-01 l
l Mn-54 5.60E+00 l
re-55 2.94E+01 l
H-3 1.21E-02 l
Co-58 5.24E-01 l
E l
re-59 1.89E-01 Co-60 3.07E+01 N1-63 1.52E-01 I
Zn-65 2.98E+01 Sr-89 3,18E-01 St-90 3.42E-02
[l Tc-99 6.81E-05 I-131 4.17E-01 Cs-134 7.51E-02 I-129 1.34E-04 l
Cs-137 2.13E+00 l
i Ba-140 1.72E-01 La-140
-5.24E-02 Ce-141 2.69E-02 l Pu-238 2.56E-04 1 1
Pu -2 39 1.36E-04 l l
Am-241 3.22E-04 l
'l Pu-241 1.53E-02 l c
Cm-242 2.56E-04 l Pu-242 1.77E-08 l l
Cm-243 7.05E-04 [
j C-14 2.40E-01 l 1
-1 1
B l
l Mn-54 l 4.13E+00 l l
Fe-55 l 2.40E+01 l i
l H-3 l 6.60E+00-l-1 l
Co-58
-l 1.04E-01.l il l
Co-60 l 4.26E+01 j
l Ni-63 l 2.41E-01 i
I Zn-65 l 1.68E+01 j
Sr-89 l 9.20E-01 i
~
l Sr-90 1.93E-01 l i
l Tc-99 1.12E-05
-l l
Cs-134 1.87E-01 l-I-129 1.91E-04 1
.m
Page 9
1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1991 Table 3 Solid waste and Irradiated ruel Shipmtnts
- 3. Solid waste disposal l Number of l Mode of-l Destinalion l
} Shipments Transportation
__ _h e m-N u c Inc., Barnwell, SC.
C l
7 Truck 5
Truck US Ecology, Richland, WA.
3 l
Railway l
US Ecology, Richland, WA.
24 l
Truck l
US Ecology, Beatty, NV.
I l
1 B.
Irradiated fuel Shipments
- 1. Disposition
~ ' ~ ~
l Number of l Mode of l
Destination
] Shipments l Transportation l None This Period C. Shipping Container and Solidification Method l
No.
Volume i
Activity l Type of FContainet l Solidification l 91-63 5.51E+00 7.54E+FT A
T A
D ~~
l M3 Ci Waste l
Code Code l
91-66 l 2.00E+01 l 1.51E+00 l A
l L
l D
l 91-69 5.83E+00 5.42E+01 l A
l A
l D
l 91-74 5.83E+00
, 5.88E+01 l A
}
A l
D l
91-75 l 5.83E+00 l 4.53E+01 l A
l A
l D
l 91-76 l 3.41E+00 l 3.05E+02 }
A
{
A l
D l
91-77 3.41E+00 l 2.39E+02 l A
}
A i
0 91-79 5.83E400 l 9.26E+01 1 A
l A
D 91-81 5.83E+00 f 6.60E+01 1 A
l A
l D
)
91-84 l 5.83E+00 3.92E+01 A
l A
l D
91-88 l 5.83E+00 1.76E+01 A
l A
l D
91-90 l 3.81E+01 1.67E+00 B
i L
l N
l 91-91 1 5.84E+00 3.45E+01
}
B l
A l
N l
91-92 9.09E+00 3.80E-01 l B
l L
l N
l l
9120a l 1.03E+00 l 1.46E-02 ;
e l
L 1
N l
9120b i 3.40E-02 l 2.86E-02 l B
l L
l N
l 9120e l 5.66E-03 l 1.03E-03 I B
l L
l U
1 9120d 9.63E-02 l 1.11E-02 i B
l L
l n
]
9120e 1.42E-02 l 3.13E-04 l B
l L
l M
l 9130a
, 1.74E+00 l 4.01E-02 l B
l L
l N
l 9130b l 3.13E+00 1 8.70E-02 l B
l L
i N
1 l 9130c l 6.03E-01 1 1.35E-02 l B
l L
l N
l 9130d I 3.40E-02 l 8.99E-02 l B
l L
l N
l 9130e 5.95E-01 l 1.69E-02 l B
l L
l N
l 9147a 5.01E-01 J 1.82E-02 l B
l L
l N
l 9147b 8.21E-01 3.18E-02 l B
l L
N i
9147c 9.06E-01 4.41E-02 l L
l L
l N
l 9147d l 4.30E-01 l 2.30E-02 l B
l L
j N
l l
I l
I l
. i Page 10 a
EFFLdENT-AND WASTE DISPOSAL SEMIANNUAL REPORT Period :-Jul - Doc 1991
,C.' Shipping Container and Solidification Method (Cont.)
-NoT Volume ActivTEy~~
Type of I ConfiTner T Yoli IITication
~
M3
~ Ci:
waste code-Code
~~
' "V147e
~4.53E-01 2.72E-02 B
L N
-9147f
-1.13E-01
- 2.09E-01 B
L N
9157a !
4.76E-01 1.06E-02 B
L t1 9157b 9.74E-01 3.13E-02 B
L N
9157c 3.60E 1.40E-02' B
L N
9157d 5.58E-01 1.43E-02 B
L N
l l'9157e 5.07E-01 1.77E-02 D
L N
9157f 6.80E-02
- 1.43E+00 B
L N
~91579-3.85E-01 9.31E-03 B
I L
N 9178a 9.63E-01.
- 8.56E-03 B-L N
-9178b 4.33E 3.67E+00 :
B l
L 1-N
.l' l
l l
l Container Codes : --
Solidification Codes :
L'-
LSA C - Cement-
.A
_ Type A U - Urea-Formaldehyde D'- Type B D - Dewatering Q -'Large Quantity N - Not Applicalble i-r G
\\
v 7.
t" - " **
- Per-*r-
-s
M-?
wy a
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NORTHERN STATES POWER COMPANY M9HTICILLO HMCLEAR_GEMEBATIH9_ELART 0FF _ SITE RhD1hTlQN_DQSE_hSJ2RBJiMENLJSR Q
Janyaj.v 1-Dece1nbgr_.;LL_.19JLL An assessment of radiation dono due to release from the Monticello Nuclear Generating Plant during 1991 was performed in accordance with the Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
Off-sito dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the two Effluent and Wacto Disposal Semiannual Reports prepared for NRC review during i
the year of 1991.
QLf-pJto Dosep from Gase_gus Relgase Computed doses due to gaseous releases are reported in Table 1.
Critical receptor location
'a r.d pathways for organ doses are reported in Table 2. Doses, both whole body and organ, are a small percent. age of Appendix I Guidelines.
Off-sile,Joses from_ Liquid Release There were no liquid Teleases made from the Monticello Plant during the 1991 calendar year.
D,9# e a t o Ind lyid u aJ p_D31g_t oJglivJlic a Inaid e_tjittli.t e_h931D Aa a 4
Occasionally sportsmen enter the Monticello site for recreational activities, in addition, an Environmental Protection Agency Field Station is located at the Monticello site (see Figure 3.8.1 and Figure 3.8.2 of Monticello Technical Specifications). Workers at this Field Station, spending an average of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week, are the most exposed individuals. Whole body doses to these individuals have been computed using stack and vent X/Q values for the Field
- Station location. Annual computed _ doses were reduced by the factor
-of_40/168 to account for the limited occupancy for workers at this location. Organ doses to workers at the EPA Field Station due to gaseous releases have been computed for inhalation pathway (no other pathway exists). Doses at this location were reported in Table 1.
4
DQJ!Le8 t O_.li9At JKp.q s_eA _}!e mh gr_gL t h e_qe RenaLEu blip _ Ing m _Ite a e t oX ReleA#RP_gpd Other_,JltanipptEuqLQyclgJp_ptgpa There are no other uranium fuel facilities in the vicinity of the Monticello site.
The only other artificial sotree of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactor and the steam turbines, MNGP started a hydrogen water chemistry (llWC) program in February 1989.
Prior to the installation of HWC, a study was conducted to determine the direct and skyshine radiation contribution from IlWC.
This study determined the maximum exposed member of the public from direct and skynhine radiation to be a residence located 0.6 mile from the reactor at the SW sector.
Using conservative assumption, calculations indicated a maximum annual dose of 4 mrom to this residence.
!!owever, a review of TLD results f rom 1987, 1988, 1989, 1990, and 1991 revealed no noticeable increase in direct and skyshina radiation as a result of the llHC program installed in early 1989.
l A calculation of the total annual dose to this residence from all existing pathways of radioactive effluents were performed by running GASPAR computer codes.
Adding the 4 mrem / year to this calculation results in a
maximum whole body dose of 4.083 mrem / year.
Therefore, the most exposed member of the general public will not receive an annual radiation dose from reactor ef fluent releases and all other fuel cycle activities in excess of 40 Crit Part 190 standards of 25 mrom to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.
t TABLE 1 OFF-SITE RADIATION DOSE ASSESSMENT - MONTICELLO l
PERIOD: JANJ h10. 1 1h_tg u g }t_pXp_E M Q E}L)12_L9391 10 CFR Part 50 Appendix I Guidelines per unit per year Gasco_gL Aglpasos Maximum Site Boundary Gamma Air Dose (mrad) 0.177 10 Maximum Sito Boundary Beta Air Dose (mrad) 0.126 20 Maximum Off-site Dose to Any Organ (mrem)*
Total 0.261 15 EPA Field Station (mrem, 40 hourn/ week)
Whole Body 0.105 5
Organ 0.167 15 Liquid _,ReleapLop Maximum Off-site Dose Whole Body (mrem) 0.0 3
Maximum Off-site Dose Organ, Total 0.0 10
4 TABLE 2 OFF-SITE RADIATION DOSE ASSESSMENT - MONTICELLO SUPPLEMENTAL INFORMATION PERIOD: aHUARYJ_t hto3g h_plcJ;MpIR_m_.J3Sl GaseoJs RoJearea Maximum Site Boundary Dose Location (from building vents)
Sector NNW Distance (miles) 0.4 EPA Field Station Sector ESE Distance (miles) 0.3 Maximum Off-site Dose Location Sector ESE Distance (miles) 2.5 Pathways
- Plume, Ground, Inhalation, Cow Milk Age Group Infant Organ Thyroid Liquid Releasqp Maximum Off-site Dose Location Downstream Pathways Drinking Water Drinking Water Fish Age Group Infant Adult Organ Whole Body GI-LLI Dilution Factor 7.1 7.1 (drinking water)
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