ML18038A135
| ML18038A135 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/31/1985 |
| From: | Abbott R, Leach E, Managan C, Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| (NMP2L-0650), (NMP2L-650), 1359G, PROC-851031, NUDOCS 8603110333 | |
| Download: ML18038A135 (109) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)
ACCESSION NBR: 8b03110333 DOC. DATE: 85/10/31 NOTARIZED:
YES DOCKET 0 FACIL: 50-410 Nine Mile Point Nucleal Stationi Unit 2> Niagara Moha 05000410 AUTH. NAME AUTHOR AFFILIATION LEACHY E. N.
Niagara Mohawk Powel Corp.
ABBOTT'. B.
Niagara Mohawk Powel Col p.
M*NAGANiC. V.
Niagal a Mohawk Powel Corp.
RECIP. NAME RECIPIENT AFFILIATION ADENSAM> E. G.
BNR ProJect Dil ectol ate 3
SUBJECT; Rev 0 to "Offsite Dose Calculation Manual." W/two ovel size figures.
DISTRIBUTION CODE:
AOO'TD COPIES RECEIVED: LTR ENCL +
SIZE:
TITLE: OR/Licensing Submittal:
Appendix I NOTES:
RECIPIENT ID CODE/NAME HWR ADTS HNR EB HNR FQB BNR PSB FIL INTERNAL: ACRS 11 ELD/HDS3 19 NRR PNR-A *DTS NRR/
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NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474-1511 March 5, 1986 (NMP2L* 0650)
Hs. Elinor G. Adensam, Director BNR Project Directorate No.
3 U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Hashington, DC 20555 Dear Hs.
Adensam:
Re:
Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are ten copies of the Nine Mile Point Unit 2 Off Site Dose Calculation Manual (ODCH) for your use.
This information is referenced in the Unit 2 Technical Specifications Section 6.14.
Sincerely, C. V. Manga Senior Vice President CVM/NLR/ar 1359G Enclosure
"jj V
1
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation
)
(Nine Mile Point Unit 2)
)
Docket No.
50-410 AFFIDAVIT C. V. Man an
, being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.
Subscribed and swor o before me, a Notary Public in York and County of
, thisQ~
day of for e State.of New 1986.
ota y Public in and for County, =New York My Commission expires:
JANIS M. MACRO Notary Put llc In tho Stats of New York Quallflad In Ononda3a County No. 4784555 hly Commlsslon frrplrcs March 30, 19.5.7...
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'INE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 2 OFF-SITE DOSE CALCULATION MANUAL (ODCM)
APPROVALS SIGNATURES DATE AND INITIALS REVISION 0 REVISION 1 REVISION 2 Chemistry and Radiation Management Superintendent E.
W. Leach c
Station Superintendent NMPNS Unit 2 R. B. Abbott Genera1 Superintendent Nuc1ear Generation T. J. Perkins
/
V (C/8l/'f13 Summar of Pa es Revision 0
(Effective 10/31/85
)
PAGE 1-52 DATE October 1985 NIAGARA MOHAWK POWER CORPORATION REC.;l"."=0 0, ~ I '*I l1,):4 '>) I I'l~ I["M 4 t i>i t'~
JDi'.:-
R 'i
~<
4 'i THIS PROCEDURE NOT TO BE USED AFTER OCTOBER 1987 SUBJECT TO PERIODIC REVIEW.
8~o>>ioSSS Ssioai PDR': ABACK asoooexo I
- I
1.0 INTRODUCTION
This is the OFFSITE DOSE CALCULATION MANUAL (ODCM)-, referenced in the Nine Mile Point Unit 2 Technical Specifications.
It describes the methodology for liquid and gaseous effluent monitor alarm setpoint calculations, the methodology for computing the offsite dose due to liquid effluents, gaseous effluents, and the uranium fuel cycle as well as the rad1olog1cal environmental monitoring and interlaboratory comparison programs.
The ODCM will be reviewed and approved by'he NRC.
Changes shall be provided in the semi.
annual radioactive effluent release reports submitted to the NRC.
2.0 LI UID EFFLUENTS Service Water A
and B,
Cooling Tower Blowdown and the Liquid Radioactive Waste Discharge comprise the Radioactive Liquid Effluents at Unit 2.
Presently there are no temporary outdoor tanks containing radioactive water capable of affecting the nearest known or future water supply in an unrestricted area.
NUREG 0133 and Regulatory Guide 1.109, Rev.
1 were followed in the development of this sect1on.
2.1 Liquid Effluent Monitor Alarm Setpoint Determinat1on 2.1.1 Basis To provide a
safe margin of assurance that the instantaneous concentration of radionuclides
$ n 11quid form at the point of discharge into-the unrestricted area do not exceed the limits of 10CFR Part 20, Appendix B; Table II, Column 2.
Methodology for calculating alarm setpoint is described, as these are the setpoints which require act1on as described in the Technical Specifications.
- However, the monitors have alert setpo1nts which may require action as described in station procedures.
These are normally set at half the alarm setpoint, but may vary as described in station procedures.
2.1.2 Setpoint Determination Methodology 2.1.2.1 Liquid Radwaste Effluent Mon1tor Alarm Setpoint:
Alarm setpoint
< kF E (Ci CF1)+ ffE (Ci/MPC1)] + Background.
1 1
Where:
k Factor to account for sample
- analysis, detector.
flow and dilution flow measurement error.
Radwaste flow rate (gpm) alarm and control setpoint. October 1985
I
(
<4
2.1.2.1 (Cont'd)
Ci Concentration of isotope i (pCi/ml) in Radwaste tank prior to dilution.
CFi Detector calibration factor for isotope i (Net cpm/yCi/ml)
Table 2-1.
MPCi ~
Concentration limit for isotope i from 10CPR Part 20 Appendix B, Table II, Column 2 (yCi/ml).
F
~
Nonradioactive dilution flow rate (gpm).
Background
~
Detector response (cpm) when sample chamber is filled with nonradioactive water.
NOTE:
1.
E(CiCPi) may be evaluated from field measurements and utilized in lieu of specific CPi's of Table 2-1.
2.
MPC for noble gases dissolved or entrained is 2.00E-4yCi/ml.
2.1.2.2 Service Water A and B and Cooling Tower Blowdown Radiation Detector Alarm Setpoint Alarm setpoint
< kP E (Ci CFi)+ r,fE (Ci/MPCi)] + Background.
i i
Where:
=
Ci Factor to account sample analysis and detector error.
Concentration of isotope i (yci/ml).
Cpi Detector calibration factor for isotope i
(net cpm/yCi/ml) Listed in Table 2-1.
f
~
Service water A, B or Cooling Tower Blowdown flow rate (gpm).
P Nonradioactive Dilution flow rate (gpm).
Concentration limit for isotope i from 10CFR Part 20'ppendix B, Table II, Column 2 (pCi/ml).
Background
Detector response (cpm) when sample chamber is filled with nonradioactive water.
NOTE:
1.
2.
E(CiCPi) may be evaluated from field measurements and utilized in lieu of specific CPi's of Table 2-1.
MPC for noble gases dissolved or entrained is
- 2. OOE-4yCi/ml. October 1985
0
TABLE 2-1 LIQUID EFFLUENT DETECTORS RESPONSES" NUCLIDE Sr 89 Sr 91 Sr 92 Y 91 Y 92 Zr 95 Nb 95 Mo 99 Tc 99m Te 132 Ba 140 Ce 144 Br 84 I 131 Z,132 I 133 I 134 I 135 Cs 134 Cs 136 Cs 137 Cs 138 Mn 54 Mn 56 Fe 59 Co 58 Co 60 0.78E-04 1.22 0.817 2.47 0.205 0.835 0.85 0.232 0.232 1.12 0.499 0.103 1.12 1.01 2.63 0.967 2.32 1.17 1.97 2.89 0.732 1.45 0.842 1.2 0.863 1.14 1.65 Values from SPEC purchase specification NMP2-P281F. October 1985
I II
2.2 Liquid Effluent Dose Calculat1on Methodology The dose contributions will be calculated for all rad1onuclides identified in liquid-effluents release to unrestricted areas using the following expression:
E [Ai~ E htk Cik Fk]
1 k
Where:
the cumulative dose commitment to the total body or any
- organ,
~,
from. the liquid effluents for the total time period E
htk, in mRem.
k the length of the kth time period over which C ik and Fk are averaged for all liquid
- releases, in hours.
Cik the average concentration of radionuclide, 1,
in undiluted liquid effluent during time period 4tk from any liquid release, in yCi/ml.
the site related ingestion dose commitment factor to the total body or any organ v for each identified principal gamma and beta emitter listed in Table 2-2 in=
mrem-ml per hr-pCi.
Air is calculated using the methodology of NUREG 0133 Section 4.3.l.
(The factor D, used to take into account the dilution of Cik to the point of adult water consumption is 78.6.)
See NMP Un1t 2 EELS, Table 5.4-2.
the'ear field average dilution factor for Cik during any liquid effluent release.
Defined as the ratio of the maximum undiluted liquid waste flow during release to the product of the average flow from the site d1scharge structure to unrestricted receiving
- waters, times 5.9.
(5.9 is the site specific applicable factor for the mixing effect of the discharge structure.)
See NMP Un1t 2
- ERMLS, Table 5.4-2. October 1985
'I I I I
TABLE 2-2 Ai~ VALUES LIQUID*
mrem - ml hr yCi NUCLIDE T BODY GI ZRACT BONE KIDNEY THYROID LUNG H 3 Cr 51 2.938-1 2.938-1 1.28
. 3.2182 2.938-1 2.938-1 2.938-1 2.938-1 2-818-1 7.628-1 1.69 Mn 54 8.3682 1.3484 Pe 59 9.3882 8.1683 Co 58 2.0182 1.8283 Mo 99 I 131 2.0281 2.4682 1.2582 5.7481 I 133 2.7581 8.1181 Cs 134 5;7985 1.2484 Cs 136 8.8684 1.4084 Cs 137 3.4285 1.0184 Ba 140 1.3681 4.2782 Ce 141 2.188-3 7.3481 Nb 95 1.3482 1.51E6 La 140 2.018-2 5.6083 Ce 144 7.958-2 5.01E2 Co 60 5.6882 4.8483 Zn 65 3.3384 4.6484 Sr 89 6.4082 3.5883 Sr 90 1.3585 1.5984 Zr 95 5.648-2 2.6482 4.3883 1.3083 1.0483 2.4583 8.9681 2.5782 2.3284 7.3784 4.9384 2.2384 5.4985 2.608-1 8.338-2 1.318-1 1.0682 2.4082 2.9885 7.0985 2.2985 3.1284 1.2385 6.8584 3.8185 5.2285 1.7785 2.0782 2.618-1 8.868-2 2.848-2 1.928-2 8.928-3 4.4782 2.4882 1.518-1 7.62E-2 2.4682 1.48 6.198-1 3.678-1 1.5282 2.1782 3.7382 7.1384 5.1981 9.0381 1.5782 1.3384 6.8482 7.6184 9.3983 5.8984 1.498-1 Calculated in accordance with NUREG 0133, Section 4.3.1 October 1985
4
,P
[1N
, ~ *
~4
3.0 GASEOUS EFPLUENTS The Main Stack arid the combined Reactor/Radwaste Building Vent comprise the Gaseous Effluent Release Points.
Although the Offgas System is not a Release Point, it is operated in such a way to limit actual or potential offsite doses.
NUREG 0133 and Regulatory Guide 1.109, Kev.
1 were followed, except where noted, in the development of this section.
3.1 3.1.1 Gaseous Effluent Monitor Setpoint Determination Basis To provide a safe margin of assurance that the instantaneous release rate of radionuclides in gaseous effluents from the site to areas at and beyond the site boundry will not exceed 500mRem/yr to the total body.
Methodology for calculating alarm setpoint is described, as these are the setpoints which require action as described in the Technical Specifications.
- However, the monitors also have alert setpoints as
- well, which may require action as described in station procedures.
These are normally set at half of the alarm setpoint, but may vary as described in station procedures.
3.1.2 Setpoint Determination Methodology 3.1.2.1 Stack Noble Gas Detector Alarm Setpoint Alarm Setpoint
<k R E (Ci CFi)
- [F E (Ci Vi)] + Background Where:
k Factor to account for detector and effluent flow measurement errors.
R A value of 500 mRem/yr or less depending upon the release rate from other points within the site such that the total rate corresponds to <500 mRem/yr.
Ci m
Concentration of isotope i, (yCi/cc).
CFi~
Detector response to isotope i, (Net cpm/yCi/cc).
Table 3-1.
F Effluent flow rate.
(cc/sec).
Vi The constant for each identified noble gas radionuclide accounting for total body dose from the elevated finite plume. in mrem/yr per yC1/sec.
Table 3-2.
Background
= Detector response (cpm) when sample chamber is filled with nonradioactive air.
NOTE:
E(CiCFi) may be evaluated from direct field measurements. October 1985
W, 4
Pn, I
I l
3.1.2.2 Vent Noble Gas Detector Setpoint
'I Alarm Setpoint
<k R E (CiCPi)+ [F(X/Q)vE(CiKi)] + Background i
i Where:
k Factor to account for detector and effluent flow measurement errors.
A value of 500 mRem/yr or less depending upon the release rate from other points within the site such that the total rate corresponds to < 500 mRem/yr.
Ci Concentration of isotope i, (yci/cc).
CFi Detector response to isotope i, (net cpm/yCi/cc).
Table 3-1.
Kffluent flow rate, (m3/sec).
(X/Q)v Highest annual average atmospheric dispersion coefficient at the site boundry: 2.08-6 sec/m3.
(FES, NUREG1085, Table D-2)
Ki The total body dose factor due to gamma emissions for each identified noble gas radionucllde, in mRem/yr per yCi/m3.
Table 3-3.
Background
=
Detector response (cpm) when sample chamber is filled with nonradioactive air.
Note:
E(CiCPi) may be evaluated from direct measurements.
3.1.2.3 Offgas Pretreatment Noble Gas Detector Setpoint Alarm setpoint is based on 100yCi/sec/MWt limit rather than methodology of NUREG 0133 Section 5.6.2 to be more conservative.
Alarm Setpoint
< k 332,300 (60)
E (CiCPi)
+ [f E Ci] + Background i
i Where:
k
=
Factor to account for detector, analysis and flow measurement errors.
332,300 3323 MVT x 100 uCi/sec/MVT.
60
=
60 sec/min.
Ci
=
Concentration of nuclide i, (pci/cc).
CFi
=
Detector Response (net cpm/yCi/cc).
f
~
Offgas system flowrate(cc/min).
Background
~
Detector response (cpm) when sample chamber is filled with nonradioactive air. October 1985
3.1.2.4 Offgas Hydrogen Detector Alarm setpoint is less than or equal to 4%, by Hydrogen volume. October 1985
NUCLIDE Kr 85 Kr 85m Kr 87 Kr 88 Xe 133 Xe 133m Xe 135 Xe 135m Xe 138 TABLE 3-1 STACK AND VENT NOBLE GAS*
DETECTOR RESPONSE NET CPM/ Ci/cc 1.00E+5 6.60E+7 3.00E+7 3.70E+6 6.10E+6 9.60E+6 5.30E+7 1.90E+7 5.60E+7 OFFGAS PRETREATMENT**
DETECTOR RESPONSE NUCLIDE NET CPM/ Ci/cc Kr 85 Kr 85m Kr 87 Kr 88 Xe 133 Xe 133m Xe 135 Xe 135m Xe 137 Xe 138 4.30E+3, 4.80E+3 8.00E+3 7.60E+3 1.75E+3 5.10E+3 8.10E+3 7.10E+3
- Values from SWEC purchase specification NMP2-U213A
- "Values from SWEC purchase specification NMP2-P281F October 1985
'v
~ I P'
r 4
i
3.2 Dose Rate Calculation Methodology:
3.2.1
Total body dose rate'due to noble gases:
mrem/yr E fVi Qi
+ Ki ((X/Q) vQiv)]
skin dose rate due to noble gases:
0 mrem/Yr E ((Lj (X/Q)s + 1 1 Bi) Qis +
i 3.2.3 (Li + 1.1 Mi)((X/Q)vQiv)]
Organ dose rates due to iodine-131.
iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days:
3.2.4 mrem/yr ~
E Pi [VsQis + Vv Qiv]
1 NOTE:
See Section 3.3.4 for symbol defination and notes.
3.3 Dose Calculations.Methodology 3.3.1 Gamma air dose due to noble gases:
mrad 3.178-8 E Mi HX/Q)v Qiv
+ Bi Q i
3.3.2 Beta air dose due to noble gases:
mrad 3.178-8 E Ni[(X/Q)vQiv + (X/Q)s Qis]
3.3.3 Organ dose due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days:
E Rj
<Ws Qis + Wv Qiv]
3.3.4 Note:(1)
When a nuclides dose factor for an organ is less than the total body factor, then the total body factor will be used in its place to calculate the organ's dose.
(2)
Organ doses are evaluated assuming the worst case dispersion factor for each respective pathway.
It should be noted that tM.s is conservative.
(3)
In lieu of the use of average annual dispersion
- factors, dispersion factors calculated for real meteorology during the period of release may be used in con)unction with release data in calculating doses. October 1985
t/
%I 4
3.3.4 (Cont'd)
Symbol Defination The inverse of the number of seconds in a year.
The constant for long term releases for each identified noble gas radionucllde account1ng
. for the gamma radiation from the elevated finite
- plume, mrad/yr per yCi/sec.
Table 3-2.
The constant for long-term releases for each identified noble gas rad1onuclide accounting for the gamma radiation from the elevated finite plume, in mrem/yr per yCi/sec.
Table 3-2.
Ki The total body dose factor due to gamma emiss1ons for each identified noble gas radionuclide, in mrem/yr per yC1/m3.
Table 3-3.
The skin dose factor due to beta emissions for each identified-noble gas radionuclide, in mrem/yr per pCi/m3.
Table 3-3.
Mi The air dose factor due to gamma emmissions for each identified noble gas radionuclide, in mrad/yr per yCi/m3 (unit conversion constant of l.1 mrem/mrad converts air dose to skin dose).
Table 3-3.
The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per yCi/m3.
Table 3-3.
Pi The dose parameter for radionuclides other than noble gases for the inhalation
- pathway, in mrem/yr per yCi/m3 and for food and ground plane
- pathways, in m2 (mrem/yr per yC1/sec).
The dose factors are
- based, on the critical individual organ and most restrictive age group (infant).
Table 3-3 thru 3W.
Ri Qis The dose factor for each identified radionuclide, 1,
in m2(mrem/yr) per yci/sec or mrem/yr per pci/m3.
Table 3-7 thru 3-21.
The release rate of radionuclides, 1, in gaseous effluents from the stack, in pCi/sec.
Qiv The release rate of radionuclides, 1,
in gaseous effluent from the vent, in yC1/sec.
The activity of a radionuclide, 1,
for releases from the
- vent, in pCi.
Releases shall be cumulative over the calendar quarter or year as appropriate.
-ll-October 1985
4>
il
,4 4
Pg Ci
Qiv =
(X/Q)
The activity of a radionuclide, i, for releases from the vent.
in pCi.
Releases shall be cumulative over the calendar quarter or year as appropriate.
1.78-6 'ec/m3.
For vent.
releases.
The highest calculated annual average relative concentration at or beyond the unrestricted area boundary.
CT Main study Oct. 85.
(X/Q)'s 2.18-8 sec/m3.
For-. stack releases.
The highest calculated annual average relative concentration at or beyond the unrestricted area boundary.
NMP Unit 2
EELS Table 7B-4.
Vv
=
The highest calculated annual average dispersion parameter for estimating the dose to an individual at 'the controlling location due to vent releases.
Table 3-22.
(X/Q or D/Q)
Vs
=
The highest calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location due to stack releases.
Table 3-22.
(X/Q or D/Q) October 1985
p~
- I
TABLE 3-2 PLUME SHINE PARAMETERS>>
NUCLIDE Kr 83m Bi mrad/ r +
Ci/sec Vi mrem/ r +
Ci/sec)
Kr 85 Kr 85m Kr 87 Kr 88 Kr 89 Kr 90 NOTE:
The valves in this table will be provided at a later time.
Xe 131m Xe 133 Xe 133m Xe.135 Xe 135m Xe 137 Xe 138 Ar 41
- Bi and V
are calculated for critical site boundary location; 1.6km in the easterly direction. October 1985
I
%d
TABLE 3-3 DOSE PROCTORS" Nuclide Ki~Bo~d "*
Lg~B-Skin **
MiQ-hiQr "**
N~~B-Air *~*
Kr 83m Kr 85m Kr 85 Kr 87 Kr 88 Kr 89 Kr 90 Xe 131m Xe 133m Xe 133 Xe 135m Xe 135 Xe 137 Xe 138 Ar 41 7.568-02 1.1783 1.6181 5.92E3 1.4784 1.6684 1.5684 9.1581 2.5182 2.9482 3.1283 1.8183 1.4283 8.8383 8.8483 l.4683 1.3483 9.7383 2.3783 1.0184 7.29E3 4.7682 9.9482 3.0682 7.1182 1.8683 1.2284 4.1383 2.6983 1.9381 1.2383 1.7281 6.1783 1.5284 1.7384 1.6384 1.5682 3.2782 3.5382 3.3683 1.9283 1.5183 9.2183 9.30E3 2.8882 1.9783 1.9583 1.0384 2.9383 1.0684 7.8383 1.1183 1.4883 1.0583 7.3982 2.4683 1.2784 4.7583 3.2883
- Prom, Table B-l.Regulatory Guide 1.109 Rev.
1
"*mrem/yr per yCi/m.
3
- mrad/yr per yCi/m.
3 October 1985
k *,
TABLE 3-4 Pi VALUES GROUND PLANE**
m~~mreml r yci/sec NUCLIDE TOTAL BODY SKIN H 3 C 14 Cr 51 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 6.6486 1.1089 3.8888 5i2788 4.4089 6.8788 3.0684 7.8586 1.2989 4.5688 6.1888 5.1789 7.9088 3.5684 Zr 95
- Nb 95 No 99 I 131 I 133 Cs 134 Cs 137 Ba 140
" La 140 Ce 141 Ce 144 3.4488 3.50ES 5.7186 2.4687 3.5086 2.8189 1.1589 2.9387 2.1088 1.9587 5.8587 3.9988 4 1288 6.6186 2.9887 4.2686 3.2889 1.3489 3.3587 2.3888 2.2087 6.7787
- Daughter Decay product.
Activity level and effective half life assumed to equal parent nuclide.
- Calculated in accordance with NUREG 0133, Section 5.2.1.2. October 1985
~l
/
TABLE 3-5 P
VALUES INHALATION**
i m~rem/
e yci/m 3'UCLIDB BONE T.
BODY THYROID KIDNEY GI-LLI H 3 6.4782, 6.4782 6.4782 6.4782 6.4782 6.4782 C 14 2.6584 5.3183 5 3183 5.3183 5.3183 5.3183 5.3183 Cr 51 Mn 54 2.5384 4.9883 4.9883 1.00E6 7.0683 8.9581 5.7581 1.3281 1.28E4 3.5782 Co 58 Co 60 Zn 65 1.9384 Sr 89 3.9885 Sr 90 4.0987 1.2283 1.8283 8.0283 6.2684 1.1884 3.1184 1.1484 2.5986 Fe 59 1.3684 2.3584 9.4883 1.0286 2.4884 7.7785 1.1184 4.5186 3.1984 3.2584 6.4785 5.14E4 2.0386 6.4084 1.1287 1.3185 Zr 95 1.1585 2.7984 2.0384
- Nb 95 1.5784 6.4383 3.7883 3.1184 1.7586 2.1784 4.7283 4.7985 1.2784 Mo 99 1.6582 3.2381 2.6582 1.3585 I 131 3.7984 4.4484 1.9684 1.4887 5.1884 I 133 1.3284 1.9284 5.6083 3.5686 2.2484
- 4. 8784 1.0683 2.1683 Ce 141 2.7784 1.6784 1.9983 Ce 144 3.1986 1.2186 1.7685 Cs 134 3.96E5 7.0385 7.4584 Cs 137 5.4985 6.1285 4.5584 Ba 140 5.6084 5.6081 2.9083
- La 140 5.0582 2.0082 5.1581 1.9085 7.9784 1.3383 1.7285 7.1384 1.3481 1.6086 1.6885 5.2583 5.1785 1.3383 3.8484 8.4S84 2.1684 5.3885 9.8486 1.4885
- Daughter Decay, Product.
Activity level and effective half life assumed to equal parent nuclide.
- Calculated in accordance with NUREG Ol33, section 5.2.1.1. October 1985
P c'
TABLE 3-6 P
VALUES.FOOD (Cow Milk)*,"*
i 2
m mrem/yr + pCi/sec NUOLZDB BONE
- 'H 3 T.
BODY" TBYBOZD KZDNBY QI-LLI 2.4083 2.4083 2.4083 2.4083'.4083.
2.4083
- C 14 3.2386 6.S985 6.S985
. 6.S985 6.S985 6.S985 6.S9E5 Cr 51 1.6485 1.0785 2.3484 2.0SBS 4.7S86 Mn 54 3.9787 S.9986 S.S086 1.4687 Fe 59 2.2SBS 3.998S 1.578S 1.1SBS 1.91ES Co 5S 2.4787 6.1687 Co 60 S.9SE7 2.128S Zn 65 5.6589 1.94810 Sr S9 1.2S810 S.9489 3.678S 9.4089 Sr 90 1.24811 Zr 95 6.93E3 1.6983*
3.15810 1.2083 1.S283
- Nb 95 7.0785 2.9185 1.6S85 2.0985 Mo 99 2.12ES 4.1387 3.178S I 131, 2.7789,
'3.2689 I 133 3.6987 5.3787 1.4389 1.07812 3.S1E9 1.5787 9.7789 6.31E7 1.7S810 7.3189 Cs 134 3.71810 6.92810 6.9989 6.1587 2.148S 1.64810 2.63ES 1.5589 S.4185 2.468S 6.9S87 1.168S 9.0986 1.SSBS Cs 137 5.24810 6.13810 4.3589 1.65810 6.6789 1.928S Ba 140 2.45ES 2.4585
- La 140 3.7982 1.4982 Ce 141 4.4184 2.6984 3.S481 1.7586 1.3987 1.368S S.3083
- 3. 1783 Ce 144 2.3786 9.6985 1.3385 3.9285 1.2687 5.S384 1.5185 6.0387
- mrem/yr per pCi/m.
- Daughter Decay Product.
equal parent nuclide.
Activity level and effective half life assumed to
- Calculated in accordance with NUREG 0133, Section 5.2.1.3. October 19S5
- k
TABLE 3-7 R
VALUES INHALATION-INFANT**
i m~rmm/ r pcs/m 3 NUCLIDE BONE T.
BODY TNYBOYD KYDNBY GI-LLI H 3 6.4782 6.4782 6.4782 6.4782 6.4782 6.4782 C 14 2-6584 5-3183 5.3183 5.3183 5.31E3 5.3183 5.3183 Cr 51 8.9581 5.7581 1.3281 1.2884 3.5782 2.5384 4.9883 4.9883 1.0086
- 7. 06E3 Co 58 Co 60 1.2283 1.8283 8.0283 1.1884 Fe 59 1.3684 2.3584 9.4883 4.5186 3.1984 1.0286 2.4884 7.7785 1.1184 Zn 65 1.9384 6.26E4 3.1184 3.2584 6.4785 5.1484 Sr 89 3.9885 1.1484 2.0386
- 6. 4084 Sr 90 4.0987 2.5986 1.1287 1.3185
- Nb 95 1.5784
- 6. 4383 3.7883 Zr 95 1.1585 2.7984 2.0384 3.1184 1.7586 2.1784 4.7283 4.7985 1.2784 Mo 99 1.6582 3.2381 I 131 3.7984 4.44E4 1.96F4 I 133 1.32E4 1.9284 5.6083 Cs 134 3.9685 7.0385 7.4584 2.6582 3.5686 2.2484 1.9085 1.4887 5.1884 1.3585 7.97E4 4.8784 1.0683
, 2.1683 1.3383 Cs 137 5.4985
.6.1285 4.5584 Ba 140 5.6084 5.6081 2.9083
- La 140 5.0582 2.0082 5.1581 Ce 141 2.7784 1.6784 1.9983 1.7285-7.1384 1.3383 1.3481 1.6086 3.8484 1.6885 8.4884 5.2583 5.1785 2.16E4 Ce 144 3.1986 1.21E6 1.7685 5.3885 9.8486 1.4885
- Daughter Decay Product.
Activt.ty level and effective half life assumed to
~
~
~
~
equal parent nuclide.
- This and following Ri Tables Calculated in accordance with NUREG
- 0133, section 5.3.1, except.
C 14 values in accordance with Regulatory Guide 1.109, Equation C-8. October 1985
I.
J
TABLE 3 B R
VALUES INHALATION-CHILD m~rem/ r ycl/m3 MDOLZDE BOME T.
BODY TMYMOZD KZDMBY LUNG QZ-LLZ H 3 1.1283 1.1283 1.1283 1.1283 1.1283 1.1283 C 14 3.5984 6.7383 6.7383 6.7383 6.7383 6.7383 6.7383 Cr 51 1.5482 8.5581 2.4381 1.7084 1.0883 4.2983 9.5183 1.0084 1.5886 2.2984 Co 58 Co 60 1.7783 3.1683 1.3184 2.2684 Pe 59 2.0784 3.3484 1.6784 1.2786 7.0784 1.1186 3.4484 7.0786 9.6284 Zn 65 4.2684 1.1385 7.0384 7.1484 9.9585 1.6384 Sr 89 5;9985 Sr 90 1.0188 1.7284 6.4486 2.1686 1.6785 1.4887 3.4385 Zr 95 1.90E5 4.1884 3.7084
- Nb 95 2.3584 9.1883 6.5583 8.6283 6.1485 3.7084 5.9684 2.2386 6.1184 Mo 99 1.7282 4.2681 3.9282 1.3585 1.2785 I 131 4.8184 4.8184 2.7384 1.6287 7.8884 I 133 1.6684 2.0384 7.7083 3.8586 3.3884 2.8483 5.4883 Cs 134 6.5185 1.0186 2.2585 Cs 137 9.0785 8.2585 1.2885 Ba 140 7.4084 6.4881 4.3383
- La 140 6.4482 2.2582 7.5581 1.2185 3.8583 3.3085
- 2. 82E5 1.0485 3.6283 1.0285 1.8385 2.2685 2.1181
, 1.7486 Ce 141 3.9284 1.9584 Ce 144 6.7786 2.1286 2.90E3 3.61E6 8.5583 1.17E6 5.4485 1.2087 5.66E4 3.89E5
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide.
. October 1985
'I I
,h
TABLE 3 9 R
VALUES INHALATIONTEEN i
m~reml r ycl/m3 NUCLIDE BONE'.
BODY THYROID KIDNSY QI-LLI H 3 1 2783 1-2783 1.2783 1.2783 1.2783 1.27E3 C 14 '.6084 4.8783 4.8783, 4.8783 4.87E3 4.8783 4.8783 Cr 51 Mn 54 5-1184 8.4083 1.2784 1.9886 6.6884 1.78E4 Fe 59 1.5984 3.7084 1.4384 1.5386 1-3582 7.5081 3.0781 2.1084 3.0083 Co 58 Co 60 2.0783'.7883'.5184 1.9884 1.3486 9.5284 8.7286 2.5985 Zn 65 3.8684 1.3485 6.2484 8.6484 1.2486 4.6684 Sr 89 4.3485 1.2584 6.6886 3.1584 2.4286 3.7185 1.6587 7.6585 Sr 90 1.0888 Er 95 1.46E5 4.5884 6.7484 2.6986 1.4985 9.6884 2.69E5 6.4983 1.0384
- Nb 95 1.8684 1.0384 5.66E3 1.0084 7.51E5 4.1182 1.5485 1.6982 3.2281 Mo 99 2.0584 I 133 1.2284 6.2283 2.9286 3.5984 I 131 3.5484 4.9184 2.6484 1.4687 8.4084 Ba 140 5.47E4 "La 140 4.7982 Ce 141 2.8484 Ce, 144 4.8986 6.7081 3.5283 2.3682 6.2681 1.9084 2.1783 2.0286 2.6285 Cs 134 5.0285 1.1386 5.49E5 Cs 137 6.7085 8.4885 3.1185 3.0485 2.2881 8.8883 1.21E6 1.2185 2.0386 2.1485 6.1485 1.3487 8.4883 2.2985 4.8785 1.2685 8.6485 3.7585 1.4685 9.7683
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
1P 1
lf CC
TABLB 3 10 R
VALUES INHALATION-ADULT i
m~reml r yci/m3 NUCLIDE BONE T.
BODY THYROID KIDNEY LUNG GI-LLZ H 3 1 26E3 1.2683 1.2683 1.2683 1.2683 1.2683 C 14 1.8284 3.4183 3.4183 3.4183 3.41E3 3.4183 3.4183 Cr 51 Mn 54 3.9684 6.3083 9.84E3 1.4086 7.7484 1.0082 5.9581 2.2881 1.4484 3.3283 Co 58 Co 60
- 1. 5883
- 2. 0783 1.1584 1.4884 Zn 65 3.2484 1.0385 4.6684 Fe 59 1.1884 2.7884 1.0684 1.0286 1.8885 9 2885 1.0685 5.9786 2.8585 6.9084 8.6485 5-3484 Sr 89 3.0485 Sr 90 9.9287 8.7283 6.1086 1.4086 3.5085 9.6086 7.2285 Zr 95 1.0785 3.4484 2.3384
- Nb 95 1.4184 7.8283 4.21E3 7.7483 5.0585 1.0485 5.4284 1.7786 1.5085 2.4885 6.2883 8.88E3 Mo 99 2.9182 9.1284 1.2182 2.3081 6.1384 1.4884 4 5283 2.1586 2.5884 I 133 8.6483 Cs 134 3.7385
- 8. 48E5
- 7. 28E5 2.8785 9.7684 1.0484 2.2285 7.5284 8.4083 1.6781 1.2786 2.1885 Cs 137 4.7885 6.2185 4.2885 2.5783 Ba 140 3.9084 4.9081 I 131 2.5284 3.5884 2.0584 1.1987
- La 140 3.4482 1.7482 4.5881 1.3685 4.5885 Ce 141 '.9984 Ce 144 3.4386 1.4386 1.8485 1.3584 1.5383 6.2683 8.4885 3.6285 7.78E6 1.2085 8.1685
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
W
TMLB 3-11 R
VALUES GROUND PLANE i
ALL AGB GROUPS m
mrem/yr + yCi/sec 2
TOTAL BODY SKIN H 3 C 14 Cr 51 Mn 54 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95
- Nb 95 Mo 99 I 131 I 133 Cs 134 Cs 137 Ba 140
- La 140 Ce 141 Ce 144 4.6586 1.4089 2.7388 3 8088 2.15810 7.4688 2.1684 2.4588 2.5088 3.9986 1.7287 2.4586 6.8389 1.03810 2.0587 1.4788 1.3787 6.9687 5.5086 1.6489 3.2088 4.4588 2.53810 8.5788 2.51E4 2.8588 2.9488 4.6386 2.0987 2.9886 7.97E9 1.20810 2.3587 1.6688 1.5487 8.07E7
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
U4q'F 4
~
TABLB 3 - 12 NUCLIDE BONE
- H 3 R
VALUBSMOWMILK-INFANT i
2 m -mrem/yr + ycl/sec T.
BODY TBYBOZD KZDNBY LUNG 2-3883 2-38g3 2-3883 2.3883 2.3883 QZ-LLI 2.3883
- C 14 3.2386 6.8985 6.8985 6.8985 6.8985 6.8985 6.B985 Cr 51 Mn 54 2.5187 5.6886 5.5686 9.2186 8.3584 5.4584 1.1984 1.0685 2.4386 Fe 59 1.2288 2.1388 8.3887 6.2987 1.0288 Co-58 Co 60 1.3987 3.4687 5.9087 1.3988 Zn 65 3.5389 1.21810 5.5889 5.8789 Sr 89 6.9389 Sr 90 8.19810 1.9988
'.09810 Zr 95.
- Nb 95 3.8583 9.3982 6.6682 3.9385 1.6285 9.3584 1.0183 1.1685 Mo 99 1.0488 2.0387 1.5588 I 131 1.3689 1.6089.
k 7.0488 5.26811 1.8789 I 133 1.8187 2.6487 7-7286 4;7989 3.1087
- 3. 4687 1.4088 1.02810 1.4288 1.0289 4.6885 1.3788 3.43E7 5.7287 4.4686 Cs 134 2.41810 4.49810 4.5489 Cs 137 3.47810 4.06810 2.8889 1.16810 4.7489 1..09810 4.4189
~ 1.2288 1.2788 Ba 140 1.2188 1.2185 6.2286 2.8784 7.4284 2.9787 Ce 141 2.2884 1.3984.
Ce 144 1.4986 6.1085
- La 140 1.8682 7.3581 1.8981 1.6483 8.3484 4.2883 2.4685 8.6385 7.1886 8.5487
- mrem/yr per yci/m3.
- Daughter Decay Product.
equal parent nuclide.
Activity level and effective half life assumed to October 1985
~ 4W
- I
TABLE 3 13 NUCLIDE BONE R
VALUES~WMILK~ILD 2
m -mrem/yr
+ ycl/sec T.
BODY THYROID KIDNBY GI-LLI "H 3 1.5783 1.57E3 1.57H3 1.5783 1.5783 1.57E3
- C 14 1.6586 3 2985 3.2985 3.29E5 3.2985 3'.2985 3.29ES Cr 51 5.2784 2.9384 7.99H3 5.3484 2.SOH6 1.3587 3.5986 3.7S86 1.1387 Fe 59 6.5287 1.068S 5.2687 3.0687 1.10ES 2.1387 6.94H6 Co 5S Co 60 4.0587 1.608S 1.2389 1.418S 1.0189 4.9S85 1.528S'.3787 5.S387 4.2786 1.328S 2.S987 S.5287 Zn 65 2.6389 7.0089 4.3589 4.4189 Sr S9 3.6489 Sr 90 7.53810 1.048S 1.91810 Zr 95 2.1783 4.7782 4.2582 6.S382 S.1984 5.S584
- Nb 95 2.1085 7.7084 Mo 99 S.6987 4.0787 1.0187 I 131 6.518S '.55HS 3.728S 2.17811 1.0S89 Cs 134 1.50810 2.45810 5.1S89 Cs 137 2.17810 2.0S810 3.0789 Ba 140 5.S787 5.1484 3.4386 2.7389 7.6189 6.7S89 2.4489 1.308S 3.0784 1.67E4 2.9787 S.6985 7.1586 S.4987
- La 140 S.9281 Ce 141 1.1584
- 3. 1281 5.7383 1.0581 S.5182 2.5183 Ce 144 1.0486 3.2685 5.5584 1.SOE5 I 133 S.SSB6 1.0687 4.0186 1.97H9 1.77E7
- mrem/yr per ycl/m3.
"*Daughter Decay Product.
equal parent nuclide.
Activity level and effective'alf life assumed to October 19S5
TABLE 3 14 NUCLIDE BONK
- H 3 LZVRR 9.9482 R
VALUBS~WMILK-THEM i
2 m ~em/yr
+ yci/sec T.
BODY THYROID KZDNBY LONG GZ-LLZ 9.9482 9.9482 9.9482 9.9482 9.9482
.*C 14 6.7085, 1.3485 Cr 51 1.3485 1.34H5 1.3485 1.3585 1.34E5 2.5884 1.4484 5.6683 3.6984 4.34H6 Mn 54 9.01E6 1.7986 2.6986 1.8587 Fe 59 2.8187 6.5787 2.5487 2.0787 1.5588 Co 58 4.5586 l.0587 Co 60 1.8687 4.1987 Zn 65 1.3489 4.6589 Sr 89 1.4789 Sr 90 4.45810 2.1789 4.2187 1.10810.
2.9789 Zr 95 9.3482 2.9582 2.0382
- Nb 95.
9.3284 Mo 99 5.1784 2.8584 2.2487 4.2786 4.3382 5.0184 5.1287 I 133 3.5386 5.9986 1.83E6 8.3688 1.0587 I 131
- 2. 6888 3.7688
- 2. 0288
- 1. 10811
- 6. 4788 6.2787 2.4288 1.9789 1.7588 1.2589 6.8085 2.2188 4;0187 7.4487 4.5386
- La 140 3.7381 1.8381 Ce 141 4.6783 3.1283 Ce 144 4.2285 1.7485 4.8780 3.5882 2.2784 Cs 134 6.4989 1.53810 7.0889 Cs 137 9.0289 1.20810 4.1889 Ba 140 2.4387 2.9884 1.5786 1.01H4 l
1 4783 1.0485 2.0084 3.75E7 1.0586 8.9186 1.0688 4.8589 1.8589 1.9088 4.0889 1.5989 1.71BS
- mrem/yr per yci/m3.
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide.. October 1985
~ y.
z Ci
TABLE 3 15 NUCLIDE BONE R
VALUES~WMILK-ADULT i
2 m -mrem/yr + yci/sec T-BODY TBYBOZD KXDNKY LDNO GI-LLI
- H 3 7.6382 7.6382'.6382 7.6382 7.6382 7.6382
- C 14 3.6385 7.2684 7.26E4 7.2684 7.2684 7.2684 7.2684 Cr 51 Mn 54 5.4186 1.0386 1.6186 1.4884 8.8583 3.2683 1.9684'.7286 1.6687 Pe 59 1.6187 3.7987 1.4587 1.0687 1.26ES 5.4787 2.0688 1.7589 1.2888 9.1188
~
5.4385 1.8488 2.8787 5.5887 3.0286 1'.5688 Co 58 Co 60 2.7086 6.0586 1.1087 2.4287 1.8589 Zn 65 8.7188 2.7789 1.2589 2.2987 Sr 89 7.9988 Sr 90 3.15810 7.7489 2.6982 1.1682 Zr 95 5.34E2 1.7182 3.04E4 1.6384 1.2487 2.3686
- Nb 95 5.4684 3.0084 2.8187 Mo 99 Cs 134 3.7489 8.8989 7.27E9 Cs 137 4.9789 6.8089 4.4689 2.8889 9.5588 2.3189 7.6888 1.3288 I 131 1.4888 2.1288 1.2188 6.94810 3.6388 I 133 1.9386 3.3686 1.0286 4.9488 5.8686 8.8385
- La 140 2.0781 Ce 141 2.54E3 1.05E1 2.7680 1.7283 1.9582 Ce 144 2.2985 9.5884 1.2384 Ba 140 1.3587 1.6984 5.7583 7.9982 5.6884
- 9. 6983 2 7787 7.6785 6 5886 7.7487
- mrem/yr per pC1/m3.
"*Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
~
1 t~'I
'k
TABLE 3 16 NUCLIDE BONE R
VALUBS~WMEA~ILD 2
m -mrem/yr + ycl/sec T.
BODY TBYBOZD KXDNBY GZ-LLI
- H 3 2.3482 2.3482 '.3482 2.3482 2.3482 2.3482 Cr 51 Mn 54 4.5583 2 5283 5.1586 1.3786 6-9082 1.4486 4.6183
- C 14 5.2985 1.0685 1.0685 1.0685 1.0685 1.0685 1.0685 2.41E5 4.3286 Fe 59 2.048S 3.308S 1.658S 9.5S87 3.448S Co 5S Co 60 9.4186 2.SS87 4.6487 1.378S Zn 65 2.3SES 6.358S 3.95ES 4.00BS Sr S9 2.658S Sr 90 7.0189 7.5786 1.7S89 Zr 95
- Nb 95 Mo 99 1.5186 3.3285 2.9585 2.4186 9.3S85 6.7185 5.4284 1.3484 4.7585 S.S285 1.1685 I 131 S.2786 S.3286 4.7387 2.7589 1.3787 I 133 2.S78-1 3.558-1 1.34E-l 6.608-1 5.928-1
- 5. 4987 2.578S 1.128S 1'. 0387 9.4487 3.468S 1.7489 4.4S84 7.4085 1.43E-l Cs 134 6.098S 1.0089 2.118S Cs 137 S.9988 S.608S 1.278S Ba 140 2.2087 1.9384 1.2S86 3.108S 1.118S 5.3986 2.SOBS 1.018S 5.39E6 6.2783 1.1584 1.1187
- La 140 1.6782 5.S481 1.9781 Ce 141 1.1784
. 5.S283 S.6482 Ce 144 1.4S86 4.65E5 7.9184 2.5583 2.5785 1.6386 7.26E6 1.21ES
- mrem/yr per pci/m.
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 19S5
TABLE 3 17 NUCLIDB HONE
<<H 3 LZVBR 1.9482 R
VALUES~WMBAT ZEEN 2
m -mrem/y + yCi/sec T
BODY TBYROZD KZDBBY LUNG GI-LLI 1".9482 1.9482 1.9482 1.9482 1.9482
- C 14 2.8185 5.6284 5.6284 5.6284 5.6284 5.6284 5.6284 Cr 51 Mn 54 4.5086 8.9385 1.3486 2.9383 1.6283 6.3982 4.1683 4.9085 9.2486 Pe 59 1.1588 2.6988 1.0488 8.4787 6.3688 Co 5B Co 60 Zn 65 1.5988 Sr 89 1.4088 Sr 90 5.4289 8.0586 1.8687 3.9087 8.8087 5 5288 2.5788 4.0186 1.3489 3.5388 Zr 95
- Nb 95 Mo 99
'8.5085 1.4086 2.6885 1.8485 7;7485 4.2685 3.9084 7.4383 3.9485 7.5185 8.9284 I'31 4.4686 6.2486 3.35H6 1.82H9 1.0787 4.608-1 I 133 1.558-1 2.628-1 8.008-2 3.6681 1.1188 5.09E8 2.3488 1.6787 1.5288
- 6. 1988 3.3189 6.9884 1.2386 1.998-1
- La 140 9.1281 Ce 141 6.1983 Ce 144 7.8785 4.4881 4.1483 3.2685 1.1981 4.7582 4-2384 Cs 134 3.4688 8.1388 3 7788 Cs 137 4.8888 6.4988'.2688 Ba 140 1.1987 1.4684 7.6885 2.2188 8.5887 4.9583 9.8183
- 1. 9583 1.9485 9.2486 1.8487 2.5786 1.1887 1.98ES 2.5888 9.8787 1.0187
- mrem/yr per yci/m3.
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
TABLE 3 18 NUCLIDE BONE R
VALUES~WMBAT-ADULT i
2 m -mrem/yr + pci/sec T.
BODY THYROZD KZDRRY LUNG GZ-LLZ
- H 3 3.2582 3.2582 3.2582 3.25S2 3.2582 3.2582
- C 14 3.3385 6.6684 6.6684 6.6684 6.6684 6.6684 6.6684 Cr 51 Mn 54 3.6583 5.9086 1.1386 1.7686 1.8187 2.1883 8.0382 4.8483 9.1785 Pe 59 1.44E8 3.3988 1.3088 Co 58 Co 60 1.0487 2.3487 5.0387 1.1188 Zn 65 2.2688 7.1988 3.2588 4.7686 2.0689 Sr 89 1.6688 8.3889 Sr 90 Zr 95 1.0686 3.4085 2.3085
- Nb 95 1.7986 9.9485 5.3585 Mo 99 4.7184 8.97E3 I 131 5.3786 7.6786 4.4086 2.5289 I 133 1.858-1 3.228-1 9.818-2 4.73Sl 4.8188 5.3485 9.83E5 1.0785 1.3287 5.618-1 9.46S7 1.1389 2.1288 9.4588 4.53E8 2.6687 2.4288 1.0889 6.0489 1.0985 2.0286 2.898-1 Ba 140 1.4487 1.8184 9.4485 Cs 134 4.3588 1.03S9 8.4588 Cs 137 5.8888 8.0488 5.2688 3.3588 1.1188 1.8187 2.7388 9.0787 1.5687 6.1583 1.0484 2.9787
- La 140 1.1182 5.5981 1.4881 Ce 141 7.3883 4.9983 5.6682 Ce 144 9.3385 3.9085 5.0184 2.3283 2.3185 4.10E6 1.9187 3.1688
- mrem/yr per yci/m.
- Daughter Decay'roduct.
Activity level and.effective half life assumed to equal parent nuclide. October 1985
TABLE 3 - 19 R
VALUES-VBGETATION~ILD i
2 m -mrem/yr + yci/sec T.
BODY THYROID KIDNEY LUNG GI-LLI 4.0183 4.0183 4.0183'.0183 4.0183 4.0183
- C 14 3.5086 7.0185 7.0185 7.0185 7.0185 7.0185 7.0185 Cr 51 1.1785 6.4984 1.7784 1.1885 6.2086 6.6588 1.7788 1.8688 Mn 54 5.5888 6.6988 3.7688 2.1089 3.8088 1.3989 1.67810 8.8688 5.4088 6.37E6 1.2887 1.7586 Pe 59 3.9788 6.4288 3.2088 1.86E8 6.45E7 1.9788 Co 58 3.7888 1.1289 Co 60 Zn 65 8.1288 2.1689 1.3589 1.3689 1.0389 3.15811 Sr 89 3.59810 Sr 90 1.24812 Zr 95 3.8686 8.5085 7.5685 1.2286 2.7485 1.6587
+*Nb 95 7.5085 2.. 92E5 7.7086 2.0985.
1.9186 Mo 99 I 133 3 5286 4.3586 1.6586 Cs 134 1.60810 2.63810 5.5589 Cs 137 2;39810 2.29810 3.3889 Ba 140 2.7788 2.4385 1.6287 8;0888 7.2586 8.1589 2.9389 1.4288 7.4689 2.6889 1.4388 7.9084 1.4585 1.4088 I 131 1.4388 1.4488 8.1687 4.75810 2.3688
"*La 140 3.3784 1.1884 3.9783 3.2888 Ce 144 1.2788.
3.9887 6.7886 Ce 141 6.5685 3.2785 4.8584 1.4385 2.2187 4.0888 1.04810
- mrem/yr per pci/m3.
<<*Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
TABLE 3 20 NUCLIDE BONE R
VALUES-VEGETATXON ZEEN i
2 m -mrem/yr + yc1/sec T.
BODY TNYBOZD KZDNBY LUNG DZ-ZLZ
<<H 3.
2.5983 2.5983 2.5983 2.5983 2.5983 2.5983 2.9185 Cr 51 Mn 54 6.1684
-3.4284 4.5488 9.0187
- C 14 1.4586 2.9185 2.9185
- 2. 9185 1.3584 1.3688 2.9185 2 91ES 8.7984 1.0387 9.3288 Pe 59 1.7988 4.1888 1.6188 1.3288 9.8988 6.0288 3.2489 6.2388 1.8089 2.11810 1.2689 8.1688 1.0187 2.1387 2.4886 4.3787 1.0188 Co 58 Co 60 2.4988 5.6088 6.86E8 4.3388 1.85811 3.7485 9.4188 Zn 65 4.2488 1.4789 Sr 89 1.51810 Sr 90 7.51811 Zr 95 1.7286 5.4485 7.9985 1.8585 1.2987
- Nb 95 3.4485 1.91E5 1.0585 5.6486 1.0886 Mo 99 4.5788 5.7486 I 133 1.9386 3.2786 9.9885 Cs 134
'7.1089 1.67810 7.7589 Cs 137 1.01810 1.35810 4-6989 Ba 140 1.3888
'1.6985 8.91E6 5.3189 2.0389 2.0888 1.7889 4.5989 1.9288 5.7484 1.1485 2.1388 I 131 7.6887 1.0788 5.78E7 3.14810 1.8588
- La 140 1.6984 8.3283
- 2. 21E3 Ce 144 5.2787 2.1887 2 8386 Ce 141 2.8385 1.8985 2.1784 8.8984 1.3087 4.7888 5.4088 1.33810
- mrem/yr per pci/m3
- Daughter Decay Product.
Activity level and effective half life assumed to equal parent nuclide. October 1985
<< l h
r-
TABLE 3 21 R
VALUES-VEGETATION-ADULT i
2 m -mrem/yr + yci/sec T.
BODY TNYBOID KIDNBY LUNG GI-LLI
- H 3
- C 14 8;97H5 2.2683 2.2683 2.2683-2.2683 1.7985 1.7985 1.7985 1.79H5 2.2683 2.2683 1.7985 1.7985 Cr. 51 Mn 54 4.6484 2.7784 3.1387 5.9787 1.0284 9.3187 6.1584 1.1787 9.5888 Pe. 59 1.2688
.Co 58 2.9688 3.0887 1 1388 6.90H7 Co 60 1.6788 Zn 65'.1788 1.0189 Sr 89 9.9586 Sr 90 6.05811 Zr 95 1.1886 3.7785 3 6988 4.568S 2.8688 1.48811 2.5585 6.7588 5.9285
- Nb 95 2.4185 Mo 99 1.34E5 7.2084 6.14E6 1.1786 1.3285 1.3987 I 133 2.0886 3.6186 1.1086 5.3188 6.3086
Cs 134 4.6789 1.11810 9.0889 Cs 137 6.3689'.7089 5.70H9 Ba 140 1.2988 1.6185 8.4286 3.5989 2.9589 5.4984 I 131'.0787 1.1588 6.6187 3.78810 1.9888 1.1989 6.2488 3.1489 6.3688 1.6089 1.75810 1.2089 8.1388 1.4287 3.0587 3.2586 1.9488 9.8188 1.6888 9.2584 2.65ES 8.2787 1.0289
- La 140 1.5884 7.93E3 2.1183 Ce 141 1.9785 1.3385 1.5184 Ce 144 '.2987 1.3887 1.7786 6.1984 8.1686 5.8688 5.0988 1.11810
- mrem/yr'er pci/m3
- Daughter Decay Product.
equal parent nuclide.
Activity level and effective half life assumed to October 1985
TMLE 3-22 DISPERSION PMl&ETERS AT CONTROLLING LOCATIONS>>
Wv and W
VALUES Inhalation and Ground Plane DIRECTION li842 1.42E-7
>~/m-2g 2.90E-9 Cow Milk Meat Animal Vegetation 2, 417 1,842
'2,072 5.44E-S 1.42E-7 1.29E-7 9.52E-10 2.58E-9 2.21E-9 STACK Inhalation and Ground Plane 1,711 8.50$ -9 1.33E-9 Cow Milk Meat Animal Vegetation NOTE:
ESE 2,366 8.84E-9 5.888-10 E
',711 1.36E-9 E
1.940 1.24B-9 1.07E-8 Inhalation and Ground Plane are annual average values.
Others are grazing season only.
- NMP-Unit-2 EELS, Appendix 7B October 1985
tp
4.0 URANIUM FUEL CYCLE The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) as follows:
"Uranium fuel cycle means the operations of milling of uranium
- ore, chemical conversion of
- uranium, isotopic enrichment of
- uranium, fabrication of uranium fuel, generation of electricity by a light~atermooled nuclear power plant using uranium fuel, and reprocessing of spent uranium. fuel, to the extent that these directly support the production of electr1cal power for public use utilizing nuclear energy.
but excludes mining operations, operations at waste disposal
- sites, transportation of any radioactive material. in support of these operations, and the reuse of recovered non-uran1um special nuclear and by-product materials from the cycle."
Section 3/4.11.4 of the Technical Specifications requires that when the calculated doses associated with the effluent releases exceed twice the applicable quarter or annual limits, Niagara Mohawk shall evaluate the calendar year doses and, if required, submit a Special Report to the NRC and limit subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem).
This report is to demonstrate
'hat radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190.
If releases that result in doses exceeding the 40 CFR 190 limits have occurred.
then a variance from the NRC to permit such releases will" be requested and if possible, action will be taken to reduce subsequent releases.
The report to the NRC shall contain:
2)
Identification of all uranium fuel cycle facilities or operat1ons within 5 miles of the nuclear power reactor units at the site, that contribute to the annual dose of the maximum exposed member of the public.
Identificat1on of the maximum exposed member of the public and a
determinat1on of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation.
The total body and organ doses resulting from radioactive material in liquid effluents from Nine Mile Point Unit 2 will be summed with the doses result1ng from the releases of noble 'gases, radioiodines, and particulates.
The direct dose components will also be determined by either calculation or actual measurement.
The doses from Nine Mile Point Unit 2 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site. October 1985
l~
t f
4.0 (Cont'd)
Por the purpose of calculating
- doses, the results of the Environmental Monitoring program may be included to provide more refined estimates of doses to a
real maximum exposed individual.
Estimated
- doses, as calculated from station effluents, may be replaced by doses calculated from actual environmental sample results.
4.1 Evaluation of Doses Prom Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered.
The dose associated with fish consumption may be calculated using the ODCM methodology or by calculating a dose to man based on actual fish sample analysis data.
The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area.
This dose may be derived from liquid effluent data or from actual shoreline sediment sample analysis data.
Doses to members of the public from the fish consumption and shoreline sediment pathways will be calculated using Regulatory Guide 1.109 or ODCM methodology.
4.2 Evaluation of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.0 of the ODCM will be considered.
- However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological
- data, location of critical receptors, etc.
Data from the most recent census and sample location surveys.
should be utilized.
Doses may also be calculated from actual environmental sample
- media, as available.
Environmental sample media data such as TLD, air sample.
milk sample and vegetable (food crop) sample data may be utilized in lieu of effluent calculational data.
Doses to members of the public from the pathways contained in ODCM section 3.0 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable.
4.3'valuation of Doses From Direct Radiation Section 3.11.4.a of the Technical Specifications qequires that the dose contribution as a result of direct radiation be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded.
Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating environmental TLD results at critical receptor locations, site boundary or other special interest locations. October 1985
Doses'o Members of the public Within the site Boundary.
Section 6.9.1.8 of the Nine Mile Point Unit 2
Technical Specifications requires that the Semiannual Effluent Release Report include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary as defined by Pigure 5.1.3 of the specifications.
A member of the public.
as defined by the Technical Specifications, would, be represented by an individual who visits the sites'nergy Information Center for the purpose of observing the educational displays or fax picnicing and associated activities.
It ls assumed that an individual would spend four, hours per week for twelve weeks at the Energy Information Center.
The time spent at the facility is assumed to occur from approximately July 1 to September 30 of each year.
- Thus, the first Semiannual Effluent Release Report will not address this particular dose because the summer season is the period of concern.
The second report will address this dose based on forty eight hours occupancy.
The pathways considered for the evaluation include the inhalation pathway with the resultant lung dose and the direct radiation dose pathway with the associated total body dose.
The direct radiation dose
- pathway, in actuality, include several pathways.
These include:
the direct radiation gamma dose to an individual from on overhead
- plume, a
submersion.
gamma plume
- dose, and a
ground plane dose (deposition).
Other
- pathways, such as the ingestion
- pathway, are not applicable.
In addition, pathways associated with water related recreational activities are not applicable here.
These inlcude swimming and wading-'which are prohibited at the facility.
The inhalation pathway ls evaluated by identifying the applicable radionuclldes. (radioiodine, tritium and particulates) in the effluent for the appropriate time period.
The radlonuclide concentrations are then. multiplied by the appropriate X/Q value, inhalation dose factor, air intake rate, and the fractional portion of the year in question.
- Thus, the inhalation pathway's evaluated using the following equation adapted from Regulatory Guide 1.109.
R
~
I 1[C1 P X/Q DPA 1)a Ra t]
where :'he dose for the period in question to the lung (j) for all radionuclldes (1) for the adult age group (a) in mrem per time period.
Clm The average concentration in the stack release of radionuclide 1 in pCi/m3 for the period in question Average effluent flowrate in m /sec. October 1985
J V
(Cont'd)
X/Q The plume dispersion parameter for a
location 0.50 miles west of NMP-1 (The plume dispersion parameter is 8.09E-9 (stack) and, 2.87E-7 (vent) and was obtained from the NMP-Unit 2 FSAR, Table 2G-2 and 2G-3.
A X/Q value based on real time meteorology may also be utilized for the period in question).
DFAiga Ra, the inhalation dose factor for radionuclide i, the lung ], and adult, age group a in mrem per pCi found on Table E-10 of Regulatory Guide 1.109.
annual air intake for individuals in age group a in M3 per year (this value is 8,000 m3 per year and was obtained from Table E-5 of Regulatory Guide 1.109).
fractional portion of the year for which radionuclide i
was detected and for which a
dose is to be calculated (equals 0.23 years).
The direct radiation gamma dose pathway includes any gamma doses from an overhead
- plume, submersion M the plume and ground plane dose (deposition).
This general pathway will be evaiuated by average environmental TLD readings.
At least two environmental TLD locations wil'1 be utilized and located in the approximate area of the Energy Information Center (EIC) and the facility picnic area.
These TLDs will be placed in the field on approximately July 1
and removed on approximately September 30 of each year (this time interval is composed of one quarterly TLD collection period).
The average TLD readings will be ad)usted by the average control TLD readings.
This is accomplished by subtracting the average quarterly control TLD value from the average EIC TLD value.
The applicable quarterly control TLD values will be utilized after ad)usting for the
.appropriate time period (as applicable).
5.0 ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2.
The Environmental Monitoring Program is a )oint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Units 1
and 2
and the James A.
FitzPatrick Nuclear Power
- Plants, respectively.
Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units. October 1985
h l g
5.1 (Cont'd)
The average dispersion and deposit1on parameters for the two units have been calculated for a 5 year period, 1978 through 1982.
These dispersian calculatians are attached.
The calculated dispersion or deposition parameters will be compared to the results of the annual land use census.
If it is determined that a milk sampling location exists at a locatian that yields a significantly higher (e.g.
50%)
calculated D/Q rate, the new milk sampling location-will be added to the monitaring program within 30. days.
If a new location is added.
the old location that yields the lowest calculated D/Q may be dropped from the program after October 31 of that year.
5.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a
Commission approved or sponsored'nterlaboratory Comparison
- Program, such as the EPA Crosscheck Program.
Participatian shall be only for those
- media, e.g.,
- air, milk, water, etc.,
that are included in the Nine Mile Point Environmental Monitoring Program and for which cross check samples are available.
.The site identification symbol or the actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.
Specific sample media for which EPA'ross Check Program samples are available include the following:
~
gross beta in air particulate filters
~
gamma emitters in air particulate filters
~
I-131. in milk
~
gamma emitters in milk
~
gamma emitters in food product
~
gamma emitters in water
~
tritium in water
~
I-131 in water 5.3 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements Required detectian capabilities for thermoluminescent dosimeters used for environmental measurements required by the Technical Spec1flcations are based on ANSI Standard
- N545, section 4.3.
Required detection capabilit1es are as follows.
TLDs are defined as phosphors packaged for field use.
In regard 'o the detection capabil1ties for thermoluminescent dosirneters, only one determination is required to evaluate the above capabilities per type of TLD.
Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs. October 1985
Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field Cycle.
The responses obtained shall have a relative standard deviation of less than 7.5%.
A total of at least 5
TLDs shall be evaluated.
Reproducibility shall be determined by giving TLDs repeated exposures equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.
The average of the relative standard deviations of the responses shall be less than 3.0%.
A total of. at least 4 TLDs shall be evaluated.
Dependence of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a
field cycle and a period equal to half the same field cycle in an area where the exposure rate is known to be constant.
This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures.
For these
- tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85.
At least 6
TLDs shall be evaluated.
Energy dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 MeV.
The response shall not differ from that obtained with the calibration source by more than 25% for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV.
A total of at least 8 TLDs shall be evaluated.
The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations.
To accomplish this, the TLD shall be rotated through at least two perpendicular planes.
The response averaged over all directions shall not differ from the response obtained in the standard calibration position by more than 10%.
A total of at least 4 TLDs shall be evaluated.
Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6.
The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10%.
A total of at least 4 TLDs shall be evaluated for each of the four conditions. October 1985
,yr.
11 A1 4'
Moisture dependence shall be determined by placing TLDs (that is, the phosphors packaged f'r field use) for a period equal to the field cycle in an area where the, exposure rate is known to be constant.
The TLDs shall be exposed under two conditions:
(1) packaged in a thin, sealed plastic
- bag, and (2) packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle.
The TLD or phosphor.
as appropriate, shall be dried before readout.
The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by-more than 10%.
A total of at least 4 TLDs shall be evaluated for each. condition.
Self irradiation shall be determined'y placing TLDs for a period equal to the field cycle in an area=- where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known. If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545, section 4.3.3).
The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.
A total of at least 3
TLDs shall be evaluated. October 1985
gA
"~
ll
'I ~
Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1,.
Type of Sam le
- Map Location Collection Site Location Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Nine-Mile Point Road north Co. Rt.
29
& Lake Road 1.8 mi 6 88 E
1.1 mi 6 104'SE Radioiodine and Particulates (air)
Co. Rt. 29 1.5 mi 6 132 SE
.Radioiodine and Particulates (air)
Village of Lycoming, NY 1.8 mi 6 143 SE Radioiodine and Particulates (air)
Montario Point Road 16.4 mi 6 42'E Direct Radiation (TLD)
Direct Direct Radiation (TLD) 7 Radiation (TLD) 8 Direct Radiation (TLD) 9 Direct Radiation (TLD) 10 Direct Radiation (TLD) 15 Direct Radiation (TLD) 16 Direct Radiation (TLD) 17 Direct Radiation (TLD) 18 Direct Radiation (TLD) ll Direct Radiation (TLD) 12 Direct Radiation (TLD) 13 Direct Radiation (TLD)
L North Shoreline Area North Shoreline Area North Shoreline Area North Shoreline Area JAF east boundary Rt. 29 Rt.
29 Miner Road Miner Road Lakeview Road Lakeview Road 0.1 mi 6 5' O.l mi 6 25 NNE 0.2 mi 6-45'E 0.8 mi 6 70'NE 1.0 mi 6 90 E
1.1 mi 9 115'SE 1.4 mi 9 1334 SE 1.6 mi 6 159 SSE 1.6 mi 6 181 S
1.2 mi 9 200 SSW 1.1 mi 6 225'W Site Meteorological Tower 0.7 mi 9 250'SW Energy Information Center 0.4 mi 6 265'
- Map - See Figures 5.1-1 and 5.1-2 October 1985
1
'W,t
Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)
Type of Sam le Map Location Collection Site Location Direct Radiation (TLD) 19 Direct Radiation (TLD) 20 Direct Radiation (TLD) 21 Direct Radiation (TLD) 22 Direct Radiation (TLD) 23 Direct Radiation (TLD) 24 Direct Radiation (TLD) 25 Direct Radiation (TLD) 26 Direct Radiation (TLD)
Direct Radiation (TLD) 27 28 Surface Water Surface. Water 38 39 Direct Radiation (TLD) 29 Direct Radiation (TLD) 30 Direct Radiation (TLD) 31 Direct Radiation (TLD) 32 Direct Radiation (TLD) 33 Direct Radiation (TLD) 34 Direct Radiation (TLD) 35 Direct Radiation (TLD) 36 Direct Radiation (TLD) 37 North Shoreline North Shoreline North Shoreline Demster Beach Road Leavitt Road Rt. 104 Rt.
51A I
Maiden Lane Road Co. Rt.
53 Co. Rt.
1 Lake Shoreline
- Phoenix, NY Control S.W. Oswego, Control
- Scriba, NY Alcan Aluminum, Rt.
1A
- Lycoming, NY New Haven, NY W. Boundary, Bible Camp N
Lake Road OSS Inlet Canal JAFNPP Inlet Canal 0.2 mi 9 294'NW O.l mi 9 315'W 0.1 mi 9 341 NNW 4.8 mi 9 97' 4.1 mi 8 ill'SE 4.2 mi 9 135'E 4.8 mi 9 156'SE 4.4 mi 9 183 S
4.4 mi 9 205'SW 4.7 mi 9 223 SW 4.1 mi 9 237'SW 19.8 mi 9 170 S-SSE 12.6 mi 9 226'W 3.6 mi 9 199 SSW 3.1 mi 9 220 SW 1.8 mi 9 1434 SE 5.3 mi 9 123'SE 0.9 mi 9 237'W-WSW 1.2 mi 9 101'-ESE 7.6 mi 9 235 SW-WSW 0.5 mi 9 70'NE
- Map See Figures 5.1-1 and 5.1-2 October 1985
sL
Nine Mile Point Nuclear Station Unit 1 Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)
Type of S
le Shoreline sediment Fish Fish
- Map Location 40 41 Collection Site Sunset Bay Shoreline NMP Site Discharge Area NMP Site Discharge Area Location 1.5 mi 9 80' 0.3 mi 9 3154 NW and/or 0.6 mi 9 55 NE Fish Oswego Harbor Area 6.2 mi 9 235'SW Milk Milk Milk Milk Milk Location 050 Milk Location $7 Milk Location
$16 Milk Location 840 9.3 mi 9 93 SE 5.5 mi 9 107'SE 5.9 mi 9 190' 15.0 mi 9 223 SW Food Product Food Product 49 Produce Location 02*"
(J. Parkhurst) 1.8 mi 9 96 ESE Produce Location Sl""
1.3 mi 9 98 E
(O'onnor)
Food Product 50 Produce Location
$3"*
(Fox) 1.9 mi 9 101 ESE Food Product 51 Produce Location 84"*
(C. Parkhurst) 1.5 mi 9 114 SW Food Product Food Product 52 53 Produce Location
$5**
(C. R. Parkhurst)
Produce Location I6**
(J. Lawton) 2.1 mi 9 ill S
2.2 mi 9 123 SE Food Product 54 Produce Location 07**
(Mc Millen) 15.0 mi 9 223 ESE 12.6 mi 9 225'W October 1985 Food Product Produce Location
$8*"
(Denman)
- Map See Figures 5.1-1 and 5.1-2
+* Food Product samples need not necessarily.
be collected from all listed locations.
Collected samples will be of the highest calculated site average D/Q.
APPENDIX, A DISPERSION CALCULATION TABLES I
October 1985
ANNUALX/Q Appendix A Page 1 of 6 (Stack Release)
HN HHH H
HtlE HE EHE E
ESF.
.805E 06 1.783E-06 1.833E-06
.055E-06 1.230E 06
- 2. 139E" 06 2.289K-06
- l. i56E-06 9.578E-07 5.118K 07 4.289E-07 4.233E-07 4.375E-07 2.S11E-07 2.903E-07 5.088E-07 5.472E-07 2.980K-O>
2.268E-07 1.38BE-07
- 1. 661E-07 1.640E-07 1.705E-07 9.816E-OS
- 1. 121E 07 1.968E-07 2.128E-07 1.160E-07
- 8. 941E-08 5.566E-OB HHP UH1 T
~ 2 STACK HO DECAY, UHDEPLE'TED CORRECTED FOR OPEN TERRAIN RECIRCULATION ANNUAL AVKRACE CHI/O (SKC/HETER CURED)
SECTOR
.500 1.000 1.500 8
6.850E-07 1.624E-07 6.539E-OB SSH 7.642E 07 1.840E-07
/.362E-08 SH 6.'370K-07 1.530K-07 6. 116K 08 NSM 3.482E-07 8 418E-08 3.366K-OS N
4.496E 07 1.068E-07 4.270E-OS NHN 6.9/3E-47 f.670E-07 6.625E-OS 2.000 3.698E-OS I. 145E-08 3.487E-OB 1.92/E-08 2.446E-OB
- 3. 751E 08 9.f23E-OB 8.970E-OS 9.422E 08 5.479E 08 e'.
s3E-oa 79E-07 69E-07 6.388K-OB 4.98tE 08 3.152K-OB 6.239E-OB 3.673E 08
- 4. 051E-08 7.076E 08 7.672E 08 4.203E-OB 3.306E"08 2.130E 08 4.589K-OB 2.736E-OB 2.968E-OB
- 5. 147E-08 5.584E-OB 3.064E-OB 2.425E-OB 1.592E-OS DISTANCE IH NILES 2.500 3.000 2.490E 08 1.85IE-OB 2.782E-OS 2.065E-OB 2.379E 08'794E-08 f.330E-08
.021E-08
- 1. 686E-08
. 291E-08 Z. SIZE-08
. 907E-08 6.004E 08 4.390E-OB 5.872E-OB 4.274E-oa 3.500 1.471E-OB 1.632K-OB
- 1. 438E-08 8.346K-09 1.052E-OB 1.521E-OB
'3.430E-OB 3.328E-OB 3.606E-08
- 2. 174E-08 2.326E-OB 3.9'98E-08 4.339E-OB 2.382E-OB 1.895E-OB 1.267E-OB 4.000 I.21'/K-08 1.346E-OB 1. 198K-08 7.097E-09 8.917E-09 1.264E-OB 2.802E-OB
- 2. /12E-08 2.960E-OB 1,803K-OB 1.90/E-08 3,247E-OB 3.524E 08 1.935K-OB 1.54SE 08 I. 051K-08 4.500 5.000 1.037E-OB 9.035E-09
- 1. 142E-08 9.920E-09 1.026E-OB 8.964K-09 6.196E-09 5.515E-09 7.764E-09 6.892E-09 1.080K-OB 9.422E-09 2.362E-OB 2.038E-OB 2.2S3E-OS 1.968E-OB
- 2. 507E-08
- 2. 172E-08 1.540E-OB 1.344E-OB 1.614E-OB 1.399E-OB 2./22E-08 2.337K-OB
.954K-OB 2.536E-OB 1.621E-OB 1.391E-OB 1.298E-OB 1.116E-OB 8.967E-09 7.826E-09 5.504 8.008E-09 8.762E-09 7.956E-09 4.978E-09 6.204E-09 8 353E-.09 790E-08 1.728E-OB I. 915E-08
- 1. 193E-08 1.234E-OB
- 2. 044E-08
.:218K-oa
- 1. 215E-08 9.777K-09 6.944E-09 AIIHUAL AUERACE DEAR IIIG 8
SSM Sll NSN M
NHN t!H lltln H
HHE ttE KtlF.
E ESE SE SSE 7.000 6.059E-09 6'.sesE-o9 6.0ZiZE-09 3.932K-09 4.869K-09 6.312K-09 e.ooo
(.soo 7.18SE>>O9 6.551E-09 7.838E-09
- 1. 281K-08 1.432K-OB 9.052E 09 9.270K-09
- oo4E-oa
.637 -08
.774 -08 9.701
-09 1.594E-OB 1.539E-OS
- 1. 711K-08
.0/ZE-08 1:104K-OB 1.814E 08 967E-08 1.077K-48 1.184K-8 1.327K-8
- 8. 421E-9
. 60'/E 9
.383E-8
.497K-8 171K 9
1 500E-08 1.625K-OS 8.87BE-09 S. 681E-09 6.238E-09 7.831K-09 S.68BE-09 7.176K-09 5.262K-09
.612E-0'9 I.891K-09 CNT/O (SEC/tlETER CUBED)
DISTAtlCE IH NILES 8.400 8.504 S.ZS6E-09 4.923E-09 8.02BE-09
.282E-08
.386E-08 7.558E 09
- 6. 122E-09 I.S65E-O'9 7.519E-9 1.1'93E-8 1.289E-8 7.022E-9 5.692E-09 4.276E-09 S.662E-09 5.289E-09 5.216E-09 I.aatE-09 3.484E-09 3.2'94K-09 4.302E 09 4.061E-09 S.I67E-09
- 5. 117K-09
- 3. 122E-09
- 3. 844K-09 4.804E 09 9.946E-09 9.614E-, 09 f.083K-OB 6.93iE-09 7.067E-09
- 1. 115K-08 1.203E-OB 6.549E-09
- 5. 313E-09 4.018E-09 4.361E-09 4.661K-09 4.315E-09 2.965E-09 3.647E-09 4.525E-O'9
- 9. 340E-09 9.033E-09
- 1. 019E-08 6 544E 09 6.664E-09 l.046E 08
- 2. 743E-.09 1.395E-09 2.865E-09 4.473E-09 2.679E-09 2.822K-09 1.96BE-09 3.468E-09 2.402E-09 4.273E-09 2.817E-09 8.798K-09 5.707E 09 8.513E-09 5.552E-O'9
- 9. 613K-09 6. 3 1OE-49 6.189E-09 4.130E-09 6.301E-09 4.224E-09 9.838E-09 6,341E-09 1.059E-OS 6.75BE-09 5.755E-09 3.651E 09 4.67'5E-09 2.979E-09 3.577E-09 2.370E-09 9.500 10.000 15.004 20.000 2.037K-09 2.094E-09 1.969E-09 1.498E-09 1.821E-09 2.074E-09
- 4. 158K-09 4.067E-09
- 4. 634K-01
- 3. 061K-49
- 3. 156E-09
- 4. 618E-09 4.844E-09 2.632E-09
- 2. 156E-09
- 1. 75 IE-09 47-ber 1985
II 4
Appendix A Page 2 of 6 ANNUAL D/Q (Stack Release)
NNP UNIT OZ STACK CORRECTED FOR OPEH TERRA ltlttllt~ tti ~ tlttttSI DIRECTION FROtt SITE
.50 IH RECIRCULATION RELATIVE DEPOSITION PER UNIT f.50 2.00 1.495E-09 7.832E-ID
- 1. 696E-09
- 8. 915E-10 1.1/7E-09 6.305 10 3.899E-0 2.139K 10 4.347K-0 2.404 10 9.36SE-SD 5.08b -10 2.55DE-09 1.334 09 1.00 3 95iE-09 4.447K,-OV 2.993K-09 9.597t-io
.054F.-09 2.327K-09 6.675E-09 8
SSH SH HSH H
NNH NH
- 1. 312E-08 1.555E-OB
.020K-08 3.054K OV 3.311E-D9 7.745K O'9 2.430E-OB NNII N
tltlF tlE EIIE E
ESE SE SSE 1.265E-09 1.297K 0'9
- 6. 091E 10 1.294E-IO Z.OVSE D9 2.77ZE-09 2.379E-OB 6
2.263F DB 6
9.6YVE OV 2 1.312K 08 3
3.VIDE 08 5.322E-OB 472K-09 2.438E-9 386F-D9 2.458F-D9 838t'-0'9 S.13St-OV 518K-09
~
I. 793E-09 2.708K-OB 7.
1.452E-09 1.3SZE-DB 3.870E-09 1.467E-09 7.688E-ID
.50
3.
0 3.5 0
4.806K-10 "3.241E-io 2.340E-10 1,765E-SO 5.482E-10 3.708E"10 2.672E-IO 2.015E-SO 3.926E-10,2.677E-S0 1.938F-IO S.466K-S0
.353E-
- 9.320K-tf
.529E-
,f.056F-10
- 3. 196K-I I 2. 91t 10
- 8. 176E-
- 5.5ifE-10 7;700E-0 5.
70E-10 1.9BBF-0 5.406F-SO 3.8f2t-fo 2.605E 10 4.487K-f0-3.031K lo
.27VE 9 8.598E-10 S.tbit-if S.BGSF li 1.206E.-fo 2.977E-10 2.783E-SD 2 936F-10 1.42/t-10 1.639E-SD 4.630E-IO 6.79bt-l 1 7.717K-ll 1.592E-S 3.960E-1 3.705E-S 3.896K-S 1.'BBBF-I
- 2. 179K f
- 6. f66E-I 8.079E
.685E-09
- 1. 129E-Ov 0 6. OSBF.-10
.OBBE 09 7.286E-10.5.21OE-IO 3.905E-10 8'.BSOE-io 5'.948K-10'4.'266E-10 3.205K-1O 4.118E 10 3 187K f0 2 VGE 10 1
731E 10 AREA INSS "2)
AT FIXED POINTS BY DOHtIHIN DISTANCES IN NILES 2
0 0
0 D SECTORS 4.50 I.378E-1 0 1.573K-fo 1
~ 145K-0 4.043E-if 4.595E-ii 9.428E-
- 2. 317E-i 0 2.i65E 0
2.289E-SO I.tf4E-IO 1.274E-io 3.600E-SO 4.706F.
10 3.033E-SO 2.494E-10
- 1. 351E-i 0
- 5. 00 1. 106E-1 0
- 1. 261E 10 9.f73E-SS 3.245E"lf 3.687K fi 7.554E-11 1.852E 10
- 1. 731E-0 1.832E-0 8.920E-ll 1.017K-0 2.876E-0 3.757E 10
- 2. 421E-10
- 1. 994E-10
- 1. 08 IE-10 S. 50 9.070E-11 1.033K-10 7.504E-ii 2.656E-SI 3.016K-SI 6.176E-if 1.513E-IO
- 1. 415E-i 0 1.498E-SO 7.288E"11 B.ZVBE-ll 2.349E-SO 3.068E to 1.977E-SO 1.631E-10 8.883E-II t t a t t I t I t I t I I I I I t t t I DIRECTION FRON SITE S
SSH SH H5 II H
HNH NH tlntl N
tltlE NE ENE E
ESE SE SSC 6.44 7.572K-8.612E-6.245E-I 2.210K-2.50BE-
- 5. 134K
.259E
. 17BE-
.247K-6.056E 6.889E
.953E-2.55fK-
.644E-
.357E-1.4t2E 6.50 6.515K-tt
- 7. 401K-f 1 5.390E-i f.920E-
- 2. 18iK-1 4.443K-
- 1. 078E-
'. 001K-
'1.072K-5.229C-
- 5. VOIK-1.670E-
- 2. 116K-
-'1. 40ZK-162K-
- 6. 314E-1 7:00 5.752K-I 6.537E-I 4.755K-f
.694K-I
.V24E-i 3.920K-i 9.511E-I
$.886E-1 9.455E 4.612E-I 5.204E-1.473E-1.920K-i f.237E-
.025E-5.'626E-I 1.50 5.120E-5.817K-I 4.231K-I 1.507E-1.711K-3.4BGE-8.458E-
'1.904K
.410K-
. 101K-
~.626E-
.3IOE-i.707E-
.SOOK-9.116E-
- 5. 001E DISTANCKS 8 04 4.5'9 E-I 5.21 E-I 3.79 E-I
.3S E-
.533E-
- 3. 122E-1.575E 1.080E 1.534K-j:.673E-4fE 73E-
.529C-
- 9. 84'1E
- 4. t41E-I 4.703K-
- 3. 411K-I 1.218E-1.382E-2.814C-6.827E-6.382K-6.792C-
- 3. 31OE-3.730E-t. 051K
- 1. 317E-8.873E-7
~ 36fK-4.049K-9.00 3.758E-4.266E 3.098E"
.104E"
.253E-2.55SE-6.187 5.785E-
- 6. 157E-3.000E-3.378K-9.580E-1.24OC-8.039E-6'.613E-
- 3. 614E-f 9.50 3.42/E-11 3.88'9E"ff 2.823E-tt i.006E-11
- 1. f42E-ll 2.324E-if 5.634K"11
- 5. 270K" 11 5.610K-I 2.732E-tl 3.0'15E-1 8.724K-f I. 136E-10 7.320E-11 6.079E-11 3,350E-1 I 10.00 3.140E-1 3.56iE-2.584E-S 9.215E-1.045E-2.S27K-
- 5. 155E-4.82ZE-
- 5. 134E-2.50OE
- 15. 00 1.642E-f
- 1. 854E-1 i.339K-1 4.790E-1
- 5. 420E-1 1.099K"i 2.653E-1
- 4. 100E-1
- 5. 331E-1 3.435K-S 2.872E-S.GDSE-S 20.00 1.026E-ii l.i54E-II 8.3D2E-SZ
- 2. 981E-IZ 3.366E-SZ 6.803E-IZ 1.635E-i 1.536E-I
.643E-1 1.95ZE-S 2 8.802E-12 2.522E-it 3.275E-II 2.110E-I 1
1.774E-i I 9.'VBBE-t2
Appendix A Page 3 of 6 GRA7ING SEASON D/Q (Stack Release)
IIHP UHII CORRECTED tttetttte DIRECTION FPOH SI TE 5
5 5 II SIT NSN II lltlll NIT NWIIII NNE NE ENE E
ESE SE SSE 1.00 3.988E-09 3,901E-09 2.43BE-09 7.609E-IO
- 8. 473E-10 2.083K-09 6.492E-09 6.549E 09 6.939E-09 2.816E-09 3.067E-09 1.092E-OB 1.35fE-OB 7.668E-09 6.533E-09 3.879E-09
.50 f.395E-OB 1.346E-OB
- 8. 131E-09 2.393E-09 2.629E-09 6.933E-09
- 2. 316E-08 2.389E-OB
- 2. 156E-08 9.594E-09
- 1. 103E-08 3.959E-OB 4.979E-OB 2.842E-OB 2.383E-OB 1.376E-OB 2.00 7.789E 10 7.836E-0
- 5. 1618-10 1.701E 10 1.948E-0
.1.522K-IO
.306E 09
.283E-09 1.50
- 1. 195E-09 1.488E-09 9.605E-LO 3.095E-IO
- 3. Sl LE-10
- 8. 342K-I 0
- 2. 18'PE-09 2.470E-09 2.668E-O'9
- 1. 122E-09
- 1. 199E-09
- 4. 178E-09
- 5. 121E-09 2.890E-09 2.151E-09
- 1. 451E-09
.406E-09 6.049E-0 6.363E 0
2.190K-9 2.664E-09 1.498E 09 1.270E 09
/.533E 10 I'IRECT IOH FROH SITE 5
NHN till NtlHtl IIIIE tlE EHE E
ESE SE SSE 6.00 6.50 7.00 7.50 7.173K-I 6.422E-II 5.670E-II 5.018E fl 7.629K-L 6.570E-II 5.799E-11 5.161E-IL 5
I 3.515E-I
.206E"f I 1.396E-I I 3.096K-I 8.338E-I I 8.073E I 0 9.125E
.356E-I j 1. 570E-I 3.481E-f 0 9. 376E-I 0 9.075E"I 0 1.026E-I I 4.584K-I 4.623E-I 0 1.567E-I 0 1. 874E-I 0 1.046C-0 8.961K-5.422E-I/7E-768E 045E-
- 4. 476E-1
.537E"I
.779E-
- 3. 915E"
.063E-I
.028E I
. 163E 5.197E-5.243E-I 1.776E-
- 1. 015E-I 6.142E-1.559E-f.239E-I f.202E-L.353E-
- 6. OIBE
- 6. 105E-2.072E-2.184E 1.388K I.187E-
- 7. 15BE-L 02 STACK FOR OPEH TERRAIN RECIRCULATIOH t ~ tet ~ ttetei RELATIVE DEPOSITION PER UHIT AREA IHet-2)
AT FIXED POINTS DISTAtlCES IN HILKS 2.50 3.00 3.50
- 4. 761E 1
4.825E-
- 3. 221K-I 1.077E-1.24fE 1
2.838E-B.OIBE-7.823E-8.660E-3.783E-I 3.935E-I 1.343E-O 2.308E-LO 2.358E-SO
.598E-10 5.422K-II
- b. 281E-I I 1.413K-I 0 3.893E-IO 3.772E-IO 0 3. 209E-10 0 3.268E-I 0.2.203E-L 0 7.430E-L 0 8.59LE-L 0 I.'945E-I 0 5.413E-L 0 5.258E-I 0 5.861E-I 1.223E-I I. 871E 0 2.585K-Ie 0 2.668K-Lv 1.923E-9 9.061K-LO 6.513E-1.625E-09 1.092E-09 7.833E-9.114K-IO 6.115E-0 4.380E-7.728E-IO 5.188E-0 3.719E-
- 1. 593E-10
- 4. 120E-11 4.77/E-11
- 1. 070E-10 2.929E-LO 2.834K-LO
- 3. 183E-10 1.117E-IO
- 1. 67 LE-10 4.50 1.359E-SO 1.390E-SO 9.461E-IL 3.229K-LL 3.744E 1 I 8.364E-IL
- 2. 281E-10
- 2. 206E-I 0
- 2. 482E-10
. 107E-10
. 128E-10
- 3. 811E-10
- 4. 575E-10 2.555E-IO
- 4. L71E-1 2.841E-I 9.750E-I 1.128K-L 2.500K"S 6.731E-I 6.520E-L 7.370E I
- 3. 2'9 IE-I 3.315E-I I. 125E-I 1.345E-I 7.5OBK-I 6.441E-I 3;904E-I 4.627E-I 3.150K-I I. 08 E-I 1.25 E-I 7.46 E-I 3.787E I 2.576E 2 8.843E-I I
.023E-1 I 2.266E-f I 6.
OOE-I I 5.911E-I I 6.682E 1 2.982E I 3.003E-I 0 1.019K-f 0 1.219E-I I 6.804E-f I 5.810E-I f 3512K I 1 3.454E-I 2.348E-2 8.061E-12 9.320E" 2
I 2.065E-I 5.556E-II I 5.385E-II I
6 OBBE-11 2.716E-I I 2.731K-1 0 9.284E"11 0 1. I LOE-10 I 6.197K-II 5.322E-II
- 3. 231E-L I
- 7. 232E-I
- 8. 175E-I
- 3. 651E-I 3.680K-I
. 218E-I I. 1'93E I 8.331K-I
- 3. 164E-
- 2. 151E-7.382E-8.533E-1.890E-
- l. 016E-I 5.670E-I 4.872E-I 2.960E-
- 4. 526E-I I 3.707E-II 5.00 1.090E-LO
- 1. 115E-10 7.589E 11 2.593E-LL 3.00SE-LL
- 6. 701E-11
- 1. 824E-10
- 1. 765E-10
- 1. 987E-10 8.860E-11 9.012E-IL
.652E-11
- 1. 119K-II 3.844E-12 4.128E-12 9.781E-12
- 2. 619K I 2.547E ll 2.883E" I 1.282E-I 1.280E I
4.374E-IL
- 5. 224E-11 2.917E-2.523E-
- 2. 159E-I 1 5.482E-11 1.490E-LO 1.413K-SO 1.625K-IO
- 7. 241E-11 7.353E-11
- 2. 491E-10 2.987E-LO 1.668E-IO 1.424E-IO 8.572E,-LI 20.00 1.016E-LI 1.032E-11 6.'964E-12 2.396E-12 2.752E-12
- 6. 061E-12 1.6LSE-11 1.575E-II 1.785E-IL
- 7. 918K-12
/.856E-12 2.696E-IL
- 3. 217E-11 1.797E-11 1.563K-II 9.657E"12
'tet ~ tttttete
~ eeeetee 49-Oct 1985
L
)to PJ J
Appendix A Page 4 of 6 ANNUAL X/Q 7Vettt Release) 5 SSH SH IISN H
NHII HH HIIII H
NIIE IIE KtIEf ESE SE SSE 2.677E-07
. IBOE-07
. 210E-07 4.285E-OS 1.883E-OB
.498K-0/
2 577E-07 1.926E-07 Z. 137E-07 1.084E 07 1.577E-07
- 5. 815E-07
- 7. 166K -07 5.580E-07 4.368E-07 1./59E 07 8.468E-OB 7.433K 08
- 7. 312E-08
- 2. 513E-08 3'.SSOE-OS 1.010E"07 1.488K-07 1
059E-07 1.394E-07 6.870E-OB 9.033E-OB 2.733E-07
- 3. 1?of-07 2.336K-07 1.939K-07
- 7. 109E-08 6.236E-OB
- 6. 021K-08 6.914K-OB 3.200K-OB
9 773E-08 1.262E-07 6.331E-OB 7.489K-OB 1.774E-07 1.842f-07 1.320t-07
- 1. 165E-07
- 4. 919E-08 ttHP UNIT IZ VEHT HO DECAY, UHDEPLETED CORRECTED FOR OPEtt TERRAIN R
CIRCULATION AtIHU4L AVER4CE CHI/O I SKC/tIETER CUBED I SECTOR
.500 1.000 1.500 2.000 5.027E-OB 5.028E-OS 6.161K-OB 3.350K-OB 5.460K-OB 9.343E 08 1.218E 07 8.750K-OB
- 1. 115E 07 5.586E-OB 6.298E 08 1.303K-07 1.280E 07 8.895E 08 B. IOSE-OS 3.862E-OS DISTANCE IN NILES 2.500 3.000 1.152E-OS 3.501E-OB c -
.558K-08 1
20 E
08 3
5.327E-OS 1
- 3. 187E-08 2
S. 213E-08 4
8.216E-OB 7
1. 051E-0/
9 7.620K-OB 6
9.62SE-OB 8
1;802E-08 5.274K-OS 1.008E-07 8
599E-08 935E-08 815E-08 77E-08 01E-08 623E-08 310 E-08 127E-08 156E-08 083K-OB 9.601E-OB 7.567E-OB 6.534E 08 5.07SE-OB 6.064E 08 1.764E-OS
- 3. 129E-08 2.603E-OS 3.500 3.005E-OB 3.054E-OB 4.002E-OB 2.677E-OB
- 4. 105E-08 6.302E-OB
- 7. 926K -08 5.797K-OB 7.234E-OB 3.578E-OB 3.816E-OS
- e. 671E-o 8
- 6. 176K -08
- 4. 100K-08 3.879E-OS 2:213E-08 4.000 2.620E-OB 2.658E-OB 3.518E-OB 2.439K-08 4.02/E-08
- 5. 581E-08 6.975F.-OB 5.123E-OB 6-363E-08 3.135E-OS 3.311E-OB 5.63tf-oo
- 5. 1/BE-08 3.112K-OB 3 246K-OB 1.916K-OS
- 1. 500
- 2. 314E-08
- 2. 312E-08
- 3. 123E-08 2.Z28E-OB 3.692E-OB
<.989K-08 6.202E-OB 4.57ZE-OB 5.656E-OB 2.777E-OB 2.910K 08 1.842E-OB 4.132E-OB
- 2. 901E-08
- 1. 118E-08 5.076E-OB 2.484E-OB 2.585E-OB 4.228E-OB 3.860E-OB
- 2. 518E-08
- 2. 114K-OS 1.497E-OS 5.500 1.867E-OB 1.878E-OB
- 2. 53 lE-08 1.883E-OB
- 3. 144E-08 4.091E-OB 5.044K-OS
'H WSH H
IIIIII IIH NIIHIt tnIE ttE KIIE E
ESE SE SSE CIII/0 I SEC/tIETER CUBED) 6.000 6.500 7.000 I:699K-08 1.5elE-os 1.458E-OS 1.703E-OB 1.563E-OB 1.452E-OB 2.305E-OB 2 I?2K-OS 1.9/BE-08 1.743K 08 1 627E-08 1.535E-OB 2.920E 08 2.737E-OB 2.592E-OS 3.746K-OS 3.468E-OS 3.249t-08 1.604E-OB 1 251E-08 3.973E-OB 3.423K-OS 3. 167t-08 2.966E-OS 4.191E-OB 3 867E-08'3.612E-OS 2.038E-OB 1.875E-OB 1.747E-OS
.09SE-08 i.'922E-08 1.783E-OB 3.341K-OB 3.032E-OS 2./BBF.-OB 3.044E-OB 2.758E-OB 2.536'-CS 1.973E-OB l.784E-OB 1.636K-OB 1.902K-OB 1.722E-OS 1.583E-OB
.848E-8 1.150E 8
2.15SE 8
3.053t-8 3.7"SE 08 2.786E-OS
- 3. 381F.-OB 1.632E 08 1.660E 08 2.5/5E-08
- 2. 312K 08 1.509E-OB 1.462E 08 9.746E-09 1.278E-OS
.265E-08 1.732E-OS
.372E 08
- 2. 331E-08 2.8/6E-08 3.502E-OB
- 2. 621E-08 3.
79E-08 1.529E-OS 1.550E-OB 2.389K-OB
- 2. 173E-08 1.397E-OS 1.356E"08
- 9. 125E-09
.202E-08
. 186E-08
.627E-08
.300E 08 2.220E-OB r.716K-OB 3.302E-OB 2.4/7K-08 2.995E-OB 1.437K-OB 1.452E-OS 2.224K-OS 2.023E-OB 1.299K-OB 1.262E-OB 8.567E-09 DIST4HCE IN tlILES 8.000 8.500
'9. 000
- 1. 132E" 08
- 1. 114E-08 1.532E-OS 1.234E-OS 2.114E 08
- 2. 571E 08
- 3. 120E-08
- 2. 341K 08 2.828E-OB 1.353E-OB 1.364E-OB 2.078E-OB
- 1. 050K-08 1.446E-OB
- 1. 173K-08
- 2. 017K-OB
- 1. 947f ~08
- 1. /72E-08 1.135K-OB 1
/ 6llf-09
- 1. 013E-08 9.908E-09 1'.3e7E-oS
- 1. 117E-08 1.927E-OB 2.3tBE-OB 2.806E-OB
- 2. 113E-08 2.S38E-OB 1.209K-OS
- 1. 213E-08 1.830E-OS 1.666K-OB t.066E-OB 1.038E"08 7.199E-09
- 8. 041E-09 7.923E-09 1.160E-OB 1.060E-OB 6.732E-09 6.605E-09 4.778K-09 9.500 10.000 15.000 20.000 4.966K-09 4,663K-07 6 552K-0 r 5 770K-or 1.054K-OB 1.2tof-ob 1.149E-OS 1.104E-OB 1.287E-OB 5.9tbf-o>
5.762E-O'9
- 8. 311E-09 7.623E-09 4.819E-09 4.753E-09 3
5 I BE-0%
50-October 1985
tlnl'n e I CORRECTED eeeee
~ eeee DIRECTION FROtt SITE 8
HNN Nlt NIIHtt HNE NE EtIE E
ESE SE 55E D I R EC I' ON FRON SITE S
5 5 II SIT N5 II M
IItHI IWI tIIIH N
HIIE tlE EWE E
- 2. 00 7.896K-fo S.itZiE to
.50
$.064E-DB 4.843E-09 3.537f-09 I.iiOE-09 1.26'7E-D9 3.204K-09 6.029K-OP 4.943K-09
- 6. 201K-09 2.232E-09 3.678E-09 1.946K-OB 2.753K-DB 2.4DOE-DB
$.728K-OB S.887E 09 1.00 1.50 3.821K 09 f.462K 09 2.042E-09 8.856K-fo i.737E-09 8.060K 10 5.689E-iO 2.657E-ID 7 594E"10 3.8$ 7E 10 1 603K 09 7.684K
$ 0 4.798F-L 1.'596K-
- 2. 366K" 1 4.62$ E 2.463E-49 1.084K-09 6.231K 1
1.982K-09 8.5 3E-lo 4.847E-I 2.502E-09 1.097E-09 6.299E-L 1.057E"09 5.0 5E-Io 2.972E-I
.949K
.543E 0
.PPOE 0
.648K 0
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1.490K 2.'77OE 3.529E 2.738K-3.563K 1.734E 2.114K 7.665E 9.462E-7.726K-6.566E-2.679E-4.774K 3.292E
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r
Page b or b-GRAZING SEASON D/Q (Velft Release)
HttP UHII CORRECTED llllllIll DIRECTION FROtt SITE S
SSH SH HSH H
HNH HH HNH N
NNK HE EllE ESESf SSE DIRECTION FROII SLTK 5
SSH SH HSH H
HNH IIH titIH N
NNE IIE KNKf ESK SE SSK 42 IIENT FOR OPEN TERRAItt RECIRCUI.ATION I ~lllllllll
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RELATIVE DKPOSITIOtt PER OMIT
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'7.206K-09 2.1LSE-D9 2.916E-09 1.905E-OS 2.603E-OS
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1.586K 0
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