ML18038A135

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Rev 0 to Offsite Dose Calculation Manual. W/Two Oversize Figures & 860305 Ltr
ML18038A135
Person / Time
Site: Nine Mile Point Constellation icon.png
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)
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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 f igures.

DISTRIBUTION CODE: AOO'TD COPIES RECEIVED: LTR ENCL + SIZE:

TITLE: OR/Licensing Submittal: Appendix I NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL HWR ADTS HNR EB 1

1 1 HNR PD3 PD BNR EICSB 01 5 5' 1

HNR FQB 1 HAUGHEY> M 1 1 BNR PSB 1 1 BtJR RSB 1 1 INTERNAL: ACRS 11 3 3 ADM/LFMB 0 ELD/HDS3 19 1 0 NRR BNR ADTS 1 NRR PNR-A *DTS 1 1 NRR PNR-B ADTS 1 1 NRR/ 1 0 NRR/TAMB 1 1 FIL 04 1 1+ RGN1 1 1 EXTERNAL: 24X LPDR 03 NRC PDR NSIC 05 TOTAL NUMBER QF COPIES REQUIRED: LTTR 28 ENCL

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NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, 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

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation ) Docket No. 50-410 (Nine Mile Point Unit 2) )

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 for e State .of New York and County of , thisQ~ day of 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 Quallf lad 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)

DATE AND INITIALS APPROVALS SIGNATURES 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 (C/8l/'f13 Nuc1ear Generation T. J. Perkins V

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Summar of Pa es Revision 0 (Effective 10/31/85 )

PAGE DATE 1-52 October 1985 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE REC.;l "."=0 USED AFTER OCTOBER 1987 0, I '*I

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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

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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: =

Factor to account sample analysis and detector error.

Ci 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 B, Table II, Column 2 (pCi/ml). 20'ppendix 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. OOE-4yCi/ml.

October 1985

0 TABLE 2-1 LIQUID EFFLUENT DETECTORS RESPONSES" NUCLIDE Sr 89 0.78E-04 Sr 91 1.22 Sr 92 0.817 Y 91 2.47 Y 92 0.205 Zr 95 0.835 Nb 95 0.85 Mo 99 0.232 Tc 99m 0.232 Te 132 1.12 Ba 140 0.499 Ce 144 0.103 Br 84 1.12 I 131 1.01 Z,132 2.63 I 133 0.967 I 134 2.32 I 135 1.17 Cs 134 1.97 Cs 136 2.89 Cs 137 0.732 Cs 138 1.45 Mn 54 0.842 Mn 56 1.2 Fe 59 0.863 Co 58 1.14 Co 60 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

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TABLE 2-2 Ai~ VALUES LIQUID*

mrem - ml hr yCi NUCLIDE T BODY GI ZRACT BONE KIDNEY THYROID LUNG H 3 2.938-1 2.938-1 2.938-1 2.938-1 2.938-1 2.938-1 Cr 51 1.28 . 3.2182 2-818-1 7.628-1 1.69 Mn 54 8.3682 1.3484 4.3883 1.3083 Pe 59 9.3882 8.1683 1.0483 2.4583 6.8482 Co 58 2.0182 1.8283 8.9681 Co 60 5.6882 4.8483 2.5782 Zn 65 3.3384 4.6484 2.3284 7.3784 4.9384 Sr 89 6.4082 3.5883 2.2384 Sr 90 1.3585 1.5984 5.4985 Zr 95 5.648-2 2.6482 2.608-1 8.338-2 1.318-1 Mo 99 2.0281 2.4682 1.0682 2.4082 I 131 1.2582 5.7481 1.5282 2.1782 3.7382 7.1384 I 133 2.7581 8.1181 5.1981 9.0381 1.5782 1.3384 Cs 134 5;7985 1.2484 2.9885 7.0985 2.2985 7.6184 Cs 136 8.8684 1.4084 3.1284 1.2385 6.8584 9.3983 Cs 137 3.4285 1.0184 3.8185 5.2285 1.7785 5.8984 Ba 140 1.3681 4.2782 2.0782 2.618-1 8.868-2 1.498-1 Ce 141 2.188-3 7.3481 2.848-2 1.928-2 8.928-3 Nb 95 1.3482 1.51E6 4.4782 2.4882 2.4682 La 140 2.018-2 5.6083 1.518-1 7.62E-2 Ce 144 7.958-2 5.01E2 1.48 6.198-1 3.678-1

  • Calculated in accordance with NUREG 0133, Section 4.3.1 October 1985

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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 Gaseous Effluent Monitor Setpoint Determination 3.1.1 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

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3.1.2.2 Vent Noble Gas Detector Setpoint

'I Alarm Setpoint <k [F(X/Q)vE(CiKi)] + Background i (CiCPi)+

R E Where:

i 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 Where:

i i 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

TABLE 3-1 STACK AND VENT NOBLE GAS*

DETECTOR RESPONSE NUCLIDE NET CPM/ Ci/cc Kr 85 1.00E+5 Kr 85m 6.60E+7 Kr 87 3.00E+7 Kr 88 3.70E+6 Xe 133 6.10E+6 Xe 133m 9.60E+6 Xe 135 5.30E+7 Xe 135m 1.90E+7 Xe 138 5.60E+7 OFFGAS PRETREATMENT**

DETECTOR RESPONSE NUCLIDE NET CPM/ Ci/cc Kr 85 4.30E+3, Kr 85m 4.80E+3 Kr 87 8.00E+3 Kr 88 7.60E+3 Xe 133 1.75E+3 Xe 133m Xe 135 5.10E+3 Xe 135m Xe 137 8.10E+3 Xe 138 7.10E+3

  • Values from SWEC purchase specification NMP2-U213A
  • "Values from SWEC purchase specification NMP2-P281F October 1985

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3.2 Dose Rate Calculation Methodology:

3.2.1 Total body dose rate'due to noble gases:

mrem/yr mrem/Yr E

E fVi Qi

((Lj

+ Ki ((X/Q) vQiv)]

skin dose rate due to noble gases:

(X/Q)s + 1 1 0

Bi) Qis +

i (Li + 1.1 Mi)((X/Q)vQiv)]

3.2.3 Organ dose rates due to iodine-131. iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days:

mrem/yr ~ E Pi [VsQis + Vv Qiv]

1 3.2.4 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)v Qiv + (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

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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 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.

Qis 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.

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Qiv = 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.

(X/Q) 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

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TABLE 3-2 PLUME SHINE PARAMETERS>>

NUCLIDE Bi mrad/ r + Ci/sec Vi mrem/ r + Ci/sec)

Kr 83m 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

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TABLE 3-3 DOSE PROCTORS" Nuclide Ki~Bo~d "* Lg~B-Skin ** MiQ-hiQr "** N~~B-Air *~

  • Kr 83m 7.568-02 1.9381 2.8882 Kr 85m 1.1783 l. 4683 1.2383 1.9783 Kr 85 1.6181 1.3483 1.7281 1.9583 Kr 87 5.92E3 9.7383 6.1783 1.0384 Kr 88 1.4784 2.3783 1.5284 2.9383 Kr 89 1.6684 1.0184 1.7384 1.0684 Kr 90 1.5684 7.29E3 1.6384 7.8383 Xe 131m 9.1581 4.7682 1.5682 1.1183 Xe 133m 2.5182 9.9482 3.2782 1.4883 Xe 133 2.9482 3.0682 3.5382 1.0583 Xe 135m 3.1283 7.1182 3.3683 7.3982 Xe 135 1.8183 1.8683 1.9283 2.4683 Xe 137 1.4283 1.2284 1.5183 1.2784 Xe 138 8.8383 4.1383 9.2183 4.7583 Ar 41 8.8483 2.6983 9.30E3 3.2883

"*mrem/yr per yCi/m3 .

      • mrad/yr per yCi/m3 .

October 1985

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TABLE 3-4 Pi VALUES GROUND PLANE**

m~~mreml r yci/sec NUCLIDE TOTAL BODY SKIN H 3 C 14 Cr 51 6.6486 7.8586 1.1089 1.2989 Fe 59 3.8888 4.5688 Co 58 5i2788 6.1888 Co 60 4.4089 5.1789 Zn 65 6.8788 7.9088 Sr 89 3.0684 3.5684 Sr 90 Zr 95 3.4488 3.9988

  • Nb 95 3.50ES 4 1288 No 99 5.7186 6.6186 I 131 2.4687 2.9887 I 133 3.5086 4.2686 Cs 134 2.8189 3.2889 Cs 137 1.1589 1.3489 Ba 140 2.9387 3.3587

" La 140 2.1088 2.3888 Ce 141 1.9587 2.2087 Ce 144 5.8587 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

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TABLE 3-5 P

i VALUES INHALATION**

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 8.9581 5.7581 1.3281 1.28E4 3.5782 Mn 54 2.5384 4.9883 4.9883 1.00E6 7.0683 Fe 59 1.3684 2.3584 9.4883 1.0286 2.4884 Co 58 1.2283 1.8283 7.7785 1.1184 Co 60 8.0283 1.1884 4.5186 3.1984 Zn 65 1.9384 6.2684 3.1184 3.2584 6.4785 5.14E4 Sr 89 3.9885 1.1484 2.0386 6.4084 Sr 90 4.0987 2.5986 1.1287 1.3185 Zr 95 1.1585 2.7984 2.0384 3.1184 1.7586 2.1784

  • Nb 95 1.5784 6.4383 3.7883 4.7283 4.7985 1.2784 Mo 99 1.6582 3.2381 2.6582 1.3585 4. 8784 I 131 3.7984 4.4484 1.9684 1.4887 5.1884 1.0683 I 133 1.3284 1.9284 5.6083 3.5686 2.2484 2.1683 Cs 134 3.96E5 7.0385 7.4584 1.9085 7.9784 1.3383 Cs 137 5.4985 6.1285 4.5584 1.7285 7.1384 1.3383 Ba 140 5.6084 5.6081 2.9083 1.3481 1.6086 3.8484
  • La 140 5.0582 2.0082 5.1581 1.6885 8.4S84 Ce 141 2.7784 1.6784 1.9983 5.2583 5.1785 2.1684 Ce 144 3.1986 1.2186 1.7685 5.3885 9.8486 1.4885
  • Daughter Decay, Product. Activity level and ef fective half life assumed to equal parent nuclide.
    • Calculated in accordance with NUREG Ol33, section 5.2.1.1.

October 1985

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TABLE 3-6 Milk)*,"*

P i VALUES 2

.FOOD (Cow m mrem/yr + pCi/sec NUOLZDB BONE T. BODY" TBYBOZD KZDNBY QI-LLI

  • 'H 3 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 6.1587 Co 60 S.9SE7 2.128S 2.148S Zn 65 5.6589 1.94810 S.9489 9.4089 1.64810 Sr S9 1.2S810 3.678S 2.63ES Sr 90 1.24811 3.15810 1.5589 Zr 95 6.93E3 1.6983* 1.2083 1.S283 S.4185
    • Nb 95 7.0785 2.9185 1.6S85 2.0985 2.468S Mo 99 2.12ES 4.1387 3.178S 6.9S87 I 131, 2.7789, '3.2689 1.4389 1.07812 3.S1E9 1.168S I 133 3.6987 5.3787 1.5787 9.7789 6.31E7 9.0986 Cs 134 3.71810 6.92810 6.9989 1.7S810 7.3189 1.SSBS Cs 137 5.24810 6.13810 4.3589 1.65810 6.6789 1.928S Ba 140 2.45ES 2.4585 1.2687 5.S384 1.5185 6.0387
    • La 140 3.7982 1.4982 3.S481 1.7586 Ce 141 4.4184 2.6984 3. 1783 S.3083 1.3987 Ce 144 2.3786 9.6985 1.3385 3.9285 1.368S
  • mrem/yr per pCi/m .
    • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.
      • Calculated in accordance with NUREG 0133, Section 5.2.1.3.

October 19S5

  • k TABLE 3-7 R

i VALUES INHALATION - INFANT**

m~rmm/ r 3

pcs/m 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 Fe 59 1.3684 2.3584 9.4883 1.0286 2.4884 Co 58 1.2283 1.8283 7.7785 1.1184 Co 60 8.0283 1.1884 4.5186 3.1984 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 Zr 95 1.1585 2.7984 2.0384 3.1184 "

1.7586 2.1784

  • Nb 95 1.5784 6. 4383 3.7883 4.7283 4.7985 1.2784 Mo 99 1.6582 3.2381 2.6582 1.3585 4.8784 I 131 3.7984 4.44E4 1.96F4 1.4887 5.1884 1.0683 I 133 1.32E4 1.9284 5.6083 3.5686 2.2484 , 2.1683 Cs 134 3.9685 7.0385 7.4584 1.9085 7.97E4 1.3383 Cs 137 5.4985 .6.1285 4.5584 1.7285- 7.1384 1.3383 Ba 140 5.6084 5.6081 2.9083 1.3481 1.6086 3.8484
  • La 140 5.0582 2.0082 5.1581 1.6885 8.4884 Ce 141 2.7784 1.6784 1.9983 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 3

ycl/m 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 Pe 59 2.0784 3.3484 1.6784 1.2786 7.0784 Co 58 1.7783 3.1683 1.1186 3.4484 Co 60 1.3184 2.2684 7.0786 9.6284 Zn 65 4.2684 1.1385 7.0384 7.1484 9.9585 1.6384 Sr 89 5;9985 1.7284 2.1686 1.6785 Sr 90 1.0188 6.4486 1.4887 3.4385 Zr 95 1.90E5 4.1884 3.7084 5.9684 2.2386 6.1184

  • Nb 95 2.3584 9.1883 6.5583 8.6283 6.1485 3.7084 Mo 99 1.7282 4.2681 3.9282 1.3585 1.2785 I 131 4.8184 4.8184 2.7384 1.6287 7.8884 2.8483 I 133 1.6684 2.0384 7.7083 3.8586 3.3884 5.4883 Cs 134 6.5185 1.0186 2.2585 3.3085 1.2185 3.8583 Cs 137 9.0785 8.2585 1.2885 2. 82E5 1.0485 3.6283 Ba 140 7.4084 6.4881 4.3383 2.1181 , 1.7486 1.0285
  • La 140 6.4482 2.2582 7.5581 1.8385 2.2685 Ce 141 3.9284 1.9584 2.90E3 8.5583 5.4485 5.66E4 Ce 144 6.7786 2.1286 3.61E6 1.17E6 1.2087 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

i VALUES INHALATION TEEN m~reml r 3

ycl/m 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 1-3582 7.5081 3.0781 2.1084 3.0083 Mn 54 5-1184 8.4083 1.2784 1.9886 6.6884 Fe 59 1.5984 3.7084 1.4384 1.5386 1.78E4 Co 58 1.3486 9.5284 2.0783'.7883'.5184 Co 60 1.9884 8.7286 2.5985 Zn 65 3.8684 1.3485 6.2484 8.6484 1.2486 4.6684 Sr 89 4.3485 1.2584 2.4286 3.7185 Sr 90 1.0888 6.6886 1.6587 7.6585 Er 95 1.46E5 4.5884 3.1584 6.7484 2.6986 1.4985

  • Nb 95 1.8684 1.0384 5.66E3 1.0084 7.51E5 9.6884 Mo 99 1.6982 3.2281 4.1182 1.5485 2.69E5 I 131 3.5484 4.9184 2.6484 1.4687 8.4084 6.4983 I 133 1.2284 2.0584 6.2283 2.9286 3.5984 1.0384 Cs 134 5.0285 1.1386 5.49E5 3.7585 1.4685 9.7683 Cs 137 6.7085 8.4885 3.1185 3.0485 1.2185 8.4883 Ba 140 5.47E4 6.7081 3.5283 2.2881 2.0386 2.2985 "La 140 4.7982 2.3682 6.2681 2.1485 4.8785 Ce 141 2.8484 1.9084 2.1783 8.8883 6.1485 1.2685 Ce, 144 4.8986 2.0286 2.6285 1.21E6 1.3487 8.6485
  • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

October 1985

1P 1

lf CC

TABLB 3 10 R

i VALUES INHALATION ADULT m~reml r 3

yci/m 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 1.0082 5.9581 2.2881 1.4484 3.3283 Mn 54 3.9684 6.3083 9.84E3 1.4086 7.7484 Fe 59 1.1884 2.7884 1.0684 1.0286 1.8885 Co 58 1. 5883 2. 0783 9 2885 1.0685 Co 60 1.1584 1.4884 5.9786 2.8585 Zn 65 3.2484 1.0385 4.6684 6.9084 8.6485 5-3484 Sr 89 3.0485 8.7283 1.4086 3.5085 Sr 90 9.9287 6.1086 9.6086 7.2285 Zr 95 1.0785 3.4484 2.3384 5.4284 1.7786 1.5085

  • Nb 95 1.4184 7.8283 4.21E3 7.7483 5.0585 1.0485 Mo 99 1.2182 2.3081 2.9182 9.1284 2.4885 I 131 2.5284 3.5884 2.0584 1.1987 6.1384 6.2883 I 133 8.6483 1.4884 4 5283 2.1586 2.5884 8.88E3 Cs 134 3.7385 8. 48E5 7. 28E5 2.8785 9.7684 . 1.0484 Cs 137 4.7885 6.2185 4.2885 2.2285 7.5284 8.4083 Ba 140 3.9084 4.9081 2.5783 1.6781 1.2786 2.1885
  • La 140 3.4482 1.7482 4.5881 1.3685 4.5885 Ce 141 '.9984 1.3584 1.5383 6.2683 3.6285 1.2085 Ce 144 3.4386 1.4386 1.8485 8.4885 7.78E6 8.1685
  • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

October 1985

W TMLB 3-11 VALUES GROUND PLANE R

i ALL AGB GROUPS 2

m mrem/yr + yCi/sec TOTAL BODY SKIN H 3 C 14 Cr 51 4.6586 5.5086 Mn 54 1.4089 1.6489 Fe 59 2.7388 3.2088 Co 58 3 8088 4.4588 Co 60 2.15810 2.53810 Zn 65 7.4688 8.5788 Sr 89 2.1684 2.51E4 Sr 90 Zr 95 2.4588 2.8588

  • Nb 95 2.5088 2.9488 Mo 99 3.9986 4.6386 I 131 1.7287 2.0987 I 133 2.4586 2.9886 Cs 134 6.8389 7.97E9 Cs 137 1.03810 1.20810 Ba 140 2.0587 2.3587
  • La 140 1.4788 1.6688 Ce 141 1.3787 1.5487 Ce 144 6.9687 8.07E7
  • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

October 1985

q'F U4 4 ~

TABLB 3 - 12 R

i VALUBSMOWMILK-INFANT 2

m -mrem/yr + ycl/sec NUCLIDE BONE T. BODY TBYBOZD KZDNBY LUNG QZ-LLI

  • H 3 2-3883 2-38g3 2-3883 2.3883 2.3883 2.3883
  • C 14 3.2386 6.8985 6.8985 6.8985 6.8985 6.8985 6.B985 Cr 51 8.3584 5.4584 1.1984 1.0685 2.4386 Mn 54 2.5187 5.6886 5.5686 9.2186 Fe 59 1.2288 2.1388 8.3887 6.2987 1.0288 Co- 58 1.3987 3.4687 3. 4687 Co 60 5.9087 1.3988 1.4088 Zn 65 3.5389 1.21810 5.5889 5.8789 1.02810 Sr 89 6.9389 1.9988 1.4288 Sr 90 8.19810 '.09810 1.0289 Zr 95 . 3.8583 9.3982 6.6682 1.0183 4.6885
    • Nb 95 3.9385 1.6285 9.3584 1.1685 1.3788 Mo 99 1.0488 2.0387 1.5588 3.43E7 I 131 1.3689 1.6089.

k 7.0488 5.26811 1.8789 5.7287 I 133 1.8187 2.6487 7-7286 4;7989 3.1087 4.4686 Cs 134 2.41810 4.49810 . 4.5489 1.16810 4.7489 ~

1.2288 Cs 137 3.47810 4.06810 2.8889 1..09810 4.4189 1.2788 Ba 140 1.2188 1.2185 6.2286 2.8784 7.4284 2.9787

    • La 140 1.8682 7.3581 1.8981 8.6385 Ce 141 2.2884 1.3984. 1.6483 4.2883 7.1886 Ce 144 1.4986 6.1085 8.3484 2.4685 8.5487
  • mrem/yr per yci/m3.
    • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

October 1985

~ 4W

  • I

TABLE 3 13 R VALUES~WMILK~ILD 2

m -mrem/yr + ycl/sec NUCLIDE BONE 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 Co 5S 6.94H6 2.1387 4.0587 Co 60 2.S987 S.5287 1.608S Zn 65 2.6389 7.0089 4.3589 4.4189 1.2389 Sr S9 3.6489 1.048S 1.418S Sr 90 7.53810 1.91810 1.0189 Zr 95 2.1783 4.7782 4.2582 6.S382 4.9S85
    • Nb 95 2.1085 S.1984 5.S584 7.7084 1.528S'.3787 Mo 99 4.0787 1.0187 S.6987 I 131 6.518S '.55HS 3.728S 2.17811 1.0S89 5.S387 I 133 S.SSB6 1.0687 4.0186 1.97H9 1.77E7 4.2786 Cs 134 1.50810 2.45810 5.1S89 7.6189 2.7389 1.328S Cs 137 2.17810 2.0S810 3.0789 6.7S89 2.4489 1.308S Ba 140 5.S787 5.1484 3.4386 1.67E4 3.0784 2.9787
    • La 140 S.9281 3. 1281 1.0581 S.6985 Ce 141 1.1584 5.7383 S.5182 2.5183 7.1586 Ce 144 1.0486 3.2685 5.5584 1.SOE5 S.4987
  • mrem/yr per ycl/m3.

"*Daughter Decay Product. Activity level and effective'alf life assumed to equal parent nuclide.

October 19S5

TABLE 3 14 R

i2VALUBS~WMILK-THEM m ~em/yr + yci/sec NUCLIDE BONK LZVRR T. BODY THYROID KZDNBY LONG GZ-LLZ

  • H 3 9.9482 9.9482 9.9482 9.9482 9.9482 9.9482

.*C 14 6.7085, 1.3485 1.3485 1.34H5 1.3485 1.3585 1.34E5 Cr 51 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 6.2787 Co 60 1.8687 4.1987 2.4288 Zn 65 1.3489 4.6589 2.1789 2.9789 1.9789 Sr 89 1.4789 4.2187 1.7588 Sr 90 4.45810 1.10810. 1.2589 Zr 95 9.3482 2.9582 2.0382 4.3382 6.8085

    • Nb 95. 9.3284 5.1784 2.8584 5.0184 2.2188 Mo 99 2.2487 4.2786 5.1287 4;0187 I 131 2. 6888 3.7688 2. 0288 1. 10811 6. 4788 7.4487 I 133 3.5386 5.9986 1.83E6 8.3688 1.0587 4.5386 Cs 134 6.4989 1.53810 7.0889 4.8589 1.8589 1.9088 Cs 137 9.0289 1.20810 4.1889 4.0889 1.5989 1.71BS Ba 140 2.4387 2.9884 1.5786 1.01H4 2.0084 3.75E7
    • La 140 3.7381 1.8381 4.8780 1.0586 l

Ce 141 4.6783 3.1283 3.5882 1 4783 8.9186 Ce 144 4.2285 1.7485 2.2784 1.0485 1.0688

  • 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 R

i 2VALUES~WMILK-ADULT m -mrem/yr + yci/sec NUCLIDE BONE 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 1.4884 8.8583 3.2683 1.9684'.7286 Mn 54 5.4186 1.0386 1.6186 1.6687 Pe 59 1.6187 3.7987 1.4587 1.0687 1.26ES Co 58 2.7086 6.0586 5.4787 Co 60 1.1087 2.4287 2.0688 Zn 65 8.7188 2.7789 1.2589 1.8589 1.7589 Sr 89 7.9988 2.2987 1.2888 Sr 90 3.15810 7.7489 9.1188 Zr 95 5.34E2 1.7182 1.1682 2.6982 ~

5.4385

    • Nb 95 5.4684 3.04E4 1.6384 3.0084 1.8488 Mo 99 1.2487 2.3686 2.8187 2.8787 I 131 1.4888 2.1288 1.2188 6.94810 3.6388 5.5887 I 133 1.9386 3.3686 1.0286 4.9488 5.8686 3.0286 Cs 134 3.7489 8.8989 7.27E9 2.8889 9.5588 1'.5688 Cs 137 4.9789 6.8089 4.4689 2.3189 7.6888 1.3288 Ba 140 1.3587 1.6984 8.8385 5.7583 9. 6983 2 7787
    • La 140 2.0781 1.05E1 2.7680 7.6785 Ce 141 2.54E3 1.7283 1.9582 7.9982 6 5886 Ce 144 2.2985 9.5884 1.2384 5.6884 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 R VALUBS~WMEA~ILD 2

m -mrem/yr + ycl/sec NUCLIDE BONE T. BODY TBYBOZD KXDNBY GZ-LLI

  • H 3 2.3482 2.3482 '.3482 2.3482 2.3482 2.3482
  • C 14 5.2985 1.0685 1.0685 1.0685 1.0685 1.0685 1.0685 Cr 51 4.5583 2 5283 6-9082 4.6183 2.41E5 Mn 54 5.1586 1.3786 1.4486 4.3286 Fe 59 2.048S 3.308S 1.658S 9.5S87 3.448S Co 5S 9.4186 2.SS87 5. 4987 Co 60 4.6487 1.378S 2.578S Zn 65 2.3SES 6.358S 3.95ES 4.00BS 1.128S Sr S9 2.658S 7.5786 1'. 0387 Sr 90 7.0189 1.7S89 9.4487 Zr 95 1.5186 3.3285 2.9585 4.7585 3.468S
    • Nb 95 2.4186 9.3S85 6.7185 S.S285 1.7489 Mo 99 5.4284 1.3484 1.1685 4.4S84 I 131 S.2786 S.3286 4.7387 2.7589 1.3787 7.4085 I 133 2.S78-1 3.558-1 1.34E-l 6.608-1 5.928-1 1.43E-l Cs 134 6.098S 1.0089 2.118S 3.108S 1.118S 5.3986 Cs 137 S.9988 S.608S 1.278S 2.SOBS 1.018S 5.39E6 Ba 140 2.2087 1.9384 1.2S86 6.2783 1.1584 1.1187
    • La 140 1.6782 -

5.S481 1.9781 1.6386 Ce 141 1.1784 . 5.S283 S.6482 2.5583 7.26E6 Ce 144 1.4S86 4.65E5 7.9184 2.5785 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 R VALUES~WMBAT ZEEN 2

m -mrem/y + yCi/sec NUCLIDB HONE LZVBR T BODY TBYROZD KZDBBY LUNG GI-LLI

<<H 3 1.9482 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 2.9383 1.6283 6.3982 4.1683 4.9085 Mn 54 4.5086 8.9385 1.3486 9.2486 Pe 59 1.1588 2.6988 1.0488 8.4787 6.3688 Co 5B 8.0586 1.8687 1.1188 Co 60 3.9087 8.8087 5.09E8 Zn 65 1.5988 5 5288 2.5788 3.5388 2.3488 Sr 89 1.4088 4.0186 1.6787 Sr 90 5.4289 1.3489 1.5288 Zr 95 '8.5085 2.6885 1.8485 3.9485 6. 1988
    • Nb 95 1.4086 7;7485 4.2685 7.5185 3.3189 Mo 99 3.9084 7.4383 8.9284 6.9884 I'31 4.4686 6.2486 3.35H6 1.82H9 1.0787 1.2386 I 133 1.558-1 2.628-1 8.008-2 3.6681 4.608-1 1.998-1 Cs 134 3.4688 8.1388 3 7788 2.5888 9.8787 1.0187 Cs 137 4.8888 6.4988'.2688 2.2188 8.5887 9.2486 Ba 140 1.1987 1.4684 7.6885 4.9583 9.8183 1.8487
    • La 140 9.1281 4.4881 1.1981 2.5786 Ce 141 6.1983 4.1483 4.7582 1. 9583 1.1887 Ce 144 7.8785 3.2685 4-2384 1.9485 1.98ES
  • mrem/yr per yci/m3.
    • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

October 1985

TABLE 3 18 R

i 2VALUES~WMBAT-ADULT m -mrem/yr + pci/sec NUCLIDE BONE 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 3.6583 2.1883 8.0382 4.8483 9.1785 Mn 54 5.9086 1.1386 1.7686 1.8187 Pe 59 1.44E8 3.3988 1.3088 9.46S7 1.1389 Co 58 1.0487 2.3487 2.1288 Co 60 5.0387 1.1188 9.4588 Zn 65 2.2688 7.1988 3.2588 4.8188 4.53E8 Sr 89 1.6688 4.7686 2.6687 Sr 90 8.3889 2.0689 2.4288 Zr 95 1.0686 3.4085 2.3085 5.3485 1.0889
    • Nb 95 1.7986 9.9485 5.3585 9.83E5 6.0489 Mo 99 4.7184 8.97E3 1.0785 1.0985 I 131 5.3786 7.6786 4.4086 2.5289 1.3287 2.0286 I 133 1.858-1 3.228-1 9.818-2 4.73Sl 5.618-1 2.898-1 Cs 134 4.3588 1.03S9 8.4588 3.3588 1.1188 1.8187 Cs 137 5.8888 8.0488 5.2688 2.7388 9.0787 1.5687 Ba 140 1.4487 1.8184 9.4485 6.1583 1.0484 2.9787
    • La 140 1.1182 5.5981 1.4881 4.10E6 Ce 141 7.3883 4.9983 5.6682 2.3283 1.9187 Ce 144 9.3385 3.9085 5.0184 2.3185 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

i VALUES-VBGETATION~ILD 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 Mn 54 6.6588 1.7788 1.8688 5.5888 Pe 59 3.9788 6.4288 3.2088 1.86E8 6.6988 Co 58 6.45E7 1.9788 3.7688 Co 60 3.7888 1.1289 2.1089 Zn 65 8.1288 2.1689 1.3589 1.3689 3.8088 Sr 89 3.59810 1.0389 1.3989 Sr 90 1.24812 3.15811 1.67810 Zr 95 3.8686 8.5085 7.5685 1.2286 8.8688

+*Nb 95 7.5085 2.. 92E5 2.0985. 2.7485 5.4088 Mo 99 7.7086 1.9186 1.6587 6.37E6 I 131 1.4388 1.4488 8.1687 4.75810 2.3688 1.2887 I 133 3 5286 4.3586 1.6586 8;0888 7.2586 1.7586 Cs 134 1.60810 2.63810 5.5589 8.1589 2.9389 1.4288 Cs 137 2;39810 2.29810 3.3889 7.4689 2.6889 1.4388 Ba 140 2.7788 2.4385 1.6287 7.9084 1.4585 1.4088

"*La 140 3.3784 1.1884 3.9783 3.2888 Ce 141 6.5685 3.2785 4.8584 1.4385 4.0888 Ce 144 1.2788. 3.9887 6.7886 2.2187 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 R

i VALUES-VEGETATXON 2

ZEEN m -mrem/yr + yc1/sec NUCLIDE BONE T. BODY TNYBOZD KZDNBY LUNG DZ-ZLZ

<<H 3. 2.5983 2.5983 2.5983 2.5983 2.5983 2.5983

  • C 14 1.4586 2.9185 2.9185 2.9185 2. 9185 2.9185 2 91ES Cr 51 6.1684 -3.4284 1.3584 8.7984 1.0387 Mn 54 4.5488 9.0187 1.3688 9.3288 Pe 59 1.7988 4.1888 1.6188 1.3288 9.8988 Co 58 4.3787 1.0188 6.0288 Co 60 2.4988 5.6088 3.2489 Zn 65 4.2488 1.4789 6.86E8 9.4188 6.2388 Sr 89 1.51810 4.3388 1.8089 Sr 90 7.51811 1.85811 2.11810 Zr 95 1.7286 5.4485 3.7485 7.9985 1.2689
    • Nb 95 3.4485 1.91E5 1.0585 1.8585 8.1688 Mo 99 5.6486 1.0886 1.2987 1.0187 I 131 7.6887 1.0788 5.78E7 3.14810 1.8588 2.1387 I 133 1.9386 3.2786 9.9885 4.5788 5.7486 2.4886 Cs 134 '7.1089 1.67810 7.7589 5.3189 2.0389 2.0888 Cs 137 1.01810 1.35810 4-6989 4.5989 1.7889 1.9288 Ba 140 1.3888 '1.6985 8.91E6 5.7484 1.1485 2.1388
    • La 140 1.6984 8.3283 2. 21E3 4.7888 Ce 141 2.8385 1.8985 2.1784 8.8984 5.4088 Ce 144 5.2787 2.1887 2 8386 1.3087 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

i VALUES-VEGETATION-ADULT 2

m -mrem/yr + yci/sec T. BODY TNYBOID KIDNBY LUNG GI-LLI

  • H 3 2.2683 2.2683 2.2683- 2.2683 2.2683 2.2683
  • C 14 8;97H5 1.7985 1.7985 1.7985 1.79H5 1.7985 1.7985 Cr. 51 4.6484 2.7784 1.0284 6.1584 1.1787 Mn 54 3.1387 5.9787 9.3187 9.5888 Pe. 59 1.2688 2.9688 1 1388 8.2787 1.0289

.Co 58 3.0887 6.90H7 6.2488 Co 60 1.6788 3 6988 3.1489 Zn 65'.1788 1.0189 4.568S 6.7588 6.3688 Sr 89 9.9586 2.8688 1.6089 Sr 90 6.05811 1.48811 1.75810 Zr 95 1.1886 3.7785 2.5585 5.9285 1.2089

    • Nb 95 2.4185 1.34E5 7.2084 1.3285 8.1388 Mo 99 6.14E6 1.1786 1.3987 1.4287 I 131'.0787 1.1588 6.6187 3.78810 1.9888 3.0587 I 133 2.0886 3.6186 1.1086 5.3188 6.3086 3.2586 Cs 134 4.6789 1.11810 9.0889 3.5989 1.1989 1.9488 Cs 137 6.3689'.7089 5.70H9 2.9589 9.8188 1.6888 Ba 140 1.2988 1.6185 8.4286 5.4984 9.2584 2.65ES
    • La 140 1.5884 7.93E3 2.1183 5.8688 Ce 141 1.9785 1.3385 1.5184 6.1984 5.0988 Ce 144 '.2987 1.3887 1.7786 8.1686 1.11810
  • mrem/yr'er pci/m3
    • Daughter Decay Product. Activity level and effective half life assumed to equal parent nuclide.

October 1985

TMLE 3-22 DISPERSION PMl&ETERS AT CONTROLLING LOCATIONS>>

Wv and W VALUES DIRECTION >~/m-2g Inhalation and Ground li842 1.42E-7 2.90E-9 Plane Cow Milk 2, 417 5.44E-S 9.52E-10 Meat Animal 1,842 1.42E-7 2.58E-9 Vegetation '2,072 1.29E-7 2.21E-9 STACK Inhalation and Ground 1,711 8.50$ -9 1.33E-9 Plane Cow Milk ESE 2,366 8.84E-9 5.888-10 Meat Animal E ',711 1.36E-9 Vegetation E 1.940 1.07E-8 1.24B-9 NOTE: 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 radiation exposures to all real individuals from all uranium 'hat 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:

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.

2) 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 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.

Ra, 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

hl 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 dosirneters, only the one detection capabil1ties for thermoluminescent 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

"~

'I ~

ll

Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1,.

Type of *Map Sam le Location Collection Site Location Radioiodine and Nine- Mile Point Road 1.8 mi 6 88 E Particulates (air) north Radioiodine and Co. Rt. 29 & Lake Road 1.1 mi 6 104'SE Particulates (air)

Radioiodine and Co. Rt. 29 1.5 mi 6 132 SE Particulates (air)

.Radioiodine and Village of Lycoming, NY 1.8 mi 6 143 SE Particulates (air)

Radioiodine and Montario Point Road 16.4 mi 6 42'E Particulates (air) 0.1 mi 6 5' L

Direct Radiation (TLD) North Shoreline Area Direct Radiation (TLD) 7 North Shoreline Area O.l mi 6 25 NNE Direct Radiation (TLD) 8 North Shoreline Area 0.2 mi 6-45'E Direct Radiation (TLD) 9 North Shoreline Area 0.8 mi 6 70'NE Direct Radiation (TLD) 10 JAF east boundary 1.0 mi 6 90 E Direct Radiation (TLD) ll Rt. 29 1.1 mi 9 115'SE Direct Radiation (TLD) 12 Rt. 29 1.4 mi 9 1334 SE Direct Radiation (TLD) 13 Miner Road 1.6 mi 6 159 SSE Direct Radiation (TLD) Miner Road 1.6 mi 6 181 S Direct Radiation (TLD) 15 Lakeview Road 1.2 mi 9 200 SSW Direct Radiation (TLD) 16 Lakeview Road 1.1 mi 6 225'W Direct Radiation (TLD) 17 Site Meteorological Tower 0.7 mi 9 250'SW Direct Radiation (TLD) 18 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

  • Map Sam le Location Collection Site Location Direct Radiation (TLD) 19 North Shoreline 0.2 mi 9 294'NW Direct Radiation (TLD) 20 North Shoreline O.l mi 9 315'W Direct Radiation (TLD) 21 North Shoreline 0.1 mi 9 341 NNW Direct Radiation (TLD) 22 Demster Beach Road 4.8 mi 9 97' Direct Radiation (TLD) 23 Leavitt Road 4.1 mi 8 ill'SE Direct Radiation (TLD) 24 Rt. 104 4.2 mi 9 135'E Direct Radiation (TLD) 25 Rt. 51A 4.8 mi 9 156'SE I

Direct Radiation (TLD) 26 Maiden Lane Road 4.4 mi 9 183 S Direct Radiation (TLD) 27 Co. Rt. 53 4.4 mi 9 205'SW Direct Radiation (TLD) 28 Co. Rt. 1 4.7 mi 9 223 SW Direct Radiation (TLD) 29 Lake Shoreline 4.1 mi 9 237'SW Direct Radiation (TLD) 30 Phoenix, NY Control 19.8 mi 9 170 S-SSE Direct Radiation (TLD) 31 S.W. Oswego, Control 12.6 mi 9 226'W Direct Radiation (TLD) 32 Scriba, NY 3.6 mi 9 199 SSW Direct Radiation (TLD) 33 Alcan Aluminum, Rt. 1A 3.1 mi 9 220 SW Direct Radiation (TLD) 34 Lycoming, NY 1.8 mi 9 1434 SE Direct Radiation (TLD) 35 New Haven, NY 5.3 mi 9 123'SE Direct Radiation (TLD) 36 W. Boundary, Bible Camp 0.9 mi 9 237'W-WSW N

Direct Radiation (TLD) 37 Lake Road 1.2 mi 9 101'-ESE Surface Water 38 OSS Inlet Canal 7.6 mi 9 235 SW-WSW Surface. Water 39 JAFNPP Inlet Canal 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 *Map S le Location Collection Site Location Shoreline sediment 40 Sunset Bay Shoreline 1.5 mi 9 80' Fish 41 NMP Site Discharge Area 0.3 mi 9 3154 NW and/or Fish NMP Site Discharge Area 0.6 mi 9 55 NE Fish Oswego Harbor Area 6.2 mi 9 235'SW Milk Milk Location 050 9.3 mi 9 93 SE Milk Milk Location $7 5.5 mi 9 107'SE Milk Milk Location $ 16 5.9 mi 9 190' Milk Milk Location 840 15.0 mi 9 223 SW Food Product Produce Location Sl"" 1.3 mi 9 98 E (O'onnor)

Food Product 49 Produce Location 02*" 1.8 mi 9 96 ESE (J. Parkhurst)

Food Product 50 Produce Location $ 3"* 1.9 mi 9 101 ESE (Fox)

Food Product 51 Produce Location 84"* 1.5 mi 9 114 SW (C. Parkhurst)

Food Product 52 Produce Location $ 5**

(C. R. Parkhurst) 2.1 mi 9 ill S Food Product 53 Produce Location I6** 2.2 mi 9 123 SE (J. Lawton)

Food Product 54 Produce Location 07** 15.0 mi 9 223 ESE (Mc Millen)

Food Product Produce Location $ 8*" 12.6 mi 9 225'W (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.

October 1985

APPENDIX, A DISPERSION CALCULATION TABLES I

October 1985

Appendix A Page 1 of 6 ANNUAL X/Q (Stack Release)

HHP UH1 T ~ 2 STACK HO DECAY, UHDEPLE'TED CORRECTED FOR OPEN TERRAIN RECIRCULATION ANNUAL AVKRACE CHI/O (SKC/HETER CURED) DISTANCE IH NILES SECTOR .500 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500 5.000 5.504 8 6.850E-07 1.624E-07 6.539E-OB 3.698E-OS 2.490E 08 1.85IE-OB 1.471E-OB I .21'/K-08 1.037E-OB 9.035E-09 8.008E-09 SSH SH 7.642E 07 1.840E-07 /.362E-08 6.'370K-07 1.530K-07 6. 116K 08 I. 145E-08 3.487E-OB 2.782E-OS 2.065E-OB 2.379E 08'794E-08 1.632K-OB

1. 438E-08 1.346E-OB 1. 142E-08 9.920E-09 1 . 198K-08 1.026E-OB 8.964K-09 8.762E-09 7.956E-09 NSM 3.482E-07 8 418E-08 3.366K-OS 1.92/E-08 f .330E-08 .021E-08 8.346K-09 7.097E-09 6.196E-09 5.515E-09 4.978E-09 N 4.496E 07 1.068E-07 4.270E-OS 2.446E-OB 1. 686E-08 . 291E-08 1.052E-OB 8.917E-09 7.764E-09 6.892E-09 6.204E-09 NHN 6.9/3E-47 f.670E-07 6.625E-OS 3. 751E 08 Z. SIZE-08 . 907E-08 1.521E-OB 1.264E-OB 1.080K-OB 9.422E-09 8 353E-.09 HN .805E 06 4.289E-07 1. 661E-07 9.f23E-OB 6.004E 08 4.390E-OB '3.430E-OB 2.802E-OB 2.362E-OB 2.038E-OB 790E-08 HHH 1.783E-06 4.233E-07 1.640E-07 8.970E-OS 5.872E-OB 4.274E-oa 3.328E-OB 2. /12E-08 2.2S3E-OS 1.968E-OB 1.728E-OB H 1.833E-06 4.375E-07 1.705E-07 9.422E 08 6.239E-OB 4.589K-OB 3.606E-08 2.960E-OB 2. 507E-08 2. 172E-08 I . 915E-08 HtlE .055E-06 2.S11E-07 9.816E-OS 5.479E 08 3.673E 08 2.736E-OB 2. 174E-08 1,803K-OB 1.540E-OB 1.344E-OB 1. 193E-08 HE 1.230E 06 2.903E-07 1. 121E 07 e'. s3E-oa 4. 051E-08 2.968E-OB 2.326E-OB 1.90/E-08 1.614E-OB 1.399E-OB 1.234E-OB EHE 2. 139E" 06 5.088E-07 1.968E-07 79E-07 7.076E 08 5. 147E-08 3.9'98E-08 3,247E-OB 2./22E-08 2.337K-OB 2. 044E-08 E 2.289K-06 5.472E-07 2.128E-07 69E-07 7.672E 08 5.584E-OB 4.339E-OB 3.524E 08 .954K-OB 2.536E-OB .:218K-oa ESF. l. i56E-06 9.578E-07 2.980K-O>

2.268E-07 1.160E-07

8. 941E-08 6.388K-OB 4.98tE 08 4.203E-OB 3.064E-OB 3.306E"08 2.425E-OB 2.382E-OB 1.895E-OB 1.935K-OB 1.621E-OB 1.391E-OB 1. 215E-08 1.298E-OB 1.116E-OB 9.777K-09 CE 1.54SE 08 SSE 5.118K 07 1.38BE-07 5.566E-OB 3.152K-OB 2.130E 08 1.592E-OS 1.267E-OB I . 051K-08 8.967E-09 7.826E-09 6.944E-09 AIIHUAL AUERACE CNT/O (SEC/tlETER CUBED) DISTAtlCE IH NILES DEAR IIIG e.ooo ( .soo 7.000 7.544 8.400 8.504 9.004 9.500 10.000 15.004 20.000 SSM 8 7.18SE>>O9 6.551E-09 7.838E-09 7. 120E-09 6.059E-09 6'.sesE-o9
5. 631E-09 S.ZS6E-09 4.923E-09 6.083E-09 S.662E-09 5.289E-09 I.627E-09 4.958E-09 4.361E-09 4.661K-09 I. 122E-09 1.395E-09
2. 743E-.09 2.865E-09 2.037K-09 2.094E-09 Sll 7.147E 09 6.513E-09 6.0ZiZE-09 5.593E-O'9 5.216E-09 I.aatE-09 I.SS3E-09 4.315E-09 4.473E-09 2.679E-09 1.969E-09 NSN 4.541E-OO 4.197E-09 3.932K-09 3.695E 09 3.484E-09 3.2'94K-09 3. 122E-09 2.965E-09 2.822K-09 1.96BE-09 1.498E-09 M 5.616K-09 5.208E-09 4.869K-09 4.569K-09 4.302E 09 4.061E-09 3. 844K-09 3.647E-09 3.468E-09 2.402E-09 1.821E-09 NHN 7.496E-09 6 829E-09 6.312K-09 5.862K-09 S.I67E-09 5. 117K-09 4.804E 09 4.525E-O'9 4.273E-09 2.817E-09 2.074E-09 t!H 1.594E-OB 1. 443E-08 1.327E-OB 1,226E-OS 1. 139K-OS 1. 062E-08 9.946E-09 9. 340E-09 8.798K-09 5.707E 09 4. 158K-09 lltln 1.539E-OS 1.393K-OB 1. 281K-08 1.184K- 8 1. 100E-08 1.027E-OB 9.614E-, 09 9.033E-09 8.513E-09 5.552E-O'9 4.067E-09 H 1. 711K-08 1.5'54E-08 1.432K-OB 1.327K- 8 1.236K-OB 1. 155E-08 f.083K-OB 1. 019E-08 9. 613K-09 6. 3 1OE-49 4. 634K-01 HHE .0/ZE-08 9.777E"09 9.052E 09 8. 421E- 9 7.86/E-09 7.375E-09 6.93iE-09 6 544E 09 6.189E-09 4.130E-09 3. 061K-49 ttE 1:104K-OB :oo4E-oa 9.270K-09 . 60'/E 9 8.02BE-09 7.519E- 9 7.067E-09 6.664E-09 6.301E-09 4.224E-09 3. 156E-09 KtlF. 1.814E 08 .637 -08 1 500E-08 .383E- 8 .282E-08 1.1'93E- 8 1. 115K-08 l.046E 08 9.838E-09 6,341E-09 4. 618E-09 E 967E-08 .774 -08 1.625K-OS .497K- 8 .386E-08 1.289E- 8 1.203E-OB 1. 127E-08 1.059E-OS 6.75BE-09 4.844E-09 ESE 1.077K-48 9.701 -09 8.87BE-09 171K 9 7.558E 09 7.022E- 9 6.549E-09 6.130E-09 5.755E-09 3.651E 09 2.632E-09 S. 681E-09 7.831K-09 7.176K-09 6. 122E-09 5.692E-09 5. 313E-09 I 976K-0'9 4.67'5E-09 2.979E-09 2. 156E-09 I..612E-0'9 SE SSE 6.238E-09 S.68BE-09 5.262K-09 891K-09 I.S65E-O'9 4.276E-09 4.018E-09 3,786E-O'9 3.577E-09 2.370E-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 ltlttllt tti CORRECTED FOR OPEH TERRA IH RECIRCULATION DIRECTION

~ ~ tlttttSI RELATIVE DEPOSITION PER UNIT AREA INSS "2)

DISTANCES IN NILES AT FIXED POINTS BY DOHtIHIND SECTORS t t a t t It It It IIII It t t I FROtt SITE .50 1.00 f.50 2.00 2 .50 3. 0 0 3.5 0 00 4.50 5. 00 S. 50 8 1. 312E-08 3 95iE-09 1.495E-09 7.832E-ID 4.806K-10 "3.241E-io 2.340E-10 1,765E-SO I. 378E-1 0 1 . 106E-1 0 9.070E-11 SSH 1.555E-OB 4.447K,-OV 1. 696E-09 8. 915E-10 5.482E-10 3.708E"10 2.672E-IO 2.015E-SO 1.573K-fo 1. 261E 10 1.033K-10 SH .020K-08 2.993K-09 1.1/7E-09 6.305 10 3.926E-10,2.677E-S0 1.938F-IO S.466K-S0 1 145K- 0 9.f73E-SS 7.504E-ii 9.597t-io 3.899E- 0 .353E-

  • 9.320K-tf 6.79bt-l 1 S.tbit-if 4.043E-if 3.245E"lf 2.656E-SI

~

3.054K OV 2.139K 10 HSH NNH H 3.311E-D9 7.745K O'9

.054F.-09 4.347K- 0 2.327K-09 9.36SE-SD 2.404 10 5.08b -10

.529E- ,f.056F-10 7.717K-ll S.BGSF

3. 196K-I I 2. 91t 10 1.592E-S li 4.595E-ii 3.687K fi 3.016K-SI 1.206E.-fo 9.428E- 7.554E-11 6.176E-if NH 2.430E-OB 6.675E-09 2.55DE-09 1.334 09 8. 176E- ;5.5ifE-10 3.960E-1 2.977E-10 2. 317E-i 0 1.852E 10 1.513E-IO NNII 2.379E-OB 6 472K-09 2.438E- 9 1.265E-09 7;700E- 0 5. 70E-10 3.705E-S 2.783E-SD 2.i65E 0 1. 731E- 0 1. 415E-i 0 N 2.263F DB 6 386F-D9 2.458F-D9 1.297K 0'9 1.9BBF- 0 5.406F-SO 3.896K-S 2 936F-10 2.289E-SO 1.832E- 0 1.498E-SO tl tlF 9.6YVE OV 2 838t'-0'9 518K-09 S.13St-OV 6. 091E 10 1.294E-IO 3.8f2t-fo 2.605E 10 1.'BBBF-I 1.42/t-10 I.tf4E-IO 8.920E-ll 7.288E"11 4.487K-f0-3.031K lo 2. 179K f 1.639E-SD 1.274E-io 1.017K- 0 B.ZVBE-ll tlE 1.312K 08 3 1. 385E-09 EIIE 3.VIDE 08 060E-08 4.024E 09 Z.OVSE D9 .27VE 9 8.598E-10 6. f66E-I 4.630E-IO 3.600E-SO 2.876E- 0 2.349E-SO E 5.322E-OB 4P2E-08 5.357E-09 2.77ZE-09 .685E-09 1. 129E-Ov 8.079E 0 6. OSBF.-10 4.706F. 10 3.757E 10 3.068E to ESE 3.4/fE 08 9 242K-09

~ 3.473E-09 I . 793E-09 .OBBE 09 7.286E-10.5.21OE-IO 3.905E-10 3.033E-SO 2. 421E-10 1.977E-SO SE 2.708K-OB 7. 401K-09 2.7'94E-09 1.452E-09 8'.BSOE-io 5'.948K-10'4.'266E-10 3.205K-1O 2.494E-10 1. 994E-10 1.631E-10 SSE 1.3SZE-DB 3.870E-09 1.467E-09 7.688E-ID 4.118E 10 3 187K f0 2 VGE 10 1 731E 10 1. 351E-i 0 1. 08 IE-10 8.883E-II DIRECTION DISTANCKS IN NILES FRON SITE 6.44 6.50 7:00 1.50 8 04 B.SO 9.00 9.50 10.00 15. 00 20.00 S 7.572K- 6.515K-tt 5.752K-I 5.120E- 4.5'9 E-I 4. t41E-I 3.758E- 3.42/E-11 3.140E-1 1.642E-f 1.026E-ii SSH 8.612E- 7. 401K- f 1 6.537E-I 5.817K-I 5.21 E-I 4.703K- 4.266E 3.88'9E"ff 3.56iE- 1. 854E-1 l.i54E-II SH 6.245E-I 5.390E-i 4.755K-f 4.231K-I 3.79 E-I 3. 411K-I 3.098E" 2.823E-tt 2.584E-S i.339K-1 8.3D2E-SZ H 5 II 2.210K- f.920E- .694K-I 1.507E- .3S E- 1.218E- .104E" i.006E-11 9.215E- 4.790E-1 2. 981E-IZ H 2.50BE- 2. 18iK-1 .V24E-i 1.711K- .533E- 1.382E- .253E- 1. f 42E-ll 1.045E- 5. 420E-1 3.366E-SZ 4.443K- 3.920K-i 2.814C- 2.55SE- 2.324E-if 2.S27K- 1.099K"i 6.803E-IZ HNH NH tlntl N

5. 134K

.259E

. 17BE-

.247K-

1. 078E-001K-

'1.072K-9.511E-I

$ .886E-1 9.455E 3.4BGE-8.458E-

'1.904K

.410K-

3. 122E-1.575E 1.080E 1.534K-6.827E-6.382K-6.792C-6.187 5.785E-
6. 157E-5.634K"11
5. 270K" 11 5.610K-I
5. 155E-4.82ZE-
5. 134E-2.653E-1
2. 480K-1 2.654K-1.635E-i 1.536E-I

.643E-1 tl tlE 6.056E 5.229C- 4.612E-I . 101K- .673E- 3. 31OE- 3.000E- 2.732E-tl 2.50OE I . 28BE-1 1.95ZE- 2 ENE NE 6.889E

.953E-

5. VOIK-1.670E-5.204E-1.473E-

~ .626E-

.3IOE-j: 4fE 73E-3.730E-t . 051K 3.378K-9.580E-3.0'15E-1 8.724K-f

2. 812E-7.980E-I 437E-1
4. 100E-1 8.802E-12 2.522E-it S

E 2.55fK- 2. 116K- 1.920K-i i.707E- .529C- 1. 317E- 1.24OC- I . 136E-10 1.039K" 5. 331E-1 3.275E-II ESE .644E- -'1 . 40ZK- f.237E- .SOOK- 9. 84'1E 8.873E- 8.039E- 7.320E-11 6.6'95E- 3.435K-S 2.110E-I 1 SE .357E- 162K- .025E- 9.116E- . 166E- 7 36fK-

~ 6'.613E- 6.079E-11 5.563E 11 2.872E- 1.774E-i I SSC 1 .4t2E 6. 314E-1 5.'626E-I 5. 001E 4.489E- 4.049K- 3. 614E-f 3,350E-1 I 3.068E-ff S.GDSE-S 9.'VBBE-t2

Appendix A Page 3 of 6 GRA7ING SEASON D/Q (Stack Release)

IIHP UHI I 02 STACK CORRECTED FOR OPEH TERRAIN RECIRCULATIOH tttetttte t DIRECTION

~ tet ~ ttetei RELATIVE DEPOSITION PER UHIT AREA IHet-2) AT FIXED POINTS BT DONHNIHD SECTORS 'tet ~ tttttete ~ eeeetee FPOH SI TE DISTAtlCES IN HILKS

.50 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50 5.00 5.50 5 f.395E-OB 3.988E-09 1. 195E-09 7.789E 10 4. 761E 1 0 3. 209E-10 2.308E-LO 1.740E-LO 1.359E-SO 1.090E-LO 8 915E-11 5 5 II 1.346E-OB 3,901E-09 1.488E-09 7.836E- 0 4.825E- 0 3.268E-I 2.358E-SO 1./BOE-10 1.390E-SO 1. 115E-10 9. 142E-1 I

8. 131E-09 2.43BE-09 9.605E-LO 1618-10 3. 221K-I 0.2.203E-L 2.393E-09 7.609E-IO 3.095E-IO 5.

SIT .598E-10 1 . 210E-10 9.461E-IL NSN 7.589E 11 6.214E-LL II 2.629E-09 8. 473E-10 3. Sl LE-10 1.701E 1.948E- 0 10 1.077E- 0 7.430E-L 5.422K-II 4. 120E-11 3.229K-LL 2.593E-LL 2,123E-ll lltlll 6.933E-09 2.083K-09 8. 342K-I 0 .1.522K-IO 1.24fE 1 0 8.59LE-L b. 281E-I I 4.77/E-11 3.744E 1 I 3.00SE-LL 2. 159E-I 1

2. 316E-08 6.492E-09 2. 18'PE-09 .306E 09 2.838E- 0 I .'945E-I 1.413K-I 0 1. 070E-10 8.364E-IL 6. 701E-11 5.482E-11 NIT B.OIBE- 0 5.413E-L 3.893E-IO 2.929E-LO 2. 281E-10 1. 824E-10 1.490E-LO NWII 2.389E-OB 6.549E 09 2.470E-09 .283E-09 7.823E- 0 5.258E-I 3.772E-IO 2.834K-LO 2. 206E-I 0 1. 765E-10 1.413K-SO II 2. 156E-08 6.939E-09 2.668E-O'9 .406E-09 8.660E- 0 5.861E-I 1.223E-I 3. 183E-10 2. 482E-10 1. 987E-10 1.625K-IO NNE 9.594E-09 2.816E-09 1. 122E-09 6.049E- 0 3.783E-I 0 2.585K-Ie I . 871E 1.117E-IO . 107E-10 8.860E-11 7. 241E-11 NE 1. 103E-08 3.067E-09 1. 199E-09 6.363E 0 3.935E-I 0 2.668K-Lv 1.923E- 1. 419E-10 . 128E-10 9.012E-IL 7.353E-11 ENE 3.959E-OB 1.092E-OB 4. 178E-09 2.190K- 9 1.343E-O 9 9.061K-LO 6.513E- 4.899E-IO 3. 811E-10 3. 019E-1 0 2. 491E-10 E 4.979E-OB 1.35fE-OB 5. 121E-09 2.664E-09 1.625E-09 1 .092E-09 7.833E- 5.883E-IO 4. 575E-10 3.656E-SO 2.987E-LO ESE 2.842E-OB 7.668E-09 2.890E-09 1.498E 09 9.114K-IO 6.115E- 0 4.380E- 3.287E-IO 2.555E-IO 2.042E-LO 1.668E-IO SE 2.383E-OB 6.533E-09 2.151E-09 1.270E 09 7.728E-IO 5.188E- 0 3.719E- 2,795E-LO 2. 175E-10 1.741E-IO 1.424E-IO SSE 1.376E-OB 3.879E-09 1. 451E-09 /.533E 10 1. 593E-10 3. 090E- 0 2. 220E- 1. 67 LE-10 1.304E-LO 1 . 046E-10 8.572E,-LI IOH I'IRECT DISTANCES IN HILES FROH SITE 6 .00 6.50 7 .00 7 .50 B.OO B.SO 9.00 9.50 lo. 00 15.00 20.00 SSN 5 7.173K-I 6.422E-II 5.670E-II 5.018E 7.629K- L 6.570E-II 5.799E-11 5.161E-IL fl 4. 526E-I I 4.085E 4.627E-I 4. L71E-1 3.707E-II 3.381E- I 3.787E 1 3.454E- 3.

098E- I 1.623E-L I 1.016E-LI 164E- .652E-11 1.032E-11 SW 5 I /7E- 4. 476E-1 I 3.950E-I I 3.515E-I 3.150K-I 2.841E-I I 2.576E I 2.348E- 2. 151E- 1. 119K-I I 6.'964E-12 II5 II 768E 045E-

.537E"I I .356E-I .206E"f I. 08 E-I 9.750E-I 2 8.843E-I 2 8.061E-12 7.382E- 3.844E-12 2.396E-12 N

1.559E-

.779E- 1. 570E-I I 1.396E-I

3. 915E" j 3.481E-f I 3.096K-I 1.25 E-I 2.500K"S 1.128K-L I .023E-1 9.320E" 2 8.533E- 4.128E-12 2.752E-12 NHN f.239E-I .063E-I 0 9. 376E- I 8.338E-I I 2.266E-f I 2.065E- 1.890E- 9.781E-12 6. 061E-12 till 7.46 E-I 6.731E-I I 6. OOE-I I 5.556E-II 5. 081E-I 2. 619K I NtlH tl f.202E-L.353E-

.028E I 0 9.075E"I I 8.073E I

. 163E 0 1.026E-I 0 9.125E

7. 232E-I 6.520E-L I
8. 175E-I 7.370E I I 5.911E-I I 6.682E I 5.385E-II 4.92'9E-6 OBBE-11 5.573E"I 2.547E 2.883E" I ll 1.6LSE-11 1.575E-II 1.785E-IL IIIIE 6. OIBE 5.197E- I 4.584K-I 1. 076E 3. 651E-I 3. 2'9 IE-I 1 2.982E 2.716E- I 2.486E-L 1.282E- I 7. 918K-12 tlE 6. 105E- 5.243E-I 4.623E-I 1.110E-I 3.680K-I 3.315E-I I 3.003E-I I 2.731K- 1 2.500E-I 1.280E I /.856E-12 EHE 2.072E- 1.776E- 0 1.567E-I 0 1.393E-S . 218E- I I . 125E-I 0 1.019K-f 0 9.284E"11 8.494E-I 4.374E-IL 2.696E-IL E 2.184E 2. 124E-I 0 1. 874E-I 0 1. 667K-1 I . 1'93E I 1 .345E-I 0 1.219E-I 0 1. I LOE-10 l. 016E-I 5. 224E-11 3. 217E-11 ESE 1.388K I .187E-I. 186K-I 0 1.046C- 0 9.302E" I
1. 015E-I 0 8.961K- I 7 . 973K-I 8.331K-I 7.5OBK-I I 6.804E-f I 6.197K-II 5.670E-I 2.917E- 1.797E-11 SE
7. 15BE-L 6.142E- 5.422E- I 4.827E-I
7. 114K-I 6.441E-I I 5.810E-I 5.322E-II 4.872E-I 2.523E- 1.563K-II SSE 4.327E-I 3;904E-I f 3512K I 3. 231E- L I 2.960E- 1. 547K-I I 9.657E"12

- 49- Oct 1985

L

)to PJ J

Appendix A Page 4 of 6 ANNUAL X/Q 7Vettt Release) ttHP UNIT IZ VEHT HO DECAY, UHDEPLETED CORRECTED FOR OPEtt TERRAIN R CIRCULATION AtIHU4L AVER4CE CHI/O I SKC/tIETER CUBED I DISTANCE IN NILES SECTOR .500 1.000 1.500 2.000 2.500 3.000 3.500 4.000 1. 500 5.000 5.500 5 2.677E-07 8.468E-OB 6.236E-OB 5.027E-OB 1.152E-OS 3.501E-OB 3.005E-OB 2.620E-OB 2. 314E-08 2.068E-OB 1.867E-OB SSH . IBOE-07 7.433K 08 6. 021K-08 5.028E-OS 1 20 c E - 08 3 .558K-08 3.054E-OB 2.658E-OB 2. 312E-08 2.087E-OB 1.878E-OB SH . 210E-07 7. 312E-08 6.914K-OB 6.161K-OB 5.327E-OS 1 599E-08 4.002E-OB 3.518E-OB 3. 123E-08 2.800E-OB 2. 53 lE-08 IISN 4.285E-OS 2. 513E-08 3.200K-OB 3.350K-OB 3. 187E-08 2 935E-08 2.677E-OB 2.439K-08 2.Z28E-OB 2.044K-OB 1.883E-OB H 1.883E-OB 3'.SSOE-OS 5. 176E-08 5.460K-OB S. 213E-08 4 815E-08 4. 105E-08 4.02/E-08 3.692E-OB 3.399E-OB 3. 144E-08 NHII .498K-0/ 1.010E"07 1.018E-07 9.343E 08 8.216E-OB 7 77E-08 6.302E-OB 5. 581E-08 <.989K-08 4,500E-OB 4.091E-OB HH 2 577E-07 1.488K-07 3J1E-0/ 1.218E 07 1 . 051E-0/ 9 01E-08 7. 926K -08 6.975F.-OB 6.202E-OB 5.569E"08 5.044K-OS HI III 1.926E-07 1 059E-07 9 773E-08 8.750K-OB 7.620K-OB 6 623E-08 5.797K-OB 5.123E-OB 4.57ZE-OB 1. 118E-08 3. 741E-08 H Z. 137E-07 1.394E-07 1.262E-07 1. 115E 07 9.62SE-OB 8 310 E-08 7.234E-OB 6-363E-08 5.656E-OB 5.076E-OB 4.595K-OB NIIE 1.084E 07 6.870E-OB 6.331E-OB 5.586E-OB 1;802E-08 127E-08 3.578E-OB 3.135E-OS 2.777E-OB 2.484E-OB 2.242E-OS IIE 1.577E-07 9.033E-OB 7.489K-OB 6.298E 08 5.274K-OS 156E-08 3.816E-OS 3.311E-OB 2.910K 08 2.585E-OB 2.3t9E-OB KtIE f 5. 815E-07

7. 166K -07 2.733E-07
3. 1?of-07 1.774E-07 1.842f-07 1.303K-07 1.008E-07 8 083K-OB e. 671E-o 8 5.63tf-oo 1.842E-OB 4.228E-OB 3.740E-OB 1.280E 07 9.601E-OB 7.567E-OB 6. 176K -08 5. 1/BE-08 4.132E-OB 3.860E-OB 3 409E-08 ESE 5.580E-07 2.336K-07 1.320t-07 8.895E 08 6.534E 08 5.07SE-OB 4. 100K-08 3.112K-OB 2. 901E-08 2. 518E-08 2.216E-OB SE 4.368E-07 1.939K-07 1. 165E-07 B. IOSE-OS 6.064E 08 1.764E-OS 3.879E-OS 3 246K-OB 2. 771E-08 2. 114K-OS 2. 130K-08 SSE 1./59E 07 7. 109E-08 4. 919E-08 3.862E-OS 3. 129E-08 2.603E-OS 2:213E-08 1.916K-OS 1.682K-OS 1.497E-OS I . 317E-08 ANIIUAL AVCRACK CIII/0 I SEC/tIETER CUBED) DIST4HCE IN tlILES BEARING 6.000 6.500 7.000 7.500 8.000 8.500 '9. 000 9.500 10.000 15.000 20.000 5 I:699K-08 1.5elE-os 1.458E-OS 1.363E- 8 1.278E-OS .202E-08 1. 132E" 08 1.0/OE-08 1. 013E-08 6. 713E-09 4.966K-09 SSN 1.703E-OB 1.563E-OB 1.452E-OB 1.353E 8 .265E-08 . 186E-08 1. 114E-08 1. 050K-08 9.908E-09 6.447E-09 4,663K-07 2.305E-OB 2 I?2K-OS 1.9/BE-08 .848E-

'H 8 1.732E-OS .627E-08 1.532E-OS 1.446E-OB 1'.3e7E-oS 9.001E-09 6 552K-0 r WSH 1.743K 08 1 627E-08 1.535E-OB 1.150E 8 .372E 08 .300E 08 1.234E-OS 1. 173K-08 1. 117E-08 7.'707K-09 5 770K-or H 2.920E 08 2.737E-OB 2.592E-OS 2.15SE 8 2. 331E-08 2.220E-OB 2.114E 08 2. 017K-OB 1.927E-OB 1.372E-OB 1.054K-OB IIIIII 3.746K-OS 3.468E-OS 3.249t-08 3.053t- 8 2.8/6E-08 r.716K-OB 2. 571E 08 2. 138E-08 2.3tBE-OB 1.599E-OB 1.2tof-ob IIH 1.604E-OB 1 251E-08 3.973E-OB 3.7"SE 08 3.502E-OB 3.302E-OB 3. 120E-08 2.956E-OB 2.806E-OB 1.92tE-OS 1.149E-OS NIIH 3.423K-OS 3. 167t-08 2.966E-OS 2.786E-OS 2. 621E-08 2.4/7K-08 2. 341K 08 2.223E-OB 2. 113E-08 1.458E-OB 1.104E-OB It 4.191E-OB 3 867E-08'3.612E-OS 3. 381F.-OB 3. 79E-08 2.995E-OB 2.828E-OB 2.676E-OB 2.S38E-OB 1 722E-08 1.287E-OB tnIE 2.038E-OB 1.875E-OB 1.747E-OS 1.632E 08 1.529E-OS 1.437K-OB 1.353E-OB 1.278E 08 1.209K-OS 8. 041E-09 5.9tbf-o>

ttE .09SE-08 i.'922E-08 1.783E-OB 1.660E 08 1.550E-OB 1.452E-OS 1.364E-OB 1 285E-08 1. 213E-08 7.923E-09 5.762E-O'9 K I IE 3.341K-OB 3.032E-OS 2./BBF.-OB 2.5/5E-08 2.389K-OB 2.224K-OS 2.078E-OB 1. 947f ~08 1.830E-OS 1.160E-OB 8. 311E-09 E 3.044E-OB 2.758E-OB 2.536'-CS 2. 312K 08 2. 173E-08 2.023E-OB 1. 891K-08 1. /72E-08 1.666K-OB 1.060E-OB 7.623E-09 ESE 1.973E-OB l.784E-OB 1.636K-OB 1.509E-OB 1.397E-OS 1.299K-OB 1.212E-OS 1.135K-OB t.066E-OB 6.732E-09 4.819E-09 SE 1.902K-OB 1.722E-OS 1.583E-OB 1.462E 08 1.356E"08 1.262E-OB 179E-08 1 105E-08 1.038E"08 6.605E-09 4.753E-09 SSE 1. 222K-08 1 . 122E-08 l . 011E-08 9.746E-09 9. 125E-09 8.567E-09 8.065E-09 / 6llf-09 7.199E-09 4.778K-09 3 5 I BE-0%

50- October 1985

tlnl'n e I CORRECTED FOR OPEH TERRAIN RECIRCuLnttOH eeeee ~ eeee e e I e e e I e I e e DIRECTION RELAT IVE DEPOS I TISH PER IINIT AREA IHee 2) ne r ewe.u DISTANCES 'IH HILES a i . .

~

FROtt SITE .50 1.00 1.50 2. 00 2.50 3.DO 3.50 4.00 4.50 5.04 5.50 8 $ .064E-DB 3.821K 09 f.462K 09 7.896K-fo 4.955E-to 3.4LDE-lo 2.495E-LO 1,948K-10 $ .507E-L 1.222E-io 1. 011E-$ 0 SSH 4.843E-09 2.042E-09 8.856K-fo S.itZiE to 3.338E-to 2.35lf-fo 1.741K-lo 1.338E-LD 1.457E-f 8.542E-L 7.030E-11 SM 3.537f-09 i.737E-09 8.060K 10 4.798F-L 3. iBBE-f0 2. 266E<<to 1. 687F.-I 0 1.299K 1D 1.026E-L 8.284E I 6.804E-. 11 HSH I.iiOE-09 5.689E-iO 2.657E-ID 1.'596K- 1.067K-LO 7.6iZE-LL S.68Of-ii 4.380E 11 3.465K-L 2.798E 2.299K-LL H 1.26'7E-D9 7 594E"10 3.8$ 7E 10 2. 366K" 1 1.608E-LO L.isSE 10 8.678F.- 6.704E-1$ 5.3D3E 4.27BE-L 3.507K-11 HNN 3.204K-09 1 603K 09 7.684K $ 0 4.62$ E 3.086K-io 2.LPVE 0 L.6386-10 1.261K-lo P. 952E-I 8. 020K i 6.574K-fl Nlt NIIH 6.029K-OP 2.463E-49 1.084K-09 4.943K-09 1.982K-09 8.5 3E-lo 6.231K 1 4.054K 10 2.846K 0 2. 42E- 0 4.847E-I 3. 137E 1 D 2. 196E I 0 L.620K- 0 610E-10 1 241K- I 4

l. 269E 9.784E-I 1 D23E I

~

7.896E-L 8.40$ E-ll 6.493K 11 tt 6. 201K-09 2.502E-09 1.097E-09 6.299E-L 4.096E 10 2.874K I 0 2. 22E- 0 1. 6ibf -10 1.281E-L I 033E-1 8. 481K 11 HNE NE 2.232E-09 1.057E"09 5.0 5E-Io 3.678E-09 $ .522E 09 6.912K-io 2.972E-I 1.969K-lo .396E 1 0 3 .949K

i. 37E-10 2.551E-iO .780E I 0 1.308E-fo 7.962E-il
9. 980E-11 6.278K-L 7.837E-L 5.056E-L 6.297E-L 4.143E il O. $ 56E- 1 EtIE 1.946K-OB 6.775E-09 2.832K-OP 1 .543E 0 .673K-LO 6.624K 0 4.813E-f 0 3.650E 10 2.858K-L 2.296E-L L.'882K- O E 2.753K-DB P. 116E-09 3.724K-09 .PPOE 0 .231E-09 8.352E 10 6.033K-LO 4.558K-l4 3.562K-L 2.858E 2.344K-LO ESE 2.4DOE-DB 7.7D6E 09 3.108E 4'9 .648K 0 .014F 09 6.856E to 4.942E 10 3.729E-14 2.912E-I 2.337K t4 1. 9 ibf"10 SE 55E

$ .728K-OB 5.876E-09 2.406E-09 S.887E 09 :Z.i33E-09 8.718K-fo

.303E 0

.842E

. 144E 10 5.573K lo 4. OSlf -1 0 3.088E-ID 2. i 44E" 10 1.57Sf-fo 3.076E-i4 2. 414K-I 1.2DSE-LD 9.502E-I

$ .944E-14 f . 598E-10 7.67'9E-lt 6.330K-li D I R EC I' ON DISTANCES IN HILES FRON SITE 6.00 S.stBE-i i 7.450E 6.50 7.00 7.50 8.00 8.50 9.40 9.50 $ 0.00 is.oo 20.00 S b.586E-L 5.873K-L 5.278E-L 4.774K 1.345K-L 3.975E-f 3.65 E I .983E- 1 "1.280E 11 5 5 II 5.876E-f 5. 176E- I 4.56SE"1 4.066K-L 3.646K 3.292E 2.99DE-i 2.710E- 2.50 E-I .330E- 8.447E 12 SIT 5. 67 LE- I 5.011E- I 4.420f-l 3. 931K-I 3.523f-f 3. 178E 2.883E"I 2.634E- 2. 40 E-If .267E- 7.984E 12 N5 II M

$ .9$ 7E-L 1 1.697E-2.915E-L I 2.588E-I 1.498K 1 2.283K 1.333E 2.03 E-I I.IPOE 1.821K I. 079E-I 1.642E-9.797E 1 1.490K 8.940E-1.359E-8.19 E 1 4.326E- 2 2.733K L2 f .245E I 6". 519E- 2 4.093E-12 IItHI 5.468E" 1 4.83OE-L 4.258E" 3.785E-I .390E 3.055E- 2.'77OE 2 524L- 2.31$ E" I .205E- 7.545E $ 2 IWI 7.006E- 6. 149E-I 5. 421E 1.8 9E- 4.316K 3.89LE- 3.529E 3. 217E- 2.946E-t .544f- I 9.724E-12 tIIIH 5.424K I 4.759E-L 4.197E 3.733E- 3.345E- 3.0i7E- 2.738K- 2.497E- 2.289K .207E" 7.637E 12 7.074E- 6.248E-I 5.473E 4.865E- 4.357E- 3.929E- 3.563K 3.249E- 2.976E" .561K- 9.840E $ 2 N

HI IE tlE 3.445E I 4.287E-3.034E-3.738E-2.673E 3.286E-

2. 374E-913E-
2. 125E" 2.602E-f.9t4E-2.339E-1.734E 2.114K L .579f-L.P22E-1.4 'E 1.754f-7.495E- 2 4.685E-12 8.956E" 2 5.554E-iZ EWE 1.570E 1.356E- .192E 056E- 9.430E- 8.477E 7.665E 6.967E-L 6.363E 3. 26$ E- 1 2.430E-l E I . 956E-10 1 . 680E- .476E 307E- 1.166E 1.047E 9.462E- S.596E-I 7.845E .DD4E- 2.487E-ESE $ .644E-ID i.372K- .205E 067E- 9.5$ 5E 8.548E- 7.726K- 7 020E-$ 6.408E- 3.278E- 2. 041K-I SE 1.337E-iO 1.157E- . 017K OIBE- 8.055E- 7.249E- 6.566E- 5 979K-1 5.47tE- 2.858E- L.BOSE- i SSE 5.344E-L 1 4.643E" 4.495E- 643E- 3.265K 2.948E- 2.679E- 2.446K-i 2.245E- I.200E- 7.679E-12 51- October 1985

r Page b or b-GRAZING SEASON D/Q (Velft Release)

HttP UHI I 42 IIENT llllllIllI lllllllll CORRECTED FOR OPEN TERRAItt RECIRCUI.ATION DIRECTION

~ ~ RELATIVE DKPOSITIOtt PER OMIT AREA (Mll 2) AT FIXED POINTS BY DOHNHLtID SECTORB DISTANCES IN MLLES llllllllllllllill ~ ~ I FROtt SITE .50 1. Oo 1. 50 2.00 2.50 3.DO 3.50 4.00 4.50 5.00 5.50 S 1.238E 48 4. 281E-09 1.592E-09 8.44&E-L 5.237E I Os 3. 579K-I 2.608E-L 0 1.990E-LO 1.572E-1 1.27Sf-l 1.057E 10 SSH 1.857E-09 1.932E-09 8. L17E-LO 4.630K-L 2.996K"1 0 2.099K-L I.SSOE-L 0 1. 189K-10 9.391E-L 7. 591E-t 6.253E-11 SH 3.515E-OV 1.603E-09 7.164E 10 4.187E-L 2.753E 1 0 1.946E-L 1 . 4 4 4F.-L 0 1.110E-LO $ .773E 7.0SSE 5.826K 11 HSH l.fo&E 09 5. 3VVE-10 2. 17SE-10 .473E 1 9.789 I 1 6.964E- 5. LBBK-L1 3.997E-LL 3. 1&LE-1

'7. $ 31E -1 6.046E-II 4.'782E-1 2.553E 1 2.098E-11 H 1.254E-09 7.095K-LO 3.501E 10 .f53E I .457E 1 0 1.046E-I 3.85BE 1 3. 163E-11 HNH 3.047E 09 1.520K-49 7.275E-IO 4.380E-I '2. 927 I 0 2.087E-L L.SSSE-L 0 1.197E-LO 9. 155K-L 7.622E-L 6. 219E-11 HH 5.990E-OV 2.472E-49 L.OSVK-OV 6.268K- .082 1 0 2.866E- 2. 11SK- 0 1. 623E-1 .279E- 1.032E-L $ .472E-11 HNH S.477E"49 2. 19SE-49 9.106E-IO 5.318E-L .4SSE 1 0 2.419E-i 1. 7S1E-1 0 1.366E-L .078E- $ .697E-I 7. 152E-1 I N '7.206K-09 2.815K-09 1. 216K-D9 6.919t-f 4. 471E" 1 0 3. 129E- 2.306E- 0 1.765E-1 .390E- f .121E- 9. 209E-11 NNK 2.1LSE-D9 9.561K-IO 4.464E 10 2. 615E-I I . '751K 0,211E- 9.217K-I 7.080E-L 5.583E- 4. 1'97E- 3.685E-LL HE 2.916E-09 1.273E-49 3. 916E-10 3.434E 1 2. 241E 1 0 .573E- 1. 161E-1 0 8.878E-L 6. 981E- S.&12E- 1.595E-ll EllE 1.905E-OS 6.$ S3K-OV 2.889E-09 1.586K 0 9. 991K- 0. 6.867E- 5.002K-l 0 3. BODE-I 2.979E- 2.395E- 1.965K-LO 2.603E-OS 8.833$ -49 3.627E-49 1.948K-O 1.249E-O 9 8.229E- S.956K- 0 4.546E-1 3.52SE- 2. 831E- 2.323E-10 ESE 1.936K-OB 6.3b4E-09 2.571K-09 1.37L -09 8.467E-LO 5.743E- 0 4.148E- 0 3.L35E-L 0 2.452E- 1.970E 1.617E-LO Sf 1.504K-OS 5. 144$ -09 2.0$ 8E 09 1. 12SE-49 7. D41E I 0 4. $ 1&E-10 3.SOL&- 0 ~ 659 E-1 0 2.087E- 1.682E- t.384E-LO SSE 5.570E-DV 1.928E 09 7.+06K-LO 1.222E 10 2.&70E-LD 1.844E-LO 1.351K-l 0 1.032E- 0 8.133E- 6.575E- S. 124K-f I DIRECTION DISTANCES Itt MILES FROII SLTK 6.00 6.50 7.00 7.50 8.00 8.50 9.0 9 50 10.00 15. 00 20.04 5 8.922K-l 7.7S3E-11 6.883K I 6. 140E- 5.52DE 1 4.996E-L 4.519K 1 4. 164K-1 3.829E- . 090E-1 1.354E 11 SSH 5.233K-l 4.644E-11 4.064E-L 1 3.614K-f 3.24fE-t 2.927K-f 2.659K 1 2.428K 1 2.228K-t . 187K-L 7.567K 12 SH 4. 861E-1 4 209K-11 3.783E- 3.366E-f 3. 017E-1 2.723f- 2.47LE 54E-f 2.066E I . 091E-1 6. 941E-12 HSH 1.750E-I 1.54$ E-fl 1.366K-l 1 . 216E- 1. 091E 1 9.844E-L 8.93'7E 2 8.156E I 7.477K-t .950K-I 2 . 498K -12 HNH H 2. 631E-I 2.334E-l

5. 19SE I 4.594K 2.059E-L 4.050E

.832E-

. 601E-I

.642E 3.226E

.1$ 1E-

,908E 1 I . 226E-1 3.637E I 2. 444E-1

l. 123f-
2. 201E-
SSBE-

.150E-3.701E-12 7.248E-I2 IIH 7.066E 6.244E-L 5.169C- 4.862K 1.355E 3.927E- 3. 561K 3.246K-L 2.'973E- .559E-f 9.823K 12 titIH 5.976E- 5.243E-L 1 4.623E- 4. 112E- 3.685E 3.324K 3.016E 2. 751E-I 2.52 E- .330E- 8. 417E 12 N 7.686E-L 6.736K"1 1 5.937E- 5.278E-i 4.727E 1 4.262E- 3.866E I 3.525E-I 3.229E- .69bf" 1.D7DE 11 NNE 3. 46SE-1 2.701E-1 1 2.380E- 2.1 6E- .894E .707K- 1.548K 1 1. 4 1 0K- L . 291E- .723E- 4.213E 12 IIE 3.824E- 3.342K-t 2.940 2 6 7E- 2.329E 2.495K- .895E 1. 723E-1 .574E- .067E- 5. DLOE-12 KNK 1.644K- 1.42 E-1 0 1.248E- 1 7E V.BS4K B.SSBE- 8.040C- 1 7 311K-1 6.680E- .438C- 2.146K-I 1 ESK f f.939E- 1.66 E 0 1.351E-LO 1. 16 E-1 0 1.466E- 0 1.299K 1.020E- 4 9.035E

. 159E 8.063E-

.041E-7.247K 9.414E-6.553f-

~

8.555E-S. 957f-

7. SLDE-S. 141E-

.OOOE-

. 797K-l 2.491E 11 1.748E 11 SE 1.158E-10 1.00 E- 0 8.820E I 7.823E- 6. 991K 6.295E- 5.703E- 5.195E- 1.755E- .491E- 1.578E-LL SSK 4.550K-IL 3.974E- 1 3.505E- 1 3. 119E- 2.795K 2.525E- 2.295E- 2. 096E-1 1.92SE- .033E- 6.633E 12 52- October 1985

1 2 . 3 4 sos.)s 5 9>>.7)'Q 1 I )i 7>>"12 13 14 '15 16 A

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