ML17348B080

Semiannual Radioactive Effluent Release Rept for Jan-June 1991 for Turkey Point Units 3 & 4. W/910827 Ltr

ML17348B080
Person / Time
Site:	Turkey Point
Issue date:	06/30/1991
From:	Plunkett T, Quinn S, Steinke R FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-91-234, NUDOCS 9109090213
Download: ML17348B080 (422)

Text

ACCELERATED D <TtuBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9109090213 DOC.DATE: 91/06/30 NOTARIZED: NO DOCKET g FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Un'it 4, Florida Power and Light. C 05000251 AUTH. NAME AUTHOR AFFILIATION QUINN,S. Florida Power & Light Co.

STEINKE,R.N. Florida Power & Ligh- Co.

PLUNKETT,T.F. Florida Power & Lighi Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept for Jan-June D 1991 for Turkey Point Units 3 & 4." W/910827 ltr.

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2) Effluent ReleaseJ ReportsI COPIES RECEIVED:LTR Semiannual ENCL SIZE: / 5 NOTES RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ~ ID CODE/NAME LTTR ENCL PD2-2 LA 3 3 PD2-2 PD, 1 1 AULUCK,R 1 1 D INTERNAL: AEOD/J3SR/~ 1 1 NRR/DREP/PRPBll 2 2 1 1 RGN2 DRSS/RPB 2 2 SH2 FILE 02 1 1 EXTERNAL BNL TICHLER F J03 EG&G SIMPSONF F 2 2 NRC PDR D

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LIFIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16

P.O. Box 029100, Miami, FI33102-9100 AUB R't I81 L-91-234 10 CFR 50.36 (a)(2)

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Semiannual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of January 1, 1991 through June 30, 1991, for Turkey Point Units 3 and 4, as required by Technical Specification 6.9.1.4 and 10 CFR 50.36(a)(2).

Should there be any questions regarding this information, please contact us.

Very truly yours, T. F. Plunkett Vice President Turkey Point Nuclear TFP/CLM/clm Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant

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TUIUMYPOINT PLANT UNITS 3 AND 4 SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY 1991 THROUGH JUNE 1991 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY S. Quinn Radiochemist R. N. Steinke Chemistry Supervisor

. A. Kaminskas Operations Superintendent L. W. Pearce Plant Manager-Nuclear

~PA E 1.0 Regulatory Limits 1~1 Liquid Effluents 1.2 Gaseous Effluents 2.0 Maximum Permissible Concentration 3.0 Average Energy 4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid Effluents - Discussion

a. Unit 3 Liquid Effluents Summation

b. Unit 4 Liquid Effluents Summation 13 4.2 Gaseous Effluents - Discussion

a. Unit 3 Gaseous Effluents Summation 10

b. Unit 4 Gaseous Effluents Summation 16 4.3 Estimate of Errors 5.0 Batch Releases 5.1 Liquid 5.2 Gaseous 6.0 Unplanned Releases 7.0 Reactor Coolant Activity 8.0 Site Radiation Dose 9.0 Offsite Dose Calculation Manual Revisions 10.0 Solid Waste and Irradiated Fuel Shipments 11.0 Process Control Program Revisions

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SUPPLEMENTAL INFORMATION JANUARY 1991 THROUGH JUNE 1991 i.o R~i i.i ~lid Hffl a) The concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed the concentration specified in 10CFR20 Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall not exceed 2.0 E-04 pCi/ml.

b) The dose or dose commitment per reactor to a member of the public from any radioactive materials in liquid effluent released to unrestricted areas shall be limited, during any calendar quarter, to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and, during any calendar year, to less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.

1.2 eous Effluen a) The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

Less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin due- to noble gases and less than or equal to 1500 mrem/year to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half lives greater than 8 days.

b) The air dose per reactor to areas at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, during any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

c) The dose per reactor to a member of the public, due to I-131, I-133, tritium and to particulates with half-lives greater than 8 days in airborne effluents released to areas at and beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

2.0 Maxim m Permi i le oncentrati n Water: As per 10CFR20, Appendix B, Table II, Column 2, except for entrained or dissolved Noble gases as described in 1.1.A of this report.

Air: Release concentrations are limited to dose rate limits described in 1.2.A 3.O The average energy of fission and activation gases in effluents is not applicable.

4.0 Measuremen and A roxima ion fT 1 Radioactivi Allliquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Regulatory Guide 1.21 was met or exceeded.

Where alpha, tritium and named nuclides are shown as curies, this should be interpreted as "no acbvity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Level of Detection (LLD) sensitivity for radioactive effluents".

'.1 U~iid ffl Aliquots of representative pre-release samples were isotopically analyzed for gamma emitting isotopes on a multichannel analyzer.

The above procedure was followed for all releases from the waste disposal system.

Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system and the storm drain system.

Monthly and quarterly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation. The monthly composite was analyzed for tritium and gross alpha activity.

Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2~ gas flow proportional counter and a solid state scintillation system. The quarterly composite was analyzed for Sr-89/90 and Fe-55 by chemical separation.

Allradioactivity concentrations determined from analysis of a pre-release composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

Aliquots of representative pre-release samples from the waste disposal system were analyzed on a per release basis for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released in order to estimate the total dissolved gases released.

The liquid waste treatment system is shared by both units at the site and generally all liquid releases are allocated on a 50/50 basis to each unit.

Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89/90 determination and gross alpha analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Analysis of water vapor in a gas sample for tritium using liquid scintillation techniques.

All gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 by use of the SPING-4 radiation monitor and the plant vent process monitor recorder chart and the current calibration curve for the monitor.

Portions of the gas waste treatment system are shared by both units and generally all gas releases from the shared system are allocated on a 50/50 basis to each unit, Meteorological data for the period January 1991 to June 1991, in the form of Joint Frequency Distribution Tables is maintained on-site.

4.3 M 4 E a) Sampling Error The error associated with volume measurement devices, flow measuring devices, etc., based on calibration data and design tolerances has been conservatively estimated to be collectively less than + 10%.

b) Analytical Error Our quarterly Q.C. cross-check program involves counting unknown samples provided by an independent external lab. The errors associated with our analysis of these unknown samples, and reported to us by the independent lab, were used as the basis for deriving the following analytical error terms.

~4* E ~E Liquid Gaseous +12

5.0 I! h 5.1 Liquid gni~4 a) Number of batch releases ~IE~+2 ~16 E+02 b) Total time period of batch releases, minutes

~j E+~4 I 55) E~+4 c) Maximum time period for a batch ~24 E+ 4 16 E+2 release, minutes d) Average time period for a batch ~2E+02 ~E~+1 release, minutes e) Minimum time period for a batch ~1E~+1 ~1E~+1 release, minutes f) Average stream flow during period ~44 E~OOj 4~4E+ 6 of release of effluent into a flowing stream, LPM 5.2 ~ae )~ Unit 4 a) Number of batch releases S~E+00 ~~E+ 0 b) Total time period of batch releases, ~120 E+0 ~1.20 E+ 3 minutes c) Maximum time period for a batch ~240 E+ 2 24 E+ 2 release, minutes d) Average time period for a batch ~240 E+ 2 ~240 E+ 2 release, minutes e) Minimum time period for a batch 2~4E+ 2 2~4E+ 2 release, minute

8. 0 880lll~l I

6. 1 fiuid anni '3 gni~4 a) Number of releases b) Total activity released, curies 7.74 E-02 7.12 E-08 6.2 Q negus a) Number of releases b) Total activity released, curies 6.3 See Attachment 1 for:

a) A description of the event and equipment involved.

b) Cause(s) for the unplanned release.

7.0 Reacor 1 n Acivi 7.1 Qni~

Reactor coolant activity limits of 100/E-Bar and 1.0 pCi/gm Dose Equivalent I-131 were not exceeded.

7.2 gni~4 Reactor coolant activity limits of 100/E-Bar and 1.0 pCi/gm Dose Equivalent I-131 were not exceeded.

8.0 D~RRi l 0 The assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary is part of the Year Ending Semiannual Report.

9.0 ffsiteDo e alc la i n Manual R vi i ns The ODCM was revised during this reporting period, see Attachment 2.

10.0 lid Waste and Irradi ed Fuel hi men No irradiated fuel shipments were made from the site, Common solid waste from Turkey Point Units 3 and 4 were shipped jointly. A summation of these shipments is given in Table 5 of this report.

11.0 Proces on r I Pr ram Revi i n See Attachment 3

FLORIDA POWER & LIGHT COMPANY TX7RKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1991 THROUGH JUNE 1991 LIQUIDEFFLUI~<S - SUMMATIONOF ALLRELEASES UNIT 3 TABLE 1 Units Quarter 1 Quarter 2 A. Fission and Activation Products I. Total Release(not including tritium, gases, alpha) Ci 1.27 E-01 1.98 E-02

2. Average diluted concentration during period pCi/ml 5.72 E-10 1.28 E-09 B. Tritium

1. Total Release Ci 9.80 E+00 8.96 E-01

2. Average diluted concentration during period pCi/ml 4.41 E-08 5.78 E-08 C. Dissolved and Entrained Gases

1. Total Release Ci 1.51 E-04

2. Average diluted concentration during period pCi/ml 6.80 E-13 N/A D. Gross Alpha Radioactivity

1. Total Release Ci <4.87 E-08~ <6.63 E48>>

E. Volume of Batch Waste Released (prior to dButioa) Liters 1.79 E+06 1.85 E+06 F. Volume of Continuous Waste Released (prior to dilutioa) Liters G. Volume of Dilution Water Used During Period 'iters 2'.22 E+11 1.55 E+10

• MDAValues in pCi/ml.

FLORIDA POWER.& LIGHT COMPANY TURKEY POINT PLANT JANUARY 1991 THROUGH JUNE 1991 LIQUID EFFLUENTS-SU1VBCATION OF ALLRELEASES UNIT 3 TABLE 2 Continuous Mode Batch Mode Nudides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Cr-51 Ci 8,78 E-03 Mn-54 Ci 1.81 E%2 5.87 E-03 Fe-55 Ci 4.39 E-03 9.27 E-03 Co-57 Ci 3,21 E45 Co-58 Ci 4.75 E42 5.39 E-04 Co%0 Ci 2.41 E-02 7.23 E-04 Zn45 Ci 4.21 E-06 Sr-89 Ci 5.07 E44 Sr-90 Ci 5A8 E-04 1.22 E-04 Nb-95 Ci 8.55 E-06 Zr-97 Ci 1.93 E-05 Ag-110 Ci 6.82 E-04 1.05 E44 Sb-124 Ci 5.57 E43 4.72 FA4 Sb-125 Ci 1.12 E-02 1.14 E-03 I-131 Ci 1.01 E-04 Cs-134 Ci 9.20 E44 2.61 E-04 Cs-137 Ci 4.06 E-03 1.32 E-03 UnidentiTied Ci Total for period Ci 1.27 E-01 1.98 E42

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 LIQUID EFFLUENTS UNIT 3 TABLE 2 (Continued)

Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 2 Quarter 1 Kr-85 Ci Xe-131m Ci Xe-133 Ci 1.51 E-04 Xe-133m Ci Xe-135 Ci Xe-135m Ci Total for Period Ci 1.51 E-04

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 GAS EFFLUENTS-SUMMATION OF ALLRELEASES UNIT 3 TABLE 3 Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 8.02 E-02

2. Average Release Rate for Period g Ci/sec 1.03 E-02 N/A B. Iodines

1. Total Iodine-131 Ci 5.06 E-05

2. Average Release Rate for Period pCi/sec 6.51 E-06 N/A C. Particulates

1. Particulates T-l/2) 8 days Ci 1.19 E-05 1.74 E-06

2. Average Release Rate for Period qCi/sec 1.53 E-06 2.21 E-07

3. Gross Alpha Radioactivity Ci (1.76 E-15>> (3.27 E-15>>

D. Tritium

1. Total Release Ci 1.55 E-01

2. Average Release Rate for Period qCi/sec 1.99 E-02 N/A

• MDAValues in pCi/ml.

10

FLORIDA POWER 4 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 GASEOUS EFFLUENTS UNIT 3 TABLE 4 A. Fission Gases Continuous Mode Batch Mode Nudides Released Units Quarter 2 Quarter 1 Quarter 2 Ar41 Ci Kr-85 Ci 2.69 E-02 Kr45m Ci Kr-87 Ci Xe-131m Ci Xe-133 Ci 4.96 E-02 3.71 E-03 Xe-133m Ci Xe-135 Ci Xe-135m Ci Total for Period Ci 4.96 E-02 3.06 E42 B. Io dines Continuous Mode Nuciides Released Units Quarter 1 Br-82 Ci I-131 Ci 5.06 E-05 I-133 Ci Total for Period Ci 5.06 E45 11

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 GASEOUS EFFLUENTS UNIT 3 TABLE 4 (Continued)

C. Particulates Continuous Mode Nudides Released Units Quarter 2 Co-58 Ci 7.10 E-06 Co%0 Ci 4.83 E46 Cs-137 Ci 1.74 E-06 Ci Ci Ci Ci Ci Total for Period Ci 1.19 E-05 1.74 E46 12

FLORIDA POWER R LIGHT COMPANY TURKEY POINT PLANT SEMI'ANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 LIQUID EFFLUENTS - SUMVCATION OF ALLRELEASES UNIT 4 TABLE 1 Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release(not including tritium, gases, alpha) Ci 4.92 E-02 1.98 E-02

2. Average diluted concentration during period pCi/ml 2.80 E-09 1.28 E-09 B. Tritium

1. Total Release Ci 9.80 E+00 8.96 E-01

2. Average diluted concentration during period pCi/ml 5.57 E-07 5.78 E-08 C.. Dissolved and Entrained Gases

1. Total Release Ci 1.51 E-04

2. Average diluted concentration during period pCi/ml 8.58 E-12 N/A D. Gross Alpha Radioactivity

1. Total Release Ci (4.87 E48>> (6.63 E48>>

E. Volume of Batch Waste Released (prior to dilution) Liters 1.78 E+06 1.85 E+06 F. Volume of Continuous Waste Released (prior to dDution) Liters G. Volume of Dilution Water Used During Period Liters 1.76 E+10 1.55 E+10

• MDAValues in pCi/ml.

13

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT JANUARY 1991 THROUGH JUNE 1991 LIQUID EFFLUENTS-SUMMATION OF ALLRELEASES UNIT 4 TABLE 2 Continuous Mode Batch Mode Nudides Released Quarter 1 Quarter 2 Quarter 1 Quarter 2 Cr-51 Ci 2.53 E-04 Mn-54 Ci 1.81 E-02 5.87 E-03 Fe-55 Ci 4.39 E-03 9.27 E43 Co-57 Ci 3.21 E-05 Co-58 Ci 2.7043 5.39 E44 Co%0 Ci 2.24 E43 7.23 E-04 Zn45 Ci 4.21 E46 Sr-89 Ci 5.07 E-04 Sr-90 Ci 5.48 E44 1.22 E44 Nb-95 Ci 8.55 E-06 Zr-97 Ci 1.93 E-05 Ag-110 Ci 6.82 E-04 1.05 E-04 Sb-124 Ci 4.10 E-03 4.72 E-04 Sb-125 Ci 1.12 E-02 1.14 E-03 I-131 Ci 1.01 E-04 Cs-134 Ci 9.20 E-04 2.61 E-04 Cs-137 Ci 3.36 E-03 1.32 E-03 Ci Unidentified Ci Total for period Ci 4.92 E-02 1.98 E-02 14

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SFMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 LIQUID EFFLUENTS UNIT 4 TABLE 2 (Continued)

Liquid Dissolved Gas Continuous Mode Batch Mode Nuclides Released Units Quarter 1 Quarter 2 Quarter 1 Kr-85 Ci Xe-131m Ci Xe-133 Ci 1.51 E-04 Xe-133m Ci Xe-135 Ci Xe-135m Ci Total for Period Ci 1.51 E-04 15

FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 GAS EFFLUENTS-SUMMATION OF ALLRELEASES UNIT 4 TABLE 3 Units Quarter 1 Quarter 2 A. Fission and Activation Products

1. Total Release Ci 2.69 E-02

2. Average Release Rate for Period qCi/sec 3.46 E-03 N/A B. Iodines

1. Total Iodine-131 Ci 4.94 E-05

2. Average Release Rate for Period pCi/sec 6.35 E-06 N/A C. Particulates

1. Particulates T-l/2>8 days Ci 1.19 E-05 1.74 E-06

2. Average Release Rate for Period pCi/sec 1.53 E-06 2.21 E-07

3. Gross Alpha Radioactivity Ci <1.76 E-15>> (3.27 E-15>>

D. Tritium I. Total Release Ci 1.16 E-01

2. Average Release Rate for Period pCi/sec 1.49 E-02 N/A

• MDAValues in qCi/ml.

16

- FLORIDA POWER & LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 GASEOUS EFFLUENTS UNIT 4 TABLE 4 A. Fission Gases Continuous Mode Batch Mode Nudides Released Units Quarter 1 Quarter 2 Quarter 1 Quarter 2 Areal Ci Ci 2.69 E-02 Kr45m Ci Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Total for Period Ci 2.69 E-02 B. Iodines Continuous Mode Nudides Released Units Quarter 2 Br42 Ci I-131 Ci 4.94 E-05 I-133 Ci Total for Period Ci 4.94 E-05 17

FLORIDA POVVER & LIGHT COMPANY TUIUCEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 GASEOUS EFFLU1PlTS UNIT 4 TABLE 4 (Continued)

C. Particulates Continuous Mode Nudides Released Units Quarter 1 Quarter 2 Co-58 Ci 7.10 E-06 Co-60 Ci 4.83 E-06 Cs-137 Ci 1.74 E-06 Ci Ci Ci Ci Ci Total for Period Ci 1.19 E45 1.74 E-06 18

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1991 THROUGH JUNE 199 1 UNITS 3 AND 4 TABLE 5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL

1. TYPE OF WASTE UNIT 6 MONTH PERIOD ~oERR

a. Spent resin, filters m 0. 00 EO sludge, evaporator bottoms Ci 0.00 EO

b. Dry Compressible waste m3 6.69 El (Note 1) Ci 4.38 E-1 20

c. Irradiated components m 0.00 EO Control rods, etc. Ci 0.00 EO

d. Other non-compressible m 2.36 El Waste (Note 2) Ci 8.69 EO 20

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION BY TYPE OF WASTE a ~

b. Fe-55 37 Co-60 31 Ni-63 15 Cs-137 9 Co-58 2 Cs-134 2 Cr-51 2 Ag-110m 1 Sb-125 1 c ~

d. Fe-55 31 Co-60 ~O 0 20 Co-58 14 Cr-51 10 Ni-63 8 H-3 9~ 7 Nb-95 3 Zr-95 9~ 2 Ru-103 2 Cs-137 1 Ru-106 1 Fe-59 1 19

Page 2 FLORZDA POWER AND LIGHT COMPANY TURKEY P01NT PLANT SEMIANNUAL REPORT JANUARY 1991 THROUGH JUNE 1991 UNITS 3 AND 4 TABLE 5

3. SOLID WASTE DISPOSITZON NUMBER OF SHIPMENTS MODE OF TRANSPORT DESTINATION 20 (Note 3) Sole use truck Oak Ridge, TN 4 Sole use truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS None RKR/eb/055 20

FLORIDA POWER 8 LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1991 THROUGH JUNE 1991 UNITS 3 R 4 TABLE 5 SOLID WASTE SUPPLEMENT (NOTE 4) (NOTE 5) (NOTE 6) (NOTE 7)

Total Total Principal Type of R.G. 1.21 Type of Solidification Waste Volune Curie Radionuclides Waste Category Container or Absorbent Classification Ft3 Quantity Agent Class A 3196.9 9. 13 Cs-137 Compactable 1.b,d Strong, N/A and Non- Tight Compactabl e Package, Trash Cask >Type A LSA

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 1991 THROUGH JUNE 1991 UNITS 3 AND 4 TABLE 5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPMENT OFFSITE FOR BURIAL OR DISPOSAL Note 1: Dry compressible waste volume indicates volume shipped to burial site following reduction by a waste processing facility. Volume shipped to the waste processing facility was 1449.8 m~

Note 2: Other noncompressible waste indicates volume shipped to burial site following decontamination and volume reduction by a waste processing facility or that shipped directly for disposal. Volume shipped to the waste processing facility was 0.0 m~.

Note 3: Material transported to Oak Ridge, Tennessee, was consigned to licensed processing facilities for volume reduction and decontamination activities. The material remaining after processing was transported by the processor to Barnwell, South Carolina, for burial.

Note 4: The total curie quantity and'adionuclide composition of solid waste shipped from the Turkey Point Plant Units 3 and 4 are determined using a combination of qualitative and quantitive techniques. The Turkey Point Plant follows the guidelines in the Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification (5/11/83) for these determinations.

The most frequent used techniques for determining the total activity in a package are the dose to curie method and inference from specific activity and mass or activity concentration and volume. Activation analysis may be applied when it is appropriate. The total activity determination by any of these methods is considered to be an estimate.

22

Page 2 FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 199 1 THROUGH JUNE 1991 UNITS 3 AND 4 TABLE 5 The composition of radionuclides in the waste is determined by both on-site analysis for principle gamma emitters and periodic off-site analyses for difficult to measure isotopes. The on-site analyses are performed either on a batch basis'r on a routine basis using representative samples appropriate for the waste type.

Off-site analyses are used to establish scaling factors or other estimates for difficult to measure isotopes.

Note 5: Principle radionuclide refers to those radionuclides contained in the waste in concentrations greater than 0.01 times the concentration of the nuclide listed in Table 1 or 0.01 times the smallest concentration of the nuclide listed in Table 2 of 10 CFR 61.

Note 6: Type of waste is specified as described in NUREG 0782, Draft Environment Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".

Note 7: Type of container refers to the transport package.

23

FLORIDA POWER AND LIGHT COMPANY TURKI<Y POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNE 1991 UNITS 3 AND 4 ATTACHMI<&T1 UNIT 3 UNPLA D RELEAS

1. On January 7, 1991, activity was found in the Northeast Storm Drain during routine analysis. Investigation showed an uncapped drain line from the Vnit 3 Caskwash area to be the source of activity. The drain line was capped to stop the release.

UNIT 4 UNPLANNED RELEASES On January 25, 1991 approximately five gallons of Component Cooling Water was released to the Southeast Storm Drain when a transfer hose was disconnected and not properly drained prior to being coiled on the ground.

2. On January 26, 1991 a leak was discovered in a fitting on a sandpiper pump being used to transfer water from the Component Cooling Water system to a holding tank for release. The fitting was repaired and a berm constructed around the pump to prevent further occurrences.

24

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUALREPORT JANUARY 1991 THROUGH JUNF 1991 UNITS 3 AND 4 ATTACERVHi22lT 2 This attachment contains the following information for the Offsite Dose Calculation Manual (ODCM), Revision 3:

1. Verification of PNSC Approval of the Revised ODCM, Rev. 3

2. An outline of the changes made to the ODCM

3. A complete copy of the ODCM No changes have been made which would reduce the accuracy or reliability of dose calculations or Setpoint determinations.

25

INTER-OFFICE CORRESPONDENCE PTN-NC-91-050 TO: PNSC DATE: June 12, 1991 S. Quinn DEPARTMENT: Nuclear Chemistry FROM'UBJECT:

Offsite Dose Calculation Manual COPIES TO: File Attached are the rewritten "Offsite Dose Calculation Manual", (ODCM), and an outline of the changes made, "Offsite Dose Calculation Manual Changes". This revision, REV. 3, is a total gewrite as described in the outline attached. The wording has been changed throughout the manual but not the intent.

This revision incorporates the Revised Technical Specifications, Objectives and Bases sections describing the intent of various applications and modifies some equations. All changes to the equations, or the assumptions they are based upon, have been made in a more conservative manor.

The outline, "Offsite Dose Calculation Manual Changes", identifies what changes have been made in each section, by section, of the ODCM.

The Revised ODCM was reviewed in draft form by A. J. Gould, P. G. Baily and R. N. Steinke, comments were submitted by all reviewers and incorporated.

The Final ODCM revision was:

Prepared by S. Quinn and N.U.S. Corporation:

S. Qui n PNSC Radiochemist APPROYAL DATE PLT. MGR Reviewed by:

APPROVAL DATE gris p G. Baily Nuclear Energy Senior Analyst R. N. Steinke Chemistry Supervisor SQ:sq

ITE D E AL ATI N MA AL HAN

1.0 INTRODUCTION

1. No changes - paragraphs rewritten for wording only, no context change 1.1 ODCM Review and Approval-1.1.1 Responsibility for Review - No changes 1.1.2 Documentation of Review - No changes 1.1.3 Institution of Changes - No changes 1.1.4 Submittal of Changes-

1. Added list ofTechnical Specification 6.14.2 requirements for Licensee-initiated changes to the ODCM 2.0 LI UID EFFLUENTS:

2.1 Objectives-

1. Added this section, description 2.2 Bases-

1. Added this section, description 2.2.1 Liquid Radwaste System

1. Added this section, description 2.2.2 Steam Generator Blowdown-

1. Added this section, description 2.2.3 Storm Drains-

1. Added this section, description 2.2.4 Radioactivity Concentration in Liquid Waste-

1. Incorporated Revised Tech Spec references

2. Clarified lower limit of detection (LLD) concentration reporting

2.2.5 Radioactivity Concentration in Water at the Restricted Area Boundary-

1. Incorporated Revised Tech Spec references

2. Moved how liquid effluents are apportioned to Section 2.2.1 2.3 Aqueous Concentration - No changes 2.3.1 Batch Releases-

1. Removed references to Gross Beta&amma analysis - no longer used for release puiposes

2. Clarified the intent of the equation

3. Placed available alternatives in the order of preference

4. Incorporated Revised Tech Spec references S. Included a conservative value for E (.5) and added the ability to use real data to account for Beta activity 2.3.2 Continuous Release-

1. See Section 2.3.1 2.3.3 Cumulative Release-

1. Added this section to account for multiple release points 2.4 Cumulative Dose-

1. Incorporated Revised Tech Spec references 2.5 Projected Dose-

1. Incorporated Revised Tech Spec references 2.6 Method of Establishing Alarm and Trip Setpoints-

1. Incorporates revised Tech spec references 2.6.1 Setpoint for a Batch Release

1. Added the S, factor in equation 9 in order to account for the multiple release points from the Plant 2.6.2 Setpoint for a Continuous Release-

1. See Section 2.6.1

Figure 2-1 Liquid Effluent Systems-

1. Updated to reflect present system 3.0 GASEOUS EFFLUENT:

3.1 Objectives-

1. added this section, description 3.2 Bases-

1. Added this section, description

2. Includes context of present ODCM Section 3.1, Introduction 3.2.1 Gaseous Radwaste System-

1. Added this section, description 3.2.2 Radioactivity in Gaseous Effluent-

1. Same context as present ODCM Section 3.2 but reworded 3.3 Dose Rate Due to Gaseous Effluent-

1. No changes but reworded 3.3.1 Total Body Dose Rate-

1. Changed Appendix A reference to the correct reference, Table 3-6 3.3.2 Skin Dose Rate-

1. No changes 3.3.3 H-3, I-131, I-133 and Particulate Dose Rate-

1. Changed receptor from adult to infant - more conservative 3.4 Dose - Noble Gases-

1. No change 3.4.1 Noble Gas Gamma Radiation Dose-

1. Incorporated Revised Tech Spec references

2. Reworded 3.4.2 Noble Gas Beta Radiation Dose-

1. Incorporated Revised Tech spec references

3.5 Dose Due to Iodine, Tritium, and Particulates-

1. No changes 3.5.1 Determining the Quantity of Iodine, Tritium and Particulates

1. Incorporates Revised Tech Spec references

2. Incorporates a Steam Mass Balance for accounting for steam loss during primary to secondary leaks, adds equation 21 3.5.2 Calculating the Dose Due to Iodine, Tritium and Particulates-

1. Incorporates Revised Tech Spec references 3.6 Effluent Noble Gas Monitor Alarm Setpoint-

1. Incorporates Revised Tech Spec references

2. Incorporates S, factor to reduce setpoints so that the sum of all releases does not exceed 1 MPC

3. Combines Sections 3.6.1 and 3.6.2 of the present ODCM 3.7 Projected Dose for Gaseous Effluents-

1. Incorporates Revised Tech Spec references Figure 3-1 Gaseous Effluent Systems-

1. Updated to reflect present system Figure 3-2 Locations At Which Doses Due to Airborne Effluents From the Turkey Point Plant are Calculated-

1. No changes Tables 3-1 to 3 1. No changes 4.0 DOSE COMMITMENTFROM RELEASES OVER EXTENDED TIME:

4.1 Releases During 12 Months-

1. Incorporates Revised Tech Spec references 4.2 Environmental Measures-

1. No changes

a; 4.3 Dose to a Person from Noble Gases-

1. Incorporates Revised tech Spec references 4.3.1 Gamma Dose to Total Body

l. Incorporates Revised Tech Spec references 4.3.2 Dose to Skin-

1. Incorporates Revised Tech Spec references

2. Changes equation 29 factor from .56 to 1.11 - more conservative by eliminating shielding consideration APPENDIX A Pathway-Dose Transfer Factors-

1. No changes APPENDIX B Technical Basis For A,>>-

1. Renamed from Appendix D APPENDIX C Radiological Environmental Surveillance-

1. Renamed from Appendix E APPENDIX D Example Calculations-

1. Added this section APPENDIX E Radioactive Effluent Technical Specifications-

1. Added this section BASIS DOCUMENT-

1. Added this section

CONTROLLED DOCUMENT NO. ¹ OFFSITE DOSE CALCULATION MANUAL FOR GASEOUS AND LIQUID EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 4 REVISION 3 AMENDMENT 1 CHANGE DATED 06 25 91 Florida Power and Light Company

Page 1 of 5 06/25/9 1 LIST OF EFFECTIVE PAGES Title Pacae Date Table of Contents "

V3. 06/25/91 06/25/91

~ ~

VI. 3.

Offsite Dose Calculation Manual 1 06/25/91 2 06/25/91 3 06/25/91 4 06/25/9 1 5 06/25/91 6 06/25/91 7 06/25/91 8 06/25/91 9 06/25/91 10 06/25/91 11 06/25/91 12 06/25/91 13 06/25/91 14 06/25/91 15 06/25/91 16 06/25/91 17 06/25/91 18 06/25/91 19 06/25/91 20 06/25/91 21 06/25/91 22 06/25/91 23 06/25/91 24 06/25/91 25 06/25/91 26 06/25/91 27 06/25/91 28 06/25/91 29 06/25/91 30 06/25/91 31 06/25/91 32 06/25/91 33 06/25/91 34 06/25/91 35 06/25/91 36 06/25/91 37 06/25/91 38 06/25/91 39 06/25/91 40 06/25/91 41 07/20/84 42 07/20/84 43 07/20/84 44 07/20/84

Page 2 of 5 06/25/91 LIST OP EPPECTZVE PAGES Title Pacae Date Offsite Dose Calculation Manual 45 07/20/84 46 07/20/84 47 07/20/84 48 07/20/84 49 07/20/84 50 07/20/84 51 07/20/84 52 07/20/84 53 07/20/84 54 07/20/84 55 07/20/84 56 07/20/84 57 07/20/84 58 07/20/84 59 06/25/91 60 06/25/91 61 06/25/91 62 06/25/91 Appendix A A-1 07/20/84 A-2 12/19/84 A-3 07/20/84 A-4 07/20/84 A-5 07/20/84 A-6 07/20/84 A-7 07/20/84 A-8 07/20/84 A-9 07/20/84 A-10 07/20/84 A-11 07/20/84 A-12 07/20/84 A-13 07/20/84 A-14 07/20/84 A-15 07/20/84 A-16 07/20/84 A-17 07/20/84 A-18 07/20/84 A-19 07/20/84 A-20 07/20/84 A-21 07/20/84 A-22 07/20/84 A-23 07/20/84 A-24 07/20/84 A-25 07/20/84 A-26 07/20/84 A-27 07/20/84 A-28 07/20/84 A-29 07/20/84 A-30 07/20/84 A-31 07/20/84 A-32 07/20/84 ii

Page 3 of 5 06/25/91 LIST OF EFFECTIVE PAGES Title Pacae Date Appendix A A-33 07/20/84 A-34 07/20/84 A-35 07/20/84 A-36 07/20/84 A-37 07/20/84 A-38 07/20/84 A-39 07/20/84 A-40 07/20/84 A-41 07/20/84 A-42 07/20/84 A-43 07/20/84 A-44 07/20/84 A-45 07/20/84 A-46 07/20/84 A-47 07/20/84 A-48 07/20/84 A-49 07/20/84 A-50 07/20/84 A-51 07/20/84 A-52 07/20/84 A-53 07/20/84 A-54 07/20/84 A-55 07/20/84 A-56 07/20/84 A-57 07/20/84 A-58 07/20/84 A-59 07/20/84 A-60 07/20/84 A-61 07/20/84 A-62 07/20/84 A-63 07/20/84 A-64 07/20/84 A-65 07/20/84 A-66 07/20/84 Appendix B B-1 07/20/84 B-2 07/20/84 B-3 07/20/84 B-4 07/20/84 B-5 07/20/84

Page 4 of 5 06/25/91 LIST OP EFFECTIVE PAGES Title Pacae Date Appendix C C-1 07/20/84 C-2 07/20/84 C-3 07/20/84 C-4 07/20/84 C-5 07/20/84 C-6 07/20/84 C-7 07/20/84 C-8 07/20/84 C-9 12/19/84 C-10 06/25/91 Appendix D D-1 06/25/9 1 D-2 06/25/9 1 D-3 06/25/9 1 D-4 06/25/91 D-5 06/25/91 D-6 06/25/91 D-7 06/25/9 1 D-8 06/25/91 D-9 06/25/9 1 D-10 06/25/9 1 D-11 06/25/9 1 D-12 06/25/9 1 D-13 06/25/91 D-14 06/25/9 1 D-15 06/25/91 D-16 06/25/91 D-17 06/25/9 1 D-18 06/25/91 D-19 06/25/91 D-20 06/25/9 1 D-21 06/25/9 1 D-22 06/25/9 1 D-23 06/25/9 1 D-24 06/25/91 D-25 06/25/9 1 D-26 06/25/91 D-27 06/25/91 Appendix E E-1 06/25/91 E-2 06/25/91 E-3 06/25/91 E-4 06/25/91 E-5 06/25/91 E-6 06/25/91 iV

Page 5 of 5 06/25/91 LIST OF EFFECTIVE PAGES Title Pacae Date Appendix E E-7 06/25/91 E-8 06/25/91 E-9 06/25/91 E-10 06/25/91 E-11 06/25/91 E-12 06/25/91 E-13 06/25/91 E-14 06/25/91 E-15 06/25/91 E-16 06/25/91 E-17 06/25/91 E-18 06/25/91 E-19 06/25/91 E-20 06/25/91 E-21 06/25/91 E-22 06/25/91 E-23 06/25/91 E-24 06/25/91 E-25 06/25/91 E-26 06/25/91 E-27 06/25/91 E-28 06/25/91 E-29 06/25/91 E-30 06/25/91 E-31 06/25/91 E-32 06/25/91 E-33 06/25/91 E-34 06/25/91 E-35 06/25/91 E-36 06/25/91 E-37 06/25/91 Figures 2-1 06/25/91 3-1 06/25/91 3-2 07/20/84 5.1-1 06/25/91 5.1-2 06/25/91

OFFSITE DOSE CALCULATION MANUAL FOR GASEOUS AND LIQUID EFFLUENT 1.0 Introduction F 1 ODCM Review and Approval 1.1.1 Responsibility for Review 1.1.2 Documentation of Reviews 1.1,3 Institution of Changes 1.1.4 Submittal of Changes 2.0 Liquid Effluents 2.1 Objectives 2.2 Bases 2 2 1

~ ~ Liquid Radwaste System 2' ' Steam Generator Blowdown 2' ' Storm Drains 2.2.4 Radioactivity Concentration in Liquid Waste 5 2.2.5 Radioactivity Concentration in Water at the Restricted Area Boundary 6 2' Aqueous Concentration 6 2.3.1 Batch Release 7 2.3.2 Continuous Release 8 2.3.3 Cumulative Release 10 2.4 Cumulative Dose 10 2.5 Projected Dose 12 2.6 Method of Establishing Alarm and Trip Setpoints 13 2.6.1 Setpoint for a Batch Release 14 2.6.2 Setpoint for a Continuous Release 15 3.0 Gaseous Effluent 17 3.1 Objectives 17 3.2 Bases 17 3.2.1 Gaseous Radwaste System 18 3.2.2 Radioactivity in Gaseous Effluent 19 3.3 Dose Rate Due to Gaseous Effluent 21 3.3.1 Total Body Dose Rate 22 3.3.2 Skin Dose Rate 23 3.3.3 H-3, Radioiodine and Particulate Dose Rate 24 3.4 Dose-Noble Gases 26 3.4.1 Noble Gas Gamma Radiation Dose 26 3.4.2 Noble Gas Beta Radiation Dose 27 3.5 Dose Due to Iodine, Tritium, and Particulates in Gaseous Effluents 29 3.5.1 Determining the Quantity of Iodine Tritium and Particulates 29 3.5.2 Calculating the Dose Due to Iodine Tritium and Particulates 31 vi REV. 3: 06/25/91

3.6 Effluent Noble Gas Monitor Alarm Setpoint 35 3.7 Projected Dose for Gaseous Effluents 38 Dose Commitment from Releases Over Extended Time 59 4.1 Releases During 12 months 59 4.2 Environmental Measurements 60 4.3 Dose to a Person from Noble Gases 60 4.3.1 Gamma Dose to Total Body 61 4.3;2 Dose to Skin 61 Figures 2-1 Liquid Effluent Systems 16 3-1 Gaseous Effluent Systems 40 3-2 Locations At Which Doses Due to Airborne Effluents From the Turkey Point Plant Are Calculated 41 Tables 3-1 Atmospheric Gaseous Release Points at the Turkey Point Units 3 and 4 42 3-2 Distribution of Radioactive Noble Gases in Gaseous Effluent from Turkey Point Units 3 and 4 43 3-3 Transfer Factors for Maximum Offsite Air Dose 44 3-4 Transfer Factors for Maximum Dose to a Person Offsite Due to Radioactive Noble Gases 45 3-5 Dose Conversion Factors for Deriving Radioactive Noble Gas Effluent Monitor Setpoints 46 3-6 Reference Meteorology: Annual. Average Atmospheric Dispersion Factors 47 3-7 Reference Meteorology: Deposition Depleted Annual Average Atmospheric Dispersion Factors 51 3-8 Reference Meteorology: Annual Averaged Relative Deposition Rate 55 Appendix A Pathway-Dose Transfer Factors B Technical Bases for A,<<

C Radiological Environmental Surveillances D Sample Calculations E Radioactive Effluent Technical Specifications vii REV. 3: 06/25/91

1.0 Introduction This manual describes methods which are acceptable for calculating radioactivity concentrations in the environment and potential offsite doses associated with liquid and gaseous effluents from the Turkey Point Nuclear Units. These calculations are performed to satisfy Technical Specifications and to ensure that the radioactive dose or dose commitment to" any member of the public is not exceeded.

The radioactivity concentration calculations and dose estimates in this manual are used to demonstrate compliance with the Technical Specifications required by 10 CFR 50.36. The methods used are acceptable for demonstrating operational compliance with 10 CFR 20 '06, 10CFR50 Appendix I, and 40CFR190 ~ Only the doses attributable to Turkey Point Units 3 and 4 are determined in demonstrating compliance with 40CFR190 since there are no other nuclear facilities within 50 miles of the plant. Monthly calculations are performed to verify that potential offsite releases do not exceed Technical Specifications and to provide guidance for the management of radioactive effluents. The dose receptor is described such that the exposure of any member of the public is not likely to be substantially underestimated.

Quarterly and annual calculations of committed dose are also performed to verify compliance with regulatory limits on offsite dose. For these calculations, the dose receptor is chosen on the basis of applicable exposure pathways identified in a land use survey and the maximum ground level atmospheric dispersion factor (X/Q) at a residence, or on the basis of more conservative conditions such that the dose to any resident near the plant is not likely to be underestimated.

1.1 ODCM Review and A royal 1~1~1 Res onsib lit for Review The Chemistry Department Supervisor or his designee shall perform a review of the ODCM annually.

1~1~ 2" umentatio of Reviews Following the performance of the annual review required by Section 1.1.1, the'individual performing the review shall submit a report for PNSC approval. This report should contain the following information:

06/25/91

1. A copy of the ODCM with any requested changes.

2. Information necessary to support the rationale for the requested changes.

3 ~ A determination that the requested changes not reduce the accuracy will or reliability of dose calculations or setpoint determinations.

4. If no changes requested, no are being actions are required.

Institution of Chan es Changes to the ODCM shall become effective upon review and acceptance by the PNSC.

8ubmittal of Chan es Changes to the ODCM and any supporting documentation shall be submitted to the NRC in 'the Semi-Annual Radioactive Effluent Release Report for the period in which the changes were made effective. This submittal, per Technical Specification 6.14.2, shall contain the following information:

1 ~ Sufficiently detailed information to totally support the rationale for the changes(s) without benefit of additional or supplemental information.

2 ~ Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered, dated and containing the revision number, together with appropriate analyses or evaluations )ustifying the change(s)

3. A determination that the change(s) will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and 06/25/91

4. Documentation of the fact that the change(s) has been reviewed and found acceptable by the PNSC.

06/25/91

1 2.0 Li id Effluents To provide calculational methodology needed to assure compliance with Technical Specification 3.11.1 which requires the following determinations and surveillances:

0 The concentration of radioactive materials released in l'iquid effluents.

0 The concentrations of radioactive materials released are maintained within the limits of Specification 3.11.1.1.

0 Quarterly and annual cumulative dose contributions to a member of the public from radioactivity in liquid effluents released from each unit to unrestricted areas are maintained within the limits of Specification 3.11.1.2.

0 Projected doses at least once per 31 days due to liquid releases to unrestricted areas are maintained within the limits of Specification 3.11.1.3.

Operation of appropriate portions of the Liquid Radwaste Treatment System if Specification 3.11.1.3.

projected doses exceed limits of 0 Verification of operability of Liquid Radwaste System by meeting Specifications 3.11.1.1. and 3.11.1.2.

2.2 Bases Radioactive liquid effluents from Turkey Point Units 3 and 4 are released through radiation monitors which provide an alarm and automatic termination of radioactive releases. There are three discharge points from the units: steam generator blowdown from each unit and a common radwaste monitor tank discharge.

The liquid effluent monitoring instrumentation and controls at Turkey Point for controlling and monitoring normal radioactive releases in accordance with Turkey Point Technical Specification 3.11.1. consist of the following:

2 2 1

~ ~ d adw ste 8 ste Potentially radioactive liquid waste from Units 3 and 4 chemistry laboratories, containment sumps, floor drains, showers and miscellaneous sources are collected in waste hold up tanks. These wastes are processed through a demineralizer system and the effluent stored in one of the three waste monitor tanks (Refer to Figure 2-1). Laundry wastes are normally segregated and sent to one of two monitor tanks. Liquid waste in the waste monitor tanks and onitor tanks are isolated and recirculated for a minimum of one(1) tank volume prior to sampling.

06/25/91

Liquids in these tanks are released after sampling and analysis'n accordance with Technical Specification Table 4.11-1. The discharge from the waste monitor and monitor tanks is monitored by a radioactive liquid effluent monitor. Since these liquid effluents are a mixture from both Units 3 and 4, the measured releases from the common discharge point are apportioned to each unit as a ratio equal to the ratio of specific isotopic concentrations in the primary coolant of the two reactors to assure the effluents are within the allowable limits per reactor. An alternate method is to allocate effluent releases equally to both Units 3 and 4.

2~2 ~2 Steam Generator Blowdown Units 3 and 4 steam generator blowdown can be discharged directly from the blowdown flashtanks to the condenser cooling water mixing basin. The activity of each steam generator blowdown discharge (a composite) is monitored prior to the Blowdown Flash Tank for Unit 3 and 4 respectively. Releases from the steam generator blowdown are sampled and analyzed in conformance with Technical Specifi-cation Table 4.11-1.

2 ' ' Storm Drains Storm drains from Units 3 and 4 discharge into both the circulating water intake and the condenser cooling water mixing basin. Storm drains are sampled and analyzed in accordance with Technical Specification Table 4.11-1.

2 ' ' Radioacti it Concentration in Li id %Paste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accord-ance with Table 4.11-1 of the Technical Specifi-cations. Zf a radionuclide is below its LLD, and the calculated LLD concentration is below the LLD concentration value specified in Technical Specifi-cation, Table 4.11-1 then being present it in the sample.

is not reported as When the radionuclide's calculated LLD is greater than the LLD listed in Technical Specification Table 4.11-1, the'alculated LLD should be assigned as the activity of the radionuclide.

06/25/91

~,

2 ' 5 Radioactivit Concentration in Rater at the Restricted Area Bounda Technical Specification 3.11.1.1 requires that the concentration of radioactive material, other than noble gases, in liquid effluent released into an unrestricted area not exceed the concentration specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. A maximum concentration, 2 x 10 4pCi/ml, for noble gas entrained in aqueous releases into an unrestricted area applies separately since the potential exposure route, immersion in water, differs from that upon which Part 20, Appendix B is based.

Radioactive material in liquid effluent from Turkey Point is diluted by condenser cooling water from fossil units 1 and 2 and from nuclear units 3 and 4 in the condenser cooling water mixing basin. Water in the basin flows into an onsite closed cooling canal system. Liquid effluent does not actually leave the site in a surface discharge. For the purpose of compliance with Technical Specification 3.11.1.1, the total condenser cooling water flow from operating condenser cooling water pumps at the four units is assumed for dilution and the restricted area boundary is assumed to be at the end of the condenser cooling water mixing basin where water enters the cooling canal system.

Sections 2.3.1 and 2.3.2 describe methods used to assess compliance with Technical Specification 3.11.1.1. Effluent monitor alarm/trip setpoints are computed on the same basis, as described in section 2.6. If an alarm/trip setpoint is not exceeded, aqueous effluents are deemed to comply with Technical Specification 3.11.1.1.

2.3 A eous Concen a ion The diluted concentration of radionuclides in the condenser cooling water mixing basin outflow is estimated with the equat'ion

= Cg Fi Cg F2 06/25/91

where:

C,< = concentration of radionuclide i in the in the condenser cooling water mixing waterbasin outflow, (pCi/ml)

C< = concentration of radionuclide radwaste released, (pCi/ml) i in liquid F>/Fz = dilution F> = flow in radioactive liquid discharge line (gal/min).*

total condenser cooling water flow, (gal/min).* Value not greater than the rated total condenser cooling water flow from operating condenser cooling water pumps at the four units.

• F> and Fz may have any suitable but identical units of flow, (volume/time).

2~3~1 Batch Release A sample of each batch of liquid radwaste is analyzed before release for I-131 and other principal gamma emitters. With the activity concentration in a batch sample b based on the total isotopic activity, the fraction of the unrestricted area MPC due to a batch release is derived by using the ratio of the individual isotopic concentrations and their related MPCs.

FMPC> is estimated with the equation si g MPH b

b (2) where:

FMPCb fraction of the unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a batch release 06/25/91

t '

C. = concentration of radionuclide i in the water in the condenser cooling water mixing basin out flow, (pCi/ml); determined from equation (1) .

MPC< = activity concentration limit in water of radionuclide i according to 10 CFR 20, Appendix B, Table 2, Column 2, (pCi/ml).

(Quarterly average of the fraction of MPC in the batch tank due to I-131 and principal gamma Eb = emitters (Quarterly average of the fraction of MPC in the batch tank due to all radionuclides measured.)

Eb is an adjustment to account for radionuclides prior to release but measured in the quarterly notsample measured Technical Specification Table 4.11-1, i.e., Sr-89, Sr-90, per Fe-

55. The value of Eb is calculated from previously measured data (a conservative value of 0.5 has been estimated for Eb a calculated value is not available), or FMPCb can be if calculated by including a previous quarter's beta C,i and MPC<

into the calculation for each release, thus eliminat~ing the Eb factor.

'lternately, the fraction of the unrestricted area MPC due to a batch release can be estimated by:

FMPC~ =

3x10 (3) where:

c~ =

$ c(pci/mi) 3 x 10 = unrestricted area MPC for unidentified radionuclides in water, (pCi/ml).

2.3.2. Continuo s Release Continuous aqueous discharges are sampled and analyzed according to the schedule in Technical Specification Table 4.11-1. The fraction of the unrestricted area MPC present in a continuously discharged radioactive stream, FMPC ., is derived from an isotopic analyses. The fraction ok the unrestricted area MPC can be derived usincj i:.ie ratio of the 06/25/9 1

individual isotopic concentrations and their related MPCs.

'MPC, is estimated with the equation Czf FMPC + MPC~

c (4) where:

FMPC fraction of the unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a continuous release C, concentration of radionuclide condenser i in the water in the cooling water mixing basin outflow determined from equation (1); (pCi/ml)

MPCI activity concentration limit in water of radionuclide i according to 10CFR20, Appendix B, Table 2, Column 2, (pCi/ml)

(Quarterly average fraction of MPC due to I-131 and principal gamma emitters measured in samples E of continuous e eases uri the art (Quarterly average fraction of MPC due to all radionuclides measured in samples of continuous releases)

E, is an adjustment to account for radionuclides not measured in individual samples of continuous releases but measured in the quarterly composite samples per Technical Specifications Table 4.11-l,i.e. Sr-89, Sr-90, Fe-55. The value of E, is calculated from previously measured data ( a conservative value of 0.5 has been estimated for E, if a calculated value is not available ), or FMPC, can be calculated by including a previous quarter's beta C,< and MPC< into the calculation for each release, thus eliminating the E factor.

Alternately, the fraction of the unrestricted area MPC present in the condenser cooling water mixing basin can be estimated by FHPCc =

3x10 (5) 06/25/91

0 Where:

3 x 10 = unrestricted area . MPC for unidentified radionuclides in water, (pCi/ml) 2 ' ' Cumulative Release To ensure that the unrestricted area MPC is not exceeded during periods of multiple releases, the fraction of MPC determined for each type of release is summed to determine a total release fraction using the following equation:

FMPCT = FMPC0 + FMPC (6)

Where:

the total fraction of the unrestricted area MPC released.

FMPCb the fraction of the unrestricted area MPC due to batch releases.e.g.monitor tanks, storm drains etc.

FMPC the fraction of the unrestricted area MPC due to continuous releases. e.g. steam generator blowdown.

2.4 Cumulative Dose Technical Specification 3.11.1.2 requires the dose or dose commitment to a member of the public from radioactive materials released in liquid effluents from each unit to unrestricted areas be limited to < 1.5 mrem to the whole body and 5 5 mrem to any organ during any calendar quarter and to

< 3 mrem to the whole body'and < 10 mrem to any organ during any calendar year.

Technical Specification 4.11.1.2 requires the dose or dose commitment to a member of the public due to radioactive material released in liquid effluent to be calculated on a cumulative quarterly and annual basis at least once per 31 days. The condenser cooling water basin and closed canal 10 06/25/9 1

system which receives aqueous effluent is entirely on FP&L property, without surface discharge offsite, and FP&L does not permit members of the public to use the water. As a result, potential exposure of a member of the public to radioactive material originating in aqueous effluent is limited to irradiation of persons by canal shoreline deposits.

Technical Specification 4.11.1.2 is satisfied by calculating the cumulative total body dose to a person who may be irradiated by radionuclides deposited on the cooling canal shoreline from radioactive liquid effluent. Compliance with the organ dose limit is assured as long as the total body dose is below its limit.

The model that is used to evaluate doses due to radioactivity in liquid effluents is O 23 gk q g shoreline . 4 CLa 'Fxx 'C v'A, g (7) where:

D total body or organ dose due to irradiation by radionuclides on the shorelines which originated in a liquid effluent release, (mrem) 0.23 = units conversion constant =

1Ci 106'i x 60 hr x 3785 ml Pal A) transfer factor relating a unit aqueous concen-tration of radionuclide i to a dose commitment rate to specific organs and the total body of an exposed person. Values for A< are tabulated in Appendix A, (mrem/Ci~gal/min)

CIR the concentration of radionuclide in the undiluted liquid waste to be discharged that is represented by sample k, (pCi/ml)

F, liquid waste discharge flow during release represented by sample k, (gal/min) cooling canal effective volume, approximately 3.75 X 109 gallons effective decay constant (A< + FpV, min ') .

06/25/91

where:

the radioactive decay constant Fz = canal-ground water interchange flow, approximately 2.25 x 10 gal/min tz = period of time (hours) during which liquid waste represented by sample k is discharged Radionuclide concentrations (C<z) in effluent are measured by the sampling and analysis program specified in Technical Specification Table 4.11-1. Typically, more than 90 percent of the potential irradiation from radionuclides deposited along the shoreline is due to Mn-54, Co-58, Co-60, Cs-134, and Cs-137. Of these radionuclides, Co-60 has the maximum dose transfer factor, A,. Thus, for the purpose of assessing compliance with Technical Specification, 4.11.1.2, the radioactive effluent source term may be either:

a) principal gamma emitters measured by the effluent sampling and analysis program, or b) Mn-54, Co-58, Co-60, Cs-134, and Cs-137 measured by the effluent sampling and analysis program and other identified gamma emitters assumed to be Co-60, or c) all gamma emitters measured by the effluent sampling and analysis program assumed to be Co-60.

Use of principal gamma emitters measured by the effluent sampling and analysis program is preferred over the other alternates.

2.5 Pro ected Dose Technical Specification 3.11.1.3 requires that the Liquid Radwaste Treatment System be operable and appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses from each unit to unrestricted areas due to liquid effluents, when averaged over a 31 day period, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

Technical Specification 4.11.1.3.1 requires the doses, to unrestricted areas, due to radioactive material released in liquid effluent to be projected at least once per 31 days unless the liquid radwaste treatment system is being fully utilized.

This requirement. is satisfied by extrapolating the dose to date during the current month to include the entire month.

The dose to date is calculated as described in section 2.4.

12 06/25/91

Il P1 t+

The dose is projected with the relation:

P =

31'D X

(8) where:

P = the projected total body or organ dose during the month, (mrem).

31 = number of days in a calendar month, (days)

X = number of days in current month to date represented by available radioactive effluent sample, (days)

D = total body or organ dose to date during current month calculated according to section 2.4, (mrem)

Alternately, the monthly dose may be projected by computing the doses to the total body and most exposed organ accumulated during the most recent month and assuming the result represents the projected doses for the current month. The dose during the preceding month will be computed as described in section 2.4.

2.6 Method of Estahlishin Alarm and Tri 8et pints The radioactive liquid effluent monitoring be operable in accor'dance with Specification 3.3.3.5, instrumentation'hould with its alarm/trip setpoints set to ensure the limit of Specification 3.11.1.1 are not exceeded.

The alarm/trip setpoint for each liquid effluent radiation monitor is derived from the concentration limits provided in 10 CFR Part 20, Appendix B, Table 2, Column 2 applied in the condenser cooling water mixing basin outflow. Radiation monitoring and isolation points are located in the steam generator blowdown lines, R-3-19, R-4-19, and the liquid waste disposal system line, R-18, through which radioactive waste effluent is eventually discharged into the canal basin. See Figure 2-1.

The alarm setpoint for each'iquid effluent monitor is based upon the measurements of radioactivity in a batch of liquid to be released or in the continuous aqueous discharge. Sample measurements are performed according to Technical Specificat ion Table 4.11-1. If the calculated setpoint is less than the existing setpoint, the setpoint shall be reduced to the new setpoint. If the calculated setpoint is greater than the existing setpoint, the setpoint may remain at the lower value or be increased to the calculated value.

13 06/25/91

8et oint for a Batch Release The liquid radwaste effluent line radiation monitor alarm setpoint for a batch release is determined with the equation below or a method which gives a S> =

where:

lower setpoint value.

Ab Sg FMPCb

+ Bkg (9)

Sb radiation monitor alarm setpoint for a batch release, (cpm)=

laboratory counting rate (cpm/ml) or activity concentration (pCi/ml) of sample from batch tank FMPCb fraction of unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a batch release; determined in section 2.3.1.

gb detection efficiency of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch sample (cpm/cpm/ml or cpm/pCi/ml) which ever units are consistent with the units A .

Bkg background (cpm)

A factor to allow for mulitple sources from different or common release points.

The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

06/25/91

set oint for a continuous Release The liquid effluent line radiation monitor alarm setpoint for a continuous release is determined with the equation below or by a method which gives S =

a lower setpoint value.

A Sg FMPC

+ Bkg (10) where:

S radiation monitor alarm setpoint for a continuous release, (cpm)

A laboratory counting rate (cpm/ml) or activity concentration (pCi/ml) of sample from continuous release FMPC fraction of unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a continuous release; determined in section 2.3.2.

gc detection efficiency of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given continuous release sample, (cpm/cpm/ml or cpm/pCi/ml), whichever units are consistent with the units A,.

A factor to allow for mulitple sources from different or common release points.

The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

15 06/25/91

Turbines Unit 3 Unit 4 Turbines Steam Steam Cond ensers Generator Rcoclor Reactor Generator Condensers

[ elk% ~

R-3-I9 R-4-19 CVCS 3 CVCS 4 I

Makeup water Vent to Blowdown and chemicals Slowdown Atmosphere Vent lo floch flash or Return Afmoephere lank tonk lo F.W.

or Return Reactor Reactor System lo F.W. Coolanl Coolant TO WHT System Drain Tank Drain Tank TO WHT Chemico l Laborotory Waste Containment Sumps Spent Fuel Holdup Boric Acid Holdup Pits Tanks I'loor Drains Tanks Laundry 4 Showers Laundry Water Boric Acid Evaporator Demlneralizer Concentrates Recovery Bottoms Holding Tank System System Intake Intake Canal Canal Monitor Solid Waste Tanks Drumming Facility R-18 Shipment Off-site Waste Monitor Tanks Discharge Canal Discharge Canal

3 ' Gaseous Effluent To provide calculational methodology needed to assure compliance with Technical Specification 3.11.2 which requires the following determinations and surveillances:

0 Radionuclide concentrations in gaseous effluents 0 The dose rate due to radioactive gaseous effluents to areas at and beyond the site boundary are maintained within the limits of Technical Specification 3.11.2.1.

Total body dose rate from radioactive noble gases Skin dose rate from radioactive noble gases Organ dose rate from radioiodines, tritium, and particulates with half-lives greater than 8 days.

Determine the cumulative quarterly and annual doses per reactor at and beyond the site boundary due to noble gases are maintained below the limits of Technical Specification 3.11.2.2 at least once per 31 days.

Determine that the cumulative quarterly and annual doses per reactor at and beyond the site boundary from radioiodines, tritium, and -particulates with half-lives greater than 8 days are maintained below the limits of Technical Specification 3.11.2.3 at least once per 31 days.

Project the doses due to gaseous releases from each unit at least once per 31 days when gaseous radwaste utilized.

treatment systems are not being fully 3.2 Bases Radioactive gaseous effluents from Turkey Point Units 3 and 4 are released through four monitored release points; a common plant vent via a stack above the containment building, the Unit 3 spent fuel pit vent, and the condenser air ejector vents from each unit. Unmonitored radioactive airborne releases can also occur from the secondary steam systems of each unit secondary leakage is occurring.

if primary to The effluent sources (refer to Figure 3-1) for each release point are tabulated in Table 3-1. The airborne releases from all these sources are treated as a mixed mode release from a single loca% ~n for dose calculational purposes.

06/25/91

0 0

Compliance for beta and gamma dose limits at and beyond the site boundary for noble gas effluents is determined by assessing the dose rate and/or dose at the location where the minimum atmospheric dispersion occurs at the site boundary since the atmospheric dispersion will be higher at all other points off-site. This minimum dispersion occurs at the site boundary 1950 meters SSE of the plant where the dispersion factor is 5.8 x 10 ~

sec/m .

The dose rate due to tritium, I-131, I-133, and radioactive particulates with half lives greater than 8 days at and beyond the site boundary is assessed by determining the dose rate to a hypothetical infant's thyroid via the inhalation pathway. The basis for this approach is NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" which states: the dose factors are dependent on the specific organ and on the age group. The infant is the most restrictive age group for the dose rate calculations and the most restrictive organ is the thyroid via either the inhalation or grass-cow-milk pathway. The dose from tritium, I-131, I-133, and particulate is calculated by assuming a cow on pasture 4.5 miles west of the plant unless there is a milk producer in a more conservative location. At that location the reference atmospheric deposition factor, D/Q, is equal to 5 x 10 m Sampling and analysis is performed as outlined in Technical Specification Table 4.11-2. Principle gamma emitters for batch gaseous effluents which are released via pathways (i.e. Plant Vent) with continuous radioiodine and particulate radionuclide sample trains are considered to be the Noble Gases.

3 ~ 2ol Gaseous advaste 8 stem Radioactive and potentially radioactive gases from units 3 and 4 containment buildings, the auxiliary building, unit 4 spent fuel pit, radwaste building and laundry area are released via the monitored plant vent after passing through filter systems. Radioactive waste gases from the primary systems (CVCS hold-up tanks) are stored in gas decay tanks to reduce activity levels by radioactive decay prior to release via the plant vent. The unit 3 spent fuel pit area is ventilated via its'wn monitored vent after passing through a filtering system.

18 06/25/91

L lpl

The steam jet air ejectors from each unit are vented through monitored release pathways. Other steam losses concurrent with primary to secondary leakage are unmonitored and gaseous activity must be accounted for.

3.2.2 Radioactivit in Gaseous Effluent Radionuclides other than noble gases in the gaseous effluents are measured by the radioactive gaseous waste sampling and analysis program described in'echnical Specification Table 4.11-2. Noble gas radionuclides are measured by continuous monitors in the four release points. The gaseous effluent streams monitoring points, and effluent discharge points are illustrated schematically in Figure 3-1.

The measured radionuclide concentrations in gaseous effluents from the plant are used for estimating off-site radionuclide concentrations and radiation doses. Sampling and analyses are performed consistent with the require-ments of Technical Specification Table 4.11-2.

The radioactive iodines and particulate radionuclides from continuous releases and batch releases ( Containment Purges and Gas Decay Tanks are released via the Plant Vent ) are determined by charcoal and filter samples removed weekly from continuous sample trains installed at each release point (plant vent, condenser air ejectors and Unit 3 Spent Fuel Pit, vent). Tritium activity is determined on monthly grab samples from the plant vent, condenser air ejector, and Unit 3 Spent Fuel Pit and by a grab sample from each containment purge.

Additional grab samples are obtained and analyzed if the conditions identified in Notes 4,5,6 and 7 of Technical Specification Table 4.11-2 exist, i.e., tritium grab samples once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded, tritium grab samples at least weekly from the spent fuel pool ventilation exhaust when spent fuel is in the spent fuel pool, and sampling shall also be performed at least once per day for at least 7 days following each shutdown, startup. or THERMAL POWER change exceeding 154 of RATED THERMAL POWER in one (1) hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing if:

analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has increased by more than a factor of 3; and (2) the noble gas activity monitor shows that the effluent activity has i~.creased by more than a factor of 3.

19 06/25/91

Activities measured by these additional samples should be included in the cumulative dose calculations.

Noble gas activity released is measured by continuous noble gas monitors installed in each discharge'point for release types listed in Technical Specification Table 4.11-2. The quantity of radioactive noble gas activity not accounted for by grab samples can be determined by integrating the release rate measurement from each effluent noble gas monitor. The total measured radioactivity discharged via a stack or vent during a specific time period can be determined from the effluent monitors by:

N 'F g

3.53x10 5'h (11) where:

Qj total measured gaseous radioactivity release via a stack or vent during counting interval j, (pci)

Nj counts accumulated during counting interval j, (counts = N(cpm) x t (min))

discharge rate of gaseous effluent stream, (ft /min) 3.53 x 10 conversion constant, ( ft~/cm~)

effluent noble gas monitor calibration or counting rate response for noble gas gamma cpm radiation P Ci

/cm'he distribution of radioactive noble gases in a gaseous effluent stream is determined by gamma spectrum analysis of gas samples from that stream., Results of previous analyses may be averaged to obtain a representative distri-bution.

20 06/25/91

rt If f< represents the fraction of radionuclide iisotopic in a given effluent stream, based on the distribution of that stream, then the quantity of radionuclide i released in a given gaseous effluent stream during counting inter-val j's:

Q= Q)

~

f; (12) where:

Q); quantity of radionuclide i released in a given gaseous effluent stream during counting interval j, (pCi) the fraction of radionuclide i released in a given effluent stream In the event the radioactive noble gas distribution is not obtainable from sample(s) taken during the current period the distribution will be obtained from recent data if available or from Table 3-2.

Some gaseous effluents from both Units 3 and 4, whose sources are identified in Table 3-1, discharge in common through the plant vent. To assure that the effluents are within allowable limits per reactor, the measured release from the plant vent is apportioned to each unit on a ratio equal to the ratio of specific isotopic concen-trations in the primary coolant in the two reactors. An alternate method is to allocate effluent releases equally to both Units 3 and 4.

Iodine and particulate release contributions will also be adjusted to account for specific containment purge releases.

3.3 Dose ate Bffluent 'eous Technical Specification 3.11.2.1 provides that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following: <500 mrem/year to the total body and <3000 mrem/year to the skin due to noble gases and 51500 mrem/year to any organ due to I-131, I-133, tritium and all radioactive materials in parti'culate form with half-lives greater than 8 days.

21 06/25/91

Compliance with the limits on dose rate from noble gases is demonstrated by establishing effluent monitor alarm setpoints such that an alarm will occur at or before a dose of the combined releases for noble gases is reachedrateforlimitthe release types listed in Technical Specification Table 4.11-2.

If an alarm occurs when the monitor setpoint is at or below the limit, compliance may be assessed by comparing the monitor record with the setpoint (limit) calculated in accordance with Section 3.6 or a more conservative method. In the event an alarm occurs and the monitored release exceeds the setpoint limit, then compliance shall be evaluated by calculating dose rates in accordance with Sections 3.3.1 and 3.3.2.

The alarm setpoints shall be derived on the basis of the radionuclide distribution from a measured gamma spectrum, a historical gamma spectrum dominated by Xe-133 or by assuming the total noble gas activity is Xe-133. If Xe-133 is the dominant radioactive gas in the airborne effluent, the gamma dose rate to a person's body is expected to be a larger fraction of the 500 mrem/year limit than is the sum of beta and gamma dose rates to the skin limit of 3000 mrem/year.

Thus, a gaseous effluent monitor setpoint may be derived on the basis of whole body gamma dose rate alone such that an alarm occurs at or before the whole body dose rate off-site exceeds 500 mrem/year as given in Technical Specification 3.11.2.1.

3 3 1

~ ~ Total Bod Dose Rate The total body dose rate from radioactive noble gases may be calculated at any location off-site by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases. The dose rate is calculated using the equation Dm X. 1 'Pg g t gg (13) where:

D Dose rate to total body from noble gases,(mrem/year)

X atmospheric dispersion factor at the off-site location of interest, (sec/m~)

22 06/25/91

tf t = Averaging time of release, i.e., increment of time during which Q< was released, (year)

Q,. = quantity of noble gas radionuclide during the averaging time, (pCi) i released P factor converting time integrated concentration of noble gas radionuclide ground-level to total body dose, i at mrem

( see Reference Table 3-4.

Since dose rate limits for airborne effluents apply everywhere off-site, compliance is assessed and alarm setpoints determined at the site boundary where the minimum atmospheric dispersion from the plant (maximum X/Q) occurs. Ordinarily, that location is selected on the basis of .reference meteorology data in Table 3-6. According to those data, the minimum dispersion off-site occurs at the site boundary 1950 meters SSE of the plant where X/Q = 5.8 x 10 ~ sec/m~. Alternately, averaged meteorology data coincident with the period of release being evaluated may be used.

3 ' ' Skin Dose Rate The dose rate to skin from radioactive noble gases may be calculated at any location off-site by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases. The dose rate to skin is calculated using the equation (14) where:

dose rate to skin from radioactive noble gases, (mrem/year) 23 06/25/91

0 alt

SP) factor converting time integrated concentration of noble gas radionuclide at ground level, to ski dose from beta i

Reference pCi ~ sec/m Table 3-4 1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mrem/mrad)

A, factor for converting time integrated concentration of noble gas radionuclide i in a semi-infinite clou , to air do e from its gamma radiation, m ad pCi sec/m

~

listed in Table 3-3 Since dose rate limits for airborne effluents apply everywhere off-site, compliance is assessed and alarm setpoints determined at the site boundary where the minimum atmospheric dispersion from the plant (maximum X/Q) occurs. Ordinarily, that location is selected on the basis of reference meteorology data in Table 3-6.

According to those data, the minimum dispersion off-site occurs at the site boundary 1950 meters SSE of the plant where X/Q = 5.8 x 10 " sec/m~. Alternately, averaged meteorology data coincident with the period of release being evaluated may be used.

3 ' ' H-3 I-131 I-133 and Particulate Dose Rate The dose rate to any organ due to H-3, I-131, I-133 and

'adioactive material in particulate form with a half life of more than 8 days is calculated with the equation.

1, Xd~~

36QQQ g ~ dk anzP (15) where:

dose equivalent rate to body organ n of a person in age group a exposed via pathway p to radionuclides i identified in all analysis k of effluent air, (mrem/year) 3600 = conversion constant, (sec/hr) period of time over which the effluent rel-eases are averaged, (hr) 24 06/25/9 1

I

= atmospheric dzspersxon factor I'QQ ad)usted for depletion by deposition(sec/m ) .(Alternately X/Q, unadjusted, may be used).

Q,.< = quantity of radionuclide time increment t i released during based on analysis k, (pCi).

a factor relating the airborne concentration snip time integral of radionuclide i to the dose equivalent to organ n of a person in age group a exposed via pathway p (inhalation),

mrem r pCi/m  ; See Appendix A.

When the dose rate due to H-3, I-131, I-133 and radio-nuclides in particulate form is calculated for the purpose of assessing compliance with Specification 3.11.2.1, a hypothetical infant located where the minimum atmospheric dispersion from the plant occurs is assumed as the receptor.

For the radioiodines and particulates with half-lives greater than eight days, the effective dose transfer factor, TA, ~, is based solely on the radioiodines (I-131, I-133). This approach was selected because the radioiodines contribute essentially all of the dose to the infant's thyroid via the inhalation and the grass-cow-milk pathway. The infant's thyroid via the inhalation pathway is the critical organ and controlling pathway respectively for the releases of radioiodines and particulates.

Ordinarily, the dose rate calculation will be based on the location of minimum dispersion adjusted for deposition according to the reference meteorology data in Table 3-7. According to those data, the minimum dispersion offsite occurs at the site boundary 1950 meters SSE of the plant and the XQQ value is 5.0 x 10 ~

sec/m~. That location is identzfied in Figure 3-2.

Alternately, averaged meteorological dispersion data coincident with the period of release may be used to evaluate the dose rate. These radionuclide concentrations in airborne effluents, Q<, are measured according to the sample and analysis scheYule in Technical Specification Table 4.11-2.

25 06/25/9 1

3.4 Dose-Noble Gases Technical Specification 3.11.2.2 requires that the air dose per reactor at and beyond the site. boundary due to noble gases released in gaseous effluents shall be limited during any calendar quarter, to <5 mrad for radiation and <10 mrad for beta radiation and duringgamma any calendar year, to <10 mrad for gamma radiation and <20 mrad for beta radiation.

3~4~1 Noble Gas Gamma Radiation Dose Specification 4.11.2.2 requires the cumulative dose contributions be determined at least once per 31 days to verify that the accumulated air dose due to gamma radiation does not exceed the'limits for the current quarter and year.

The gamma radiation dose to air offsite as a consequence of noble gas discharged from each unit can be calculated with the equation go+

I 0,8 g

~

+o~g rcpt (16) where:

D Y

noble gas gamma dose to air due to a mixed mode release, (mrad) 0' a conservatism factor which, in effect, increases the estimated dose to comp-sate for variability in radionuclide distribution x/0 atmospheric dispersion factor at the off-site location of interest, (sec/m~)

jeff effective gamma air dose factor converting time-integrated, ground-level, total activity concentration of radio-active noble gas, to air dose due to gamma radiation. This factor has been derived from noble gas radionuclide

'distributions in routine operational releases. Refer to Appendix B for a detailed explanation. The effective gamma air dose factor is:

26 06/25/91

A )f = 1.4 x 10 mrad pCi ~

sec/m )

Q. = the measured gaseous radioactivity released via a stack or vent during a single counting interval j, (pCi)

Specification 4.11.2.2 is satisfied by calculating the noble gas gamma radiation dose to air at the location identified in Figure 3-2. At that location, 1950 meters SSE of the Plant, the reference atmospheric dispersion factor to be used" is X/Q = 5.8 x 10 ~ sec/m~.

Alternately, Specification 4.11.2.2 may be satisfied by calculating the gamma dose to air with the equation (17) where:

the fraction of radionuclide i released in a given effluent stream A I= factor converting time integrated, ground level concentration of noble gas radionuclide i to air do e from gamma ra iation listed in Table 3-3, mrad pCi ~ sec/m Noble Gas Beta Radiation Dose Technical Specification 4.11.2.2 requires an evaluation be performed once per 31 days to verify that the accumulated air dose due to beta radiation does not exceed the limits as given in 3.4 above.

The beta radiation dose to air offsite as a consequence of noble gas discharged from each unit can be calculated with the equation:

Dp = '+ 'Ap~~~'g (18) 27 06/25/9 1

.where:

noble gas beta dose to air due to a mixed mode release, (mrad) 0.8 a conservatism factor which, in effect, increases the estimated dose to comp-ensate for variability in radionuclide distribution Apef f effective beta air dose factor converting time-integrated, ground-level, total activity concentration of radioactive noble gas to air dose due to beta radiation. This factor has been derived from noble gas radionuclide distributions in routine operational releases. Refer to Appendix B for a detailed explanation.

The effective beta air dose factor is:

-5 Ap)) = 3.4 x 10 mrad pCi ~ sec/m~

Specification 4.11.2.2 is satisfied by calculating the noble gas beta radiation dose to air at the location identified in Figure 3-2. At that.

location, 1950 .meters SSE of the Plant, the reference atmospheric dispersion factor to be used is X/Q = 5.8 x 10 sec/m~.

Alternately, Specification 4.11.2.2 may be satisfied by calculating the beta radiation dose to air with the equation Dp=+ gg'fg'Apg 0 (19) where:

A>, factor converting time-integrated, ground level concentration of noble gas radionuclide i to air dose from beta radiation, listed in Table 3-3: .

pCi ~ sec/m )

28 06/25/91

0 0

3.5 Dose Due to Iodine Tritium and Particulates in Gaseous Effluents Technical Specification 3.11.2.3 requires the dose per reactor to a member of the public due to I-131, I-133, tritium, and particulates with half-lives greater than 8 days in airborne effluents released to areas at or beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

3 'o1 Determinin the uantit of Iodine Tritium and Particulates Radionuclides, other than noble gases, in gaseous effluents that are measured by the radioactive gaseous waste sampling and analysis program described in Technical Specification Table 4.11-2 are used as the release term in dose calculations. Airborne releases are discharged either via a stack above the top of the containment building or via other vents and are treated as a mixed mode release from a single location. Releases of steam from the secondary system concurrent with primary to secondary leakage will also result in the release of activity to the atmosphere. For steam generator blowdown, using a blowdown sample analysis, it is assumed that 54 of the I-131 and I-133 and 33%

of the tritium in the blowdown stream become airborne with the remainder staying in the liquid phase. For other unmonitored releases, the quantity of airborne releases may be det-ermined by performining a steam mass balance.

For each of these release combinations, samples are analyzed weekly, monthly, quarterly, or for each batch releases according to Table 4.11-2.

Each sample provides a measure of the concentration of specific radionuclides, C<, in gaseous effluent discharged at flow, F, during a time increment, ~t. Thus, each release is quantified according to the relation Q)~= C)~')'d t)

(20) 29 06/25/91

where:

the quantity of radionuclide i released in a given effluent stream based on analysis k, (pCi)

C,.z = .concentration of radionuclide i in a gaseous effluent identified by analysis k, ( pCi/cc) time increment j during which radio-nuclide i at concentration C<z is being discharged, (sec).

FJ = effluent stream discharge rate during time increment ~tJ, (cc/sec)

Note: A steam mass to determine other unmonitored releases may be determined using the following M- (M + M) (21) where:

the measured mass of makeup water entering the secondary system during time interval ~tJ (gm /sec).

M, the measured mass of water discharged from the secondary system as liquid during time interval at, e.g. steam generator blowdown.

MS the measured mass of steam or non-condensible gases discharged from the secondary system during time interval

~t>. e.g. air ejector discharge.

Note: it is assumed that all of the I-131, I-133 and tritium in the other unmonitored releases are discharged as airborne species. It also assumed that gm/sec is equivalent to cc/sec.

30 06/25/9 1

1f 3 ' ' Calculatin the Dose Due to Xodine Tritium and Particulates A person may be exposed directly to an airborne concentration of radioactive material discharged in an effluent gaseous stream and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates should account for the exposure via the following pathways:

direct radiation from airborne radionuclides except noble gases 0 inhalation 0 direct radiation from ground plane deposition 0 fruits and vegetables 0 air-grass-cow-meat 0 air-grass-cow-milk Of all these pathways, the air-grass-cow-milk pathway is by far the controlling dose contributor.

The radioiodines contribute essentially all of the dose, by this pathway, with I-131 typically contributing greater than 95%. The dose transfer factors for the radioiodines are much greater than for any of the other radionuclides. The critical organ is the infant's thyroid. For this reason, the potential critical organ dose via airborne effluents can be estimated by determining an effective dose transfer factor for the radioiodines based on the typical radioactive effluent distribution, the air-grass-cow-milk pathway, and the infant thyroid as the receptor. Then for conservatism the total cumulative release of all radioiodines and particulates can be used along with the effective dose transfer factor to determine a conservative estimate of the infant thyroid dose.

Technical Specification 4.11.2.3, requires an evaluation be performed once per 31 days to verify that the accumulated total body or organ dose for the current calendar quarter and calendar year does not exceed the limit as given in 3.5. Dose commitment due to iodines and particulates may be calculated by using the following equation 3.17MO, D,~ .V g2k k 0 8 g 131+

(22) 31 06/25/91

li

'1

where:

DM~ the dose commitment to an infant's thyroid received from exposure via the air-grass-cow-milk pathway and attri-butable to iodines identified in analysis k of effluent air, (mrem) 3.17 x 10 = conversion constant, (yr/sec) 0.8 a conservatism factor which, in effect, increases the estimated dose to comp-pensate for variability in the radio-nuclide distribution.

D/Q relative deposition rate onto ground from a mixed mode atmospheric release (m ~)

TG131 factor converting ground deposition of radioiodines to the dose commitment to an infant's thyroid expos d via the gras-cow-milk pathway, mrem r pCi/m csee the quantity of radionuclide I-133) released in a given effluent i (I-131 and stream based on a single analysis k, (pCi)

Specification 4.11.2.3 is satisfied by calculating the dose to an infant from iodine and particulates discharged as airborne effluents via the air-grass-cow-milk pathway and is evaluated by assuming a cow on pasture 4.5 miles west'f the plant. (There are no milk or meat animals within 5 miles). At that location the reference atmos-pheric deposition factor is D/Q = 5 x 10 'o m When equation 22 is used to estimate the critical organ dose commitment, the effective dose transfer factor is:

TG)~i 6 ~ 5 x 10 em pCi/m ~ sec The reference data from which TG was derived are summarized in Table B-2 of Appenhi~x B.

Alternately, the requirement of Specification 4.11.2.3, to perform once per 31 days determ-minations of dose commitments due to radioiodine, tritium and radioactive particul"tes in effluent air may be made by using equations (22), (23),

(24), and (25):

32 06/25/91

The dose commitment from exposure to airborne concentrations of radioactive material other than noble gas from a release, Q~k, via the inhalation and irradiation pathways is calculated with the equation Da>> = 3o17>10 ' ' g)k 'TA P (23) where:

ank the dose commitment to organ n of a person in age group a due to radio-nuclides identified in analysis k of an air effluent, (mrem).

3.17 x 10 8 conversion constant, (yr/sec)

X+Q = atmospheric dispersion factor adjusted for depletion by deposition, (sec/m~).

Qo the quantity of radionuclide i released in a given effluent stream based on analysis k, (pCi) .

= a factor converting airborne concen-tration of radionuclide i to dose comm-TAan~p itment to organ n of a person in age group a where exposure is directly due to airborne material via pathway p (inhalation or externa exposure to the plume), m em pCi/m ;See Appendix A.

The dose to a person from iodine and particulates discharged as airborne effluents via the inhalation and irradiation pathways is evaluated at the nearest garden 3.6 miles west northwest of the plant. At that location, the reference atmospheric dispersion factor adjusted for depletion by deposition is XQQ = 1 x 10 sec/m, (Table 3-7).

o The dose commitment via exposure pathways involving radionuclide deposition from the atmosphere onto vegetation or the ground is calculated with the equation 33 06/25/9 1

D~ =3 17x10 ' ' ' 2G

~

gg>>

p (24) where:

D/Q = relative deposition rate onto ground from a mixed mode atmospheric release, (m ~)

<<snap = factor converting ground deposition of radionuclide i to dose commitment to organ n of a person in age group a where exposure is due to radioactive material via pathway p (direct radiation from ground plane deposition, fruits and vegetables, air- rass-cow-meat, o air-grass-cow-milk), mrem r pCi/m csee , See Appendix A.

The dose to a person from iodine and particulates discharged as airborne eff-luents via the air-grass-cow-milk pathway is evaluated by assuming a cow on pasture 4.5 miles west of the plant. (There are no milk or meat animals within 5 miles). At this location, the reference atmospheric deposition factor is D/Q = 5 x 10 '

(Table 3-8).

0 The concentration of tritium in vegetat-ion is a function of the airborne concen-tration rather than the deposition. Thus, the dose commitment from airborne tritium via vegetation(fruit and vegetables),air-grass-cow-milk, or air-grass-cow-meat pathways is calculated with the equation D~ = 3 17x10-s, + . g>j.. TA (25) where:

X/Q = atmospheric dispersion factor at the off-site location of interest (sec/m~)

34 06/25/91

0 The dose to a person from tritium via the vegetation (fruit and vegetables),

air-grass-cow-milk, or air-grass-cow-meat pathways is evaluated at the nearest garden (with residence assumed) 3.6 miles west northwest of the plant. At that location, the reference atmospheric dis-persion factor is X/Q = 1 x 10 ~ sec/m~.

0 The dose commitment via a given pathway as a result of measured discharges from a release point is accumulated with (26) where:

the dose commitment to organ n of a person in age group a k = the counting index; either:

it may represent p, analysis of a grab sample w, a weekly sample analysis m, a monthly composite analysis, or q, a quarterly composite analysis 3 ' Effluent Noble Gas Monitor Alarm Set oint The radioactive gaseous effluent monitoring instrumen-tation channels alarm setpoints are set in accordance with Specification 3.3.3.6, to ensure the limits of Specification 3.11.2.1 are not exceeded.

Each radioactive noble gas effluent monitor setpoint is derived either on the basis of total body dose equivalent rate or noble gas concentration, at or beyond the site boundary. The setpoint derivations assume that noble gas releases occur at ground-level.

For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways:

35 06/25/91

I Preferably, the radionuclide distribution is obtained by gamma spectrum analysis of identifiable noble in effluent gas samples. Results of analysis of onegases or more samples may be averaged to obtain a representative spectrum.

In the event a representative distribution is unobtain-nable from measurements by the radioactive gaseous waste sampling and analysis program, historical spectrum appearing in Table it may be based upon a 3-2.

Alternately, the total activity concentration of radioactive noble gases may be assumed to be Xe-133.

This approach is valid because Xe-133 contributes about 994 of the noble gas activity.

A noble gas effluent monitor setpoint, based on dose rate, is calculated with the equation below, or a method which gives a lower setpoint value.

Qc, S = 1.06 + Bkg Cg 'Fg (27) where:

S = The alarm setpoint, (cpm) 1.06 conversion constant; 500 mrem/yr~ 60 1m~/106cm~

sec/min ~ 35. 37 ft /m~~

monitor re ponse to activ ty concentration of effluent, pCi/cm flow of gaseous effluent stream, i.e., flow past the monitor, (ft~/min) x/0 atmospheric dispersion factor at the off-site location of .interest, (sec/m3)

C) concentration of radionuclide i in gaseous effluent (pCi/cc).

DF, factor converting ground-level or split-wake release of radionuclide i to the total body dose equivalent ate at t e location of potential exposur , re yr~ pCi/m;See Table 3-5.

36 06/25/9 1

0 tf h4 AC

Sf A factor to allow for multiple sources from different or common release points. The allow-owable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

Atmospheric dispersion depends upon the local atmospheric conditions. For the purpose of calculating a radioactive noble gas effluent monitor setpoint, the atmospheric dispersion factor, X/Q, will be based on prevailing meteorological conditions or on reference meteorological conditions. The minimum atmospheric dispersion off-site derived from reference meteorological conditions at the site boundary is 5.8 x 10 ~ sec/m~ at a location 1950 meters south southeast of the plant.

The applicable dose conversion factors, DF<, for deriving setpoints are in Table 3-5.

The limiting factor for Equation 27 is the total body dose rate limit of 500 mrem/year which is included in the 1.06 conversion factor. The use of the total body dose assumes that the total body dose will be the controlling dose rate and the dominant contributor to this dose will be Xe-133.

Setpoints may also be calculated based on concentration using the equation below, or a method which gives a lower setpoint value.

MPC Il Sr 4 7x10i F '/g + BKG (28) where:

MPC = the unrestricted area maximum concentration for the effluent noble gas mixture. The MPC for noble gas is calculated from the distribution of noble gases in the release with the equation:

MPC = Cg +

(29) 37 06/25/91

where:

MPC; = 10CFR20, Appendix B, Table 2, Column 1 value 4.7 x 10 .CI = conversion constant, 1m~ x 1 min 35.37ft~ 60 sec monitor esponse to activity concentration of pci/cm'low of gaseous effluent stream, i.e. flow past the monitor (ft~/min) .

X/Q atmospheric dispersion factor at the off-site location of interest (sec/m~).

S] A factor to allow for multiple sources from different or common release points. The allow-able operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

3.7 Pro'ected Dose for Gaseous Effluents Technical Specification 3.11.2.4 requires that the gas decay tank system shall be operable and used to reduce radioactive materials in gaseous waste prior to their discharge if the projected gaseous effluent dose per reactor due to gaseous effluent releases to areas at and beyond the site boundary when averaged over 31 days exceeds 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation, and the ventilation exhaust treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge if the projected gaseous effluent dose per reactor due to gaseous effluent releases to areas at and beyond the site boundary when averaged over 31 days exceeds 0.3 mrem to any organ.

Technical Specification 4.11.2.4.1 requires the doses, to areas at and beyond the site boundary, due to radioactive material released in gaseous effluent to be projected at least once per 31 days.

This requirement is satisfied by extrapolating the dose to date during the current month to include the entire month. The dose to date is calculated as described in Sections 3.4.1, 3.4.2, and 3.5.2.

38 06/25/91

The dose is projected with the relation:

p 31 'D X (30) where:

P = the projected dose during the month, (mrem) 31 = number of days in a calendar month, (days)

X = number of days in current month to date represented by available radioactive effluent sample, (days)

D = dose to date during current month calculated according to Sections 3.4.1, 3.4.2, and 3.5.2, (mrem), i.e., gamma, beta, or organ dose respectively.

Alternately, the monthly dose may be projected by computing the dose accumulated during the most recent month and assuming the result represents the projected dose for the current month. The dose during the proceeding month will be computed as described in Sections 3.4.1, 3.4.2, and 3.5.2.

39 06/25/9 1

Steam Steam Sa(sties Dumps Unit 3 Unit O Dumps Sofeltos Vent Tv*Ines Turbines H In Aux. Prtmln Food Jot xnausl Aux Prtmary Condense Pum s Prfmary Condenser Coolant

'eed Pum s rtmln Coolant In Exhaust x aust Exhoust Exhaust Exhaust Blowdown S.JA.E. ss Blowdown S.J.A.E. ~ ~

Flash and Gland Flash and Gland Tank Seel Exhaust Tank Seel Exhaust 35.000 cfm 35,000 cfm 35.000 Roughing Unit 3 Unit O ctm filter Containment Conlalnmenl roug ning fitter 35.000 cfm To CVCS Roughing Holdup Tanks filler for reuse Laundry ctm 525 cu.ft. Area Cas Decay Tank (6) 11,200 CVCS s Waste gas clm Holdup compressors Inleaka go HEPA Filter Tanks 40,000 ofm 13,500 ofm Auxiliary Bldg. Prottllers Outstde AII 13,500 cfm VenlllaHon System 40,000 ofm Roughing HEPA Filler Fitters HEPA Exhaust HEPA 1000 Filter 1000 cf Filter 20,000 cfm Unit 3 Unit O ofm Fuel Pil 20,000 Fuel PH Area cfm Area 2000 Protllter Proliller 2000 afm ofm 7500 cfm tntoakago Inteakage How Rad Waste Building HEPA Pre flit sr Filter 7500 cfm

~ CVCS

-- Chemical and Volume Steam Jot Air E]octor Control System SJAE Eltluenl Monttortng Instrumentalton Figure 3-1 40 06/25/91

P.

~a) ag 7M

~

l xa J

, >c5-,

Figure 3-2 Locations .>t "hick Ooses Due to kirborne - luencs F om the .:key Poinc Plane are CalaxTacnd

1. Beta md amma Ooses to Ai < 1950 m SSF

2. Aax .-,ai'y "=xyosed Personi 5800 m/'(P.v Assumed 3ee" and Hi'c.'z Co@i 7250 m 9 41 07/20/84

Table 3-1 Atmospheric Gaseous Release Points at the Turke Point Units 3 and 4 Effluent Release Source Poi t Gas decay tanks Plant vent Radwaste Building Plant vent Auxiliary Building Plant vent Containment Purge Plant vent No. 4 spent fuel pit Plant vent No. 3 spent fuel pit Spent fuel pit vent Air ejectors Turbine deck Steam generator Blowdown vent blowdown 42 07/20/84

Table 3-2 Distribution of Radioactive Noble Gases in Gaseous Eff uent from Turke Point Units 3 & 4 Nuclide elease fraction ~~ ~

Ar-41 9.2E-3 Kr-83m Kr-85m 2.5E-4 Kr-85 2 'E-4 Kr-87 1.6E-4 Kr-88 2.1E-4 Xe-131m 4.4E-4 Xe-133m 1.2E-3 Xe-133 9.9E-1 Xe-135m 8.0E-4 Xe-135 3.4E-3 Xe-137 Xe-138 3.7E-4 Based on measured discharge from Turkey Point Units 3 &

4 during 1978 through 1980.

To estimate radionuclide concentrations in a sample in which only the total activity concentration has been measured, multiply the total activity concentration by the fraction of respective radionuclides listed here.

43 07/20/84

Table 3-3 Transfer Factors for Maximum Offsite Air Dose Air Dose T ansfer Factors Ap(

mrad Radionuclide Ci sec Kr-83m 6.1E-7 9. 1E-6 Kr-85m 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-5 Kr-87 2.OE-4 3.3E-4 Kr-88 USE-4 9.3E-5 Kr-89 5.5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-131m 4.9E-6 3.5E-5 Xe-133m 1.OE-5 4.7E-5 Xe-133 1.1E-5 3.3E-5 Xe-135m 1.1E-4 2.3E-5 Xe-135 6.1E-5 7.8E-5 Xe-137 4.8E-5 4.OE-4 Xe-138 2.9E-4 1.5E-4 Ar-41 2 'E-4 1.OE-4 Ref: Regulatory Guide 1.109, Revision 1, Table B-1 Note: Values in the regulatory guide are in units of pCi*yr, to convert to units of pCi*sec multiply by a factor of 3.171 E-2.

44 07/20/84

Table 3-4 Transfer Factors for Maximum Dose to a Person Offsite due to Radioactive Noble Gases A Dose Transfer Factors P ) Sp; Radionucl'de Ci sec m Kr-83m 2.4E-9 Kr-85m 3.7E-5 4. 6E-5 Kr-85 5.1E-7 4.2E-5 Kr-87 1.9E-4 3.1E-4 Kr-88 4.7E-4 7.5E-5 Kr-89 5.3E-4 3.2E-4 Kr-90 4.9E-4 2.3E-4 Xe-131m 2.9E-6 1.5E-5 Xe-133m 8.OE-6 3.1E-5 Xe-133 9.3E-6 9.7E-6 Xe-135m 9.9E-5 2.3E-5 Xe-135 5.7E-5 5.9E-5 Xe-137 4.5E-5 3.9E-4 Xe-138 2.8E-4 1.3E-4 Ar-41 2.8E-4 8.5E-5 Ref: Regulatory Guide 1.109, Revision 1, Table B-1.

Note: Values in the regulatory guide are quoted in units of pCi*yr, to convert to units of pCi*sec multiply by a factor of 3.171 E-2.

45 07/2 0/84

Table 3-5 Dose Conversion Factors for Deriving Radioactive Noble Gas Effluent Monitor Setpoints Factor DF< for Ground-level or Split-Wake Release Radionuclide Kr-83m 7.56 E-2 Kr-85m 1.17 E3 Kr-85 1.61 E1 Kr-87 5.92 E3 Kr-88 1.47 E4 Kr-89 1 66 E4 Kr-90 1.56 E4 Xe-131m 9.15 E1 Xe-133m 2.51 E2 Xe-133 2.94 E2 Xe-135m 3.12 E3 Xe-135 1.81 E3 Xe-137 1.42 E3 Xe-138 8.83 E3 Xe-139 5.02 E3 Ar-41 8.84 E3 46 07/20/84

Table 3-6 REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS X sec Q 3 X/{} are annual averaged factors of atmospheric dispersion of a mixed mode gaseous release from the Turkey Point Plant at. various distances and compass points from the plant.

Period of record: 01/01/76 to 12/31/77 BASE DISTANCE /

IN MILES KILOMETERS MILES .25 .75 1.50 2.50 3.50 4.50 5.50 7.00

.40 1.21 2.41 4.02 5.63 7.24 8.85 11.26 NNE 8.9E-07 1.9E-07 8.3E-OS 5.0E-08 3. OE-08 2. 2E-OS 1. 9E-08 1.4E-08 NE 6.9E-07 1.5E-07 6.3E-08 3.8E-OS 2.5E-OS 2.1E-08 1.3E-08 1.0E-08 ENE 8.4E-07 1.4E-07 7.5E-08 3.9E-OS 2.8E-08 2.3E-OS 1.8E-OS 1.3E-08 E 8.6E-07 1.9E-07 9 'E-08 5.1E-OS 3.6E-OS 2.7E-08 2.2E-OS 1.7E-OS ESE 6.6E-07 1.5E-07 7.9E-OS 4.5E-08 2.9E-08 2.3E-08 1.9E-08 1.2E-OS SE 1.6E-06 2.8E-07 1.1E-07 6.1E-OS 4.2E-08 3.0E-OS 2.6E-08 2.1E-OS SSE 4.9E-06 9.2E-07 3.6E-07 1.8E-07 1.1E-07 9.0E-08 7.1E-OS 4.9E-OS 2.9E-06 4.6E-07 1.8E-07 1.0E-07 7.8E-08 5.4E-OS 4.6E-08 3.3E-OS SSW 6.5E-07 1.6E-07 6.5E-08 4.6E-08 2.4E-08 2.6E-08 1.8E-OS 1.4E-08 SW 1.5E-06 3.2E-07 1.4E-07 7.9E-08 4.9E-08 3.2E-08 2.7E-08 1.9E-OS 47 07/20/84

Table 3-6 continued Page 2 REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS MILES .25 .75 1.50 2.50 3.50 4.50 5.50 7.00

.40 1.21 2.41 4.02 5.63 7.24 8.85 11.26 WSW 2.9E-06 6.3E-07 2.3E-07 1.3E-07 7.6E-08 5.5E-08 4.2E-08 3. 1E-08 6.3E-06 1.3E-06 5.2E-07 2.6E-07 1.7E-07 1.2E-07 9.2E-08 6.6E-08 4,1E-06 8.7E-07 3. 4E-07 1.7E-07 1.2E-07 8.1E-OS 6.3E-OS 4.2E-OS 2.7E-06 6.0E-07 2.4E-07 1.2E-07 7.6E-08 5.1E-08 4.3E-OS 3.2E-OS 1.4E-06 2.9E-07 1.2E-07 6.8E-OS 4.5E-08 3.0E-OS 2.4E-08 1.5E-OS N 9.5E-07 2.1E-07 8.5E-08 4.5E-OS 3.2E-08 2.2E-08 1.7E-08 1.3E-08 48 07/20/84

Table 3-6 continued Page 3 REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS X sec Q 3 X/Q are annual averaged factors of atmospheric dispersion of a mixed mode gaseous release from the Turkey Point Plant at various distances and compass points from the plant.

Period of record: 01/01/76 to 12/31/77 BASE DISTANCE IN MILES / KILOMETERS MILES 9.00 11.00 .79 5.00 1.00 2.00 2.75 4.30 14.48 17.70 1.27 8.04 1.61 3.22 4.42 6.92 NNE 9.8E-09 6.6E-09 1.8E-07 2.0E-08 1.4E-07 6.2E-08 4.4E-OS 2.3E-08 NE 7.3E-09 5.4E-09 1.5E-07 1.6E-08 1.1E-07 4.8E-08 3.5E-08 2.1E-08 ENE 1.1E-08 7.4E-09 1.4E-07 2.0E-08 1.0E-07 5.2E-08 3.6E-08 2.4E-08 E 1.3E-08 9.8E-09 1.7E-07 2.4E-08 1.3E-07 6.3E-08 4.6E-OS 2.8E-OS ESE 1.1E-08 9.6E-09 1.4E-07 2.0E-08 1.2E-07 5.7E-08 4.0E-08 2.4E-OS SE 1.5E-OS 1.3E-08 2.7E-07 2.7E-08 1.9E-07 7.8E-OS 5.5E-OS 3.1E-08 SSE 3.5E-08 2.7E-08 8.7E-07 7.9E-OS 6.3E-07 2.5E-07 1.6E-07 9.4E-OS 2.3E-OS 1.8E-OS 4.2E-07 5.0E-08 3.1E-07 1.3E-07 9.5E-OS 5.8E-OS SSN 9.4E-09 7.1E-09 1.5E-07 2.1E-08 1.1E-07 5.4E-OS 3.8E-08 2.5E-OS SW 1.4E-OS 1.0E-08 3.0E-07 2.9E-OS 2.3E-07 1.0E-07 6.9E-08 3.5E-OS 49

'07/20/84

Table 3-6 continued Page 4 REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS BASE DISTANCE IN MILES / KILOMETERS MILES 9.00 11.00 .79 5.00 1.00 2.00 2.75 4.30 14.48 17.70 1.27 8.04 1.61 3 '2 4.42 6.92 WSW 2.2E-08 1.8E-08 5.9E-07 4.8E-OS 4.3E-07 1.7E-07 1.0E-07 5.8E-OS 4.5E-OS 3.5E-08 1.2E-06 1.0E-07 9.0E-07 3.5E-07 2.3E-07 1.3E-07 2.9E-08 2.3E-OS 8.1E-07 7.1E-08 5.9E-07 2.3E-07 1.6E-07 8.6E-OS 2.0E-08 1.5E-08 5.6E-07 4.7E-OS 4.1E-07 1.6E-07 1.0E-07 5.6E-OS NNW 1.0E-08 8.3E-09 2.7E-07 2.6E-08 2.0E-07 9.1E-08 6.1E-OS 3.2E-OS N 1.0E-OS 7.2E-09 1.9E-07 2.0E-08 1.5E-07 5.9E-OS .4.0E-08 2.3E-OS NUMBER OF VALID OBSERVATIONS 16538 NUMBER OF INVALID OBSERVATIONS 1006 NUMBER OF CALMS LOWER LEVEL 195 NUMBER OF CALMS UPPER LEVEL 383 50 07/20/84

Table 3-7 REFERENCE METEOROLOGY DEPOSITION DEPLETED ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS

~X sec Q- 3 XgQ are annual averaged factors of atmospheric dispersion of a mixed mode gaseous release at various distances from the Turkey Point Plant which have been corrected for depletion from the plume by fallout and deposition.

Period of record: Ol/01/76 to 12/31/77 BASE DISTANCE /

IN MILES KILOMETERS SECT .25 .75 1.50 2.50 3.50 4.50 5.50 7.00

.40 1.21 2.41 4.02 5.63 7.24 8.85 11.26 NNE 8.7E-07 1.7E-07 7.3E-08 4.4E-08 2.7E-08 1.9E-08 1.6E-08 1.2E-08 NE 6.9E-07 1.4E-07 5.5E-08 3.3E-08 2.2E-08 1.7E-OS 1.2E-08 8.8E-09 ENE 8.0E-07 1.2E-07 6.5E-OS 3.4E-08 2.4E-OS 2.0E-08 1.6E-08 1.2E-OS E 8.6E-07 1.7E-07 7.6E-08 4.4E-08 3.1E-08 2.4E-08 1.9E-OS 1.5E-OS ESE 6.1E-07 1.3E-07 6.9E-08 3.9E-08 2.5E-08 2.0E-08 1.6E-08 1. 1E-08 SE 1.5E-06 2.6E-07 9.5E-OS 5.2E-08 3.4E-08 2.4E-08 2.1E-OS 1.7E-08 SSE 4.7E-06 8.2E-07 3.1E-07 1.5E-07 9.2E-08 7.4E-OS 5.8E-08 3.8E-OS 2.8E-06 4.2E-07 1.5E-07 8.5E-08 6.4E-08 4.4E-08 3.7E-OS 2.6E-OS SSW 6.1E-07 1.4E-07 5.6E-08 3.9E-08 2.0E-08 2.2E-08 1.5E-08 1.2E-OS SW 1.3E-06 2.8E-07 1.3E-07 6.7E-OS 4.2E-OS 2.7E-08 2.3E-08 1.5E-08 51 07/20/84

Table 3-7 Page 2 REFERENCE METEOROLOGY DEPOSITION DEPLETED ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS BASE DISTANCE IN MILES / KILOMETERS MILES .25 .75 1.50 2.50 3.50 4.50 5.50 7.00

.40 l. 21 2.41 4.02 5.63 7.24 8.85 11.26 WSW 2.7E-06 5.6E-07 2.1E-07 1.0E-07 6.4E-OS 4.6E-OS 3.5E-08 2.6E-OS 5.9E-06 1.2E-06 4.4E-07 2.2E-07 1.4E-07 9.9E-08 7.6E-OS 5.4E-OS 3.8E-06 7.7E-07 2.9E-07 1.5E-07 9.8E-OS 7.0E-08 5.4E-08 3.6E-08 2.5E-06 5.4E-07 2.1E-07 1.1E-07 6.8E-08 4.5E-OS 3.8E-08 2.8E-OS 1.4E-06 2.6E-07 1.1E-07 6.0E-OS 4.0E-OS 2.6E-OS 2.0E-08 1.3E-08 N 8.8E-07 1.9E-07 7.8E-08 3.9E-OS 2.8E-08 1.9E-08 1.5E-OS 1.1E-OS 52 07/20/84

Table 3-7 continued Page 3 REFERENCE METEOROLOGY DEPOSITION DEPLETED ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS BASE DISTANCE IN MILES / KILOMETERS MILES 9.00 11.00 .79 5.00 1.00 2.00 2.75 4.30 14.48 17.70 1.27 8.04 1.61 3.22 4.42 6.92 NNE 8.5E-09 6.0E-09 1.6E-07 1.8E-08 1.2E-07 5.5E-OS 3.8E-08 2.1E-OS NE 6.3E-09 4.5E-09 1.3E-07 1.4E-08 9.4E-OS 4.2E-08 3.0E-08 1.8E-OS ENE 9.0E-09 6.7E-09 1.2E-07 1.8E-08 9.1E-OS 4.5E-08 3.1E-08 2.0E-08 E 1.1E-08 7.9E-09 1.5E-07 2.1E-OS 1.2E-07 5.5E-OS 3.9E-OS 2.4E-OS ESE 8.8E-09 8.3E-09 1.3E-07 1.8E-08 1.0E-07 5.0E-08 3.4E-08 2.0E-08 SE 1.3E-08 1 'E-08 2.4E-07 2.3E-OS 1.7E-07 6.7E-OS 4 'E-08 2.6E-OS SSE 2.7E-08 2.1E-08 7.7E-07 6.4E-OS 5.6E-07 2.2E-07 1.3E-07 7.7E-OS 1.9E-08 1.3E-OS 3.8E-07 4.1E-08 2.7E-07 1. 1E-07 7.8E-08 4.8E-08 SSW 7.9E-09 5.7E-09 1.4E-07 1.8E-08 9.6E-08 4.7E-OS 3.2E-08 2.2E-08 SW 1.1E-OS 8.6E-09 2.7E-07 2.4E-08 2.0E-07 9.1E-OS 5.9E-08 2.9E-OS 53 07/20/84

Table 3-7 continued Page 4 REFERENCE METEOROLOGY ANNUAL AVERAGE ATMOSPHERIC DISPERSION FACTORS BASE DISTANCE IN MILES / KILOMETERS MILES 9.00 11.00 .79 5.00 1.00 2.00 2.75 4.30 14.48 17. 70 1.27 8.04 1.61 3.22 4.42 6.92 WSW 1.8E-08 1.4E-OS 5.2E-07 4.0E-08 3.8E-07 1.4E-07 8.7E-08 4.8E-OS 3.7E-OS 2.8E-OS 1.1E-06 8.6E-08 7.9E-07 3.1E-07 2.0E-07 1.0E-07 2.5E-OS 2.0E-08 7.3E-07 6.1E-08 5.1E-07 2.0E-07 1.4E-07 7.4E-08 1.8E-OS 1.3E-08 5.1E-07 4.1E-08 3.6E-07 1.4E-07 8.9E-OS 5.0E-08 9.1E-09 6.9E-09 2.4E-07 2.3E-OS 1.8E-07 7.7E-08 5.4E-OS 2.8E-OS N 8.7E-09 6.3E-09 1.8E-07 1.7E-08 1.3E-07 5.2E-OS 3.5E-08 2.0E-OS NUMBER OF VALID OBSERVATIONS 16538 NUMBER OF INVALID OBSERVATIONS 1006 NUMBER OF CALMS LOWER LEVEL 195 NUMBER OF CALMS UPPER LEVEL 383 54 07/20/84

~ ' ~

P

~ ~

I ~ ~ ~ ~

P ~ ~ ~ ~ ~ ~ ~

~ II ~

~ ~ ~ ~ ~ I

~ II ~ ~ ~ ~ II

~ ~ ~ ~ ~ I ~ ~

~

~

I ~

I ~

~ ~ I I

~

~ ~ ~ I I I I

~ I ~ I ~ ~

~

~

I '

Table 3-8 Page 2 REFERENCE METEOROLOGY ANNUAL AVERAGED RELATIVE DEPOSITION RATE BASE DISTANCE IN MILES / KILOMETERS MILES .25 .75 1.50 2.50 3.50 4.50 5.50 7.00

.40 l. 21 2.41 4.02 5. 63 '.24 8.85 11.26 WSW 2.3E-08 5.0E-09 1 5E-09 6.1E-10 3.2E-10 2.0E-10 1.4E-10 8.5E-11 5.7E-08 1.2E-08 3.5E-09 1.4E-09 7.6E-10 4.9E-10 3.3E-10 2.1E-10 4.1E-08 9.6E-09 2.7E-09 1.0E-09 5.7E-10 3.4E-10 2.4E-10 1.4E-10 2.4E-08 6.2E-09 1.7E-09 6.1E-10 3.1E-10 1.8E-10 1.3E-10 8.5E-11 NNW 1.2E-08 3.0E-09 9.5E-10 3.6E-10 2.0E-10 1.1E-10 7.5E-11 4.2E-11 N 5.8E-09 1.6E-09 4.8E-10 1.8E-10 9.6E-11 5.8E-11 4.0E-11 2.5E-ll 56 07/20/84

Table 3-8 continued Page 3 REFERENCE METEOROLOGY ANNUAL AVERAGED RELATIVE DEPOSITION RATE BASE DISTANCE IN MILES / KILOMETERS MILES 9.00 11.00 .79 5.00 1. 00 2.00 2.75 4.30 14.48 17.70 1.27 8.04 1.61 3.22 4.42 6. 92 NNE 1.6E-11 9 3E-12 1.4E-09 4.7E-11 9.6E-10 2.8E-10 1.6E-10 6.2E-ll NE 9.9E-12 6.2E-12 8.1E-10 3.2E-11 5.6E-10 1.8E-10 1.1E-10 4.6E-ll ENE 8.1E-12 5.2E-12 5. OE-10 2.3E-11 3.6E-10 1.2E-10 6.4E-11 3.0E-11 E 1.0E-11 6.6E-12 5.9E-10 3.0E-11 4.3E-10 1.5E-10 8.8E-11 3.9E-ll ESE 7.5E-12 5.8E-12 4.1E-10 2.2E-11 3.1E-10 1.2E-10 6.5E-11 2.8E-11 1 8E-11 1.3E-ll 1.1E-Q9 4.7E-ll 7.1E-10 '.3E-10 1.3E-10 6 OE-ll SSE 6.6E-ll 4.5E-11 4.9E-09 2.1E-10 3.4E-09 1.1E-09 5.8E-10 2.6E-lo S 3.4E-ll 2.3E-ll 1.9E-09 1.0E-10 1.4E-09 4.4E-10 2.7E-10 1.3E-10 SSW 1.0E-11 6.6E-12 6.7E-10 3.6E-11 4.5E-10 1.7E-10 9.7E-11 4.8E-11 3.5E-ll 2.2E-11 2.5E-09 1.1E-10 1.9E-09 6.3E-10 3.6E-10 1.4E-10 57 07/20/84

Table 3-8 continued Page 4 REFERENCE METEOROLOGY ANNUAL AVERAGED RELATIVE DEPOSITION RATE BASE DISTANCE IN MILES / KILOMETERS MILES 9.00 11.00 .79 5.00 1.00 2.00 2.75 4.30 14.48 17.70 1.27 8.04 1.61 3.22 4.42 6.92 WSW 5.5E-11 3.8E-ll 4.6E-09 1.6E-10 3.2E-09 9.7E-10 4.9E-10 2.2E-10 1 ..2E-10 8.7E-11 1.1E-09 3.9E-10 7.4E-09 2.2E-09 1.2E-09 5.0E-10 8.8E-11 6.1E-ll 8.7E-09 2.8E-10 5.7E-09 1.6E-09 9.0E-10 3.8E-10 4.5E-ll 3.2E-ll 5.6E-09 1.5E-10 3.7E-09 9.5E-10 5.0E-10 2.0E-10 NNW 2.5E-ll 1.8E-ll 2.7E-09 8.8E-11 1.8E-09 5.4E-10 3.0E-10 1.2E-10 N 1.7E-11 1.1E-ll 1.4E-09 4.8E-11 1.0E-09 2.7E-10 1.5E-10 6.5E-11 NUMBER OF VALID OBSERVATIONS 16538 NUMBER OF INVALID OBSERVATIONS 1006 NUMBER OF CALMS LOWER LEVEL 195 NUMBER OF CALMS UPPER LEVEL 383 58 07/20/84

4.0 Dose Commitment from Releases Over Extended Time F 1 Releases Durin 12 Months Technical Specification 3.11.4 implements 40 CFR Part 190.102. It requires the annual (calendar year) dose or dose commitment to any member of the public from all uranium fuel cycles to be limited to less than or equal to 75 mrem to the thyroid and 25 mrem to the total'ody or any other organ.

Fuel cycle sources or nuclear power reactors other than the Turkey Point Plant itself do not measurably or significantly increase the radioactivity concentration in the vicinity of the Plant; therefore, only radiation and radioactivity in the environment attributable to the Plant itself are considered 'in the assessment of compliance with 40 CFR Part 190.102.

In the event a dose calculated for the purpose of assessing compliance with Specification 3.11.1.2, 3.11.2., or 3.11.2.3, exceeds 2 times the limit stated therein, then a calculation shall be made to determine whether any limit in 3.11.4 has been exceeded. The total dose calculated pursuant to Technical Specification 3.11.4 must include direct radiation contributions and the methodology for calculating direct radiation con-tribution must be indicated in the Semi-Annual Report.

These calculations should be made on the basis of radio-active effluents during the year-to-date and reference meteorological data or averaged meteorological data during completed quarters of the year-to-date.

Separately, an evaluation of doses due to effluents during the year is performed annually and reported in the

.Semiannual Radioactive Effluent Release Report submitted within 60 days after the end of the year. This evaluation uses reference meteorological data or annual averaged meteorological data concurrent with the annual gaseous releases to evaluate atmospheric dispersion, deposition, and plume gamma exposure.

To assess compliance with Technical Specification 3.11.4, evaluations of dose due to liquid and gaseous effluents are calculated as described by the equations for:

total body dose due to liquid effluent via irradiation by radionuclides deposited on cooling canal shoreline as in Section 2.4 (Equation 7) total body dose due to noble gas y as in Section 3.4.1 (Equation 16) 59 06/25/91

o skin dose due to noble gas P as in Section 3.4.2

(Equation 17) o total body and maximally exposed organ doses due to gaseous effluents other than noble gases* as in Section 3.5.2 (Equation 22).

The doses are calculated on the basis of liquid and gaseous effluents from the Plant, sampled and analyzed in accord with Technical Specification Tables 4.11-1 and 4.11-2.

The receptor of the dose is described such that the dose to any member of the public is not likely to be underestimated.

The receptor is selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census and maximum ground level X/Q at the residence. Conditions more conservative than appropriate for the maximally exposed person may be assumed in the dose assessment. Environmental pathway-to-dose transfer factors used in the dose calculations appear in Appendix A.

4.2 Environmental Measurements When assessing compliance with 40 CFR Part 190 or 10 CFR Part 50 Appendix I dose limits, Radiological Environ-mental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attribu-butable to the Turkey Point Plant as an alternate to calculating the concentrations from radioactive effluent measurements. The measured environmental activity levels may thus be used to supplement the evaluation of doses to real persons for assessing compliance with 40 CFR Part 190 or 10 CFR Part 50 Appendix I.

4.3 Dose to a Person from Noble Gases Technical Specification 3.11.4 requires the calculation of the annual (calendar year) dose or dose commitment to a person off-site exposed to radioactive liquid and gaseous effluents from the plant. One component of personal dose is total body irradiation by gamma rays from noble gases. Another is irradiation of skin by beta and gamma radiation from noble gases. The methods for calculating these doses are presented in Sections 4.3.1 and 4.3.2.

The amount of radioactive noble gas discharged is determined in the manner described in Section 3.3.

• Radioactive I-131, I-133, tritium, and radioactive material in particulate form having a half-life greatc-than 8 days.

60 06/25/91

Gamma Dose to Total Bod The gamma radiation dose to the whole body of a member of the public as a consequence of noble gas released from the Plant is calculated with the equation:

v Z~~ v~

(31) where:

D = noble gas gamma dose to total body, (mrem)

Q<

quantity of radioactive noble gas discharged in gaseous effluent, (pCi) i X/Q= atmospheric dispersion factor at the off-site location of interest, (sec/m~)

factor converting time integrated, ground level concentration of noble gas nuclide iisted to total body dose from gamma radiation in Tab e 3-4, rem pCi ~ sec/m When the total body dose due to gamma radiation from noble gas required by Technical Specification 3.11.4 is calculated, the most exposed receptor is located 3.6 miles west northwest of the plant where the reference meteorological dispersion factor, X/Q, is 1 x 10 " sec/m .

This calculation is the same technique used in Section 3.3.1, Equation 13, but is extrapolated to an annual release except the g/Q value is for the most exposed receptor, not the minimum dispersion point off-site.

Dose to 8kin The radiation dose to the skin of a member of the public due to noble gas released from the Plant may be calculated with the equation:

61 06/25/91

0 where:

D = dose to skin due to noble gases, (mrem)

X/Q = atmospheric dispersion factor at the off-site location of interest,(sec/m~) .

Q; quantity of radioactive noble gas i discharged in gaseous effluent, (pCi).

s~, = factor converting time integrated ground level concentration of noble gas to skin dose from eta radiation listed in Table 3-4, mrem pCi ~ sec/m 1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mrem/mrad)

A )

factor for converting time integrated, ground-level concentration of noble gas radionuclide in Table 3-3,

""'/

When the skin beta dose due to noble gas required by Specification 3.11.4 is calculated, the most exposed receptor is located 3.6 miles west northwest of the Plant where the reference meteorological dispersion factor, X/Q, is 1 x 10 sec/m~.

The total dose to the skin from noble gases is approximately equal to the beta radiation dose to the skin plus the gamma radiation dose to the total body.

This is the same technique used in Section 3.3.2, Equation 14, but is extrapolated to an annual release, except the X/Q value is for the most exposed receptor rather than the minimum dispersion point off-site.

62 06/25/91

APPENDIX A PATHWAY-DOSE TRANSPER FACTORS

APPENDIX "A PATHWAY-DOSE TRANSFER FACTORS Environmental pathway transfer factors, usage factors, and dose commitment factors appropriate for each exposure pathway, age, and organ are combined into integrated environmental concentration-to-dose factors for each radionuclide. This appendix includes tables of values of the transfer factors calculated in accord with equations and values recommended in NUREG-0133'or individual environmental pathways. In the event a single, composite transfer factor is desired for a given organ and age group, it can be obtained by summing the factors for appropriate pathways.

Appropriate transfer factors from Appendix A are used in performing dose assessment calculations prescribed in the ODCM.,'5

1. J. Boegli, et. al., eds., 1978, Pre aratio of ad'o o ica f ue t ec 'c ec'c t'o s NUREG-0133, USNRC, Office of Nuclear Reactor Regulation.

A-1 07/20/84

+t C

l

DOSE FACI'DRS fOR LIQUID DISCHARGES BASED ON 1 CI/TR RELEASE OF EACH ISOTOPE IN DISCHARGE FLOU OF 1 GPH MITH NO ADDITIONAL DILUTION PATHMAT - DISCHARGE CANAL SHORLINE DEPOSITS -

AGE GROUP ADULT NUCLIDE ORGAN DOSE (HREH)

LIVER THTROID KIDNET LUNG GI-LLI SCIN TOTAL BMT H-3 0. 0. 0. 0. 0. 0. 0.

P-32 0. 0. 0. 0. 0. 0. 0.

CR-51 3.69-01 3.69E-OI 3.69E-01 3.69E-01 3.69E-01 3.69E-DI 4.36E-01 3.69E-01 HN-54 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.28t02 1.09E+02 FE-5 0. 0. 0. 0. 0.

FE-59 2.17E+01 2.17E+Ol 2.17E+01 2.17E+01 2.17E+01 2.17E+01 2.55E+01 2.17E+01 CO-58 3.DOE+01 . DOE+01 3.DOE+01 3.DOE+01 3.00E+01 3.DOE+01 3.51E+Ol 3.DOE+01 C0.60 1.69E+03 1.69E+03 1.69E+03 1.69E+03 1.69E+03 1.69E+03 1. 99E+03 1.69E+03 ZN-6 +01 .86E+01 5.86E+01 5.86E+01 5.86E+01 6.74E+01 5.86E+01 RB-86 7.11E.01 7.11E.01 7.11E-01 7.11E-01 7.11E-01 7.11E.01 8.12E-01 7.11E-01 SR-89 1.71E-03 1.71E-03 1.71E-03 1.71E-03 1.71E.03 1.71E-03 1.98E-03 1.71E-03 SR 90 4.23E-01 4.23E.01 4.23E-01 4.23E-OI 4.23E.01 4.23E-01 4.99E-01 4.23E-OI Y-91 E 0 E- 8.54E-02 8.54E-02 8.54E-02 8.54E-02 9.61E 02 8.54E-02 ZR-95 3.96E+01 3.96E+01 3.96E+Ol 3.96E+Ol 3.96E+01 3.96E+Ol 4.62E+01 3.96E+01 ZR-97 4.32E-01 4.32E 01 4.32E-01 4.32E-01 4.32E-01 4.32E-01 5.04E.Ol 4.32E-01 NB-95 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08&01 1.27E+01 1. OBE+01 ZR-9 4. 2E-01 4.32E-01 4. 2E-01 4.32E-01 4.32E.01 4.32E 01 5.04E-OI 4.32E.OI HB-95 1.ME+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.27E+01 1.08E+01 H0.99 4.66E-01 4.66E.01 4.66E-01 4.66E-01 4.66E 01 4.66E-01 5.37E 01 4 66E-01 RU-103 d.69E+00 8.69E+00 8.69E+00 8.69E+00 8.69Et00 8.69E+00 1 ~ 01E+01 8.69E+00 RU-106 . DE+01 . DE+01 +01 . DE+01 3.30E+Ol 3.30E+01 3.97E+01 3.30E+01 AG-11N 2.82E+02 2.82E+02 2.82E+02 2.82E+02 2.82E+02 2.82E+02 3.29E+02 2.82E+02 SB-124 4.72E+01 4.72E+01 4.72E+01 4.72E<01 4. 72E+01 4.72E+01 5.45E+01 4.72E+01 SB-125 1.81E+02 1.81E+02 1.81E+02 1.81E+02 1.81E+02 1.81E+02 2.05Et02 1.81E+02 TE-125ll E-ol . 2E- 1 .22E-01 1.22E-01 1.22E-01 1.22E-01 1.68E.01 1.22E-01 TE-127ll 6.94E-02 6.94E-02 6.94E-02 6.94E-02 6.94E-02 6.94E-02 7.68E-02 6.94E-02 TE-129H 3.04E+00 3.04E+00 3.04E+00 3.04E+00 3.04E+00 3.04E+00 3.57Ei00 3.04E+00 TE 13TH 8.41E-01 8.41E-01 8.41E-01 8.41E-01 8.41E-01 8.41E-01 3.68E+Ol 8.41E-OI TE- .66E+00 .66E+ .66E+00 .66E+00 .66E+00 3.66E+00 4.31E+00 3.66E+00 I-131 1.36E+00 1.36E+00 1.36E+00 1.36E+00 1.36E+00 1.36E+00 1.65E+00 1.36E+00 I-133 1.95E-01 1.95E-01 1.95E-01 1.95E-01 1.95E-Ol 1.95E-01 2.38E.OI 1.95E-01 CS-134 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 5.51E+02 6.43E+02 5.51E+02 CS- . BE+01 . BE+1 .18E+01 l. BE+01 1.18E+01 1.18E+01 1.33E+01 1.18Et01 CS-137 8.13Ei02 d.13E+02 8.13E+02 8.13E+02 8. 13E+02 8.13E+02 9.48E+02 8.13E+02 BA-140 1.32E+01 1.32E+01 1.32E+01 1.32E+01 1.32E+01 1.32E+01 1.50E+01 1.32E+01 LA-140 1.52E+00 1.52E+00 1.52E+00 1.52E+00 1.52E+00 1.52E+00 1.72E+00 1.52E+00 CE- 4 ~ + .OBE+ .OBE+00 1.ME+00 1.08E+00 1.08E+00 1.22E>00 1.08E+00 CE-143 1.82E-01 1.82E-01 1.82E-01 1.82E-01 1.82E-01 1.82E 01 2.07E.OI 1.82E-01 CE.144 8.94E+00 8.94E+00 8.94E+00 8.94E+00 8.94E+00 8.94E+00 1.03E+01 8.94E+00 NP-239 1.35E-01 1.35E-01 1 ~ 35E-01 1.35E.01 1.35E-OI 1.35E-01 1.56E-01 1.35E-OI A-2 07/20/84

a~

PATHMAY - DISCHARGE CANAL SHORELINE DEPOSITS AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE (HREII)

LIVER THTRO ID KIDNEY LUNG GI-LLI SKIN TOTAL BOOT H-3 0. 0. 0. 0. 0. 0. 0.

P-32 0. 0. 0. 0. 0. 0. 0.

CR-51 2.ME+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.06E+00 2.43E+00 2.06E+00 NN-54 6.09E+02 4.09E+02 6.09E+02 6.09E+02 6.09E+02 6.09E+02 7.15E+02 6.09Ei02 FE- 0. 0. 0. 0. 0. 0.

FE-59 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.42E+02 1.21E+02 CO-58 1.67E+02 1.67E+02 1.67E+02 1.67E+02 1.67E+02 1.67Et02 1.96E+02 1.67E+02 9.45E+03 9 45E+03 9.45E+03 9.45E+03 9.45Ei03 9.45E+03 1.11E+04 9.45Ei03 ZN- 5 + +2 .27E+02 3.27E+02 3.27E+02 3.27E+02 3.76E+02 3.27E+02 RB 86 3.97E+00 3.97E+00 3.97E+00 3.97E+00 3.97E+00 3.97E+00 4.53E+00 3.97E+00 SR-89 9.54E-03 9. E-03 9.54E-03 9.54E-03 9.54E-03 9.54E-03 1.11E-02 9.54E-03 2.36E+00 2. +00 2.36E+00 2.36E+00 2.36E+00 2.36E+00 2.79E+00 2. 36E+00

4. 4~ -01 4. .01 4.77E-Ol 4.77E-01 5.35E.01 4.77E 01 ZR-95 2.21E+02 2.21E+02 2.21E+02 2.21E+02 2.21E+02 2.21E+02 2.58E+02 2.21E+02 ZR-97 2 4IE+00 2 41E+00 2.41E+00 2.41E+00 2.41E+00 2.41E+00 2.82E+00 2. 41E+00 NB-95 6.01E+01 6.01E+01 6.01E+01 6.01E+01 6.01E+01 6.01E+01 7.07E+01 6. 01E+01 NO-99 .60E+00 .60E+ .60E+ 2.60E+00 2.60E+00 2.60E+00 .DOE+00 2.60E+00 RU-103 4.85E+01 4.85E+01 4.85E+Ol 4.85E+01 4.85E+01 4.85E+01 5.66E+01 4.85E+01 RU-106 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 2.21E+02 1.85E+02 AG-110N 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.84E+03 1.58E+03 SB- 24 .64E+0 ~ E+02 .64E+02 .64E+0 2.64E+02 2.64E+02 3.04E+02 2.64E+02 58-125 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.01E+03 1.14E+03 1.01E+03 TE-125N 6.84E Ol 6.84E-01 6.84E-01 6.84E-01 6.84E-01 6.84E.01 9.38E.01 6.84E-01 TE-127N 3.87E-01 3.87E-Ol 3.87E-01 3.87E-01 3.87E-01 3.87E-01 4.29E-01 3.87E-01 TE- ~ + +01 +01 . DE+01 1.70E+01 1. DE+01 1.99E+01 1. 70Et 0 1 TE-131N 4.69E+00 4.69E+00 4.69E+00 4.69Ei00 4.69E+00 4.69E+00 2.05E+02 4.69E+00 TE-132 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.05E+01 2.41E+01 2.05E+01 1-131 7.59E+00 7.59E+00 7.59E+00 7.59E+00 7.59E+00 7.59E+00 9.22E+00 7.59E+00 I- 3 + .09E+00 .09E+00 1.09E+00 1.09E+00 1.33E+00 1.09E+00 CS-134 3.ME+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.59E+03 3.08E+03 CS-136 6.57E+01 6.57E+01 6.57E+01 6.57E+01 6.57E+01 6.57E+01 7.44E+01 6.57Ei01 CS-137 4. E+03 4.54Ei03 4.54E+03 4.54E+03 4.54E+03 4.54E+03 5.29Ei03 4.54E+03 BA- 4 + tO +01 +01 F01 +01 8.36E+01 .38E+01 LA-140 8.46E+00 8.46E+00 8.46E+00 8.46E+00 8.46Ei00 8.46E+00 9.59E+00 8.46E+00 CE-141 6.02E+00 6.02E+00 6.02E+00 6.02E+00 . 6.02E+00 6.02E>00 6.79E+00 6.02E+00 CE-143 1.02E+00 1.02E+00 1.02E+00 1.02E+00 1.02E+00 1.02E+00 1. 16E+00 1.02E+00

+ 4. + +01 4.99E+0 4;99E+01 4.99E+01 5.76E+01 4.99E+01 NP-239 7.52E-01 7.52E-01 7.52E-Ol 7.52E-01 7.52E-01 7.52E-01 8.71E 01 7.52E-01 A-3 12/19/84

d Pp

PATHMAY - DISCHARGE CANAL SHORELINE DEPOSITS AGE CROUP- CHILD NUCLIDE ORGAN DOSE (HREH)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY

0. 0. 0. 0. 0. 0. 0.

P-32 0. 0. 0. 0. 0. 0. 0.

CR-51 4.30E-01 4. -01 4.30E-01 4.30E-01 4.30E-01 4.30E-01 5.09E-OI 4.30E.01 1.27E+02 +02 1.27E+02 1.27E+02 1.27E+02 1.27E+02 1 49E+02 1.27E+02 FE-55 0. 0. 0. 0. 0.

FE-59 2.53E+01 . 3E+Ol 2.53E+01 2.53E+01 2.53E+Ol 2.53E+01 2.98E+01 2.53EiOI CO-58 3.50E+0 +01 3.50E+01 3.50E+01 3.50E+01 3.50E+01 4.10E+Ol 3.50E+01 1.97E+ .9 +03 1.97E+03 1.97E+03 1.97E+03 1.97E+03 2.32E+03 1.97E+03 ZN-6 6. + E 6. E+01 6.84E+01 6.84E+01 6. 84E+01 r.erE+ol 6.84E+01 RB-86 d.29E.01 8.29E-01 d.29E-01 8.29E-DI 8.29E-01 8.29E-01 9.47E-01 8.29E-01 SR-89 1.99E-03 .99E-03 1.99E-03 1.99E-03 1.99E-03 1.99E-03 2.31E-03 1.99E-03 SR-90 4.93E-01 4 93E 01 4.93E-01 4.93E-01 4.93E-01 4.93E.01 5.83E-01 4.93E.01 Y.9 ~ 2 9. -02 9.96E-02 9.96E-02 1.12E-01 9.96E.02 ZR-95 4.62E+Ol 4.62E+01 4.62E+01 4.62E+Ol 4.62E+01 4.62E+01 5.39E+01 4.62E+01 ZR-97 5.03E-OI 5.03E-01 5.03E-01 5.03E-01 5.03E-01 5.03E.01 5.88E-01 5.03E-01 NB-95 1.26E+01 1.26E+01 1.26E+01 1.26E+01 1 ~ 26EtDI 1.26E+Ol 1.48E+Ol 1.26E+01 E- .4 E-01 .4 E-01 5 '3E-01 5.43E-01 6.27E-01 5.43E.OI RU-103 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+Ol 1.18E+01 1.DIE<01 RU.106 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 4.83E+Ol 3.86E+01 AG-'I 'I Ql 3.29E+02 3.29E+02 3.29E+02 3.29E+02 3.29E+02 3.29E+02 3.84E+02 3.29E+02 SB 4 f+ E+01 E+ 1 . 1E+01 5.51E+OI .51E+01 6.35E+01 .51E+01 58-125 2.11E+02 2.11E+02 2.11E+02 2.11E+02 2.11E+02 2.11E+02 2.39E+02 2.1IE+02 TE- 125ll 1.43E.01 1 43E-OI 1.43E-01 1 43E-OI 1 43E-OI 1.43E.01 1.98E-01 1.43E.OI TE-127M 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.97E-02 8.09E-02 TE- E E+ E+ ~ E+00 . 4E+00 3.54Ei00 4.18Ei00 3.54E+00 TE-13IN 9.80E-01 9.80E.OI 9.80E-01 9.80E.01 9.80E-OI 9.80E-01 4.28E+01 9.80E.01 TE-132 4.28E+00 4.28E+00 4..28E+00 4.28Et00 4.28E+00 4.28E+00 5.03E+00 4.28E+00 I-131 1.59E+00 1.59E+00 1.59E+00 1.59E+00 1.59E+00 1.59E+00 1.93E+00 1.59Ei00

. BE-01 ~ BE-01 2.28E-01 -01 2.28E.01 CS.134 6.43E+02 6 43E+02 6.43E+02 6 43E+02 6 43E+02 6.43E+02 7.50E+02 6.43E+02 CS-136 1.37E+01 1. 7E+01 1.37E+Ol 1.37E+01 1.37E+01 1.37E+01 1. 58E+01 1.37E+01 CS-137 9 48E+02 9 48E+02 9.48E+02 9 48E+02 9.48E+02 9.48E+02 1.11E+03 9.48Ei02

. 4E+ E+ ~ E+ E+0 1. 4E+ 1 . 4E+01 1. E+01 1.54E+01 LA.140 1.77E+00 1.77E+00 1.77E+00 1.77E+00 1.77E+00 1.77E+00 2.DOE+00 1.77E+00 CE-141 1.26E+00 1.26E+00 1.26E+00 1.26E+00 1.26E+00 1.26E+00 1.42E+00 1.28Ei00 CE-143 2.13E-01 2.13E-01 2.13E.01 2.13E-OI 2.13E-01 2.13E-01 2.42E-01 2.13E.01 E E+ E+ E 1. E+ 1 1. 04E+01 1.20E+01 1.04E+01 KP.239 1.57E-Ol 1.57E.01 1.57E-01 1.57E-01 1.57E.OI 1 ~ 57E-01 1.82E-01 1.57E-01 A-4 12/19/84

DOSE FACTORS FOR LIQUID DISCHARGES BASED ON 1 C1/TR RELEASE OF EACH ISOTOPE IN DISCHARGE FLOV OF 1 GPH VITH NO ADDITIONAL DILUTION PATHVAY - SALT VATER FISH AGE GROUP - ADULT NUCLIDE ORGAN DOSE (HREH)

L IVER THTRO ID KIDNET LUNG GI-LLI SKIN TOTAL BOOT H-3 0. 1.27E+00 1.27E+00 1.27E+00 1.27E+00 1.27E+00 0. 1.27E+00 P-32 5.63E+07 3.53E+06 0. 0. 0. 6.33E+06 0. 2.18E+05 CR-5'I 0. 6.55E+00 2 42E+00 1.45E+01 2.76E+03 0. 1.10E+01

0. E 0. 7.ME+03 0. 8.11E+04 0. +0 FE-55 1.96E+05 .83E+05 0. 0. 1.02E+06 3.45E+05 0. 2.32E+05 FE.59 1.35E+ E+05 0. 0. 8.92E+04 1.06E+06 0. 1.22E+05 CO.58 0. .80E+02 0. 0. 0. 1.58E+04 0. 1.75E+03 CO-60 0. 0. 0. 0. 4.24E+04 0. 4.98E+03 ZN-65 1.02E+05 3.24E+05 0. 2.17E+05 0. 2.04E+05 0. 1.47E+05 RB.86 0. 1. +03 0. 0. 0. 3.51E+02 0. 8.31E+02 SR-89 '.43E+03 0. 0. 0. 0. 1.03E+03 0. 1.84E+02 SR- E+ 0. 0. 8.29E+03 0. 3.93E<04 Y.91 3.68E+01 0. 0. 0. 0. 2.02E+04 0. 9.86E-01 ZR-95 1.01E+02 4.14E+01 0. 5.30E+01 0. 1.90E+05 0. 2.21E+DI ZR-97 8.03E+00 1.96E+00 0. 2.38Ei00 0. 8.95Ei04 0. 7.42E 01 NB- .9 E+0 .0 +0 1.0 +03 0. 6.52E+06 0. 4.22E+02 1.85E-02 3.55E+02 0. 8.06E+02 2.56E-02 8.54E+02 0. 6.82E+01 RU-103 5.76E+00 0. 0. 2.20E+01 0. 6.72E+02 0.. 2.48E+00 RU-106 8.69E+01 0. 1.68E+02 0. 5.63Ei03 0. 1.10E+01 AG- . 4E .01E+04 0. 2.10E+06 0. 3.06E+03 SB-124 1.17E+03 2.21E+01 2.83E+00 0. 9.10E+02 3.32E+04 0. 4.63E+02 SB 125 9.42E+02 1.04E+01 1.05Ei00 2.87E+00 9.83E+04 8.31E+03 0. 1.89E+02 TE-125H 2.80E+02 1.02E+02 8.42E+01 1.14E+03 0. 1.12E+03 0. 3.74E+01 TE- . DE+0 E+02 +0 .92E+03 0. 3.13E+03 0. 8.87E+01 TE-129H 1.19E+03 4.46E+02 4.12E+02 4.97E+03 0. 5.99Ei03 0. 1.89E+02 TE-131H 1.31E+02 8.94E+01 1 '9E+04 5.75E+02 0. 4.99E+03 0. 6.43E+01 TE-132 2.18E+03 1.88E+02 6.43E+03 1.43E+03 0. 6.59E+03 0. 1.48Et02

+ + +05 9.88E+02 1.52E+02 0. 3.30E+02 I-133 6.84E+Ol .19E+02 2.28E+04 2.07E+02 0. 1.04E+02 0. 3.62E+01 CS.134 2.62E+04 .24E+04 0. 2.03E+04 6.71E+03 1.09E+03 0. 5. 10E+04 CS-136 2.61E+03 .03E+04 0. 5.72E+03 7.85E+02 1. 17Ei03 0. 7.41E+03

+ + +04 ~ 9E+03 8.87E+02 0. .02E+04 BA-140 2.63E+03 .66E+00 0. 8.68E-O'I 1.45E+00 1.22E+04 0. 1.54E+02 LA-140 4.36E-01 .20E-01 0. 0. 0. 1.61E+04 0. 5.83E.02 CE-141 3.68E-01 6.55E 01 0. 3.04E-01 0. 2.50E+03 0. 7.42E-02

+0 .60E-0 0. 3.32E+03 0. 1.33E.02 CE-144 5.15E+01 2 45E+OT 0. 1.27E+01 0. 1.74E+04 0. 2.70E+01 NP-239 9.59E-02 9 49E-03 0. 2.89E-02 0. 1.89E+03 0. 5.12E-03 A-5 07/20/84

~ l f

• V$

DOSE FACTORS FOR LIQUID DISCHARGES BASED ON 1 CI/YR RELEASE OF EACH ISOTOPE IN DISCHARGE FLOM OF 1 GPH IJITH NO ADDITIONAL DILUTIOH PATHMAY - SALT ilATER FISH AGE GROUP - TEEHAGER NUCLIDE ORGAN DOSE (HREH)

BONE LIVER THYROID KIDNEY LUHG Gl-LLI SHIN TOTAL BOOT H-3 0. 7.6 -01 7.67E-01 9;70E-01 7.67E.Ol 7.67E-01 0. 7.67E 01 P-32 4. +07 .69E+06 0. 0. 0. 4.82E+06 0. 1.68E+05 CR-51 0. 0. C.99E+00 1.85E+00 1.11E+01 2.10E+03 0. 8.35E+00

0. .02E+04 0. 6.DOE+03 0. 6. 18E+04 0. 5.85E<03 FE-55 . OE+ f+ 0. 7.79E+05 2.63E+05 0. 1.77E+03 FE-59 .0 E+ .4 E+05 0. 0. 6.79E+04 8.08E+05 0. 9.31E+04 CO-58 0. 7.90E+02 0. 0. 0. 1.07E+04 0. 1.80E+03 CO-60 0. 2.22E+03 0. 0. 0. 2.68E+04 0. 5.06E+03 ZN-6 ~ + 0. 1.65E+05 0. 1.56E+05 0. 1.12E+05 RB-86 0. 0. 0. 2.68E+02 0. 6.33E+02 SR-89 7.30E+03 0. 0. 0. 0. 7.92E+02 0. 2.09E+02 SR-90 1.87E+05 0. 0. 0. 1.72E+03 8.54E+03 0. C.13E+04 Y-91 .89E+01 0. 0. 0. 0. 1 ~ 50E+04 0. 1.04E+00 ZR-95 9. +01 3. +0 0. 4.04E+01 0. 1.25Ei05 0. 2.52E+01 ZR-97 6.13E+00 1.50E+00 0. 1.SlE+00 0~ 6.S3E+04 0. 5.65E 01 NB-95 1.71E+03 1.03E+03 0. 8.11E+02 0. 4.21E+06 0. 5.82E+02

. 1E-0 E+0 6. TCEi02 1.95E-02 6.51E+02 0. 5. 19E+01 RU-10 .62E+00 0. 0. 1.68E+01 0. 4.39E+02 0. 2.51Ei00 RU-106 9.63E+01 0. 0. 1.29E+02 0. 4.36E+03 0. 1.21E+01 AG-110I 4.24E+03 3.92E+03 0. 7.70E+03 0. 1.60E+06 0. 2.33E+03 SB- 4 E+0 .69E+01 .16E+00 0. 6.93E>02 2.53Ei04 0. 3.53Ei02 SB- . BE+0 S.DOE+00 8. 4E-01 .19E+00 .49Ei04 6.33E+03 0. 1.44Ei02 TE-125ll 3.04E+02 1.09Ei02 8.58E+01 8.66E+02 0. S.50E+02 0. C.OCEi01 TE-127M 5.52E+02 1.93E+02 1.45E+02 2.23E+03 0. 2.61Ei03 0. 6.81E+01 TE- ~ f+ 4.86E+ . DE+02 +03 0. 4.57E+03 0. 2.07E+02 TE- II ~ + +0 . 5E+04 4.39E+02 0. 3.80E+03 0. 5.55E+01 TE-132 2.45E+02 1.80E+02 4.93E+03 1.09E+03 0. 5.21E+03 0. 1.C9E+02 1-131 4.11E+02 5.8IE+02 1.68E+05 7.53E+02 0. 1.10E+02 0. 3.45E+02

+0 1. E+02 . BE+04 1.58E+02 0. 9.10E+Ol 0. 3.86E+Ol

. 9E+ 6. 4E+04 0. 1.54E+04 .55E+03 .20E+02 0. 2.9IEi04 CS-136 1.99E+03 7.24E+03 0. 4.36Ei03 5.98E+02 8.91E+02 0. 5.'64Ei03 CS-137 3 CCE+04 4.63E+04 0. 1.19E+04 6.14E+03 6.18Et02 0. 1.82Et04 SA- 40 . 6E+0 . 6E+00 0. 6.61E 1.78Ei00 6.60E+03 0. 1.39E+02 LA- C 4.63E- 1 -01 0. 0. 1.26E+04 0. 6.05E 02 CE-141 9.92E-01 6.68E-01 0. 2.31E-01 0. 1.80Ei03 0. 7.64E-02 CE-143 1.52E-01 5.93E+01 0. 4.27E-02 0. 2.53E+03 0. 1.01E 02

+1 + 9. 1E+00 0. 1.36E+04 0. 3.67E+03 KP- 9 E-0 ~ BE-03 0. 2.20E-02 0. 1.44E+03 0. 3.91E-03 A-6 07/20/84

t.

l l .

T

DOSE FACTORS FOR LIOUID DISCHARGES BASED ON 1 Cl/YR RELEASE OF EACH ISOTOPE IN DISCHARGE FLOU OF 1 GPH MITH NO ADDITIONAL DILUTION PATHNAY - Salt Mater fish AGE GROUP - CHILD NUCLIDE ORGAN DOSE (HREII)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BMY 8-3 0. 6.34E-01 6.34E.01 4.1&E 01 6.34E-01 6.34E-01 0. 6.34E-01 P-32 1.85E+07 1.16E+06 0. 0. 0. 2.08E+06 0. 7.1&E>05 CR-51 0. 0. 2.15E+00 7.94E-01 4 ~ 7&E+00 9.05E+02 0. 3.60E+00 NN-54 0. +0 '0. 2.59E+03 0. 2.66E+04 0. 1.66E+03 fE-55 6 45E+04 2.90E+05 0. 0. 3.36E+05 1.13E+05 0. 7.62E<04 FE-59 4 CSE+04 1.06E+05 0. 0. 2.93E+04 3.48E+05 0. 4.02E+04 CO-58 0. 6.35E+02 0. 0. 0. 3.78E+03 0. 1.92E>03 CO-60 0. +0 0. 0. 0. 9.92E+03 0. 5.37E+03 ZN-65 3.35E+04 1.07E+05 0. 7.12E+04 0. 6.71E+04 0. 4.82E+04 RB-86 0. 5.85E+02 0. 0. 0. 1.15E+02 0. 2.73Et02 SR-89 9 CCE+03 0. 0. 0. 0. 3.52E+02 0. 2.70E+02 SR-90 0. 0. 3.97E+03 0. 3.02E+04 Y-91 5.01E+01 0. 0. 0. 0. 6.66E+03 0. 1.34Ei00 ZR-95 1.10E+02 3.32E+01 0. 1.74E+01 0. 4.59E+04 0. 2.73E+01 ZR-97 2.64E+00 6 CCE-OT 0. 7.83E-01 0. 2.95E+04 0. 2.C4E-01 NB-95 .99E+0 8 49E+02 3.50E+02 0. 1 47E+06 0. 6.23Et02 N-99 6.08E.03 1.17E+02 0. 2.6CE+02 8.41E 03 2.&OEi02 0. 2.24E+01 RU-103 6.93E+00 0. 0. 7.23E+00 0. 1.82E+02 0. 2.80E+00 RU-106 1.24E+02 0. 0. 5.52E+01 0. 1.92E+03 0. 1.54E+01 AG- 10l .83E+03 .69E+ 3.32E+03 0. 6.89E+OS 0. 1.DOE+03 S&-124 3.85E+02 7.27E+00 9.31E-01 0. 2.99E+02 1.09Ei04 0. 1.52E+02 S&-125 3.10E+02 3.60E+00 5.52E.01 9.43E-01 3.23E+04 2.73E+03 0. 6.22E+01 TE-125N 3.91E+02 1.06E+02 1.10E+02 3.74Et02 0. 3.77E+03 0. 5.21E+01 TE.1 7N ~ 4 +0 . 1E+01 6.84E+01 9.60E+02 0. 1.33E+03 0. 3.12E+01 TE-129H 1.68E+03 4.69E+02 5 '8Ei02 1.63E+03 0. 2 '3E+03 0. 2.60E+02 TE-131N 6.92E+01 5.25E+01 1.17E+04 1.89E+02 ~

0. 1.64E+03 0. 4.09E+01 TE-132 2.92E+02 1.42E+02 2.25E+03 C.6&E+02 0. 2.21E+03 0. 1.5&E+02

. 9E+ . 1E+0 E+ .25E+02 0. C.55E+01 0. 4.01E+02 1-133 9.39E+01 1.16E+02 2.&DE+04 6.&DE+01 0. 4.70E+01 0. 4.56E+01 CS-134 3.11E+04 5.23E+04 0. 6.65E+03 5.81E+03 2.&3E+02 0. 1.11E+04 CS-136 8.56E+02 3.38E+03 0. 1.&BE+03 2.58E+02 3.84E+02 0. .43E+03 CS- E+ 4. 9E+0 . SE+0 4.91E+03 2.55E+02 0. 6.2CEi03 BA-140 2.71E+03 2.48E+00 0. 2.&SE-01 1.42E+00 3.DOE+03 0. 1.59E+02 LA-140 5.79E-01 2.02E-01 0. 0. 0. 5.73E+03 0. 6.82E-02 CE-141 1 ~ 28E+00 6.38E-01 0. 9.98E.02 0. 8.01E+02 0. 9.51E.02 CE- 4 E- . 6E+0 0. .&CE-02 0. 1.09E+03 0. 14.33.03 CE-144 7.45E+01 2.32E+01 0. 4.19E+00 0. 8.02E+03 0. 3.94E+00 NP-239 3.19E-02 3. 16E-03 0. 9 49E-03 0. 6.20E+02 0. 1.69E-03 A-7 07/20/84

0 l

't IIL V, 4% 4

DOSE FACTORS FOR LIOUID DISCHARGES BASED ON 1 CI/YR RELEASE OF EACH ISOTOPE IN DISCHARGE FLOM OF 1 GPH MIIH HO ADDITIONAL DILUTION PATHMAY - SALT MATER SHELL FISH AGE GROUP - ADULT NUCLIDE ORGAN DOSE (HREH)

BONE L IVER THYROID KIONET LUNG GI-LLI SKIN TOTAL BODY H-3 0. 3.13E-01 3.13E-01 3.13E-01 3.13E-01 3.13E-01 0. 3.13E-01 P-32 1.39E+07 8.69E+05 0. 0. 0. 1.56E+06 0. 5.37E+05 CR-51 0. 0. 7.80E+00 2.88E+00 1.73E+01 3.28E+03 1.30E+01 HN-54 0. . BE+0 0. 1.36E+03 0. 1.40E+04 0. 8. 6Ei02 FE-55 3.11E+05 1.40E+06 0. 0. 1.62E+06 5.47E+05 0. 3.68Ei03 FE-59 2.15E+05 5.10E+05 0. 0. 1.42E+05 1.68E+06 0. 1.94E<05 CO-58 0. 1.86E+03 0. 0. 0. 3.76E+04 0. 4.18E+03 CO-60 0. .40E+03 0. 0. 0. 1.01E+05 0. 1.19E+04 ZN-65 6.08E+05 1.93E+06 0. 1.29E+06 0. 1.22E+06 0. 8.73E+05 RB-86 0. 8.69E+02 0. 0. 0. 1.71E+02 0. 4.05E+02 SR-89 1.53Ei04 0. 0. 0. 0. 2.45E+03 0. 4.39E+02 SR-90 .83E+ 0. 0. 0. 6.36E+04 0. 9.35E+04 T-91 3.50E+02 0. 0. 0. 0. 1.93E+05 0. 9.39E+00 ZR-95 6.08E+00 1.96E+00 0. 3.08E+00 0. 6.13E+03 0. 1.33E+00 ZR-97 1.32E-01 2.69E-02 0. 4.03E-02 0. 7.93E+03 0. 1.23E-02 NB-95 E+00 . 3E.01 0. ~ 8.45E-01 0. 5.17E+03 0. 3.35E-OI NO-99 2.02E.02 8.46E+01 0. 1.93E-02 3.05E-02 2.33E+02 0. 1.09E+OI RU-103 4.57E+02 0. 0. 1.75E+03 0. 5.34E+04 0. 1.97E+02 RU-106 6.90E+03 0. 0. 1.33E+04 0. 4.47E+05 0. 8.73Ei02 AG-110H . 2E+03 1. 2E+ .41E+03 0. 5.DOE+05 0. 7.28E+02 58-124 3.49E+01 6.58E-Ol 8.43E-02 0. 2.71E+01 9.87E+02 0. 1.38E+Ol S8-125 2.97E+01 9.11E-01 5.31E-01 6.83E+00 2.93E+03 2.54E+02 0. 5.86E+00 TE-125N 6.66E+02 2.42E+02 2.DOE+02 2.71E+03 0. 2.66E+03 0. 8.92E+OI TE-127H . 1E 6.DOE+02 4 49E+0 6.96E+03 0. 7.45E+03 0. 2.11E+02 TE-129H 2.84E+03 1.06E+03 9.79E+02 1.18Et04 0. 1.43E+04 0. 4.50E+02 TE-13111 2.78E+02 1.67E+02 1.54E+04 1.29E+03 0. 1 ~ 19E+04 0. 1.26E+02 TE-132 5.16E+03 3.90E+02 7.84E+03 3.30E+03 0. 1.57Ei04 0. 3.31E+02

4. +2 6. +0 .2 E+05 .18E+03 0. 1.81E+02 0. 3.93E+02 1-133 8.14E+01 1.41E+02 2.71E+04 1.46E+02 0. 1.24E+02 0. 4.31E>01 CS-134 3.90E+03 9.29E+03 0. 3.01E+03 9.98Ei02 1.63E+02 0. 7.60E+03 CS-136 3.88E+02 1.53E+03 0. 8.52E+02 1.17E+02 1.74Et02 0. 1.10E+03 CS- ~ 01E+0 6.85E+03 2.33E+03 .73E+02 1. 2E+02 0. 4.49E+03 BA-140 4.83E+03 7.11E+00 0. 2.07E+00 3.48Ei00 8.65Ei04 0. 3.19E+02 LA-140 4.15E+00 2.09E+00 0. 0. 0. 1.54Ei05 0. 5.55E 01 CE-141 1.38Et01 9.36E+00 0. 4.34E+00 0. 3.57Ei04 0. 1.06Ei00 CE- 4 .40E+ 1. 1E+03 0. 6.97E-01 0. 4.54E+04 0. 1.67E 01 CE-144 7.36E+02 3.07E+02 0. 1.82E+02 0. 2.48E+05 0. 3.94E+01 NP-239 4.82E-02 5.73E-03 0. 9.53E-03 0. 4.49E+02 0. 1.85E 03 A-8 07/20/84

E'I r

~1

DOSE FACTORS FOR LIOUID DISCHARGES BASED ON 1 CI/YR RELEASE OF EACH ISO'IOPE IN DISCHARGE FLOM OF 1 GPH QITH NO ADDITIONAL DILUTIOH PATHNAY - Salt lister Shell Fish AGE GROUP- TEENAGER NUCLIDE ORGAN DOSE (HREII)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN 'IOTAL BODY H-3 0. 1.88E-01 1.88E-01 2.38E-01 1.88E-Ol 1.88E-01 0. 1.88E.01 P-32 1.05E+07 6.61E+05 0. 0. 0. 1.19E+06 0. 4.08E+05 CR-51 0. 0. 5.92E+00 2.19E+00 1.32E+01 2.49E+03 0. 9.91Et00 NN-54 +0 0. 1.04E+03 0. 1.07E+04 0. 6.66E+02 FE-55 2.37E+05 1.07E+06 0. 0. 1.23E+06 4. 16E+05 0. 2.80Ei05 FE-59 1.83E+05 3.87E+05 0. 0. 1.08&05 1.28E+06 0. 1.47E+05 C0-58 0. 1.ME+03 0. 0. 0. 2.53E+04 0. 4.27E+03 CO-60 0. +0 0. 0. 0. 6.32E+04 0. 1.20Ei04 ZN-65 4.62E+05 1 47E+06 0. 9.81E+05 0. 9.24E+05 0. 6.64E+05 RB 86 0. 6.60E+02 0. 0. 0. 1.30E+02 0. 3.08E+02 SR-89 1.73E+04 0. 0. 0. 0. 1.ME+03 0. 4.97E+02

+ 0. 0. 0. 1.64E+04 5.59E+04 0. 9.82E+04 Y-91 3.70E+02 0. 0. 0. 0. 1.42E+05 0. 9.87E+00 ZR-95 5.65E+00 1.90E+00 0. 2.34Et00 0. 4.12E+03 0. 1.32E+00 ZR-97 1.61E-01 2.05E-02 0. 3.06E-02 0. 6.03E+03 0. 9.33E-03 NB- +00 8.16E- 6.42E-01 0. 3.33E+03 0. 4.61E-01 NO-99 1.67E-02 6.42E+01 0. 1.47E+02 2.32E-02 1.77E+02 0. 1.28E+01 RU-103 4 45E+02 0. 0. 1.33Ei03 0. 3.47E+04 0. 1.99E+02 RU 106 7.63E+03 0. 0. 1.01E+04 0. 3.45E+05 0. 9.59E+02 AG- 011 . 1E+ 9. +0 0. ~ 83E+03 0. 3.80E+05 0. 5.53E+02 SB-124 2.65E+01 5.00E-01 6.41E-02 0. 2.06E+01 7.51E+02 0. 1.05E+01 SB 125 2.31E+01 8.82E-01 5.33E-01 5.19E+00 2.22E+03 1.93E+02 0. 4.52E+00 TE-125II 7.23E+02 2.59E+02 2.04E+02 2.06E+03 0. 2.02E+03 0. 9.59E+01 TE- E+ .44E+0 .29E+03 0. 6.21E+03 0. 1.62E+02 TE-129li 3.12E+03 1.15E+03 9.97E+02 9.DOE+03 0. 1.09E+04 0. 4.89E+02 TE-131N 2.21E+02 1.38E+02 1.36E+04 9.82E+02 0. 9.01E+03 0. 1.04E+02 TE-132 5.64E+02 3.86E+02 6.04E+03 2.51E+03 0. 1.23E+04 0. 3.39E+02

~ M&0 6. + + .94E+02 0. 1. 1E+02 0. 4.11E+02 I-133 8.78E+01 1.49E+02 2.70E+04 1.87E+02 0. 1.08E+02 0. 4. 58E+01 CS.134 3.84E+03 9.26E+03 0. 2 ~ 29E+03 1.12E+03 1.07E+02 0. 4.32E+03 CS-136 2.95E+02 1.16E+03 0. 6.47E+02 8.87E+01 1.32E+02 0. 8.38E+02 CS- E+ 6. BBE+0 +0 9.12E+02 9.17E+01 0. 2.41E+03 BA-140 5.12E+03 7.38E+00 0. 1.57E+00 4.22E+00 6.03E+04 0. 3.29E+02 LA-140 4.69E+00 2.17E+00 0. 0. 0. 1.20E+05 0. 5.73E.01 CE.141 1.41E+01 9.49E+00 0. 3.38E+00 0. 2.57E+04 0. 1.09E+00

+ ~ f+ -01 0. .46E+04 0. 1.27E-01 CE-144 8.25E+02 3.38E+02 0. 1.38E+02 0. 1.94E+05 0. 4.38E+01 NP-239 4.09E-02 5.00E-03 0. 7.24E-03 0. 3.41E+02 0. 1.51E 03 12/19/84

f' DOSE FACTORS FOR LIQUID DISCHARGES BASED ON 1 CI/YR RELEASE OF EACH ISOTOPE IN DISCHARGE FLNI OF 1 GPN MITH NO ADDITIONAL DILUTIOH PATHIIAY - Salt Mater Shell Fish AGE GROUP - CHILD NUCLIDE ORGAN DOSE (HREN)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 1.61E-01 1.61E-01 1.07E-01 1.61E-01 1.61E.01 0. 1.61E-01 P-32 4.71E+06 2.96E+05 0. 0. 0. 5.30E+05 1.82E+05 CR-51 0. 0. 2.65E+00 9.78E.01 5.88E+00 1.12E>03 4.43E+00 HH-54 0~ +03 0. 4.64E+02 0. 4.77Ei03- 0. . BE+02 FE-55 1.05E+05 4.76E+05 0. 0. 3.52E+03 1.86E+05 0. 1.25E+05 FE-59 7.03E+04 1.73t+05 0. 0. 4.S1E+04 5.72E+05 0. 6.60E<04 CO-58 0. 1.57E+03 0. 0. 0. 9.31E+03 0. 4.72E+03 CO-60 .4 E+0 0. 0. 0. 2.44E+04 1.32Ei04 ZN-65 2.07E+05 8.56E+05 0. 4.39E+05 0. 4.13Ei05 0. 2.97E+05 RB-86 0. 2.95E+02 0. 0. 0. 5.82E+01 0. 1.38E+02 SR-89 2.33E+04 0. 0. 0. 0. 8.68E+02 0. 6. 66E+02 SR-90 . 4E+ 0. 0. 0. 2.73E+04 0. 7.45E+04 Y-91 4.94E+02 0. 0. 0. 0. 6.56E+04 0. 1.32E+01 ZR-95 7.06Ei00 1.65E+00 0. 1.05E+00 0. 1.71E+03 0. 1.50E+00 ZR-97 4.50E-02 9.17E.03 0. 1.37E-02 0. 2.70E+03 0. 4.18E.03 HB- .6 E+00 6. 7E-01 .87E-01 0. 1.21E+01 0. 5.12E-01 7.49E-03 2.87E+01 0. 6.54E+01 1.04E.02 7.91E+01 0. 5.74E+00 RU-103 5.69E+02 0. 0. 5.94E+02 0. 1.50Ei04 0. 2.30E+02 RU-106 1.02E+04 0. 0. 4.54E+03 0. , 1.58E+05 0. 1.26E+03 AG- OH +0 4. 6E+0 0. 8.'I BE+02 0. 1.70E+05 0. 2.48E+02 SB-124 1.19E+01 2.24E-01 2.87E-02 0. 9.2IEi00 3.36E+02 0. 4.69E+00 SB 125 1.20E+01 7.61E-01 6.90E-01 2.32E+00 9.95E+02 8.64E+01 0. 2.23E+00 TE-125N 9.63E+02 2.61E+02 2.70E+02 9.20E+02 0. 9.29E+02 0. 1.28E+02 TE- 2 +0 1.69E+02 +03 0. 3.27E+03 0. 7.66E+01 TE-129N 4.14E+03 1.16E+03 1.32E+03 4.03E+03 0. 4.99E+03 0. 6.42E+02 TE-131N 1.27t+02 8.51E+01 1 45E+04 4.39E+02 0. 4.03Et03 0. 6.75E+01 TE-132 7.11E+02 3.30E+02 3.DOE+03 1.12E+03 0. 5.45E+03 0. 3.81E+02

~ 9t+ 6. E .1 E+0 .DOE+02 0. .61E+01 0. 4.94E+02 I-133 1.16E+02 1.43E+02 3.44E+04 8.38E+01 0. 5.79Ei01 0. 5. 61E+01 CS-134 4.78E+03 8.05E+03 0. 1.02E+03 8.94E+02 4.35E+01 0. 1.71Ei03 CS.136 .32E+02 .21E+02 0. 2.90E+02 3.97E+01 5.91E+01 0. 3.75E+02 CS- .66E+ E+03 .92E+02 . 6E+0 3.93E+01 0. 9.61E+02 BA.140 6.69E+03 .86E+00 0. 7.03E-01 3.50E+00 2.84E+04 0. 3.93Et02 LA-140 5.7IEi00 .99E+00 0. 0. 0. 5.65E+04 0. 6.72E 01 CE-141 1.89E+01 .44E+00 0. 1 48E+00 0. 1.18E+04 0. 1.41E+00 E- + 0. 1 0. 1.54E+04 0. 5.69E.02 CE-144 1.09E+03 3.43E+02 0. 6. 19E+01 0. 8.90E+04 0. 5.83E+01 NP-239 2.28E.02 2.62E-03 0. 3.24E-03 0. 1.53E+02 0. 7.87E.04 A-1 0 12/19/84

0 ENVIROHHENTAL PATHNAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHMAY - GROUND PLANE DEPOSITION AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI -LLI SKIH TOTAL BMY H-3 0. 0. 0. 0. 0. 0. 0. 0.

C-14 0. 0. 0. 0. 0. 0. 0. 0.

P-32 0. 0. 0. 0. 0. 0. 0. 0.

CR-51 .68E+ 4.68& 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53Ei06 4.68E+06 NH-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE.59 2;75E+08 2.75E+08 2.75E+08 2.75E+M 2.75EiM 2.75E+08 3.23Ei08 2.75E+08 CO-57 1.89E+M 1.89E+08 1.89E+M 1.89E+08 '.89E+M 1.89E+08 2.08EiM 1.89E+08 CO-58 .BOE+M .BOE+08 ~ BOE+08 .BOE+08 .BOE+08 3.80E+08 4.45E+08 3.80E+08 C0.60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2 ~ 15E+10 2.52E+10 2.15E.10 NI-63 0. 0. 0. 0. 0. 0. 0. 0.

ZN.65 7.43E+08 7 43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+M 8.54E+08 7.43E+08 RB 86 9.01E+06 9.01E+06 9.01E+06 .01E+06 9.01E+06 9.01E+06 1.03E+07 9.0IEt06 SR-89 2.17E+04 2.17Ei04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17Ei04 SR-90 5.35E+06 5.35Ei06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.ME+06 1.08E+06 1.08E+06 1.08E+06 1.M&06 1.08E+06 1.22E+06 1.08E+06 E+ . 1E+08 . 1E+ .01E+08 5.01E+08 5.01E+M 5.86E+08 5. 01E+08 NB-95 1.36E+08 1.36E+08 1.36E+08 1.36Et08 1.36E+08 1 ~ 36E+08 1.61E+08 1.36E+08 RU.103 1.10E+M 1.10EiM 1.10E+08 1.10E+08 1 ~ 10E+08 1.10E+08 1.28E>M 1. 10E+08 RU-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+M 4 ~ 19E+08 5.03E+M 4.19E+08 AG + . BE+ . BE+09 . BE+09 3. BE+09 3. BE+09 4.17E+09 3. BE+09 CO-115II 0. 0. 0. 0. 0. 0. 0. 0.

BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION A-11 07/20/84

i i is

~ I II I

ENVIRONHENTAL PATHMAY.DOSE CONVERSION FAC'IORS FOR GASEOUS DISCHARGES PATHNAT - GROUND PLANE OEPOSITIINI - ADULT AGE GROUP NUCLIDE ORGAN DOSE FACTORS (SO.HETER-HREH/TR PER UCI/SEC)

L IVER 1HTRO ID K I 0 NET LUNG GI-LLI SKIN TOTAL BOOT SN-123 0. 0. 0. 0. 0. 0. 1;37E+06 0.

SN-126 5.16E+10 5.16E+10 5.16E+10 5. 16E+10 5.16E+10 5. 16E+10 5.76E+10 5.16E+10 S8-124 5.98E+08 5.98E+09 5.98E+08 5.98E+08 5.98E+08 5.98E+08 6.90E+08 5.98E+08 S8-12 + + . DE+09 2. DE+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE 125H 1.55E+06 1.55E+06 1 ~ 55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127H 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 9.74E+05 8.79E+05 TE-129H 3.SSE+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07 I- 30 5. 3E+06 .53E+06 .53E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72Et07 2.09E+07 1.72Et07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 1-133 2.CSE+06 2.48E+06 2.48E+06 2.48E+06 2.CSE+06 2.48E+06 3.DIE+06 2.4SE+06

4. OE+ 4. OE+ 4.50E+ 4.50E+05 4.50E+05 4.50E+05 5.35Ei05 4.50E+05 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS-136 1A9E+OS 1.49E+08 1A9E+08 1.49E+08 1.49E+08 1.49E+08 1.69E+08 1. C9E+08 CS .0 E+ . 3E+10 .03E+ 0 .03E+10 1.03E+10 1.03E+10 1 ~ 20E+10 1.03E+10 BA-1CO 1.68E+08 1.68E+08 1.68E+08 1.6SE+08 1.68E+08 1.68E+08 1.90E+08 1.68E+OS CE.141 1.37E+07 1.37E+07 1.37E+07 1.37Ei 07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE.144 1.13E+M 1.13E+08 1 ~ 13E+08 1.13E+08 1.13E+OS 1.13E+08 1.31E+08 1.13E+08

. BE+09 0. 0. 0.

ND 147 BASE+06 8.48E+06 BASE+06 e.csE+06 8.48E+06 e.CSE+06 1.02E+07 8.48E+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AHD RELATIVE DEPOSITION A-12 07/20/84

r t I j

ENVIRONHENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATWAY - GROUND PLANE DEPOSITION -

AGE GROUP TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BODY H-3 O. 0. 0. 0. 0. 0. 0. 0.

C-14 0. 0. 0. 0. 0. 0. 0. 0.

P-32 0. 0. 0. 0. 0. 0. 0. 0.

CR- 1 4.68E+06 4. +06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53E+06 4.68E+06 NN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 38E+09 1.38E+09 1.62E+09 1 ~ 1.38E+09 FE-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 2.75E+08 CO-57 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.ME+08 1.89Ei08 CO-58 .BOE+08 3.80E+08 .BOE+08 BOE+08 3.80EiM 3.80E+08 4.45E+M

~

3.80E+08 CO-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2 ~ 15E+10 2.15E+10 2.52E+10 2.15E+10 NI-63 0. 0. 0. 0. 0. 0. 0. 0.

ZN-65 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 8.54E+08 7.43E+08 RB-86 . 1E+06 9.01E+06 9.01E+06 9.01Ei06 9.01E+06 9.01E+06 1.03E+07 9.01E+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 SR-90 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 ZR- 1E+08 5.01E+08 .01E+08 '01E+08 5.01E+08 1 AD OBE+06 5.01E+08 5.86E+08 1.08E+06 5.DIE+M NB-95 1.36E+M 1.36E+08 1.36E+08 1.36E+08 1.36Et08 1.36E+08 1.61E+08 1.36E+08 RU-103 1.10E+M 1.10E+08 1.10E+08 1.10E+M 1.10E+08 1.10E+08. 1.28E+08 1.10E+M RU.106 4.19E+M 4 19E+08 4.19E+08 4.19E+M 4.19E+08 4.19E+08 5.03E<08 4.19E+08 AG- 1 . BE+ . BE+ . BE+09 ~ BE+09 . BEt09 3.58E+09 4.17E+09 .58E+09 CO-115N 0. 0. 0. 0. 0. 0. 0. 0.

BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELA'TIVE DEPOSITION A-13 07/20/84

ENVIRONHENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - GRQIND PLANE DEPOSITIOI AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (S4.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN IOIAL BODY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 0.

SN-126 5.16E+10 5.16E+10 5.16E+10 5. 16E+10 5.16E+10 5.16E+10 5.76E+10 5. 16E+10 SB-124 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 5.98E+08 6.90E+08 5.98E+08 SB- F09 2. DE+09 ~ 30E+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125N 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127II $ .79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 9.74E+05 8.79E+05 TE-129H 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07

.53E+06 . 3E+ .53E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 I-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1.72E+07 I-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 1-133 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 2.48E+06 3.01E+06 2.48Ei06 1-134 4 ~ OEi 4. DE+ . DE+05 4.50E+05 4.50E+05 4.50E+05 5.35E+05 4.50E+05 1-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS.134 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS-136 1 49E+0$ 1.49E+08 1.49E+08 1.49E+08 1.49E+M 1.49E+08 1.69E+08 1.C9E+08 CS- 3 0 E+10 .03E+ 0 ~ 03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA-1CO 1.68E+08 1.68Ei08 1.68E+08 1.68E+08 1.68Ei08 1.68E+08 1.90E+M 1.68E+08 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE-144 1.13E+08 1.13E+08 1.13E+0$ 1.13E+08 1.13E+M 1.13E+08 1.31E+08 1.13E+08 PR- 0. 0. 0. 0. 0.

N0-147 8.48E+06 8.48E+06 8.48E+06 e.ceE+06 8.48E+06 8 CBE+06 1.02E+07 8.48E+06 BASED ON < UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AIO A VALUE OF 1. FOR X/4, DEPLE'TED X/4 AND RELATIVE DEPOSI'TION A-14 07/20/84

ENVIRONHENTAL PATHMAT-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAT GRQBID PLANE DEPOS IT IQI AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-NREH/YR PER UCI/SEC)

MNE LIVER THTROID KIDNEY LUNG GI-LLI SKIN TOTAL BMT H-3 0. 0. 0. 0. 0. 0. 0. 0.

C-14 0. 0. 0. 0. 0. 0. 0. 0.

P.32 0. 0. 0. 0. 0. 0. 0. 0.

CR- 1 ~ + +06 4.68E+06 4.68E+06 4.68E+06 4.68E+06 5.53E+06 4.68E+06 NN-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE-59 2.75E+08 2.75E+N 2.75E+08 2.75E+08 2.75E+08 2.75E+08 3.23E+08 2.75E+08 Co-57 1.89E+Oe 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.08E+08 1.89E+08 Co- 8 .BDE+M +08 ~ BDE+08 .BDE+08 3.80E+08 3.80Et08 4.45E+08 3.80E+08 CO-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 2.15E+10 NI -63 0. 0. 0. 0. 0. 0. 0. 0.

ZN-65 7.43E+08 7 43E+08 .43E+08 7.43E+08 7.43E+M 7.43E+M 8.54E+08 7.43Ei08 RB 86 .01E+06 . 1E+ . 1E+06 9.DIE+06 .01E+06 9.01Ei06 1.03E+07 9.DIE+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E<06 5.35E+06 Y-91 1.ME+06 1.08E+06 1.ME+06 1 ~ 08E+06 1.M&06 1.08E+06 1.22E+06 1.08E+06 ZR ~ IE+ ~ 0 E+  ; 1E+08 ~ 01E+08 .01E+08 5.01E+M 5.86E+08 5.01E+08 NB-95 1.36E+08 1.36E+08 1.36EtM 1.36E+08 1.36E+08 1.36E+08 1.61E+M 1.36E+M RU.103 1.10E+08 1 ~ 10E+N 1. DE+08 1 ~ 10E+08 1. 10E+08 1.10E+08 1.28E+08 1. 10E<08 RU-106 4.19E+08 4.19E+08 4 ~ 19E+08 4.19E+08 4.19E+08 4.19E+08 5.03Ei08 4.19E+08

~ + . BE+09 .58E+ 3.58E+09 .58E+09 4.17E+09 3. BE+09 CD-115N 0. 0. 0. 0. 0. 0. 0. 0.

BASED ON 1 Ucl/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE Of 1. FOR X/a, DEPLETED X/O AND RELATIVE DEPOSITION A-15 12/19/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY - GRIND PLANE DEPOSITION AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 SN-126 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5 ~ 16E+10 5.16E+10 5. 76E+10 5.16E+10 58-124 5.98E+08 5.98E+M 5.98E+08 5.98E+OS 5.98E+08 5.98E+OS 6.90E+08 5.9SE+M SB- + ~ DE+09 2. DE+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125H 1.55Ei06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127H S.79E+05 8.79E+05 e.79E+os S.79E+05 e.79E+05 e.79eos 9.74E+05 e.79eos TE-129H 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07

.53E+06 ~ + 5.53E+06 ~ 53E+06 5.53Ei06 5.53E+06 6. 71E+06 5.53E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1.72E+07 I.132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1.25E+06 I-I33 2 CSE+06 2.48E+06 2.CBE+06 2.48E+06 2.4SE+06 2.48E+06 3.DIE+06 2.48E+06

4. OE 4. OE+ . DE+05 . DE+05 4. OE+05 4 '0E+05 5.35E+05 4.50E+05 I-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 6.99E+09 8.15E+09 6.99E+09 CS 136 1.49E+OS 1 49E+OS 1.49E+08 1.49E+M 1.49E+08 1 49E+M 1.69E+08 1.49E+08 CS-1 ~ E+ .03E+ . 3E+10 1 ~ 03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA.NO 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+08 1.68E+M 1.90EtOS 1.68E+M CE-N1 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.5CE+07 1.37E+07 CE-N4 1.13E+08 1.13E+08 1.13E+08 1.13E+M 1.13E+08 1.13E+Oe 1.31E+OS 1.13E+08

0. 0. 0.

NO-N7 8.48E+06 S.CSE+06 S.CSE+06 S.CSE+06 e.ceE+06 e.CSE+M 1.02E+07 8.48E+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/Q, DEPLETED X/Q ANO RELATIVE DEPOSITION A-16 12/19/SC

ENVIRONHENTAL PATHMAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHMAY - GROUND PLANE DEPOSITION AGE GROUP . IHFANT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BCOY H-3 0. 0. 0. 0. 0. 0. 0.

C-14 0. 0. 0. 0. 0. 0. 0. 0.

P 32 0. 0. 0. 0. 0. 0. 0. 0.

CR-5 .68E+06 4.6BE+06 4.68E+06 4.68E+06 4. 68E+06 5.53E+06 4.68E+06 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.62E+09 1.38E+09 FE-59 2.75E+08 2.75E+M 2.75E+08 2.75E+M 2.75E+08 2.75E+08 3.23E+08 2.75E+08 CO-57 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 2.08E+08 1.89E+08 CO- 8 .BOE+08 .BOE+08 .BOE+08 3.80E+08 3.80E+08 3.80E+08 4.45E+08 3.80E+08 C0.60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.52E+10 2.15E+10 NI-63 0. 0. 0. 0. 0. 0. 0.

ZN.65 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 7.43E+08 8.54E+08 7.43Ei08 RB- 9.01E+06 9.01E+06 1E+06 9.01E+06 9.01E+06 9.01E+06 1.03E+07 9.DIE+06 SR-89 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.17E+04 2.51E+04 2.17E+04 SR-90 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 5.35E+06 6.33E+06 5.35E+06 Y-91 1.ME+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.22E+06 1.08E+06 ZR- . 1E . 1E+08 E+08 .01E+08 5.01E+08 5.01E+08 5.86E+08 5.DIE+08 NB-95 1.36E+M 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36EtM 1.61E+08 1.36E+08 RU.103 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10E+08 1.10EiM 1.28E+08 1.10E+M RU-106 4.19E+08 4.19E+08 4.19E+M 4.19Ei08 4.19E+08 4.19E+08 5.03E+08 4.19E+08 AG- TON + . 8E+ .58E+09 . BE+09 3.58Ei09 4.17E+09 3.58E+09 CO-115N 0. 0. 0. 0. 0. 0~ 0. 0.

BASED ON 1 UCI/SEC RELEASE RATE Of EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/Q, DEPLE'IED X/Q AND RELATIVE DEPOSITION A-17 07/20/84

ENVIRONHENTAL PATHNAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PAYDAY - GROUND PLANE OEPOSITIQI AGE GROUP INFANT NUCL IDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SHIH TOTAL BMY SN-123 0. 0. 0. 0. 0. 0. 1.37E+06 0.

SN-126 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.16E+10 5.76E+10 5.16E+10 58-124 5.98E+08 5.98E+08 5.98E+08 5.98E+M 5.98E+M 5.98E+08 6.90E+08 5.98EiM SB-1 +09 ~ DE+09 2.30E+09 2.30E+09 2.30E+09 2.59E+09 2.30E+09 TE-125N 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 2.13E+06 1.55E+06 TE-127H 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 8.79E+05 9.74E+05 8.79Et05 TE-129H 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 3.85E+07 4.52E+07 3.85E+07 I-130 .53E+06 .5 E+06 ~ E+06 5.53E+06 5.53E+06 5.53E+06 6.71E+06 5.53E+06 I-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09Ei07 1.72E+07 I-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25Ei06 1.25E+06 1.47E+06 1.25E+06 l-133 2.48E+06 2.48E+06 2 48E+06 2 48E+06 2.48E+06 2.48E+06 3.01E+06 2.48E+06 l-134 4. DE+05 4.50& . DE+05 4.50E+05 4.50Ei05 4.50E+05 5.35E+05 4.50E+05 I-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.99E+06 2.56E+06 CS-134 6.99E+09 6.99E+09 6.99Ei09 6.99E+09 6.99E+09 6.99Et09 8.15E+09 6.99E+09 CS-136 1 49E+08 1 49E+M 1.49E+M 1.49E+08 1.49E+M 1 49E+08 1.69E+08 1.49E+08 CS- +10 E+ 0 .03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 1.03E+10 BA-140 1.68E+08 1.68E+M 1.68E+M 1.68E+08 1.68E+08 1.68E+08 1.90E+08 1.68E+08 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.54E+07 1.37E+07 CE-144 1.13E+M 1.13E+08 1.13E+08 1.13E+M 1.13E+08 1.13E+08 1.31E+08 1.13E+08

0. 0. 0. 0.

ND-147 8.48E+06 8.48E+06 8 48E+06 8.48E+06 8.48E+06 8.48E+06 1.02E+07 8.48E+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1 ~ FOR X/O, DEPLETED X/0 AND RELATIVE DEPOSITION A-18 07/20/84

ENVIROHHENTAL PATHWAY DOSE COHVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHWAY - INHALATION AGE GROUP - ADULT NUCLIDE ORGNI DOSE FACTORS (HREH/YR PER UCI/CU.HETER)

BONE LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BCOY H-3 0. 1.07E+03 1.07E+03 1.07Ei03 1.07E+03 1.07E+03 0. 1.07E+03 C-14 1.82E+04 3 42E+04 3.42E+03 3.42E+03 3.42E+03 3.42E+03 0. 3.42E+03 P-32 1.32E+06 i04 0. 0. 0. 8.64E+04 0. 5.02E+04 CR-5 .95E+01 2.28E+01 1.44E+04 3.32E+03 0. 1.DOE+02 HH-54 0. 3.96E+04 0. 9.84E+03 1.40E+06 7.74E+04 0. 6.30E+03 FE-59 1.18E+04 2.78E+07 0. 0. 1.02Et06 1.88E+05 0. 1.06E+04 CO-57 0. 6.92E+02 0. 0. 3.70Et05 3.14E<04 0. 6.71E+02 C0.58 1.58E+ 3 0. 0. 9.28E+05 1.06E+05 0. 2.07Ei03 C0.60 0. 1.15E+04 0. 0. 5.98E+06 2.85E+05 0. 1.48E+04 N 1-63 4.32E+05 3.14E+04 0. 0. 1.78E+05 1 '4E+04 0. 1.45E+04 ZN.65 3.24E+04 '.03E+05 0. 6.90E+04 8.72E+05 5.34Ei04 0. 4.66E+04 RB-86 0. 1.35E+ 0. 0. 0. 1.66E+04 0. 5.90E+04 SR-89 3.04E+05 0. 0. 0. 1 40E+06 3.50E+05 0. 8.72E+03 SR-90 9.92E+07 0. 0. 0. 9.60Ei06 7.22Ei05 0. 6.10E+06 Y-91 4.62E+05 0. 0. 0. 1.70E+06 3.85E+05 0. 1.24E+04 ZR- E+04 0. .42E+04 1.78E+06 1.50E+05 0. 2.33E+04 HB-95 1 41E+04 7.82E+03 0- 7.74E+03 5.06E+05 1.04E+05 0. 4.21Ei03 RU-103 1.58E+03 0. 0. 5.83E+03 5.06E+05 1 '0E+05 0. 6.58E+02 RU-106 6.91E+IV 0. 0. 1.34E+05 9.44E+06 9.12E+05 0. 8.72E+03 AG OH 1.97E+04 4.64E+06 3.02E+05 0. 5.94Et03 CD-115H . 0. 1.97E+05 0. 1.50E+05 1.41E+06 3.84E+05 0. 6.36E<03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AHD A VALUE OF 1 ~ FOR X/4, DEPLETED X/4 AHD RELATIVE DEPOSITION A-19 07/20/84

0 ENVIRONHENTAL PATHMAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHMAT - INHALATION AGE GROUP - ADULT HUCL IDE ORGAN DOSE FACTORS (HREH/TR PER UCI/CU.HETER)

LIVER THTROIO KIDNET LUNG Gl-LLI SKIN TOTAL BCOY SH-123 2 42E+05 5.33E+03 4.53E+03 0. 2.30E+06 3.14E+05 0. 7.86E+03 SN-126 1.26E+06 3.34E+04 9.8CE+03 0. 9.36E+06 1.27E+05 0. C.SDEt04 5$ -124 3.12E+04 5.89E+02 7.55E+01 0. 2.48E+06 4.06E+05 0. 1.24E+04 SB- 6.61E E+0 .8 +01 0. 2. DE+06 1.DIE+05 0. 1.33E+04 TE-125H 3 42E+03 1.58E+03 1.05E+03 1.24E+04 3.14E+05 7.06E+04 0. 4.67E+02 TE-127N 1.26E+04 5.62E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 0. 1.57Ei03 TE-129H 9.76E+03 4.67E+N 3 CCE+03 3.66E+04 1.16E+06 3.83E+05 0. 1.5SE+03 1-130 4. BE+0 E+ . 4E+06 .09E+04 0. 7.69Et03 0. 5.29Ei03 1-131 2.52E+04 3.58E+04 1.19E+07 6. 1CE+04 0. 6.28E+03 0. 2.05E+04 1-132 1.16E+03 3.26E+N 4.38E+05 5.19E+03 0. 4.06E+02 0. 1.16E+03 1-133 8.6CE+03 1 49Ei04 2.93E+06 2.60E+04 0. S.72E+03 0. 4.5CE+03 6.C E 1. E+03 . DE+05 .75E+03 0. 1.01E+00 0. 6.16E+02 1-135 2.89E+03 6.99E+03 9.36E+05 1.11E+04 0. 5.25E+03 0. 2.58E+03 CS-134 3.74E+05 8 CSE+05 0. 2.ME+05 9.76E+04 1.0CE+04 0. 7.29E+05 CS-136 3.91E+04 1.46E+05 0. 8.56E+04 1.20E+04 1 ~ 17E+04 0. 1.11E+05 CS- 4. + . 2E+ 0. 2.22E+05 7.53E+04 8 COEt03 0. C.29E+05 BA-140 3.90E+04 4.90E+01 0. 1.67E+01 1.27E+06 2.ISEt05 0. 2.57E+03 CE-141 1.99E+04 1.35E+04 0. 6.26E+03 3.62E+05 1.20E+05 0. 1.53Ei03 CE-144 3 43E+06 1.43E+06 0. 8.48E+05 7.78E+06 8.16E+05 0. 1. 84E+05

~ + ~ E+ .16E+03 .SIE+05 .DOE+05 0. 4.63E+02

16. 147 5.27E+03 6.10E+03 0. 3.56E+03 2.21E+05 1.73E+05 0. 3.65Ei02 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITIOH A-7 II 07/20/84

I ENVIRONHENTAL PATHMAY-DOSE CONVERSION FAClORS FOR GASEOUS DISCHARGES PATHMAY - INHALATION AGE 'GRIJP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SO.HETER HREH/YR PER UCI/CU.HETER)

L IVER THYROID KIDNEY LUNG Gl-LLI SKI H TOTAL BODY 8.3 0. dASE+02 8ASE+02 1.07E+03 8.48E+02 8.48E+02 0. 8.48E+02 C.14 4.58E+N 4.53Ei03 4.53E+03 3.42E+03 4.53Ei03 4.58E+03 0. 4.53E+03 P-32 1.32E+06 .72E+OC 0. 0. 0. 8.64E+04 0. 5.02E+04

0. E+01 ~ 28E+01 1.44E+04 3.32E+03 0. 1.DOE+02

0. 3.96E+04 0. 9.84E+03 1.40E+06 7.74E+04 0. 6.30Et03 FE-59 1.18E+04 2.78E+07 0. 0. 1.02E+06 1.88E+05 0. 1.06E+04 CO-57 0. 6.92E+02 0. 0. 3.70Ei05 3.14E+04 0. 6.71Ei02 CO-SS 1. 6E+0 ~ 37E+06 9.52E+04 0. 2.34E.02 CO-60 0. 1.24E+03 0. 0. 8.56E+06 2.35E+05 0. 1.65E+34 NI-63 4.32E+05 3.ICE+04 0. 0. 1.78E+05 1.34E+04 0. 1.C5E+04 ZN-65 .24E+04 1.03E+05 0. 6.90E+04 8.72Ei05 5.34E+04 0. 4.66E+04 RB-86 1. E+ 0. 0. 1.66Ei04 0. 5.90Ei04 SR-89 3.37E+04 0. 0. 0. 2.50E+06 3.54E+05 0. 1.11Et03 SR-90 1.18E+07 0. 0. 0. 1.66E+07 7.24E+05 0. 7.23E+05 Y-91 5.38E+04 0. 0. 0. 2.86E+06 3.74E+05 0. 1.44Ei03

~ + .42E+04 2.56E+06 1. 3Ei05 0. 2.54E+03 NB-95 1.36E+03 8.24E+02 0. 7.74E+03 7.17E+05 8.80E+04 0. 4.62E+02 RU-103 1.63E+02 0. 0. 5.83E+03 7.51E+05 9.44E+04 0. 7.32E+01 RU-106 d.40E+03 0. 0. 1.34E+05 1.64E+07 9.28E+05 0. 1.06E>03 AG- ON + + .97E+04 4.64E+06 .02E+05 0. 5.9CE+03 CD-115N 0. 1 97E+05 0. 1.58E+05 1.41E+06 3.8CE+05 0. 6.36E+03 BASED ON 1 UCI/SEC RELEASE RAlE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/4, DEPLElED X/4 ANO RELAllVE DEPOSITIOH A-21 12/19/84

ENVIRONHENTAL PATNMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY INHALATION AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (HREH/YR PER UCI/CU.HETER)

BONE LIVER THTROID XIDNET LUNG Gl-LLI SABIN TOTAL BOOT SN-123 2.79E+04 6.14E+02 4.92E+02 0. 3.91E+06 3.13E+05 0. 9.20E+02 SN 126 1.26E+06 3.34E+04 9.84E+03 0. 9.36E+06 1.27E+05 0. 4.80E+04

$ 8-124 .12E+04 5.89E+02 7.55E+01 0. 2.48E+06 4.06E+05 0. 1.24E+04 SB-12 ~ E+ +01 0. 2.20E+06 1.01E+05 0. 1.33E+04 TE-125H 4.07E+02 1.86E+02 1.17E+02 1.24E+04 5.36E+05 7.08E+04 0. 5.53E+01 TE-127H 1.26E+04 5.62E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 0. 1.57E+03 TE-129H 1.19E+03 5.64E+02 3.90E+02 3.66E+04- 2.03E+06 3.84E+05 0. 1.92E+02 1-1 0 +03 E+04 E+06 .09E+04 0. 7.69E+03 0. 5.29E+03 I-131 3.37E+04 4.72E+04 1.39E+07 6.14E+04 0. 5.96E+03 0. 2.82Et04 I-132 1 ~ 16E+03 3.26E+03 4.38E+05 5.19E+03 0. 4.06E+02 0. 1.16E+03 1-133 1.23E+04 2.06E+04 3.83E+06 2.60E+04 0. 1.DOE+04 0. 6.34E+03 I. 34 6.45E+0 +0 .30E+05 E+03 0. 1. 01E+00 0. 6.16E+02 I-135 2.69E+03 6.99E+03 9.36E+05 1. 'I 1E+04 0. 5.25Ei03 0. 2.58E+03 CS-134 4.83E+05 1.TOE+06 0. 2.ME+05 1.44E+05 8.96&03 0. 5.44Ei05 CS.136 3.91E+04 1.46E+05 0. 8.56E+04 1.20E+04 1.17E+04 0. 1.11E+05

+ 8. 4E+ .22E+ 1.18E+05 7.68E+03 0. 3.03E+05 BA 140 5.30E+03 4.85E+00 0. 1.67E+01 2.02Et06 2.12E+04 0. 3.42E>02 CE-141 2.27E+03 1.52E+03 0. 6.26E+03 5.83E+05 1.14E+05 0. 1.74E+02 CE-144 4.19E+05 1.74E+05 0. 8.48E+05 1.38E+07 8.40E+05 0. 2.24E+04 E+ 0. . 6E+0 .81E+05 2.DOE+05 0. 4.63Ei02 IO.147 5.27E+03 6.10E+03 0. 3.56E+03 2.21E+05 1.73E+05 0. 3.65E+02 BASED ON 1 UCI/SEC RELEASE RATE Of EACH ISOTOPE IN AND A VALUE OF 1. fOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION A-22 l2/19/84

0 ENVIRONMENTAL PATHNAY-DOSE CONVERSION FACtORS fOR GASEOUS DISCHARGES PATHNAY - INHALATION - CHILD AGE CROUP NUCLIDE ORGAN DOSE FACTORS (HREH/TR PER UCI/CU.HETER)

LIVER THTROID KIDNET LUNG GI-LLI SKIM TOTAL SCOT H-3 0. 7.51E+02 7.51E+02 4.96E+02 7.51E+02 7.51E+02 0. 7.51E+02 C-14 6.25E+N 6.25E+03 6.25E+03 1.58E+03 6.25E+03 6.25E+03 0. 6.25E+03 P-32 6.TIE+05 .57E+04 0. 0. 0. 4.DOE+04 0. 2.32E+04 E+01 1.06E+01 6.66E+03 1.54E+03 0. 4.63E+01 NM-54 0. 1.83E+04 0. 4.55E+03 6.48E+05 3.58E+04 0. 2.91E+03 FE.59 5 44E+03 1.28E+07 0. 0. 4.70E+05 8.70E+04 0. 4.88E+03 C0-57 0. 3.20E+02 0. 0. 1.71E+05 1.45E+04 0. 3.10E+02 CO-5 0. E+02 0. 0. 1.13E+06 3.62E+04 0. 2.68E+02

0. 1.07E+03 0. 0. 6.92E+06 9.36E+04 0. 1.88E+03 NI -63 ~

2.DOE+05 1.45E+04 0. 0. 8.25E+04 6.18E+03 0. 6.70E+03 ZN- 1.50E+04 4.77E+04 0. 3.19E+04 4.03E+05 2.47E+04 0. 2.15Ei04 RB.86 0. 6. E+04 0. 0. 0. 7. E+03 0. 2.73E+04 SR-89 5.37E+04 0. 0. 0. 2.24E+06 1.69E+05 0. 1.54Ei03 SR-90 1.64E+07 0. 0. 0. 1.48E+07 3.45E+05 0. 9.99E+05 T-91 7.44E+04 0. 0. 0. 2 '5E+06 1.78E+05 0. 1.98E+03 ZR E+ ~ 8&0 0. .51E+04 2.12E+06 5.74E+04 0. 2.98E+03 NB.95 1.70E+03 7.25E+02 0. 3.58E+03 5.85E+05 3.32E+04 0. 5.33E+02 RU-103 2.16E+02 0. 0. 2.70E+03 6.33E+05 4.22E+04 0. 8.73E+01 RU-106 1.15E+04 0. 0. 6.18E+04 1.45E+07 4.37E+05 0. 1.44E+03 AG- DN E+ 0. . DE+03 .1 E+06 1.40E+05 0. 2.75Ei03 CD.TTSN 0. 9.10E+04 0. 7.33E+04 6.51E+05 1.78E+05 0. 2.94E+03 BASED Ql 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AMD A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITION A-23 12/19/84

ENVIRONNENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - INHALATION AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (HREH/YR PER UCI/CU.HETER)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SXIN TOTAL BODY SN-123 3.85E+04 6.44E+02 6.81E+02 0. 3.50E+06 1.49E+05 0. 1.27E+03 SN-126 5.85E+05 1.55E+04 4.55E+03 0. 4.33E+06 5.88E+04 0. 2.22E+04

$ 8-124 1 CCE+04 2.72E+02 3.49E+01 0. 1.15E+06 1.88E+05 0. 5.74E+03 SB .06E+04 E+01 0. 1.02E+06 4.66E+04 0. 6.14E+03 TE-125N 5.62E+02 1.9CE+02 1.61E+02 5.74E+03 4.81E+05 3.38E+04 0. 7.62E+01 TE-127ll 5.85E+03 2.60E+03 1.52E+03 2.12E+04 4.44E+05 6.92E+04 0. 7.25E+02 TE-'l29H 1.64E+03 S.SSE+02 5 COE+02 1.69E+04 1.80E+06 1.82E+05 0. 2.60E+02 1-130 .1 E+0 6. + S.O +05 9.66E+03 0. 3.56E+03 0. 2.45E+03 I-131 4.55E+04 4.63E+04 1.5CE+07 2.84E+04 0. 2.65E+03 0. 3.50E+04 I-132 5.37E+02 1 ~ 51E+03 2.03E+05 2.40E+03 0. 1.88E+02 0. 5.37E+02 I-133 1.68E+04 2.05E+04 5.03E+06 1.20E+04 0~ 5.55E+03 0. 8.03E+02

~ SE+ +0 ~ 06E+0 .27E+03 0. 4.66E-01 0. 2.85E>02 l-135 1.24E+03 3.23E+03 4.33E+05 5.14E+03 0. 2.43E+03 0. 1.19Ei03 CS-134 6.22E+05 9.95E+05 0. 1.33E+05 1.19Ei05 3.77E+03 0. 2.23E+05 CS-136 1.81E+04 6.77E+04 0. 3.96E+04 5.55E+03 5.40Ei03 0. 5.14E+04 CS- .66E+ ~ + .03E+05 1.DOE+05 3.41E+03 0. 1.25E+05 BA-140 7.14E+03 4.66E+00 0. 7.73E+00 1.74E+06 9.92E+03 0. 4.22E+02 CE-141 3.13E+03 1.57E+03 0. 2.90E+03 5 '4E+05 5.44E+04 0. 2.33E+02 CE-144 5.81E+05 1.82E+05 0. 3.92E+05 1.23E+07 4.DOE+05 0. 3.10E+04

~ + E ~ 99E+0 1.30Ei05 9. 5E+04 0. 2.14E+02 ND-147 2 CCE+03 2.82E+03 0. 1.65E+03 1.02Ei05 7.99E+04 0. 1.69E+02 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/O, DEPLE'IED X/O AHD RELATIVE DEPOSITION A-24 12/19/84

ll ENVIRONNENI'AL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - INHALATION AGE'GROUP INFANT NUCLIDE ORGAN DOSE FACTORS (HREN/YR PER UCI/CU.HETER)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BCOY H-3 0. 4.30E+02 4.30E+02 1.88E+02 4.30E+02 4.30E+02 0. 4.30E+02 C-14 5.04E+03 4.28E+N 4.28E+03 5.98E+02 4.28E+03 4.28E+03 0. 4.28E+03 P-32 2.31E+05 1.35E+04 0. 0. 0. 1.51E+04 0. 8.78E+03

.94E+01 3.99E+00 2.52E+03 5.81Ei02 0. 1.75E+01 HN-54 0. 6.93E+03 0. 1.72E+03 2.45E+05 1.35E+04 0. 1.TOE+03 FE-59 2.06E+03 4.86E+06 0. 0. 1.78E+05 3.29E+04 0. 1.85E+03 CO-57 0. 1.21E+02 0. 0. 6.47E+04 5.50E+03 0. 1.18E+02 CO- 8 .18E+ 0. 0. 8.79E+05 1.21E+04 0. 1.68E+02 CO-60 0. 8.40E+02 0. 0. 5.57Ei06 3.28E+04 0. 1.17E+03 NI-63 7.56E+04 5.49E+03 0. 0. 3.12Ei04 2.34E+03 0. 2.53E+03 ZN 65 5.67E+03 1.81E+04 0. 1.21E+04 1.53Ei05 9.35E+03 0. 8.15Ei03 RB-86 0. 7E+ 0. 0. 0. 2.91E+03 0. 1.03E+04 SR-89 4.31E+04 0. 0. 0. 2.31E+06 6.80E+04 0. 1.24E+03 SR-90 1.32E+07 0. 0. 0. 1.53E+07 1.39Ei05 0. 8.06E+05 Y.91 5.98E+04 0. 0. 0. 2.63E+06 7.17Ei04 0. 1.60Ei03 ZR- .08& ~ E+0 0. 9 48E+03 1.81E+06 1.41E+04 0. 1.95E+03 NB-95 1.28E+03 5.75E+02 0. 1.35Ei03 4.77E+05 1.21E+04 0. 3.37E+02 RU-103 1.69E+02 0. 0. 1.02E+03 5.66E+05 1.58E+04 0. 5.85E+01 RU-106 9. 1E+03 0. 0. 2.34E+04 1 '0E+07 1.76E+05 0. 1 ~ 14E+03 E+ 0. E+03 8.12E+05 +04 0. 1.04E+03 CD'115N 0. 3 44E+04 0. 2.77E+04 2.46E+05 6.72E+04 0. 1.11E+03 BASED Ol 1 UCI/SEC RELEASE RATE OF EACH ISO'TOPE IN ANO A VALUE OF 1. FOR X/B, DEPLETED X/0 AND RELATIVE DEPOSITION A-25 07/20/84

ENVIROHNENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES SABIN PATNIAY - INHALATION AGE GROUP - IHFANT NUCLIDE ORGAN DOSE FACTORS (HREN/YR PER UCI/CU.HETER)

LIVER THYROID KIDNEY LUNG Gl LLI TOTAL BODY SN 123 3.11E+04 6.45E+02 6.45E+02 0. 3.61E+06 5.99E+04 0. 1.02E+03 SN-126 2.21E+05 5.85E+03 1.72E+03 0. 1.64E+06 2.23E+04 0. 8.40Et03 SB-124 5.46E+03 1.03E+02 1.32E+01 0. 4.34E+05 7.11E+04 0. 2.17E+03

.16E+04 E .03E+01 0. 3.85E+05 1. 6E+04 0. 2.32E+03 TE-125N 4.54Ei02 1.95E+02 1.53E+02 2.17E+03 4.96E+05 1.36E+04 0. 6.16Ei01 TE-127ll 2.21E+03 9.83E+02 5.75E+02 8.DIE+03 1.68E+05 2.62E+04 0. 2.74E+02 TE-129N 1.32E+03 5.80E+02 5.08E+02 6.40E+03 1.83E+06 7.32E+04 0. 2.06Ei02 1-1 0 8.02E+02 E+ .05E+05 .65E+03 0. 1.35E+03 0. 9.25Et02 1-131 3.63E+04 4.27E+04 1.41E+07 1.07E+04 0. 1.07E+03 0. 2.51E+04 1-132 2.03E +0 2 , 5. 70E+02 7.67E+04 9.09E+02 0. 7.11E+01 0. 2.03E+02 1-133 1.34E+04 1.93E+04 4.66E+06 4.55E+03 0. 2 '8E+03 0. 5.87Ei03 E+02 E+02 .02E+04 4.82E+02 0. 1.76E-01 0. 1.08E+02 1-135 4.70E+02 1.22E+03 1.64E+05 1.95E+03 0. 9.18E+02 0. 4.51E+02 CS-134 4.80E+05 8.25E+05 0. 5.04E+04 1.01E+05 1.37Ei03 0. 7.32Ei04 CS-136 6.85E+03 2.56E+04 0. 1.50E+04 2.10E+03 2.04Ei03 0. 1.95E+04 6.86E . 1E+ 0. .89E+04 9.45E+04 1.32E+03 0. 4.41E+04 BA-140 5.70E+03 4.27E+00 0. 2.93E+00 1.64E+06 3.88E+03 0. 2.95E+02 CE-141 2.52E+03 1.55E+03 0. 1.10E+03 5.24E+05 2.06E+04 0. 1.81E+02 CE-144 4 68E+05 1.82E+05 0. 1 48E+05 1.27E+07 1.61E+05 0. 2.49E+04 PR- 4 E+ 6. + +0 4.91E+04 . DE+04 0. 8.11E+01 le-147 9.28E+02 1.07E+03 0. 6.28E+02 3.86E+04 3.02E+04 0. 6.38EiOI BASED ON I UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/O, DEPLETED X/O AND RELATIVE DEPOSITION A-26 12/19/84

ENVIRONHENI'AL PATHWAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHMAY AIR GRASS-COLI-HEAT (C(NITAHINATED FORAGE) AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THTROI 0 KIDNEY LUNG GI-LLI SKIH TOTAL SOOY H 0. E+02 4.13E+02 4.13E+02 4.13E+02 4.13E+02 0. 4.13Ei02 C.14 3.33E+05 6.67E+04 6.67E+04 6.67E+04 6.67E+04 6.67E+04 0. 6.67E+04 P-32 4.67E+09 2.93E+08 0. 0. 0. 5.25E+08 0. 1.81E+08 CR-51 0. 0. 4 '3E+03 1.56E+03 9.38E+03 1.78E+06 0. 7.07E+03

0. E+06 0. 2.81E+07 0. 1.75E+06 FE 59 2.67E+0& 6.33E+08 0. 0. 1.76E+08 2.09E+09 0. 2.41E+08 CO.57 0. 5.6CE+06 0. 0. 0. 1.43E+08 0. 9.3&E+06 C0-58 0. 1.&3E+07 0. 0. 0. 3.70E+08 0. C.09E+07

0. E+ O. 0. 0. 1.41E+09 0. 1.66E+08 Nl-63 1.89E+09 1.31E+08 0. 0. 0. 2.73E+07 0. 6.33Ei07 ZN 65 3.56E+08 1.13E+09 0. 7.57E+08 0. 7.13E+08 0. 5.12E+08 RS-86 0. 4.89E+0& 0. 0. 0. 9.6CE+07 0. 2.2&E+08 SR-89 ~ 03E+08 0. 0. 0. 0. C.&4E+07 0. 8.67E+06 SR-90 1.25E+10 0. 0. 0. 0. 1.45Ei09 0. 3.05E+09 Y 91 1.14E+06 0. 0. 0. 0. 6.26E+08 0. 3.05E+04 ZR-95 3.78E+06 .67E+06 0. 2.01E+06 0. 8.30E+09 0. 8.26E+05 NS- . DE+06 +06 .27E+06 0. 7.75E+09 0. 5.02E+05 RU-103 1.06E+0& 0. 0. 4.06Ei08 0. 1.24E+10 0. C.59E+07 RU-106 2.ME+09 0. 0. 5.41E+09 0. 1.81E+11 0. 3.5CE+08 AG-11N 6.71E+06 6.21E+06 0. 1.22E+07 0. 2.53E+09 0. 3.69E+06

~ + 1.16E+06 6.15E+0 0. 4.67E+04 SASED (Nl 1 UCI/SEC RELEASE RATE OF EACH ISOtOPE IN AND A VALUE OF 1. FOR X/Q, DEPLETED X/Q AND RELAtlVE DEPOSITIOH NOTE - THE NITS fOR C 14 AND H-3 ARE (HREH/TR PER UCI/CU.HETER)

A-? 7 07/20/84

ENVIRONHENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY - AIR-GRASS-CN-IKlT ((XNITAHIHATED FORAGE) -

AGE GROUP ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BODY SN-1 0. 0. 0. 0. 0. 0. 0.

SN-126 1.86E+10 3.69E+08 1.08E+08 0. 6 46E+06 6.19E+09 0. 5.33E+08 SB 124 1.99E+07 3. 8+05 4.80E+04 0. 1.54E+07 5.62E+08 0. 7.85E+06 SB 125 6.65E+07 1.58E+07 1.29E+07 1.74E+08 2.49E+09 3.80E+M 0. 1.05E+07 TE-1 II ~ + .OSE+08 1.46E+09 0. 1.43E+09 0. 4.81E+07 TE-127N 1.13E+09 3.93E+08 2.96E+08 4.56E+09 0. 5.11E+09 0. 1.39E+08 TE-129N 1.14E+09 4.29E+08 3.95E+OS 4.79E+09 0. 5.76E+09 0. 1.82Ei08 1-130 2.38E-06 7.05E.06 8.96E.04 1.10E.05 " 0. 6. 04E-06 0. 2.77E.06 1-131 1.08E+0 1. E .06E+09 .65E+07 0. 4.07E+06 0. 8.85E+06 1-132 0. 0. 0. 0. 0. 0. 0. 0.

1-133 . 4.COE-OI 7.63E-01 1.47E+02 1.33E+00 0. 6.71E.01 0. 2.33E.01 1-134 0. 0. 0. 0. 0. 0. 0. 0.

1-135 .60E 02 E- .01E-02 9.04E-03 1.86E-03 0. 3.53E.02 CS-134 6.58E+M 1.57E+09 0. 5.08E+08 1.68E+08 2.74E+07 0. 1.28E+09 CS.136 1.1SE+07 4.67E+07 0. 2.60E+07 3.56E+06 5.31E+06 0. 3.36E+07 CS.137 8.73EiM 1.19E+09 0. 4.06E+08 1.35E+08 2.30E+07 0. 7.82E+08 BA 1C .SSE+0 3. E+04 0. 1. E+04 2.07E+04 6.87E+07 0. 1.90E+06 CE-141 1 CTE+04 9.52E+03 0. 4.41E+03 0. 3.63E+07 0. 1.08Ei03 CE-144 1.46E+06 6.10E+05 0. 3.62E+05 0. 4.93E+OS 0. 7.83E+04 PR-143 2.13E+04 8.57Ei03 0. 4.94E+03 0. 9.34E+07 0. 1.06E+03 IO.14 E+ 9. + 6.64E+03 0. 4.13E+07 0. 8.76Et02 BASED OI 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN NO A VALUE OF 1. FOR X/O, DEPLETED X/O ANO RELATIVE DEPOSITION NO'IE - THE UNITS FOR C-14 AND H-3 ARE (HREN/YR PER UCI/CU.HETER)

A-28 12/19/BC

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY - AIR-CRASS-CN HEA't (CONTAHINATED FORAGE) -

ACE GROUP TEENAGER NUCL IDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

B(WE LIVER THTRO ID KIDNEY LUNG GI-LLI SKIN TOTAL B(X)Y H-3 0. .93E+02 1.93E+02 2.44E+02 1.93E+02 1.93E+02 0. 1.93E+02 C-14 5.23E+04 5.23E+04 5.23E+04 3.94E+04 5.23E+04 5.23E+04 0. 5.23E+04 P-32 2.76E+09 1.73E+08 0. 0. 0. 3.10E+OS 0. 1.07E+OS CR-51 0. 0. 2.50E+02 9.22E+02 5 '5E+03 1.05E+06 0. 4.18Ei03

0. .4 + 0. 1.61E+06 0. 1.66E+07 0. 1.04E+06 FE-59 1.58E+08 3.74E+08 0. 0. 1.04E+OS 1.24E+09 0. 1.42E+08 CO-57 0. 3.33E+06 0. 0. 0~ 8.45E+07 0. 5.54E+06 C0.5S 0. 1.44E+07 0. 0. 0. 1.94E+08 0. 3.27Ei07

0. ~ E+0 0. 0. 0. 6.87E+08 0. 1.31E+M Nl-63 1.12E+09 7.74E+07 0. 0. 0. 'I . 61E+07 0. 3.74E+07 ZN.65 2.11E+08 6.69E+08 0. 4 47E+08 0. 4.21E+M 0. 3.03Ei08 RB-86 0. 2.89E+OS 0. 0. 0. 5.69E+07 0. 1.35E+08 SR- .66E+08 0. 0. 0. 2.89E+07 0. 7.64E+06 SR-90 1.01E+10 0. 0. 0. 2.79E+08 1.02E+09 0. 2.49E+09 Y-91 9.34E+05 0. 0. 0. 0. 3.59E+08 0. 2.49Ei04 ZR 95 2.67E+06 1.24E+06 0. 1.18E+06 0. 4.20E+09 0. 7.61Et05 NB . SE+ E+ .4SE+0 0. .SSE+09 0. 5.37E+05 RU.103 S.OSE+07 0. 0. 2.40E+M 0. 6.2SE+09 0. 3.60E+07 RU.106 2.40E+09 0. 0. 3.20E+09 0. 1.09E+11 0. 3.02Ei08 AG. II(BI 3.97E+06 3.67E+06 0. 7.21E+06 0. 1.50E+09 0. 2.18E+06

.64E+ 6. E+05 0. 3.63E+0 0. 2.76E+04 BASED ON 'I UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/O, DEPLETED X/O AND RELATIVE DEPOSI'TION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREH/YR PER UCI/CU.HEtER)

A-29 12/19/84

ENVIRONHENTAL PATHMA'Y DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - AIR-GRASS-COM HEAT (C(NITANINATEO FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SO.HETER-HREH/TR PER UCI/SEC)

LIVER THTROID KIDNET LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0.

SN 126 1.10E+10 2.18E+08 6.38E+07 0. 3.82E+06 3.66E+09 0. 3.14Ei08 SB-124 1.17E+07 2.21E+05 2.84E+04 0. 9.11E+06 3.32E+08 0. 4.64E+06 SB-125 -

5.DIE<07 1.31E+07 1.02E+07 1.03Ei08 1 47E+09 2.25E+08 0. 7.60E+06 TF-1 .0 1.08E+ 8. E+07 8.63E+08 0. 8.47E+08 0. 4.02E+07 TE.127H 6.60E+08 2.34E+08 1.77E+08 2.69Et09 0. 3.35E+09 0. 8.28E+07 TE.129ll 9.78E+08 3.63E+08 3.13E+08 2.83Ei09 0. 3.41E+09 0. 1.53E+08 I-130 1 41E-06 4.16E-06 5.30E-04 6.47E-06 0. 3.57E-06 0. 1.64E-06

8. E+06 1. 1E+0 .48E+09 1.56E+07 0. 2.28Et06 0. 7.19E+06 I-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 3.69E-01 6.26E-01 1.14E+02 7.88E-01 0. 4.55E-01 0. 1.93E-01 I-134 0. 0. 0. 0. 0. 0~ 0. 0.

-02 C.69E 0 0. -02 5. E-03 1.10E 03 0. 2.08E-02 CS.134 5.03E+08 1.21E+09 0. 3.DOE+08 1.C7E+08 1.COE+07 0. 5.66E+08 CS-136 6.99E+06 2.76E+07 0. 1.54E+07 2.TIEi06 3.14E+06 0. 1.99Ei07 CS-137 9.31E+08 0. 2.40E+08 1.24Et08 1.24E+07 0. 3.27E+08 BA 40 +04 . DE+04 1.95E+04 9.19E+06 0. 1.53E+06 CE-141 1.12E+04 7.51E+03 0. 2.61E+03 0. 2.03E+07 0. 8.61E+02 CE 144 1.28E+06 5.23E+05 0. 2.14E+05 0. 3.DOE+08 0. 6.76E+04 PR-143 1.26E+04 5.07E+03 0. 2.92E+03 0. 5.52E+07 0. 6.26E+02 ND. 4 . 1E+04 .49E+0 .92E+0 0~ 2.44E+0 0. 5.18E+02 BASED (Nl 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 ANO H-3 ARE (HREH/TR PER UCI/CU.HETER)

A-30 12/19/84

0

~

EKVIRONHENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - AIR-GRASS-CN-%AT (C(BITANINATED FORAGE) -

AGE GRIXIP CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/TR PER UCI/SEC)

B(NE LIVER THTRO ID KIDNEY LUNG Gl -LLI S<IN TOTAL BODY

0. E+0 2.33E+02 1.54E+02 2.33E+02 2.33E+02 0. 2.33E+02 C-14 9.87E+04 9.87E+04 9.87E+04 2.49E+04 9.87E+04 9.87E+04 0. 9.87E+04 P-32 1.74E+09 1.09E+M 0. 0. 0. 1.96E+OS 0. 6.73E+07 CR-51 0. 0. 1.58E+03 5.82E+02 3.50E+03 6.63E+05 0. 2.64E+03

~ + 1.02E+06 0. 1.05E+07 0. 6.54E+05 FE-59 9.95E+07 2.37E+DS 0. 0. 6.55E+07 7.79E+OS 0. 8.93E+07 CO-57 0. 2.10E+06 0. 0. 0. 5 '3E+07 0. 3.50E+06

0. 1.69E+07 0. 0. 0. 1.DOE+08 0. 5. 10E+07 CO-60 6. +0 0. 0. 0. 3.75E+08 0. 2.03E+08 NI-63 7.04E+08 4.88E+07 0. 0. 0. 1.02E<07 0. 2.36E+07 ZN-65 1.33E+08 4.22E+08 0. 2.82E+08 0. 2.66E+08 0. 1.91E+08 RB-86 0. 1.82E+M 0. 0. 0. 3.59E+07 0. 8.50E+07 SR- E+ 0. 0. 0. 1.88E+07 0. 1.44E+07 1.05E+10 0. 0. 0. 0. 7.02E+OS 0. 2.67E+09 Y-91 1.76E+06 0. 0. 0. 0. 2.33E+08 0. 4.69E+04 ZR-95 4.62Ei06 1.51E+06 0. 7.47E+05 0. 2.22E+09 0. 1.20E+06 NB E+06 0. 4. + 0. 1.9SE+09 0. 8.41E+05 RU.103 1.54E+08 0. 0. 1.51E+08 0. 3.S1E+09 0. 5.87E+07 RU-106 4.51E+09 0. 0. 2.02E+09 0. 7.01E+10 0. 5.61E+08 AG.1101 2.50E+06 2.3IE+06 0. 4.55E+06 0. 9.44E+08 0. 1.38E+06

~ E+ . 2E+ 0. +07 0. 1.74E+04 BASED ON 1 UCI/SEC RELEASE kATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/Q, DEPLETED X/O AND RELATIVE DEPOSITION NOTE - THE NITS FOR C-14 ANO H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-3 1 12/19/84

C ENVIRONHENTAL PATHlJAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATNAY - AIR-GRASS-CON-I%AT (C(NITANINATED FORAGE) AGE GRQJP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/TR PER UCI/SEC)

LIVER THTROI 0 KIDNET LUNG GI-LLI SKIN TOTAL BMY SN-1 0. 0. 0. 0. 0. 0. 0.

SK-126 6.92E+09 ~

1.37E+08 4.02E+07 0. 2.41E+06 2.31E+09 0. 1.98E+08 SB-124 7.40E+06 1AOE+05 1.79E+04 0. 5.74E+06 2.10E+08 0. 2.93E+06 SB-125 +07 1.84E+07 1.90E+07 6A7E+07 9.26E+08 1.44E+OS 0. 1.08E+07 TE- E 1.60E+08 5.44E+08 0. 5.49E+OS 0. 7.59E+07 TE-127N 4AOE+OS 1.51E+OS 1.24E+08 1.70E+09 0. 2.54E+09 0. 5.61E+07 TE-129H 1.84Ei09 5.12E+OS 5.87E+08 1.78E+09 0~ 2.21Ei09 0. 2.84E+08 1-130 8.87E-07 2.63E-06 3.34E-04 4.08E-06 0. 2.25E.06 0. 1.03E-06

. BE+0 .62E+0 . 5E+09 9.86E+06 0. 1.38E+06 0. 1.22Et07 1-132 0. 0. 0. 0. 0. 0. 0. 0.

I-'133 6.86E 01 8.47E-01 2.04E+02 4.97E.01 0. 3.43E-01 0. 3.33E-01 1-134 0. 0. 0. 0. 0. 0. 0. 0.

1-135 E.02 2.96E-02 0. 1.12E-02 3.3 -03 6.92E-04 0. 1.32E-02 CS.134 8.83E+08 1.49E+09 0. 1.89E+08 1.65E+08 8.04E+06 0. 3.16E+08 CS-136 4.41E+06 1.74E+07 0. 9.69E+06 1.33E+06 1.98E+06 0. 1.25E+07 CS-137 1.27E+09 1.23Et09 0. 1.51E+08 1.44E+08 7.50E+06 0. 1.84E+08 BA-1 +0 E+ 4.59E+03 .29E+04 6.03E+06 0. 2.57E+06 CE-141 2.10E+04 1.05E+04 0. 1.65E+03 0. 1.32E+07 0. 1.57E+03 CE-144 2.38E+06 7A6E+05 0. 1.35E+05 0. 1.94Et08 1.27E+05 PR-143 .96E+N 3.20E+03 0. 1.84E+N 0. 3ABE+07 0. 3.95E+02

~ + .48E+ 0. l. 3E+07 0. 3.27E+02 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-32 07/20/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNY - AIR-GRASS-CSIS-NILK (CNTANINATED FORAGE) AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SO.HETER-HREH/YR PER UCI/SEC)

IHHIE LIVER TH'YRO ID KIDNEY LUNG GI-LLI SKIN TOTAL BODY

0. +02 9.73E+02 9.73E+02 9.73E+02 9.73E+02 0. 9.73E+02 C-14 3.63E+05 7.28E+04 7.28E+04 7.28E+04 7.28E+04 7.28E+04 0. 7.28E+04 P-32 1.71E+10 1.07E+09 0. 0. 0. 1.92E+09 0. 6.62Et08 CR-51 0. 0. 1.71E+04 6.32E+03 3.80Et04 7.20E+06 0. 2.86E+04 E+06 2.50E+06 0. 2.58E+07 0. 1.61E+06 FE 59 2.98E+07 7.06E+07 0. 0. 1.96Ei07 2.33E+08 0. 2.69E+07 CO-57 0. 1.28E+06 0. 0. 0. 3.25E+07 0. 2.13E+06 C0-58 0. 4.72E+06 0. 0. 9.56E+07 0. 1. 06E+07 CO-60 0. .6 E+ 0. 0. 0. 3.08E+08 0. 3.62E+07 Nl.63 6.73E+09 4.67E+08 0. 0. 0. 9.73E+07 0. 2.26E+08 ZN-65 ~

1 ~ 37E+09 4.36E+09 0. 2.92E+09 0. 2.75E+09 0. 1.98E+09 RB 86 0. 2.60E+09 0. 0. 0. 5.12E+M 0. 1.21E+09 SR-89 1. + 0. 0. 2.33E+08 0. 4.17E+07 SR-90 4.70E+10 0. 0. 0. 0. 6.37E+M 0. 1.15E+10 Y-91 8.60E+03 0. 0. 0. 0. 4.73E+06 0. 2.31E+02 ZR-95 3.18E+04 1.75E+04 0. 1.75E+04 0. 1.05E+08 0. 6.95E+03 NB 8. 6E+ 4.55E+04 0. 2.79E+08 0. 1.80E+04 RU-103 1.02E+03 0. 0. 3.91E+03 0. 1 ~ 19E+05 0. 4.41E+02 RU.106 2.04E+N 0. 0. 3.95E+04 0. 1.32E+06 0. 2.58E+03 AG 110N 5.84E+07 5 40E+07 0. 1.96Et08 0. 2.20E+10 0. 3.21E+07

0. E+06 0. 9.89E+0 0. 5 '4E+07 0. 3.98E+04 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AHD A VALUE OF 1 FOR X/4, DEPLETED X/Q AHD RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-33 12/19/84

ENVIROMHENtAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - AIR-CRASS-CONS HICK (CSITAHINATED FORAGE) AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACtORS (SO.HETER-HREH/YR PER UCI/SEC)

LIVER THTROI D KID MET LUNG CI-LLI SKIM TOTAL BODY SN 1 0. 0. 0. 0. 0. 0. 0.

SN.126 1.65E+09 3.27E+07 9.56E+06 0. 4.67E+06 1.09E+09 0. 4.94E+07 SB-124 2.58E+07 4.87E+05 6.24E+04 0. 2.DOE+07 7.31E+08 0. 1.02E+07 58-125 2.84E+07 6.06E+05 2.99E+05 3.72E+06 2.66E+09 2.29E+08 0. 5.23E+06 TE 1 E+ . 1E+ 4.91E+06 6.63E+07 0. 6.50E+07 0. 2.18E+06 TE-127H 4.63E+07 1.63E+07 1.21E+07 1.88E+08 0. 2.11E+08 0. 5.72E+06 TE-129H 8.06E+07 2.27E+07 2.09E+07 2.53E+08 0. 3.04E+08 0~ 9.61E+06 1.130 4.27E+05 1.26E+08 1.61E+08 1.96E+06 " 0. 1. 08E+06 0. 4.97E+05 I-131 .96E+ 4. E+08 . 9E+11 ~ 27E+08 0. 1.12E+08 0. 2.43E+08 I-132 1.67E-01 4.47E-01 5.88E+01 7.12E-01 0. 8.39E-02 0. 1.59E-01 1-133 4.DOE+06 6.94E+06 1.33Ei09 1.21E+07 0. 6.10E+06 0. 2.12E+06 l-134 0. 0. 9.98E-10 0. 0. 0. 0. 0.

1. + . OE+ ~ 84E+06 .88E+04 7.5 -02 4.14E+04 0. 1.36E+04 CS-134 5.66E+09 1.35E+10 0. 4.36Ei09 1.45E+09 2.36E+08 0. 1.10E+10 CS-136 2.61E+08 1.03E+09 0. 5.74E+08 7.87E+07 1.17E+08 0. 7.43E+08 CS-137 7.39E+09 1.01E+10 0. 3.44E+09 1.14E+09 1.95E+08 0. 6.62E+09 BA- 40 + + 1.15E+04 1.93E+04 5.70E+07 0. 1.78E+06 CE-141 2.91E+04 1.97E+04 0. 9.13E+03 0. 7.52E+07 0. 2.23E+03 CE-144 2.15E+06 8.97E+05 0. 5.32E+05 0. 7.26E+08 0. 1 '5E+05 PR 14 1.59E+02 6.39E+01 0. 3.68E+01 0. 6.96E+05 0. 7.89E+OO

. 6E+ +0 0. 5. BE+05 0. .34E+00 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AHD A VALUE OF 1. FOR X/4, DEPLETED X/4 NN RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AHD H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-34 12/19/84

ENVIRONMENTAL PATMMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATMMAY - AIR-GRASS-CONS-MILK IXMITAHIMATED FORAGE) -

AGE GRIXJP TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIM TOTAL BODY H-3 0. +0 9.93E+02 1.26E+03 9.93E+02 9.93E+02 0. 9.93E+02 C-14 1.25E+05 1.25E+05 1.25E+05 9.39E+04 1.25E+05 1.25E+05 0. 1.25E+05 P-32 2.21E+10 1.38E+09 0. 0. 0. 2.48E+09 0. 8.54E+08 CR-51 0. 0. 2.21E+04 8.15E+03 4.90E+04 9.29E+06 0. 3.69Ei04

0. 0. 3.32E+06 0. .33E+07 0. 2.07E+06 FE-59 3.84E+07 9.12E+07 0. 0. 2.53E+07 3.01E+08 0. 3.47E+07 C0.57 0. 1.65E+06 0. 0. 0. 4.19E+07 0. 2.75E+06 CO-58 0. S.10E+06 0. 0. 0. 1.10E+08 0. 1.85E+07 CO-60 0. + 0. 0. 0. 3. 7E+OS 0. 6.23E+07 Nl-63 8.68E+09 6.02E+08 0. 0. 0. 1.26E+08 0. 2.9IE+08 ZM.65 1.77E+09 5.63E+09 0. 3.77E+09 0. 3.55E+09 0. 2.55E+09 RB-86 0. 3.35E+09 0. 0. 0. 6.61E+08 0. 1.56E+09 SR-89 2.80E+ 0. 0. 0. 3.03E+08 0. 8.03E+07 SR-90 8.29E+10 0. 0. 0. 3.38E+06 1.76E+09 0. 2.05E+10 Y-91 1.54E+04 0. 0. 0. 0. 5.93E+06 0. 4.12E+02 ZR-95 4.78E+04 2.84E+04 0. 2.25E+04 0. 1. 15E+08 0. 1.60E+04 NS- ~ f+ .87E+04 0. .05E+OS 0. 4.21Ei04 RU-103 1.69E+03 0. 0. 5.04E+03 0. 1.32E+05 0. 7.56E+02 RU-106 3.83E+04 0. 0. 5.09E+04 0. 1.73E+06 0. 4.81E+03 AG-1101 7.53E+07 6.97E+07 0. 1.37E+08 0. 2.84E+10 0. 4. 14E+07 E . BE+06 0. 6.77E+07 0. 5.14E+04 BASED Ol 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AMD A VANE OF 1. FOR X/O, DEPLETED X/O AMD RELA'TIVE DEPOSITION MOTE - THE UNITS FOR C-14 AIM) H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-35 12/19/84

ENVIROHHEN'PAL PATHHAT-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHUAT - AIR GRASS-CQIS.NILK (COITANINATED FORAGE) AGE GRQJP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SO.HETER HREH/TR PER UCI/SEC)

BONE LIVER THTROID KIDNET LUHG GI -LLI SKIN TOTAL SOOT SN-1 0. 0. 0. 0. 0. 0.

SN-126 2.12E+09 4.21E+07 1.24E+07 0. 6.03E+06 1.41E+09 0. 6.37E+07 58-124 3.33E+Ol 6.29E+05 8.05E+04 0. 2.59E+07 9.43E+M 0. 1.32E+07 SB-125 3ASE+Ol 9.58E+05 5.05E+05 4.80E+06 3.C3E+09 2.95E+08 0. 6.82E+06 TE- 25H .DOE+ 8.4 +06 8.55E+07 0. 8.39E+07 0. 3.98E+06 TE-127M 6.02E+07 2.'11E+Ol 1.59E+Ol 2.C3E+M 0. 3.02E+08 0. 7.45E+06 TE-129N 1.13E+08 4.18E+07 3.61E+07 3.27E+08 0. 3.93E+08 0. 1.78E+07 1-130 5.51E+05 1.63E+06 2.07E+08 2.53E+06 0. 1.40E<06 0. 6.41E+05 I- 3 .12E+ E+08 .09E+ 1 9.38E+08 0. 1.37E+08 0. 4.31E+08 1-132 2.16E.01 5.76E.01 7.59E+01 9.19E-01 0. 1.08E-01 0. 2.05E-01 1-133 7.33E+06 1.24E+Ol 2.26E+09 1.56E+Ol 0. 9.02E+06 0. 3.83E+06 1-134 0. 0. 1.29E-09 0. 0. 0. 0. 0.

1-1 5 .8IE+ 6. 4E+06 ~ 58E+04 9.79E-02 5.34E+04 0. 1.75E+04 CS-134 9A4E+09 2.28E+10 0. 5.63E+09 2.76E+09 2.63E+M 0. 1.06E+10 CS-136 3.37E+08 1.33E+09 0. 7.4IEiM 1.02E+08 1.51E+08 0. 9.58E+08 CS-137 1.28E+10 1.72E+10 0. 4.43E+09 2.28E+09 2.29E+08 0. 6.04E+09 BA-14 E ~ E+ 0. .48E+04 .98E+04 9.16E+06 0. 3.11E+06 CE-N1 5.05E+04 3.39E+04 0. 1.18E+04 0. 9.18E+07 0. 3.89E+03 CE-144 4.10E+06 1.68E+06 0. 6.87E+05 0. 9.65Et08 0. 2.17E+05 PR N3 2.05E+02 8.25E+01 0. 4.75E+01 0. 8.98E+05 0. 1.02E+01

. 9E+0 A4E . CE+1 a. 6.82E+05 0. 9.48E+00 BASED (Nl 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AHD RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREN/TR PER UCI/CU.HETER)

A-36 12/19/84

ENVIRONMENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY - AIR-GRASS-CSIS-NILK C(STAN!HATED FORGE) AGE GROUP - CHILD IRICLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIM TOTAL BODY 8- 0. +0 .57E+03 1.04E+03 1.57E+03 1.57E+03 0. 1.57E+03 C-T4 3.08E+05 3.08E+05 3.08E+05 7.75E+04 3.08Ei05 3.08E+05 0. 3.08E+05 P-32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 0. 7.05E+08 CR-51 0. 0. 1.82E+04 6.72E+03 4.04E+04 7.66E+06 0. 3.05E+04

0. 0. 2.67E+06 0. 2.74E+07 0. 1.71E+06 FE 59 3.17E+07 7.52E+07 0. 0. 2.09E+07 2 48E+08 0. 2.86E+07 C0.57 0. 1. +06 0. 0. 0. 3.46E+07 0. 2.27E+06 CO-58 0. 1.25E+07 0. 0. 0. 7.41E+07 0. 3.76E+07 CO.60 0. E 0. 0. 0. 2.33E+08 0. 1.27E+08 NI.63 7.16E+09 4.97E+08 0. 0. 0. 1.04E+08 0. 2.40E+08 ZN-65 1.46E+09 . 4.65E+09 0. 3.11E+09 0. 2.93E+09 0. 2 '0E+09 RB-86 0. 2.77E+tN 0. 0. 0. 5.45E+08 0. 1.29E+09 SR-89 6. E+ 0. 2.58E+08 0. 1.98E+08 SR-90 1.13E+11 0. 0. 0. 0. 1.52E+09 0. 2.87E+10 Y-91 3.80E+04 0. 0. 0. O. 5.05E+06 0. 1.01E+03 ZR-95 1.06E+05 4.47E+04 0. 1.86E+04 0. 7.68E+07 0. 3.29Ei04 NS- ~ E+ 4.84E+04 0. 2.03E+08 0. 8.63E+04 RU-103 3.99E+03 0. 0. 4.16E+03 0. 1.05E+05 0. 1.61E+03 RU 106 9.39E+04 0. 0. 4.20E+04 0. 1.46E+06 0. 1.17E+04 AG.TIN 6.21E+07 5.75E+07 0. 1.13E+08 0. 2.35E+10 0. 3.42E+07

~ + ~ E+ 0. 5. 8E+0 0. 4.24E+04 SASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/O, DEPLETED X/0 AMD RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (NREM/YR PER UCI/CU.HETER)

A-37 12/19/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARCES PATHNAY - AIR-GRASS CONS.HILK C(NITAHINATED FORAGE) AGE CROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SO.HETER HREH/YR PER UCI/SEC)

LIVER THTRO ID KIDNEY LUNG Gl-LLI SKIN TOTAL SOOT sx-1 0. 0. 0. 0. 0. 0.

SN.126 1.75E+09 3 48E+07 1.01E+07 0. 4.97E+06 1.16E+09 0. 5.25E+07 S8-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 7.78E+08 0. 1.09E+07 SB-125 -

3.13E+07 1 41E+05 1.18E+06 3.96E+06 2.83E+09 2.43E+M 0. 5.99E+06 TE 25H + + +07 .05E+07 0. 7.12E+07 0. 9.84E+

TE-127H 5.18E+07 1.7SE+07 1 46E+07 2.DOE+08 0. 2.99E+M 0. 6.60E+06 TE-129H 2.77E+OS 7.73E+07 8.85E+07 2.70Et08 0. 3.33E+OS 0. 4.28E+07 l-130 4.54E+05 1.35E+06 1.71E+M 2.09E+06 0. 1.15E+06 0. 5.29E+05 I- E+ + E+11 . 4E+08 0. 1.09E+08 0. 9.56E+08 I-132 1.18E.01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E-02 .0. 1.69E-01 I-133 1.78E+07 2.20E+07 5.30E+09 1.29E+07 0. 8.90E+06 0. 8.63E+06 I-134 0. 0. 1.06E-09 0. 0. 0. 0. 0.

.49E+ E+ E+06 6. 6E+04 8.07E-02 4.41E+04 0. 1.44E+04 CS-134 2.17E+10 3.65E+I 0 0. 4.65E+09 4.06E+09 1.97E+08 0. 7.76E+09 CS.136 2.78E+08 1.10E+09 0. 6.11Et08 S.37E+07 1.25E+08 0. 7.90E+08 CS.137 3.08E+10 2.98E+10 0. 3.66E+09 3 49E+09 1.81E+08 0. 4.44E+09

~ + .0 E+ 0. 1. 2E+04 6.09E+04 7.75E+06 0. 6.84E+06 CE-141 1.24E+05 6.22E+04 0. 9.72E+03 0. 7.80E+07 0. 9.26E+03 CE-144 1 DOE+07 3.14E+06 0. 5.67E+05 0. S.15E+08 0. 5.34E+05 PR-143 1.69E+02 6.80E+01 0. 3.92Ei01 0. 7.41E+05 0. 8.40E+00 E+ ~ + . 1E+01 0. 5.63E+ 0. 7. 81E+00 QASED ON I UCI/SEC RELEASE RATE OF EACH ISOT$ % IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION NOTE - THE NITS FOR C-14 ANO H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-38 07/20/84

I h

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATNAYA- AIR-GRASS-CSIS-NILK (C(NITANINATED FORAGE) AGE GROUP - INFANt NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY

0. . 7E+03 1.04E+03 2.37E+03 2.37E+03 0. 2.37E+03 C-14 6.55E+05 6.55E+05 6.55E+05 7.55E+04 6.55E+05 6.55E+05 0. 6.55E+05 P.32 1.82E+10 1.14E+09 0. 0. 0. 2.05E+09 0. 7.05E+08 CR-51 0. O. 1.82E+04 6.72E+03 4.04E+04 7.66E+06 0. 3.05E+04

0. 2.67E+06 0. 2.74E+07 0. 1.7IE+06 FE-59 3.17E+07 7.52E+07 0. 0. 2.09E+07 2.48E+08 0. 2.86E+07 CO-57 0. 1.36E+06 0. 0. 0. 3.46E+07 0. 2.27Ei06

0. 2.55E+07 0. 0. 0. 6.60Et07 0. 6.24Et07 E 0. 0. 0. 2 ~ 16E+08 0. 2.09E+08 NI-63 7.16E+09 4.97E+08 0. 0. 0. 1.04E+08 0. 2.40E+08 ZN-65 1 46E+09 4.65E+09 0. 3.11E+09 0. 2.93Ei09 0. 2.TOE+09 RB-86 0. 2.77E+09 0. 0. 0. 5.45E+08 0. 1.29Ei09

.4 + 0; 0. 2.75E+08 0. 4.22E+08 SR-90 1.65E+11 0. 0. 0. 0. 1.61E+09 0. 4.21E+10 Y-91 8.12E+04 0. 0. 0. 0. 5.37E+06 0. 2.16E+03 ZR-95 2.12E+05 9 41E+04 0. 1.86E+04 0. 7.47E+07 0. 5.56E+04 KB- .4 + 4.84E+04 0. 1.98E+08 0. 1.45E+05 RU-103 8.30E+N 0. 0. 4.16E+03 0. 1.04E+05 0. 2.86Ei03 RU-106 2.01E+05 0. 0. 4.20E+04 0. 1.56E+06 0. 2.46Ei04 AG-110N 6.21E+07 5.75E+07 0. 1.13E+08 0. 2.35E+10 0. 3.42E+07

+ 0. E+06 5 '8E+07 0. 4.24E+04 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AIO A VALUE OF 1. FOR X/4, DEPLETED X/0 AND RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREN/YR PER UCI/N.HETER)

A-39 I 2/19/84

8 ENVIRONMENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - AIR-GRASS CSIS-MILK (COITANINATED fORAGE) AGE GROUP - INFANT

'UCLIDE ORGAN DOSE fACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

BOtE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BCOY SN-1 0. 0. 0. 0. 0. 0. 0.

SN-126 1.75E+09 3.48E+07 1.01E+07 0. 4.97E+06 1.16E+09 0. 5.25E+07

$ 8-124 2.75E+07 5.19E+05 6.64E+04 0. 2.13E+07 7.78E+08 0. 1.09E<07 SB-125 3.59E+07 3.17E+06 2.93E+06 3.96E+06 2.83E+09 2.43E+08 0. 6.62E+06 TE- 25M ~ + . BE+07 .05E+07 0. 7.57E+07 0. 2.10Et07 TE-127N 5.54E+07 1.93E+07 1.79E+07 2.00E+08 0. 3.24E+08 0. 7.38E+06 TE-129H 5.87E+08 2.02E+08 2.21E+08 2.70E+08 0. 3.54E+08 0. 8.95Ei07 1-130 4.54E+05 1.35E+06 1.71E+08 2.09E+06 0. 1.15E+06 0. 5.29Ei05

+09 ~ + .94E+11 . 4E+08 0. 1.16E+08 0. 1.81E+09 1.132 1.78E-01 4.76E-01 6.26E+01 7.58E-01 0. 8.93E.02 0. 1.69E.01 1-133 3.75E+07 5 48E+07 '1.30E+10 1 ~ 29E+07 0. 9.74E+06 0. 1.66Ei07 1-134 0. 0. 1.06E-09 0. 0. 0. 0. 0.

.49E+04 .94E+04 .15E+06 6.26E+04 8.07E-02 4.41E+04 0. 1.44E+04 CS- 134 4.48E+10 7.97E+10 0. 4.65E+09 9.12E+09 1.90E+08 0. 6.75Ei09 CS-136 2.78E+08 1 ~ 10E+09 0. 6.11E+08 8.37E+07 1.25Ei08 0. 7.90Eim CS-137 6 44E+10 7.21E+10 0. 3.66E+09 8.69E+09 1.86E+08 0. 4.14Ei09 BA- 40 E+ + 1.22E+04 1.51E+05 8.13E+06 0. 1.27Et07 CE-141 2.65E+05 1.62E+05 0. 9.72E+03 0. 7.87E+07 0. 1.90E+04 CE-144 2.10E+07 8.29E+06 0. 5.67E+05 0. 8.66E+08 0. 1.13Et06 PR-143 1.69E+02 6.80E+01 0. 3.92E+01 0. 7.41E+05 0. 8.40E+00 E+ +0 .21E .63E+05 0. 7.81E+00 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN NO A VALUE OF 1. FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION MOTE - THE UNITS FOR C-14 AND H-3 ARE (HREII/YR PER UCI/CU.HETER)

A-40 12/19/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - AIR-GRASS-GOATS-NILK (IXNITANINATED FORAGE) AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIH TOTAL BODY

0. 1. + .99E+03 1.99E+03 1.99E+03 1.99E+03 0. 1.99E+03 C-14 3.63E+05 7.28E+04 7.28E+04 7.28E+04 7.28E+04 7.28E+04 0. 7.28E+04 P-32 2.05E+10 1.29E+09 0. 0. 0. 2.31E+09 0. 7.94E+08 CR-51 0. 0. 2.05E+08 7.58E+02 4.56E+03 8.64E+05 0. 3.43E+03

0. E+ 0. 3.DOE+05 0. 3.09E+06 0. 1.93Ei05 FE-59 3.87E+05 9.18E+05 0. 0. 2.55E+05 3.03E+06 0. 3.50E+05 CO-57 0. 1.54E+05 0. 0. 0. 3.90E+06 0. 2.55E+05 CO-58 0. 5.67E+05 0. 0. 0. 1.15E+07 0. 1.27E+06 CO 60 0. 1. + 0. 0. 0. 3.70E+07 0. 4.34E+06 Nl-63 8.07E+08 5.60E+07 0. 0. 0. 1.17E+07 0. 2.71E+07 ZN 65 -1.65E+08 5.24E+08 0. 3.50E+08 0. 3.30E+08 0. 2.37E<08 RB-86 0. 3.12E+08 0. 0. 0. 6.15Ei07 0. 1.45E+08 SR-89 .06E+09 0. 0. 0. 0. 4.89E+08 0. 8.76E+07 SR-90 9.87E+10 0. 0. 0. 0. 1.32E+09 0. 2.41E+10 Y.91 1.03E+03 0. 0. 0. 0. 5.68E+05 0. 2.77E+01 ZR 95 3.82E+03 2 10E+03 0. 2.10E+03 0. 1.26E+07 0. 8.34E+02 NB 0. 5.46E+03 0. 3.34E+07 0. 2.173i03 RU-103 1.23E+02 0. 0. 4.69E+02 0. 1 43E+04 0. 5.30E+01 RU 106 2 45E+N 0. 0. 4.73E+03 0. 1.58E+05 0. 3.10E+02 AG.TTINI 7.DOE+06 6.48E+06 0. 1.27E+07 0. 2.64E+09 0. 3.85E+06

. OE+ . 9E+ 0. 6. +06 4. +03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOT$ % IN AHD A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITION NOTE - THE NITS FOR C-14 A I H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-41 12/19/84

ENVIRONHENTAL PATHNAY DOSE CONVERSION FAClORS FOR GASEOUS DISCHARGES PATHMAY - AIR-GRASS-MATS-HILK (C(HITAHINATED FORAGE) AGE GROUP ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BODY SN-12 0. 0. 0. 0. 0. 0. 0.

SN-126 1.97E+08 3.92E+06 1.15E+06 0. 5.61E+05 1.31E+08 0. 5.92E+06 SB-124 3.10E+06 5.85E+04 7.49E+03 0. 2.40E+06 8.77E+07 0. 1.22E+06 SB.125 3.16E+06 7.28E+04 3.58E+04 4.47E+05 3.19E+08 2.74E+07 0. 6.29E+05 TE1 H 1.96E+06 . OE+ .89E+05 ~ 95E+06 0. 7.81E+06 0. 2.62E+05 TE-127H 5.57E+06 1.94E+06 1.47E+06 2.26E+07 0. 2.52E+07 0. 6.86E+05 TE-129H 7 27E+06 2.72E+06 2.51E+06 3.04E+07 0. 3.65E+07 0. 1.15E+06 I-130 5.12E+05 1.52E+06 1.93E+08 2.36E+06 0. 1.30E+06 0. 5.96Ei05

. 6E+08 5.1 +08 1.67E+11 8. E+08 0. 1.34E+08 0. 2.92E+M 1-132 2.00E-01 5.36E-01 7.06E+01 8.55E-01 0. 1.01E-01 0. 1.91E-01 I-133 4.80E+06 8.32E+06 1.60E+09 1.45E+07 0. 7.32E+06 0. 2.54E+06 I-134 0. 0. 1.20E-09 0. 0. 0. 0. 0.

.68&04 4.44E+04 .BOE+06 7.05Ei04 2.28E-01 4.97E+04 0. 1.63E+04 CS-134 1.78E+10 4.04E+10 0. 1.31E+10 4.34Ei09 7.06E+08 0. 3.30E+10 CS-136 7.84E+08 3.09E+09 0. 1.72E+09 2.36E+08 3.52E+08 0. 2.23E+09 CS-137 2.22E+10 3.03E+10 0. 1.03E+10 3.42E+09 5.83Ei08 0. 1.99E+10 4.05E+ 0. 1.38E+0 2.32E+03 6.84E+06 0. 2.13E+05 CE.141 3.49E+03 2.36E+03 0. 1.10E+03 0. 9.02E+06 0. 2.68E+02 CE-144 2.58E+05 1.08E+05 0. 6.39E+04 0. 8.71E+07 0. 1.38Et04 PR-143 1.91E+Ol 7.67K+00 0. 4.42E+00 0. 8.35E+04 0. 9.47E-01

+01 E+ B. 3E+00 0. 6.35E+04 0. 8.81E-DI BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/0, DEPLElED X/0 AMO RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-42 12/19/84

ENVIRONHENTAL PATHNAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATNAZ - AIR-GRASS-GOATS-HILK (C(NITAHINATED FORAGE) - TEENAGER AGE CROUP NUCL IDE ORGAN DOSE FACTORS (SO.HETER HREII/YR PER UCI/SEC)

LIVER THYROID K ID NE'Y LUNG GI-LLI SKIN TOIAL BODY H-3 0. .03E+0 2.03E+03 2.56E+03 2.03E+03 2.03E+03 0. 2.03E+03 C-14 1.25E+05 1.25E+05 1.25E+05 9.39E+04 1.25E+05 1.25Ei05 0. 1.25E+05 P 32 2.65E+10 .66E+09 0. 0. 0. 2.98E+09 0. 1.03E+09 CR-51 0. 0. 2.65E+03 9.78E+02 5.88E+03 1 ~ 11E+06 0. 4.43Et03

0. 3.88E+05 0. 3.99E+06 0. 2.49Et05 fE-59 4.99E+05 1.19E+06 0. 0. 3.29E+05 3.91E+06 0. 4.51E+05 C0-57 0. 1.98Ei05 0. 0. 0. 5.03E+06 0. 3.30E+05 CO-58 0. 9.72E+05 0. 0. 0. 1.31E+07 0. 2.22E+06 C0-60 0. +06 0. 0. 0. 3.93E+07 0. 7.48E+06 Nl-63 1.04E+09 7.23E+07 0. 0. 0. 1.51E+07 0. 3.C9E+07 ZN-65 2.13E+08 6.76E+08 0. 4.52E+08 0. 4.26E+08 0. 3.06E+08 RB-86 0. 4.02E+08 0. 0. 0. 7.93E+07 0. 1.88E+08 SR- .87E+09 0. 0. 0. 6.37E+08 0. 1.69E+08 SR-90 1.74E+11 0. 0. 0. 4.05E+05 3.68E+09 0. C.30E+10 Y-91 1.85Ei03 0. 0. 0. 0. 7.11E+05 0. 4.94E+01 ZR-95 5.74E<03 3 CTE+03 0. 2.70E+03 0. 1.38E+07 0. 1.93E+03 NB .49E+ 8.96E+0 0. .05E+03 0. 3.66E+07 0. 5.05Ei03 RU-103 2.03E+02 0. 0. 6.05E+02 0. 1.58E+04 0. 9.08E+Ol RU-106 4.59E+03 0. 0. 6.11E+03 0. 2 ~ OSE+05 0. 5.78Ei02 AG-110H 9.04E+06 8.36E+06 0. 1.64E+07 0. 3.41E+09 0. 4.97E+06 CD- H 0. + 0. . 3E+05 0. 8.12E+06 0. 6.17E+03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AIO A VALUE OF 1. fOR X/O, DEPLETED X/0 AND RELAI'IVE DEPOSITIOH NOTE - THE UNITS FOR C 14 AIR) H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-43 12/19/S4

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATNAY - AIR-GRASS-GOATS MILK CQITANINATED FORAGE) AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SO.HETER-HREH/TR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TO'IAL BODY SN-I 0. 0. 0. 0. 0. 0. 0.

SN-126 2.54E+M 5.05E+55 1 CSE+06 0. 7.23E+05 1.69E+08 -0. 7.6CE+06 58-124 4.DOE+06 7.54E+04 9.66E+03 0. 3.10E+06 1.13E+08 0. 1.58E+06 S$ -125 4.14E+06 1.15E+05 6.06E+04 5.77E+05 C.12E+OS 3.54E+07 0. 8.19E+05 TE 125H .6 E+ 1. E+06 1.03E+07 0. 1.01E+07 0. 4.78E+05 TE-127N 7.23E+06 2.52E+06 1.91E+06 2.92E+07 0. 3.63E+07 0. 8.9CE+05 TE-129N 1.35E+07 5.02E+06 4.34E+06 3.92E+07 0. 4.72E+07 0. 2.13Et06 I.130 6.61E+05 1.96E+06 2.49E+08 3.04E+06 0. 1.68E+06 0. 7.69Ei05 I-l 1 6.1 E+08 .68E+OS . DE+11 1.13E+09 0. 1.64E+08 0. 5.17E+M I-132 2.59E-01 6.92E-01 9.11E+01 1.10E+00 0. 1.30E-01 0. 2.46E-01 I-133 8.79E+06 1.49E+07 2.71E+09 1.ME+07 0. 1.OS'7 0. 4.59E+06 l-134 0. 0. 1.55E-09 0. 0. 0. 0. 0.

I- 35 .1 + E+ . 9E+06 9.10E+04 2.94E.01 6.4IEi04 0. 2.10Ei04 CS-134 2.88E+10 6.83E+10 0. 1.69E+10 8.27E+09 7.88E+08 0. 3.19E+10 CS-136 1.01E+09 3.99E+09 0. 2.22E+09 3.05E+08 4.54E+08 0. 2.87E+09 CS-137 3.8CE+10 5.16E+10 0. 1.33E+10 6.8SE+09 6.88E+08 0. 1.81E+10 BA- 40 E . CE+ 1.78E+03 4.78E+03 1 ~ 10E+06 0. 3.73Ei05 CE-141 6.06E+03 4.07E+03 0. 1.41E+03 0. 1. TOE>07 0. 4.66Ei 02 CE-144 4.92E+05 2.02E+05 0. 8.24E+04 0. 1.16E+OS 0. 2.61E+04 PR-143 2.46E+01 9.90E+00- 0. 5.70E+00 0. 1.08E+05 0. 1.22E+00

~ + +01 0. E+01 0. 8.19E+04 0. 1.14E+00 BASED (Nl 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITION NOTE - THE UNITS FOR C-1C NN H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-44 12/19/84

ENVIRONHENTAL PATHHAY-DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHHAY - AIR-GRASS-GOATS-NILK (C(HITANINATED FORAGE) AGE GRIXIP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TO'IAL B(SY

0. + ~ 20E+03 2.11E+03 3.20E+03 3.20E+03 0. 3.20E+03 C-14 3.ME+05 3.ME+05 3.08E+05 7.75E+04 3.08E+05 3.08E+05 0. 3.ME+05 P-32 2.19E+10 1. 7E+09 0. 0. 0. 2.46E+09 0. 8.46E+08 CR-51 0. 0. 2.19E+03 8.07E+02 4.85E+03 9.19E+05 0. 3.66E+03

0. .20E+05 0. 3.29E+06 0. 2.05E+05 FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 0. 3.72E+05 CO-57 0. 1.64E+05 0. 0. 0. 4.15E+06 0. 2.72E+05 CO-58 0. 1.50E+05 0. 0. 0. 8.90E+06 0. 4.51Et06 CO-60 +06 0. 0. 2.80E+07 0. 1.52E+07 NI-63 8.60E+08 5.96E+07 0. 0. 0. 1.24E+07 0. 2.88E+07 ZN-65 1.76E+08 5.57E+08 0. 3.73E+08 0. 3.51E+08 0. 2.52Ei08 RB-86 0. 3.32E+08 0. 0. 0. 6.54E+07 0. 1.55E+08 SR-89 1.45E+10 0. 0. 0. 0. 5.43E+08 0. 4. 16E+08 SR-90 2.37E+11 0. 0. 0. 0. 3.16E+09 0. 6.02E+10 Y-91 4.56E+03 0. 0. 0. 0~ 6.06E+05 0. 1.22Et02 ZR-95 1.27E+04 5.37E+03 0. 2.23E+03 0. 9.22E+06 0. 3.96Ei03 NB- . DE+04 E+04 .81E+03 0. 2.44Ei07 0. 1.04E+04 RU-103 4.79E+02 0. 0. 4.99E+02 0. 1.26E+04 0. 1.94E+02 RU-106 1.13E+04 0. 0. 5.04E+03 0. 1.75E+05 0. 1.40E+03 AG-TTOI 7.45E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 0. 4.10E+06

+ . 6E+ 0. 6. E+06 0. 5.09E+03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/O, DEPLETED X/O AND RELATIVE DEPOSITION NOTE - THE UNI'IS FOR C-14 Ale H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-45 12/19/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - AIR-GRASS-GOATS-NILK COITANINATED FORAGE) AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREN/TR PER UCI/SEC)

BONE LIVER THYROID KIDNET LUNG Gl-LLI SKIN TOTAL BCDY SN-1 0. 0. 0. 0. 0. 0.

SN-126 2.10E+08 4.17E+06 1.22E+06 0. 5.97Ei05 1.40E+08 0. 6.30E+06 58-124 3.30E+06 7.97E+03 0. 2.56E+06 9.33E+07 0. 1.30E+06 SB-125 3.75E+06 1. +05 1.43E+05 4.76E+05 3.40E+08 2.92E+07 0. 7.19E+05 TE- 8. E . 9E+06 8.46E+06 0. 8.54E+06 0. 1.18E+06 TE-127M 6.21E+06 2.14E+06 1.75E+06 2 40E+07 0. 3.58E+07 0. 7.92E+05 TE-129N 3.32E+07 9.27E+06 1.06E+07 3.23E+07 0. 4.DOE+07 0. 5.15E+06 1-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 0. 6.35E+05 1-1 1 1.48E+09 E+09 .94E+11 9. BE+08 0. 1.30E+08 0. 1.15E+09 I-'132 1-133 1-134 2.18E-Ol 0.

14E+07 5.71E-01 2.64E+07 0.

7.51E+Ol 6.36E+09 1 ~ 27E-09 9.10E-01 1.55E+07 0.

0.

0.

0.

1.07E-01 1.07E+07 0.

0.

2.03E-01 1.04E+07

0. 0. 0.

+ 4. +04 6.18E+ 7. 1E+04 .42E-01 5.29Ei04 0. 1.73E+04 CS.134 6.50E+10 1 ~1 DE+11 0. 1.39E+10 1.22E+10 5.92E+08 0. 2.33E+10 CS-136 8.34E+08 3.29E+09 0. 1.83E+09 2.51E+08 3.74E+08 0. 2.37E+09 CS-137 9.28E+10 8.93E+10 0. 1.10E+10 1.05E+10 5.44E+08 0. 1.33E+10 BA-140 1 ~ E+04 0. .48E+03 ~ 1E+03 9. DE+05 0. 8.21E+05 CE-141 1.49E+04 7 46E+N 0. 1.17E+03 0. 9.36E+06 0. 1.11E+03 CE-144 1.20E+06 3.76E+05 0. 6.80E+04 0. 9.78Ei07 0. 6.41E+04 PR- 143 2.03E+Ol 8.16E+00 0. 4.70E+00 0. 8.89E+04 0. 1. DIE+00 ND- 4 +1 +0 0. 6. E+04 0. 9.38E.01 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/Q, DEPLETED X/Q AND RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREN/YR PER UCI/CU.HETER)

A-46 12/19/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATNAY - AIR-GRASS-GOATS NILR (C(NITAHINATED FORAGE) AGE GRIP - INFANT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BODY

0. E+ 4.84E+03 2.11E+03 4.84E+03 4.84E+03 0. 4.84E+03 C-14 6.55E+05 6.55E+05 6.55E+05 7.75E+04 6.55E+05 6.55E+05 0. 6.55E+05 P.32 2.19E+10 1.37E+09 0. 0. 0. 2.46E+09 0. 8.46E+08 CR-51 0. 2.19E+03 8.07E+02 4.85E+03 9.19E+05 0. 3.66E+03

0. + 3. DE+05 0. 3.29Ei06 0. 2.05E+05 FE-59 4.12E+05 9.78E+05 0. 0. 2.72E+05 3.23E+06 0. 3.72E+05 CO-57 0. 1.64E+05 0. 0. 0. 4.15E+06 0. 2.72Et05 CO-58 0. 3.06E+06 0. 0. 0. 7.92E+06 0. 7.49Ei06 C0.60 0. E+0 0. 0. 0. 2.59E+07 0. 2.51E+07 NI-63 8.60E+08 5.96E+07 0. 0. 0. 1.24E+07 0. 2.88E+07 ZN-65 1.76E+08 5.57E+08 0. 3.73E+M 0. 3.51E+08 0. 2.52E+08 RB-86 0. 3.32E+M 0. 0. 0. 6.54E+07 0. 1.55E+08 SR-89 ~ 09E+ 0 0. 0. 0. 0. 5. +08 0. 8.87E+M 3.46E+11 0. 0. 0. 0. 3.35Ei09 0. 8.83E+10 Y-91 9.74E+03 0. 0. 0. 0. 6.45E+05 0. 2.60E+02 ZR-95 2.54E+04 1.13E+04 0. 2.23E+03 0. 8.95E+06 0. 6.67E+03 NB- ~ 9E+ + .81E+03 0. 2.37E+07 0. 1.75E+04 RU-103 9.96E+02 0. 0. 4.99E+02 0. 1.24E+04 0. 3.43E+02 RU-106 2 41E+04 0. 0. 5.04E+03 0. 1.87E+05 0. 2.96E+03 AG-110K 7.45E+06 6.90E+06 0. 1.36E+07 0. 2.81E+09 0. 4.10E+06 CD N + . 6E+ 0. 6. E+06 0. 5.09Ei03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTO% IN AND A VALUE OF 1. FOR X/4, DEPLETED X/0 AND RELATIVE DEPOSITION NOTE - THE UNITS FOR C-14 AND H-3 ARE (HREN/YR PER UCI/CU.HETER)

A-47 12/19/84

ENVIRONMENTAL PATHNAT-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAT - AIR-GRASS-GOATS-NILK (C(HITANINATED FORAGE) AGE GROUP - INFANT NUCLIDE ORGAN DOSE FACTORS (SO.HETER-HREN/TR PER UCI/SEC)

LIVER THTROID KIDNET LUNG GI-LLI SKIN TOTAL BOOT SN-1 0. 0. 0. 0. 0. 0. 0.

SN-126 2.10E+08 4.17E+06 1.22E+06 0. 5.97E+05 1.40E+DS 0. 6.30E+06 58-124 3.30E+06 6.22E+04 7.97E+03 0. 2.56E+06 9.33E+07 0. 1.30E+06 58-125 4.31E+06 .92E+05 3.52E+05 4.76Et05 3 40E+08 2.92E+07 0. 7.94E+05 TE-125M 1.89E+0 + 6.21E+06 8.46E+06 0. 9.09E+06 0. 2.52Et06 TE-127N 6.64E+06 2.31E+06 2.15E+06 2 40E+07 0. 3.88E+07 0. 8.85Et05 TE-129II 7.05E+07 2.42E+07 2.66E+07 3.23E+07 0. 4.25E+07 0. 1.07E+07 1-130 5.45E+05 1.61E+06 2.05E+08 2.51E+06 0. 1.38E+06 0. 6.35E+05 1-131 3.11E+09 +09 1.19E+12 9.28E+08 0. 1.39E+08 0. 2.17E<09 1-132 2.13E-01 5.71E-01 7.51E+01 9.10E-Ol 0. 1.07E-01 0. 2.03E-01 1-133 4.50E+07 6.57E+07 1.55E+10 1.55E+07 0. 1.17E+07 0. 1.99E+07 1-134 0. 0. 1.27E-09 0. 0. 0. 0. 0.

1-135 1. +04 4. E+04 6.18E+06 . 1E+04 2.42E-01 5.29E+04 0. 1.73E+04 CS-134 1.33E+11 2.39E+11 0. 1.39E+10 2.74E+10 5.69E+08 0. 2.02E+10 CS-136 8.34E+08 3.29E+09 0. 1.83E+09 2.51E+08 3.74E+08 0. 2.37E+09 CS-137 1.93E+11 2.16E+11 0. 1.10E+10 2.61E+10 5.59E+08 0. 1.24E+10 SA- 40 .95E+0 .96E+04 0. 1.47E+03 1.81E+04 9.76E+05 0. 1.52E+06 CE-141 3.17E+04 1.95E+04 0. 1.17E+03 0. 9.44E+06 0. 2.28E+03 CE.144 2.52E+06 9.95E+05 0. 6.80E+04 0. 1.04E+08 0. 1.36E+05 PR-143 2.03E+01 8.16E+00 0. 4.70E+00 0. 8.89Ei04 0. 1.01E+00 ND- 4 + +0 8.66E+00 0. 6. E+04 0. 9.38E-01 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION MOTE - THE UNITS FOR C-14 AND H-3 ARE (NREM/TR PER UCI/CU.HETER)

A-48 12/19/84

K ENVIRONHENI'AL PATHNAY-DOSE CONVERSION FAClORS FOR GASEOUS DISCHARGES PATHMAY - FRESH AND STORED fRUITS AND VEGETABLES AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACtORS (SO.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THTRO ID K IONET LUNG GI-LLI SKIN '10TAL BODY H-3 0. + .86E+03 2.86E+03 2.86Et03 2.86E+03 0. 2.86E+03 C.14 S.97EK5 1.ME+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 0. 1.80E+05 P-32 1 41E+09 d.dlE+07 0. 0. 0. 1.58E+OS 0. 5.44Et07 CR-51 0. 0. 2.78E+04 1.03E+04 6.19E+04 1.17E+07 0. 4.66E+04

0. + 0. 9. 1E+07 0. 9.58EtM 0. 5.97E+07 FE-59 1.27E+08 3.01E+08 0. 0. 8.37E+07 9.95EtM 0. 1.15EiM CO-57 0. 1.17E+07 0. 0. 0. 2.97E+OS 0. 1.95E+07

0. 3.08E+07 0. 0. 0. 6.24E+08 0. 6.90E+07 C0.60 0. 0. 0. 0. 3.14E+09 0. 3.68E+08 Nl-63 1.04E+10 7.22E+08 0. 0. 0. 1.50E+08 0. 3.49E+08 ZN-65 3.18E+08 1.01E+09 0. 6.75E+08 0. 6.35E+08 0. 4.56E+M RB-86 0. 2.20E+08 0. 0. 0. 4.34E+07 0. 1.03EiM SR-89 .DOE+10 0. 0. 0. 1.60E+09 0. 2.86E+08 SR-90 6.07E+11 0. 0. 0. 0. 1.61E+10 0. 1.49E+ll Y.91 5.14E+06 0. 0. 0. 0. 2.83E+09 0. 1.38Ei05 ZR-95 1.40E+06 5.02E+05 0. 7.21E+05 0. 1.92E+09 0. 3.06Ei05 NB- .90& 0. 7.83Ei04 0. 4.79Ei08 0. 3.10Ei04 RU-103 4.84E+06 0. 0. 1.86E+07 0. 5.66E+08 0. 2.09E+06 RU 106 1.93E+08 0. 0. 3.72E+OS 0. 1.25E+10 0. 2.43E+07 AG-11QI 1.06E+07 9.81E+06 0. 1.93E+07 0. 4. 01E+09 0. 5.84E+06 tO 4.10E+0 . 0. 2.17E+09 0. 1.65E+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AHD RELATIVE DEPOSITION ISlE - THE UNIlS fOR C-14 NO H-3 ARE (HREH/TR PER UCI/CU.HETER)

A-49 12/19/84

ENVIRONHENlAL PATHMAY-DOSE CONVERSION FACtORS FOR GASEOUS DISCHARGES PATHMAY - FRESH AND STORED FRUllS Ni VEGETABLES AGE GROUP - ADULT NUCL IDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY SN-1 .OOE. 1.41E-07 0. 0. 2.04E-05 0. 2.45E.07 SN.126 6.16E+09 1.37E+08 3.99E+07 0. 5.16E+07 8.84E+09 0. 2.23E+08 SB-124 1.04E+08 1.97E+06 2.51E+05 0. e.06E+Or 2.94E+09 0. 4.10E+07 SB-125 1.94E+I 1.06E+07 7.39E+07 9.77E+07 1.78E+10 1.59E+09 0. 3.73E+07 TE-1 5H ~ 6 Ei Et . 1E+0 3.93E+08 0. 3.85Eim 0. 1.29Et07 TE-127H 3.50E+08 1.22E+08 9.18E+07 1.42E+09 0. 1.59E<09 0. 4.31E+07 TE 129H 2.55E+08 9.54E+07 S.79E+07 1.06E+09 0. 1.28E+09 0. 4.05E+07 1-130 3.93E+05 1.16E+06 1.48E+08 1.81E+06 0. 9.98E+05 0. 4.58E+05 1-131 .83E+0 . 6E+08 +10 1.98E+08 0. 3.05E+07 0. 6.63E+07 1.132 5.57E+01 1A9E+02 1.96E+04 2.38E-02 0. 2.80Ei01 0. 5.29E+01 1-133 2.13E+06 3.69E+06 7. 10E+08 6A4E+06 0. 3.24Ei06 0. 1.13E+06 1.03E-04 2.79E-04 .63E-02 4ASE-04 0. 2A3E.07 0. 9.99E.05 I -'l3 .04E+04 1.0 + 1.40E+0 1. DE+05 6. 7E-02 1.19E+05 0. 3.91E+04 CS-134 4.87E+09 1.11E+10 0.

3.61E<09 1.19E+09 1.94E+08 0. 9.09E+09 CS-136 4.20E+07 1.66E+08 0. 9.23E+07 1.27E+07 1.89E+07 0. 1.19E+08 CS-137 6.37E+09 8.70E+09 0. 2.96E+09 9.81E+08 1.67E+08 0. 5.71E+09 BA-140 ~ + +05 5.50E+04 9.25E+04 8.54E+08 0. e.4eE+06 CE 141 1.98E+05 1.34E+05 0. 6.19E+04 0. 5.09E+08 0. 1.5IE+04 CE.144 3.30E+07 1.38E+07 0. B.ME+06 0. 1. 11E+10 0. 1. 77E+06 PR-143 6.35E+04 2.55E+04 0. 1A7E+04 0. 2.78E+08 0. 3.15E+03

+04 . OE+ 0. .40E+04 0. 1.95E+OS 0. 4.73E-03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/O, DEPLElED X/O AND RELATIVE DEPOSITION NOlE - THE UNITS FOR C-14 ANO H-3 ARE (HREH/YR PER UCI/CU.HETER)

A-50 12/19/84

ENVIRONHENTAL PATHNAY DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATIHIAY - Fresh and Stored Fruits and V etabies AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE (SQ HETER - HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H- +0 .5 +03 .24E+03 2.57E+03 2.57E+03 0. 2.57E+03 C-14 2.71E+05 2.71E+05 2.71E+05 2.03E+05 2.71E+05 2.71E+05 0. 2.71E+05 P.32 1.13+09 7.06E+07 0. 0. 0. 1.27E+08 0. 4.36E+07 CR.51 0. 0. 2.74E+04 1.01E+04 6.ME-04 1.15E+07 0. 4.58E+04 1.05E+08 0. 1.08E+09 0. 6.72E+07 FE-59 1.34E+08 3.18E+M 0. 0. 8.80E+07 1.05E+09 0. 'I . 21E+08 CO-57 0. 1.31E+07 0. 0. 0. 3.34E+M 0. 2 ~ 19E+07 C0.54 0. 4 45E+07 0. 0. 0. 6.02E+08 0. 1.02EtM CO 60 0. E+08 0. 0. 0. 2.93E+09 0. 5.57E+08 NI-63 1.18E-10 8.18E+08 0. 0. 0. 1.71E+08 0. 3.96E+08 ZN 65 3.57E+08 1.14E+09 0. 7.57E+08 0. 7.13E+08 0. 5.12E+08 RB 86 0. 1.94E+M '0. 0. 0. 3.83Ei07 0. 9.06E+07 SR-89 1.58E+10 0. 0. 0. 1.72E+09 0. 4.55E+08 SR-90 9.40E+1'I 0. 0. 0. 3.36E+09 2.97E+10 0. 2.33E+11 Y-91 7.69E+06 0. 0. 0. 0. 2.95E+09 0. 2. 06E+05 ZR-95 1.87E+06 7.03E+05 0. 7.90E+05 0. 1.86Ei09 0. 4.66E+05 NB- .69E+05 .02E+ 0. B.DOE+04 0. 4.15E+08 0. 5.73E+04 RU-103 6.46E+06 0. 0. 1.93E+07 0. 5.04E+08 0. 2.89E+06 RU-'106 3.15E+08 0. 0. 4 '0E+08 0. 1.43E+10 0. 3.96E+07 AG- I ION 1.19E+07 1.10E+07 0. 2.17E+07 0. 4.50E+09 0. 6. 56E+06

&0 4. +0 0. 2.28E+09 0. 1.73E+06 Based on 1 UCI/SEC release rate of each isotope in and a value of 1. for X/Q. Depleted X/0 and relative deposition.

Note - The mits for C-14 and H-3're (HREH/YR PER UCI/CU.HETER).

A-51 12/19/84

ENVIROHHENTAL PATHMAY - DOSE COHVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHMAY - Fresh and Stored Fru ts and V stables AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE (SQ. HETER HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG Gl-LLI SKIN TOTAL BODY SN 123 ~ E- -0 .22E-07 0. 0. 1.33E-05 0. 2.28E-07 SH.126 7.79E+09 1.54E+08 4.53E+07 0. 6.DIE+07 1.02E+10 0. 2.54Ei08 SB-124 1.12E+08 2.11E+06 2.71E+05 0. 8.69E+07 3.17E+09 0. 4.42E+07 SB-125 2.33E+M 1.66E+07 1.16E+07 1.15E+08 2.01E+10 1.82E+09 0. C.COE+07 TE-1 + . BE+0 C.22E+08 0. 4. 14E+08 0. 1.97E+07 TE. 127)1 '.58E+08 1.36E+05 1.03E+M 1.56E+M 0. 1.95E+09 0. 4.81E+07 TE-129H 3.74E+05 1.39E+08 1.20E<08 1.08E+09 0. 1.31E+09 0. 5.90Ei07 I-'l30 2.58E+05 7.6CE+05 9.72E+07 1.19E+06 0. 6.55E+05 0. 3.DOE+05 1-1 1 . 3E+ .03E+08 +10 1.34E+08 0. 1.96E+07 0. 6. 17Ei07 1.132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E+01 0. 3.47E+01 1.133 1.98E+06 3.36E+06 6.10E+08 4.23E+06 0. 2.44E+06 0. 1.04E+06 I-13C 6.75E-05 1.53E.04 2.3SE-02 2.92E-04 0. 1.60E-07 0. 6.56E-05 1-1 5 .6 E+ .DOE+ E+06 1.11E+05 .12E-02 7.84E+04 0~ 2.57EiOC CS-134 6.84E+09 1.65E+10 0. 4.08E+09 2.DOE+09 1.90E+08 0. 7.69E+09 CS-'136 3.25E+07 1.28E+08 0. 7.13E+07 9.78E+06 1.46E+07 0. 9.21E+07 CS-'137 9.65E+09 'l. 1E+10 0. 3.35E+09 1.73E+09 1.74E+OS 0. 4.57E+09 BA- 4 ~ + 4. E+04 .1 E+0 4.94E+OS 0. e.e6c+M CE-141 2.68E+05 1.79E+05 0. 6.25E+04 0. C.e7E+Oe 0. 2.07Ei04 CE-144 5.47E+07 2.25E+07 4. 9.17E+06 0. 1.29E+10 0. 2.91E+06 PR-143 5.DOE+04 2.20E+04 0. 1.16E+04 0. 2.19E+08 0. 2.C9E+03

+ E +04 0. 1.45E+08 0. 4.50E+03 Based on 1 UCI/SEC release rate of each isotope in and a value of 1. for X/4. Depleted X/4 and relative deposition.

Note - The wits for C-14 and H-3 are HREH/YR PER UCI/CU.HETER).

A-52 12/19/SC

ENVIRONMENTAL PATHNAY - DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - Fresh and Stored FrUIts and V etables AGE GROUP - CHILD NUCLIDE ORGAN DOSE (SQ.METER-MREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIH TOTAL BODY

0. .98&0 .98E+03 2.62E+03 3.98E+03 3.98E+03 0. 3.98E+03 C-14 6.54E+05 6.54E+05 6.54E+05 1.65E+05 6.54E+05 6.54E+05 0. 6.54Ei05 P-32 7.89E+08 4.94E+07 0. 0. 0. 8.87E+07 0. 3.05E+07 CR-51 0. 0. 2.10E+04 7.76E+03 4.67E+04 8.84E+06 0. 3.51E+04

0. E+08 0. 8.45E+07 0. 8.70E+08 0. 5 42E+07 FE-59 1.05E+08 2.50E+08 0. 0. 6.95E+07 8.26E+08 0. 9.52E+07 CO-57 0. 1.06E+07 0. 0. 0. 2.69E+08 0. 1.77E+07 CO-SB 0. 6.62E+07 0. 0. 0. 3.94E+08 0. 2.DOE+08 CO-60 0. .69E+08 0. 0. 0~ 2.05E+09 0. 1.11E+09 NI-63 9.54E+09 6.62E+08 0. 0. 0. 1.38E+08 0. 3.20E+08 ZN.65 2.88E+08 9.12E+08 0. 6.10E+08 0. 5.75E+08 0. 4.13Ei08 RB-86 0. 1.43E+08 0. 0. 0. 2.82E+07 0. 6.66Ei07 SR-89 .76E+10 0. 0. 0. 0. 1.40E+09 0. 1.08E+09 1.26E+12 0. 0. 0. 0. 2.54E+10 0. 3.19E+11 Y-91 1.82E+07 0. 0. 0. 0. 2 42E+09 0. 4.87E+05 4.15E+06 1.09E+06 0. 6.33E+05 0. 1.32E+09 0. 9.43E+05 NB-95 .55E+ E+0 0. 6. 4Ei04 0. 2.26E+08 0. 1.11E+05 RU-103 1.45E+07 0. 0. 1.51E+07 0. 3.81E+08 0. 5.86E+06 RU-106 7.57E+08 0. 0. 3.38E+08 0. 1.18E+10 0. 9.42E+07 AG-11OH 9.61E+06 8.89E+06 0. 1.75E+07 0. 3.63E+09 0. 5.29E+06

0. . 6E+0 0. +07 0. 1.79E+09 0. 1.36E+06 Based on 1 UCI/SEC release rate of each isotope in and a value of 1 for X/O, depleted X/0 and relative deposition.

NOTE - the wits for C-14 and H-3 ere MREH/YR PER UCI/CU.HETER.

A-53 12/19/84

,i',~-,~., ENVIRONHENTAL PATHMAY - DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - Fresh and Stored Fruits and V etabtes AGE GRQJP - CHILD NUCLIDE ORGAN DOSE (SO.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BCOY SN-123 . 1E. E-0 . 6E-07 0. 0. 8.503-06 0. 4.21E-07 SN.126 6.29E+09 1.25E+08 3.66E+07 0. 4.91E+07 8.33E+09 0. 2.06E+08 SB-124 8.90E+07 .68E+M 2.15E+05 0. 6.90E+07 2.52E+09 0. 3.51E+07 58-125 2.54E+08 2.86E+07 2.ME+07 9 47E+07 1.62E+10 1.46E+09 0. 4.44E+07 TE 1 ~ OE+ E+0 3. 5E+08 0. 3.38E+08 0. 4.67E+07 TE.127N 3.25E+08 1.12E+08 9.15E+07 1.26E+09 0. 1.87E+09 0. 4.14E+07 TE 129H 8.69E+08 2.42E+08 2.77EiOS 8 43E+08 0. 1.05E+09 0. 1.34E+08 1-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 0. 1.86E+05 I-131 1 ~ + . 9E+08 4. 2E+ 0 8.48E+07 0. 'I . 19E+07 0. 1. 05E+08 I-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 0. 2.15E+01 I-133 3.61E+06 4 46E+06 1.08E+09 2.62E+06 0. 1.81E+06 0. 1.75E+06 I-134 4.18E+05 1.14E+04 1.47E-02 1.81E-04 0. 9.89E-OB 0. 4.06E-05 I- 3 .64E+ 4.33E+04 .6 + 6.89E+04 E-02 4.85E+04 0. 1.59E+04 CS-134 1.54E+10 2.59E+10 0. 3.29E+09 2.MEi09 1.40E+08 0. 5.51E+09 CS-136 2.23E+07 8.80E+07 0. 4.90E+07 6.72E+06 1.DOE+07 0. 6.34E+07 CS-137 2.28E+10 2.21E+10 0. 2.72E+09 2.59E+09 1.34E+08 0. 3.29E+09 BA-140 . 6E+ E+ .89E+04 .44Ei05 3.60E+08 0. 1.62E+07 CE-141 6.21E+05 3.10E+05 0. 4.85E+04 0. 3.89E+08 0. 4.62E+04 CE- 144 1.31E+08 4.10E+07 0. .39E+06 0. 1.06E+10 0. 6.97E+06 PR. 143 3.48E+04 1 40E+04 0. 8.03E+03 0. 1.52E+08 0. 1.72E+03 E+ + ~ + 9.80E+07 3.40E+03 Based on 1 UCI/SEC release rate of each isotope in and ~ value of 1 for X/O, depleted X/O and relative deposition.

NOTE - the units for C-14 and H-3 are HREN/YR PER UCI/CU.HETER A-54 12/19/84

ENVIROHHENTAL PATHHAY - DOSE CONVERSIOH FACTORS FOR GASEOUS DISCHARGES PATHMAY - Stored Fruits and V tables AGE GRMIP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER HREII/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 2 46E+t6 2 46E+03 2.46E+03 2.46E+03 2.46E+03 0. 2.46E+03 C-14 7.72E+05 1.55E+05 1.55E+05 1.55E+05 1.55E+05 1.55E+05 0. 1.55E+05 P-32 3.67E+08 2.30E+07 0. 0. 0. 4.13E+07 0. 1.42E+07 CR- 1 0. E+04 6.03E+03 3.63E+04 6.87E+06 0. 2.73E+04 NN.54 0. 2.64E+08 0. 7.86E+07 0. 8.09E+08 0. 5.04E+07 FE-59 9.06E+07 2.15E+08 0. 0. 5.97E+07 7.10E+08 0. 8.18E+07 CO-57 0. 9.85E+06 0. 0. 0. 2.50E+08 0. 1.64E+07

0. . 9E+ 0. 0. 4.84E+08 0. 5.36E+07 C0-60 0. 1 44E+08 0. 0. 0. 2.69E+09 0. 3.16E+08 NI.63 8.95E+09 6.21E+08 0. 0. 0. 1.29E+08 0. 3.00Ei08 ZN-65 2.67E+08 8.46E+08 0. 5.66E+08 0. 5.33E+08 0. 3.83E+08 RB-86 0. 9.DOE+0 0. 0. 0. 1.78E+07 0. 4.20E+07 SR-89 7.34E+09 0. 0. 0. 0. 1.17E+09 0. 2.10E+08 SR 90 5.22E+11 0. 0. 0. 0. 1.40E+10 0. 1.28E+11 Y-91 3.88E+06 0. 0. 0. 0. 2.14E+09 0. 1.04E+05 ZR- E+ 4.04E 0. +05 0. 1.59E+09 0. 2.42E+05 NB-95 9.35E+04 5.19E+04 0. 5.15Ei04 0. 3.15E+08 0. 2.04E+04 RU.103 3.34E+06 0. 0 1.28E+07 0. 3.90E+08 0. 1.44E+06 RU-106 1.63E+08 0. 0. 3.15E+08 0. 1.06E+10 0. 2.06E+07 AG- 0N + E+ .62E+0 .37E+09 0. 4.91E+06 CD-115N 0. 3.64E+07 0. 2.89E+07 0. 1.53E+09 0. 1.16E+06 Based on 1 UCI/SEC release rate of each isotope in and a value of 1 for X/0, depleted X/0 and relative deposition.

A-55 12/19/84

E ./4 fl ENVIRONHENTAL PATHMAY - DOSE CONVERSION FACTORS FOR CASEOUS DISCHARGES PATINAT - Stored Fruits and V tables ACE CROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNET LUNG GI-LLI SKIN TOTAL BODY SN-123 0. 0. 0. 0. 0. 0. 0. 0.

SN-126 5.91E+09 1.1SE+08 3.44E+07 0. 4.73E+07 7.99E+09 0. 1.94E+M SB.124 7.ME+07 1.49E+06 1.90E+05 0. 6.11E+07 2.23E+09 0. 3.11E+07 SB-1 E+06 .99E+06 9. 6E+0 1.52E+10 1.37E+09 0. 3.23E+07 TE.125H 7.27E+07 2.64E+07 2.19E+07 2.96E+08 0. 2.90E+OS 0. 9.74E+06 TE-127H 2.82E+M 9.87E+0 7A1E+07 1 ~ 15E+09 0. 1.28E+09 0. 3.48Ei07 TE-124H 1.25E+08 6.20E+07 5.72E+07 6 92E+08 0. 8.32E+M 0. 2.63E+07 1-1 0 0. 0. 0. 0. 0. 0. 0.

1-131 2.99E+06 4.28E+06 1.40E+09 7.33E+06 0. 1.13E+06 0. 2.45E+06 1-132 0. 0. 0. 0.. 0. 0. 0. 0.

1-133 0. 0. 0. 0. 0. 0. 0. 0.

0. 0. 0. 0. 0. 0.

1-135 5.14E-01 4.74E-01 0. 1.80E-01 5.40E 02 1.11E-02 0. 2.11E-OI CS-134 3.99E+09 9.50E+09 0. 3.08E+09 1.02E+09 1.66E+08 0. 7.76E+09 CS.136 S.82E+06 3ABE+07 0. 1.94E+07 2.66E+06 3.96E+06 0. 2.51E+07 CS-1 . 5E+09 8.44EtOS 1.44E+08 0. 4.91E<09 BA-140 2.60E+07 3.45E+04 0. 1.11E+04 1.87E+04 1.89E+08 0. 1.71E+06 CE-141 1.26E+05 8.50E+04 0. 3.94E+04 0. 3.24E+M 0. 9.63E+03 CE-144 2.7SE+07 1.16E+07 0. 6.87E+06 0. 9.37E+09 0. 1.49E+06 PR- 4 E+ 6. + A9E+0 0. 6.60E+07 0. A9E+02 Ie-147 6.19E+04 1.06E+04 0. 1.33E+04 0. 3.19E+07 0. 2.49E+03 Based on 1 UCI/SEC release rate of each isotope in and a value of 1. For X/Q, depleted X/Q and relative deposition.

A-56 12/19/84

ENVIRONHENTAL PATHVAY - DOSE CONVERSIOH FACTORS FOR GASEQJS SUBSTANCES PATHVAY - Stored Fruits and V tables AGE GROUP - TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-HREH/YR PER UCI/SEC)

LIVER THTROID KIDNEY LUNG GI-LLI SKIN TOTAL BODY H-3 0. 2.36E+03 2.36E+03 2.98E+03 2.36E+03 2.36E+03 0. 2.36E+03 C-14 2 49E+05 2 49E+05 2 49E+05 1.87E+05 2.49E+05 2.49E+05 0. 2.49Ei05 P-32 4 45E+08 2. 407 0. 0. 0. 5.DOE+07 0. 1.72E+07 1.98E+ . 1E+03 4.40E+04 8.33E+06 0. 3.31E+04

0. 3.20E+08 0. 9.52E+07 0. 9.80E+08 0. 6.11E+07 FE-59 1.10E+08 2.61E+08 0. 0. 7.23E+07 8.60E+08 0. 9.91E+07 C0.57 0. 1.19E+07 0. 0. 0. 3.03E+08 0. 1.99E+07

0. .8 E+0 0. 0. 5.21E+08 0. 8.78E+07 CO-60 0. 2.24E+08 0. 0. 0. 2.69E+09 0. 5.11E+08 HI-63 1.08E+10 7.52E+08 0. 0. 0. 1 ~ 57Ei08 0. 3.64E+08 2H-65 3.23E+08 1.03E+09 0. 6.86E+08 0. 6.46E+08 0. 4.64Ei08 RB.86 + 0. 0. 0. 2.15E+07 0. 5.09E+07 SR-89 1.32E+10 0. 0. 0. 0. 1.44E+09 0. 3.80Ei08 8.64E+11 0. 0. 0. 3.12E+09 2.74E+10 0. 2.14E+11 Y-91 6.54E+06 0. 0. 0. 0. 2.51E+09 0. 1.75E+05 ZR- E+ 6. E 6.9 E+ 0. 1.67E+09 0. 4.10E+05 NB-95 1.32E+05 7.93E+04 0. 6.24E+04 0. 3.24E+08 0. 4.47E+04 RU 103 .19E+06 0. 0. 1.55E+07 0. 4.05Ei08 0. 2.32E+06 RU.106 .87E+08 . 0. 0. 3.28E+08 0. 1.30E+10 0. 3.61E<07

.08& ~ + .9 i0 0. 4.08E+09 0. .95E+06 CD-115H 0. 4.41E+07 0. 3.50E+07 0. 1.86E+09 0. 1 41E+06 Based on 1 UCI/SEC release rate of each isotope in and a value of 1. For X/O, depleted X/O and relative deposition.

A-57 12/19/84

ENVIRONHENTAL PATHMAY - DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATV.'sT - Stored Fru ts V tables AGE GROUP - TEENAGER INCLIDE ORGAN DOSE FACTORS (SQ. HETER-HREN/TR PER UCI/SEC)

BONE LIVER THTRO ID KIDNET LUNG GI-LLI SKIN TOTAL BODY SN.123 0. 0. 0. 0. 0. 0.

SN-1 6

.16E+ +0 0. 5.73E+07 9.67E+09 0. 2.35E+08 SB-124 9.55E+07 1.80E+06 2.31E+05 0. 7.41E+07 2.70E+09 0. 3.77E+07 SB 125 2.15E+08 1.60E+07 1.13E+07 1.12E+08 1.84E+10 1.67E+09 0. 4.06Ei07 TE-1 N 1.26E+ ~ +0 . SE+0 .58E+08 0. 3.52E+08 0. 1.67E+07 TE-1 7H .4 + E .09E+0 1.38E+09 0. 1.73E+09 0. 4.26E+07 TE-129N 2.90E+08 1.07E+08 9.27E+07 8.38E+08 0. 1.DIE+09 0. 4.56E+07 1-130 0. 0. 0. 0. 0. 0. 0. 0.

1-131 4.85E+ 6. E+06 1.98E+ 8.88E+06 0. 1.30E+06 0. 4.08E+06 1-132 0. 0. 0. 0. 0. 0. 0.

1-133 0. 0. 0. 0. 0. 0. 0. 0.

1-134 0. 0. 0. 0. 0. 0. 0. 0.

1-1 5 6. EO E-0 0. .18E-01 6.55E-02 1.34E.02 0. 2.55E-01 CS.1 . 6E+ 1. 1E+ Ei09 1.83E+09 1. 4E+08 0. 7.04E+09 CS 136 1.07E+07 4.22E+07 0. 2.35E+07 3.22E+06 4.79E+06 0. 3.04E+07 CS-137 8.90E+09 1.2OE+10 0. 3.08E+09 1.59E+09 1.60Ei08 0. 4.20Ei09 BA-1C +04 E+ .61E+04 .75E+08 0. 2.82Ei06 CE- 4 ~ E+ ~ + 4. +04 0. E+08 0. 1.58E+04 CE-144 4.97E+07 2.04E+07 0. 8.33E+06 0. 1.17E+10 0. 2.6CE+06 PR-1C3 1.83E+04 7.35E+03 0. 4.23E+03 0. B.DOE+07 0. 9.07Ei02 8+04 + 1.61E+04 0. 3.86E+07 0. 3.03E+03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH lSOTOPE IN AND A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITION A-58 12/19/84

ENVIRONHENTAL PATHWAY-DOSE COIVERSIOH FACTORS FOR GASEOUS DISCHARGES PATINAY - Stored Frulta and V tables AGE 'GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SO. HETER-HREH/TR PER UCI/SEC)

LIVER THYROID KIDNET LUNG Gl LLI SKIN TOTAL SCOT H-3 0. 3.73E+03 3.73E+03 2.46E+03 3.73E+03 3.73E+03 0. 3.73E+03 C-14 6.14E+05 6.14E+05 6.14E+05 1.55E+05 6.14E+05 6.14E+05 0. 6.14E+05 P-32 3.67E+M 2. +07 0. 0. 0. 4.13E+07 0. 1.42E+07 E+04 6.03E+03 .63Ei04 6.87E+06 0. 2.73E+04 HH-54 0. 2.64E+08 0. 7.86E+07 0. 8.09E+08 0. 5.04E+07 FE-59 9.06E+07 2.15E+08 0. 0. 5.97E+07 7.10E+08 0. S.18E+07 CO-57 0. 9.85E+06 0. 0. 2.50E+08 0. 1.64E+07 CO- 8 E+0 0. 0. 0. 3.53E+08 0. 1.79E+08 CO.60 0. 3 46E+08 0. 0. 0. 1.92E+09 0. 1.04E+09 N 1-63 8.95E+09 6.21E+M 0. 0. 0. 1.29E+08 0. 3.00Ei08 ZN 65 2.67E+08 8 46E+08 0. 5.66E+08 0. 5.33E+08 0. 3.83E+08 RB 86 0. 0. 1.78E+07 0. 4.20E+07 SR 89 3.28E+10 0. 0. 0. 0. 1 ~ 22E+09 0. 9.38E+DS 1.18E+12 0. 0. 0. 0. 2.39E+10 0. 2.99E+l1 T-91 1.61Ei07 0. 0. 0. 0. 2.14E+09 0. 4.30E+05 ZR E+06 . 3E+ E+05 0. 1.21E+09 0. 8.55E+05 NB-95 2.93E+05 1.25E+05 0. 5.15E+04 0. 2.16E+OS 0. 9.17E+04 RU 103 1.23E+07 0. 0. 1.28E+07 0. 3.22E+OS 0. 4.95E+06 RU-106 .05E+08 0. 0. 3.15E+08 0. 1 ~ 10E F10 0. 8.77E+07 AG-1 E+ S. E+ 0. 1.62E+0 0. 3.37E+09 0. 4.91E+06 CD-115H 0. 3 64E+07 0. 2.89E+07 0. 1.53E+09 0. 1.16E+06 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/0, DEPLETED X/0 AND RELATIVE DEPOSITIOH A-59 12/19/84

ENVIRONHENTAL PATHMAY-DOSE COHVERSIOH FACTORS fOR GASEOUS DISCHARGES PATHMAY - Stored Fruits and V tables AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ. HETER-HREH/TR PER UCI/SEC)

LIVER THYROID KIDNET LUNG Gl-LLI SKIN TOTAL SCOT SN-123 0. 0. 0. 0. 0. 0. 0. 0.

SN-126 5.91E+09 1.18E+M 3 44E+07 0. 4.73E+07 7.99E+09 0. 1.94E+08 5$ -124 7.88E+07 1.49E+06 1.90E+05 0. 6.11E+07 2.23E+09 0. 3.11E+07 SB. 25 +08 +0 ~ E+07 9.26E+07 1.52E+10 1.37E+09 O. 4.21E+07 TE-125N 3.09E+M S.38E+07 8.68E+07 2.96E+M 0. 2.98E+08 0. 4.12E+07 TE- 12711 2.96&08 1.02E+M 8.34E+07 1.15E+09 0. 1.71E+09 0. 3.77E+07 TE-129H 7.12E+08 1.98E+M 2.27E+08 6.92E+DS r. 0. 8.57E+08 0. 1.10E+08 I- 0 0. 0. 0. 0. 0. 0. 0.

I-131 1.17E+07 1.20E+07 3.90E+09 7.33E+06 0. 1.03E+06 0. 9.0SEi06 1-132 0. 0. 0. 0. 0. 0. 0. 0.

I-133 0. 0. 0. 0. 0. 0. 0. 0.

0. 0. 0. 0. 0. 0.

I-135 5.14E-01 4.74E 01 0. 1.80E-DI 5.40E.02 1.11E-02 0. 2.11E-01 CS.134 1.44E+10 2 42E+10 0. 3.08E+09 2.69E+09 1.31E+08 0. 5.15E+09 CS.136 8.82E+06 3 48E+07 0. 1.94E+07 2.66E+06 3.96E+06 0. 2.51E+07 CS ~ E+ 0 .55E+09 .43E+09 1.26E+08 0. 3.09Ei09 BA-140 1.06E+08 9.79E+04 0. 1.11E+04 5.52E+04 1.52E+08 0. 6.20E+06 CE-141 5.04E+05 2.52E+05 0. 3.94E+04 0. 3.16E+08 0. 3.7SE+04 CE-144 1.22EtM 3.81E+07 0. 6.87E+06 0. 9.89E+09 0. 6.4SE+06 PR 4 E 0. 3.49E+03 0. 6.60E+07 0. .49E+02 HD-147 6.19E+04 1.06E+04 0. 1.33E+04 0. 3.19E+07 0. 2.49E+03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/O, DEPLETED X/O AND RELATIVE DEPOSITIOH A-60 12/19/84

ENVIRONNENTAL PATHNAY DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - fRESH FRUITS AND VEGETABLES - ADULT AGE GROUP NUCLIDE ORGAN DOSE FACTORS (SQ.HETER HREH/TR PER UCI/SEC)

LIVER THTROID K IDNET LUNG GI-LLI SKIN TOTAL BOOT H-3 0. 4.02E+02 4.02E+02 4.02E+02 4.02E+02 4.02E+02 0. 4.02E+02 C-14 1.25E+05 2.50E+04 2.50E+04 2.50E+04 2 '0E+04 2.50E+04 0. 2.50E+04 P-32 1.04E+09 6.51E+07 0. 0. 0. 1.17E+08 0. 4.02E+07 CR- 1 .1 E+04 4.25E+03 2.56E+04 4.85E+06 0. 1.93E+04 NN-54 0. 4.87E+07 0. 1.45E+07 0. 1.49E+08 0. 9.31E+06 FE-59 3.64E+07 8.64E+07 0. 0. 2 40E+07 2.85E+08 0. 3.29E+07 CO-57 0. 1.85E+06 0. 0. 0. 4.70E+07 0. 3.08E+06 CO-58 0. 6.89E+06 0. 0. 0. 1.40E+08 0. 1.54E+07 CO-60 0. 2.38E+07 0. 0. 0~ 4.46E+M 0. 5.23E+07 Nl-63 1.45E+09 1.01E+08 0. 0. 0. 2.10E+07 0. 4.87E+07 ZN-65 5. 'I 1E+07 1.62E+08 0. 1.09E+08 0. 1.02E+08 0. 7.34Ei07 RB 86 +08 0. 0. 2.56E+07 0. 6.06Et07 SR-89 2.67E+09 0. 0. 0. 0. 4.26E+08 0. 7.64E+07 8.49E+10 0. 0. 0. 0. 2.14E+09 0. 2.07E+10 Y-91 1.26E+06 0. 0. 0. 0. 6.92E+08 0. 3.37E+04 ZR- E+ 1.49E+05 0. .34E+08 0. 6.38E+04 NB-95 4.87E+04 2.71E+04 0. 2.68E+04 0. 1.64E+M 0. 1. 06E+04 RU.103 1.50E+06 0. 5.75E+06 0. 1.76E+08 0. 6.49E+05 RU-106 2.95E+07 0. 0. 5.71E+07 0. 1.91E+09 0. 3.74E+06

+ + .08E+06 0. 6.38E+0& 0. 9.30E+05 CD-115H 0. 1.53E+07 0. 1.21E+07 0. 6.42E+08 0. 4.88E+05 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. fOR X/O, DEPLETED X/O AHD RELATIVE DEPOSITION A-61 I2/19/84

ENVIRONHENTAL PATHMAT-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAT FRESH FRUITS NO VEGETABLES AGE GROUP - ADULT NUCLIDE ORGAN DOSE FACTORS (S4. HETER-HREII/TR PER UCI/SEC)

LIVER THYROID KIDNET LUNG GI-LLI SKIN TOTAL BCDY SN-123 1.00E-05 1.66E.07 1A1E-07 0. 0. 2.04E-05 0. 2.45E-07 SH 126 4.52E+M 1.89E+07 5.54E+06 0. 4.31E+06 8.46E+OS 0. 2.94E+07 SB-124 .52E+07 4. E+05 6.ME+04 0. 1.95E+07 7.12E+08 0. 9.94E+06 58& E+ ~ + 5.14E+06 2.56E+09 2.22E+08 0. 5.10E+06 TE 125H 2.38E+07 8.65E+06 7.17E+06 9.69E+07 0. 9.51E+07 0. 3.19E+06 TE-127H 6.75E+07 2.36E+07 1.77Et07 2.73E+OS 0. 3.06E+M 0. 8.32E+06 TE-129H 8.93E+07 3.34E+07 3.08E+07 3.73E+08 0. 4A9E+08 0. 1.42E+07

. 6E+ .48E+08 1.S1E+06 0. 9.98Ei05 0. 4.58E+05 1-131 7.78E+07 1.12E+08 3.65E+10 1.91E+M 0. 2.94E+07 0. 6.38E+07 I-132 5.57E+01 . 1.49E+02 1.96E+04 2.38E+02 0. 2.80E+01 0. 5.29E+01 1-133 2.13E+06 3.69E+06 7.10E+08 6A4E+06 0. 3.24E+06 0. 1.13E+06 I- 34 .0E04 -04 E-0 4.45E-04 0. 2.43E-07 0. 9.99E-05 I-135 4.04E+04 1.07E+05 1.40E+07 1.70E+05 8.65E-03 1.19E+05 0. 3.91E+04 CS.134 6.82E+OS 1.62E+09 0- 5.26E+08 1.74E+08 2.84E+07 0. 1.33E+09 CS.136 3.32E+07 1.31E+08 0. 7.29E+07 9.99E+06 1.C9E+07 0. 9.43E+07

~ E+09 0. 4.14E+08 1.37E+08 2.34E+07 0~ 7.98E+08 BA.140 1.03E+08 1.35E+05 0. 4.39E+04 7.38E+04 6.65E+M 0. 6.77E+06 CE-141 .16E+04 4.85E+04 0. 2.25E+04 0. 1.85EiM 0. 5.49E+03 CE-144 5.19E+06 2.17E+06 0. 1.29E+06 0. 1.75E+09 0. 2.78E+05 E .94E .1 +04 0. . 2E+OS 0. 2.40E+03 ND 147 3A9E+04 3A3E+04 0. 2.07E+04 . 0. 1.63Ei08 0. 2.24E+03 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN Ne A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION A-62

ENVIRONNENTAL PATHWAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY FRESH FRUITS AND VEGETABLES AGE GROUP TEENAGER NUCLIDE ORGAN DOSE FACTORS (SQ. HETER-HREH/YR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL INNY H- +02 2.64E+02 2 '9E+02 2.09E+02 0. 2.09E+02 C-14 .18E+04 1.64E+04 .18E+04 2.18E+04 0. 2.18E+04 P-32 6.81E+08 4.27E&7 0. 0. 0. 7.66E+07 0. 2.64E+07 CR-51 0. 0. 7.56E+03 2.79E+03 1.68E+04 3.18E+06 0. 1.27E+04

0. 9. 2E+06 0. 9.80E+07 0. 6.11E+06 FE-59 + .6 +0 0. 1.57E+07 1.87E+07 0. 2.16E+07 CO-57 0. 1.22E+06 0. 0. 0. 3.09E+07 0. 2.02Ei06 CO-58 0. 6.01E+06 0. 0. 0. 8.12E+07 0. 1.37E+07

. 1E+ 0. 0. 2.41E+08 0. 4.58E+07 Nl- + . 6.61E 0. 0. 1.38E+07 0. 3.19E+07 ZN-6 3.35E+07 1.06E+08 0. 7.12E+07 0. 6.70E+07 0. 4.82E+07 RB-86 0. 8.52E+07 0. 0. 0. 1.68E+07 0. 3.97E+07 E 0. 0. 0. 2.83E+08 0. 7.48E+07 E+ 0. .41E+08 2.31E+09 0. 1.ME+10 Y.91 1.15E+06 0. 0. 0. 0. 4.41E+08 0. 3.06E+04 ZR 95 2.35E+05 8.19E+04 0. 9.81E+04 0. 1.92E+08 0. 5.61E+04 NB- ~ + E+ 1. 6E+04 0. 9.14E+0 0. 1.26Ei04 RU- +06 9.87E+0 0. 5.66E+05 RU-106 2.82E+07 0. 0. 3.75E+07 0. 1.28E+09 0. 3.54E+06 AG 110N 1.11E+06 1.03E+06 0. 2.02E+06 0. 4.19E+08 0~ 6. 10E+05

.94E+06 0. 4.21E+08 0. 3.20E+05 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AND A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION A-63 12/19/84

&Aj " 'NVIRONHENTAI PATHNAY DOSE CONVERSIDN FACTORS FOR CASEOUS DISCHARCES PATHMAY- FRESH FRUITS NO VECETABLES ACE GROUP - TEENACER NUCLIQE ORGAN DOSE FACTORS (SO. HETER-HREH/TR PER UCI/SEC)

LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAl. BODY SN-123 9.25E.06 1.53E-OT 1.22E.QT 0. 0. 1.33E-05 0. 2.2SE-OT SN-126 6.25E+08 1. 4E+OT 3.64E+06 0. 2.83E+06 5.5SE+OS 0. 1.94E+07 SS-124 .6 E .99E+04 0. 1 '8E+07 4.67E+OS 0. 6.53E+06 SS-125 1.73E+Ol 5.97E+05 3 48E+05 3.38Ei06 1.68E+09 1 4SE+08 0. 3.40E+06 TE-125H 2.23E+07 7.99E+06 6.30E+06 6.36E+07 0. 6.24E407 0. 2.96E+06 TE- 12711 4.46E+Ql. 1.55E+07 1.18E+07 1.8OE+OS 0. 2.23E+OS 0. 5.51E+06 TE- 29II +0 .14E+0 1E+0 2.45E+07 0. 2.95E+OS 0. 1.33E+07 l-130 2.58E+05 7.64E+05 9.72E+OT 1.19E+06 0. 6.55E+05 0. 3.DOE+05 I-131 6.84E+07 9.66E+Ol 2.79E+10 1.25E+M 0. 1.83E+07 0. 5.76E+07 1-132 3.65E+01 9.77E+01 1.29E+04 1.56E+02 0. 1.84E~OI 0. 3 47EiOl I- 3 +06 6. + 4.23E+06 2.44E+06 0. 1.04E+06 1-134 6.75E-05 1.83E-04 2.38E-02 2.92E-04 0. 1.6QE.OT 0. 6.56E.05 I-135 2.65E+04 T.DOE+04 9.15E+06 1.11E+05 5.67E-03 7.84E+04 0. 2.57E+04 CS-134 5.79E+08 1 40E+09 0. 3 45E+08 1.69E+M 1.61E+Ol 0. 6.52E+M CS- + +0 6. 6E+06 .77E+06 0. 6.19E+07 CS-137 7.83E+08 1.05E+09 0. 2.72E+08 1 40E+M 1.41E+07 Q. 3.TOE+M SA-140 9.38E&7 1.21E+05 0 2.8SE+04 7.73E+04 3.19E+OS 0. 6.04Ei06 CS-'l41 6.32E+04 4.24E+04 0 1 47E+04 0. 1.15E+M 0. 4.86E+03

8. E+ . 9E+09 0. 2.67E+05 PR-143 3.17E+04 1.28E+04 0. 7.34E+03 0. 1.39E+08 0. 1.5SE+03 ND 147 2.29E+04 2.26E+04 0. 1.36E+04 0. 1.06E+08 0. 1.47Ei03 SASED Nl 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/O, DEPLETED X/0 AHD RELATIVE DEPOSITION A-64 12/19/84

I r

ENVIRONNENTAL PATHIC DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHNAY - FRESH fRUITS NO VEGETABLES AGE GROUP - CHILD NUCLIDE ORGAN DOSE FACTORS (SQ.HETER-NREH/YR PER UCI/SEC)

BONE LIVER THYROID KIDNEY LUNG GI-LLI SKIN TOTAL BCOY H.3 0. 2 47E+02 2 47E+02 1.63E+02 2.47E+02 2.47E+02 0. 2 47E+02 C-14 4.04E+04 4.04E+04 4.04E+04 1.02E+04 4.04E+04 4.04E+04 0. 4.04E+04 P- 2 E 0. 4.74E+07 0. 1.63E+07 CR-51 0. 0. 4.68E+03 1.73E+03 1.04E+04 1.97Ei06 0. 7.83E+03

0. 1.98E+07 0. 5.89Ei06 0. 6.07E+07 0. 3.78E+06 fE-59 1.48E+07 3.51E+07 0. 0. 9.75Ei06 1. 16E+08 0. 1.34E+07

0. 0. a 0 1.91E+07 0. 1.25E+06 CO-58 0. 6.94E+06 0. 0. 0. 4.13E+07 0. 2.09E+07 CO-60 0. 2.33E+07 0. 0. 0. 1.29E+08 0. 6.98E+07 N I -63 5.90E+08 4.09E+07 0. 0. 0. 8.53E+06 0. 1.98E+07 ZNre ~ + 6. + 4.41E+0 0. 4.15E+07 0. 2.98E+07 RB 86 0. 5.28E+07 0. 0. 0. 1.04E+07 0. 2.46E+07 4.84E+09 0. 0. 0. 0. 1.81E+08 0. 1.39EiM SR 90 7.79E+10 0. 0. 0. 0. 1.52Ei09 0. 1.98E+10 E 0. 2.82Et08 0. 5.65E+04 4.06E+05 9.87E+04 0. 6.07E+04 0. 1. ME+08 0. 8.81E+04 IS-95 6.20E+04 2.64E+04 0. 1.09E+04 0. 4.58E+07 0. 1.94E+04 RU-103 .24E-06 0. 0. 2.34E+06 0. 5.88E+07 0. 9.05E+05

. 2E+0 0. 8.07E+08 6.46E+06 AG.TTOH 6.87E+05 6.36E+05 0. 1.25E+06 0. 2.59E+08 0. 3.78E+05 CO-115N 0. 6.20E+06 0. 4.92E+06 0. 2.6IE4M 0. 1.98E+05 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN AHD A VALUE OF 1. FOR X/0, DEPLETED X/0 AHO RELATIVE DEPOSITION A-65 12/19/84

ENVIRONHENTAL PATHMAY-DOSE CONVERSION FACTORS FOR GASEOUS DISCHARGES PATHMAY - FRESH FRUITS AID VEGEtABLES - CHILD AGE GRQJP NUCLIDE ORGAN DOSE FACTORS (SO.HETER-HREH/YR PER UCI/SEC)

INNE LIVER THYROID KIDNEY LUNG Gl LLI SKIN TOTAL BODY SN-123 1.17E.05 .14E-07 2.26E-07 0. 0. 8.50E-06 0. 4.21E-07 SN.126 3.87E+N .68E+06 2.25E+06 0. 1.75Ei06 3.44E+08 0. 1.19E+07 SB- 24 + + 0. 7.93E+06 2.89E+08 0. 4.40E+06 SB.125 1.22E+07 6.99E+05 6.22E+05 2.09E+06 04E+09 9.02E+07 0.

1 ~ 2.29E+06 TE-125N 4-12E+07 1.12Et07 1.16E+07 3.94E+07 0. 3.97E+07 0. 5.49E+06 TE-127N 2.ME+07 9.90'6 8.09E+06 1.11E+08 0. 1.65E+08 0. 3.67E+06 TE- + E+0 4.99e0 1. 1E+08 0. 1.8SE+08 0. 2.41E+07 1-130 1.60E+05 4.73E+05 6.02E+07 7.35E+05 0. 4.05E+05 0. 1.86E+05 1-131 1.24E+08 1.27E+08 4.13E+10 7.75E+07 0. 1.09E+07 0. 9.5SE+07 1-132 2.26E+01 6.05E+01 7.97E+03 9.65E+01 0. 1.14E+01 0. 2.15EiOI I- 33 .6 E+ +06 .OSE+09 .62E+06 0. 1.81E+06 0. 1.75E+06 1.134 4.18E-05 1.14E-04 1A7E-02 1.81E-04 0. 9.89E-DS 0. 4.06E-05 1-135 1.64E+04 4.33E+04 5.67E+06 6.89E+04 3.51E-03 4.85E+04 0. 1.59E+04 CS.134 9 9lE+08 1.68E+09 0. 2.14E+08 1.87E+08 9.ME+06 0. 3.57E+DS CS- E +0 .96E+0 4.06E+06 6.05E+06 0. 3.83E+07 CS-137 1A1E+09 '1.37E+09 0. 1.68E+OS 1.60E+08 8.34E+06 0. 2.04E+08 BA 140 1.70E+08 1.56E+05 0. 1.78Ei04 8.87E+04 2.0SE+08 0. 9.96E+06 CE-141 1.17E+05 5.84E+04 A) ~ 9.13Ei03 0. 7.33E+07 0. 8.69E+03 E + + 0~ . 1E+OS 0. 4.92E+05 PR-143 1.97E+04 7.89E+03 0. 4.54E+03 0. 8.60E+07 0. 9.75E+02 IN-147 1A2E+04 1. 9E+04 0. 8.42E+03 0. 6.61E+07 0. 9.08E+02 BASED ON 1 UCI/SEC RELEASE RATE OF EACH ISOTOPE IN ANO A VALUE OF 1. FOR X/4, DEPLETED X/4 AND RELATIVE DEPOSITION A-66 12/19/84

l 1

1

APPENDIX B TECHNICAL BASIS POR A f~

APPENDIX B Technical Bases for Aeff ff overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactivity released to approximate the dose in the environment, ie, instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (A,ff times the total quantity of radioactive material released) would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.

Dete i at'o o A ff The effective dose transfer factor is based on past operating data. The radioactive effluent distribution for the past years can be used to derive a single effective factor by the following equation.

(Eq. B-1) where:

A~)~ the effective dose transfer factor A, the dose transfer factor for radionuclide the fractional abundance of radionuclide i in the radioactive effluents 07/20/84

This equation yields a single dose factor, weighted by the typical radionuclide distribution.

To determine the appropriate effective factor to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for 3 years have been evaluated. An effective dose transfer factor has been determined for the gaseous effluents for all pathways of interest. Tables B-1 and B-2 present the results of this evaluation.

For the radioiodines and particulates with half-lives greater than 8 days, the effective dose transfer factor is based solely on the radioiodines (Z-131, and I-133). This approach was selected because the radioiodines contribution essentially all of the dose to the infant's thyroid via the cow-milk pathway. The infant's thyroid and the cow-milk pathway are the critical organ and controlling pathway, respectively, for the releases of radioiodine and particulates. All other particulates contribute less than 14 of the dose. The effective dose transfer factor is determined by applying equation B-1 to the radioiodines. However, in determining the dose, this effective dose transfer factor should be applied to the total*release of all radioiodines and to particulates with half lives greater than 8 days. This uniform application is conservative in providing reasonable assurance that the actual dose will not be underestimated by the use of this simplified method.

The determination of A,<< is limited to three years (1978, 1979, and 1980) because of the changes that occurred in the waste processing'ystem. A demineralizer system replaced the previously used evaporator in the liquid waste processing system.

B-2 07/20/84

As can be seen from Tables B-1 and B-2, the effective dose transfer factor varies little from year to year. The maximum observed variability from the average value is 13% for the noble gases and 254 for the radioiodines. This variability is minor considering other areas of uncertainty and conservatism inherent in the environmental dose calculational models.

To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculational process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

B-3 07/20/84

Table B-1 Effective Dose Transfer Factors Noble Gases-Air Dose yeff Pef f Year mrad mrad (pCi ~ sec/m ) (pCi ~ sec/m )

1978 1.3 x 10 3.4 x 105 1979 x 10 3.4

'.3 x 10 ~

1980 1.6 x 10 3.4 x 10 Average 1.4 x 10 5 3.4 x 10 ~

B-4 07/20/84

Table B-2 Effective Dose Transfer Factor for Air-Grass-Cow-Milk-Znfant-Thyroid Pathway Radio Annual Fraction Dose Weighted nuclide Airborne Dose Factor Release Factor'rem r mrem r (Ci) pCi/ (m sec)

~

pCi/ (m sec)

~

1978 I-131 0.381 0. 688 9.9E11 I-133 0.129 0.233 1.3E10 6.9E11 I-135 0.044 0.079 5.2E6 1979 I-131 0.0188 0. 520 9.9Ell I-133 0.0156 0.432 1.3E10 5.2E11 I-135 0.0018 0.048 5.2E6 1980 I-131 0.0518 0.756 9.9E11 I-133 0.0124 0. 181 1.3E10 7.5Ell I-135 0.0043 0.063 5.2E6 Average 6.5Ell a-Air-grass-cow-milk-infant-thyroid dose transfer factor.

b-Effective dose commitment transfer factor is the average of weighted dose transfer factor over three years.

B-5 07/20/84

APPENDIX C RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE

APPENDIX C RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key,to Sample Locations It is the policy of Florida Power and Light Company (FPL) that the Turkey Point 3 and 4 and St. Lucie 1 and 2 Radiological Environmental Monitoring Programs are conducted by the State of Florida Department of Health and Rehabilitative Services (DHRS),

pursuant to an Agreement between FPL and DHRS and; that coordination of the Radiological Environmental Monitoring Programs with DHRS and compliance with the Radiological Environmental Monitoring Program Technical Specifications are the responsibility of the Nuclear Division Health Physics/Chemistry Staff.

C-1 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEI LIANCE TURKEY POINT PLANT Key to Sample Locations Pathway .,Location Description Samples Sample Approximate Direction g p)~',q Collected Collection Distance Sector Frequency (miles)

Direct N-1 Convoy Quarterly Radiation Point Direct N-5 North of Quarterly Radiation Moody Dr.

Direct N-10 Old Cutler Quarterly 12 Radiation Rd at S.W.

87th Ave Direct NNW-1 Turkey Quarterly Radiation Point Entrance Rd Direct NNW-10 Burr Rd at TLD Quarterly NNW Radiation Hainlin Mill Dr Direct Turkey Quarterly Radiation NW/WNW-1 Point Entrance Rd Direct NW-5 Dolan's Farm Quarterly NNW Radiation on King' Highway C-2 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location Description Samples Sample Approximate Direction Collected Collection Distance Sector Frequency (miles)

Direc- NW-10 Inter- Quarterly 10 Radia -ion section of Farm Life Rd and Coconut Palm Dr Direct W/WNW-5 Palm Drive at TLD Quarterly Radiation Tallaha-see Rd Direct WNW-10 Homestead TLD Quarterly Radiation near vehicle inspection station Direct W-1 On site near Quarterly Radiation cooling tower Direct W-10 Florida City TLD Quarterly 10 Radiation near fire tower Direct WSW-10 Old Hawk TLD Quarterly 12 WSW Radiation missile site south of Florida City C-3 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location Description Samples Sample Approximate Direction Collected Collection Distance Sector Frequency (miles)

Direct SW/SSW-1 On site near Quarterly SSW Radiation land utilization offices Direct SW-10 U.S.1 south TLD Quarterly 10 SW Radix;=ion of Florida City Direct SSW/SW-5 On site, TLD Quarterly SSW Radiation southwest corner of cooling canals Direct SSW-10 At Card Sound Quarterly 10 SSW Radiation Bridge Direct S-5 On site, Quarterly Radiation south end of cooling canals Direct S-10 Card Sound Quarterly 10 Radiation Road at Steamboat Creek C-4 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location Description, Samples Sample Approximate Direction Collected Collection Distance Sector Frequency (miles)

Direct SSE/S-l Turtle Point Quartley SSE Radiation Direct SSE-10 Ocean Reef Quartley SSE Radiation Airborne T51 Homestead Radioiodine Weekly NNW Bayfront Park and Particulate Airborne T57 Tree Nursery Radioiodine Weekly 316th Street and Particulate Airborne T52 Florida City Radioiodine Weekly (Alternate Substation and to T57) Particulate Airborne T58 Turkey Point Radioiodine Weekly Entrance Rd and Particulate C-5 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location Description Samples Sample Approximate Direction Collected Collection Distance Sector Frequency (miles)

Airborne T64* Natoma Radioiodine Weekly 22 NNE Substation and Particulate Airborne T72 Turkey Point Radioiodine Weekly WSW Boy Scout and Camp Particulate Waterborne T42 Biscayne Bay, Surface Water Monthly ENE at Turkey Shoreline Point Sediment Semi-annually Waterborne T67* Biscayne Bay, Surface Water Monthly 13-18 N,NNE vicinity of Cutler Plant Shoreline north Sediment Semi-to Matheson annually Hammock Park Waterborne T81 Card Sound, Surface Water Monthly near mouth of old Shoreline discharge Sediment Semi-canal annually

• Denotes control sample.

C-6 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location.

f 'f/~pi Description Samples Sample Approximate Direction

$ <'f,y.' i~

's Collected Collection Distance Sector Frequency (miles)

Food T67* Biscayne Bay, Crustacea Semi- 13-18 N,NNE Products vicinity of annually Cutler Plant north Fish Semi-to Matheson annually Hammock Park Food T81 Card Sound Crustacea Semi-Products vicinity of annually Turkey Point Facility Fish Semi-annually Food T40 South of Palm Broad Monthly Products Dr. on SW leaf 117th St vegetation extension Food T41 Palm Dr. West Broad Monthly Products of old leaf missile vegetation site near the site boundary

• Denotes control sample.

C-7 07/20/84

RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE TURKEY POINT PLANT Key to Sample Locations Pathway Location Description Samples Sample Approximate Direction Collected Collection Distance Sector Frequency (miles)

Food T67* Near Broad Monthly 13-18 N,NNE Products Biscayne leaf Bay, vegetation Vicinity of Cutler Plant North to Matheson Hammock Park

• Denotes control sample.

C-8 07/20/84

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8'-10 06/25/91 h I I

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APPENDIX D EXAMPLE CALCULATIONS

APPENDIX D EXAMPLE CALCULATIONS

1. Determination of Radionuclide Concentration in the Condenser 2 ')

Cooling Water Mixing Basin, C., from a Liquid Release (Section

~

= Cg F~

Cg z F2 (1)

• where:

C,+ concentration of radionuclide radwaste released, i in the liquid pCi/ml, obtained from nuclide analyses report for the liquid release sample taken prior to release.

F) Flow rate from monitor tank = 100 gal/min.

Total condenser cooling water flow = 156,000 gpm/circulating pump; total capacity Units 3 and 4 = 8 pumps x 156,000 = 1,248,000 gal/min.

+ Note: When determining actual release concentrations, contact units 1 and 2 to determine how many, if any, circulating pumps were running during release. The flow of these pumps must be included when determining Fz.

Example:

For a monitor tank analysis (from Nuclide Analysis Report),

C< is equal to the following concentrations:

Co-60 8 x 10 pCi/ml Co-58 2 x 10 pCi/ml Cr-51 7 x 10 pCi/ml Mn-54 5 x 10 6 pCi/ml Cs-137 5 x 10 ~

pCi/ml I-131 3 x 10 pCi/ml F,/Fz = 100 gpm/1,248,000 gpm = 8 x 10

• Note: Equation numbers refer to the equation listed by that number i>. i'ie ODCM text.

D-1 06/25/91

/F Co-60 8 x10~ 8x10~ 6.4 x 2xlO x10~

10'.6 Co-58 8 X 10 Cr-51 7 x lo" 8 x 10' 5.6 x 10" Mn-54 5 x 10 x lo' 4.0 x 10 >o Cs-137 5 x10~ x 4.0 x 10 "

lo'xlO~

I-131 3 x 10' 2~4 x 10 11 D-2 06/25/91

2. Determination of the Fraction of the Unrestricted Area MpC from a Batch Release of Liquid Radwastep FMpCb (8ection, 2~3 ~ 1) ~

b (2) where:

Czi Radionuclide concentration in condenser cooling water mixing basin, pCi/ml Mpci Maximum permissible concentration from 10 CFR 20 Appendix B, Table 2, Column 2, pCi/ml Eb 0.5; E> is an adjustment to account for radionuclides not measured prior to release but measured in the monthly and quarterly sample per Technical Specification Table 4.11-1~

Example:

Z FMPC for a release must be less than 1 or the release cannot be made. Z FMPC for the batch release in example 1 above is calculated as follows:

Nuclide MPC.* C /MPC. FMPC Co-60 6.4 x 10 ~ 3 x 2.1 x 10 0.5 4.2 x 10 10'x105 Co-58 1.6 x 10 >0 1.8 x 10 0.5 3.6 x 10 Cr-51 5.6 x 10 " 2 x 10' 2.8 x 10 0.5 5.6 x 10 Mn-54 4.0 x 10 >0 x 10~ 4.0 x 10 0~5 8.0 x 10 Cs-137 4.0 x 10 2 x 105 2.0 x 0.5 4.0 x 10 2.4 x 10 "

10'.0 I-131 3 x 10" x 10 ~

0.5 1.6 x 10 7 08 x 10 ~

~ 2.98 x 10 0.5 6.0 x 10

• Use the smaller value of the soluble(s) or insoluble (I) MPC values given in 10 CFR 20, Appendix B, Table 2, Column 2.

D-3 06/25/9 1

The fraction of unrestricted area MPC from a continuous release (Section 2.3.2) is calculated in the same manner as the batch release shown above.

D-4 06/25/9 1

3. Determination of Cumulative Dose from Radioactive Liquid Effluents (Section 2.4).

The dose or dose commitment to a member of the public from radioactive liquid effluent shall be calculated on a cumulative quarterly and cumulative annual basis at least once per 31 days.

The dose or dose commitment from radioactive liquid releases at Turkey Point is based on the irradiation of a child on the canal kg shoreline, the most restrictive age group and is calculated using equation 7.

0 23 ~ ~ gshozel2ne . ik 1k k (7) where:

D = total body or organ dose due to irradiation by radionuclides on the shoreline which originated in a liquid effluent release, (mrem).

0.23 = units conversion constant = ~1 C x 60 min x 3785 ~m 10 pCi hr gal

= transfer factor relating a unit aqueous concentration of radionuclide i (pCi) to dose commitment rate to A<

specific organs and the total body of an exposed person tabulated in Appendix A, (mrem/Ci . min/gal).

C~<

= the concentration of radionuclide in the undiluted liquid waste to be discharged that is represented by sample k, (gal/min).

V = cooling canal effective volume, approximately 3.75 x 10~ gallons.

tz = period of time (hours) during which liquid waste represented by sample k is discharged.

~ = effective decay constant (X,. + FJV,minute ') .

where:

A,< = the radioactive decay constant F> = canal-ground water interchange flow, approximately 2.25 x 10 gal/min D 5 06/25/9 1

Example:

The concentration of radionuclides in liquid waste discharges to the condenser cooling water mixing basin during the month of February was determined by summing the results of the radionuclide analysis sheets for each sample taken prior to the release. The total concentration of each radionuclide was:

Radionuclide C) ~~Ci~mL Co-60 4 x10~

Co-58 1x10' Cr-51 x 10s Cs-134 5 x 10' Cs-137 x10' Mn-54 x10' I-131 x 10 The average flow rate from the monitor tanks during the releases (F<z) = 100 gpm.

The total period of time for the releases (tz) was 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

1 The cumulative whole body dose to a child due to these releases is determined by summing the dose from each radionuclide as shown in the. Example 3 Work sheet.

D-6 06/25/91

EXAMPLE 3 WORKSHEET FOR DOSE TO WHOLE BODY FROM LIQUID RELEASE

..Radio-nuclide Cik Ai Fl tt ~ 0.23AiCik F3/V i Xe-Vowel I

Flktt Co-60 4E-4 9.45E+3 100 15 1.30E+3 2.53E-7 6.0E-5 6.02E-5 2.26E+5. 5.8E-3 Co-58 1E-5 1.67E+2 100 15 5.76E-l 6.80E-6 6.0E-5 6.68E-5 2.50E+5 2.3E-6 Cr-51 4E-6 2.06E+0 100 15 2.84E-3 1. 74E-5 6.0E-5 7.74E-5 2.90E+5 9.8E-9 Cs-134 5E-6 3.08E+3 100 15 5.31E+0 6.39E-7 6.0E-5 6.06E-5 2.27E+5 2.3E-5 Cs-137 2E-6 4.54E+3 100 15 3. 13E+0 4.37E-8 6.0E-5 6.00E-5 2.25E+5 1.4E-5 Mn-54 2E-5 6.09E+2 100 15 4. 20E+0 1.54E-6 6.0E-5 6.15E-5 2.31E+5 1.8E-5 1-131 1E-6 7.59E+0 100 15 2.62E-3 5.98E-5 6.0E-5 1.19E-4 4.46E+5 5.9E-9 Eo- 5.9E-3 Total whole body dose to child from irradiation by radionuclides on the shoreline from radioactivity released in month of February is 5.9E-3 mrem. Cumulative dose for first quarter would be sum of January dose + February dose. Cumulative annual dose in this example would be the same as the quarterly dose.

In this case the organ dose is the same as the whole body dose since the dose transfer factors for direct radiation is the same.

D-7 06/25/91

4 ~ Determination of the projected Dose (Section as)

The dose, to unrestricted areas, from liquid effluent must be projected at least once per 31 days when the liquid radwaste treatment system is not being fully utilized. The dose projection can be made using equation (8).

p- 31 X

D (8) where:

the projected total body or organ dose during the month (mrem) 31 number of days in a calendar month, (days) number of days in current month to date represented by available radioactive effluent sample, (days)

D total body or organ dose to date during current month calculated according to section 2.4, (mrem).

Example:

The whole body dose calculated as of March 15 was 7.5 x 10 ~ mrem.

The projected dose for the 31 day period in March would be:

31 x D 31 x 7 .5 x 10 mrem = 1.55 x 10 i mrs 15 15 Thus, in accordance with Technical Specification 3.11.1.3, appropriate portions of the liquid radwaste treatment system must be used to reduce releases of radioactivity since the dose from each unit would exceed 0.06 mrem.

D-8 06/25/9 1

5. Liquid Radwaste Effluent Monitor Marm Setpoint (Section 2 ~ 6+i) ~

The monitor alarm setpoint for liquid batch releases is based on the fraction of the unrestricted area MPC (FMpC) that will be present in the condenser cooling water mixing basin as a result of the activity concentration present in the liquid radwaste to be released.

The monitor setpoint can be determined using equation (9) for batch and continuous releases respectively.

Example:

Sb =

Ab 'g gb + Bkg

~pCb (9) where:

s radiation monitor alarm setpoint for a batch release, (cpm) laboratory counting rate (cpm/ml) or activity concentration (pCi/ml) of sample from batch tank FMPCb fraction of unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a batch release; determined in section 2.3.1.

gb detection efficiency of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch sample (cpm per cpm/ml or cpm per pCi/ml which ever units are consistent with the units A ).

Bkg background, (cpm)

$ A factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the releases.

D-9 06/25/9 1

1 4

Determine the monitor setpoint when:

FMPCb 6 x 10 8.85 x 10, pCi/ml gb 15, 000 cpm/pCi/ml S) .8 Bkg 10,000 cpm

' -5 Sb =

6 x 104 x1.5 x104+ 1 X104 = 11,770 cpm D-10 06/25/91

6 ~ Determining the Total Body Dose Rate from Noble Gas (Section 3 ~ 3. 1) ~

The total body dose rate from the radioactive noble gases may be calculated at any location by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases.

Compliance is assessed and alarm setpoints established based on the dose rate at the site boundary where the minimum atmospheric dispersion from the plant occurs. This location is 1950 meters SSE of the plant where g/Q = 5.8 x 10 " sec/m~.

The dose rate D may be calculated using equation (13).

Example:

During a 31 day period the following noble gas activity was released from Unit 3. The total body dose rate is calculated by:

1 TB v g (13) where:

D Dose rate to total body from noble gases, (mrem/year)

X/Q = atmospheric dispersion factor at the off-site location of interest, (sec/m~)

t = Averaging time of release, i.e.', increment of time during which released, Q~ was- (year)

Q<

= quantity of noble gas radionuclide i released during the averaging time, (pCi)

P I factor converting time integrated concentration of noble gas radionuclide ody dose, i at ground level, to total em  ; See Reference Table 3-4 pCi~ sec/m D-11 06/25/91

The, total body dose is summarized in the following table:

Radionuclide Q( P )

Kr-85m 3.6E-2 3.7E-5 1.33E-6 Kr-85 2.8E-1 5.1E-7 1.43E-7 Kr-87 2.5E-3 1.9E-4 4.75E-7 Kr-88 1. 4E-2 4.7E-4 6.58E-6 Xe-131m 1. OE+1 2.9E-6 2.90E-5 Xe-133 4.3E+1 9.3E-6 4.00E-4 Xe-135 6.0E-1 5.7E-5 3.42E-5 Ar-41 7.7E-2 2.6E-4 2.00E-5 The value of ZQ<P,. is equal to 4.92 E-4 D = 5.8 E-7 x 11.77 x 4.94 E-4 = 3.36 E-9 mRem/yr Note: The time (t) is for 31 day period stated as years which equals 31d/365d/yr or 0.085 yr. The value in the table, 1/t is 1/0.085 = 11.77.

D-12 06/25/91

7. Determination of Skin Dose Rate from Noble Gases (Section 3.3.2)

The skin dose rate from radioactive noble gases may be calculated at any location in a manner similar to example 3.3.1 using Equation (14) .

Example:

Using the noble gas release data given in Example 3.3.1 the skin dose rate is calculated by:

D = 4 [7 g SP + 1.11' Ag]

(14) where:

Ds dose rate to skin from radioactive noble gases (mrem/year)

SP) factor converting time integrated concentration of noble gas radionuclide ose from b ta radiation, i at ground-level, to skin

" "'/ Reference Table 3-4

1. 11 ratio of tissue dose equivalent to air dose in a radiation field, (mrem/mrad).

A factor for converting time integrated concentration

)

of noble gas radionuclide i in a to ai dose from its gamma radiation, semi-infinite'loud, rad  ; Listed in Table 3-3 pCi~ sec/m D-13 06/25/9 1

The skin dose rate is summarized in the following table:

Nuclide Q; SPi Q,.SPi Q;A; Kr-85m 3.6E-2 4.6E-5 1.7E-6 3.9E-5 1.40E-6 Kr-85 2.8E-1 4.2E-5 1.2E-5 2.0E-3 5.60E-4 Kr-87 2.5E-3 3.1E-4 7.8E-7 2.0E-4 5. OOE-7 Kr-88 1.4E-2 7.5E-5 1.1E-6 4.8E-4 6.72E-6 Xe-131m 1.0E+1 1.5E-5 1.5E-4 4. 9E-6 4.90E-5 Xe-133 4.3E-1 9.7E-6 4.2E-6 1.1E-5 4.73E-6 Xe-135 6.0E-1 5.9E-5 3.5E-5 6.1E-5 3.66E-5 Ar-41 7.6E-2 8.5E-5 6.5E-6 2.9E-4 2.20E-5 The value of EQiSSi = 2.11 E-4 and the value of EQiAyi = 5.9 E-4 D =5.8E-7 x 11.77 (2.11E-4 + [1.11 x 5.9E-4]) = 5.58E-9 mrem/yr Note: The value 1/t is 11.77 (see Example 6 table note), and X/Q is 5.8E-7 sec/m~

D-14 06/25/9 1

8, Determining Dose Rate from Tritium, Zodines, and particulates (Section 3.3.3)

The total body and/or organ dose rate due to tritium, radioiodines, and radioactive particulates with half-lives greater than 8 days released in the effluent air may be calculated at any location off-site using equation (15).

For assessing compliance with Technical Specification 3.11.2.1, the thyroid dose rate for a hypothetical infant located at the site boundary where the minimum atmospheric dispersion from the plant occurs is the assumed receptor.

Example:

During a calendar quarter (2184 hrs) the following activities were released from Unit 4. The dose rate from activity is calculated by:

where:

dose equivalent rate to body organ n of a person in age group a exposed via pathway p to identified in analysis k of radionuclide effluent air, i

(mrem/year) 3600 conversion constant, (sec/hr) period of time over which the effluent releases are averaged, (2184 hrs/qtr) quantity of radionuclide i released during time increment t based on analysis k,'pCi).

quantity of radionuclide i released during increment time t based on analysis k (uCi).

TA, a factor relating the airborne concentration time integral of radionuclide i to the dose equivalent to organ n of a person in age group a exposed via pathway p, mre r See Appendix A pci/m D-15 06/25/9 1

The dose rate from tritium; iodine and particulate is summarized in the following table.

Radionuclide TAanrp Q kTAsn) p

~

H-3 1.6E+5 2.37E+3 3.79E+8 Cr-51 8 'E-6 1.8E+4 1 44E-1

~

Co-58 5.0E-7 Co-60 9.5E-7 I-131 3.5E-7 9.94E+ll 3.48E+5 Cs-137 2.0E-6 Notes: The time factor 1/3600t The

= 1.27E-7 where value of ZQ,TA,< = 3.8E+8 t= 2184hrs/qtr The value of XgQ = 8.8E-7 D, = 1.27E-7 x 5.8E-7 x 3.8E+8 = 2.8E-5 mrem/yr D-16 06/25/91

9 ~ Determining the Noble Gas Gamma Radar.ation Dose (8ection 3 4 1)~ ~

The cumulative dose due to gamma radiation from radioactive noble gases discharged from the plant shall be calculated once per 31 days to verify the quarterly and annual limits will not be exceeded.

The gamma radiation dose from noble gases are calculated at the site boundary where the minimum atmospheric dispersion occurs, i.e., 1950 meters SSE of the plant where g/Q = 5.8 x 10 ~ sec/m~.

The gamma dose is calculated using equati'on (16) or (17). The example given here uses equation (17).

Example:

The noble gas activity discharged during a 31 day period from gas decay tanks, containment purges, and the spent fuel pit vent were totaled as tabulated below. The gamma dose from the noble gas release is calculated as follows:

Dy=+$ $ 0g'fg'Ag (17) where:

D = The noble gas dose to air due to a mixed mode Y

release (mrad).

X/Q = The atmospheric dispersion factor for a mixed-mode discharge, (sec/m~) .

Q>

= The measured radioactivity released via stack or vent during a single counting interval,j (pCi).

f< = The fraction of radionuclide i released in a given effluent stream.

A Factor converting time integrated, ground-level

)

concentration of noble gas radionuclide dose from gamma radiation listed in Table 3-3, i to air pCi ~ sec/m~

D-17 06/25/91

The noble gas gamma radiation dose is summarized in the following table.

Radio- Q; A Qif(A x/Q nuclide Kr-85m 5.4E+1 6.7E-4 3.9E-5 1.4E-6 5.8E-7 Kr-85 5.4E+1 5.2E-3 5.4E-7 1.5E-7 5.8E-7 Kr-.87 5.4E+1 4.6E-5 2.0E-4 5.0E-7 5.8E-7 Kr-88 5.4E+1 2.6E-4 4.8E-4 6.7E-6 5.8E-7 Xe-131m 5.4E+1 1.8E-1 4.9E-6 4.8E-5 5.8E-7 Xe-133 5.4E+1 8.0E-1 1.1E-5 4.8E-4 5.8E-7 Xe-135 5.4E+1 1 'E-2 6.1E-5 3.6E-5 5.8E-7 Ar-41 5.4E+1 1.4E-3 2.9-4 2.2E-8 5.8E-7 The value of ZQif<A J < z~l

= 5.95E-4 D

Y

= 5.95E-4 x 5.8E-7 = 3.45-10 D-18 06/25/91

10. Determining Noble Gas Beta Radiation Dose (section 3.4.2)

The beta air dose due to noble gases discharged from the plant shall be determined for the current calendar quarter and current calendar year at least once per 31 days. The beta air dose is calculated in the same manner as the gamma air dose in Sections 3.4.1 above using the effective beta air dose factor from Table 3-3 and Equation (18).

D-19 06/25/91

11. Determining Dose Due to Iodine, Tritium, and Particulates (section 3.5.2)

Dose estimate should account for exposure of a person via the following pathways involving deposition of radioactivity on the ground.

direct radiation from airborne radionuclides except noble gases inhalation direct radiation from ground plane deposition fruits and vegetables air-grass-cow-meat air-grass-cow-milk The requirement to determine the dose commitments due to radioiodine, tritium, and radioactive particulates once per 31 days may be satisfied by using Equations (21),

(22), (23), and (24) .

Example:

The organ and total body dose to an infant from tritium inhalation and irradiation pathways and from radioiodines and particulates via the grass-cow-milk pathway is calculated using Equations 22 and 23. The major non-noble gas activities released over a 31 day period were used for the calculation. The atmospheric dispersion factor, XQQ and deposition rate, D/Q values for a mixed mode release at 3.6 miles WNW and 4.5 miles west of the plant respectively were obtained from Tables 3-7 and 3-8.

Factors TA,< and TG,< converting airborne activity to dose commitment are obtained from Appendix A for the organ, age group, and pathway.

D~ = 3.17 x 10 8 XQ gz> g TA~<>

P (22)

D~ = 3.17 x'0 -e gg~ g TG~gy P

(23) where:

atmospheric dispension factor for a mixed mode release, adjusted for depletion by deposition, (sec/m3) .

relative deposition rate onto ground from a mixed mode atmospheric release (m 2).

D-20 06/25/91

the quantity of radionuclide i released in a given effluent stream based on 'analysis k, (pCi) ~

a factor converting airborne concentration of radionuclide i to a dose commitment to organ n TA~n)p of a person in age group a where exposure is directly due to airborne material via pathway P (inha ation o external exposure to the plume), mrem~r pCi/m factor converting ground deposition of TGan~p radionuclide i to dose commitment to organ n of a person in age group a where exposure is due to radioactive material via pathway P (direct radiation from ground plane deposition, fruits and vegateabl s, air-grass-cow-meat, or air-grass-cow-milk) mre pci/m ~ secI Donk the dose commitment to organ n of a person in age group a due to radionuclides identified in analysis k of an air effluent, (mrem).

The organ and total body dose to an infant from radioiodines and particulates via the grass-cow-milk pathway is shown in the Example 10 Horksheet.

D-21 06/25/91

EXAMPLE 10 WORKSHEET - PAGE 1 GRASS-COW-MELK PATHWAY Organ TA~)p Xd/Q 3.17E-8 Total Dose Radio- Qlk or or Sum of D,<

nuclide TG D/Q (mrem)

Bone H-3 2.0E+8 Co-58 2.0E+1 Co-60 1.7E+1 I-131 3.9E+3 2 59E+9 5E-10 3.17E-8 1.6E-4 Cs-137 6.1E+1 6.44E+10 5E-10 3.17E-8 6.2E-5 2.2E-4 Liver H-3 2.0E+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2. OE+1 2.55E+7 5E-10 3. 17E-8 8. 1E-9 Co-60 1.7E+1 8.73E+7 5E-10 3. 17E-8 2.4E-8 I-13 1 3.9E+3 3.09E+9 5E-10 3.17E-8 1.9E-4 Cs-137 6.1E+1 7.21E+10 5E-10 3.17E-8 7.0E-5 1.8E-3 Thyroid H-3 2.0E+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 Co-60 1.7E+1 I-131 3.9E+3 9 '4E-11 5E-10 3.17E-8 6.1E-l 6.1E+1 6.1E-1 Cs-137 D-22 06/25/91

EXAMPLE 10 WORKSHEET - PAGE 2 GRASS-COW-MILK PATHWAY Organ SA1P XQQ 3. 17E-8 ank Total Dose Radio- or 01 Sum of D, nuclide TG D/Q (mr em)

Kidney H-3 2.0E+8 1.04E+3 lE-7 3. 17E-8 6.6E-4 Co-58 2.0E+1 Co-60 1.7E+1 I-131 3.9E+3 7.74E+8 5E-10 3.17E-8 4.8E-5 Cs-137 6.1E+1 3.66E+9 5E-10 3. 17E-8 3.5E-6 7.1E-4 Lung H-3 2.0E+8 2.37E+3 1E-7 3.17E-8 1.5E-3 Co-58 2.0E+1 Co-60 1. 7E+1 I-131 3.9E+3 Cs-137 6.1E+1 8.69E+9 5E-10 3. 17E-8 8.4E-6 1.5E-3 GI/LI H-3 2.0E+8 2.37E+3 lE-7 3. 17E-8 1.5E-3 Co-58 2.0E+1 6.6E+7 Co-60 1.7E+3 2.16E+8 I-131 3.9E+3 1.36E+8 Cs-137 6.1E+1 1.86E+8 5E-10 3.17E-8 1.83E-7 1.5E-3 D-23 06/25/91

EXAMPLE 10 WORKSHEET PAGE 3 GRASS-COW-MILK PATHWAY Organ TA ; x+0 3. 17E-8 ink Total Dose.

Radio- or or Sum of D nuclide TG D/Q (mrem)

Total Body H-3 2.0E+8 2.37E+3 lE-7 3.17E-8 1.5E-3 Co-58 2.0E+1 6. 24E+7 Co-60 1.7E+3 2.09E+8 I-131 3.8E+3 1.81E+9 Cs-137 6.1E+1 4.14E+9 5E-7 3.17E-8 4.0E-6 1.5E-3 Skin H-3 2.0E+8 Co-58 2.0E+1 Co-60 1.7E+1 I-131 3.9E+3 Cs-137 6.1E+1 D-24 06/25/91

12. Determining the Noble Gas Monitor Alarm setpoint (Section 3.6)

Standard Technical Specifications require release setpoints to be based on a dose rate. Derivations used to determine setpoints

'z assume that noble gas releases occur at ground level. The noble gas affluent monitor setpoint, based on dose rate is calculated using Equation (26).

.,06 S =

'Fi (26) where:

The alarm setpoint (CPM).

1 '6 Conversion factor; 500 ~mre e 60 sec ~ 35.37 ft3 ~ 1m~

yr min ~m ~10 cm~

Monitor response to activi y concentration oi effluent c m pci/CM'low

',J of gaseous effluent stream past the monitor x/Q atmospheric dispersion factor at the offsite location of interest ~s m3 a factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled by assigning a fraction of the allowable release to each of the release sources.

DF) factor converting ground-level or split-wake release of radionuclide i to the total body dose equivalent rate at he location of potential exposure ~ere .

see Table 3-5.

of radionuclide i in gaseous effluent yr.pci/m'oncentration C;

(pCi/cc) e Bkg monitoring instrument background (cpm).

D-25 06/25/91

Example:

The measured concentration of noble gases to be discharged to the atmosphere are:

Radionuclide g<~Ci~cc Kr-85m 3.6 x 10 ~

Kr-85 2.8 x 10 4 Kr-87 2.5 x 10 Kr-88 1.4 x 10 ~

Xe-131m 1.0 x 10 ~

Xe-133 4.3 .x 10 ~

Xe-135 6.0 x 10 Ar-41 7.7 x 10 ~

Determine the alarm setpoint, S (cpm) when:

3.0 x 10 ~

pci/cm

1. 7 x 104 ft~

min x/Q 5.8 x 10 sec (Note: This is the value at the point of minimum atmospheric dispersion which occurs at 1950 meters SSE of the plant).

Sf = .25 Bkg = 20 cpm D-26 06/25/91

Calculate the effect of a ground level release as follows:

Radionuclide DF C xDF Kr-85m 3 ' x 10 ~

1.17 x 10 4. 2 x 10-2 Kr-85 2.8 x 10 1 61 x 101 4.5 x 10 ~

Kr-87 2.5 x 10 5.92 x 1.5 x 10 ~

10'.47 Kr-88 1.4 x 10 x 10 2.1 x 10 Xe-131m 1.0 x 9.15 x x

'.1 10 10 10'.3 Xe-133 4.3 x 10~ 2.94 x 10~ x 10'.1 Xe-135 6.0 x 10 1.81 x 10 x 10 Ar-41 7.7 x 10 8.85 x 10 6.8 x 10 i ZC) = 5. 4 x 10 EC)DFt = 1.6 x 10 Calculate the setpoint as follows:

3.0 x 10 ~

.25 5.4 x 10 1.7 x 10~ 5.8x10 ~

1.6 x 10~

=I8.06 x 10'] [3.4 x 10 '] + 20

= 294.0 cpm D-27 06/25l91

APPENDIX E RADIOACTIVE EFFLUENT TECHNICAL SPECIFICATIONS

APPENDIX E This Appendix contains all the radioactive effluent technical specifications and specification tables referenced in the Turkey Point Offsite Dose Calculation Manual (ODCM).

E-1 06/25/91

SECTION 1.0 DEFINITIONS E-2 06/25/91

DEFINITIONS FRE UENCY NOTATION 1.12 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GAS DECAY TANK SYSTEM 1.13 A GAS DECAY TANK SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant system off gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or

c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.

ME BER S OF H UB C 1.15 MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, vendors or members of the Armed Forces using property located within the SITE BOUNDARY. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes-not associated with the plant.

OFFSITE DO E CALCULA ION MANUAL 1.16 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Envir.",.:" ~ntal Radiological Monitoring Program.

E-3 06/25/91

DEFINITIONS OPERABLE OPERABILIT 1.17 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when specified function(s), and it when is capable of performing its all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIO AL MODE MODE 1.18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PURGE PURGING 1.22 PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

S BOUNDARY 1.27 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

UNRESTRICTED 1.34 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

E-4 06/25/91

VENTILATION EXHAUST TREATMENT SYSTE 1.35 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.

such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.36 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system 'names, does not imply a VENTING process.

E-5 06/25/91

TAB E .1 FRE U CY NOTATION NOTATION FRE UENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

Completed prior to each release.

E-6 06/25/91

TAB 1. 2 OPERATIONAL MODES REACTIVITY RATED AVERAGE COOLANT MODE CONDITION K ~) THE L OWER* TEMPERATURE

1. POWER OPERATION ) 0.99 5$ 350'F 2 ~ STARTUP 0.99 < 54 350'F

3. HOT STANDBY 0.99 350 F

4. HOT SHUTDOWN 0.99 350'F ) T 200'F

5. COLD SHUTDOWN 0 '9 200'F 6 ~ REFUELING** 0.95 140'F

• Excluding decay heat.

• • Fuel in the reactor vessel with'he vessel head closure bolts less than fully tensioned or with the head removed.

E-7 06/25/91

3 4.11 RADIOACTIVE EFFLUENTS 3 4.11.1 LI UID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microCurie/ml total activity.

APPLICABILITY: At all times.

ACTION With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SUR ILLANCE RE U E N S 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.

E-8 06/25/91

TAB 4.1 0 CT V LI D WAST S SIS PRO LIQUID RELEASE SAMPLING MINIMUM TYPE OF ACTIVITY LOWER LIMIT TYPE 'FREQUENCY ANALYSIS ANALYSIS OF FREQUENCY DETECTION (LLD)

( p Ci/ml )

1. Batch Waste P P Principal ( Gamma 5x10 7 Release Tanks Each Batch Each Batch Emitters I-131 lxlo'.

Dissolved and One Batch/M Entrained Gases (Gamma Emitters) lx10'.

P M H-3 lxlo Batch Composite( ) Gross Alpha 1xlo ~

'ach P Q Sr-89, Sr-90 5xl0 8 Each Batch Composite(4) Fe-55 lxlo Continuous Gamma 5x10 'rincipal Releases Emitters(~)

I-131 lxlo'x10

a. Steam M(8) M(8) Dissolved and 8 Generator Entrained Gases Blowdown (Gamma Emitters)

W(8) M(8) H-3 1xlo Gross Alpha lx10 " 'omposite W(8) Q(8) Sr-89, Sr-90 5x10-8 Composite' Fe-55 1x10

b. Storm Principal Gamma 5x10 "

Drain Emitters'3)

I-131 lxlo

'-9 06/25/91

TABLE 4-1 -1 co ti ued TABL 0 ATIO S (1) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with only 54 probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.

(V) (2.22 X 10~) (y) [EXP(-Xh C) ]

66'E) where:

LLD = the "a priori" lower limit of detection (as @Curie per unit mass or volume).

Sb the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute) .

E the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 10'6 = the number of disintegrations per minute per p Curie, the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide and the elapsed time between the midpoint of sample collection and the time of counting (for plant effluents, not environmental samples).

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and ~t should be used in the calculation.

E-10 06/25/9 1

(2) A batch release is the discharge of liquid wastes of discrete volume. Prior to sampling for analyses, each batcha shall be isolated,and then thoroughly mixed to by a method described in the ODCM to assure representative sampling.

(3) The principal gamma emitters for which the LLD specification exclusively applies are the following radionuclides: Mn-54, FE-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4.

(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscreet volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(7) Sampling and analysis of steam generator blowdown is not required during Mode 5 or 6.

(8) Sampling and analysis of steam generator blowdown on the applicable unit is only necessary for these species when primary to secondary leakage is occurring as indicated by the condenser air ejector monitor. (See Specification 3.3.3.6 in Table 3.3-8, Item 3a).

E-ll 06/25/91

RAD OACTIVE EFFLUENTS DOS LIMITING CONDITION 0 OPE ION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (See Figure 5.1-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

PLICABILIT  : At all times.

ACTION a~ With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE RE 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

E-12 06/25/91

RADIOACTIVE EFFLUENTS LI UID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FO OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (See Figure 5.1-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION: With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1 ~ Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2 ~ Action(s) taken to restore the inoperable equipment to OPERABLE status and 3 ~ Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

S VE L C RE 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be ~onsidered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

E-13 06/25/91

RADIOA EFFLUEN 3 4.11. GASEOUS EFFLU NTS DOSE RATE LIMITING COND TIO OR OPERATIO 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (See Figure 5.1-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and

b. For Iodine-131, for Iodine-133, for tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

AP LICABILI Y: At all times.

~A /ION: With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

S VE LLANC R U N S 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with,the sampling and analysis program specified in Table 4.11-2 ~

E-14 06/25/91

TABLE 4.11-2 RAD OA T VE GASEOUS VASTE SAHPLING AND ANALYSIS PROGRAH HINI HEI TYPE OF LONER LIHIT OF SAHPL ING ANALYSIS ACTIVITY ANALYSIS DETECTIOH (LLD)( )

GASEOUS RELEASE TYPE FREOUENCY FREQUENCY (gci/cc)

1. Gas Decay P P 1x10 Tank (Batch) Each Tank Each Tank Principal Gmllna Emitters Grab S le

2. Contairm>>nt Purge p(6) P Principal Gwlma Emitters 1x10 or Venting (Batch) Grab Sample E ch PURGE( )

H-3 1x10

3. Condenser Air H(6) H(6) Principal Gamsa Emitters 1x10 4 Ejectors Grab Sample Gas Sample H-3 1x10

4. Plant Vent (Includes H(6) H(6) Principal Ganna Emitters 1x10 Unit 4 Spent Fuel Gl'ab S Lc Gas S le Pit Building Vent.)

H(4)i(5) H-3 1x10 Grab S le

5. Uni' Spent fuel H II Principal Gaana Emitters 1x10 Pit Building Gl'ab S Lc Gas S le Vent H(4)g(5) H-3 1x10 Grab S le

6. All Release Types Conti~(3> (T) 1-131 1x10 as Listed in 3., Charcoal S le 4., and 5. above conti~(3> M(7) Principal Gasna Emitters 1x10 Particulate S le Conti~(3> H Gross Alpha Ixio "

Composite S 'articulate le conti~(3> 0 Sr-89, Sr-90 1x10-11 Coopos i te Pal'tICULatc S Lc conti~(3> Noble Gas Noble Gas 1x10 Honitor Gross Beta or Ganlm

T B 411-2 ni TABL TA

<'> The LLD is the sinallest concentration of radioactive material in a sample that willbe detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4. 66 si, E~ V (2. 22x10') ~ Y~ [exp (-A,h C) ]

Where:

LLD = the "a priori" lower limit of detection as defined above as a blank sample (microCurie per unit mass or volume),

s = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency.(counts per disintegration)

V = the sample size (units of mass or volume),

2.22 x 10 = the number of disintegrations per minute per microCurie, Y = the fractional radiochemical yield, when applicable, the radioactive decay constant for the particular radionuclide, and ht = the elapsed time between the midpoint of sample collection and the time of counting (for plant effluents, not environmental samples)

The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on. an unverified theoretically predicted variance. Typical values of E, V, Y, and ht shall be used in the calculation.

E-16 06/25/91

T L 4 -2 ni BLE N TA in

< i The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other gamma peaks that are measurable and indentifiable, together with the above nuclides, shall also be identified and reported pursuant to Specification 6.9.1.4.

Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD for that nuclide. When a radionuclide's calculated LLD is greater than its listed LLD limit, the calculated LLD should be assigned as the activity of the radionuclide; or, the activity of the radionuclide should be calculated using measured ratios with those radionuclides which are routinely identified and measured.

"> The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11,2.1, 3.11.2.2, and 3.11.2.3.

<4~

When a Unit's refueling canal is flooded Tritium grab samples shall be taken on that Unit only from the following respective area(s) at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

For Unit 3 sample the plant vent and the Unit 3 spent fuel pool area ventilation exhaust.

For Unit 4 sample the plant vent only.

<~~

When spent fuel is in the spent fuel pool, tritium grab samples shall be taken from the following respective area at least once per 7 days:

For Unit 3, sample the Unit 3 spent fuel pool area ventilation exhaust For Unit 4, sample the plant vent.

Sampling and analysis shall also be performed following shutdown, startup,'r a THHMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period if (1) analysis shows that the DOSE EQUIVALENTI-131 concentration in the primary coolant has increased by more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.

E-17 06/25/91

E T

< Sample collection media on the applicable Unit shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Sample collection media on the applicable Unit shall also be changed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing if: (1) analysis shows that the DOSE EQUIVALENTI-131 concentration in the primary coolant has increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has increased more than a factor of 3. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

E-18 06/25/91

RADIOACTIV EFFLUENTS DOSE-NOBLE GASES L MITING CONDITION FOR OP RATIO 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see figure 5.1-1) shall be limited to the following:

a ~ During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days pursuant. to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE E I N S 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

E-19 06/25/9 1

RADIOACTIVE EFFLUENTS DOSE - IODINE-131 IODINE-13> TRITIUM AND OACTIVE MATERIAL PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (See Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

ACTION:

a ~ With the calculated dose from the release of Iodine-131, Iodine-133 tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the release and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEI 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

E-20 06/25/91

RADIOACTIV EFFLUENTS GASEOUS W STE T ATMENT E LIMITING CONDITION FOR 0 ERATION 3.11.2 ' The VENTILATION EXHAUST TREATMENT SYSTEM and the GAS DECAY TANK SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

~CT~IO a ~ With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVE RE 4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GAS DECAY TANK SYSTEM shall be considered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

E-21 06/25/91

RADIOACTIVE EF LUENTS 3 4.11.4 TOTA DOSE LIMITING CONDIT ON FOR OPE TION 3.3.1.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY At all times.

ACTION

'a ~ With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limit of specification 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a or 3.11.2.3b, calculations shall be made including direct radiation contributions from the units to determine whether the above limits of Specifications 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the releases(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose(s) exceeds the above limits, and release condition resulting in violation of 40 CFR Part 190 has not if the already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVE 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and the methodology used shall be indicated in the Effluent Release Report. This requirement is applicable Semiannual'adioactive only under conditions set forth in ACTION a. of Specification 3.11.4.

E-22 06/25/91

INSTRUMENT IO DIOACTIV I U D F UENT MO ITORING TR NT T ON IMITING CONDITION FO OPE T ON 3.3.3.5 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-7 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specifications 3.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

~CT ON

'a ~ With a radioactive licpxid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so conservative, it is acceptably

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-7. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.4 why this inoperability was not corrected in a timely manor.

c ~ The provisions of Specifications 3.0.3 are not applicable.

S VE L 4.3.3.5 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-5.

E-23 06/25/91

TABLE 3. 3-7 RADIOACTIVE LI UID EPPLUENT MONITORING INST UMENTATION MINIMUM CHANNELS INSTRUMENT QZEMLBLB Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Line 35

b. Steam Generator Blowdown Effluent Line 36

2. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Line 37

b. Steam Generator Blowdown ] ** 37 Effluent Line steam/generator

• Applicable during liquid effluent releases.

• • Applicable during blowdown operations.

E-24 06/25/91

ACTION 35 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1,.

and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this path-way.

ACTION 36 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross (beta or/gamma) radioactivity at a lower limit of detection of no more than 1 x 10 "

mcurie/ml; or analyzed iaotopically )Gamma) at a limit of detection of at least 5 x 10 @Curie/ml:

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 @Curie/gram DOSE EQUIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 @Curie/gram DOSE EQUIVALENT I-131.

ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

Pump performance. curves may be used to estimate flow.

E-25 06/25/91

4 TABLE 4.3-5 C V U ONI ORING S EN TION SURVEILLANCE RE UIREMENTS ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL

~CH C CHECK CAL BRATION ~EST Gross Radioactivity Monitors Providing Alarm and Automatic Termination of Release R(2)* Q(l)

a. Liquid Radwaste Effluents Line R(2) Q(l)

b. Steam Generator Blowdown Effluent Line

2. i"low Rate Measurement Devices

a. Liquid Radwaste Effluent Line D(3) N.A.

b. Steam Generator Blowdown Effluent Lines D(3) N.A.

• Channel calibration frequency shall be at least once per 18 months.

BE 0 0 S (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measures levels above the Alarm/Trip Setpoint.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm/Trip Setpiont.

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

E-27 06/25/91

I TRUMENTATION DIOACT VE GAS OUS EFFLUENT MONITOR NG E TATION LIMITING CONDITION FO OPERAT 0 3.3.3.6 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.1.2.5 are not exceeded. The Alarm/Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

A~CTIO a ~ With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable or change the setpoint so acceptably conservative, it is

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take ACTION shown in Table 3.3-8. Restore the inoperable instrumentation to OPERABLE status within 30 days and, unsuccessful explain in the next Semiannual Radioactive if Effluent Release Report pursuant to Specification 6.9.1.4 why this inoperability was not corrected in a timely manner.

C~ The provisions of Specifications 3.0.3 are not applicable.

N 4.3.3.6 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECKS, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-6.

E-28 06/25/91

V G OUS F ONITOR G I S RUMENT TION MINIMUM CHANNELS

~OEf~BLE ACTION GAS DECAY TANK SYSTEM

a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release (Plant Vent Monitor) 45

b. Effluent System Flow Rate Measuring Device 46

2. WASTE GAS DISPOSAL SYSTEM (Explosive Gas Monitoring System) 49

a. Hydrogen and Oxygen Monitors

3. CONDENSER AIR EJECTOR VENT SYSTEM

a. Noble Gas Activity Monitor (SPING or PRMS) 47

b. Iodine Sampler 48

c. Par".iculate Sampler 48

d. Effluent System Flow Rate Measuring Device ¹¹ 46

e. Sampler Flow Rate Measuring Device 46 CI Vl

ABL 3 3-8 Continued V G OU UN 0 OR G ION SURV LANCE RE UIR ENTS MINIMUM CHANNELS

~EEAEEE APP IC BILIT ACTION

4. Plant Vent System (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Monitor 47 (SPING or PRMS) 48

b. Iodine Sampler 48

c. Particulate Sampler 46

d. Effluent System Flow Rate Measuring Device 46

e. Sampler Flow Rate Measuring Device

5. Unit 3 Spent Fuel Pit Building Vent 47

a. Noble Gas Activity Monitor 48

b. Iodine Sampler 48

c. Particulate Sampler 46

d. Sar.pier Flow Rate Measuring Device

TAB At all times.

During GAS DECAY TANK SYSTEM operation.

Applies during MODE 1, 2, 3 and 4.

Applies during MODE 1, 2, 3 and 4 when primary to secondary leakage is detected as indicated by condenser air ejector noble gas activity monitor.

ACTION 45- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations,and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 47- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 48- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2 and analyzed at least weekly.

ACTION 49- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the GAS DECAY TANK SYSTEM may continue provided that grab samples are collected and analyzed for hydrogen and oxygen concentration at least a) once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during degassing operations, and b) once per day during other operations.

E-31 06/25/91

U 0 0 G NS RU ENTATION SURVEILLANCE RE UIREMENTS ~

MODES FOR ANALOG WHICH CHANNEL ~ SURVEILLANCE CHANNEL SOURCE CHANNEL OPERATIONAL IS IKXKHKEX ~C ~C CALIBRAT 0 TEST RRIRUIRED

1. GAS DECAY TANK SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release R(3) Q(l)

(Plant Vent Monitor)

N.A. N.A.

b. Effluent System Flow Rate Measuring Device

2. GAS DECAY TANK SYSTEM (Explosive Gas Monitoring System)

a. Hydrogen and Oxygen Monitors N.A. Q(4 5)

3. CONDENSER AIR EJECTOR VENT SYSTEM

a. Noble Gas Activity Monitor (SPING or PRMS) R(3) Q(2)

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. N.A. N.A.

d. Effluent System Flow Rate N.A. N.A. ¹¹ Measuring Device

TABLE 4 3-6 Conti ued V G F U OR G IN EN T ON SURVEILIANCE E UIREMENTS MODES FOR ANALOG WHICH CHANNEL SURVEILLANCE CHANNEL SOURCE CHANNEL OPERATIONAL IS ZEKEKNKK ~E ~CECK CALIBRATION TEST . ~RE UIRED

3. Condenser Air E)ector Vent System (Continued)

e. Sample Flow Rate Measuring N.A. N.A.

Device

4. Plant Vent System (Include Unit 4's Spent Fuel Pool)

a. Noble Gas Activity Monitor (3,6) Q(2)

(SPING or PRMS)

N.A. N.A. N.A.

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. (6) N.A.

d. Effluent System Flow Rate Measuring Device N.A. (6) N.A.

e. Sampler Flow Rate Measuring Device

TABLE 4 3-6 Continued C V 0 0 G T 0 SURVEILIANCE RE UIREMENTS MODES FOR ANALOG WHICH CHANNEL SURVEILLANCE CHANNEL SOURCE CHANNEL OPERATIONAL IS

~C CA IBRA ON TEST //QUIRED

5. Unit 3 Spent Fuel Pit Building Vent R(3) Q(2)

a. Noble Gas Activity Monitor N.A. N.A. N.A.

b. Iodine Sampler N.A. N.A. N.A.

c. Particulate Sampler N.A. N.A.

d. Sampler Flow Rate Measuring Device 0 T 0 At all times.

During GAS DECAY TANK SYSTEM operation.

Applies during MODE 1,2,3 and 4.

Applies during MODE 1,2,3 and 4 when primary to secondary leakage is detected as indicated by condenser air ejector noble gas activity monitor.

(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the instrument indicates measured levels above the Alarm/Trip Setpoint.

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that if the instrument indicates measured levels abov'e the Alarm Setpoint, alarm annunciation occurs in the control room (for PRMS only) and in the computer room (for SPING only).

o (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the V initial calibration shall be used.

TABLE 4.34 (Continued)

BLE OTA ONS onti ued (4) The CHANNEL CALIBRATIONshall include the use of standard gas samples containing a nominal.

a. One volume percent hydrogen, balance nitrogen, and

b. Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATIONshall include the use of standard gas samples containing a nominal:

a. One volume percent oxygen, balance nitrogen, and

b. Four volume percent oxygen, balance nitrogen.

(6) CHANNEL CALIBRATIONfrequency shall be at least once per 18 months.

E-35 06/25/91

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TURKEY POINT OFFSITE DOSE CALCULATION MANUAL BASIS DOCUMENT

1.0 Introduction The operation of a nuclear facility is regulated by requirements contained in the Code of Federal Regulations (CFR's). Section 50.36 of 10CFR50 requires that each nuclear power reactor operating license contain technical specifications that describe limits, operating conditions and other regulatory requirements imposed on the facility operation for protection of the health and safety of the public. At each site, conditions and limitations which are system dependent and site related must be incorporated in the technical specifications. These technical specifications are submitted to the Nuclear Regulatory Commission as part of the licensing process and upon approval are included in Appendix A of the facility operating license.

Technical specifications for a nuclear power plant require the operator to establish alarm and trip setpoints for each liquid and gaseous effluent release point. In addition, these setpoints must be maintained in auditable records and be determined in accordance with an Offsite Dose Calculation Manual (ODCM). The ODCM must also include the methodology and parameters used in the calculation of offsite doses due to radioactive liquid and gaseous effluents.

06/25/91

2.0 Offsite Dose Calculation Manual Methodolo The Nuclear Regulatory Commission has developed calculation methodology which the NRC considers acceptable fordose (NRC) use in the ODCM. .The NRC guides are:

Regulatory Guide 1.109 "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I" (Revision 1),

October 1977.

Regulatory Guide 1.110 "Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors," March 1976.

Regulatory Guide 1.111 "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors" (Revision 1), July 1977.

Regulatory Guide 1.112 "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,"

April 1976.

Regulatory Guide 1.113 "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I" (Revision 1),

April 1977.

The NRC has also developed computer codes which may be used with these guides. The codes are:

NUREG-0017 "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)," April 1976.

NUREG-0324- "XOQDOQ, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," September 1977.

NUREG-0 13 3 Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978.

06/25/91

Conformance with the NRC guidelines for dose calculation methodology is not required. However, if different mathematical models and parameters are used to calculate set points, release rates or dose estimates, the parameters and calculations used shall be substantiated in the ODCM.

The Turkey Point ODCM uses equations and models adopted from the methodology provided in the regulatory guides.

06/25/91

3.0 Definitions The technical specifications contain terms which must be defined in order to clarify limits and the applicability of methodology employed in the ODCM. The terms and their definitions are as follows:

3.1 Fre enc Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in table 3.1.

3.2 Gas Deca Tank S ste A GAS DECAY TANK SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant system off gases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

3.3 Identified Leaka e IDENTIFIED LEAKAGE shall be:

a\ Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or

c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.

3.4 M e s o t e Public MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, vendors or members of the Armed Forces using property located within the SITE BOUNDARY. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

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3.5 Offsite Dose Calculation Manual The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

3.6 0 erable 0 erabilit A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

3 ' 0 erational Mode MODE An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

3;8 re-PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

3.9 te u The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

3.10't i e Area

-An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commerical, institutional,,

and/or recreational purposes.

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3.11 Venti ation Exhaust Treatment S stem A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

3. 12 dentin VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

6 06/25/91

0 TABLE 3. 1 FRE UENCY NOTATION NOTA ION FRE UENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

At least once per 7 days.

At least once per 31 days.

At least once per 92 days.

SA At least once per 184 days.

At least once per 18 months.

S/U Prior to each reactor startup.

NA Not applicable.

Completed prior to each release.

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TABLE 3.

OPERATIONAL ODES REACTIVITY RATED AVERAGE COOLANT MODE CONDITION K ff THERMAL POWER* TEMPERATURE POWER OPERATION > 0.99 > 54 350 F

2. STARTUP 0.99 < 54 350 F

3. HOT STANDBY 0.99 350 F

4. HOT SHUTDOWN 0.99 350F > T, 200 F

5. COLD SHUTDOWN 0.99 200 F

6. REFUELING** < 0.95 140 F

• Excluding decay heat.

• • Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

06/25/91

4.0 Li id Radwaste Releases Liquid radwaste from Turkey Point Nuclear Units 3 and 4 are discharged to the condenser cooling water mixing basin which in turn discharges to a closed cooling loop water canal system. Liquid radwaste releases may be discharged in batches from holding tanks, continuously from steam generator blowdown or through storm drains. Radwaste entering the mixing basin is mixed with and diluted by condenser cooling water from Fossil Units 1 and 2 and Nuclear Units 3 and 4 before being discharged to the canal.

At Turkey Point, all liquid radwaste are sampled and analyzed in accordance with Technical Specification Table 4.11-1. In addition, batch and continuous release are continuously monitored by in-line radiation monitors during release.

Storm drain releases are not continuously monitored.

4.1 Technical Specifications for Liquid Effluents The following Technical Specification requirements must be met when releasing radioactive liquid effluents and the methodology for calculating the specifications must be contained in the ODCM.

4.1.1 Liquid Effluent Concentrations Technical Specification 3.11.1.1 requires that the radioactive concentration of liquid effluents discharged to the U restr'cted A ea be limited to the radionuclide Maximum Permissible Concentrations (MPCs) given in 10CFR20, Appendix B Table II, Column 2 for radionuclides other than dissolved ~ or entrained noble gases. A separate MPC of 2x10 pCi/ml is given for noble gases dissolved or entrained in liquids.

For purposes of implementation at Turkey Point, the Unrestricted Area for liquid effluents begins where the water from the mixing basin enters the cooling canal.

The methodology for satisfying Technical Specification 3.11.1.1 is provided in ODCM equations 1 to 6. In addition to providing the required calculational techniques, some of these equations contain conservative factors to ensure that the requirements of Technical Specification 3.11.1.1 are not exceeded.

06/25/9 1

4.1.1.1 Diluted Radwaste Concentrations Diluted radwaste concentrations are determined using ODCM equation 1:

Cg=C~-

z F~

F2 where:

Czi concentration of radionuclide i water in the condenser cooling water in the mixing basin outflow, (pCi/ml).

C<

= concentration of radionuclide radwaste released, (pCi/ml).

i in liquid F~/Fq = dilution.

F> = flow in radioactive liquid discharge line (gal/min).*

total condenser cooling water flow,"

(gal/min).* Value not greater than the rated total condenser cooling water flow from operating condenser cooling water pumps at the four units.

• F> and F> may have any suitable but identical units of flow, (volume/time).

This equation is a simplification of the completely mixed model given in Regulatory Guide 1.113 for impoundments. As used at Turkey Point this equation provides conservative estimates of diluted radionuclide concentrations because:

The volume of the mixing basin and the canal are not included in the total volume.

The effects of radioactive decay are ignored.

10 06/25/91

A I 1

In practice, the equation is used in the following way:

To make pre-release estimates. These estimates are made using condenser cooling water flows from the nuclear units only as total flow (F>)

because cooling water flow for the fossil units is regulated by the Fossil Plant control room and may change during the period of release.

To make post release estimates. These estimates are made using cooling water from both the fossil and the nuclear units as total .

flow '(F>). In general, post release estimates are less than or equal to pre-release estimates.

In addition to radioactive decay, ODCM equation 1 also ignores the rate of buildup of long-lived isotopes. Regulatory Guide 1.113 expresses this rate as:

W C

where:

C, = steady state concentration . of non-decaying substances.

w = the rate of addition of radioactivity q = pond blowdown or volume removal factor-Because of the closed nature of the cooling canal at Turkey Point, the only loss or removal factor (q ) is evaporation which effects only volatile radionuclides and since, except for seasonal variations, the volume in the cooling canal remains relatively constant the rate of buildup maybe expressed as:

CO = w In other words the rate of buildup is equivalent to the steady state .'encentration at any point in time.

06/25/91

4. 1. 1. 2 Maximum permissible Concentrations (MpCs)

Liquid radwaste activity release concentrations are determined by using ODCM equations 2 to 6.

Equations 2, 3, 4 or 5 provide methods for determining the fractions of the MPC in batch or continuous releases. Equation 6 provides a means of totalling the fractional MPCs from all releases.

Equations 2, 3, 4 and 5 are simple fractional equations which compare the measured released concentrations of radionuclides in effluents to the limit or MPC. For conservatism, the resulting fraction is further divided by an adjustment factor to account for radionuclides released but not measured prior to release. Since these equations are simple ratios, they are not directly related to or derived from the modeling equations used in the Regulatory Guides.

4.1.1.2.1 ODCM Equations 2 and 4 These two equations use the diluted nuclide concentration (C,<) from ODCM equation 1 and MPC values for individual nuclides, i from 10CFR20, Appendix B, Table IZ, Column 2 (MPC<)

to determine the fraction of MPC for individual nuclides (FMPC) present in the cooling water mixing basin as a result of batch (FMPC~) and/or continuous releases (FMPC,). The equation(s) are:

<sX

~ MPC (2/4) b(c) where:

FMPC~( ) the fraction of the unrestricted area MPC present in the condenser cooling water mixing basin outflow due to batch (b) or continuous (c) releases.

Czi the concentration of a radionuclide, i, in the conde-='"'ooling water mixing basin outflow.

12 06/25/91

limit activity MPC< the concentration in water of radionuclide i according to 10CFR20 Appendix B Table ZI, Column 2 (pCi/ml)

Quarterly average of FMPC in the batch tank (b) or continuous release (c) due to I-131 and principal gamma b<c) emitters.

Quarterly average of FMPC in the batch tank (b) or continuous release (c) due to all radionuclides measured.

The term E <,> is an adjustment to account for radionuclicYes such as Sr-89, Sr-90, Fe-55 etc.

which are not measured prior to release but are measured in quarterly samples per Technical Specification Table 4.11-1. The value of Eb,> is calculated from previously measured dna. Zf calculated data is not available, historical values may be used.

Historical data quarterly analysis have established a value for Eb< of about 0.8. To ensure conservatism an8 to allow for occasional concentrations which exceed the historical value, a value of 0.5 can be used as an alternative for Eb<,>.

Alternatively, the Eb<,> factor can be eliminated by including a previous Quarter's beta activity and MPC values into the calculations for each release. The addition of these values corrects for unmeasured activity making the Eb<c) factor redundant and not required.

4.1.1.2.2 ODCM Equations 3 and 5 These two equations are an alternate means of determining the fraction of MPC for a batch (b) or (c) continuous release., The equation(s).are:

13 06/25/91

~blc)

~PCir(~) (3/5) 3x10 8 where:

~b(c) g c 3 x108 the unrestricted area MPC for unidentified radionuclides in water from 10CFR20 Appendix B Table II.

Equation 3/5 differs from equation 2/4 as follows:

A gross value for radionuclides in water of 3 x 10 ~ pCi/ml is used instead of MPC values for individual radionuclides (i).

The diluted concentrations (C <) of individual radionuclides are summed to produce a gross activity value.

There is no adjustment for radionuclides not measured prior to release but measured in the monthly and quarterly samples.

As a result, the alternate equations 3/5 will generally yield fractional MPC values that are less conservative than equations 2/4.

4.1.1.2.3 ODCM Equation 6 This equation is used to sum all of the fractional MPC's to provide a cumulative total from all release paths, since simultaneous liquid radwaste releases may be occurring from several sources. This equation accounts for simultaneous releases from:

Batch tanks.

Continuous releases from Units 3 and 4.

14 06/25/9 1

The equation does not account for releases from storm drains although this release pathway may be considered a batch release and its contribution determined from monthly sample results.

4.1.2 Dose to a Member of the Public Technical Specification 3.11.1.2 requires that the dose or dose commitment to a ember of the Publ'c from radioactive materials in liquid effluents released from each unit to Unrestr'cted Areas shall be limited to:

During any calendar quarter 1.5 mrems to the whole body

< 5.0 mrems to any organ During any calendar year

< 3.0 mrems to the whole body

< 10.0 mrems to any organ The methodology for satisfying Technical Specification 3.11.1.2 is provided in ODCM equation 7. This equation considers only irradiation from shoreline as a dose factor at Turkey Point because of the nature of the cooling canal and restrictions on access to the site. At Turkey Point, both the condenser cooling water mixing basin and the closed loop cooling canal system are located entirely on FP&L property. Cooling water leaving the plant circulates through the canal system and returns to the plant cooling water inlet without offsite discharge. Since FP&L limits access to the canal and does not permit members of the public to use the water for drinking, bathing, gardening or any other purpose determination of dose is simplified. Dose factors that are important at other sites such as use of the water for drinking and gardens; the consumption of fish and shellfish etc. may be ignored at Turkey Point. Public access is limited by FP&L to occasional use of areas near the canal for camping by scout troops. As a result, the

,potential exposure of a member of the public to

.,radioactive material in liquid effluent is limited to

.'irradiation of campers by canal shoreline deposits.

15 06/25/9 1

The equation used in the ODCM is:

Cik'Flk'Ck 0 23 gk gi +shoreline .

VA i (7) where:

D total body or organ dose due to irradiation by radionuclides on the shorelines which originated in a liquid effluent release, (mrem) 0.23 units conversion constant =

1' 60 min x 3785 ~1 10~pCq hr gal A, transfer factor relating a unit aqueous concentration of radionuclide commitment rate to specific organs and the i (pCi) to dose total body of an exposed person (mrem/Ci gal/min)

CIR the concentration of radionuclide in the undiluted liquid waste to be discharged that is represented by sample k, (pCi/ml)

F>k

= liquid waste discharge flow during release represented by sample k, (gal/min)

V = cooling canal effective volume, approximately 3.75 x 10~ gallons tk = period of time (hours) during which liquid waste represented by sample k is discharged effective decay constant (A,< + FpV, min ')

where:

the radioactive decay constant F> = canal-ground water interchange flow, approximately 2.25 x 10 gal/min This equation is an adaptation of the shoreline dose equation in NUREG 1.109. This equation determines dose by combining the summed quantities of individual radionuclides i for three discrete terms.

16 06/25/91

The term A,. referred to as a transfer factor is a site related ingestion dose commitment factor to the total body or any organ for each identified principal gamma and beta emitter. The term A~ is an adaptation of ingestion dose data contained in Regulatory Guide 1.109 Appendix B.

The other terms are related to specific site and radionuclide criteria for a given release of liquid effluent. In practice at Turkey Point only the dose to the whole body is determined because if this dose is within specification, organ dose will be below its limit.

4.1.3 Projected Dose Technical Specification 4.11.1.2 requires that cumulative dose contributions from liquid effluents for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

In addition, Technical Specification 3.11.1.3 requires that the Liquid Radwaste Treatment system shall be

~O arable and appropriate portions of the system shall be used to reduce releases of radioactivity when the to the Unrestricted areas would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ when averaged over a 31 day period.

Technical Specification 4.11.1.3.1 rat@liras that ~oses due to liquid releases om each unit to U rest 'cted Areas shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the Liquid Radwaste Treatment Systems are not being fully utilized.

At Turkey Point, the Technical Specification requirements are satisfied with ODCM equation 8. The dose is projected with the relation:

P = 31'D X

(8) where:

p the projected total body or organ dose during the month, (mrem) 31 number of days in a calendar month, (days) number of days in current month to date represented by available radioactive effluent sample, (days) 17 06/25/91

D = total body or organ dose to date during current month calculated according to ODCM dose equations, (mrem)

Alternately, the monthly dose may be projected by computing the doses to the total body and most exposed organ accumulated during the most recent month and assuming the result represents the projected doses for the current month.

This equation is a simplification of dose projection equations described in Regulatory Guide 1.109 and NUREG-0133.

4.1.4 Effluent Monitor Setpoints Technical Specification 3.3.3.5 requires that liquid effluent monitoring instrumentation channels be ~0 arable with their alarm/trip setpoints set to ensure that the limits of specifications 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

The requirements of this Technical Specification are met by using ODCM equations 9 and 10. These equations are:

A~ S~

S~ = 'gg, + Bkg (9)

FMPC~

Ac S (10) where:

Sb] radiation monitor alarm setpoint for a batch release (b)/continuous release (c) (cpm)

Nzc laboratory counting rate (cpm/ml) or activity concentration (pi/ml) of sample from batch tank (b)/continuous release (c)

FMPCbl = fraction of unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a batch release (b)/continuous release (c) 18 06/25/91

gbic detection efficiency of monitor detector; ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch sample (cpm/cpm/ml or cpm/pCi/ml) which ever units are consistent with the units ~A, Bkg = background (cpm)

S) A factor to allow for multiple sources from different or common release points. The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

The setpoint equation(s) used at Turkey Point are derived from setpoint determinations provided in NUREG-0133 Addendum. The general equation has been altered to include a safety factor. This factor was added because there is a possibility of continuous releases from Units 3 and 4 occurring at the same time as a batch release.

If this event occurs, the limits of Technical Specification 3.11.1.1 could be exceeded if the safety factor were not included.

19 06/25/9 1

5.0 Gaseous Radwaste Releases Gaseous radwaste releases from Turkey Point Nuclear Units 3 and 4 are discharged from four monitored .release points.

These release points are:

~

A common plant vent

~

Unit 3 spent fuel pit vent

~

Unit 3 and 4 air ejector vents In'ddition, unmonitored gaseous releases occur from six release points in the Unit 3 and Unit 4 secondary system.

These release points are:

~

Blowdown flash tanks (2)

~

Hogging jet exhausts (2)

~

Water box priming jets (2)

Releases from the unmonitored points can result in discharges of radioactive gases if primary to secondary leakage occurs.

For calculational purposes, airborne releases from all discharge points are treated as a mixed mode, ground level release from a single location. The equations used for calculating gaseous release rates, atmospheric dispersion, dose rates and radiation monitor setpoints are adapted from models and equations given in regulatory guides and NUREG's.

The principal references used in the Turkey Point ODCM for radioactive gaseous releases are Regulatory Guides 1.109 and 1.111 and NUREG-0133.

The standard technique is to use Turkey Point meteorological data from daily measurements and/or historical data with models from the regulatory guide to provide atmospheric dispersion factors for the plant. These dispersion factors are determined in 16 compass directions from the plant release point to locations within, at and beyond the site boundary.

Because there are physical and chemical differences between the noble gases, radioiodines, tritium and particulates being released and dispersed in gaseous effluents, there are three dispersion factors which must be determined, these are referred to as:

The atmospheric dispersion factor (X/Q)

The atmospheric dispersion factor adjusted for depletion by deposition (ggQ)

The relative deposition rate onto ground (D/Q) 5.1 Technical Specifications for Gaseous Effluents The following Technical Specification requirements must be met when releasing radioactive gases and the 20 06/25/91

methodology for calculating releases must be contained in the ODCM.

5.1.1 Gaseous Effluent Dose Rates Technical Specification 3.11.2.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

~

Noble Gases 500 mrem/yr to the whole body 3000 mrem/yr to the skin I-131, I-133, Tritium and Particulates with half lifes greater than 8 days.

1500 mrems/yr to any organ The requirements of the specification reflect the differences between the behavior of noble gases as opposed to radioiodines, tritium and particulates. As a result of these differences, several equations are required in the ODCM to estimate the quantities of radionuclides released and the dose rate. The methodology for satisfying Technical Specification 3.11.2.1 is provided in ODCM equations 11 to 15.

5.1.1.1 Noble Gas Activity Release Quantities The total measured quantity of noble gas activity released via a stack or vent during a specific time period can be determined using the appropriate gaseous effluent monitor, data as follows:

N F 0 ~'h (11) 3.53x10 Qj 'otal where:

measured gross gaseous radioactivity release via a stack or vent during counting interval j, (pCi)

N>

= counts accumulated during counting interval j, (counts = N(cpm) x t(min))

21 06/25/91

F = discharge rate of gaseous effluent t

stream, (f /min) 3.53 X 10 conversion constant, ( ft~/cm~)

effluent noble gas monitor calibration or counting rate response )for noble gas gamma radiation, ( ~cm I pCi/cm The distribution of radioactive noble gases in a gaseous effluent stream is determined by gamma spectrum analysis of gas samples from that stream.

Results of previous analyses may be averaged to obtain a representative distribution.

If f< represents the fractionbasedof radionuclide a given effluent stream, on the isotopic i in distribution of that stream, then the quantity of radionuclide i released in a given gaseous effluent stream during counting interval j is:

Q);=Q; where:

Q)j quantity of radionuclide i released in a given gaseous effluent stream during.

counting interval j, (pCi) f~ = the fraction of radionuclide in a given effluent stream i released Equation ll is an which converts the efficiency correction equation relative counts of a radiation monitor to an absolute release activity using the known monitor efficiency to make the conversion.

If a gamma spectrum analysis is available for the noble gases in a release, the relative ratios of

'he gases in the spectrum may be used to convert the gross activity, Qj from equation 11 to specific radionuclide (i) activity as shown in equation 12.

If a gamma spectrum is not available, historical noble gas activities may be averaged to produce release fractions for noble gases. These release fractions from historical Turkey Point noble gas data are given i'n ODCM Table 3-2.

22 06/25/91

5.1.1.2 Noble Gas Total Body Dose Rate The total body dose rate due to noble gas releases is determined using the following equation:

(13) where:

D,8 = Dose rate to total body from noble gases, (mrem/year) atmospheric dispersion factor at the off-site location of interest, (sec/m~)

t = averaging time increment of time of release, during which i.e.,

Q< was released, (year)

Q<

= quantity of noble released during the gas radionuclide averaging time, (pCi) i P factor converting time integrated concentration of noble gas radionuclide at ground-level to total body dose, i

p,Ci sec/m Equation 13 is an adaptation of the total body dose rate equations from Regulatory Guide 1.109. The atmospheric dispersion factor(s) g/Q were developed from Turkey Point Meteorological data collected during calendar years 1976 and 1977 and atmospheric models from Regulatory Guide 1.111. The air dose transfer factor P is derived from Regulatory Guide 1.109 Table B-1. Factors required for Turkey Point calculations are contained .in ODCM tables. The factor(s) g/Q is contained in ODCM Table 3-6 and the factor(s) Py< ln ODCM Table 3 4.

This equation assumes that the person subjected to the dose rate from noble gases is immersed in a semi-infinite cloud of the gases, which infers immersion in gases that are totally mixed and present at some uniform concentration. The limiting case for total body dose rates at or beyond the site boundary is the location at the 23 06/25/91

W f f

,1

site boundary where the highest concentration of radioactive noble gases occurs. This location will be the point or quadrant where X/Q data indicate that atmospheric dispersion is at a minimum.

Present data indicate that minimum dispersion occurs at, the site boundary 1950 meters SSE of the plant where X/Q is equal to a value of 5.8 x 10 sec/m~. This value will be used in equation 13 to determine total body dose rates from noble gases unless subsequent X/Q data indicate that the minimum dispersion value and/or location at the site boundary has changed.

5.1.1.3 Noble Gas Skin Dose Rate The skin dose rate due to noble gas releases is determined using the following equation:

(14) where:

D S

dose rate to skin from radioactive noble gases, (mrem/year) factor converting time integrated concentration of noble gas radionuclide at ground level, to'kin dose from beta i

radiation,

~

mrem pCi sec/m

~

)

1.11 = ratio of tissue dose equivalent to air dose in a radiation field, (mrem/mrad)

A, factor for converting time integrated Y

concentration of noble gas radionuclide i in a semi-infinite cloud, to air dose from its gamma radiation, re p,Ci sec/m Equation 14 is an adaptation of the skin dose rate equations from Regulatory Guide 1.109. This equation also uses historical X/Q values from ODCM Table 3-6. The air dose transfer factor A and S>

for gamma and beta doses respectively are derivei <

from Regulatory Guide 1.109 Table B-1. The factor(s) A is contained i,q.ODCM Table 3-3 and the factor S>~ in ODCM Table 3-4.

24 06/25/91

This equation also assumes a person immersed in a semi-infinite cloud of noble gases boundary where minimum atmospheric

't the site dispersion occurs. As in equation 13, this location is 1950 meters SSE of the plant where y/Q is equal to a value of 5.8 x 10 ~ sec/m .

5.1.1.4 Tritium, I-131, I-133 and Particulate Dose Rate The dose rate due to tritium, I-131, I-133 and particulates with a half-life greater than 8 days released in gaseous effluents is determined with the following equation:

1, g 36 00 g Xd zk 4llfP (15) where:

D, = dose equivalent rate to body organ n of 'a person in age group a expos'ed via pathway

p. (mrem/year) 3600 = conversion constant, (sec/hr) t = period of time over which the effluent releases are averaged, (hr) atmospheric dispersion factor, adjusted for depletion by deposition (sec/m~).

(Alternatively X/Q, unadjusted, may be used).

Q<z

= quantity of radionuclide t i during time increment based on analysis released k, (pCi) .

TA)= a factor relating the airborne concentration time integral of radionuclide organ n i to the dose equivalent to of a person in age group a exposed via pathway p, m em r pCi/m Equation 15 is an adaptation of equations for radioiodines and other radionuclides discharged to the atmospheric contained in regulatory guide 1.109. This equation uses historic",1 g+Q values which are given in ODCM Table 3-7 and are derived 25 06/25/9 1

from Turkey Point historical meteorological data and the atmospheric models contained in Regulatory Guide 1.111. The dose transfer factor TA < is based on dose transfer factors given in Reguia(ory Guide 1.109 appendix E. These dose transfer factors are given for total body and organ doses to four categories of individuals, these are:

Adult Teenager Child Infant The doses to these individuals are expected to occur via two pathways, these are:

Inhalation Ingestion Pathway-dose transfer factors for Turkey Point are given in the ODCM Appendix A.

To ensure compliance with Technical Specification 3.11.2.1, a hypothetical infant located at the site boundary where the minimum atmospheric dispersion occurs is assumed as the receptor. This approach assures the most conservative estimate of dose.

When this assumption is used, the infant's thyroid via the inhalation pathway is the critical organ and controlling pathway respectively. When estimating dose for radioiodines and particulates with half-lifes greater than 8 days, the dose transfer factor, TA,<, is based solely on the radioiodines (I-131, I-133) because the radioiodines contribute essentially all of the dose to the infant's thyroid.

The limiting case for the dose rate due to iodine, tritium and particulates at or bey'ond the site boundary is the location at the site boundary where there is minimum dispersion ad)usted for deposition. Present data from ODCM Table 3-7 indicate that minimum dispersion adjusted for deposition, Xgg, occurs at the site boundary 1950 meters SSE of the plant where the XQQ value is 5.0 x 10 sec/m .

5.1.2 Gaseous Effluent Dose From Noble Gases Technical Specification 3.11.2.2 requires that the ~r.

ose eacto at and beyond the site boundary',~ue to noble gases in gaseous effluents shall be limited to:

26 06/25/91

During any calendar quarter

< 5 mrad for gamma radiation

< 10 mrad for beta radiation During any calendar year 10 mrad for gamma radiation 20 mrad for beta radiation In addition, Technical Specification 4.11.2.2 requires that the cumulative gamma and beta radiation dose be determined at least once per 31 days to verify that accumulated air dose due to gamma radiation and beta radiation does not exceed the limits for the current quarter and year.

5.1.2.1 Noble Gas Gamma Radiation Dose The gamma radiation dose is calculated with the following equation:

Qy 1 o + +~ o g (16) where:

D noble gas gamma dose to air due to a mixed mode release, (mrad) 0.8 a conservatism factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution atmospheric dispersion factor for a mixed mode discharge, (sec/m~)

yeff effective gamma air dose time-integrated, ground-level,factor'onverting total activity concentration of radioactive noble gas, to air dose due to gamma radiation. This factor has been derived from noble gas radionuclide distributions in routine operational releases. The effective gamma air dose factor is:

d A~)) = 1.4 x 10 ( pCi sec/m 27 06/25/9 1

the measured gaseous radioactivity released via a stack or vent. during a single counting interval j, (pCi)

Equation 16 is derived from dose equations for noble gas gamma activity in Regulatory Guide 1.109.

The measured gross activity value, Q. is determined using ODCM equation 11. The atmospheric dispersion factor X/Q was developed from Turkey Point historical meteorological data using Regulatory Guide 1.111. Turkey Point X/Q data are given in ODCM Table 3-6. The conservatism value, 0.8, is based on Turkey Point historical noble gas data.

This historical variability has been observed in both liquid and gas samples. In the case of liquids, the conservatism value was further reduced to 0.5 because of higher uncertainty of mixing in the liquids. The effective gamma air dose factor, A,<<, is based on historical Turkey Point noble gas data collected during the years 1978, 1979 and 1980. The technical basis for A~~ff is described in the ODCM Appendix B.

The limiting case for gamma dose from noble gases occurs at the location on the site boundary where minimum atmospheric dispersion, g/Q, occurs. At Turkey Point, this location is at the site boundary 1950 meters SSE of the plant where the X/Q value is 5.8 x 10 ~ sec/m~.

5.1.2.2 Noble Gas Beta Radiation Dose The beta radiation dose. is calculated with the following equation:

DP =

8 Q

~Pere'18) where:

D>

= noble gas beta dose to air due to a mixed mode release, (mrad) 0.8 = a conservatism factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution .

28 06/25/91

Ap )) effective beta air dose factor converting time-integrated, ground-level, total activity concentration of radioactive noble gas to air dose due to beta radiation. This factor has been derived

~

from noble gas radionuclide distributions in routine operational releases.

The effective beta air dose factor is:

Ap )] = 3.4 x 10 -5 mrad

-.r. I This equation is identical in format to equation 16, except. the effective beta air dose factor has been substituted for A,<< to determine noble A>,<< gas beta dose. The technical Basis for the term A>,ff is described in the ODCM Appendix B. Beta doses are also calculated for the location on the site boundary where minimum dispersion occurs, this location is 1950 meters SSE of the plant where g/Q equals 5.8 x 10 sec/m .

5.1.2.3 Alternate Noble Gas Radiation Dose Calculations The gamma and beta radiation doses from noble gases may also be calculated using the following equations:

(17 )

Dp = + . gg'f'g'Apg (1S) 0 where:

f< = the fraction of radionuclide in a given effluent stream i released A I factor converting time integrated, ground level concentration of noble gas radionuclide i to air dose from gamma radiation, m pCi sec/m )

29 06/25/91

Ap( factor converting time-integrated, ground level concentration of noble gas radionuclide i to air dose from beta radiation,

~

~

mrad

~

)

The difference between these equations and equations 16 and 18 is that A 'and A>jeff are calculated (A~ f~) for each analysis,yeffas descry.rfed in ODCM Appendix B. Since the factors are determined on each set. of analysis data, the conservatism factor, 0.8 is not included in the equations because variability in the radionuclide distribution is reflected in sample analysis data.

5.1.2.4 Cumulative Noble Gas Gamma and Beta Radiation Dose Determinations The cumulative gamma and beta radiation dose determinations required by Technical Specification 4.11.2.2 is satisfied by summing all the noble gas analysis performed on samples taken during releases using equations 16 or 17 and 18 or 19.

5.1.3 Gaseous Effluent Dose From Iodine, Tritium and Particulates Technical Specification 3.11.2.3 requires that the dose to a member of the public from I-131, I-133, tritium and all radionuclides in particulate form with half-lifes each unit to areas at and beyond the Site Boundary shall be limited to:

During any calendar quarter

< 7.5 mrems to any organ and During any calendar year

< 15 mrems to any organ In addition, Technical Specification 4.11.2.3 requires that cumulative dose contributions during the current calendar quarter and current calendar year be determined at least once per 31 days.

5.1.3.1 Iodine, Tritium and Particulate Activity Release {}uantities 30 06/25/91

The quantity of iodine, tritium and particulate activity released in gaseous effluents is determined with the following equation:

Qi~ = ci~'Q F~'dl, tp (20) where:

the quantity of radionuclide i released in a given effluent stream based on analysis k, (pCi)

Cik concentration of radionuclide i in a gaseous effluent identified by analysis k, (pCi/cc)

F,. = effluent stream discharge rate during time increment ht>, (cc/sec) htJ = time radionuclide increment i j during which at concentration C<z is being discharged, (sec) .

Equation 20 is an integration equation used to determine the total activity entering the atmosphere at a known flow for a measured period of time. The term C<z is the concentration values from sampling and analysis performed in accordance with Technical Specification Table 4.11-2 using weekly, monthly and/or quarterly analysis results. The value of C<< may have to be adjusted, changing the value of Q<z under certain circumstances. During normal operations, gaseous releases from stacks and vents require no adjustment of the term C<>.

However, if primary to secondary leakage xs occurring radioactivity will be released to the atmosphere via gaseous releases from the secondary system. Under these circumstances C) is determined by sampling steam generator blowdown and assuming that 54 of the I-131 and I-133 and 334 of the tritium in the blowdown stream becomes airborne with the remainder staying in the liquid phase.

This assumption has been validated during historical measurements of the blowdown liquid and steam phases.

31 06/25/91

For other unmonitored releases, the quantity of airborne releases may be determined by performing a steam mass balance using the following equation:

>c+>s (21) where:

the measured mass of makeup water entering the secondary system during time interval ~tj. e.g. steam generator shutdown.

ML the measured mass of water discharged from the secondary system as liquid during time interval a,tj. e.g. steam generator blowdown.

MS the measured mass of steam or non-condensible gases discharged from the secondary system during time. interval a,tj. e.g. air ejector discharge.

Equation 21 is a simple balance equation comparing input to losses. This equation assumes that when the water injected into the secondary system as makeup (M) is equal to the rate of known discharges of steam and gases (M ) and liquid (M,) that the discharge from the secondary system (F>) will be zero. When F> is a value greater than zero, assumed that the release rate is due to other it is unmonitored releases. For purposes of determining doses due to iodine, tritium and particulates it is further assumed that these other releases are as steam and their concentrations are the same as their concentrations in steam (C<z) generator blowdown samples. This assumption is valid because of the large temperature and pressure differences between the operating secondary system and the ambient environment. Equation 20 is a great simplification of the complex mass balance equations in NUREG 1.109.

5.1.3.2 Determining Dose Due to Zodine, Tritium and Particulate Gaseous Releases Doses from iodine, tritium and particulates discharged in gaseous effluents can result in exposure to a person by several pathways. These pathways are:

32 06/25/91

Direct radiation from airborne radionuclides except noble gases Inhalation Direct radiation from ground plane deposition Fruits and vegetables Air-grass-cow-meat Air-grass-cow milk Research, field studies and modeling indicate that of all these pathways, the air-grass-cow-milk pathway is by far the dominant and controlling dose factor. This occurs because:

The dose factors for the radioiodines are much greater than dose factors for any of the other radionuclides The radioiodines contribute essentially all of dose by this pathway with I-131 typically contributing greater than 954.

Since the air-grass-cow-milk pathway is the controlling pathway and radioiodine the controlling activity, the critical organ is the thyroid. To produce the most conservative result, doses are determined using effective dose transfer factors for radioiodine via the air-grass-cow-milk pathway and the infant thyroid as the receptor. An additional degree of conservatism is provided by totalling the cumulative release of all radio'odines and articulates with the radioiodine effective dose transfer factor to estimate infant thyroid dose.

Doses due to iodines and particulates are determined with the following equation:

DM = 3. 17x20, D,>G .V (22) 0 8 g 131 + dk where:

DM~ the dose commitment to an infant's thyroid received from exposure via the air-grass-cow-milk pathway and attributable to iodines identified in analysis k of effluent air, (mrem) 33 06/25/91

3.17 x 10 = conversion constant, (yr/sec) 0 ' a conservatism factor which, in effect, increases the estimated dose to compensate for variability in the radionuclide distribution D/Q = relative deposition rate onto ground from a mixed mode atmospheric release (m ~)

TG,z,= factor converting ground deposition of radioiodines to the dose commitment to an infant's thyroid exposed via the grass-cow-milk pathway.

TG,q, = 6.5 x 10 mrem r pci/m .sec the quantity of radionuclide I-133) released in a given effluent i (I-131 and stream based on a single analysis k, (p,Ci)

Equation 22 is adapted from radioiodine dose equations in Regulatory Guide 1.109. The conservatism factor, 0.8, is derived from historical radionuclide distributions observed in gas samples. The relative deposition rate onto ground D/Q is derived from Turkey Point historical meteorological data collected during calendar years 1976 and 1977 and atmospheric models from Regulatory Guide 1.111. The effective dose transfer factor for the air-grass-cow-milk-infant-thyroid pathway, TG,>i, is based on historical data collected in 1978, 1979, and 1980. The technical basis for TG>zi is given in the ODCM Appendix B. The quantity of radionuclide i released in a given effluent stream (Q<<) is determined using ODCM equation 20.

The specifications for determining dose via the air-grass-cow-milk pathway given in NUREG-0133 states that the cow should be within 5 miles of the release point. At Turkey Point, there are no milk cows within 5 miles of the plant release point.

Under these circumstances, NUREG-0133 states that a cow may be assumed between 4.5-5.0 miles in the worst sector. For the Turkey Point plant, the worst sector is the populated area due west of th' plant. As a result, dose due to iodine, tritium, and particulates is determined for a phantom cow on pasture 4.5 miles west of the plant where the 34 06/25/91

relative deposition rate onto the ground D/Q is 5.0x10 m 5.1.3.3 Alternate Methods of Determining Dose Due to Airborne Iodines, Tritium and Particulates In addition to determining dose due to the dominant air-grass-cow-milk pathway, the ODCM provides equations for evaluating dose via other pathways.

These equations are based on examples described in Regulatory Guide 1.109 and NUREG-0133. Equations are provided to evaluate the following dose pathways:

Inhalation and irradiation dose due to airborne concentrations of radioactive material other than noble gas. ODCM equation 23.

Deposition from the atmosphere onto vegetation or the ground. ODCM equation

24. Deposition is from airborne concentrations of radioactive material other than noble gas.

Dose from airborne tritium via vegetation, air-grass-cow-milk or air-grass-cow-meat. ODCM equation 25.

Cumulative dose via a given pathway as a result of measured discharges from a release point. ODCM equation 26.

These alternate equations may be used to satisfy the requirements of Technical Specification 3 '1.2.3.

Except for the cumulative dose equation (26), all of the dose equations share a common format as illustrated by equation 23:

D~ = 3.17x10 ' Xd

~

'gj, '

P TA~gp (23) 35 06/25/91

where:

ank the dose commitment to organ n of a person in age group a due to radionuclides identified in analysis k of an air effluent, (mrem) 3.17 x 10 conversion constant, (yr/sec)

X+Q = atmospheric dispersion factor adjusted for depletion by deposition, (sec/m~)

the quantity of radionuclide i released in a given effluent stream based on analysis k, (pCi)

All of the equations are used to determine a dose (D) to an organ (n) of a person in a particular age group (a) identified in an analysis (k) of an effluent air sample. Although no specific age group '(a) or organ (n) is identified in the equation, the most restrictive case is'he infant for any organ. As a result the infant will be selected for purposes of making conservative dose estimates.

All of the equations use an atmospheric dispersion factor (g/Q, XQQ or D/Q) . These factors have been determined using historical Turkey Point meteorological data and models from Regulatory Guide 1.111. The factors for sixteen compass sectors around the Turkey Point plant are given in the ODCM Tables 3-6 (X/Q), 3-7(g+Q) and 3-8 (D/Q).

Each of the pathways uses a unique location to evaluate dose to a person, these are:

The inhalation and irradiation and tritium pathways evaluate dose at the nearest garden (with residence assumed) which is 3.6 miles west of the plant where the X+Q factor (for inhalation and irradiation) is 1 x 10 sec/m3 and the X/Q factor (tritium) is also 1 x 10 sec/m'.

The deposition from the atmosphere onto vegetation or the ground pathway evaluates dose at the phantom cow location 4.5 mil~s west, of the plant where the D/Q value is 5.0 x 10' 36 06/25/91

To determine conformance with Technical Specification 3.11.2.3, a cumulative dose calculation is made using the following equation:

=Z >~ (26) where:

D, = the dose commitment to organ n of a person in age group (a) k = the counting either:

index; it may represent p, analysis of a grab sample w, a weekly sample analysis m, a monthly composite analysis, or q, a quarterly composite analysis 5.1.4 Projected Dose Technical Specification 3.11.2.4 requires that the ventilation exhaust treatment system and gas decay tank system shall be operable and appropriate portions of these systems shall be used to reduce releases of radioactivity when the o'ected doses i 31 da s due to gaseous effluent releases, From each unit, to areas at 0.2 mrad to air from gamma radiation or 0.4 mrad to air from beta radiation or 0.3 mrad to any organ of a Member of the Public ses o e c u 'o Technical Specification 4.11.2.4 further states that areas at and beyond the site boundary shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.

At Turkey Point, these Technical Specifications requirements are satisfied with ODCM cmation 29 as follows:

37 06/25/91

P = 3'1 X

'D (30) where:

the projected dose during the month, (mrem) 31 number of days in a calendar month, (days) number of days in current ,month to date represented by available radioactive effluent sample, (days)

D dose to date during current month calculated according to ODCM dose equations Alternately, the monthly dose may be projected by computing the dose accumulated during the most recent month and assuming the result represents the projected dose for the current month.

This equation, adapted from dose projection equations in Regulatory Guide 1.109 and NUREG-0133, extrapolates the dose to date in a current month to include the entire month. It should be noted that equation 30 is the same as ODCM equation 8 for liquids.

5.1.5 Effluent Noble Gas Monitor Setpoints Technical Specification 3.3.3.6 requires that radioactive gaseous effluent monitoring instrumentation channels be

~o crab e with their alarm/trip setpoints set to ensure that the limits of specification 3.11.2.1 and 3.11.2.5 are not exceeded. The alarm/trip setpoints of the channels meeting specification 3.11.2.1 shall be determined and adjusted in accordance with methodology and parameters in the ODCM.

The requirements of this Technical Specification can be met using the following equation:

h Sq S = 1.06 + Bkg (27)

F X/0 Cg 'DFg 38 06/25/91

where:

S = The alarm setpoint, (cpm) 1.06 = conversion constant; 500 mrem/yr . 60 sec/min

~

35. 37 ft~/m~ 1m~/10~em~

h = monitor response to activity concentration of effluent, c m pCi/cm F = flow of gaseous effluent stream, i.e., flow past the monitor, (ft~/min) atmospheric dispersion factor at the offsite location of interest, (sec/m~)

C< = concentration of radionuclide effluent (pCi/cc) i in gaseous DF, factor converting ground-level or split-wake release of radionuclide i to the total body dose equivalent rate at the location of potential exposure, mre yr pci/m S) a factor to allow for multiple sources from different or common release points. The allowable operating setpoints controlled administratively by assigning a will be fraction of the total allowable release =to each of the release sources.

Equation 27 is based on setpoint methodology described in NUREG-0133. This equation uses known factors about the gas monitor, atmospheric dispersion, and radionuclide distribution and background radiation to determine a setpoint. The required equation factors are:

~

The monitor An efficiency factor, h, must be known.

Gas flow past the monitor must be known.

It should be noted that this is not the flow of the vent or stack through which gas is being discharged.

39 06/25/91

Atmospheric dispersion (y/Q)

The y/Q values for Turkey Point are based on historical meteorological data and methodology from Regulatory Guide 1.111.

Turkey Point g/Q data are given in ODCM Table 3-6.

The air dose conversion factor DF< is a factor which converts the ground level release of radionuclide i to the total body dose equivalent at the location of potential exposure. DF~ factors for Turkey Point are taken from Regulatory Guide 1.109 Table B-1 and are given in ODCM Table 3-5.

Radionuclide distribution There are three acceptable means to determine radionuclide distribution, these are:

To perform a gamma spectrum analysis of the gas release. Results of one or more analysis may be averaged to obtain a representative spectrum. This is the preferred way of determining release concentrations.

From the historical spectrum of noble gas distributions given 'in ODCM Table 3-2.

This table is used in conjunction with a noble gas gross activity analysis.

By attributing the total or gross activity to Xe-133. This technique is valid because Xe-133 comprises about 994 of the noble gas activity.

~

Background (Bkg)

The radioactive background in which the monitor operates should be known and added to the setpoint value to prevent setting the monitor setpoint too low.

The set point is determined by evaluating the location at the site boundary where minimum atmospheric dispersion occurs. This location is 1950 meters SSE of the plant where the g/Q value is 5.8 x 10 ~ sec/m~.

40 06/25/91

The limiting factor when using equation 27 to determine a setpoint is the total body dose rate limit of 500 mrem/yr which is included in the 1.06 conversion factor. The use of total body dose assumes that the total body dose will be the controlling dose rate and the dominant contributor to this dose will be Xe-133.

The requirements of Technical Specification 3.3.3.6 can also be met by using the following equation:

S- MPC ' 'g (2s) 4.7xao-' X/0 where:

MPC = the unrestricted area maximum permissible concentration for the effluent noble gas mixture 4.7 x 10 conversion constant, 1m~ x 1 ll~

~35. 37ft 60 sec h = monitor response to activity concentration of effluent, c m pCi/cm F = flow of gaseous effluent stream, i.e.,

flow past the monitor ( ft~/min) atmospheric dispersion factor at the offsite location of interest, (sec/m~)

S) A factor to allow for multiple sources from different or common release points.

The allowable operating setpoints will be controlled administratively by assigning a fraction of the total allowable release to each of the release sources.

The unrestricted area maximum permissible concentration (MPC) for the noble gases is determined from the distribution of noble gases in the release as follows:

MPC= Cg + (2s) where:

41 06/25/91

C~ = concentration of radionuclide effluent i in a gaseous MPC. the unrestricted area maximum permissible concentration for radionuclide i. Values of 1

MPC< for the noble gases are given in 10CFR20, Appendix B, Table 2,.Column l.

The differences between equation 27 and equation 28 are:

The dose rate in equation 27 represented by the term

$ Cf DPI has been replaced by maximum permissible concentration values based on noble gas release concentration as represented by the term MPC which is derived using equation 28 and MPC< values for the noble gases from 10CFR20 Appendix B, Table 2, Column l. As a result of this replacement, the air dose conversion constant DF< is not required in equation 28.

The background term included in equation 27 is not required in equation 28 because background is an inherent part of MPC.

The limiting factor of 500 mrem/yr total body dose in equation 27 has been replaced by MPC.

As a result the conversion factor changes in equation 28.

The atmospheric dispersion factor X/Q for both equation 27 and equation 28 are the same.

Setpoints using MPC are also evaluated at the point of minimum atmospheric dispersion which is 1950 meters SSE of the plant where the g/Q value is 5.8x10 " sec/m~.

6.0 nnu ose o t e ts Technical Specification 3.11.4 requires that the annual (calendar year) dose or dose commitment to any Member, of the Public due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to:

42 06/25/91

25 mrems whole body or any organ except the thyroid

< 75 mrems to the thyroid The requirements of Technical Specification 3.11.4 can be satisfied by applying the following equations from the ODCM.

~

Total body dose due to liquid effluent deposited on the cooling canal shoreline.

D=0.23~ ~ A~ (7) k V'l g Total body dose due to noble gas gamma (y) .

D =

X.' 1 'Pg (13)

Ta go gg Total body dose due to noble gas beta (p).

(14)

Thyroid dose due to gaseous effluents other than noble gases.

3. 17MO D,Z,g.,~ gik (22) k 0 8 g 131

+

When equations 13 and 14 are used to assess compliance with Technical Specification 3.11.4, a different atmospheric dispersion factor g/Q must be used. For determinations of annual dose, the X/Q value is for the most exposed receptor not the minimum dispersion point at the site boundary. For Turkey Point the most exposed receptor is located 3.6 miles west northwest of the plant at the location of the nearest garden. The g/Q value at that location is 1.0xlO ~ sec/m~.

43 06/25/91

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT PLANT SEMIANNUAL REPORT JANUARY 199 1 THROUGH JUNE 1991 UNITS 3 AND 4 ATTACHMENT 3

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM During this reporting period, Turkey Point, Operating Procedure 11550.48, Process Control Program for Dewatering Radioactive Waste Liners, was revised as follows:

Steps 3.1.1, 3.1.2, 3.1.3, 3.1.4, 3.1.5, 3.1.6, 3.1.7, 6.1.2, 6.1.3, 6 '.4, 6.1.5, 6.1.6, 6.1.7 and 6.1.8 were revised to change the Site Document Control Controlled Vendor Manual number for the referenced procedures from AA693 to T-087.

2. Step 6.1.1 was revised to reference new Technical Specifi-~tion 3.11.3.

These changes are administrative only. They have no impact on the degree of assurance that the waste form produced under the Process Control Program will conform to the requirements of 10CFR61 and the disposal site licenses.

RKR/eb/114

FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 OPERATING PROCEDURE 11550. 48 HEALTH PHYSICS PROCEDURE HP-48 March 14 1991*

1.0 Title

PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 2.0 A royal and Li st of Ef fective Pa es:

2. 1 ~Arova 1:

Change gated ~3 14 91 Reviewed by Plant Nuclear Safety Committee: 91-040 and Approved by Plant Manager - Nuclear:~3 14 91 2.2 List of Effective Pa es:

Pa<ac Date PacLe Date ~Pa e Date 03/14/91* 4 03/14/91* 02/13/90 03/14/91* 5 03/14/91*

02/13/90 6 03/14/91*

OTSCs Incorporated by Word Processing:

OTSC Approval Originator Safety Review By Approved By Approved By (PSN) PNSC No.

Number Oate 1 8896 R.C. Wel O.j. Fein old O.M. Haa W. G. Hale 91%40 3/14/91 3.0 ~pur ose:

The Turkey Point Process Control Program (PCP) implements requirements of the Turkey Point 3 and 4 Technical Specifications and provides instructions for the removal of free-standing water from liners containing radioactive bead resin, powdex resin, or charcoal.

3.1 Discussion

The PCP contains provisions to ensure that dewatering of radioactive bead resin, powdex resin and charcoal results in a waste form with characteristics that meet the requirements of 10CFR 61 as implemented by 10CFR 20 and of the low level radioactive waste disposal site. The Process Control Program includes in addition to this procedure, the following related documents:

3.1.1 Westinghouse Radiological Services, Inc. procedure I OTSC STD-D-03-009, A Users Manual for the Westinghouse RADLOK-200, RADLOK-500, RADLOK-100, RADLOK-179, and RADLOK-195, SDC Controlled Vendor Manual T-087 8896 an 0 T.S.C (On T'e 1898, 88-2985, 90-0137P This procedure may be affected by RTSs Spot Change) veniy information pnor toute.

Date verified initials 0/em/sw/dja

3/14/91*

OPERATING PROCFDURE 11550.48, HP-48, PAGE 2 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 3.1.2 Westinghouse Radiological Services, Inc. procedure OTSC STD-P-03-003, RADLOK Manway Assembly Closure and Sealing Procedure, SDC Controlled Vendor Manual T-087 3.1.3 Westinghouse Radiological Services, Inc. procedure STD-P-03-004, Closure of Hittman RADLOK High Integrity Container Fill Port Closure Assembly, SDC Controlled Vendor Manual T-087 3.1.4 Westinghouse Radiological Services, Inc. procedure STD-P-03-046, Transfer and Dewatering Ion Exchange Resin and/or Activated Charcoal Filter Media Using the Hittman Rapid Dewatering System, SDC Controlled Vendor Manual T-087 3.1.5 Westinghouse Radiological Services, Inc. procedure STD-P-03-052, Transfer and Dewatering Ion Exchange Resin and/or Filter Media Using the Press Pak System, SDC Controlled Vendor Manual T-087 3.1.6 Westinghouse Radiological Services, Inc. procedure STD-P-03-010, Transfer and Dewatering Bead Resin in Hittmam RADLOK High Integrity Containers With a Single Layer Underdrain Assembly to Less Than 1X Drainable Liquid, SDC Controlled Vendor Manual T-087 3.1.7 Westinghouse Radiological Services, Inc. procedur e STD-P-03-020, RADLOK Inspection Procedure, SDC Controlled Vendor Manual T-087 I 8896 3.1.8 Westinghouse Radiological Services, Inc. Process Control Program STD-PCP-03-003, Westinghouse Hittman Mobile Incontainer Dewatering and Solidification Systems 3.1.9 Duratek Corporation procedure TP8 10-3, Duratek Sluicing Media 3.1.10 Duratek Corporation procedure TPf 12-1, Operation of the HED System I 3.1.11 Duratek Corporation procedure TP$ 10-1, Operation of the Duratek EVR System I 3.1.12 Duratek Corporation Process Control Program 14-2, HED Process Control Program I 3.1.13 Duratek Corporation Topical Report Number D-EVR/HED-1-NP-"A",

Topical Report for EVR/HED System for Treatment of Nuclear Power Reactor Waste Liquids

3.2 Authority

The authority and responsibility to perform this procedure comes from 10CFR 20, 10CFR 61, Turkey Point Plant Units 3 and 4 Technical Specifications, and disposal site licenses.

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2/13/90 OPERATING PROC(DURE 11550.48, HP-48, PAGE 3 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS

3.3 Definitions

3.3.1 Dewatering

The process of removing "Free-Standing" water from a final disposal package.

3.3.2 "Free-Standing Water": Liquid which is not retained by the waste form.

3.3.3 Process Control Program (PCP): A program which contains the provisions, based on full scale testing, to ensure that dewatering of radioactive bead resin, powdered resin or charcoal results in a waste form with the properties that meet the requirements of 10CFR 61 (as implemented by 10CFR 20) and of the low level radioactive waste disposal site.

4.0 Precautions

4.1 Instructions used for the dewatering of liners which establish the conditions to be met, shall be based on full scale testing. This is to provide reasonable assurance that the dewatering will result in volumes of free-standing water, at the time of disposal, within the limits of 10CFR, Part 61 as implemented by '10CFR 20 and of the low level, radioactive waste disposal site.

4.2 Class "8" and "C" radioactive waste (as determined by 10CFR 61 and O-HPA-040, Shipping and Receiving Radioactive Material) may be transferred to the disposal site in a High Integrity Container (HIC) approved for disposal by the licensing agency for the disposal site.

No other containers may be used without PNSC approval.

4.3 Do not use High Integrity Containers for radioactive material that could chemically or physically damage or otherwise exceed the allowable limits of the HIC.

4.4 Changes to the Turkey Point Plant Process Control Program shall be reviewed and approved by the PNSC before they become effective.

4.5 Changes to the Turkey Point Plant Process Control Program shall be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall. contain the following:

.4.5.1 Sufficiently detailed, information. to, support, the rationale for the change.

4.5.2 A determination that the change did not reduce the overall conformance of the dewatered waste to existing criteria for stabilized waste form.

4.5.3 Documentation of the fact that the change has been reviewed and found acceptable by the PNSC.

0/em/ew

3/14/91*

OPERATING PROCEDURE 11550.48, HP-48, PAGE 4 PROCESS CONTROL PROGRAM NOR DEWATERING RADIOACTIVE- WASTE LINERS 4.6 Disposal of radioactive bead resin which is Class 8 or Class C, or which is Class A and has a concentration of radionuclides with half-lives greater than five years and exceeding one microcurie per cubic centimeter, is limited to HICs with an approved certificate of compliance issued by the licensing agency for the disposal site.

4.7 Radioactive bead resin which is Class A, and which has a concentration of radionuclides with half-lives greater than five years but not exceeding one microcurie per cubic centimeter, may be packaged in HICs or disposable carbon steel cask liners.

4.8 Disposal of radioactive charcoal filter media which is Class 8 or Class C, or which has a concentration of radionuclides with half-lives greater than five years and exceeding one microcurie per cubic centimeter, is limited to HICs with an approved certificate of compliance issued by the licensing agency for the disposal site.

4.9 Radioactive charcoal filter media which is Class A, and which has a concentration of radionuclides with half-lives greater than five years but not exceeding one microcurie per cubic centimeter, may be packaged in HICs or disposable carbon steel cask liners.

4.10 Disposal of condensate polishing resin is permitted in HICs or disposable cargon steel cask liners.

4.11 Personnel performing the dewatering procedure should be aware that strong oxidizing agents such as nitric acid, when in contact with organic ion-exchange material and in the presence of air, may produce a slightly degraded resin in an exothermic reaction, up to an explosion. The first indication of an exothermic reaction due to the presence of oxidizing agents is some fuming and a slight rise in temperature on the outside of the container. If this condition is found when dewatering a vessel, immediately refill the vessel with water. This will eliminate one of the ingredients necessary for the reaction (air) and will dissipate the majority of the heat, returning the temperature of the vessel to ambient. When the condition has stabilized, notify the immediate supervisor.

5.0 Res onsibilities:

5.1 It is the responsibility of the Plant Manager to assure that necessary procedures, equipment and support are provided to properly implement the PCP.

5.2 It is the responsibility of the Health Physics Supervisor, or designee, to ensure that all liners will be dewatered in accordance with the PCP.

6.0 References Commitment Documents:

6.1 References 6.1.1 Turkey Point Units 3 and 4 Revised Technical I OTSC Specifications No. 3.11.3 I 8896 I

0/em/sw/dja

3/14/91*

OPERATING PROC;DURE 11550.48, HP-48, PAGE 5 PROCESS CONTROL PROGRAM FOR OEWATERING RADIOACTIVE WASTE LINERS 6.1.2 Westinghouse Radiological Services, Inc. procedure OTSC STD-0-03-009, A Users Manual for the Westinghouse RAOLOK-200, RAOLOK-500, RADLOK-100, RAOLOK-179, and RADLOK-195, SOC Controlled Vendor Manual T-087 6.1.3 Westinghouse Radiological Services, Inc. procedure STD-P-03-003, RAOLOK Manway Assembly Closure and Sealing Procedure, SDC Controlled Vendor Manual T-087 6.1.4 Westinghouse Radiological Services, Inc. procedure STD-P-03-004, Closure of Hittman RADLOK High Integrity Container Fill Port Closure Assembly, SOC Controlled Vendor Manual T-087 6.1.5 Westinghouse Radiological Services, Inc. procedure STO-P-03-046, Transfer and Dewatering Ion Exchange Resin and/or Activated Charcoal Filter Media Using the Hittman Rapid Dewatering System, SDC Controlled Vendor Manual T-087 6.1.6 Westinghouse Radiological Services, Inc. procedure STO-P-03-052, Transfer and Oewatering Ion Exchange Resin and/or Filter Media Using the Press Pak System, SOC Controlled Vendor Manual T-087 6.1.7 Westinghouse Radiological Services, Inc. procedure STO-P-03-010,Transfer and Dewatering Bead Resin in Hittman RAOLOK High Integrity Containers With A Single Layer Underdrain Assembly to Less Than 1X Orainable Liquid, SOC Controlled Vendor Manual T-087 6.1.8 Westinghouse Radiological Services, Inc. procedure STD-P-03-020, RADLOK Inspection Procedure, SOC Controlled Vendor Manual T-087 8896 6.1.9 Westinghouse Radiological Services, Inc. Process Control Program STO-PCP-03-003, Westinghouse Hittman Mobile Incontainer Oewatering and Solidification Systems 6.1.10 Ouratek Corp. procedure TP8 10-3, Slucing Media I 6.1.11 Duratek Corp. procedure TPk 12-1, Operation of the HEO System 6.1.12 Duratek Corp. Process Control Program 14-2, HEO Process Control Program 6.1.13 Ouratek Corp. procedure TP8 10-1, Operation of the Ouratek EVR System 6.1.14 Ouratek Corp., Topical Report Number 0-EVR/HED-1-NP-"A", Topical Report for the EVR/HED System for Treatment of Nuclear Power Reactor Waste Liquids.

6.1.15 Health Physics Administrative Procedure, 0-HPA-040 "Shipping and Receiving Radioactive Material."

• /em/sw/dja

t f

3/14/91*

OPERATING PROCi.DURE 11550.481 HP-48, PAGE 6 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 6.1.16 49CFR 6.1.17 10CFR 61 6.1. 18 OP-5333.1 "WOS - Transf erring Spent Storage Tank To Shielded Shipping Cask" I

6.2 Commitment Documents , I 6.2. 1 quality Assurance Audit gAO-PTN-89-996 7.0 Records and Notifications:

7.1 If it is suspected that the free-standing water requirements have not been met for any container shipped to a disposal site, the Plant I Manager and the Health Physics Supervisor shall be notified.

7.2 If the Process Control Procedures have not been fol lowed or if free standing water is suspected in the final shipping container in amounts greater than allowed by regulations, the Radwaste Supervisor shall be notified.

7.3 Completed copies of the below listed item(s) constitute guality Assurance Records and shall be transmitted to Site Document Control gA Records Section for retention in accordance with guality Assurance Records Program requirements:

7.3.1 Form HP-72C, Specification Container Shipping Release 7.3.2 Form HP-72-L, Powdex Resin Liner Shipping Release Form

8.0 Instructions

8.1 Oewatering shall be performed in accordance with the applicable I vendor procedure for each liner or High Integrity Container (HIC). I 8.2 If the dewatering is not performed in accordance with the vendor procedure, the process shall be terminated. The package shall not be shipped for disposal until it is dewatered in accordance with the vendor procedure.

8.3 If the final waste form is found to be unacceptable (freestanding liquid in excess of 0.5Ã of the waste volume for steel liners or 1.0X for high integrity containers) processing and shipping shall be stopped until the procedures and/or dewatering equipment 'are corrected to prevent recurrence.

8.4 Oewatering of Westinghouse RADLOK HICs 8.4.1 Westinghouse RAOLOK HICs shall be dewatered in I OTSC accordance with Westinghouse Radiological Services, Inc. procedures STD-P-03-046 (reference 6.1.5),

STO-P-03-052 (reference 6.6), or STO-P-03-010 (reference 6.1.7) I 8896

• /em/sw/dja

2/13/90 OPERATING PROC .DURE 11550.48, HP-48, PAGE 7 PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 8.4.2 HICs shall be dewatered to less than one percent free-standing liquid. I 8.5 Dewatering of NuPak 210 HICs fitted with Duratek Oewatering Internals which contain bead resin and Charcoal Filter Media 8.5. 1 NuPak 210 HICs fitted with Duratek dewatering internals shall be dewatered using Duratek Corp procedures TP$ 10-3 (reference 6. 1. 10), TPt 12-1 (reference 6. 11), and TP$ 10-1 (reference 6.1.13).

8.5 Dewatering of Westinghouse RADLOK HICs or carbon steel liners containing Powdered Ion Exchange Resin 8.6. 1 Westinghouse RADLOK HICs and carbon steel cask liners containing powdered ion exchange resin intended for direct disposal shall be dewatered in accordance with Westinghouse Radiological Services, Inc. procedure STD-P-03-046 (reference 6.1.5).

8.6.2 The above containers shall be dewatered to less than one half of one percent free-standing water (carbon steel liners) or one percent free-standing water (HICs).

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