ML20217P014

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Annual Radioactive Effluent Release Rept,Jan-Dec 1997
ML20217P014
Person / Time
Site: Humboldt Bay
Issue date: 12/31/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML20217P007 List:
References
NUDOCS 9804090288
Download: ML20217P014 (18)
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, Enclosure PG&E Letter HBL-98-008 l

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l HUMBOLDT BAY POWER PLANT UNIT 3 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

! renuary 1 through December 31,1997 I

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9004090288 900331 PDR R ADOCK 05000133 PDR ,

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PACIFIC GAS AND ELECTRIC COMPANY HUMBOLDT BAY POWER PLANT DOCKET NO. 50-133, LICENSE NO. DPR-7 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1,1997 THROUGH DECEMBER 31,1997 TABLE OF CONTENTS l INTRODUCTION . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . .. . . .. 2

1. SUPPLEMENTAL INFORMATION. , . . . . . . . .. . . . . . . . 4 II. GASEOUS AND LIQUID EFFLUENTS... . .. .. . .. . . . . . . . . . . . . . 8 Table 1 - Gaseous Efiluents - Summation of All Releases.... . . .. .. . . . . . . . . . 9 l Table 2 - Gaseous Efiluents - Nuclides Released... .. . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Table 3 - Liquid Efiluents - Summation of All Releases..... .. . .. . . . . I1 Table 4 - Liquid Efiluents - Nuclides Released... . . ,. .. . .. . . . . . . . . . . . 12 III. SOLID RADIOACTIVE WASTE.. .. .... . . . . . . . .. . . . . . . . . . . . . 13 Table 5 - Solid Waste and Irradiated Fuel Shipments... ... . . . . .. . . . . . . .14  :

I IV. RADIOLOGICAL IMPACT ON MAN.. . . .... . .. .. . . .. .. .. . ..... 16  !

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e Table 6 - Radiation Dose for Maximally Exposed Individuals. . . . ... .. 17 )

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HUMBOLDT BAY POWER PLANT

' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 INTRODUCTION This report summarizes gaseous and liquid radioactive effluent releases from Humboldt Bay Power Plant Unit 3 for the four quarters of 1997. The report includes calculated potential l

radiation doses from these radioactive effluents and a comparison with the numerical guidelines of 10 CFR 50, Appendix 1, as well as a summary of shipments of solid radioactive waste. The concentrations of plant effluent releases during the reporting period were well below Technical Specification limits.

! The information is reported as required by Section VII.H.3 of the Technical Specifications, and it l is presented in the general format of Regulatory Guide 1.21, Appendix B (except for the topics identified below).

Meteorology l The meteorological data logging system was removed from service in 1967 so the information j specified by Regulatory Guide 1.21, Appendix B, Section F, is not available. Previous Humboldt Bay Power Plant Annual Radioactive Efiluent Release Reports summarized the cumulative joint frequency distribution of wind speed, direction, and atmospheric stability for the period April 1962 through June 1967, when the meteorological data logging system was in service.

Short-lived Nuclides The Unit was last operated on July 2,1976. Due to the long decay time since operation, short-lived radionuclides are neither expected nor reported. This includes iodines and noble gases other than Krypton-85.

Air Particulate Filter Composites - Sr-90 Air particulate sample filters are combined for approximately monthly intervals and analyzed off- ,

site for Sr-90.  !

l Air Particulate Filter Composites - Gross Alpha  !

Each weekly sample filter is individually counted for gross alpha activity, rather than analyzing a monthly composite of the filters, as described in Regulatory Guide 1.21.

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!- Gaseous Effluents- Tritium l Tritium releases during plant operation were less than detection levels. Since the plant was

j. permanentlp shutdown in 1976, current tritium release levels are less than the release levels that occurred during plant operations. Therefore, no tritiua samples were collected during this  ;

reporting period.

Liquid Composites - Gross Alpha & Tritium Gross alpha and tritium data are based on monthly composites, as described in Regulatory Guide l - 1.21, but they are maintained separately for the batch and (semi-) continuous releases.

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6-I? SUPPLEMENTALINFORMATION A.- Regulatory Limits'

l. Gaseous Efiluents Noble Gas Release Rate Limit The noble r elease rate limit is based on the Maximum Permissible Concentraux%MPC) of 10 CFR 20, divided by an atmospheric dispersion factor of 1.4E-6 seconds per cubic meter. This dispersion factor is the annual average dispersion factor for the sector with the least favorable atmospheric dispersion.
b. Iodine Release Rate Limit Due to the long decay time since the Unit was shutdown, the license does not define an iodine release rate limit.
c. Particulate Release Rate Limit The radioactive particulate release rate limit is based on the Maximum Permissible Concentrations of 10 CFR 20, divided by a dispersion factor of 1.4E-6 seconds per cubic meter. This dispersion factor is the annual average i dispersion factor for the sector with the least favorable atmospheric dispersion.  !
2. Liquid Efiluents
a. Concentration Limit Liquid effluent radioactivity concentrations released to Humboldt Bay are limited to the Maximum Permissible Concentratior.s of 10 CFR 20.

B. Maximum Permissible Concentrations  !

.l. Gaseous Efiluents Maximum Permissible Concentrations for gaseous effluents are taken from 10 CFR 20, Appendix B, Table II, Column I.

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i Regulatory limits in this report are based on the version of 10 CFR 20 in efTect prior to January 1, 1994 (20.1-20.602), as referenced in the Technical Specifications.

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2. Liquid Efiluents I

Maximum Permissible Concentrations for liquid efiluents are taken from 10 CFR 20, Appendix B, Table 11, Column 11.

i C. Measurements and Approximations of Total Radioactivity I

1. Gaseous Efiluents
a. Fission and Activation Gases All ventilation and system vents are routed to the Unit 3 stack. The gaseous '

activity released from the stack is monitored by an off-line monitor equipped with a beta scintillator, with its response calib ed for Kr-85.

The "less than" value reported for Kr-85 is based on the estimated sensitivity of the stack Kr-85 monitor. i l

The estimated sensitivity of the stack Kr-85 monitor permits detection of Kr-85 at approximately 0.5% of the applicable Lower Limit of Detection (LLD) guidance presented in Regulatory Guide 1.21, which is IE-4 micro- j Ci/cc. '

b. lodines Due to the long decay dme since operation (shutdown July 2,1976), no detectable releases ofradioactive iodines can be expected. Therefore, the Technical Specifications do not require that these radionuclides be monitored.
c. Particulates Radioactive particulates released from the plant stack are monitored by l continuous sample collection on particulate filters. Filter papers are removed from the stack sampling system weekly. After decaying 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, they are analyzed for gross alpha (internal proportional counter) and for the concentration of gamma-emitting nuclides (intrinsic germanium detector).

All statistically significant peaks are identified. Filters for each quarter are analyzed for radioactive strontium-90 (the only strontium present).

l The estimated error of the reported particulate release values is based on uncertainty in sample flow rate, stack flow rate, detector calibration, and typical sample counting statistics.

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The Minimum Detectable Activity (MDA) for all particulate filter samples was less than the applicable Lower Limit of Detection (LLD) guidance presented in plant procedures (IE-11 micro-Ci/cc). This LLD is approximately equivalent I to the sensitivity level in Regulatory Guide 1.21, which is based on detection of an annual exposure of 15 millirem to any organ of an individual in an unrestricted area.

2. Liquid Efiluents
a. Batch Releases All water from contaminated plant systems was collected, filtered, and analyzed before discharge (on a batch basis) through the liquid radwaste process monitor. Analysis of weekly composite samples from the plant efIluent canal did not detect any significant additional release of radioa, 'ive liquids during the report period.

Samples ofliquid waste batches were analyzed for the concentration of gamma-emitting nuclides (intrinsic germanium detector). All statistically important peaks were identified. Quarterly composites of all batches were analyzed for radioactive strontium (Sr-90), and monthly composites of al!

batches were analyzed for gross alpha and tritium.

The error of the reported release values is estimated based on uncertainty in sample volume, batch volume, detector calibration, and typical sample counting statistics.

The Minimum Detectable Activity (MDA) for all batch samples was less than the applicable Lower Limit of Detection (LLD) guidance presented in Regulatory Guide 1.21, with the following exception. For Am-241,3 samples (out of 99) had an MDA above the guidance LLD (5E-7 micro-Ci/ml), with the highest MDA being 6.7E-7 micro-Ci/ml.

b. Continuous Releases Beginning in August 1996, Humboldt Bay Power Plant was able to determine conditions when ground. vater leakage into the reactor caisson sump did not require treatment in the Radwaste Treatment System. When treatment was not required, this groundwater was discharged through the liquid radwaste process monitor, and a continuous composite sample was collected during discharge.

i The composite sample was analyzed weekly (or more frequently) for the l

conwetration of gamma-emitting nuclides (intrinsic germanium detector). All statistically important peaks were identified

l The composite accumulation container was found empty for the week ending 2/14/97, and a grab sample of the continuous disdiarge was promptly collected. As analysis results were normal, the release for that composite sample period was calculated using the grab sample results.

Composite samples collected 7/11/97,7/18/97 and 7/22/97 indicated higher than usual concentrations of Co-60, that were determined to not represent the discharge for the sample period, based on comparison with the liquid radwaste process monitor and with grab samples of the continuous discharge. Alt.'iough the unusual samples were determined to be the result of contaminated sample tubing, they were used to conservatively determine the amount of radioactivity released.

Quarterly composites of the weekly samples were analyzed for radioactive strontium (Sr-90), and monthly composites of the weekly samples were analyzed for gross alpha and tritium.

The error of the reported release values is estimated based on uncertainty in sample volume, flow measurement, detector calibration, and typical sample counting statistics.

The Minimum Deteuable Activity (MDA) for all continuous release samples was less than the applicable Lower Limit of Detection (LLD) guidance presented in Regulatory Guide 1.21.

D. Batch Release Statistics

1. Liquid
a. Number of batch releases... . . . . . 99
b. Total time period for batch releases . . . . 2.74E4 minutes
c. Maximum time period for a batch release.. 4.40E2 minutes
d. Average time period for a batch release . . . . 2.77E2 minutes
e. Minimum time period for a batch release . . . 1.50E1 minutes I

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' a. Nu mber o f bat ch releases .. .. ... . . . . . . . . . .. . . . .. . .. . . .. . .. . .. . . . . . . . .. . . . . . . . . O .. .. . . . . . . . j

b. Total time period for batch releases ...... ....... ... . . ... .... .. .. .... .. .. .. .... . N/A i

L c. ' Maximum time period for a batch release'........ ... ........ ............ ..... . ...... ..... N/A i

d. Average tim'e period for a batch release .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N/A -

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e. Minimum time period for a batch release . ............................... .. .. N/A L E. ' Abnormal Release Statistics
1. Liquid
a. Number of abnormal releases..... .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 0 ,

. b. Total activity released.. .. ... . .... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N/A if GASEOUS AND LIOUID EFFLUENTS A. Gaseous Emuents Table I summarizes the total quantities of radioactive gaseous emuents. Table 2 -

presents the quantities of each of the nuclides determined to be released.

B. Liquid Emuents i

Table 3 summarizes the total quantities of radioactive liquid emuents. Table '4 presents the quantities of each of the nuclides determined to be released.

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HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 TABLE 1 GASEOUS EFFLUENTS 'UMMATION OF ALL RELEASES Units First Second Third Fourth Est. Total Quarter Quarter Quarter Quarter Error, %

A. Fission & Activation Gases

1. Total release Ci <5.46El <5.52El <5.58E1 <5.58El 3.20El l
2. Average release rate pCi/sec <7.02E0 <7.02E0 <7.02E0 <7.02E0
3. Percent of applicable limit  % <3.28 E-3 <3.28 E-3 <3.28E-3 <3.28 E-3 B. Particulates
1. Total release Ci 1.21 E-5 3.53 E-6 6.70E-6 2.18E-6 2.70El l
2. Average release rate pCi/see 1.56E-6 4.48E-7 8.43E-7 2.75 E-7
3. Percent of applicable limit  % 5.50E-7 1.58E-7 3.92E-7 1.04E-7
4. Applicable limit (mixture MPC) Ci/cc 3.97E-10 3.97E-10 3.01 E-10 3.72E-10
5. Gross alpha radioactivity Ci 4.04E-7 2.29E-7 2.70E-7 3.26E-7 i

Note: The < symbol used in this table means that all or a majority of the measurements contributing to the result were less than the Minimum Detectable Activity (MDA) for the I analyses. Data fo individual nuclides combines detected and non-detected results as if all values were detected, but the < symbol is applied ifmore than 50% of the combined value is made up of non-detected results. When combining results for differerlLnuclides (e.g.

activity totals of multiple nuclider), values with the < symbol are ignored (i.e. treated as zero).

1 HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 TABLE 2 GASEOUS EFFLUENTS - NUCLIDES RELEASED Continuous Mode Nuclides Released Unit First Second Third Fourth Quarter Quarter Quarter - Quarter

1. Fission Gasses Krypton-85 Ci <5.46El <5.52El <5.58El ' <5.58El Total for period Ci <5.46El <5.52El <5.58El <5.58El
2. Particulates Cobalt-60 Ci 4.73E-6 1.38E-6 3.55 E-6 1.13 E-6 Strontium-90 Ci <5.28 E-8 <5.57E-8 1.38E-7 <4.55 E-8 Cesium-137 Ci 7.39E-6 2.15E-6 3.15 E-6 1.05E-6 Am-241 Ci <l .09E-5 <9.69E-6 <2.22E-6 <l .60E-6 Total for period Ci 1.21E-5 3.53E-6 6.70E-6 2.18E-6 Note: The < symbol used in this table means that all or a majority of the measurements contributing to the result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected, but the < symbol is applied if more than 50% of the combined value is made up of non-detected results. When combining results for different nuclides (e.g.

activity totals of multiple nuclides), values with the < symbol are ignored (i.e. treated as zero).

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, HUMBOLDT B.W POWER PLANT-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 TABLE 3 l LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES First Second Third Fourth Est. Total

' Units Quarter Quarter Quarter Quarter Error, %

1 A. Fission & Activation Products

1. Total release (not including tritium, gases, alpha) Ci 2.l lE-3 2.61E-3 8.15E-3 4.65 E-4 2.00El
2. Average diluted concentration pCi/ml 8.90E-11 1.50E-10 4.52E-10 2.65E-11
3. Percent of applicable limit  % 1.42E-3 2.05E-3 2.12E-3 2.41 E-3
4. Applicable limit (Mixture MPC) Ci/ml 6.27E-6 7.32E-6 2.13E 1.10E-6 B. Tritium l
1. Total release Ci <l .39E-3 <l .53 E-3 <l .02 E-3 2.76E-3 5.00El l
2. Average diluted concentration Ci/ml <5.84E-11 <8.79E-11 <5.67E-11 1.57E-10
3. Percent of applicable timit  % <l .95 E-6 <2.93 E-6 <l .89E-6 5.23E-6 C. Gross Alpha Radioactivity i l1. Total release l Ci l <l.53E-5 l <l.29E-5 l 1.55E-5 l 3.07E-6 l 5.00El l

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D. Volume of waste released Liters 2.37E6 2.80E6 1.96E6 9.85E4 1.00El (prior to dilution) l E. Volume of oaution water l Liters l 2.37E10 l 1.74E10 l 1.81E10 l 1.76E10 l 1.50El l Note: The < symbol used in this table means that all or a majority of the measurements contributing to the result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected, but the < symbol is applied if more than 50% of the combined value is made up of non-detected results. When combining results for different nuclides (e.g.

activity totals of multiple nuclides), values with the < symbol are ignored (i.e. treated as '

zero).

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HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 TABLE 4 -

LIQUID EFFLUENTS - NUCLIDES RELEASED Batch Mode Nuclides Released Uni lirst Quarter I Second Quarter l Third Quarter l Fourth Quarter Strontium-90 Ci 4.94E-5 6.71E-5 2.01 E-5 1.22 E-4 Cesium-137 Ci 2.00E-3 2.44E-3 2.47E-3 2.51E-4 Cobalt-60 Ci 2.42E-5 8.85 E-5 2.83E-4 9.llE-5 Am-241 Ci <8.69E-5 <l .31 E-4 <l .14 E-4 <6.47E-6 l Total for perio_d Ci 2.07E-3 2.59E-3 2.78 E-3 4.65E-4 Continuous Mode Nuclides Released Unit First Quarter l Second Quarter l Third Quarter l Fourth Quarter Strontium-90 Ci 2.ll E-5 <2.12 E-6 <7.74E-7 N/A Cesium-137 Ci 1.82E-5 2.23E-5 6.99E-5 N/A '

Cobalt 60 Ci <l .37E-5 < l .56E-5 5.30E-3 N/A Am-241 Ci <l .17E-4 <2.18E-4 <l .37E-4 N/A Total for period Ci 3.93 E-5 2.23 E-5 5.37E-3 N/A Notes: The < symbol used in this table means that all or a majority of the measurements i contributing to the result were less than the Minimum Detectable Activity (MDA) for the analyses. Data for individual nuclides combines detected and non-detected results as if all values were detected, but the < snabolis applied if more than 50% of the combined value is made up ofnon-detected results. When combining results for difTerent nuclides (e.g.

activity totals of multiple nuclides), values with the < symbol are ignored (i.e. treated as zero). y N/A - There weie no continuous mode liquid efiluents during the fourth quarter.

1 lit -SOLID RADIOACTIVE WASTE

' Table 5 summarizes the shipments of solid radioactive waste made during the report period.

The volume reported is the 'as-buried' quantity, c

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HUMBOL.DT BAY POWER PLANT 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 TABLES SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS A. Solid Waste Shipped Offsite For Burial Or Disposal

1. Type of Waste Unit 12 Month Period Estimated Total Error, %
a. Spent resins, filter sludges, Cubic Meter None N/A l evaporator bottoms, etc. Ci N/A N/A -i
b. Dry mpressible waste, Cubic Meter 7.84E-1 7.50E0 contaninated equipment, etc. Ci 6.33 E-1 5.60El
c. Irradiated components, Cubic Meter None N/A control rods, etc. Ci N/A N/A ,
d. Other(dewatered sludge) Cubic Meter None N/A l Ci N/A N/A -
2. Estimate of major nuclide Unit Nuclide 12 Month Period composition (by type of waste)
b. Dry compressible waste,  % 11-3 6.00E0 contaminated equipment, etc.  % C-14 1.57E-2 j

% Mn-54 3.41E-3 '

% Fe-55 7.50E0

% Co-57 5.13 E-3

% Co-60 3.14E0

% Ni-59 1.85E-2

% Ni-63 3.14E0

% Sr-90 2.63E0

% Tc-99 6.40E-3 .j

% l-129 3.15E-4

% Cs-134 3.36E-2 l

% Cs-137 7.52E1 l

% Ce-144 1.80E-7

% Pu-238 2.62E-2 l~  % Pu-239/240 5.72E-2

% Pu-241 2.05E0

!  % Pu-242 2.49E-5

% Am-241 1.48E-1

% Cm-242 1.62E-4

% Cm-243/244 1.69E-2 f

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HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997 TABLE 5 - Continued i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS i

A. Solid Waste Shipped OfTsite For Burial Or Disposal - Continued

3. Solid Waste Disposition Number of Mode ofTransportation Destination Shipments 2 Truck Clive, UT 1

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! 1 Irradiated Fuel Disposition Number of Mode of Transportation Destination Shipments None N/A N/A l

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l IV. RADIOLOGICAL IMPACT ON MAN

'A comharison of calculated doses from various paths has shown that the ofTsite doses are 4 primarily due to direct radiation and to the consumption of aquatic foods. Maximum doses to individuals (for the maximally exposed organs and age groups) are summarized in Table 6.

These doses comply with 40 CFR 190 as there are no other uranium fuel cycle facilities ,

within 8 km of the Humboldt Bay Power Plant. I A. Doses to the average individual in the population from all receiving-water-related pathways were calculated for detected releases, based on the guidance of Regulatory Guide 1.109. The results were 0.003 mrem /yr (total body) for the Adult age group, and 0.004 mrem /yr for the bone of the Child age group.

These doses are well below the 10 CFR 50, Appendix I numerical guidelines for limiting  ;

efIluents as low as is reasonably achievable (ALARA) (3 mrem /yr to the total body and 10 mrem /yr to any organ).

B. Total body doses to the average individual in the population from gaseous efiluents to a distance of 50 miles from the site are not calculated, but this dose is less than the total body dose to an average individual present at the maximally exposed location. For an average individual at the maximally exposed location, the total body dose (calculated .

with the same dispersion and deposition parameters as were used to calculate maximum l exposure) was less than 0.001 mrem /yr.

This maximum calculated dose is well below the 10 CFR 50, Appendix 1 numerical ALARA guidelines (10 mrem /yr for gamma radiation and 20 mrad /yr for beta radiation from noble gases and <15 mrem /yr to any organ from tritium and radionuclides in particulate form).

C. Total body doses (to the average individual in unrestricted areas from direct radiation from the facility) are based on TL.D results of stations at the site boundary, using the shoreline occupancy factors given in Regulatory Guide 1.109 for the highest average potential individual (Teen age group). For this group, direct radiation would result in an exposure of 0.016 mrem /yr.

This maximum potential dose is well below the 10 CFR 20.1302(b)(2)(ii) limit of 50 mrem /yr from external sources necessary to demonstrate compliance with the 10 CFR 20.1301 dose limit for individual members of the public.

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HUMBOLDT BAY POWER PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1997

, TABLE 6 RADIATION DOSE FOR MAXIMALLY EXPOSED INDIVIDUALS Annual Dose, milli-rem (1)

First Second Third f

Fourth Annual Dose Source Quarter Quarter Quarter Quarter Average Liquid Efiluents Water-related Pathways (2) 0.01(6) 0.01(6) 0.02(6) <0.01(6) 0.01(6) 0.01(8) 0.02(8) 0.09(9) - 0.01(10) 0.02(9)

Airbome Effluents Particulates (3) <0.01(6) <0.01(6) <0.01(7) <0.01(6) <0.01(6)

<0.01(8) <0.01(8) <0.01(8) <0.01(8) <0.01(8)

Noble Gases (4) - - - - -

Direct Radiation (5) 0.04 0.03 0.02 0.01 0.02 Notes

1. The dose shown for each quarter is calculated on an annual basis (i.e. milli-rem / year) for fouridentical quarters.
2. haximum total body and organ doses to individuals in unrestricted areas from i receiving-water-related exposure pathways were calculated from the average concentrations ofliquid releases detected during the report period, following the )

applicable portions of Regulatory Guide 1.109.

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3. Maximum total body and organ doses to individuals in unrestricted areas from I airborne-particulate-related exposure pathways were calculated from the average concentrations of airborne particulate releases detected during the report period, following the applicable portions of Regulatory Guide 1.109.
4. Total body and skin doses to potentially exposed individuals located at the point of maximum offsite ground-level concentrations of radioactive gaseous effluents were not calculated because there were no detected releases of radioactive noble gases, and because the total body doses would be less than 0.005 milli-rem /yr at the level at which the releases could be detected.

l 5. Total body doses (to the maximum individualin the population) are based on TLD l results of stations at the site boundary, using the shoreline occupancy factors of l Regulatory Guide 1.109 for the maximum potentialindividual (Teen age group).

l 6. Total body (Adult age group).

7. Total body (Child age group).
8. Bone (Child age group).
9. GI/LLI(Adult age group).
10. Bone (Adult age group).
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