ML20082V239
| ML20082V239 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/1994 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-3201, NUDOCS 9505090124 | |
| Download: ML20082V239 (201) | |
Text
{{#Wiki_filter:. a n u, f* I901 Onoutaab Avenue Post Office Box 149 t, SL louis. Missouri 63166 314-554-2650 DonaldF. Schnen Senior Vice President Nudea!
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U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen: ULNRC-3201 DOCKET NUMBER 50-483 CALIAWAY PLANT FACILITY CPERATING LICENSE NPF-30 1994 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Please f'ind enclosed the 1994 Annual Radioactive Effluent Release Report for the Callaway Plant. This report is submitted in accordance with Section 6.9.1.7 of the Technical Specifications. Very truly yours, c'M4't
/ Donald F. Schnell BFH/plr Enclosure 9505090124 PDR 941231ADOCK PDR 05000483 R
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N< l l cc* 'P . A. Baxter, Esq. f Sc , Shaw, Pittman, Potts & Trowbridge i
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Washington, D.C. 20037
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M. H. Fletcher f Professional Nuclear Consulting, Inc. 19041 Raines Drive ; Darwood, MD 20855-2432 7 N. J. Farber . Chief, Reactor Projects Section III A U.S. Nuclear Regulatory Commission , Region III 801 Warrenville Road ! Lisle, IL 60532-4351 Bruce Bartlett l Callaway Resident Office U.S. Regulatory Commission RR#1 , Steedman, MO 65077 l L. R.-Wharton (2) ' Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E21 i 11555 Rockville Pike ' Rockville, MD 20852-2738 Manager, Electric Department Missouri Public vervice Commission . P.O. Box 360 ! Jefferson City, MO 65102 Bob Hentges Regional Administrator Department of Natural Resources Central Regional Office l P.O. Box 176 ' Jefferson City, MO 65102 Gerhard K. Samide ANI Account Engineer ' Town Center, Suite 3005 29 S. Main St. West Hartford, CT 06107-2445 i
DOCKET NO. 50-483 UMON Etscrme j s , 4 CALLAWAY PLANT ; ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - I d 1 JANUARY DECEMBER 1994 1 l ib.: u .. , b o
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ANNUAL RADIQACTIVE EFFLUENT RELEASE REPORT CALLAWAY NUCLEAR PLANI' UNION ELECTRIC CCMPANY LICENSE NPF - 30
. JANUARY - DECEMBER 199 l
' TABLE OF CO?TTENTS
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION i 3.1 Regulatory Limits 2.2 . Maximum Permissible Concentrations 2.3 Average Energy 8.4 MeaJurements and Approximations of Total Radioactivity I 3.5 Batch Releases ' 2.6 Abnormal Releases 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTES SHIPMENTS 6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.2 Changes to the Process Control Program 6.3 Changes to the Offsit's Dose Calculation Manual 6.4 Major Changes to Radwaste Treatment Systems 6.5 Land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrumentation , 6.7 Instances of Liquid Holdup Tasks or Waste Dect.y Tanks Exceeding i Technical Specification Limits 7.0 METEOROLOGICAL DATA 8.0 ASSESSMENT OF DOSES ; 8.1 Dese at the Site Boundary and Nearest Residence from Gaseous Effluents 8.2 Dose to the MEMBER OF THE PUBLIC i S.2.1 Dose at the Nearest Residence from Geseous Effluents i i 8.2.2 Dose to the MEMBER OF THE PUBLIC from Activities Within the SITE BOUNDARY l 8.3 Total Dose Due to the Uranium Fuel Cycle 8.4 Doae Due to Liquid Effluents i
t-TABLE OF CONTElfrS e
. Table 1A Annual Summation of. Gaseous' Releases Table 1B Annual Airborne Continuous and Batch Releases i
Table-2A Annual Summation of Liquid Releases i Table 2B Annual' Liquid Continuous'and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments j i Table 4 - Cumulative Joint Frequency Distributions Table 5 Dose at the SITE BOUNDARY and Nearest Resident f Table'6 Dose to the MEMBER OF THE PUELIC from Activities within the l SITE BOUNDARY ! Table 7 Total Dose Due to the Uranium Fuel Cycle Table 8 Dose Ode to Liquid Effluents I
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1.0 INTRODUCTION
This Annual Radioactive Effluent Release Report is submitted in accordance with Section 6.9.1.7 of the Callaway Plant Technical , Specifications. I The report presents a summary of radioactivity released in liquid l and gaseous effluents, and solid waste shipped from the Callaway ' Plant during the period from January 1, 1994 to December 31, 1994. I The information is presented in the format outlined in Appendix B of l Regulatory Guide 1.21, Revision 1, June 1974. l l All liquid and gaseous effluents discharged during this reporting i period were in compliance with federal regulations and the limits of .) Union Electric Administrative Procedure APA-ZZ-01003, Offaite Dose ! Calculation Manual (ODCM). 3.O SUPPLEMENTAL INFORMATION 3.1 Reculatory Limits Specified as follows are the Radiological Effluent Control (REC) limits applicable to the release of radioactive material in liquid and gaseous effluents. 3.1.1 Fission and Activation Gases (Noble Gases) j l The done rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total l body and less than or equal to 3000 mrem /yr to the skin. The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be li;ited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.2 Radiciodine, Tritium, and Particulates The dose rate due to Iodine-131 and 133, tritium and all radionuclides in particulate form with half-lives greater than eight (B) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem /yr to any organ. The dose to a member of the public from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluent o released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, 1 .
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Appendix B, Table II, Column 2 to 10CFR20.001 to 20.601 for radionuclides other than disso'.ved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/El to:al activity. The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem
- to the total body and less than or equal to 5 mrem to any organ, and
- b. During any crlendar year to less than or equal io.3 mrem to the whole body and to less than or equal to 10 mrem to any organ.
2.1.4 Uranium Fuel Cycle Sources The annual lealendar 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 mrem to the total body or any organ, except the thyroid, which shall ba limited to less than or equal to 75 mrem. 2.2 Maximum Permissible ConcentratisLqg 2.2.1 The maximum permissible concer.!xation values specified in Appendix B, Table II, Column 2 to 10CFR20.001 to 20.601 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the limiting concentration for dissolved and entrained noble gases in liquid effluents. 2.2.2 For gaseous effluents, maximum permissible concentrations are not utilized in release rate calculations since the applicable limits are based on dose rate at the site boundary. The " Percent of Tech , Spec Limit" for Table LA is therefore not applicable to the callaway Plant. ' 2.3 Avernoe Enerev This requirement is not applicable to the Callaway Plant radiological effluent monitoring program since the release rate limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture. 2.4 Measurements and Acoroximations of Total Radioactivity 1.M .iuclide concentrations in liquid and gaseous effluents was
<tained by effluent sampling and radiological analysis in
_ccordance with the requirements of Table 9.3-A and Table 9.6 A of APA-ZZ-01003, Offsite Dose Calculation Manual. s
t Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, and Fo-55 by an independent laboratory. Tritium and gross alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively. The total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.
- 2.5 Batch Releases '
Summary information relating to batch releases of gaseous and liquid effluents to the environment from the Callaway Plant during this , year is presented below. 2.5.1 Licuid Number of batch releases: 249 Total time period for batch releases: 115,941 minutes Maximum time period for a batch release: 1,843 minutes Average time period for batch releases: 466 minutes Minimum time period for a batch release: 8 minutes Average stream flow during periods of release of effluent into a flowing stream: 92,481 cfs* ,
*Ref: Letter, United States Department of the Interior - Geological ,
Survey - Ndssouri, dated January 23, 1995. l 2.5.2 Gaseous Total fwr the Reoortina Period Number of batch releases: 91 Total time period for batch releases: 15,191 minutes Maximum time period for a batch release: 2,229 minutes Average time period for batch releases: 16" minutes Minimum time period for a batch release: 19 minutes 2.6 Unclanned Releases 2.6.1 Licuid Number of releases: 0 Total Activity released: O Ci l l 3-l 1 I
1 1 I l 2.6.2 Gaseous Number of releases: 0 l l Total Activity released: O Ci 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 3.1 The quantity of radioactive material released in gaseous effluents during the year is summarized in Tables LA and IB. During this year all gaseous effluents were considered as ground level releases. , 4.0
SUMMARY
OF LIOUID RADIOACTIVE EFFLUENTS 4.1 The quantity of radioactive material released in liquid effluents during the year is summarized in Tables 2A and 2B, During this year there was no continuous release of liquid effluent from the plant. 5.0 SOLID WASTES 5.1 The quantities of radioactive material released in shipments of solid waste for burial and irradiated fuel transported from the site during the year are summarized in Table 3. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory. The curie concentration of each nuclide listed in Table 3 was determined as the product of the fractional abundance and the total curies shipped. Those nuclides which comprise at least it of the total activity for a particular waste type are presented in Table 3. 6.0 RELATED INFORMATION 6.1 Unclanned Releases 1 Unplanned releases are: 1) Inadvertent or accidental releases o.1 radioactive material; 2) Releases of radioactive material via normal pathways without a release permit, proper authorization, or proper sampling and analysis; and 3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit. There were no unplanned releases during the reporting period. 6.2 Chances to the Process Control Procram ' There were no changes made to Administrative Procedure APA-ZZ-01011,
" Process Control Program Manual", during this year.
6.3 Chances to the Offsite Dose Calculation Manual Revision 4 of Administrative Procedure APA-ZZ-01003, Offsite Dose " Calculation Manual (.O DCM) was approved September 30, 1994 In this revision the minimum number of radioactive gaseous effluent monitoring instrument channels required operable for the containment purge system were increased from 1 channel to 2 channels. Also, the associated action statement was revised to allow containment purges to continue for 72 hours with one monitor out of service during modes 1, 2, 3, and 4. 4 . t
4 A complete copy of Administrative Procedure APA-ZZ-01003, Revision 4 is included as Attachment 1. 6.4 Maior Chances to Radwaste Treatnent Systems During the year there were no changes to the plant which would be considered a major change to a Liquid, Gaseous, or Sclid Radwaste Treatment System. 6.5 Land Use Census Chances , There were no changes identified in critical receptor locations for dose calculations during this year's Land Use Census. 6.6 Inocerability of Effluent M3nitorino Instrumentation All effluent monitoring instrumentation was OPERABLE within the limits specified by APA-ZZ-01003, Section 9.1.1 and 9.2.1'during the year. 6.7 Instances of Licuid Holduo Tanks or Waste Gas Decav Tanks Exceedino Technical Soecification Limits All liquid tanks and waste gas decay tanks were within the limits of Technical Specifications 3.11.1.4 and 3.11.2.6 during the reporting period. ' 7.0 METEOROLOGICAL DATA The on-site meteorological data for this reporting period is presented in Table 4. The data is presented as Cumulative Joint Frequency Distributions of wind speed and wind direction by atmospheric stability class for the 10 and 60 meter tower elevations. This year's valid data recovery was greater than 90% for all required parameters. 8.0 ASSESSMENT OF DOSES Assessment of dose to the maximum exposed individuals from gaseous and liquid effluents released was performed for locations representing the maximum dose. This assessment is performed in accordance with Administrative Procedure APA-ZZ-01003 as described in the following sections. For all effluent released from the Callaway Plant during this year, the annual dose to the maximum exposed individuals was less than 1 % of the Radiological Effluent Control limits presented in Section 2.1 of this report. i 8.1 Dose at the Site Boundarv from Gaseous Effluents The dose at the Site Boundary is due to plume exposure from noble gases, ground plane exposure, and inhalation. It is conservatively assumed a hypothetical maximum exposed individual is present at the Site Boundary location with the most limiting atmospheric dispersion parameter, based on actual meteorological conditions for { the year. Dose is conservatively calculated using a child as the i critical age group. 1 The dose from gaseous effluent at the Site Boundary for 1994 is I presented in Table 5. i 5-I
8.2 Dose to the MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC is considered to be a real individual, including all persons not occupationally associated with the plant, but who use portions of the plant site for recreational or other purposes not associated with the plant operation. This individual's utilization of areas both inside and outside the Site Boundary are characterized for this calculation. To evaluate total dose from,the Uranium Fuel Cycle to any MEMBER OF THE PUBLIC, the critical MEMBER OF THE PUBLIU within the Site Boundary, and the Nearest Resident were evaluated. 8.2.1 Dose at the Nearest Resident from Gaseous Effluent The dose to the Nearest Resident is due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion. Dose is calculated at the nearest actual resident location with the most limiting atmospherie dispersion, based on meteorological conditions for the year. It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at this location. Dose is conservatively calculated assuming the child as the critical age group. Dose from activities within the Site i Boundary is negligible and not included in this calculation. The doses to the Nearest Resident for 1994 are presented in Table 5. 8.2.2 Dose to the MEMBER OF THE PUBLIC from Activities within the site Boundarv Based on existing land use within the Site Boundary, the MEMBER OF THE PUBLIC with the highest dose would be a farmer. Dose from farming activities within the Site Boundary is due to direct radiation exposure, plume exposure from noble gases, ground plane exposure, and inhalation. The current tenant estimates spending 1100 hours per year working within the Site Boundary area. Dose is calculated using the adult farmer as the critical age group. Dose to the MEMBER OF THE PUBLIC from activities within the Site Boundary is presented in Table 6. 8.3 Total Dese Due to the T9anium Fuel Cycle Since there are no ather Uranium Fuel Cycle facilities within 8 kilometers of the Callaway Plant, the tecal dose to the most likely exposed MEMBER OF THE PUBLIC results from direct radiation exposure and radioactive effluents from Callaway Plant itself. Therefore, Dose from mining, fuel fabrication, and waste disposal are not included in this calculation. Since dose via liquid releases is conservatively evaluated, reasonable assurance exists that no real individual will receive a significant dose from radioactive liquid release pathways. Therefore, only dose to individuals from airborne pathways and dose resulting from direct radiation are considered in this assessment. The total dose to the MEMBER OF THE PUBLIC within the Site Boundary (Table 7) is the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence. It is assumed that each food ingestion pathway exists l
'1 1
i i l I ^ at his' residence. Dose i.s calculated using the adult farmer as the ! critical age group. The total dose from the Uranium Fuel Cycle is presented in Table 7. ; 8.4 Dose Due to Liould Effluents Dose due to liquid effluents assumes contribatisns from the maximum ; exposed individual's consumption of fish and potable water, as appropriate. An adult is considered to be the maximum exposed individual in this assessment. As there are currently no potable water intakes within 50 river .; miles of the' discharge point to the Missouri River, the' potable , water pathway is not included in the dose assessment. Therefore, i dose contribution from fish consumption accounts for 95% of the total dose from liquid effluents discharged to the river. Dose ' from recreational activities contributes the additional 5%. It is ; conservatively assumed the hypothetical maximum exposed individual ! obtains his entire annual fish intake from near the plant discharge. . i Total dose due to liquid effluents from Callaway Plant during the < year is presented in Table 8. i 5 l 4 l 6 5 I b L 7 .
l l TABLE 1A SEMIANNUAL SUMMATION OF GASEOUS RELEASES
' ALL AIRBORNE EFFLUENTS
]
QUARTERS 1 AND 2,1994 - FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER , QUARTER ERROR % (a) i A. FISSION AND ACTIVATION GASES ,
- 1. TOTAL RELEASE CURIES 8.46E+00 1.4IE+01 20 ).
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.09E+00 1.79E+00 l
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A l i
B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 335E-06 7.78E-06 23 !
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 431E-07 9.89E-07 f
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A :
s C. PARTICULATES i
- 1. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 7.43E-06 1.02E-07 30
- 2. AVERAGE RELEASE RA*IE FOR PERIOD uCi/SEC 9.55E-07 1.29E-08 f
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A j
- 4. GROSS ALPHARADIOACTIVITY CURIES 5.02E-07 3.59E-07 i D.1RITIUM ,
- 1. TOTAL RELEASE CURIES 133E+01 3.52E+01 14 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.71E+00 4.48E+00 ;
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A '
f (a) Safety Analysis Calculation 87-063-00, January 6,1988 , 5 t Page 1 of 2 j
l TABLE 1A j l 7 SEMIANNUAL SUMMATION OF GASEOUS RELEASES i ALL AIRBORNE EFFLUENTS f QUARTERS 3 AND 4,1994 i THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) i I i A. FISSION AND ACTIVATION GASES l CURIES 6.07E+00 4.38E+00 ' 20 1.'IOTAL RELEASE ]
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 7.64E-01 5.51E-01 f
- 3. PERCENT OFTECH SPEC LIMIT % N/A N/A t
B.RADIOIODINES t
- 1. TOTAL IODINE-131 CURIES 3.64E-06 4.48E-07 23
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 4.58E-07 5.63E-08 l
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A r
C. PARTICULATES
- l. PARTICULATE (HALF-LIVES > 8 DAYS) CURIES 2.87E-06 3.45E-06 30 l
- 2. AVERAGE RELEASE RA'IE FOR PERIOD uCi/SEC 3.62E-07 4.34E-07 f
- 3. PERCENT OFTECH SPEC LIMIT % N/A N/A !
- 4. GROSS ALPHA RADIOACTIVITY CURIES 4.91E-07 3.68E-07 I
i D."IRITIUM e i
- 1. TOTAL RELEASE CURIES 2.29E+01 1.80E+01 ' 14
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC ' 2.88E+00 2.27E+00 j
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A {
r h (a) Safety Analysis Calculation 87-063-00, January 6,1988 f i
-i Page 2 of 2 )
b i
x , j i TABLEIB SEMIANNUAL AIRBORNE CONTINUOUS AND BAKH RELEASES ! GROUND LEVEL RELEASES ! FISSION GASES, IODINES, AND PARTICULATES .} I QUARTERS 1 AND 2,1994 l l CONIINUOUS RELEASES BAKH RELEASES ; i FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER !
- 1. FISSION GASES KR-88 CURIES 4.94E-01 0.00E+00 1.54E-04 0.00E+00 -l AR-41 CURIES 0.00E+00 0.00E+00 5.97E-02 7.53E-02 l KR-85M CURIES 1.08E-01 0.00E+00 5.63E-04 5.06E-04 i XE-133 CURIES 1.40E+00 6.44E+00 8.71E-01 1.45E+00 !
XE 133M CURIES 0.00E+00 0.00E+00 L11E-02 1.87E-02 l XE 135 CURIES 2.97E+00 6.08E+00 1.78E-02 4.04E-02 i KR-85 CURIES 0.00E+00 0.00E+00 2.52E+00 0.00E+00 l XE 131M CURIES 0.00E+00 0.00E+00 8.05E-03 0.00E+00 ! XE-127 CURIES 0.00E+00 0.00E+00 3.59E-05 0.00E+00 . ! XE 135M CURIES 0.00E+00 0.00E+00 0.00E+00 7.95E-05 l l TOTAL FOR PERIOD CURIES 4.97E400 1.25E+01 3.49E+00 1.59E+00
- 2. IODINES I133 CURIES 1.65E-05 3.19E-05 0.00E+00 8.80E-09 l 1 131 CURIES 335E-06 7.78E-06 1.99E-09 0.00E+00 l f
TOTAL FOR PERIOD CURIES 1.98E-05 3.97E-05 1.99E-09 8.8CE-09
~ 3.PARTICULATES l NB-95 CURIES 4.22E-06 0.00E+00 0.00E+00 0.00E+00 ZR-95 CURIES 2.46E-06 0.00E+00 0.00E+00 0.00E+00 i CO-58 CURIES 7.41E-07 1.02E-07 0.00E+00 0.00E+00 l 0.00E+00 ALPHA CURIES - 5.01E-07 3.59E-07 8.01E j TOTAL FOR PERIOD CURIES 7.93E-06 4.61E-07 8.01E 10 0.00E+00 }
- 4. TRITIUM l H-3 CURIES 131E+01 3.44E+01 1.72E-01 8.00E-01 !
1 . Page 1 of 2
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i TABLE IB SEMIANNUAL AIRBORNE CO?(11NUOUS AND BA'ICH RELEASES GROUND LEVEL RELEASES l FISSION GASES IODINES, AND PARTICULATES j QUARTERS 3 AND 4,1994 l 1 COril1NUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH , NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER
- 1. FISSION GASES KR 88 CURIES 0.00E+00 0.00E+00 2.68E-04 0.00E+00 AR-41 CURIES 0.00E+00 0.00E+00 4.69E-01 9.64E-01 KR-85M CURIES 0.00E+00 0.002+00 3.20E.04 0.00E+00 XE-133 CURIES 2.12E+00 237E+00 2.62E+00 7.52E-01 i
XE-133M CURIES 0.00E+00 0.00E+00 2.42E-02 0.00E+00 XE-135 CURIES 7.81E-01 2.62E-01 4.77E-02 2.56E-02 KR-85 CURIES 0.00E+00 0.00E+00 0.00E40 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 3.42E-03 0.00E+00 , XE-127 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-135M CURIES 0.00E+00 0.00E+00 1.06E-04 7.25E-05 KR-87 CURIES 0.00E+00 0.00E+00 0.00E400 1.08E-05 t TOTAL FOR PERIOD CURIES 2.90E+00 2.63E+00 3.17E+00 1.74E+00 2.lODINES f l I-133 CURIES 2.05E-05 0.00E+00 2.10E-08 5.20E-09 l I131 CURIES 3.63E-06 4.46E-07 4.60E-09 136E-09 0.00E+00 4.96E-09 1.76E-09 I-132 CURIES 0.00E+00 I-135 CURIES 0.00E+00 0.00E+00 135E48 6.19E-09 ! TOTAL FOR PERIOD CURIES 2.4IE-05 4.46E-07 4.40E-08 1.45E-08 j i 3.PARTICULATES l NB-95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ! CO-58 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 : CS-138 CURIES 0.00E+00 0.00E+00 7.80E-07 3.27E-07 ! SB-125 CURIES 1.71E-06 0.00E+00 0.00E+00 0.00E+00 TC-99M CURIES 3.84E-07 0.00E+00 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 1.49E-06 0.00E+00 0.00E+00 i PR 144 CURIES 0.00E+00 1.49E-06 0.00E+00 0.00E+00 CO-60 CURIES 0.00E+00 139E47 0.00E+00 0.00E+0c ' ALPHA CURIES 4.91E-07 3.68E-07 0.00E+00 0.00E+0D ; TOTAL FOR PERIOD CURIES 2.59E-06 3.49E-06 7.80E-07 3.27E-07 t
- 4. TRITIUM H-3 CURIES 1.82E+01 1.48E+01 4.63E+00 3.23E+00 Page 2 of 2 l
TABLE 2A i SEMIANNUAL SUMMATION OF LIQUID RELEASES ! ALL LIQUID EFFLUENTS l QUARTERS 1 AND 2,1994 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) i A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOT INCLUDING TRITIUM. GASES, ALPHA] CURIES 2.78E-03 6.24E-03 20
- 2. AVERAGE DILUTED CONCENTRATION I DURING PERIOD uCi/ML 5.29E-09 1.IIE-08 1
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A B. TRITIUM i
- 1. TOTAL RELEASE CURIES 1.07E+02 3.88E+02 14
- 2. AVERAGE DILU'IED CONCENTRATION DURING PERIOD uCi/ML 2.N E-04 6.93E-04
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.31E44 130E-03 27
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.50E-10 231E-09 D. GROSS ALPHA RADIOACTIVITY
- l. TOTAL RELEASE CURIES 1.97E-03 3.90E-04 29 E. WASTE VOLUME RELEASED (PRE-DILIJTION) GAL 6.04E+06 5.67E+06 10 F. VOLUME OF DILUTION WATER USED GAL 1.33E+08 1.42E408 10 (c) Safety Analysis Calculation 87-063-00, January 6,1988 4
Page 1 of 2
TABLE 2A SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 3 AND 4,1994 THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) A. FISSION AND ACITVATION PRODUCTS
- 1. "IOTAL RELEASE [NOTINCLUDING TRITIUM, GASES, ALPHA] CURIES 539E-04 137E-04 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.19E-09 3.41E-10
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A B. TRITIUM
- 1. TOTAL RELEASE CURIES 2.55E+02 2.80E+02 14
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.61E-Ot 7.01E-04
- 3. PERCENT OF APPLICABLE LIMIT % N/A N/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 2.05E-03 5.02E-03 27
- 2. AVERAGE DILIJIED CONCENTRATION DURING PERIOD uCi/ML 4.52E-09 1.26E-08 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 5.86E-Ot 4.42E-Of 29 E. WASTE VOLUME RELEASED (PRE-DILUTION) GAL 5.79E+06 5.59E+06 10 F. VOLUME OF DILUTION WATER USED GAL 1.14E+08 1.00E+08 10 (a) Safety Analysis Calculation 87-063-00, January 6,1988 1
Page 2 of 2
F -l E , p ; TABLE 2B . l SEMIANNUAL LIQUID CONTINUOUS AND B ATCH RELEASES l TOTALS FOR EACH NUCLIDE RELEASED q l QUARTERS 1 AND 2,1994 - t i CONTINUOUS RELEASES BA'ICH RELEASES _ FIRST SECOND FIRST SECOND l NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER. j
.i
- 1. ALLNUCLIDES -!
ALPHA CURIES 0.00E+00 ' O.00E+00 1.97E-03 3.90E-04 i' H-3 CURIES 0.00E+00 0.00E+00 1.07E+02 3.88E+02 ; SR-89 CURIES 0.00E+00 0.00E+00 7.22E-04 0.00E+00 XE 135 CURIES 0.00E+00 0.00E+00 2.23E-06 1.75E-05 -l CO-60 CURIES 0.00E+00 0.00E+00 333E-04 1.93E-04 i CO-58 CURIES 0.00E+00 0.00E+00 1.93E-04 6.42E-05 ! MN-54 CURIES 0.00E+00 0.00E+00 2.70E-05 8.25E-06 i NB-95 CURIES 0.00E+00 0.00E+00 1.85E-05 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 1.24E-05 0.00E+00 ! CS 137 CURIES 0.00E+00 0.00E+00 2.43E 3.85E-05 i CS-134 CURIES 0.00E+00 0.00E+00 8.84E-06 2.66E-05 i XE-133 CURIES 0.00E+00 0.00E+00 . 1.29E-04 1.28E-03 l FE-55 ' CURIES 0.00E+00 0.00E+00 1.40E-03 5.89E-03 l CE-144 : CURIES 0.00E+00 0.00E+00 1.56E-05 1.84E-05 I o NA-24 CURIES 0.00E+00 0.00E+00 2.40E-05 0.00E+00 ! 0.00E+00 . 0.00E+00 - 1.92E-06 i IN-113M CURIES 0.00E+00 SN 113 CURIES 0.00E+00 0.00E+00 . 0.00E+00 1.92E l TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 1.07E402 3.88E+02 l i l 1 i l l i i Page 1 of 2 f i I I
TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BA*ICH RELEASES . TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 3 AND 4,1994 l l CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER l QUARTER QUARTER QUARTER
- 1. ALL NUCLIDES ALPHA CURIES 0.00E+00 0.00E+00 5.86E-04 4.42E-04 H-3 CURIES 0.00E+00 0.00E+00 2.55E+02 2.80E+02 SR-89 CURIES 0.00E+00 0.00E+00 0.00E+00, 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 3.62E-05 0.00E+00 CO-60 CURIES 0.00E+00 0.00E+00 134E-04 6.00E-05 CO-58 CURES 0.00E+00 0.00E+00 1.75E-05 0.00E+00 l
MN-54 CURIES 0.00E+00 0.00E+00 130E-05 0.00E+00 NB-95 CURIES 0.00E+00 0.00E+00 5.22E-06 0.00E+00 ZR-95 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-137 CURIES 0.00E+00 0.00E+00 1.76E-05 1.42E-05 CS-134 CURIES 0.00E+00 0.00E+00 0.00E+00 3.23E-06 XE-133 CURIES 0.00E+00 0.00E+00 2.02E-03 4.86E-03 FE-55 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NA-24 CURES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 IN-ll3M CURES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SN-113 CURES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-90 CURES 0.00E+00 0.00E+00 338E-04 5.08E-05 AG-110M CURES 0.00E@ 0.00E+00 6.07E-06 0.00E+00 SB-125 CURES 0.00E+00 0.00E+00 4.82E-06 0.00E+00 I-133 CURES 0.00E+00 0.00E+00 2.92E-06 0.00E+00 XE 131M CURES 0.00E+00 0.00E@ 0.00E+00 1.60E-04 BA 133M CURIES 0.00E+00 0.00E+00 0.00E+00 8.21E-06 TOTALS FOR PERIOD CURES 0.00E+00 0.00E+00 2.55E+02 2.80E+02 i l Page 2 of 2
i TABLE 3 SOLID WASTE & IRRADIATED FUEL SHIPMENTS 122.1 A. SOLID WASTE SHIPPED OFFSITE FOR BUFIAL OR DISPOSAL (DOES NOT INCLUDE IRRADIATED FUEL) TYPE OF WASTE 6-MOhTH EST. TOTAL PERIOD _ ERROR (%) _
- c. Spent resins, filter slu'dges 24.78 m' evaporator bottoms, etc. 7.12E+02Ci 125%
Nuclide Percent Abundance Curies Cs-134 22.032% 1.56E+2 Fe-55 20.349% 1.44E+2 Co-58 18.478% 1.31E+2 Cs-137 18.399% 1.31E+2 Co-60 6.340% 4.50E+1 Be-7 4.705% 3.34E+1 Mn-54 3.642% 2.59E+1 Ni-68 2.348% 1.67E+1 Sb 125 1.629% 1.16E+1
- b. Dry compressible waste, 47.13 m*
contaminated equipment, etc. 7.64E+00 Ci 125% Nuclide Percent Abundance Curies Fe-55 49.941% 3.82E+0 Co-60 23.721% 1.81E+0 Ni-63 11.661% 8.91E-1 Mn-54 4.506% 3.44E-1 Co-58 4.367% 3.34E-1 Sb-125 1.612% 1.23E-1 Cr-51 1.527% 1.17E-1 Nb-95 1.433% 1.09E-1
- c. Irradiated components, control 0.24 m*
rods, etc. 6.34E-02 Ci Nuclide Percent Abundance Curies Fe-55 69.30% 4.40E-2 Co-60 25.70% 1.63E-2 Mn-54 2.80% 1.76E-3 Ni-63 1.90% 1.21E-3 *
- d. Other: Solidified oil and oil sludges O m' 0 Ci Solid waste Discosition Number of Mode of Class of Solid 7ype of l Shioments Transoortation Destination Waste Shicoed Container ,
l 10 Cask Barnwell, SC A,B,C LSA l + 1 Truck Oak Ridge, TN A LSA 1 (QUADREX) 12 Truck Oak Ridge, TN (SEG) A LSA l Page 1 of 2 ' i 1
4 *
- 1. ,
3
;m i?
TABLE 3 (cont'd.) SOLID WASTE & IRRADIATED FUEL SHIPMElfrS OUARTERS 3 & 4, 1993 Solidification Acent . None used.
- B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Nu=har of Shioments Mode of Transoortation Destination 0 N/A N/A-5 I 4-l t a 4 4 4 j j Page 2 of 2 g , ,,s , m
i ' TABLE 4 l N Union Electric- Callaway Plant ReportDate/rirne: 9-MAR-199513:43:09.44 l
. Meteorological Data Averages Using Hourly Averaged Data' 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 i
. % GOOD -
UNITS VALUES DATA .i Stability Class A-G E 98 % Total Precipitation CM. 2.64E+02 94 % 10 Meter Level: Wind Speed Meter /Sec 3.07E+00 '99%.
;. Wind Direction Degrees 1.83E+02 98 % ;
Wind Direction Variability Degrees 1.30EW1 98 % Reference Temperature Degrees C 1.23E41 99% Dewpoint Degrees C 5.02E+00 97 % 60 Meter Level: Wind Speed Meter /Sec 4.86E40 97 % ! Wind Direction Degrees 1.%Ed2 95 % Wind Direction Variability . Degrees 8.70E40 98% - Dewpoint Degrees C .NONE 0% Temperature Difference 60 - 10 Degrees C 3.33E41 98 % i t t i i i Page 1 of 15
. _ _ = _ _ . . - _
TABLE 4 Cont. I EUnion Electric - Callaway Plant Report Date/Ilme: 9-MAR-199513:43:34.24 i Meteorological Data ) Totals of Hours at Each Wind Speed & Direction , 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 Stability Class: A 3 j Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL ! N 0 1 1 0 0 0 2 -* t
'I NNE O O 0 0 0 0 0 NE 0 'l 0 0 0 0 1 j ENE 0 0 0 0 0 0 0. ,
E 0 0 0 0 0 0 0 i ESE O 3 0 0 0 0 3 i-i SE O 14 2 0 0 0 16 l SSE 1 24 10 1 0 0 36 i S , 0 29 9 4 0 0 42 ! SSW 0 29 42 6 0 0 77 i SW 0 8 10 3 0 0 21 ! WSW 1 4 1 0 0 0 6' W 0 1 2 0. 0 0 3 i WNW 1 0 1 0 0 0 2 i NV/ 0 0 0 7 0 0 7 ! NNW 0 0 2 1 0 0 3 i TOT 3 114 80 22 0 0 219 I l Hours of Calm Data: 2 I Hours ofInvalid Data: 5 ! l Page 2 of 15
. - . + - , .-
TABLE 4 Cont. l Unisn Electric - Callaway Plant Report DateFune: 9-MAR-199513:43:34.24 3 Meteorological Data - i Totals of Hours at Each Wind Speed & Direction j 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 Stability Class: B ~ Wind Speed at 10.00 Meter Level (MPH) , i 1-3 4-7 8-12 13-18 19-24 >24 TOTAL j N 0 2 0 0 0' 0 2 , NNE O 0 1 0 0 0 1 f NE O l' 0 0 0 0 1 { ENE 0. 1 0 0 0 0 1 E. I 1 0 0 0 0 2' ! ESE O 2 2 0 0 0 4 l SE 0 18 5 0 0 0 23 t SSE 0 14 7 4 0 0 25 l S 1 15 12 5 0 0 33 SSW 1 14 14 2 0 0 31 SW 2 16 9 3 0 0 30 WSW 1 1 2 0 0 0 -4 W 1 6 3 0 0 0 10 WNW 0 1 3 0 0 0 4 NW 0 3 4 6 0 0 13 NNW 0 1 4 0 0 0 5 TOT 7 96 66 20 0 0 189-Hours of Calm Data: 0
; - Hours ofInvalid Data: 8 i
Page 3 of 15
TABLE 4 Cont. 1 l
' Union Electric - Callaway Plant Report DateKune: 9-MAR-199513:43:3 i
Meteorological Data Totals of Hours at Each Wind Speed & Direction ; 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 l Stability Class: C - Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL , N 0 -- 3 7 2 0 0 12 NNE 1 1 0 0 0 0 2 l NE 2 7 2 0 0 0 11 ENE 1 1 1 0 0 0 3 , 4 E 0 4 1 0 0 0 5- ; ESE 0 3 1 0 0 0 4 SE O 12 11 2 0 0 25 SSE O 21 18 2 0 0 41 : S 2 14 16 6 0- 0 38 ! SSW 0 26 18 2 0 0 46 ( SW 0 15 9 3 0 0 27 l WSW 2 4 5 1 0 0 12 i W 2 7 5 0 0 0 14 WNW 1 5 13 0 0 0 19- , NW 1 6 11 1 0 0 19 i NNW 0 2 16 0 0 0 18 TOT 12 131 134 19 0 0 2% Hours of Calm Data: 0 Hours ofInvalid Data: 9 Page 4 of 15 I
TABLE 4 Cont. . ~ Union Electric- Callaway Plant Report Date/ rime: 9-MAR-199513:43:34.24 Meteorological Data Totals of Hours at Each Wind Speed a Direction 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 . l Stability Class: D Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12' 13-18 19-24 >24 TOTAL N 6 80 61 6 .0 0 153 NNE 8 77 32 1 0 0 118 1 NE 10 60 21 0 0 0 91 - ENE 11 59 42 1 0 0 113 , E 5 29 24 0 0 0 58 j ESE 7 55 22 2 0 0 S6 SE 13 75 58 13 0 0 159 SSE 13 70 36 13 0 0 132 S 19 51 63 16 1 0 150 SSW 7 47 73 18 2 0 147 [ SW 12 35 25 24 1 0 97 > WSW 11 27 18 4 0 0 60 W 16 43 42 12 1 0 114 , WNW 6 45 56 15 2 0 124 NW 11 55 75 11 0 0 152 ! NNW 8 58 F7 2 0 0 155 TOT 163 866 735 138 7 0 1909 Hours of Calm Data: 1 Hours ofInvalid Data: 54 , Page 5 of 15
TABLE 4 Cont. Union Electric- Callaway Plant Report Date/ rime: 9-MAR-199513:43:34.24 . Meteorological Data , Totals of Hours at Each Wind Speed & Direction 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 Stability Class: E Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL r i N' 28 136 108 12 0 0 284 NNE 48 162 63 6 0 0 279 l NE 55 137 38 0 0 0 230 l i ENE 29 118 47 2 0 0 1% E' 31 112 61 0 0 0 204 l i ESE 16 116 87 3 0 0 222 SE 30 149 138 15 0 0 332 j SSE 22 126 127 22 0 0 297 f S 35 124 129 31 0 0 319 i i SSW 25 85 41 9 0 0 160 SW 25 70 49 9 0 3 156 j WSW 23 47 30 15 5 0 120 ; t W 25 59 60 19 0 0 163 l 1 WNW 35 130 55 10 0 0 230 NW 37 110 130 10 0 0 287 NNW 41 135 82 14 0 0 272 j TOT 505 1816 1245 177 5 3 3751 ! Hours of Calm Data: 16 ! Hours ofInvalid Data: 62 i i Page 6 of 15 ; i
TABLE 4 Cont. , i
-Uni:n Electric - Callaway Plant Report Date/ Time: 9-MAR-199513:43:34.24 !
Meteorological Data '! Totals of Hours at Each Wind Speed & Direction l 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 ; i Stability Class: F Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18. 19-24 >24 TOTAL l N- 26 22 3 0 0 0 51 ; NNE 35 - 30 1 0 0 0 66 NE 45 19 1 0 0 0 65 ENE 41 20 2 0 0 0 63 l E 27 16 0 0 0 0 43 j ESE 26 43 1 0 0 0 70 . SE 34 124 22 0 0 0 180 ! l SSE 28 178 28 0 0 0 234 l S 19 120 58 0 0 0 197 j SSW 23 45 14 0 0 0 82 j SW 20 37 20 0 0 0 77 l WSW 23 23 5 0 0 0 51 i t W 30 42' 7 0 0 0 79 l WNW 37 41 2 0 0 0 80 NW 27 27 0 0 0 0 54 I NNW 26 32 1 0 0 0 59 TOT 467 819 165 0 0 0 1451 1
- Hours of Calm Data: 27 Hours ofInvalid Data: 36 Page 7 of 15
. . . . . . . - . . = - - - - _- .. .. 1 TABLE 4 Cont. 1 Union Electric - Callaway Plant ReportDate/I~une: 9-MAR-199513:43:34.24 Meteorological Data Totals of Hours at Each Wind Speed & Direction . 31-DEC i993 00:55:31.29 to 31-DEC-1994 23:00:00.00 i Stability Class: G l Wind Speed at 10.00 Meter Level (MPH) - 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 33 24 0 0 0 0 57 ! NNE 0 0 31 13 0 0 44 NE 49 4 0 0 0 0 53 l ENE 14 1 9 0 0 0 24 E 14 7 5 4 0 0 30 ESE 15 1 0 0 0 0 16 SE 29 49 1 0 0 0 79 ; SSE 40 69 4 0 0 0 113 l t S 22 37 2 0 0 0 61 < SSW 21 16 1 0 0 0 38 ! SW 17 10 1 0 0 0 28 . i WSW 14 4 0 0 0- 0 18 . W 12 10 0' 0 0 0 22
-l WNW 18 16 0 0 0 0 34 1
NW 22 25 0 0 0 0 47 : NNW 23 28 0 0 0 0 51- l TOT 374 314 23 4 0 0 715 i Hours of Calm Data: 20 ! Hours ofinvalid Data: 4 ) Hours of Good Data: 85% = 97.9% of Total Hours i l i Page 8 of 15 ) l l
1
. TABLE 4 Cont. ;. Union Electric - Callaway Plant Report Date/ rime: 9-MAR-199513:43:53.12 Meteorological Data Totals of Hours at Each Wind Speed & Direction 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 Stability Class: A Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 1 0 1 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 1 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E O O 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE O 8 3 0 0 0 11 SSE O 13 18 1 0 0 32 S u 16 19 3 2 0 40 SSW 0 12 37 9 4 0 62 SVV 1 4 14 10 2 0 31 WSW 0 0 1 0 0 0 1 W 0 0 2 0 0 0 2 WNW 0 2 1 0 1 0 4 NW 0 0 0 1 6 0 7 NNW 0 0 1 1 0 0 2 TOT 1 58 % 26 15 0 1%
7 Hours of Calm Data: 2 Hours ofInvalid Data: 28 Page 9 of 15
- TABLE 4 Cont.
Union Electric- Callaway Plant Report Date/1'une: 9-MAR-199513:43:53.12 , Meteorological Data Totals of Hours at Each Wind Speed & Direction 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 , P Stability Class: B t Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 3 N 0 1 1 0 0 0 2 NNE O 0 1 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E O 1 0 0 0 0 1 ESE 0 1 3 0 0 0 4 SE 0 6 9 0 0 0 15 ! SSE O 17 10 3 3 0 33 S 1 9 12 9 1 0 32 SSNV 0 6 16 8 1 1 32 SW I 12 9 6 2 0 30 l I WSW 0 3 3 0 1 0 7 W 1 0 4 0 0 0 5 WNW 0 2 3 4 0 0 9 NW 0 2 3 4 6 0 15 1 l NNW 0 1 2 2 0 0 5 TOT 3 61 76 36 14 1 191 Hours of Calm Data: 0 Hours ofInvalid Data: 6
),
T'ABLE 4 Cont. Union Electric - Callaway Plant ' ReportDateffime: 9-MAR-199513:43:53.12 i Meteorological Data Totals of Hours at Each Wind Speed & Direction 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 Stability Class: C Wind Speed at 60.00 MeterI2 vel (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL , N 0 0 4 7 0 0 11
'l NNE 0 1 1 0 0 0 2 ;
NE 0 2 4 0 0 0 6 l ENE O 5- 2 0 0 0 7 , E 1 0 2 0 0 0 3 ! ESE 1 0 2 0 0 0 3 i SE 4 10 3 0 0 18 1 f SSE 1 18 16 7 0 0 42 'f i S 0 13 12 7 3 0 35
' 13 SSW 0 28 14 0 0 55 SW 0 9 11 6 1 1 28 WSW 0 3 2 4 2 0 11 W I 4 7 3 0 0 15 WNW 0 3 11 8 0 0 22 f NW 0 2 10 1 1 0 14 !
NNW 1 2 7 8 0 0 18 TOT 6 79 129 68 7 1 290 , Hours of Calm Data: 0 Hours ofInvalid Data: 15 , i Page 11 of 15 i
TABLE 4 Cdnt. - 2 Union Electric- Callaway Plant ReponDate/ rime: 9-MAR-199513:43:53.12 ; i Meteorological Data l Totals of Hours at Each Wind Speed & Direction ! t 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 f l Stability Class: D ; Wind Speed at 60.00 Meter Level (MPH) j 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 35 81 24 2 0 147 : NNE 4 48 61 6 0 0 119 i NE 5 43 38 5 0 0 91 - i ENE 4 46 58 7 0 0 115 f E 4 38 25 0 0 0 67 f ESE 5 35 35 4 0 0 79 I i SE 6 50 57 19 3 0 135 SSE 7 53 53 27 4 0 144-S 3 38 57 33 9 2 142 { SSVV 5 33 65 45 16 3 167 SW 3 28 30 25 11 6 105 WSW 4 17 21 7 5 0 54 ; W 3 24 39 31 11 5 113 WNW 5 26 46 37 8 2 124' i i : NW 2 44 62 36 8 0 152 ! NNW 1 29 77 27 1 0 135 i TOT 68 587 805 333 78 18 1889 l . t Hours of Calm Data: 0 Hours ofInvalid Data: 75 I 4 Page 12 of 15 f
. . . . ,_. . =. .-.
~
TABLE 4 Cont. Union Electric- Callaway Plant Report Date/I'une: 9-MAR-199513:43:53.12 Meteorological Data ! Totals of Hours at Each Wind Speed & Direction { 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 ( Stability Class: E : Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 42 119 78 4 0 249 NNE 9 74 130 47 2 0 262 NE 9 87 131 13 0 0 240 i ENE 8 55 114 22 2 0 201 E 2 56 127 21 0 0 206 [ t ESE 3 55 117 5'S 1 0 231 - t SE 4 47 124 106 4 0 285 SSE 5 21 103 105 9 0 243 S 11 23 109 160 29 1 333 ! SSW 5 30 93 79 8 0 215 SW 6 33 63 53 11 4 170 i WSW 4 25 44 29 16 6 124 W 4 29 50 61 24 1 169 ; WNW 6 29 107 52 8 1 203 NW 12 41 102 124 13 0 292 NNW 9 50 113 59 10 1 242 TOT 103 697 1646 1064 141 14 3665 Hours of Calm Data: 1 Hours ofInvalid Data: 163 i Page 13 of 15 l l
. TABLE 4 Cont.
Union Electw - Callaway Plant Report DateEune: 9-MAR-199513:43:53.12 s Meteorological Data Totals of Hours at Each Wind Speed & Direction ) 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 l l Stability Class: F Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 14 24 11 0 0 53 NNE 3 17 27 3 0 0 50 i NE 5 17 31 2 0 0 55 ENE 0 13 42 5 0 0 60 , E 4 18 50 1 0 0 73 > ESE 4 20 54 11 0 0 89 SE 1 14 79 16 0 0 110 SSE 1 24 110 45 0 'O 180 - S 0 10 120 79 1 0 210 f SSW 3 16 83 77 2 0 181 , SW 1 12 35 35 2 0 85 - , i WSW 0 18 25 13 0 -0 56 i W 0 14 40 23 2 0 79 WNW 2 6 34 28 0 0 70 NW 7 9 27 13 0 0 56 I i NNW 4 13 25 8 0 0 50 ' r TOT- 39 235 806 370 7 0 1457 e Hours of Calm Data: 0 l Hours ofInvalid Data: 57 ; i l Page 14 of 15 i
TABLE 4 Cont.
. Union Electric - Callaway Plant Repon Date/1une: 9-MAR-199513:43:53.12 i
Meteorological Data Totals of Hours at Each Wind Speed & Direction 31-DEC-1993 00:55:31.29 to 31-DEC-1994 23:00:00.00 Stability Class: G Wind Speed at 60.00 Meter Level (MPH) L 1-3 4-7 8-12 13-18 19-24 >24 TOTAL ; N 0 6 22 6 0 0 . 34 i NNE O 3 38 7 0 0 48 l NE 0 12 24 1 0 0 37 ENE 1 9 22 19 0 0 51 j 1 E 0 8 39 11 1 0 59 l ESE 2 8 18 0 0 0 28 SE 0 10 16 2 0 0 28 SSE 1 5 40 3 0 0 49 S 0 12 74 8 0 0 94 SSW 0 17 35 30 1 0 83 SVV 2 2 16 13 1 0 34 WSW 0 18 7 4 0 0 29 W 1 12 8 3 0 0 24 WNW 5 3 5 5 0 0 18 NW 2 7 14 19 0 0 42 NNW 2 4 7 8 0 0 21 TOT 16 136 385 139 3 0 679 Hours of Calm Data: 0 Hours ofInvalid Data: 60 Hours of Good Data: 8370 = 95.3% of Total Hours Page 15 of 15
TABLE 5 ; I DOSE AT THE SITE BOUNDARY AND 'IO THE N'3AT.10T RESIDENT ; FROM GASEOUS EFFLUENTJ j i i STIE BOUNDARY NEARESTRESIDENT : LOCATION: 1.40km SSW LOCATION: 1.90 km WSW AGE GROUP: CHILD AGE GROUP: CHILD f ORGAN UNITS DOSE % LIMIT (a) DOSE % LIMIT (b) ! 1.' GAMMA AIR DOSE
- MRAD 1.74E-03 0.02 9.46E-04 N/A l
- 2. BETA AIR DOSE
- MRAD 2.02E-03 0.01 1.09E-03 N/A i
- 3. WHOLE BODY "* MREM 1.63E-03 N/A 8.85E-04 N/A ,
- 4. SKIN ** MREM 3.13E-03 N/A 1.70E-03 N/A l
- 5. BONE ** MREM 2.06E-06 N/A 5.26E-06 0.00
- 6. LIVER " MREM 3.21E-03 N/A 1.53E-02 0.10 . -l l
- 7. TOTAL BODY " MREM 3.21E-03 N/A 1.53E-02 0.10 ;
i
- 8. THYROID " MREM 3.22E-03 N/A 1.66E 0.11 l
- 9. KIDNEY ** MREM 3.21E-03 N/A 1.53E-02 0.10 !
i
- 10. LUNG " MREM 3.21E-03 N/A 1.53E-02 0.10 i
- 11. GI-LLI ** MREM 3.21E-03 N/A 1.53E-02 0.10 l i
- Dose from Noble Gases only
** Dose frem Tritium, Radioxxhnes, and Particulates only '
*** Dose fmn Noble Gases plus Ground Plane dose 1
(a) Annuel dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 10 mrad gamma air dose and 20 mrad beta air dose. i r (b) Annual dose limits of Offsite Dose Calculation Manual (APA ZZ-01003) of 15 mrem to any organ from I-131,1-133. H-3 and particulate j radionuclides with halflives greater than 8 days. Page 1 of1 i
TABLE 6 DOSE 70 THE MEMBER OF THE PUBLIC FROM ACTIVITIES WITHIN THE SITE BOUNDARY l l i EFFLUENT DIRECT DmECT TOTAL i' DOSE WITHIN RADIATION RADIATION DOSE THE SITE FROM THE FROM OUTSIDI FOR THE ORGAN UNITS BOUNDARY UNIT TANKS YEAR . t i
- 1. SKIN MREM 5.77E-04 N/A N/A 5.77E-04
- 2. BONE MREM 7.03E 05 8.79E-03 3.54E-04 9.21E-03
- 3. LIVER MREM 8.20E-04 8.79E4)3 3.54E-04 9.96E-03 )
- 4. TOTAL BODY MREM 1.12E-03 8.79E-03 3.54E-04 1.03E-02 l l
- 5. THYROID MREM 8.22E-04 8.79E-03 3.54E-04 9.97E-03 ;
- 6. KIDNEY MREM 8.20E-04 8.79E-03 3.54E-04 9.96E-03
- 7. LUNG MREM 8.20E-04 8.79E-03 3.54E-04 9.96E-03
- 8. GI-LLI MREM 8.20E-04 8.79E-03 3.54E-04 9.96E 03 n
9 i I Page 1 of 1
. e TABLE 7 TCTTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OF THE PUBLIC)
DOSE FROM 'IOTAL DOSE DOSE ATTHE ACTIVITIES 'ID THE RESIDENCE WITHIN STIE MEMBER OF ORGAN _ UNITS LOCATION BOUNDARY THE PUBLIC % LIMITS *
- 1. SKIN MREM 736E-04 5.77E-04 131E-03 0.01
- 2. BONE MREM 9.54E-07 9.21E-03 9.22E-03 0.04
- 3. LIVER MREM 3.79E-03 9.96E-03 138E-02 0.06 .
- 4. TOTAL BODY MREM 4.18E-03 1.03E42 1.44E-02 0.06
- 5. THYROID MREM 4.00E-03 9.97E-03 1.40E-02 0.02
- 6. KIDNEY MREM 3.80E-03 9.96E-03 138E-02 0.06
- 7. LUNG MREM 3.79E-03 9.96E-03 138E-02 0.06
- 8. GI-LLI MREM 3.80E-03 9.96E-03 138E-02 0.06
- Annual dose limits from 40CFR190.10(a) of 25 mrem whole body,75 mrem to the thyroid, and 25 mrem to any other organ.
i k Page1ofI l l l
t TABLE 8 I l DOSE DUE *IO LIQUID EFFLUENTS (MEMBER OF THE PUBLIC) ; l 1994 i i ORGAN UNITS DOSE LIMIT * % LIMIT
- 1. BONE MREM 3.11E-03 10.00 3.11E-02 i
, 2. LIVER MREM 3.48E-03 10.00 3.48E-02 [ f
- 3. TOTAL BODY MREM 3.79E-03 3.00 1.26E-01 ..
- 4. THYROID MREM 2.58E-03 10.00 2.58E-02 ,
- 5. KIDNEY MREM 2.87E-03 10.00 2.87E-02
- 6. LUNG MREM 2.70E-03 10.00 2.70E-02
- 7. GI-LLI MREM 3.17E-03 10.00 3.17E-02 l
- Annual dose limits of APA-ZZ-01003, Section 9.4.1.1. i i .
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i I P l l ATTACHMENT 1 APA-ZZ-01003, OFFSITE DOSE CALCULATION MANUAL, REVISION 4 f I 6
l l l Rev. 4 Unios Ettcraic a CALLAWAY PLANT OFFSITE DOSE CALCULATION MANUAL SEPTEMBER 1994 O LU
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i APA-ZZ-01003 j Rev.4 i September 28,1994 i 1 NUCLEAR FUNCTION AD-S-E PROCEDURE APA-ZZ-01003 Sup5RS .' . i i OFFSITE DOSE CALCULATION MANUAL l l 1 RESPONSIBLE DEPARTMENT N E Al TR tti! t C.J PREPARED BY - WN' DATE ktJ[Taf ! APPROVED BY C DATE - J9
/ / r
/ t i
l DATEISSUED .3 0 '9 Y i This procedure contains the following: Pages I through 127 l Attachments 1 through 2 I Figures 1 through 5 l Appendices A through A l CheckoffLists through ,
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i l i 14540329 47361337 i b
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I APA-ZZ 01003 I ~ Rev. 4 ! l i TABLE OF CONTENTS I i
}
Purpose and Soope . ..~ . . . . . . ... I 1 Liquid Einuests
. ...- .. .. _._. ... . _. .._. _ .. .. .. ... . . 2 l Laqad Ef11uent Monitors. _ . . . .. .... .... . . 2 i Calculanon of Liqmd EfIluent Monitor Setpoints . ... . . .. .... 3 Liquid Eifluent Concentration Measurements.. . . .. . .... . ... .. 6 Dose Due to Laqad ElIluents .. . .... .. . . .. . . .. ... .. ... .. 6 ne Maximum Exposed Indmdual ... _ . _ . ..._. _6 Calculataan af Dose ikcan Liquad Ef!!uents . .....
._......7 !
Summary, Palmi =8v= ofDose Due to Liquid Effluents . . .. . .. .. 8
. Laquid Radweste Treatme=* Symem . . . .. .. . .... .._ .9 Gessous Effluents. ._._... . ... . . . .. . . _....14 Determananon of Gaseous Ef!!uent Monitor Setpoints... . . . .. . ... .. . ..._... . . .. 16 Total Body Dose Rate Setpoint Calculations.... . .
. _ . . . . . . . . . . . . . . - 16 Sida Dose Rate Setpoint Calculations.. . ... . . ...._ . .. . . .. .. . ._ _.. .. . .. . 17 t
i Noble Geses .. ..... ........._...... . . . . . . . . ~ . . . . . . =18 : Radionuclides Other Than Noble Gases. . .. . . _ .. ..._. . . . . . . ... _ _18 1 j Does Due To Gaseous Ef!!uents.... _.... . .. .. ... _ ... . .. ... . .... .19 Noble Gases . . . . . .._... . .. .. . . . . .. ... . . . _. . 19 ! n san -irive i
............._......................20 >
Gassous Radwaele Treatment Symem. .._...
. . . .. 21
. ... .._ . i Does and Dose Commitment kom Uranium Fuel Cycle Sources. .. ... ... . .. . ....._. 56 i calml=ev= of Does and Dose ra==it=nt Doni Uranium Fuel Cycle Sources . .._... . ... ..... ... 56 ,
Identine=naa of the MEMBER OF THE PUBLIC . . . . . .. . 56 ! Total Dose to the Nearest Resident . ._ ... .... .... . .. . ..... ..... .. _..... .... _.. . 56 : Total Does to the Critical Raceptor Within the SITE BOUNDARY.. _......... ..... - ..~_..... ... ... 5 7 Radiological Enytroamental Monitoring . . . . . . ...... ....... . ... . ... .. . 60 Descripoon of the Radiological Environmental Monitoring Program . . . . . 60 Performance Testing of Environmental Thermolumme= ream Dosuneters.. . . ............_.. . 60 Detersunation of Annual Average and Short Term Atmospheric Dispersion Parameters - 73 ; Atmospheric Dispersion Parameters. ... ... . . .. . . . . . . .... ...._ .. .... . 73 l Long-Term Dispersion Feimates . . . . . . . . . . . . . . . . . . 73 ! Determination of Long-Term Dispersion Feimasa for Special Receptor Locations . .. . 73 ! Short. Term Dispersion Feimates . ..... .. ._... _. . .. _ . . 74 I Reporung Requirements. _.... ._..._.. . .... . . . . . . - . . . . . . . 81 Annual Radiological Environmental Operaung Report. 81 Semi-Annual Radioacuve Eftluent Release Report l
. . . . . . . . . . . - .. ..~... 81 i f=P l*~aratiaa of ODCM Methodology. . . . . . . 84
[ Radacectrve Ef!!uent Controls (REC) .. .... .._.. . .. .. ... . . ..... .... .. .. . 85 ! Radacectrve Liquid Ef!!uent Monitoring Instrumentation.... ... . ... . ... .. . 86 ; Radacactrve Gaseous Ef!!uent Monitoring Instrumentation. _ _ . . . . . . . . . . . . . . 91 ! Liquid Ei!!uents Concentration .. .... .. .. .. _ . . . . _ . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . . . .. 97 ! Does hoan Laquid Ef!!uents - . . . . . . . . . . . . . . . ..,.........................100 Liquid Radwaste Trenunent System.- . . . . . . . . . . . . . . . . . . . _ . . . . . . _ . . . . . . . . . . . .101 : Gaseous EfDuents Dose Rate . .
.102 l
Dose . Noble Gases.... . . . . . . . .
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. -105 Dose - Iodine-131 and 133. Tritium, and Radioactive Material in Particulate Form....__. .106 Gaseous Radwaste Treatment System... ....... ., _. .. .... . _ .. .. ... .. . . . . . .107 t Total Dose...._ .. ...... .. . . .. .. . . .. ... . . ... .. . . . . . 108 Radiological Environmental Monitoririg Program .. . . . .. 109 1 J. ad.ioggsc.a_m.wigmena.l piwirpag:0 census-
. _ _ _ - .119
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APA ZZ.01003 Rev. 4 TABLE OF CONTENTS Radiological Environmental Monitoring Interlaboratory Companson Program - 120 Adnuaistrative Controls.. . . . . - . . ....
.121 Major Changes to Liquid and Gascous Radw2ste Treatment Systems = . . ..121 Changes to the Offsite Dose Calculation Manual (ODCM) . . . . ....... . . .~.. .-.. ... . . 121 References - - - - '
_123 Figure 4.1..... .... ....... .. .... .. . . .59 ; Figure 5.l A-- . .. . . . . . . . . . . . . . . . . . .... . . 61 ' Figure 5. lB ...... ...... .. .. ..... . . . . - - .._. . . . . . . . . ... 62 Figure 5.2A.... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 63 Figurc 5.2B .. ... .. ... ,.
. . . .............. - 64 Figure 5.3 .. . . . . . . . . . . . . . . . 65 ' .
Table 2.1 . . . . . . . . . . . 10 Table 2.2... . ... . . . . . . . . . . . . . - . . . 13 Table 3.1.. .. . .. . . - -
. 22 Table 3.2.. . . . . . 23 Table 3.3... . .. . . . . . 26 ,
Table 3.4...... ... . . . .. . . . . . .
.. .41 Table 5.1.- . . .
. . 66 -
Table 6.1-- . . . . - - .. . 76 Table 6.2 -- .
.................. . . 77 . Table 6.3....... ...--- . . . . . . . . . .. . . . . . . . . . . . . 78 ,
Table 6.4.. .. . . . . . . . .~. .. . 79 Table 6.5 -- . . . . . . . . . . . . . . . - - . . . . . . ... 80 Table 9.1 A.. . .. .. - ..
. .87 Table 9.1-B - . . . . . . . .. .
. 89 Table 9.2 A. . . . 92 Table 9.2-B - . . . 95 Table 9.3-A.. .
. . . . 98 Table 9.6-A--- . . . . . . .
.103 Table 9.ll-A . . . . . .
. . . .. ..111 Table 9.11-B . .. . . . . .
. ..-... . 116 Table 9.ll-C.. ., . . . . . ..
. ..!!7 Attachment ! - Lower Limit of Detection (LLD) . . . ..1Page !
Attachment 2 - Bases for Radiological EfDuent Controls.. . . . .
- 8 Pages Appendix A - Summary Review Of Radiological E51uent Tech Spec Potentially Affected By i The implementation Of The Revued 10 CFR 20 .16 Pages C
1 4 5 4 0~E:2 9 47361339 1
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APA-ZZ-01003 Rev.4 RECORD OF REVISIONS Revision Number Daig Reason for Revision Rev.O March 1983 Rev.1 November 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments. Rev.2 March 1984 Revised to incorporate NRC Staff comments. Rev.3 June 1985 Revised to incorporate errata identified by ULNRC-803 and changes to the Environmental Monitoring Program. Incorporate results of 1984 Land Use Census. , Rev.4 February 1987 Minor clarifications, incorporated 31-day projected dose methodology. Change in the utilization of areas within the Site Boundary. Rev.5 January 1988 Minor clarifications, revised descriptions ofliquid and gaseous rad monitors, revised liquid setpoint methodology to incorporate monitor background, revised dose calculations for 40CFR190 requirements, Revised Table 6 and Figures 5.1 A and 5.1B to refine descriptions of environmental TLD stations, incorporated description of environmental TLD testing required by Reg. Guide 4.13, revised Tables 1,2,4 and 5 to add additional nuclides deleted redundant material from Chapter 6. Rev.6 May 1989 Revised methodology for calculating maximum permissible liquid efIluent discharge rates and liquid effluent discharge rates and liquid efIluent monitor setpoints, provided methodology for calculating liquid efiluent monitors response correction factors, provided an enhanced description of controls on liquid monitor background limits, provided additional liquid and gaseous dose conversion factors and bioaccumulation factors (Tables 1,2,4 & 5), provided description of the use of the setpoint required by Technical Specification 4.9.4.2 dunng Core Alterations, added discussion of gaseous and liquid monitor setpoint selection in the event that the sample contains no detectable activity, added mirdmum holdup requirements for Waste Gas Decay tanks, resised dispersion parameters and accompanying description y 4g . 47 gSghange Notice 88-42.
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APA-ZZ-01003 Rev.4 RECORD OF REVISIONS
- Revision Number Date Reason for Revision - APA-Z7A1003 August 1989 Radiological EfDuent Technical Specifications were Rev.O moved from the Callaway Plant Technical Specifications to Section 9.0. Radioactive Effluent Controls, of the ODCM as per NRC Generic Letter 89-
- 01. At the same time, in order to formalize control of the entire ODCM, it was converted to APA-ZZ-01003, OFFSITE DOSE CALCULATION MANUAL.
Rev. 1 October,1990 Revise Action 41 of Table 9.2 A to allow continued purging for 24 hours as per Amendment 20 to operating license, issued 4/10/87. r Rev.2 May,1991 Section 2.4.2 - Changed gross alpha analysis frequency from "cach batch" to a monthly composite as per Table 9.3 A, and the Callaway Plant NPDES permit (reissued March 15,1991). , Rev.3 June,1993 Deleted HF-RE-45 and LE-RE-59 as effluent monitors. Revised table numbenng for consistency with those in Section 9.0, deleted redundant material, incorporated 1992 Land Use Census results, moved , LLD description to Attachment 1, moved REC Bases to Attachment 2. Deleted reporting requirements for solid radwaste, which are described in APA ZZ-01011, PROCESS CONTROL PROGRAM. , Addressed compliance with 10 CFR 20.1301. Revised the dilution flow rate to allow values other than 5000 gpm, based on dilution flow monitor setpoint. Revised "MPC" terminology to "ECV". Added Action 46 to REC 9.2 to clarify actions for inoperable mid and high range WRGM Channels. Revised references to be consistent with the revised 10 CFR 20. Added Appendix A. Revised Action 41 of Rec 9.2 and , the operability requirements of GT-RE-22/33. Incorporated the revised R values in Tables 3.2 and 3.3. Added Section 6.2 and Table 6.5. Rev.4 September,1994 ' Increased the minimum channel OPERABLE requirement of REC 9.2 for GT RE-22 & 3 from I channel to 2 channels. Revised Action 41 and the Bases for REC 9.2 accordingly. Incorporated the , operability requirements from Tech Spec 3.9.9 into the Action statement for clarity. (Refer to SOS 94-1176) 14540329 47361341
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APA-ZZ-01003 l Rev.4 i OFFSITE DOSE CALCULATION MANUAL 1.0 PURPOSE AND SCOPE The OFFSITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains the Radioactive Effluent Controls and Radiological Emironmental Monitoring Programs required by Technical Specification 6.8.4 . and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Redioactive Efiluent Release Reports required by N:nical Specifications 6.9.1.6 and 6.9.1.7. The ODCM also contains a list and description of the specific sample locations for the radiological environmental monitoring program. Compliance with Radiological Efiluent Controls limits demonstrates compliance with the limits of 10 CFR 20.1301. (Ref. I1.1.1,11.2.1,11.23.3) (CTS #4121) { i o h 1454032 5r - 47 361342
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I APA-ZZ-01003 Rev.4 2.0 LIOUID EFFLUENTS 2.1 LIOUID EFFLUENT MONITORS Gross radioactivity monitors which provide for automatic termination ofliquid emuent releases are present on the liquid efDuent lines. Flow rate measurement devices are present on the liquid efDuent lines and the discharge line (cooling tower blowdown). Setpoints, precautions, and limitations applicable to the operation of the Callaway Plant liquid emuent monitors are provided in the appropriate Plant Procedures. Setpoint values are calculated to assure that alarm and trip actions occur prior to exceeding the EfDuent Concentration Values (ECV) limits in 10 CFR Part 20 at the release point to the UNRESTRICTED AREA. The calculated alarm and trip action setpoints for the liquid emuent line monitors and flow measuring devices must satisfy the following equation: cf 5; C (2.1) F+f Where: C= The liquid emuent concentration value (ECV) implementing REC 9.3.1.1 for the site in ( Ci/ml). c= The setpoint, in ( Ci/ml), of the radioactivity monitor measuring the radioactivity concentration in the efDuent line prior to dilution and subsequent release; the serpoint, which is inversely related to the volumetric flow of the emuent line and directly related to the volumetric flow of the dilution stream plus the efDuent steam, represents a value, which, if exceeded, would result in concentrations exceeding the values of 10 CFR Part 20 Appendix B. Table II, Column 2, in the UNRESTRICTED AREA. f= The flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below. F= The dilution water flow rate setpoint as measured prior to the release point, in volume per unit time. (If (F) is large compared to (f), then F + f a F). (Ref.11.8.1) If no dilution is provided, then c < C. The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River. Normally, the dilution flow is obtained from the cooling tower blowdown, but 4 should this become unavailable, the plant water treatment facility supplies the necessary dilution flow via a byptss line. The limiting concentration which corresponds to the liquid radwaste emuent monitor setpoint is to be calculated using methodology from the expression above. Thus, the expression for detennining the setpoint of the liquid radwaste efDuent line monitor becomes: 1 i 14540329 c4Ndh/IG ml) f (2.'2) 2-
APA-ZZ-01003 Rev.4 The alarm / trip serpoint calculations are based on the minimum dilution flow rate (corresponding to the dilution flow rate setpoint), the maxunum emuent stream flow rate, and the actual isotopic analysis. Due to the possibility of a simultaneous release from more than one release pathway, a portion of the total site release limit is allocated to each pathway. The determination and usage of the allocation factor is discussed in Section 2.2. In the event the alarm / trip setpoint is reached, an evaluation will be performed using actual dilution and emuent flow values and actual isotopic analysis to ensure that REC 9.3.1.1 timits were not exceeded. 2.1.1 Continuous Liould EfDuent Monitors The radiation detection monitor associated with continuous liquid efiluent re! eases is (Ref.11.6.1,11.6.2): Monitor I.D. Descriotion BM-RE-52 Steam Generator Blowdown Discharge Monitor The Steam Generator Blowdown discharge is not considered to oc radioactive unless radioactivity has been detected by the associated efDuent ; nation monitor or by laboratory analysis. The sampling frequency, minimum analysis frequency, and type of analysis performed are as per Table 9.3-A. 2.1.2 Radioactive Liouid Batch Release EfDuent Monitors
'Ibe radiation monitor which is associated with the liquid effluent batch release system is (Ref.
11.6.4): Monitor I.D. Descripii.9a HB-RE-18 Liquid Radwaste Discharge Monitor This efDuent stream is normally considered to be radioactive. The sampling frequency, minimum analysis frequency, and the type of analysis performed are as per Table 9.3-A. 2.2 CALCULATION OF LIOUID EFFLUENT MONITOR SETPOINTS The dependence of the setpoint (c), on the radionuclide cistribution, yields, calibration, and monitor parameters, requires that several variables be considered in setpoint calculations. (Ref. 11.8.1) 14540329 47361344
APA-ZZ-01003 Rev.4
'2.2.1 Calculation of the ECV Sum The isotopic concentration of the release (s) being considered must be determined. This is obtained from the analyses required per Table 9.3-A, and is used to calculate an ECV sum (ECVSUM): .
ECVSUM = ([(C,)/(ECV,)) - i = g, a, s, t, f (2.3) Where: C=E the concentration of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample. C*= a the measured concentration of alpha emitting nuclides measured by gross alpha analysis of the monthly composite sample. Cs*= the measured concentrations of Sr-89 and Sr-90 as determined by analysis of the quarterly composite sample. C=t the measured concentration of H-3 in the waste sample. Cr* = the measured concentration of Fe-55 as determined by analysis of the quarterly composite sample. ECVE, ECV s, ECV ,aECVr, ECV =t are the limiting concentrations of the appropriate radionuclides from 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2x10-4 Ci/mi total activity. For the cr.se ECVSUM si, the monitor tank effluent concentration meets the limits of REC 9.3.1.1 without dilution and the efHuent may be released at any desired flow rate. If ECVSUM
> 1 then dilution is required to ensure compliance with REC 9.3.1.1 concentration limits. If sinnultaneous releases are occurring or are anticipated, an allocation fractien, N, must be applied so that available dilution flow may be apportioned among simultaneous discharge pathways. The value of N may be any value between 0 and I for a particular discharge point, provided that the sum total allocation fractions for all discharge points must be si.
2.2.2 Calculation of the Maximum Permissible Liauid Effluent Discharce Flowrate The maximum permissible liquid efDuent discharge flowrate is calculated by: fmax s (F + fp)(SF)(N) + (ECVSUM) (2.4) g .
.SY lY '
a.
I 4 mn APA-ZZ-01003 I
'Rev.4 i
Where: fmax = maximum permissible liquid effluent discharge flowrate, in (gallons / minute); f=p . the expected undiluted liquid emuent flowrate, in gpm. ; N=' the allocation fraction which apportions dilution flow emong simultaneous discharge , pathways (see discussion above) SF = the safety factor, an administrative factor used to compensate for statistical fluctuations , and errors of measurements. This factor also provides a margin of safety in the calculation of the maximum liquid emuent discharge flowrate (fmax). The value of SF should be < l. - l F & ECVSUM, are previously defined. The dilution water supply is furnished with a flow monitor which isolates the liquid effluent i discharge if the dilution flow rate falls below its setpoint value. t In the event that fmax is less than fp, then the value of fmax is substituted into the equation for - f p, and a new value of fmax is calculated. This substitution is performed for three iterations in order to calculate the co Tect value of fmax-2.2.3 Calculation of Liould Emuent Monitor Setnoint i The liquid effluent monitors are Nal(TI) based systems and respond primarily to gamma -! radiation. Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides in the effluent: c = BKG + ( E g (C ) + SF) = Ci/ml (2.5) Where: r ' c= the monitor setpoint as previously defined, in ( Ci/ml); + BKG = the monitor background prior to discharge,in ( Ci/ml); Cgand SF are as previously defined. ! The mordtor's background is controlled at an appropriate limit to ensure adequate sensitivity. Utilizing the methodology of ANSI N13.10-1974 (Ref. I1.21), the background must be , maintained at a value ofless than or equal to 2.23E-6 pCi/ml (reiative to Cs-137) in order to j i detect a change of IE-7 Ci/mi ofI-134 (the most restrictive nuclide in Table 1 of reference 11.21). j 1 In the event that there is no detectable gamma activity in the emuent or if the value of (I(C )g+ SF) is less than the background of the monitor, then the monitor setpoint will be set at twice the cunent background of the monitor. 14540329~47361346 1 i 1
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APA-ZZ-01003 Rev.4 As previously stated, the monitor's response is dependent on the gamma emitting radionuclide distribution of the emuent. Accordingly, a new database conversion factor is calculated for each release based mn the results of the gamma spectrometric analysis of the efIluent sample and the measured response of the monitor to National Institute of Standards and Technology (NIST) traceable calibration sources: DBCFc = k(C,)) + (CMR) x (ECF) (2.6) DBCFe = the monitor data base conversion factor which converts count rate into concentration (pCi/ml); CMR= the calculated response of the radiation monitor to the liquid effluent; ECF = the conversion factor for Cs-137, which converts count rate into concentration ( Ci/ml). Cgis as previously defined. The new value of the DBCFcis calculated and entered into the monitor data base prior to each discharge. A more complete discussion of the derivation and calculation of the CMR is given in reference 11.14.7. 2.3 LIOUID EFFLUENT CONCENTRATION ME ASUREMENTS Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at the time of release. To assure representative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection. The methods for mixing, sampling, and analyzing each batch are outlined in applicable plant procedures. The allowable release rate limit is calculated for each batch based upon the pre release analysis, dilution flow-rate, and other procedural conditions, prior to authorization for release. The liquid efIluent discharge is monitored prior to entering the dilution discharge line and will automatically be terminated if the pre-selected alarm / trip setpoint is exceeded. Concentrations are determined primarily from the gamma isotopic and H-3 analyses of the liquid batch sample. For gross alpha, St-89, St-90, & Fe-55, the measured concentration from the previous composite analysis is used. Composite samples are collected for each batch release. Monthly analysis for gross alpha and quarterly analyses for St-89, Sr-90, and Fe 55 are performed in accordance with Table 9.3-A. Doses from liquids discharged as continuous releases are calculated by utilizing the last measured values of samples required in accordance with Table 9.3-A. , 2.4 DOSE DUE TO LIOUID EFFLUENTS 2.4.1 The Maximum Exposed Individual 1 The cumulative dose determination considers the dose contributions from ?: maximum exposed individual's consumption of fish and potable water, as appropriate. Nont illy, the adult is considered to be the maximum exposed individual. (Ref.11.8.3) 14540329 473E.1347 1 l
APA 72-01003 Rev,4 The Callaway Plant's liquid emuents are discharged to the Missouri Rive' . As there are no potable water intakes within 50 miles of the discharge point (Ref. 11.7.1,11.6.6), this pathway does not require routine evaluation. Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from discharges to the Missouri River. Dose from recreational activities is expected to contribute the additional 5%, which is considered to be negligible. (Ref. I1.6.7) 2.4.2 Calculation of Dose From Licuid Emuents The dose contributions for the total time period.
=
[ At, tal are calculated at least once each 31 days and a cumulative summation of the total body and individual organ doses is maintained for each calendar quarter. Dose is calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS using the following expression (Ref.11.8.3): D, = [ Ai , [ 4t, C ,i F, (2.12)
- i. r-1 .
Where: D,= the cumulative dose commitment to the total body or any organ, t, from the liquid emuents for the total period m [ At, in mrem. At , = the length of the l th time period over which C i, and F, are averaged for all liquid releases, in hours. At, corresponds to me actual uotion of the release (s). C,= i the average measured concentration of radionuclide, i, in undiluted liquid effluent during time period At, from any liquid release,in ( Ci/ml). Aj, = the site related ingestion dose commitment factor to the total body or any organ i for each identified priticipal gamma and beta emitter listed in Table 9.3 A, (in mrem /hr) per ( Ci/ml). The calculation of the Aj, values is detailed in Ref. I1.14.5 and are given in Table 2.1. F, = the near field average dilution factor for C , during any liquid emuent release: F, = (F.,_ + f=) 89.77 14540329 4 7 3 6 1 3 % =: . i I
APA-ZZ-01003 Rev.4 Where: fmax = maximum undiluted effluent flow rate during the release F= average dilution flow . 89.77 = site specific applicable factor for the mixing effect of the discharge structure. (Ref. 11.5.1) The term C;, is the undiluted concentration of radioactive material in liquid waste at the common release point determined in accordance with REC 9.3.1.1, Table 9.3.A " Radioactive Liquid Waste Sampling and Analysis Program". All dilution factors beyond the sample point (s) are included in the F, term. , The nearest municipal potable water intake downstream from the liquid effluent discharge point into the Missouri River is located near the city of St. Louis, Missouri, approximately 78 miles downstream. As '.here are currently no potable water intakes within 50 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual, or in dose estimates to the population. Should future potable water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be revised to include this pathway in dose estimates. (Ref. I1.6.6). 2.4.3 Summarv. Calculation of Dose Due to Liauid Effluents The dose contribution for the total time period , m [ At, tel is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter. The projected dose contribution from liquid effluents for which radionuclide concentrations are determined by periodic composite and grab sample analysis, may be approximated by using the last measured value. Dose contributions are determined for all radionuclides identified in liquid effluents released to UNRESTRICIT.D AREAS. Nuclides which are not detected in the analyses are reponed as "less than" the nuclide's Minimum Detectable Activity (MDA) and are not reponed as being present at the Lower Level of Detection (LLD) level for that nuclide. The "less than" values are not used in the dose calculations. 14540329 47361349
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f APA-ZZ-01003 I Rev.4 2.5 LIOUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is capable of varying treatment, depending on waste type and product desired. It is capable of concentrating, gas stripping, and distillation of liquid wastes through the use of the evaporator system. The demineralization system is capable of removing radioactive ions fro,m solutions to be reused as makeup water. Filtration is performed on certain liquid wastes and it may, in some cases, be the only required treatment prior to release. The system has the ability to absorb halides through the use of charcoal filters prior to their . release. The design and operation requirements of the LIQUID RADWASTE TREATMENT SYSTEM provide assurance that releases of radioactive materials in liquid effluents will be kept "As Low As Reasonably Achievable"(ALARA). The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for use when liquids require treatment prior to their release to the environment. OPERABILITY is demonstrated through compliance with REC 9.3.1.1. and 9.4.1.1. Projected doses due to liquid releases to UNRESTRICTED AREAS are determined each 31 days by dividing the cumulative annual total by the number of elapsed months. t T4540339 47361350 9 1
i 4 APA-ZZ-01003 Rev.4 TABLE 2.1 INGESTION DOSE COMMITMENT FACI'OR (Aj ) FOR ADULT AGE GROUP (mrem /hr)per( Ci/ml) Nuclides Bone Liver Total Thyroid Kidney Lung GI-LLI Body $QChefd"97NN"MT""@%fMfgQEEgy@Hff H3 No Data 2.26E-01 2.26E 01 2.26E 01 2.26E-01 2.26E-01 2.26E-01 Be-7 1.30E-02 2.98E-02 1.45E-02 No Data 3.15E-02 No Data 5.16E+00 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E403 6.26E+03 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 I P-32 4.62E+07 2.87E+06 1.78E+06 No Data No Data No Data 5.19E+06 Cr 51 No Data No Data 1.27E+00 7.62E-01 2.81E-01 1.69E+00 3.20E+02 Mn-54 No Data 4.38E+03 8.35E+02 No Data 1.30E+03 No Data 1.34E+04 Mn-56 No Data 1.10E+02 1.95E+01 No Data 1.40E+02 No Data 3.52E+03 Fe-55 6.57E+02 4.54EM2 1.06E+02 No Data No Data 2.53E+02 2.6IE+02 Fe-59 1.04EM3 2.44E+03 9.34E+02 No Data No Data 6.81E+02 8.13E+03 Co-57 No Data 2.09E+01 3.48E+01 No Data No Data No Data 5.3IE+02 Co-58 No Data 8.94E+01 2.00E+02 No Data No Data No Data 1.81E+03 Co-60 No Data 2.57E402 5.66E+02 No Data No Data No Data 4.82E+03 Ni-63 3.1IE+04 2.15E+03 1.04E+03 No Dac2 No Data No Data 4.49E+02 Ni-65 1.26EM2 1.64E+01 7.48E+00 No Data No Data No Data 4.16E+02 : Cu-64 No Data 1.00E+01 4.69E+00 No Data 2.52E+0! No Data 8.52E+02 Zn-65 2.32EM4 7.38E+04 3.33EM4 No Data 4.93E+04 No Data 4.65E+02 Zn-69 4.93E+01 9.44E+01 6.56E+00 No Data 6.13E401 No Data 1.42E+01 Br-82 No Data No Data 2.27E+03 No Data No Data No Data 2.60E+03 Br-83 No Data No Data 4.04E+01 No Data No Data No Data 5.81E+01 Br-84 No Data No Data 5.26E+01 No Data No Data No Data 4.13E-04 ! Br 85 No Data No Data 2.15E+00 No Data No Data No Data O Rb-86 No Data 1.01E+05 4.71E+04 No Data No Data No Data 1.99E+04 Rb-88 No Data 2.90E+02 1.54E+02 No Data No Data No Data 4.00E-09 Rb-89 No Data 1.92E+02 1.35E402 No Data No Data No Data O Sr-89 2.21E+04 No Data 6.35E+02 No Data No Data No Data 3.55E+03 Sr-90 5.44E M5 No Data 1.34E+05 No Data No Data No Data 1.57E+04 St-91 4.07E+02 No Data 1.64E+01 No Data No Data No Data 1.94E+03 Sr 92 1.54E+02 No Data 6.68E+00 No Data No Data No Data 3.06E+03 Y-90 5.75E-01 No Data 1.54E-02 No Data No Data No Data 6.10E+03 14540329 47361351 n APA-ZZ-01003 Ra. 4 , TABLE 2.1 (Cont'd) INGESTION DOSE COMMITMEhT FACTOR (Aj.) FOR ADULT AGE GROUP (mrem /hr) per (pCi/ml) Nuclide Bone Liver Total Thyroid Kindey Lung GI-LLI tame XT22EM12TREm BQm% m?BW525522Lw 25 m 5mm Y-91M 5.44E-03 No Data 2.10E-04 No Data No Data No Data 1.60E-02 Y-91 8.43E+00 No Data 2.25E-01 No Data No Data No Data 4.64E+03 Y-92 5.05E-02 No Data 1.48E-03 No Data No Data No Data 8.85E+02 Y-93 1.60E-01 No Data 4.42E 03 No Data No Data No Data 5.08E+03 Zr-95 2.40E-01 7.70E-02 5.21E-02 No Data 1.21E-01 No Data 2.44E+02 Zr 97 1.33E-02 2.68E-03 1.22E 03 No Data 4.04E-03 No Data 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 No Data 2.46E+02 No Data 1.5 IE+06 Mo-99 No Data 1.03E+02 1.96E+01 No Data 2.33E+02 No Data 2.39E+02 Tc-99M 8.87E-03 2.51E-02 3.19E-01 No Data 3.81E-01 1.23E-02 1.48E+01 - Tc 101 9.llE-03 1.31E-02 1.29E-01 No Data 2.36E-01 6.70E-03 0 Ru-103 4.42E+00 No Data 1.90E+00 No Data 1.69E+01 No Data 5.17E+02 Ru-105 3.68E 01 No Data 1.45E-01 No Data 4.76E+00 No Data 2.25E+02 Ru-106 6.57E+01 No Data 8.32E+00 No Data 1.27E442 No Data 4.25E+03 Cd-109 No Data 5.54E+02 1.94E+01 No Data 5.31E+02 No Data 5.59E+03 Sn-113 5.66E+04 1.61E+03 3.26E+03 9.18E+02 No Data No Data 1.69E+05 ; Sb-124 6.69E+00 1.26E-01 2.65E+00 1.62E-02 No Data 5.21E+00 1.90E+02 Sb-125 4.28E+00 4.78E-02 1.02E+00 4.35E-03 No Data 3.30E+00 4.71E+01 Te-125M 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 No Data 1.02E+04 Te-127M 6.47E+03 2.32E+03 7.90E402 1.66E403 2.63E+04 No Data 2.17E+04 Te-127 1.0$E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 No Data 8.30E+03 Te-129M 1.10E+04 4.llE+03 1.74E+03 3.78E+03 4.60E+04 No Data 5.54E%4 Te-129 3.01E+01 1.13E+01 7.33E+00 2.31E+01 1.26E+02 No Data 2.27E441 Te 131M 1.66E403 8.09E+02 6.75E+02 1.28E+03 8.21E+03 No Data 8.03E+04 Te-131 1.89E+01 7.88E+00 5.96E 40 1.55E+01 8.25E+01 No Data 2.67E+00 ; Te-132 2.41E+03 1.56E403 1.47E403 1.72E+03 1.50E+04 No Data 7.38E+04 I-130 2.71E+01 8.01E+01 3.16E+01 6.79E+03 1.25E402 No Data 6.89E+01 1-131 1.49E+02 2.14E+02 1.22E+02 7.00E+04 3.66E+02 No Data 5.64E+01 1-132 7.29E+00 1.95E+01 6.82E+00 6.82E+02 3. I IE+01 No Data - 3.66E+00 I-133 5.10E+01 8.87E+01 2.70E+0! 1.30E+04 1.55E+02 No Data 7.97E+01 1-134 3.81E+00 1.03E+01 3.70E400 1.79E+02 1.64E+01 No Data 9.01E-03 I-135 1.59E+01 4.16E+01 1.54E+01 2.75E+03 6.68E+0! No Data 4.70E+01 14540329 473E.1352 APA ZZ-01003 Rev.4 TABLE 2.1 (Cont'd) INGESTION DOSE COMMITMENT FACTOR (Ais) FOR ADULT AGE GROUP , (mrem /hr)per( Ci/ml) Nuclide Bone Liver Total Thyroid Kindey Lung GI-LLI Body , n.ssstm!sD& ki
"" = ~ymmy~e3ppnmmme mnnmmemwnwgbObsMWska4%simGikoMGAsas.vu;x w,wengy;;;wmmqpn_gmr~w; wM?i34Mhms,Mee s%k%2r M.sv.4Mawa@;M're4Sl55f\
Cs-134 2.98E405 7.09E+05 5.80E+05 No Data 2.29E+05 7.62E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 No Data 6.85E+04 9.39E+03 1.40E+04 Cs 137 3.82E+05 5.22E+05 3.42E+05 No Data 1.77E+05 5.89E404 1.01E+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 No Data 3.84E+02 3.79E+01 2.23E-03 Ba 139 9.29E-01 6.62E-04 2.72E-02 No Data 619E-04 3.76E-04 1.65E+00 ; Ba 140 1.94E+02 2.44E-01 1.27E+01 No Data 8.31E-02 1.40E-01 4.00E+02 , Ba 141 4.50E-01 3.40E 04 1.52E 02 No Data 3.16E-04 1.93E-04 2.12E 10 Ba 142 2.04E-01 2.09E-04 1.28E-02 No Data 1.77E-04 1.19E-04 0 La-140 1.50E-01 7.53E 02 1.99E-02 No Data No Data No Data 5.53E+03 La-142 7.65E-03 3.48E-03 8.66E 04 No Data No Data No Data 2.54'i+0 '. Ce-141 2.24E-02 1.51E-02 1.72E-03 No Data 7.03E 03 No Data 5.78E+0! Cc.143 3.94E 03 2.92E+00 3.23E-04 No Data 1.28E-03 No Data 1.09E+02 Cc-144 1.17E+00 4.88E-01 6.26E-02 No Data 2.89E 01 No Data 3.94E+02 , Pr-143 5.50E 01 2.21E 01 2.73E-02 No Data 1.27E-01 No Data 2.41E+03 Nd-147 3.76E-01 4.35E-01 2.60E-02 No Data 2.54E-01 No Data 2.09E+03 Eu 154 3.67E+0! 4.52E+00 3.21E+00 No Data 2.16E+01 No Data 3.27E+03 Hf 181 3.99E 02 1.94E-01 1.80E-02 No Data 4.17E-02 No Data 2.21E+02 W-187 2.96E+02 2.47E+02 8.64E401 No Data No Data No Data 8.09E+04 Np',39 2.84E-02 2.80E-03 1.54E 03 No Data 8.72E-03 No Data 5.74E+02 s i i 1 4 5 4 0 3 3 cf 47361353 r
i i APA-ZZ-01003 l Rev.4 TABLE 2.2 BIOACCUMULATION FACTOR (BFj) USED IN THE ABSENCE OF SITE-SPECIFIC DATA (a) (oCi/ke) per (oCi/ liter) Bj Element Fish (Freshwater) H 9.0 E - 01 Be 2.0 E + 00 C 4.6 E + 03 Na 1.0 E + O2 P 1.0 E + 05 Cr 2.0 E + O2 l Mn 4.0 E + 02 Fe 1.0 E + 02 Co 5.0 E + 01 Ni 1.0 E + 02 Cu 5.0 E + 01 Zn 2.0 E + 03 Br 4.2 E + 02 Rb 2.0 E + 03 Sr 3.0 E + 01 Y 2.5 E + 01 Zr 3.3 E + 00 Nb 3.0 E + 04 Mo 1.0 E + 01 Tc 1.5 E + 01 Ru 1.0 E + 01 Rh 1.0 E + 01 Cd 2.0 E + 02 Sn 3.0 E + 03 Sb 1.0 E + 00 Te 4.0 E + O2 I 1.5 E + 01 Cs 2.0 E + 03 Ba 4.0 E + 00 La 2.5 E + 01 Ce 1.0 E + 00 l Pr 2.5 E + 01 Nd 2.5 E + 01 l Eu 2.5 E + 01 ) Hf 3.3 E + 00 W l.2 E + 03 Np 1.0 E + 01 (a) Values from Regulatory Guide 1.109, Rev.1, Table A-1 and References 11.14.4 and 11.14.8. 14540329 47361354 i l
APA-ZZ-01003 I Rev.4 l 3.0 GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITORS J Noble gas activity monitors are present on the containment building ventilation system, plant unit ventilation system, and radwaste building ventilauon system. ; The alarm / trip (alarm & trip) setpoint for any gaseous emuent radiation monitor is determmed bast.d on the instantaneous noble gas total body and skin dose rate limits of REC 9.6.1.1, at the : SITE BOUNDARY location with the highest annual average X/Q value. , t Each monitor channel is provided with a two level system which provides sequential a! ras o increasing radioactivity levels. These setpoints are designated as alen setpoints and alarm / trip setpoints. (Ret 11.6.3) l The radiation monitor alarm / trip setpoints for each release point are based on the radioactive - noble gases in gaseous emuents. It is not considered practicable to apply instantaneous alarm / trip , setpoints to integrating radiation monitors sensitive to radiciodines, radioactive materials in paniculate form and radionuclides other than noble gases. Conservative assumptions may be necessary in establishing setpoints to account for system variables, such as the measurement system emeiency and detection capabilities dunng normal, anticipated, and unusual operating conditions, the variability in release flow and principal radionuclides, and the time lag between alarm / trip action and the final isolation of the radioacuve emuent. (Ref. I1.8.5) Table 9.2-B provides the instrument surveillance requirements, such as calibration, source checking, functional testing, and channel checking. 3.1.1 Continuous Release Gaseous Emuent Monitors T The radiation detecuon monitors associated with continuous gaseous emuent releases are (Ref. 11.6.8, 11.6.9): Monitor I.D. Description GT RE-21 Unit Vent GH-RE-10 Radwaste Building Vent Each of the above continuously monitors gaseous radioactivity concentrations dowtistream of the last point of potential influent, and therefore measures emuents and not inplant concentrations. 4 The unit vent monitor continuously monitors the emuent from the unit vent for gaseous radioactivity. The unit vent, via ventilation exhaust systems, continuously purges various tanks , and sumps normally containing low-level radioactive aerated liquids that can potentially generate l airborne activity. The exhaust systems which supply air to the unit vent are from the fuel i building, auxiliary building, the access control area, the containment purge, and the conden er air discharge. The unit vent monitor provides alarm functions only, and does not terminate releases from the unit vent. 14570329 47361355 ~
. I i
i APA-ZZ-01003 Rev.4 ! The Radwaste Building ventilation efHuent monitor continuously monitors for gaseous l radioactivity in the efnuent duct downstream of the exhaust filter and fans. The flow path l provides ventilation exhaust for all parts of the building structure and components within the l building and provides a discharge path for the waste gas decay tank release line. These : components represent potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing ! quen . This monitor will isolate the waste gas decay tank discharge line upon a high gaseous radioactivity alarm. The continuous gaseous efDuent monitor setpoints are established using the methodology described in Section 3.2. Since there are two continuous gaseous efDuent release points, a fraction of the total dose rate limit (DRL) will be allocated to each release point. Neglecting the batch releases, the plant Unit Vent monitor has been allocated 0.7 DRL and the Radwitste Building Vent monitor has been allocated 0.3 DRL. These allocation factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e.,1.0). Therefore, a particular monitor reaching the utpoint would not necessarily mean the dose rate limit at the SITE BOUNDARY is being exceed;d; the alarm only indicates that the specific release point is contributing a greater fraction of the dose rate limit than was allocated to the associated monitor, and will necessitate an evaluation of both systems. 3.1.2 Batch Release Gaseous Monitors i The radiation monitors associated with batch release gaseous efnuents are (Ref. 11.6.9, 11.6.10, , 11.6.I1): Monitor I D. DescriptioD GT-RE-22 Containment Purge System GT-RE-33 GT-RE-10 Radwaste Building Vent The Containment Purge System continuously monitors the containment purge exhaust duct , during purge operations for gaseous radioactivity. The primary purpose of these monitors is to 1 isolate the containment purge system on high gaseous activity via the ESFAS. The sample points are located outside the containment between the containment isolation dampers and the containment purge filter adsorber unit. The Radwaste Building Vent monitor was previously described. A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides. The alarm / trip setpoint(s) is adjusted accordingly to ensure that 'he limits of REC 9.6.1.1 are not exceeded. 3.2 GASEOUS EFFLUErTr MONITOR SETPOINTS The alarm / trip setpoint for gaseous effluent monitors is determined based on the lesser of the - total body dose rate (equation 3.1) and skin dose rate (equation 3.3), as calculated for the SITE 14d .ci9 47361356 l i
e . APA-ZZ-01003 Rev.4 During core alterations, the setpoint for the Containment Purge Monitors, GT-RE-22 and GT-RE-33 is set at a value ofless than or equal to SE-3 Ci/ce, as required by Technical
- Specification 4.9.4.2. The actual setpoint value will be reduced according to the Instrument Loop Uncertainty Estimate (ILUE). This value will also be utilized in the event that there is no detectable noble gas activity in the containment atmosphere sample analyzed in accordance with REC 9.6.1.1. The full derivation of this value is discussed in reference 11.14.6.
3.2.1 Total Body Dose Rate Setooint Calculations To ensure that the limits of REC 9.6.1.1 are met, the alarm / trip setpoint based on the total body dose rate is calculated according to: S. s D.R.F,F, (3.1) Where: Stb = the alarm / trip setpoint based on the total body dose rate ( Ci/cc). Dtb = REC 9.6.1.1 limit of 500 mrem /yr, conservatively interpreted as a continuous release over a one year period. F= s the safety factor, a conservative factor used to compensate for statistical fluctuations and errors of measurement. (For example, Fs = 0.5 corresponds to a 100% variation.) Default value is Fs = 1.0. Fa = the allocation factor which will modify the required dilution factor such that ! simultaneous gaseous releases may be made without exceeding the limits of REC 9.6.1.1 The default value is 1/n, where n is the number of pathways planned for release. Rtb = factor used to convert dose rate to the efnuent concentration as measured by the e1E.:ent monitor, in (pCi/cc) per (mrem /yr) to the total body, determined according to: l R. = C + (X/Q) [ K,Q, (3.2) l
. s .
l Where: j l [ C= monitor reading of a noble gas monitor corresponding to the sample radianuclide I concentrations for the batch to be released. Concentrations are determined in accordance with Table 9.6-A. The mixture of Ladionuclides determined via grab sampling of the effluent stream or source is correlated to a calibration factor to determine monitor response. The monitor response is based on concentrations, not release rate, and is in units af( Ci/cc). X / Q the highest calculated annual average relative concentration for any area at or beyond the SITE 3OUNDARY in (sec/m 3). Refer to Tables 6.1,6.2 and 6.4. K= i the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrem /yr) per ( Ci/m3). (Table 3.1) 14 5Q'[C 3aG: @releaftlif @bigggs _r:rd_icoqctide, i, in ( Ci/ sect
1 APA-ZZ-01003 Rev.4 l Qi si calculated as the product of the ventilation path flow rate and the measured activity of the j effluent stream as determined by grab sampling. j 3.2.2 Skin Dose Rate Setnoint Calculation To ensure that the limits of REC 9.6.1.1 are met, the alarm / trip setpoint based on the skin dose rate is calculated according to: 3 I ' S, s D,R,F,F, (3.3) Whi.re: Fsand F aare as previously defined. S= s the alarm / trip setpoint based on the skin dose rate. I D=s REC 9.6.1.1 timit of 3000 mrem /yr, conservatively interpreted as a continuous release over a one year period. - R=s factor used to convert dose rate to the efhuent concentration as measured by the effluent monitor, in ( Ci/cc) per (mrem /yr) to the skin, determined according to: l R, = C + (X/Q)[ i(L +i 1.1M ) Qi (3.4) Where: L=i the skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem /yr) per (pCi/m3 ). 1.1 = conversion factor 1 mrad air dose = 1.1 mrem skin dose. M;= the air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad /yr)per( Ci/m3). C, (X / Q) and Qi are previously defined. 3.3 CALCULATION OF DOSE AND DOSE RATE FROM GASEOUS EFFLUENTS 3.3J Calculation of Dose Rate The following methodology is applicable to the location (SITE BOUNDARY or beyond) characterized by the values of the parameter (X/Q) which results in the maxunum total body or skin dose rate, in the event that the analysis indicates a different location for the total body and skin dose limitations, the location selected for consideration is that which minimizes the allowable release values. (Ref. I1.8.6) i
- The factors Kj, Lj, and M; relate the radionuclide airborne concentrations to various dose rates, l assuming a semi-infinite cloud model.
f f l'4370329 47361358 l
-17
l l APA-ZZ-01003 ] Rev.4 3.3.1.1 Noble Gases The telease rate limit for noble gases is determined according to the following general ] relationships (Ref. I1.8.6): D. =[ K,((X/Q)Q,) s500 mrem /yr (3.5) D, = [ (L, + 1.1 M,)((X/ Q)Q4) s 3000 mrem / yr (3.6) Where: Dtb = Total body dose rate, conservatively averaged over a period of one year. K= i Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrem /yr) per (pCi/m3 ). X / Q = The highest calculated annual average relative concentration for any area at or beyond l the SITE BOUNDARY. Refer to Tables 6.1,6.2, and 6.4 for applicability. . 1 Qi = The release rate of noble gas radionuclides, i, in gaseous effluents, from all vent releases in ( Ci/sec). Q is calculated as the product of the ventilation path flow rate and the i measured activity of the effluent stream as determined by grab sampling. 1 D,= Skin dose rate, conservatively averaged over a period of one year. l Lg = Skin dose factor due to beta emissions for each identified noble gas radionuclide, in (mrem /yr)per( Ci/m3 ). 1.1 = Units conversion factor, I mrad air dose = 1.1 mrem skin dose. l M= i Air dose factor due to gamma emissions for each identified noble gas radionuclide, in ; 3 (mradlyr)per( Ci/m ). 3.3.1.2 Radionuclides Other Than Noble Gases The release rate limit for Iodine 131 and Iodine 133, for tritium, and for all radioactive materials in particultte form with halflives greater than 8 days is determined according to (Ref. I1.8.7): , l , D, = [ R i ,X/Q , Qi s 1500 mrem /yr (3.7) 6 Where: D= o Dose rate to any critical organ, in (mrem /yr). R= Dose parameter for radionuclides other than noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem /yr) per ( Ci/m3), 14570329 47361359
APA-ZZ-01003 Rev.4 Qj and (X / Q) are as previously defined. The dose parameter (Rj) includes the internal dosimetry of radionuclide, i, and the receptor's breathing rate, which are functions of the receptor's age. The child age group has been selected as the limiting age group. All radiodines are assumed to be released in elemental fann (ref. I 1.8.7). Rg values were calculated according to (Ref. I1.8.8): R; = K' (BR) DFA, (3.8) Where: ,, K' = Units conversion factor: IE06 pCi/ Ci BR= The breathing rate. (Regulatory Guide 1.109, Table E-5). DFA i= The maximum organ inhalation dose factor for the ith radionuclide, in (mrem /pCi). The total body is considered as an organ in the selection of DFA . (Ref. I1.11.5 and 11.14.4) 3.3.2 Dose Due to Gaseous EffluentJ 3.3.2.1 Noble Gases The air dose at the SITE BOUNDARY due to noble gases is calculated according to the following methodology (Ref.11.8.9): During any calendar quarter, for gamma radiation: D, = 3.17E-08 [ M (X/Q) q, s 5 mrad (3.9) ; During any calendar quarter, for beta radiation: D, = 3.17E-08 [ N (X/Q) qi 3 510 mrad (3.10) During any calendar year, for gamma radiation: D, = 3.17E-08 [ Mi (X/Q)qi s 10 mrad (3.11) i During any calendar year, for beta radiation: D, = 3.17E-08 [ Ni (X/Q) q, s 20 mrad (3.12) i l 14570329 47361360 , 1 l
+ i 1
l APA-ZZ-01003 i Rev.4 l l Where: , D=g Air dose from gamma radiation due to noble gases released in gaseous emuent. D=b Ai. dose from beta radiation due to noble gases released in gaseous emuents. N=i The air dose factor due to beta emissions for each identified noble gas radionuclide, i, in (mradlyr)per(pCi/m3). q= The releases of radioiodines, radioactive materials in paniculate form, and radionuclides other than noble gases, i, in gaseous emuents, for all gaseous releases in ( Ci). Releases ) tre cumulative over the calendar quaner or year as appropriate. 3.17L 08 = The is verse of the number of seconds per year. ., X / Q & M are i , s preve. 'y defined. 3.3.2.2 Radionuclides Other Than Noble Gases . The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in paniculate form with half-lives greater than 8 days in gaseous emuents released, to areas at and beyond the SITE BOUNDARY, is calculated according to the following expressions: During any calendar quaner: D; = 317E-08 [Ri[W qi] s 7.5 mrem (3.13) i During any calendar year: D = 3.17E-08 [Ri[W qi] s 15 mrem 3 (3.14) , 6 , Where: ; D= i Dose to a MEMBER OF THE PUBLIC from radionuclides other than noble gases. R= The dose factor for each identified radionuclide, i, in m2 (mrem /yr) per ( Ci/sec) or (mrem /yr)per( Ci/m3 ). W= (X / Q) for the inhalation and tritium pathways, in (sec/m 3). Refer to Tables 6.1,6.2, and 6.4 for applicability. W= (D / Q) for the food and ground plane pathways, in (meters-2). Refer to Tables 6.1, 6.2 a ad 6.4 for applicability. 145%gg avegg tive qepositio of the emuent at er beyond the SITE BOUNDARY, considering depletion oftNpYu'me during transpon. APA-ZZ-01003 Rev.4 4 i 3.17 E-08 = The inverse of the number of seconds per year. q is as previously defined. For the direction sectors with existing pathways within 5 miles from the site, the appropriate Rj values are used. If no real pathway exists within 5 miles from the center of the building complex, the cow-milk R; value is used, and it is assumed that this pathway exists at the 4.5 to 5.0 mile distance in the limiting-case sector. If the Rj for an existing pathway within 5 miles is less than a cow-milk R iat 4.5 to 5.0 miles, then the value of the cow-milk R; at 4.5 to 5.0 miles is used. (Ref. 9.8.10) Although the annual average relative concentration (X/Q) and the average relative deposition rate (D/Q) are generally considered to be at the approximate receptor location in lieu of the SITE BOUNDARY for these calculations, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist at the location of the nearest residence with the highest value of (X/Q). (Ref. I1.8.9) The Total Body dose from ground plane deposition is added to the dose for each individual organ. (Ref. I1.11.3) 3.4 GASEOUS RADWASTE TREATMENT SYSTEM ne gaseous radwaste treatment system and the ventilation exhaust system are available for use whenever gaseous efDuents require treatment prior to being released to the environment. The , gaseous radwaste treatment system is designed to allow for the retention of all gaseous fission products to be discharged from the reactor coolant system. The retention system consists of eight (8) waste gas decay tanks. Normally, waste gases will be retained for at least 60 days prior to discharge. These systems will provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept ALARA. The OPERABILITY of the gaseous radwaste treatment system ensures this system will be available for use when gases require treatment prior to their release to the environment. OPERABILITY is demonstrated through compliance with REC 9.6.1.1,9.7.1.1, and 9.8.1.1. Projected doses (gamma air, beta air, and organ dose) due to gaseous efDuents at or beyond the SITE BOUNDARY are determined each 31 days by dividing the cumulative annual total by the number of clapsed months. I i 14570329 47361362 ! I 21-
)
1 1 1
Y y;jy APA-ZZd1003 , Rev.4 g TABLE 3.1 - , f 2 DOSE FACTOR FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASESa O _ I) Total Body Gamma Air Beta Air I.d Dose Factor Skin Dose Factor Dose Factor Dose Factor h) ",
. . Q1 Kg L;- Mi . Ni -
(mrad /yr)per(pCi/m3 ) -3 ) l Radionuclide (mrem /yr)per(pCi/m3 ) (mradlyr)per(pCi/m3 ) (mradlyr per(pCi/m E F;9mWNE?Rr8%ggs Kr-83m 7.56 E.02 - I.93 E+01 2.88 E442 ~ .
- - @ Kr-85m 1.17E+03 1.46E+03 1.23 E+03 1.97 E+03 I
H Kr-85 1.61 E+01 1.34 E+03 1.72 E+01 1.95 E+03 ~f Id Kr-87 5.92 E+03 9.73 E+03 6.17 E+03 ' l.03 E+04
@ Kr-88 1.47 E+04 2.37 E+03 1.52 E+04 . 2.93 E+03 ,
j (1 Kr-89 1.66 E404 1.01 E+04 1.73 E+04 1.06 E+04 Kr-90 1.56 E+04 7.29 E+03 1.63 E+04 7.83 E+03 > Xe-131m 9.15 E+01 4.76 E+02 1.56 E+02 ' l.11E+03 ' Xe-133m 2.51 E+02 9.94 E+02 3.27 E+02 1.48 E+03 Xe-133 2.94 E+02 3.06 E+02 3.53 E+02 1.05 E+03 > > Xe-135m 3.12 E+03 7.11 E+02 3.36 E+03 7.39 E+02 Xe-135 1.81 E+03 1.86 E+03 1.92 E+03 2.46 E+03 I Xe-137, 1.42 E+03 1.22 E+04 .1.51 E+03_ l.27 E+04 l Xe-138 8.83 E+03 _ 4.13 E+03 9.21 E+03 4.75 E+03 ' Ar-41 8.84 E+03 2.69 E+03 9.30 E+03.- 3.28 E+03 ', l
=+
t (a) The listed dose factors are derived from Reg. Guide 1.109, Table B-I (Rev.1,1977) I l _ _ ~ . . . _ . . _ . . . _ . . ..n.-_.___... _.._......__._._.,,.-._n._...n._._..-...,..__;_...._-.~._.._._____.._____________-
APA-71.-01003 Rev.4 TABLE 3.2 PATHWAY DOSE FACTORS (Rj) FOR RADIONUCLIDES OTHERTHAN NOBLE GASESa Ground Plane Pathway (m2mrem /yr)per( Ci/sec)
' NUCLIDE TOTAL BODY M Be-7 2.24E+07 3.21E+07 Na-24 1.19E+07 1.39E+07 Cr-51 4.66E+06 5.51E+06 Mn-54 1.39E409 1.63E+09 Mn-56 9.04E+05 1.07E+06 Fe-59 2.73E408 3.21E+08 Co-57 2.98E+08 4.37E+08 Co-58 3.79E408 4.44E+08 Co-60 2.15E+10 2.53E+10 Ni-65 2.97E+05 3.45E+05 Cu-64 6.07E+05 6.88E+05 Zn-65 7.47E+08 8.59E+08 Br-82 3.14E+07 4.49Et07 Br-83 4.87E+03 7.08E403 Br-84 2.03E+05 2.36E+05 b86 8.99E+06 1.03E+07 Rb-88 3.31E+04 3.78E+04 6 89 1.23E+05 1.48E+05 St-89 2.16E404 2.51E+04 St-91 2.15E+06 2.51E+06 St-92 7.77E+05 8.63E+05 Y-90 5.35E+06 6.32E+06 Y-91m 1.00E+05 1.16E+05 Y-91 1.07EC 1.21E+06 ;
Y-92 1.80E4 t." 2.14E+05 Y 93 1.83E+05 2.51E+05 Zr-95 2.45E+08 2.84E+08 Zr-97 2.96E+06 3.45E+06 Nb-95 2.50E+08 2.94E+08 Mo-99 4.00E+06 4.63E+06 i 14570329 47361354 I l 23- l
)
1
! APA-ZZ-01003 Rev.4 TABLE 3.2 (Cont'd) PATInVAY DOSE FACTORS (Rj) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Ground Plane Pathway (m2mrem /yr)per( Ci/sec) i NUCLIDE TOTAL BODY SKIN Tc-99m 2.02E+06 2.31E+06 Tc 101 2.04E+04 2.26E+04 Ru-103 1.08E+08 1.26E+08 Ru-105 6.36E+05 7.21E+05 Ru 106 4.22E+08 5.07E+08 Ag-110m 3.44E+09 4.01E+09 Cd-109 3.76E+07 1.54E+08 Sn-113 1.43E+07 4.09E+07 Sb 124 8.74E+08 1.23E+09 Sb-125 3.57E+09 5.19E+09 Te-125m 1.55E+06 2.13E+06 Te-127m 9.17E+04 1.08E+05 Te-127 2.98E%3 3.28E+03 Te-129m 1.98E+07 2.31E+07 Te-129 2.62E+04 3.10E+04 Te-131m 8.03E+06 9.46E+06 Te 131 2.92E+04 3.45E+04 Te-132 4.23E+06 4.98E+06 1-130 5.51E406 6.69E+06 I-131 1.72E407 2.09E+07 I132 1.25E+06 1.47E+06 I-133 2.45E406 2.98E+06 I-134 4.47E+05 5.31E+05 I135 2.53E+06 2.95E+06 Cs 134 6.85E409 8.00E+09 Cs-136 1.51E+08 1,71E+08 Cs-137 l.03E+10 1.20E+10 Cs-138 3.59E+05 4.10E+05 Ba-139 1.06E+05 1.19E+05 Da-140 2.0$E+07 2.35E+07 1 14570329 473E13E3 24- , I
3 APA-ZZ-01003 l Rev.4-a TABLE 3.2 (Cont'd) . l
.I PATHWAY DOSE FACTORS (Ri ) FOR RADIONUCLIDES l OTHERTHAN NOBLE GASES- i
~
Ground Plane Pathway (m2 miem/yr)per( Ci/sec) j l NUCLIDE TOTAL BODY SM -
.l Ba-141 . . - 4.17E+04 4.75E+04 !
Ba-142 4.49E+04 5.11E+04 l' La-140 1.47E+08 1.66E+08 La-142 7.60E+05 9.12 EMS Cc 141 1.37E+07 1.54E+07 _q Cc-143 2.31E+06 2.63E+06 f
. Cc-144 6.96E+07 8.04E+07 ;
Pr-144 4.35E+07 5.00E+07 i 8.39E+06 1.01E+07 j Nd-147 Eu-154 2.21E+10 3.15E+10 l
-l
- Hf 181 1.97E+08 2.82E+08 j W-187 2.35E+06 2.73E46 !
I Np-239 1.71E+06 1.98E+06 I l t 5 i I l l i 14570329 47361366 l l 1 25-1 I
i' APA-ZZ-01003 Rev. 4 ; t TABLE 3.3 CHILD PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa
. Inhalation Pathway. ;
I (mrem /yr) per (pCi/m') TOTAL NUCLIDE RQNE LIVER BODY THYROID KIDNEY LUNG GI-LLI { l H-3 l ND l 1.12E+03 l 1.12E+03 l 1.12E+03 l.1.12EM3 l 1.12E+03 l .1.12E+03 l l Be-7 l 8.47E+02 l 1.44E+03 l 9.25E+02 l ND l ND l 6.47EM4 l 2.55E+03 l l lC-14 l 3.59E+04 l 6.73E+03 l 6.73E+03 l . 6.73E+03 l 6.73E+03 l 6.73E+03 l 6.73E+03 l 1 l Na 24 l 1.61E+04 l 1.61E+04 l 1.61E+04 l 1.61E+04 l 1.61E+04 l 1.61E+04 l 1.61E+04 l ! l P-32 l 2 40E+06 l 1.14E+05 l 9.88E+04 l ND l ND l ND l 4.22E+04 l ! l Cr-51 l ND l ND l 1.54E+02 l 8.55EMI l 2.43E+01 l 1.70E+04 l 1.08E+03 l l Mn-54 l ND l 4.29E+04 l 9.51E+03 l ND l 1.00E+04 l 1.58E+06 l 2.29E+04 l l l Mn-56 l ND l 1.66E+00 l 3.12E-01 l ND l 1.67E400 l 1.31E+04 l 1.23E+05 l l l Fe 55 l 4.74E+04 l 2.52E+04 l 7.77E+03 l ND l ND l 1.11E+05 l 2.87E+03 l ! l Fe-59 l 2.07E+04 l 3.34E+04 l 1.67E+04 l .ND l ND l 1.27E+06 l 7.07E+04 l ~ j lCo57 l ND l 9.03E+02 l 1.07E+03 l ND l ND l 5.07E+05 l 1.32E+04 l ! l Co-58 l ND l 1.77E+03 l 3.16E+03 l ND l ND l 1.11E+06 l 3.44E+04 l ; l Co-60 l ND l 1.31E+04 l 2.26E+04 l ND l ND l 7.07E+06 l 9.62E+04 l l Ni-63 l 8.21E+05 l 4.63E+04 l 2.80E+04 l ND l ND l 2.75E+05 l 6.33E+03 l ' l Ni-65 l 2.99E+00 l 2 %E-01 l 1.64E-01 l ND l ND l 8.18E+03 l 8.40E+04 l , l Cu-64 l ND l 1.99E+00 l 1.07E+00 l ND l 6.03E+00 l 9.58E+03 l 3.67E+04 l .l l Zn 65 l 4.26E+04 l 1.13E+05 l 7.03EM4 l ND l 7.14E+04 l 9.95E+05 l 1.63E+04 l j l Zn-69 l 6.70E-02 l 9.66E 02 l 8.92E-03 l ND l 5.85E-02 l 1.42E+03 l 1.02E+04 l l l Br-82 l ND l ND l 2.09E+44 l ND l ND l ND l 0.00E+00 l t lBr-83 l ND l ND l 4.74EM2 l ND- l ND l ND l 3.70E-15 l j lBr-84 l ND l ND l 5.48E+02'l ND l ~ND l ND l 3.70E-15 l I l Br 85 l ND l ND l 2.53E+01 l ND l ND l ND l - 3.70E-15 l , l Rb-86 l ND l 1.98E+05 l 1.14E+05 l ND l ND l ND l 7.99E403 l 1 l Rb-88 l ND l 5.62E+02l 3.66E+02 i ND l ND l ND. l 1.725+01 l l Rb-89 l ND l 3.45E+02 l 2.90E+02 i ND l ND l ND l 1.89E+00 l l St-89 l 5.99E+05l ND l 1.72E+04 l ND l ND l 2.16E+06 l 1.67E+05 l l lSt-90 l 1.01E+08 l ND l 6.44EM6 l ND l ND l - 1.48E+07 l 3.43E+05 l ; l Sr-91 l 1.21E+02 l ND l 4.59E+00 l ND l ND l 5.33E+04 l 1.74E+05 l l Sr-92 l 1.31E+01 l ND l 5.25E-01 ] ND l ND l 2.40E+04 l 2.42E+05 l lY-90 l 4.11E+03 l ND l 1.llE+02 l ND l ND l 2.62E+05 l ' 2.68E+05 l , 14570329 47361367 I
.. j
'f APA-ZZ-01003 l Rev. 4 TABLE 3.3 (Con't)
CHILD PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Inhalation Pathway 5 (mrem /yr)per( C1/m') ,. TOTAL
~ NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l Y-91m l 5.07E-01 l ND l 1.84E-02 l ND l ND l 2.81EM3 l 1.72E+03 l lY-91 l 9.14E+05 l ND l 2.44E+04 l ND l ND l 2.63E+06 l 1.84E+05 l . l Y-92 l 2.03E+01 l ND l 5.81E-01 l ND l ND l 2.39E+04 l 2.39E+05 l i lY-93 l 1.86E+02 l ND l 5.llE+00l ND l ND l 7.44E+04 l 3.88E+05 l t l Zr-95 l 1.90E+05 1 4.18E+04 l 3.70E+04 l ND l 5.96E+04 l 2.23E+06 l 6.llE+04 l l Zr-97 l 1.88E+02 l 2.72E+01 l 1.60E+01 l ND l 3.89E+01 l 1.13E+05 l 3.51E+05 l t l Nb-95 l 2.35E+04 l 9.18E+03 l 6.55E+03 l ND l 8.62E+03 l 6.14E+05 l 3.70E+04 l !
l Mo-99 l ND l 1.72E+02 l 4.26E+01 l ND l 3.92E+02 l 1.35E+05 l 1.27E+05 l l Tc 99m l 1.78E 03 l 3.48E-03 l 5.77E-02 l ND l 5.07E-02 l 9.51E+02 l 4.81E+03 l l Tc-101 l 8.10E-05 l 8.51E-05 l 1.08E-03 l ND l 1.45E-03 l 5.85E+02j 1.63E+01 l l Ru-103 l 2.79E+03 l ND l 1.07E+03 l ND l 7.03E+03 l 6.62E+05 l 4.48E+04 l , l Ru-105 l 1.53E+00 l ND l 5.55E-01 l ND l 1.34E+00 l 1.59E+04 l 9.95E+04 l l Ru-106 l 1.36E+05 l ND l 1.69E+04 l ND l 1.84E+05 l 1.43E+07 l 4.29E+05 l l Ag-110m l 1.69E+04 l 1.14E+04 l 9.14EM3 l ND l 2.12E+04 l 5.48E+06 l 1.00E+05 l l Cd-109 l ND l 5.48E+05 l 2.59E+04 l ND l 4.96E+05 l 1.05E+06 l 2.78E+04 l [ Sn-ll3 l 1.13E+05 l 3.12E+03 l 8.62E+03 l 2.33E+03 l ND l 1.46E+06 l 2.26E+05 l l Sb-124 ' l 5.74E+04 l 7.40E+02 l 2.00EM4 l 1.26E+02 l ND l 3.24E+06 l 1.64E+05 l lSb-125 l 9.84E+04 l 7.59E+02 l 2.07E+04 l 9.10E+01 l ND l 2.32E+06 l 4.03E+04 l l Te-125m l 6.73E403 l 2.33E+03 l 9.14E402 l 1.92E+03 l 0.00E40 l 4.77E405 l 3.38E+04 l l Te-127m l 2.49E+04 l 8.55E+03 l 3.02E+03 l 6.07EM3 l 6.36E+04 l 1.48E+06 l 7.14E+04 l lTe-127 l 2.77E+00 l 9.51E-01 l 6.llE-01 l 1.96E+00 l 7.07E+00 l 1.00E+04 l 5.62E+04l l Te 129m l 1.92E+04 l 6.84E+03 l 3.04E403 l 6.33E403 l 5.03E+04 l 1.76E+06 l 1.82E+05 l l Te-129 l 9.77E-02 l 3.50E-02 l 2.38E-02 l 7.14E-02 l 2.57E-01 l 2.93E+03 l 2.55E+04 l ? l Te-131m j 1.34E+02 l 5.92E+01 l 5.07E+01 l 9.77E+01 1 4.00E+02 l 2.06E+05 l 3.08E+05 l l Te-131 l 2.17E-02 l 8.44E-03 l 6.59E-03 l 1.70E 02 l 5.88E-02 l 2.05E+03 l 1.33E+03 l l Te 132 l 4.81EM2 l 2.72E+02 l 2.63E+02 l 3.17E+02 l 1.77E+03 l 3.77E+05 l 1.38E+05 l l I-130 l 8.18E+03 l 1.64E+04 l 8.44E+03 l 1.85E+06 l 2.45E+04 l ND l 5.llEM3 l l I-131 ] 4.81E+04 l 4.81E404 l 2.73E+04 l 1.62E+07 l 7.88E+04 l ND l 2.84E+03 l > l l-132 l 2.12E+03 l 4.07E+03 l 1.88E+03 l 1.94E+05 l 6.25E403 l ND l 3.20E+03 l lI133 l 1.66E+04 l 2.03E404 l 7.70E+03 l 3.85E+06 l 3.38E+04 l ND l 5.48E+03 l - _ l I-134 l 1.17E+03 l 2.16E+03 l 9.95E+02 l 5.07EM4 l 3.30E+03 l ND l 9.55E+02 ] , i 14570339 47361368 l
APA-ZZ-01003 ] Rev. 4 TABLE 3.3 (Con't) l CHILD PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER TTIAN NOBLE GASESa Inhalation Pathway i (mrem /yr) per (pCl/m') TOTAL ;
' NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GT-LLI ,
lI-135 l 4.92E+031 8.73E+03 l 4.14E+03 l 7.92E+05 l 1.34E+04 l ND l 4.44E+03 l ! l Cs-134 l 6.51E+05 l 1.01E+06 l 2.25E+05 l ND l 3.30E+05 l 1.21E+05 l 3.85E403 l , l Cs-136 l 6.51E+04 l 1.71E+05 l 1.16E+05 l ND l 9.55E+04 l 1.45E+04 l 4.18E+03 l ! l Cs-137 l 9.06E+05 l 8.25E+05 l 1.28E+05 l ND l 2.82E+05 l 1.04E+05 l 3.62E+03 l < l Cs-138 l 6.33E+02 l 8.40E+02 l 5.55EM2 l ND l 6.22E402 l 6.81E+01 l 2.70E+02 l j l Ba-139 l 1.84E+00 l 9.84E-04 l 5.37E-02 l ND l 8.62E-04 l 5.77E+03 l 5.77E+04 l l Ba 140 l 7.40E+04 l 6.47E+01 l 4.33E+03 l ND l 2.11E+01 l 1.74E+06 l 1.02E+05 l i l Ba-141 l 1.96E-01 l 1.09E-04 l 6.36E-03 l ND l 9.47E-05 l 2.92E+03 l 2.75E+02 l ! l Ba-142 l 5.00E 02 l 3.60E45 l 2.79E-03 l ND l 2.91E-05 l 1.64E+03 l 2.74E+00 l i l La 140 l 6.44E+02 l 2.25E+02 l 7.55E+01 1 ND l ND l 1.83E+05 l 2.26E+05 l ! ND ND 5 l La-142 l 1.29E+00 l 4.11E-01 l 1.29E-01 l l l 8.69E+03 l 7.59E+04 l l Cc 141 l 3.92E+04 l 1.95E+04 l 2.90E+03 l ND l 8.55E+03 l 5.44E+05 l 5.66E+04 l l lCe-143 l 3.66E+02 l 1.99E+02 l 2.87E+01 l ND l 8.36E+01 l 1.15E405 l 1.27E+05 1 ! l Cc-144 l 6.77E406 l 2.12E+06 l 3.61E+05 l ND l 1.17E+06 l 1.20E+07 l 3.88EM5 l j l Pr-143 l 1.85E+04 l 5.55E403 l 9.14E+02 l ND l 3.00E+03 l 4.33E+05 l 9.73E+04 l ! l Pr-144 l 5.%E-02 l 1.85E-02 l 3.00E 03 l ND l 9.77E-03 l 1.57E+03 l 1.97E+02 l l l Nd 147 l 1.08E+04 l 8.73E+03 l 6.81E+02 l ND l 4.81E+03 l 3.28E%$ l 8.21E+04 l l Eu-154 l 1.01E+07 l 9.21EM5l 8.40E+05 l ND l 4.03E406 l 6.14E+06 l 1.10E+05 l l Hf-181 l 2.78E+04 l 1.01E+05 l 1.25E+04 l ND l 2.05E+04 l 1.06E+06 l 6.62E+04 l l W-187 l 1.63E+01 l 9.66EMO l 4.33E+00 l ND l ND l 4.11E404 l 9.10E%4 l l Np-239 l 4.66E+02 l 3.34E+01 l 2.35EMI l ND l 9.73E+01 l 5.81E+04 l 6.40E+04 l i l 14570329 4736-1369 l
-2 8-
. 1 I
APA-ZZ-01003 Rev. 4 TA.BLE 3.3 (Cont'd) CHILD PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa , Meat Pathway (m2 mrem /yr)per(pCi/sec) TOTAL NUCLIDE RQ.N.E LIVER BODY THYROID _ KIDNEY LUNG GI-LLI a l H-3 l ND l 2.34E-K)2 l 2.34E+02 l 2.34E+02 l 2.34E+02 l 2.34E+02 l 2.34E+02 l . l Be-7 l 7.38E+03 l 1.26E+04 l 8.07E+03 [ 0.00E+00 l 1.23E%4 l 0.00E+00 l 7.00E+05 l lC-14 l 3.84E+08 l 7.68E+07 l 7.68E+07 l 7.68E+07 l 7.68E+07 l 7.68E+07 l 7.68E+07 l l Na-24 l 1.73E-03 l 1.73E-03 l 1.73E-03 l 1.73E-03 l 1.73E-03 l 1.73E-03 l 1.73E-03 l l P-32 l 7.43E+09 l 3.48E+08 l 2.86E+08 l 0.00E+00 l 0.00E+00l 0.00E+00 l 2.05E%8 l l Cr 51 l 0.00E%0 l 0.00E+00 l 8.80E+03 l 4.88E+03 l 1.33E+03 l 8.92E+03 l 4.67E+05 ! l Mn-54 l 0.00E+00 l 8.02E%6 l 2.14E+06 l 0.00E+00 l 2.25E+06 l 0.00E+00 l 6.73E+06 l l Mn-56 l 0.00E+00 l 1.82E-53 l 4.11E-54 l 0.00E+00 l 2.20E-53 l 0.00E+00l 2.64E-51 l lFe-55 l 4.58E+08 l 2.43E+08 l 7.52E-K)7 l 0.00E+00 l 0.00E+00 l 1.37E+08 l 4.50E+07 l , l Fe-59 l 3.77E+08 l 6.10E+08 l 3.04E+08 l 0.00E+00 l 0.00E+00 l 1.77E+08 l 6.35E+08 l l Co-57 1 0.00E+00 l 5.92E+06 l 1.20E+07 l 0.00E+00 l 0.00E%0l 0.00E+00 l 4.85E%7 l l Co-58 l 0.00E+00 l 1.64E+07 l 5.03E+07 l 0.00E+00 l 0,.00E+00 l 0.00E+00 l 9.59E+07 l l l Co-60 l 0.00E+00 l 6.94E+07 l 2.0$E+08 l 0.00E400l 0.00E+00 l 0.00E+00 l 3.84E+08 l l Ni-63 l 2.92E+10 l 1.56E+09 l 9.92E+08 l 0.00E400 l 0.00E+00 l 0.00E+00 l 1.05E+08 l t l Ni-65 l 3.62E-52 l 3.41E 53 l 1.99E-53 l 0.00E+00l 0.00E+00 l 0.00E+00 l 4.18E-51 l l Cu-64 l 0.00E+00 l 2.99E-07 l 1.80E-07 l 0.00E+00 l 7.22E-07 l 0.00E+00 l 1.40E-05 l , l Zn-65 l 3.76EM8 l 1.00E+09 l 6.23E408 l 0.00E+00 l 6.31E+08 l 0.00E+00 l 1.76E+08 l l l Zn-69 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E400 l 0.00E+00 l 0.00E+00l 0.00E+00 l l l Br-82 l 0.00E+00l 0.00E+00[ 1.53E+03l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+00 l r l Br-83 l 0.00E+00 l 0.00E+00 l 9.82E-57 l 0.00E+00 l 0.00E+00 l 0.00EM0 l 5.74E-74 l l lBr-84 l 0.00E+00 l 0.00E+00 l 0.00E%0 l 0.00E+00l 0.00E+00 l 0.00E+00l 0.00E+00 l l Br-85 l 0.00E+00 l 0.00E+00[ 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00l
- l Rb-86 l 0.00E+00 l 5.77E+08 l 3.55E+08 l 0.00E+00 l 0.00E+00 l 0.00E+00l 3.71E+07 l l Rb-88 l 0.00E+00 l 0.00E+00 l 0.00E+00 [ 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l >
l Rb-89 l 0.00E+00 l 0.00E+00 l 0.00E+00l 0.00E+001 0.00E+00 l 0.00E+00 l 0.00E+00 l l Sr-89 l 4.82E+08 l 0.00E+00 l 1.38E+07 l 0.00E+00l 0.00E400 l 0.00E+00 l 1.87E+07 l , l Sr 90 l 1.04E+10 l 0.00E+00 l 2.64EM9 l 0.00E+00l 0.00E%0 ! 0.00E+00 l 1.40E+08 l , l S -91 l 2.42E-10 l 0.00E+00 l 9.13E 12 l 0.00E+00l 0.00E+00 l 0.00E+00 l 5.34E-10 l l l Sr-92 l 1.90E-49 l 0.00E400 l 7.60E-51 l 0.00E+00l 0.00E+00l 0.00E+00 l 3.59E-48 l ' lY-90 l 1.93E+05 l 0.00E+00l 5.16E+03 l 0.00E+00l 0.00E40 l 0.00E+00 l 5.49E+08 l 14570329 47361370 __r
APA-ZZ-01003 Rev. 4 i TABLE 3.3 (Cont'd) l CHILD PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Mest Pathway (m8 mrem /yr)per(pCi/sec) TOTAL 'f NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG Q-LTJ l Y-91m l 0.00E+00 l 0.00E+001 0.00E@0 l 0.00E+00 l 0.00EM0l 0.00E+00 l 0.00E+00 l 1 lY-91 l 1.80E+06 l 0.00E+00 l 4.82E+04 l 0.00E40 l 0.00E+00 ] 0.00E+00 l 2.40E+08 l l Y-92 l 2.46E-39 l 0.00E400 l 7.04E-41 l 0.00E+00 l 0.00E+00 l 0.00E40 l 7.llE-35 l lY-93 l 7.50E-12 l 0.00E+00 l 2.06E-13 l 0.00EMOl 0.00E+00 l 0.00E+00 l 1.12E-07 l , l Zr-95 l 2.67E+06 l 5.86E+05 l 5.22E+05l 0.00E+00 l 8.39E+05 l 0.00E40 l 6.llE+08 l l Zr-97 l 3.22E-05 l 4.66E-06 l 2.75E 06 l 0.00E+00 l 6.68E-06 l 0.00E+00 l 7.05E-01 l l l Nb-95 l 4.26E+06 l 1.66EM6 l 1.18E+06 l 0.00E+00 l 1.56E+06 l 0.00E+00l 3.07E+09 l l l Mo-99 l 0.00E+00 l 1.15E+05 l 2.85E+04 l 0.00E+00 l 2.46E+05 l 0.00E+00 l 9.53E+04 l [ Tc-99m l 4.00E+02 l 7.84E+02 l 1.30E+04 l 0.00E+00 l 1.14E+04 l 3.98E+021 4.46E+05 l l Tc-101 l 0.00E+00l 0.00E40l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+001 0.00E+00 l l Ru-103 l 1.55E+08 l 0.00E+00 l 5.96E+07 l 0.00E+00l 3.90E408 l 0.00E+00l 4.01E+09 l f' l Ru-105 l 9.17E-28 l 0.00E+00 l 3.33E-28 l 0.00E+00 l 8.06E-27 l 0.00E+00 l 5.99E 25 l l Ru-106 l 4.44E+09 l 0.00E+00 l 5.54E+08 l 0.00E+00l 6.00E+09 l 0.00E+00 l 6.91E+10 l , l Ag-110m l 8.40E+06 l 5.67E+06 l 4.53E+06 l 0.00E+00 l 1.06E+07 l 0.00E+00 l 6.75E+08 l l Cd-109 l 0.00E+00 l 1.91E+06l 8.84E+04 l 0.00E+00 l 1.70E+06 l 0.00E+00l 6.18E+06 l l Sn-ll3 l 2.18E+09 l 4.48E+07 l 11.4E+08 l 3.31E+09 l 0.00E+00 l 0.00E40 l 1.54E+09 l l Sb-124 l 2.93E+07 l 3.80E405 l 1.03E+07 l 6.46E+04 l 0.00E+00 l 1.62E+07 l 1.83E+08 l lSb-125 l 2.85E+07 l 2.20E+05 l 5.97E+06 l 2.64E+04 l 0.00E+00 l 1.59E+07 l ' 6.81E+07 l ; l Te-125m j 5.70E+08 l 1.54E+08 l 7.59E+07 l 1.60E+08 l 0.00E+00 l 0.00E+00 l 5.50E+08 l - l Te-127m ] 1.78E449 l 4.78E408 l 2,11E@8 l 4.25E+08 l 5.07E+09 l 0.00E400 l 1.44E+09 l j lTe-127 l 3.42E-10 l 9.21E-11 l 7.33E 11 l 2.36E-10 l 9.72E-10 l 0.00E+00 l 1.33E-08 l
.i l Te-129m l 1.79Et09 l 5.00E+08 l 2.78E+08 l 5.78E+08 l 5.26E+09 l 0.00E+00 l 2.19E+09 l .
l Te 129 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00EMO l 0.00E+00 l , l Te-131m l 7.02E+02 l 2.43E+02 l 2.58E+02 l 4.99E+02 l 2.35E+03 l 0.00E+00 l 9.85E+03 l l Te 131 l 0.00E400 l 0.00E+00l 0.00E+00 l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+00 l l Te 132 l 2.12E+06 l 9.40E+05 l 1.14E+06 l 1.37EM6 l 8.73E+06 l 0.00E+00 l 9.47E+06 l l1130 l 3.06E-06 l 6.18E-06 l 3.18E-06 l 6.80E-04 l 9.23E-06 l 0.00E+00 l 2.89E-06 l l l I-131 l 1.66E447 l 1.67E+07 l 9.47E+06 l 5.51E+09 l 2.74E+07 l 0.00E+00 l 1.48E+06 l I lI-132 l 1.06E-58 l 1.94E-58 l 8.93E-59 l 9.01E 57 l 2.97E-58 l 0.00E40 l 2.28E 58 l l I-133 l 5.70E-01 l 7.05E-01 l 2.67E-01 l 1.31E+02 l 1.17EMO l 0.00E+00 l 2.84E-01 l l lI134 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00EM0 l 0.00E+00_ l 0.00E+00 l j 14570329 47361371 I
APA-ZZ-01003 Rev. 4 TABLE 3.3 (Cont'd) . 6 CHILD PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Meat Pathway (m* mrem /yr) per (pC1/sec) TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI i l I-135 l 6.59E-17 l 1.19E-16 l 5.62E-17 l 1.05E-14 l 1.82E-16 l 0.00E+00 l 9.04E-17 l ! l Cs-134 l 9.23E+08 l 1.51E+09 l 3.20E+08 l 0.00E+00 l 4.69E+08 l 1.68E+08 l 8.17Et06 l t l Cs-136 l 1.62E+07 l 4.46E407 l 2.89E+07 l 0.00E+00 l 2.38E+07 l 3.54E+06 l 1.57E+06 l l Cs-137 l 1.33E+09 l 1.28E+09 l 1.89E+08 l 0.00E+00l 4.16E+08 l 1.50E+08 l 8.00E+06 l l l Cs-138 l 0.00E+001 0.00EMO l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+00 l 0.00E+00 l l Ba-139 l 0.00E+00l 0.00E+00 l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+00 l 1.20E 99 l l l Ba 140 l 4.39E+07 l 3.85E+04 l 2.56E+06 1 0.00E+00 l 1.25EM4 l 2.29E+04 l 2.22E+07 l ; l Ba-141 l 0.00E+00l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+00l 0.00E+00 l 0.00E+00 l s l Ba-142 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E%0 l 0.00E+00 l 0.00E+00 l l La 140 l 3.33E402 l 1.17E+02 l 3.93E+01 1 0.00E400 l 0.00E+00 l 0.00E+00 l 3.25E+06 l ; l La-142 1 5.50E-92 l 1.75E-92 l 5.49E-93 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.48E-87 l [ l Cc-141 l 2.22E+04 l 1.11E+04 l 1.65E+03 l 0.00E+00 l 4.86E+03 l 0.00E+00 l 1.38E+07 l ; l Cc-143 l 3.18E-02 l 1.72E4Cl l 2.50E 03 l 0.00E+00 l 7.23E-03 l 0.00E+00l 2.52E+02 l l Cc-144 l 2.32E+06 l 7.27E+05 l 1.24E+05 l 0.00E400 l 4.02E+05 l 0.00E+00l 1.89E+08 l ] Pr-143 -l 3.34EM4 l 1.00E+04 l 1.66E+03 l 0.00E+00l 5.43E+03l 0.00E+00 l 3.61E+07 l , l Pr-144 l 5.63E+02 l 1.74E+02 l 2.83E+01 l 0.00E+00 l 9.21E+01 1 0.00E+00 l 3.75E+05 l l Nd-147 l 1.17E44 l 9.48E+03 l 7.34E402 l 0.00E+00l 5.20E+03 l 0.00E+00 l - 1.50E+07 l l l Eu-154 l 1.12E+07 l 1.01E+06 l 9.20EM5 l 0.00E+00 l 4.43E+06 l 0.00E+00 l 2.34E+08 l l i l Hf-181 l 4.77E+06 l 1.74E+07 l 2.15E+06 l 0.00E+00 l 3.53E+06 l 0.00E+00 l 6.41E+09 l l W-187 l 3.22E-02 l 1.91E-02 l 8.56E-03 l 0.00E400 l 0.00E+00l 0.00E+00 l 2.68E+00 l t l Np-239 l 4.33E-01 l 3.IIE-02 l 2.19E-02 l 0.00E+00 l 9.00E-02 l 0.00E+00 l 2.30E+03 l l l 1 14570329 47361372 l l
i APA-ZZ-01003 Rev. 4 ! 1 TABLE 3.3 (Cont'd) > CIULD PATHWAY DOSE FACTORS (Ri )FOR RADIONUCLIDES OTHER THAN ; NOBLE GASESa Grass-Cow-Milk Pathway (m8mrem /yr) per (pCi/sec) TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI lH3 l 0.00E+00 l 1.57E+03 l 1.57E+03 l 1.57E+03 l 1.57E+03 l 1.57E+03 l 1.57E+03 l l l Be-7 l 7.50E403 l 1.28E+04 l 8.20E+03 l 0.00E+00 l 1.25E+04 l 0.00E+00 l 7.12E+05 l j lC-14 l 1.20E+09 l 2.39E+08 l 2.39E+08 l 2.39E+08 l 2.39E+08 l 2.39E+08 l 2.39E+08 l l Na-24 - l 8.87E+06 l 8.87E+06 l 8.87E+06 l 8.87E+06 l 8.87E+06 l 8.87EM6 l 8.87E+06 l l P-32 l 7.79E+10 l 3.64E+09 l 3.00E+09 l0.00E+00 l 0.00E+00 l 0.00E+00 l 2.15E+09 l l Cr-51 , l 0.00E+00 [0.00E+00 l 1.02E+05 l 5.66E+04 l 1.55E+04 l 1.03E+05 l5.40E+06 l l Mn-54 l0.00E+00 l 2.10E+07 l5.59E+06 l0.00E+00 l 5.89E+06 l0.00E+00 l 1.76E+07 l : l Mn-56 l 0.00E+00 l 1.30E-02 l 2.93E-03 l 0.00E+00 l 1.57E-02 l 0.00E400 l1.88E+00 l l Fe-55 l 1.12E+08 l 5.94E+07 l 1.84E+07 l 0.00E+00 l 0.00E+00 l 3.36E407 [1.10E+07 l i l Fe-59 l 1.20E+08 l 1.95E+08 l 9.70E+07 l 0.00E+00 l 0.00E+00 l 5.64E+07 l 2.03E+08 l l Co-57 l0.00E+00 l 3.84E+06 [ 7.78E+06 l0.00E+00 l0.00E+00 1 0.00E+00 l 3.15E+07 l-l Co-58 l0.00E+00 l 1.21E+07 l 3.72E+07 1 0.00E+00 [ 0.00E+00 - l 0.00E+00 l 7.08E+07 l l Co-60 l0.00E400 [ 4.32E+07 l 1.27E+08 l0.00E+00 [0.00E400 l0.00E+00 l 2.39EM8 l , [ Ni-63 l 2.97E+10 l 1.59E+09 l 1.01E+09 l0.00E+00 l 0.00E+00 l 0.00E+00 l 1.07E+08 l l Ni-65 l 1.66E+00 l 1.56E-01 l 9.13E-02 l 0.00E+00 l0.00E+00 1 0.00E+00 l 1.92E+01 l ; 1 Cu-64 l0.00E400 l 7.47E+04 l 4.52EM4 l0.00E+00 l 1.81E+05 l0.00E+00 l 3.51E+06 l l Zn-65 l 4.14E+09 l 1.10E+10 l 6.86EM9 l 0.00EMO l 6.95E+09 l0.00E+00 l 1.94E+09 l l Zn-69 l 9.55E 12 l 1.38E Il l 1.28E-12 l 0.00E+00 l 8.37E-12 l 0.00E+00 l 8.70E-10 l t l Br-82 10.00E400 l0.00E+00 l 1.15E+08 l 0.00E+00 l 0.00E+00 l0.00E+00 l 0.00E+00 l l Br-83 l0.00E+00 l 0.00E+00 l 4.42E-01 l 0.00E+00 - l 0.00E+00 l 0.00E+00 l 2.58E-18 l , l Br-84 l 0.00E+00 l 0.00E+00 l 6.60E-23 l0.00E+00 l 0.00E+00 l 0.00E+00 l 3.34E-40 l , [ Br-85 l 0.00E+00 l0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l0.00E400 l 0.00E+00 l l Rb-86 1 0.00E+00 l 8.78E409 l5.40EM9 l 0.00E+00 l 0.00E+00 l0.00EM0 l5.65E+08 l [ Rb-88 l 0.00E+00 l 7.33E-45 l 5.09E-45 l0.00E+00 l0.00E+00 l 0.00E+00 l 3.60E-46 l l Rb-89 [0.00E+00 l 1.38E 52 l 1.23E-52 l0.00E+00 l0.00E+00 l0.00E400 l 1.21E-54 l l Sr-89 l 6.63E+09 [0.00E40 l 1.89E+08 l0.00E+00 l0.00E+00 l 0.00E+00 l 2.57E+08 l t l St-90 l 1.12E+11 l0.00E+00 l 2.84E+10 1 0.00E+00 l 0.00E+00 l 0.00E+00 [1.51E+09 l l St-91 l 1.31E+05 l 0.00E+00 l 4.93E+03 l 0.00E+00 l 0.00E+00 l0.00E+00 l 2.88E+05 l l St-92 l 2.19E+00 l 0.00E+00 l 8.79E-02 l0.00EMO l0.00E+00 [ 0.00E+00. l 4.15E+01 l t l Y-90 l 3.38E+03 l0.00E+00 l 9.05E+01 l0.00E+00 l 0.00E+00 l0.00E+00 l 9.62E+06 - l 14570329 47361373 1
.-l r .
APA-ZZ-01003 I Rev. 4 ! TABLE 3.3 (Cont'd) CHILD PATHWAY DOSE FACTORS (Rj)FOR RADIONUCLILES OTHER THAN ) NOBLE GASESa Grass-Cow-Milk Pathway l i (m8 mrem /yr)per(pC1/sec) ! i TOTAL l NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI ! l Y-91m l 2.70E-19 l 0.00E+00 l 9.83E-21 l0.00E+00 l0.00E+00 l 0.00E+00 l 5.29E-16 l . lY-91 [ 3.91E+04 l0.00E+00 l 1.04E+03 l 0.00E+00 - l 0.00E+00 l0.00E+00 l 5.20EM6 l' i l Y-92 l 2.54E-04 l0.00E+00 l 7.26E-06 l 0.00E+00 l 0.00EM0 l 0.00E+00 l 7.33E+00 l l l Y 93 l 1.01E+00 1 0.00E+00 l 2.78E-02 ]0.00E+00 l 0.00E+00 l 0.00E+00 l 1.51E+04 l l l Zr-95 l 3.84E+03 l 8.43E+02 l 7.51E+02 l0.00E+00 l 1.21E+03 l0.00E+00 l 8.80E45 l ; I l Zr-97 l 1.92E+00 l 2.78E-01 l 1.64E-01 l0.00E+00 l 3.99E-01 l0.00E+00 l 4.21E+04 l [ Nb-95 [ 3.72E+05 l 1.45E+05. l 1.03E+05 l0.00E+00 l 1.36E+05 l 0.00E+00 l 2.68E+08 l t l Mo-99 l 0.00E@0 l 8.15E47 l 2.02E+07 l 0.00E+00 l 1.74E+08 l0.00E+00 l 6.74E+07 l 'l l Tc-99m l 1.88E+04 l 3.70E+04 l 6.13E+05 l 0.00E%0 . l 5.37E+05 l 1.88E+04 l 2.10E+07 l { l Tc-101 l 1.20E-59 l 1.26E-59 l 1.59E-58 l 0.00E400 l 2.14E 58 l 6.64E-60 l 3.99E-59 l l Ru-103 l 4.29E+03 l0.00E+00 l 1.65E+03 l 0.00E+00 l 1.08E+04 l0.00E+00 l 1.llE+05 l , l Ru-105 l 3.83E-03 l0.00E+00 l 1.39E-03 l0.00E+00 l 3.37E 02 l 0.00E+00 l 2.50E+00 l f l Ru-106 l 9.25E+04 [0.00E+00 l 1.15EM4 l 0.00EMO l 1.25E+05 l 0.00E+00 l 1.44E+06 . l ! l Ag-110m l 2.09EM8 l 1.41E+08 j 1.13E+08 l0.00E+00 l 2.63E40& l 0.00E+00 l 1.68E+10 l [
. l Cd-109 l0.00E+00 l 3.86E+06 l 1.79EM5 ' l 0.00E+00 l 3.45E+06 l0.00E+00 l 1.25E+07 l l l Sn-113 l 6.llE+08 l 1.26E+07 l 3.48EM7 l 9.29E408 l 0.00E+00 l 0.00E+00 l 4.32E+08 l ;
i lSb-124 l 1.09E+08 l 1.41E+06 l 3.81E+07 l 2.40E+05 l0.00E+00 l 6.03E+07 l 6.80E+08 l' f lSb-125 l 8.71E+07 l 6.72E+05 l 1.83EM7 l 8.07E+04 1 0.00E+00 l 4.86E+07 l 2.08E+08 l i l Te-125m l 7.38E+07 l 2.00E+07 l 9.85E+06 l 2.07E+07 l 0.00E+00 l 0.00E+00 l 7.13E+07 l ! l Te-127m l 2.08E+08 l5.61E407 l 2.47E+07 l 4.98E+07 l5.94E408 1 0.00E+00 l 1.69E+08 l l lTe-127 l 2.98E+03 l8.04E402 l 6.39E+02 l 2.06E+03 l 8.48E+03 l0.00E400 l 1.16E+05 l ; i l Te-129m l 2.72E+08 l 7.59E+07 l 4.22E+07 l 8.76E407 l 7.98E+08 l 0.00E+00 l 3.31E+08 l: ! l Te-129 l 1.29E-09 l 3.61E 10 l 3.07E-10 l 9.22E-10 l 3.78E-09 l0.00E+00 l 8.04E-08 . l l Te-131m l 1.60E+06 l5.54E+05 l5.90E+05 l 1.14E+06 l5.36E+06 l 0.00E+00 l 2.25E+07 l l l Te-131 l 1.65E-32 l 5.02E-33 l 4.90E 33 l 1.26E 32 l 4.98E-32 l 0.00E+00 l 8.64E-32 l l 1.03E+07 l 4.54E+06 l 5.49E+06 l 6.61E+06 l 4.22E+07 l0.00E+00 l 4.57E+07 l l Te-132
.i l I-130 l 1.73E+06 l 3.50E+06 l 1.80E@6 l 3.85E+08 l 5.23E46 l 0.00E+00 l 1.64E+06 l .
l I-131 l 1.30E+09 l 1.31E+09 l 7.46E+08 l 4.34E+11 l 2.15E+09 l0.00E+00 l1.17E+08 l l l I-132 l 6.92E-01 l 1.27E+00 l 5.85E-01 l5.90E+01 l 1.95E+00 l0.00E+00 l 1.50E+00 l l l I-133 l 1.72E+07 l 2.13E+07 l 8.0$E+06 l 3.95E+09 l 3.54E+07 l 0.00E+00 l 8.57E+06 l
'lI-134 l 8.56E-12 l 1.59E-Il l 7.32E-12 l 3.66E-10 l 2.43E Il l 0.00EMO l 1.05E-11 l l
14570329 47361374 I APA-22-01003 Rev. 4 ) TABLE 3.3 (Cont'd) - l CHILD PATHWAY DOSE FACTORS (Rj)FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Grass-Cow-Milk Pathway (m8 mrem /yr)per(pCi/sec) TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l I-135 l 5.41E404 l 9.74E+04 l 4.61E+04, j 8.63E+06 l 1.49E+05 l 0.00E+00 l 7.42E+04 l l Cs-134 l 2.27E+10 l 3.72E+10 l 7.84EM9 [0.00E+00 l 1.15E+10 l 4.14EM9 l 2.00E+08 l l Cs-136 l 1.01E+09 l 2.78E+09 l 1.80E+09 l0.00E+00 l 1.48E+09 l 2.21E+08 l 9.78E+07 l l l Cs-137 l 3.23E+10 l 3.09E+10 l 4.56E+09 l 0.00E+00 l 1.01E+10 l 3.62E+09 l 1.93E+08 l l Cs-138 l 4.03E-23 l 5.61E-23 l 3.56E-23 l 0.00E+00 l 3.95E-23 l 4.25E-24 l 2.58E-23 l l Ba-139 l 2.02E-07 l 1.08E-10 ' l 5.86E-09 l0.00E+00 l 9.42E-11 l 6.34E-11 l 1.17E-05 l l Ba-140 l 1.17E%8 l 1.03E+05 i 6.84E406 l 0.00E+00 l 3.34E+04 l 6.12E+04 l 5.94E+07 l l Ba-141 l 1.90E-45 l 1.06E-48 l 6.17E-47 . l 0.00E+00 l 9.19E-49 l 6.24E-48 l 1.08E-45 l l Ba-142 l 1.21E-79 l 8.70E 83 l 6.75E-81 l 0.00E+00 l 7.04E-83 [ 5.12E-83 l 1.58E-81 l l La-140 l 1.78E+02 l 6.23E+01 l 2.10E+01 10.00EMO l 0.00E+00 l 0.00EMO l 1.74E+06 l l La-142 l 8.14E-11 l 2.60E-11 l 8.13E-12 l0.00E+00 l 0.00E+00 l0.00E+00 l 5.14E-06 l l Cc-141 l 2.19E+04 l 1.09EM4 l 1.62E+03 l0.00E+00 l 4.79E+03 l0.00E+00 l 1.36E+07 l lCc-143 l 1.88E+02 l 1.02E+05 l 1.47E+01 l 0.00E+00 l 4.27E+01 l 0.00E+00 l 1.49E+06 l l Ce 144 l 1.62E+06 [5.09 EMS l 8.67E+04 l0.00E%0 l 2.82E+05 l 0.00E%0 l 1.33E+08 l l Pr-143 l 7.19E+02 l 2.16E+02 l 3.57E+01 l0.00E+00 l 1.17E+02 [0.00EMO l 7.76E+05 l l Pr-144 l 5.04E+00 l 1.56E+00 l 2.53E-01 l0.00E+00 l 8.24E 01 1 0.00E+00 l 3.35E+03 l l Nd-147 l 4.45E+02 l 3.61E+02 l 2,79E+01 l0.00E+00 l 1.98E+02 l0.00EMO l5.71E+05 l l Eu 154 l 9.43E+04 l8.48E+03 l 7.75E+03 l0.00E+00 l 3.73E+04 l 0.00E400 l 1.97E+06 l l Hf-181 . l 6.44E+02 l 2.35EM3 l 2.91E+02 l 0.00E+00 l 4.76E+02 l0.00E+00 l 8.66E+05 -l l W-187 l 2.89E+04 l 1.71E%4 l 7.69E+03 l0.00E+00 l0.00E+00 l 0.00E+00 l 2.41E+06 l l Np-239 l 1.73E+01 l 1.24E+00 ' l 8.74E-01 l 0.00E%0 l 3.60E+00 l0.00E%0 l 9.21E+04 l 1 i I 14570329 473E1375 I j 1
]
APA-ZZ-01003 Rev. 4 i TABLE 3.3 (Cont'd) CHILD PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Gritss-Goat-Milk Pathway (m8 mrem /yr)per(pCl/sec) j TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG ' GI-LLI-l H-3 l 0.00E+00 l 3.20E+03 l 3.20E+03 l 3.20E+03 l 3.20E+03 l 3.20E+03 l 3.20E+03 l ; l Be-7 l. 9.00E+02 l 1.53E+03 l 9.84E+02 l 0.00E+00 l .1.50E43 l 0.00E+00 l 8.55E+04 l l C-14 l 1.20E+09 l 2.39E+08 l 2.39E+08 l 2.39E+08 l 2.39E+08 l 2.39E+08 l 2.39E+08 l l Na-24 l 1.06E+06 l 1.06E+06 l 1.06E+06 l 1.06E+06 l 1.06E+06 l 1.06E+06 l 1.06E+06 l l P-32 l 9.34E+10 [ 4.37EM9 l 3.60E+09 l 0.00E+00 l 0.00E+00l 0.00E+00 l 2.58E+09 l l Cr-51 l 0.00E+00 l 0.00E+00l 1.22E+04 l 6.79E63 l 1.85E+03 l 1.24E+04 l 6.48E+05 l l Mn-54 l 0.00E+00 l 2.52E+06 l 6.71E+05 l 0.00E+00 [ 7.06E+05 l 0.00E+00 [ 2.llE+06 l l Mn-56 l 0.00E+00 l 1.56E-03 l 3.52E-04 l 0.00E+00 l 1.89E-03 l 0.00E+00 l 2.26E-01 l l Fe-55 l 1.45EM6 l 7.72 EMS [ 2.39E+05 l 0.00E+00 l 0.00E400 l 4.36E445 l 1.43E+05 l l Fe-59 l 1.56E+06 l 2.53EM6 l 1.26E+06 l 0.00E+00 l 0.00E+00 l 7.34E+05 l 2.64E+06 l l Co-57 l 0.00E+00l 4.61E405 l 9.33E+05 l 0.00E400l 0.00E+00l 0.00E+00 l 3.78E+06 l l t'o-58 l 0.00E+00 l 1.46E+06 l 4.46E+06 l 0.00E+00l 0.00E+00 l 0.00E+00 l 8.50E+06 l l Ct. 60 l 0.00E+00 l 5.19E+06 l 1.53E+07 l 0.00E+00l 0.00E40 l 0.00E+00 l 2.87E+07 l l Ni43 l 3.56E+09 l 1.91EM8 l 1.21E+08 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.28E+07 l l Ni-63 l 1.99E-01 l 1.88E-02 l 1.10E-02 l 0.00E+00 l 0.00E+00 [ 0.00E+00 l 2.30E+00 l l Cu-64 1 0.00E440 l 8.33E+03 l 5.03E403 l 0.00EMO l 2.01E44 l 0.00E@0 l 3.91E+05 ! ,
- l Zn-65 l 4.976M? l L22N9 l 8.23E+08 l 0.00E+00 [ 8.34E+08 l 0.00E+00l 2.32E+08 l !
l Zn-69 l 1.15E-12 l 1.66E-12 l 1.53E-13 l 0.00E+00 l 1.00E-12 l 0.00E+00 l 1.04E-10 l < lBr-82 l 0.00EMO l 0.00E+00 l 1.38E+07 l 0.00EM0 l 0.00E+00 l 0.00E+00 l 0.00E+00 l l Br-83 l 0.00E400 l 0.00E+00 l 5.30E-02 1 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.10E-19 l I l Br-84 l 0.00E%0 l 0.00E+00l 7.92E-24 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.00E41 l l Br 85 l 0.00E+00l 0.00E400 l 0.00E+00 l 0.00E400l 0.00E+00 l 0.00E+00 l 0.00E+00 l l Rb-86 l 0.00E+00 l 1.05E+09 l 6.48E+08 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 6.78E+07 l l Rb-88 l 0.00E+00l 8.80E-46 l 6.llE-46 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.32E-47 l l Rb-89 l 0.00E+00 l 1.66E 53 l 1.48E-53 l 0.00E+00l 0.00E@0 l 0.00E+00 l 1.45E-55 l l St-89 l 1.39E+10 l 0.00EWO l 3.97E+08 l 0.00E+00l 0.00E+00l 0.00E+00l 5.39E+08 l , t 1 Sr-90 l 2.35E+11 l 0.00E+00 l 5.95E+10 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.16E49 l l St-91 l 2.74E+05 l 0.00E+00 l 1.04E+04 l 0.00E@0 l 0.00E400 l 0.00E400 l 6.06E+05 l , l St-92 l 4.60E+00 l 0.00E+00 l 1.84E-01 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 8.72E+01 l l Y-90 l 4.06E+02 l 0.00E+00 l 1.09E+01 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.15EM6 l ,
)
14svosas 47ssis7s i I 1 I
. 4 - _ . . . __ . _._ _ __ _ . _ . _ . . _ _ . . _,
~
APA-ZZ-01003 Rev. 4 - TABLE 3.3 (Cont'd) i CHILD PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN j NOBLE GASESa j t
- Grass-Goat-Milk Pathway I (m2 mrem /yr)per(pCi/sec) .l TOTAL NUCLIDE , BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI !
l l Y-91m l 3.24E-20 l 0.00E+00 l 1.18E-21 l 0.00E+00 l 0.00E+00 l 0.00E400 l 6.35E 17 l t l Y-91 l 4.69E+03 l 0.00E+00 l 1.25E402 l 0.00E+00 l . 0.00E400 l 0.00E+00l 6.25E+05 l lY-92 l 3.05E-05 l 0.00E+00 l 8.72E-07 l 0.00E400l 0.00E+00 l 0.00E+00 l' 8.80E-01 [ lY-93 l 1.22E-01 l 0.00E+00 l 3.34E-03 l 0.00E+00l 0.00E400 l 0.00E+00 l 1.81E+03 l i l Zr-95 l 4.60E+02 l 1.01E+02 l 9.01E+01 l 0.00E+00 l 1.45E4021 0.00E+00 l 1.06E+05 l l 6 Zr-97 l 2.31E-01 l 3.33E-02 l 1.97E-02 l 0.00E+00l 4.78E 02 l 0.00E400 l 5.05E+03 l ; l Nb-95 l 4.46E+04 l 1.74E+04 l 1.24E+04 l 0.00E+00 l 1.63E+04 l 0.00E+00 l 3.21E+07 l . l Mo-99 [ 0.00E+00l 9.78E406 l 2.42E+06 l 0.00E+00 l 2.09E+07 l 0.00E+00 l 8.09E+06 l t l Tc-99m l 2.26E+03 l 4.44E+03 l 7.35E44 l 0.00E400 l - 6.44E+04 l 2.25E+03 l 2.52E+06 l .I r l Tc-101 l 1.44E-60 l 1.51E-60 l 1.91E-59 l 0.00E+00 l 2.57E-59 l 7.96E-61 l 4.79E-60 l' Ru-103 l 5.14E+02 l 0.00EM0l 1.98E+02 1 0.00E+00 l 1.29E+03 l 0.00E+00 l 1.33E+04 l j Ru-105 l 4.60E-04 l 0.00EMO l 1.67E-04 l 0.00E+00 l 4.04E-03 l 0.00E400 j 3.00E l l Ru-106 l 1.11E4041 0.00E+00 l 1.38E+03 l 0.00E+00 l 1.50E404 l 0.00E+00 l 1.73E+05 l l l Ag-110m l 2.51E+07 l 1.69E+07 l 1.35E407 l 0.00E+00 l 3.15E+07 l 0.00E400 l 2.01E+09 l J
-l Cd-109 l 0.00E+00 l 4.64E+05 l 2.15E+04 l 0.00E+00 l 4.14E+05 l 0.00E+00 l 1.50E+06 j
- l Sn-113 l 7.33E+07 l 1.51E+06 l 4.18E406 l 1.11E+08 l 0.00E+00 l 0.00E+00 l 5.18E+07 l ,
j Sb 124 l 1.30E+07 l 1.69E-t05 l 4.57E+06 l 2.88E+04 l 0.00E400 l 7.24E+06 l 8.16E+07 l l lSb-125 l 1.05E+07 l 8.06E+04 l 2.19E+06 l 9.68E+03 l 0.00E+00 l 5.83E+06 l 2.50E407 l , l Te 125m l S.86E+06 l 2.40E+06 l 1.18E+06 l 2.49E+06 l 0.00E+00l 0.00E+00 l 8.55E+06 l : l Te 127m l 2.50E+07 l 6.73E+06 l 2.97E+06 l 5.98E+06 l 7.13E+07 l 0.00E+00 l 2.02E+07 j _ j lTe-127 . l '.58E+02 l 9.65E+01 1 7.67E+01 l 2.48E402 l 1.02E+03 l 0.00E+00 l 1.40E44 l l l Te 129m l 3.26E+07 l 9.10E+06 l 5.06E+06 l 1.05E+07 l 9.57E+07 l 0.00E+00 l 3.98E+07 l ! l Te-129 l 1.55E-10 l 4.33E-11 l 3.68E-11 l 1.11E-10 l 4.54E-101 0.00E400 , 9.65E-09 l l Te-131m l 1.92E+05 l 6.65E+04 l 7.07E+04 l 1.37E+05 l 6.43E+05 l 0.00E+00 l 2.70E+06 l l Te-131 l 1.97E-33 l 6.02E 34 l 5.88E-34 l 1.51E 33 l 5.97E-33 l 0.00E+00 l 1.04E-32 l , lTe132 l 1.23E+06 l 5.45E+05 l 6.58E+05 l 7.94E+05 l . 5.06E+06 l 0.00E+00 l ' 5.49E+06 l l1130 l 2.08E+06 j 4.20E+06 l 2.16E406 l 4.62EM8 l 6.27E+06 j 0.00E+00 l 1.%E+06 l l I 131 l 1.57E+09 l 1.57E+09 l 8.95E+08 l 5.21E+11 l 2.58E+09 l 0.00E400 l 1.40E+08 l ' l I-132 l 8.30E-01 l 1.53E+00 l 7.02E-01 l 7.08E+01 l 2.34E+00 l 0.00E+00 l 1.80E+00 l ll133 l 2 06E+07 l 2.55E+07 l 9.66E406 l 4.74E+09 l 4.25E+07 l 0.00E400 l 1.03E+07 l ; l I-134 l 1.03E-11 l 1.91E 11 l 8.78E 12 l . 4.39E-10 l - 2.92E-11 l 0.00E+00 l 1.27E-11 l
- i i
14570329 47361377 i l j
.. APA-ZZ-01003 -
Rev. 4 TABLE 3.3 (Cont'dl _ j CHILD PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN , NOBLE GASESa i Grass-Goat-Milk Pathway (m* mrem /yr) per (pC1/see) . 3 TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LVNG GJ-LLI - I l I-135 l 6.49E+04 l 1.17E+05 l 5.53E+04 l 1.04E+07 l 1.79E+05 l 0.00EMO l 8.90E+04 l l Cs-134 l 6.80E+10 l 1.12E+11 l 2.35E+10 l 0.00E+00 l 3.46E+10 l 1.24E+10 l 6.01E+03 l- ,; l Cs-136 l 3.04E+09 l 8.35E+09 l 5.40E409l 0.00E+00 l 4.45E+09 l 6.63E+08 l 2.93E+08 l l l Cs 137 l 9.68E+10 l 9.27E+10 l 1.37E+1^ l 0.00E+00 l - 3.02E+10 l 1.09E+10 l 5.80E+08 l-l Cs-138 l 1.21E-22 l 1.(BE-22 l 1.07E-22 l 0.00E+00 l 1.18E-22 l 1.27E-23 l 7.75E-23 l l Ba-139 l 2.42E-08 l 1.29E-11 l 7.03E-10 l 0.00E+00 l 1.13E-Il l - 7.61E-12 l 1.40E,-06 l l Ba-140 l 1.41E+07 l 1.23E+04 l 8.21E+05 l 0.00E+00 l 4.01E+03 l 7.35E403 l 7.13E+06 l j Ba-141 l 2.28E-46 l 1.27E-49 l 7.41E-48 l 0.00E+00 l 1.10E-49 l 7.49E-49 l 1.30E-46 l l Ba-142 l 1.45E-80 l 1.04E-83 l 8.10E-82 l 0.00E+00 l 8.45E-84 l 6.14E-84 l 1.89E-82 l 1~ l La 140 l 2.14E+01 l 7.47E400 l 2.52E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l - 2.08E+05 l i l La-142 l 9.77E-12 l 3.llE-12l 9.75E-13 l 0.00E+00 l 0.00E+00l 0.00E+00 l 6.17E-07 l l Cc-141 l 2.63E+03 l 1.31E+03 l 1.95E+02 l 0.00E+00l 5.75E+02 l 0.00E+00 l 1.63E+06 l : l Cc 143 l 2.25E+01 l 1.22E+04 l 1.77E+00 1 0.00E+00 l 5.12E+00l 0.00E+00 l 1.79E+05 l l Cc 144 l 1.95E+05 l 6.llE+04 l 1.04E+04 l 0.00E+00 l 3.38E+04 l 0.00E+00 l 1.59E+07 l ! l Pr-143 l 8.63E+01 l 2.59E+01 l 4.28E+00 l 0.00E+00 l 1.40E+01 l 0.00E+00 l 9.31E+04 l l Pr 144 l 6.05E-01 l 1.87E-01 l 3.04E-02 l 0.00E+00 l 9.89E-02 l 0.00E+00 l 4.03E+02 l l Nd-147 l 5.34E+01l 4.33E+01 l 3.35E+00 [ 0.00E400 l 2.37E+01 l 0.00E+00 l 6.85E+04 l l Eu-154 l 1.13E+04 l 1.02E+03 l 9.29E402 1 0.00E400 l 4.47E+03 _ l 0.00E+00 l 2.37E+05 l , l Rf 181 l 7.73E+01 l 2.81E+02 l 3.49E+01 l 0.00E+00 l 5.72E+01 l 0.00E+00l 1.04E+05 l l l W-187 l 3.47E+03 l 2.06E+03 l 9.22E+02 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 2.89E+05 l ; j Np-239 l 2.08E+00 l 1.49E-01 l 1.05E-01 l 0.00E+00 l 4.32E-01 l 0.00E+00 l 1.10E+04 l ; t i j i l t 14570329 4735137s ; i
-3 7- ;
l APA-ZZ 01003 l Rev. 4 TABLE 3.3 (Cont'd) CHILD PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa 1 Vegetation Pathway (m8 mrem /yr)per(pCl/sec) ) TOTAL ! NUCLIDE BONE LIVER BODY THYROID KIDNEY MEG GT-LLI l H-3 l -ND l 4.01E+03 l 4.01E+03 l 4.01E+03 l 4.01E+03 l 4.01E403 l 4.01E+03 l l Be-7 l 3.38E%5 l 5.76E%5l 3.70E+05 l 0.00E+00 l 5.65E+05 l 0.00E+00 l 3.21E+07 l lC-14 l 8.89E+08 l 1.78E+08 l 1.78E+08 l 1.78E+08 l 1.78E+08 l 1.78E+08 l 1.78E+08 l , l Na-24 l 3.73E+05 l 3.73E+05 l 3.73E+05 l 3.73E+05 l 3.73E+05 l 3.73E+05 l 3.73E405 l , l P-32 j 3.37E%9 l 1.58E+08 l 1.30E+08 l 0.00E+00 l 0.00E,00l 0 00E+00 l 9.32E+07 l j l l Cr-51 l 0.00E+00 l 0.00E+00 l 1.17E+05 l 6 6.50E+04 l 1.78E+04 l 1.19E+05 l .21E+06l j l Mn-54 l 0.00E+00 l 6.65EM8 l 1.77E+08 l 0.00E+00 l 1.86E+08 l 0.00E%0 l 5.58E408 l l Mn-56 l 0.00E+00 l 1.89E+01 l 4.26E+00 l 0.00E+00 l 2.28E+01 l 0.00E+00 l 2.74E+03 l j l Fe-55 l 8.01E+08 l 4.25E+08 l 1.32E+08 1 0.00E+00 l 0.00E+00 l 2.40E+08 l 7.87E+07 l . l Fe 59 l 3.98E+08 l 6.43E+08 l 3.20E408 l 0.00E+00l 0.00E+00 l 1.87E+08 l 6.70E+08 l l l Co-57 l 0.00E+00 l 2.99E+07 l 6.04E+07 l 0.00E+00l 0.00E+00 l 0.00E+00 l 2.45E+08 l l Co-58 l 0.00E40[ 6.44E+07 l 1.97E+08 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 3.76E+08 l [ Co-60 l 0.00E400 l 3.78E+08 l 1.12E+09 l 0.00E%0 l 0.00E+00l 0.00E+00 l 2.10E+09 l l Ni-63 1 3.95E+10 l 2.llE+09 l 1.34E+09 l 0.00E+00 l 0.00E+00l 0.00E+00 l 1.42E+08 l l Ni-65 l 1.05E+02 l 9.90E+00 l 5.78EMO l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.21E+03 l l l Cu-64 l 0.00E+00 l 1.10E+04 l 6.64E+03 l 0.00E+00 l 2.66E+04 l 0.00E+00 l 5.16E+05 l l l Zn-65 1 8.13E+08 l 2.17E%9 l 1.35E+09 l 0.00EMO l 1.36E+09 l 0.00E+00 l 3.80E+08 l i l Zn-69 l 9.53E-06 l 1.38E-05 l 1.27E-06 l ' 0.00E+00 l 8.35E-06 l 0.00E+00 l 8.68E-04 l l l Br-82 l 0.00E+00l 0.00E+00 l 2.04E+06 l 0.00E+00l 0.00E+00 l 0.00E+00l 0.00E+00 l . l Br-83 l 0.00E+00l 0.00E+00 l 5.38E+00 l 0.00E+00l 0.00E+001 0.00E+00 l 3.14E-17 l { l Br-84 l 0.00Et00l 0.00E+00 l 3.85E-Il l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1.94E-28 l l lBr-85 l 0.00E+00l 0.00EM0 l 0.00E+00l 0.00E+00 l 0.00E+00 l 0.00E%0 l 0.00EM0 l l Rb-86 l 0.00E400 l 4.52E+08 l 2.78E+08 l 0.00E+00 [ 0.00E+00 l 0.00E400 l 2.91E+07 l l Rb-88 l 0.00E+00 l 4.43E-22 l 3.08E-22 l 9.00E+00 l 0.00E+00 l 0.00E400 l 2.17E-23 l l l Rb-89 l 0.00E+00 l 4.67E-26 l 4.15E-26 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.07E-28 l j l St-89 l 3.60E+10 l 0.00E+00 j 1.03E+09l 0.00E+00l 0.00E+00 l 0.00E+00 l 1.39E+09 l , l St 90 l 1.24E+12 l 0.00E+00 l 3.15E+11 l 0.00E+00 l 0.00E+001 0.00E+00 l 1.67E+10 l l Sr 91 [ 5.24E45 l 0.00E+00 l 1.98E+04 1 0.00E+00 l 0.00E+00l 0.00E+00 l 1.16E+06 l l Sr 92 l 7.29E+02 l 0.00E+00l 2.92E+01 l 0.00E+to l 0.00E+00l 0.00E+00 l 1.38E+04 l j l Y-90 l 3.01E+06 l 0.00E+00 l 8.04E+04 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 8.56E+09 l ) 1 14570329 47361379 i i
)'
38
4 APA-ZZ-01003 > Rev. 4 TABLE 3.3 (Cont'd) { CHILD PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN { NOBLE GASESa 1 1 Vegetation Pathway
- (m8 mrem /yr)per(pCi/sec) l TOTAL .
NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l Y-91m l 8.95E-09 l 0.00E+00 l 3.26E-10 l 0.00E+00l 0.00E%0 l 0.00E+00 l 1.75E-05 l ! lY-91 l 1.86E+07 l 0.00E400 l 4.99E+05 l 0.00E40l 0.00E+00l 0.00E+00 l 2.48E+09 l l Y-92 l 1.59E+00 l 0.00E+00 l 4.54E-02 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 4.58E+04 l l Y 93 l 2.93E+02 l 0.00E+00l 8.05E@0 l 0.00E+00 j 0.00E+00l 0.00E+00 l 4.37E+06 l l l Zr-95 l 3.86E406 l 8.48E+05 l 7.55E+05 l 0.00E+00 l 1.21E+06 l 0.00E+00 l 8.85E+08 l l [
] Zr-97 l 5.70E+02 l 8.24E+01 l 4.86E+01 l 0.00E+00 l 1.18E+02 l 0.00E+00 l 1.25E+07 l I l Nb-95 l 7.48E+05 l 2.91E+05 l 2.08E405 l 0.00E+00 l 2.74E+05 l 0.00E+00 l 5.39E+08 l t l Mo-99 l 0.00E+00l 7.71EM6 l 1.91E+06 l 0.00E40 l 1.65E+07 l 0.00E+00 l 6.38E+06 l l Tc-99m l 5.35E+02l 1.05E+03 l 1.74E+04 l 0.00E40 l 1.53E+04 l 5.33E+02 l 5.97E+05 l ,
l Tc-101 l 1.43E-30 l 1.49E-30 l 1.89E-29 l 0.00E+00 l 2.55E-29 l 7.90E-31 l 4.75E-30 l l Ru-103 l 1.53E+07 l 0.00E+00 l 5.90E+06 l 0.00E400 l 3'86E+07 l 0.00E+00 l 3.97E+08 l l Ru-105 l 9.17E+01 l 0.00E+00 l 3.33E+01 l 0.00E+00 l 8.06E+02 [ 0.00E+00 l 5.99E+04 l l Ru-106 l 7.45E408 l 0.00E+00 l 9.30E+07 l 0.00E+00 l 1.01E+09 l 0.00E+00 l 1.16E+10 l ! l Ag-110m l 3.21E+07 l 2.17E+07 l 1.73E+07 l 0.00E+00l 4.04E+07 l 0.00E+00 l 2.58E+09 l , l Cd-109 l 0.00E+00 l 2.45E+08 l 1.14E+07 l 0.00EM0 l 2.18E+08 l 0.00E+00l 7.94E+08 l l Sn-113 l 1.58E+09 l 3.25E+07 l 9.00E+07 l 2.40E+09 l 0.00E+00 j 0.00E+00 l 1.12E+09 l . lSb-124 l 3.52E+08 l 4.57E+06 l 1.23E+08 l 7.77E+05 l 0.00E+00 l 1.95E+08 l 2.20E+09 l ; j Sb-125 l 4.99E+08 l 3.85E+06 l 1.05E+08 l 4.63E+05 l 0.00Ee0 l 2.78E+08 l 1.19E+09 l l Te-125m l 3.51E+08 l 9.50E+07 l 4.67E+07 l 9.84E+07 l 0.00E+00 l 0.00E+001 3.38E+08 l l l Te 127m l 1.32E+09 l 3.56E+08 l 1.57E+08 l 3.16E+08 l 3.77E+09 j 0.00E+00l 1.07E+09 l . lTe-127 l 9.85E+03 l 2.66E+03 l 2.11E+03 l 6.82E+03 l 2.80E+041 0.00E+00 l 3.85E+05 l [ l l Te-129m l 8.41E+08 l 2.35E+08 l 1.31E+08 l 2.71E+08 l 2.47E+09 l 0.00E+00 l 1.03E+09 l l Tc-129 l 1.33E-03 l 3.70E-04 l 3.15E-04 l 9.46E-04 l 3.88E-03 l 0.00E+00 l 8.25E-02 l li l Te-131m l 1.54E+06 l 5.33E+05 l 5.68E+05 l 1.10E+06 l 5.16E+06 l 0.00E+00 l 2.16E%7 l l Te 131 l 2.59E-15 l 7.90E-16 l 7.71E-16 l 1.98E-15 l 7.84E-15 l 0.00E+00 l 1.36E-14 l ! lTe-132 l 7.00E+06 l 3.10E+06 l 3.74E+06 l 4.51E406 l 2.88E+07 l 0.00E+00 l 3.12E+07 l l I-130 l 6.16E+05 l 1.24E+06 l 6.41E+05 l 1.37E+08 l 1.86E+06 l 0.00E+00 l 5.82E+05l lI131 l 1.43E+08 l 1.44E+08 l 8.17E+07 l 4.76E+10 l 2.36E+08 l 0.00E+00l 1.28E+07 l l I-132 l 9.23E+01 l 1.70E+02 l 7.80E+01 l 7.87E+03 l 2.60E+02 l 0.00E60 l 2.00E402 l , l I-133 l 3.53E+06 l 4.3*/E406 l 65EM6 l 8.12E+08 l 7.28E+06 l 0.00E+00 l 1.76E+06 l ; l I-134 l 1.56E-04 l 2.89E-04 l 1.33E-04 l 6.65E-03 l 4.42E-04 l 0.00E+00 l 1.92E-04 l i
+
l 14570329 47361380 l l
APA-ZZ-01003 Rev. 4 1 TABLE 3.3 (Cont'd) , CHILD PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN ; NOBLE GASESa Vegetation Pathway
- (m8 mrem /yr) per (pCl/sec) j TOTAL ,
NUCLIDE BONE LIVER ,B,,p D Y THYROID KIDNEY LUNG GT-LLI l l-135 - l 6.26E+04 l 1.13E405 l 5.33E+04l 9.98EM6 l 1.73E+05 l 0.00E+00 l 8.59E+04.l [ l Cs-134 l 1.60E+10 l 2.6.1E+10 l 5.55E+09 l 0.00E+00 l 8.15E+09 l 2.93E409 l 1.42E+08 l t l Cs-136 l 8.24E+07 l 2.27EM8 l 1.47E+08 l 0.00E+00l 1.21E+08 l 1.80E+07 l 7.96E+06 l [ l Cs-137 l 2.39E+10 l 2.29E+10 l 3.38E+09 l 0.00E+00 l 7.46E+09 l 2.68E+09 l 1.43E+08 l l Cs-138 l 6.61E-Il l 9.20E-11 l 5.83E-11 l 0.00EMO l 6.47E-11 l 6.%E-12 l 4.24E-11 l 7 l Ba 139 l 4.97E-02 l 2.65E-05 l 1.44E-03 l 0.00E+00l 2.32E-05 [ 1.56E-05 l 2.87E+00 l [ l Ba-140 l 2.77E+08 l 2.43E+05 l 1.62E+07 l 0.00E+00 l 7.90EM4 l 1.45E+05 l 1.40E+08 l t l Ba 141 l 2.01E-21 l 1.13E-24 l 6.54E-23 l 0.00EMO l 9.74E-25 l 6.61E-24 j 1.15E 21 l ! l Ba-142 l 1.02E 38 l 7.31E-42 l 5.67E-40 l 0 00E+00 l 5.91E 42 l 4.30E-42 l 1.32E 40 l l La-140 l 3.36E+04 l 1.18E44 l 3.%E+03 l 0.00E+001 0.00EMO l 0.00E+001 3.28E+08 l- ; l La-142 l 3.37E-04 l 1.07E 04 l 3.36E-05 l 0.00E+00l 0.00E+00 l 0.00E+00 l 2.13E+01 l l Cc-141 l 6.56E+05 l 3.27E+05 l 4.86E+04 l 0.00EMO l 1.43E+05 l 0.00E+00 l 4.08EM8 l l Cc 143 l 1.72E+03 l 9.31E+05 l 1.35E402 l 0.00EMO l 3.91E+02 l 0.00E+00 l 1.36E+07 l 1 l Cc-144 l 1.27E+08 l 3.98EM7 l 6.78EM6 l 0.00E+00l 2.21E+07 l 0.00E400 l 1.04E+10 l l l Pr-143 l 1.46E+05 l 4.37E+04 l 7.23E+03 l 0.00E+00l 2.37E+04 l 0.00E+00 l 1.57E+08 l l Pr-144 l 7.88E+03 l 2.44E+03 l 3.97E402 l 0.00E+00l 1.29E+03 j 0.00E+00 l 5.25E+06 l I l Nd-147 [ 7.15E+04 l 5.79EM4 l 4.48E+03 l 0.00E+00l 3.18E+04 l 0.00E+00[ 9.17E+07 l l l Eu-154 l 1.66E408 l 1.50E+07 l 1.37E+07 l 0.00E+00 l 6.57E+07 l 0.00E+00l 3.48E+09 l r l Hf-181 ] 4.90E+05 l 1.79E+06 l 2.21E+05 l 0.00E4001 3.63E+05 l 0.00E+00 l 6.59E408 l l W-187 l 6.44E+04 l 3.81E+04 l 1.71E+04 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 5.36E+06 l l Np 239 l 2.57E+03 l 1.84E+02 l 1.30E+02 l 0.00E+00 l 5.33E+02 l 0.00E400 l 1.36E407 l i i l 14570329 47361381 : 4
-40 j l
l
APA-ZZ41003 i Rev. 4 - TABLE 3.4
-ADULT PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN l NOBLE GASESs i Inhalation Pathway i
- (arem/yr) per (pCi/m=)
i TOTAL j NUCLIDE RQHE LIVER BODY THYROID KIDNEY .L,.yNG GI-LLI l l H-3 l ND . l 1.26E403 l 1.26E+03 l 1.26E+03 l 1.26E+03 l 1.26E+03 l 1.26E+03 l l Be-7 l 4.27E+02 l 9.68E+02 l 4.70E+02 l ND l ND -l 4.21E+04 l 5.35E+03 l { lC-14 l 1.82E+04 l 3.4IE+03 1 3.4IE+03 l 3.4IE+03 l 3.41E+03 l 3.41E+03 l 3.41E+03 l 1 l Na-24 l 1.02EM4 l 1.02E+64 l 1.02E+04 l 1.02E+04 l1.02E+04 l 1.02E+04 l 1.02E+04 l i l P-32 l1.32E+06 l 7.71E+04 l 5.01E+04 l ND l ND l ND l 8.64E+04 l l l Cr-51 l ND l ND l 1.00E+02 1 5.95E+01 l 2.28E+01 l 1.44E+04 l 3.32E+03 l j l Mn-54 l ND l 3.96E+04 l 6.30E+03 l ND l 9.84E+03 l 1.40E+06 l 7.74E+04 l l l Mn-56 l ND - l 1.24E+00 l 1.83E-01 l ND l 1.30E+00 l 9.44E+03 l 2.02E+04 l l l Fe-55 l 2.46E+04 l 1.70E+04 l 3.94E+03 l ND l ND l 7.21E+04 l 6.03E+03 l l l Fe-59 l 1.18E+04 l 2.78E+04 l 1.06E+04 l ND l ND l 1.02E+06 l 1.88E+05 - l -l a l 6.92E+02 l 6.71E+02 l ND l ND l 3.70E+05 l 3.14E+04 l. ! l Co-57 l ND l Co-58 l ND l.1.58E+03 l 2.07E+03 l ND ' l ND l 9.28E+05 _ l 1.06E+05 l ! l Co-60 l ND l 1.15E+04 l 1.48E+04 l ND l ND l 5.97E46 '_ l 2.85E+05 l l l Ni-63 l 4.32E+05 l 3.14E+04 . l 1.45E+04 l ND l ND l 1.78E+05 l 1.34E+04 l ! l Ni-65 l 1.54E+00 l 2.10E-01 l 9.12E-02 l ND l ND l5.60E+03 l 1.23E+04 l l t l Cu l ND l 1.46E+00 l 6.15E-01 l ND l 4.62E+00 l 6.78E+03 l 4.90E+04 l l Zn-65 [ 3.24E+04 l 1.03E+05 l 4.66E+04 l ND l 6.90E+04 l8.64E+05 l 5.34E+04 l l Zn-69 l 3.38E42 l 6.51E-02 l 4.52E-03 l ND l 4.22E-02 ; 9.20E+02 l 1.63E+01 l l Bc-82 l ND l ND l 1.35E+04 l ND l ND lND l 1.04E+04 l l lBr-83 l ND l ND l 2.41E+02 l ND l ND l ND l 2.32E402 l l l Br 84 l ND l ND l 3.13E+02 l ND l ND l ND l 1.64E 03 J j l Br-85 l ND l ND l 1.28E+01 l ND l ND l ND l 8.00E-15 l c l Rb-86 [ ND l 1.35E+05 l5.90E+04 l ND l ND l ND., l 1.66E+04 l j l Rb-88 l ND l 3.87E+02 l 1.93E+02 l ND l ND l ND l 3.34E-09 l }
} Rb-89 l ND l 2.56E+02 l 1.70E+02 l ND l ND l ND l 9.28E 12 l i-
.j St 89 l 3.04E+05 l ND l 8.72E+03 l ND l ND [ 1.40E+06 l 3.50E+05 l l St-90 l 9.92E+07 l ND l 6.10E+06 l ND l ND l 9.60E+06 l 7.22E+05 l t l St-91 l 6.19E+01 l ND l 2.50E+00 l ND l ND l 3.65E+04 ; l 1.91E+05 _ l 'l*
l Sr-92 l 6.74E+00 l ND l 2.91E-01 l ND l ND l 1.65E+04 l 4.30E+04 l lY-90 l 2.09E+03 l ND l5.61E+01 l ND l ND l 1.70E+05 l 5.06E+05 l l l 1 14570329 47361382 ] l
\
_l
i APA-ZZ-01003 Rn. 4 I TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (R i) FOR RADIONUCLIDES OTHER THAN - NOBLE GASESa , Inhalation Pathway i (mrem /yr) per (pCi/m') t TOTAL [ NUCLTDR BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l Y-91m l 2.61E l ND l 1.02E-02 l ND l ND l 1.92E+03 l 1.33E+00 l lY-91 l 4.62E+05 l ND l 1.24E+04 l ND l ND l 1.70E+06 l 3.85E+05 l l Y-92 l 1.03E+01 l ND l 3.02E-01 l ND l ND l 1.57E+04 l 7.35E+04 l i lY-93 l 9.44E+01 l ND l 2.61E+00 l ND l ND l 4.85E+04 . l 4.22E+05 l l Zr-95 l 1.07E+05 l 3.44E+04 l 2.33E+04 l ND l 5.42E+04 l 1.77E+06 l 1.50E+05 l , j Zr-97 l 9.68E+01 l 1.96E+0! l 9.04EMO l ND l 2.97E+01 1 7.87E+04 l5.23E+05 l : l Nb-95 l 1.41E+04 l 7.82E+03 l 4.21E+03 l ND l 7.74E+03 l 5.0$E405 l 1.04E+05 l ; l Mo-99 l ND l 1.21E+02 l 2.30E+01 1 ND l 2.91E+02 l 9.12E+04 l 2.48E+05 l ! l Tc-99m l 1.03E-03 l 2.91E-03 l 3.70E-02 l ND l 4.42E-02 l 7.64E402 j 4.16E+03 l ~ l Tc-101 l 4.18E-05 l 6.02E-05 l 5.90E-04 l ND l 1.08E-03 l 3.99E+02 -l 1.09E-11 [ l Ru-103 l 1.53E43 l ND l 6.58E+02 l ND l5.83E403 l 5.05E%5 l 1.10E+05 l l Ru-105 l 7.90E-01 l ND l 3.11E 01 l ND l 1.02EMO l 1.10E+04 l 4.82E+04 l l Ru-106 l 6.91E+04 l ND l 8.72E+03 l ND l1.34E+05 l 9.36E406 l 9.12E+65 l l Ag-110m l 1.08E+04 [ 1.00E+04 l 5.94E+03 l ND l 1.97E+04 l 4.63E+06 l 3.02E+05 l l 1 Cd 109 l ND l 3.67E+05 l 1.31E+04 l ND l 3.57E+05 l 6.83E+05 l5.82E+04 l l Sn-113 l5.72E+04 l 2.18E+03 l 4.39E403 l 1.24E+03 l ND l 9.44E+05 l 1.18E+05 l l Sb-124 l 3.12E+04 l 5.89E+02 l 1.24E+04 l 7.55E+01 l ND l 2.48E+06 l 4.06E+05 l lSb-125 l 5.34E+04 l 5.95E+02 l 1.26E+04 l5.40E+01 l ND l 1.74E+06 l 1.01E+05 l l Te-125m l 3.42EM3 l 1.58E+03 l 4.67E402 l 1.0$E+03 l 1.24EM4 l 3.14E405 l 7.06E+04 l l Te-127m l L26E 44 l 5.77E+03 l 1.57E403 l 3.29E+03 l 4.58E+04 l 9.60E+05 l 1.50E+05 l lTe-127 l 1.40EMO l 6.42E-01 l 3.10E-01 l 1.06E+00 l5.10E400 l 6.51E+03 i 5.74E404 l ; l Te-129m l 9.76E+03 l 4.67E+03 l 1.58E+03 l 3.44E+03 l 3.66E+04 l 1.16E+06 l 3.83E+05 l lTe-129 l 4.98E-02 l 2.39E-02 l 1.24E-02 l 3.90E-02 l 1.87E-01 l 1.94E+03 l 1.57E+02 l l Te-131m l 6.99E+01 l L36E+01 l 2.90E+01 l5.50E+01 l 3.09E402 l 1.46E+05 l 5.56E+05 l-l Te-131 - l 1.llE-02 l 3.95E-03 l 3.59E.03 l 9.36E-03 l 4.37E 02 l 1.39E+03 l 1.84E+01 l lTe-132 l 2.60E+02 l 2.15E+02 l 1.62E+02 l 1.90E+02 l 1.46E+03 l 2.88E+05 l 5.10E+05 l l I-130 l 4.58E+03 l 1.34E+04 l5.28E+03 l 1.14E+06 l 2.09E+04 l ND l 7.69E+03 l t l I-131 l 2.52E444 l 3.58E+04 l 2.05E+04 l1.19E+07 l 6.13E404 l ND l 6.28E+03 l l I-132 l 1.16E+03 [ 3.26E+03 l 1.16E+03 l 1.14E+05 l 5.18E+03 l ND l 4.06E+02 l ' l I-133 1 8.64E+03 l 1.48E+04 l 4.52E+03 l 2.15E+06 l 2.58E+04 l ND l 8.88E+03 l ll134 l 6.44E+02 l 1.73E403 l 6.15E+02 l 2.98E+04 l 2.75E+03 l ND l 1.01E+00 l . 14s70329 473s13s3
APA-ZZ-01003 Rev. 4 i 1 $ TABLE 3.4 (Cont'd) i ADULT PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN 3 l NOBLE GASESa ! I Inhalation Pathway (mrem /yr) per( Ci/m') i l TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY 'ANG GI-LLI i ll-135 l 2.68E403 l 6.98E+03 l 2.57E403 [ 4.48E+05 l 1.liEve l ND l5.25E+03 l ; l Cs-134 l 3.73E405 j 8.48E+05 [ 7.28E+05 l ND l 2.87E+05 l 9.76E+04 l 1.04E+04 l l Cs-136 - l 3.90E+04 l 1.46E+05 l 1.10E+05 l ND l8.56E+04 l 1.20E+04 l 1.17E+04 l l Cs-137 l 4.78E+05 l 6.21E+05 l 4.28E+05 l ND l 2.22E+05 l 7.52E+04 [ 8.40E+03 l : l Cs-138 l 3.31E+02 l 6.21E+02 l 3.24E+02 l ND l 4.80E+02 l 4.86E+01 l 1.86E-03 l l l Ba-139 l 9.36E-01 l 6.66E-04 l 2.74E-02 l ND l 6.22E-04 l 3.76E+03 l 8.96E+02 l l l Ba-140 l 3.90E+04 l 4.90E+01 l 2.57E+03 l ND l 1.67E+01 l 1.27E+06 l 2.18E+05 l ' l Ba-141 l 1.00E-01 l 7.53E-05 l 3.36E-03 l ND l 7.00E-05 j 1.94E+03 l 1.16E-07 l l Ba-142 l 2.63E-02 l 2.70E-05 l 1.66E-03 l ND l 2.29E-05 l 1.19E+03 l 1.57E-16 l l La-140 l 3.44E402 l 1.74E+02 l 4.58E401 l ND l ND j1.36E+05 l 4.58E+05 l ; i t l La-142 l 6.83E-01 l 3.10E-01 l 7.72E-02 l ND l ND l 6.33E+03 l 2.11E+03 l l Cc 141 l 1.99E+04 l 1.35E+04 l 1.53E+03 l ND l 6.26E+03 l 3.62E+05 l 1.20E+05 l ! l Ce 143 l 1.86E+02 l 1.38E+02 l 1.53E+01 l ND l 6.08E+01 l 7.98E+04 l 2.26E%5 l lCe-144 l 3.43E+06 l 1.43E+06 l 1.84E445 l ND l 8.48E+05 l 7.78E+06 l 8.16E+05 l : l Pr-143 l 9.36E+03 l 3.75E+03 l 4.64E+02 l ND [ 2.16E+03 l 2.81E445 l 2.00E+05 l } l Pr-144 l 3.01E-02 l 1.25E-02 l 1.53E-03 l ND l 7.0$E-03 l 1.02E+03 l 2.15E-08 l , 1 Nd-147 l5.27E+03 l 6.10E+03 l 3.65E+02 l ND l 3.56E+03 l 2.21E+05 l 1.73E+05 l l l Eu 154 l 5.9?E+06 l 7.28E+05 l 5.18E+05 l ND l 3.49E+06 l 4.67E446 l 2.72E+05 l ! l Hr.181 l 1.41E+04 l 6.82E+04 l 6.32E+03 l ND [1.48E+04 l 6.85E445 l 1.39E+05 l , l W-187 l 8.48E+00 l 7.08E+00 l 2.48E+00 l ND l ND l 2.90E+04 l 1.55E+05 l l l Np-239 l 2.30E+02 l 2.26E+01 l 1.24E+01 l ND l 7.00E+0! l 3.76E+04 l 1.19E+05 l l t
?
t i 14570329 47361384 l
-4 3 -
l
APA-ZZ-01003 Rev. 4 TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa - Meat Pathway (m8 mrem /yr)per(pCi/sec) TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l H-3 l ND l 3.25E+02 l 3.25E+02 l 3.25E402 l 3.25E+02 l 3.25E+02 l 3.25E+02_ l l Be-7 [ 4.57E+03 l 1.04E+04 l 5.07E+03 l ND l 1.10E+04 l ND l 1.81E+06 l
'lC-14 l 2.41E+08 l 4.82E+07 l . 4.82E+07 l 4.82E+07 l 4.82E+07 l 4.82E+07 l 4.82E+07 l l Na-24 l 1.36E-03 l 1.36E 03 l 1.36E-03 l 1.36E-03 l 1.36E-03 l 1.36E-03 l 1.36E-03 l l P-32 l 4.65E+09 l 2.89E+08 l 1.80E+08 l ND l ND l ND l _ 5.23E+08 l l Cr-51 l ND l ND l 7.04E+03 l 4.21E+03 l 1.55E+03 l 9.34E+03 l 1.77E+06 l l Mn-54 l ND l 9.17E+06 l 1.75E+06 l ND i 2.73E+06 l ND l 2.81E+07 l l Mn-56 l ND l 1.68E-53 l 2.98E-54 l ND l 2.13E 53 l ND l 5.36E 52 l l Fe-55 l 2.93E+08 l 2.02E+08 l 4.72E+07 l ND l ND l 1.13E+08 l 1.16E+08 l l Fe-59 l 2.65E+08 l 6.24EM8 l 2.39E+08 l ND l ND l 1.74E+08 l 2.08E+09 l l Co-57 l ND l 5.63E+06 l 9.36E+06 l ND l ND l ND l 1.43E+08 l l Co-58 l ND l 1.82E+07 l 4.08E+07 l ND l ND l ND l 3.69E+08 l l Co-60 l ND l 7.51E+07 l 1.66E+08 l ND l ND l ND l 1.41E+09 l l Ni-63 l 1.89E+10 l 1.31E+09 l 6.33E+08 l ND l ND l ND l 2.73E+08 l l Ni-65 l 2.31E-52 l 3.00E-53 l 1.37E 53 l ND l ND l ND l 7.61E-52 l l Cu-64 l ND l 2.72E-07 l 1.28E-07 l ND [ 6.86E-07 l ND l 2.32E-05 l l Zn-65 l 3.56E%8 l 1.13E409 l 5.11E+08 l ND l 7.57E+08 l ND l 7.13E+08 l l Zn-69 l 0.00E+00l 0.00E+00 l 0.00E+00 l ND l 0.00E+00l ND l 0.00E+00 l lBr-82 l ND l ND l 1.22E+03 l ND l ND l ND l 1.40E+03 l lBr-83 l ND l ND l 6.18E-57 l ND l ND l ND l 8.90E-57 l l Br 84 l ND l ND l 0.00E+00l ND l- ND l ND l 0.00E+00 l l Br-85 l ND l ND l 0.00E+00 l ND l ND l ND l 0.00E+00 l l Rb-86 l ND l 4.87E+08 l 2.27E408 l ND l ND l ND l 9.60E+07 l l Rb-88 l ND l 0.00E+001 0.00E+00 l ND l ND l ND l 0.00E+00 l l Rb-89 l ND l 0.00E+00l 0.00E400 l ND l ND l ND l 0.00E+00 l l St-89 l 3.01E+08 l ND l 8.65E+06 l ND l ND l ND l 4.83E+07 l lSt-90 l 1.24E+10 l ND ] 3.05E+09 l ND l ND l ND l 3.59E+08 l l St-91 l 1.53E-10 l ND l 6.18E-12 l ND [ -ND l ND .l 7.28E-10 l lSr-92 l 1.21E-49 l ND l 5.23E 51 i ND l ND l ND l 2.39E-48 l l Y-90 l 1.21E+05 l ND l 3.24E+03 l ND l ND l ND l 1.28E+09 l 14570329 47361385
-44
APA-ZZ-01003 Rev. 4 TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Meat Pathway (m8 mrem /yr)per(pCi/sec) TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l _Y-91m l 0.00E+00 l ND l 0.00E+001 ND l ND l ND l 0.00E+00 1 - l Y-91 l 1.13EM6 l ND l 3.02E+04 l ND l ND l ND l 6.23E+08 l l Y-92 l 1.55E-39 l ND l 4.52E-41 l ND l ND l ND l 2.71E-35 l lY-93 l 4.72E-12 l ND l 1.30E-13 l ND l ND l ND l 1.50E-07 l l Zr-95 l 1.87E+06 l 6.00E+05 l 4.06E+05 l ND l 9.42E+05 l ND l 1.90E+09 l l Zr-97 l 2.07E-05 l 4.18E-06 l 1.91E-06 l ND l 6.32E-06 l ND l 1.30EH0 l l Nb-95 l 3.15EM6 l 1.75E+06 l 9.43E+05 l ND l 1.73E+06 l ND l 1.06E+10 l l Mo 99 l ND l 1.00E+05 l 1.90E+04 l ND l 2.26E+05 l ND l 2.32E+05 l l Tc-99m l 2.87EM2 l ' 8.10E+02 l 1.03E+04 l ND l 1.23E+04 l 3.97E+02 l 4.79E+05 l l Tc-101 l 0.00E400 l_ 0.00E40 l 0.00E+00 l ND l 0.00E+00 l 0.00E+00l 0.00E+00 l l Ru-103 l 1.05E+08 l ND l 4.53E+07 l ND [ 4.01E+08 l ND l 1.23E+10 l l Ru-105 l 5.86E-28 l ND l 2.32E-28 l ND l 7.58E-27 l ND l 3.59E-25 l l Ru-106 l 2.805409 l ND l 3.54E%8 l ND l 5.40E+09 l ND l 1.81E+11 j l Ag-110m l 6.68E+06 l 6.18E+06 { 3.67EM6 l ND~ j 1.21E+07 l ND l 2.52E+09 l l Cd-109 l ND 1 1.59E+06 l 5.55E+04l ND l 1.52E+06 l ND l 1.60E+07 l l Sn-113 l 1.37E+09 l 3.88E+07 l 7.86E+07 l 2.22E+07 l ND l ND l 4.09E+09 l lSb-124 l 1.98E+07 l 3.74E+05 l 7.84E406 l 4.79E+04 l ND l 1.54E+07 l 5.61E+08l l Sb-125 l 1.91E+07 l 2.13E+05 l 4.54E+061 1.94E+04 l ND l 1.47E+07 l 2.10E+08 l l Te-125m l 3.59E408 l 1.30E+08 l 4.80E47 l 1.08E+08 l 1.46E+09 l ND l 1.43E+09 l j l Te-127m l 1.11E+09 l 3.98E+08 l 1.36E+08 l 2.85E+08 l 4.53E+09 l ND l 3.74E+09 l ! l Te 127 l 2.14E-10 [ 7.67E-Il l 4.62E-Il l 1.58E-10 l 8.70E 10 l ND l 1.69E-08 l l Te 129m l 1.13E+09 l 4.23E+08 l 1.79EM8 1 3.89E+08 l 4.73E+09 l ND l 5.71E+09l l Te-129 l 0.00E400 l 0.00E+00 l 0.00E+00 l 0.00E+00l 0.00E+00 l ND l 0.00E+00 l ; l Te-131m l 4.52E442 l 2.21E+02 l 1.84E+02 l 3.50E+02 l 2.24E403 l ND l 2.19E+04 l ' l Te-131 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l ND l 0.00E+00 l lTe-132 l 1.42E+06 i 9.18E+05 l 8.62E+05 l 1.01E+06 l 8.84E+06 l ND l 4.34E+07 l l I-130 l 2.12E-06 l 6.27E-06 l 2.47E-06 l 5.31E-04 l 9.78E-06 l ND l 5.40E-06 l lI131 l 1.08E+07 l 1.54EM7 l 8.82E+06 l 5.04E+09 l 2.64E+07 l ND l 4.06E+06 l , lI132 l 7.20E-59 l 1.93E-58 l 6.74E 59 l 6.74E-57 l 3.07E-58 l ND -l 3.62E-59 l l 1133 l 3.67E-01 l 6.39E-01 l 1.95E-01 l 9.38E+0! l 1.llE+00 l ND l 5.74E-01 l j l1134 l 0.00E+00l 0.00E+00 [ 0.00E+001 0.00E+00 l 0.00E+00 l ND l 0.00E+00 l l 14570329 47361386
-4 5-
APA-ZZ-01003 Rev. 4 TABLE 3.4 (Cont'd)
' ADULT PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Meat Pathway (m8 mrem /yr) per(pCi/nc)
TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l l 1-135 l 4.48E 17 l 1.17E-16 l 4.33E 17 l 7.74E 151 1.88E-16 [ ND l 1.33E-16 l l Cs 134 l 6.57E+08 l 1.56E+09 l 1.28E+09 l ND l 5.06E+08 l 1.68E+08 l 2.74E+07 l l Cs-136 l 1.20E+07 l 4.76E+07 l 3.42EM7 l ND l 2.65E+07 l 3.63E+06 l 5.40E+06 l l Cs-137 l 8.71E+08 l 1.19E+09 l 7.81E408 l ND l 4.04E+08 l 1.34E+08 l 2.3IE+07 l _ l Cs-138 l 0.00E+00l 0.00E+00 l 0.00E+00 l ND l 0.00E+00l 0.00E+00 l 0.00E+00 l l Ba 139 l 0.00E+001 0.00E+00 l 0.00E+00 l ND 1 0.00E+00 l 0.00E400 l 0.00E+00 l l Ba-140 l 2.87E+07 l 3.61E+04 l 1.88E+06 l ND l 1.23E+04 l 2.07E+04 l 5.91E+07l l Ba-141 l 0.00E+00 l 0.00E+00 l 0.00E+00 l ND l 0.00E+00 l 0.00E+001 0.00E+00 l l Ba 142 l 0.00E+00l 0.00E+00 l 0.00E+00 l ND l 0.00E+00l 0.00E+00 l 0.00E+00 l l La-140 l 2.21E402 l 1.11E+02 l 2.94E+01 l ND l ND l ND l 8.18E+06 l l La-142 l 3.60E-92 l 1.64E 92 l 4.08E 93 l ND l ND l ND l 1.20E-88 l l Cc-141- [ 1.40E+04 l 9.49E+03 l 1.08E+03 l ND l 4.41E+03 l ND l 3.63E+07 l lCc-143 l 2.01E 02 l 1.49E+0! l 1.64E-03 l ND l 6.54E-03 l ND l 5.55E+02 l l Ce-144 l 1.46E+06 l 6.09E+05 l 7.82E+04 l ND l 3.61E+05 l ND l 4.92E+08 l l Pr-143 l 2.10E+04 l 8.40E+03 l 1.04E+03 l ND l 4.85E+03 l ND l 9.18E+07 l l Pr 144 l 3.52E402 l 1.46E+02 l 1.79E+01 l ND l 8.24E+01 l ND l 5.06E-05 l l Nd 147 l 7.07E+03 l 8.17E403 l 4.89E+02 l ND l 4.77E+03 l ND ] 3.92E+07 l l Eu 154 l 8.02E+06 l 9.86E+05 l 7.01E+05 l ND l 4.72E406 i ND l 7.14E+08 l l Hf-181 l 3.01E+06 l 1.46E+07 l 1.35E+06 l ND l 3.14E406 l ND l 1.66E+10 l l W-187 l 2.07E-02 l 1.73E-02 l 6.05E-03 l ND l ND -l ND l 5.67E+00 l l Np-239 l 2.63E-01 l 2.59E-02 l 1.43E 02 l ND l 8.07E-02 l ND l 5.30E+03l l 14570329 47361387
APA-ZZ-01003 Rev. 4 TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Grass-Cow-Milk Pathway j (m8 mrem /yr)per(pCisec) TOTAL NUCLIDE RQEE MYER BODY THYROID KIDNEY LUNG GI-LLI I l H-3 l ND l 7.63E+02 l 7.63E+02 l 7.63E402 l 7.63E+02 l 7.63E402 l 7.63E+02 l l Be-7 l 1.63E+03 l 3.72E+03 l 1.81E+03 l ND l 3.93E403 l ND- l 6.45E405 l l C-14 l 2.63E+08 l 5.27E+07 l 5.27E+07l 5.27E+07 l 5.27E+07 l 5.27E+07 l 5.27E+07 l 'l l Na-24 l 2.44E406 l 2.44E+06 l 2.44EM6 l 2.44E406 l 2.44E+06 l 2.44E+06 l 2.44E+06 l l P-32 l 1.71E+10 l 1.06E+09 l 6.61E+08 l ND l ND l ND l 1.92EM9 l l Cr 51 l ND l ND l 2.86E+04 l 1.71E+04 l 6.30E+03 l 3.79E+04 l 7.19E+06 l l Mn-54 l ND l 8.42E+06 l 1.61E+06 l ND l 2.50E+06 l ND l 2.58E+07 l l Mn-56 l 'ND l 4.20E-03 l 7.45E-04 l ND l 5.33E-03 l ND l 1.34E-01 l l Fe-55 l 2.51E+07 l 1.74E+07 l 4.05E+06 l ND l ND l 9.68E+06 l 9.96E406 l l Fe-59 l 2.97E+07 l 6.98E+07 l 2.68E+07 l ND l ND l 1.95E+07 l 2.33E+08 l l Co-57 l ND l 1.28E+06 l 2.13E406 l ND l ND l ND l 3.25E+07 l l Co-58 l ND l 4.72E+06 l 1.06E+07 l ND l .ND l ND l 9.56E+07 l l Co-60 l ND l 1.64E+07 l 3.62E+07 l ND l ND l ND l 3.08E+08 l l Ni 63 l 6.73E+09 l 4.67E+08 l 2.26E408 l ND l ND l ND l . 9.73E407 l l Ni-65 l 3.71E-01 l 4.82E-02 l 2.20E-02 l ND l ND l ND l 1.22E+00 l l Cu-64 i ND l 2.39E+04 l 1.12E+04 l ND l 6.01E+04 l ND l 2.03E+06 l l Zn-65 l 1.37E+09 l 4.37E+09 l 1.97E+09 l ND l 2.92E+09 l ND l 2.75E+09 l l Zn-69 l 2.llE-12l 4.03E 12 l 2.80E-13 l ND l 2.62E-12 l ND l 6.06E-13 l l Br-82 l ND l ND l 3.23E+07 l ND l ND l ND l 3.71E+07 l l Br-83 l ND l ND l 9.75E-02 l ND l ND l ND l 1.40E-01 l lBr-84 l ND l ND l 1.63E-23 l ND l ND l ND l 1.28E-28 l l Br-85 l ND l ND l 0.00E+00 l ND l ND l ND l 0.00E+00 l l Rb-86 l ND l 2.60E+09 l 1.21E+09 l ND l ND l ND l 5.12E+08 l l Rb-88 l ND l 2.19E-45 [ 1.16E-45 l ND l ND l ND l 3.03E-56 l l Rb-89 l ND l 4.45E 53 l 3.13E 53 l ND l ND l ND l 2.59E-66 l l Sr-89 1.45E+09 l ND l 4.17E+07 l ND l ND l ND l 2.33E+08 l l St-90 4.68E+10 l ND l 1.15E+10 l ND l ND l ND l 1.35E+09 l l Sr-91 l 2.90E404 l ND l 1.17E+03 l ND l ND l ND l 1.38E+05 l l St 92 l 4.90E-01 l ND l 2.12E-02 l ND l ND l ND l 9.71E+00 l lY-90 l 7.43E+02 l ND l 1.99E+01 l ND 'l ND l ND l 7.87E+06 l 14580329 ~47361388
-47
APA-ZZ-01003 Rev. 4 l l TABLE 3.4 (Cont'd) ADULT PA THWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa l Grass-Cow-Milk Pathwdy j (m* mrem /yr) per (pct /sec) l. TOTAL l NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l Y-91m l 6.04E-20 l ND l 2.34E-21 l ND l ND l ND l 1.77E-19 l lY-91 l 8.59EM3 l ND l 2.30E+02 l ND l ND l ND l 4.73E+06 l ' l Y-92 l 5.59E-05 l ND l 1.63E-06 l ND l ND l ND l 9.80E-01 l l Y-93 l 2.24E-01 l ND l 6.18E-03 l ND l ND l ND l 7.09E+03 l l Zr-95 l 9.44E+02 l 3.03E+02 l 2.05E+02 l ND l 4.75E+02 l ND l 9.59E+05 l ND ND ! l Zr 97 l 4.34E-01 l 8.75E 02 l 4.00E-02 l l 1.32E-01 l l 2.71E+04 l l Nb-95 l 9.65E+04 l 5.37E+04 l 2.89E+04 l ND 1 5.31E+04 l ND l 3.26E+08 l ; l Mo-99 l ND l 2.48E+07 l 4.72E+06 l ND l 5.61E+07 l ND l 5.74E+07 l l Tc 99m l 4.73E+03 l 1.34E+04 l 1.70E+05 l ND l 2.03E405 l 6.56E+03 l 7.92E%6 l l Tc-101 l 2.67E-60 l 3.85E-60 l 3.78E-59 l ND l 6.93E-59 l 1.97E-60 l 1.16E-71 l . l Ru-103 l 1.02E+03 l ND l 4.39E+02 l ND l 3.E9E+03 l ND l 1.19E+05 l ! l Ru-105 l 8.58E-04 l ND l 3.39E-04 l ND l 1.11E-02 l ND l 5.25E-01 l 3 l Ru-106 l 2.04E404 l ND l 2.58E+03 l ND l 3.94E+04 l ND l 1.32E+06 l ' l Ag-110m j 5.82E+07 l 5.39E+07 l 3.20E@7 l ND l 1.06E+08 l ND l 2.20E+10 l 1 Cd-109 l ND l 1.13E+06 l 3.95E+04 l ND l 1.08E+06 l ND l 1.14E47 l l Sn-113 l 1.34E+08 l 3.81E+06 l 7.73E+06 l 2.18E+06 l ND l ND l 4.02E+08 l l Sb-124 l 2.57E+07 l 4.86E+05 l 1.02E+07 l 6.24E+04 l ND l 2.00E+07 l 7.31E408 l lSb-125 l 2.04E+0's l 2.28E+05 l 4.87E+06 l 2.08E+04 l ND l 1.58E+07 l _2.25E+08 J , l Te-125m l 1.63EM7 l 5.90E+06 l 2.18E+06 l 4.90E+06 [ 6.63E+07 l ND l 6.51E+07 l ! l Te-127m l 4.58EM7 l 1.64E+07 l 5.58E+06 l 1.17E+07 l 1.86E+08 l ND l 1.54E+08 l l l Te-127 l 6.54EM2 l 2.35E+02 l 1.41E402 l 4.84E+02 l 2.66E+03 l ND l 5.16E+04 l l l Te-129m l 6.02E+07 l 2.25E+07 l 9.53E+06 l 2.07E+07 l 2.51E+08 l ND l 3.03E408 l l Te-129 l 2.84E-10 l 1.07E-10 l 6.92E-Il l 2.18E-10 l 1.19E-09 l ND l 2.15E-10 l l Te 131m l 3.61E+05 l 1.77E+05 l 1.47E+05 l 2.80E+05 l 1.79E+06 l ND l 1.75E+07 l l Te-131 l 3.67E-33 l 1.53E-33 l 1.16E-33 l 3.02E-33 l 1.61E-32 l ND l 5.19E-34 l l Te-132 l 2.40E446 l 1.55E+06 l 1.46E+06 l 1.72E+06 l 1.50E+07 l ND l 7.35E407 l l 1 lI130 l 4.21E+05 l 1.24E+06 l 4.91E+05 l 1.05E+08 l 1.94E+06 l ND l 1.07E+06 l l I-131 1 2.97E+08 l 4.25E+08 l 2.43E+08 l 1.39E+11 l 7.28E+08 l ND l 1.12E+08 l l I-132 l 1.65E-01 l 4.42E-01 l 1.55E-01 l 1.55E401 l 7.04E-01 l ND -l 8.30E-02 l l I-133 l 3.88E+06 l 6.75E+06 l 2.06E+06 l 9.92E+08 l 1.18E+07 l ND l 6.07E+06 l ) l I-134 l 2.04E-12 l 5.54E-12 l 1.98E-12 l 9.60E-Il l 8.81E 12 l ND l 4.83E-15 l 1 i i 14580329 47361389 j i
-4 8-
m t
. APA-ZZ-01003 i Rev. 4 l
- TABLE 3.4 (Cont'd) )
ADULT PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa , Grass-Cow-Milk Pathway , (m8 mrem /yr)per(pCi/sec) j TOTAL NUCLIDE 3.QE LIVER BODY THYROID KIDNEY LUNG GI-LLI i l I-135 l 1.29E+04 l 3.37EM4 l 1.25E+04 l 2.23E+06 l 5.41E+04 l ND l 3.81E+04 l l Cs-134 l 5.65E+09 l 1.35E+10 l 1.10E+10 l ND l 4.35E+09 l 1.45E409 l 2.35E+08 l [ l Cs-136 l 2.63E+08 l 1.04E+09 . ] 7.48E+08 l ND l 5.79E+08 l 7.93EM7 l 1.18E+08 l ! l Cs-137 l 7.38E409 l 1.01E+10 l 6.61E+09 l ND l 3.43E409 l 1.14E+09 l 1.95E+08 l 1 l Cs-138 l 9.17E-24 l 1.81E-23 l 8.97E-24 l ND l 1.33E-23 l 1.31E-24 l 7.72E-29 l l Ba-139 l 4.44E-08 l 3.17E-11 l 1.30E-09 l ND l 2.%E-11 l 1.80E-11 l 7.88E-08 l ', i Ba-140 l 2.69E+07 l 3.38E+04 l 1.76E+06 l ND l 1.15E+04 l 1.93E+04 l 5.54E+07 l : l Ba-141 l 4.19E-46 l 3.17E 49 l 1.42E-47 l ND l 2.95E-49 l 1.80E-49 l 1.98E-55 l ! l Ba-142 l 2.77E 80 l 2.84E-83 l 1.74E-81 l ND l 2.40E-83 l 1.61E-83 l 3.90E-98 l t l La-140 l 4.14E401 l 2.09E+01 l 5.51E+00 l ND l ND l ND l 1.53E+06 l .-
-- t l La-142 l 1.87E-11 l 8.49E 12 l 2.12E-12 l ND l .ND l ND l 6.20E-08. [ ;
lCe-141 l 4.85E+03 l 3.28E+03 l 3.72E+02 l ND l 1.52E403 l ND l 1.25E+07 l i l Cc 143 l 4.16E+01 l 3.08E+041 3.40E+00 l ND l 1.35E+01 l ND l 1.15E+06 l lCc-144 l 3.f8E405 l 1.50E+05 l 1.92E+04 l ND l 8.87E+04 l ND. l 1.21E+08 l l Pr-143 l 1.3 8E+02 l 6.34E+01 l 7.83E+00 l ND l 3.66E+01 l ND l 6.92E+05 l l Pr-144 l 1.10EM0 l 4.58E 01 l 5.61E-02 l ND l 2.58E.01 l ND l 1.59E-07 l ; l Nd-147 l 9.42E+01 l 1.09E+02 l 6.51E+00 l ND l 6.36E+01 l ND l 5.23E+05 l l l Eu 154 l 2.37E+04 l 2.91E+03 l 2.07E+03 l ND l 1.39E+04 l ND l 2.11E+06 l l l Hf 181 l 1.42E+02 l 6.92E+02 l 6.41E+01 l ND l 1.49E+02 l ND l 7.87E+05 { , j W-187 l 6.52E+03 l 5.45E+03 l 1.91E+03 l ND l ND l ND l 1.78E+06 l . l Np-239 l 3.69E400 l 3.62E-01 l 2.00E-01 l ND l 1.13E+00 l ND l 7.43E+04 l 1 l, 14580329 47361390 !
-49 l l
APA-ZZ 01003 Rev. 4 TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Grass-Goat-Milk Pathway (m8 mrem /yr) per( Ci/sec) TOTAL NUCLIDE BONE LIVER BODY TITYROID KTDNEY LUNG GI-LLI l H-3 l ND l 1.56E+03 l 1.56E+03 l 1.56E+03 l 1.56E+03 l 1.56E403 l 1.56E+03 l l Be-7 l 1.96E+02 l 4.47E402 l 2.17E402 l ND l 4.72E402 l ND l 7.74E+04 l lC-14 l 2.64E+08 l 5.27E+07 l 5.27E+07 l 5.27E+07l 5.27E+07 l 5.27E407 l 5.27E+07 j l Na-24 l 2.93E+05 l 2.93E405 l 2.93E+05 l 2.93E405 l 2.93E+05 l 2.93E+05 l 2.93E+05 l l P-32 l 2.05E+10 l 1.28E+09 l 7.94E+08 l ND l ND l ND l 2.31E+09 l l Cr-51 l ND l ND l 3.43E+03 l 2.05E+03 l 7.56E+02 l 4.56E+03 l 8.63E+05 l l Mn-54 l ND l 1.01E+06 l 1.93E+05 l ND l 3.01E+05 l ND l 3.10E+06 l l Mn-56 l ND l 5.04E-04 l 8.94E-05 l ND l 6.40E-04 l ND l 1.61E-02 l l Fe-55 l 3.27E+05 l 2.26E+05 l 5.26E+04 l ND l ND l 1.26E+05 l 1.30E+05 l lFe-59 l 3.87E+05 l 9.08E+05 l 3.48E405 l ND l ND l 2.54E+05 l 3.03E+06 l l Co-57 l ND l 1.54EM5 l 2.56E+05 l ND l ND l ND l 3.90E406 l l Co-58 l ND l 5.66E+05 l 1.27E+06 l ND l ND l ND l 1.15E+07 l l Co-60 l ND l 1.97E+06 l 4.35E+06 l ND l ND l ND l 3.70E+07 l l Ni-63 l 8.08E+08 l 5.60E+07 l 2.71E+07 l ND l ND l ND l 1.17E+07 l l Ni-65 l 4.46E-02 1 5.79E-03 l 2.64E-03 l ND l ND l ND l 1.47E-01 l l Cu-64 l ND l 2.66E+03 l 1.25E403 l ND l 6.71E+03 l ND l 2.27E+05 l l Zn-65 l 1.65E+08 l 5.24E+08 l 2.37E+08 l ND l 3.51E+08 l ND l 3.30E+08 l l Zn-69 l 2.53E-13 l 4.84E-13 l 3.37E-14 l ND l 3.15E-13 l ND l 7.28E-14 l l Br-82 l ND l ND l 3.88E+06 l ND l ND j ND l 4.45E+06 l lBr-83 i ND l ND l 1.17E-02 l ND l ND l ND l 1.69E-02 l l Br-84 l ND l ND l 1.96E-24 l ND l ND l ND l 1.54E-29 l lBr-85 l ND l ND l 0.00E+00l ND l ND l ND l 0.00E+00 l [ Rb-86 l ND l 3.12E+08 j 1.45E+08l ND j ND l ND l 6.15E+07 l l Rb-88 l ND l 2.63E-46 l 1.40E-46 l ND l ND l ND l 3.64E-57 l l Rb-89 l ND l 5.35E-54 l 3.76E-54 l ND l ND l ND l 3.1IE-67 l lSt89 l 3.05E+09 l ND l 8.75E+07 l ND l ND l ND l 4.89E+08 l l Sr-90 l 9.84E+10 l ND l 2.41E+10 l ND l ND l ND l 2.84E+09 l l St 91 l 6.09E+04 l ND l 2.46E+03 l ND l ND l ND l 2.90E+05 l l Sr-92 l 1.03E+00 l ND l 4.45E-02 l ND l ND l ND .] 2.04E+01 l l Y-90 l 8.92E+01 l ND l 2.39E+00 l ND l ND l ND l 9.46E+05 l t 14580329 47361391 l l
APA-ZZ-01003
%:: Rev. 4 F
TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (Rj) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa-Grass-Goat-Milk Pathway
. (m8 mrem /yr)per(pC1/sec)
. TOTAL NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI l Y-91m ' l 7.25E-21 l - ND l 2.81E-22 l ND l ND l ND l 2.13E-20 l l Y-91 l 1.03E%3 l ND l 2.76E+01 l ND l ND l ND l 5.68E+05 l l Y-92 l 6.72E-06 l ND l 1.96E-07 l ND l ND l ND l 1.18E-01 1 l Y-93 l 2.69E-02 l ND l 7.42E-04 l ND l ND l ND l 8.52E402 l l Zr-95 l 1.13EM2 l 3.63E+01 l 2.46E+01 l ND l 5.70E+01 l ND l . 1.15E+05 l l Zr-97 l 5.21E-02 l 1.05E-02 l 4.80E-03 l ND l 1.59E-02 l ND l 3.25E+03 l l Nb-95 l 1.16E+041 6.45E+03 l 3.47E@3 l ND l 6.37E+03 l ND l 3.91E+07 l l Mo-99 l ND l 2.98E+06 l 5.66E+05 l ND l 6.74E+06 l ND l 6.90E+06 l l Tc-99m l 5.69E+02 l 1.61E+03 l 2.05E+04 l - ND l 2.44E+04 1 7.87E+02. l 9.51E+05 l .
l Tc-101 l 3.21E-61 l 4.62E-61 l 4.54E-60 l ND l 8.33E-60 l 2.36E-61 l 1.39E-72 l l Ru-103 l 1.22E+02 l ND l 5.27EMI l ND l 4.67E+02 l ND l 1.43E+04 l l Ru-105 l 1.03E 04 l ND l 4.07E-05 l ND l 1.33E-03 l ND l 6.31E-02 l l Ru-106 l 2.45E+03 l ND l 3.10E+02 l ND l 4.73E+03 l ND l 1.59E*05 l . l Ag-110m l 6.99E+06 l 6.47E+06 l 3.84E+06 l ND l 1.27EM7 l ND l 2.64E+09 l l Cd-109 l ND l 1.36E+05 l 4.74E+03 l ND l 1.30E+05 l ND l 1.37E+06 l l Sn-113 l 1.61E+07 l 4.58E+05 l 9.28E+05 l 2.62E+05 l ND l ND l 4.83E+07 l l Sb-124 l 3.09EM6 l 5.84E+04 l 1.23E@6 l 7.50E+03 l ND l 2.41E+06 l 8.78E+07 l lSb-125 l 2.46EM6 l 2.74E+04 l 5.84E+05 l 2.50E+03 l ND l 'l.89E+06 l 2.70E+07 l l Te-125m l 1.96E+06 l 7.09E+05 l 2.62E+05 l 5.89E+05 l 7.96E406 l ND l 7.81E+06 l l Te-127m l 5.50E+06 l 1.97E+06 l 6.70E405 l 1.41E+06 l 2.23E+07 l ND l 1.84E+07 l l Te-127 l 7.85E+01 l 2.82E+01 l 1.70E+01 l 5.82E+01l 3.20E+02 l ND l 6.19E+03 l l Te-129m l 7.23E406 l 2.70E+06 l 1.14E+06 l 2.48E+06 l 3.02E+07 l ' ND l 3.64E+07 l l Te-129 l 3.41E-11 1 1.28E-11 l 8.32E-12 l 2.62E-11 1 1.43E-10 l ND l 2.58E-Il l l Te-131m l 4.34E+04 l 2.12E+04 l 1.77E+04 l 3.36E+04 l 2.15E+05 l 'ND l 2.llE+06 l l Te-131 l 4.40E 34 l 1.84E 34 l 1.39E-34 l 3.62E-34 l 1.93E-33 l ND l 6.24E-35 l l Te 132 l 2.89E+05 l 1.87E+05 l 1.75E+05 l 2.06 EMS l 1.80E+06 l ND l 8.83E+06 l l l-130 1 5.05E+05 l 1.49E+06 l 5.88E+05 l 1.26E+08 l 2.32E+06 l ND 1.1.28E+06l l l-131 l 3.56E+08 l 5.09E+08 l 2.92E+08 l 1.67E+11 l 8.72E48 l ND l 1.34E+08 l lI132 l 1.98E-01 l 5.29E-01 l 1.85E-01 l 1.85E+01 l 8.43E-01 l ND <l 9.95E-02 l JI.133 l 4.65E+06 l 8.09E+06 l 2.47E+06 l 1.19E+09 l 1.41E+07 l ND l 7.27E+06 l l I-134 l 2.44E-12 l 6.64E 12 l 2.37E-12 l 1.15E 10 l 1.06E-11 l ND l 5.78E-15 l 14580329 47361392
-51
~
V , APA-ZZ-01003 1 Rev. 4 TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m2 mrem /yr) per(pClhec) TOTAL NUCLIDE E B_QN_E. LIVER BODY TITYROID KIDNEY LUNG GT-LLI l I 135 l 1.54E+04 l 4.04E+04 l 1.49E+04 l 2.67E46 l 6.48EM4 l ND l 4.57E+04 l l Cs-134 l 1.70E+10 l 4.04E+10 l 3.30E+10 l ND l 1.31E+10 l 4.34E+09 l 7.07E+08 l l Cs-136 l 7.91E+08 l 3.12E+09 l 2.25E49 l ND l 1.74E+09 l 2.38E+08 l 3.55E+08 l ~ l Cs-137 l 2.22E+10 l 3.03E+10 l 1.99E+10 l ND 1 1.03E+1.0 l 3.42E+09 l 5.87EM8 l l Cs-138 l 2.75E-23 l 5.43E-23 l 2.69E-23 l ND l 3.99E-23 l 3.94E-24 l 2.32E-28 l l Ba-139 l 5.34E-09 l 3.80E-12 l 1.56E-10 l ND l 3.55E-12 l 2.16E-12 l 9.46E-09 l l Ba-140 l 3.23E+06 l 4.06E+03 l 2.12E+05 l ND l 1.38EM3 l 2.32E+03 l 6.65E+06 l l Ba-141 l 5.03E-47 l 3.80E-50 l 1.70E-48 l ND [ 3.54E-50 l 2.16E-50 l 2.37E-56 l l Ba 142 l 3.32E-81 l 3.42E-84 l 2.09E-82 l ND l 2.89E-84 l 1.93E-84 l 4.68E-99 l
- l La 140 l 4.97E+00 l 2.51E40 l 6.62E-01 l ND l ND l ND l 1.84E+05 l l La-142 l 2.24E-12 l 1.02E-12 l 2.54E-13 l ND l ND l ND l 7.45E-09 l l 5.82E+02 l 3.94E+02 l 4.46E+01 l ND l 1.83E+02 l ND. l 1.50E+06 l l Cc-141 lCc-143 l 4.99E+00 l 3.69E+03 l 4.09E-01 l ND l 1.63E+00 l ND l 1.38E+05 l l Cc 144 l 4.30E+04 l 1.80EM4 l 2.31E+03 l ND l 1.07E+04 l ND 1 1.45E+07 l l Pr-143 l 1.90E+01 l 7.61E+00 l 9.40E-01 l ND l 4.39E400 l ND l 8.31E+04 l l Pr-144 l 1.33E 01 l 5.50E-02 l 6.74E-03 l ND l 3.10E-02 l ND l 1.9f E-08 l l Nd-147 l 1.13E+01 [ 1.31E+01l 7.82E-01 l ND l 7.64E+00 l ND l 6.28h'+04 l l Eu 154 l 2.84E+03 l 3.49Ee2 l 2.49E+02 l ND l 1.67E+03 l ND l 2.53E+05 l
[ Hf-181 l 1.71E401 l 8.31E+01 l 7.70E+00 l ND l 1.79E+01 l ND l 9.46EM4 l l W-187 l 7.83E+02 l 6.54E+02 l 2.29E+02 l ND l ND l ND l 2.14E+05 l l Np-239 l 4.43E-01 l 4.35E-02 l 2.40E-02 l ND l 1.36E-01 l ND l 8.93E+03 l 14580329 47361393
-5 2 -
b
APA-ZZ-01003 Rev. 4 TABLE 3.4 (Cont'dt j ADULT PATHWAY DOSE FACTORS (R[) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa - Vegetation Pathway (m8 mrem /yr)per(pCi/sec) TOTAL ! NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI , l H-3 l ND l 2.26E+03 l 2.26E+03 l 2.26E+03 l 2.26E+03 l 2.26E+03 l 2.26E+03 l l Be 7 l 9.24E+04 l 2.11E+05 l 1.03E405 l ND l 2.23E+05 l ND l 3.66E+07 l l lC-14 l 2.28E+08 l 4.55E+07 l' 4.55E+07 l 4.55E+07 l 4.55E+07 l ' 4.55E+07 l 4.55E+07 l , l Na-24 l 2.69E+05 l 2.69E+05 l 2.69E+05 l 2.69E+05 l 2.69E+05 l 2.69E+05 l 2.69E+05 l l P-32 l 1.40E+09 l 8.74E+07 l 5.43E+07 l ND l ND l ND l 1.58E408 l j Cr-51 l ND l ND l 4.64E+04 l 2.78E+04 l 1.02E+04 l 6.16E+04 l 1.17E+07 l j l Mn-54 l ND l 3.13E+08 l 5.97E+07 l ND l 9.31E+07 l ND l 9.59E+08 l l Mn-56 l ND l 1.60E+01 l 2.84E+00 l ND l 2.03E+01 l ND l 5.10E+02 l l Fe 55 l 2.10E+08 l 1.45E+08 l 3.38E+07 l ND l ND l 8.08E+07 l 8.31E+07 l [ l Fe-59 l 1.26E+08 l 2.96E+08 l 1.14E+08 l ND l ND l 8.28E+07 l 9.88E+08 l l l Co-57 l ND l 1.17E+07 l 1.95E+07 l ND l ND l ND l 2.97E+08 l l Co-58 l ND l 3.07E407 l 6.89E+07 l ND l ND l ND l 6.23E+08 l l Co40 l ND l 1.67E+08 l 3.69E+08 l ND l ND l ND l - 3.14E+09 l l Ni-63 l 1.04E+10 l 7.21E+08 l 3.49E408 l ND l ND l ND l 1.50E+08 l , l Ni-65 l 6.16E+01 l 8.00E+00 l 3.65E+00 l ND l ND- l ND l 2.03E+02 l l l Cu.64 l ND l 9.20E+03 l 4.32E+03 l ND l 2.32E+04 l ND l 7.84E+05 l l Zn-65 l 3.17E+08 l 1.01E+09 j 4.56E+08 l ND l 6.75E+08 l ND l 6.36E+08 l l lZn49 l 5.52E.06 l 1.05E-05 l 7.34E-07 l ND l 6.85E-06 l ND l 1.59E-06 l j l Br-82 l ND l ND l 1.50E+06 l ND l ND l ND l 1.72E+06 l ! l Br-83 l ND l ND l 3.11E+00 l ND l ND l ND l 4.48E+00 l l l Br-84 l ND l ND l 2.49E-11 l ND l ND l ND l 1.96E-16 l l l Br-85 l ND l ND l 0.00E+00 l ND l ND l ND l 0.00E+00 l l l Rb-86 l ND l 2.19E+08 l 1.02E+08 l ND l ND l ND l 4.33E+07 l t l Rb-88 l ND l 3.47E-22 l 1.84E-22 l ND l ND l ND l 4.79E-33 l 1 l Rb-89 l ND l 3.94E-26 l 2.77E-26 l ND l ND l ND l 2.29E-39 l l St-89 l 9.97E+09 l ND l 2.86E+08 l ND l ND l ND l 1.60E+09 l . I l St-90 l 6.05E+11 [ ND l 1.48E+11 l ND l ND l ND l 1.75E+10 l l Sr-91 l 3.05E405 l ND l 1.23E+04 l ND l ND l ND j 1.45E+06l l St-92 l 4.27E+02 l ND l 1.85E+01 l ND l ND l ND l 8.46E403 l ) l Y-90 l 7.67E+05 l ND l 2.06E+04 l ND l ND l ND l 8.14E+09 l l 14580329 47361394 1
APA-ZZ-01003 : Rev. 4 i l TABLE 3.4 (Cont'd) i i
' ADULT PATHWAY DOSE FACTORS (R;) FOR RADIONUCLIDES OTHER THAN ,
NOBLE GASESa ! r L Vegetation Pathway (m8 mrem /yr) per(pCl/sec) ! TOTAL , NUCLIDE BONE LIVER BODY THYROtD KIDNEY LUNG GI-LLI f l Y-91m l 5.24E-09 l ND 1 2.03E-10 l ND l ND l ND l .1.54E-08 l f lY-91 l 5.llE+06 l ND l 1.37E+05 l ND l ND l ND l 2.81E+09 l i l Y-92 l 9.16E-01 l ND l 2.63E-02 l ND l ND. l ND l 1.60EM4 l ! lY-93 l 1.70E402 l ND l 4.68E+00 l ND l ND l ND l 5.38E+06 l . l Zr-95 l 1.17E+06 l 3.77E+05 l 2.55E+05 i ND l 5.91EM5 l ND l 1.19E+09 l l Zr-97 l 3.37E+02 l 6.81E+01 l 3.11E+01 l ND l 1.03E+02 l ND l 2.11E@7 l l Nb-95 l 2.40E45 l 1.34E+05 l 7.19E+04 l ND l 1.32E+05 l ND l . 8.11E+08 l : l Mo-99 l 0.00E+00l 6.15E+06 l 1.17E+06 [ ND l 1.39E+07 l ND l 1.43E+07 l ; l Tc-99m l 3.53E+02 l 9.%E402 l 1.27E+04 l ND l 1.51E+04 l 4.88E+02 l 5.90E+05l ! ND l Tc 101 l 8.34E-31 l 1.20E-30 l 1.18E-29 l l 2.16E-29 1 6.14E-31 l 3.61E-42 l l Ru-103 l 4.77E+06 l ND l 2.06E+06 l ND l 1.82E+07 l ND l 5.57EM8 l - ! l Ru-105 l 5.39E+01 l ND l 2.13E+01 l ND l 6.97E+02 l ND l 3.30E+04 l l l Ru-106 l 1.93E+08 l ND l 2.44E+07 l ND l 3.72E+08 1 ND l 1.25E+10 l , l Ag-110m l 1.05E+07 l 9.75E+06 l 5.79E+06 l ND l 1.92E+07 l ND l 3.98E+09 l i l Cd-109 l 0.00E+00 l 8.36EM7 l 2.92E+06 l ND l 8.00E+07 l ND l 8.43EM8 l t l Sn-113 l 4.16E+08 l 1.18E+07 l 2.40EM7 l 6.75E+06 l ND l ND l 1.2SE+09 l [ l Sb-124 l 1.04E+08 l 1.96E+06 l 4.llE407 l 2.51E+05 l ND l ~ 8.07E+07 l 2.94E+09 l
.]Sb-125 l 1.37E+08 l 1.53E+06 j . 3.25E+07 l 1.39E+05 l ND l 1.05E+08 l 1.50E+09 l !
l Te-125m l 9.66E+07 l 3.50E+07 l 1.29E407 l 2.90E+07 l 3.93E+08 l ND l 3.86E+08 l v l Te-127m l 3.49E+08 l 1.25E+08 l 4.26E+07 l 8.92E+07 l 1.42E+09 l ND -l 1.17E+09 l ! l Te 127 l 5.66E+03 l 2.03E+03 l 1.23E+03 l 4.20E+03 l 2.31E+04 l ND l 4.47E+05 l l Te-129m l 2.51E+08 l 9.38E+07 l 3.98E+07 l 8.64E+07 l 1.05E+09 l ND l 1.27E+09 l f l Te-129 l 7.65E-04 l 2.87E-04 l 1.86E-04 l 5.87E-04 l 3.22E-03 l ND l 5.77E-04 l l l Te-131m l 9.12E+05 l 4.46E+05 l 3.72E+05 l 7.07E+05 l 4.52E+06 l . ND l 4.43E+07 l ! ND ! l Te-131 l 1.51E-15 l 6.32E 16 l 4.78E-16 l 1.24E 15 l 6.63E-15 l l 2.14E-16 l l Te 132 l 4.30E+06 l 2.78E+06 l 2.61E+06 l 3.07E+06 l 2.68E+07 l ND- l 1.32E+08 l ! l lI130 l 3.93E+05 l 1.16E+06 l 4.57E+05 l 9.81E+07 l 1.81E+06 l ND. l 9.97E+05 l i lI131 l 8.08E47 l 1.16E+08 l 6.62E+07 l 3.79E+10 l 1.98E+08 l ND l 3.05E+07 l [ lI132 l 5.77E+01 l 1.54E+02 l 5,40E+01 l 5.40E+03 l 2.46E+02 l ND :l 2.90E401 l
- 11133 l 2.09E+06 l 3.63E+06 l 1.1IE+06 l 5.33E+08 l 6.33E+06 l ND l 3.26E+06 I l l
l I-134 l 9.69E-05 l 2.63E-04 l 9.42E-05 l 4.56E-03 l 4.19E-04 l ND l 2.30E-07 l ! l-l ! l 14580329"47361395 f
APA-ZZ-01003 Rev. 4 TABLE 3.4 (Cont'd) ADULT PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASESa Vegetation Pathway (m8 mrem /yr)per(pCi/sec) TOTAL NUCLIDE RQEE LIVER ),QDX THYROID . KIDNEY LUNG GI-LLI l I-135 l 3.90E+04 l 1.02E+05 l 3.77E404 l 6.74E46 l 1.64E+05 l ND l 1.15E+05 l l Cs 134 l 4.67E409 l 1.11E+10 l 9.08EM9 l ND l 3.59E+09 l 1.19E+09 l 1.94E+08 l l Cs 136 l 4.27E+07 l 1.69E+08 l 1.21E+08 l ND -l 9.38E407 l 1.29E+07 l 1.91E+07 l o l Cs-137 l 6.36E+09 l 8.70E+09 l 5.70E+09 l ND l 2.95E+09 l 9.81E+08 l 1.68E+08 l l Cs-138 l 3.94E-11 l 7.78E-11 l 3.86E-11 l ND l 5.72E-11 l 5.65E-12 l 3.32E-16 l . j Ba-139 l 2.86E-02 l 2.04E-05 l 8.39E-04 l ND l 1.91E-05 l 1.16E-05 l 5.08E-02 l l Ba-140 l 1.29E+08 j 1.61E+05 l 8.42E+06 l ND l 5.49E404 l 9.24E+04 l 2.65E+08 l l Ba-141 1 1.16E-21 l 8.81E-25 l 3.93E-23 l ND l 8.19E-25 l 5.00E-25 l 5.49E-31 l
. l Ba-142 l 6.09E-39 l 6.26E-42 l 3.83E-40 l ND l 5.29E-42 l 3.55E-42 { 8.58E-57 l j La-140 l 1.58E+04 l 7.98E+03 l 2.11E+03 l ND l ND l ND l 5.86E+08 l l La-142 l 2.03E 04 i . 9.21E-05 l 2.29E-05 l ND l ND l ND l 6.72E-01 l l Cc-141 l 1.97E445 l 1.33E+05 l 1.51E+04 l ND l 6.19E404 l ND l 5.10E+08 l lCc-143 l 9.98E+02 l 7.38E+05 l 8.17E+01 l ND l 3.25E+02 l ND l 2.76E+07 l l Cc 144 l 3.29E+07 l 1.38E+07 l 1.77E+06 l ND l ~_8.16E+06 l ND l 1.11E+10 l !
l Pr-143 l 6.26E+04 l 2.51E404 l 3.10E+03 l ND l 1.45E+04 l ND l 2.74E+08 l ! l Pr-144 l 2.03E+03 l 8.43EM2 l 1.03E+02 l ND l 4.75E+02 l ND l 2.92E-04 l l Nd-147 l 3.33E+04 l 3.85E+04 l 2.31E+03 l ND l 2.25E+04 l ND l 1.85E+08 l l Eu-154 l 4.85E+07 l 5.97E+06 l 4.25E+06 l ND l 2.86E+07 l ND l 4.32E+09 l 1 l Hf-181 l 1.40E+05 l 6.82E+05 l 6.32E+04 l ND l 1.47E+05 i ND l 7.76E+08 l l W-157 l 3.80E+041 3.18E+04 l 1.11E+04 l ND l ND l ND l 1.04E+07 l l Np-239 l 1.43E+03 l 1.41EM2 l 7.76E+01 l ND l 4.39E+02 l ND l 2.89E+07 l i 14580329 47361396
5 APA-ZZ-01003 Rev. 4 4.0 DOSE AND ROSE COMMTTMENT FROM URANIUM FUEL CYCLE SOURCES 4.1 CALCULATION OF DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES The annual dose or dose commitment to a MEMBER OF THE PUBLIC for Uranium Fuel Cycle Sources is determined as:
- a. Dose to the total body and internal organs due to gamma ray exposure from submersion in a cloud of radioactive noble gases, ground plane exposure, and direct radiation from the Unit and outside storage tanks;
- b. Dose to skin due to beta radiation from submersion in a cloud of radioactive noble gases, ,
and ground plane exposure; &
- c. Thyroid dose due to inhalation and ingestion of radioiodines; and
- d. Organ dose due to inhalation and ingestion of radioactive material.
It is assumed that total body dose from sources of gamma radiation irradiates internal body organs at the same numerical rate. (Ref.11.12.5) The dose from gaseous efDuents is considered to be the summation of the cose at the individual's residence and the dose to the individual from activities within the SITE BOUNDARY. Since the doses via liquid releases are very conservatively evaluated, there is reasonable assurance that no real individual will receive a sigmficant dose from radioactive liquid release pathways. Therefore, only doses to individuals via airborne pathways and doses resulting from direct radiation are considered in determining compliance to 40 CFR 190 (Ref. I1.12.3). There are no other Uranium Fuel Cycle Sources within Skm of the Callaway Plant. 4.1.1 Identification of the MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC is considered to be a real individual. including all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site for recreational or other purposes not associated with the plant (Ref.11.4 and 11.8.10). Accordingly, it is necessary to characterize this individual with respect to his utilization of areas - both within and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions which could be reevaluated if necessary to demonstrate continued compliance with 40 CFR 190 through the use of more realistic assumptions (Ref.11.12.3 and 11.12.4). The evaluation of Total Dose from the Uranium Fuel Cycle should consider the dose to two Critical Receptors; a) The Nearest Resident, and b) The Critical Receptor within the SITE BOUNDARY. 4.1.2 Tvtal Dose to the Nearest Resident The dose to the Nearest Resident is due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestion 14b. 3.J 4 h_. APA-ZZ-01003 Rev. 4 It is assumed that direct radiation dose from operation of the Unit and outside storage tanks, and dose from gaseous efIluents due to activities within the SITE BOUNDARY, is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is calculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q. The location of the Nearest Resident in each meteorological sector is determined from the Annual Land Use Census conducted in accordance with the Requirements of REC 9.12.1.1. 4.1.3 Total Dose to the Critical Receotor Within the SITE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri , , Depanment of Conservation for management of the residual lands surrounding the Callaway ! Plant, including some areas within the SITE BOUNDARY. Under the terms of this agreement, certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, ; sightseeing, etc.) but recreational use is excluded in an area immediately surrounding the plant site (refer to Figure 4.1). Much of the residual lands within the SITE BOUNDARY are ! cased to l area farmers by the Department of Conservation to provide income to suppon management and l development costs. Activities conducted under these leases are primarily comprised of farming l (ammal feed), grazing, and forestry (Ref. I1.7.2,11.7.3,11.13, and 11.13.1). Based on the utilization of areas within the SITE BOUNDARY, it is reascnable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities ; within the SITE BOUNDARY is due to exposure incurred while conducting his farming activities. The current tenant has esumated that he spends approximately 1100 hours per year working in this area (Ref 11.5.5). Wey of areas within the SITE BOUND ARY is assumed to be averaged over a period of one year. Any reevaluation of assumptions should include a reevaluation of the occupancy period at the locations of real exposure (e.g. a real individual would not simultaneously exist at each point of maximum exposure). 4.1.3.1 Total Dose to the Farmer from Gaseous Efiluents The Total Dose to the farmer from gaseous efIluents is calculated for the adult age group using the methodology discussed in Section 3, utilizing concurrent meteorological data at the farmer's residence and historical meteorological data from Table 6.1 for actisities within the SITE BOUNDARY. These dispersion parameters were calculated by assuming that the farmer's time is equally distributed over the areas farmed within the SITE BOUNDARY, and already have the total occupancy of 1100 hours / year factored into their value (Ref. I1.5.6). The residence of the current tenant is located at a distance of 3830 meters in the SE sector. No meat or milk animals or vegetable gardens were identified by the latest Land Use Census for this location, therefore, the gaseous efIluents dose at the farmer's residence is due to plume exposure from Noble Gases and the ground plane and inhalation pathways. For conservatism, it is j acceptable to assume that the ingestion pathways exist at this location. It is assumed that food ingestion pathways do not exist within the SITE BOUNDARY, therefore the gaseous effluents dose within the SITE BOUNDARY is due to plume exposure from Noble Gases and the ground plane and inhalation pathways. 14380329 47361398 APA-ZZ-01003 Rev. 4 4.1.3.1.1 Direct Radiation Dose from Outside Storace Tanks The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radioactive materials, and constitutes the only potentially significant source of direct radiation dose from outside storage tanks to a MEMBER OF THE PUBLIC (Ref. I1.6.14, 11.6.15,11.6.16 and 11.6.17). Direct radiation dose from the RWST to a MEMBER OF THE PUBLIC is determined at the nearest point of the Owner Controlled Area fence which is not obscured by significant plant structures, which is 450 meters from the RWST. The RWST is a right circular cylinder approximately 12 meters in diameter,14 meters in height with a capacity of approximately 1,514,000 liters (Ref.11.6.17). The walls are of type 304 stainless steel and have an average thickness of.87 cm. (Ref. I1.14.1). The direct radiation dose from the RWST is calculated based on the tank's average isotopic content and the parameters discussed above, considering buildup and attenuation within the volume source. Appropriate methodology for calculating the dose rate from a volume source is given in TID-7004, " Reactor Shielding Design Manual" (Ref.11.17). The computer program ISOSHLD (Ref. 11.18,11.19 and 11.20) will normally be utilized to perform this calculation. 4.1.3.1.2 Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC has been determined to be 7E 2 mrads/ calendar year, based on a point source of primary coolant N-16 in the steam generators. This source term was then projected onto the inside surface of the containment dome, taking credit for shielding provided by the containment dome and for distance attenuation. No credit was allowed for shielding by other structures or components within the Containment Building. The number of gammas per second was generated and then converted to a dose rate at the given distance by use of ANSI /ANS-6.6.1, " Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plant 1979", which considers attenuation and buildup in air. The final value is based on one unit operating at 100% Power. The distance was determined to be 367 meters, which is approximately the closest point of the boundary of the Owner Controlled Area fence which is not obscured by significant plant structures (Ref. I1.14.3). The maximum direct radiation dose from the Unit to the farmer is thus approximately 9E 3 mrads per year, assuming a maximum occupancy of 1100 hours per year. I 1 l l 145SO3'29 4 7 3:5.1 3 9 9 l
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APA-ZZ-01003 Rev. 4 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING i 5.1 ' DESCRIlrTION OF THE RADIOLOGICAL ENVIRONMENTAL MONITORINO PROGRAM The Radiological Environmental Monitoring Program is intended to act as a background data l base for preoperation and to supplement the radiological efHuent release monitoring program , during plant operation. Radiation exposure to the public from the various specific pathways and : direct radiation can be adequately evaluated by this program. l Some deviations from the sampling frequency may be necessary due to seasonal unavailability, , hazardous conditions, or other legitimate reasons. Efforts are made to obtain all required samples ; within the required time frame. Any deviation (s) in sampling frequency or location is documented in the Annual Radiological Environmental Operating Report. . t The Environmental samples are collected and analyzed at the frequency shown in Table 5.1. - Sampling, reporting, and analytical requirements are given in Tables 9.11-A, 9.11-B, and .
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Airborne, waterborne, and ingestion samples collected under the monitoring program are i analyzed by an independent, third-party laboratory. This laberatory is required to participate in l the Environmental Protection Agency's (EPA) Environmental i'adioactivity Laboratory ; Intercomparison Studies (Crosscheck) Program or an equivalent program. Participation includes l all of the determinations (sample medium - radionuclide combination) that are offered by the l EPA and that are also included in the monitoring program. > l 5.2 PERFORMANCE TFJf]NG OF ENVIRONMENTAL THERMOLUMINESCENCE ! DOSIMETEFS c Thermoluminescence Detectors (TLD's) used in the Environmental Monitoring Program are ! tested for accuracy and precision to demonstrate compliance with Regulatory Guide 4.13 (Ref. ! 11.16). l Energy dependence is tested at several energies between 30 kev and 3McV corresponding to the ; approximate energies of the predominant Noble Gases (80,160,200 kev), Cs-137 (662 kev), , Co-60 (1225 kev), and at least one energy less than 80 kev. Other testing is performed relative i to either Cs-137 or Co-60. (Ref.11.14.10) i i i 14580329 47361401 l i 1
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\
% [ / ~_
l
~
!/ r s s
i it T l<\[ - b/ /f p 1.' 4580329 473s.140E.
APA-ZZ-01003 Rev,4 H TABLE 5.1 O (Jl RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM C0 0
- 1. - Drect Radistica 40 routine mentoring stations either with two or more dosimeters or with one instrumed for measuring and recordssg dose rate continuously, coesisting of an fij irmer reg of sixteen stations, one in each meteorological sector in the general area of the SITE BOUNDARY.
l[I Station g C_ oste Sector 3. Lie Deseptron Location
~)
04 A 0.3 miles east ofIIwy O and CC Jenction, Callaway Elearie Coop. thihty Pole 1.91 mi @ 349' N () Na 18892 hl 47 B Courey Road 448,0.9 miles south ofIIwy O Callawny Eledric Coop. thility Pole 0.9 mi. @ 17 NNE ga Na 28151 b da C County road 448,1.5 miles south ofilwy O, Plant Securay Are Sygn Post 0.4 rri @ 45' NE l) 05 D Pnmary MceW Tower
.q 13 mi @ 7t* ENE 49 E County road 448, Callaway Eledric Coop Utihty Pole No. 06959. Reform I.7 mi. @ 9t* E Wildhfe Management Parking Area 52 F ligN pole near East Plant Securny Fence 0.4 mi. @ II4* ESE 5I G Imcated in the "Y" of the abandoned railroad spur northwest of sludge lagoon 0.7 mi- @ 137' SE 50 11 County road 439,3.3 miles north ofifwy. 94, Callawny Electne Conp. tblity Pole 0.9 mi.@-163* SSE Na 35086 07 J County road 439,2.6 nules north ofIfwy. 94, Callaway Electric Coop. L'tilwy Pole 13 mi. @ l8l' S Na 35097 37 K County road 459,0 9 trules sonah of11wy CC, Callaway Electric Coop. Utildy 0.7 mi. @ 202* SSW Pole No. 35077 43 L Couray road 459,0 7 nules sough ofIfwy CC, Callaway Electnc Coop. thihty 0.5 mi. @ 230* SW Pole No. 35073 d4 M liighway CC, t 0 miles south of county road 459 Callaway Electric Coop. thility 1.7 rni. @ 257 WSW Pole No I8769
_ ._- , ,, _ . _ . . . - ~ . . . ._.- - . _ . _ . . , _ . . _ _ ...___
APA-ZZ-01003 Rev,4 TABLE 5.1 (Cont'd)
- H h RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I.S l'il
( Sector $13 Descretion IJsajagg y 06 N County road 428,1.2 miles west of Hwy CC, Callaway Dectric Coop. Bildy Pole th I. No I8609 2.0 mi. @ 277* W 43 P Couray road 428,0.1 miles west ofIlwy CC, Callaway Elcctric Coop. Utility Pole I.0 mi. @ 290* WNW No. I3580 h 03 q* Q 01 nules west ofIlwy CC on gravel road 0.8 miles south ofIlwy O. Callaway 1.3 mi. @ 30d* NW Deanc Coop uility Pole Na I8559 k'.1 g 46 R North <ast side ofilwy CC and Couray Road 446 Interseoion Callaway Electne Coop. Utilny Pole No. 25242 1.5 mi @ 333' NNW W p An outer ring ofsixteen stations, one in each meteorological sectw in the 6 to 8 km range from the site. b 36 A County Road 155,0.8 nules south of Couray Road 132, Callaway Electric Coop. 5.2 mi. @ 7'N j
@ Miley Pole No.19137 2i B Coway Road I 55,1.9 miles north ofIlwy O, Callaway Dectric Coop. Mility Pole 4.0 rni. @ 23* NNE No.19100 20 C Ilighway D,0 4 nules north ofitwy K.Callaway Electric Cocp. Bildy role No. 4.s mi @ 47'NE I2830 18 D liighway D,0.4 neles south of11wy O, Callaway Decedc Coop. Mility Pole No. 3.8 mi. @ 63* ENE I2952 17 E County Road 4053,0.3 miles east ofIlwy D, Kingdom Telephone Company Pole 4.0 mi @ 89* E No. 3 x 12 34 F South-eam side ofIlwy 94 and liwy D innersection Callaway Dectric Coop. Utility 5.0 mi. @ 121' ESE Pole No. I1940 1I O City of Portland, Callaway Dearie Coop. Giley Pole No.12112 4.8 mi. @ 139' SE 10 J liighway 94,1.8 miles east of County Road 459 Callaway Electric Coop. Utiley
' 4.0 me. @ 157* SSE Pole No. I2182
m APA-ZZ-01003 Rev.4 ' TABLE 5.1 (Cont'd) t" fa RADIOLOGICAL ENVIRONMENTAL MONTTORING PROGRAM O (0 - 0 ,,,i,, S I,sI M h & Descrweien Locaticri p* 09 J North-west ade Ifwy 94 and Couray Road 459 Juncsson, Cattawny Elearic Coop. 3.7 ni @ 183* S h thisty Pole No. 06754 30 K West side of Caussy Road 447 at the Junaion with Coursy Road 463 Kingdorn 4 6 ni @ 208* SSW
-{,8 Telephone Company Pole No. 2KI
'Nj 42 L Courty Road 447,2.6 nules north of Coursy Road 463, Caltaway Electnc Coop.
q. v Utilssy Pole No. 06326 4 4 mi @ 233* SW
@ 32 M liighway VV,0.6 miles west ofCourey Road 447, Callaway Eleane Coop. (Niay g 5 4 mi. @ 251* WSW Pole No. 27031 h
41 N Ilighway AD,2.5 miles east of Hwy C, Canaway Electric Coop. LAildy Pole No. O 18239 4 8 mi. @ 279* W 40 P Northeast mde of Courvy Road i12 and 11wy O Junctiert Callaway Electric Coop. 4 2 ini. @ 294* WNW 1Ailrty Pole No. 06326 39 Q Courny Road 112,0.7 miles cast of Courry Road l i t Callaway Electne Coop. 5 4 mi. @ 3I5* NW (Miity Pole No.17516 38 R Courey Road I33,1.5 miles south ofIlwy UU Callaway Electric Coop. tAility 4.8 mi. @ 337' NNW Pole No. 34708 Eight Stations to be placed in special interest areas such as population cenders, nearby ressdences, schools, and in I er 2 areas to serve as casarei statiora 33 N Csty ofllams Prmine, south east of the Hwy C and liwy AD Junction 7.4 mi @ 273* W 31 L City of Mokane, Callaway Electric Coop. IAility Pole No. 06039 7.4 mi. @ 21t* SW 26 E Town of Amencus, CaHaway Electric Coop. thility Pole No. Il 159 12.1 mi. @ 82* E
-6 8-
APA-ZZ-01003 Rev.4 H TABLE 5.1 (Cont'd) di y RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (0 0 b- Station h) M sector site Descnotion Location 27 F Town of Blum Callaway Electric
- 9. Utility Pole No. II496 9.6 mi. @ l10* ESE g 35 R City ofToledo, Callaway Electric Coop. Utility Pole No.17684 5.8 mi. @ 342' NNW
** )
23 B City of Yucatan, Callaway Electric Coop. Utilny Pole No.12670 6.3 mi. @ 16' NNE W lI O City of Portland Callaway Electric Conp. Utildy Pole No.12112 4.3 mi @ 139* SE H 20 C City of Readsville, Callaway Electric Coop. Utility Pole No.12830 4.8 rni. @ 47' NE A 34 P North east side oflIwy C and County Road 408 Junction 9.7 eni. @ 293* WNW N (P<ontrol) 0 01 Q liighway Z 0.8 miles east of Dummens 54, Catlaway Electric Coop. Utility Pole 11.0 mi. @ 312* NW (Q Contrei) No. 21544
- 2. Aarborne RadWine and Particulates Three samples frorn close to the tivee SITE DOUNDARY locatums,in duTerere sectors, of the average highest calculated annual average ground level D/Q.
Station CM h Eg Description Locat'on a AI D Primary Mescorological Tower 1.3 mi. @ 78* ENE A8 B County Road 448,1.0 nules south of Hwy 0 0.8 mi. @ 24' NNE B3 A 0.3 miles east ofIlwy O and liwy CC Jurstion 1.9 mi. @ 349' N
m APA-ZZ-01003 - Rev.4. ' l c TABLE 5.1 (Cont'd) H dk RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - UI 0)
, O j One san @ freen the cremsnmuty with the highest DQ
(\\ Station g Geis sisi.a sewi t-to. A9 R Conunumty of Refonn 1.7 ini. @ 338' NNW di
**) One sample Eroen a controllocasson, ma for exasnple 15-30 km h and in ene least prevalent wini dwecesan.
I (e,I '
@ Station Ce!l t - ifCBE Eing Descristsee im H
A7 Q Bartley fas=n 9.5 ni @ 312* NW H
- 3. g Waterborne 1
- a. Swface One sample upstrearn Station Co!!E SeEt.E - Si!!Desensteen Location 50i H s4 feet upserearn of discharge, nonk bank 4.8 mi. @ l 44* SE One sample upsiscam Suison Cesig Sector St Descristion Location So2 o I.I miles downnream .f ducharge. nonk bank 5.2 mi. @ 133' SE P
i
+
.__ _ _ _.-_ . _ . - _ _ . _ _ _ . _ ~ . _ . _ . . _ _ _ _ . . . _ _ - _ . ,
--__..~.-~._,_.._._-..u..-_-_-.__.._-_.___._...,.,._,--_,.-__..._ -.__.u__. _ _ _ _ _ _ . , _
7
.APA-ZZ 01003 s
+
- Rev.4-m TABLE 5.1 (Cant *d)
H M RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
\A 0)
"'"d' ** *""'"""PP I 'es within 10 meiles downsereans that could be afected by its dacharge,to a snanimum of theee senylan, and one mangle Desa a .
O * """' , (e,I gj As there are no dnnlung water intakes within 10 miles downstressa ofthe discharge point, the dnnlung water pathway in curressly not incleaded as part af the CaNeway Ptere Radiolopcal Environmental Monitoring Program. Should funne water intakes be construssed wishin 10 river nailes downstream of the W poine,then the proyam will h be revised to include this paahway (Ref I1.6.6).
- c. Seduneet One sa.nple frern dowmarcam area with existing or potestsal reweational value.
*.j Station C_.od_e Sector SitgDesenstaan Location
@ .C O l.3 river mile downseream ofdracharge, marth bank 3.2 mL @ 135* SE H
M
- 4. P Ingestion L)
[el* a. Milk Sarnples from miudng animals in three ddlerent J -
- secsers wishin a 5 km distance havis.g the higlisse dose pesantial. If there are mane,then ene sample frosa miudng animals in each of three difIerent snescorolopcal sectors between 5 to 8 kar desane where doses are calculated to be yester than I snrera par par.
Due to a lack of milk animals winch satisfy these . , . the snitt pathway is carrently not inchuled as a part of the Callaway Piers Radialopcal E.... i Monitoring Program. Should the Arunsel Land Use Census identify the existence ofusiiking ananals in locations which satisfy these respearenieres, then the propam wiR be revised to include this pathway.
- b. Fish One sample ofeach commercially and recreationally important species in vicinity ofplant discharge area.
, Station Q2de Sector Eie.g Descreceson location - C O l.5 river nule downstream of discharge, north bank 3.2 mi. @ 135' SE i 4
-71 =
- n. - o.,.w.r - , -. . - - < . ww-...--.'v-t -
e nn . e 4 t t er. , w .r -mr. * - - n --w ec-+-.-rm- . - - w w. w = w -- . t. s e m ww -w e wr%v ,w-=r .W..-- - . .ww .- *.rm .....n- -... m.-.- -. sem+--*-n-- s-- .....,e~e.er.-e,en. .n-w---...,-_o .r-,,
~
- APA-ZZ-01003 Rev. 4 TABLE 5.1 (Cont'd)
H
.h RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ,
Ut (0
. One aangde of sarne species in areas not Wluenced by plant escharge
- U hj Simian E9!it EE!21 E.!f i W I' cation -4 II.I .
de A H 0.6 river miles upstream ofdischarge. north bank 4.9 mi @ l$4' SSE t h gj ,
- c. Food One sarnple of each pnnnpal class of products froen any area that is irrigased by weser na which liquid plant wasses have been encharged Products h.I g As there are no areas irrigated by water in which liquid plant wastes have been encharged within 50 river miles downseream of the discharge point, this sample type is not currently included as part of the Callaway Plast Radiological Envuonmerwal Mamiannf, Proerans. Should future irrigation waner intakes be constructed within to river snilen H downstream of the discharge point, then the program will be revised to inchade this sempic type (Ref. I1.7.4 and i1.7.3).
p . . . Samples of tivee ddlerent kinds of broad learvegetation grown nearest each of two ddferers offsiae locations ofhighest predicted annual average ground-level DQ (if anIk M sampling is not performed). l'.I Staban Cg!k Sector 3jeg Desmssion 8ccanon , V6 R Beder's farm 1.3 rni. @ 344' NNW V7 A Meehan's farm 1.3 ni@ 356' N One sample of each ofsinular broad len(vegetation syown 15 to 30 km distant in the least r ..act wind f,+ctee Q . ?> s%*b W performedk Station CM Sector Es Descnesson '.m:stion V3 1. Beazley% farm 15.0 mi. @ 227* SW E _ . , . _ ,. _ _ _ . , . _ , . _ - _ _ - . , _ . . . . - - _ , . . , _ _ . , . , - . - - . _ . _ . . _ . _ _ - . _ , ~ . - . . - - . _ - _ , , _ _ _ . . ._. _ _-_._ _ _ . . . _ _ _ . . _ _ _ _ _ _ _ _ _
r APA-ZZ-01003 Rev.4 i 6.0 DETERMINATION OF ANNUAL AVERAGE AND SHORTTERM ATMOSPHERIC DISPERSION PARAMETERS 6.1 ATMOSPHERIC DISPERSION PARAMETERS ; The values presented in Table 6.1 and Tabic 6.2 were determined t!viough the analysis of on-site meteorological data collected during the three year period of May %,1973 to May 5,1975 and March 16,1978 to March 16,1979. 6.1.1 Long-Term Dispersion Estimates He variable trajectory plume segment atmospheric transport model MESODIF-II (NUREG/-CR-0523) and the straight-line Gaussian dispersion model XOQDOQ (NUREG/CR2919) were used for determination of the long-term atmospheric dispersion parameters. A more detailed discussion of the methodology and data utilized to calculate these parameters can be found elsewhere (Ref. I1.6.12). The Unit Vent and Radwaste BuinEng Vent releases are at elevations of 66.5 meters and 20 meters above grade, respectively. Both release points are within the building wake of the stmetures on which they are located, and the unit Vent is equipped with a rain cover which effectively climinates the possibility of the exit velocity exceeding five times the horizontal wind speed. All gaseous releases are thus considered to be ground-level releases, and therefore no mixed mode or elevated release dispersion parameters were determined (Ref.11.5.2). 6.1.2 Determination of Lone-Term Dispersion Estimates for Soecial Receptor Locations Calculations utilizing the PUFF model were performed for 22 standard distances to obtain the desired dispersion parameters. Dispersion parameters at the SITE BOUNDARY and at special receptor locations were estimated by logarithmic interpolation according to (Ref. I1.6.13): X = X, (d / d i )" (6.1) Where: B m in (X2 / X,)/1n (d2/ di )- Xg, X2 = Atmospheric dispersion parameters at distance id and d2 , respectively, from the source. The distances di and d 2were selected such that they satisfy the relationship. d<d<d i 2 h 14580329 47361414 " i i i
APA ZZ-01003 Rev.4 6.1.3 Short Term Disnersion Estimalg Airborne releases are classified as short term if they are less than or equal to 500 hours during a calendar year and not more than 150 hours in any quarter. Short term dispersion estimates are determined by multiplying the appropriate long term dispersion estimate by a correction factor (Ref.11.9.1 and 11.15.1): F = (T, / T,)* (6.2) Where: Tg = The total number of hours of the short term release. T=a The total number of hours in the data collection period from which the long term diffusion estimate was determined (Refer to Section 6.1). Values of the slope factor (S), are presented in Table 6.3. Short term dispersion estimates are not applicable to short term releases which are sufliciently random ia both time of day and duration (e.g., the short term release periods are not dependent solely on atmospheric conditions or time of day) to be represented by the annual average , dispersion conditions (Ref. I1.8.1). l 6.1.3.1 The Determination of the Slooe Factor (S) The general approach employed by subroutine PURGE of XOQDOQ (Ref,11.15.1) was utilized to produce values of the slope of the (X/Q) curves for both the Radwaste Building Vent and the Unit Vent. However, instead of using approximation procedures to produce the 15 percentile l (X/Q) values, the 15 percentile (X/Q) value for each release and at each location was determined by ranking all the 1 hour ((X/Q);) values for that release and at that location in descending order. The (X/Q)g value which corresponded to the 15 percentile of all the calculated (X/Q) values within a sector was extracted for use in the intermittent release (X/Q) calculation. The intermittent release (X/Q) curve was constructed using the calculated 15 percentile (X/Q)] and its corresponding annual average (X/Q)a. A graphic representation of how the computational procedure works is illustrated by Figure 4.8 of reference 11.15.1. The straight line connecting these points represents (X/Q); values for intennittent releases, ranging in duration from one hour to 8760 hours. The slope (S) of the curve is expressed as:
-log ((X / Q), /(X /Q),)
S= (6.3) log (T, / T,) or
-(log (X / Q), - log (X / Q),)
S= (6.4) log T, - log Ti 14580329 47361415 _ . _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ ~
APA-ZZ-01003 Rev.4 6.1.4 Atmospheric Dispersion Parameters for Farmine Areas within the SITE BOUNDARY The dispersion parameters for farming areas within the SITE BOUNDARY are intended for a narrow scope application: That of calculating the dose to the current farmer from gaseous efnuents while he conducts farming activities within the SITE BOUNDARY. For the purpose of these calculations, it was assumed that all of the farmer's time, approximately 1100 hours per year, is spent on croplands within the SITE BOUNDARY, and that his time is divided evenly over all of the croplands. Fracti.ase screage/ time - weighted dispersion parameters were calculated for each plot as dese 3ec in reference 11.5.6. The weighted dispersion parameters for each plot were then su reed (according to type) in order to produce a composite value of the dispersion parameters which are presented in Tables 6.1 and 6.2. These dispersion parameters therefore represent the distributed activities of the farmer within the SITE BOUNDARY and his estimated occupancy period. 6.2 ANNUAL METEOROLOGICAL DATA PROCESSING The annual atmospheric dispersion parameters utilized in the calculation of doses for demonstration of compliance with the numerical dose objectives of 10 CFR 50, Appendix I, are determined using computer codes and models consistent with XOQDOQ (Ref. I1.15). These codes have been validated and verified by a qualified meteorologist prior to implementation. Multiple sensors are utilized to ensure 90% valid data recovery for the wind speed, wind direction, and ambient air temperature parameters as required by Regulatory Guide 1.23. The selection hierarchy is presented in Table 6.5. 1 s 14580339 47361416
APA-ZZ-01003 Rev.4 TABLE 6.1 H
.h HIGHEST ANNUAL AVERAGE ATMOSPIERIC DISPERSION PARAMETERS (a)
I.b C0 W VENT O lti DISTANCE XQ XQ ' (\'l wCATION(b) SECTOR (METERS) X/Q DECAYEDr DECAYED / DQ g [LQdB0 !:&IQmext: Rw3EI55firfigy'GWUITTT&!.TMERICENiwKPWMpf?JfMMIM*TN@MhnNsHREQQDN UNDEPLETED DEPLETED U1mi.Upm 3 (sechn ) (sec/m') (sec/m ) (mk I8 SITE BOUNDARY NNW 2200 I.0E-6 9.9L7 S.5L7 43L9 - Nemes Cow (c) WSW 2172 4.4L7 4.4L7 3.857 1.6E-9 h1
@ Nearest Oon:(c) WSW 2172 4.4L7 4.4L7 3.8L7 1.6E-9 H
,, Nearest Meat Animal (d) NNW 2864 6807 6.8E-7 5.707 2.6L9 H Nearest Vegetable (c) NNW 2864 6.3L7 6.8L7 5.7L7 2.6E-9 q Garden Nearest Residence (c) NNW 2864 6.3L7 6.tE 7 5.7L7 2.6E-9 Farming Areas withinthe N/A N/A 2.1L7 2.1E-7 1.9E-7 1.169 Site Boundary (c)(e)
(a) Values given are from FSAR Table 2 3-82 (b) Data from 1992 Land Use Census (c) Values dmved from FSAR Table 2.3-83, using the methodology presented in Equation (6.1)(Ref i1.5.6) (d) The nearest meat animal is assumed to exist at the location of the nearest resident (e) These values were derived for a narrow scope application. Extreme caution should be exercised wien deternuning their suitability for use in other applications. Building Shape Parameter (C) = 0.5 (Ref. I1.53) Verticallleight ofliighest Adjacent Buildmg(V) = 66 45 meters (Ref. II.53)
- _ , , _ - - .- _ - - . . . w . - , - - -
.- , . _ -- ,_ _ _m. _ __ ._
APA-ZZ-Ol003 i a
~ Rev.41- ,
- TABLE 6.2 = ,
p HIGHEST ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS (al 5 RADWASTE BUILDING VENT g , M DISTANCE w w. O LOCATION (b) SECTOR (METERS) X/Q DECAYED / UNDEPLETED DECAYEDr. DEPLETED
..DQ f.1 Um gaac,c ;zmnTT!hwr;4?KRtMYEMssnmM&mmmmmmyh.: ~ ~
\ (sedm#) (sec/m') (sec/m*) (m*)
~
' NNW 2200 .13E4 13E4 LIE 4 43L9 I SITE BOUNDARY p Nearest Cow (c) WSW 2172 5.7L7 5.7L7 ' 4.967 :1.669-N Nearest Goat (c) WSW 2172 5.7E-7 5.7L7 4.967 1.6L9 (d MNW 2864 8.7L7 5.7E.7 7.2E-7 2.6E-9 Nearen Mears Animal (d) H Newest Vegetable Garden (c) NNW 2864 8.7L7 8.7E-7 7.2E-7 2.6L9 j , 8 2.6E-9 Nearest Residence (c) NNW 2864 5.767 8.7E-7 7.2E-7 H Farming Areas Within N/A N/A 2.9E-7 2.9E-7 2.6E-7 1.1E-9 [, Site Boundary (c)(e) (a) Values given are from FSAR Table 23 84 (b) Data from 1992 Land Use Census 1 (c) Values derived from FSAR Table 23 8I, using the methodology preserned in Equation (6. I)(Ret I 1.5.6) . (d) The nearest meat anwnal is assumed to exist at the location ofshe nearest resident. (e) These values were derived for a narrow scope apphcation. Extreme caution should be exercised when d. .. ___- .their suitabildy for use in other applications. Buildeg Shape Parameter (C) = 0.5 (Ref 11.53) i Vertical Height of11ishest Adjacent Building (V)- 19.96 meters (Ret I 1.53) 4 J _ _ _ _ _ _ . . _ _ ._.__-..._..__~.._-_.:_-.-..-- -
. . ~ . -- -._ .--._._ ._._._-_.;_.-.__u...--__2..-. -
....c._._......_.___2___.-
- . , s~ - _ .
I g _ APA-ZZ-01003 j A' Rev.4 , TABLE 6.3 - ! SHORT TERM DISPERSION PARAMETERS (a) (c) Slope Factor (s) l Location (b). Sector Distance ' Unit Vent Radwaste i
. :g Building Vent l r
Site Boundary S 1300 .32% . 320' ; e Nearest Cow NW 5053 .263 .266 I Nearest Goat NW 5053 . 263 .266 - NearestMeat Animal NNW 2736 .262 .268 i I Nearest Vegetable Garden NNW 2865 .264 .268.
- Nearest Residence NNW 2865 .264 .268 f
f (a) Reference 11.5.3 ;
-(b)' Data from 1992 Land Use Census (c) Recirculation Factor = 1.0 !
r J I i i
'I i
l'4580329 47361419 1 _I
' APA-ZZ 01003 -
Rev.4: TABLE 6.4 H APPLICATION OF ATMOSPHERIC DISPERSION PARANETERS dh I0
~ .
(0 0 (,j DOSE PATHWAY DISPERSION PARAMETER CONTROLLING AGE GROUP CONTROLLING l.OCATION N Noble Gas, Beta Air x/Q, decayed /undepleted Site Boundary. g (2.26 day halflife) dhNoble Gas, Gamrna Air x/Q, decayed /undepleted - Site Boundary
%} (2.26 day halflife) '
(0
@ Noble Gas, Total Body x/Q, decayed /undepleted -
Site Boundary H . (2.26 day halflife) kh y Noble Gas Skin x/Q, decayed /undepleted - Site Boundary _ (2.26 day halflife) 0 Ground Plane Deposition D/Q - Nearest Resident 3 Inhalation x/Q, decayed / depleted Child Nearest Resident (8 day halflife) Vegetation D/Q* Child Nearest Resident
~
Milk D/Q* Child Nearest Resident
. Meat D/Q* Child Nearest Resident i
- For 11-3 and C-14, x/Q,' decayed / depleted is used instead of D/Q (Ref. I1.I1.1).
._ _ . _ . __ _ . . , - . - _ - _.__---...n . . . _ _ _ _ , . - .-.._ u ._-._ _ _ _ _ .-... .. ... _ _. .-,~ ..._ .. . . . - _ .
jf.n. APA-ZZ-01003 .' . Rev.4-
- TABLE 6.5 h,
METEOROLOGICAL DATA SELECTION HIEARCHY ?l l: b ' Parameter
. Primary First Second Third F Alternate Ahernate . Alternate Wind Speed 10m Pri 10m Sec 60m Pri 90m Pri 1~
L Wind Direction 10m Pri 10m Sec 60m Pri 90m Pri t-Air Temperature 10m Pri 10m Sec Wind Variability 10m Pri 10m Sec 60m Pri 90m Pri Temp Difference 60-10m Pri 90-10m Pri 90-60m Pri Dew Point 10m Pri Precipitaiton im Pri
-(a) Priindicates primary tower (b) Sec indicates secondary tower ,
14580329'47361421 i 1 I
APA-ZZ-01003 Rev.4 7.0 REPORTING REOUIREMENTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (CTS #2804) i Routine Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The Annual Radiological Environmental Operating Repon shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls and with previous environmental surveillance repons, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by REC 9.12. The Annual Radiological Environmental Operating Repon shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event . , that some individual resu!!c are not available for inclusion with the report, the repon shall be ; submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary desenption of the radiological . environmental monitoring program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action being !
taken if the specified program is not being performed as required by REC 9.13.1; reasons for not conducting the Radiological Environmental Monitoring Program as required by REC 9.11.1 and discussion of all deviations from the sampling schedule of Table 9.11-A, discussion of i environmental sample measurements that exceed the reponing levels of Table 9.ll-B, but are not , the result of the plant emuents, pursuant to REC 9,11.1; and discussion of all analyses in which the LLD required by Table 9.11-C was not achievable. 7.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (CTS # 2805) Routine Semiannual Radioactive Emuent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The Semiannual Radioactive Emuent Release Report shall include a summary of the quantities of radioactive liquid and gaseous emuents released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reponing Radioactivity in Solid Wastes and Releases Gaseous Emuents from Light Water- Cooled Nuclear Power Plants, " Revision 1, June 1974 with data suntmarized on a quanerly basis following the format of Appendix B thereof. j l l
.i 1
-81 I l
l I
i APA-ZZ-01003 Rev.4 r The Semiannual Radioactive Emuent Release Report to be submitted within 60 days after - January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form ofjoint frequency distribution of wind speed, wind direction, and atmospheric stability * . This same repon shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous emuents released from the unit during the previous calendar year. This same repon shall also include an assessment of the radiation doses fro'n radioactive liquid and gaseous emuents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Technical Specifications, Figures 5.1-3 and 5.14) during the repon period using historical average atmospheric conditions. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous emuents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL ; (ODCM). The Semiannual Radioactive Emuent Release Repon to be submitted within 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most ; exposed ME.MBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary emuent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Pan 190, " Environmental Radiation Protection , Standards for Nuclear Power Operation." Doses to the MEMBER OF THE PUBLIC shall be calculated using the methocology and parameters of the ODCM. The Semiannual Radioactive Emuent Release Repons shall include a list and description of , unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in t gaseous and liqmd emuents made during the reponing period. , The Semiannual Radioactive Emuent Release Reports shall include a summary description of any major changes made during the reponing period to any Liquid or Oaseous Treatment Systems, pursuant to Section 10.1. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to REC 9.12.1. Reponing requirements for changes to Solid Waste Treatment Systems is addressed in APA-ZZ-010ll, PROCESS CONTROL PROGRAM (PCP). The Semiannual Radioactive Emuent Release Reports shall also include the following , information: An explanation as to why the inoperability ofliquid or gaseous emuent monitoring instrumentation was not corrected within the time specified in REC 9.1.1 or REC 9.2.1, and a description of the events leading the liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6.
- In licttsf.spl 3mission Qh thebmmnng gdjoac,tg Emuent Release Repon, Union Electric has the optoYdrEtiirttn$ltfrstnnma'iyot reiitrred"mefcortogical l data on site in a file that shall be provided to the NRC upon request.
em
,. j --
APA-ZZ 01003 ' Rev.4 The Semiannual Radioactive Effluent Release Reports shall also include as a part of or submitted - concurrent with, a complete and legible copy of all revisions of the ODCM that occurred during the reporting period pursuant of Technical Specification 6.14. Solid Waste reporting is addressed in APA-ZZ-010ll, PROCESS CONTROL PROGRAM y (PCPk I I i 1 l l l i 1 l i r I 14580329 47361424 k I 33 l -.
\
APA-ZZ-01003 Rev.4 l 8.0 IMPLEMENTATION OF ODCM METHODOLOGY (CTS #2791) t The ODCM provides the mathematical relationships used to implement the Radioactive Effluent Controls. For routine effluent release and dose assessment, computer codes are utilized to ; implement the ODCM methodologies. These codes are evaluated in accordance with the requirements of HDP-ZZ-04500, " Rad / Chem Computer Systems Conduct of Operations", to ensure that they produce results consistent with the methodologies presented in the ODCM. Procedures which implement the ODCM methodology are contained in the Plant Operating Manual. f I i I l l l l I 14580329 47361425 l
-84
(. APA-ZZ-01003 Rev.4 9.0 RADIOACTIVE EFFLUE?TT CONTROLS (REC) NOTE 1. The terms in this section that appear in capitalized type are defined in Technical Specifications.
- 2. All frequency notations are per Table 1.1 of Technical Specifications.
9.0.1 Compliance with the Controls contained in the succeeding Controls is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACTION requirements shall be met. 9.0.2 Noncompliance with a Control shall exist w hen the requirements of the Control and essociated ACTION requirements are not met within the specified time intervals. If the Control is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
- l I
E4580329 47361426 m__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
APA-ZZ-01003 j Rev.4 l l l 9.1 RAD 10ACT1VE L10UID EFFLUENT MONITORING INSTRUMENTATION l .9.1.1 Controls (CTS # 41834) ! s 9.1.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 9.1-A shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of PIC 9.3.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be deternuned and adjusted in j accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM). ; APPLICABILITY: At all times. ACTION
- a. With a radioactive liquid emuent monitoring instrumentation channel Alann/ Trip Setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid emuents monitored by the affected channel, or declare the .
channel inoperable.
- b. With less than the minimum number of radioactive liquid emuent monitoring I instrumentation channels OPERABLE, take the ACTION shown in Tabic 9.1-A. Restore the inoperable instrumentation to OPERABLE status within the time specified in the !
ACTION, or explain in the next Semiannual Radioactive Emuent Release Report, pursuant to Section 7.2, why this inoperability was not corrected within the time specified. ,
- e. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.1.2 Surveillance Renuirements 2 9.1.2.1 Each radioactive liquid efDuent monitoring instrumentation channel shall be demonstrated OPERABLE by perfonnance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 9.1-B. f i 14580329 47361427
-86
g,
-;m. , -
APA-ZZ-01003 c
- Rev. 4
.u .;
TABLE 9.1-A H l$ RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION m I3
;0)
MIN M M O INSTRUMENT CHANNELS OPERABLE ACTION (,y
- 1. ioactivity Monitors Providing Alarm and Automatic Termination of Release , .
- a. quid Radwaste Discharge Monitor (HB-RE-18) 1 31 b."dteam Generator Blowdown Discharge Monitor (BM-RE-52) 1 '32 fM 01 H
Na
- 2. [il Rate Measurement Devices
- a. Liquid Radwaste Discharge Line (llB-FE-2017) 1 34
~
It Steam Generator Blowdown Discharge Line (BM-FE-0054) 1 34
- c. Combined Cooling Blowdown and Bypass Flow I 34
_...,-.._.-__,..-__-_._a_._...___._...~.-<. ..._:_....--.....--.c,..~._._......u._.- - . - _ . . . _ _ ___ _..--.._ _ __- _ . _ . . .
APA-ZZ-01003 Rev.4 ! TABLE 9.1-A (Cont'd) : ACTION STATEMENTS ACTION 31 - With the number of charmels OPERABLE less than required by the Minimum Channels OPERABLE requirements, emuent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with REC 9.3.2. I, and
- b. At least two technically qualified members of the facility staffindependently verify ,
the release rate calculations and discharge line valving. Otherwise, suspend release of radioactive emuents via this pathway. ! ACTION 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, emuent releases via this pathwap may continue for up to 30 , days provided grab samples are analyzed for principal gamma emitters and 1-131 at a lower limit of detection as specified in Table 9.3-A:
- a. At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 micro-Curie / gram DOSE EQUIVALENT I-131, or
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.
ACTION 33 - (Deleted) ACTION 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, emuent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flow. l i l 14580329 47361429 l i l j l
APA-ZZ-01003 Rev.4 TABLE 9.1-B - H
- f. RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUKENTATION SURVEILLANCE REOUIREhENTS O
m:
- ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL I INSTRUNENT CHECK CIECK CALIBRATION TEST W
- l. Radioactivity Monitors Providing Alarm and Automatic Tfrmination of Release
*- )
a(i, Liquid Radwaste Discharge Monitor (IIB-RE-18) D P R(2) Q(1) b team Generator Blowdown Discharge Monitor D M R(2) Q(1) 4.(BM-RE-52) [0 C
- 2. Flow Rate Measurement Devices
- a. Liquid Radwaste Blowdown Discharge Line (IIB-FE-2017) D(3) N.A. R N.A.
- b. Steam Generator Blowdown Discharge Line (BM-FE-0054) D(3) N.A. R N.A.
- c. Combined Cooling Tower Blowdown and Bypass Flow D(3) N.A. R N.A.
APA-ZZ-01003 Rev.4 TABLE 9.1-B (Cont'd) TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropnate if any of the following conditions exists:
- a. Instntment indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), ;
or ] I
- b. Circuit failure (alarm only), or
- c. Instrument indicates a downscale failure (alarm only), or
- d. Instrument controls not set in operate mode (alarm only).
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards obtained from the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the ' system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by tne same geometry and type of source standard traceable to NIST. (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. 14580329 47361431 o w.1 3,
, n
] !
t n _ APA-ZZ-01CO3 j Rev.4. l
.j 9.2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION - f
..9.2.1 Controls (CTS # 41834) 1 9.2.1.1 The radioactive gaseous emuent monitoring instrumentation channels shown in Table 9.2-A shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of REC 9.6.1.1 :
and Technical SpeciScation 3.11.2.5 are not exceeded
- The Alann/ Trip Setpoints of thesc '!
channels meetmg REC 9.6.1.1 shall be determined and adjusted in accordance with the . l methodology and parameters in the ODCM. APPLICABILITY: As shown in Table 9.2-A. i
-l ACTION: 1
.. a. With a radioactive gaseous emuent monitoring instnunentation channel Alarm / Trip Setpoint ;
less conservative than required by the above speci5 cation, immediately suspend the release .. of radioactive gaseous emuents monitored by the affected channel, or declare the channel ! inoperable. j
- b. With less than the minimum number of radioactive gaseous emuent monitoring l instrumentation channels OPERABLE, take the ACTION shown in Table 9.2-A. Restore i the inoperable instrumentation to OPERABLE status within the time specified in the 'l ACTION, or explain in the next Semiannual Radioactive Emuent Release Report, pursuant i to Technical SpeciScation 6.9.1.7, why this inoperability was not corrected within the time : ,
specified. j c.1 The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable .; 9.2.2 Surveillance Reauirements .! 9.2.2.1 Each radioactive gaseous emuent monitoring instrumentation channel shall be demonstratr,d ) OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in i Table 9.2-B, .j l r i
)
1 1 14580339'47'361432 1 I l
A'. ~ APA-ZZ41003 , ,- Rev.4= TABLE 9.2-A L
" RADIOACTIVE CASEOUS EFFLUENT MQNITORING INSTRUMENTATION Ik
$b *
' MINIMUM CHANNEIE ([I) APPf3 CAB 1111Y ACT10N l a INSTRtHD(T OPERABLE U
- t. M *eraSyneen
- a. owe Ces Actiq Monitor-Pnmdmig Alaren i At au tienes 40,46 '
i IMT.RE.2I)
- b. Jodiew Sannpler . I At mil tienea 43
.(s I At all tunes 43
- c.piculase Sampler I Vest Flow Rate
&.du i At all tinws 43 e Parta:ende and Iodine Sampler Flow Rate Monitor 1 At alltimes 39
- 2. C%inment Purge Syneen e able Ons Actidy Monitor- hovedug Alann and 2 Modes 1. 2,3. 4 .- 41 l
' and during , h'OT-RE-33)hutomatec Termination of Releman (GT.RE-22 Core Ahrsations or movement ofirred Anet in Cisnt 1 +
- b. Indone Sarnpler I Modes I,2,3,4 - 43 and during
' Cor. Ahermicas er, vane.s orirrad i fuelirt Cimt ! c. N6culate Sarnpler. I Modes 1.2. 3. 4 43 ' ' and.hwing Core Ahcrassons er snevement efirvad And in Cimt d Flow Rate N/A N/A N/A , 4
- e. Particulate and ladine Sampler Flow Rate Monitor i Moden I,2,3. 4 39
- and dunns Core Aherseiens or snovemese ofirred ~ .
A.elin Came e 1
- -_.--.. -.-,._. . - . . .-.~..-.--.----,.~.-.-.-,,-..,....-,-.-..;-------,-.-.- - - - - - - - - . - - - _ - - - - - - .
l j j1i l \ ; 1 qli . N 0, O " v I T 4, 3 3 3 C 8 4 4 F 3 0 3 0 A 1 0-Z Z- 4 A v. Pe AR Y T s s s s U e e e e B mm i i i Ati m m A t t
/
t N l l tt ll C a a l a l a N I L s A A A t t A t O I P P T A A T _ N _ E _ M _ U R T S _ N I G 3 1 _ E N I N l R NE dO AL fT HB A CA nI R 1 I i / i o N ME N _ C ( O UP A M MO I -
- N 3 -
2 T I 9-9 N M E E L U B L F A F TE S U O E S A G E V I T C - A O I r D d) o A T n0 a1 tu r R N mE a E rR a M l - e M Ail ta U gG R R in( T s w o S M. a ee l N I
.le f
r TR lp e rf 5 m3 se o inn o S m a o i dn Mt a e e ym r i n e d V in t v lp o g n im t cT r e m a I d n u i A s lp m S a e u a^ a te t e B S a a ta G^- e lu R l u n ic i c ao GOO}g} b h*. hH[kWI i
.,QI h R . . . .
a b c d e. 3 l
APA-ZZ-01003 Rev.4 TABLE 9.2-A (Cont'd) TABLE NOTATIONS ACTION STATEMENTS ACTION 38 - With the number oflow range channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days 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 qualiSed members of the facility staffindependently verify the release rate calculations and discharge valve lineup.
l Otherwise, suspend release of radioactive emuents via this pathway. , ACTION 39 - With the number of channels OPERABLE less than required by the Mimmum Channels OPERABLE requirements, emuent releases via this pathway may continue provided the flow rate is estimated based on fan status and operating curves or actual measurements at least once per 4 hours. l ACTION 40 - With the number oflow range channels OPERABLE less than required by the Muumum Channels OPERABLE requirement, emuent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours and these samples are analyzed for radioactivity within 24 hours. ACTION 41 - MODES 1,2,3, & 4: With the number of channels OPERABLE one less than required by the Muumum Channels OPERABLE requirement, PURGING or venting of radioactive effluents via this pathway may continue for 72 hours. With both channels inoperable, immediately suspend the release of radioactive efDuents via this pathway. I During CORE ALTERATIONS or movement ofinadiated fuel within the containment: With the number of channels OPERABI .' ff's than required by the Minimum Channels OPERABLE requirement,immediately n.e r ad the release of radioactive effluents via this pathway. ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, cfDuent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Tabic 9.6-A. ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements. ACTION 46 - For midrange and high range channels only - with the number of OPERABLE channels less than the minimum channels OPERABLE requirements of Table 9.2-A, take the action specified in Technical Specification 3.3.3.6, ACTION C. 14580329'47361435
APA-ZZ-01003 Rev.4 TABLE 9.2-B 14 h RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIRENENTS g 0) O ANAtoO CllANNEL MODES FOR WHICil hJ CllANNEL SOURCE CllANNEL OPERATIONAL SURVEll1ANCE
'. INSTRUMENT CllECK CIIECK CAI.!DRATION IISI IS REOUIRED
- l. dQ vern systera
- a. Noble Oas Activity Monitor rpovidmg Alane(OT-RE-21) D M RO) Q(2) At all times b9 fbdine Sarryter W NA N.A NA At all tirnes c" aniculate Sampler W NA NA NA At all times it Vent How Rate NA NA R(4) Q At all times
- c. ' articulate and Radiciodine Sampler How Rate Manrior D NA R Q As all times
- 2. innent Purge System
# Noble oss Activity Monitor.
pvideg Alarm and Automatic Modes I,2,3,4 erwunation of Release and during b GT-RE-22,GT-RE-33) D P RO) Q(1) Core Aherations or movemerd of irrad fuelin Ctmt. b@. todine Sampler W NA NA NA Same as 2.a.
- e. Panicriate Sampler W NA NA NA Same as 2.s
- d. Containment Purge Ventilation How Rate NA NA R(4) NA Same as 2.a
- e. Particulate and Radiciodine Sampler How Rate Monitor D NA R NA Same as 2.a
- 3. Radweste Buildmg Vent System
- a. Noble Oas Activity Morutor.
Providmg Alarm and Automatic Temanation of Release (Gil-RE-10) D,P M,P R(3) Q(1) At all times
- b. Iodme Sampler W NA N A. NA At all times
- c. Paniculate Sampler W NA NA NA At a!! times d Radwaste Duilding Vent How Rate NA NA R(4) NA At all times
- c. Paniculate aml Radiciodine Sampler How Rate Monitor D N A. R NA At all tirnes l . _- _ -_. _ - _ - _ . -. . . . . . - - .
APA ZZ-01003 ! Rev.4 TABLE 9.2-B (Cont'd) f TABLE NOTATIONS ; i (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isc' a of this pathway and control room alarm annunciadon occur as appropriate if any of the foi .ng conditions exists:
- a. Instrument indicates measured levels above the AlarmfTrip Setpoint (isolation and Liarm), ,
or
- b. Circuit failure (alarm only), or
- c. Instrument indicates a downscale failure (alarm only), or
- d. Instrument controls not set in operate mode (alarm only).
(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following condidons exists:
- a. Instrument indicates measured levels above the Alann Serpoint, or
- b. Circuit failure, or
- c. Instrument indicates a downscale failure, or
- d. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Institute of Standards & Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a ; solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) by the same geometry and type of ! source traceable to NIST. (4) If flow rate is determined by exhaust fan status and fan performance curves, the followi..g surveillance operations shall be performed at ! cast once per 18 months;
- a. The specific vent flows by direct measurement, or
- b. The differential pressure across the exhaust fan and vent flow established by the fan's " flow-AP" curve, or
- c. The fan motor horsepower measured and vent flow established by the fan's " flow-horsepower" curve.
14580329 47361437 I
-96 !
APA-ZZ-01003 Rev.4 9.3 LIOUID EFFLUENTS CONCENTRATION 9.3.1 Controls (CTS # 41834) 9.3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Technical Specifications, Figure 5.1-4) shall be limited to the concentration specified in 10 CFR Part 20.120.601, 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 104 microcurie /ml total activity. (CTS # 4160) APPLICABILITY: At all times. ACTION:
- a. 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.
- b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.3.2 Surveillance Reouirements 9.3.2.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 9.3-A. 9.3.2.2 The results of the radioactivity analysis shall be used in accordance with the methodology and paraueters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of REC 9.3.1.1. i 14580329 47361438 l l 1
\
APA-ZZ-01003 l l Rev.4 TABLE 9.3-A RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM
. UQUID RELEASE" SAMPLING . MINIMUM TYPE OF LOWER LIMIT
. TYPE FREQUENCY (7) . ANALYSIS ' ACTIVFlY ' '
OF DETECTION FFIQUENCY ANALYSIS (11D)(1)
> 6Ci/m0
- 1. Datch Waste P Principal g)amma Release Tanks (2) Each Batch Emitteni 5x10-7 1-131 1 x 10 4
- a. Discharge Dissolved and 1x10-5 Morutor Entramed Gases Tank (Canuna Eminers)
P Each Batch H-3 lx10-5 M Gross Alpha Ix10-7 Componne (4) t Q Sr-89, Sr-90 5x10'8 Composite (4) Fe 55 lx10 4
- 2. Continuous Daily Principal Gamma 5x10-7 [
Releases (S) Errutters(3) 1-131 1x10 4 i Steam Dissolved and Ix10*3 Generator Entrained Gases Blowdown (Gamma Enutters) Dail[) , Orab Sample H-3 1x10-5 M Gross A!pha Ix10*7 Composite (4) Q Sr 89, Sr-90 5x10-8 4 Canposite(4) Fe-55 lx104 14580329 473g,143g 1 98-
y APA-ZZ-01003 Rev.4 TABLE 9.3-A (Cont'd) TABLE NOTATIONS i l
- (1) The LLD is described in Attachment 1.
l
.(2) A batch release is the discharge ofliquid wastes of a discrete volume. Prior to sampling for !
analyses, each batch shall be isolated, and then thoroughly mixed a method described in the ODCM to assure representative sampling. (3) The principal gamma emitters for which the LLD control applies include the following radionuclides: Mn-54, Fe-59, Co-58,2n-65, Mo-99, Cs-134, Cs-137, Cc-141, and Cc-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are i identifiable, together with those of the above in the Semiannual Radioactive Emuent Release . Report pursuant to Technical Specification 6.9.1.7, in the format outlined in Regulatory Guide l 1.21, Appendix B, Revision 1, June 1974. (4) A composite sample is one in which the quantity ofliquid sampled is proportional to the quantity ofliquid waste discharged and in which the method of sampling employed results in a specium that is representative of the liquids released.- Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the emuent release. (5) A continuous release is the discharge ofliquid wastes of a nondiscrete volume, e.g., from a volume of a syst':m that has an input flow during the continuous release. (6) Samples shall be taken at the initiation of emuent flow and at least once per 24 houls thereafter while the release is occurring. To be representative of the liquid emuent, the sample volume shall be proportioned to the emuent stream discharge volume. The ratio of sample volume to I emuent discharge volume shall be maintained constant for all samples taken for the composite sample. (7) Samples shall be representative of the emuent release. A 14580329 47361440
l APA-22-01003 Rev.4 9.4 DOSE FROM LIOUID EFFLUENTS 9.4.1 Controls (CrS# 41834) 9.4.1.1 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 Technical Specifications, Figure 5.1-4) 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.
APPLICABILITY: At all times. ACTION: (CrS# 1161)
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, preparc and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, 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. This Special Report shall also include: (2) the results of radiological impact on finished dnnkmg water supplies with regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act.*
- b. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.4.2 Surveillance Reouirements 9.4.2.1 Cumulative dose contributions from liquid effluents for the current calendar quaner and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. I 1 l
- The requirements of ACTION a.(1) and (2) are applicable only if dnnking water supply is taken from ge. In e case f river-sited plants this is 3
(( b*$, "2" fsc
-100-
1 APA-ZZ-01003 Rev.4 f 9.5 LIOUID RADWASTE TREATMENT SYSTEM 9.5.1 Controls (CTS # 41834) 9.5.1.1 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 Technical Specifications, Figure 5.1-
- 4) 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:(CTS #1161)
- a. 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 wititin 30 days, pursuant to Technical Specification l 6.9.2, a Special Repcrt 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 Technical Specifications 3.0.3 and 3.0.4 are not applicable.
l 9.5.2 Surveillance Reauirements 9.5.2.1 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. 9.5.2.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting REC 9.3.1.1 and 9.4.1.1. 14580329 47361442 l
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APA ZZ-01003 Rev.4 9.6 OASEOUS EFFLUENTS DOSE RATE 9.6.1 Controls (CTS # 41834) . 9.6.1.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Technical Specifications, Figure 5.1-3) 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 and 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.
APPLICABILITY: At all times. 4 ACTION:
- a. With the dose rate (s) exceeding the above limits, inunediately restore the release rate to within the above limit (s). ,
i
- b. The provisions ofTechnical Specifications 3.0.3 and 3.0.4 are not applicable.
9.6.2 Eurveillance Reouirements 9.6.2.1 The dose rate due te noble gases in gaseous efDuents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM. 9.6.2.2 The dose rate due to Iodine-131 and 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 Tabic 9.6-A, f I 14580329 47361443
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APA-ZZ-OlCD3 Rev.4 TABLE 9.6-A H RADIOACTIVITY GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM b IA lower t.D.GT OF - ( GASEOUS RFJEASE TYPE . SAMPtJNG FREQUENCY (9) EEN1 MUM ANALYSIS - FREQUENCYc
..TYPEOF ACTIVITY ANALATISS - _ DETECTION ('1D)(1)'
O"Q ~
. ww>
(1i Pnncipal Gamma Enune s(2) 1x10
- 1. W ~ Gas Decay P P T Each Tank Grab Sample Each Tank I.1%
d 2 Certamrnerd Purge er VenaO) P P PnncgalGamma Emuneg2) 1x10 g Each PURGE II Grab $ ample Each PURGEII) S.) M 1:10 4 H-3(omde)
\ I 10#
3 Vent k[3M4) h/3) Pnacgal Gamma Ernancrs@ Grab Sarryle _ k/4) H-3 (omade) 1 10 4
$a 45 Fuel Bolens Exhaum h/3) M Pnnegal Gamme Enuuer @ la104 Grab Sample W g5) 15 3(ande) tul0 4 Greb Sample d
- 5. Redwame Bml4 Vem M M Pnncipal Garwna Ennuers@ Islo Grab Sample 6 All Release Types as trsted a l.2,3 4 Corsmunus(6Xt) g7) 1 131 Ix10'I2 and 5 above Charcoal Sample 1-133 lx10-10 Caramuum(6X3) M7) Pnncipal Gamma Ernancy2) ImI0'II Parteculase Sarrete Contmuous(6XI) M Greas Alpha I 10 4i Cornposite Part culare Sample Conimuous(6X8) Q Sr-89, $r-90 lx10'II Componne Panmalase Sample s
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APA-ZZ-01003 Rev.4 TABLE 9.6-A (Cont'd) . TABLE NOTATIONS (1) The LLD is described in Attachment 1. (2) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xc-138 in noble gas releases and Mn 54, Fe-59, Co-58, Co-60,2n-65, Mo-99, I-131, Cs-134, Cs 137, Cc-141, and Ce-144 in iodine and particulate releases. 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 Ef!1uent Release Report . pursuant to Technical Specification 6.9.1.7, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within I hour period. (4) Tritium grab samples shall be taken and analyzed at least once per 24 hours when the refueling canalis flooded. (5) Grab samples need to be taken only when spent fuel is in the spent fuel pool. The ratio of the sample flow rate for the sampled stream flow rate shall be known for the time (6) period covered by each dose or dose rate calculation made in accordance with REC 9.6.1.1, 9.7.1.1, and 9.8.1.1. (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. For unit vent, sampling shall also be performed at least once per 24 hours 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 hours of changing. When samples coIIected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does t ot apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 > concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that efnuent activity has not increased more than a factor of 3. (8) Continuous sampling of the spent fuel building exhaust needs to be performed only when spent fuelis the spent fuel pool. (9) Samples shall be representative of the efHuent release. 1 14580329 47361445 I
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APA-ZZ-01003 Rev.4 9.7 DOSE - NOBLE GASES 9.7.1 Controls (CTS # 41834) 9.7.1.1 The air dose due to noble gases released in gaseous efiluents, from each unit, to areas at and beyond the SITE BOUNDARY (see Technical Specifications Figure 5.1-3) 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.
APPLICABR.ITY: At all times. ACTION:(CTS # 1161)
- a. With the calculated air dose from radioactive noble gases in gaseous efiluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical 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 Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.7.2 Surveillance Reauirements 9.7.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year for nobic gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. l l 1 4 I i i 14580329 47361446
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l l APA-ZZ-01003 l Rev.4 9.8 DOSE -IODINE-131 AND 133. TRITIUM. AND RADIOACTIVE MATERIAL IN PARTICULATE FORM 9.8.1 Controls (CTS # 41834) 9.8.1.1 The dose to a MEMBER OF'IEE PUBLIC f2om Iodine-131 and 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 BOUND ARY (see Technical Specifications, Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 miems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
APPLICABILITY: At all times. i
~
ACTION: (CTS # 1161)
- a. With the calculated dose from the release ofIodine-131 and 133, tntium, 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 ,
Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limits 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 Technical Specifications 3.0.3 and 3.0.4 are not applicable.
i 9.8.2 Surveillance Recuirements i
- 9.8.2.1 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 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.
i l l 14580329 47361447
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APA-ZZ-01003 Rev.4 9.9 GASEOUS RADWASTE TREATMENT SYSTEM 9.9.1 Controls (CTS # 41834) 9.9.1.1 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP 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 (see Figure Technical Specification's 5.1-3) 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 ACTION:
- a. With radioactise gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specifications 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 provision of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.9.2 Surveillance Recuirements 9.9.2.1 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. 9.9.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEMS shall be considered OPERABLE by meeting REC 9.6.1.1 and 9.7.1.1 or 9.8.1.1. 14580329 47361449
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APA-ZZ-01003 Rev.4 9.10 TOTAL DOSE 9.10.1 Contrqlj (CTS # 41834) 9.10.1.1 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 2$ mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. APPLICABILITY: At all times. ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous efDuents exceeding twice the limits of REC 9.4.1.la,9.4.1.lb,9.7.1.la,9.7.1.lb,9.8.1.la, or 9.8.1.lb, calculations should be made including direct radiation contributions from the units and from outside storage tanks to detennine whether the above limits of REC 9.10.1.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent release to prevent recurrence of exceeding the above limits r.nd includes the schedule fw achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all efnuent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It sha!! 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 if the release condition resulting in violation of 40 CFR Part 190 has not 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 Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.10.2 Surveillance Recuirements 9.10.2.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with REC 9.4.2.1,9.7.2.1, and 9.8.2.1, and in accordance with the methodology and parameters in the ODCM. 9.10.2.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirements is applicable only under conditions set forth in ACTION a. of REC 9.10.1.1. 14580329 47361449
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APA-ZZ-01003 Rev.4 9.11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 9.11.1 Controls (CTS # 41835) 9.11.1.1 The Radiological Environment Monitoring Program shall be conducted as spe iin Table 9.11-A.
- APPLICABILITY: At all times.
ACTION
- a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 9.4-A, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.6, a description . .. !
of the reasons for not conducting the program as required and the plans for preventing a ! recurrence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reponing levels oiTable 9.11-B when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive
~ efDuents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of REC 9.4.1.1,9.7.1.1, or 9.8.1.1, When more than one of the radionuclides in Table 9.ll-B are detected in the sampling medium, this report shall be submitted if:
i c.oncentration (1) concentration (2) + 21.0 " reporting level (1) reporting (2) When radionuclides other than those in Table 9.ll-B are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to A MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of REC 9.4.1.1,9.7.1.1 or 9.8.1.1. This report is not required if the measured level of radioactivity was not the result of plant efnuents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report, required by Technical Specification 6.9.1.6.
- T)e S '
3 aw;thodology4pd pramete+s used4ofstimate php potential annual dose to a MEMBER OF THE POBLICT!5 ail'SeiiidiFatTd in tiIs RT' fel t?
-109-
i APA-ZZ-01003 Rev.4 t
- c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 9.11-A, identify specific locations for obtaining replacement sampics and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.** The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 6.14, submit as part of, or concurrent with, the next Semiannual Radioactive Efiluent Release Report a complete and legible copy of the entire ODCM, including the revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of Oc unavailability of samples and justifying the selection of new location (s) for obtaining saeples.-
- d. When LLDs specified in Table .1.ll-C are unachievable due to uncontrollable cin.ugatuices, (such as backgrouad fluctuations, unavailable small sample sizes, the presence ofinterfHng nuclides, ett ) the contributing factors shall be identified and described in the Annual Radiologic:u Environmental Operating Report.
- e. The provisions of Technical Specificatio*is 3.0.3 and 3.0.4 are not applicable.
9.11.2 Surveillance Reauirements 9.11.2.1 The radiological environmental monitoring samples shall be collected pursuant to Table 9.11-A from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Tabic 9.11-A and the detection capabilities required by Table 9.11-C.
** Excluding short term or temporary unavailability.
1 14580329 47361451 l
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. . . _ , .u. . - _ -
APA-ZZ-01003 Rev.4
^
TABLE 9.ll-A H RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM b LR . 0) y NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND ('kXPOSURE PATHWAY AND SAMg COLLECTION TYPE ANDFREQUENCY LOCATIONS ( ) FREOUENCY OF ANALYSIS {Q ANDOR SAMPLE
- 1. D Radiation @ Forty routine monitoring stations either with two or more Quarterly Gamma dose quarterly dosimeters or wiih one instrument for measurms and recording dose rase conunuously, placed as follows:
"*j An inner ring of sixteen stehens, one in each meteorological
+metoe in the general area of the SITE BOUNDARY; J
@ An outer ring of stahans, one in each meteorological sector in the 6- to g-km (3 to 5 mile) range from the site; and g
h Eight stations to be placed in special interest areas such as (g population centers, nearby residences, sduools, and in one or two
, areas to serve as control stations.
l,V
- 2. Airbome Radioeodine and Samples from five locations, Continuous sampler operation with sample Radionaduw Canspec 1131 analysis weekly.
Particulates collection weekly, or more frequently ifrequired "Dwee samples from close to the three SITE BOUNDARY bydust W Pasticulate Sampler. Gross beta . " ;4, locations, in diferent sectors, of the highest calculated annual analysis followingfiker disage:(4) and gemena average ground level D/Q. isotopic analysis ( )ofcomposite(bylocation) quarterly. One sunple from the vicinity of a community having the highest i calculated annual average ground level D/Q. One sample from a control locaban, as for example 15 to 30 km (g0 to 20 mile) distant and in the lease prevalent wind direction ( ). P
-lil- . __ .,-..c___ , _ . . - - . . - _ . - - - _ . _ _ . . - _ . , - , _ _ . _ . . - - _ _ . _ _ . - _-, _u.--_ . - _ _ _ , . _ _ . -
APA-ZZ-01003 Rev.4 TABLE 9.Il-A (Cont'd) H RADIOLOGICAL ENVIRONhENTAL MONITORING PROGRAM M Ul (0 Q NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND k'.I TYPE AND FREQUENCY COLLECTION AND SAMPy OF ANALYSIS
%$XPOSURE PATI!WAY ANDOR SAMPLE LOCATIONS ( ) FREOUENCY
- 3. Waterbome Camma isotopk(5) and tritium ace [) One sample upstream
- a. Composite I-erumth periodsanylj)over
(. analysis monthly N One sample downstream I-131 analysis on each composite when the dose
- b. inking One sample of each ofone to three of the nearest water supplies vnthin 10 miles downstream that could be afTected by ks Composite 2 week period sy(when)e overanalysis is 1-131 calculated for the comumptigofthe uter is Qi performed, monthly composite otherwise. greater than I nwem per yeart ) Composite for discharge.
g gross beta and gamma isotopic analyses (5) monthly. Composite for tritium analysis h One sample from a cc,ntrol locatiart quarterty. (q Sernannually Gamma isotopic analysis (5) semiannually
- e. Niment from One sample frorn downstream area with existing or poteraial shoreime recreational value
- 4. Ingestion S . . cl. , when animals are on pasture, Gamma isotopkt $) and 1-131 analysis a Milk Samples from nutking animals in Livee different meteorlogical monthly at other tunes sermmmahiy when animals are on pasture:
sectors within 5 km (3 mile) distance having the highest dose monthly at other times potential. If there are none,then one sample from nutking animals in each of three different meteorlogical sectors between 5 to 8 km (1 to 5 mile) distance where doses are calculated to be greater than i mrem per 37. One sample from milking animals at a control location, I 5 to 30 km(10 to 20 mile) distance and in the least prevalent wind dweaion.
-112-o
-____________..__________._-_m _. ., . - - _ . - . . - . - - - - -- - , , .-- - - --
~
' APA-ZZ-01003 Rev.4.
TABLE 9.11-A (Cont'd) M RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM b UI
@ NUMBER OF O REPRESEfffATIVE SAMPLES SAMP11NO AND COLLECTION TYPE AND FREQUENCY (t)XPOSURE PAT 11WAY AND SAMg LOCATIONS ( ), OF ANALYSIS FREOUENCY
; ANDORSAMPLE
- 4. Inh (Cortd)
One sarnple of each commercially and recreationally importara Sample in season, or sermannually if they are Gamma isotopic analysis (5) on edble postions
- b. [ish species in vicinity ofplara discharge area. not sessenal
% One sample ofsame species in areas not influe:wd by plant (d discharge.
s One sample ofeach pnncipal class of food prod:w frown any area At time ofharvesa (')(10) % g,,gg ,,,9;, g )5 on e6W pian
- c. (god Products that is irrigated by water in which liquid plant v asses have Esen disdwged.
I* Samples of three diNerent kinds of broad leaf vesetation if . Gamma isotopic (5)and 1131 analysis available yown nearest each of two different orisite locations of . Monthly when available highest predicted annual average ground level D/Q if milk samplingis not performed One sample ofendi of the similar broad leaf vgetation youn 15 Mey when available Gamrna isotopic (3) and Fl31 analysis to 30 km (10 to 20 mile) distars in the team pr* valent wind direction if milk sampling is not performed.
-i13-
___________=..____._.______..c.__._,_.__..__ . . _ . . . . . - , - - _ _ . . . . . _ _ _ . . _ . _ . .. _ _ . _ _ _ _ _ _ _ _ _ __
APA-ZZ-010m Rev.4 TABLE 9. ll-A (Continued) l TABLE NOTATIONS j (1) Specific parameters of distance and direction sector from the centerline of one unit, and additional description where pertinent, shall be provided for each and every sample location in Table 9.11-A in a table and Sgure(s) in the ODCAL Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.6. (CTS # 2804) It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific l alternative media and locations may be chosen for the panicular pathway in question and l appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Repon documentation for a change in the ODCM including the revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway andjustifying the selection of the new location (s) for obtaining samples. (2) One or more instruments, such as a pressurtzed ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of direct radiation monitoring stations may l be tvinced according to geographical limitations; e.g., at an ocean site, some sectors will be over I water so that the number of dosimeters may be re iu.d rccrdirT,1y The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (3) The purpose of this sample is to obtain background information. Ifit is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. l I l (4) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air paniculate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. j (5) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. (6) The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone. (7) In this program, composite sample aliquots shall be collected at time intervals that are very short 1 3 8b kgg., monWy)in oder to assure omg a 3 114 I _j
i l APA ZZ-01003 Rev.4 l l TABLE 9. Il-A (Continued) TABLE NOTATIQNS (8) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge propenies are suitable for contamination. (9) The dose shall be calculated for the minimum organ and age group, using the methodology and parameters in the ODCM. . (10) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. ; I L t b I [ r 15010329 47361456 . l
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-- ' -s i q
1- c.s _ APA-ZZ-010031
~Rev.4.
TABLE 9.Il-B REPORTING LEVELS FOR RADIOACTIVITY CONCENIRATIONS IN ENVIRONMENTAL SAMPLES U O REPoRTINo tevELs l-d O FISH MILK (e,\ ANALYS13 WATER 1. FOOD (,Ca. PRT.->
~
. AIRBORNEPARTICL,YTE oR oases <,Cv- <,Ca ->$ c,Cyt r g (,Cye f t0 n.3 20.000*
tamMrsammm=wmmmmmemmemammmMrmeemmeneasemarmrammes Mn-54 1.000 30,000 ' ESE: EMNEIN$M Fe 59 meDOMITdMM$2dd$@EN7tENIEi3$ildhW4MidEEdihMDEEME$iMMMMMM._ 400 10,000 sagsmmmarammmmamarmMananmananmasammmmmvmarassex
~
Ns Co-58 1.000 . 30,000
' M b E@ M 8 I M mE E M I M d N fdY2dE T E d l47d D E$ N $[ D i N M $ $ @ @2 M Y10,000 dd d M
- M M 75$ E 8a D M IIM M @ M 2 D 2 $.3 g.4 CW 300 M LMMZ$$MAMidUEIBEM31%Mi!3?iCMRisWdid@i%B3Z3 h Zr Nb-95 400 lim 5ERTNERK2TMK%MMMMMXCHM%
LG i(,qTGMsild?i2~0TM2?M 23LEIiMLMLMMiMMAWMMEMMEWARMMGEslitMMTZ$QiMft%SBRMMa%%DM 0.9 3 100 I-I31 V5 yen $?$5E SSENk5 M U S $ES$?$$ NNIENIN5li M I5kT D M & WEN M & M W$$$$$$$ M $$t M M M $$?$NL M M BE M Cs-134 30 10 1,000 60 I,000 -
@iY7$MIJEMM7hYslidEMdEdMS@ s DIM $1$2Edif[$$$MMMfY8MlD327Ed!1MTMM@[ds7dSIMEM5MufM@aD3I.d 20 2,000 70 2.000 Cs-137 50 .
M l M E 5 M S h 5 M M $ $ $$$?$$ 200
$$$Iili & SSiE?E Q $b M M M IN? & $$ $ 5Ti$ M %9 M U N U G EIN$ 300 M i$$% W W M M EN S M D i[$ 5 C M M Ba-La-140 (a) Multiply he valves en this table by IE-9 to convert to umas of pCVml.
(b) Muhiply the values in this table by IE 9 to convert to units of pCVg.
- For drinking water samples. This is 40 CFR Part 141 value. For surface water samples, a value of 30,000 pCill may be used.
** Total activity, parent plus daughter activity.
-l16-
V Q y s s s h APA-ZZ-01003 Rev.4 TABLE 9.11-C H DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS U Q LOWER LIMIT OF DETECTION (LLD) (I),(2), (3) H O ANALYSIS SURFACE DRINKING AIRBORNE FISH MILK SEDIM W WATER W ATER PARTICULATE (pCng wet)b pf )n FOOD (pCag,PROy) wet (pCi13 ] dry) (pcut )* (pevt la OR OASES (pCVm ) l9
@ Gross Beta 4 4
~
0.01 n;:wwww. sww n,mm,mpawwnp.ye r;3w:m k :.M < ." Asw4*w.e a:xw.w*.cA%.>
.~erm. m a o w n i m m ;wz ,:0,m;Awwu ung , .m y.m.rw aaw.~xa;AMsd;a,y.y.p.i&mem A:xwh m:u ~ss :mudypp&pmmmmm#esihbakmMausw>sw.mawammmmm*EGNW.+m.
sm Aekham gem:q wh&J46u
,f'a H-3 3000 7000 mm L
t mm :y:m m nw ~ m.mm.a:w m .
>g ).6.Y.x;as ur!4:&& W & hr.1% W As W h2d...O:m%v?.e. :g a.m:n s~wym:u
.0 4MdL&NFSh m ah:>4YA%e&$mng&pu>>mEun*;.gmwmp a . 14MW ;s4Gn pw W:GKhaiM 4L w , .u-
;Ls2ik'@mmm,y&Mhw:
s.Amd emwe nse wM #f& w n^w<uwwvg weWim: EA%E sObhny 1 hhwS4 15 15 130 pm 4.A.m e(a t teysw. mwo.-m .
<n vav.m <w~e kh.+w.x.em.:d.<enw h&ELoew uqqx nex.x > g5pcug:wgap:g:r.ve:.p:
. AAs:w:s >imc hwnsmhno.c pgag%p&hd<d:m
~
pyggenpyye:wayy.py:gntyymm:pggf 3*wm3c3..--a:a W a d w A wwau h a:xxv.w d:M exadeswta mw& M 5. wpp w.:agp$xsxayg w:=.v.a Fe-59 30 30 260 m, 5.s y
.mm c m rp::wS
.;. %.d %g w <eAa m.wsp;$.:hexw m;r:e A wH.2:xwAAeu::whastedsu:6 y y pp:gemg.twargyrm&y M: hw .te c
=nm.wms A g xmwwywe ww=**.m e ;.:ey w gbp-Ay3i.swsmm2%g4:dLand.a:wwd4&3kshi: w w&a* p mgp WqS .4,d 3A .m.. m f.s Co-58,60 15 15 130 g~- m e ,-
ude c gea c . g wcwn n:c.; xn M.uk f N;shLw24s+.6dauce.+:wAxt; Dei &dMia&&ans$MN,y.m;Ur&& c .yyy q, #. Aisi sv (g g .<.a mmq&whw3'.wsCMmE3&6U2Mdhhgnwm mWa0Gfl0i-KWxMw
.pg p%w.mg m.y mswwgem.s<cx avnWEenMe%vedhiWwJi::w:09" 4.. #c-w--;.w A R.M ewege.m m wahz Zr-Nb-95 15 15 ,
en: d o,;.u. w~e.A. %pr ehmesda.1. mvw:w.3;. .A 7:m ww . .
#s:&&n.Ai:d-de%sp&yernw . .c w:y
;.f.w::ss;p.:&y.v;;s:w&.m :;p:tmwggnes*wswwqv;epdWirs ~ yo u:ww>nqsvgmanewgym;gy;yt:p:x:*
"' :is!QLdehhS4EW:cas44,.w.hw V40*g.s nf wgyg.<a;g JGwasnSL+me w: A a ,:hi.L?M&xAo4417Ai&A8Mit:&4MJudW&WW;:mSKSM&sh:::0M:w -
M I-131 1000 1 0.07 1 60 ex:. n ,nw naam&e-mwwwmynn
&i -w.s.av. sea %.w:As.w M, 2x 4 as.4;p w::urm: .:mps w m :v~ m mm m y ismsha.a.midrugssp4:ahuuwgeweremmm.sAhu.m:mssc:&Asmusw.1wA&&::wwwnew>xmmmmewwwww vnwnwngs;tde u&;s:ac -
. 4s de4+.dadsaEMia:4 Kasaa&:Acha-siiasiawm Cs-134 15 . 15 0.05 130 15 60 ISO krpmWwed :n esmmmmem::en h Ju Aic h AA&xMaids;v xpme ::yn >meuxwyy.:ympy:ywa. .? msyn %t.s;pem,&M.iN#xddFb ess enwxe;w~. ss;. m mser-mp-MMAyu4
. ',ne ssn.h m:e:Xi4i ia2A;M e s w nm;mmmsmgy;MEFishif;Khmew;AmeawsuWs>.eSit::#q&w0rM;x.
fx4., nSsh?aZvndeWe;%ivM>x: QMas4A i.nM4 dmR 4iM43n sed Cs-137 18 - IS 0 06 150 18 80 ISO
~ m.~
, m.c~e~w s w:3 p:;;;u m. q w.mww.m.nwww wpu misi :ks.7y:#mcom. y:mwen w.myupmwwg;39seypp:sgpmywemmewcmm psp;wp . mvey.pg. 9
- r e
musaas:uas.wsussm;irmmm.u.asusewsamm;nswagumum. masse,:s w;merr.::ch.wd ! Ba-La-140 ; u.uu;mitanzae;aa 15 15 15 l I (a) Muhipty the values in this table by 1 E-9 to convert to units cf pCi/ml. 4 (b) Muhiply the values in this table by 1 E-9 to convert to units of pCi/g, l 1
" Total aethity, parent plus daughter activity.
l
-l17-l l
L_______ -
I APA-ZZ-01003 Rev.4 TABLE 9.Il-C (Continued) TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiabic, together with those of the listed nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13 Revision 1, July 1977. (3) The LLD is described in Attachment 1. i i l 1 i l l l l l 15010329 47361459 118-
APA-ZZ-01003 Rev.4 9.12 RADIOLOGICAL ENVIRONMElfTAL MONITORING LAND USE CENSUS 9.12.1 Controls (CTS #41835) 9.12.1.1 A Land Use Census shall be conducted and shallidentify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk ammal, the nearest residence 2 2 and the nearest garden
- of greater than 50m (500 ft ) producing broad leaf vegetation.
APPLICABILITY: At all times. ACTION:
- a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the salues currently being calculated in REC 9.8.2.1, identify the new location (s) in the next Semiannual Radioactive Ef!1uent Release Report, pursuant to Technical Specification 6.9.1.7.
- b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with REC 9.11.1.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which tlus Land Use Census was conducted. Pursuant to Technical Specification 6.14, submit as part of, or concurrent with, the next Semiannual Radioactive Effluent Release Report a complete and legible copy of the entire ODCM, including the revised figure (s) and table (s) reflecting the new location (s) with information supporting the change in sampling locations.
- c. The provisions of Technical Specifications 3.0.3 and 3.0.4 are not applicable.
9.12.2 Surveillance Reauirements 9.12.2.1 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information which will provide the best results, such as, but not limited to, door-todoor survey, aerial survey, or by consulting local agriculture authorities and/or residents. The results of the Land Use Census shall be included in the Annual Radio ogical Environmental Operating Report pursuant to Technical Specification 6;r.l.6.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each to two different direction sectors with the highest predicted D/Q's in lieu of the garden census. Specifications for broad !caf vegetation sampling in Table 9.11-A, Part 4.c shall be followed, including analysis of control samples.
15010325r 47361460
-119-r
l AP A-ZZ-01003 i Rev.4 I 9.13 RADIOLOGIC AL ENVIRONMEdTTAL MONITORING INTERLABORATORY COMPARISON PROGRAM 9.13.1 p_qnt.mh (CTS # 41835) 9.13.1.1 Analyses shall be performed on radioactive materials supp led as pan of an Interlaboratory l 5 Comparison Program that has been approved by the USNRC. 1 AEELLC/31 TTY At all times. ACTION:
- a. With analyses not being performed as required above, repon the corrective actions taken to prevent a recurrence to the Commission in The Annual Radiological Environmental Operating Repon pursuant to Technical Specification 6.9.1.6.
- b. The provisions of Technical Specificatbns 3.0.3 and 3.0.4 are not applicable.
9.13.2 Surveillutce Reauirements 9.13.2.1 The Interlaboratory Companson Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Repon pursuant to Technical Specification 6.9.1.6. I f 1 5 0'1 0 3 2 9 47361461
-120-
i APA-ZZ-01003 Rev.4 10.0 ADMINISTRATIVE CONTROLS 10.1 MAJOR CHANGES TO LIOUID AND GASEOUS RADWASTE TREATMENT SYSTEMS
- 10.1.1 Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Semiannual Radioactive EfDuent Release Report for the period in which the evaluation was reviewed by the On-Site Review Committee (ORC). '1he discussion of each change shall contain; 1.) A summary of the evaluation that led to the determination that the change could be l i
made in accordance with 10 CFR 50.59; 2.) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; l 1 3.) A detailed description of the equipment, components and process involved and the ! l interfaces with'other plant systems; 4.) An evhluation of the change, which shows the predicted releases of radioactive , materials in liquid and gaseous effluents that differ from those previously predicted in ) the License application and amendments thereto; 5.) An evaluation of the 1 change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from diose previously estimated in the License application and amendments thereto; 6.) A comparison of the predicted releases of radioactive materials, in liquid and gaseous f effluents, to the actual releases for the period prior to when the changes are to be made; 7.) An estimate of the exposure to plant operating personnel as a result of the change; and 8.) Documentation of the fact that the change was reviewed and found acceptable by the ORC.
- b. Shall become effective upon review and approval by the ORC and in accordance with Technical Specification 6.5.3.1.
10.2 CHANGES TO THE OFFSITE DOSE CALCULATION M ANUAL (ODCM) (CTS # 2815) 10.2.1 All changes to the ODCM shall be completed pursuant to Technical Specification 6.14 and approved as per APA-ZZ-00101, " Preparation, Review, Approval and Control of Procedur " 10.2.1.1 All changes shall be approved by the ORC prior to implementation. 10.2.2 Cross Disciplinary Review for each revision cf the ODCM must include, as a minimum, the Health Physics, Quality Assurance, and Licensing and Fucts Radiological Engineering , Departments.
;h13'*1"5M'b'" 3MtTa%""s "'""*d ' ' '" *i" "" ' ** """"* ^""" '
-121-
- e APA-ZZ-01003 Rev 4-10.2.3 A complete and legible copy of each revision of the ODCM that became effective during the last semiannual period shall be submitted as a part of, or concurrent with that periods Semiannual Radioactive Effluent Release Report pursuant to Technical Specification 6.14.
d 15010329 47361463
-122-
APA-ZZ-01003 Rev.4
11.0 REFERENCES
11.1 Title 10. " Energy", Chapter 1, Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402. l I 11.1.1 Statements of Consideration, Federal Register, Vol. 56, No. 98, Tuesday, May 21,1991, ' [ Subpart D, page 23374. 11.2 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S. , Government Printing Omce, Washington, D.C. 20402. l 11.2.1 10 CFR 50.36 a (b) i 11.3 Title 40, " Protection of Environment", Chapter 1 Code of Federal Regulations, Part 190; U.S. , Government Print Omce, Washington, D.C. 20402. I1.4 U.S. Nuclear Regulatory Commission, " Technical Specifications Callaway Plant Unit NO.1", NUREG-1058 (Rev.1), October 1984. 11.4.1 Section 6.8.1 (CTS # 2791) f 11.4.2 Section 6.8.4f(CTS # 41834) 11.5 Communications 11.5.1 Letter NEO-54, D. W. Capone to S. E. Miltenberger, dated January 5,1983; Union Electric Company correspondence. ; 11.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values", J. H. Smith (Bechtel Power Corporation), to D. W. Capone (Union Electric Co.), dated February 27,1984 11.5.3 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Electric Co.), dated February 9,1984, t 11.5.4 Reference Deleted : 11.5.5 Private Communication, H. C. Lindeman & B.F. Holderness, August 6,1986 ! i 11.5.6 Calculation ZZ-67," Annual Average Atmospheric Dispersion Parameters", April 1989. I1.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report. , 11.6.1 Section 11.5.2.2.3.1 11.6.2 Section 11.5.2.2.3.4 i 11.6.3 Section 11.5.2.1.2 11.6.4 Section 11.5.2.2.3.2 1 N 1 8@ h .2.3g 7 3 5 1 4 5 4 I1.6.6 Section 11.2.3.3.4
-123-
g, APA-ZZ-01003 Rev.4 l t 11.6.7 Section 11.2.3.4.3 l1.6.8 Section 11.5.2.3.3.1 11.6.9 Section 11.5.2.3.3.2 11.6.10 Section 11.5.2.3.2.3 11.6.11 Section 11.5.2.3.2.2 11.6.12 Section 2.3.5 11.6.13 Section 2.3.5.2.1.2 11.6.14 Section 9.2.6 11.6.15 Section 9.2.7.2.1 11.6.16 Section 6.3.2.2 11.6.17 Table 11.16 11.6.18 Deleted 11.6.19 Deleted ! 11.6.20 Deleted l 11.6.21 Deleted l 11.6.22 Tab!c 2.3-68 ; 11.7 Union Electric Company Callaway Plant Environmental Report. Operating License Stage. I1.7.1 Table 2.1 19 11.7.2 Section 2.1.2.3 11.7.3 Section 2.1.3.3.4 11.7.4 Section 5.2.4.1 11.7.5 Table 2.1-19 11.8 U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants". USNRC NUREG4133 Washington, D. C. 20555, 1 October 1978. I 11.8.1 Pages AA-1 through AA 3 1 T1.b1M5@f:f.3 47361465 ;
-124-
)
APA-ZZ-01003 Rev.4 [ 11.8.3 Section 4.3 i 11.8.4 Section 5.3.1.5 l 11.8.5 Section 5.1.1 11.8.6 Section 5.1.2 11.8.7 Section 5.2.1 F 11.8.8 Section 5.2.1.1 , 11.8.9 Section 5.3.1 11.8.10 Section 3.8 11.8.11 Section 3.3 t i1.9 U.S. Nuclear Regulatory Commission, "XOQDOQ, Program For the Meterological Evaluation of Routine Efiluent Releases at Nuclear Power Stations". USNRC NUREG-0324 Washington, D. C. 20555. 11.9.1 Pages 19-20 Subroutine PURGE 11.10 Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of i Gaseous Effluents in Routine Releases from Light Water-Cooled Reactors", Revision 1. U. S. Nuclear Regulatory Commission, Washington, D. D. 20555, July,1977. I1.10.2 Section c.l.b i1.10.3 Figures 7 through 10 11.10.4 Section e.4 11.11 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Efiluents for the Purposes of Evaluating Compliance with 10 CFR Part 50, Appendix 1", Revision
- 1. U. S. Nuclear Regulatory Commission, Washington, D. C. 20555 October 1977.
11.11.1 Appendix C, Section 3.a - 11.11.2 Appendix E, Table E-15 11.11.3 Appendix C, Section i 11.11.4 Appendix E, Table E-!1 11.11.5 Appendix E, Table E 9 11.12 U. S. Nuclear Regulatory Commission, " Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D. I 1 SO 3.0P>S*E*3 '8073F.,14 S E 11.12.1 Section I, Page 2
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I APA-ZZ-01003 ; Rev.4 , i 11.12.2 Section IV, Page 8 i 11.12.3 Section IV, Page 9 l I 11.12.4 Section III, Page 6 11.12.5 Section III, Page 8 1 11.13 Management Agreement for the Public Usa, of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 21,1982. 11.13 Exhibit A 11.14 Miscellaneous References 11.14.1 Drawing Number M 1094007-06, Revision 5 11.14.2 Callaway Plant Annual Environmental Operating Report (updated annually) 11.14.3 UE Safety Analysis Calculation 87-001-00 11.14.4 Calculation ZZ-48; " Calculation of inhalation and Ingestion Dose Commitment Factors for the Adult and Child", January,1988 11.14.5 HPCI 8942, " Calculation of ODCM Dose Commitment Factors" March,1989 11.14.6 HPCI 87 04, " Calculation of the Limitiag Setpoint for the Containment Purge Exhaust i Monitors, GT RE-22 and GT RE 33", March,1987 11.14.7 HPCI 88-10, " Methodology for Calculating the Response of Gross NaI(TI) Monitors to Liquid Efiluent Streams", June,1988 11.14.8 Calculation ZZ-57, " Dose Factors for Eu-154", January,1989 i 11.14.9 Calculation ZZ-78, "ODCM Gaseous Pathway Dose Factors for Adult Age Group", July,1992. 11.14.10 HPCI 88-08, " Performance Testing of the Environment TLD System at Callaway Plant", , August,1989. I1.14.!! Calculation ZZ-250, Rev. I "ODCM Gaseous Pathway Dose Facters for Child Age Group and Ground Plane Dose Factors". l 11.15 U. S. Nuclear Regulatory Commission, "XOQDOQ: Computer Program for the Meterological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2919, September 1982, Washington, D. C. 20555 I1.15.1 Section 4, " Subroutine PURGE", pages 27 and 28 11.16 Regulatory Guide 4.13. " Performance, Testing, and procedural specifications for j 15C no D 5 i
-126-l
APA-ZZ-01003 Rev.4 11.17 TID-7004, " Reactor Shielding Design Manual", Rockwell. Theodore, ed; March 1956. 11.18 BNWL 236, "ISOSHLD - A computer code for General Purpose Isotope Shielding Analysis". Engel, R. C., Greenberg, J., Hendrichson, M. M.; June 1966 11.19 BNWL-236, Supplement 1, "ISOSHLD-II: Code Revision to include calculation of Dose Rate from Shielded Bremstrahlung Sources", Simmons. G. L., et al; March 1967 11.20 BNWL 236, Supplement 2, "A Revised Photon Probability Library for use with ISOSHLD-III", Mansius, C. A.; April 1969. I1.21 ANSI N13.10-1974 , " Specification & Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in EfHuents"; September,1974 11.22 Nuclear Regulatory Commission Generic Letter 89-01, " Guidance for the Implementation of Programmatic Controls for RETS in the Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989 11.23 NRC Answers to 10 CFR 20 Implementation Questions 11.23.1 Letter, F. J. Congel to J. F. Schmidt, dated December 9,1991. I1.23.2 Internal USNRC memo, F. J. Congel to V. L. Miller, et al, dated April 17,1992. 11.23.3 Letter, F. J. Congel to J. F. Schmidt. dated April 23,1992. I1.23,4 Letter, F. J. Congel to J. F. Schmidt, dated September 14,1992. 11.23.5 Letter, F. J. Congel to J. F. Schmidt. dated June 8,1993. I 15010329 4736146,8 !
-127-
e r APA-ZZ-01003 Rev.4 ; ATTACHMENT 1
+
LOWER LIMIT OF DETECTION (LLD) A detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual. HASL-300 (revised annually), Curie, L A. " Limits for Qualitative Detection and Qualitative Determination - Application to Radiochemistry", Anil. Chem. 40. 586-93 (1986), and Hartwell, J. K..
" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be 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 S 6 LLD = E x V x 2.22E6 x Y x exp(-AAt) Where: LLD = the "a priori" lower limit of detection (microCuries per unit mass or volume), S=b 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), t V= the sampic size (units of mass or volume), i 2.22E6 = the number of disintegrations per minute per microcurie, l Y= the fractional radiochemical yield, when applicable, !
- 1. = the radioactive decay constant for the particular radionuclide (sec-I), and At = the clapsed time between the midpoint of the sample collection period, and the time of counting (sec), for efIluent samples, or At = the clasped time between the end of the sample collection period, and the time of counting (sec), for environmental samples.
l Typical values of E, V, Y, and at should be used in the calculation. It should be recognized that the LLD is defined as a a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLD's will be ac!deved under ! routine conditions. l The definition of at applies only to the calculation of the LLD. A more rigorous treatment of the buildup i and decay during the sample collection and/or counting period (s) may be applied to actual sample analysis of desired. l ! l 15010329 47361469 Page1ofI ATTACHMENT 1
l APA-ZZ-01003 Rev.4 ATTACHNENT 2 , BASES FOR R ADIOLOGICAL EFFLUENT CONTROLS I NOTE The BASES presented below summarize the reasons for the specified Radiological Emuent l Control, but in accordance with 10 CFR 50.36 are not part of these controls. i i REC 9.1 Badioactive Liould Emuent Monitorine Instrumentation The radioactive liquid emuent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid emuents during actual or potential releases ofliquid emuents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the values of 10 CFR Part 20.120.60, Appendix B. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 of Appendix A l to 10 CFR Part 50. REC 9.2 Radioactive Gaseous Emuent Monitorine Instrumentation The radioactive gaseous emuent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous emuents during actual or potential releases off;aseous emuents. The Alarm /frip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,63, and 64 and Appendix j A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show j compliance with the gaseous emuent release requirements of REC 9.7.1.1 shall be such that concentrations as low as 1 x 10-6 Ci/cc are measurable. The Containment Purge Monitor (noble gas channel) closes the Containment Isolation Valves in the Mini Purge System and the Shutdown Purge System. This action isolates the Containment atmosphere from the environment to minimize releases of radioactivity in the event of an accident. The Mini Purge System is normally used during Reactor operation and the Shutdown Purge System will be in use with the Reactor shutdown. Each of the purge systems has inner and outer Containment Isolation Valves in its supply and exhaust ducts. A high radiation signal from either monitor initiates Containment Purge Isolation, which closes both inner and outer Containment Isolation Valves in the Mini Purge System and the Shutdown Purge System. The Containment Purge Isolation Radiation Monitoring Instrumentation isolates the Containment atmosphere from the environment to minimize releases of radioactivity in the event of an accident. l 15010329 47361470 l Page 1 of 8 ATTACHMENT 2 l
1 APA-ZZ-01003 Rev.4 1 ATTACHME?TT 2 B ASES FOR RADIOLOGICAL EFFLUEt(T COtfrROLS The safety analyses assume that the Containment remains intact with penetrations unnemury for core cooling isolated early in the event, and that the purge valves isolate 1 rapidly. The Containment purge isolation radiation monitors act as backup to the S1 signal to ensure closing of the purge valves. They are also the primary means for automatically isolating Containment in the event of a fuel handling accident during shutdown. Containment isolation in turn ensures meeting the Containment leakage rate assumptions of the safety analyses, and ensures that the calculated accidental offsite radiological doses are below 10 CFR 100.11 limits. The Containment Purge Isolation Functions are required OPERABLE in MODES 1, 2,3, and 4, and during CORE ALTERATIONS or movement ofirradiated fuel assemblies within Containment. Under these conditions, the potential exists for an accident that could release fission product radioactivity into Containment. Therefore, the Containment Purge Isolation instrumentation must be OPERABLE in these MODES. While in MODES 5 and 6 without fuel handling in progress, the Containment Purge Isolation Instrumentation need not be OPERABLE since the potential for radioactive releases is minimized and operator action is sufficient to ensure post accident offsite doses are maintained within the limits of 10 CFR 100.11. I FSAR Section 7.3.2 describes GT-RE-22 & 33 as redundant and independent monitors 2 which are designed to meet the Single Failure Criteria ofIEEE 279-1971. FS AR Table 7.3-4," Containment Purge Isolation System Failure Modes and Effects Analysis" l indicates that the effect of a downscale failure of the radiation monitor is that one channel remams operable. Consequently, both channels are required OPERABLE in order to meet the system operational design requirements. (Refer to SOS 94-1176) Tech Spec 3/4.9.9 requires that both channels be OPEPABLE during CORE ALTERATIONS; or movement ofirradiated fuel within the containment; otherwise, the purge valves must be closed. l l 1 1 1 1 1 3 ' Standard Technical Specifications Westinghouse Plants", NUREG-1431, U.S. Nuclear Regulatory l Commission, Office of Nuclear Reactor Regulation. September,1992. l DlI5f273i'!39ElEEB Stan3aEEriEril.for,.Pptqe, tion Systems for Nuclear Power Generating l Stationsi The Institute of Electrical and Electronics Engineers, Inc. April,1972. Page 2 of 8 ATTACHMENT 2 l I I
P APA-ZZ-01003 Rev.4 ATTACHMENT 2 4 B ASES FOR RADIOLOGICAL EFFLUENT CONTROLS REC 9.3 LIOUID EFFLUENTS CONCENTRATION This section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in Appendix B. Table II, Column 2 to 10 CFR 20.120.601. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in Internatio.ul Commission on Radiological Protection (ICRP) Publication 2. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLD's). 15010329 47361472 Page 3 of 8 ATTACHMENT 2
S APA-ZZ-0100'4 Rev.4 ATTACID4ENT 2 , BASES FOR PADIOLOGICAL EFFLUENT CONTROLS REC 9.4 Dose From Liould Emuents Tids section is provided to implement the requirements of Sections II.A and IV.A cf Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the - guides set forth in Section II.A of Appendix L The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid emuents to UNRESTRICTED AREAS will be kept "as low as is wonably achievable" Also, for fresh water sites with drinking water supplies that can be potendally affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix ! which specify that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid emuents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculations of Annual Doses to Man from Routine Releases of Reactor Efiluents with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic and Dispersion of Emuents from accidental and Routine Reactor Releases for the Purpose ofImplementing Appendix I", April 1977, REC 9.5 LIOUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid efflucuts will be kept "as low as is reasonably achievable". This section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the desi;;n objective given in Section II.D of Appendix ! to 10 CFR Pan
- 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section 11.A of Appendix 1,10 CFR Part 50, for liquid efIluents, i
l 1 l l l l 15010329 47361473 1 Page 4 of 8 ATTACHMENT 2
r APA-ZZ-01003 Rev.4 ATTACHMENT 2 , l BASES FOR RADIOLOGICAL EFFLUENT CONTROLS REC 9.6 GASEOUS EFFLUENTS DOSE RATE
- This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous efnuents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The dose rate limits are the doses associated with the concentrations of 10 CFR Part 20.1-20.601, Appendix B, Table :
II, Column 1. These limits provide reasonable assurance that radioactive material , discharged in gaseous efnuents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY. to annual average concentrations exceeding the dose limits specified in 10 CFR Part 20 10 CFR 20.1301. For hEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that hEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such hEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEhGER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the whole lady or to less than or equal to 3000 mrems/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation , pathway to less than or equal to 1500 mrems/ year. The required detection capabilities for radioactive materials in gaseous waste samples are , tabulated in terms of the lower limits of detection (LLD's). , REC 9.7 DOSE - NOBLE GASES This section is provided to implement the requirements of Sections II.B, Ill.A, and IV.A of Appendix I,10 CFR Part 50. The Limiting Conditions for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactive material in gaseous efnuents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix ! be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC ; through appropriate pathways in unlikely to be substantially underestimated. The dose ! calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases on Reactor EIDuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous EfDuents in Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the ] SITE BOUNDARY are based upon the historical average atmospheric conditions. I 15010329 47361474 l Page 5 of 8 ATTACHMENT 2
APA-ZZ-01003 j Rev.4
. A'ITACHAENT 2 BASES FOR RADIOLOGICAL EFFLUENT CONTROLS REC 9.8 DOSE -IODINE-131. & 133. TRITIUM. AND RADIOACTIVE MATERIAL IN PARTICULATE FORM This section is provided to implement the requirements of Sections ll.C, III.A, and IV.A of Appendix I,10 CFR Part 50. The Limiting Condidons for Operation are the giddes set forth in Section II.C of Appendix !. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous emuents to UNRESTRICTED AREAS will be kept "as low as reasonably achievable". The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section IILA of Appendix ! that conformance with the guides of Appendix I be shown by calculational procedures based on snodels and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Emuents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1 October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous EfDuent sin Routine Releases from Light-Water Cooled Reactors", Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine 131, and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in the areas at a4 beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition of radionuclides onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
REC 9.9 GASEOUS RADWASTE TREABENT SYSTEM The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gascous emuents require treatment prior to release to the environment. The requirenien't that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous i efIluents will be kept "as low as is reasonably achievable". This contml implements the l requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part
- 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.B and ILC ofAppendix I,10 CFR Part 50, for gaseous emuents.
i 15010329 47361475 l l Page 6 of 8 ATTACHMENT 2
i APA-ZZ-01003 Rev.4 A'ITACHMENT 2 BASES FOR RADIOLOGICAL EFFLUENT CONTROLS . REC 9.10 TOTAL DOSE This REC is provided to meet the dose limitations of 40 CFR Pan 190 that have been incorporated into 10 CFR Part 20.1301. The control requires the preparation and l submittal of a Special Repon whenever the calculated doses due to releases of radioactivity and the radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Pan 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and from outside storage tanks are kept small. The Special Repon will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Repon, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the , exception that dose contributions from other nuclear fuel cycle facilities at the same site or ; within a radius of 8 km must be considered. If the dose to any MEMBER OF THE , PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Pan 190 have not already been corrected), in accordance with the provisions of 40 CFR Pan 190.1i _ad 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only , relates to 40 CFR Pan 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in REC 9.3.1.1 and 9.6.1.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is pan of the nuc! car fuel cycle. REC. 9.11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this REC provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures i of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring l program implements Section IV.B.2 of Appendix I to 10 CFR Pan 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the l environmental exposure pathways. Guidance for this monitoring program is provided by j the Radiological Assessment Branch Technical Position on Environmental Monitoring, i Revision 1, November 1979. The initially specified monitoring program will be effective ; for at least the first 3 years of commercial operation. Following this period, program i changes may be initiated based on operational experience. The required detection capabilities for emironmental sample analyses are tabulated in terms of the lower limits of detection (LLD's). The LLD's required by Table 9.11-C are , 15010d5"d dDs"I'N *f"c',nment
? I measurements in industrial laboratones.
l l 4 Page 7 of 8 ATTACHMENT 2
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APA-ZZ-01003 Rev.4 ATTACHMENT 2 BASES FOR RADIOLOGICAL EFFLUENT CONTROLS REC 9.12 RADIOLOGICAL ENVIRONMENTAL MONITORING LAND USE CENSUS This REC is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. j Information that will provide the best results, such as door-to-door survey, aerial survey, or consulting with local agricultural authorities, shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the f i muumum required to produce the quantity (26 kg/ year) ofleafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden ; size, the following assumptions were made: (1) 20% of the garden was used for growing j i broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2. l REC 9.13 RADIOLOGICAL ENVIRONMENTAL MONITORING INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the j measurements of radioactive material in environmental sample matrices are performed as l part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purpose of Section IV.B.2 of Appendix ! to 10 CFR Part 50. 15010329 47361477 Page 8 of 8 ATfACHMENT 2
s-. . . APA-ZZ-01003. i Rev.4- l
\
i i i APPENDIX A 4 i
SUMMARY
REVIEW OF RADIOLOGICAL EFFLUENT , TECH SPECS POTENTIALLY AFFECTED BY TILE IMPLEMENTATION OF THE REVISED 10 CFR 20 ; i-i, i
.l 15010329 47361478 5
b Page1of16 APPENDIX A i t i
APA-ZZ-01003 Rev.4
SUMMARY
REVIEW OF RADIOLOGICAL EFFLUENT TECH SPECS POTENTIALLY AFFECTED BY THE IMPLEMENTATION OF THE , REVISED 10CFR20 The following is a summary review of the current Tech Specs that are potentially affected by the implementation of the revised 10CFR20. In general, the potential impact is due to changes in the E01uent Concentration Values (ECV's) in 10CFR20, Appendix B, Table 2, Columns 1 and 2 (formerly MPC's), and 10CFR20.1601. This summary is not intended to review those changes that may be necessary as a result of the eventualissuance of the Generic Letter. The NRR staff has stated that the current level of effluent controls is sufficient to protect the health and safety of the public, and further restdctions resulting from the revision to 3 Appendix B, Table 2, were unintentional. They are currently preparing a Generic Letter that will provide guidance for submitting Tech Spec changes that will return to the current level of control. This is currently anticipated during late 1993. Those who implement the revised rule pdor to January 1,1994, will have to do so under the requirements of , 10CFR20.1008, which basically requires that the more restrictive requirement (Tech Specs
, or 10CFR20) be implemented.
i DEFINITIONS OF RESTRICTED AREA & MEMBER OF THE PUBLIC, : AND TECH SPEC 5.1.2, SITE BOUNDARY FOR GASEOUS EFFLUENTS , The defmition of Restricted Area has not changed significantly from that in the former rule. The defmition of the Member of the Public in the revised mle is significantly i different from that in the Callaway Plant Technical Specifications (TS 1.17). There is no corresponding definition of Controlled Area in the former rule. . The Callaway Plant was licensed to operate with a Restricted Area as defined in the FSAR and shown on the figures in TS 5.1.4 and in the ODCM. Since the requirements have not been revised, there is no compelling reason to change the Callaway Plant Restricted Area from its current boundaries. In ad.fition, the NRC's backfit analysist, performed pursuant to 10 CFR 50.109, concludes that the revisions to 10CFR20 apply primarily to operational procedures and should cause no modifications in facility design. Since the plant siting and the location and size of the Restricted Area are considered to be a part of the facility design, it is clearly not the intent
- of the TC that revisions to 10CFR20 would require changes to the Restricted Area for l curretdy icensed facilities. -
I final,BaQ/mtvsisAr the,Revi@p.ory03FR2(1,." Standards for Protection Against Radiation'"', U$NRC,if!TceY$uTTc6RegTt atorf166arth.DIviston ofRegulatory Applications. August,1990. (Available USNRC Public Documents Review.) Page 2 of16 APPENDIX A , i
t APA-ZZ-01003 l Rev.4 f There is also no requirement for the existence of a Controlled Area as defined in the l revised rule ,2 therefore it is not necessary that one be created at Callaway. The definition of the Member of the Public is significantly different in the revised rule relative to that provided in TS 1.17 and in 40 CFR 190. The revised rule defines the Member of the Public as anyone who is not in the Restricted Area. The Tech Specs and l 40 CFR 190 generally define the Member of the Public as anyone who is not occupationally associated with plant operations, and also recognizes that the Member of the Public may, at times, be within the Restricted Area. The major difference is that pursuant to the revised rule, the Member of the Public receives dose against the occupational dose limits of 10 CFR 20.1201 once inside the Restricted Area, but the Tech Spec definition would limit the dose within the Restricted Area to the limits of 10 CFR 20.1301. Since the limit provided in 20.1301 is much lower than that of 20.1201, the continued use of the mere restrictive 40 CFR 190 and Tech Spec 1.17 definitions for the Member of the Public is appropriate and is reauired pursuant to 10 CFR 20.1008(c). A more thorough and detailed analysis of the definitions of the Member of the Public ' found in 10 CFR 20,40 CFR 190. and Tech Spec 1.17, focusing on the applicability of Occupational Vs. Non-occupational dose limits, indicates a confusing and inconsistent array of defmitions and dose limit applicability. For conservatism and simplicity, Union Electric has deSned occupational dose as dose received while working with or around radioactive materials. This definition is more restrictive than the definition in 10 CFR 20 in that the more restrictive dose limits of 10 CFR 20.1301 are applied to Members of the Public within the Restricted Area, instead of the less restrictive limits of 10 CFR 20.1201. It is more restrictive than the Tech Spec definition in that delivery persons, service technicians, and others who may enter the site to perform non-radiological work activities are also limited to the more restrictive dose limits of10 CFR 20.1301. There are no changes recommended for those definitions and maps relative to the Restricted Area, Site Boundary, and dose to the Member of the Public. TECII SPEC 6.8.4.F.2, LIQUID EFFLUENT RELEASE RATE LIMITS (REC 9.3) On December 1,1992, Union Electric Co. provided notification3 ofintent to implement the revised 10 CFR 20, Parts 20.1001- 20.2401 and associated appendices, pursuant to 10 CFR 20.1008(a). The revised rule was fully implemented on January 1,1993. The following provides clarification with respect to compliance to 10 CFR 20.1001- 20.2401 and Callaway Plant Technical Specifications 6.8.4.f(2) and 6.8.4.f(7). 2Rf3 p,,py,egy;;2{ag y 7.g;g y 4 g g 3 UI.NRC 92-2729, D. F. Schnell to A. Bert Davis, dated December 1,1992. Page 3 of16 APPENDIX A
APA-ZZ-01003 Rev.4 l
)
Union Electric implemented the use of the revised Appendix B, Table 2 values concurrent with the implementation of the revised rule. Technical Specification 6.8.4.f(2) requires that the concentration of radioactive material in liquid discharges not exceed the values of 10 CFR 20, Appendix B, Table II, Column 2. The NRC had indicated via the revision to 10 CFR 50.72 that the concentration values have nominally decreased by a factor of 10, and the NRC staff had stated on numerous occasions that they considered the values in the revised mie to be more restrictive than the those in the old rule. This was frequently referred to as an " implicit" change to the Technical Specifications. 10 CFR 20.1008 (a) requires that if the revised rule is implemented prior to January 1, 1994, then "the licensee shall implement all provisions of these sections,.... and shall provide written notificati'on... . that the licensee is adopting early implementation (of the revised rule) and associated appendices." 10 CFR 20.1008 (b) requires that once implemented, "the applicable section of(the revised mie) shall be used in lieu of any section (of the old rule) th'at is cited in license conditions or technical specifications." It further states, "if the requirements of(the revised rule) are more restrictive than the existing license condition, then the licensee shall comply with (the revised rule). Additionally, the NRC had clarified the applicability of the revised Appendix B values to the Technical SpeciScation instantaneous release rate limits via their formal response to three separate licensee questions. Question # 18 states 4 that the Tech Spec instantaneous release rate limit is based on the old Part 20 concentrations, and asks if changes are . required in the Tech Specs and ODCM as a result of the revised rule. The NRC replies " l the instantaneous release rates for liquid effluents, to the extent that they directly reference Appendix B concentration values, will need to be changed. The corresponding bases and certain alarm set- points will have to be changed by license amendment." Question # 23 asks 5 if computer data bases that use the old Appendix B values must be revised to the use the new values. The NRC simply answers, "Yes" l 4 Letter, F. J. Cc,jel (USNRC) to J. F. Schmitt (NUMARC), dated December 9.1991. page 16 of Enclosure 1. 3 bi ek bnbhe1.473b'1Ob1 Page 4 of16 APPENDIX A
APA-ZZ-01003 Rev.4 Question # 22 states 6that many alarm set-points are based on 10 CFR 20 Appendix B concentrations, and asks if they will have to be changed. The NRC answers that the alarm - set-points ofliquid efDuent monitors are likely to require change, since they are based on 10 CFR 20 Appendix B concentrations, as required by Tech Specs. Because Appendix B concentration values differ for many radio nuclides between the old and new versions of Part 20, these set points may have to be changed. This is analogous to a restriction in flow rate, and the NRC cites the reduction in Appendix B concentrations as the root cause of the change. Based on the preceding information, Union Electric implemented the use of the revised Appendix B values concurrent with the implementation of the revised rule on January 1, 1993. Because there were no values in the revised Appendix B for dissolved and entrained noble gases in liquid efDuents, the old value of 2E-4 uCi/ml was used pending regulatory guidance. The Callaway Plant Technical Specifications contain, in Section 6.8.4.f, several specifications which provide appropriate limits on the maximum quarterly and annual whole body and organ dose to the Member of the Public from the discharge ofliquid and gaseous radioactive efDuents. Compliance with these specifications demonstrates compliance with the limits of 10 CFR 50, Appendix I, and 40 CFR 190 and, as stated in the supplementalinformation to the revised rule7, demonstrates compliance with the 100 mrem /yr dose limit of 10 CFR 20.1301. However, compliance with the dose rate limits of Specifications 6.8.4.f items (2) and (7) with respect to the implementation of the revised rule is less clear, as there is no longer a regulatory basis for these Specifications. These Specifications formerly implemented the requirements of 10 CFR 20.106, which provided annual average concentration limits on liquid and gaseous efDuents, and specifically referenced the limits of Appendix B, Table II, Columns 1 and 2. i 6 USNRC Memorandum, F. J. Conjet to V. L Miller, et al, dated April 17,1992. page 13 of Enclosure 1. 7 PedekbrM.$, NoN$k!NfTih91. pages 23360-23474. Page 5 of16 APPENDIX A i
e 5 t-APA-ZZ-01003 Rev.4 Unlike the former rule, the values in the revised Appendix B, Table 2, Columns 1 and 2 do not of themselves constitute a limit on the release rate of radioactive effluents, but rather, as discussed in 10 CFR 20.1302 (b)(2)(i), merely provide one means of demonstrating compliance with the annual dose limit of 10 CFR 20.1301. Since there is no release rate limit provided in the rev: sed mie, the subject Specifications are therefore license conditions. 10 CFR 20.1008 (c) requires that any existing license condition that is more restrictive than the revised rule remain in force until there is a technical spcification change. Additionally, since the values in the revised Appendix B, Table 2 are not limits as was the case with 20.106, there is no corresponding provision in the new rule to 20.106. 10 CFR 20.1008(e) requires that is a license condition cites a provision in the old mie for which there is no corresponding provision in the new mle, then the license condition remains in force until there is a technical specification change. The values of Appendix B, Table 2, Columns 1 and 2 of the revised mle did not change in a uniform fashion, i.e., certain nuclides numerically decreased in value whereas others numerically increased in value. Furthermore, the values did not change by a consistent amount, varying by as much as a factor of 20 with respect to the corresponding nuclide in the former rule. This inconsistency is clearly evident for those nuclides which are commonly associated with nuclear power plant effluents. In addition, the bases for the revised values is the dosimetry system ofICRP 26 8 and ICRP 30 8. This is inconsistent with the bases for the dose limits of 10 CFR 50, Appendix I and 40 CFR 190, and the dose calculational methodologies of Regulatory Guide 1.109, which are largely based on the dosimetry system ofICRP 210 8 International Commission on Radiation Protection, Publication 26, " Recommendations of the International Commission on Radiation Protection" , Annals cf the ICRP, Volume 1, No. 2,1977.
' Intemational Commission on Radiation Protection, Publication 30, " Limits for Intakes of Radionuclides by Workers", Annals of the ICRP, Volume 2, No. 3/4,1979.
Ibn rhtibhbbhon obd it!hNroNtid, Publication 2, " Report of Committee 11 on Permissible Dose for Internal Radiation",1960. Page 6 of16 APPENDIX A
l APA-ZZ-01003 Rev.4 ,~ Since the values of the revised Appendix B, Table 2, Columns 1 and 2 did not uniformly l increase or decrease in value, it is not possible to determine whether Appendix B, Table II 1 of the former rule or Appendix B, Table 2 of the revised rule provides, in toto, the more l conservative values for implementation of the subject license conditions. It is clear, l however, that the bases for the revised Appendix B, Table 2 values are inconsistent with ; the bases of 10 CFR 50, Appendix I and 40 CFR 190, and Regulatory Guide 1.109. Furthermore, the operational history of the Callaway Plant demonstrates that the use of the 10 CFR 20.1- 20.601, Appendix B, Table II values is appropriate to maintain compliance with the requirements of 10 CFR 50, Appendix I and 40 CFR 190, which, in turn, demonstrates compliance with the 100 mrem /yr dose limit of 10 CFR 20.1301. The concentration limits of the old Appendix B, Table II were based on a dose of 500 mrem /yr, which, when expressed as a dose rate, is equal to .057 mrem /hr. , Compliance with the requirements of Technical Specifications 6.4.8.f(2) and (7) using 10CFR 20.106, Appendix B, Table II values is conservative with respect to the 2 mrem /hr limit of 10CFR20.1301(a)(2). Additionally, Technical Specifications 6.4.8.f(2) and (7) speci5cally require the use of Appendix B, Table II to 10CFR20.1- 20.601, since there is no corresponding provision in the revised rule. Thus,10 CFR 20.1008 (c) and (e) require the continued use of the values provided in Appendix B, Table II to 10 CFR 20.1 20.601 for the implementation ofTechnical Specifications 6.8.4.f, items (2) and (7). Although the 2 mrem /hr limit of 10 CFR 20.1301(a)(2) was referenced in the preceding discussion, it is important to note that the regulation specifically states that this limit is applicable to external sources. Since, for the Callaway Plant, the only dose pathway to man from the discharge ofliquid radioactive emuent is through the consumption of fish, there are no external dose pathways, and therefore the requirements of 10 CFR 20.1301(a)(2) are satisfied apriori. Union Electric re instituted the use of the values in Appendix B, Table II, Columns 1 and 2, to 10 CFR 20.1- 20.601 for Technical Specifications 6.8.4.f, items (2) and (7) pursuant to the requirements of 10 CFR 20.1008(c) and (e), on May 4,1993. This position was affirmed by the USNRC on June 30,199311 EFFLUENT CONCENTRATION VALUE FOR GROSS ALPilA IN LIQtRD EFFLUENTS There are two values in the revisei Appendix B for unknown mixtures in liquid efIluents: ' 2E-9 and IE-6 uCi/ml. The less restrictive value is appropriate ifit is known that certain nuclides are "not present". The appropriate value for gross alpha in liquid effluents at the Callaway Plant from Appendix B, Table 2, Column 2 is IE-6 uCi/ml. I ebob.hibey, E!ikt Kk-lfS 5No Thomas E. Tipton, NUMARC, dated June 30,1993. Page 7 of16 APPENDIX A
APA-ZZ-01003 Rev.4 The value of IE-6 uci/ml in Appendix B, Table 2, Column 2 only applies to an unknown mixture of nuclides where those listed opposite the value are known to be "not present". These nuclides are Fe-60, Sr-90, Cd-l13m, Cd-l13, In-115, I-129, Cs-134, Sm-147, Gd-148, Gd-152, Hg-194 (organic), Bi-210m, Ra-223, Ra-224, Ra-225, Ac-225, Th-228, Th-230, U-233, U-234, U-235, U-236, U-238, U-nat., Cm-242, Cf-248, Es-254, Fm-257, and Md-258. The other nuclides listed in the immediately preceding values for unknown mixtures in gaseous emuents do not apply, since they specifically apply to gaseous eEuents as indicated by the designation of applicable lung clearance classifications for each of the nuclides listed. The NRC's response to Question # 71 reiterates that ingestion ALI's do not have lung clearance classifications, which is also consistent with ICRP 30 and all other industry standards. Additionally, several of those listed in the list for liquid efDuents also appear in the list of nuclides given for airborne activity, which indicates that only those specifically listed with the liquid emuent value apply. Of those nuclides listed for unknown mixtures in liquid efDuents. only Ra-224, Th-228, U-234, U-235, U-236, U-238, and Cm-242 are LWR produced alpha emitting nuclides. Sr-90, Cd-ll3m, I-129, and Cs-134 are also LWR produced, but are beta or beta / gamma emitters, and are not determined via a gross alpha analysis. The remainder of the nuclides in the list are not LWR produced. The phrase "not present" is not defined in the revised 10 CFR 20, however there is a large body ofinformation which can be applied to determine the meaning of"not present". The former rule, in footnote 5 to Appendix B, stated that a nuclide may be considered to be "not present" ifit constitutes less than 10% of the total activity, provided that the aggregate of all such "not present" nuclides does not exceed 25% of the total activity. l The use of the " ten percent mie" is consistent with the basis of the revised rule, the NRC's response to questions regarding the meaning of"not present", and the cunent ICRP guidance as shown below:
- a. The revised mle is based on the dosimetry and methodology of]CRP 3012, which in paragraph 3.1.3, describes the use of the cunent ten percent rule.
- b. The NRC's response to Question # 14613 clearly indicates that the ten-percent rule is applicable to Appendix B.
l l
/
l 12I CRP Publication 30, " Limits for Intakes of Radionuclides by Workers", in Annals of the ICRP, Volume 2, Number 3/4,1979. 13 Letter, Frank J. Congel, Director, DRPEP, USNRC, to John F. Schmidt, NUMARC, dated September 14,1992 (co.mmonly referred to as the 4th set of Q&A) ! 15010329 47361485 Page 8 of 16 APPENDIX A
APA-ZZ-01003 Rev.4
- c. The current ICRP recommendations on the release ofradioactive materials to the environment14, and the updated recommendations 15t o ICRP 30 continue to propagate the ten-percent rule, and apply it to offsite dose as well as dose to radiation workers.
It is therefore clear that the ten-percent mle continues to apply to the values in Appendix B of the revised mle. Callaway Plant liquid efIluents have been analyzed for transuranic nuclides (TRU) on two separate occasions, during the second and third quarters of 1987. In each instance, TRU nuclides were not detectable, with an MDA of IE-8, uCi/ml, which is a factor of 10 below the gross alpha LLD of IE-7 uCi/ml. The concentration of the TRU nuclides can be inferred through the use of a tracer nuclide, l such as Ce-144. Ce-144 is particularly well suited for this purpose in that it is a fission product, can be measured by gamma ray spectroscopy, and is chemically similar to the TRU nuclides. Based on published ORIGEN code calculations!6 of a representative LWR, and assuming a 90 day decay, the ratio of the nuclides ofinterest to Ce-144 is: Ra-224/Ce-144 1.45E-9 Th-228/Ce-144 1.45E-9 U-234/Ce-144 1.14E-6 U-235/Ce-144 1.75E-8 U-236/Ce-144 2.58E-7 U-238/Ce-144 3.24E-7 Cm-242/Ce-144 2.66E-2 Vollique, et al 17, found the Cm-242/Ce-144 ratio to be 6.5E-3, which is consistent with the above value. Based on the above, it can be seen that Cm-242 is the only nuclide with a significant Ce-144 ratio. 14 ICRP Publication 56, " Age-dependent doses to Members of the Public from the Intake of Radionuclides: Pan 1", Annals of the ICRP, Volume 20, Number 2,1989. 15 ICRP Publication 61, " Annual Limits on Intake of Radionuclides by Workers Based on the 1990 Recommendations", Annals of the ICRP, volume 21, Number 4,1991. 35 Licht Water Reactor Nuclear Fuel Ovele. Wymer, Raymond G. and Vondra, Benedict L., editors, Table 6, pages 70- 71 and Table 7, page 72. CRC Press,1981. 17 13ouiqug G c;,al "Sokbility_pf,Jransuranic g Nuclides in Aerosols in Two Ginna Steam Generator
% or ~Nnur0Etn6 tits".-Procec~dfiigs%fThebtienTyfrst Midyear Topical Meeting of the Health Physics Society, Pages 251260. 1987.
Page 9 of 16 APPENDIX A
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APA-ZZ-01003 Rev. 4 Based on the data contained in the Semiannual Emuent Release Reports for the period ' January,1989- July,1992, Ce 144 accounted for less than 0.3% of the total fission and activation product activity in liquid emuents, and less than SE-6% of the total activity discharged in liquid emuents during the same period. Therefore, the maximum activity that could have been discharged of each of the above listed nuclides is much less than 10%. Accordingly, these nuclides are "not present" , TECH SPEC 6.8.4.F.4, DOSE FROM LIQUID EFFLUENTS (REC 9.4), & TECH SPEC 6.8.4.F.5, LIQUID RADWASTE TREATMENT SYSTEM (REC 9.5) These specifications are derived from 10CFR50, Appendix I, and are not affected by the revisM rule. Doses are calculated in accordance with Regulatory Guide 1.109 which has not been revised. No changes are anticipated for these specifications. TECH SPEC 3.11.1.4, CURIE CONTENT OF OUTDOOR LIQUID , STORAGE TANKS 1 The purpose of this specification is to limit the activity in the nearest receiving waters, excluding tritium and entrained noble gases, to the concentrations in 10CFR20, ! Appendix B, Table 2, Column 2. The effect of accidental contamination of the nearest ground water discharge locations due to accidental rupture of tanks containing radioactive liquids was performed as detailed in FSAP. Section 2.4.13.3. It was assumed that the liquid contents of a ruptured tank would immediately merge with the ground water 5 feet below plant grade and travel directly from the tank to the nearest down-gradient well (Well 23). The results of the calculation show that, with the exception of H-3 and Sr-90, the radio nuclide concentrations found in ground water after a tank rupture will be below the original 10CFR20, Appendix B, Table II, Column 2 values by the time the contaminated ground water reaches the nearest stream tributaries. The dilution capability of the streams is su5cient to reduce the concentration of H-3 and Sr-90 below the original Appendix B values. All computed concentrations at Well 23 were below the Appendix B limits for unrestricted areas. 15010329 473s1487 Page 10 of16 APPENDIX A
\
APA-ZZ-01003 Rev.4 Tables I and II list the curie contents of the primary spent resin storage tank and refueling water storage tank used in the FSAR calculations. These values were adjusted to reflect a total tank curie content of 150 Curies, the limit identified in Tech Spec 3.11.1.4. (Even though the spent resin storage tank is not an outdoor tank, the data was used for this calculation since it is expected to have the highest curie contents for Sr-90, Cs-137 and Co-60 and the postulated accident assumes that allliquid released immediately merges with the ground water.) The resultant peak concentrations at the discharge point at Logan , Creek were calculated using the normalized values then compared to the revised ' Appendix B efDuent concentration values (ECV). All calculated concentrations at the discharge point were less than the applicable ECV. Based on the above calculation, the existing Tech Spec limit of 150 Curies is conservative in comparison to the revised 10CFR20, Appendix B values and is therefore still applicable. 15010329 47361488 Page11 of16 APPENDIX A ; I l
APA-ZZ-01003 Rev.4 TABLEI l: A. Curie Content ofRadionuclides in the Primary Spent Resin Storage Tank i NUCLIDE Ci' (in tank) Ci (normalized to 150 C1, i total) Mn-54 2.91E+01 8.17E-01 Co-58 6.10E+02 1.71E+01 i Co-60 2.56E+02 7.19E+00 l Sr-89 9.80E+00 2.75E-01 Sr-90 1.35E+00 3.79E-02 Nb-95 3.00E+00 8.42E-02 I Zr-95 2.12E+00 5.95E-02 I-131 1.17E+03 3.28E+01 Cs-134 1.78E+03 5.00E+01 ! C3-137 1.48EK)3 4.15E+01 i Ba-140 1.63E+00 4.58E-02 ; TOTAL 5.343E+03 149.91
- Values are from FSAR Table 2.4-28.
B. Peak Concentrations of Radionuclides at the Logan Creek Discharge Point l NUCLIDE pCi/ml* pCi/ml(baseo ECV %ECV l (original cale) on 150 Ci ! total) [ Mn-54 3.1E-22 8.7E-24 3E-05 3E-17% f Co-60 3,6E-23 1.0E-24 3E-06 3E-20% l Sr-90 1.2E-05 3.4E-07 5E-07 67.4 % ; Cs-137 5.5E-06 1.5E-07 IE-06 15.4 % -l
' ' Values are from FSAR fable 2.4-30. l l
1 i 15010329 47361489 l l
- Page 12 of16 APPENDIX A !
i
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l APA-ZZ-01003 Rev.4 TABLE II- ! A. Curie Content ofRadionuclides in Refueling Water Storage Tank - NUCLIDE Cia (in tank) Ci (normalized to 150 Ci,- l total) l Mn-54 6.99E-06 2.19E-02 .! Co-58 3.36E-04 1.05E+00 l Co-60 4.58E-05 1.43E-01 I Sr-89 5.92E-05 1.85E-01 '[ Sr-90 1.92E-06 6.02E-03 ; Nb-95 1.31E-06 4.10E-03 Zr-95 1.2512-06 3.92E-03 l I-131
~
2.34E-02 7.33E+01 Cs-134 1.39E-02 4.35E+01 Cs-137 1.01E-02 3.16E+01 Ba-140 2.56E-05 8.02E-02 ; i TOTAL 4.788E-02 149.9 !
' Values are from FSAR Table 2.4-28.
B Peak Concentrations of Radionuclides at Logan Creek Discharge Point i NUCLIDE Ci'ml* pCi/ml (based ECV %ECV_ l (original calc) on 150 Ci ! total) ! Co-60 1.1E-30 3.4E-27 iE 06 1E-19% Sr-90 2.5E-13 7.8E-10 SE-07 0.16 % : Cs-137 8.4E-13 2.6E-09 IE-06 0.26% l
- Values are from FSAR Table 2.4-30. ;
1 1 i 15010329 473614Eso Page 13 of16 APPENDIX A ! l v - < -- .m n - . . . - - - .-- ,,- .
- APA-ZZ-01003 Rev.4 TECH SPEC 6.8.4.F.7, DOSE RATE LIMIT FOR GASEOUS EFFLUENTS (REC 9.6)
This specification provides a gaseous effluent dose rate limit conforming to the ECVs in 10CFR20, Appendix B, Table 2, Column 1. For the nuclides ofinterest to Callaway, the revised ECVs are numerically greater, therefore the current REC is more restrictive than the dose rates conforming to the revised Appendix B values.10CFR20.1008 requires the implementation of the more restrictive of the requirements of 10CFR20, technical specifications, or any special license conditions. The current REC represents the more restrictive requirement and will be implemented without revision. The former rule, in 20.106(a), limited the amount of radioactivity released in effluents to the concentrations specified in Appendix B, Table 2, averaged over a period of one year. Although not specified as a limit, this corresponded to an annual whole body dose limit of 500 mrem to the Member of the Public. The former rule did not specify a dose rate limit. The revised rule, in 20.1301, specifies two limits on radioactivity in effluents: An annual l dose limit of 100 mrem, TEDE (20.1301(a)(1)) and a dose rate limit of 2 mrem /h l TEDE (20.1301(a)(2)). Note that the revised rule does not specify limits on concentration l as did the former mie but does allow licensees to utilize the concentration values in i Appendix B, Table 2 to demonstrate compliance with the limits of 20.1301 (20.1302(b)(2)). Note that 20.1302(b)(2)(i) describes these as " annual average l concentrations" as opposed to instantaneous limits. Measurements and calculation means l nre also allowed (20.1302(b)(1)). Radiological Efiluent Control (REC) 9.6 is required by Technical Specification 6.8.4.f.7 to contain:
" Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10CFR20, Appendix B, Table 2, Column 1."
The bases for this Control state that its purpose is to ensure that the dose at any time from gaseous effluents is within the annual dose limit of 10CFR20, which is the dose associated with the concentrations of 10CFR20, Appendix E .ble 2, Column 1. Additionally, this Control provides assurance that the release of gaseous efiluents will not result in the exposure of a Member of the Public to annual average concentrations in excess of the values of 10CFR20, Appendix B, Table 2, Column 1. Note that in each case, the bases references an annual dose limit but makes no reference to a dose rate limit. , The REC establishes a release rate limit of 500 mrem /y that is equal to approximately 0.06 mrem /h, well below the dose rate limit of 2 mrem /h specified in 20.1301(a)(2), and is therefore more restrictive. 15010329 47361491 Page 14 of 16 APPENDIX A
APA-ZZ-01003 Rev.4 The preamble to the revised rule states that demonstration of compliance with the limits of 40CFR190 and with 10CFR50, Appendix Iis sufficient to demonstrate compliance with the 100 mrem dose limit of 20.1301(a)(1). Other Controls are provided as required Technical Specification 6.8.4.f(items 8,9, and 10) which ensure that the limits of 40CFR190 and 10CFR50, Appendix I are not exceeded. The Bases for this Control reference the concentration values of 10CFR20, Appendix B, Table 2, Column I as a basis for the specified dose rate limits. These values were derived using ICRP 30 calculation methodology and the dose and dose rate values they represent are the Total Effective Dose Equivalent (TEDE) which is the summation of the external and internal dose components. Compliance with the Control is demonstrated through calculation methodologies and parameters as established in Regulatory Guide 1.109 and NUREG 0133, which are based on the ICRP 2 maximum organ methodology, and thus I cannot be used to calculate efDuent doses and dose rates that correspond to the concentration values specified in the revised 10CFR20, Appendix B, Table 2, Column 1. The table below compares the numerical value of the former and revised Appendix B l values for those nuclides most commonly reported in the Callaway Plant's gaseous efDuents: 10CFR20 APPENDIX B CONCENTRATION VALUES Nuclide Former Rule Revised Rule New/Old Kr-85 3E-7 pCi/mi 7E-7 Ci/ml 2.3 Xe-133 3E-7 SE-7 1.7 Xe-135 IE-7 7E-8 0.7 I-131 lE-10 2E-10 2.0 I-133 4E-10 1E-9 2.5 Co-58 2E-9 IE-9 0.5 Co-60 3E-10 SE-11 0.2 Of these, Xe-133 accounts for greater than 90% of the total activity celeased from the Callaway Plant in gaseous efDuents for the past three years (1989-1991). The concentration value for Xe-133 actually increased in the revise rule, as did that for Kr-85 and boti iodine nuclides. Although the Co-58 and Co-60 values did decrease in the revised rule, they are relatively insignificant contributors to the whole body and organ dose from gaseous effluents discharged from the Callaway Plant as summarized below. 15010329 4 73E.14'Ei2 Page 15 of16 APPENDIX A
l APA-ZZ-01003 I Rev.4 l GASEOUS EFFLUENT ACTIVITY PROFILE 1989 - 1991 , Fraction ofTotal Ratio of Appendix B [ Nuclide Activity Released Concentration Values l t Noble Gases: Xe-133 0.92 1.7 i Xe-135 0.04 0.7 . Xe-133m 0.01 2.0 Kr-85m 0.01 1.0 Kr-85 0.01 2.3 Particulates and Iodines: i I-131 0.72 2.0 I-133 0.11 2.5 Co-58 0.03 0.5 Co-60 0.14 0.2 The NRC states, in their response to Question 19, that until 10CFR50, Appendix I is ! changed, licensees must continue to show compliance with Tech Specs in terms of organ , and whole body doses as per Regulatory Guide 1.109. The response to Question 21 states ;' that Regulatory Guide 1.109 will not be revised at this time, thus Regulatory Guide 1.109 methodology continues to be utilized to show compliance with Tech Specs. Since the , dose calculation methodology has not been revised, it would be more conservative to l continue to utilize the current REC values vice dose rate limits calculated from the revised 10CFR20, Appendix B values. Refer to the discussion of T/S 6.8.4.f.2 (REC 9.3) for additional details. . 1 TECH SPEC 6.8.4.F.6, GASEOUS RADWASTE TREATMENT SYSTEM OPERABILITY (REC 9.9) TECH SPEC 6.8.4.F.8, DOSE FROM NOBLE GASES (REC 9.7) ' TECH SPEC 6.8.4.F.9, DOSE FROMIODINES AND PARTICULATES IN GASEOUS EFFLUENTS (REC 9.8) TECH SPEC 6.8.4.F.10, TOTAL DOSE FROM THE URANIUM FUEL l CYCLE (REC 9.10) These specifications are derived from 10CFR50, Appendix I and 40CFR190 and are not ' affected by the revised rule. Doses continue to be calculated in accordance with , Regulatory Guide 1.109 which has not been revised. No changes are anticipated for these i specifications. 15010329 47361493
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Page 16 of16 APPENDIX A l l .}}