ML18033A919
| ML18033A919 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1989 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18033A913 | List: |
| References | |
| PROC-890630, NUDOCS 8909050485 | |
| Download: ML18033A919 (160) | |
Text
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT CHANGES TO THE BFN OFFSITE DOSE CALCULATION MANNUAL JANUARY THROUGH JUNE 1989
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Title; Handling of Changes to. the BFN Offsite Dose RARC OP 9 Calculation Manual Revision 1 Page 4 of 4 TVANUCLEAR Appendix 1 BFN ODCM Change Description Form Description of change '
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Justification for change:
I P~ 7 ~7 W (~W Analysis of effect of change on dose calculations, projections, or setpoint calculations:
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RARC Review: Date: I5 RC C i an 0357p/DNS01
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Handling of Changes to the BFN Offsite Dose RARC OP 9 Ca 1 cul ati on Hanual Revi sion 0 Page 4 of 4 Appendix 1 8FN ODCH Change Description Form Description of change:
I. l on Pages affected ~ ~ P Justification for change: Q 1$ u Analysis of effect of change on dose calculations, pro)ections, or setpoint calculations:
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RARC Review: Date: l5 95 C C i man 0678o/COC4
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QN Handling of Changes to the BFN Offsite Dose RARC QP 9 Calculation Manual Revision 0 Page 4 of 4 Appendi x 1 BFN ODCM Change Description Form Description of change: Ma 4. )A i h~ . 4 a o
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RARC Review: Date: Z 1S g R RC irman 0678o/CGC4
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Handling of Changes to the SFH Offsite Dose RARC OP 9 Calculation Manual Revision 0 Page 4 of 4 Appendix 1 BFH QOCM Change Description Form Oescription of change:
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RARC Review: Date: z I 5 RC C i man 0678o/COC4
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UNITED STATES GOVERNi~lENT Memorandum TENNESSEE VALLEY AUTHORITY 0 F. W. Reimann,'hief, Water and Waste Processing, IBH 1N 52A-C FROalf E. Ely Driver, Manager, Engineering Laboratory, ENG LAB-N DATE - October 17, 1988
SUBJECT:
VERIPICATION OF DILUTION FACTOR POR BROWNS PERRY NUCLEAR PLANT (BFN)
This memo is in response to your memo of September 29, 1988, concerning the dilution value provided by the Engineering Laboratory for release of radiological effluents from the subject plant.
A dilution factor of 5 was provided in 1979 as a conservative value to be used in calculations. Pield studies and model results (Reference 1) have indicated the dilution factor range at BPN varies from 4 to ll. Rote that a dilution factor of 4 does not mean 1/4 (or 25 percent) of the river flow
.is available for mixing with the diffuser effluent. The dilution factor is the ratio of diffuser flow to the fraction of river flow available for mixing (entrained river flow).
The fraction of river flow available for mixing is a function of river flow, ambient river temperature, diffuser discharge temperature, diffuser flow, and the number of diffusers in operation. The smallest fraction of river flow avaiiahle for mixing occurs during high river flows and.sincnle di fuser operation. Therefore, a conservative value can be obtained using a high mont ly average river flow of 70,000 cfs and a single diffuser discharge. Under these conditions, analysis shows that the fraction of river flow available for mixing is 30 percent. This translates to a value of 0.3 for variable d in equation 2.5, Section 2.3.2.1 of the RETS Manual.
Please feel free to call walter Harper ( 1882-K) should you have any questions or require additional information.
Reference 1: Almquist, C. W., C. D. Ungate, and W. R. Waldrop, 'Pield and Model Results for Multiport Diffuser Plume,'resented at the American Society of Civil Engineers Hydraulic Division Specialty Conference on Verification of Mathematical and Physical Models in Hydraulic Engineering, College Park, Maryland, August 9-11, 1978.
Reference 2: Stolzenbach, K. D., 'Estimation of Water Temperature Increases in Wheeler Reservoir Caused >y- the Discha rge": o f Heater Water from Browns Perry Nuclear plant Duri'ng Open Cycle Operation,'emo to TVA Engineering Laboratory, Pebruary 1975.
WLH:TSH cc: Vahid Alavian, ENG LAB-N Piles, ENG LAB, 335 EB-K I ~j.
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Handling of Changes to the BFN Offsite Dose RARC QP 9 Calculation Manual Revision 0 Page 4 of 4 Appendix 1 8FN ODCM Change Description Form Description of change:
Pages affected:
lustification for change:
Analysis of effect of change on dose calculations, pro]ections, or setpoint calculations:
At@eh marked-up pages from the current revision of the SQH OOCM which show the change.
RARC Review: Date: < IS RC C an 0678o/COC4
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Title. Handling of Changes to the BFN Offsite Dose RARC OP 9-Calculation Manual Revision 0 Page 4 of 4 Appendix 1 BFN ODCM Change Description Form Description of change:~~b4~ c W<, .
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Analysis of effect of change on dose calculations, pro)ectians, or setpoint calculations: /
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RARC Review: Date: I~
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Handling of Changes to the BFN Offsi te RARC QP 9 Hanual Dose'alculati,on Revision 0 Page 4 of 4 Appendix 1 BFN ODCM Change Description Form Description of change: li ix S r 5'o-m.i4 Pages affected: . %'t: 8 "I Justification for change: )4am Lc~s i l
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Analysis of effect of change on dose calculations, pro)ections, or setpoint calculations:
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RARC Revi ew: Date: ls RC irman 0678o/COC4
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Changes to QWATA e General Changes in Methodology and Data
- 1. Two age groups were added, teen and infant.
- 2. Two organs were added, kidney and lung. Skin dose is only calculated for recreation pathway.
- 3. Shoreline recreation dose is the only dose considered in the recreation pathway. In-water and above-water pathways were deleted from the recreation pathway dose based on the determination that they contributed less than one percent each to the total recreation dose.
4 . Dose factors are from R.G. 1.109 if possible. For those nuclides which are considered but not listed in R.G. 1.109, Kocher is used as the reference for external dose (recreation ) and NUREG 0172 is used for ingestion pathways.
- 5. If dose fact'ors for specific organs were not listed for a nuclide that is in R.'G. 1;109 the dose factors were considered zero. For recreation pathway, dose factors for all organs except skin were set equal to the total body dose factor for each nuclide.
- 6. Daughter ingrowth is not considered in the new code. However, the isotopes are decayed.
- 7. Travel times and average flow past the site are no longer calculated but are part of the input data.
- 8. Sixty-three nuclides were deleted <e.g. natural decay chains and transuranics ) while the following four were added: Zn-69m, Br-82, Tc-101, Sb-125.
This decreases 'the concentration in the first reach considered for each plant which in turn lowers the dose calculated for that reach.
- 10. Acres per reach changed to reflect memo from D.L. stone on April 26, 1988.
- 11. Kocher was used as the reference for all half-lifes which are consistent to 2 decimal places.
- 12. All files were updated to reflect the most recent data available.
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Changes Which Affect Population Dose Calculations Only 1.~ Total fish harvest" in pounds per reach were changed from 52.2 lbslacre-yr to 3.04 for SQN and WBN and to 8.32 for BFN based on surveys of fish caught
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in the Chickamauga and Wheeler reservoirs. This decreases the population
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dose from fish ingestion.
- 2. Population doses are calculated for a 50 mile radius downstream of each plant instead of to the rivers mouth. This decreases the-population doses from every pathway.
- 3. The most recent data is used for the population numbers in place of the
- 21. growth rate each year currently assumed. This gives a more realistic assessment of the population potentially receiving dose from plant operation.
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Nuclides Deleted from QMATA
- l. Na-22 33. Pb-212
- 2. As-74 34. Pb-214
- 3. As-76 35. Bi-212
- 4. Kr-83m 36. Bi-214
- 5. Kr>>85m 37. Po-212
- 6. Kr-85 38. Po-214
- 7. Nb-95m 39. Po-216
- 8. Nb-97m 40. Po-218
- 9. Tc-99 41. Ra-224
- 10. Rh-103m 42. Ra-226
- 11. R}1-105 43. Ra-228
- 17. 1-129 49. Pa-234 1'8. Xe-'133m 50. U-234
- 19. Xe-133 51. U-238
- 20. Xe-13Sm S2. Np-238
- 21. Xe-135 53. PU-238
- 22. Cs-135 S4 . Pu-239
- 23. Ba-137m S5. Pu-240
- 24. Pr-144m 56. Pu-. 241
- 25. Pm-147 57. Fu-242
- 26. Pm-149 58. Am-241
- 27. Sm-147 59. Am-242
- 28. SG!-15) 60. Am-243
- 29. SmlS3 61. Cm-242
- 30. Eu-155 62. Cm-243
- 31. Ta-182 63. Cm-244
- 32. Pb-210
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fitwg Handl i ng of Changes to the BFN Offs i te Dose RARC Qp 9 Calculati.on Manual Revision 0 Page 4 of 4 Appendix 1 SFN OOCH Change Description Form Description of change: M Pages'affected: E'M Justification for change: '
0 Analysis of effect of change on dose calculations, pro)ections, or setpoint calculations: r Attach marked-up pages from the current revision of the SQN OOCM which show the change.
RARC Review: Date: z 5 NARC irman 0678o/CGC4
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QN' Tltte. Handling of Changes to the SFN Offsite Dose RARC OP 9 e Calculation Hanua 1 Revision 0 4 of 4 'age Appendix 1 BFN ODCH Change Description Form Description of change: Qe 4
Pages affected:
Justification for change:
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Analysis of effect of change on dose calculations, pro)ectians, or setpoint.
calculations:
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RARC Review: Date: > s RARC irman 0678o/COC4
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RETS Manual Revision 5 Page 37 TABLE OF CONTEVZS
~Pa e 2.2 Instrument Setpoints 2.2.1 Setpoint Determination 81 2.2.2 Post-Release Analysis 81 2.3 Dose 82 2.3.1 RETS Requirement 82 2.3.2 Monthly Analysis 83 2.3.2.1 Mater Ingestion 84 2.3.2.2 Fish Ingestion 85
,2.3.2.3 Recreation 86 ~
2.3.2.4 Monthly Summary 87 2.3.3 Quarterly Dose Calculations 88 2.3.3.1 Mater Ingestion 88 2.3.3.2 Fish Ingestion 2.3.3.3 Recreation Shoreline 89 2.3.3.4 Total Maximum Individual Dose 90 2.3.3.5 Population Dose 91 2.4 Operab'ility of Liquid Radwaste Equipment 93 2.5 Liquid Dose Factor Equations 93 2.5.1 Mater Ingestion Dose Factors 93 2.5.2 Fish Ingestion Dose Factors 93 2.5.3 Shoreline Recreation Dose Factor . 94 3.0 Radiological Environmental Monitoring 94 3.1 Monitoring Program 94 3.2 Detection Capabilities 95
- 3. 3 Nonroutine Reports 95 4.0 Annual Maximum Individual Doses - Total
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RETS Manual Revision 5 Page 38 LIST OF TABLES Table Number Ti tie BFN-Offsite Receptor Location Data 1.2 Expected Annual Routine Atmospheric Gaseous Releases from One Unit at BFN 1.3 (Sheets 1-22) Joint Percentage Frequencies of Wind Speed by Wind Direction for Stability Class 1.4 Dose Factors for Submersion in Noble Gases 1.5 Sector Elements Considered for Population Doses 1.6 BFN '50-Mile Population Within Each Sector 1.T (Sheets 1<<8) Ingestion Dose Factors 1.8 (Sheets 1 & 2) Radionuclide Decay and Stable Element Transfer Data.
1.9 (Sheets 1 & 2) Dose Calculation Factors 1.10 (Sheets 1-8) Inhalation Dose Factors 1.11 (Sheets 1 & 2) External Dose Factors for Standing on Contaminated Ground 2.1 Receptors for Liquid Dose Calculations 2.2 Bioaccumulation Factors for Freshwater Fish 3.1 (Sheets 1-4) Radiological Environmental Monitoring 3.2 Atmospheric and Terrestrial Monitoring Station Locations 3.3 Maximum Values for the Lower Limit of Detection (LLD)
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A' RETS Manual Revision 5 Page 48 0.9 fraction of total gamma dose expected to be contributed by the assumed nuclides.
10~ = pCi/Ci conversion factor.
- 3. 15x10 ~ = s/yr conversion factor.
Qi monthly release of radionuclide i, Ci.
DFYi gsmma-to-air dose factor for radionuclide i, mrad/yr per pCi/ms (Table 1.4).
Monthl Conservative Model Beta dose to air (X/Q) (1.5)
Dg Ql DFl3i 0.9 3.15x10 ~
where:
~ beta dose to air, mrad.
X/Q = highest land-site boundary annual-average relative concentration, s/m~ (from Table 1.1).
~ 1.84x10 ~ for ground level releases,
~ 2.08x10"8 for elevated releases (stack).
0.9 fraction of total beta dose expected to be contributed by the assumed nuclides.
pCi/Ci conversion factor.
3.15x10 ~ ~ s/yr conversion factor.
monthly release of radionuclide i, Ci.
Dpi beta-to-air dose factor for radionuclide i, mrad/yr per pCi/m~ (Table 1.4).
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RETS ~wnual Revision 5 Page 55 1.3 uarterl Dose Calculations A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in Specifications 6.7.5. Hethodology for this analysis is that which is described in Section 1.5, using the quarterly release values reported by the plant personnel. For iodine releases, it will be assumed that halE the iodines released are organic iodines, which contribute only to the inhalation dose. All real pathways and receptor locations (as identified in the most recent land use survey) are considered. En addition, actual meteorological data representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in section 1.7.
Stack releases will be considered elevated releases. Radwaste and reactor building releases will be considered split-level releases. Turbine building releases will be treated as ground level.
The highest gamma-air Md beta-air doses calculated will be used to check compliance with the quarterly limits of Specification 3.8.B.3. The highest organ dose Eor a real receptor is determined by summing the dose contribution
'from all real pathways including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow andir'or goat milk ingestion (if a cow or goat is identified for the location), beef ingescion (the beef ingestion dose for the location of highest beef dose for all receotors will be considered the beef dose for all receptors). The receptor having the highest organ dose is then used to check compliance with the quarterly limits of Specification 3.8.B.5.
Po ulation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken down into elements. These elements are defined in Table 1.5. For each of these sector elements, an average dose is calculated, and then multiplied by the population in that sector element.
Dispersion factors are calculated for the midpoint of each sector element (see Table 1.5). For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally.
The general equation used for calculating the population dose in a given sector element is:
Dosepop $ RATIOP + POPN
- AGE + 0.001
- DOSEP P
where RATIOP = ratio of average to maximum dose for pathway P. (Average inges tion rates are obtained from Regulatory Guide 1. 109, Table E-4.)
~,0.5 for, submersion and ground exposure pathways, a shieldingloccupancy factor.
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RETS Manual Revision 5
'Page 74 1.7 Dis ersion Methodolo Dispersion factors are calculated for radioactive effluent releases using hourly, average meteorological data collected onsite.
Meteorological data for ground level releases consist of windspeed and direction measurements at 10m and temperature measurements of 10m and 45 m.
Hourly average meteorological..data for the ground level portion of a split level release consist .of. wind speeds and directions measured at the 10m level and temperature measurements at 10m and 45m. The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.
~ ~
Raw meteorological data .for the elevated releases consist of windspeed and directions measured at 93m. Stability class D is assumed to persist
' during the entire period for elevated releases, except for the quarterly dose calculations described in Section 1.3 when all stability classes will be used to evaluate the elevated releases.
Meteorological data are expressed as a joint-frequency distribution of wind speed, wind direction, and atmospheric stability for each release level (ground, split and elevated). The joint-frequency distributions which represent the historical meteorological data for the period January 1977 to December 1979 are given in Table 1.3.
The wind speed classes that are used are as follows:
Number Ran e (m/s) Mid oint (m/s)
<0.3 0.13 0.3-0.6 0.45 0.7-1.5 1.10 1.6-2.4 1.99 2.5-3.3 2.88 3.4-5.5 4.45 5.6-8.2 6.91 8.3-10.9 9.59
>10.9 10. 95 The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A=1~ B=2, ..., G=7.
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RETS i~fanual Revision 5 Page 84 2.3.2.1 Water In estion The dose to an individual from ingestion of water is described by the following equation.
20 Djk =
~~ 10> z i=1 (DCF)ijk Zik, mrem where:
Djk dose for the jth'organ and the kth age group from the 20 radionuclides, mrem.
the organ of interest (bone, GIT, thyroid, liver or total body).
the age group being considered, child or adult.
10
- i~ .conversion factor, pCi/Ci.
0.95 conservative correction factor, considering only 20 radionuclides.
DCFijk ingestion dose commitment factor for the ith radionuclide for the jth organ for the kth age group, mrem/pCi (Table 1.7)
Iik monthly activity ingested of the ith radionuclide by the kth
,age group, Ci.
The activity ingested due to drinking water, Iik, is described by:
10 'Ai Uwa (1/12)
I1k Ci F d (7 34 x 10zo) where:
= conversion factor, ml/L.
Ai = activity released of ith radionuclide during the month, Ci.
Uwa = maximum individual water consumption rate corresponding to the kth age group (Table 1.9), L/yr.
1/12 = conversion factor, yr/month.
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RETS Manual Revision 5 Page 85
~ average river flow rate for the month (cubic Eeet per second)
= fraction oE river flow available for dilution (0.30) 7.34x10i o = conversion from cubic feet per second to milliliters per month Inserting this for Iik in equation 2.4, the dose equation for water ingestion then becomes:
20 3.98 x 10~
Djk F i=1 Uwa DCFijk Ai, mrem 2.3.2.2 Fish In estion The"dose'to an individual from the consumption of fish is described by Equation 2.4. In this case the activity ingested of the ith radionuclide due to eating fish (Iik) is described by 10 Ai Bi Ufa (1/12)
Iik Ci (2. 7)
Fd (7.34 x 10lo) where:
10' conversion factor, g/kg.
Ai ~ activity released of the ith radionuclide during the month, Ci Bi ~ bioaccumulation factor of ith radionuclide, pCi/g per pCi/ml. (Table 2.2.)
Ufa amount of fish eaten yearly by the kth age group (Table 1.9), kg/yr.
1/12 conversion factor, yr/month.
~ average river flow rate for the month, cubic feet per second.
fraction of river flow available for dilution, 0.30.
7.34x10x o ~ conversion from cubic feet per second to milliliters per month.
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RETS .'fanua5 Revision 5 Page 86 inserting this for Iig in equation 2.4, the dose equation for fish ingestion then becomes'.
20 3.98 x 102 Ai Bi Ufa DCFi jk (2.8) i=1 2-3.2.3 Recreation For the recreation dose calculation, the total dose is estimated based on a calculation of the shoreline dose for Co-58, Co-60, Cs-134, and Cs-137. The shoreline dose due to these four nuclides is expected to contribute over 95 percent of the total recreation dose. The total body and maximum organ dose to an individual via the shoreline recreation pathway are assumed to be equal. The recreation dose is described by the following equation:
4 Dr ~ 10 0.95 i=1
$ [42 ~ RCDFi ~ pi], mrem where:
Dr ~ recreation dose from plant releases, mrem.
10 1.2 ~ conversion factor, pCi/Ci.
0.95 = conservative correction factor for considering only 4 radionuclides.
RDCFi = dose commitment factor for standing on contaminated ground for the ith radionuclide, mrem/hr per pCi/m2 (Table 1.11).
~ concentration of ith radionuclide in shoreline sediment, Ci/m2, as described by the following equation (based on equation A-5 in Regulatory Guide 1.109).
~i 10 '.94E-04 ~ 100 ~ RHL ~ C. ~ M [1-exp( ~i (2.10) where:
102 = conversion factor, ml/L 100 = transfer constant defined in Regulatory Guide 1.109 equation A-4, L per m2-day.
RHLi ~ radiological half-life of the ith radioisotope, minutes (Table 1.8) ~
Ci = concentration of ith radionuclide in the Tennessee River, Ci/ml.
~ A ~
/(F ~ d ~ 7.34 x 10 )
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RETS L~ianual Revision 5 Page 87 where:
Ai activity released of ith radionuclide during the month, Ci.
average river flow Eor the month, cubic Eeet per second.
d fraction of river flow available Eor dilution, 0.30.
7.34 x 10 conversion from cubic feet per second to milliliters per month.
shoreline width factor, (Table 1.9).
decay constant of the ith radionuclide, sec (Table 1.8).
tb buildup time in sediment, seconds (Table 1.9) 42 = assumed monthly exposure time for maximum individual,
= 500 hlyear -. '12 monthslyear.
The recreation dose equation then becomes:
1 Dy ~ (29 ~ 8 Al + 1690 A2 + 539 A3 + 812 A4) (2. 11) where:
Al, A2, A3, A4, = the activities of Co-58, Co-60, Cs-134, and Cs-137, respectively, Ci.
2.3. 2. 4 Nonthl S ummar To obtain the total monthly dose to the total body, sum the total body dose from water ingestion, the total body dose from fish ingestion, and the recreation dose. This value will be compared to the Technical Specification limit for total body dose. To obtain the total monthly dose to the maximum organ, sum the maximum organ dose from water ingestion, the maximum organ dose from Eish ingestion, and the recreation dose. This value will be compared to the Technical Specification limit for maximum organ dose. Calendar quarter doses are first estimated by summing the doses calculated for each month in that quarter. Calendar year doses are first estimated by summing the doses calculated for each month in that year. However, if the annual doses determined in this manner exceed or approach the spedification limits, doses calculated for previous quarters with the methodology of Section 2.3.2 vill be used instead of those quarterly doses estimated by summing monthly results.
An annual check will'e made to ensure that the monthly dose estimates account for at least 95 percent of the dose calculated by the method described in Section 2.3.3. If less than 95 percent of the dose has been estimated, either a new list if principal isotopes will be prepared or a new correction factor will be used. The latter option will not be used if less than 90 percent of the total dose is predicted.
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RETS Manual Revision 5 Page 88 2.3.3 uarterl Dose Calculations A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required in Section F.2 of the REM. Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel. The releases are assumed, for this calculation, to be continuous over the 90 day period.
The average dilution factor, D, used for the quarterly calculations is ~
1 D ~
- 0.30 (for receptors upstream (2. 13a)
RF of Wheeler Dam)
(for receptors downstream (2.13b) of Wheeler Dam) where:
RF ~ the average actual riverflow for the location at which the dose is being determined, cfs.
0.30 ~ the fraction of the riverflow available for dilution in the near field, dimensionless.
2.3.3.1 Water In estion Mater ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of BFN (Table 2.1). Water ingestion doses are calculated for the total body and each internal organ as
'escribed below:
Dorg 10 9.8E-09 AMit Qi D exp(-8.64E+04 Ai td) (2.14) where
~ conversion factor, pCi/Ci.
9.8E-09 = conversion factor, cfs per ml/hour.
AMit ~ Dose factor for water ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 2.5.1.
Qi ~ Quantity of nuclide i released during the quarter, Curies.
~ dilution factor, as described above, cfs->.
~ radiological decay constant of nuclide i, seconds (Table 1.8).
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RETS tanua1 Revision 5 Page 89 td decay time for water ingestion, equal to the travel time from the plant to the water supply plus one-half day (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) to account for the time of processing at the water supply (per Regulatory Guide 1.109), days.
8.64E+04 = conversion factor, seconds per day.
2.3.3.2 Fish In estion Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 2.1). Individual fish ingestion doses are calculated for the total body and each internal organ as described belo~:
Dorg = 10 9.8E&9 0.25 AFit Qi D exp(M.64E+04 Xi d) (2.15 where
= conversion factor, pCi/Ci.
9.8E-09 ~ conversion factor, cfs per ml/hour.
0.25 = fraction of the yearly fish consumption eaten in one quarter, dimensionless.
AFit ~ Dose factor for fish ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 2.5.2.
~ Quantity of nuclide i released during the quarter, Curies.
usaf
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~ dilution factor, as described above, cfs
= radiological decay constant of nuclide
'(Table 1.8).
i, seconds td decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days.
8.64E+04 = conversion factor, seconds per day.
2.3.3.3 Recreation Shoreline Recreation doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 2.1). It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline at a location immediately downstream from the diffusers. Individual General Revision 0547p
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-Page 90 recreation shoreline doses are calculated for the total body and skin as described below:
Dorg ~ 10 9.8E&9 rf ARit Qi D exp(-8.64E+04 Ai td) (2.16) where
= conversion factor, pCi/Ci.
10'.8E-09
= conversion factor, cfs per ml/hour.
= recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter. Recreation factors used are:
1st quarter 0.1 2nd quarter - 0.3 3rd quarter -'.4 4th quarter 0.2.
ARit = Dose factor for shoreline recreation for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 2.5.3.
Qi = Quantity of nuclide i released during the quarter, Curies.
D ~ dilution factor, as described above, cfs
~ radiological decay constant of nuclide i, seconds (Table 1.8).
td ~ decay time for recreation, equal to the travel time from the plant to the center of the reach, days.
8.64E+04 =.conversion factor, =.seconds per day.
2.3.3.4 Total Maximum Individual Dose The total maximum individual total body dose is obtained by summing the follow'ing for each age group: the highest total body water ingestion dose from among all the public water supplies; the highest total body f ish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies; that organ's highest fish ingestion dose from among all the reaches; and the total body maximum shoreline recreation dose. The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.
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RETS Manual Revision 5 Page 91 2.3.3.5 Population Doses For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and then multiplied by the population.
For water ingestion, the general equation used for calculating the population doses, POPWTR, inman-rem for a given PWS is:
5 4 POPWTRt = 10 $ POPm $ POPa + ATLLWa
- TWDOSamt m=1 a=1 where:
POPWTRt ~ water ingestion population dose to organ t, man-rem.
POPa ~ fraction of population in each age group a (from NUREG CR-1004, table 3.39).
Adult ~ 0.665 Child = 0.168 Infant = 0.015 Teen = 0.153 POPm = population at PWS m. The 3 PWSs and their populations are listed in Table 2.1.
ATMWa ~ ratio of average to maximum water ingestion rates for each age group a. Maximum water ingestion rates are given in Table 1.9. Average water ingestion rates, in L/year, (from R.G. 1.109 Table E-4) are:
Adult = 370 Child ~ 260 Infant = 260 Teen = 260 TWDOSamt = total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 2.3.3.1, mrem.
10 3 ~ conversion factor for remlmrem.
For population doses resulting from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of BPif are consumed by local population. An additional 7-day decay term is added due to distribution time of sport fish. The general equation for calculating population doses, POPF, in man-rem from fish ingestion of all fish caught within a 50-mile radius downstream is:
- HVST 4 3 453%6 APR TFDOSart + POPa POPFt 10 + 10 FISHa
- POPa 1
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POPFt = total fish ingestion population dose to organ t, man-rem.
HVST = fish harvest for the Tennessee River, 8.32 lbs/acre/year.
= size of reach, acres (Table 2.1).
TFDOSart = total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 2.3.3.2, mrem.
POPa ~ fraction of population in each age group a, as given'bove.
FISHa ~ amount of fish ingested by each age group a, kg/year. The average fish ingestion rates (R.G. 1.109 Table E-4) are:
Adult = 6.9 Child = 2.2 Teen ~ 5.2 453.6 ~ conversion factor, g/lb.
~ conversion factor, mrem/rem.
10s ~ conversion factor, g/'kg.
For recreation shoreline, the general equation used for calculating the population doses, POPR, in man-rem is:
REQFRA POPRt = $ TSHDOSrt SHVISz HRSVISz.
10 8760 r=l
-..where:
POPRt ~ total recreation population dose for all reaches to organ t, man-rem.
REQFRA = fraction of yearly recreation which occurs in that quarter, as given in Section 2.3.3.3.
TSHDOSz.t = total shoreline dose rate for organ t, in reach r, mrem/h.
SHVISr = shoreline visits per year at each reach r, (Table 2.1).
= length of shoreline recreation visit at reach r, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
HRSVISz'760
~ conversion factor, mremlrem.
= conversion factor, bours/year.
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RETS ~manual Revision 5 Page 93 2.4 Ooerabilit of Liquid Radwaste Eouioment The Radiological Effluent Manual (REM) requires that the liquid radwaste system (Figure 2.3) shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases* to unrestricted areas (see Figure 2.1) when averaged over 31 days would exceed 0.06 mrem to the total body or 0.21 mrem to any organ. Doses will be projected monthly.
Dose projections will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.
2.5 Liquid Dose Factor E uations 2.5 ~ 1 MATER INGESTION DOSE FACTORS Agit (mrem/hr per pCi/ml)
DFLiat Uwa 10 10 8760 where:
DF- iat ~ ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 1.7) ~
I
~ water consumption rate for age-group a, L/year, (Table 1.9).
~ conversion factor, pCi/pCi.
= conversion factor, ml/L.
8760 ~ conversion factor, hours per year.
2.5.2 FISH INGESTION DOSE FACTORS - AFit (mrem/hr per pCi/ml)
DFLiat Ufa Bi 10 10 AFit 8760 where:
DFLiat = ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 1.7). I Ufa ~ fish consumption rate for age group a, kg/year, (Table 1.9).
Bi = bioaccumulation factor for nuclide i, pCi/kg per pCi/L, (Table 2.2).
- >r operating reactor unit.
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= conversion factor, pCi/pCi.
= conversion factor, ml/L.
10'760
= conversion factor, hours per year.
2.5.3 SHORELINE RECREATION DOSE FACTOR - ARit (mrem/hr per pCi/ml).
D Git Kc M W 10 10 U ARit [1-exp(-X tb)]
~
8760
- 3600 Ai where:
DFGit = dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m~, (Table 1.11).
Kc ~ transfer coefficient from water to shoreline sediment, L/kg-hr, (Table 1.9).
~ mass density of sediment, kg/m~, (Table 1.9).
= shoreline width factor, dimensionless, (Table 1.9).
10s = conversion factor, ml/L.
~ conversion factor, pCi/pCi.
10'600
= conversion factor, seconds/hour.
= decay constant for nuclide i, seconds ~, (Table 1.8).
tb = time shoreline is exposed to the concentration in'the water,
=.
seconds, (Table 1.9).
U = usage factor, 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year.
8760 = conversion factor, hours/year.
3.0 Radiolo ical Environmental Monitorin 3.1 Monitorin Pro ram An environmental radiological monitoring program as described in Tables 3.1 and 3.2 and in Figures 3.1, 3.2, 3.3, and 3.4 shall be conducted. Results of this program shall be reported in accordance with Section F-1 of the REM.
The atmospheric environmental radiological monitoring program shall consist of 10 monitoring stations from which samples of air particulates and radioiodine shall be collected.
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RETS Manual Revision 5 Page 95 The terrestrial monitoring program shall consist of the collection of vegetation, milk, soil, drinking water, and food crops. In addition, direct gamma radiation levels will be measured at 40 or more locations in the vicinity of the plant.
The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sample unavilability, or malfunction of sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next samoling period+
3.2 Detection Ca abilities Analytical techniques shall be such that the detection capabilities listed in Table 3.3 are achieved.
" '.3 'Nonroutine Reports Nonroutine reports shall be submitted pursuant to Section F-3 of the REM.
4.0 Annual Maximum Individual Doses - Total To determine compliance with 40 CFR 190, the annual dose contributions to the maximum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by: first, summing the total body air submersion dose, and the critical organ dose (except thyroid) from gaseous effluents; the total body dose, and critical organ dose (except thyroid) from liquid effluents for each quarter calculated in accordance with sections 1.3 and 2.3.3. Then to this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in section 3.0. These quarterly sums are then conservatively summed for the four calendar quarters to estimate the maximum individual dose for the year. This dose is compared to the limit of Technical Specification 4.8.C, i.e., 25 mrem per year to the total body or any organ (except thyroid), to determine compliance.
The total annual thyroid dose to the maximum individual will be conservatively estimated in the following manner. For each calendar quarter, a total dose will be obtained'y summing the total body gaseous submersion dose, the gaseous thyroid dose, the liquid total body dose, and the liquid thyroid dose. To this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the General Revision 0547p
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RET8 .'manual Revision 5 Page 96 plant as determined by the environmental monitoring program outlined in section 3.0. These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year. This dose is compared to the limit of Technical Specification 4.8.C, i.e., 75 mrem per year to determine compliance.
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RETS Manual Revision 5 Page 97 Table 1.1 BFN OFFSITE RECEPTOR LOCATION DATA GROUND LEVEL ELEVATED DISTANCE Elev above X/Q . D/Q X/Q D/Q POINT from plant plant grade (s/m ) (1/m2 ) (s/m ) (1/m2)
(m) (m)
Site Boundary 1525 N 7 1.60E-06 5.64E-09 9.79E-11 8.578-10 Site Boundary 1300 NNE 4 7.88E-07 1.97E-09 7.86E-12 5.24E-10 Site Boundary 1250 NE 7 4.52E-07 1.56E-09 5.91E-12 4.66E-10 Site Boundary 1450 ENE 0 7.30E-07 2.92E-09 1.37E-11 4.11E-10 Site Boundary 1375 E 0 8.24E-07 4.04E-09 8.84E-12 4. 75i-10 Site Boundary 1575 ESE 0 4.56E-07 3.28E-09 4.98E-11 5.98E-10 Site Boundary 5600 SE -6 7.61E-08 3.63E-10 7.24E-49 3.00E-10 Site Boundary 2875 SSE -6 4.86E-07 1.77E-09 1.58E-09 5. 59E-10 Site Boundary 2550 S -6 8.27E-07 ~ 2.24E-09 1 '2E-09 6.67E-10 Site Boundary 2425 SSW -6 1.08E-06 '2. 92E-09 9'27E-10 7.07E-10 Site Boundary 2300 SW -6 6.87E-07 1. 75E-09 5.94E-10 6.06E-10 Site Boundary 2500 WSW -6 6.38E-07 1.14E-09 5.34E-10 3.45E-1.0 Site 'Boundary 2550 W -6 6.70E-07 1. 25E-09 5.06E-10 2.74E-10 Site Boundary 3325 WNW -6 3.69E-07 9.07E-10 2.69E-09 4.75E-10 Site Boundary 2275 NW <<6 1.69E-06 4-92E-09 1. 10E-09 1.24E-09 Site Boundary 1650 NNW -6 1.84E-06 5.29E-09 1.31E-10 1.05E-09 Garden 1830 NNW -6 1.57E-06 4.46E-09 3.29E-10 1. 13EW9 Milk Cow 8045 N -6 1.47E-07 3.16E-10 N/A 2.30E-10 Milk Cow 10975 NNW -6 N/A N/A 1.69E-08 N/A NOTE: For quarterly dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.
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RETS .'!anual Revision 5 Page 121 Table 1.4 DOSE FACTORS FOR SUBi!ERSIOil EiN i!OBLE GASES Submersion dose Air dose mrem/yr per pCi/m~ mrad/yr per pCi/m~
DFBi DFSi DFyi DFQi Kr-83m 7.56E-02 1.93E+01 2. 88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2. 51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2. 94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Ze-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 I
Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
Reference:
Regulatory Guide 1.109, Table B-l.
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RETS: ~annual Revision 5 Page 124 Table 1.7 (1 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)'DULT H-3 bone 1.05E-07 liver 1.05E-07 t body 1.05E-07 thyroid kidney lung gi-lli 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2 84E&6 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1-70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.17E-05 Cr-51 O.OOE+00 O.OOE+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 O.OOE+00 4.57E-06 8.72E-07 0 OOE+00 1.36E-06 O.OOE+00 1.40E-05 Mn-56 O.OOE+00 1. 15E-07 2 04EMS O.OOE+00 1.46E-07 0.00E+00 3.67E-06 Fe-55 2.75E-06 l. 90E-06 4.43E-07 O.OOE+00 0.00E+00 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 O.OOE+00 0. OOE+00 2.85E-06 3.40E-05 Co-57 0.00E+00 1.75E-07 2.91E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.44E-06 Co-58 0.00E+00 7.45E-07 1.67E-06 O.OOE+00 0.00E+00 O.OOE+00 1.51E-05 Co-60 O.OOE+00 2.14E-06 4.72E-06 0.00E+00 O.OOE+00 O.OOE+00 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 O.OOE+00 1.88E-06 Ni-65 5.28E-07 6.86E-OS 3.13E-OS O.OOE+00 O.OOE+00 O.OOE+00 1.74E-06 Cu-64 O.OOE+00 8.33E-OS 3.91E-OS O.OOE+00 2. 10E&7 O.OOE+00 7.10E-06'.70E-06 Zn-65 4.'84E-'06 1.54E-05 6 96EM6 O.OOE+00 1.03E-05 O.OOE+00 Zn-69 1.03E-OS 1.97E-OS 1.37E-09 O.OOE+00 1.28E-OS O.OOE+00 2.96E-09 Zn-69m 1.70E-07 4.08E-07 3.73E-OS O.OOE+00 2.47E-07 0.00E+00 2.49E-05 Br-82 O.OOE+00 O.OOE+00 2.26E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.59E-06 Br-83 0.00E+00 O.OOE+00 4.02E-08 O.OOE+00 0.00E+00 0.00E+00 5.79E-OS Br-84 O.OOE+00 0.00E+00 5.21E-OS O.OOE+00 O.OOE+00 O.OOE+00 4.09E-13 Br-85 0.00E+00 O.OOE+00 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
'b-86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 O.OOE+00 0.00E+00 4.16E-06 Rb-88 O.OOE+00 6.05E-08 3-21E-08 0.00E+00 0.00E+00 O.OOE+00 8.36E-19 Rb<<89 O.OOE+00 4.01E-08 2.82E-OS O.OOE+00 0.00E+00 O.OOE+00 2.33E-21 Sr-89 3.08E-04 O.OOE+00 8.84E-06 O.OOE+00 O.OOE+00 O.OOE+00 4.94E-05 Sr-90 7.58E-03 O.OOE+00 1.86E-03 O.OOE+00 O.OOE+00 '0.00E+00 2.19E-04 Sr-91 5.67E-06 O.OOE+00 2.29E-07 0.00E+00 O.OOE+00 O.OOE+00 2.70E-05 Sr-92 2.15E-06 0.00E+00 9.30E-08 O.OOE+00 0.00E+00 O.OOE+00 4.26E-05 Y-90 9.62E-09 O.OOE+00 2.58E-10 O.OOE+00 0.00E+00 O.OOE+00 1.02E-04 Y-'91m 9.09E-11 O.OOE+00 3.52E-I.2 O.OOE+00 0.00E+00 O.OOE+00 2.67E-1.0 Y-91 1.41E-07 O.OOE+00 3.77E-09 O.OOE+00 0.00E+00 O.OOE+00 7.76E-05 Y-92 8.45E-10 O.OOE+00 2.47E-1.1 O.OOE+00 0.00E+00 O.OOE+00 1.48E-05 Y-93 2.68E-09 O.OOE+00 7.40E-1.1 O.OOE+00 0.00E+00 O.OOE+00 8.50E-05 Zr-95 3.04E-OS 9.75E-09 6.60E-09 0.00E+00 1.53E-OS O.OOE+00 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 O.OOE+00 5.12E-10 O.OOE+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 O.OOE+00 2.10E-05 Nb-97 5.22E-11 1.32E-11 4.82E-12 O.OOE+00 1.54E-11 O.OOE+00 4.87E-OS Mo-99 O.OOE+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 O.OOE+00 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 O.OOE+00 1.06E-OS 3.42E-10 4. 13E-07 Tc-101 2.54E-10 . 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1 ~ 10E-21 Ru-103 1.85E-07 O.OOE+00 7.97E-08 0.00E+00 7.06E-07 O.OOE+00 2.16E-05 RG-105 1.54E-08 O.OOE+00 6.08E-09 O.OOE+00 1.99E-07 O.OOE+00 9.42E-06 RQ-106 2.75E-06 O.OOE+00 3.48E-07 O.OOE+00 5.31E-06 O.OOE+00 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 0.00E+00 2.91E-07 O.OOE+00 6.04E-05 General Revision 0530p
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Tab le 1. 7 (2 o 8 )
INGESTION DOSE FACTORS (mrem/pCi ingested)
ADULT Sb-124 bone 2.80E-06 liver 5.29E-OS t body 1.11E-06 thyroid kidney lung gi-lli 6.79E-09 O.OOE-OO 2.18E-06 7.95E-05 Sb-125 1.79E-06 2.00E-OS 4.26E-07 1.82E-09 0.00E-OO 1.38E-06 1.97E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 O.OOE+00 2.27E-05 Te-127 1.10E-07 3.95E-OS 2.38E-OS 8.15E-08 4.48E-07 O.OOE+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 Te-129 3.14E-OS 1.18E-OS 7.65E-09 2.41E-OS 1.32E-07 O.OOE+00 2.37E-OS Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 Te-131 1.97E-OS 8.23E-09 6.22E-09 1.62E-08 8.63E-OS O.OOE+00 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+00 7.71E-05 I-130 7.56E-07 2.23E-06 S.SOE-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 O.OOEjoo 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+00 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51E-10 I-135 .43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+00 1.31E-06
's-134 6.22E-05 1.48E-04 1.21E-04 O.OOE+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2-57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 O.OOE+00 3.70E-05 1.23E-05 2. 11E-06 Cs-138 5.52E-OS 1.09E-07 5.40E-08 O.OOE+00 8.01E-OS 7. 91E-09 4.65E-13
'a-139 9.70E-OS 6.91E-11 2.84E-09 O.OOE+00 6.46E-l.l 3.92E-1.1 1.72E-07 Ba-140 2.03E-05 2. 55E-08 1.33E-06 O.OOE+00 8.67E-09 1.46E-OS 4.18E-05 Ba-141 4.71E-OS 3.56E-11 1.59E-09 O.OOE+00 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 O.OOE+00 1.85E-11 1.24E-11 3.00E-26 La-140 2.50E-09 1.26E-09 3.33E-10 O.OOE+00 O.OOE+00 0.00E+00 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 0.00E+00 0.00E+00 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 O.OOE+00 2.94E-09 0.00E+00 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 O.OOE+00 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-l.o O.OOE+00 2.13E-09 O.OOE+00 4.03E-05
'Pr-144 3.01E-11 1.25E-11 1.53E-12 O.OOE+00 7.05E-12 O.OOE+00 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 O.OOE+00 4.25E-09 O.OOE+00 3.49E-05 M-187 1.03E-07 8.61E-OS 3.01E-OS O.OOE+00 0.00E+00 O.OOE+00 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-11 0.00E+00 3.65E-10 O.OOE+00 2.40E-05
References:
Regulatory Guide 1.109, Table E-ll.
Dose Factors for Co-57, Zn-69m, Br-82, iib-97, Sb-124 and Sb-125 are from NUREG-0172 A e Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 4.
~ ~
I NOTE: The tritium dose factor for bone is assumed to be equal to the
'I total body dose factor.
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RETS 'manual Revision 5 Page 126 Table 1.7 (3 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested.)
TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E07 8.12E-07 8 12EW7 8.12E-07 8.12E-07 8.128-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 l. 71E&5 1.07E-05 0.00E+00 0.00E+00 O.OOE+00 2.32K-05 Cr-51 0.00E+00 O.OOE+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Nn-54 0.00E+00 5. 90E&6 1.17E-06 O.OOE+00 1.76E-06 0.00E+00 1.21E-05 i4hx-56 O.OOE+00 1.58E&7 2.81E-08 O.OOE+00 2.00E-07 O.OOE+00 1.04E-05 Fe-55 3.78E-06 2. 68E-06 6.25E-07 O.OOE+00 O.OOE+00 1.70E-O6 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 O.OOE+00 O.OOE+00 4.32E-06 3.24E-05 Co-57 O.OOE+00 2.38E-07 3.99E-07 0.00E+00 O.OOE+00 O.OOE+00 4.44E-06 Co-58 O.OOE+OO 9. 72E&7 2.24E-06 O.OOE+00 0.00E+00 0.00E+00 1.34E-05 Co-60 0.00E+OO 2.81E-06 6.33E-06 0.00E+00 0.00E+00 O.OOE+00 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 O.OOE+00 O.OOE+00 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.19E-06 CL1-64 0.00E+00 1.15E-07 5.41E-08 O.OOE+00 2.91E-07 O.OOE+00 8.92E-06 Zn-65 '5.76E-06'.47E-OS 2.00E-05 9.33E-06 O.OOE+00 1.28E-05 O.OOE+00 8.47E-06 Zn-69 2.80E-08 1.96E-09 O.OOE+00 1.83E-08 0.00E+00 5.16E-08 Zn-69m 2.40E-07 5.66E-07 5.19E-08 O.OOE+00 3.44E-07 O.OOE+00 3. 11E-05 Br-82 O.OOE+00 0.00E+00 3.04E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 0.00E+OO 0.00E+00 5.74E-08 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-84 0.00E+00 O.OOE+00 7.22E-08 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Br-85 O.OOE+00 0.00E+00 3.05E-09 O.OOE+00 40.00E+00 O.OOE+00 0.00E+00 Rb-86 0.00E+00 2.98E-05 1.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.41E-06 Rb-88 O.OOE+00 8.52E-08 4.54E-08 0.00E+00 O.OOE+00 0.00E+00 7.30E-1.5 Rb-89 O.OOE+00 5.50E-08 3.89E-08 O.OOE+00 0.00E+00 O.OOE+00 8.43E-17 Sr-89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 Sr-90 8.30E-O3 O.OOE+00 2.05E-O3 O.OOE+00 O.OOE+00 0.00E+00 2.33E-04 Sr-91 8.07E-06 O.OOE+00 3.21E-07 0.00E+00 O.OOE+00 0.00E+00 3.66E-05 Sr-92 3.05E-06 O.OOE+00 1.30E-07 O.OOE+00 O.OOE+00 0.00E+00 7.77E-05 Y-90 1.37E-OS O.OOE+00 3.69E-10 0.00E+00 0.00E+00 O.OOE+00 1.13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 O.OOE+00 O.OOE+00 O.OOE+00 6.09E-09 Y-91 2.01E-07'.21E-09 O.OOE+00 5.39E-09 O.OOE+00 O.OOE+00 O.OOE+00 8.24E-05 Y-92 0.00E+00 3.50E-11 0.00E+00 O.OOE+00 O.OOE+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1.05E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 O.OOE+00 7.11E-10 O.OOE+00 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 O.OOE+00 4.42E-09 O.OOE+00 1.95E-05 Nb-97 7.37E-1.1 1.83E-11 6.68E-12 O.OOE+00 2. 14E-11 0.00E+00 4.37E-07 No-99 O.OOE+00 6.03E-06 1.15E-06 0.00E+00 1.38E-OS O.OOE+00 1.08E-05 Tc-99m 3.32E-10 9.26E-10 1.20E-08 O.OOE+00 1.38E-08 5.14E-I.O 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 O.OOE+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.09E-07 0.00E+00 8.99E-07 0.00E+00 2.13E-05 Ru-105 2.18E-08 0.00E+00 8.46E-09 O.OOE+00 2.75E-07 O.OOE+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.94E-07 O.OOE+00 7.56E-06 O.OOE+00 1.88E-04 Ag-110m 2.05E-07 1.94E-07 1. 18E-07 O.OOE+00 3.70E-07 O.OOE+00 5.45E-05 General Revision 0530p
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RETS manual Revision 5 Page 127 Table 1.7 (4 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
TEEN bone liver t body thyroid kidney lung gi-1li Sb-124 3.87E-06 7.13E-OS 1.51E-06 8.78E-09 . O.OOE-OO 3.38E-06 7.80E-05 Sb-125 2.48E-06 2.71E-OS 5.80E-07 2.37E-09 O.OOE+00 2. 18E&6 1.93E-05 Te-125m 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 Te-127m 9.67E&6 3.43E-06 1.15E-06 2.30E-06 3.92E-05 O.OOE+00 2.41E-05 Te-127 1. 58E-07 5.60E-OS 3.40E-OS 1.09E-07 6.40E-07 O.OOE+00 1.22E-05 Te-129m 1. 63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 O.OOE+00 6. 12E-05 Te-129 4. 48E-08 1.67E-OS 1.09E-08 3.20E-08 1.88E-07 O.OOE+00 2. 45E-07 Te-131m 2. 44E-06 1.17E-06 9. 76E-07 1.76E-06 1.22E-05 O.OOE+00 9.39E-05 Te-131 2. 79E-08 1.15E-OS 8. 72E-09 2.15E-08 1.22E-07 O.OOE+00 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E&6 2.33E-06 2.12E-05 O.OOE+00 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E>>04 4.59E-06 O.OOE+00 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 O.OOE+00 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 O.OOE+00 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 O.OOE+00 2.58E-06 I-134 =
1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5. 10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 O.OOE+00 1.74E-06
's-134 8.37E-05 1.97E-04 9.14E-05 O.OOE+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 O.OOE+00 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 Cs-138 7. 76E-08 1.49E-07 7.45E-OS O.OOE+00 1.10E-07 1.28E-08 6.76E-ll Ba-139 1. 39E-07 9.78E-11 4.05E-09 O.OOE+00 9.22E-11 6.74E-11 1. 24EW6 Ba-140 2.84E-05 3.48E-OS 1.83E-06 O.OOE+00 1.18E-.OS. 2.34E-OS 4.38E-05
.Ba-141 6.71E-OS 5.01E-11 2.24E-09 O.OOE+00 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-OS 2.99E-11 1.84E-09 O.OOE+00 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 O.OOE+00 0.00E+00 O.OOE+00 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 O.OOE+00 0.00E+00 O.OOE+00 2.42E-06 Ce-141 1.33E-OS S.SSE-09 1.02E-09 0.00E+00 4.18E-09 O.OOE+00 2.54E-05 Ce-143 2. 35E-09 1.71E-06 1.91E-10 0.00E+00 7.67E-10 O.OOE+00 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E>>08 0.00E+00 1.72E-07 0.00E+00 1.75E-04 Pr-143 1.31E-OS 5.23E-09 6.52E-10 O.OOE+00 3.04E-09 0.00E+00 4.31E-05 Pr-144 ~
- 4. 30E-11 1.76E-11 2.18E-12 O.OOEe00 1.01E-11 O.OOE+00 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 O.OOE+00 5.99E-09 0-OOE+00 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-OS O.OOE+00 0.00E+00 O.OOE+00 3.22E-05 Np-239 1 ~ 76E-09 1.66E-10 9.22E-11 0.00E+00 5.21E-10 O.OOE+00 2.67E-05
References:
Regulatory Guide 1.109, Table E-12.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from MEEG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 3.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
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RETS .Vanua1 Revision 5 Page 129 Table 1.7 (6 of 8)
IVGESTIOiV DOSE FACTORS (mrem/pCi ingested)
CHILD Sb-124 bone 1.11E-05 liver 1.44E-07 t body 3.89E-06 thyroid kidney lung gi-lli 2.45E-OS O.OOE+00 6.16E-06 6.94E-05 Sb-125 7.16E-06 5.52E-OS 1.50E-06 6.63EW9 O.OOE+00 3.99E-06 1. 71E-05 Te-125m 1.14E-05 3.09E-06 1.52E-06 3.20E-06 O.OOE+00 O.OOE+00 1.10E-05 Te-127m 2.89E-05 7.78E-06 3.43E-06 6.91E&6 8.24E-05 O.OOE+00 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3. 26E-07 1.34E-06 O.OOE+00 1.84E-05 Te-129m 4.87E-05 1.36E-05 7.56E-06 1. 57E-05 1.43E-04 O.OOE+00 5.94E-05 Te-129 1.34E-07 3.74E-OS 3.18E-OS 9.56EWS 3.92E-07 O.OOE+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5. 12E&6 2.41E-05 O.OOE+00 1.01E-04 Te-131 8.30E-OS 2.53E-08 2.47E-OS 6. 35E-08 2.51E-07 O.OOE+00 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+00 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 O.OOE+00 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 O.OOE+00 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 O.OOE+00 2.95E-06 I-134 4.19E-07 7. 78E-07 3.58E-07 1.79E-05 1.19E-06 O.OOE+00 5.16E-07 I-135 1;75E-06 3.15E-06 1.49E-06 2. 79EM4 4.83E-06 O.OOE+00 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-'05 O.OOE+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E>>05 4.18E-05'.62E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 O.OOE+00 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 O.OOE+00 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-OS O.OOE+00 '1..93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-OS 4.85E-06 O.OOE+00 2.37E-OS 4.34E-OS 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 O.OOE+00 9.69E-ll 6.58E-10 1.14E-07 Ba-142 8.74E-OS 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1. 14E-09 La-140 1.01E-OS 3.53E-09 1.19E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-11 O.OOE+00 O.OOE+00 O.OOE+00 3.31E-05 Ce-141 3.97E-OS 1.98E-OS 2.94E-09 O.OOE+00 8.68E-09 O.OOE+00 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 O.OOE+00 1.59E-09 O.OOE+00 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 O.OOE+00 3.61E-07 O.OOE+00 1.70E-04 Pr-143 3.93E-OS 1.18E-OS 1.95E-09 O.OOE+00 6.39E-09 O.OOE+00 4.24E-05 Pr-144 1.29E-10 3.99E-11 6.49E-12 O.OOE+00 2.11E-11 O.OOE+00 8.59E-OS iVd-147 2.79E-OS 2.26E-OS l. 75E-09 0.00E+00 1.24E-OS O.OOE+00 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.57E-05 imp-239 5.25E-09 3.77E-10 2.65E-10 O.OOE+00 1.09E-09 O.OOE+00 2.79E-05 Ref erences:
Regulatory Guide 1.109, Table E-13.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake, iVovember, 1977, Table 2.
VOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
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RETS Manual Revision 5 Page 128 Table 1.7 (5 of 8)
IiVGESTION DOSE FACTORS (mrem/pCi ingested)
CHILD bone liver t body thyroid kidney lung gi-11'.03E-07 H-3 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.2SE-05 Cr-51 O.OOE+00 0.00E+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 iM-54 O.OOE+00 1.07E-05 2.85E-06 O.OOE+00 3.00E-06 O.OOE+00 8.98E-06 Mn-56 O.OOE+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 O.OOE+00 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 O.OOE+00 0.00E+00 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 7. 74E-06 2.78E-05 Co-57 O.OOE+00 4.93E-07 9.98E-07 O.OOE+00 O.OOE+00 0.00E+00 4.04E-06 Co-58 0.00E+00 1.80E-06 5.51E-06 O.OOE+00 O.OOE+00 0.00E+00 1.05E-05 Co-60 0.00E+00 5.29E-06 1.56E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.56E-05 CLL-64 0.00E+00 2.45E-07 1.48E-07 O.OOE+00 5.92E-07 0.00E+00 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 0.00E+00 2.30E-05 O.OOE+00 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 O.OOE+00 3.84E-08 O.OOE+00 3.99E-06 Zn-69m 7;10E-07 1.21E-06 1.43E-07 0.00E+00 7.03E-07 O.OOE+00 3.94E-05 Br-82 0.00E+00 0.00E+00 7.55E-06 0.00E+00 O.OOE+00 O.OOE+00 O.OOEj00 Br-83 0.00E+00 0.00E+00 1.71E-07 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Br-84 , O.OOE+00 O.OOE+00 1.98E-07 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Br-85 O.OOE+00 O.OOE+00 9.12E-09 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Rb-86 O.OOE+00 6.70E-05 4.12E-05 0.00E+00 0.00E+00 0.00E+00 4.31E-06 Rb-88 0.00E+00 1.90E-07 1.32E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.32E-09 Rb-89 0.00E+00 1.17E-07 1.04E-07 O.OOE+00 O.OOE+00 0.00E+00 1.02E-09 Sr-89 1.32E-03 0.00E+00 3.77E-05 O.OOE+00 O.OOE+00 0.00E+00 5.11E-05 Sr-90 1.70E-02 O.OOE+00 4.31E-03 O.OOE+00 O.OOE+00 0.00E+00 2.29E-04 Sr-91 2.40E-05 O.OOE+00 9.06E-07 O.OOE+00 O.OOE+00 O.OOE+00 5.30E-05 Sr-92 9.03E-06 0.00E+00 3.62E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.71E-04 Y-90 4.11E-08 0.00E+00 1.10E-09 O.OOE+00 O.OOE+00 0.00E+00 1.17E-04 Y-91m 3;82E-10 O.OOE+00 1.39E-11 O.OOE+00 O.OOE+00 O.OOE+00 7.48E-07 Y-91 6.02E-07 0.00E+00 1.61E-08 O.OOE+00 0.00E+00 0.00E+00 8.02E-05 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 O.OOE+00 O.OOE+00 1.04E-04 Y-93 1.14E-08 0.00E+00 3.13E-10 O.OOE+00 0.00E+00 O.OOE+00 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 O.OOE+00 3.65E-08 O.OOE+00 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 O.OOE+00 1.53E-04 Nb-95 2.25E-08 8. 76E-09 6.26E-09 O.OOE+00 8.23E-09 O.OOE+00 1.62E-05 Nb-97 2.17E-10 3.92E-11 1.83E-l.l O.OOE+00 4.35E-11 0.00E+00 1.21E-05 Mo-99 O.OOE+00 1.33E-05 3.29E-06 O.OOE+00 2.84E-05 O.OOEjoo 1.10E-05 Tc-99m 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9. 19E-10 1.03E-06 Tc-101 1.07E-09'.31E-07 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 RLL-103 0.00E+00 2.81E-07 O.OOE+00 1.84E-06 O.OOE+00 1.89E-05 R11-105 6.45E-08 O.OOE+00 2.34E-08 O.OOE+00 5.67E-07 0.00E+00 4.21E-05 Ru>>106 1.17E-05 O.OOE+00 1.46E-06 O.OOE+00 1.58E-05 0.00E+00 1.82E-04 Ag-110m 5.39E-07 3.64E-07 2.91E-07 O.OOE+00 6.78E-07 O.OOE+00 4.33E-05 General Revision 0530p
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RETS .'fanual Revision 5 Page 130 Table 1.7 (7 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
INFANT bone liver t body thyroid kidney lung gi-lli H-3 3.08E-07 3.08E-07 3.08E07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-O5 P-32 1.70E-03 1.00E-O4 6.59E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.30E-05 Cr-51 O.OOE+00 O.OOE+00 1.41E-OS 9.20E-09 2.01E-09 1.79E-O8 4.11E-07 Nn-54 O.OOE+00 1.99E-05 4.51E-06 O.OOE+00 4.41E-06 O.OOE+00 7.31E-06 Hn-56 O.OOE+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 O.OOE+00 7.43E-05 Fe-55 1. 39E-05 8.98E-06 2.40E-06 0.00E+00 O.OOE+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.1.2E-05 O.OOE+00 '.OOE+00 1.59E-05 2.57E-05 Co-57 0.00E+00 1.15E-06 1.87E-06 O.OOE+00 0.00E+00 O.OOE+00 3.92E-06 Co-58 O.OOE+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 O.OOE+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.55E&5 0.00E+00 O.OOE+00 0.00E+00 2.57E-.05 Ni-63 6.34E-04 3. 92E5 2.20E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 O.OOE+00 O.OOE+00 0.00E+00 4.05E-05 CLL-64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05
Zn-65'n-69 1.84E-OS 6.31E-05 2.91E-05 O.OOE+00 3.06E-05 O.OOE+00 5.33E-05 9.33E-08 1. 68E-07 1.25E-08 0.00E+00 6.98E-08 O.OOE+00 1.37E-05 Zn-69m 1.50E-06 3.06E-06 2.79E-07 0.00E+00 1. 24E&6 O.OOE+00 4.24E-05 Br-82 0.00E+00 O.OOE+00 1.27E-05 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 O.OOE+00 3.63E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br<<84 O.OOE+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 0.00E+00 1.94E-08 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0-OOE+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 O.OOE+00 4.35E-06 Rb-88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 O.OOE+00 0.00E+00 4.85E-07 Rb-89 O.OOE+00 2.86E-07 1.97E-07 O.OOE+00 0.00E+00 O.OOE+00 9.74E-08 Sr-89 2-51E-03 0.00E+00 7.20E-05 ,O.OOE+00 O.OOE+00 O.OOE+00 5.16E-05 Sr-90 1.85E-02 O.OOE+00 4.71E-03 O.OOE+00 0.00E+00 O.OOE+00 2.31E-04 Sr-91 5.00E-05 0.00E+00 1.81E-06 O.OOE+00 0.00E+00 0.00E+00 5.92E-05 Sr>>92 1.92E-05 0.00E+00 7.13E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 Y-90 8-69E-08 0.00E+00 2.33E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.20E-04 Y-91m,. 8.10E 0.00E+00 2.76E-11 O.OOE+00 0.00E+00 0.00E+00 2.70E-06 Y-91 1.13E-06 O.OOE+00 3.01E-08 O.OOE+00 O.OOE+00 O.OOE+00 8.10E-05 Y-92 7.65E-09 O.OOE+00 2.15E-10 O.OOE+00 0.00E+00 O.OOE+00 1.46E-04 Y-93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 O.OOE+00 0 OOE+00 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 O.OOE+00 5.41E-08 O.OOE+00 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 Nb-97 4.59E-10 9.79E-11 3.53E-11 O.OOE+00 7.65E-11 0.00E+00 3.09E-05 Mo-99 O.OOE+00 3.40E-05 6.63E-06 O.OOE+00 5.08E-05 O.OOE+00 1.12E-05 Tc-99m 1-92E-09 3.96E-09 5.10E-08 O.OOE+00 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 0.00E+00 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 0.00E+00 4.95E-07 O.OOE+00 3.08E-06 O.OOE+00 1.80E-05 Ru-105 1.36E-07 0.00E+00 4.58E-08 O.OOE+00 1.00E-06 0.00E+00 5.41E-05 Ru-106 2.41E-05 O.OOE+00 3.01E-06 O.OOE+00 2.85E-05 O.OOE+00 1.83E-04 Ag-110m 9.96E-07 7.27E-07 4.81E-07 O.OOE+00 1.04E-06 O.OOE+00 3.77E-05 General Revision 0530p
1 RETS manual Revision 5 Page 131 Table 1.7 (8 of 8)
INGESTIOiV DOSE FACTORS (mrem/pCi ingested)
INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 O.OOE+00 1.34E-05 6.60E-05 Sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 O.OQE+00 7.72E-06 1.64E-05 Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 O.OOE+00 O.OOE+00 1.11E-05 Te-127m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 Te-127 1.00E-06 3.35E-07 2. 15E-07 8. 14E-07 2.44E-06 0. OOE+00 2.10E-05 Te-129m 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.00E+00 5.97E-05 Te-129 2.84E-07 9. 79E&8 6.63E-08 2.38E-07 7.07E-07 O.OOE+00 2.27E-05 Te-131m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+00 '.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.00E+00 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+00 2.83E-06 I-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+00 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 I-133 l. 25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.00E+00 3.08E-06 I-134 8. 69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 1-135- 3. 64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 l. 10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 O.OOE+00 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 O.OOE+00 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 O.OOE+00 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71E-04 1.71E-07 8.81E-06 O.OOE+00 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 O.OOE+00 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 O.OOE+00 8.81E-11 9.26E-11 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.77E-05 La-142 1.10E>>09 4.04E-10 9.67E>>11 O.OOE+00, O.OOE+00 0.00E+00 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 O.OOE+00 1.48E-08 O.OOE+00 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 O.OOE+00 2.86E-09 O.OOE+00 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 O.OOE+00 4.93E-07 O.OOE+00 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 O.OOE+00 1.13E-08 0.00E+00 4.29E-05 P,r-144 2.74E-10 1.06E-10 1.38E-11 O.OOE+00 3.84E-11 O.OOE+00 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 O.OOE+00 0.00E+00 0.00E+00 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 O.OOE+00 2.87E-05
References:
Regulatory Guide 1.109, Table E-14.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table l.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
General Revision 0530p
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RETS 1anua1 Revision 5 Page 132 Table 1.8 (1 of 3)
RADIONUCLIDE DECAY AND STABLE ELEi1EVZ TRANSFER DATA Half-Life X Biv Fmi Fmi Ffi (minutes) (1/s ) (cow) (goat) (beef )
H-3 6.46E+06 l. 79EW9 4.80E+00 1.00E-02 1.70E-01 1.20E-02 C-14 3.01E+09 3.84E-12 5.50E+00 1.20E-02 1.00E-01 3.10E-02 Na-24 9.00E+02 ~ 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 P-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-51 3.99E+04 2.90E-07 2.50E-04 2. 20E-03 2.20E-03 2.40E-03 Hn-54 4.50E+05 2.57E-08 2.90E-02 2. 50E-04 2.50E-04 8.00E-04 Hn-56 1.55E+02 7.45E-05 2.90E-02 2.50E-04 2.50E-04 8.00E-04 Fe-55 1.42E+06 8.13E-09 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.20E-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.02E+05 1.13E-07 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-60 2.77E+06 4.17E-09 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Ni-63 5.27E+07 2.19E-10 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62E+02 1.52E-05 1.20E-Ol 1.40E-02 1.30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90E-02 3-90E-02 3.00E-02
,Zn-69m 8.26E+02 1. 40E-05 4.00E-Ol 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.56E+01 2. 08E-04 4.00E-01 3.90E-02 3.90E-02 3.00E-02 Br-82 2.12E+03 5.45E-06 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-83 1.43E+02 8.08E-05 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-84 3.18E+01 3.63E-04 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Br-85 2.87E+00 4.02E-03 7.60E-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.29E-07 1.30E-Ol 3.00E-02 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.49E-04 1.30E-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.50E-04 1.30E-01 3.00E-02 3.00E-02 3 '0E-02 Sr-89 7.28E+04 1.59E-07 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-90 1.50E+07 7.70E-10 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-91 5. 70E+02 2.03E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Sr-92 1. 63E+02 7.09E-05 1.70E-02 1.40E-03 1.40E-02 6.00E-04 Y-90 3.85E+03 3.00E-06 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-91m 4.97E+01 2.32E-04 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-9.1 8.43E+04 1.37E-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.12E+02 5.45E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-93 6.06E+02 1.91E-05 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Zr-95 9.22E+04 1. 25E-07 1. 70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01E+03 1.14E-05 1. 70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.29E-07 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21E+01 1.60E-04 9.40E-03 2.50E-03 2.50E-03 2.80E-01 iso-99 3.96E+03 2.92E-06 1.20E-01 7.50E-03 7.50E-03 1.10E-03 Tc-99m 3.61E+02 3.20E-05 2.50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-101 1.42E+01 8.13E-04 2.50E-01 2.50E-02 2.50E-02 4.00E-01 RG-103 5.67E+04 2.04E-07 5.00E-02 1.00E-06 1.00E-06 4.00E-01 RLI-105 2.66E+02 4.34E-05 S.OOE-02 1.00E-06 1.00E-06 4.00E-01 RLI-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-110m 3.60E+05 3.21E-08 1.50E-01 5.00E-02 5.00E-02 1.70E-02 General Revision 0530p
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?age 133 Table 1.8 (2 of 3)
RADIONUCLIDE DECAY AND STABLE ELE~1EiVT TRANSFER DATA Half-Life Biv Fmi Fmi -i (beef (minutes) (1/s) (cow) (goat) )
Sb-124 8.67E+04 1.33E-07 N/A 1.50E-03 1.50E-03 V/A Sb-125 1.46E+06 7.91E-09 N/A 1.50E-03 1.50E-03 V/A Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1.QOE-03 7.70E-02 Te-127m 1.57E+05 7.36E-08 1.30E+00 1.00E-03 1.00E-03 7. 70E-02 Te-127 5.61E+02 2.06E-05 1.30E+00 1.00E-03 1.00E-03 7. 70E-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1.00E-03 7. 70E-02 Te-129 6.96E+01 1.66E&4 1.30E+00 1.00E-03 1.00E&3 7. 70E-02 Te-131m 1.80E+03 6.42E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-131 2.50E+01 4. 62E-04 1.30E+00 1.00E-03 1.00E-03 7.70E-02 Te-132 4.69E+03 2.46E-06 1.30E+00 1.00E-03 1.00E-03 7.70E-QZ I-130 7.42E+02 1.56E-05 2.00E&2 1.20E-02 4.30E-01 2.90E-03 I-131 1.16E+04 9.96E-07 2.00E&2 1.20E-02 4.30E-01 2.90E-03 I-132 1.38E+02 8.37E-05 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-133 1.25E+03 9.24E-06 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-134 5.26E+01 2.20E-04 2.00E-02 1.20E-02 4.30E-01 2.90E-03 I-135 3.97E+02 2.91E-05 2.00E-02 1.20E-02 4.30E-Ol 2.90E-03
'Cs'-134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 '.90E+04 6.08E-07 l. QOEWZ 8.00E-03 3.00E-01 1.50E-Q2 Cs-137 1.59E+07 7.26E-10 1-OOE-02 8.00E-03 3.00E-01 1.50E-02 Cs-138 3.22E+01 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31E+Ol 1.39E-04 5.00E-03 4.00E-04 4.00E&4 3.20E-03 Ba-'140 1.84E+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31E-04 5.00E-03 4.00E-04 4.00E&4 3.20E-03 Ba-142 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4. QQE-04 3.20E-03 La-140 2.41E+03 4.79E-06 2.50E-03 5.00E-06 5.00E&6 2.00E-04 La-142 9.54E+01 1.21E-04 2.50E-03 5.00E-06 5.00EM6 2.00E-04 Ce-141 4.68E+04 2.47E-07 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-143 1.98E+03 5.83E-06 2.50E-03 1.00E-04 1.00E-04 1.20E-03 Ce-144 4.09E+05 2.82E-OS 2.50E-03 1.00E-04 1. OOE-04 1.20E-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E&6 4.70E-03 Pr-144 1. 73E+01 6.68E-04 2.50E-03 5.00E-06 5.00EM6 4.70E-03 N6-147 1.58E+04 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 W-187 1.43E+03 8.08E-06 1.80E-02 5.00E-04 5.00E&4 1.30E-03 Np-239 3.39E+03 3.41E-06 2.50E-03 5.00E-06 5.00E-06 2.00E-04 Ar-41 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1.05E-04 N/A N/A N/A N/A Kr-85m 2.69E+02 4.29E-05 N/A iV/A iV/A N/A Kr-85 5.64E+06 2.05E-09 N/A N/A N/A V/A Kr-87 7.63E+01 1.51E-04 N/A N/A N/A V/A Kr-88 1.70E+02 6.79E-05 N/A iV/A iV/A V/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 2.14E-02 N/A N/A Vi/A N/A Xe-131m 1.70E+04 6.79E-07 N/A Vi/A iV/A N/A Xe-133m 3.15E+03 3.67E-06 N/A iV/A N/A V/A
'General 'Revision 0530p
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RETS Manual Revision 5 Page 134 Table 1.8 (3 of 3)
RADIONUCLIDE DECAY AiVD STABLE EL"=fEVT TRAVSFER DATA Half-Life 'A Biv Fmi Fmi Ffi (minutes) (1/s) (cow) (goat) (beef )
Xe-133 7.55E+03 1.53E-06 N/A N/A N/A N/A Xe-135m 1.54E+Ol 7.50E-04 iV/A N/A N/A N/A Xe-135 5.47E+02 2.11E-05 iV/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 N/A N/A N/A N/A Xe-138 1.41E+Ol 8.19E-04 N/A N/A N/A N/A
References:
Half lives for all nuclides: DOE-TIC-11026, "Radioactive Decay Data Tables - A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D. C. Kocher, 1981.
Transfer factors for Sb- isotopes are from ORNL 4992, "Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.
Cow-milk transfer factors for Iodine, Strontium, and Cesium nuclides are from NUREG/CR-1004, Table 3.17.
Goatmilk transfer factors for Iodine nuclides are from NUREG/CR-1004, Table 3.17.
Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18.
All other nuclides'ransfer factors are from Regulatory Guide 1.109, Tables E-1 and E-2.
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RE:S .'!anuai Revis'on 5 Page 135 Table 1.9 (1 of 2)
DOSE CALCULATEON FACTORS Factor Value Units Reference BRa (infant) 1400 m~ /'year 1CRP 23 BRa (child) 5500 m~ /year ZCRP 23 BRa (teen) 8000 m~/year 1CRP 23 BRa (adult) 8100 m~ /year ICRP 23 fg 1 TVA Assumotion fL 1 R. G. 1.109 (Table E-15) fp 1 TVA Assumotion fs 0 TVA Assumotion H 9 g/m~ TVA Value Kc 0.072 L/kg-hr R. G. 1.109 (Section 2.C.)
M 40 kg/m~ R. G. 1.109 (Section 2.C.)
P 240 kg/mi R. G. 1.109 (Table E-15)
'Q f (cow) 64 kg/day NEEG/CR-1004 (Sect. 3.4)
Qf (goat) 08 kg/day NUREG/CR-1004 (Sect. 3.4) r 0.47 IlRREG/CR-1004 (Sect. 3.2) tb 4.73K+08 seconds R. G. 1.109 (Table E-15)
(15 years) tcb 7.78E+06 seconds SQN FSAR Sect'on 11.3.9.1 (90 days) tcsf 1.56E+07 seconds SQN FSAR Section 11.3.9.1 (180 days) te 5.18E+06 seconds R. G. 1.109 (Table E-15)
(60 days) tep 2.59E+06 seconds R. G. 1.109 (Table E-15)
(30 days) tesf 7.78E+06 seconds R. G. 1. 109 (Tab le E-15 )
(90 days)-
tfm 8.64E+04 seconds SQN FSAR Section 11.3.9.1 (1 day) thc 8.64E+04 seconds NUREG/CR-1004, Table 3.40 (1 day) ts 1.12E+06 seconds NUREG/CR-1004, Table 3.40 (13 days) tsv 2.38E+07 seconds SQN FSAR Section 11.3.9.1 (275 days)
Uam (infant) 0 kg/year R. G. 1.109 (Table E-5)
U~ (child) 41 kg/year R. G. 1.109 (Table E-5)
Uam (teen) 65 kg/year R. G. 1.109 (Table E-5)
Uam (adult) 110 kg/year R. G. 1.109 (Table E-5)
Uap (infant ) 330 L/year R. G. 1.109 (Table E-5)
Uap (child) 330 L/year R. G. 1.109 (Table E-5)
Uap (teen) 400 L/year R. G. 1.109 (Table E-5)
Uap (adult) 310 L/year R. G. 1.109 (Table E-5)
General Revision 0530p
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DOSE CALCULATION FACTORS Factor Value Units Reference Ufa(infant ) 0 kg/year R. G. 1.109 (Table E-5)
Ufa(child) 6.9 kg/year R. G. 1.109 (Table E-5)
Ufa(teen) 16 kg/year R. G. 1.1.09 (Table E-5)
Ufa(adult) 21 kg/year R. G. 1.109 (Table E-5)
UFL (infant) 0 kg/year R. G. 1.109 (Table E-5)
UFL (child) 26 kg/year R. G. 1.109 (Table E-5)
UF1 (teen) 42 kg/year R. G. 1.109 (Table E-5)
UF1 (adult) 64 kg/year R. G. 1.109 (Table E-5)
USa (infant) 0 kg/year R. G.'.109 (Table E-5)
USa (child) 520 kg/year R. G. 1.109 (Table E-5)
USa (teen) 630 kg/year R. G. 1.109 (Table E-5)
USa (adult) 520 kg/year R. G. 1.109 (Table E-5)
U~a(infant) 330 L/year R. G. 1.109 (Table E-5)
U~a(child) 510 L/year R. G. 1.109 (Table E-5)
U~a(teen) 510 L/year R. G. 1.109 (Table E-5)
Uma (adul t) 730 L/year R. G. 1.109 (Table E-5)
M 0.3 none R. G. 1.109 (Table A-2)
Yf 1.85 kg/m~ NUREG/CR-1004 (Table 3.4)
Yp 1.18 kg/m~ NUREG/CR-I.004 (Table 3.3)
Ysf 0.64 kg/m~ NUREG/CR-1004 (Table 3.3)
Ysv 0.57 kg/m~ NUREG/CR-1004 (Table 3.4)
(value selected is for non-l.eafy vegetables)
X~ (iodines) 7.71E-07 sec NUREG/CR-1004 (Table 3.10)
(15.4 d half-life)
'X~ (particulates) 5.21E-07 sec NUREG/CR-1004 (Table 3.10)
(10.4 d half-life)
General Revision 0530p
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RETS Manual Revis on 5 Page 137
,Table 1.10 (1 of 8)
INHALATION DOSE FACTORS (mremlpCi inhaled).
ADULT bone liver t body thyroid kidney lung gi-lli H-3 1.58E-07 1. 58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2. 27EW6 4. 26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1. 28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.2SE-06 P-32 1.65E-04 9.64E-06 6.26E-06 O.OOE+00 O.OOE+00 0.00E+00 1.08E-05 Cr-51 O.OOE+00 0.00E+00 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 0.00E+00 4 95E-06 7.87E-07 O.OOE+00 1. 23EW6 1.75E-04 9.67E-06 Hn-56 O.OOE+00 1. 55E-1.0 2.29E-11 O.OOE+00 1.63E-10 1. 18E-06 2.53E-06 Fe-55 3.07E-06 2. 12E-06 4.93E-07 O.OOE+00 0.00E+00 9. 01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 O.OOE+00 O.OOE+00 1.27E&4 2.35E-05 Co-57 0.00E+00 8.65E-08 8.39E-OS O.OOE+00 0.00E+00 4. 62E-05 3.93E-06 Co-58 O.OOE+00 1.98E-07 2.59E-07 0.00E+00 O.OOE+00 1. 16E-04 '.
1.33E-05 Co-60 O.OOE+00 1.44E-06 1.85E-06 O.OOE+00 O.OOE+00 46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 O.OOE+00 O.OOE+00 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 O.OOE+00 O.OOE+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.69E-11 O.OOE+00 5.78E-10 8.48E-07 6.12E-06 Zn-65 '4;05E-06 1.29E-05 5."82E-06 O.OOE+00 8.62K-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 O.OOE+00 5 '7E-12 1.15E-07 2.04E-09 Zn-69m 1.02E-09 2.45E-09 2.24E-10 O.OOE+00 1.48E-09 2.38E-06 1.71E-05 Br-82 0.00E+00 0.00E+00 1. 69E-06 0.00E+00 O.OOE+00 O.OOE+00 1.30E-06 Br-83 O.OOE+00 0.00E+00 3.01E-OS 0.00E+00 O.OOE+00 O.OOE+00 2.90E-OS Br-84 O.OOE+00 O.OOE+00 3.91E-OS O.OOE+00 O.OOE+00 O.OOE+00 2.05E-13 Br-85 O.OOE+00 O.OOE+00 1.60E-09 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 1.69E-05 7.37E-06 0;OOE+00 0.00E+00 0.00E+00 2.08E-06 Rb-88 O.OOE+00 4.84E-08 2.41E-08 O.OOE+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 O.OOE+00 3.20E-OS 2.12E-OS O.OOE+00 O.OOE+00 O.OOE+00 1.16E-21
,Sr-89 3.80E-05 0.00E+00 1.09E-06 O.OOE+00 O.OOE+00 1.75E-04 4.37E-05 Sr-90 1.24E-02 O.OOE+00 7.62E-04 O.OOE+00 O.OOE+00 1.20E-03 9.02E-05 Sr-91 7.74E-09 0.00E+00 3.13E-10 O.OOE+00 O.OOE+00 4.56E-06 2.39E-05 Sr-92 8.43E-10 O.OOE+00 3.64E-ll 0.00E+00 0.00E+00 2.06E-06 5.38E-06 Y-90 2.61E-07 0.00E+00 7.01E-09 O.OOE+00 0.00E+00 2.12E-05 6.32E-05 Y-91m 3.26E-11 O.OOE+00 1.27E-12 O.OOE+00 O.OOE+00 2.40E-07 1.66E-10 Y-91 5.78E-05 0.00E+00 1.55E-06 O.OOE+00 O.OOE+00 2.13E-04 4.81E-05 Y-92 1.29E-09 O.OOE+00 3.77E-ll 0.00E+00 O.OOE+00 1.96E-06 9.19E-06 Y-93 1.18E-OS 0.00E+00 3.26E-10 0.00E+00 O.OOE+00 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 O.OOE+00 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 O.OOE+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 0.00E+00 9.67EW7 6.31E-05 1.30E-05 Nb-97 2.78E-11 7.03E-12 2.56E-12 O.OOE+00 8.18E-12 3.00E-07 3.02E-OS Mo-99 O.OOE+00 1.51E-OS 2.87E-09 O.OOE+00 3.64E-OS 1.14E-05 3.10E-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 O.OOE+00 5.52E-12 9.55E-OS 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 0.00E+00 1.35E-13 4.99E-OS 1.36E-21 RLL-103 1.91E-07 O.OOE+00 8.23E-OS O.OOE+00 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-11 O.OOE+00 3.89E-11 0.00E+00 1.27E>>10 1.37E-06 6.02E-06 Ru-106 8.64E-06 O.OOE+00 1.09E-06 O.OOE+00 1.67E-05 1.17E-03 l.l.4E-04 Ag-110m 1.35E-06 1. 25E-06 7.43E-07 O.OOE+00 2.46E-06 5.79E-04 3-78E-05 General Revision 0530p
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C""TS '~mewl Revision 5 Page 138 Table 1.10 (2 oi 8)
INHALATIGN DOSE FACTORS (mrem/pCi inhaled)
ADULT bone liver t body thyroid kidney lung gi-lli Sb-124 3. 90E&6 7.36E-OS 1..55E-06 9.44E-09 O.OOE+00 3.10E-04 5.08E-05 Sb-125 6.67E-06 7.44E-08 1.58E-06 6 '5E-09 O.OOE+00 2. 18E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-OS 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.1.4E-07 7.17E-06 Te-129m 1. 22E&6 5.84E-07 1..98E-07. 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-OS Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-OS 1.S2E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 3.25E-OS 2. 69E&8 2.02E-OS 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6. 60E-07 1.42E-04 2.61E-06 O.OOE+00 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 O.OOE+00 7.85E-07 I-132 1. 45E-07 4.07E-07 1. 45E-07 1.43E-05 6.48E-07 O.OOE+00 5.08E-OS I-133 1.08E-06 1.SSE-06 S. 65E-07 2.69E-04 3.23E-06 0.00E+00 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10
" "3.35E-'07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 O.OOE+00 6.56E-07 I-135's-134 4.66E-05 1.06E-04 9.10E-05 O.OOE+00 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.S3E-05 l. 38E-05 O.OOE+00 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-O5 O.OOE+00 2.78E-O5 9.40E-06 1.05E-06 Cs-138 4.14E-OS 7.76E-OS 4.05E-OS O.OOE+00 6.00E-OS 6.07E-09 2.33E-1.3 Ba-139 1.17E-10 8.32E-14 3.42E-12 0.00E+00 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 O.OOE+00 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 O.OOE+00 8.7SE-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 O.OOE+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-OS 2.17E-OS 5.73E-09 O.OOE+00 O.OOE+00 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.6SF;12 O.OOE+00 O.OOE+00 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1. 91E7 O.OOEw00 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-OS 1.72E-OS 1.91E-09 O.OOE+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-OS 0.00E+00 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-OS 0.00E+00 2.70E-07 3.51E-05 2.50E-05 Pr-144. 3.76E-12 1.56E-12 1.91E-13 0.00E+00 8.81E-13 1.27E-07 2. 69E-18 Nd-147 6.59E-07 7.62E-07 4.56EMS 0.00E+00 4.45 E-07 2.76E-05 2. 16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 0.00E+00 O.OOE+00 3.63E-06 1.94E-05 Np-239 2.87E-OS 2.82E-09 1.55E-09 O.OOE+00 8.75E-09 4.70E-06 1.49E-05
Reference:
Regulatory Guide 1.109, Table E-7.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e Soecific Radiation Dose Comnitzent ".>>actors for a One Year Chronic Intake November 1977, Table 8.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
General Revision 0530p
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RETS Manual Revision 5 Page 139 Table 1.I.O (3 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
TEEN bone liver t body thyroid kidney lung gi-lli H-3 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3. 25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1. 72E-06 1.72E06 1.72E-06 1.72E06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.16E-05 Cr-51 O.OOE+00 O.OOE+00 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 O.OOE+00 6.39E-06 1.05E&6 O.OOE+00 1.59E-06 2.48E-04 8.35E-06 Mn-56 O.OOE+00 2.12E-10 3. 15E-11 O.OOE+00 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 O.OOE+00 O.OOE+00 l. 55E-05 7.99E-07 Fe-59 1. 99E&6 4.62E-06 1.79E-06 O.OOE+00 O.OOE+00 1.91E-04 2.23E-05 Co-57 O.OOE+00 1.18E-07 1.15E-07 O.OOE+00 0.DOE+00 7.33E-05 3.93E-06 Co-58 0.00E+00 2.59E-07 3.47E-07 0.00E+00 O.OOE+00 1.68E-04 1.19E-05
'Co-60 O.DOE+00 1.89E-06 2.48E-06 O.OOE+00 O.OOE+00 1.09E-03 3.24E-05 Ni-63 7. 25E-05 5.43E-06 2.47E-06 O.OOE+00 O.OOE+00 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-11 O.OOE+00 O.OOE+00 1.17E-06 4.59E-06 Cu-64 0. OOE+00 2.54E-10 ~ 1.06E-10 O.OOE+00 8.01E-10 1.39E-06 7.68E-06
'Zn-65 4. 82E-06 1.67E-05 7.80E-06 O.OOE+00 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 O.OOE+00 7.53E-12 1.98E-07 3.56E-08 Zn-69m 1.44E-09 3.39E-09 3.11E-10 O.OOE+00 2.06E-09 3.92E-06 2.14E-05 Br-82 O.OOE+00 0.00E+00 2.28E-06 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 0.00E+00 4.30E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00
. Br-84 0.00E+00 O.OOE+00 5.41E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 2.29E-09 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Rb-86 O.OOE+00 2.38E-05 1.05E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.21E-06 Rb-88 0.00E+00 6.82E-08 3.40E-08 O.OOE+00 O.OOE+00 0.00E+00 3.65E-15 Rb-89 O.OOE+00 4.40E-08 2.91E-08 O.OOE+00 O.OOE+00 O.OOE+00 4.22E-17 Sr-89 5.43E-05 O.OOE+00 1.56E-06 0.00E+00 O.OOE+00 3.02E-04 4.64E-05 Sr-90 1.35E-02 0.00E+00 8.35E-04 O.OOE+00 0.00E+00 2.06E-03 9.56E-05 Sr-91 1.10E-08 0.00E+00 4.39E-10 O.OOE+00 O.OOE+00 7.59E-06 3.24E-05 Sr-92 1.19E-09 0.00E+00 5.08E-11 0.00E+00 O.OOE+00 3.43E-06 1.49E-05 Y-90 3.73E-07 0.00E+00 1.00E-08 0.00E+00 O.OOE+00 3.66E-05 6.99E-05
,Y-.91m- 4.63E-ll O.OOE+00 1.77E-12 0.00E+00 O.OOE+00 4.00E-07 3.77E-09 Y-91 8.26E-05 0.00E+00 2.21E-06 O.OOE+00 0.00E+00 3.67E-04 5.11E-05 X-92 1.84E-09 0.00E+00 5.36E-11 O.OOE+00 O.OOE+00 3.35E-06 2.06E-05 Y-93 1.69E-08 O.OOE+00 4.65E-10 O.OOE+00 O.OOE+00 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 O.OOE+00 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 O.OOE+00 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 0.00E+00 1. 25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-11 9.72E-12 3.55E-12 O.OOE+00 1.14E-11 4.91E-07 2.71E-07 Mo-99 O.OOE+00 2.11E-08 4.03E-09 O.OOE+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 O.OOE+00 7.20E-12 1.44E-07 7.66E-07 Tc-l.01 7.40E-15 1.05E-14 1.03E-13 O.OOE+00 1.90E-13 8.34E-08 1.09E-16 RG-103 2.63E-07 0.00E+00 1.12E-07 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 O.OOE+00 5.42E-11 O.OOE+00 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 0.00E+00 1.55E-06 O.OOE+00 2.38E-05 2.01E-03 1 . 20E-04 Ag-110m 1.73E-06 1.64E-06 9.99E-07 0 OOE+00 3.13E-06 8.44E-04 3.41E-05 General Revision 0530p
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RETS "fan~1 Revision 5 Page 140 Table 1.10 (4 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
TEEN bone liver t body thyroid kidney lung gi-lli Sb-124 5.38E-06 9.92E-OS 2.10E-06 1.22E-08 O.OOE+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01E-07 2.15E-06 S.SOE-09 O.OOE+00 3.42E-04 1.24E-05 Te-125m 6.10E-07 2.80E-07 8.34E-OS 1. 75E-07 O.OOE+00 6.70E-05 9.38E-06 Te-127m 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te>>127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131m 1.23E-OS 7.51E-09 5.03E-09 9.06E-09 5.49E-OS 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-OS 2.74E-OS 3.07E-OS 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 O.OOE+00 8.11E-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 O.DOE+00 1.59E-07 I-133 1.52E&6 2. 56E&6 7.78E-07 3.65E-04 4.49E-06 O.OOE+00 1.29E-06 I-134 1.11E-07 2. 90E-07 1.05E-07 4.94E-06 4.58E-07 O.OOE+00 2.55E-09
'I-'135 4.6'2E&7 1.18E-06 4.36E-07 7.76E-05 1;86E-06 O.OOE+00 8.69E-07 1.41E-04 6.86E-05 4.69E-05 1.83E-05 1.22E-06 Cs<<134 28E&5 O.OOE+00 Cs-136 6.44E-06 2.42E-05 1.71E-05 O.OOE+00 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 O.OOE+00 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-OS 1.07E-07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-11 Ba-139 1.67E-10 1.18E-13 4.87E-12 O.OOE+00 1.11E-13 S.OSE-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 O.OOE+00 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 O.OOE+00 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 0.00E+00 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-OS 2.95E-OS 7.82E-09 0.00E+00 0.00E+00 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-ll 1.32E-11 O.OOE+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 O.OOE+00 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-OS 2.42E-OS 2.70E-09 O.OOE+00 1.08E-OS 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.'67E-06 6.64E-07 8.28E-08 O.OOE+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 O.OOE+00 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 O.OOE+00 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 O.OOE+00 0.00E+00 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 O.OOE+00 1.25E-OS 8.11E-06 1.65E-05
Reference:
Regulatory Guide 1.109, Table E-8.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e Soecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 7.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
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RETS M~nual Revision 5 Page 141 Table 1.10 (5 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
CHILD I bone liver t body thyroid kidney lung gi-lli H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3. 04E-07 3.04E-07
~ J C-14 9. 70E&6 1.82E&6 1. 82E-06 1.82E-06 1.82E-06 1.82E-06 1.828-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-O6 4.35E-06 P-32 7.04E-O4 3.09E-05 2.67E-05 O.OOE+00 0.00E+00 O.OOE+00 1.14E-05 Cr-51 0.00E+00 O.OOE+00 4.17E-OS 2.31E-OS 6.57E-09 4.59E-06 2.93E-07 Mn-54 O.OOE+00 1.16E-05 2.57E-06 O.OOE+00 2.71E-06 4.26E-04 6.19E-06 Mn-56 O.OOE+00 4.48E-10 8.43E-11 O.OOE+00 4.52E-10 3.55E-06 3.33E-05 Fe-55 l. 28E&5 6.80E-06 2. 10E-06 O.OOE+00 O.OOE+00 3.00E-05 7.75E-07 Fe-59 5.59E&6 9.04E-06 4.51E-06 O.OOE+00 O.OOE+00 3.43E-04 1.91E-05 Co-57 0.00E+00 2.44E-07 2.88E-07 O.OOE+00 O.OOE+00 1.37E-04 3.58E-06 Co-58 O.OOE+00 4.79E-07 8.55E-07 0.00E+00 O.OOE+00 2.99E-04 9. 29EW6 Co-60 O.OOE+00 3.55E-06 6.12E-06 O.OOE+00 O.OOE+00 1.91E-03 2.60E-05 Ni-63 2. 22E&4 1.25E-05 7.56E-06 O.OOE+00 O.OOE+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-ll 4.44E-11 O.OOE+00 O.OOE+00 2.21E-06 2.27E-05 CLL-64 O.OOE+00 5.39E-10 2.90E-10 O.OOE+00 1.63E-09 2.59E-06 9.92E-O6
" 'Zn-'65 1.15E-05 3.06E-05 1.90E-05 0.00E+00 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-11 2.61E-ll 2.41E-12 .0. OOE+00 1.58E-11 3.84E-07 2. 75E-06 Zn-69m 4.26E-09 7. 28E&9 8.59E-10 O.OOE+00 4.22E-09 7.36E-06 2.71E-05 Br-82 O.OOE+00 0.00E+00 5.66E-06 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Br-83 O.OOE+00 0.00E+00 1.28E-07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 0.00E+00 0.00E+00 1.48E-07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 0.00E+00 6.84E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 '5.36E-05 3.09E-05 0.00E+00 O.OOE+00 O.OOE+00 2. 16F;06 Rb-88 0.00E+00 1.52E-07 9.90E-08 O.OOE+00 0.00E+00 O.OOE+00 4.66E-09 I Rb-89 0.00E+00 9.33E-OS 7.83E-OS 0.00E+00 0.00E+00 O.OOE+00 5.11E-10 Sr-89 1.62E-04 0.00E+00 4.66E-06 0.00E+00 O.OOE+00 5.83E-04 4.52E-05 Sr-90 2.73E-02 0.00E+00 1.74E-03 O.OOE+00 0.00E+00 3.99E-03 9.28E-05 I Sr-91 3.28E-OS 0.00E+00 1.24E-09 O.OOE+00 O.OOE+00 1.44E-05 4.70E-05
-.il Al&hhh Sr-92 3.54E-09 0.00E+00 1.42E-10 0.00E+00 O.OOE+00 6.49E-06 6.55E-05 Y-90 1.11E-06 0.00E+00 2.99E-OS 0.00E+00 0.00E+00 7.07E-05 7.24E-05 Y-91m .1.37E-10 0.00E+00 4.98E-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07
% 'i Y-91 2.47E-04 0.00E+00 6.59E-06 O.OOE+00 0.00E+00 7.10E-04 4.97E-05 Y-92 5.50E-09 0.00E+00 1.57E-10 O.OOE+00 O.OOE+00 6.46E-06 6.46E-05 Y-93 5.04E-OS O.OOE+00 1.38E-09 0.00E+00 O.OOE+00 2.01E-05 1.05E-04
'9 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-OS 7.34E-09 4.32E-09 0.00E+00 1.05E-OS 3.06E-05 9.49E-05
,V 1
Nb-95 6.35E-06 2.48E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00E-05
~ '.1 Nb-97 1.16E-10 2.08E-11 9.74E-12 O.OOE+00 2.31E-11 9.23E-07 7.52E-06
~~
J Mo-99 O.OOE+00 4.66E-08 1.15E-OS O.OOE+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 0.00E+00 1. 37E-11 2.57E-07 1.30E-06 1
1 Tc-101 2.19E-14 2.30E-14 2.91E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-09 RQ-103 7.55E-07 0.00E+00 2.90E-07 0.00E+00 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 O.OOE+00 1.50E-10 0.00E+00 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 O.OOE+00 4.57E-06 0.00E+00 4.97E-05 3.87E-03 1 ~ 16E-04 Ag-110m 4.56E-06 3.08E-06 2.47E-06 O.OOE+00 5.74E-06 1.48E-03 2- 71E-05
~ 'I General Revision 0530p
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RETS Nanyal Revision 5 Page 142 Table 1.10 (6 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
CHILD bone liver t body thyroid kidney lung gi-lli Sb-124 1.55E-05 2.00E-07 5.41E-06 3.41E-OS O.OOE+00 8. 76E-04 4.43E-05 Sb-125 2. 66E<5 2.05E-07 5.59E-06 2.46E&8 O.OOE+00 6.27E-04 1.09E-05 Te-125m 1.82E-06 6. 29E-07 2.47E-07 5. 20E-07 O.OOE+00 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31E&6 8.16E-07 1.64EW6 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E&6 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4. 76E-04 4.91E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-OS 1.37E-OS 2.64E-OS 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3. 60E-07 Te-132 1.30E-07 7.36E-OS 7.12E-08 8.58E-OS 4.79E-O7 '.02E-04 3.72E-05 I-130 2.21E-O6 4.43E-06 2.28E-06 4. 99E-04 6 ~ 61EW6 O.OOE+00 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-O6 4.39E-03 2.13E-05 O.OOE+00 7.68E-07 I-132 5.72E-07 1.10E-O6 5.07E-07 5.23E-05 1.69E-06 O.OOE+00 .8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 O.OOE+00 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 O.OOE+00 2.58E-07
'I-135 ' 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 O.OOE+00 1.20E-06 Cs-134 1.76E'-04 2.74E-O4 6.07E-05 O.OOE+00 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-O5 3.14E-O5 0.00E+00 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 O.OOE+00 7.63E>>05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2. 27E-07 1.50E-07 O.OOE+00 1. 68E-07 1.84E-OS 7.29E-OS
'a-139 4.98E-10 2.66E-13 1.45E-ll O.OOE+00 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-OS 1.17E-06 O.OOE+00 5.71E-09 4.71E-04 2. 75E-05 Ba-141 5.29E-11 2.95E-14 1.72E-12 O.OOE+00 2.56E-14 7.89E-07 7. 44E-08 Ba-142 1.35E-11 9.73E-1.5 7.54E-13 O.OOE+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-OS 2.04E-08 0.00E+00 O.OOE+00 4.94E-05 6.10E-05 La-142 3.50E-10 1.11E-10 3.49E-11 O.OOE+00 O.OOE+00 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 0.00E+00 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-OS 5.37E-OS 7.77E-09 O.OOE+00 2.26E-OS 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 O.OOE+00 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 0.00E+00 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E<<12 8.10E-13 O.OOE+00 2.64E-12 4.23E-07 5.32E-OS Nd-147 2.92E-06 2.36E-06 1.84E-07 O.OOE+00 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2. 61E-09 1.17E-09 O.OOE+00 O.OOE+00 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 O.OOE+00 2.63E-OS 1.57E-05 1.73E-05
Reference:
Regulatory Guide 1.109, Table E-9.
',I
'C Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from
~
A NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year
'\ ~
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,s$
'i NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
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.. General Revision 0530p
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RETS Manual Revision 5 Page 143 Table 1.10 (7 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
INFANT bone liver t body thyroid kidney lung gi-lli
C C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06
~ ~
Na-24 7.54E-O6 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E+05 5.53E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.15E-05 Cr-51 O.OOE+00 O.OOE+00 6.39E-08 4.11E-08 9.45E-09 9 .'1 7E-06 2.55E-07 Mn-54 O.OOE+00 1.81E-05 3.56E-06 0.00E+00 3.56E-06 7.14E-04 5.04E-06 Mn-56 O.OOE+00 1.10E-09 1.58E-10 O.OOE+00 7.86E-10 8. 95EW6 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 O.OOE+00 O.OOE+00 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 0.00E+00 O.OOE+00 7.25E-04 1.77E-05 Co-57 O.OOE+00 4.65E-07 4.58E-07 0.00E+00 O.OOE+00 2.71E-04 3.47E-06 Co-58 0.00E+00 8.71E-07 1.30E-06 O.OOE+00 0.00E+00 5.55E-04 7.95E-06
~ .1 Co-60 0.00E+00 5.73E-06 8.41E-06 O.OOE+00 O.OOE+00 3.22E-03 2.28E-05 I Ni-63 2.42E-04 1.46E-05 8.29E-06 O.OOE+00 O.OOE+00 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-11 0.00E+00 0.00E+00 5.80E-06 3.58E-05 CLI-64 0.00E+00 1.34E-09 5.53E-10 O.OOE+00 2.84E-09 6.64E-06 1.07E-05
" Zn-65 1.38E-05 4.47E-05 2. 22E&5 O.OOE+00 2.32E-05 4.62E-04 3.67E-05 Zn-'69 3.85E-11 6.91E-11 5.13E-12 O.OOE+00 2.87E-11 1.05E-06 9.44E-06 Zn-69m 8.98E-09 1.84E-08 1.67E-09 O.OOE+00 7.45E-09 1.91E-05 2.92E-05 Br-82 O.OOE+00 ,0. OOE+00 9.49E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 r Br-83 0.00E+00 O.OOE+00 2.72E-07 O.OOE+00 O.OOE+00 0. OOE+00 O.OOE+00
~ i Br-84 O.OOE+00 O.OOE+00 2.86E-07 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 J
Br-85 0.00E+00 0.00E+00 1.46E-08 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Rb-86 O.OOE+00 1.36E-04 6.30E-05 0.00E+00 O.OOE+00 O.OOE+00 2.17E-06 Rb-88 0.00E+00 3.98E<<07 2.05E-07 0.00E+00 0.00E+00 0.00E+00 2.42E-07
.Rb-89 0.00E+00 2.29E-07 1.47E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.87E-08 Sr-89 2.84E-04 O.OOE+00 8. 15E-06 0.00E+00 O.OOE+00 1.45E-03 4.57E-05
~~
Sr-90 2.92E-02 0.00E+00 1.85E-03 O.OOE+00 O.OOE+00 8.03E-03 9.36E-05
~ 'I Sr-91 6.83E-08 O.OOE+00 2.47E-09 O.OOE+00 O.OOE+00 3.76E-05 5.24E-05 Sr-92 7.50E-09 O.OOE+00 2.79E-10 O.OOE+00 0.00E+00 1.70E-05 1.00E-04 Y-90 2.35E-06 O.OOE+00 6.30E-08 0.00E+00 0;OOE+00 1.92E-04 7.43E-05 Y-91m 2.91E-10 0;OOE+00 9.90E-12 0.00E+00 O.OOE+00 1.99E-06 1.68E-06
.Y.-91 4.20E-04 O.OOE+00 1.12E&5 O.OOE+00 O.OOE+00 1.75E-03 5.02E-05 r Y-92 1.17E-08 0.00E+00 3.29E-10 O.OOE+00 O.OOE+00 1.75E-05 9.04E-05
),' Y-,93 1.07E-07 0.00E+00 2.91E-09 0.00E+00 0.00E+00 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 0.00E+00 2.22E-05 1. 25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 O.OOE+00 '1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 O.OOE+00 3.37E-06 3.42E-04 9.05E-06 Nb-97 2.44E-10 5.21E-11 1.88E-11 O.OOE+00 4.07E-11 2.37E-06 1.92E-05 Mo-99 O.OOE+00 1.18E-07 2.31E-08 O.OOE+00 1.89E-07 , 9.63E-05 3.48E-05, I Tc-99m 9.98E-13 2.06E-12 2.66E-11 0.00E+00 , 2.22E-11 5. 79EW7 1.45E-06 1%4 Tc-101 4.65E-14 5.88E-04 5.80E-13 O.OOE+00 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 O.OOE+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1.15E-05
, C Ru-105 8.74E-10 O.OOE+00 2.93E-10 O.OOE+00 6.42E-10 1.12E-05 3.46E-05
-1 Ru-106 6.20E-05 O.OOE+00 7.77E-06 O.OOE+00 7.61E-05 8.26E-03 1.17E-04 I Ag-110m 7.13E-06 5.16E-06 3.57E-06 0.00E+00 7.80E-06 2. 62EW3 2.36E-05
~ r
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RETS "fan,ual Revision 5 Page 144 Table 1.10 (8 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
INFANT bone liver t body thyroid kidney lung gi-lli Sb-124 2. 71E-05 3.97E-07 8. 56E-06 7.18E-08 O.OOE+00 1.89E-03 4.22E-05 Sb-125 3.69E-05 3.41E-07 7. 78E-06 4.45E-08 O.OOE+00 1.17E-03 1.05E-05 Te-125m 3.40E-06 1.42E-06 4.70E-07 1.16E-06 O.OOE+00 3.19E-04 9.22E-06 Te-127m 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E&6 1.74E-05 Te-129m 1.01E&5 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1. 20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E 11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E08 3.93E-08 2.59E-O8 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1 ~ 24E-11 5.87E-12 3-57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-132 2.66E-O7 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 O.OOE+00 1.42E-06 I-131 2. 71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 O.OOE+00 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0.00E+00 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 O.OOE+00 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-07
" .'I-135 '-2. 76E06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 O.OOE+00 1.31E~06 Cs-134 2.83E-04 5.02E-04 5.32E-05 O.OOE+00 1.36E-04 5.69E&5 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 O.OOE+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3. 25E-05 O.OOE+00 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 O.OOE+00 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 O.OOE+00 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 O.OOE+00 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 O.OOE+00 4.64E-14 2. 12E&6 3.39E-06 Ba-142 2.84E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 0.00E+00 O.OOE+00 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 O.OOE+00 O.OOE+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 0.00E+00 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 0.00E+00 4.03E-08 8.30E-05 3.55E-05
~
Ce ]44 2.28E-03 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-,11 1.32E-11 1.72E-12 O.OOE+00 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 0.00E+00 2.25E-06 2.30E-04 2.23E-05 W-187 9. 26E-09 6.44E-09 2.23E-09 0.00E+00 O.OOE+00 2.83E-05 2.54E-05 Np-239 2. 65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05 Reference Regu latory Guide 1;109, Table E-10.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5.
NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.
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RETS ~!anual Revision.5 Page 145 Table 1.11 (1 of 2)
EXT"-RNAL DOSE FACTORS FOR STANDING ON CONTANINATED GROlPQ (mrem/h per pCi/m~)
Nuclide To tal Body Skin H-3 0.0 0.0 C-14 0.0 0.0 24 2.50E-OS 2.90E-OS
?-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 M-54 5.80E-09 6.80E-09 Nn-56 1.10E-OS 1.30E-OS Fe-55 0.0 0.0 Fe-59 S.OOE-09 9.40E-09 Co-57 1.77E-09 2.21E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-OS 2.00E-OS Ni-63 0.0 0.0 Ni-65 3. 70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m . 5.50E-09 6.59E-09 Br-82 3.18E-OS 3.90E-08 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-OS 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-OS 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-OS Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11
'-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09" 5.80E-09 Zr-97 5. 50E-09 6.40E-09 Nb-95 5. 10E-09 6.00E-09 Nb-97 8. 11E-09 1.00E-OS No-99 1. 90E-09 2. 20E-09 Tc-99m 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 RQ-103 3.60E-09 4.20E-O9 Ru-105 4.50E-O9 5.10E-O9 Ru-106 1.50E-09 1.80E-09 Ag-110m 1.80E-OS 2.10E-OS Sb-124 2.17E-OS 2.57E-08 General Revision 0530p .
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RETS .'manual Revision 5 Page 146 Table 1.11 (2 of 2)
EXTERNAL DOSE FACTORS FOR STA KING ON CONTA fINATED GROIN (mrem/h per pCi/m~)
Nuclide Total Body Skin Sb-125 5 48E-09 6.80E-09 Te-125m 3.50E-ll 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129m 7. 70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131m 8 40E-09 9 '0E-09 Te-131 2.20E-09 2-60E-06 Te-132 1.70E-09 2.00E-09 I-130 1 40E-08 1.70E-08 I-131 2 80E-09 3-40E-09 I-132 1-70E-08 2.00E-08 I-133 3 70E&9 4.50E-09 I-134 1. 60E-08 1.90E-08 I-135 1-20E-08 1.40E-08
'Cs-134 1.20E-08 1.40E-08 Cs-136 1-50E-08 1.70E-OS
,Cs-137 4.20E-09 4-90E-09 Cs-138 2.10E-08 2.40E-08 Ba-l.39 2.40E-09 2.70E-09 Ba-140 2.10E-09 2 40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-OS 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6 20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10
. Nd-147 1.00E-O9 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1-10E-09
References:
Regulatory Guide 1.109, Table E-6.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Ex osure to Photon and Electron Radiation from Radionuclides Occurrin in Routine Releases from Nuclear Fuel C cle Facilities D. C. Kocher, Health Physics Volume 38, April 1980.
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RETS Manual Revision- 5 Page 147 Table 2.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Name Beginning Ending Size Recreation TRM TRM (acres) visits/year Wheeler Lake 294.0 275.0 26076 1,408,600 below BFN Wilson Lake 275.0 260.0 15930 3,816,800 Pickwick Lake 260.0 230.0 15048 705,500 Public Water Supplies Within 50 Mile Radius Downstream of BFN Name Population Muscle Shoals, AL 259. 6 10,740 Sheffield, AL 254. 3 13,065 Cherokee, AL 239. 2 3,400 General Revision 0530p
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RETS Manual Revision- 5 Page 148 Table 2.2 BIOACCUWL LATION FACTORS FOR FRESHWATER FISH (Page 1 of 1)
Nuclide Nuclide H-3 9.0E-01 Tc-101 1.5E+101 C-14 4.6E+03 Ru-103 1.0E+01 Na-24 1.0E+02 Ru-105 1.0E+01 P-32 1.0E+05 Ru-106 1.0E+01 Cr-51 2.0E+02 Ag-110m O.OE+00 Mn-54 4.0E+02 Sb-124 1.0E+00 Mn-56 4.0E+02 Sb-125 1.0E+00 Fe-55 1.0E+02 Te-125m 4.0E+02 Fe-59 1.0E+02 Te-127m 4.0E+02 Co-57 5.0E+01 Te-127 4.0E+02 Co-58 5.0E+01 Te-129m 4.0E+02 Co-60 5.0E+01 Te-129 4.0E+02 P
~
Ni<<63 1.0E+02 Te-131m 4.0E+02 I Ni-65 1.0E+02 Te-131 4.0E+02
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I Cu-64 5.0EWl Te-132 4.0E+02 Zn-65 2.0E+03 I-130 4.0E+01
'Zn-69 , 2.0E+03 I-131 4.0E+01 Zn-69m 2.0E+03 I-132 4.0E+01 Br-82 4.2E+02 I-133 4.0E+01 Br-83 4.2E+02 I-134 4.0E+01 Br-84 4.2E+02 I-135 4.0E+01 Br-85 4. 2E+02 Cs-134 1.9E+03 Rb-86 2.0E+03 Cs-136 1.9E+03 Rb-88 2.0E+03 Cs-137 1.9E+03 Rb-89 2.0E+03 Cs-138 1.9E+03 Sr-89 5.6E+01 Ba-139 4.0E+00 Sr-90 5.6E+01 Ba-140 4.0E+00 Sr-91 5.6E+01 Ba-141 4.0E+00 Sr-92 5.6E+01 Ba-142 4.0E+00
-Y-90 2.5E+01 La-140 2.5E+01 Y-91m 2.5E+01 La-142 2.5E+01
,Y-91 2.5E+01 Ce-141 1.0E+00 Y-92 2.5E+01 Ce-143 1.0E+00 Y-93 2.5E+01 Ce-144 1.0E+00 Zr-95 3.3E+00 Pr-143 2.5E+Ol Zr-97 3 'E+00 Pr-144 2.5E+01 Nb-95 3.0E+04 Nd-147 2.5E+01 Nb-97 3.0E+04 W-187 1.2E+03 Mo-99 1.0E+01 Np-239 1.0E+01
References:
Bioaccumulation factors for Sb- nuclides are from ORNL-4992, "A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A.
Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.
All other nuclides'ioaccumulation factors are from Regulatory Guide 1.109, Table A-l.
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RETS Hanual Revision 5 Page 152 TABLE 3.1 (Sheet 4 of 4)
ENVI RONHENTAL RAOIOLOGICAL HONITORING
~i Exposure Pathway Fish Number of Samples Locations and 3 samples representing commercial Sampling and At least once per 184 days Type and Frequency Gamma of Anal sis scan at least once per and game species in Guntersville 184 days on edible portions, Reservoir above the plant 3 samples representing commercial and game species in Wheeler Reservoir near the plant 3 samples representing commercial and game species in Wilson Reservoir near the plant Clams Sample from same locations as Same as sediment Gamma scan on flesh only sediment (if available)
Fruits & Samples of food crops such as At least once per year at Gamma scan on edible portion Vegetables corn, green beans, tomatoes, time of harvest and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from the nearby dairy Once per 31 days I-131, gamma scan once per (pasturage farms (Farms B, Bn, L and T), and 31 days. Sr-89 and Sr-90 and grass) from the local atmospheric mon- analysis on'the last monthly i*toring stations (LH-1, LH-2, sample of each quarter.
LH-3, LH-4, LH-6 and LH-7)
Control samples from remote air 1
monitor (RH-1) and 1 control dairy farm (Farm 0)
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RETS Manual Revision. 5 Page 153 TABLE 3 ' A BROWNS FERRY itUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Approximate Indicator (I)
Location Distance or Samples Number a Station Sector (Miles) Control (C) Collected>
1 PM-1 NW 13.8 I AP, CF, S 2 PM-2 NE 10.9 I AP, CF, S 3 PM-3 SSE 8.2 I AP, CF, S 4 LM-7 W 2.1 I AP, CF, S, V 5 RM-1 W 31.3 C 6 RM-6 E 24.2 C AP, CF, S
~ ~ 7 LM-1 N 0.97 I AP, CF, S, V 8 LM-2 NNE 0.88 I
,I 9 LM-3 ENE 0.92 I 10 LM-4 NNM 1.7 I
~ I 11 LM-6 SSW 3.0 I
~
V ti 12 Farm B NNW 6.8 I M, V 13 Farm Bn N 5.0 I M, V 14 Farm L ENE 5.9 I M, V, M
.22 Well 86 NW 0.02 I W 23 c 282 6 11.4d I PM 24 TRM 303.0 12.0 C PM 25 Muscle Shoals, AL W 31.3 I PM 26 TRM 274.9 19.1d I PW
~
1 0 28 TRM 293.5 O.Sd I SM 29 TRM 305.0 11 Od Ce SW 30 TRM 307.52 13.52 C CL, SD 31 TRM 293.7 0.3d I CL, SD 32 TRM 288.78 s.zzd I CL, SD 33 TRM 277.98 16 02 I CL, SD 34 Farm Be NW 28.8
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WNM 26.2 3.2 C
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'Wilson'Reservoir I F (TRM zs9-27s)
Wheeler Reservoir (TRM 275-349)
Guntersville Reservoir (TRM 349-424) a See figures 3.1, 3.2, and 3.3 b Sample codes:
li AP ~ Air particulate filter S = Soil SD = Sediment
~
CF ~ Charcoal Filter SW = Surface Water CL ~ Clams 4
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F ~ Fish V = Vegetation PW ~ Public Water W ~ Well Water
~ I c TRM ~ Tennessee River Mile d Miles from plant discharge'(TRM 294) e Also used as a control for public water General Revision 0530p
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RETS "ianual Revision .5 Page 173 Figure 3.2 Environmental Radiological Sampling Locations
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i'4 Those listed FROM D. R. Gallien, Supervisor, Chemical Technical Support Section,'rowns Ferry Nuclear Plant DATES
SUBJECT:
BROWNS FERRY NUCLEAR PLANT (BFN) INOPERABLE'ADIOACTIVE EFFLUENT INSTRUMENT REPORT COMMITMENT DATES Attached is the draft of the semi-annual Inoperable Radioactive Effluent Instrument Report prepared by the Chemical Technical Support Section. A breakdown of the completion dates for work involving several groups follows:
Responsible Comp
~Grou Item Date Liquid Process Rad ation Monitors:
Mods Complete field work 4-22-88 PMT Complete Post Mod Test 5-20-88 CTS Source check SI written and approved 5-20-88 ISC Tech Calibration and Functional SIs 5-20-88 0 IMs written Run New Liquid and approved SIs Radwaste 6-17-88 Effluent Instrumentation:
PMT Complete Post Mod Test 4-29-88 IRC Tech New SIs written and approved 4-29-88 IMs Run ne SIs 5-27-88 Other dates involving only instrument maintenance (IM) are listed in the report. It is important that the dates committed to in the semi-annual report be met. Please rev ew those commitments related to your section and contact John Wilson at ex ension 2652 by January 28, 1988 if you cannot meet the commitment date.
D. R. Gallien G. A. artsfield, BFN J. A. Savage, BFN A. W."McCaleb, BFN T. E. Scott, BFN P. McGraw, BFN R. L. Smith, BFN S. H. McRight, BFN JAW:LSM Attachment cc (Attachment):
RIMS, MR 4N'72A-(
This was prepared principally by P. S. Kirby.
1 ~t TO Patrick P. Carier, Manager of Site Licensing, PAB C, Browns Ferry Nuclear Plant ROM Guy G. Campbell, Plant Manager, POB C, Browns Ferry Nuclear Plant DATE
SUBJECT:
BROWNS FERRY NUCLEAR PLANT TRANSMITTAL OF INOPERABLE RADIOACTIVE EFFLUENT INSTRUMENT REPORT
/
/
Attached is~the Inoperable Radioactive Effluent Instrument Report for the period from January 1 through June 30, 1989. The report was prepared by the Chemistry Techhical Support Section for incorporation into the Semi-annual Radioactive Rel ase Report, /in Operations 3.2.K 2 and 3.2 D.2.
accordance with Limiting Conditions of Guy G. Campbell DCS:NMM:PSK:TRS Attachment cc (Attachment):
RIMS, MR 4N 72A-C J. L. Bates,~ CST 11A 8A-,C W. Christopher, PMB A, BFN C. M. Crane, PMC F, BFN J. W. Hutton, POB E, BFN T. E. Scott, PMC F, BFN W. L. Sudor, PEB A4, BFN This was pr pared principally by P. S. Kirby.
Ol'51m/2
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT INOPERABLE RADIOACTIVE EFFLUENT INSTRUMENTATION REPORT
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no erable Radioactive Effluent Instrumentation Re ort This report, is to comply with Radiological Effluent-Technical Specifications (RETS) section 3.2.D.2 and 3.2.K.2 reporting requirements for instruments that are inoperable for more than 30 days. The RETS became effective at BFN on-May 6, 1987. This report covers the period from January 1 June 30, 1989.
Because of significant technical specification changes, a large number of radioactive effluent monitoring instruments became technically inoperable on May 6, 1987. RETS were incorporated during a BFN administrative outage. Site resources were, and still are endeavoring to resolve previously identified
'problem areas.- Modifications required to bring BFN effluent monitoring equipment into technical compliance with RETS compete for resources with other regulatory driven modifications.
The instruments that were inoperable for more than 30 days are:
RHR service water monitor (1-RM-90-133)
RHR service water monitor (1-RM-90-134)
RHR service water monitor (2-RM-90-133)
RHR service water monitor (3-RM-90-133)
RHR service water monitor (3-RM-90-134)
Raw cooling water monitor (2-RM-90-132)
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Stack effluent flow meter (0-FE-90-271)
Off Gas Post Treatment noble gas activity monitor (2-RM-90-265)
Off Gas Post Treatment noble gas activity monitor (2-RM-90-266)
Off Gas Post Treatment noble gas activity monitor (3-RM-90-265)
Off Gas Post Treatment noble gas activity monitor (3-RM-90-266)
Off Gas Sample Flow Abnormal (2-PA-90-262)
During the entire reporting period, fuel was off loaded from units one and three,and all compensatory sampling requirements were met.
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L uid Process Radiation M 'rs BFN Tech Spec Table 3.2.D requires Residual Heat Removal (RHR) service water monitors (1-RM-90-133, 1-RM-90-134, 2-RM-90-133, 3-RM-90-133, and 3-RM-90-134) 1 and raw are cooling water monitor (2-RM-90-132) to be operable when these systems in service. Contrary to this requirement, these six monitors were not available for operability for greater than 30 days during this reporting period.
1-RM-90-133, 3-RM-90-133, and 3-RM-90-134 monitors were not available for operability because they were not designed to meet the requirements in Tech Spec Table 4.2.D, Footnote 2. This footnote requires that control room annunciation occur if instrument controls are not set in operate mode. Design
" ~ "~'hange Request='(DCR) 1687, revision 1, was written to correct this problem and was approved on September 29, 1986. 1-RM-90-133, 3-RM-90-133, and 3-RM-90-134 are still not in service due to the associated residual heat removal piping being capped and out of service. 1-RM-90-134 was removed from service due to eismic concerns which are being resolved with Design Change Notice (DCN)
H3949 and 2-RM-90-133 was declared inoperable on April 4, 1989 because a downscale alarm came in. After investigation, it was determined there was not sufficient flow from the RHR headers causing problems with the monitor's flow switch. The monitor was functioning properly and the operability SI was successfully completed on the monitor on May 12, 1989.
2-RM-90-132 was removed from service because the system was not designed to operate at very low RCW discharge flow rates. DCN H4377 was written to redesign the suction tap for 2-RM-90-132 to allow obtaining a sample from RCW t
regardless of RCW flow rate. DCN H4377 is complete except for paperwork closure and plant acceptance. Compensatory sampling is being utilized to erify discharge release rates are met.
4 Effl ent Instrumentation The stack effluent flow meter (0-FE-90-271) was inoperable for more than 30 days during this reporting period.
The stack effluent flow meter (0-FE-90-271) was declared inoperable on May 27, 1989 due to a loss of flow indication in the control room. The meter has not been returned to service because the spare parts had to be ordered and have not been received.
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Off Gas Post Treatment BFN Technical Specification Table 3.2.K requires the Off Gas Post Treatment noble gas activity monitors (1-RM-90-265, 1-RM-90-266, 2-RM-90-265,
-RM-90-266, 3-RM-90-265, and 3-RM-90-266) to be operable at all times.
Contrary to this requirement, four of these monitors (2-RM-90-265, 2-RM-90-266, 3-RM-90-265 and 3-RM-90-266) along with Sample Flow Abnormal (2-PA-90-262), were inoperable for more than 30 days during this reporting period.
The Unit 2 monitors, 2-RM-90-265 and 266, and Sample Flow Abnormal, 2-PA-90-262, were declared inoperable on February 7, 1989 due to the failure of a daily alarm check on 2-PA-90-262. The problem was corrected and the monitors .were returned,to service on March 10, 1989.
The Unit 3 monitors, 3-RM-90-265 and 266, were taken out of service on January 19, 1989 due to the lack of performance of the Quarterly Functional est Surveillance Instructions (SIs). The SIs could not be performed due to a hold order on the Unit 3 offgas isolation valve. The SIs were added to the hold order to ensure no releases were made through this pathway. This is in compliance with Technical Specification Table 3.2.K, action (F). These monitors were returned to service on July 12, 1989 to support Unit 3 off gas layup.
The off gas systems were not in service during this period.
0151m/8
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TVA 64 (OS 9 65) (OP.WP 5 85) RQ 890714 96 Z I:iNITED STATES GOVERNilIEiNT Memorandum, ,TENNESSEE VALLEY AUTHORITY TO: Patrick P ant P. ~ Carier;, Manager of Site Licensing, PAB C, Browns Ferry Nuclear FROM : Guy G. ~ Campbell, Plant Manager, POB C, Browns Ferry Nuclear Plant DATE: JUL 18 1989
SUBJECT:
BROWNS FERRY NUCLEAR PLANT TRANSMITTAL OF INOPERABLE RADIOACTIVE EFFLUENT INSTRUMENT REPORT Attached is the Inoperable Radioactive Effluent Instrument Report for the period from January 1 through June 30, 1989. The'report was prepared by the Chemistry Technical Support Section for incorporation into the Semi-annual Radioactive Release Report, in accordance with Limiting Conditions of Operations 3.2.K.2 and 3.2.D.2.
uy G. Campbell DCS:NHM:PSK:TRS Attachment cc (Attachment):
RIHS, MR 4N 72A-C J. L. Bates, CST llA BA-C W. Christopher, PMB A, BFN
, C. H. Crane, PMC F, BFN J. W. Hutton, POB E, BFN T. E. Scott, PHC F, BFN W. L. Sutor, PEB A4, BFN
'This was prepared principally by P. S. Kirby.
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TENNESSEE VALLEY AUTHORITY BRONNS FERRY NUCLEAR PLANT INOPERABLE RAOIOACTIVE EFFLUENT INSTRUMENTATION REPORT
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Ino erable Radioactive
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Effluent Instrumentation Re ort This report is to comply with Radiological Effluent Technical Specifications
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3.2.K.2 reporting requirements for instruments that
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(RETS) section 3.2.0.2
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are inoperable for more than 30 days. The RETS became effective at BFN on Hay 6, 1987. This report covers the period from January 1 - June 30, 1989.
Because of significant technical specification changes, a large number of radioactive effluent monitoring instruments became technically inoperable on May 6, 1987. RETS were incorporated during a BFN administrative outage. Site resources were, and still are endeavoring to resolve previously identified problem areas. Modifications required to bring BFN effluent monitoring equi'pment into technical compliance with RETS compete for resources with other regulatory driven modifications.
The instruments that were inoperable for more than 30 days are:
RHR service water monitor (1-RM-90-134)
RHR service water monitor (2-RH-90-133)
RHR service water monitor (3-RM-90-133)
RHR service water monitor (3-RH-90-134)
Raw cooling water monitor (2-RH-90-132) 0151m/4
Stack effluent flow meter (0-FE-90-271) 1 Off Off Gas Gas Post Treatment noble gas Post Treatment noble gas activity activity monitor (2-RM-90-265) monitor ( 2-RM-90-266)
Off Gas Post Treatment noble gas activity monitor (3-RM-90-265)
Off Gas Post Treatment noble gas activity monitor (3-RM-90-266)
Off Gas Sample Flow Abnormal (2-PA-90-262)
Ouring the entire reporting period, fuel was off loaded from units one and three and all compensatory sampling requirements were met.
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Li uid Process Radiation Monitors 1
BFN Tech Spec Table 3.2.D requires Residual Heat Removal (RHR) service water monitors (1-RH-90-133, 1-RH-90-134, 2-RM-90-133, 3-RM-90-133, and 3-RM-90-134) and raw cooling water monitor (2-RH-90-132) to be operable when these systems are in service. Contrary to this requirement, these six monitors were not available for operability for greater than 30 days during this reporting period.
1-RH-90-133, 3-RH-90-133, and 3-RH-90-134 monitors were not available for operability because they were not designed to meet the requirements in Tech Spec Table 4.2. D, Footnote 2. This footnote requires that control room annunciation occur if 'instrument controls are not set in operate mode. Design Change Request (DCR) 1687, revision 1, was written to correct this problem and t was approved are still on September being capped and out of service.
H3949 and 2-RH-90-133 was 29, 1986. 1-RH-90-133, 3-RM-90-133, and 3-RM-90-134 not in service due to the associated residual heat removal piping 1-RM-90-134 was removed from service due to seismic concerns which are being resolved with Design Change Notice declared inoperable on April 4, 1989 because (DCN) it would not auto start. An HR to correct the auto start problem was completed on June 20, 1989 but the monitor is still out of service due to operability SIs not being completed.
2-RH-90-132 was removed from service because the system was not designed to operate at very low RCW discharge flow rates. DCN H4377 was written to redesign the suction tap for 2-RH-90-132 to allow obtaining a sample from RCW regardless of RCW flow rate. DCN H4377 is complete except for paperwork closure and plant acceptance. Compensatory sampling is being utilized to verify discharge release rates are met.
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h Stack Radioactive Ef fluent Instrumentation The stack effluent flow meter (0-FE-90-271) was inoperable for more than 30 days during this reporting period.
The stack effluent flow meter (0-FE-90-271) was declared inoperable on May 27, 1989 due to a loss of flow indication in the control room. The meter has not been returned to service because the spare parts had to be ordered and have not been received.
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Off Gas Post Treatment BFN Technical Specification Table 3.2.K requires the Off Gas Post Treatment noble gas activity monitors (1-RM-90-265, 1-RH-90-266, 2-RM-90-265, 2-RM-90-266, 3-RM-90-265, and 3-RN-90-266) to be operable at all times.
Contrary to this requirement, four of these monitors (2-RH-90-265, 2-RH-90-266, 3-RN-90-265 and 3-RH-90-266) along with Sample Flow Abnormal (2-PA-90-262), were inoperable for more than 30 days during this reporting period.
The Unit 2 monitors, 2-RH-90-265 and 266, and Sample Flow Abnormal, 2-PA-90-262', were de'clared inoperable on February 7, 1989 due to the failure of a daily alarm check on 2-PA-90-262. The problem was corrected and the monitors were returned to service on March 10, 1989.
The Unit 3 monitors, 3-RH-90-265 and 266, were taken out of service on January 19, 1989 due to the lack of performance of the quarterly Functional Test Surveillance Instructions (SIs). A hold order was placed on the Unit 3 off gas isolation valve to ensure no releases were made through this pathway.
This is in compliance with Technical Specification Table 3.2.K, action (F).
These monitors were returned to service on July 12, 1989 to support Unit 3 off gas layup.
The off gas systems were not in service during this period.
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LICENSING SUBMITTAL CHECKLIST Submittal
Subject:
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~P@ u ~~4 Preparer:
Submittal has been proofed/spell checked Independent reading by licensing engineer Licensing strategy approved by senior management Backup documentation list is complete Engineering/Technical Report is preliminaryp final New commitments identified. If yes, Ccrg load sheets complete concsrrences obtained from responsible organization Notarization required (Yes/No)
Proper docket number(s) included on submittal Tac number included on submittal Contains Safeguards Information per 10 CFR 73.21 (Yes/No)
Contains proprietary information per 10 CFR 2.790 (Yes/No)
I Fee required per 10 CFR 170.12 (Yes/No)
Submittal affects Final Safety Analysis Report (Yes/No)
If yes copy provided to pgAR coordinator Status of corrective actions:
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I" Page 2 LICENSING SUBMITTAL CHECKLIST (Cont'd)
(a) CAQR/SCR/NCR kP condition identified corrective action approved corrective action complete*
root cause determined recurrence control*
CAQ closed (b) ECN/WP ECN 7P issued WP PP status (c) WR/MR 8 status (d) CCTS iP status Other status notes:
- If not 100% complete indicate by 'R/C'hat action is restart complete.
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