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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TVANUCLEAR Title; Handling of Changes to. the BFN Offsite Dose Calculation Manual RARC OP 9
Revision 1
Page 4 of 4 Appendix 1
BFN ODCM Change Description Form Description of change
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Justification for change:
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Handling of Changes to the BFN Offsite Dose Ca 1 cul ati on Hanual RARC OP 9
Revi sion 0 Page 4 of 4 Appendix 1
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Handling of Changes to the SFH Offsite Dose Calculation Manual RARC OP 9
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UNITED STATES GOVERNi~lENT Memorandum TENNESSEE VALLEYAUTHORITY 0
FROalf F.
W. Reimann,'hief, Water and Waste Processing, IBH 1N 52A-C 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:
Temperature Discha rge": of Duri'ng Open Laboratory, Stolzenbach, K. D.,
'Estimation of Water Increases in Wheeler Reservoir Caused
>y-the Heater Water from Browns Perry Nuclear plant Cycle Operation,'emo to TVA Engineering Pebruary 1975.
WLH:TSH cc:
Vahid Alavian, ENG LAB-N
- Piles, ENG LAB, 335 EB-K
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Prepared by Walter Harper Bnv TJ.S. Snvin.ggr Bonrls Hapularlv on the Pnvroll Snng'gg~g Plnn
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Handling of Changes to the BFN Offsite Dose Calculation Manual RARC QP 9
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:
RC C
an Date: < IS 0678o/COC4
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Title.
Handling of Changes to the BFN Offsite Dose Calculation Manual RARC OP 9-Revision 0 Page 4 of 4 Appendix 1
BFN ODCM Change Description Form y~S Description of change:~~b4~
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Handling of Changes to the BFN Offsite Dose'alculati,on Hanual RARC QP 9
Revision 0 Page 4 of 4 Appendix 1
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. %'t: 8 "I Justification for change: )4am Lc~s i l
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RC irman Date:
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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.
9.
Dilution factors were changed from 0.2 to 0.6 for SQN and 0.3 for BFN.
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 in the Chickamauga and Wheeler reservoirs.
This decreases the population 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.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.
12.
Na-22 As-74 As-76 Kr-83m Kr>>85m Kr-85 Nb-95m Nb-97m Tc-99 Rh-103m R}1-105 Rh>>105m Rh-106 Ag-ill Sb-122 Sb-127 20.
21.
22.
23.
24.
25.
26.
27.
28.
29.
30.
31.
32.
Xe-13Sm Xe-135 Cs-135 Ba-137m Pr-144m Pm-147 Pm-149 Sm-147 SG!-15)
SmlS3 Eu-155 Ta-182 Pb-210 17.
1-129 1'8.
Xe-'133m
- 19. Xe-133 33.
Pb-212 34.
Pb-214
- 35. Bi-212
- 36. Bi-214 37.
Po-212
- 38. Po-214 39.
Po-216 40.
Po-218 41.
Ra-224 42.
Ra-226 43.
Ra-228 44..Ac-228
- 45. Th-228
- 46. Th-230 47.
Th-232 48.
Th-234 49.
Pa-234 50.
U-234 51.
U-238 S2.
Np-238 53.
Pu-240 56.
Pu-. 241 57.
Fu-242 58.
Am-241 59.
Am-242 60.
Am-243 61.
Cm-242 62.
Cm-243 63.
Cm-244
.~4 Pf if 8c tt "p'
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~fitwg Handl i ng of Changes to the BFN Offs i te Dose Calculati.on Manual RARC Qp 9
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:
NARC irman Date: z 5 0678o/CGC4
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Handling of Changes to the SFN Offsite Dose e
Calculation Hanua 1
RARC OP 9
Revision 0
'age 4 of 4 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:
RARC irman Date:
> s 0678o/COC4
g,7 4 IVI
RETS Manual Revision 5
Page 37 TABLE OF CONTEVZS
~Pa e
2.2 Instrument Setpoints 2.2.1 Setpoint Determination 2.2.2 Post-Release Analysis 81 81 2.3 Dose 82 2.3.1 RETS Requirement 2.3.2 Monthly Analysis 82 83 2.3.2.1 Mater Ingestion 2.3.2.2 Fish Ingestion 84 85
,2.3.2.3 Recreation 2.3.2.4 Monthly Summary 86
~
87 2.3.3 Quarterly Dose Calculations 2.3.3.1 Mater Ingestion 2.3.3.2 Fish Ingestion 2.3.3.3 Recreation Shoreline 2.3.3.4 Total Maximum Individual Dose 88 88 89 90 2.3.3.5 Population Dose 2.4 Operab'ility of Liquid Radwaste Equipment 2.5 Liquid Dose Factor Equations 2.5.1 Mater Ingestion Dose Factors 2.5.2 Fish Ingestion Dose Factors 2.5.3 Shoreline Recreation Dose Factor 91 93 93 93 93 94 3.0 Radiological Environmental Monitoring 94 3.1 Monitoring Program 3.2 Detection Capabilities 94 95
- 3. 3 Nonroutine Reports 4.0 Annual Maximum Individual Doses - Total 95
'General Revision 0543p
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LIST OF TABLES RETS Manual Revision 5
Page 38 Table Number Titie 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 1.5 1.6 Dose Factors for Submersion in Noble Gases Sector Elements Considered for Population Doses 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 2.2 3.1 (Sheets 1-4)
Receptors for Liquid Dose Calculations Bioaccumulation Factors for Freshwater Fish Radiological Environmental Monitoring 3.2 3.3 Atmospheric and Terrestrial Monitoring Station Locations Maximum Values for the Lower Limit of Detection (LLD)
General Revision 0543p
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0.9 RETS Manual Revision 5
Page 48 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 Dg (X/Q) 0.9 3.15x10
~
Ql DFl3i (1.5) 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).
General Revision 0543p
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1.3 uarterl Dose Calculations RETS ~wnual Revision 5
Page 55 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 0.7-1.5 1.6-2.4 2.5-3.3 3.4-5.5 5.6-8.2 8.3-10.9
>10.9 0.45 1.10 1.99 2.88 4.45 6.91 9.59
- 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.
General Revision 0547p
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2.3.2.1 Water In estion RETS i~fanual Revision 5
Page 84 The dose to an individual from ingestion of water is described by the following equation.
20 10> z Djk = ~~
(DCF)ijk Zik, mrem i=1 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:
I1k 10
'Ai Uwa (1/12)
F d (7 34 x 10zo)
Ci where:
Ai
= conversion factor, ml/L.
= 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.
General Revision 0547p
~
~
WP lt
'P lb,g
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 Uwa DCFijk Ai, mrem F
i=1 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 Iik where:
10 Ai Bi Ufa (1/12)
Fd (7.34 x 10lo)
Ci (2. 7) 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.
General Revision 0547p
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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'.
2-3.2.3 20 3.98 x 102 Ai Bi Ufa DCFijk i=1 Recreation (2.8)
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
$ [42 ~ RCDFi ~ pi], mrem 0.95 i=1 where:
Dr 10 1.2
~ recreation dose from plant releases, mrem.
~ 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 RHLi Ci
= transfer constant defined in Regulatory Guide 1.109 equation A-4, L per m2-day.
~ radiological half-life of the ith radioisotope, minutes (Table 1.8)
~
= concentration of ith radionuclide in the Tennessee
- River, Ci/ml.
~ A ~ /(F
~ d
~ 7.34 x 10
)
General Revision 0547p
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RETS L~ianual Revision 5
Page 87 where:
Ai d
7.34 x 10 tb activity released of ith radionuclide during the month, Ci.
average river flow Eor the month, cubic Eeet per second.
fraction of river flow available Eor dilution, 0.30.
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).
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:
Dy ~
(29 ~ 8 Al + 1690 A2 + 539 A3 + 812 A4) 1 (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.
General Revision 0547p
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 ~
RF
- 0.30 (for receptors upstream of Wheeler Dam)
(2. 13a)
- where:
(for receptors downstream of Wheeler Dam)
(2.13b)
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) where (2.14)
~ 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).
General Revision 0547p
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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) where (2.15
= 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 <<<<s~
~ dilution factor, as described
- above, cfs
= radiological decay constant of nuclide i, seconds
'(Table 1.8).
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.
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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) where (2.16) 10'.8E-09
= conversion factor, pCi/Ci.
= 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 D
= 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).
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 fish 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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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:
453%6
- HVST APR TFDOSart
+ POPa 4
3 POPFt 10
+
10 1
FISHa
- POPa General Revision 0547p
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Page 92 where:
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 10s
~ conversion factor, g/lb.
~ conversion factor, mrem/rem.
~ 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 HRSVISz'760
= 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 />.
~ conversion factor, mremlrem.
= conversion factor, bours/year.
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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) where:
DFLiat Uwa 10 10 8760 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).
8760
~ conversion factor, pCi/pCi.
= conversion factor, ml/L.
~ 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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Page 94 10'760
= conversion factor, pCi/pCi.
= conversion factor, ml/L.
= conversion factor, hours per year.
2.5.3 SHORELINE RECREATION DOSE FACTOR - ARit (mrem/hr per pCi/ml).
ARit where:
D Git Kc M
W 10 10 U
[1-exp(-X ~ tb)]
8760
- 3600 Ai 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).
10s
~ mass density of sediment, kg/m~, (Table 1.9).
= shoreline width factor, dimensionless, (Table 1.9).
= conversion factor, ml/L.
10'600
~ conversion factor, pCi/pCi.
= 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 8760
= usage factor, 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year.
= 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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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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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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Table 1.1 BFN OFFSITE RECEPTOR LOCATION DATA RETS Manual Revision 5
Page 97 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 Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site 'Boundary Site Boundary Site Boundary Site Boundary Garden Milk Cow Milk Cow 1525 N
1300 NNE 1250 NE 1450 ENE 1375 E
1575 ESE 5600 SE 2875 SSE 2550 S
2425 SSW 2300 SW 2500 WSW 2550 W
3325 WNW 2275 NW 1650 NNW 1830 NNW 8045 N
10975 NNW 7
4 7
0 0
0
-6
-6
-6
-6
-6
-6
-6
-6
<<6
-6
-6
-6
-6 1.60E-06 7.88E-07 4.52E-07 7.30E-07 8.24E-07 4.56E-07 7.61E-08 4.86E-07 8.27E-07
~
1.08E-06 6.87E-07 6.38E-07 6.70E-07 3.69E-07 1.69E-06 1.84E-06 1.57E-06 1.47E-07 N/A 5.64E-09 1.97E-09 1.56E-09 2.92E-09 4.04E-09 3.28E-09 3.63E-10 1.77E-09 2.24E-09
'2. 92E-09
- 1. 75E-09 1.14E-09
- 1. 25E-09 9.07E-10 4-92E-09 5.29E-09 4.46E-09 3.16E-10 N/A 9.79E-11 7.86E-12 5.91E-12 1.37E-11 8.84E-12 4.98E-11 7.24E-49 1.58E-09 1 '2E-09 9'27E-10 5.94E-10 5.34E-10 5.06E-10 2.69E-09
- 1. 10E-09 1.31E-10 3.29E-10 N/A 1.69E-08 8.578-10 5.24E-10 4.66E-10 4.11E-10
- 4. 75i-10 5.98E-10 3.00E-10
- 5. 59E-10 6.67E-10 7.07E-10 6.06E-10 3.45E-1.0 2.74E-10 4.75E-10 1.24E-09 1.05E-09
- 1. 13EW9 2.30E-10 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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Table 1.4 DOSE FACTORS FOR SUBi!ERSIOil EiN i!OBLE GASES RETS.'!anual Revision 5
Page 121 Submersion dose mrem/yr per pCi/m~
DFBi DFSi Air dose mrad/yr per pCi/m~
DFyi DFQi Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Ze-138 Ar-41 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01
- 2. 51E+02
- 2. 94E+02 3.12E+03 1.81E+03 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.11E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03 9.21E+03 9.30E+03
- 2. 88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 I
3.28E+03
Reference:
Regulatory Guide 1.109, Table B-l.
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Table 1.7 (1 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)'DULT RETS: ~annual Revision 5
Page 124 H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85
'b-86 Rb-88 Rb<<89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-'91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 RG-105 RQ-106 Ag-110m bone 1.05E-07 2 84E&6 1.70E-06 1.93E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.75E-06 4.34E-06 0.00E+00 0.00E+00 O.OOE+00 1.30E-04 5.28E-07 O.OOE+00 4.'84E-'06 1.03E-OS 1.70E-07 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 3.08E-04 7.58E-03 5.67E-06 2.15E-06 9.62E-09 9.09E-11 1.41E-07 8.45E-10 2.68E-09 3.04E-OS 1.68E-09 6.22E-09 5.22E-11 O.OOE+00 2.47E-10 2.54E-10 1.85E-07 1.54E-08 2.75E-06 1.60E-07 liver 1.05E-07 5.68E-07 1.70E-06 1.20E-05 O.OOE+00 4.57E-06
- 1. 15E-07 l.90E-06 1.02E-05 1.75E-07 7.45E-07 2.14E-06 9.01E-06 6.86E-OS 8.33E-OS 1.54E-05 1.97E-OS 4.08E-07 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 2.11E-05 6.05E-08 4.01E-08 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9.75E-09 3.39E-10 3.46E-09 1.32E-11 4.31E-06 6.98E-10
. 3.66E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-07 t body 1.05E-07 5.68E-07 1.70E-06 7.46E-06 2.66E-09 8.72E-07 2 04EMS 4.43E-07 3.91E-06 2.91E-07 1.67E-06 4.72E-06 4.36E-06 3.13E-OS 3.91E-OS 6 96EM6 1.37E-09 3.73E-OS 2.26E-06 4.02E-08 5.21E-OS 2.14E-09 9.83E-06 3-21E-08 2.82E-OS 8.84E-06 1.86E-03 2.29E-07 9.30E-08 2.58E-10 3.52E-I.2 3.77E-09 2.47E-1.1 7.40E-1.1 6.60E-09 1.55E-10 1.86E-09 4.82E-12 8.20E-07 8.89E-09 3.59E-09 7.97E-08 6.08E-09 3.48E-07 8.79E-08 thyroid 1.05E-07 5.68E-07 1.70E-06 O.OOE+00 1.59E-09 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 kidney 1.05E-07 5.68E-07 1.70E-06 O.OOE+00 5.86E-10 1.36E-06 1.46E-07 0.00E+00
- 0. OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00
- 2. 10E&7 1.03E-05 1.28E-OS 2.47E-07 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.53E-OS 5.12E-10 3.42E-09 1.54E-11 9.76E-06 1.06E-OS 6.59E-09 7.06E-07 1.99E-07 5.31E-06 2.91E-07 lung 1.05E-07 5.68E-07 1.70E-06 O.OOE+00 3.53E-09 O.OOE+00 0.00E+00 1.06E-06 2.85E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00
'0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.42E-10 1.87E-10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 1.05E-07 5.68E-07 1-70E-06 2.17E-05 6.69E-07 1.40E-05 3.67E-06 1.09E-06 3.40E-05 4.44E-06 1.51E-05 4.02E-05 1.88E-06 1.74E-06 7.10E-06'.70E-06 2.96E-09 2.49E-05 2.59E-06 5.79E-OS 4.09E-13 O.OOE+00 4.16E-06 8.36E-19 2.33E-21 4.94E-05 2.19E-04 2.70E-05 4.26E-05 1.02E-04 2.67E-1.0 7.76E-05 1.48E-05 8.50E-05 3.09E-05 1.05E-04 2.10E-05 4.87E-OS 9.99E-06
0
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Tab le 1. 7 (2 of 8 )
INGESTION DOSE FACTORS (mrem/pCi ingested)
RETS.'fanual Revision 5
Page 125 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135
's-134 Cs-136 Cs-137 Cs-138
'a-139 Ba-140
- Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143
'Pr-144 Nd-147 M-187 Np-239 bone 2.80E-06 1.79E-06 2.68E-06 6.77E-06 1.10E-07 1.15E-05 3.14E-OS 1.73E-06 1.97E-OS 2.52E-06 7.56E-07 4.16E-06 2.03E-07 1.42E-06 1.06E-07
.43E-07 6.22E-05 6.51E-06 7.97E-05 5.52E-OS 9.70E-OS 2.03E-05 4.71E-OS 2.13E-08 2.50E-09 1.28E-10 9.36E-09 1.65E-09 4.88E-07 9.20E-09 3.01E-11 6.29E-09 1.03E-07 1.19E-09 liver 5.29E-OS 2.00E-OS 9.71E-07 2.42E-06 3.95E-OS 4.29E-06 1.18E-OS 8.46E-07 8.23E-09 1.63E-06 2.23E-06 5.95E-06 5.43E-07 2.47E-06 2.88E-07 1.16E-06 1.48E-04 2-57E-05 1.09E-04 1.09E-07 6.91E-11
- 2. 55E-08 3.56E-11 2.19E-11 1.26E-09 5.82E-11 6.33E-09 1.22E-06 2.04E-07 3.69E-09 1.25E-11 7.27E-09 8.61E-OS 1.17E-10 t body 1.11E-06 4.26E-07 3.59E-07 8.25E-07 2.38E-OS 1.82E-06 7.65E-09 7.05E-07 6.22E-09 1.53E-06 S.SOE-07 3.41E-06 1.90E-07 7.53E-07 1.03E-07 4.28E-07 1.21E-04 1.85E-05 7.14E-05 5.40E-08 2.84E-09 1.33E-06 1.59E-09 1.34E-09 3.33E-10 1.45E-11 7.18E-10 1.35E-10 2.62E-08 4.56E-l.o 1.53E-12 4.35E-10 3.01E-OS 6.45E-11 ADULT thyroid 6.79E-09 1.82E-09 8.06E-07 1.73E-06 8.15E-08 3.95E-06 2.41E-OS 1.34E-06 1.62E-08 1.80E-06 1.89E-04 1.95E-03 1.90E-05 3.63E-04 4.99E-06 7.65E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 kidney O.OOE-OO 0.00E-OO 1.09E-05 2.75E-05 4.48E-07 4.80E-05 1.32E-07 8.57E-06 8.63E-OS 1.57E-05 3.48E-06 1.02E-05 8.65E-07 4.31E-06 4.58E-07 1.86E-06 4.79E-05 1.43E-05 3.70E-05 8.01E-OS 6.46E-l.l 8.67E-09 3.31E-11 1.85E-11 O.OOE+00 0.00E+00 2.94E-09 5.37E-10 1.21E-07 2.13E-09 7.05E-12 4.25E-09 0.00E+00 3.65E-10 lung 2.18E-06 1.38E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOEjoo O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.59E-05 1.96E-06 1.23E-05
- 7. 91E-09 3.92E-1.1 1.46E-OS 2.02E-11 1.24E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 7.95E-05 1.97E-05 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-OS 8.40E-05 2.79E-09 7.71E-05 1.92E-06 1.57E-06 1.02E-07 2.22E-06 2.51E-10 1.31E-06 2.59E-06 2.92E-06
- 2. 11E-06 4.65E-13 1.72E-07 4.18E-05 2.22E-17 3.00E-26 9.25E-05 4.25E-07 2.42E-05 4.56E-05 1.65E-04 4.03E-05 4.33E-18 3.49E-05 2.82E-05 2.40E-05
~
~
I
'I NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the
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.
General Revision 0530p
V iC J,III4/
pl
~h
Table 1.7 (3 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested.)
RETS 'manual Revision 5
Page 126 H-3 C-14 Na-24 P-32 Cr-51 Nn-54 i4hx-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 CL1-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 No-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m bone 1.06E-07 4.06E-06 2.30E-06 2.76E-04 0.00E+00 0.00E+00 O.OOE+00 3.78E-06 5.87E-06 O.OOE+00 O.OOE+OO 0.00E+OO 1.77E-04 7.49E-07 0.00E+00
'5.76E-06'.47E-OS 2.40E-07 O.OOE+00 0.00E+OO 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 4.40E-04 8.30E-O3 8.07E-06 3.05E-06 1.37E-OS 1.29E-10 2.01E-07'.21E-09 3.83E-09 4.12E-08 2.37E-09 8.22E-09 7.37E-1.1 O.OOE+00 3.32E-10 3.60E-10 2.55E-07 2.18E-08 3.92E-06 2.05E-07 liver 1.06E-07 8.12E07 2.30E-06
- l. 71E&5 O.OOE+00
- 5. 90E&6 1.58E&7
- 2. 68E-06 1.37E-05 2.38E-07
- 9. 72E&7 2.81E-06 1.25E-05 9.57E-08 1.15E-07 2.00E-05 2.80E-08 5.66E-07 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 2.98E-05 8.52E-08 5.50E-08 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 1.30E-08 4.69E-10 4.56E-09 1.83E-11 6.03E-06 9.26E-10 5.12E-10 0.00E+00 0.00E+00 0.00E+00 1.94E-07 t body 1.06E-07 8.12E-07 2.30E-06 1.07E-05 3.60E-09 1.17E-06 2.81E-08 6.25E-07 5.29E-06 3.99E-07 2.24E-06 6.33E-06 6.00E-06 4.36E-08 5.41E-08 9.33E-06 1.96E-09 5.19E-08 3.04E-06 5.74E-08 7.22E-08 3.05E-09 1.40E-05 4.54E-08 3.89E-08 1.26E-05 2.05E-O3 3.21E-07 1.30E-07 3.69E-10 4.93E-12 5.39E-09 3.50E-11 1.05E-10 8.94E-09 2.16E-10 2.51E-09 6.68E-12 1.15E-06 1.20E-08 5.03E-09 1.09E-07 8.46E-09 4.94E-07
- 1. 18E-07 TEEN thyroid 1.06E-07 8 12EW7 2.30E-06 0.00E+00 2.00E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney 1.06E-07 8.12E-07 2.30E-06 0.00E+00 7.89E-10 1.76E-06 2.00E-07 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 2.91E-07 1.28E-05 1.83E-08 3.44E-07 O.OOE+00 O.OOE+00 O.OOE+00 40.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.91E-08 7.11E-10 4.42E-09
- 2. 14E-11 1.38E-OS 1.38E-08 9.26E-09 8.99E-07 2.75E-07 7.56E-06 3.70E-07 lung 1.06E-07 8.12E-07 2.30E-06 O.OOE+00 5.14E-09 0.00E+00 O.OOE+00 1.70E-O6 4.32E-06 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 5.14E-I.O 3.12E-10 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 1.06E-07 8.128-07 2.30E-06 2.32K-05 6.05E-07 1.21E-05 1.04E-05 1.16E-06 3.24E-05 4.44E-06 1.34E-05 3.66E-05 1.99E-06 5.19E-06 8.92E-06 8.47E-06 5.16E-08
- 3. 11E-05 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 4.41E-06 7.30E-1.5 8.43E-17 5.24E-05 2.33E-04 3.66E-05 7.77E-05 1.13E-04 6.09E-09 8.24E-05 3.32E-05 1.17E-04 3.00E-05 1.27E-04 1.95E-05 4.37E-07 1.08E-05 6.08E-07 8.75E-17 2.13E-05 1.76E-05 1.88E-04 5.45E-05 General Revision 0530p
+I) 1 P
V
Table 1.7 (4 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
RETS manual Revision 5
Page 127 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135
's-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140
.Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 3.87E-06 2.48E-06 3.83E-06 9.67E&6
- 1. 58E-07
- 1. 63E-05
- 4. 48E-08
- 2. 44E-06
- 2. 79E-08 3.49E-06 1.03E-06 5.85E-06 2.79E-07 2.01E-06
= 1.46E-07 6.10E-07 8.37E-05 8.59E-06 1.12E-04
- 7. 76E-08
- 1. 39E-07 2.84E-05 6.71E-OS 2.99E-OS 3.48E-09 1.79E-10 1.33E-OS
- 2. 35E-09 6.96E-07 1.31E-OS
~ 4. 30E-11 9.38E-09 1.46E-07 1 ~ 76E-09 liver 7.13E-OS 2.71E-OS 1.38E-06 3.43E-06 5.60E-OS 6.05E-06 1.67E-OS 1.17E-06 1.15E-OS 2.21E-06 2.98E-06 8.19E-06 7.30E-07 3.41E-06 3.87E-07 1.57E-06 1.97E-04 3.38E-05 1.49E-04 1.49E-07 9.78E-11 3.48E-OS 5.01E-11 2.99E-11 1.71E-09 7.95E-11 S.SSE-09 1.71E-06 2.88E-07 5.23E-09 1.76E-11 1.02E-08 1.19E-07 1.66E-10 t body 1.51E-06 5.80E-07 5.12E-07 1.15E-06 3.40E-OS 2.58E-06 1.09E-08
- 9. 76E-07
- 8. 72E-09 2.08E&6 1.19E-06 4.40E-06 2.62E-07 1.04E-06 1.39E-07 5.82E-07 9.14E-05 2.27E-05 5.19E-05 7.45E-OS 4.05E-09 1.83E-06 2.24E-09 1.84E-09 4.55E-10 1.98E-11 1.02E-09 1.91E-10 3.74E>>08 6.52E-10 2.18E-12 6.11E-10 4.17E-OS 9.22E-11 TEEN thyroid 8.78E-09 2.37E-09 1.07E-06 2.30E-06 1.09E-07 5.26E-06 3.20E-08 1.76E-06 2.15E-08 2.33E-06 2.43E>>04 2.39E-03 2.46E-05 4.76E-04 6.45E-06 1.01E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOEe00 O.OOE+00 O.OOE+00 0.00E+00 kidney
. O.OOE-OO O.OOE+00 O.OOE+00 3.92E-05 6.40E-07 6.82E-05 1.88E-07 1.22E-05 1.22E-07 2.12E-05 4.59E-06 1.41E-05 1.15E-06 5.98E-06 6.10E-07 2.48E-06 6.26E-05 1.84E-05 5.07E-05 1.10E-07 9.22E-11 1.18E-.OS.
4.65E-11 2.53E-11 0.00E+00 0.00E+00 4.18E-09 7.67E-10 1.72E-07 3.04E-09 1.01E-11 5.99E-09 0.00E+00 5.21E-10 lung 3.38E-06
- 2. 18E&6 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.39E-05 2.90E-06 1.97E-05 1.28E-08 6.74E-11 2.34E-OS 3.43E-11 1.99E-11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0-OOE+00 O.OOE+00 O.OOE+00 gi-1li 7.80E-05 1.93E-05 1.13E-05 2.41E-05 1.22E-05
- 6. 12E-05
- 2. 45E-07 9.39E-05 2.29E-09 7.00E-05 2.29E-06 1.62E-06 3.18E-07 2.58E-06
- 5. 10E-09 1.74E-06 2.45E-06 2.72E-06 2.12E-06 6.76E-ll
- 1. 24EW6 4.38E-05 1.43E-13 9.18E-20 9.82E-05 2.42E-06 2.54E-05 5.14E-05 1.75E-04 4.31E-05 4.74E-14 3.68E-05 3.22E-05 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 total body dose factor. for bone is assumed to be equal to the General Revision 0530p
r P
t 4
If P
T lc p
C t!
Table 1.7 (6 of 8)
IVGESTIOiV DOSE FACTORS (mrem/pCi ingested)
RETS.Vanua1 Revision 5
Page 129 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 iVd-147 W-187 imp-239 bone 1.11E-05 7.16E-06 1.14E-05 2.89E-05 4.71E-07 4.87E-05 1.34E-07 7.20E-06 8.30E-OS 1.01E-05 2.92E-06 1.72E-05 8.00E-07 5.92E-06 4.19E-07 1;75E-06 2.34E-04 2.35E-05 3.27E-04 2.28E-07 4.14E-07 8.31E-05 2.00E-07 8.74E-OS 1.01E-OS 5.24E-10 3.97E-OS 6.99E-09 2.08E-06 3.93E-OS 1.29E-10 2.79E-OS 4.29E-07 5.25E-09 liver 1.44E-07 5.52E-OS 3.09E-06 7.78E-06 1.27E-07 1.36E-05 3.74E-OS 2.49E-06 2.53E-08 4.47E-06 5.90E-06 1.73E-05 1.47E-06 7.32E-06
- 7. 78E-07 3.15E-06 3.84E-04 6.46E>>05 3.13E-04 3.17E-07 2.21E-10 7.28E-OS 1.12E-10 6.29E-11 3.53E-09 1.67E-10 1.98E-OS 3.79E-06 6.52E-07 1.18E-OS 3.99E-11 2.26E-OS 2.54E-07 3.77E-10 t body 3.89E-06 1.50E-06 1.52E-06 3.43E-06 1.01E-07 7.56E-06 3.18E-OS 2.65E-06 2.47E-OS 5.40E-06 3.04E-06 9.83E-06 6.76E-07 2.77E-06 3.58E-07 1.49E-06 8.10E-'05 4.18E-05'.62E-05 2.01E-07 1.20E-OS 4.85E-06 6.51E-09 4.88E-09 1.19E-09 5.23E-11 2.94E-09 5.49E-10 1.11E-07 1.95E-09 6.49E-12
- l. 75E-09 1.14E-07 2.65E-10 CHILD thyroid 2.45E-OS 6.63EW9 3.20E-06 6.91E&6
- 3. 26E-07
- 1. 57E-05 9.56EWS
- 5. 12E&6
- 6. 35E-08 6.51E-06 6.50E-04 5.72E-03 6.82E-05 1.36E-03 1.79E-05
- 2. 79EM4 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 8.24E-05 1.34E-06 1.43E-04 3.92E-07 2.41E-05 2.51E-07 4.15E-05 8.82E-06 2.84E-05 2.25E-06 1.22E-05 1.19E-06 4.83E-06 1.19E-04 3.44E-05 1.02E-04 2.23E-07
'1..93E-10 2.37E-OS 9.69E-ll 5.09E-11 O.OOE+00 O.OOE+00 8.68E-09 1.59E-09 3.61E-07 6.39E-09 2.11E-11 1.24E-OS O.OOE+00 1.09E-09 lung 6.16E-06 3.99E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.27E-05 5.13E-06 3.67E-05 2.40E-08 1.30E-10 4.34E-OS 6.58E-10 3.70E-11 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi-lli 6.94E-05
- 1. 71E-05 1.10E-05 2.34E-05 1.84E-05 5.94E-05 8.34E-06 1.01E-04 4.36E-07 4.50E-05 2.76E-06 1.54E-06 1.73E-06 2.95E-06 5.16E-07 2.40E-06 2.07E-06 2.27E-06 1.96E-06 1.46E-07 2.39E-05 4.21E-05 1.14E-07
- 1. 14E-09 9.84E-05 3.31E-05 2.47E-05 5.55E-05 1.70E-04 4.24E-05 8.59E-OS 3.58E-05 3.57E-05 2.79E-05
References:
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 total body dose factor. for bone is assumed to be equal to the General Revision 0530p
n, h
1, b
Table 1.7 (5 of 8)
IiVGESTION DOSE FACTORS (mrem/pCi ingested)
RETS Manual Revision 5
Page 128 H-3 C-14 Na-24 P-32 Cr-51 iM-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 CLL-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 RLL-103 R11-105 Ru>>106 Ag-110m bone 2.03E-07 1.21E-05 5.80E-06 8.25E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.15E-05 1.65E-05 O.OOE+00 0.00E+00 0.00E+00 5.38E-04 2.22E-06 0.00E+00 1.37E-05 4.38E-08 7;10E-07 0.00E+00 0.00E+00
, O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.32E-03 1.70E-02 2.40E-05 9.03E-06 4.11E-08 3;82E-10 6.02E-07 3.60E-09 1.14E-08 1.16E-07 6.99E-09 2.25E-08 2.17E-10 O.OOE+00 9.23E-10 1.07E-09'.31E-07 6.45E-08 1.17E-05 5.39E-07 liver 2.03E-07 2.42E-06 5.80E-06 3.86E-05 0.00E+00 1.07E-05 3.34E-07 6.10E-06 2.67E-05 4.93E-07 1.80E-06 5.29E-06 2.88E-05 2.09E-07 2.45E-07 3.65E-05 6.33E-08 1.21E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 6.70E-05 1.90E-07 1.17E-07 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 2.55E-08 1.01E-09
- 8. 76E-09 3.92E-11 1.33E-05 1.81E-09 1.12E-09 0.00E+00 O.OOE+00 O.OOE+00 3.64E-07 t body 2.03E-07 2.42E-06 5.80E-06 3.18E-05 8.90E-09 2.85E-06 7.54E-08 1.89E-06 1.33E-05 9.98E-07 5.51E-06 1.56E-05 1.83E-05 1.22E-07 1.48E-07 2.27E-05 5.85E-09 1.43E-07 7.55E-06 1.71E-07 1.98E-07 9.12E-09 4.12E-05 1.32E-07 1.04E-07 3.77E-05 4.31E-03 9.06E-07 3.62E-07 1.10E-09 1.39E-11 1.61E-08 1.03E-10 3.13E-10 2.27E-08 5.96E-10 6.26E-09 1.83E-l.l 3.29E-06 3.00E-08 1.42E-08 2.81E-07 2.34E-08 1.46E-06 2.91E-07 CHILD thyroid 2.03E-07 2.42E-06 5.80E-06 O.OOE+00 4.94E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney 2.03E-07 2.42E-06 5.80E-06 O.OOE+00 1.35E-09 3.00E-06 4.04E-07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.92E-07 2.30E-05 3.84E-08 7.03E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 3.65E-08 1.45E-09 8.23E-09 4.35E-11 2.84E-05 2.63E-08 1.91E-08 1.84E-06 5.67E-07 1.58E-05 6.78E-07 lung 2.03E-07 2.42E-06 5.80E-06 O.OOE+00 9.02E-09 O.OOE+00 O.OOE+00 3.45E-06
- 7. 74E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOEjoo
- 9. 19E-10 5.92E-10 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 gi-11'.03E-07 2.42E-06 5.80E-06 2.2SE-05 4.72E-07 8.98E-06 4.84E-05 1.13E-06 2.78E-05 4.04E-06 1.05E-05 2.93E-05 1.94E-06 2.56E-05 1.15E-05 6.41E-06 3.99E-06 3.94E-05 O.OOEj00 O.OOE+00 0.00E+00 O.OOE+00 4.31E-06 9.32E-09 1.02E-09 5.11E-05 2.29E-04 5.30E-05 1.71E-04 1.17E-04 7.48E-07 8.02E-05 1.04E-04 1.70E-04 2.66E-05 1.53E-04 1.62E-05 1.21E-05 1.10E-05 1.03E-06 3.56E-09 1.89E-05 4.21E-05 1.82E-04 4.33E-05 General Revision 0530p
1;
~,
N fQ.
~t L
Sj lf
Table 1.7 (7 of 8)
INGESTION DOSE FACTORS (mrem/pCi ingested)
RETS.'fanual Revision 5
Page 130 H-3 C-14 Na-24 P-32 Cr-51 Nn-54 Hn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 CLL-64
Zn-65'n-69 Zn-69m Br-82 Br-83 Br<<84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr>>92 Y-90 Y-91m,.
Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m bone 3.08E-07 2.37E-05 1.01E-05 1.70E-03 O.OOE+00 O.OOE+00 O.OOE+00
- 1. 39E-05 3.08E-05 0.00E+00 O.OOE+00 0.00E+00 6.34E-04 4.70E-06 0.00E+00 1.84E-OS 9.33E-08 1.50E-06 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0-OOE+00 0.00E+00 O.OOE+00 2-51E-03 1.85E-02 5.00E-05 1.92E-05 8-69E-08 8.10E 1.13E-06 7.65E-09 2.43E-08 2.06E-07 1.48E-08 4.20E-08 4.59E-10 O.OOE+00 1-92E-09 2.27E-09 1.48E-06 1.36E-07 2.41E-05 9.96E-07 liver 3.08E-07 5.06E-06 1.01E-05 1.00E-O4 O.OOE+00 1.99E-05 8.18E-07 8.98E-06 5.38E-05 1.15E-06 3.60E-06 1.08E-05
- 3. 92E5 5.32E-07 6.09E-07 6.31E-05
- 1. 68E-07 3.06E-06 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.70E-04 4.98E-07 2.86E-07 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 5.02E-08 2.54E-09 1.73E-08 9.79E-11 3.40E-05 3.96E-09 2.86E-09 0.00E+00 0.00E+00 O.OOE+00 7.27E-07 INFANT t body thyroid 3.08E07 3.08E-07 5.06E-06 5.06E-06 1.01E-05 1.01E-05 6.59E-05 O.OOE+00 1.41E-OS 9.20E-09 4.51E-06 O.OOE+00 1.41E-07 0.00E+00 2.40E-06 0.00E+00 2.1.2E-05 O.OOE+00 1.87E-06 O.OOE+00 8.98E-06 0.00E+00 2.55E&5 0.00E+00 2.20E-05 O.OOE+00 2.42E-07 O.OOE+00 2.82E-07 0.00E+00 2.91E-05 O.OOE+00 1.25E-08 0.00E+00 2.79E-07 0.00E+00 1.27E-05 O.OOE+00 3.63E-07 O.OOE+00 3.82E-07 0.00E+00 1.94E-08 0.00E+00 8.40E-05 0.00E+00 2.73E-07 0.00E+00 1.97E-07 O.OOE+00 7.20E-05
,O.OOE+00 4.71E-03 O.OOE+00 1.81E-06 O.OOE+00 7.13E-07 O.OOE+00 2.33E-09 O.OOE+00 2.76E-11 O.OOE+00 3.01E-08 O.OOE+00 2.15E-10 O.OOE+00 6.62E-10 0.00E+00 3.56E-08 O.OOE+00 1.16E-09 0.00E+00 1.00E-08 0.00E+00 3.53E-11 O.OOE+00 6.63E-06 O.OOE+00 5.10E-08 O.OOE+00 2.83E-08 0.00E+00 4.95E-07 O.OOE+00 4.58E-08 O.OOE+00 3.01E-06 O.OOE+00 4.81E-07 O.OOE+00 kidney 3.08E-07 5.06E-06 1.01E-05 O.OOE+00 2.01E-09 4.41E-06 7.03E-07 O.OOE+00
'.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.03E-06 3.06E-05 6.98E-08
- 1. 24E&6 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 5.41E-08 2.56E-09 1.24E-08 7.65E-11 5.08E-05 4.26E-08 3.40E-08 3.08E-06 1.00E-06 2.85E-05 1.04E-06 lung 3.08E-07 5.06E-06 1.01E-05 O.OOE+00 1.79E-O8 O.OOE+00 O.OOE+00 4.39E-06 1.59E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 2.07E-09 1.56E-09 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 gi-lli 3.08E-07 5.06E-06 1.01E-O5 2.30E-05 4.11E-07 7.31E-06 7.43E-05 1.14E-06 2.57E-05 3.92E-06 8.97E-06 2.57E-.05 1.95E-06 4.05E-05 1.25E-05 5.33E-05 1.37E-05 4.24E-05 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 4.35E-06 4.85E-07 9.74E-08 5.16E-05 2.31E-04 5.92E-05 2.07E-04 1.20E-04 2.70E-06 8.10E-05 1.46E-04 1.92E-04 2.50E-05 1.62E-04 1.46E-05 3.09E-05 1.12E-05 1.15E-06 4.86E-07 1.80E-05 5.41E-05 1.83E-04 3.77E-05 General Revision 0530p
1
Table 1.7 (8 of 8)
INGESTIOiV DOSE FACTORS (mrem/pCi ingested)
RETS manual Revision 5
Page 131 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 1-135-Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 P,r-144 Nd-147 W-187 Np-239 bone 2.14E-05 1.23E-05 2.33E-05 5.85E-05 1.00E-06 1.00E-04 2.84E-07 1.52E-05 1.76E-07 2.08E-05 6.00E-06 3.59E-05 1.66E-06 l.25E-05
- 8. 69E-07
- 3. 64E-06 3.77E-04 4.59E-05 5.22E-04 4.81E-07 8.81E-07 1.71E-04 4.25E-07 1.84E-07 2.11E-08 1.10E>>09 7.87E-08 1.48E-08 2.98E-06 8.13E-08 2.74E-10 5.53E-08 9.03E-07 1.11E-08 liver 3.15E-07 1.19E-07 7.79E-06 1.94E-05 3.35E-07 3.43E-05
- 9. 79E&8 6.12E-06 6.50E-08 1.03E-05 1.32E-05 4.23E-05 3.37E-06 1.82E-05 1.78E-06 7.24E-06 7.03E-04 1.35E-04 6.11E-04 7.82E-07 5.84E-10 1.71E-07 2.91E-10 1.53E-10 8.32E-09 4.04E-10 4.80E-08 9.82E-06 1.22E-06 3.04E-08 1.06E-10 5.68E-08 6.28E-07 9.93E-10 INFANT t body thyroid 6.63E-06 5.68E-08 2.53E-06 1.54E-08 3.15E-06 7.84E-06 7.08E-06 1.69E-05
- 2. 15E-07
- 8. 14E-07 1.54E-05 3.84E-05 6.63E-08 2.38E-07 5.05E-06 1.24E-05 4.94E-08 1.57E-07 9.61E-06 1.52E-05 5.30E-06 1.48E-03 1.86E-05 1.39E-02 1.20E-06 1.58E-04 5.33E-06 3.31E-03 6.33E-07 4.15E-05 2.64E-06 6.49E-04 7.10E-05 O.OOE+00 5.04E-05 O.OOE+00 4.33E-05 O.OOE+00 3.79E-07 O.OOE+00 2.55E-08 O.OOE+00 8.81E-06 O.OOE+00 1.34E-08 O.OOE+00 9.06E-09 O.OOE+00 2.14E-09 O.OOE+00 9.67E>>11 O.OOE+00, 5.65E-09 O.OOE+00 1.12E-09 O.OOE+00 1.67E-07 O.OOE+00 4.03E-09 O.OOE+00 1.38E-11 O.OOE+00 3.48E-09 O.OOE+00 2.17E-07 O.OOE+00 5.61E-10 0.00E+00 kidney O.OOE+00 O.OQE+00 O.OOE+00 1.44E-04 2.44E-06 2.50E-04 7.07E-07 4.21E-05 4.50E-07 6.44E-05 1.45E-05 4.94E-05 3.76E-06 2.14E-05 1.99E-06 8.07E-06 1.81E-04 5.38E-05 1.64E-04 3.90E-07 3.51E-10 4.06E-08 1.75E-10 8.81E-11 O.OOE+00 O.OOE+00 1.48E-08 2.86E-09 4.93E-07 1.13E-08 3.84E-11 2.19E-08 0.00E+00 1.98E-09 lung 1.34E-05 7.72E-06 O.OOE+00 O.OOE+00
- 0. OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 7.42E-05
- l. 10E-05 6.64E-05 6.09E-08 3.54E-10 1.05E-07 1.77E-10 9.26E-11 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 gi-lli 6.60E-05 1.64E-05 1.11E-05 2.36E-05 2.10E-05 5.97E-05 2.27E-05
'.03E-04 7.11E-06 3.81E-05 2.83E-06 1.51E-06 2.73E-06 3.08E-06 1.84E-06 2.62E-06 1.91E-06 2.05E-06 1.91E-06 1.25E-06 5.58E-05 4.20E-05 5.19E-06 7.59E-07 9.77E-05 6.86E-05 2.48E-05 5.73E-05 1.71E-04 4.29E-05 4.93E-06 3.60E-05 3.69E-05 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 NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a Chronic Intake
, November, 1977, Table l.
are from One Year NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the General Revision 0530p
WH l
~c'
RETS 1anua1 Revision 5
Page 132 Table 1.8 (1 of 3)
RADIONUCLIDE DECAY AND STABLE ELEi1EVZ TRANSFER DATA H-3 C-14 Na-24 P-32 Cr-51 Hn-54 Hn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65
,Zn-69m Zn-69 Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-9.1 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 iso-99 Tc-99m Tc-101 RG-103 RLI-105 RLI-106 Ag-110m Half-Life (minutes) 6.46E+06 3.01E+09 9.00E+02
~
2.06E+04 3.99E+04 4.50E+05 1.55E+02 1.42E+06 6.43E+04 3.90E+05 1.02E+05 2.77E+06 5.27E+07 1.51E+02 7.62E+02 3.52E+05 8.26E+02 5.56E+01 2.12E+03 1.43E+02 3.18E+01 2.87E+00 2.69E+04 1.78E+01 1.54E+01 7.28E+04 1.50E+07
- 5. 70E+02
- 1. 63E+02 3.85E+03 4.97E+01 8.43E+04 2.12E+02 6.06E+02 9.22E+04 1.01E+03 5.05E+04 7.21E+01 3.96E+03 3.61E+02 1.42E+01 5.67E+04 2.66E+02 5.30E+05 3.60E+05 X
(1/s )
- l. 79EW9 3.84E-12 1.28E-05 5.61E-07 2.90E-07 2.57E-08 7.45E-05 8.13E-09 1.80E-07 2.96E-08 1.13E-07 4.17E-09 2.19E-10 7.65E-05 1.52E-05 3.28E-08
- 1. 40E-05
- 2. 08E-04 5.45E-06 8.08E-05 3.63E-04 4.02E-03 4.29E-07 6.49E-04 7.50E-04 1.59E-07 7.70E-10 2.03E-05 7.09E-05 3.00E-06 2.32E-04 1.37E-07 5.45E-05 1.91E-05
- 1. 25E-07 1.14E-05 2.29E-07 1.60E-04 2.92E-06 3.20E-05 8.13E-04 2.04E-07 4.34E-05 2.18E-08 3.21E-08 Biv 4.80E+00 5.50E+00 5.20E-02 1.10E+00 2.50E-04 2.90E-02 2.90E-02 6.60E-04 6.60E-04 9.40E-03 9.40E-03 9.40E-03 1.90E-02 1.90E-02 1.20E-Ol 4.00E-01 4.00E-Ol 4.00E-01 7.60E-01 7.60E-01 7.60E-01 7.60E-01 1.30E-Ol 1.30E-01 1.30E-01 1.70E-02 1.70E-02 1.70E-02 1.70E-02 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.60E-03
- 1. 70E-04
- 1. 70E-04 9.40E-03 9.40E-03 1.20E-01 2.50E-01 2.50E-01 5.00E-02 S.OOE-02 5.00E-02 1.50E-01 Fmi (cow) 1.00E-02 1.20E-02 4.00E-02 2.50E-02
- 2. 20E-03
- 2. 50E-04 2.50E-04 1.20E-03 1.20E-03 1.00E-03 1.00E-03 1.00E-03 6.70E-03 6.70E-03 1.40E-02 3.90E-02 3.90E-02 3.90E-02 5.00E-02 5.00E-02 5.00E-02 5.00E-02 3.00E-02 3.00E-02 3.00E-02 1.40E-03 1.40E-03 1.40E-03 1.40E-03 1.00E-05 1.00E-05 1.00E-05 1.00E-05 1.00E-05 5.00E-06 5.00E-06 2.50E-03 2.50E-03 7.50E-03 2.50E-02 2.50E-02 1.00E-06 1.00E-06 1.00E-06 5.00E-02 Fmi (goat) 1.70E-01 1.00E-01 4.00E-02 2.50E-01 2.20E-03 2.50E-04 2.50E-04 1.30E-04 1.30E-04 1.00E-03 1.00E-03 1.00E-03 6.70E-03 6.70E-03 1.30E-02 3-90E-02 3.90E-02 3.90E-02 5.00E-02 5.00E-02 5.00E-02 5.00E-02 3.00E-02 3.00E-02 3.00E-02 1.40E-02 1.40E-02 1.40E-02 1.40E-02 1.00E-05 1.00E-05 1.00E-05 1.00E-05 1.00E-05 5.00E-06 5.00E-06 2.50E-03 2.50E-03 7.50E-03 2.50E-02 2.50E-02 1.00E-06 1.00E-06 1.00E-06 5.00E-02 Ffi (beef )
1.20E-02 3.10E-02 3.00E-02 4.60E-02 2.40E-03 8.00E-04 8.00E-04 1.20E-02 1.20E-02 1.30E-02 1.30E-02 1.30E-02 5.30E-02 5.30E-02 9.70E-04 3.00E-02 3.00E-02 3.00E-02 2.60E-02 2.60E-02 2.60E-02 2.60E-02 3.10E-02 3.10E-02 3 '0E-02 6.00E-04 6.00E-04 6.00E-04 6.00E-04 4.60E-03 4.60E-03 4.60E-03 4.60E-03 4.60E-03 3.40E-02 3.40E-02 2.80E-01 2.80E-01 1.10E-03 4.00E-01 4.00E-01 4.00E-01 4.00E-01 4.00E-01 1.70E-02 General Revision 0530p
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.g g
Revis'on 5
?age 133 Table 1.8 (2 of 3)
RADIONUCLIDE DECAY AND STABLE ELE~1EiVT TRANSFER DATA Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135
'Cs'-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-'140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 N6-147 W-187 Np-239 Ar-41 Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Half-Life (minutes) 8.67E+04 1.46E+06 8.35E+04 1.57E+05 5.61E+02 4.84E+04 6.96E+01 1.80E+03 2.50E+01 4.69E+03 7.42E+02 1.16E+04 1.38E+02 1.25E+03 5.26E+01 3.97E+02 1.08E+06
'.90E+04 1.59E+07 3.22E+01 8.31E+Ol 1.84E+04 1.83E+01 1.07E+01 2.41E+03 9.54E+01 4.68E+04 1.98E+03 4.09E+05 1.95E+04
- 1. 73E+01 1.58E+04 1.43E+03 3.39E+03 1.10E+02 1.10E+02 2.69E+02 5.64E+06 7.63E+01 1.70E+02 3.16E+00 5.39E-01 1.70E+04 3.15E+03 (1/s) 1.33E-07 7.91E-09 1.38E-07 7.36E-08 2.06E-05 2.39E-07 1.66E&4 6.42E-06
- 4. 62E-04 2.46E-06 1.56E-05 9.96E-07 8.37E-05 9.24E-06 2.20E-04 2.91E-05 1.06E-08 6.08E-07 7.26E-10 3.59E-04 1.39E-04 6.28E-07 6.31E-04 1.08E-03 4.79E-06 1.21E-04 2.47E-07 5.83E-06 2.82E-OS 5.92E-07 6.68E-04 7.31E-07 8.08E-06 3.41E-06 1.05E-04 1.05E-04 4.29E-05 2.05E-09 1.51E-04 6.79E-05 3.66E-03 2.14E-02 6.79E-07 3.67E-06 Biv N/A N/A 1.30E+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 2.00E&2 2.00E&2 2.00E-02 2.00E-02 2.00E-02 2.00E-02 1.00E-02 l.QOEWZ 1-OOE-02 1.00E-02 5.00E-03 5.00E-03 5.00E-03 5.00E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.40E-03 1.80E-02 2.50E-03 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Fmi (cow) 1.50E-03 1.50E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.20E-02 1.20E-02 1.20E-02 1.20E-02 1.20E-02 1.20E-02 8.00E-03 8.00E-03 8.00E-03 8.00E-03 4.00E-04 4.00E-04 4.00E-04 4.00E-04 5.00E-06 5.00E-06 1.00E-04 1.00E-04 1.00E-04 5.00E-06 5.00E-06 5.00E-06 5.00E-04 5.00E-06 N/A N/A iV/A N/A N/A iV/A N/A N/A Vi/A iV/A Fmi (goat) 1.50E-03 1.50E-03 1.QOE-03 1.00E-03 1.00E-03 1.00E-03 1.00E&3 1.00E-03 1.00E-03 1.00E-03 4.30E-01 4.30E-01 4.30E-01 4.30E-01 4.30E-01 4.30E-Ol 3.00E-01 3.00E-01 3.00E-01 3.00E-01 4.00E&4 4.00E-04 4.00E&4
- 4. QQE-04 5.00E&6 5.00EM6 1.00E-04 1.00E-04
- 1. OOE-04 5.00E&6 5.00EM6 5.00E-06 5.00E&4 5.00E-06 N/A N/A iV/A N/A N/A iV/A N/A Vi/A iV/A N/A
-i (beef )
V/A V/A 7.70E-02
- 7. 70E-02
- 7. 70E-02
- 7. 70E-02
- 7. 70E-02 7.70E-02 7.70E-02 7.70E-QZ 2.90E-03 2.90E-03 2.90E-03 2.90E-03 2.90E-03 2.90E-03 1.50E-02 1.50E-Q2 1.50E-02 1.50E-02 3.20E-03 3.20E-03 3.20E-03 3.20E-03 2.00E-04 2.00E-04 1.20E-03 1.20E-03 1.20E-03 4.70E-03 4.70E-03 3.30E-03 1.30E-03 2.00E-04 N/A N/A N/A V/A V/A V/A N/A N/A N/A V/A
'General 'Revision 0530p
0 lt 4
RETS Manual Revision 5
Page 134 Table 1.8 (3 of 3)
RADIONUCLIDE DECAY AiVD STABLE EL"=fEVT TRAVSFER DATA Fmi (cow)
Half-Life
'A Biv Fmi (minutes)
(1/s)
(goat)
Ffi (beef )
Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 7.55E+03 1.54E+Ol 5.47E+02 3.83E+00 1.41E+Ol 1.53E-06 7.50E-04 2.11E-05 3.02E-03 8.19E-04 N/A iV/A iV/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 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.
i
~
~
P h
Jh
~ h I ~
1 I
'General'Revision 0530p
h~ S yg Q t 4 C
Table 1.9 (1 of 2)
DOSE CALCULATEON FACTORS RE:S.'!anuai Revis'on 5
Page 135 Factor BRa (infant)
BRa (child)
BRa (teen)
BRa (adult) fg fL fp fs H
Kc M
P
'Qf (cow)
Qf (goat) r tb tcb tcsf te tep tesf tfm thc ts tsv Uam (infant)
U~ (child)
Uam (teen)
Uam (adult)
Uap (infant )
Uap (child)
Uap (teen)
Uap (adult)
Value Units m~ /'year m~ /year m~/year m~ /year 1400 5500 8000 8100 1
1 1
0 9
g/m~
0.072 L/kg-hr 40 kg/m~
240 kg/mi 64 kg/day 08 kg/day 0.47 4.73K+08 seconds (15 years) 7.78E+06 seconds (90 days) 1.56E+07 seconds (180 days) 5.18E+06 seconds (60 days) 2.59E+06 seconds (30 days) 7.78E+06 seconds (90 days)-
8.64E+04 seconds (1 day) 8.64E+04 seconds (1 day) 1.12E+06 seconds (13 days) 2.38E+07 seconds (275 days) 0 kg/year 41 kg/year 65 kg/year 110 kg/year 330 L/year 330 L/year 400 L/year 310 L/year Reference 1CRP 23 ZCRP 23 1CRP 23 ICRP 23 TVA Assumotion R.
G. 1.109 (Table E-15)
TVA Assumotion TVA Assumotion TVA Value R. G. 1.109 (Section 2.C.)
R.
G.
1.109 (Section 2.C.)
R.
G. 1.109 (Table E-15)
NEEG/CR-1004 (Sect. 3.4)
NUREG/CR-1004 (Sect. 3.4)
IlRREG/CR-1004 (Sect.
3.2)
R.
G.
1.109 (Table E-15)
R.
G. 1.109 R.
G.
1.109 R.
G.
1.109 R.
G.
1.109 R.
G.
1.109 R.
G. 1.109 R.
G. 1.109 R.
G. 1.109 (Table E-5)
(Table E-5)
(Table E-5)
(Table E-5)
(Table E-5)
(Table E-5)
(Table E-5)
(Table E-5)
SQN FSAR Sect'on 11.3.9.1 SQN FSAR Section 11.3.9.1 R.
G.
1.109 (Table E-15)
R.
G. 1.109 (Table E-15)
R.
G. 1. 109 (Tab le E-15 )
SQN FSAR Section 11.3.9.1 NUREG/CR-1004, Table 3.40 NUREG/CR-1004, Table 3.40 SQN FSAR Section 11.3.9.1 General Revision 0530p
,<t,
Table 1.9 (2 of 2)
DOSE CALCULATION FACTORS RETS.'Ianua1 Revision 5
Page 136 Factor Value Units Reference Ufa(infant )
Ufa(child)
Ufa(teen)
Ufa(adult)
UFL (infant)
UFL (child)
UF1 (teen)
UF1 (adult)
USa (infant)
USa (child)
USa (teen)
USa (adult)
U~a(infant)
U~a(child)
U~a(teen)
Uma (adul t )
M Yf Yp Ysf Ysv X~ (iodines)
'X~ (particulates) 0 6.9 16 21 0
26 42 64 0
520 630 520 330 510 510 730 0.3 1.85 1.18 0.64 0.57 kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year L/year L/year L/year L/year none kg/m~
kg/m~
kg/m~
kg/m~
7.71E-07 sec (15.4 d half-life) 5.21E-07 sec (10.4 d half-life)
R.
G. 1.109 (Table E-5)
R.
G.
1.109 (Table E-5)
R.
G.
1.1.09 (Table E-5)
R.
G.
1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R. G.'.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R. G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G. 1.109 (Table E-5)
R.
G.
1.109 (Table E-5)
R.
G. 1.109 (Table A-2)
NUREG/CR-1004 (Table 3.4)
NUREG/CR-I.004 (Table 3.3)
NUREG/CR-1004 (Table 3.3)
NUREG/CR-1004 (Table 3.4)
(value selected is for non-l.eafy vegetables)
NUREG/CR-1004 (Table 3.10)
NUREG/CR-1004 (Table 3.10)
General Revision 0530p
l t
k l
,Table 1.10 (1 of 8)
INHALATION DOSE FACTORS (mremlpCi inhaled).
RETS Manual Revis on 5
Page 137 H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Hn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89
,Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 RLL-103 Ru-105 Ru-106 Ag-110m bone 1.58E-07
- 2. 27EW6
- 1. 28E-06 1.65E-04 O.OOE+00 0.00E+00 O.OOE+00 3.07E-06 1.47E-06 0.00E+00 O.OOE+00 O.OOE+00 5.40E-05 1.92E-10 0.00E+00
'4;05E-06 4.23E-12 1.02E-09 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 3.80E-05 1.24E-02 7.74E-09 8.43E-10 2.61E-07 3.26E-11 5.78E-05 1.29E-09 1.18E-OS 1.34E-05 1.21E-08 1.76E-06 2.78E-11 O.OOE+00 1.29E-13 5.22E-15 1.91E-07 9.88E-11 8.64E-06 1.35E-06 liver
- 1. 58E-07
- 1. 55E-1.0
- 2. 12E-06 3.47E-06 8.65E-08 1.98E-07 1.44E-06 3.93E-06 2.62E-11 1.83E-10 1.29E-05 8.14E-12 2.45E-09 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 1.69E-05 4.84E-08 3.20E-OS 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 4.30E-06 2.45E-09 9.77E-07 7.03E-12 1.51E-OS 3.64E-13 7.52E-15 O.OOE+00 O.OOE+00 O.OOE+00
- 1. 25E-06 t body 1.58E-07 4.26E-07 1.28E-06 6.26E-06 1.25E-08 7.87E-07 2.29E-11 4.93E-07 1.32E-06 8.39E-OS 2.59E-07 1.85E-06 1.81E-06 1.14E-11 7.69E-11 5."82E-06 5.65E-13 2.24E-10
- 1. 69E-06 3.01E-OS 3.91E-OS 1.60E-09 7.37E-06 2.41E-08 2.12E-OS 1.09E-06 7.62E-04 3.13E-10 3.64E-ll 7.01E-09 1.27E-12 1.55E-06 3.77E-ll 3.26E-10 2.91E-06 1.13E-09 5.26E-07 2.56E-12 2.87E-09 4.63E-12 7.38E-14 8.23E-OS 3.89E-11 1.09E-06 7.43E-07 ADULT thyroid 1.58E-07 4.26E-07 1.28E-06 O.OOE+00 7.44E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0;OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 kidney 1.58E-07 4.26E-07 1.28E-06 O.OOE+00 2.85E-09
- 1. 23EW6 1.63E-10 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.78E-10 8.62K-06 5 '7E-12 1.48E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.77E-06 3.71E-09 9.67EW7 8.18E-12 3.64E-OS 5.52E-12 1.35E-13 7.29E-07 1.27E>>10 1.67E-05 2.46E-06 lung 1.58E-07 4.26E-07 1.28E-06 0.00E+00 1.80E-06 1.75E-04
- 1. 18E-06
- 9. 01E-06 1.27E&4
- 4. 62E-05
- 1. 16E-04 46E-04 2.23E-05 7.00E-07 8.48E-07 1.08E-04 1.15E-07 2.38E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 1.75E-04 1.20E-03 4.56E-06 2.06E-06 2.12E-05 2.40E-07 2.13E-04 1.96E-06 6.06E-06 2.21E-04 9.84E-06 6.31E-05 3.00E-07 1.14E-05 9.55E-OS 4.99E-OS 6.31E-05 1.37E-06 1.17E-03 5.79E-04 gi-lli 1.58E-07 4.26E-07 1.2SE-06 1.08E-05 4.15E-07 9.67E-06 2.53E-06 7.54E-07 2.35E-05 3.93E-06 1.33E-05 3.56E-05 1.67E-06 1.54E-06 6.12E-06 6.68E-06 2.04E-09 1.71E-05 1.30E-06 2.90E-OS 2.05E-13 O.OOE+00 2.08E-06 4.18E-19 1.16E-21 4.37E-05 9.02E-05 2.39E-05 5.38E-06 6.32E-05 1.66E-10 4.81E-05 9.19E-06 5.27E-05 1.88E-05 6.54E-05 1.30E-05 3.02E-OS 3.10E-05 5.20E-07 1.36E-21 1.38E-05 6.02E-06 l.l.4E-04 3-78E-05 General Revision 0530p
P lp E
4'
Table 1.10 (2 oi 8)
INHALATIGN DOSE FACTORS (mrem/pCi inhaled)
C""TS '~mewl Revision 5
Page 138 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135's-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144.
Nd-147 W-187 Np-239 bone
- 3. 90E&6 6.67E-06 4.27E-07 1.58E-06 1.75E-10
- 1. 22E&6 6.22E-12 8.74E-09 1.39E-12 3.25E-OS 5.72E-07 3.15E-06
- 1. 45E-07 1.08E-06 8.05E-08 "3.35E-'07 4.66E-05 4.88E-06 5.98E-05 4.14E-OS 1.17E-10 4.88E-06 1.25E-11 3.29E-12 4.30E-OS 8.54E-11 2.49E-06 2.33E-OS 4.29E-04 1.17E-06 3.76E-12 6.59E-07 1.06E-09 2.87E-OS liver 7.36E-OS 7.44E-08 1.98E-07 7.21E-07 8.03E-11 5.84E-07 2.99E-12 5.45E-09 7.44E-13
- 2. 69E&8 1.68E-06 4.47E-06 4.07E-07 1.SSE-06 2.16E-07 8.73E-07 1.06E-04 1.S3E-05 7.76E-05 7.76E-OS 8.32E-14 6.13E-09 9.41E-15 3.38E-15 2.17E-OS 3.88E-11 1.69E-06 1.72E-OS 1.79E-04 4.69E-07 1.56E-12 7.62E-07 8.85E-10 2.82E-09 t body 1..55E-06 1.58E-06 5.84E-OS 1.96E-07 3.87E-11 1..98E-07.
1.55E-12 3.63E-09 4.49E-13 2.02E-OS
- 6. 60E-07 2.56E-06
- 1. 45E-07 S. 65E-07 7.69E-08 3.21E-07 9.10E-05 l.38E-05 5.35E-O5 4.05E-OS 3.42E-12 3.21E-07 4.20E-13 2.07E-13 5.73E-09 9.6SF;12
- 1. 91E7 1.91E-09 2.30E-OS 5.80E-OS 1.91E-13 4.56EMS 3.10E-10 1.55E-09 ADULT thyroid 9.44E-09 6 '5E-09 1.31E-07 4.11E-07 1.32E-10 4.30E-07 4.87E-12 6.88E-09 1.17E-12 2.37E-08 1.42E-04 1.49E-03 1.43E-05 2.69E-04 3.73E-06 5.60E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOEw00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 1.55E-06 5.72E-06 6.37E-10 4.57E-06 2.34E-11 3.86E-OS 5.46E-12 1.82E-07 2.61E-06 7.66E-06 6.48E-07 3.23E-06 3.44E-07 1.39E-06 3.59E-05 1.07E-05 2.78E-O5 6.00E-OS 7.78E-14 2.09E-09 8.7SE-15 2.86E-15 O.OOE+00 O.OOE+00 7.83E-07 7.60E-09 1.06E-04 2.70E-07 8.81E-13 4.45 E-07 O.OOE+00 8.75E-09 lung 3.10E-04
- 2. 18E-04 3.92E-05 1.20E-04 8.1.4E-07 1.45E-04 2.42E-07 1.S2E-05 1.74E-07 3.60E-05 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 1.22E-05 1.50E-06 9.40E-06 6.07E-09 4.70E-07 1.59E-04 2.42E-07 1.49E-07 1.70E-05 7.91E-07 4.52E-05 9.97E-06 9.72E-04 3.51E-05 1.27E-07 2.76E-05 3.63E-06 4.70E-06 gi-lli 5.08E-05 1.26E-05 8.83E-06 1.87E-05 7.17E-06 4.79E-05 1.96E-OS 6.95E-05 2.30E-09 6.37E-05 9.61E-07 7.85E-07 5.08E-OS 1.11E-06 1.26E-10 6.56E-07 1.30E-06 1.46E-06 1.05E-06 2.33E-1.3 1.12E-07 2.73E-05 1.45E-17 1.96E-26 5.73E-05 2.64E-07 1.50E-05 2.83E-05 1.02E-04 2.50E-05
- 2. 69E-18
- 2. 16E-05 1.94E-05 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 total body dose factor. for bone is assumed to be equal to the General Revision 0530p
~C 4
I1',;$
II 0,
Table 1.I.O (3 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
RETS Manual Revision 5
Page 139 H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58
'Zn-65 Zn-69 Zn-69m Br-82 Br-83
. Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90
,Y-.91m-Y-91 X-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-l.01 RG-103 Ru-105 Ru-106 Ag-110m bone 1.59E-07
- 3. 25E-06
- 1. 72E-06 2.36E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.18E-06
- 1. 99E&6 O.OOE+00 0.00E+00 O.DOE+00
- 7. 25E-05 2.73E-10
- 0. OOE+00
- 4. 82E-06 6.04E-12 1.44E-09 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 5.43E-05 1.35E-02 1.10E-08 1.19E-09 3.73E-07 4.63E-ll 8.26E-05 1.84E-09 1.69E-08 1.82E-05 1.72E-08 2.32E-06 3.92E-11 O.OOE+00 1.73E-13 7.40E-15 2.63E-07 1.40E-10 1.23E-05 1.73E-06 liver 1.59E-07 6.09E-07 1.72E06 1.37E-05 O.OOE+00 6.39E-06 2.12E-10 2.98E-06 4.62E-06 1.18E-07 2.59E-07 1.89E-06 5.43E-06 3.66E-11 2.54E-10
~
1.67E-05 1.15E-11 3.39E-09 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 2.38E-05 6.82E-08 4.40E-08 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 5.73E-06 3.40E-09 1.29E-06 9.72E-12 2.11E-08 4.83E-13 1.05E-14 0.00E+00 O.OOE+00 0.00E+00 1.64E-06 t body 1.59E-07 6.09E-07 1.72E-06 8.95E-06 1.69E-08 1.05E&6
- 3. 15E-11 6.93E-07 1.79E-06 1.15E-07 3.47E-07 2.48E-06 2.47E-06 1.59E-11 1.06E-10 7.80E-06 8.07E-13 3.11E-10 2.28E-06 4.30E-08 5.41E-08 2.29E-09 1.05E-05 3.40E-08 2.91E-08 1.56E-06 8.35E-04 4.39E-10 5.08E-11 1.00E-08 1.77E-12 2.21E-06 5.36E-11 4.65E-10 3.94E-06 1.57E-09 7.08E-07 3.55E-12 4.03E-09 6.24E-12 1.03E-13 1.12E-07 5.42E-11 1.55E-06 9.99E-07 TEEN thyroid 1.59E-07 6.09E-07 1.72E06 O.OOE+00 9.37E-09 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 kidney 1.59E-07 6.09E-07 1.72E-06 O.OOE+00 3.84E-09 1.59E-06 2.24E-10 O.OOE+00 O.OOE+00 0.DOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.01E-10 1.08E-05 7.53E-12 2.06E-09 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 8.42E-06 5.15E-09
- 1. 25E-06 1.14E-11 5.14E-08 7.20E-12 1.90E-13 9.29E-07 1.76E-10 2.38E-05 3.13E-06 lung 1.59E-07 6.09E-07 1.72E-06 O.OOE+00 2.62E-06 2.48E-04 1.90E-06 l.55E-05 1.91E-04 7.33E-05 1.68E-04 1.09E-03 3.84E-05 1.17E-06 1.39E-06 1.55E-04 1.98E-07 3.92E-06 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 3.02E-04 2.06E-03 7.59E-06 3.43E-06 3.66E-05 4.00E-07 3.67E-04 3.35E-06 1.04E-05 3.36E-04 1.62E-05 9.39E-05 4.91E-07 1.92E-05 1.44E-07 8.34E-08 9.79E-05 2.27E-06 2.01E-03 8.44E-04 gi-lli 1.59E-07 6.09E-07 1.72E-06 1.16E-05 3.75E-07 8.35E-06 7.18E-06 7.99E-07 2.23E-05 3.93E-06 1.19E-05 3.24E-05 1.77E-06 4.59E-06 7.68E-06 5.83E-06 3.56E-08 2.14E-05 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 2.21E-06 3.65E-15 4.22E-17 4.64E-05 9.56E-05 3.24E-05 1.49E-05 6.99E-05 3.77E-09 5.11E-05 2.06E-05 7.24E-05 1.86E-05 7.88E-05 1.21E-05 2.71E-07 3.36E-05 7.66E-07 1.09E-16 1.36E-05 1.13E-05 1. 20E-04 3.41E-05 General Revision 0530p
"0 a 1 g h
E 4
'gfll
~ 8
Table 1.10 (4 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
RETS "fan~1 Revision 5
Page 140 Sb-124 Sb-125 Te-125m Te-127m Te>>127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134
'I-'135 Cs<<134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 5.38E-06 9.23E-06 6.10E-07 2.25E-06 2.51E-10 1.74E-06 8.87E-12 1.23E-OS 1.97E-12 4.50E-08 7.80E-07 4.43E-06 1.99E-07 1.52E&6 1.11E-07 4.6'2E&7 28E&5 6.44E-06 8.38E-05 5.82E-OS 1.67E-10 6.84E-06 1.78E-11 4.62E-12 5.99E-OS 1.20E-10 3.55E-06 3.32E-OS 6.11E-04 1.'67E-06 5.37E-12 9.83E-07 1.50E-09 4.23E-08 liver 9.92E-OS 1.01E-07 2.80E-07 1.02E-06 1.14E-10 8.23E-07 4.22E-12 7.51E-09 1.04E-12 3.63E-OS 2.24E-06 6.14E-06 5.47E-07
- 2. 56E&6
- 2. 90E-07 1.18E-06 1.41E-04 2.42E-05 1.06E-04 1.07E-07 1.18E-13 8.38E-09 1.32E-14 4.63E-15 2.95E-OS 5.31E-ll 2.37E-06 2.42E-OS 2.53E-04 6.64E-07 2.20E-12 1.07E-06 1.22E-09 3.99E-09 t body 2.10E-06 2.15E-06 8.34E-OS 2.73E-07 5.52E-11 2.81E-07 2.20E-12 5.03E-09 6.30E-13 2.74E-OS 8.96E-07 3.30E-06 1.97E-07 7.78E-07 1.05E-07 4.36E-07 6.86E-05 1.71E-05 3.89E-05 5.58E-08 4.87E-12 4.40E-07 5.93E-13 2.84E-13 7.82E-09 1.32E-11 2.71E-07 2.70E-09 3.28E-05 8.28E-08 2.72E-13 6.41E-08 4.29E-10 2.21E-09 TEEN thyroid 1.22E-08 S.SOE-09
- 1. 75E-07 5.48E-07 1.77E-10 5.72E-07 6.48E-12 9.06E-09 1.55E-12 3.07E-OS 1.86E-04 1.83E-03 1.89E-05 3.65E-04 4.94E-06 7.76E-05 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 8.17E-06 9.10E-10 6.49E-06 3.32E-11 5.49E-OS 7.72E-12 2.44E-07 3.44E-06 1.05E-05 8.65E-07 4.49E-06 4.58E-07 1;86E-06 4.69E-05 1.38E-05 3.80E-05 8.28E-08 1.11E-13 2.85E-09 1.23E-14 3.92E-15 0.00E+00 0.00E+00 1.11E-06 1.08E-OS 1.51E-04 3.86E-07 1.26E-12 6.28E-07 0.00E+00 1.25E-OS lung 4.81E-04 3.42E-04 6.70E-05 2.07E-04 1.40E-06 2.47E-04 4.12E-07 2.97E-05 2.92E-07 5.61E-05 0.00E+00 O.OOE+00 O.DOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.83E-05 2.22E-06 1.51E-05 9.84E-09 S.OSE-07 2.54E-04 4.11E-07 2.39E-07 2.68E-05 1.27E-06 7.67E-05 1.63E-05 1.67E-03 6.04E-05 2.19E-07 4.65E-05 5.92E-06 8.11E-06 gi-lli 4.98E-05 1.24E-05 9.38E-06 1.99E-05 1.01E-05 5.06E-05 2.02E-07 7.76E-05 1.89E-09 5.79E-05 1.14E-06 8.11E-07 1.59E-07 1.29E-06 2.55E-09 8.69E-07 1.22E-06 1.36E-06 1.06E-06 3.38E-11 8.06E-07 2.86E-05 9.33E-14 5.99E-20 6.09E-05 1.50E-06 1.58E-05 3.19E-05 1.08E-04 2.67E-05 2.94E-14 2.28E-05 2.21E-05 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 total body dose factor. for bone is assumed to be equal to the General Revision 0530p
'/
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KI "4
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4 E
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Table 1.10 (5 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
RETS M~nual Revision 5
Page 141 I
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'9
,V 1
~ '.1
~ ~J 1
1 H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 CLL-64
" 'Zn-'65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 RQ-103 Ru-105 Ru-106 Ag-110m bone 3.04E-07
- 9. 70E&6 4.35E-06 7.04E-O4 0.00E+00 O.OOE+00 O.OOE+00 l.28E&5 5.59E&6 0.00E+00 O.OOE+00 O.OOE+00
- 2. 22E&4 8.08E-10 O.OOE+00 1.15E-05 1.81E-11 4.26E-09 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.62E-04 2.73E-02 3.28E-OS 3.54E-09 1.11E-06
.1.37E-10 2.47E-04 5.50E-09 5.04E-OS 5.13E-05 5.07E-OS 6.35E-06 1.16E-10 O.OOE+00 4.81E-13 2.19E-14 7.55E-07 4.13E-10 3.68E-05 4.56E-06 liver 3.04E-07 1.82E&6 4.35E-06 3.09E-05 O.OOE+00 1.16E-05 4.48E-10 6.80E-06 9.04E-06 2.44E-07 4.79E-07 3.55E-06 1.25E-05 7.99E-ll 5.39E-10 3.06E-05 2.61E-ll
- 7. 28E&9 0.00E+00 0.00E+00 0.00E+00 0.00E+00
'5.36E-05 1.52E-07 9.33E-OS 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 1.13E-05 7.34E-09 2.48E-06 2.08E-11 4.66E-08 9.41E-13 2.30E-14 0.00E+00 O.OOE+00 O.OOE+00 3.08E-06 t body 3.04E-07
- 1. 82E-06 4.35E-06 2.67E-05 4.17E-OS 2.57E-06 8.43E-11
- 2. 10E-06 4.51E-06 2.88E-07 8.55E-07 6.12E-06 7.56E-06 4.44E-11 2.90E-10 1.90E-05 2.41E-12 8.59E-10 5.66E-06 1.28E-07 1.48E-07 6.84E-09 3.09E-05 9.90E-08 7.83E-OS 4.66E-06 1.74E-03 1.24E-09 1.42E-10 2.99E-OS 4.98E-12 6.59E-06 1.57E-10 1.38E-09 1.00E-05 4.32E-09 1.77E-06 9.74E-12 1.15E-OS 1.56E-11 2.91E-13 2.90E-07 1.50E-10 4.57E-06 2.47E-06 CHILD thyroid 3.04E-07 1.82E-06 4.35E-06 O.OOE+00 2.31E-OS O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00
.0. OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 kidney 3.04E-07 1.82E-06 4.35E-06 0.00E+00 6.57E-09 2.71E-06 4.52E-10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.63E-09 1.93E-05 1.58E-11 4.22E-09 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 1.61E-05 1.05E-OS 2.33E-06 2.31E-11 1.06E-07
- 1. 37E-11 3.92E-13 1.90E-06 3.63E-10 4.97E-05 5.74E-06 lung
- 3. 04E-07 1.82E-06 4.35E-O6 O.OOE+00 4.59E-06 4.26E-04 3.55E-06 3.00E-05 3.43E-04 1.37E-04 2.99E-04 1.91E-03 7.43E-05 2.21E-06 2.59E-06 2.69E-04 3.84E-07 7.36E-06 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.83E-04 3.99E-03 1.44E-05 6.49E-06 7.07E-05 7.60E-07 7.10E-04 6.46E-06 2.01E-05 6.03E-04 3.06E-05 1.66E-04 9.23E-07 3.66E-05 2.57E-07 1.58E-07 1.79E-04 4.30E-06 3.87E-03 1.48E-03 gi-lli 3.04E-07 1.828-06 4.35E-06 1.14E-05 2.93E-07 6.19E-06 3.33E-05 7.75E-07 1.91E-05 3.58E-06
- 9. 29EW6 2.60E-05 1.71E-06 2.27E-05 9.92E-O6 4.41E-06
- 2. 75E-06 2.71E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
- 2. 16F;06 4.66E-09 5.11E-10 4.52E-05 9.28E-05 4.70E-05 6.55E-05 7.24E-05 4.64E-07 4.97E-05 6.46E-05 1.05E-04 1.65E-05 9.49E-05 1.00E-05 7.52E-06 3.42E-05 1.30E-06 4.41E-09 1.21E-05 2.69E-05 1 ~ 16E-04 2-71E-05
~ 'I
- I General Revision 0530p
t, I'
I s
s V' ll~4
Table 1.10 (6 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
RETS Nanyal Revision 5
Page 142 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134
'I-135 '
Cs-134 Cs-136 Cs-137 Cs-138
'a-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone 1.55E-05
- 2. 66E<5 1.82E-06 6.72E-06 7.49E-10 5.19E&6 2.64E-11 3.63E-08 5.87E-12 1.30E-07 2.21E-O6 1.30E-05 5.72E-07 4.48E-06 3.17E-07 1.33E-06 1.76E'-04 1.76E-05 2.45E-04 1.71E-07 4.98E-10 2.00E-05 5.29E-11 1.35E-11 1.74E-07 3.50E-10 1.06E-05 9.89E-OS 1.83E-03 4.99E-06 1.61E-11 2.92E-06 4.41E-09 1.26E-07 liver 2.00E-07 2.05E-07
- 6. 29E-07 2.31E&6 2.57E-10 1.85E-06 9.45E-12 1.60E-OS 2.28E-12 7.36E-OS 4.43E-06 1.30E-05 1.10E-O6 5.49E-06 5.84E-07 2.36E-06 2.74E-O4 4.62E-O5 2.23E-04
- 2. 27E-07 2.66E-13 1.75E-OS 2.95E-14 9.73E-1.5 6.08E-OS 1.11E-10 5.28E-06 5.37E-OS 5.72E-04 1.50E-06 4.99E<<12 2.36E-06
- 2. 61E-09 9.04E-09 t body 5.41E-06 5.59E-06 2.47E-07 8.16E-07 1.65E-10 8.22E-07 6.44E-12 1.37E-OS 1.78E-12 7.12E-08 2.28E-06 7.37E-O6 5.07E-07 2.08E-06 2.69E-07 1.12E-06 6.07E-05 3.14E-O5 3.47E-05 1.50E-07 1.45E-ll 1.17E-06 1.72E-12 7.54E-13 2.04E-08 3.49E-11 7.83E-07 7.77E-09 9.77E-05 2.47E-07 8.10E-13 1.84E-07 1.17E-09 6.35E-09 CHILD thyroid 3.41E-OS 2.46E&8
- 5. 20E-07 1.64EW6 5.30E-10 1.71E-06 1.93E-11 2.64E-OS 4.59E-12 8.58E-OS
- 4. 99E-04 4.39E-03 5.23E-05 1.04E-03 1.37E-05 2.14E-04 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 1.72E-05 1.91E-09 1.36E-05 6.94E-11 1.08E-07 1.59E-11 4.79E-O7 6 ~ 61EW6 2.13E-05 1.69E-06 9.13E-06 8.92E-07 3.62E-06 8.93E-05 2.58E-05 7.63E>>05
- 1. 68E-07 2.33E-13 5.71E-09 2.56E-14 7.87E-15 O.OOE+00 O.OOE+00 2.31E-06 2.26E-OS 3.17E-04 8.11E-07 2.64E-12 1.30E-06 O.OOE+00 2.63E-OS lung
- 8. 76E-04 6.27E-04 1.29E-04 4.00E-04 2.71E-06
- 4. 76E-04 7.93E-07 5.56E-05 5.55E-07
'.02E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.27E-05 3.93E-06 2.81E-05 1.84E-OS 1.56E-06 4.71E-04 7.89E-07 4.44E-07 4.94E-05 2.35E-06 1.47E-04 3.12E-05 3.23E-03 1.17E-04 4.23E-07 8.87E-05 1.11E-05 1.57E-05 gi-lli 4.43E-05 1.09E-05 9.13E-06 1.93E-05 1.52E-05 4.91E-05 6.89E-06 8.32E-05
- 3. 60E-07 3.72E-05 1.38E-06 7.68E-07
.8.65E-07 1.48E-06 2.58E-07 1.20E-06 1.04E-06 1.13E-06 9.78E-07 7.29E-OS 1.56E-05
- 2. 75E-05
- 7. 44E-08 7.41E-10 6.10E-05 2.05E-05 1.53E-05 3.44E-05 1.05E-04 2.63E-05 5.32E-OS 2.22E-05 2.46E-05 1.73E-05
',I
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( ~
j4r
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NOTE: The tritium dose factor total body dose factor. for bone is assumed to be equal to the
Reference:
Regulatory Guide 1.109, Table E-9.
Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a Chronic Intake November 1977, Table 6.
are from One Year
.. General Revision 0530p
V 4,
J%
\\
P P
Table 1.10 (7 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled)
INFANT RETS Manual Revision 5
Page 143
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.H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 CLI-64
" Zn-65 Zn-'69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88
.Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m
.Y.-91 Y-92 Y-,93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m bone
,4. 62E&7 1.89E-05 7.54E-O6 1.45E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.41E-05 9.69E-06 O.OOE+00 0.00E+00 0.00E+00 2.42E-04 1.71E-09 0.00E+00 1.38E-05 3.85E-11 8.98E-09 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 2.84E-04 2.92E-02 6.83E-08 7.50E-09 2.35E-06 2.91E-10 4.20E-04 1.17E-08 1.07E-07 8.24E-05 1.07E-07 1.12E-05 2.44E-10 O.OOE+00 9.98E-13 4.65E-14 1.44E-06 8.74E-10 6.20E-05 7.13E-06 liver
- 4. 62E-07 3.79E-06 7.54E-06 8.03E+05 O.OOE+00 1.81E-05 1.10E-09 8.39E-06 1.68E-05 4.65E-07 8.71E-07 5.73E-06 1.46E-05 2.03E-10 1.34E-09 4.47E-05 6.91E-11 1.84E-08
,0. OOE+00 O.OOE+00 O.OOE+00 0.00E+00 1.36E-04 3.98E<<07 2.29E-07 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0;OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.99E-05 1.83E-08 4.59E-06 5.21E-11 1.18E-07 2.06E-12 5.88E-04 O.OOE+00 O.OOE+00 O.OOE+00 5.16E-06 t body 4.62E-07 3.79E-06 7.54E-06 5.53E-05 6.39E-08 3.56E-06 1.58E-10 2.38E-06 6.77E-06 4.58E-07 1.30E-06 8.41E-06 8.29E-06 8.79E-11 5.53E-10
- 2. 22E&5 5.13E-12 1.67E-09 9.49E-06 2.72E-07 2.86E-07 1.46E-08 6.30E-05 2.05E-07 1.47E-07
- 8. 15E-06 1.85E-03 2.47E-09 2.79E-10 6.30E-08 9.90E-12 1.12E&5 3.29E-10 2.91E-09 1.45E-05 8.36E-09 2.70E-06 1.88E-11 2.31E-08 2.66E-11 5.80E-13 4.85E-07 2.93E-10 7.77E-06 3.57E-06 thyroid 4.62E-07 3.79E-06 7.54E-06 O.OOE+00 4.11E-08 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 kidney 4.62E-07 3.79E-06 7.54E-06 O.OOE+00 9.45E-09 3.56E-06 7.86E-10 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 2.84E-09 2.32E-05 2.87E-11 7.45E-09 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0;OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 2.22E-05
'1.85E-08 3.37E-06 4.07E-11 1.89E-07
, 2.22E-11 6.99E-13 3.03E-06 6.42E-10 7.61E-05 7.80E-06 lung 4.62E-07 3.79E-06 7.54E-06 O.OOE+00 9.'1 7E-06 7.14E-04
- 8. 95EW6 6.21E-05 7.25E-04 2.71E-04 5.55E-04 3.22E-03 1.49E-04 5.80E-06 6.64E-06 4.62E-04 1.05E-06 1.91E-05 O.OOE+00
- 0. OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 1.45E-03 8.03E-03 3.76E-05 1.70E-05 1.92E-04 1.99E-06 1.75E-03 1.75E-05 5.46E-05
- 1. 25E-03 7.88E-05 3.42E-04 2.37E-06
, 9.63E-05
- 5. 79EW7 4.17E-07 3.94E-04 1.12E-05 8.26E-03
- 2. 62EW3 gi-lli 4.62E-07 3.79E-06 7.54E-06 1.15E-05 2.55E-07 5.04E-06 5.12E-05 7.82E-07 1.77E-05 3.47E-06 7.95E-06 2.28E-05 1.73E-06 3.58E-05 1.07E-05 3.67E-05 9.44E-06 2.92E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.17E-06 2.42E-07 4.87E-08 4.57E-05 9.36E-05 5.24E-05 1.00E-04 7.43E-05 1.68E-06 5.02E-05 9.04E-05 1.19E-04 1.55E-05 1.00E-04 9.05E-06 1.92E-05 3.48E-05, 1.45E-06 6.03E-07 1.15E-05 3.46E-05 1.17E-04 2.36E-05
, - General Revision 0530p
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Table 1.10 (8 of 8)
INHALATION DOSE FACTORS (mrem/pCi inhaled).
RETS "fan,ual Revision 5
Page 144 liver 3.97E-07 3.41E-07 1.42E-06 4.93E-06 6.81E-10 4.35E-06 2.48E-11 3.93E-08 5.87E-12 1.69E-07 9.91E-06 3.17E-05 2.53E-06 1.37E-05 1.34E-06 5.43E-06 5.02E-04 9.61E-05 4.37E-04 5.58E-07 7.03E-13 4.00E-08 7.70E-14 2.36E-14 1.43E-07 2.69E-10 1.19E-05 1.38E-07 8.65E-04 3.74E-06 1.32E-11 5.81E-06 6.44E-09 2.37E-08 bone
- 2. 71E-05 3.69E-05 3.40E-06 1.19E-05 1.59E-09 1.01E&5 5.63E-11 7.62E08 1 ~ 24E-11 2.66E-O7 4.54E-06 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130
- 2. 71E-05 1.21E-06 9.46E-06 6.58E-07
'-2. 76E06 2.83E-04 3.45E-05 3.92E-04 3.61E-07 1.06E-09 4.00E-05 I-131 I-132 I-133 I-134
".'I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 1.12E-10 2.84E-11 3.61E-07 7.36E-10 1.98E-05 2.09E-07 2.28E-03 1.00E-05 3.42E-,11 5.67E-06
- 9. 26E-09
- 2. 65E-07 La-140 La-142 Ce-141 Ce-143
~ Ce ]44 Pr-143 Pr-144 Nd-147 W-187 Np-239 Reference Regu latory Guide 1;109, t body
- 8. 56E-06
- 7. 78E-06 4.70E-07 1.48E-06 3.49E-10 1.59E-06 1.34E 11 2.59E-O8 3-57E-12 1.26E-07 3.98E-06 1.40E-05 8.99E-07 4.00E-06 4.75E-07 1.98E-06 5.32E-05 3.78E-05
- 3. 25E-05 2.84E-07 3.07E-11 2.07E-06 3.55E-12 1.40E-12 3.68E-08 6.46E-11 1.42E-06 1.58E-08 1.26E-04 4.99E-07 1.72E-12 3.57E-07 2.23E-09 1.34E-08 INFANT thyroid 7.18E-08 4.45E-08 1.16E-06 3.48E-06 1.32E-09 3.91E-06 4.82E-11 6.38E-08 1.13E-11 1.99E-07 1.14E-03 1.06E-02 1.21E-04 2.54E-03 3.18E-05 4.97E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 Table E-10.
kidney O.OOE+00 O.OOE+00 O.OOE+00 2.68E-05 3.47E-09 2.27E-05 1.25E-10 1.89E-07 2.85E-11 7.39E-07 1.09E-05 3.70E-05 2.82E-06 1.60E-05 1.49E-06 6.05E-06 1.36E-04 4.03E-05 1.23E-04 2.93E-07 4.23E-13 9.59E-09 4.64E-14 1.36E-14 O.OOE+00 O.OOE+00 3.75E-06 4.03E-08 3.84E-04 1.41E-06 4.80E-12 2.25E-06 O.OOE+00 4.73E-08 lung 1.89E-03 1.17E-03 3.19E-04 9.37E-04 7.39E&6
- 1. 20E-03 2.14E-06 1.42E-04 1.47E-06 2.43E-04 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 5.69E&5 8.40E-06 5.09E-05 4.67E-08 4.25E-06 1.14E-03
- 2. 12E&6 1.11E-06 1.20E-04 5.87E-06 3.69E-04 8.30E-05 7.03E-03 3.09E-04 1.15E-06 2.30E-04 2.83E-05 4.25E-05 gi-lli 4.22E-05 1.05E-05 9.22E-06 1.95E-05 1.74E-05 4.93E-05 1.88E-05 8.51E-05 5.87E-06 3.15E-05 1.42E-06 7.56E-07 1.36E-06 1.54E-06 9.21E-07 1.31E~06 9.53E-07 1.02E-06 9.53E-07 6.26E-07 3.64E-05 2.74E-05 3.39E-06 4.95E-07 6.06E-05 4.25E-05 1.54E-05 3.55E-05 1.06E-04 2.66E-05 3.06E-06 2.23E-05 2.54E-05 1.78E-05 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 total body dose factor. for bone is assumed to be equal to the General Revision 0530p
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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~)
?-32 Cr-51 M-54 Nn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-91 Sr-92 Y-90 Y-91m Y-91
'-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 No-99 Tc-99m Tc-101 RQ-103 Ru-105 Ru-106 Ag-110m Sb-124 Total Body 0.0 0.0 2.50E-OS 0.0 2.20E-10 5.80E-09 1.10E-OS 0.0 S.OOE-09 1.77E-09 7.00E-09 1.70E-OS 0.0
- 3. 70E-09 1.50E-09 4.00E-09 0.0 5.50E-09 3.18E-OS 6.40E-11 1.20E-OS 0.0 6.30E-10 3.50E-09 1.50E-OS 5.60E-13 7.10E-09 9.00E-09 2.20E-12 3.80E-09 2.40E-11 1.60E-09 5.70E-10 5.00E-09"
- 5. 50E-09
- 5. 10E-09
- 8. 11E-09
- 1. 90E-09 9.60E-10 2.70E-09 3.60E-09 4.50E-O9 1.50E-09 1.80E-OS 2.17E-OS Skin 0.0 0.0 2.90E-OS 0.0 2.60E-10 6.80E-09 1.30E-OS 0.0 9.40E-09 2.21E-09 8.20E-09 2.00E-OS 0.0 4.30E-09 1.70E-09 4.60E-09 0.0 6.59E-09 3.90E-08 9.30E-11 1.40E-08 0.0 7.20E-10 4.00E-09 1.80E-08 6.50E-13 8.30E-09 1.00E-OS 2.60E-12 4.40E-09 2.70E-11 1.90E-09 7.80E-10 5.80E-09 6.40E-09 6.00E-09 1.00E-OS
- 2. 20E-09 1.10E-09 3.00E-09 4.20E-O9 5.10E-O9 1.80E-09 2.10E-OS 2.57E-08 General Revision 0530p
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EXTERNAL DOSE RETS.'manual Revision 5
Page 146 Table 1.11 (2 of 2)
FACTORS FOR STA KING ON CONTA fINATED GROIN (mrem/h per pCi/m~)
Nuclide Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135
'Cs-134 Cs-136
,Cs-137 Cs-138 Ba-l.39 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144
. Nd-147 W-187 Np-239 Total Body 5 48E-09 3.50E-ll 1.10E-12 1.00E-11
- 1. 60E-08 1-20E-08 1.20E-08 1-50E-08 4.20E-09 2.10E-08 2.40E-09 2.10E-09 4.30E-09 7.90E-09 1.50E-OS 1.50E-08 5.50E-10 2.20E-09 3.20E-10 0.0 2.00E-10 1.00E-O9 3.10E-09 9.50E-10 Skin 6.80E-09 4.80E-11 1.30E-12 1.10E-11 9.00E-10 8.40E-10 9 '0E-09 2-60E-06 2.00E-09 1.70E-08 3-40E-09 2.00E-08 4.50E-09 1.90E-08 1.40E-08 1.40E-08 1.70E-OS 4-90E-09 2.40E-08 2.70E-09 2 40E-09 4.90E-09 9.00E-09 1.70E-08 1.80E-08 6 20E-10 2.50E-09 3.70E-10 0.0 2.30E-10 1.20E-09 3.60E-09 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.
General Revision 0530p
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Table 2.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS RETS Manual Revision-5 Page 147 Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Name Beginning TRM Ending TRM Size Recreation (acres) visits/year Wheeler Lake below BFN Wilson Lake Pickwick Lake 294.0 275.0 260.0 275.0 26076 1,408,600 230.0 15048 705,500 260.0 15930 3,816,800 Public Water Supplies Within 50 Mile Radius Downstream of BFN Name Muscle Shoals, AL Sheffield, AL
- Cherokee, AL 259. 6 254. 3 239. 2 Population 10,740 13,065 3,400 General Revision 0530p
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Nuclide RETS Manual Revision-5 Page 148 Table 2.2 BIOACCUWL LATION FACTORS FOR FRESHWATER FISH (Page 1 of 1)
Nuclide P ~
I
~ I
~<
H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni<<63 Ni-65 Cu-64 Zn-65
'Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92
-Y-90 Y-91m
,Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 9.0E-01 4.6E+03 1.0E+02 1.0E+05 2.0E+02 4.0E+02 4.0E+02 1.0E+02 1.0E+02 5.0E+01 5.0E+01 5.0E+01 1.0E+02 1.0E+02 5.0EWl 2.0E+03
, 2.0E+03 2.0E+03 4.2E+02 4.2E+02 4.2E+02
- 4. 2E+02 2.0E+03 2.0E+03 2.0E+03 5.6E+01 5.6E+01 5.6E+01 5.6E+01 2.5E+01 2.5E+01 2.5E+01 2.5E+01 2.5E+01 3.3E+00 3 'E+00 3.0E+04 3.0E+04 1.0E+01 Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 1.5E+101 1.0E+01 1.0E+01 1.0E+01 O.OE+00 1.0E+00 1.0E+00 4.0E+02 4.0E+02 4.0E+02 4.0E+02 4.0E+02 4.0E+02 4.0E+02 4.0E+02 4.0E+01 4.0E+01 4.0E+01 4.0E+01 4.0E+01 4.0E+01 1.9E+03 1.9E+03 1.9E+03 1.9E+03 4.0E+00 4.0E+00 4.0E+00 4.0E+00 2.5E+01 2.5E+01 1.0E+00 1.0E+00 1.0E+00 2.5E+Ol 2.5E+01 2.5E+01 1.2E+03 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.
~I General Revision 0530p
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TABLE 3.1 (Sheet 4 of 4)
ENVIRONHENTAL RAOIOLOGICAL HONITORING RETS Hanual Revision 5
Page 152 Exposure Pathway Number of Samples and
~i Locations Fish 3 samples representing commercial and game species in Guntersville 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 Sampling and At least once per 184 days Type and Frequency of Anal sis Gamma scan at least once per 184 days on edible portions, Clams Sample from same locations as sediment (if available)
Same as sediment Gamma scan on flesh only Fruits Vegetables Samples of food crops such as
- corn, green
- beans, tomatoes, 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 At least once per year at Gamma scan on edible portion time of harvest Vegetation (pasturage and grass)
Samples from the nearby dairy farms (Farms B, Bn, L and T), and from the local atmospheric mon-i*toring stations (LH-1, LH-2, LH-3, LH-4, LH-6 and LH-7)
Once per 31 days I-131, gamma scan once per 31 days.
Sr-89 and Sr-90 analysis on'the last monthly sample of each quarter.
Control samples from 1 remote air monitor (RH-1) and 1 control dairy farm (Farm 0)
General Revision hC')A~
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A BROWNS FERRY itUCLEAR PLANT Environmental Radiological Monitoring RETS Manual Revision. 5 Page 153 Program
~ ~
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~l Sampling Locations Approximate Distance (Miles) 13.8 10.9 8.2 2.1 31.3 24.2 0.97 0.88 0.92 1.7 3.0 6.8 5.0 5.9 0.02 11.4d 12.0 31.3 19.1d 8.8d O.Sd 11 Od 13.52 0.3d s.zzd 16 02 28.8 26.2 3.2 Location Number a Station Sector NW NE SSE W
W E
N NNE ENE NNM SSW NNW N
ENE NW 1
2 3
4 5
6 7
8 9
10 11 12 13 14
.22 23 24 25 26 27 28 29 30 31 32 33 34
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36 37 PM-1 PM-2 PM-3 LM-7 RM-1 RM-6 LM-1 LM-2 LM-3 LM-4 LM-6 Farm B
Farm Bn Farm L Well 86 c 282 6
TRM 274.9 TRM 285.2 TRM 293.5 TRM 305.0 TRM 307.52 TRM 293.7 TRM 288.78 TRM 277.98 Farm Be NW Farm 0 E
Farm T WNM TRM 297.0
'Wilson'Reservoir (TRM zs9-27s)
Wheeler Reservoir (TRM 275-349)
Guntersville Reservoir (TRM 349-424)
Samples Collected>
V M,
V M,
V M, V, M
W PM PM PM PW SW SM SW CL, SD CL, SD CL, SD CL, SD II I
I C
CIIIIIIIIII CIIII Ce CI II CIII M, V V
F F
Indicator (I) or Control (C) li 4 ~
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S = Soil SW = Surface Water V = Vegetation See figures 3.1, 3.2, and 3.3 Sample codes:
AP ~ Air particulate filter CF ~ Charcoal Filter F ~ Fish W ~ Well Water TRM ~ Tennessee River Mile Miles from plant discharge'(TRM 294)
Also used as a control for public water SD =
CL ~
PW ~
Sediment Clams Public Water General 0530p Revision
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Figure 3.2 RETS "ianual Revision.5 Page 173 Environmental Radiological Sampling Locations From 1 to 5 Miles From The Plant
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Those listed FROM DATES D. R. Gallien, Supervisor, Chemical Technical Support Section,'rowns Ferry Nuclear Plant
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:
0 Responsible
~Grou Mods PMT CTS ISC Tech IMs Comp Date 4-22-88 5-20-88 5-20-88 5-20-88 Item Liquid Process Rad ation Monitors:
Complete field work Complete Post Mod Test Source check SI written and approved Calibration and Functional SIs written and approved Run New SIs 6-17-88 Liquid Radwaste Effluent Instrumentation:
PMT IRC Tech IMs Complete Post Mod Test New SIs written and approved Run ne SIs 4-29-88 4-29-88 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 A. W."McCaleb, BFN P.
- McGraw, BFN S.
H. McRight, BFN J. A. Savage, BFN T. E. Scott, BFN R. L. Smith, BFN JAW:LSM Attachment cc (Attachment):
- RIMS, MR 4N'72A-(
This was prepared principally by P.
S. Kirby.
1 ~t
TO ROM Patrick P. Carier, Manager of Site Licensing, PAB C, Browns Ferry Nuclear Plant 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 accordance with Limiting Conditions of Operations 3.2.K 2 and 3.2 D.2.
Guy G. Campbell DCS:NMM:PSK:TRS Attachment cc (Attachment):
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
gL C
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)
'N p
,E
,I C
0
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.
i yV 4'4 r'<
L uid Process Radiation M'rs BFN Tech Spec Table 3.2.D requires Residual Heat Removal (RHR) service water 1
monitors (1-RM-90-133, 1-RM-90-134, 2-RM-90-133, 3-RM-90-133, and 3-RM-90-134) and raw cooling water monitor (2-RM-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-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 regardless of RCW flow rate.
DCN H4377 is complete except for paperwork closure and plant acceptance.
Compensatory sampling is being utilized to terify 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.
1 I' k~gg 0
', ~+q't
, 4 I
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
Q~
TVA 64 (OS 9 65) (OP.WP 5 85)
RQ 890714 96 Z I:iNITED STATES GOVERNilIEiNT Memorandum,
,TENNESSEE VALLEYAUTHORITY
~
~
TO:
Patrick P. Carier;, Manager of Site Licensing, PAB C, Browns Ferry Nuclear P ant 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.
DCS:NHM:PSK:TRS Attachment cc (Attachment):
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 uy G.
Campbell
'This was prepared principally by P.
S. Kirby.
Jbf. t, 'o) 015101/2
)
f But> L.S. Savin<<s BonrIs R('<~ularlv on tl(e Pavroll Savings Plan
TENNESSEE VALLEY AUTHORITY BRONNS FERRY NUCLEAR PLANT INOPERABLE RAOIOACTIVE EFFLUENT INSTRUMENTATION REPORT
I I I, I 'a
Ino erable Radioactive Effluent Instrumentation Re ort
~
~
~
~
~
~
~
~
~
~
~
This report is to comply with Radiological Effluent Technical Specifications (RETS) section 3.2.0.2 and 3.2.K.2 reporting requirements for instruments that are inoperable for more than 30 days.
The RETS became effective at BFN on 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
1 Stack effluent flow meter (0-FE-90-271)
Off Gas Post Treatment noble gas activity monitor Off Gas Post Treatment noble gas activity monitor (2-RM-90-265)
( 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.
015101/5
II' wQ r
ki)
I
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 was approved on September 29, 1986.
1-RH-90-133, 3-RM-90-133, and 3-RM-90-134 t
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 seismic concerns which are being resolved with Design Change Notice (DCN)
H3949 and 2-RH-90-133 was declared inoperable on April 4, 1989 because 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.
0151m/6
h
Stack Radioactive Effluent 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.
0151m/7
I 4>>
0 4P, "If
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.
0151m/8
'I-p
'%~i)
LICENSING SUBMITTAL CHECKLIST Submittal
Subject:
~P@
u ~~4
~ l lh
'0 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:
0100y/6
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 WP PP (c) WR/MR 8 (d)
CCTS iP issued status status status Other status notes:
- If not 100% complete indicate by 'R/C'hat action is restart complete.
0100y/7
0