ML20206C571
| ML20206C571 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/16/1998 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20206C549 | List: |
| References | |
| PROC-980416, NUDOCS 9905030076 | |
| Download: ML20206C571 (111) | |
Text
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l Offsite Dose Calculation Manual Revision 11 Peach Bottom Atomic Power Station Units 2 and 3 4'
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PECO Energy Company Docket Nos. 50-277 & 50-278 PORC Approval : .
444 Y 6 f[
PORC Chairman ' D'at e )
I PORC Meeting ~# : k[-C/ 2 G ! l Date L
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9905030076 990420 PDR ADOCK 05000277 R PDR <
Table of Contento
. 'I. ' Purpose ]
II. Instrument Setpoints III. Liquid Pathway Dose Calculations A. Liquid Radwaste Release Flow Rate Determination B. ODCMS 4.8.B.2.1 C. ODCMS 4.8.B.4.1
.IV. Gaseous Pathway Dose Calculations
-A. ODCMS 4.8.C.1.1 and 4.8.C.1.2 B. ODCMS 4.8.C.2.1 l C. ODCMS 4.8.C.3.1 ,
-D. ODCMS 4.8.C.5.1 l E. Technical Requirements Manual Test Requirement (TR) ]
3.5.3 F. ODCMS 4.8.C.7.1 and 4.8.C.7.2 l
) V. Nuclear Fuel Cycle Dose Assessment - 40 CFR 190 A. ODCMS 4.8.D.1.1 and 4.8.D.1.2 VI. Calendar Year Dose Calculations A. Unique Reporting Requirement ODCMS 3.10.3 VII. Radiological Environmental Monitoring Program A. ODCMS 4 . 8. E .1.1 and 4 . 8. E .1. 2 VIII. Bases e ;AppendixLA Radioactive Effluents Control-Program
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. l Page 3 of 46, Rev. 11 I. Purpose
"*g The purpose of the Offsite Dose Calculation Manual is to
' establish methodologies and procedures for calculating doses to individuals in areas at and beyond the SITE BOUNDARY due to radioactive effluents from Peach Bottom Atomic Power Station.
The results of these calculations are required to determine compliance with the requirements of Specification 5.5.4,
" Radioactive Effluent Controls Program" of Appendix A to Operating Licenses DPR-44 and DPR-56, " Technical Specifications for Peach Bottom Atomic Power Station Units No.
2 and 3". The Radioactive Effluents Control Program is located in Appendix A of this Offsite Dose Calculation Manual and contains offsite Dose Calculation Manual Specifications (ODCMS) and their associated Bases which implement the requirements of Technical Specification 5.5.4.
II. Setooint Determination for Licuid & Gaseous Monitors II.A Licuid Radwaste Activity Monitor Setooint Each tank of radioactive waste is sampled prior to release. A small liquid volume of this sample is analyzed for gross gamma activity in a NaI well counter. This NaI well counter activity is then converted to an equivalent liquid radwaste monitor reading.
1 CPS (R/W Monitor) = [ Net CPM /ml (well) x Eff W/RW) +
Background CPS Where:
CPS (R/W Monitor) = liquid radwaste gross activity monitor reading in CPS Net CPM /ml (well) = gross gamma activity for the radwaste sample tank [ determined by the well counter)
Eff W/RW = conversion factor between well counter and liquid radwaste gross activity monitor [ determined by calibrating both detectors with the same liquid radioactive source]
Background CPS = background reading of the liquid radwaste gross activity monitor in CPS Exceeding the expected response would indicate that an incorrect sample had been obtained for that release and the release is automatically stopped.
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Paga 4 of 46, Rev. 11 The alarm and trip pot setpoints for the liquid radwaste activity monitor are determined from a calibration curve for )
the alarm pot and trip pot. The alarm pot setting includes a
] factor of 1.25 to allow for analysis error, pot setting error, j
instrument error and calibration error. The trip pot setting includes a factor of 1.35 to allow for analysis error, pot setting error, instrument error and calibration error.
1 II.B Licuid Radwaste Release Flowrate Setooint Determination i
The trip pot setpoint for the liquid radwaste release flowrate i is determined by multiplying the liquid radwaste flowrate (from Section III.A) by 1.2 and using this value on the j appropriate calibration curve for the discharge flow meter to be used. The Peach Bottom radwaste system has two flow monitors - high flow (5 to 300 gpm) and low flow (0.8 to 15 l gpm). The factor of 1.2 allows for pot setting error and I instrument error. The flow rate determination includes a margin of assurance which includes consideration of this error '
such that the instantan6ous release limit of 10 CFR 20 is not exceeded.
II.C Setooint Determination for Caseous Radwaste l
The high and high-high alarm setpoints for the main stack l radiation monitor, Unit 2 roof vent radiation monitor and Unit l 3 roof vent radiation monitor are determined as follows:
) Hich Alarm - the high alarm setpoint is set at approximately 3 x the normal monitor reading.
Hich-Hich Alarm - the high-high alarm setpoint is set at a release rate from this vent of approximately 30% of the instantaneous release limit of 10 CFR 20 as specified in ODCMS 3.8.C.1.a for the most restrictive case (skin or total body) on an unidentified basis. To determine these setpoints, solve the gaseous effluent dose rate equations in section IV.A of the ODCM to determine what main stack release rate and roof vent release rate will produce a dose rate of 150 mrem /yr to the total body (30% of the limit of 500 mrem /yr) and a dose rate of 900 mrem /yr to the skin (30% of the limit of 3000 mrem /yr) from each release point. Using the smallest (most restrictive) release rate for each release point determine monitor response required to produce this release rate assuming a normal vent flow rate and pressure correction factor. Set the high-high alarm for approximately this monitor response.
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Page 5 of 46, Rev. 11 i
II.D. Setroint Determination for Gaseous Radwaste !
Flow Monitors
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The alarm setpoint for the main stack flow monitor is as follows:
Low Flow Alarm - 10,000 CFM. - 1his setting ensures that the main stack minimum dilution flow as specified in ODCMS 3.8.C.4.a is maintained.
The alarm setpoints for the roof vent flow monitors are as follows:
Low Flow Alarm -
1.5 x lo s cfm .
High Flow Alarm - 5.4 x 10 5 cfm i III. Licuid Pathway Dose Calculations III.A Licuid Radwaste Release Flow Rate Determination (
Peach Bottom Atomic Power Station Units 2 and 3 have one common discharge point for liquid releases. The following calculation assures that the radwaste release limits are met.
The flow rate of liquid radwaste released from the site to c
3 areas at and beyond the SITE BOUNDARY shall be such that the 1 concentration of radioactive material after dilution shall be limited to 10 times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases and 2E-4 pCi/ml total activity concentration for all noble gases as specified in ODCMS 3.8.B.1. Each tank of radioactive waste is sampled prior to release and is quantitatively analyzed for identifiable gamma emitters as specified in Table 4.8.B.1 of the ODCMS. From this gamma isotopic analysis the maximum permissible release flow rate is determined as follows:
Determine a Dilution Factor by:
Dilution Factor = )[pCi/ml i t 10x ECLi pCi / mli = the activity of each identified gamma emitter in pCi/ml ECLi = The effluent concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases or 9 2 x 10-4 Ci/ml for noble gases.
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i Page 6 of 46, Rev. 11 I l
! III.A (Cont'd) I l !
' "T Determine the Maximum Permissible Release Rate with this l
/ Dilution Factor bv:
A x 2.0 x 10 5 Release Rate (gpm) = .
B x C x Dilution Factor i A = The number of circulating water pumps running which will provide dilution 2.0 x 10 5 = the flow rate in gpm for each circulating water pump running B = margin of assurance which includes consideration of the maximum error in the activity setpoint, the maximum error in the flow setpoint, and possible loss of 5 out of the 6 possible circulating water pumps during a release. The value used for B is 10.0. ,
i 4
C = concentration gradient factor. The value used for C is 5.0 for discharge canal water levels l less than 104' and 3.0 for canal water levels greater than 104'.
I m ODCMS 4.8.B.2.1 l
~')III.B Dose contributions from liquid effluents released to areas at I
and beyond the SITE BOUNDARY shall be calculated using the equation below. This dose calculation uses those appropriate radionuclides listed in Table III.A.1. These radionuclides account for virtually 100 percent of the total body dose and organ dose from liquid effluents.
The dose for each age group and each organ should be calculated to determine the maximum total body dose and organ dose for each quarter and the year, as appropriate.
Cumulative dose files for quarterly and yearly doses should be maintained separately and the maximum total body and organ dose reported in each case. CM-1 NRC URI 88-33-01, T00353.
D, =
[i. Ag[t=1At, C 3 F, .
where:
D, = The cumulative dose commitment to the total body or any organ, t, from liquid effluents for the total time period At, , in mrem.
t=1
./
} At, = The length of the 4th time period over which C3 and F, are averaged for the liquid release, in hours.
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Pdge 7 of 46, Rev. 11 III.B (Cont'd)
Cy The average concentration of radionuclide, i, in
) =
undiluted liquid effluent during' time period At, from any liquid release, (determined by the effluent sampling analysis program, ODCMS Table 4.8.B.1), in pCi/ml.
A3 = The site related ingestion dose commitment factor to the total body or organ, T, for each radionuclide listed in Table III.A.1, in mrem-ml per hr-pci. See Site Specific Data.** {
J F, = The near field average dilution factor for Cy during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow through the l discharge pathway.
ODCMS 4.8.B.4.1 }
III.C Projected dose contributions from liquid effluents shall be calculated using the methodology described in section III.B.
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- See Note 1 in Bases l
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Page 8 of 46, Rev. 11 TABLE III.A.1
~N g LIQUID EFFLUENT INGESTION DOSE FACTORS
/ (DECAY CORRECTED)
A3 DOSE FACTOR (MREM-ML PER HR-pCi)
TOTAL BODY RADIO-NUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 r
NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 5.93E+04 6.49E+04 8.33E+04 MN-54 9.82E+02 1.00E+03 1.08E+03 FE-55 1.31E+02 1.40E+02 1.96E+02 FE 1.14E+03 1.17E+03 1.36E+03
.CO-58 2.59E+02 2.62E+02 3.17E+02 CO-60 7.40E+02 7.48E+02 9.07E+02 ZN-65 3.87E+04 3.95E+04 4.16E+04
. . , SR-89 8.83E+02 9.45E+02 1.48E+03 SR-90 1.88E+05 1.56E+05 1.72E+05 TE-129M 2.01E+03 2.17E+03 2.79E+03 TE-131M 4.57E+02 4.81E+02 5.74E+02 TE-132 1.40E+03 1.44E+03 1.65E+03 I-131 1.86E+02 1.79E+02 2.36E+02 I-133 1.97E+01 2.03E+01 3.20E+01 CS-134 6.74E+05 3.88E+05 1.49E+05 CS-136 9.79E+04 9.15E+04 7.30E+04 CS-137 3.98E+05 2.20E+05 8.49E+04 BA-140 3.66E+01 3.62E+01 7.42E+01 j i
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NOTE: The listed dose factors are for radionuclides that may be !
detected in liquid effluents and have significant dose 77N~ consequences. The factors are decayed for one day to account gj for the time between effluent release and ingestion of fish by j the maximum exposed individual.
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Page 9 of 46, Rev. 11 TABLE III.A.1
! LIQUID EFFLUENT INGESTION DOSE FACTORS LDECAY CORRECTED)
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A3 DOSE FACTOR LMREM-ML PER HR-pCi)
LIVER RADIO-NUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 9.55E+04 1.04E+05 1.01E+05 MN-54 5.15E+03 5.06E+03 4.03E+03 FE-55 5.62E+02 6.01E+02 6.33E+02 FE-59 2.96E+03 3.02E+03 2.73E+03 i
CO-58 1.16E+02 1.14E+02 1.04E+02 CO-60 3.35E+02 3.32E+02 3.07E+02 i
ZN-65 8.55E+04 8.46E+04 6.69E+04
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- SR-89 no data no data no data SR-90 no data no data no data TE-129M 4.74E+03 5.09E+03 5.02E+03 TE-131M 5.48E+02 5.77E+02 5.40E+02 TE-132 1.48E+03 1.53E+03 1.36E+03 I-131 3.25E+02 3.32E+02 4.16E+02 I-133 6.48E+01 6.66E+01 8.45E+01 CS-134 8.25E+05 8.36E+05 7.06E+05 CS-136 1.36E+05 1.36E+05 1.13E+05 CS-137 6.07E+05 6.32E+05 5.75E+05 BA-140 7.00E-01 6.90E-01 1.11E+00 NOTE: The listed dose factors are for radionuclides that may be l
detected in liquid effluents and have significant dose DT consequences. The factors are decayed for one day to account f) for the time between effluent release and ingestion of fish by the maximum exposed individual.
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l Paga 10 of 46, Rev. 11 TABLE III.A.1 i
j-LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
A3 DOSE FACTOR (MREM-ML PER HR-pCi)
BONE RADIO-NUCLIDE ADULT TEEN CHILD H-3 .no data r.o data no data
'NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 2.38E+05 2.58E+05 3.35E+05 MN-54 no data no data no data FE-55 8.12E+02 8.47E+02 1.19E+03 FE-59 1.26E+03 1.30E+03 1.68E+03 CO-58 no data no data no data CO-60 no data no data no data
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~3 SR-89 3.08E+04 3.30E+04 5.19E+04 SR-90 7.67E+05 6.31E+05 6.78E+05 1.27E+04 1.37E+04 1.80E+04 TE-129M TE-131M 1.'12E+03 1.21E+03 1.56E+03 2.29E+03 2.42E+03 3.07E+03 TE-132 2.28E+02 2.38E+02 4.13E+02 I-131 3.72E+01 3.92E+01 6.84E+01 I-133 3.47E+05 3.55E+05 4.30E+05 CS-134 3.45E+04 3.46E+04 4.10E+04 CS-136 4.44E+05 4.75E+05 6.01E+05 CS-137 5.57E+02 5.63E+02 1.27E+03 BA-140 l The listed dose factors are for radionuclides that may be l NOTE:
detected in liquid effluents and have significant dose J consequences. The factors are decayed for one day to account n j x';) for the time between effluent release and ingestion of fish by PJ the maximum exposed individual. ;
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1 Page 11 of 46, Rev. 11 TABLE III.A.1 l i
~h LIQUID EFFLUENT INGESTION DOSE FACTORS '
I (DECAY CORRECTED)
Ah DOSE FACTOR (MREM-ML PER HR-pCi)
KIDNEY RADIO-NUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 l l
NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 no data no data no data MN-54 1.53E+03 1.51E+03 1.13E+03 FE-55 no data no data no data FE-59 no data no data no data l CO-58 no data no data no data CO-60 no data no data no data ZN-65 5.72E+04 5.41E+04 4.22E+04
- SR-89 no data no data no data SR-90 no data no data no data TE-129M 5.31E+04 5.74E+04 5.29E+04 TE-131M 5.55E+03 6.01E+03 5.22E+03 TE-132 1.43E+04 1.47E+04 1.27E+04 I-131 5.57E+02 5.73E+02 6.82E+02 I-133 1.12E+02 1.16E+02 1.41E+02 CS-134 2.67E+05 2.66E+05 2.19E+05 CS-136 7.57E+04 7.42E+04 6.00E+04 CS-137 2.06E+05 2.15E+05 1.87E+05 BA-140 2.38E-01 2.34E-01 3.62E-01 l
l NOTE: The listed dose factors are for radionuclides that may be
! detected in liquid effluents and have significant dose consequences. The factors are decayed for one day to account
)E) for the time between effluent release and ingestion of fish by I the maximum exposed individual.
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l Pega 12 of 46, Rev. 11 TABLE III.A.1 l
'} LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
A3 DOSE FACTOR (MREM-ML PER HR- Ci)
GI-LLI ,
RADIO-NUCLIDE ADULT TEEN CHILD H-3 2.13E+00 1.53E+00 2.70E+00 NA-24 1.65E+02 1.70E+02 1.98E+02 P-32 1.73E+05 1.41E+05 5.98E+04 l
MN-54 1.58E+04 1.04E+04 3.38E+03 1
FE-55 3.22E+02 2.60E+02 1.17E+02 i
FE-59 9.90E+03 7.15E+03 2.84E+03 CO-58 2.35E+03 1.56E+03 6.04E+02 CO-60 6.30E+03 4.33E+03 1.70E+03 ZN-65 5.38E+04 3.58E+04 1.18E+04
- SR-89 4.94E+03 3.93E+03 2.01E+03 SR-90 2.22E+04 1.77E+04 9.13E+03 TE-129M 6.40E+04 5.15E+04 2.19E+04 TE-131M 5.44E+04 4.63E+04 2.19E+04 TE-132 7.02E+04 4.85E+04 1.37E+04 I-131 8.58E+01 6.57E+01 3.70E+01 I-133 5.82E+01 5.03E+01 3.40E+01 CS-134 1.44E+04 1.04E+04 3.80E+03 CS-136 1.55E+04 1.09E+04 3.96E+03 CS-137 1.18E+04 9.00E+03 3.60E+03 l BA-140 1.15E+03 8.69E+02 6.43E+02 l
NOTE: The listed dose factors are for radionuclides that may be detected in liquid -ffluents and have significant dose
- /,.T consequences. The tactors are decayed for one day to account tj for the time between effluent release and ingestion of fish by the maximum exposed individual.
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Paga 13 of 46, Rev. 11 IV. Easeous Pathway Dose Calculations i
! ~ ODCMS 4.8.C.1.1 and 4.8.C.1.2 IV.A.
The dose rate in areas at and beyond the SITE BOUNDARY due to radioactive materials released in gaseous effluents shall be determined by the expressions below:
! IV.A.1 Noble ~ Gases:
The dose rate from radioactive noble gas releases shall be determined by either of two methods. Method (a) , the Gross
' Release Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for total body dose (vent and stack releases) and skin Jose (vent releases) and Kr-87 for skin dose (stack releases). Method (b), the Isotopic Analysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.
- a. Gross Release Method D TB Ybs+E(X[O)y N b NV Ds =
Ls(%/Q)s+1.1BDs+ N Ly + 1.1M (x/Q)y Dv N
.c
.. where:
The location is the site boundary, 1097m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases.
D73 = total body dose rate, in mrem /yr.
Ds = skin dose rate, in mrem /yr.
V = 4.72 X 10-4 mrem /yr per pCi/sec; the constant for Kr-88 accounting for the gamma radiation from the elevated finite plume. This constant was developed using MARE program with plant specific inputs for PBAPS.
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Paga 14 of 46, Rev. 11 IV.A.1.a (Cont'd)
DN.s = The gross release rate of noble gases from the stack determined by gross activity stack monitors averaged over one hour, in pCi/sec.
K = 1.47 X 104 mrem /yr per pCi/m3 ; the total body dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-1).
(X/Q)y = 5.33 X 10-7 sec/m 3
- the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
Dnv = The gross release rate of noble gases in gaseous effluents from vent releases determined by gross activity vent monitors averaged over one hour, in Ci/sec.
Ly = 2.37 x 10 3mrem /yr per pCi/m 3; the skin dose factor due to beta emissions for Kr-88. (Reg.
Guide 1.109, Table B-1).
Ls = 9.73 X 103mrem /yr per pCi/m3; the skin dose factor due to beta emissions for Kr-87. (Reg.
I Guide 1.109, Table B-1).
(X/Q)s
= 9.97 X 10-8 sec/m 3 ; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
B = 1.74 X 10~4 mrad /yr per pCi/sec; the constant for Kr-87 accounting for the gamma radiation from the elevated finite plume. This l constant was developed using MARE program with plant specific inputs for PBAPS.
M = 1.52 X 104 mrad /yr per pCi/m3; the air dose factor due to gamma emissions for Kr-88.
(Reg. Guide 1.109, Table B-1).
1.1 = Unit conversion, converts air dose to skin dose, mrem / mrad.
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Paga 15 of 46, Rev. 11 i
l IV.A.1. b. Isotopic Analysis Method Drs = 1[ ViD3s + Ki (x/Q)y Div t . .
3 Ds =
1 - (Li(%/0)s + 1.1B i
] Dis i
+ (Li + llMy bv i
)(X/O where:
The location is the site boundary, 1097m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases.
D73 = total body dose rate, in mrem /yr. ;
i
= skin dose rate, in mrem /yr.
Ds
= The constant for each identified noble gas Vi radionuclide for the gamma radiation from the l elevated finite plume. The constants were j developed using the MARS program with plant specific inputs for PBAPS. Values are listed on Table IV.A.1, in mrem /yr per pCi/sec. l I
Ds = The release rate of noble gas radionuclide, i, 'in gaseous effluents from the stack determined by isotopic analysis averaged over one hour, in pCi/sec.
i Ki = The total body dose factor due to gamma emissions for each identified noble gas radionuclide. Values are listed 3 on Table IV.A.1, in mrem /yr per pCi/m .
(X/Q)y = 5.33 X 10-7 sec/m 3
- the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
Unr
= The release rate of noble gas radionuclide, i, in gaseous effluents from all vent
' releases determined by isotopic analysis averaged over one hour, in Ci/sec.
Li = The skin dose factor due to beta emissions for each identified noble gas radionuclide.
p Values are listed on Table IV.A.1, in mrem /yr b'.
per Ci/m3 .
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Page 16 of 46, Rev. 11 l
IV. A.1.b (Cont ' d) '
i
) (x/Q)s = 9.97 X 10-8 sec/m 3
- the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
Bi = The constant for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume.
The constants were developed using MARE program with plant specific inputs for PBAPS.
l Values are listed on Table IV.A.1, in mrad /yr per pCi/sec.
l l Mt = The air dose factor due to gamma emissions
! for each identified noble gas radionuclide. .
Values are listed on Table IV.A.1, in mrad /yr l per pCi/m 3. I l
L1 = Unit. conversion, coverts air dose to skin l
dose, mrem / mrad. l c'::'
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Page 18 of 46, Rev. 11 IV.A.2 Iodine-131, iodine-133, tritium and radioactive materials in l particulate form, other than noble cases, with half-lives
' creater than eicht davs:
The dose rate shall be determined for either of two critical organs and most restrictive age group. Child thyroid dose is limiting when iodine releases exceed 10 percent of the total release rates. The teenager lung dose is limiting when iodine is either not present or a small fraction of the total release.
When it is not clear which organ dose will be limiting, doses for both restrictive age group organs will be calculated and the limiting organ dose identified.
D=[P 1
i W3 33+ Wy ty+ WyQiy where:
The location is the site boundary, 1097m SSE from the vents.
l D = dose rate to the critical organ most l
restrictive age group, in mrem /yr.
P = The dose parameter for radionuclides cther than noble gases for the inhalation pathway.
,} The dose factors are based on the critical
- organ, and most restrictive age group. All l values are from Reg. Guide 1.109 (Tables E-5, j E-E and E-9). Values are listed on Table !
IV.A.2, in mrem /yr per pCi/m 3 W3 = 1.03 X 10-7 sec/m 3
- the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY from stack releases. (SSE boundary) i 1
g = The release rate of radionuclides; i, in l gaseous effluents from the stack determined l by the effluent sampling and analysis program (O DCMS Table 4.8.C.1) in pCi/sec.
Wy = 4.78 X 10~7 sec/m 3
- the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases. (SSE boundary) f t
i Page 19 of 46, Rev. 11 IV.A.2. (Cont'd) dy = The release rate of-radionuclide, i,in gaseous
! ,)
effluents from all vent releases, determined by i . the effluent sampling and analysis program i
- (O DCMS Table 4. 8.C.1) in pCi/sec.
gg = The release rate of radionuclide, i, in gaseous effluents from the auxiliary boiler stack releases, determined by the oil sampling and analysis program (ODCM Specification Table 4.8.C.1) in pCi/sec as calculated below:
C iy x 3785 x Z ,
! = T i
l where:
l l The location is the site boundary, 1097m SSE from the vents.
C,y = activity concentration measured in oil for nuclide, i, in Ci/ml.
3785 = milliliters per gallon.
)
l 2 = gallons of oil consumed.
T = number of seconds used for release Method (a) 60 second Method (b) number of seconds used to burn oil for release.
i l
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Page 20 of 46,,Rev. 11 l
TABLE IV.A.2 i
! Pi CONSTANTS FOR CRITICAL ORGAN FOR THE MOST RESTRICTIVE AGE GROUP (mrem /yr per pCi/m3)
Child Thyroid Teenager Lung Radionuclide Dose Factor Dose Factor l H-3 1.12 x 10 3 1.27 x 10 3 l Mn-54 0 1.98 x 10 6 l Cr-51 8.55 x 10 1 2.10 x 10 4 l Co-SB 0 1.34 x 10 6 l Co-60 0 8.72 x 10 6 l Zn-65 0 1.24 x 10 8
, Sr-89 0 2.42 x 10 6 l Sr-90 0 1.65 x 10 7 l I-131 1.62 x 10 7 0
~
l I-133 3.85 x 10 6 0 l I-135 7.92 x 10 5 0 l Cs-134 0 1.46 x 10 5 l Cs-137 0 1.21 x 10 5 l Ba-140 0 2.03 x 10 6 l Ce-141 0 6.14 x 10 5 l
lO l l
i
i Pugs 21 of 46, Rev. 11 I I
IV.B. ODCMS 4.8.C.2.1 l
~g The air dose in areas at and beyond the SITE BOUNDARY due to
/ noble gases released in gaseous effluents shall be determined by the expressions below.
The air dose shall be determined by either of two methods.
Method (a), the Gross Release Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for gamma radiation and Kr-87 for beta radiation. Method (b), the Isotopic Analysis Method, utilizes the results of noble gas l analyses required by ODCMS 4.8.C.1.1. )
l IV.B.1 for gamma radiation:
i Gross Release Method a.
Dy = 327 x 10-8 M(X/Q)y by + B hs j 1
where: l The location is the SITE BOUNDARY 1097m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.
-.i D, = gamma air dose, in mrad.
317 x 10'8 = years per second.
= 1.52 x 10 4 mrad /yr per pCi/m ; the air dose 3 l M
factor due to gamma emissions for Kr-88.
(Reg. Guide 1.109, Table B-1)
(x/Q)y = 5.33 x 10 ~# sec/m 3 ; the highest calculated annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
by = The gross release of noble gas radionuclides in gaseous effluents from all vents, determined by gross activity vent monitors, in Ci. Releases shall be cumulative over the calendar quarter or year as appropriate.
4 Pago 22 of 46, Rev. 11 IV.B.1. a (Cont'd)
B = 4.90 x 10-4 mrad / year per pCi/sec; the constant for Kr-88 accounting for the gamma
~} -
radiation from the elevated finite plume.
The constant was developed using the MARE program with plant specific inputs for PBAPS.
Os = The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitor in pCi.
Releases shall be cumulative over the calendar quarter or year as appropriate.
- b. Isotopic Analysis Method D, = 3.17 x 10-8 M i(x/Q)y hy+B i i bis where:
The location is the SITE BOUNDARY, 1097m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.
Dy = gamma air dose, in mrad.
327 x 10-8 = years per second.
~
Mi = The air dose factor due to gamma emissions l
for each identified noble gas radionuclide. l Values are listed on Table IV.A.1, in mrad /yr per Ci/m3 .
(x/Q)y = 5.33 x 10~7 sec/m 3
- the highest calculated l average relative concentration from vent releases for any area at or beyond the SITE ,
BOUNDARY. l On = The release of noble gas radionuclides, i, in j gaseous effluents from all vents as determined by isotopic analysis, in pCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
= The constant for each identified noble gas Bi radionuclide accounting for the gamma radiation for the elevated finite plume. The constants were developed using the MARE r"g program with plant specific inputs for PBAPS.
- j Values are listed on Table IV.A.1, in mrad /yr per pCi/sec.
l
r _
]
Page 23 of 46, Rev. 11 IV.B.1. b. (Cont'd)
, his = The release of noble gas radionuclides, i, in
} gaseous effluents from the stack determined by isotopic analysis, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
IV.B.2. for beta radiation:
- a. Gross Release Method D, = 3.17 x 10-8 N (x/Q)y hy + (x/Q)g h3 where:
1 The location is the SITE BOUNDARY 1097m SSE from the !
vents. This location results in the highest calculated gamma air dose from noble gas releases.
D, = beta air dose, in mrad.
3.17 x 10-8 = years per second.
N = 1.03 x 10 4 mrad /yr per pCi/m 3 ; the air dose factor due to beta emissions for Kr-87.
(Reg. Guide 1.109, Table B-1)
(x/Q)y = 5.33 x 10-7 sec/m 3
- the highest calculated annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
v = The gross release of noble gas radionuclides in gaseous effluents from all vents determined by gross activity vent monitors, in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
(x/Q)3 = 9.97 x 10-8 sec/m 3
- the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
Os = The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitors, in pCi.
"T, Releases shall be cumulative over the
]) calendar quarter or year, as appropriate.
r ,
Page 24 of 46, Rev. 11 IV.B.2. b. Isotopic Analysis Method ,
l D, = 3.17 x 10-8 [ Ni (x/Q)y Qiy+(x/Q)s 03
,)
1 317 x 10 years per second.
Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide.
Values are listed on Table IV.A.1, in mrad /yr per pCi/m 3.
(x/Q), = 5.33 x 10-7 sec/m3 ; the highest calculated annual average relative concentration from i vent releases for any area at or beyond the l SITE BOUNDARY.
Ou - The release of noble gas radionuclide, i, in gaseous effluents from all vents as determined by isotopic analysis, in pCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
(x/Q)s
= 9. 97 x 10-8 sec/m 3
- the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
}
Qsi
= The release of noble gas radionuclide, i, in gaseous effluents from the stack as i determined by isotopic analysis, in pCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
IV.C ODCMS 4.8.C.3.1 The dose to an individual from iodine-131, icdine-133, tritium and radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY.
The dose shall be determined for the limiting organ. Infant
-thyroid doses are dominating any time that either iodine-131 i
l release rates are more than two (2) percent of total release l rates or iodine-133 exceeds 25 percent of total release rates.
In these cases only iodine-131 and iodine-133 are potentially significant.
For cases where there is no detectable iodine releases, doses ng shall be-determined for infant bone and liver. Both bone and liver doses are calculated because the controlling dose is 1)'
. dependent upon the presence of strontium.
i l
F _
e Paga 25 of 46, Rev. 11 IV.C (Continucd)
When it is not clear whether thyroid, bone, or liver doses are
' controlling, all three shall be calculated and the limiting l dose identified. . -
D = 3.17x10-7F R i W3 h33+Wy hiy+ Wyhiy 1
where:
Location is the critical pathway dairy 1431m WSW from vents.
D = limiting dose to the critical infant organ, from the milk pathway, in mrem.
327 x 10-8 = years per second. )
F, = Fraction.that is elemental (0.5 for iodines l and 1.0 for all other elements).
l 8 = The dose factor for each identified radionuclide; i, in m 2 (mrem /yr) per pCi/sec l except tritium, which is in mrem /yr per Ci/m3 . The dose factors are for the critical individual organ for the most restrictive age )
group, infant. Values are listed in Table
"#}
-. IV.C.1. See Site Specific Data.**
R', = 8.78 x 10-10 meters-2; (D/Q) for the food pathway for stack releases except tritium3 which uses a ( y /Q) of 8.78 x 10-8 sec/m .
Q, = The release of radionuclide, i, in gaseous effluents from the stack determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1), in pCi. Releases shall be cumulative over the calendar quarter or year, as appropriate.
Wy = 1.58 x 10-8 meters-2; (D/Q) for the food pathway for vent releases except , tritium3 which uses a ( y /Q) of 1.58 x 10- sec/m .
@y = The release of radionuclide, i, in gaseous effluents from the vents determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in pCi. Release shall be cumulative over the calendar quarter or year,
?}::
' ~
as appropriate.
- o See Note 2 and 3 in Bases l
l n :
~
. I Pega 26 of 46, Rev. 11 ]
IV.C (Continued)
~
,,4 g,y = The release of radionuclide, i, in gaseous effluents from the auxiliary boiler stack l
~
releases, determined by the oil sampling and analysis program ('ODCMS Table 4.8.C.1) in I pCi. Release shall be cumulative over the ;
calendar quarter or year, as appropriate. l l
l t #-
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l Paga 27 of 46, Rev. 11 TABLE IV.C.1 Ri CONSTANTS INGESTION PATHWAY 2
(mrem /yr) per pCi/sec) *
] (m RADIONUCLIDE Infant Liver Infant Thyroid Infant Bone H-3 -1.30 x 10 3 1.30 x 10 3 0 Cr-51 0 3.35 X 10 4 0 Mn-54 1.93 x 10 7 0 0 ,
Co-58 9.57 x 10 8 0 0 7
Co-60 4.69 X 10 'O O Zn-65 9.22 x 10 8 0 2.69 x 10 8 Sr-89 0 0 4.58 x 10 8 Sr-90 0 0 6.55 x 10 10 I-131 9.37'x los 3.08 x 10 11 7.95 x 10 8 I-133 1.56 x 10 7
2.84 x 10 8 1.07 x 10 7 Cs-134 3.54 x 10 10 0 1.90 x 10 10 Cs-137 3.24 x 10 10 0 2.77 x 10 10 Ba-140 7.09 x 10 4 0 7.09 x 10 7 Ce-141 - 8.69 x 10 3 0 1.42 x 10 4
- Tritium Ri values in units of mrem /yr per pCi/m 3
I Page 28 of 46, Rev. 11 IV.D ODCMS 4.8.C.5J l The projected doses from releases of gaseous effluents to l
~% areas at and beyond the SITE BOUNDARY shall be calculated in )'
! accordance with the following sections of this manual:
- a. gamma air dose - IV.B.1
- b. beta air dose - IV.B.2
- c. organ dose - IV.C The projected dose calculation shall be based on expected release from plant operation. The normal release pathways 1 result in the maximum releases from the plant. Any l alternative release pathways result in lower releases and, '
therefore, lower doses. l IV.E Technical Recuirements Manual Test Recuirement (TFO 3.5.3 i
IV.E.1 The recombiner hydrogen analyzers currently used at Peach Bottom are Whittaker Electrochemical type. (Analyzers 4083A and 4083B on Unit 2. Analyzers 5083A and 5083B on Unit 3.)
IV.E.2 The calibration gas for the Whittaker Analyzers is 2%
Hydrogen, Balance Air.
IV.F ODCMS 4.8.C.7.1 and 4.8.C.7.2
) IV.F.1 The dose rate in areas at and beyond the SITE BOUNDARY due to
'" radioactive materials released in gaseous effluents from the incineration of waste oil from the auxiliary boilers shall be l calculated by the equation in IV.A.2.
The dose rate from radioactive particulate release shall be determined by either of two methods. Method (a) , total instantaneous release assumes that the total activity contained in the waste oil is released in the first minute of incineration. Method (b) uses the activity release over the entire time of incineration.
For normal operations, it is assumed that Method (a) will be used, since the total activity from the waste oil is expected to contribute an insignificant dose compared to the annual limits. However, in the event that the activity is significantly higher than administrative or regulatory limits, then Method (b) would be used because it is more accurate in calculating the dose rate.
Since the auxiliary boiler stacks are at approximately the same height as the reactor vents and discharge from the auxiliary boilers will also be heated, the use of the reactor vent D/Q value for the calculations is considered conservative.
)_.
I' -
! Page 29 of 46, Rev. 11 l
l IV.F.2 The dose to an individual from radioactive materials in
! particulate form and radionuclides other than noble gases with
,} half-lives greater than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY from the incineration of contaminated waste oil from the auxiliary l
boiler stacks shall be calculated by the equation in IV.C.
V.A. ODCMS 4.8.D.1.1 and 4.8.D.1.2 If the doses as calculated by the equations in this manual do not exceed the limits given in ODCMS 3.8.3.2, 3.8.C.2, or 3.8.C.3 by more than two times, the conditions of ODCMS 3.8.D.1 have been met.
If the doses as calculated by the equations in this manual exceed the limits given in ODCMS 3.8.B.2, 3.8.C.2, or 3.8.C.3 by more than two times, the maximum dose or dose commitment to a real individual shall be determined utilizing the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977. Any deviations from the methodology provided in Regulatory Guide 1.109 shall be documented in the Special Report to be prepared in accordance with ODCMS 3.8.D.1.
The cumulative dose contribution from direct radiation from
- ) the two reactors at the site and from radwaste storage shall
_J be determined by the following methods:
Cumulative dose contribution from direct radiation -
Total dose at the site of interest (as evaluated by TLD measurement) -
Mean of background dose (as evaluated by TLD's at background sites) -
Effluent contribution to dose (as evaluated by ODCMS 4.8.D.1.1).
This evaluation is in accordance with ANSI /ANS 6.6.1-1979 Section 7. The error using this method is estimated to be approximately 8*<.
I l
f Page 30 of 46, Rev. 11 l VI.A. Uniaue Reportina Recuirement ODCMS 3.10.3. Dose Calculations f, for the Radiation Dose Assessment Report
! The assessment of radiation doses for the radiation dose l assessment report shall be performed utilizing the methodology l provided in Regulatory Guide 1.109, " Calculation of Annual Doses To Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977. Any deviations from the methodology provided in Regulatory Guide 1.109 shall be documented in the radiation dose assessment report.
The meteorological conditions concurrent with the time of release of radioactive materials (as determined by sampling frequency of measurement) or approximate methods shall be used as input to the dose model.
The Radiation Dose Assessment Report shall be submitted within 120 days after January 1 of each year in order to allow time for the calculation of radiation doses following publication of radioactive releases in the Radioactive Effluent Release Report. There is a very short turnaround time between the determination of all radioactive releases and publication of the Radioactive Effluent Release Report. This would not allow time for calculation of radiation doses in time for publication in the same report.
VII.A ODCMS 4.8.E.1.1 and 4.8.E.1.2 The radiological environment monitoring samples shall be collected pursuant to Table VII.A.1 from the locations shown l on Figures VII.A.1, VII.A.2, and VII.A.3, and shall be l analyzed pursuant to the requirements of Table VII.A.1.
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l Page 41 of 46, Rev. 11 VIII. Bases Site Specific Data NOTE 1 l Liquid dose factors, A ,, i for section III.B were developed using the following site specific data. The liquid pathways involved i are drinking water and fish.
l A,, = (U,lD, + U, x BE)k ox DR xRC 1
l U'. = liters per year; maximum age group usage of drinking water (Reg. Guide 1.109, Table E-5)
D. = 5.4; average annual dilution at Conowingo intake U, = kg per year; maximum age group usage of fish (Reg. Guide 1.109, Table E-5)
RF = bioaccumulation factor for nuclide, i, in freshwater fish. Reg. Guide 1.109, Table A-1, 3 except P-32 which uses a value of 3.0 x 10
~ pCi/kg per pCi/ liter.
3 1.14 x 10 5 = (106 pCi/pCi x 10 ml/1 )/ 8760
~
ko =
hr/yr) units conversion factor.
DE = dose conversion factor for nuclide, i, for the age group in total body or organ, as applicable. Reg. Guide 1.109, Table E-11, except P-32 bone which uses a value as indicated below.
3.0 x 10-5 mrem /pCi RC = 1.16; reconcentration from PBAPS discharge back through PBAPS intake.
The data for Dw and RC were derived from data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos. 50-277 and 50-278) Radioactive Effluent Dose Assessment, Enclosure A, September 30, 1976. All other data except P-32 BF and DF were used as given in Reg.
Guide 1.109, Revision 1, October 1977. The P-32 BF and j DF were used in accordance with information supplied in f
Branagan, E.F., Nichols, C.R., and Willis, C.A., "The Importance of P-32 in Nuclear Reactor Liquid Effluents",
NRC, 6/82. The teen and child dose factors were derived
( . }:.
- by the ratio of the adult bone dose factors in Reg. Guide 1.109 and Branagan, et al.
F _ l Page 42 of 46, Rev. 11 VIII. (Cont'd)
NOTE 2 To develop constant R for section IV.C, the following site specific data were used:
~f,f, (1-f,f,)e"4'*
l g(DlQ)=K'Q ,.(U,,) F,,(r)(DFL,)
y + y
~,
e J
where:
K' = 108 pCi/ Ci; unit conversion factor Gy = 50 kg/ day; cow's consumption rate U,, = 330 1/yr; yearly milk consumption by an infant A, = radioactive decay constant for nuclide of interest, sec ~1 (e.g. 9.97 x 10~7 sec ~1 for I-131)
L A, = 5.73 x 10~7 sec ~1; decay constant for removal of activity in leaf and plant surfaces u.n F. = stable element transfer coefficient for nuclide i
'"J of interest, day / liter (e.g. 6.0 x 10~3 day / liter for I-131) r = fraction of deposited nuclide retained in cow's feed grass, 1.0 for radiciodine; 0.2 for particulates D)95, = ingestion dose factor in infant for nuclide of I interest, mrem /pCi (e .g. 1. 3 9 x 10-2 mrem /pCi !
for I-131) f, = 0.6; the fraction of the year the cow is on 1
. pasture (average of all farms) f, = 0.487; the fraction of cow feed that is pasture grass while the cow is on pasture (average of all farms)
Y, = 0.7 kg/m2 ; the agricultural productivity of pasture feed grass Y, = 2.0 kg/m2 ; the agricultural productivity of
' ,, )
9 stored feed I
l>
\
Page 43 of 46, Rev. 11 VIII. (Cont'd)
I f
= 1.73 x 10 5 sec (2 days); the transport time
) from pasture, to cow, to milk, to receptor t
a
= 7.78 x 10 6 sec (90 days); the transport time from pasture, to harvest, to COW, to milk, to receptor NOTE 3 To develop constant R for tritium for section IV.C, the following site specific data were used:
1 i
The concentration of tritium in milk is based on the airborne concentration rather than the deposition. The following additional constants and formula are used:
Rj_3(y/Q)=K'K' "F,, Q, U,,(DFL,) 0.75(03 / H) where:
AI' = 10 3 gm/kg; a constant of unit conversion
'~) H = 14.61 gm/m 3
- absolute humidity of the atmosphere 0.75 = the fraction of total feed that is water 05 = the ratio of the specific activity of the feed 4 grass water to the atmospheric water {
The pathway is the grass-cow-milk ingestion pathway.
These data were derived from data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos.
50-277 and 50-278) Radioactive Effluent Dose Assessment, Enclosure A, September 30, 1976. All other data were used as given in Reg. Guide 1.109, Revision 1, October 1977.
ODCMS 4.8.B.2.1, Licuid Pathway Dose Calculations The equations for calculating the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the methodology provided in l
Regulatory Guide 1.109, " Calculation of Annual Doses to l Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, ex Appendix I", Revision 1, October 1977 and NUREG-0133
" Preparation of Radiological Effluent Technical l
"J L
Specifications for Nuclear Power Plants", October 1978.
Pago 44 of 46, Rev. 11 ODCMS 4.8.C 1.1 and 4.8.C.1.2 l Dose Rate Noble Gases l The equations for calculating the dose rate due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133 " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",
August 1978, and the atmospheric dispersion model presented in Information Recuested in Enclosure 2 to letter from Georce Lear to E. G. Bauer dated February 17, ,
1221, September 30, 1976. The specified equations 1 l provide for determining the dose rates in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.
l The dose rate due to noble gas release as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method.
Assuming the release rates given in Radioactive Effluent Dose Assessment, September 30, 1976, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 6.0 times and 5.7 times,
,) respectively, the values calculated by the Isotopic Analysis Method.
Dose Rate I-131. I-133, Tritium and Radioactive Material in Particulate Form.
The model Technical Specification LCO of NUREG-0133 for all radionuclides and radioactive materials in particulate form and radionuclides other than noble gases requires that the instantaneous dose rate be less than the equivalent of 1500 mrem per year.
The release data from 1994 to 1996 were evaluated and the i critical organs were determined to be the child thyroid j or teenager lung. The child thyroid dose rate is ;
limiting when iodine releases exceed 10 percent of the j total release rates. The teenager lung dose rate is limiting when iodine is either not present or a small .
fraction of the total release. i l
Because of good fuel performance the amount of I-131 l released has decreased. The thyroid may not be the {
critical organ. When it is not clear which organ dose is l limiting, doses for the child thyroid and teenage lung )
are calculated. )
1
Page 45 of 46, Rev. 11 {
QDCMS 4. 8. C . 2.1 l Dose Noble Gases The equations for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents were dev31oped from the methodology provided in )
Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Release: of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, f Appendix I", Revision 1, October 1977, NUREG-0133 l
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", August 1978, and the atmospheric dispersion model presented in ;
Information Recuested in Enclosure 2 to letter from Georce Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. The specified equations provide for determining the air doses in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.
The dose due to noble gas releases as calculated by the Gross Release Method is much more conservative than the ;
dose calculated by the Isotcpic Analysis Method. !
Assuming the releases rates given in Radioactive Effluent Dose Assessment, September 30, 1976, the values calculated by the Gross Release Method for total body dose rate and skin dose rate are 4.3 times and 7.2 times, j respectively, the values calculated by the Isotopic I m
.) Analysis Method.
ODCMS 4.8.C.3.1 Dose. Iodine-131. Iodine-133. Tritium, and Radioactive Material in Particulate Form The equation for calculating the doses due to the actual release of radiciodines, radioactive material in particulate form, and radionuclides Other than noble gases with half-lives greater than 8 days were developed using the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releaces of Reactor Effluents for the Purpose of Evaluating Compliance wi.th 10 CFR Part 50, Appendix I", Revision 1, l
October 1977, NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978, and the atmospheric dispersion model presented in Information Reauested in Enclosure 2 to Letter from Georce Lear to E. G. Bauer dated February
- 17. 1976, September 30, 1976. These equations provide for determing the actual doses based upon the historical average atmospheric conditions.
FT - 1 Paga 46 of 46, Rev. 11 VIII. (Cont'd)
! Compliance with the 10 CFR 50 limits for radiciodines, i T radioactive materials in particulate form and u _/ radionuclides other than noble gases with half lives
! greater than eight days is to be determined by i calculating the infant thyroid, infant liver and infant
, bone dose. These organs were determined to be the l critical organs based on the release data from 1994 to 1996.
l l Because of a decrease in the amount of I-131 released, l the thyroid may not be the critical organ. The isotopic l analysis method is used to calculate dose to the infant
- thyroid, infant liver and infant bone.
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4 APPENDIX A ,
RADIOACTIVE EFFLUENTS CONTROLS PROGRAM i
CONTAINING OFFSITE DOSE CALCULATION MANUAL
- ,,} SPECIFICATIONS (ODCMS) AND BASES 1-l 1 FOR PEACH BOTTOM ATOMIC POWER STATION f
l UNITS 2 AND 3 REVISION 11 f.
g.
r: .
RADIOACTIVE EFFLUENTS CONTROLS PROGRAM i
TABLE OF CONTENTS m.,
l 3.8.A Definitions.......................................ODCM 3.8.A-1 3.8.B Liquid Radwaste Effluents .........................ODCM 3.8.B-1 1 3.8.C Gaseous Effluents.................................ODCM 3.8.C-1 l
3.8.D 40 CFR 190........................................ODCM 3.8.D-1 3.8.E Radiological Environmental Monitoring .............ODCM 3.8.E-1 3.9 Major Changes to Radioactive Waste Treatment Systems ...........................................ODCM 3.9-1 3.10 Reporting Requirements............................ODCM 3.10-1
1 i
l I
1 i
l l.
l 4
ve PBAPS Units 2 and 3 ODill 3. 8 Revision 11 I
F _
Dsfinitions 3.8.A I
ODCMS 3.8.A Definitions
) !
j ------------------------------NOTE------------------------------------
l The defined terms of this section appear in capitalized type and are l cpplicable throughout these Offsite Dose Calculation Manual Specifications and Bases.
l l Term Definition ,
1 FUNCTIONAL TESTS A FUNCTIONAL TEST is the manual operation or initiatien of a system, subsystem, or L
l component to verify that it functions within l
design tolerances (e.g. , the manual start of a
! core spray pump to verify that it runs and
! that it pumps the required volume of water) .
1 l GASEOUS RADWASTE Any system designed and installed to reduce TREATMENT SYSTEM radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or
(
t holdup for the purpose of reducing the total radioactivity prior to release to the l
l environment.
l l
g INSTRUMENT CALIBRATION An INSTRUMENT CALIBRATION means the adjustment of an instrument signal output so that it
~J corresponds, within acceptable range, and accuracy, to a known value(s) of the parameter which the instrument monitors. The known
! value of the parameter shall be injected into the instrument as close to the primary sensor as practicable.
INSTRUMENT CHECK An INSTRUMENT CHECK is a qualitative determination of acceptable OPERABILITY by observation of instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
INSTRUMENT FUNCTIONAL An INSTRUMENT FUNCTIONAL TEST means the TEST injecti'a of a simulated signal into the instrucc.it as close to the primary sensor as practicable to verify the proper instrument response, alarm and/or initiating action.
(continued) j
\
PBAPS Units 2 and 3 ODCM 3. 8. A-1 Revision 11 e i i
i
I .
Definitions 3.8.A ODCMS 3.G.A Definitions (continued) t MEMBERS OF THE PUBLIC MEMBERS OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE Contains the current methodology and CALCULATION MANUAL parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and describes the radiological environmental monitoring program.
OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s) and all necessary attendant instrumentation, controls, normal and
-.. emergency electrical power, cooling and seal water, lubrication, and other auxiliary
-") equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function (s) are also capable of performing their related ,
support function (s) . {
PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to '
maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
SITE BOUNDARY That line beyond which the land is not owned, leased, or otherwise controlled by licensee as defined in Figure 3.8.A.1.
l SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
PBAPS Units 2 and 3 ODCM 3.8.A-2 Revision 11
f .
Dafinitionc 3.8.A
\ --
l
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/ ', EL 7es- 5 -
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+':/~ h ' '
AUXIUARY BotLERS EL. 300 ft.
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STRUCTURE t .
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l Figure 3.8.A.1 SITE BOUNDARY (including gaseous and liquid effluent release points) l PBAPS Units 2.and 3 ODCM 3.8.A-3 Revision 11
E _
Liquid Radwaste Effluents
! 3.8.B.1 l
! 3.8.B Liquid Radwaste Effluents i-ODCMS 3.8.B.1 The concentration of radioactive material released to areas at or beyond the SITE BOUNDARY shall be limited l to: )
- a. 10 times the concentration specified in 10 CFR 20 )
Appendix B, Table 2, Column 2 for radionuclides '
other than noble gases; and
- b. 2 X 10d pCi/ml total activity concentration for i all dissolved or entrained noble gases.
l l
APPLICABILITY: At all times.
COhcENSATORY MEASURES ;
1 I
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME j
s A. Concentration of A.1 Decrease the release Immediately radioactive material rate of radioactive
'}
s.c released to areas at materials to restore or beyond the SITE concentration to BOUNDARY exceeding within limits.
limits.
QB A.2 Increase the dilution Immediately j flow rate to restore concentration within limits.
DE A.3 Decrease the release Immediately rate of radioactive materials and increase the dilution flow rate to restore concentration within limits.
PBAPS Units 2 and 3 ODCM 3. 8.B-1 Revisior.11
r _
Liquid Radwasta Effluents 3.8.B.1 l
ODCMS REQUIREMENTS
) FREQUENCY J . ODCMS REQUIREMENT
-ODCMS 4.8.B.1.1 Take a sample of each batch of Prior to each liquid effluent and analyze for the release concentration of each significant Base the release
- gamma energy peak.
l rate on the circulating water flow rate at the time of discharge.
ODCMS 4.8.B.1.2 Record radioactive concentrations During each and volume before dilution of each l
release batch of liquid effluent released, l
the average dilution flow, and length of time over which each discharge occurred. These facility records shall be maintained.
l l
ODCMS 4.8.B.1.3 Perform radioactive liquid waste In accordance
- sampling and activity analysis. with Table 4.8.B.1 l
l l
l l
WS l'
PBAPS Units 2 and 3 ODCM 3.8.B-2 Revision 11
I l
l Liquid Radwaste Effluents
! 3.8.B.1 l Table 4.8.B.1 (Page 1 of 2)
Radioactive Liquid Waste Sampling and Analysis
')
SAMPLE TYPE SAMPLE SAMPLE ANALYSIS SAMPLE LOWER FREQUENCY LIMIT OF l DETECTION (LLD)
(a) , (d) , (e)
Waste Tank to Each batch Quantitative 5 X 10-7pCi/ml be released (b) Analysis of l Identifiable Gamma ;
Emitters ,
I-131 1 X 10-6pCi/ml !
Proportional 31 days (c) Fe-55 1 X 10-6 Ci/ml Composite of Batches Tritium 1 X 10-5 Ci/ml Gross Alpha 1 X 10-7pCi/ml Proportional 31 days (c) Sr-89 5 X 10-8pCi/ml Composite of Batches Sr-90 5 X 10'8pCi/ml One Batch 31 days Dissolved noble 1 X 10~8pCi/ml gases (a) The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. The values for the lower limit of detection are based on a 95% confidence level.
(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated and thoroughly mixed to assure representative sampling.
(c) A composite sample is one in which the quantity of the sample is
- proportional to the quantity of liquid waste discharged and in f
which the method of sampling results in a sample representative l
of the liquids released.
PBAPS Units 2 and 3 ODCM .3.8.B-3 Revision 11 1
Liquid Radwaste Effluents 3.8.B.1
~
Table 4.8.B.1 (Page 2 of 2)
Radioactive Liquid Waste Sampling and Analysis (d) The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level. When unusual circumstances result in sample detectable limits higher than required, the reasons shall be documented in l the Radioactive Effluent Release Report. The values listed are believed to be attainable.
(e) Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations. Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides.
9 PBAPS Units 2 and 3 ODCM 3.8.B-4 Revision 11
\
E
]
Liquid'Kadwaste Effluents 3.8.B.2 3.8.B . Liquid Radwaste Effluents ,
ODCMS 3.8.B.2- The dose or dose commitment to a MEMBER OF THE PUBLIC i from radioactive material in liquid effluent releases' from the two reactors at the site to the areas at or beyond the SITE BOUNDARY shall be limited to:
- a. s 3.0 mrem to the total body and 5 10.0 mrem to any organ during any calendar quarter; and
- b. 5 6.0 mrem to the total body and s 20.0 mrem to any organ during any calendar year.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated dose A.1 Submit a Special 31 days
'7) from the release Report to the NRC
,_1 of radioactive that identifies materials in causes for exceeding.
liquid effluents limits, actions taken exceeds required to reduce releases of limits. radioactive materials in'11guid effluents, corrective actions' ;
taken to assure subsequent releases are within limits, results of :
radiological analyses of the drinking water source, and the i radiological impact ;
on the potentially affected drinking water supplies with regard so 40 CFR 141,
~
Safe Drinking Water Act.
r PBAPS Units 2 and 3 CDCM 3.8.B-5 Revision 11
r ..
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Liquid Radwaste Effluents
- 3.8.B.2
.. ODCMS REQUIREMENTS y !
, ODCMS REQt.TIREMENT FREQUENCY i
ODCMS ' 4.8.B.2.1 Determine ' cumulative dose contributions 31 days i
in accordance with the methodology and' I- parameters in the ODCM.
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PBAPS Units 2 and 3 ODCM 3.8.B-6 Revision 11 i
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- V Liquid Radwaste Effluents l 3.8.B.3 3.8.B Liquid Radwaste Effluents o ODCMS 3.8.B.3 The following conditions shall be met:
I \
l a. Dilution water flow rates necessary to satisfy l l
requirements of ODCMS 3.8.B.1 shall be maintained; 1
e l b. The gross activity monitor and the flow monitor on l I
l the waste effluent line shall be OPERABLE; and l c. The liquid effluent control monitor shall be set in ;
l accordance with methodology and parameters in the ODCM to alarm and automatically close the waste discharge valve prior to exceeding limits in ODCMS 3.8.B.1.
l APPLICABILITY: During release of radioactive wastes.
1 COMPENSATORY MEASURES l CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME lr l l
l j
A. Gross activity A.1 Initiate action to Immediately I l monitor on the restore monitor to !
waste activity OPERABLE status. !
l line inoperable. H l M A.2 Analyze two Prior to independent samples- relecce of tank's contents.
M i
A.3 Perform independent Prior to verification of the release release rate calculations and discharge line valve line-up using at least two technically qualified members of the facility staff.
(continued)
PBAPS Unit: 2 and 3 ODCM 3.8.B-7 Revision 11
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Liquid Radwaste Efflusnts 3.8.B.3 COMPENSATORY MEASURES (Continued) i
. CONDITION REQUIRED COMPENSATORY COMPLETION 1
') MEASURE TIME B. Flow monitor on B.1 Initiate action to Immediately the waste effluent restore monitor to line inoperable. OPERABLE status.
1 AND B . 2 - - - - - - - - NOTE - - - - - - -
Pump performance curves l may be used to estimate I flow.
Estimate waste effluent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> line flow rate.
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Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter C. Required C.1 Suspend release of Immediately
"') Compensatory radioactive effluents j Measures and via this pathway.
associated Completion Time of Condition A or B not met. {
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DE l Dilution water l flow rates not :
satisfying <
requirements of ODCMS 3.8.B.1. (
- . . . . . _ . . _ _ . . . - . . . . . . . - . . . AL l D. Liquid radwaste D.1 Explain the reason the Prior to effluents inoperability was not submittal of l corrected in a timely the next radiation monitors inoperable for > manner in the Radioactive 30 days. Radioactive Effluent Effluent Release Report. Release Report PBAPS Units 2 and 3 ODCM 3.8.B-8 Revision 11 a
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Liquid Radwaste Effluents 3.8.B.3
. ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.1 Perform INSTRUMENT CHECK of liquid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radwaste effluents radiation monitor. during release ;
i ODCMS 4.8.B.3.2 Perform INSTRUMENT CHECK of liquid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> effluent flow monitor, during release ,
I ODCMS 4.8.B.3.3 Perform INSTRUMENT FUNCTIONAL TEST of 31 days liquid radwaste effluents radiation monitor, including OPERABILITY l {
- demonstration of the radwaste !
discharge automatic isolation valve and control room annunciation in response to alarm / trip setpoint being exceeded and an instrument INOP l
failure.
ODCMS 4.8.B.3.4 Perform SOURCE CHECK of liquid 92 days l '~
! radwaste effluents radiation monitor.
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.ODCMS 4. 8.B.3.5 Perform INSTRUMENT CALIBRATION .of the 12 months liquid radwaste effluents radiation monitor with a known radiation source positioned in'a reproducible geometry with respect to the sensor.
l ODCMS 4.8.B.3.6 Perform INSTRUMENT CALIBRATION of the 12 months liquid effluents flow monitor.
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-PBAPS Units 2 and 3' ODCM 3.8.B-9 Revision 11
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Liquid Radwaste Effluents 3.8.B.4 3.8.B Liquid Radwaste Effluents I
l ODCMS 3.8.B.4 Liquid effluent releases shall be processed through one of the radwaste subsystems or combination of subsystems listed below:
- a. waste collector filter and demineralizer;
- b. floor drain filter; l c. fuel pool filter demineralizer;
- d. chemical / oily waste cleanup subsystem; l e. laundry drain filter i APPLICABILITY: Prior to all liquid effluent release (s) whenever the l release (s) would cause the projected dose, when it is averaged over 31 days to exceed 0.12 mrem to the j total body or 0.4 mrem to any organ (combined total l from the two reactors at the site).
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME l -)
4 l A. Liquid waste A.1 Submit a Special Report 31 days discharged without to the NRC that includes, required an explanation of why processing. liquid radwaste was discharged without required processing, identification of any j inoperable equipment or subsys*. ems and the reason for the inoperability, the action taken to restore the inoperable equipment to OPERABLE ,
I status, and the action taken to prevent recurrence.
PBAPS Units 2 and 3 ODCM 3.8.B-10 Revision 11 2
Liquid Radwaste Efflu@nts 3.8.B.4 1
- ODCMS REQUIREMENT FREQUENCY
')
ODCMS 4.8.B.4.1 Project doses due to liquid 31 days i effluent releases to areas at I and beyond the SITE BOUNDARY in accordance with the methodology j and parameters in the ODCM. (
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ODCMS 4.8.B.4.2 Demonstrate OPERABILITY of the 9? days waste collector filter and demineralizer and the floor drain filter by analyzing the liquid processed through the subsystem and determining it meets the requirements of ODCMS 3.8.B.1.
l ODCMS 4.8.B.4.3 Demonstrate OPERABILITY of the Prior to release i fuel pool filter demineralizer of liquid by analyzing the liquid effluents
? "-) processed through the subsystem processed by this
.) and determining it meets the requirements of ODCMS 3.8.B.1.
subsystem ODCMS 4.8.B.4.4 Demonstrate OPERABILITY of the Prior to release chemical / oily waste cleanup of liquid subsystem by analyzing the effluents liquid processed through the processed by this subsystem and determining it subsystem meets the requirements of l ODCMS 3.8.B.1.
ODCMS 4.8.B.4.5 Demonstrate OPERABILITY of the Prior to release laundry drain filter by of liquid analyzing the liquid processed effluents through the subsystem and processed by this determining it meets the subsystem requirements of ODCMS 3.8.B.1.
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PBAPS Units 2 and 3 ODCM 3.8.B-11 Revision 11
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. 1 Gastous Effluents l 3.8.C.1 i 3.8.C Gaseous Effluents ODCMS 3.8.C.1 The dose rate at or beyond the SITE BOUNDARY due to radioactive materials in gaseous effluents released from the two reactors at the site shall be limited to the following: l
- a. For noble gases, 5 500 mrem per year to the total body and s 3000 mrem per year to the skin; and
- b. For iodine-131, iodine-133, tritium, and all i l
radionuclides in particulate form with half lives > 8 days, s 1500 mrem per year to any 1 organ. l l
APPLICABILITY: At all times.
COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION
' MEASURE TIME l l
w A. Dose rates at or beyond A.1 Decrease release Immediately l the SITE BOUNDARY exceed rates to comply l 1
.J limits due to with limits. l i
radioactive material in gaseous effluents.
ODCMS REQUIREMENTS FREQUENCY ODCMS REQUIREMENT ,
ODCMS 4.8.C.1.1 Verify the dose rate due to noble In accordance l j
gases in gaseous effluents is with sampling within limits in accordance with and analysis methods and procedures of the program ODCM. specified in Table 4.8.C.1 ;
(continued) i f'}
2)
PBAPS Units 2 and 3 ODCM 3.8.C-1 Revision 11 1
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Gassous Effluents 3.8.C.1
.ODCMS REQUIREMENTS (Continued)
ODCMS REQUIREMENT FREQUENCY h:
ODCMS 4.8.C.1.2 Obtain representative samples and In accordance verify the dose rate due to with sampling iodine-131, iodine-133, tritium, and analysis and all radionuclides in program particulate form with half lives specified in
> 8 days in gaseous effluents are Table 4.8.C.1 within limits in accordance with the methods and procedures of the :
ODCM.
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ODCM 3.8.C-2 Revision 11 PBAPS~ Units 2 and 3
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1 Gaseous Effluents 3.8.C.1 Table 4.8.C.1 (page 1 of 2)
! Radioactive Gaseous Waste Sampling and Analysis from Main Stack, Vent Stack, and Auxiliary Boiler Exhaust Stack r
SAMPLE TYPE SAMPLE SAMPLE ANALYSIS SAMPLE FREQUENCY LOWER LIMIT OF DETECTION (LLD)
(a) (d) l l
Grab Sample 31 days (b) Quantitative analysis 1 X 10-4pCi/cc(c) of identifiable gamma ,
emitters l Grab Sample 92 days Tritium 1 X 10-6pCi/cc Charcoal 7 days (c) I-131 1 X 10-12 Ci/cc (c)
Filters Particulate 7 days (c) Quantitative analysis 1 X 10-10pCi/cc (c) l Filters of identifiable gamma l emitters l
I-131 1 X 10-12 Ci/cc(c) l g Particulate 31 days Gross Alpha 1 X 10-llpCi/cc l 1 Filters (composite of weekly filters)
Particulate 31 days Sr-89 1 X 10-11pCi/cc Filters (composite of Sr-90 1 X 10-llpci/cc weekly filters)
Noble Gas Continuously Noble Gas Gross or y 1 X 10-8pCi/cc Monitor (Main Stack)
Noble Gas Continuously Noble Gas Gross or y 1 X 10-6pCi/cc l Monitor (Roof l Vents)
Auxiliary Prior to Quantitative analysis 5 X 10-7pCi/ml Boiler Waste batch of identifiable gamma Oil Grab Sample release for emitters burn PBAPS Units 2 and 3 ODCM 3.8.C-3 Revision 11
- 1 Gaseous Effluents {
3.8.C.1 J Table 4.8.C.1 (page 2 of 2) !
Radioactive Gaseous Waste Sampling and Analysis from
) Main Stack, Vent Stack, and Auxiliary Boiler Exhaust Stack (a)- The sample lower limit of detection is defined as an a priori j (before the fact) limit representing the capability of l measurement system and not as an a posteriori (after the fact) limit for a particular measurement. The values for the lower limit of detection are based on a 95% confidence level.
(b) Sampling and_ analysis shall be performed following shutdown, startup or a thermal power change exceeding 15% of rated thermal power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from a steady state condition unless (1) analysis shows that the dose equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
i (c) Samples shall be changed at least once per 7 days and analyses ,
1 shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 3 days following each shutdown, startup or thermal power change exceeding 15% of rated thermal power in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall ;
be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD may be increased by a factor of 10. This requirement does not apply if (1)
- 'g analysis has shown that the dose equivalent I-131 concentration
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f in the primary coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has j not increased more than a factor of 3.
1 (d) Certain mixtures of radionuclides may cause interference in the l measurement of individual radionuclides at their detectable limit ]
especially if other radionuclides are at much higher I concentrations. Under these circumstances use of known ratios of l radionuclides will be appropriate to calculate the levels of such j radionuclides. Nuclides which are below the sample detectable limit fer the analyses should not be reported as being present at the sample detectable limit level.
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pBAPS Units 2 and 3 ODCM 3.8.C-4 Revision 11 i
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Gascous Effluents 3.8.C.2 i 3.8.C Gaseous Effluents
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, ODCMS 3.8.C.2 The air dose at or beyond the SITE BOUNDARY due to i noble gases in gaseous effluents released from the l l two reactors at the site shall be limited to the l following:
- a. For gamma radiation, 5 10 mrad during any calendar quarter;
- b. For beta radiation, 5 20 mrad during any calendar quarter;
- c. For gamma radiation, 5 20 mrad during any calendar year; and I
- d. For beta radiation, 5 40 mrad during any calendar year.
APPLICABILITY: At all times.
1
. COMPENSATORY MEASURES
- CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated air dose A.1 Submit a Special 31 days at or beyond the Report to the NRC that SITE BOUNDARY from identifies causes for radioactive noble exceeding limits, gases in gaseous corrective actions effluents exceeds taken to reduce the i limits. releases, and corrective actions to assure that subsequent releases are within limits.
l PBAPS Units 2 and 3 ODCM 3.8.C-5 Revision 11
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! Gascous' Effluents 3.8.C.2 j
ODCMS REQUIREMENTS 1
.,T FREQUENCY i
.1 ODCMS REQUIREMENT l l
1 ODCMS 4. 8 C.2.1 Determine cumulative dose contributions 31 days for noble gases in accordance with the
- met.nodology and parameters in the ODCM.
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o PBAPS Units 2 and 3 ODCM 3.8.C-6 Revision 11 l
Gcssous Efflunnts 3.8.C.3
- 3. 8. C' Gaseous Effluents ODCMS 3.8.C.3 The dose to a MEMBER OF THE PUE : at or beyond the SITE BOUNDARY from iodine-131, iodine-133, tritium and all radionuclides in particulate form, with half lives > 8 days, in gaseous effluents released from the two reactors at the site shall be limited to:
- a. 5 15 mrem during any calendar quarter; and 3
- b. 5 30 mrem during any calendar year. ,
APPLICABILITY: At all times.
1 COMPENSATORY MEASURES i
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME 1 l
A. Calculated dose from A.1 Submit a Special 31 days the release of Report to the NRC that iodine-131, idsntifies causes for h iodine-133, tritium exceeding limits, l
.' ',7 and radionuclides in corrective actions particulate form, taken, and proposed <
with half-lives corrective actions to
> 8 days in gaseous assure that subsequent .
effluents exceeds releases are within J limits. liuits.
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PBAPS Units 2 and 3 ODCM 3.8.C-7 Revision 11 ,
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Gascous Effluents 3.8.C.3 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.3.1 Determine cumulative dose contributions 31 days for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives > 8 days in accordance with the methodology and parameters in the ODCM.
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1 PBAPS Units 2 and 3 ODCM 3.8.C-8 Revision 11 1
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Gascoun Effluents 3.8.C.4 3.8.C Gaseous Effluents
...., ODCMS 3. 8.C.4 The following conditions shall be met:
- a. Main stack dilution flow shall be 2 10,000 cfm;
- b. .One vent stack noble gas monitor and one main stack noble gas monitor shall be OPERABLE and set to alarm in accordance with the methodology and parameters in the ODCM;
- c. ' One vent stack iodine filter and one main stack iodine filter and one vent stack particulate filter and one main stack particulate filter with their respective flow rate monitors shall be OPERABLE; and
- d. One vent stack flow rate monitor and one main stack flow rate monitor shall be OPERABLE and set to alarm in accordance with the methodology and parameters in the ODCM.
I APPLICABILITY: During release of radioactive wastes.
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ODCM 3.8.C-9 Revision 11 PBAPS Units 2 and 3 l l
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E - 1 l . j G2stous Effluento {
3.8.C.4 COMPENSATORY MEASURES i
~~---NOTE------------------------------------
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Separate dition con entry is allowed for each instrument.
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One required vent A.1 Collect two 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> l
l stack noble gas independent grab monitor inoperable. samples from the AND l
affected effluent QB release pathway. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> One required main thereafter stack noble gas AND monitor inoperable.
A.2 -------NOTE---------
Perform independent verification of the release rate calculations using at least two technically qualified members of l a the facility staff.
_) -_-___._...__...____
( Analyze grab samples- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from from the affected time of release pathway for collection l activity.
1 (continued) 1.
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l PBAPS Units 2 and 3 ODCM 3.8.C-10 Revision 11 I
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Gassous Effluents 3.8.C.4 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION
) TIME MEASURE B. One required vent B.1 Collect samples from Immediately stack iodine filter the affected effluent inoperable. release pathway continuously with QE auxiliary sampling equipment such that One required vent each sample period stack particulate duration is filter inoperable. approximately 7 days.
OE AND i
One required main B.2 Analyze collected 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after stack iodine filter samples. end of each inoperable. sampling period QE One required main stack particulate
, , . filter inoperable.
l C. One required vent C.1 Estimate flow rate 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
! stack flow' rate from the affected I monitor inoperable. effluent release AER pathway.
QB once per 4 i hours One required main thereafter stack flow rate monitor inoperable.
D. Main off-gas stack D.1 Initiate action to re- Immediately I dilution flow establish main off-gas I
< 10,000 cfm. stack flow 2 10,000 cfm.
(continued) l 1
PBAPS Units 2 and 3 .ODCM 3.8.C-11 Revision 11 l l
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Gascous Effluants 3.8.C.4 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME E. One or more E.1 Explain the reason Prior to required inoperability was not submittal of radioactive corrected in a timely next gaseous effluent manner in the Radioactive Radioactive l Effluent monitoring Effluent Release Report.
instrumentation Release channels Report inoperable for
> 30 days.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.4.1 Perfonn INSTRUMENT CHECK of the vent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> stack and main stack noble gas radiation monitors.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
") ODCMS 4.8.C.4.2 Perform .T.NSTRUMENT CHECK of the vent stack and the main stack flow rate monitors.
l ODCMS 4.8.C.4.3 Section Removed 4.8.C.4.4 Perform INSTRUMENT FUNCTIONAL TEST of 92 days I ODCMS the vent stack and main stack noble gas radiation monitors, including control room alarm annunciation in response to alarm setpoint being exceeded and an instrument downscale failure.
l ODCMS 4. 8.C.4. 5 Section Removed (Continued) i PBAPS Units 2 and 3 ODCM 3.8.C-12 Revision 11 i
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Gascous Effluents 3.8.C.4 ODCMS REQUIREMENTS (Continued) l ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.4.6 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack noble gas 1 radiation monitors with a known radioactive source positioned in a f reproducible geometry with respect to i the sensor.
18 months ODCMS 4.8.C.4.7 Perform INSTRUMENT CALIBRATION of the vent stack and main stack flow rate i monitors.
ODCMS 4.8.C.4.8 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack iodine and l particulate sample flow rate monitors.
I ODCMS 4. 8.C.4. 9 Section Removed i
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PBAPS Units 2 and 3 ODCM 3.8.C-13 Revision 11
Gaseous Effluents 3.8.C.5 3.8.C Gaseous Effluents
/ ODCMS 3.8.C.5 Gaseous effluents shall be processed through the Gaseous Waste Treatment System described below prior '
to discharge:
- a. Steam jet air ejector discharge shall be processed l through the recombiner, holdup pipe, off-gas filter, and off-gas stack;
- b. Mechanical vacuum pump and gland steam exhauster discharge shall be processed through the off-gas stack;
- c. Auxiliary boiler exhaust shall be processed through the auxiliary boiler stack when burning radioactive waste oil;
- d. Reactor, turbine, radwaste, and recombiner building atmospheres shall be processed through !
permanently or temporarily installed equipment in the appropriate building ventilation system and the vent stack, with the exception of the l following unmonitored exhausts: )
- 1. Recirculation M-G set and reactor building o cooling water equipment rooms;
- 2. Control room utility and toilet rooms;
- 3. Cable spread room;
- 4. Emergency switchgear rooms;
- 5. 125/250 VDC battery rooms and the 250 VDC battery rooms, and ;
- 6. Administration building maintenance decontamination area.
APPLICABILITY: Prior to all gaseous release (s) whenever the release (s) would cause the projected dose, when it is averaged over 31 days to exceed 0.6 mrem to any organ (combined total from the two reactors at the site).
PBAPS Units 2 and 3 ODCM 3.8.C-14 Revision 11
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Gastous Effluents 3.8.C.5 COMPENSATORY MEASUP2S CONDITION REQUIRED COMPENSATORY COMPLETION 3 MEASURE TIME
.J j A. Gaseous waste A.1 Submit a Special Report 31 days i discharged without to the NRC that required processing. explains the reasons ;
gaseous radwaste was discharged without j processing, identifies .
inoperable equipment or subsystems and the I reasons for the f inoperability, {
identifies actions l I
taken to restore the inoperable equipment to OPERABLE status, and actions taken to prevent a recurrence.
l ODCMS REQUIREMENTS
_ __ l ODCMS REQUIREMENT FREQUENCY )
I ODCMS 4.8.C.5.1 Project doses due to gaseous effluent 31 days i releases at and beyond the SITE .
BOUNDARY in accordance with the i methodology and parameters in the i ODCM.
ODCMS 4.8.C.S.2 Collect and analyze air samples from 31 days each building area with an unmonitored exhaust.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.C-15 Revision 11
Gaseous Effluents 3.8.C.5 ODCMS REQUIREMENTS (Continued)
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.5.3 Demonstrate OPERABILITY of required 92 days gaseous radioactive waste system equipment by analyzing the gaseous waste processed through the required equipment to determine it meets the requirements of ODCMS 3.8.C.1 PBAPS Units 2'and 3 -ODCM 3.8.C-16 Revision 11 i
Gascous Efflucnts 3.8.C.6 3.8.C Gaseous Effluents ODCMS 3.8.C.6 PURGING of the primary containment shall be:
- a. Through the Standby Gas Treatment System whenever primary containment is required to be OPERABLE; and
- b. Through the Reactor Building Ventilation Exhaust System or the Standby Gas Treatment System whenever primary containment is not required to be OPERABLE.
APPLICABILITY: During PURGING of the primary containment.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirement of A.1 Suspend PURGING. Immediately g ODCMS 3.8.C.6 not
_,1 met.
l ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.6.1 Verify primary containment PURGING Prior to is through required effluent release PURGING pathway of ODCMS 3.8.C.6. primary l containment i
PBAPS Units 2 and 3 ODCM 3.8.C-17 Revision 11
Gascous Effluents 3.8.C.7 3.8.C Gaseous Effluents 3.8.C.7 Burning of radioactive waste oil shall be allowed:
~'} ODCMS
- a. In accordance with the requirements of 10CFR20.2004.
- b. Through the Auxiliary Boilers (Common) with the exhaust stack of the affected auxiliary boiler as a release point for radioactive effluents.
- c. With the radioactive content of the oil determined prior to incineration.
- d. With the radioactive effluents from this pathway summed with other effluents from the site and l reported to the Commission in the Radioactive Effluent Release Report.
APPLICABILITY: At all times COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Gaseous effluents A.1 Submit a Special Report to 31 days discharge without the NRC that explains the required processing reasons gaseous radwaste
~
) or was discharged without processing, identifies Gaseous effluents exceed limits inoperable equipment or specified in subsystems and the reasons 3.8.C.3 for the inoperability, identifies actions taken to restore the inoperable equipment to OPERABLE status, and actions taken to prevent a recurrence.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY j ODCMS 4.8.C.7.1 Project doses due to gaseous ef fluent Each Batch releases at or beyond the SITE Incinerated BOUNDARY.
ODCMS 4.8.C.7.2 Determine dose and dose rate Each Batch contributions for radionuclides in Incinerated particulate form with half lives > 8 days in accordance with the
,( methodology and parameters in ODCM v Section IV.F.
PBAPS Units 2 and 3 ODCM 3.8.C-18 Revision 11
l 40 CFR 190 3.8.D.1 3.8.D 40 CFR 190
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ODCMS 3.8.D.1 The dose or dose commitment to a MEMBER OF THE PUBLIC over the calendar year from all uranium fuel cycle i sources within 8 kilometers shall be:
I
- a. s 25 mrem to the total body or any organ (except the thyroid); and
- b. s 75 mrem to.the thyroid.
{
APPLICABILITY: At all times. ,
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION i
)
MEASURE TIME A. Calculated dose to a ----------NOTE------------
MEMBER OF THE PUBLIC Calculations shall include exceeds twice the direct radiation limits specified in contributions from reactor
' 1 ODCMS 3.8.B.2 or units and outside storage ODCMS 3.8.C.2 or tanks.
ODCMS 3.8.C.3. -------------------------
A.1 Calculate dose or dose Immediately commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources within i 8 kilometers to determine if specified limits were exceeded.
(continued) l i
PBAPS Units 2 and 3 ODCM 3.8.D-1 Revision 11
]
40 CFR 190 3.8.D.1 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Calculated dose or B.1 --------NOTE--------- )
dose commitment Estimates of radiation l exceeds specified exposure shall include limits of the effects of all ODCMS 3.8.D.1. effluent pathways and direct radiation including releases covered by this 1 Special Report, j Submit a Special 31 days Report to the NRC that includes the corrective actions taken to prevent recurrence, the 1 schedule for achieving conformance with required limits, estimates of radiation
,)
exposure to a MEMBER OF THE PUBLIC for the calendar year, I
descriptions of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure level or concentrations.
AND (continued)
PBAPS Units 2 and 3 ODCM 3.8.D-2 Revision 11
40 CFR 190 3.8.D.1 COMPENSATORY MEASURES (Continued)
, CONDITION REQUIRED COMPENSATORY COMPLETION TIME MEASURE
)
B. (continued) B.2 --------NOTES--------
1.Only applicable if the release condition resulting in violation of 40 CFR 190 has not been corrected.
2.Special Report submittal is considered a timely request and a variance is granted until NRC action on the request is complete.
Submit a request for a 31 days variance in accordance with 40 CFR 190 in the Special Report to the NRC.
ODCMS REQUIREMENTS i
ODCMS REQUIREMENT FREQUENCY l
ODCMS 4. 8.D.1.1 De cermine cumulative dose In accordance evntributions from liquid and with ODCM gaseous effluents in accordance with methodology and parameters in the ODCM.
1 1
(continued)
PBAPS Units 2 and 3 ODCM 3.8.D-3 Revision 11 l
40 CFR 190 3.8,D.1 ODCMS REQUIREMENTS (Continued)
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.D.1.2 Determine cumulative dose In accordance contributions from direct with ODCM radiation from the reactor units and from radwaste storage in accordance with methodology and parameters in the ODCM.
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i 1
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i PBAPS Units 2 and 3 ODCM 3.8.D-4 Revision 11 i
Rcdiologien1 Environmentcl Monitoring 3.8.E.1 1 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.1 Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in Table 4.8.E.1 and the ODCM.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Milk samples A.1 Identify locations for 31 days permanently obtaining replacement unavailable from any samples and add them of the sample to radiological locations listed in environmental the ODCM. monitoring program.
Delete locations from which samples are unavailable,
~ h BER A.2 Identify in the Prior to Radioactive Dose submittal in Assessment Report the next cause of the Radioactive unavailability of Dose samples and new Assessment locations for Report obtaining samples and include in the report revised figures and tables for the ODCM reflecting the new locations.
(continued)
-a if PBAPS Units 2 and 3 ODCM 3.8.E-1 Revision 11
Radiological Environmantal Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)
%) CONDITION REQUIRED COMPENSATORY COMPLETION
- MEASURE TIME B. Level of B.1 Submit a Special Report 31 days after radioactivity as a to the NRC which end of result of plant includes an evaluation affected effluents in an 'of any release calendar environmental conditions, quarter sampling medium at environmental factors, one or.more or other aspects which locations specified caused the reporting in the ODCM exceeds level of Table 3.8.E.1 the reporting levels to be exceeded and the of Table 3.8.E.1 corrective actions to be when averaged over taken to reduce the calendar radioactive effluents so quarter. that the potential annual dose to a MEMBER QB OF THE PUBLIC is less than the calendar year Level of reporting level of radioactivity as a Table 3.8.E.1.
recult of plant
, effluents in an environmental
.-' ) sampling medium at one or more locations specified in the ODCM exceeds the reporting levels of Table 3.8.E.1 when averaged over the calendar quarter and more than one radionuclide from Table 3.8.E.1 is !
detected and the equation in ODCMS 4.8.E.1.2 is satisfied.
(continued)
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PBAPS Units 2 and 3 ODCM 3.8.E-2 Revision 11 l
l
bdiologicalEnvironmsntalMonitoring 3.8.E.1 i 1
l COMPENSATORY MEASURES (Continued)
,) CONDITION REQUIRED COMPENSATORY COMPLETION TIME MEASURE C. Radionuclides other C.1 -------NOTE-------
than those in Only required if the Table 3.8.E.1 radionuclides detected'and the detected are the potential annual result of plant dose to a MEMBER OF effluents.
THE PUBLIC is --------------------
greater than or equal to the Submit a Special 31 days after calendar year limits Report to the NRC end of of ODCMS 3.8.B.2, or which includes an affected ODCMS 3.8.C.2, or evaluation of any calendar ODCMS 3.8.C.3, or release conditions, quarter ODCMS 3.8.D.1. environmental factors, or other aspects which caused the reporting level of Table 3.8.E.1 to be exceeded; and the corrective actions to be taken to reduce ,
... )
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radioactive effluents so that potential' annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level of Table 3.8.E.1 AND (continued) h' PBAPS Units 2 and 3 ODCM 3.8.E-3 Revision 11
=
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R2diological Environm:ntal Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued) )
COMPLETION TIME
) CONDITION REQUIRED COMPENSATORY MEASURE l C. (continued) C.2 ------NOTE--------
Only required if the radionuclides detected are not the result of
$$$$.$ !$$$1.___
Describe the condition Prior to in the Annual submittal of Radiological next Annual Environmental Operating Radiological Report. Environmental Operating Report D. Requirements of D.1 Prepare and submit, in Prior to ODCMS 3.8.E.1 the Annual Radiological submittal of not met. Environmental Operating next Annual Report, a description of Radiological
) Environmental
'~/ the reasons for not conducting the Operating radiological Report environmental monitoring program as required and the actions taken to prevent recurrence.
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PBAPS Units 2 and 3 ODCM 3.8.E-4 Revision 11 i
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Rndiological Environm2ntal Monitoring 3.8.E.1
!_ ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4 . 8 . E .1.1 - - - - - - - - - - - NO TE S - - - - - - - - - - - - - - - -
- 1. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailabilities, malfunction of automatic sampling equipment or other legitimate reasons.
- 2. If equipment malfunction occurs, an effort shall be made to complete corrective actions prior to the end of the next sampling period.
Collect radiological environmental In accordance monitoring samples at the locations with and analyze as specified in Table 4.8.E.1 Table 4.8.E.1 and the ODCM.
ODCMS 4 . 8 . E .1. 2 - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - -
All radionuclides used in this evaluation shall be averaged on a calendar quarterly basis.
Evaluate the concentration of 92 days radioactivity as a result of plant effluents in an environmental sampling medium against the following equation:
concentration (1)
+ I reporting level (1) concentration (2)
+
reporting level (2) .. 2 1.0
(,3 b) l l
PBAPS Units 2 and 3 ODCM 3.8.E-5 Revision 11 i
L
C _ 1 Rndiological Environm:ntal Monitoring 3.8.E.1 Table 3.8.E.1 (page 1 of 1)
Reporting Levels for Radioactivity Concentration in Environmental Samples Reporting Levels ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS (pCi/1) PARTICULATE (pCi/kg, wet) (pCi/1) (pCi/kg, wet, ORGASgS (pci/m )
H-3 20,000*
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
- For drinking water samples. This is 40 CFR part 141 value.
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PBAPS Units 2 and 3 ODCM 3.8.E-6 Revision 11
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Rcdiological' Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 3 of 3)
Radiological Environmental Monitoring Program
}.
NOTES (a) Fixed sample locations are shown in the Offsite Dose Calculation Manual, Table VII.A.1 and Figures VII.A.1, VII.A.2, and VII.A.3. At times it may not be possible or practicable to obtain samples of the media of choice at the most desired location or time. In those instances suitable alternative media and locations may be chosen for the particular pathway in question. Such necessary deviations are reported in the Annual Environmental Radiological Operating Report.
(b) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
-(c) Sample collection frequencies are defined as follows:
7 days 7 calendar days 1 2 days 14 days 14 calendar days 1 3 days 31 days 31 calendar days 8 days 92 days 92 calendar days 10 days 6 months 6 calendar months 20 days i
) (d) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. ,
-(e) Each phosphor is considered one thermoluminescent dosimeter.
(f) If the gross beta activity in air attributable to plant operation is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
1 l
PBAPS Units 2 and 3 ODCM 3.8.E-9 Revision 11 i
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Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.2 (nace 2 of 2) l Notes:
(a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable at 95% confidence level, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
- 03) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation) :
LLD = 4 . 6 6 Sn E 'V
- 2.22
- Y
- exp (-LAt)
Where:
LLD is the a priori lower limit of detection as defined above (as picocuries per unit mass or volume),
Sp is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate (as counts per minute),
} E is the counting efficiency (as counts per disintegration),
V is the sample size (in units of mass or volume), )
\
2.22 is the number of disintegrations per minute per picoeurie, j I
Y is the fractional radiochemical yield (when applicable) )
i l
A is the radioactive decay constant for the particular radionuclide, and At for the environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of j counting.
Typical values of E, V, Y, and At should be used in calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing
'T factors shall be identified and described in the Annual Radiological Ef-Environmental Operating Report.
PBAPS Units 2 and 3 ODCM 3.8.E-11 Revision 11
--__-____________a
g-Radiological Environmantal Monitoring 3.8.E.2 3.8.E Radiological Environmental Monitoring ODCMS 3.8 E.2 A land use census shall be conducted and shall identify the location of the nearest milk animal in each of the 16 meteorological sectors within a distance of five miles.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Land use census A.1 Add the new location to 31 days identifies a the radiological location which environmental yields a calculated monitoring program.
dose or dose commitment (via the AND same exposure pathway) that is at least 20% greater
) than a location from i which samples are currently being obtained in accordance with ODCMS 3.8.E.1. (continued)
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.g PBAPS Units 2 and 3 ODCM 3.8.E-12 Revision 11
(
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Radiological Environmtntal Monitcring 3.8.E.2 COMPENSATORY MEASURES (Continued) m CONDITION REQUIRED COMPENSATORY COMPLETION
) MEASUPS TIME A. (continued) A . 2 - - - - - - - - NOTE - - - - - - - - -
The indicator sampling location having the lowest ! '
calculated dose or dom commitment (via the ,ame exposure pathway) may be deleted from the radiological environmental monitoring program after October 31 of the year in which land use census was conducted.
_____________________ l Identify the new Prior to location in the submittal of Radioactive Dose the next Assessment Report and Radioactive Dose
~
-) include the revised
. figures and tables Assessment for the ODCM Repor'.
reflecting the new location.
B. Land use census B.1 Identify the new Prior to identifi=s a location in the submittal of location which Radioactive Dose the next yields a calculated Assessment Report. Radioactive dose or dose Dose commitment that is Assessment greater than values Report currently being calculated in l ODCMS 3.8.C.3.
PBAPS Units 2 and 3 ODCM 3.8.E-13 Revision 11 i
Radiological Environm:ntcl Monitoring
?.8.E.2 ODCMS REQUIREMENTS _
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.2.1 Conduct a land use census by a door-to- 12 months door survey or by consulting local agriculture authorities or by some other ,
appropriate means.
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PBAPS Units 2 and 3 ODCM 3.8.E-14 Revision 11 a_
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tediological Environmental Monitoring 3.8.E.3 3.8.E Radiological Environmental Monitoring
.ODCMS 3.8.E.3 Analyses shall be performed on radioactive materials supplied as part of the EPA Environmental Radioactivity Intercomparison Studies Program, or another Interlaboratory Comparison Program traceable to NIST.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirements of A.1 Include corrective Prior to ODCMS 3.8.E.3 not actions to prevent submittal of met. recurrence in the next Annual Annual Radiological Radiological Environmental Environmental Operating Report. Operating Report ODCMS REQUIREMENTS J
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.3.1 Include a summary of the results of In accordance the_Interlaboratory Comparison with Technical Program in the Annual Radiological Specification Environmental Operating Report. 5.6.2 i
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PBAPS Units 2 and 3- ODCM 3.8.E-15 Revision 11 i
1
{F Major Changas to Radioactive Wmato Treatmsnt Systems 3.9 3.9 Major Changes to Radioactive Waste Treatment Systems ODCMS 3.9.1 The radioactive waste treatment systems are those systems described in ODCMS 3.8.B.3, 3.8.B.4, 3.8.C.4, and 3.8.C.5, which are used to maintain control over radioactive materials in gaseous and liquid effluents.
ODCMS 3.9.2 Major changes to the radioactive waste systems shall be made by either of the following methods. For the purpose of this Specification " major changes" is defined in ODCMS 3.9.3.
- a. Licensee initiated changes:
- 1. Licensee initiated changes shall be reported to the NRC as part of the Modification Report required by 10 CFR 50.59. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59; l
- b. Sufficient detailed information to totally support the reason for the change without
^. benefit of additional or supplemental
- information;
- c. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;
- d. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid wastes, to the actual releases for the period prior to when the changes are to be made;
- e. An estimate of the exposure to plant operating personnel as a result of the change; and i
- f. Documentation of the fact that the change was revicwed and found acceptable by the PORC.
- 2. The change shall become effective upon review and acceptance by both the PORC and NRB. !
l 4 (continued) 1 PRAPS Units 2 and 3 ODCM 3.9-1 Revision 11 g,
d
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Major Changas to R diotctivo Waste Trontm:nt Systems j 3.9 '
3.9 Major Changes to Radioactive Waste Treatment Systems (continued)
ODCMS 3.9.2
- b. Commission initiated changes:
- 1. The applicability of the change to the facility shall be determined by the PORC after consideration of the facility design.
- 2. The licensee shall provide the Commission with written notification of its determination of applicability including any necessary revisions to reflect facility design.
- 3. The change shall be reviewed by the NRB at its I next regularly scheduled meeting.
1 l
- 4. The change shall become effective on a date i proposed by the licensee and confirmed by the Commission. )
ODCMS 3.9.3 " Major Changes" to radioactive waste systems shall j include the following: J
- a. Changes in process equipment, components, l structures, and effluent monitoring instrumentation
") from those described in the Final Safety Analysis l
Report (FSAR) and evaluated in the staff's Safety Evaluation Report (SER);
- b. Changes in the design of radwaste treatment systems that significantly alter the characteristics and/or quantities of effluents released from those previously considered in the FSAR and SER;
- c. Changes in system design which invalidate the accident analysis as described in the SER; and I
- d. Changes in system design that result in a significant increase in occupational exposure of operating personnel.
k PBAPS Units 2 and 3 ODCM 3.9-2 Revision 11 P
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Reporting Requircmtnts 3.10 3.10 Reporting Requirements ODCMS 3.10.1 Annual Radiolocical Environmental Operatina Report The Annual Radiological Environmental Operating Report shall be submitted in accordance with the requirements of Technical Specification 5.6.2. In addition to the requirements of Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report shall include or reference from previous reports:
- a. A summary description of the radiological environmental monitoring program including sampling methods for each sample type, size, and physical I characteristics of each sample type, sample )
preparation methods, and measuring equipment used; l
- b. At least two maps of all sampling locations keyed f to a table giving distances and directions from the !
midpoint between reactor vents;
- c. Results of the land use census required by ODCMS 3.8.E.2; and
- d. Results of the Interlaboratory Comparison Program
,g required by ODCMS 3.8.E.3 and discussion of all
'~ f analyses in which the LLD required by Table 4.8.E.2 was not achievable.
ODCMS 3.10.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with the requirements of Technical Specification 5.6.3. In addition to the requirements of Technical Specification 5.6.3, the Radioactive Effluent Release Report shall include:
- a. Information for each class of solid waste (as defined by 10 CFR part 61) shipped offsite during the report period:
- 1. Container volume;
- 2. Total curie quantity (specify whether determined by measurement or estimate);
- 3. Principal radionuclides (specify whether determined by measyrement or estimate);
(continued)
PBAPS Units 2 and 3 ODCM 3.10-1 Revision 11
Reporting Requircmento 3.10 3.10 Reporting Requirements
- ODCMS 3.10.2 Radioactive Effluent Release Report (continued)
- 4. Source of waste and processing employed (e.g. ,
dewatered spent resin, compacted dry waste, evaporator bottoms); and
- 5. Type of container (e . g . , LSA, Type A, Type B, Large Quantity).
- b. A list and description of unplanned releases from the site to areas at or beyond the SITE BOUNDARY of radioactive materials in gaseous and liquid .
effluents made during the reporting period.
- c. Changes made during the reporting period to the Offsite Dose Calculation Manual ('O DCM) and a list of new locations for dose calculations and/or environmental monitoring identified by the land use census required by ODCMS 3.8.E.2.
ODCMS 3.10.3 Radiation Dose Assessment Reports The radiation dose assessment reports shall be submitted within 120 days after January 1 of each year.
h The Radiation Dose Assessment Report shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured) ,
or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. The licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assensment of the radiation doses from radioactive liquid and gaseous effluent to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions 1
(continued)
C, q.
PBAPS Units 2 and 3 ODCM 3.10-2 Revision 11
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Reporting Requiremonto 3.10 3.10- Reporting Requirements ODCMS 3.10.3 Badiation Dose Assesement Reoorts (continued) concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for dete mining the gaseous pathway doses. Approximate methods are acceptable. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).
The Radiation Dose Assessment Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Guidance for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977. If doses from plant effluents do not exceed twice the Appendix I limits, a statement to that effect shall constitute a 40 CFR 190 assessment.
.a l
- T .
4 .
PBAPS Units 2 and 3 ODCM 3.10-3 Revision 11 l
ODCM Spncificctions Bases B 3.8 B 3.8 ODCM SPECIFICATIONS
} BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in Section 20.1302 of 10 CFR, Part 20. At the same time, the licensee is permitted the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in Section 20.1302 of 10 CFR, Part 20. It is expected that in using this operational flexibility under unusual operating conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.
Liouid Radwaste Effluents Concentration This specification is provided to ensure that the concentration of rtdioactive materials released in liquid waste effluents to areas at and beyond the SITE BOUNDARY will be within 10 times the concentration levels specified in 10 CFR, Part 20, Appendix B, Table 2, Column 2. This
. instantaneous limitation provides additional assurance that the levels of
) rcdioactive materials in bodies of water in areas at or beyond the SITE
~
BOUNDARY will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR, Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR, Part 20.1302 to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.
Dose This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. ODCMS 3.8.B.2 implements the guidance set forth in Section II.A of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the gu4Jas of Appendix I be shown by calculational procedures based on models cri 'ita such that the actual exposure of a MEMBER OF THE PUBLIC through cpprvpriate pathways is unlikely to be substantially underestimated. The equations described in the Offsite Dose Calculation Manual for calculating the doses due to the actual release rates (continued)
PBAPS Units 2 and 3 ODCM B 3.8-1 Revision 11
- I
r~ _
ODCM Specifications Bases B 3.8 BASES
)
Licuid Radwaste Effluents Dome (continued) of radioactive materials in liquid effluents are consistent with the m thodology provided in Regulatory Guide 1.109, " Calculation of Annual Dores to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Rovision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor R31 eases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid effluents from the cite.
Instrumentation Tha radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential release of liquid offluents. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
System Operation Tha OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents rcquire treatment prior to release to the environment. The rcquirement that the appropriate portions of this system be used when l cpecified provides assurance that the releases of radioactive mnterials in liquid effluents will be kept "as low as reasonably cchievable." This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design objective Section II.D of Appendix I to 10 CFR, Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a cuitable fraction of the guide set forth in Section II.A of Appendix i I, 10 CFR, Part 50, for liquid effluents. l The chemical / oily waste cleanup subsystem may include the portable Epicor oil / water emulsion system (as described in RW-625), an installed chemical / oily waste cleanup subsystem, or equivalent chemical / oil waste system.
The laundry drain filter may be used to process liquid wastes containing detergents or similar cleaning agents. Waste water such as river water that is acceptable for release may be processed through the laundry drain filter.
(continued)
)
PBAPS Units 2 and 3 ODCM B 3.8-2 Revision 11
.. ..,.>.,a.a. . . . . . . , . . . .
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ODCM Spscifications Bases B 3.8 BASES (continued)
I Gaseous Effluents Dore This specification is provided to ensure that the dose from radioactive m terials in gaseous effluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Pnrt 20, Appendix B, Table 2, Column 1. These limits provide reasonable m surance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding tha limits specified in Appendix B, Table 2 of 10 CFR part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC with tho appropriate occupancy factors are given in the ODCM. The specified limits restrict, at all times, the gamma and beta dose rates above bnckground to a MEMBER OF THE PUBLIC, at or beyond the SITE BOUNDARY to 5 500 mrem / year to the total body or to 6 3000 mrem / year to the skin.
These dose rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to 5 1500 mrem / year.
T
_# Dose, Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. ODCMS 3.8.C.2 implements the guidance set forth in Section II.B of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I.to assure that the releases of rtdioactive material in gaseous effluents will be kept "as low as reasonably achievable." ODCMS 4.8.C.2.1 implements the requirements in Section III.A of Appendix I that conformance with the guidance of Appendix I be shown by calculational procedures based on models and data cuch that the actual exposure of a MEMBER OF THE PUBLIC through the cppropriate pathways is unlikely to be substantially underestimated. ,
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and the atmospheric dispersion model submitted on Septenber 30, 1976, in a report titled: ;
"Information Requested in Enclosure 2 to letter from George Lear to E. ]
G. Bauer dated February 17, 1976." The ODCM equations provided for i dstermining the air doses at and beyond the SITE BOUNDARY are based upon l the historical average atmospheric conditions. j k (continued)
PBAPS Units 2 and 3 ODCM B 3.8-3 Revision 11
ODCM Sp0cifications Baseo B 3.8 BASES
) Gaseous Effluents (continued)
Dose - Iodine-131, Tritium and Radionuclides in Particulate Form This specification is provided to implement the requirements of Sactions II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. ODCMS 3.8.C.3 implements the guidance set forth in Section II.C of Appendix I and provides the required operating flexibility to implement the j guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods I cpecified in the ODCMS 4.8.C.3.1 implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and dsta such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methods for calculating the doses due to the cctual release rates of the subject materials are consistent with the nathodology provided in Regulatory Guide 1.109, " Calculation of Annual Joses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Rsvision 1, October 1977 and the Atmospheric Dispersion Model cubmitted on September 30, 1976 in a report titled: "Information j Rnquested in Faclosure 2 to letter from George Lear to E. G. Bauer
- dnted February 17, 1976." These equations also provide for
) d2termining the actual doses based upon the historical average etmospheric conditions. The release rate specifications for iodine- l 131, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with cubsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.
Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The OPERABILITY and use of instrumentation is consistent with the requirements of General Design Criteria 60, 63, cnd 64 of Appendix A to 10 CFR, Part 50.
(continued)
PBAPS Units 2 and 3 ODCM B 3.8-4 Revision 11
7 ODCM Spacificntions Bac30 B 3.8 BASES
..,. g Gaseous Effluents (continued)
System Operation The OPERABILITY of the Gaseous Radwaste Treatment System ensures that this system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when cpecified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design objective Section II.D of Appendix I to 10 CFR, Part 50. The specified limits governing the use of appropriate portions of the Gaseous Radwaste Treatment System were cpecified as a suitable fraction of the guidance set forth in Section II.B and II.C of Appendix I, 10 CFR, Part 50, for gaseous effluents.
To determine if gaseous effluents shall be processed through installed treatment equipment, the average projected dose will be determined.
For gaseous effluent pathways other than the specified unmonitored cxhausts, treatment and monitoring will only be required for pathways that are significant. Regulatory Guide 1.109, " Calculations of Annual Doses to Man From Routine Releases of Reactor Effluents for the T Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
~
J etates that a pathway is considered significant if a conservative ovaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways. Therefore, the total dose from all release pathways that do not require treatment or monitoring can not exceed 10 percent of the limit specified in Section II.C of Appendix I, 10 CFR Part 50.
Containment PURGE ODCMS 3.8.C.6 requires that the primary containment atmosphere receive treatment for the removal of gaseous iodine and particulates prior to release to provide reasonable assurance that PURGING operations will not result in exceeding the annual dose limits of 10 CFR Part 20 for creas at or beyond the SITE BOUNDARY.
(Continued)
]f PBAPS Units 2 and 3 ODCM B 3.8-5 Revision 11
ODCM Specifications Bnsos B 3.8 BASES-1
~I' Gaseous Effluents (Continued) 40 CFR 190 This specification is provided to meet the dose limitations of 40 CFR i Part 190 that~have now been incorporated into 10 CFR Part 30. This cpecification requires the' preparation and submittal of a Special Rcport whenever the calculated doses from plant radioactive effluents I exceed twice the design objective doses of Appendix I. It is highly unlikely that the resultant. dose to a MEMBER OF THE PUBLIC.will exceed the dose limits of 40 CFR Part:190 if the individual reactors remain within the reporting requirement level. The Special Report will
~
dascribe a' course of action that should result in the limitation of !
the annual dose to a MEMBER OF THE PUBLIC to within'the 40 CFR Part i
'190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose i i
contributions from other nuclear fuel cycle facilities at the same cite or within a radius of 8 kilometers (km) must be considered. If the dose to any MEMBER OF'THE PUBLIC is estimated to exceed the requirements of 40.CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with is ar)theprovisionsof40CFRPart.190.11and10CFRPart20.405c,
.;} considered.to be a timely request and fulfills.the requirements of 40 CFR Part 190 until NRC staff. action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the' nuclear fuel cycle.
l i
l i
(Continued)
.PBAPS Units 2:and 3_ ODCM B~.3.8-6 Revision 11
ODCM Spacifications Bases B 3.8 i
BASES
}-
Radioloaical Environmental Monitorina
-Monitoring Program The radiological environmental monitoring program required by this cpecification provides measurements of radiation and of radioactive mnterials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the two reactors at the sites. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the bnsis of the effluent measurements and the modeling of the environmental _ exposure pathways.
'The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limit of Detection (LLD). The LUJ's required by Table 4.8.E.2 of the specificati:ons are considered optimum for routine environmental measurements in industrial 1choratories. The monitoring program was developed utilizing the experience of'the first seven years of commercial operation. Program
, changes may be initiated based on the additional operational
) cxperience.
../
L nd Use Census
^This specification is provided to ensure that significant changes in the use of areas at and beyond the SITE BOUNDARY are identified and J that modifications to the radiological environmental monitoring program are made if required by the results of this census. This i ccnsus satisfies the requirements of Section IV.B.3 of Appendix I to j 10 CFR Part 50. l l
i Interlaboratory Comparison Program The requirement for participation in an Interlaboratory comparison Program is provided to ensure that independent checks on the precision end accuracy of the measurements of radioactive material in environmental sample matrices, are performed as part of the quality casurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of
'Saction IV.B.2 of Appendix I to 10 CFR Part 50.
i PBAPS Units'2 and 3 ODCM B 3.8-7 Revision 11 i l
l j