ML20217M830
| ML20217M830 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/30/1997 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20217M791 | List: |
| References | |
| PROC-970130, NUDOCS 9805050146 | |
| Download: ML20217M830 (118) | |
Text
IAy i
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9 9
Offsite Dose Calculation Manual Revision 10 l
i Peach Bottom Atomic Power Station Units 2 and 3 I
PECO Energy Company Docket Nos. 50-277 & 50-278
/ 80/f 7 PORC Approval
_h l
/
/
PORC Chairman Date l
/~8O'k7 PORC Meeting # :
l Date 9805050146 980420 PDR ADOCK 05000277 l
R pm j
s
,o Table of Contents 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 C.
ODCMS 4.8.C.3.1 D.
Technical Requirements Manual Test Requirement (TR) 3.5.3 l
F.
ODCMS 4.8.C.7.1 and 4.8.C.7.2 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 l
Appendix A Radioactive Effluents Control Program
r Pcg3 3 of 51, Rsv. 10 I.
Purposq 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 l
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 l
activity is then converted to an equivalent liquid radwaste monitor reading.
l l
CPS (R/W Monitor)
[ Net CPM /ml (well) x Eff W/RW] +
=
l Background CPS i
l j
Where:
liquid radwaste gross activity CPS (R/W Monitor)
=
monitor reading in CPS gross gamma activity for the Net CPM /ml (well)
=
radwaste sample tank (determined by the well counter) conversion factor between well Eff W/RW
=
counter and liquid radwaste gross
(
activity monitor [ determined by calibrating both detectors with the same liquid radioactive source]'
i background reading of the liquid l
Background CPS
=
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.
t 9
I f
Prgs 4 of 51, Rsv. 10 I
The alarm and trip pot setpoints for the liquid radwaste activity monitor are determined from a calibration curve for The alarm pot setting includes a the alarm pot and trip pot.
factor of 1.25 tv allow for analysis error, pot setting error,,
instrument thror 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.
l Licuid Radwaste Release Flowrate Setooint Determination l
II.B The trip pot setpoint for the liquid radwaste release flowrate 1
is determined by multiplying the liquid radwaste flowrate (from Section III.A) by 1.2 and using this value on the appropriate calibration curve for the discharge flow meter to The Peach Bottom radwaste system has two flow be used.
monitors - high flow (5 to 300 gpm) and low flow (0.8 to 15 The factor of 1.2 allows for pot setting error and gpm).
The flow rate determination includes a instrument error.
margin of assurance which includes consideration of this error such that the instantaneous release limit of 10 CFR 20 is not i
exceeded.
Setooint Determination for Gaseous Radwaste II.C The high and high-high alarm setpoints for the main stack radiation monitor, Unit 2 roof vent radiation monitor and Unit
- l 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 l
the gaseous effluent dose rate equations in section IV.A of l
the ODCM to determine what main stack release rate and roof vent release rate will produce a dose rate of 150 mrem /yr to and a dose the total body (30% of the limit of 500 mrem /yr) rate of 900 mrem /yr to the skin (30% of the limit of 3000 from each release point.
Using the smallest (most mrem /yr) 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 Set the high-high alarm for approximately this factor.
monitor response.
Prga 5 of 51, R3v. 10 s
l II.D.
Setooint Determination for Gaseous Radwaste Flow Monitors l
The alarm setpoint for the main stack flow monitor is as follows:
Low Flow Alarm 10,000 CFM. - This 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:
5 1.5 x 10 cfm Low Flow Alarm 8
High Flow Alarm - 5.4 x 10 cfm III.
Licuid Pathway Dose Calculations III.A Licuid Radwaste Release Flow Rate Determination Peach Bottom Atomic Power Station Units 2 and 3 have one l
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 l
areas at and beyond the SITE BOUNDARY shall be such that the l
concentration of radioactive material.after dilution shall be l
limited to 10 times the concentration specified in 10 CFR 20, j
Appendix B, Table 2, Column 2 for radionuclides other than I
l 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 i
determined as follows:
Determine a Dilution Factor by:
1 MCI!"2f i
l Dilution Factor =
10xECL1 the activity of each identified gamma emitter pCi/ml i
=
in pCi/ml' The effluent concentration specified in 10 CFR ECLi
=
l 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases or 2 x lod Ci/ml for noble gases.
s
~
peg 3 6 of 51, R3v. 10
'III.A
,(Cont'd)-
Determine the Maximum Permissible Release Rate with this Dilution Factor by:
Release Rate (gpm)
B X C X Di uc2o actor
=
The number of circulating water pumps running A
=
which will provide dilution the flow rate in gpm for each circu"Eting water 5
2.0 X 10
=-
pump running.
margin of assurance which includes B
=
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.
concentration gradient factor.
The.value used C
=
for C is 5.0 for discharge canal water levels less than 104' and 3.0 for canal water levels greater than 104'.
III.B ODCMS 4.8.B.2.1 Dose contributions from: liquid effluents released to areas at and beyond the SITE BOUNDARY shall be' calculated.using the This dose calculation uses those appropriate equation below..
radionuclides listed in Table III.A.1.
These radionuclides account for virtually 100 percent of the total body dose and
' organ dose from liquid affluents.
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.
b bc3 D=
[
A%
C F 33 3 3
11 where:
The cumulative dose ' commitment to the total body or, D
=
any organ, from liquid effluents for the total time period $ Ac2 in arem.
J=1 The length of the lth time period over which C;i and At
=
i F. are averaged for the liquid release, in hours.
3 l
l-
,.s Paga 7 of 51, Rsv. 10 III.B (Cont'd)
The average concentration of radionuclide, i, in Ca
=
undiluted liquid effluent during time period At from any liquid release, (determined by the effluent. in sampling analysis program, ODCMS Table 4.8.B.1),
pCi/ml.
The site related ing stion dose commitment factor to Ar
=
i the total body or organ, r, for each radionuclide liste.d in Table III.A.1, in mrem-m1 per hr-Ci.
See Site Specific Data.**
The near field average dilution factor for Ca F,
=
during any liquid effluent release.
Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow through the discharge structure.
III.C ODCMS 4.8.B.4.1 Projected dose contributions from liquid effluents shall be-calculated using the methodology described in section III.B.
- See Note 1 in Bases
Pago 8 of 51, R;v. 10 a.
TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
Ar DOSE FACTOR (MREM-ML PER HR pCi) i TOTAL BODY 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 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-59 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 1.8kiE+02 1.79E+02 2.36E+02 I-131 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 NOTE:
The listed dose factors are for radionuclides that may be detected in liquid effluents and have significant dose The factors are decayed for one day to account consequences.
for the time between effluent release and ingestion of fish by the maximum exposed individual.
Pag 3 9 of 51, R0v. 10 TABLE III.A.1
_ LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
Ar DOSE FACTOR (MREM-ML PER HR pCi) i 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
/
CO-58 1.16E+02 1.14E+02 1.04E+02 CO-60 3.35E+02 3.32E+02 3.07E+02 ZN-65 8.55E+04 8.46E+04 6.69E+04 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 3.2SE+02 3.32E+02 4.16E+02 1-133 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 The listed dose factors are for radionuclides that may be NOTE:
detected in liquid effluents and have significant dose The factors are decayed for one day to account consequences.
for the time between effluent release and ingestion of fish by.
the maximum exposed individual.
Paga 10 Of 51, Rav.'10
,6 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE' FACTORS (DECAY CORRECTED)
Ag DOSE FACTOR (MREM-ML PER HR-Ci)
BONE CHILD RADIO-TjlZE ADULT NUCLIDE no data no data no data H-3 1.98E+02 1.70E+02 1.65E+02 NA-24 3.35E+05 2.58E+05 2.38E+05 P-32 no data no data no data MN-54 1.19E+03 8.47E+02 8.12E+02 FE-55 1.63E+03 1.30E+03 1.26E+03
.FE-59 no data no data no data
-CO-58 no data no data no data CO-60 2.51E+04 2.43E+04 2.69E+04 ZN-65 5.19E+04 3.30E+04 3.08E+04 SR-89 6.78E+05' 6.31E+05 7.67E+05 SR-90 1.80E+04 1.37E+04 1.27E+04 TE-129M-1.56E+03 1.21E+03 1.12E+03 TE-131M 3.07E+03 s
2.42E+03 2.29E+03 TE-132 4.13E+02 2.38E+02 2.28E+02 I-131 6.84E+01 3.92E+01 3.72E+01 I-133 4.30E+05 3.55E+05 3.47E+05 CS-134 4.10E+04 3.46E+04 3.45E+04 CS-136 6.01E+05 4.75E+05 4.44E+05 CS-137 1.27E+03 5.57E+02' 5.63E+02 BA-140 The listed dose factors are for radionuclides that may be detected in. liquid effluents.and have significant doseThe fac NOTE:
for the time between affluent release and ingestion of fish by consequences.
the maximum exposed individual.
O
Pcga 11 cf 51, R;v. 10
[
TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
A;f DOSE FACTOR (MREM-ML PER HR pCi)
KIDNEY 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 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 CO-58 no data no data no data CO-60 no data no data no data l
ZN-65 5.72E+04 5. 4'1E+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 l
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 NOTE:
The listed dose factors are for radionuclides that may be detected in liquid effluents.and have significant dose The factors are decayed for one day to account consequences.
for the time between effluent release and ingestion of fish by i
l the maximum exposed individual.
i l
i
(
Paga 12 of 51, R,v. 10 1
TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS l
(DECAY CORRECTED)
{
A r DOSE FACTOR (MREM-ML PER HR pCi) i GI-LLI RADIO-I 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 s
P-32 1.73E+05 1.41E+05 5.98E+04 i
l MN-54 1.58E+04 1.04E+04 3.38E+03 i
l FE-55 3.22E+02 2.60E+02 1.17E+02 l
FE-59 9.90E+03 7.15E+03 2.84E+03 CO-58 2.35E+03 1.56E+03 6.04E+02 l
CO-60 6.30E+03 4.33E+03 1.70E+03 l
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
. T. E-13 2 7.02E+04 4.85E+04 1.37E+04 I-131 8.58E+01 6.57E+01 3.70E+01 1-133 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 BA-140 1.15E+03 8.69E+02 6.43E+02 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 for the time between effluent release and ingestion of fish by the maximum exposed individual.
P293 13 of 51, Rsv. 10 IV.
Gaseous Pathway Dose Calculations IV.A.
ODCMS 4.8.C.1.1 and 4.8.C.1.2 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 dose (vent releases) and Kr-87 for skin dose (stack releases).
Method (b), the Isotopic Ana)ysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.
For normal operations, it is expected that method.(a) will be if noble gas releases are close to the limits used.
- However, as calculated by method (a), method (b) can be used to allow more operating flexibility by using data that more accurately reflect actual releases, Gross Release Method a.
V dyg + K (RTC) v byv D,
=
n
{L,(FR), + 1.1B]
+ [Lv + 1.1N3 (2TC) v yv D,
=
g where:
The location is the site boundary, 1097m SSE from the This location results in the highest calculated vents.
dose to an individual from noble gas releases.
^
Dn,
= total body dose rate, in mrem /yr.
skin dose rate, in mrem /yr.
D, a
4.72 X 10" mrem /yr per pCi/sec; the constant V
= for Kr-88 accounting for the gamma radiation from the elevated finite plume.
This F.onstant was developed using MARE program with plant specific inputs for PBAPS.
Pegs 14 of 51, Rsv. 10 IV.A.1.a (Cont'd)
= The gross release rate of noble gases from d,
the stack determined by gross activity stack monitors averaged over one hour, in pCi/sec.
= 1.47 X 10' area /yr per pCi/m'; the total body
' dose factor due to gamma emissions for Kr-88 K-(Reg. Guide 1.109, Table B-1).
sec/m'; the highest calculated 4
= 5.33 X 10
('f7'C) y
-annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
= The gross release rate of noble gases in bk gaseous. effluents from vent releases determined by gross activity vent monitors averaged over one hour,in Ci/sec.
= 2.37 x 10 strem/yr per Ci/m ; the skin dose 8
3 (Reg.
Ly factor due to beta emissions for Kr-88.
Guide 1.109, Table B-1).
= 9.73 X 10 mram/yr per Ci/m ; the skin ' dose 8
8 L,
factor due to beta emissions for Kr-87. (Reg.
Guide 1.109, Table B-1).
sec/m ;. the highest calculated 3
4
= 9.97 X 10 (2TC),
annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
arad/yr per pCi/sec; the constant I
d
= 1.74 X 10 for Kr-87 accounting for the gamma radiation I
B This from the elevated finite plume.
constant was developed using MARE program l-l with plant specific inputs for PBAPS.
mrad /yr per pCi/m'; the air dose 8
= 1.52 X 10 factor due to gamma emissions for Kr-88.
f.
N (Reg. Guide 1.109, Table B-1).
= Unit conversion, converts air dose to skin 1.1 dose, mrem /arad.
l.
i 1
Pag 3 15 of 51, R1v. 10 IV.A.1. b.
Isotopic Analysis Method (27D),dy,)
Da=
( Vj 3, + K3
((Lj (X7D), + 1.1Bj)' d, + (43 + 1.1Nj) (T/D) y (djy))
D, 3
=
a where:
The location is the site boundary, 1097m SSE from the This location results in the highest calculated vents.
dose to'an individual from noble gas releases.
Dy,
= total body dose rate, in mrem /yr.
3 D,
= sNin dose, in mram/yr.
V
= The constant for each identified noble gas radionuclide for the gamma radiation from the j
' elevated finite plume.
The constants were i
developed using the MARE program with plant specific inputs for PBAPS.
Values are listed on Table IV.A.1, in mram/yr per pCi/sec.
d j,
= The release rate of noble gas radionuclide, i, in gaseous effluents from the stack deternined by isotopic analysis averaged over one hour, in pCi/sec.
Kj
= The total body dose factor due to gamma i
emissions for each identified noble gas radionuclide.
Values are listed on Table 3
IV.A.1, in mrem /yr per pCi/m.
(X/0)y
= 5.33 X 10 sec/m ; the highest calculated 4
3 annual average relative concentration for any area at or beyond the SITE BOUNDARY for all-vent releases.
djy
= 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.
= The skin dose factor due to beta emissions Lj for each identified noble gas radionuclide.
Values are listed on Table IV.A.1,'in mrem /yr 3
per pCi/m.
1 Paga 16 of 51, Rsv. 10 IV.A.1.b (Cont'd)
(T/D),
= 9.97 X 10 sec/m ; the highest calculated 4
3 annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
= The constant for each identified noble gas B3
.radionuclide accounting for the gamma radiation from the elevated finite plume.
The constants were developed using MARE program with plant specific inputs for PBAPS.
Values are listed on Table IV.A.1, in arad/yr per ci/sec.
= The air dose factor due to gamma emissions Hj for each identified noble gas radionuclide.
Values are listed on Table IV.A.1, in mrad /yr 3
i per pCi/m.
1.1
= Unit conversion, coverts air dose to skin dose, mram/arad.
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1 Paga 18 of 51, Rav. 10 Iodine-131, iodine-133,. tritium and radioactive materials in particulate form, other than noble gases, with half-lives IV.A.2 greater than'aight days.
The dose rate shall be determined by either of two methods.
Method (a), the Iodine-131 Method, uses the iodine-131 releases and a correction factor to calculate the dose ratethe Isotopic Analysis from all nuclides released.
Method (b),
Method, utilizes all applicable nuclides.
will be For normal operations, it is expected that Method (a) used since iodine-131 dominates the critical pathway -
thyroid.
However, in the event iodine-131 releases are minimal (e.g., during long term shutdown) Method (b) will be In the-absence of used to provide accurate calculations.
iodine-131 releases, the lung is the critical organ.
~
Iodine-131 Method a.
yy]
(CE) P (W, y, + W
.D y
y
=
r where:
The location is the site boundary, 1097m SSE from the vents.
= dose rate to the thyroid, in arem/yr.
D7 1.09; the correction factor accounting for CF
= the use of iodine-131 in lieu of all radionuclides released in gaseous effluents including iodine-133.
3 1.624 X 10 ares /yr per pCi/m ; the dose 7
I Py
= parameter for I-131 via the inhalation The dose factor is~ based on the pathways.
critical individual organ, thyroid, and most restrictive age group, child.
All values are from Reg. Guide 1.109 (Tables E-5'and E-9).
1.03 X 10 sec/m'; the highest calculated 4
W, annual average relative concentration for any
=
area at or beyond the SITE BOUNDARY from stack releases.
(SSE boundary)
= The release rate of iodine-131 in gaseous b y, effluents from the stack determined by the effluent sampling and analysis' program (ODCMS Table 4.8.C.1) in pCi/sec.
Wy
= 4.78 X 10 sec/m ; the highest calculated 4
3 annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases (SSE boundary).
I 1
l l
s Pags 19 of 51, Kav. 10 (Cont'd)
IV.A.2. a.
The release rate of iodine-131 in gaseousefflue rv =
the affluent sampling and analysis program in pCi/sec.
(ODCMS Table'4.8.C.1)
Isotopic Analysis Method IV.A.2. b.
is
- Wv sk P[W D
=
3 s
t where:
h The location is the site boundary, 1097m SSE from t e vents.
= dose rate to the' lung, in mram/yr.
D ther t
= The dose parameter for radionuclides o than noble gases for the inhalation pathway.
. Pg The dose factors are based on the critica All values are from Reg.
age group-child.(Tables E-5 and E-9).
Values are Guide 1.109 in mrem /yr per listed on Table IV.A.2, 3
pCi/m.
= 1.03 X 10 'sec/m ; the highedt calculate 4
8 W,
area at or beyond the SITE BOUNDARY from (SSE boundary) stack releases.
= The release rate of radionuclides; i, in gaseous effluents from the stack det d f, in pCi/sec.
(ODCMS Table 4.8.C.1) sec/m'; the highest calculated 4
annual average relativo concentration for any
= 4.78 X 10 Wy area at or beyond~the f,ITE BOUNDARY for all (SSE boundary) vent releases.
i, in
= The release rate of radionuclides, gaseous effluents from all vent releases, by determined by the effluent sampling and f
in analysis program (ODCMS Table 4.8.C.1) pCi/sec.
\\
i
/
O
-Prga 20 of 51, R3v. 10 TABLE IV.A.2 - CONSTANTS FOR ISOTOPIC ANALYSIS METHOD S
(mrem /yr per ci/m )
Pi - Inhalation Radionuclide lunc Dose Factor
.1. 58 X10'
.Mn-54 1.70x10' Cr-51 8
1.11x10 Co-58 7.07x10' Co-60 5
Zn-65 9.95x10 6
Sr-89 2.16x10 7
'1.48x10 Sr-90 5
Ce-141 5.44x10 5
Cs-134 1.21x10 5
Cs-137 1.04x10
- 1. 74 x10
Ba-140 in
.-..c
i Paga 21 of 51, Rsv. 10 i
IV.B.
ODCMS 4.8.C.2.1 The air dose in areas at and beyond the SITE BOUNDARY due'to ll be determined
. noble gases released in gaseous effluents sha 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 Method (b), the radiation and Kr-87 for beta radiation.
Isotop.ic Analysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.
l it is expected that Method (a) will be i
For normal operations, However, if noble' gas releases are close to the limits used.
can be used to allow as calculated by Method (a), Method (b) more operating flexibility by using data that more accurately reflect actual releases.
.IV.B.1 for gamma radiation:
Gross Release Method a.
3.17 x 10-s [g (y73) y p + 33,)
D
=
y y
where:
The location is the SITE BOUNDARY 1097m SSE from the This location results in the highest calculated vents.
gamma air dose from noble gas releases.
l D
= gamma air dose, in mrad.
y 3.17 x 10-s= years per second.
Ci/m?; the air dose
= 1.52 x 10' mrad /yr per factor due to gamma emissions for;[ Kr-88.
N (Reg. Guide 1.109, Table B-1) sec/m'; the highest calculated
= 5.33 x 10 (X/D) y annual average relative concentration from vent releases for any area at or beyond the j
SITE BOUNDARY.
= The gross release of noble gas radionuclides Dy 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.
Paga 22 of 51, R&v. 10 IV.B.1. a (Cont'd)
= 4.90 x lod arad/ year per pCi/sec;_the B
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.
The gross release of noble gas radionuclides n
17,
= 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 3.17 x 10-8 (Mj (77"C) y Djy + Bj Dj,)
D
=
y where:
The location is the SITE BOUNDARY, 1097m SSE from the This location results in the highest calculated vents.
gamma air dose from noble gas releases.
gamma air dose, in mrad.
D,
=
3.17 x 10-8 = years per second.
The air dose factor due to gamma emissions Nj for each identified noble gas radionuclide.
=
Values are listed on Table IV.A.1, in arad/yr 3
per pCi/m.
5.33 x 10 sec/m ; the highest calculated 4
S (X7D) y
= average relative concentration from vent.
releases for any area at or beyond the SITE BOUNDARY.
The release of noble gas radionuclides, i, in
.Djy
= 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 By radionuclide accounting for the gamma radiation for the elevated finite plume.
The constants were developed using the MARE program with plant specific inputs for PBAPS.
Values are listed on Table IV.A.1, in arad/yr.
per ci/sec.
Paga 23 of 51, rov. 10 IV. B.1'. b.
(Cont'd)
Dj,
= 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:
Gross Release Method a.
D,
= 3.17 x 10-s y [(y73) y p (gj g), p, ]
y where:
The location is the SITE BOUNDARY 1097m SSE from the This location results in the highest calculated vents.
gamma air dose from noble gas releases.
beta air dose, in mrad.
D,
=
3.17 x 10-8 = years per second.
8
- 1. 03 x 10' mrad /yr per Ci/m ; the air dose N
=
factor due to beta emissions for Kr-87.
(Reg. Guide 1.109, Table B-1) 5.33 x 10 sec/m ; the highest calculated 4
8 (X73)y
= annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
The gross release of noble gas radionuclides Dv
=
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.
sec/m ; the highest calculated 8
9.97 x 10'8 (X/ 0),
= annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
The gross release of noble gas radionuclides V,
=
in gaseous releases from the stack determined by gross activity stack monitors, in pCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
I Pcga 24 cf 51, R v'.
10 Isotopic Analysis Method
~
i (y73)sDu}
l IV.D.2. b.
= 3.17 x 10-e y, {(y7p) y 3,y +
D, i
3.17 x 10-8 = years per second.
i i
s for l
= The. air dose factor due to beta em ss on each identified noble gas radionuclide.
in arad/yr N
Values are listed on Table IV.A.1, 3
per pCi/m'.
sec/m ; the highest calculated 3
annual average relative concentration fro
= 5.33 x 10 (77D) y SITE BOUNDARY.
lide, i, in
= The release of noble gas radionuc gaseous effluents from all vents asdetermine Djy Releases shall be cumulative over thecal sec/m ; the highest calculated 3
4 annual average relative concentration fr
= 9.97 x 10 (77D),
d the SITE BOUNDARY.
i, in
= The release of noble gas radionuclide, gaseous effluents from the stack as Dj, Ci.
determined by isotopic analysis, in Releases shall be cumulative over theca ODcMS 4.8.c.3.1 iodine-133, tritium IV. C -
The dose to an individual from iodine-131, nd and ' radioactive materials in particulate form ara i
greater than eight days in gaseous effluents release beyond the SITE BOUNDARY.
hd Method The dose shall be determined by one of two met o s.
leases and a (a), the Iodine-131 Method, uses the iodine-131 re ll nuclides correction factor to calculate the dose from a i
Method (b), the' Isotopic Analysis Method, util zes-released.
all applicable nuclides.
i l be it is expected that Method (a) w l thway -
For_ normal operation, used since' iodine-131 dominates the critical paHowe minimal (e.g. during long term shutdown) Met oIn the absence of L
thyroid.
used to provide accurate calculations. iodine-131 re a
Pig 3'25 of 51, Rav. 10 Iodine
.131 Method IV. C..
a.
Dr
- = 3.17 x 10-s (CE) (0.5) R [W, Dy, + W Dy y
where:
Location is the critical pathway dairy 1431m WSW from l
vents.
from all
=. critical organ dose, thyroid, D7 pathways, in arem.
3.17 x 10-8 = years per second.
= 1.09; the corraction factor accounting for the use of Iodine-131 in lieu of all radio-CF nuclides released in gaseous effluents including Iodine-133.
= fraction of iodine releases which are 0.5 nonelemental.
= 3.08 x 10" m (aram/yr) per pCi/sec; the dose 2
The dose factornis R
factor for' iodine-131.
based on'the critical individual organ, thyroid, and most restrictive age group, infant.
See Site Specific Data.**
= 8.78 x 10# meters ;
(F/D) 4 j
W, for the food pathway for stack releases.
= The release of iodine-131 from the stack Dr, determined by the affluent sampling and in analysis program (ODCMS Table 4.8.C.1),
. Releases shall be cumulative over the Ci.
calendar quarter or, year, as appropriate.
= 1.58 x 10 meters ;
(DTD) 4 4
j W'y for the food pathway for vent releases.
= The release of iodine-131 from the vent Dy determined by the effluent sampling and in analysis program (ODCMS Table 4.8.C.1),
Releases shall be cumulative over the Ci.
calendar quarter or year, as appropriate.
~
- See Note 2 in Bases.
Paga 26 of 51, R3v. 10 Isotopic Analysis Method IV.C._
b.
R (W b s
- W Uk
~
= 3.11 x 10**
1 s i V
l Dzy where:
Location is the critical pathway dairy 1431m WSW from ll vents.
critical organ dose, liver, from all
=
Dy j
pathways, in arem.
t 3.17 x 10-8 = years per second.
= The dose factor for each identified 3
radionuclide, i, based on the critical R
liver and most restrictive individual organ, Values are listed on age group,-infant.
Table IV.C.1, in.m (mrem /yr) per pCi/sec.
2
= 8.78 x 10'" meters ;
(F/D) 4 j
W, for the food pathway for stack releases.
= The release of radionuclides, i, in gaseous effluents from the stack determined by the Dj, in effluent sampling (ODCMS Table 4.8.C.1),
Releases shall be cumulative over the Ci.
calendar quarter or year, as appropriate.
= 1.58 x 10 meters ;
(D7D) 4 4
l Wy for the food pathway for vent releases.
= The release of radionuclides, i,_in gaseous Djy 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.
I
<ryv
~
Pags 27 of 51, Rev. 10 TABLE IV.C.1 - CONSTANTS FOR ISOTOPIC ANALYSIS METHOD (m (arem/yr) per pCi/sec) 2 RADIONUCLIDE Bi 7
1.93 x 10 Mn-54 5.14' x 10'*
Cr-51 6
9.58 x 10 Co-58 7
4.69 x 10 Co-60 9.21 x 10' Zn-65 8
- 1. 31 x 10
- Sr-89 M
'Sr-90 1.67 x 10
- 3 8.68 x 10 Ce-141 5
3.54 x 10 Cs-134 3.24 x 10" Cs-137 8
7.09 x 10 Ba-140 There is no liver dose factor given in R.G. 1.109 for these nuclides.
Therefore, the whole body dose factor was used.
I 9
9 9
- 1 Paga 28 of 51, R3v. 10 IV.D ODCMS 4.8.C.5.1 The projected doses from releases of gaseous effluents to areas at and beyond the SITE BOUNDARY shall be calculated in accordance with the following sections of this manual:
gamma air dose - IV.B.1 a.
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 result in the maximum releases from the plant.
Any alternative release pathways result in lower releases and, therefore, lower doses.
(TR) 3.5.3 IV.E Ischnical Reauirements Manual Test'Recuirement IV.E.1 The t.wo types of recombiner hydrogen analyzers currently used
~
at Peach Bottom are:
Hays Thermal Conductivity type -(Analyzers 4083, 4084, a.'
4029, and 4047 on Unit 2.
Analyzers 5083, 5084,.5029 and 5057 on Unit 3.)
Scott Series 900 Helium - Immune type (Analyzers 4083X b.
and 4084X on Unit 2.
Analyzers 5083X and 5084X on Unit 3.)
These analyzers will be replaced, per Mod P61, with the Whittaker Electrochemical type (Analyzers 4083A and 4083B on Unit 2.
Analyzers 5083A and 5083B on Unit 3).
IV.E.2 The calibration' gases for the three types are:
a.
Hays Analyzers Zero Gas - Air Calibration Gas - 4% Hydrogen, Balance Nitrogen b.
Scott Analyzers Zero Gas - Air Calibration Gas - 2% Hydrogen, Balance Air c.
Whittaker Analyzers Calibration Gas - 2% Hydrogen, Balance Air I
f IV.F ODCMS 4.8.C.7.1 and 4.8.C.7.2 11 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 ca1culated by the expressions below.
~
Pegs 29'of 51, Rsv. 10
+
IV.F.1 (Continued) h ll be
~
The dose rate from radioactive particulate release s aMethod (a), total determined by either of two methods.
instantaneous release assumes that the total activity s
i ute of j
contained in the waste oil is. released in the first m nMethod (b? us
{
l incineration.
l entire time of incineration.
ill be j
For normal operations, it is assumed that Method (a) wtd used, since the total activity from the waste oil is expec e ual l
to contribute an insignificant dose compared to the ann l
However, in the event that the activity is
- limits, significantly higher than administrative or regulatorywould be used limits.
j j
then Method (b) j calculating the dose rate.
l the j
Since the auxiliary boiler stacks are at approximate y the l
same height as the reactor vents and discharge fromaux h
reactor l
[
vent D/Q value for the calculations is considered j
l conservative.
Instantaneous Release Method a.
(
D4 "[P W
J v iv l
l where:
The location is the site boundary, 1097m SSE from the l
.l l
vents.
instantaneous dose rate to the lung, in j
l D
=
3 l
mrem / year l
The dose parameter for radionuclides for theThe dose facto l
l l
P,
=
inhalation pathway.on the critical individual organ-lung,'and most j
All values are l
restrictive age group-child.(Tables E-5 and E-9).
from Reg. Guide 1.109 in mrem / year i
j Values are listed on Table IV.A.2, l
per Ci /m'.
the highest calculated j
4 8
4.78 X 10 sec/m ;:
annual average relative concentration for any i
F
=
area at or beyond the SITE BOUNDARY for all l
y j
(SSE boundary).
j Vent releases.
l l
l
1 PIga 30 of 51, Rsv. 10 IV.F.,1 (Continued) 8 i, in gaseous The release rate of radionuclide, effluents from the auxiliary stack releases, j
djy
=
determined by the oil sampling and analysis j
in program (ODCM Specification Table 4.8.C.1) j j
Ci/sec as calculated below:
i Cy x 3785 x Z s
f I
60 l
l where:~
l The location is the site boundary, 1097m SSE from the vents.
l activity concentration measured in oil for l
Cjy
=
nuclida, i, in Ci/ml.
I milliliters per gallon.
3785 =
l gallons of oil consumed.
Z
=
number of seconds used for release.
60
=
Constant Release Method b.
I' I
Dg =
P,Wh0gy where:
j The location is the site boundary, 1097m SSE fr.om the l'
vents.
8 dose rate to the lung, in arem/ year D
=
3 The dose parameter for radionuclides for the.The do Pi
=
inhalation pathway.
l on the critical individual organ-lung, and most j
All values are l-restrictive age group-child.(Tables E-5 and E-9).
l from Reg. Guide 1.109 in aren/ year j
Values are listed on Table IV.A.2, j
per pCi/m'.
l sec/m ; the highest calculated 3
4 4.78 X 10 annual average relative concentration for any W
=
l y
.l area at or beyond.the SITE BOUNDARY for all l
vent releases.
(SSE boundary).
I
Ptg2 31 of 51, Rsv. 10
' IV.F.1 (Continued)
The release rate of radionuclide, i, in gaseous b,=
effluents from the auxiliary stack releases, 3
determined by the oil sampling and analysisin program (ODCM Specification Table 4.8.c.1) l Ci/sec as calculated below:
8 I
L x 3785 x Z f
)) C y f
T
\\
g where:
j The location is the site boundary, 1097m SSE from the i
8 vents activity concentration measured in oil for Cy.=
nuclide, i, in pCi/ml.
j' f
i milliliters per gallon.
3785 =
gallons of oil consumed.
2
=
l l
number of seconds used to burn oil for release.
T
=
l The dose to an individual from radioactive materials in l
ih particulate form and radionuclides other than noble gases w t l IV.F.2 half-lives greater _than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY from the j
incineration of contaminated waste oil from the auxiliary l
's.
boiler stacks.
l The dose from radioactive particulate release shall l
l In the absence of iodine-131 releases l
applicable nuclides.
l the liver is the critical organ.
8
's Isotopic Analysis Method i
l l
= 3.17 x 10**
R W T7 y 3
y 3
?
Dz, l
where:
The location is the critical pathway dairy 1431m WSW from the vents.
I
= critical organ dose, liver, from all l
pty pathways, in mrem.
3.17 X 10-8
= years per second.
i
p l
Pags 32 of 51, Rsv. 10
~
l.IV.F.2 (Continued) i i,
The dose factor for each identified radionucl de, liver and Rj based on the critical individual organ, Values are
=
r l
the most restrictive age group, infant. per pCi/sec.
in m (mrem /yr) 2 j
listed on Table IV.C.1, meters.2; (D7D)for the food pathway for 4
1 58 X 10
. W'y
=
f vent releases..
i, in gaseous effluents The release of radionuclide,from the auxiliary stack releas l
I l
j O jy
=
l oil sampling and analysis program (ODCMS Table Release shall be cumulative over j
4.8.C.1) in pCi.
l the calendar quarter or year,- as appropriate.
j 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 3.8.C.2, or not exceed the limits given in ODCMS 3.8.B.2, 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 3.8.C.2, or 3.8.C.3 exceed the limits given in ODCMS 3.8.B.2, by more than two times, the maximum dose or dose cocmitment to a real individual shall be determined utilizing the" Calculation.
methodology provided in Regulatory Guide 1.109, of Annual Doses
".o Man from Routine Releases of ReactorEffluents for the Any Appendix I", Revision 1, October 1977.
l deviations from the methodology provided in Regu Part 50, in accordance with ODCMS 3.8.D.1.
The cumulative dose contribution from direct radiation be determined by the following methods:
Cumulative dose contribution from direct radiation =(as evaluated
~
Total dose at the site of interest measurement)
(as evaluated by TLD's at Mean of background dose background sites)
Effluent contribution to dose (as evaluated by ODCMS 4.8.D.1.1).
6.6.1-1979 This evaluation is in accordance with ANSI /ANSThe error using t Section 7.
/
approximately 8%.
Paga 33 of 51, Rsv. 10 Uniaue Reportina Recuirement ODCMS 3.10.3. Dose Calculations VI.A.
for the Radiation Dose Assessment Reoort i
The assessment of radiation doses for the radiation dose assessment report shall be p,erformed utilizing the methodology
" Calculation of Annual provided in Regulatory Guide 1.109, Doses To Man'from Routine Releases of Reactor Effluents for l
the Purpose of Evaluating Compliance with'10 CFR Part 50, October 1977. 'Any deviations from Appendix I",
Revision 1, 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 There.is a very.short turnaround time between the Report.
determination _of all radioactive releases and publication of This would not allow the Radioactive Effluent Release Report.
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 VII.A.2, and VII.A.3, and shall be on Figures VII.A.1, analyzed pursuant to the. requirements of Table VII.A.1.
i 1
I i
4 1
0 y
1 lr e
v t
sR r
a q
u 1
5 s
e s
f e
o s
o y
D 4
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a a
n m
2 A
ma ga G
P l
o s
g d
a nd Dt n
.n n
n i
in s
La y
e 1o is to c
a T
l s
i wr spy e
n n
r ohSmttoo a
tl p
os.
) o e
htMeapnt eoil ssirs 4i t
ciCtteocy~ gna nten ma d
doato (tyr wDIscCebeni r
o g
ala e
O x
s hicr ni m ni n
h i
en, rcru re 1 ye g dtwie atret o o t
P Mo uoeq ecm.r nee ovv
_aoca o
ttf c
r wnoEasosrnn t
t ns f
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Page 40 of 51, Rev. 10 N
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- Bases, site specific Data 1
NOTE 1 l-Liquid dose factors, Ar,. for section III.B i
. were developed using the following site specific data.
The liquid pathways involved are drinking water-and fish.
I (U,/D, + U x BF ) f x DFg x RC Ap r
i
=
j liters per year;-maximum age group usage of drinking I
UL
=
water (Reg. Guide 1.109, Table E-5) 5.4; average annual dilution at Cor.owingo intake D,
=
kg per year; maximum age group usage of fish (Reg.
U
=
r Guide 1.109,. Table E-5)
/
bioaccumulation factor for nuclide, i, in freshwater Br. =
fish.
Reg. Guide 1.109, Table A-1, except P-32 8
which uses a_value of.3.0 x 10 pCi/kg per pCi/ liter.
1.14 x 10 = (10' pCifuci x 10 ml/1~+ 8760 hr/yr) 5 5
Ky
=
units conversion factor.
dose conversion factor for nuclide, i, for the age DF 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.
L 3.0 x 10-8 mrem /pci l
l 1.16; reconcentration from PBAPS discharge back RC
=
through PBAPS intake.
and RC were derived from data published in The data for Dw Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos.
50-277 and 50-278) Radioactive Effluent Dose Assessment.
l-September 30, 1976.
All other data except P-32 Enclosure A, Revision 1, BF and DF were'used as given in Reg. Guide'1.109,The P-32 BF and D i
(:
October 1977.
information supplied in Branagan, E.F.,. :Nichols, C.R., and l
"The Importance of P-32.in Nuclear Reactor
- Willis, C.A.,
6/82.
The teen and child dose factors Liquid Effluents", NRC,were derived by'the ratio of the adult bone dose facto j
Reg. Guide 1.109 and Branagan, et al.
I i
l l
i
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'VIII.
(Cent'd)-
NOTE 2 To develop constant R for section IV.C, the following site specific data were used:
~
R[(D/0) = K' F,(r) (DFLg)
+
Y Y
where:
10' pCi/ Ci; unit conversion factor.
K'
=
50 kg/ day;_ cow's consumption rate O,
=
f 330 1/yr; yearly milk consumption by an infant' U,,
=
radioactive decay constant for nuclide of interest, Aj
=
s e c'8 (e.g. 9.97 x 10 s e c'8 for I-131) 4 5.73 x 10 sec'8;= decay constant for removal of A
=
y activity in leaf and plant surfaces
~
stable element transfer coefficient for nuclide of F,
interest, day /litar (e.g. 6.0 x 10'3 day /litar
=
for I-131) fraction of deposited nuclide retained in cow's feed r
=
1.0 for radioiodine; 0.2 for particulates
- grass, ingestion dose factor in infant for nuclide of DFLj=-
interest, mres/pCi -(e.g. 1.39 x 10-2 mram/pci for I-131) 0.6; the fraction of the year the cow is on pasture f,
=
(average of all farms) 0.487; the fraction of cow feed that is pasture i
f,
=
grass while the' cow is on pasture (average.of all farms) 0.7 kg/m ; the agricultural productivity of pasture 2
Y,
=
feed grass 2.0 kg/m ; the agricultural productivity of stored 2
Y,
=
feed 1.73 x 10 sec (2 days);'the transport time from 5
t
=-
pasture, to cow, to milk, to receptor 7.78 x 10' sec (90 days) ; the transport time from c
=
pasture, to harvest, to cow, to milk, to receptor 3
wago ov es av.
l l
hIII.
(Cent',d)-
i Th:ta pathway.
The pathway is the grass-cow-milk ingest ondata we h Bottom Atomic Enclosure A, September Power Station Units 2 and 3 Radioactive Effluent Dose Assessment,All other data were used Guide F
30, 1976.
October 1977.
Revision 1, 1.109, Dose Calculations Licuid Pathway ODCMS 4.8.B.2.1.
due to the actual The equations for calculating the doses liquid effluents release rates of radioactive materials inided in Regulatory were developed from the methodology prov" Calculation of Ann tine Releases of Reactor Effluents for the PurposI", Revision 1, Guide 1.109, i
Compliance with 10 CFR Part 50, Append x of Radiological i
October 1977 and NUREG-0133 "Preparat onEfflue lear Power Plants",
October 1978.
4.8.C.1.2_
_ODCMS 4.8.C.1.1 and Dose Noble Gases due to the actual in gaseous effluents The equations for calculating the doses ided in Regulatory' release rates of radioactive noble gases Routine were developed from the methodology prov" Calculation of An Releases of Reactor Effluents for the Guide 1 109, dix I", Revision 1, f Radiological Effluent Compl'iance with 10 CFR Part 50, Appen October 1977, NUREG-0133 " Preparation oPlants", August Technical Specifications for Nuclear Powerand the at ted in Information Reauested in Enclosure 2 to September 30,
- 1978,
- 17. 1976, mining the air Bauer dated February t
The specified equations provide for de erARY based upon the l
G.
L_ ear to E.
doses in areas at and beyond the SITE BOUND l
1976.
historical average atmospheric conditions.
l ulated by th'e Gross The dose due to noble gas release as ca c l
i than the dose Release Method is much more conservat ve Assuming the hd calculated by the Isotopic Analysis Met o.t_ pose Assessment, release rates given in Radioactive Effluen1976, the values s Release September 30, Method for total body dose rate and skinvalues ca h
times and 5.7 times, respectively, t e the Isotopic Analysis Method.
1 1
Prga 50 of 51, R3v. 10 VIII.
(Cont'd)
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.
For the purpose of calculating this instantaneous dose rate, thyroid dose from iodine-131 through the inhalation pathway will be used.
Since the operating history to date indicates that iodine-131. releases have had the major dose impact, this approach is appropriate.
The value calculated is increased by nine per cent to account for the thyroid dose from all other nuclides.
This allows for
, expedited analysis and calculation of compliance with the requirements of ODCMS 3.8.C.1.
In the event that the plant is shutdown long enough so that iodine-131 is no longer present in gaseous effluents, an Isotopic Analysis Method is available. Since no iodines are present, the critical organ changes from the thyroid to the lung.
ODCMS 4.8.C.2.1 Dese Noble Gases The equations for calculating the doses 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 Complianc~e with 10 CFR Part 50, Appendix I",
Revision 1, October 1977, NUREG-0133 " Preparation of Radiological Effluent Technical Specificati'ons 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, The specified equations provide for determining the air 1976.
doses in areas at and beyond the SITE BOUNDARY based upon'the historical average. atmospheric conditions.
The dose due to noble gus releases as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic 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, respectively, the values calculated by the Isotopic Analysis Method.
i l
1 l
)
Prga 51 of 51, Rsv. 10 VIII.-
(Cont'd)
ODCMS 4.8.C.3.1 Dose. Iodine-131. Iodine-133. Tritium. and Radioactive Material-in Particulate Form l
The equations for calculating the doses due to the actual '
release rates of radioiodines, 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 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", October 1978, and the atmospheric dispersion model presented in Information Recuested in G. Bauer dated to Letter from Georae Lear to E.
February 17, 1976, September 30, 1976.
These equations provide for determing the actual doses based upon the historical average atmospheric conditions.
Compliance with the 10 CFR 50 limits for radiciodines, radioactive materials in particulate form and radionuclides other than noble gases.with half lives greater than eight days is to be determined by calculating the thyroid dose from Since the iodine-131 dose accounts for iodine-131 releases.
the value 92 percent of the total dose to the thyroid, calculated is increased by nine percent to account for the dose from all other nuclides.
In the event that the plant is shutdown long enough so that iodine-131 is no longer present in gaseous effluents, an Since no iodines are Isotopic Analysis Method is available.
the critical organ changes from the thyroid to the
- present, liver.
~
4
APPENDIX A RADI0 ACTIVE EFFLUENTS CONTROLS PROGRAM CONTAINING OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS (ODCMS) AND BASES
.FOR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 REVISION 10 l
4 e
9
RADIOACTIVE EFFLUENTS CONTROLS PROGRAM
- TA8LE 0F CONTENTS 3.8.A--
Definitions ODCM 3.8.A-1 3.8.B Liquid Radwaste Effluents
............... ODCM 3.8.8-1 l
3.8.C Gaseous Effluents ODCM 3.8.C-1 3.8.0 -
40 CFR 190....................... ODCM 3.8.D-1 3.8.E Radiological Environment'al Monitoring ODCM 3.8.E-1
-3.9 Major, Changes to Radioactive Waste Treatment Systems.,, ODCM 3.9-l' 3.10 Reporting Requirements.........,....... ODCM 3.10-1 8 3.8 ODCM Specifications Bases
............... ODCM 8 3.8-1 l
l l
l t
1 1
PBAPS Units 2 and 3 ODCM 3.8 Revision 10
Definitions 3.8.A q
ODCMS 3.8.A Definitions
..................................... NOTE----
The defined terms of this section ap) ear in ca italized ty e and areSpecifications and applicable throughout these Offsite bse Calcu ation Manua Bases...............................................................................
Definition
. Tg.rl0 A FUNCTIONAL TEST is the manual operation or FUNCTIONAL TESTS initiation of a system, subsystem, or component to verify that it functions withir; 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).
Any system designed and installed to reduce GhSEOUSRADWASTE radioactive gaseous effluents by collecting TREATMENT SYSTEM primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
AnINSTRUMENTCALIBRdTIONmeanstheadjustmentof INSTRUMENT CALIBRATION an instrument signal output so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the inr.rument monitors. The known value of the parameter shall be injected into the instrument as close to the primary sensor as practicable.
An INSTRUMENT CHECK is a qualitative determination INSTRUMENT CHECK of acceptable OPERABILITY by observation of.
L instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
l INSTRUMENT FUNCTIONAL TEST An INSTRUMENT FUNC'TIONA to the primary sensor as practicable to verify the proper instrument response, alarm and/or initiating action.
(continued)
PBAPS Units 2 and 3
'0DCM 3.8.A-1 Revision 10
Definitions 1
3.8.A ODCMS 3.8.A Definitions (continued?
l 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 l
l of the utility, its contractors, or vendors. Also I
excluded from this category are persons who enter the site' to service equipment or to make deliveries. This category does i.nclude persons who use portions of the, site for recreational, occupational, or other purposes 'not associated with the plant.
OFFSITE COSE CALCULATION Contains the current methodology and parameters MANUAL used in the calculation of offsite' doses due to radioactive gaseous and liquid effluents and describes the environmental radiological monitoring program.
CFE MELE ODERABILITY A system'. subsystem. division, componem, 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.
l component, or device to perform its spedfied 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.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of c.hannel response when the channel sensnr is I
exposed to a radioactive source.
1 l
t I
I PBAPS Units 2'and 3 ODCM 3.8.A-2 Revision 10 j
I
l Definitions 3.8.A
, =
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EL 7ss -
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UNITS 2 & 3 ROOF VENTS j
EL seset l
h +N ALDOuARY SolLERS s.
N
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z.
EL300 ft.
's.s/
-5 s
24 UNff 1
,' M ML.
UQUID DISCHARGE O
l
"'Ifi: f STRUCTURE l
8 g
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/<,
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4 Figure 3.8.A.1 SITE BOUNDARY (including gaseous and ' liquid effluent release points) t PBAPS Units 2 and 3 ODCM 3.8.A-3
. Revision 10
l Liquid Radwaste Effluents.
3.8.B.1 3.8.8 Liquid Radwaste Effluents ODCMS 3.8.B.1 The concentration of radioactive material released to areas at or beyond the SITE BOUNDARY shall be limited to:
10 times the concentration specified in 10 CFR 20 a.
Appendix B. Table 2. Column 2 for radionuclides other tlan noble gases; and b.
2 X 10"gCi/mi total activity concentration for all dissolved or entrained noble gases.
APPLICABILITY:
At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.
Concentration of A.1 Decrease the release Immediately radioactive material rate of radioactive released to areas at materials to restore or beyond the SITE concentration to BOUNDARY' exceeding within limits.
limits.
A.2 Increase the dilution Immediately flow rate to restore concentration within limits.
2 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 Revision 10 e
Liquid Radwaste Effluents 3.8.B.1 ODCMS REQUIREMENTS I
FREQUENCY ODCMS REQUIREMENT
'0DCMS 4.8.B.1.1 Take a sample of each batch of liquid Prior to each release effluent and analyze for the
' concentration of each significant-
\\
gamma energy peak. Base the release rate on' the circulating water flow rate at the time of discharge.
ODCMS'4.8.B.1.NRecord radioactive concentrations and During each release volume before dilution of each batch of liquid effluent released, the average dilution flow. and length of time over which each discharge occurred. These facility records shall be maintained.
-03 0'S 4.8 E.1.3-Perform radioactive liquid waste In.accordance with sampling and activity analysis.
Table 4.8.B.1 l
Revision 10 PBAPS Units 2 and 3 ODCM 3.8.B-2
~
3.
Liquid Radwaste Effluents 3.8.B.1 Table 4.8.B.; (Page 1 of 2)
Radioactive Liquid V.sste Sampling and Analysis I
SAMPLE TYPE SAMPLE SAMPLE SAMPLE LOWER LIMIT' FREQUENCY ANALYSIS OF DETECTION (LLD)
.(a).(d),(e) d Waste Tank'to be Each batch (b)-
Quantitative 5 X 10 yCi/ml
. released Ana' lysis of Identifiable '
Gamma Emitters I
I-131 1 X 10'5gCi/ml Pro 3ortional Composite 31 days (c)
Fe-55 1 X 10 'gCi/mi of 3atches Tritium 1 X 10-5 Ci/ml Gross Alpha 1 X 10 gC1/ml 1
Proportional Composite 31 days (c)
Sr-89 5.X 10 vC1/ml -
j 8
of Batches Sr-90 5 X 10-8gCi/ml One' Batch 31 days Dissolved 1,X 10'5gC1/ml '
noble gases The Sample Lower Limit of Detection ~ is defined as an a priori '(before (a) 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 l
thoroughly mixed tc assure representative sampling.
A. composite sample is one in which the quantity of the sample is (c) proportional to the quantity of liquid waste discharged and in which the L
metlod of sampling results in a sample representative of the liquids released.,
1 PBAPS Units 2 and 3 DDCM 3.8.B-3 Revision 10
Liquid Rad' waste Effluents 3.8.B.1 Table 4.8.B.1 (Page 2 of 2)
Radioactive Liquid Waste Sampling and Analysis The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides:
-(d)
Mn-54. Fe-59. Co-58. Co-60. Zn-65, Mo'-99. Cs-134. Cs-137. Ce-141. and This list. does 'not mean that only _these nuclides are to'be Ce-144.
Other peaks which are measurable and detected and reported.
identifiable. together with the above nuclides. shall also be identified Nuclides which are below the sample detectable limit for and reported.
the analyses should not be reported-as being present at the sample detectable limit level.
detectable limits higher than required. 'the reasons shall be documented.
The values listed in the Annual Radioactive Effluent Release Report.
l' are believed to be attainable.
Certain mixtures of radionuclides may cause interference in the m'easurement of individual radionuclides at their detectable limit (e) especially if other radionuclides are at much higher concentrations.
Under these circumstances use of known ratios of radionuclides.will' b appropriate to' calculate the levels of such radionuclides.
s
~
l j
r Revision 10 ODCM 3.8.B-4 PBAPS Uni.ts 2 and 3
Liquid Radwaste Effluents
.~
3.8.B.2
~
3.8.B Liquid' Radwaste Effluents.
l l
0DCMS 3.8.B.2 The dose or dose commitment to a MEMBER OF 1BE PUBLIC 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.
s 6.0 mrem to the total body and 5 20.0 mrem to any organ during any calendar year.
APPLICA5ILITY:
At all times.
COMDEt:5:~ E FEASURES C:!OITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME L.
- 5':a'5:ed dose from A.1 Submit a Special 31 days ease of Report to the NRC
- e 5:
- .e naterials '
that identifies
- .'
- ef fluents causes for exceeding
( :.-:: -eaJ1 red limits.. actions taken to reduce releases of radioactive materials in liquid effluents.
corrective actions taken to assure Subsequent releases are within limits.
results of radiological analyses of the-drinking water source. and the radiological impact on the potentially affected drinking water supplies with regard to 40 CFR 141.
Safe Drinking Water Act.
l PBAPS Units 2 and 3 ODCM 3.8.B-5 Revision 10 L
I
Liquid Radwaste Effluents 3.8.8.2 ODCMS REQUIREMENTS FREQUENCY ODCMS REQUIREMENT J
31 days Determine cumulative dose ODCM514.8.8.2.1 contributions in accordance with the methodology and parameters in the ODCM.
4 Revision 10 ODCM 3.8.B-6
-PBAPS Units 2 and 3
c.
?
Liquid Radwaste Effluents l,
3.8.B.3 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.3 The following conditions shall be met:
Dilution water flow rates necessary to satisfy a.
requirements of ODCMS 3.8.B.1 shall be maintained; b.
The gross activity monitor and the flow monitor on the waste effluent line shall be OPERABLE: and The liquid effluent control monitor shall be set in c.
accordance with methodolo y and parameters in the ODCM to alarm and automaticall close the waste discharge valve prior to exceeding imits in ODCMS 3.8.8.1.
APPLICABILITY:
During release of radioactive wastes.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME i
A.
Gross activity monitor A.1 Initiate action to Immediately Oa the waste activity restore monitor to line inoperable.
OPERABLE status.
AND 4
A.2 Analyze two Prior to release independent samples of tank's contents.
AND A.3 Perform independent Prior to release verification of the release rate calculations and discharge line valve line-up using at least two technically qualified members of the facility staff.
i (continued) l PBAPS Units 2 and 3 ODCM 3.8.B-7 Revision 10
c Liquid Radwaste Effluents 3.8.B.3 t
- COMPENSATORY MEASURES -(continued)
CONDITION, REQUIRED COMPENSATORY MEASURECOMPLETION TIME B.
Flow monitor.on the B.1 Initiate action to Immediately t
waste effluent line restore monitor to OPERABLE' status.
1,noperable.
9.D B.2
-..----.. NOTE-------
Pump performance curves may be used to estimate flow.
~
Estimate waste 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> effluent line flow rate.
MS Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter C.
- e: re:. ompensatory C.1 Suspend release of Immediately radioactive effluents
"+::.m and
- n;;;
- ute:1 Completion via this pathway.
! Tre :' Condition A or E ':: re; "i.
01 M1? <.ste'r flow rates nr. satisfying re:a renents'of CD:MS 3.6.B.1.
D.
Liquid radwaste D.1 Explain the reason Prior to effluents radiation the inoperability was submittal of the~
monitors-inoperable not corrected in a next Annual for > 30 days, timely manner in the' Radioactive Annual. Radioactive Effluent Release Effluent Release Report Report.
I
f.
)
f PBAPS Units 2 and 3 ODCM 3.8.B-8 Revision 10
Liquid Radwaste Effluents i.
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 /> during radwaste effluents radiation monitor.
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 /> during effluent flow monitor.
release ODCMS 4:8.B.3.3 Perform INSTRUMENT FUNCTIONAL TEST of31 days liquid radwaste effluents radiation monitor, including OPERABILITY demonstration of the radwaste discharge automatic isolation valve and control ' oom annunciation in response to alarm / trip setpoint being exceeded ard an instrument INOP failure.
Perform SOURCE CHECK of liquid 92 days ODCMS 4.8.B.3.4 radwaste effluents radiation monitor.
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.
ODCMS 4.8.B.3.6 Perform INSTRUMENT CALIBRATION of the 12 months liquid effluents flow monitor.
l l~
i Revision 10 PBAPS Units 2 and 3 ODCM 3.8.B-9 l
\\
l
Liquid Radwaste Effluents 3.8.B.4 3.8.B Liquid Radwaste Effluents Liquid effluent releases shall be processed through one of ODCMS 3.8.8.4 the radwaste subsystems or combination of subsystems listed below:
waste collector filter and demineralizer:
a.
b.
floor drain filt6 :
c.
fuel pool filter demineralizer: or d.
chemical / oily waste cleanup subsystem APPLICABILITY:
Prior to all licuid effluent release (s) whenever the release (s) woulc cause the projected dose, when it is averaged over 31 days to exceed 0.12 mrem to the total body or 0.4 mrem to any organ (combined total from the two reactors at the site).
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.
Liquid waste A.1 Submit a Special 31 days discharged without Report to the NRC required processing.
that includes, an explanation of why liquid radwaste was discharged without required processing, identification of any inoperable equipment or subsystems and the reason for the inoperability', the action taken to restore the inoperable equipment to OPERABLE status, and the action taken to prevent recurrence.
PBAPS Units 2 and 3 ODCM 3.8.B-10 Revision 10
Liquid Sadwaste Effluents 3.8.B.4
=
ODCMS REQUIREMENTS FREQUENCY DDCMS REQUIREMENT 31 days Project doses due to licuid effluent ODCMS'4.8.B.4.1 releases to areas at anc beyond the SITE BDUNDARY in accordance with the methodology and parameters in the ODCM.
92 days Demonstrate OPERABILITY of the waste collector filter and demineralizer and ODCMS 4.8.B.4.2 the floor drain filter by analyzing the liquid processed through the subsystem and determining it meets the requirements of ODCMS 3.8.B.1.
Prior to Demonstrate OPERABILITY of the fuel release of pool. filter demineralizer by analyzingliquid ODCMS 4.8.8.4.3 the liquid processed through the effluents subsystem and determining it meets theprocessed by requirements of ODCMS 3.8.B.1.
this subsystem Prior to Demonstrate OPERABILITY of the release of ODCMS 4.8.B.4.4 chemical / oily waste cleanup subsystem liquid by analyzing the liquid processed effluents
.through the subsystem and determining processed by it meets the requirements of this subsystem 4-00 CMS 3.8.B.1.
Revision 10 ODCM 3.8.B-11 PBAPS Units 2 and 3
Gaseous Effluents 3.8.C.1 3.8.C Gaseous Efflsents The dose rate at or beyond the SITE BOUNDARY due to two reactors at the site shall be limited to the fo ODCMS 3.8.C.1 For noble gases, s 500 mrem per year to the total body and and 5 3000 mrem per year to the skin:
a.
For iodine-131. iodine-133. tritium, and all radionuclides in particulate form with half lives b.
> 8 days, s 1500 mrem per year to any organ.
APPLICABILITY:
At all times.
COMPENSATORY MEASURES REQUIRED COMPENSATORY MEASURE COMPLETI0N TIME l
CONDITION Immediately A.1 Decrease release l
A.
Dose rates at or rates to comply with l
beyond the SITE limits.
BOUNDARY exceed limits l
due to radioactive material in gaseous effluents ODCMS REQUIREMENTS FREQUENCY ODCMS REQUIREMENT In accordance Verify the dose rate due to noble with sampling ODCMS 4.8.C.1.1 gases in gaseous effluents is within and analysis limits in accordance with methods andprogram procedures of the 0DCM.
specified in Table 4.8.C.1 (continued)
Revision 10 ODCM 3.8.C-1
'PBAPS Units 2 and 3
p..
Gaseous Effluents 3.8.C.1 l
ODCMS REQUIREMENTS (continued)
ODCMS REQUIREMENT-FRE0VENCY I
k 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 and analysis all radionuclides in particulate form program with half lives > 8 days in gaseous specified in effluents are within limits in Table 4.8.C.1
'accordance with the methods and procedures of the ODCM.
l 1
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1 1
'PILAPS Units 2 and 3 ODCM 3.8.C-2 Revision 10 l
Gaseous Effluents 3.8.C.1 Table 4.8.C.1 (page 1 of 2)
Waste Sampling and Analysis from
.RadioactiveGaseoupd. and Auxiliary Boiler Exhaust Stack Main Stack, Vent Stack
. l SAMPLE TYPE SAMPLE SAMPLE ANALYSIS.
~ SAMPLE LOWER LIMIT OF FREQUENCY
. DETECTION (LLD)
(a)(d) 4 Grab. Sample 31 days (b)
Quantitative analysis 1 X 10uti/cc(c) of identifiable gamma emitters Grab Sample 92 days Tritium 1 X 10gC1/cc l~
Charcoal Filters 7 days (c)
I-131 1 X 1012 C1/cc(c)
Particulate 7 days (c)
Quantitative analysis 1 -X 10-2'gCi/cc(c) of identifiable gamma Filters emitters I-131 1 X 1012yCi/cc(c) l
(
Particulate 31 days Gross Alpha 1 X 10'22pCi/cc Filters.
(composite of
. weekly filters)
Particulate 31 days Sr-89 1 X 10'22pC1/cc Filters 1 X 10~22 C1/cc (composite of Sr-90 weekly filters) 1X10p#C1/cc(g)
C1/cc (f)
Noble Gas Monitor Continuously Noble Gas Gross # or 1 X 10 (Main Stack).
y Noble Gas Monitor Continuously Noble Gas Gross S or.
1 X 10 C1/cc (Roof Vents) y 4
Auxiliary Boiler Prior to Quantitative analysis 5 X 10 pC1/ml Waste Oil Grab batch of identifiable gamma Sample release for emitters burn PBAPS Unit's 2 and 3 ODCM 3.8.C-3 Revision 10
Gaseous Effluents 3.8.C.1
,~
Table 4.8.C.1 (page 2 of 2)
Radioactive Gaseous Waste Sampling and Analysis ~from l
Main Stack, Vent Stack *. and Auxiliary Boiler Exhaust Stack (a)
The sample lower limit of detection is defined as an a priori (before the fact) limit representing the capability of 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.
(c)
Samples shall be changed at least once per-7 days 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 /> 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 I hour and analyses shall be com)leted 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 1ours are analyzed. the corresponding LLD may be increased by a factor of 10. This requirement does not apply if (1) analysis has shown 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 monitor shows that effluent activity has not increased more than a factor of 3.
(d)
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 a3propriate to calculate the levels of such radionuclides. Nuclides w1ich are below the sample detectable limit for the analyses should not be reported 'as being present at the sample detectable limit level.
l (e)
Un'til completion of Modification 5384. the Reactor Building Vent Exhaust Stacks shall be considered to be the Vent Stacks.
l (f)
After completion of Modification 5386.
l (g) -Until completion of Modification 5386.
1 L
ODCM 3.8.C-4 Revision 10 PBAPS Units 2 and 3
Gaseous Effluents 3.8.C.2 3.8.C Gaseous Effluents 1
The air dose at or beyond the SITE BOUNDARY due tG noble gases in gaseous effluents released from the two reactors at
'~
ODCMS 3.8.C.2 the site shall be limited to the following:
For gamma radiation, s 10 mrad during any calendar f.
a.
quarter; For beta radiation, s 20 mrad during any calendar b.
l quarter:
For gamma radiation. s 20 mrad during any calendar year; c.
l-and l
For beta radiation, s 40 mrad during any calendar year.
d.
4:FL]CASILITY:
At all times.
- G7ENSt.TDRY MEASURES REQUIRED COMPENSATORY MEASURE-COMPLETION TIME CONDITION A.
Calculated air dose at A.1 Submit a Special 31 days or Deyond the SITE.
Report to the NRC that identifies EOUNDARY from causes for exceeding radioactive noble limits, corrective gases in gaseous actions taken to effluents exceeds reduce the releases,
- limits, and corrective actions to. assure that subsequent releases are within limits.
Revision 10 00CM 3.8.C-5 PBAPS Units 2 and 3 t
Gaseous Efflu;nts 4
3.8.C.2 ODCMS REQUIREMENTS FREQUENCY ODCMS REQUIREMENT i
ODCMS 4.8.C.2.1l Determine cumulative dose 31 days.
contributions for noble gases in accordance with the methodology and parameters in the ODCM.
i l
l l
l 1
l l
l 1
I F
~
i l
Revision 10 ODCM 3.8.C-6 PBAPS Units 2 and 3' f
/
1 Gaseous ' Effluents 3.8.C.3 3.8.C - Gaseous Effluents-
- 0DCMS' 3.8.C.3 The dose to a MEMBER OF THE PUBLIC at or beyond the SITE B0UNDARY 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.
s 15 mrem during any calendar quarter: and b.
s 30 mrem during any calendar year.
APPLICABILITY:
At all times.
COMPENSATORY-MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME
~
A..' Calculated dose from A.1L Submit a Special 31 days
.the release of Report to the NRC iodine-131, that. identifies iodine-133, tritium causes for exceeding and radionuclides in.
limits, corrective 3 articulate form, with actions'taken, and 1alf-lives > 8 days in proposed corrective gaseous effluents actions to assure exceeds limits.
that subsequent-releases are within limits.
i 4
i S.
PBAPS Units 2 and 3' ODCM 3.8.C-7 Revision 10
i Gaseous Effluents 3.8.C.3
~
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.3.1 Determine cumulative dose 31 days contributions 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.
c I
~
PBAPS Units'2 and 3 ODCM.3.8.C-8
. Revision 10
c Gaseous Effluents 3.8.C.4 3.8.C Gaseous Effluents ODCMS 3.8.C.4 The following conditions shall be met:
Main stack dilution flow shall be = 10.000 cfm:
a.
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:
One vent stack iodine filter and one main Stack iodine c.
filter and one vent stack parti.culate 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.
.............................N0TE---------------------------
Until completion of Modification 5384, the vent stack nobis gas monitors, filters, and flow rate monitors shall be considered to be the reactor building exhaust vent noble gas monitors, filters. and flow rate monitors, respectively.
. APPLICABILITY:
During release of radioactive wastes.
PBAPS Units 2 and 3-ODCM 3.8.C-9 Revision 10
o Gaseous Effluents':
3.8.C.4
' COMPENSATORY MEASURES.
...............................-------NOTE---------.--..-.-------..
I Separate condition entry is allowed for each instrument.
1 CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME I
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 /> I
)
stack noble gas independent grab monitor inoperable.
samples from the.
AND 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 /> thereafter One required main stack noble gas AN_Q
]
monitor inoperable.
A.2
NOTE---------
Perform independent verification of'the release rate' calculations using at least two technically qualified members of o
I
~
the facility staff.
I 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
_ gross activity.
(continued) i~
l
~
i l
l l
PBAPS Units 2 and 3-00CM 3.8.C-10 Revision 10 i.
Gaseous Effluents
/
3.8.C.4 (continued)
' COMPLETION TIME lC0MPENSATORY MEASURESREQUIRED COMPENSATORY MEASURE CONDITION Immediately Collect samples from B.1 One required vent the affected effluent B: ' stack iodine filter release pathway inoperable.
continuously with auxiliary sampling equipment such that QB each sample period Gne required vent duration is approximately 7 days.
stack particulate filter. inoperable.
MD 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after OB Analyze collected end of each B.2 One recu1 red main samples.
sampling period sta:t 1odine filter
'r:re-atle.
'a + re:v: red main sta:. : articulate
' ';e noperable.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Estimate flow rate C.1 C
e-/ red vent from the affected ANQ 3:.
- c.. rate effluent release
.:- :naperable.
pathway.
Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter i_
One re:atred main sta:L 'ica rate mor. tcr inoperable.
Immediately Initiat? action to D.1 O.
Main off-gas stack re-establish main dilution flow off-gas stack flow
< 10.000 cfm.
a 10.000 cfm.
~
(continued)
/
I Revision 10 ODCM 3.8.C-11 PBAPS Units 2 and 3
t Gaseous Effluents p
3.8.C'.4 4
COMPENSATORY M'EASURES (continued) l CONDITION-REQUIRED COMPENSATORY MEASURE COMPLETION TIME E. _One or more required E.1 Explain the reason Prior to radioactive ga'seous inoperability was not submittal of effluent monitoring corrected in a timely next Annual instrumentation manner in the Annual Radioactive channels inoperable Radioactive Effluent Effluent Release
-for > 30 days.
Release Report.
Report ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY DDCMS 4.8.C.4.1'
. Perform 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.
ODCMS 4.8.C.4.2
NOTE-----------------
The requirement to perform an INSTRUMENT CHECK of the reactor building exhaust vent sample. flow rate monitors is only applicable until completion of Modification 5384.
Perform INSTRUMENT CHECK of the vent stack and the main stack flow rate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4
)
monitors, and the Unit 2 reactor
. buildirig exhaust vent samole flow rate monitor.
ODCMS 4.8.C.4.3
NOTE---------------
i This requirement is only applicable until completion of Modification 5386.
Perform INSTRUMENT CHECK'of the main 7 days stack sample flow rate monitor.
(Continued)
PBAPS Units 2 and 3 ODCM 3.8.C-12 Revision 10
Gaseous Effluents 3.8.C.4
~
ODCMS REQUIREMENTS (continued)
ODCMS REQUIREMENT FREQUENCY
~
ODCMS 4.8.C.4.4 Perfonn INSTRUMENT FUNCTIONAL TEST of 92 days 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.
ODCMS 4.8.C.4.5
NOTE-----------------
This requirement is caly applicable until completion of Modification 5386.
Perform INSTRUMENT FUNCTIONAL TEST of 184 days the main stack sample flow line Hi/Lo pressure switches.
(Continued) f PBAPS Units 2 and 3 ODCM 3.8.C-13 Revision 10
Gaseous Effluents 3.8.C.4 t
ODCMS REQUIREMENTS (continued)
ODCMS REQUIREMENT FREQUENCY 18 months ODCMS 4.8.C.4.6 Perform INSTRUMENT CALIBRATION of the
, vent stack and main stack noble gas AND radiation monitors with a known radioactive source positioned in a
NOTES-----
reproducible geometry with respect to
- 1. Only the sensor, applicable to vent stack monitors until-completion of Modification 5384.
- 2. Only applicable to main stack radiation monitors until.
completion of Modification 5386.
~
12 months (continued) 4 PBAPS Units _2 and 3 ODCM 3.8.C-14 Revision 10:
Gaseous Effluents 3.8.C.4
~
4 ODCMS REQUIREMENTS (continued)
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.4.7 Perform INSTRUMENT CALIBRATION of the vent. stack and main stack f'ow rate 18 months monitors.
AND
..... NOTES-----
- 1. Only
. applicable to vent stack flow monitors until completion of Modification 5384.
- 2. Only applicable to main stack flow rate monitors
~
until completion of Modification 5386.
12 months (continued)
PBAPS Units 2 and 3 ODCM 3.8.C-15 Revision 10 k
.---.-..--..-.-.a
Gaseous Effluents 3.8.C.4 ODCMS REQUIREMENTS (continued)
ODCMS R'EQUIREMENT FRE0VENCY ODCMS 4.8.C.4.8 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack iodine and particulate sample flow rate monitors.
..... NOTES-----
1.' Only
. applicable to vent.
stack sample flow rate monitors until completion of Modification 5384
- 2. Only applicable' to main stack sample flow rate monitors-until completion of Modification 5386.
12 months
NOTE-----------------
ODCMS 4.8.C.4.9 This requirement is only applicable until completion of Modification 5386.
Perform INSTRUMENT CALIBRATION of the 24 months main stack. sam)le flow-line Hi/Lo pressure switcles.
i P8APS Units 2 and 3 ODCM 3.8.C-16 Revision 10 a
r Gaseous Effluents 3.8.C.5
\\
\\
3.8.C Gaseous Effluents t
Gaseous effluents shall be processed through the Gaseous Waste Treatment System described below prior to discharge:
ODCMS 3.8.C.5 Steam jet air ejector discharge shall be processed through the recombiner, holdup pipe, off-gas filter.. and a.
off-gas stack:
l Mechanical vacuum pump and gland steam exhauster discharge shall be processed through the off-gas stack:
b.
Reactor, turbine, radwaste. and recombiner building atmospheres shall be processed through permanently or c.
l temporarily installed equipment in the appropriateb exception of the following unmonitored exhausts:
- 1. Recirculation M-G set and reactor building cooling water equipment rooms:
l
- 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.
.............................N0TE---------------------------
Until completion of Modification 5384, the Reactor Building Ventilation Exhaust Stacks shall be considered to be the Vent Stacks.
i APPLICABILITY:
At all times.
Revision 10 ODCM 3.8.C-17 PBAPS Units 2 and 3
Gaseous Effluents
-3.8.C.5 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.
Gaseous waste A.1 Submit a Special 31 days discharged without Report to the NRC required processing.
that explains the reasons gaseous radwaste w6s discharged without-processing.
identifies inoperable equipment -or subsystems and the reasons.for the inoperability.
identifies actions taken to restore the inoperable equipment to OPERABLE status.
and actions taken to prevent a recurrence.
l ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.5.1 Project doses due to gaseous effluent 31 days releases at and beyond the SITE BOUNDARY-in accordance with the methodology and parameters in the ODCM.
ODCMS --4.8.C.5.2
' Collect and analyze air samples from 31 days each' building area with an unmonitored exhaust.
(continued)
PBAPS Units 2 and 3 00CM 3.8.C-18 Revision 10 j
Gase6us Effluents 3.8.C.5 ODCMS PE0VIREMENTS (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 ODCHS 3.8.C.1
~
PBAPS Units 2 and 3 DDCM 3.8.C-19 Revision 10 n
i
.i.
Gaseous Effluents 3.8.C.6 4
\\
3.8.C Gaseous Effluents
' 00 CMS 3.8.C.6 PURGING.of the primary. containment shall be:
Through the' Standby Gas Treatment System whenever a.
and primary containment is required to be OPERABLE:
Through the Reactor Building Ventilation Exhaust System b.
or the Standby Gas Treatment System whenever primary containment is not required to be OPERABLE.
APPLICABILITY:
Auring PURGING'of the primary containment.
COMPENSATORY MEASURES REQUIRED COMPENSATORY MEASURE COMPLETION TIME CONDITION A.
Requirement of-A.1 Suspend PURGING.
Immediately DDCMS 3.8.C.6 not met.
'0DCMS REQUIREMENTS FREQUENCY ODCMS REQUIREMENT Prior to ODCMS 4.8.C.6.1 Verify primary containment PURGING is PURGING primary through required effluent release containment pathway.of ODCMS 3.8.C.6.
l
-i Revision 10 PBAPS Units 2 and 3 ODCM 3.8.C-20
Gaseous Effluents 3.8.C.6 I
i 3.8.C Gaseous' Effluents 3.8.C.7. Burning of radioactive waste oil shall be allowed:
ODCMS In accordance with the requirements of 10CFR20.2004.
a.
Through the Auxiliary Boilers (Common) wit b.
for radioactive effluents.
With the radioactive content of the oil determined prior
^
c.
to incineration.
With the radioactive effluents from this pathway summed with other effluents from the site and reported to the d.
Commission in the Annual Radioactive Effluent Rele Report.
J' APPLICABILITY: At all times l COMPENSATORY MEASURES COM
' REQUIRED COMPENSATORY MEASURE CONDITION 31 days Submit a Special Report to the A.1 A.
Gaseous ' effluents NRC that explains the. reasons discharge Without' gaseous radwaste was discharge required processing' without processing. identifies inoperable equipment or or Gaseous effluents-subsystems'and the reasons for exceed limits specified the inoperability, identifies in 3.8.C.3 actions taken to restore the inoperable equipment to OPERABLE status, and actions taken to prevent a recurrence.
l-CDCM5 REQUIREMENTS FREQUENCY ODCMS REQUIREMENT.
l Each Batch Project doses due to gaseous effluent Incinerated releases. at or beyond the SITE BOUNDARY.
00 CMS 4.8:C.7.1 Each Batch Determine dose and dose rate contributions-Incinerated
~for radionuclides in particulate form with ODCMSc 4.8.C.7.2 half lives > 8 days in accordance with the methodology and parameters in ODCM Section IV.F.
Revision 10 ODCM 3.8.C-21 PBAPS Units 2 and 3 3
40 CFR 190 3.8.D.1 i
l l ODCMS REQUIREMENTS (continued) 3.8.D 40 CFR 190 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 sources within 8 kilometers shall be:
a.
s 25 mrem to the total body or any organ (except the thyroid); and b.
s 75 mrem to the thyroid.
1 APPLICABILITY:
At all times.
COMPEn5'T:2.v MEASURES
- 'C'ITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.
'. ':..~3.ed dose to a
NOTE-------------
?"-i-
- THE PUBLIC Calculations.shall includa
+ :
- w ce the direct radiation
- ;;e:1fied in contributions from reactor
- .. 3 'E B.2 or units and outsids sLcrage
- v'. : E.C.2 or tanks.
- .:v: :. E C.3.
c A.1 Calculate dose or immediately dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources within 8 kilometers to determine if specified limits were exceeded.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.D-1 Revision 10
40 CFR 190 3.8.D.1 COMPENSATORY MEASURES (continued)
CONDITION
~ REQUIRED COMPENSATORY MEASURE COMPLETION TIME B.
Calculated dose or B.1
NOTE---------
dose connitment Estimates of.
exceeds specified radiation exposure shall include the limits of 00 CMS 3.8.D.I.
effects of all effluent pathways and direct radiation including releases covered by this Special Report.
Submit a Special 31 days Report to the NRC that includes the corrective actions taken to prevent recurrence, the schedule for achieving conformance with required limits, estimates of radiation exposure to a MEMBER OF B E PUBLIC for the calendar year, descriptions of the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure level or concentrations.
BlD (continued) l t
PBAPS Units 2 and 3 ODCM 3.8.D-2 Revision 10
1 40 CFR 190 3.8.0.1 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B.
(continued) _
B.2
NOTES--------
- 1. Only applicable if l
I the release-condition resulting in
' violation of 40 CFR 190 has not I
been corrected.
l
- 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 31 days a variance in accordance with 40 CFR 190 in the Special Report to the NRC.
l a
00 CMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.D.1.1 Determine cumulative dose In accordance contributions from liquid'and gaseous with ODCM effluents in accordance with methodology and parameters in the l
ODCM.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.D-3 Revision 10 l
40 CFR 190 3.8.0.1
~
'0DCMS REQUIREMENTS (continued)
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.D.1 2 Determine cumulative. dose In accordance contributions from direct radiation with ODCM from the reactor units and from radwaste storage in accordance with methodology and parameters in the ODCM.
s t
L.
l l
t g
PBAPS Units 2 and 3 ODCM 3.8.D-4 Revision 10 1
Radiological Environmental Monitoring 3.8.E.1 3'
~
3.8,E Radiological Environmental Monitoring Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in ODCMS 3.8.E.1 Table 4.8.E.1 and the ODCM.
APPLICABILITY:
At all times.
COMPENSATORY MEASURES REQUIRED COMPENSATORY. MEASURE COMPLETION TIME
. CONDITION A.
Milk samples A.1 Identify locations 31 days for obtaining permanently replacement samples unavailable from any and add them to of the sample radiological
'1ocations li.sted in environmental the ODCM.
monitoring program.
Delete locations from which samples are unavailable.
AND A.2 Identify in the Prior to Radioactive Dose submittal in Assessment Report the next Radioactive c
cause of the Oose Assessment unavailability of Report samples and new locations for obtaining samples and include in the report revised figures and tables for the.00CM reflecting the new locations.
(continued)-
Revision 10 00CM 3.8.E-1 PBAPS Units 2 and 3
.j
l Radiological Environmental Monitoring 3.8.E.1
~
COMPENSATORY MEASURES (continued) i CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIMC B.
Level of radioactivity B.1 Submit a Special 01 days after as a result of plant Report to the NRC end of affected l
effluents in an which incluCas an calendar quarter environmental sampling evaluation o1 any medium at one or more release conditions.
locations specified in environmental the ODCM exceeds the factors. or other reporting levels of aspects which caused Table 3.8.E.1 when the reporting level averaged over the of Table 3.8.E'.1 to calendar quarter.
be exceeded and the corrective actions to QR be taken to reduce radioactive effluents Level of radioactivity so that the potential as a result of plant annual dose to a effluents in an -
MEMBER OF THE PUBLIC environmental sampling is less than the medium at one or more calendi, year locations specified in reporti19 level of the ODCM exceeds the Taale 3.8.E.1.
reporting levels of
. Table 3:8.E.1 when averaged over the calendar quarter and' more than one l
radionuclide from l
Table 3.8.E.1 is detected and the equation in ODCMS 4.8.E.1.2 is satisfied.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.E-2 Revision 10 w
Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME I
C.
Radionuclides other C.1
NOTE--------
than those in Only required if the Table 3.8.E.1 detected radionuclides and the potential detected are the annual dose to a result of plant MEMBER OF THE PUBLIC effluents.
is greater than or equal to the calendar year limits of
' Submit a Special 31 days after ODCMS 3.8.B.2. or Report to the NRC end of affected ODCMS 3.8.C.2 or which includes an calendar quarter ODCMS 3.8.C.3. or evaluation of any ODCMS 3.8.D.1.
release conditions, environmental factors, or other aspects which caused l
the reporting level of Table 3.8.E.1 to be exceeded: and the corrective actions to be taken to reduce radioactive effluents so that potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year reporting level of i
Table 3.8.E.1 AND (continued)
PBAPS Units 2 and 3 ODCM 3.8.E-3 Revision 10
Radiological Environmental Monitoring 3.8.E.I
~
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY. MEASURE COMPLETION TIME-C. -(continued)
C'. 2
NOTE--
Only required if the radionuclides detected are not the result of plant effluents.
Describe the Prior to condition in the submittal of Annual Radiological next Annual Environmental Radiological Operating Report.
Environmental Operating Report 0..
Requirements of D.1 Prepare and submit.
Prior to ODCMS 3.8.E.1 not met.
ir) the Annual submittal of Radiological next Annual Environmental Radiological l.
Operating Report, a Environmental description of the Operating Report reasons for not conducting the radiological environmental monitoring program as required and the actions taken to.
prevent recurrence.
i e
A
-PBAPS Units.2 and 3 0DCM 3.8.E-4 Revision 10
~
L
Radiological Environmental Monitoring 3.8.E.1
~
ODCMS REQUIREMENTS FREQUENCY ODCMS REQUIREMENT ODCMS 4.8.E.1.1
NOTES--------------
- 1. Deviations are permitted from the required sampling schedule if 1
specimens are unobtainable due to hazardous conditions. seasonal unavailabilities. malfunction of automatic sampl.ing 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 with monitoring sampl.es at the locations Table 4.8.E.1 and analyze as specified in Table 4.8.E.1 and the ODCM.
1 f
3'M5 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)
+
reporting level (1) concentration (2) 2 1.0 reporting level (2)
Revision 10 ODCM 3.8.E-5 PBAPS Units 2 and 3 e
i 1
)
Radiological Environmental Monitoring 3.8.E.1
,j Table 3.8.E.1 (page 1 of 1)
Reporting Levels for Radioactivity Concentration in Environmental Samples Reporting Levels f
ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS (pCill)
PARTICULATE OR (pCi/kg. wet)
(pC1/1)
(pC1/kg. wet)
GASES (pC1/r.'.')
[.
l H3 20.000*
Mn-54 1.000 30.000 Fe-59 400 10,000 Co-58 1.000 30.000 l'
Co-60 300 10.000 Zn '300 20.000 Zr-Nb-95 400 3
100 I 131 0.9 Cs-134 30 10 1.000 60 1.000 t
Cs 137' 50 20 2.000 70 2.000 i
300 Ba-La 140 200
- For drinking water samples. This is 40 CFR part 141 value.
PBAPS Units 2 and 3 ODCM'3.8.E-6 Revision 10 g
I
Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 1 of 3)
Radiological Environmental Monitoring Program SAhPLING AND TYPE AND NUMBER OF SAMPLES AND SAMPLE LOCAfl0N(a)
COLLECTION FREQUENCY OF EXPOSURE PATHWAY AND/OR SAMPLE FREQUENCY ANALYSIS (b),(c)
At least 40 routine monitoring stations either Every 31 days Every 31 days (Gamma dose) 1.
Direct with two or more dosimeters or with one Radiation (e) instrument for measuring and recording dose or rate continuously to be placed as follows: 1) or an inner ring of stations in the general ares Every 92 days Every 92 days of the SITE BOUNDARY and an outer ring in the 3 to 6 mile range from the site. A station is (Gamma dose) in each sector of each ring except as dictated by local geography. The bat W e of the stations are in special interest areas such as population centers,- nearby residences, schools and in areas to serve as control stations.
j 1
2.
Airborne Continuous Radiciodine Radiciodine and Samples from 5 locations:
sampler canisters:
3 sanples from close to the SITE BOUNDARY operation with I-131 analysis Particulates locations (in different sectors) of the sanple every 7 days a.
collection every highest calculated annual average ground Particulate 7 days or level D/2.
required by dust sampler: (f) b.
1 sample from the vicinity of a conmJnity
- loading, gross beta whichever is radioactivity having the highest calculated annual more frequent, analysis average ground level D/Q.
following j
i filter change; 1 sample from a controt location unlikely ganma isotopic i
c.
I to be affected by the plant.
analysis of composite (by location) 92 days 3.
Waterborne Conposite (b)
Ganna isotopic a.
Surface a.
1 sample upstream sample over 31 (d) analysis day period.
every 31 days.
b.
1 sample downstream Composite for tritium analysis at least every 92 days (continued)
Revision 10 PBAPS Units 2 and 3 ODCM 3.8.E-7
Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 2 of 3)
- Radiological Environmental Monitoring Program EXPOSURE PATHWAY
. MUMBER OF SAMPLES AND SAMPLE LOCATION SAMDLI'.G AND TYPE ANO COLLfETIch FREQUENCY OF AND/0R SAMPLE FRFJUENCY ANALY$l$
(b),(c) 3.
Waterborne (cont'd) 1 sample of each of 1 to 3 of the nearest Composite (b)
Composite for water supplies that could be effected by sample over 31 gross beta and
- b. Drinking a.
day composite gasmus (d) period isotopic l
its discharge, analyses every j
b.
i sample from a control tocation.
j 31 days.
Composite for l
tritium l
analysis at l
i teast every 92 days j
l 1 sample from downstream area with existing or Every 6 months Genus isotopic l
(d) analysis
- c. Sediment from potentist recreationat value.
every 6 months j
Snoretine
'I Ingestion samples from milking animals in 3 Every 14 days Gausna isotopic locations within 3 miles distance having when animals are (d) analysis
- s. with a.
the highest dose potential.
on pasture, or 134, 137 Cs every 31 days at by chemical b.
1 sample from milking animals at a other times.
separation every 92 days.
controt location (Leslikely to be affected 1 131 analysis by the plant).
of each
- sample,
- 1. sample of each casusercially and sample in Gausne isotopic recreationally (sportant species in season, or every '(d) analysis b.
Fish a.
6 months if they on edible vicinity of discharge point when portions.
are not avaltable.
- seasonst, b.
1 sample of same species in areas not influenced by plant discharge then -
available.
Sampits of 3 different kinds of broad Every 31 days-Gamuna isotopic tesf vegetation grown nearest offsite idsen available (d) and I 131
- c. Food a.
garden of highest annual average ground if milk sampling analysis Products level D/Q if afsk sampling is not is not performed.
performed.
b.
1 sample of each of the similar broad Every 31 days Gasuna isotopic
~
' leaf vegetation grown 15 - 30 km distant
' when available (d) and 1 131 in the toast prevalent wind direction if if milk sampling analysis milk sampling is not performed.
Is not performed PBAPS Units 2 and 3 ODCM 3.8.E-8 Revision 10
F l
Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 3 of 3)
I
' Radiological Environmental Monitoring Program NOTES (a) Fixed sosple locations are shown in the Offsite Dose Calculation Manual, Table VII.A.1 and Figures v!!.A.1, V11.A.2, and V11.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.sultable alternative media and locations may be chosen for the particular pathway in qwstion. Such necessary deviations are reported in the Annual Environmental Radiological Operating Report.
l (b) Composite sanples 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) Sanple collection frequencies are defined as follows:
7 days 7 calendar days 1 2 days 14 days 14 calendar days 13 days 31 days 31 calendar days 1 8 days 92 days 92 calender days 110 days 6 months 6 calendar months 1 20 days (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.
I (f) If the gross beta activity in air attributable to plant operation is greater than ten times the yearly mean of control samples, gasuna isotopic analysis shall be performed on the individual samples.
1 1
l 1
I i
PBAPS Units 2 and 3 ODCM 3.8.E-9 Revision 10
Radiological Environmental Monitoring 3~.8.E.1 Table 4.8.E.2 (page 1 of 1)
DETECTION CAPABILITIES FOR [WIRONMENTAL SAMPLE ANALYs!S*
Lower Limit Of Detection (LLD)*
ANALY$15-WATER AIRg0RNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT (pci/t)
(pC1/m')
(pci/kg, wet)
(pci/L)
(pci/kg, wet)
(pci/kg, dry) l Gross iets 4
0.01 f
H-3 2,000 130 Mn-54 15 260 Fe 59 30 i
130 Co-58,60 15 260 2n-65 30 2r-95 30 Mb-95 15 1
' 60 0.07 I 131 Cs 134 15 0.05 130 15 60 150 Cs 137 18 0.06 150 18 80 180 l
'O Ba 140 60 15 La 140 15 Other peaks that are l
This list does not mean that only these nuclides are to be considered. Identifiable at (a) and reported in the Annual Radiological Environmental Operating Report.
f i
The LLD is defined, for purposes of these controls, as the smeltest concentration of rad onct ve d with meterial in a sample that will yield a net count (above system background (b)
"real" signal.
For a particular measurement system (which may include radiochemical separation):
4.66s.
LLO s E V 2.22 T exp (-AAt) l
)
LLD is the a priori tower limit of detection as defined above (as picoeuries per unit mess or vo une,
Where:
k sample as 5,is the standard. deviation of the background counting rate or of the counting rate of blan appropriate (as comts per minute),
E is the counting efficiency (as comts per disintegration),.
V is the saepte size (in mits of mass or votuee),
2.22 is the raaber of disintegrations per minute per picoeurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the porticular radionuclide, and At for the environmental saeptes is the elapsed time between sample collection (or and of the sae cettection period) and time of 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) timit representing the capability of a measurement system and not as an after :he fact limit for a particular measurement.
i ditions.
Anotyses shall be performed in such a menner that the stated LLDs will be a f i
- clides, i.
or other uncontrottable circumstances may render these LLDs machievable.f actors sh Revision 10 ODCM 3.8.E-10
'PBAPS Units 2 and 3
Radiological Environmental Monitoring f..
3.8.E.2-4 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 MEASURE COMPLETION TIME
).
A. ' Land use census A.1 Add the new location 31 days j
identifies a location to the radiological v.h1 :' v: elds a environmental ca':/'a:ec dose or monitoring program.
- e :ccr : ment (via I
th+ :3 e exposure AND I
- : *.
- 4 5..
that is at e2;; :21 creater than
~
S ~. : 3*. i on f rom whiwh
~.;. are currently 53 :
- +".;1 ;tained in c:::-:3":e with CD:: 2 E.E.1.
(continued) s I
PBAPS Units 2 and 3 ODCM 3.8.E-11 Revision 10
Radiological Environmental Monitoring
~
3.8.E.2 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETIDN TIME A.
(continued)
A.2
NOTE---------
The indicator sampling location having the lowest calculated dose or dose commitment (via the same exposure may be pathway)from the deleted
' radiological environmental monitoring program after October 31 of the year in which land use census was conducted.
Identify the new Prior to' location in the submittal of the Radioactive Dose next Radioactive Assessme'nt Report and Dose Assessment
(
include the revised Report figures and tables for the ODCM reflecting the new location.
B.' Land use census B.1 Identify the new Prior to identifies a location location in the submittal 'of the which yields a Radioactive Dose next Radioactive calculated dose or Assessment Report.
Dose Assessment Report dose commitment that is greater than values currently being calculated in ODCMS 3.8.C.3.
PBAPS Units 2 and 3.
-ODCM 3.8.E-12 Revision 10
Radiological Environmental Monitoring 3.8.E.2 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.2.1 Conduct a land use census by a door-12 months to-door survey or by consulting local agriculture authorities or by some other appropriate means.
1 l
J 4
s-PBAPS Units 2 and 3 ODCM 3.8.E-13 Revision 10
Radiological Environmental Monitoring
~
3.8.E.3 3.8.E ~ Radiological Environmental' Monitoring Anal {sesshallbeperformedonradioactivematerials 00 CMS' 3.8.E.3 supp.ied as part of the EPA Environmental Radioactivity Intercomparison Studies Program, or another Interlaboratory Comparison Program approved by the NRC.
i APPLICABILITY:
At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A.
Fe: r ements of A.1 Include corrective Prior to CC:M; 3 8.E.3 not met.
actions to prevent submittal of recurrence'in the next Annual Annual Radiological
~ Radiological Environmental Environmental.
Operating Report.
Operating Report-ODS ;i. 5::EMD.TS ODCMS REQUIREMENT FREQUENCY I-ODCMS
- 5 E.3.1 Include a sumary of the results of In accordance the Interlaboratory Comparison Program with Technical in the Annual Radiological-Specification Environmental Operating Report.
- 5. 6. 2,
PBAPS Units 2 and 3 ODCM 3.8.E-14 Revision 10 e
Major Changes to Radioactive Waste Treatment 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.
00 CMS 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 initipted 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:
- b. Sufficient detailed information to totally support the reason for the changa 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 l
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
- f. Documentation of the fact that the change was reviewed and found acceptable by the PORC.
- 2. The change shall become effective upon review and acceptance by both the PORC and NRB.
(continued)
PBAPS Units 2 and 3 ODCM 3.9-1 Revision 10
Major Changes to Radioactive Waste Treatment Systems 3.9 o
3.9 Major Changes to Radioactive Waste Treatment Systems ODCMS 3.9.2 (continued) b.
Commission initiated changes:
- 1. The ap)licability of the change to the facility shall De determined by the PORC after consideration of the facility design.
The licensee shall provide the Commission with 2.
written not'ification of its determination of applicability including any necessary revisions to reflect facility design.
- 3. The change shall be reviewed by the NRB at its next regularly scheduled meeting.
- 4. The change shall become effective on a date proposod by the licensee and confirmed by the Commission.
ODCMS 3.9.3
" Major Changes".to radioactive waste systems shall include the following:
Changes in process equipment. components. structures, a.
and effluent monitoring instrumentation from those described in the Final Safety Analysis 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:
Changes in system design which invalidate the accident c.
analysis as described in the SER: and d.
Changes in system design that result in a significant increase in occupational exposure of operating personnel.
P8APS Units 2 and 3 ODCH 3.9-2 Revision 10
5 Reporting Requirements 3.10 3.10 Reporting Requirements ODCMS 3.10.1 Annual Radioloaical Environmental Doeratina Reoort The Annual Radiological Environmental Operating Report shall be submitted in accordance.with tie 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 4.ncluding sampling methods for each sample type, size, and physical characteristics of each sample type, sample preparation methods, and measuring -
equipment used;
- b. At least two maps of all sampling locations keyed to a table giving distances and directions from the midpoint between reactor vents:
- c. Results of the land use census required by ODCMS I
)
3.8.E.2: and
-d.
Results of the Interlaboratory Comparison Program require'.,y ODCMS 3.8.E.3 and discussion of all analyses-in whic' the LLD' required by Table 4.8.E.2 was not achievable.
ODCMS 3.10.2 Radioactive Effluent Release Reoort 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. Coritainer volume:
- 2. Total curie quantity (specify whether determined by measurement or estimate);
3.
Principal radionuclides (specify whether determined by measurement or estimate):
(continued)
PBAPS Units 2 and 3 ODCM 3.10-1 Revision 10
L Reporting Requirements 3.10 I
l
...-3.10 Reporting Requirements ODCMS 3.10.2 Radioactive Effluent Release Reoort (continued) 4.
Source of waste and processing employed (e.g..
dewatered s)ent resin, compacted dry waste, evaporator acttoms); and
- 5. Type of container (e.g., LSA. Type A Type B. Large
-Quantity).
- b. A list a.nd description of unplanned releases from the site to areas at or beyond the SITE BOUNDARY of l
~
radioactive materials in gaseous and liquid effluents l
made during the reporting period.
- c. Changes made during the reporting period to the Offsite Dose Calculation Manual (0DCM) 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.
l
'0DCMS 3.10.3 Radiation Dose Assessment Reoorts The radiation dose assessment reports shall be submitted within 120 days after January 1 of each ' year.
The Radiation Doie Assessment Report shall include an annual summary of hourly meteorological data collecte.d over This annual summary may be either in i
the previous year.
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.
In lieu of submission with the first half year Radioactive Effluent Release Report, ~the l
licensee will retain 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 assessment of the l
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 (continued) l PBAPS Units 2 and 3 ODCM 3.10-2 Revision 10 J
^
~
Reporting Requirements 3.10 3.10 Reporting Requirements-I ODCMS 3.10.3 Radiation Dose Assessment 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 determining the gaseous pathway doses. Approximate methods are acceptable. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (0DCM).
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.
1 Environmental Radiation Protection Standards for Nuclear 4
Power Operation.
Guidance for calculating the dose contribution from liquid and gaseous effluents are g'iven in Regulatory Guide 1.109. Revision 1. October 1977.
If dos.es from plant effluents do not exceed twice the Appendix I limits. a statement to that effect shall constitute a 40 CFR 190 assessment.
PBAPS Units 2 and 3 ODCM 3.10-3 Revision 10
a-ODCM Specifications Bases B 3.C B 3.8 O L i SPECIFICATIONS BASES General It is expected that releases of radioactive material in effluents will be kept 20.1302 of 10 CFR. Part I at small fractions of the limits specified in SectionAt the same time, the lic compatible with consideration of health and safety. to assure that the public 20.
is provided a dependable source of power even under unusual o 3orarily result in releases higher than such small 20.1302 of 10 CFR.
j fractions, but still witain the limits specified in SectionIt is expected that in Part 20.
unusual operating conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.
Licuid Radwaste Effluents Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to areas at and beyond the SITE' l BOUNDARY will be within 10 times the concentration levels specified in 10 CFR, This instantaneous limitation Part 20. Appendix B. Table 2. Column 2.
provides additional assurance that the levels of radioactive 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. 20.1302 l Part 50 to a MEMBER OFLTHE PUBLIC and (2) the limits of 10 CFR. Par to the population.
assumption that Xe-135 is the controlling radioisotope and its M 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 im31ements the guidance set forth in Section II.A of Appendix I and provide Appendix I to assure that t1e releases of radioactive material in liquid The dose effluents will be kept "as low as reasonably achievable."
calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be sh exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to
~
The ecuations described in the Offsite Dose be substantially underestimated.
Calculation Manual fce calculating the c,oses due to the actual release rates (continued)
PBAPS Units 2 and 3 ODCM B 3.8-1 Revision 10
ODCH Specifications Bases B 3.8 i
l l
BASES l
Licuid Radwaste Effluents Dose (continued) of radioactive materials in liquid 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 Part 50. Appendix I." Revision 1. October I
1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Efflucnts from Accidental and Routine Reactor Releases for the Purpose of
- l Appendix I." April 1977.
effluents from the site.
Instrumentation The radioactive' liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid The effluents during actual or potential release of liquid effluents.
OPERABILITY and use of this instrumentation is consist j
i Part 50.
I System Operation The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatmen The requirement'that the appropriate prior to release to the environment.
portions of this system be used when specified provides assurance that th releases to radioactive materials in liquid effluents will be kept "
CFR, Part 50.36a. General Design Criterion-60 of Appendix A to 10 CFR. P reasonably achievable."
The and design objective Section II.D of Appendix I to 10 CFR Part 50.
specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the guid set forth in Section II.A of Appendix I.10 CFR. Part 50, for liquid l
effluents.
The chemical / oily waste cleanup subsystem may' incl
. waste cleanup subsystem, or equivalent chemical / oil waste system.
(continued) l 4
1 Revision 10 ODCM B 3.8-2
, PBAPS Units 2 and 3
o 1
ODCM Specifications' Bases
.j yll B 3.8
' BASES (continued)
Gaseous Effluents Dose This specification is provided to ensure that the dose from radioactive materials in gaseous effluents at and beycnd 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 Part 20. Appendix These limits provide reasonable assurance that B. Table 2. Column 1.
radioactive material discharged in gaseous effluents will not result in the exoosure of a MEMBER OF THE PUBLIC. either within or outside the SITE BOUNDARY. to annual average concentrations exceeding the limits spec 1fied in l 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 sufficiertly low to com]ensate for any increase in the atmospheric diffusion factor above that for tne SITE BOUNDARY.
Examples of calculations for such t'EMEERS OF THE PUBLIC with the appropriate occupancy factors are given in the The specified limits restrict. at all times, the gama and beta dose 0:M.
ates aD0/e background to a MEMBER OF THE PUBLIC. at or beyond the SITE U1DARY to s 500 mrem / year to the total body or to s 3000 mrem / year to the.
E:
These dose rate limits also restrict, at all times, the corresponding stin
- ryroic c:se rate above background to a child via the inhalation pathway to 5 150C :~em. year.
Dcse. fcDie Gases Tr.1s spe:1fication 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 im)lements the guidance set forth in Section II.B of Appendix I and provides tie 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 gaseous effluents will be kept "as low as reasonably achievable." ODCMS 4.B.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 such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate. 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 arovided 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.
Ap]endix I." Resistor 1. October 1977 and the atmospheric dispersion model suamitted on September 30. 1976. in a report titled: "Information Requested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February 17.
l l
1976." The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.
(continued)
PBAPS Units 2 and 3 ODCM B 3.8-3 Revision 10 i
h
'e ODCM Specifications Bases 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. Sections II.C.
III.A and IV.A of Appendix I. 10 CFR Part 50. ODCMS 3.8.C.3 im]lements the guidance Ct forth in Section II.C of Appendix I and provides t1e required operating flexibility to implement the 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 specified in the 00 CMS 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 data such that the actual exposure of a MEMBER OF THE PUBLIC through app'ropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50. Appendix I," Revision 1. October 1977 and the Atmospheric Dispersion Model submitted on September 30, 1976 in a report titled:
"Information Requested in Enclosure 2 to letter from George Lear to E. G.
Bauer dated February 17, 1976." These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for iodine-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
- 1) individual inhalation of airborne radionuclides 2) calculations were:
deposition of radionuclides onto green leafy vegetation with subsequent 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, and 64 of Appendix A to 10 CFR. Part 50.
(continued) t PBAPS Units 2 and 3 ODCM B 3.8 4 Revision 10 l
)
c ODCM Specifications Bases B 3.8 BASES I
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 l
portions of this system be used when specified provides reasonable assurance l
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.specified as,a suitable frhction of the guidance set forth in Section II.B and II.C of Appendix I.10 CFR. Part l
50, for gaseous' effluents.
Containment PURGE ODCMS 3.8.C.6 requires that th'e 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 l
exceeding the annual dose limits of 10 CFR Part 20 for areas at or beyond the SITE BOUNDARY.
40 CFR 190 This specification is provided to meet the dose limitations of 40 CFR Pa'rt 190 that have now been incorporated into 10 CFR Part 33. This saecification requires the preparation and submittal of a Special Report wienever the
' calculated doses from plant radioactive effluents 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 wili describe-a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the pur)oses of the Special Report, it may be assumed that the dose comitment to t1e MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 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 the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.405c. is (continued)
PBAPS Units 2 and 3 ODCM B 3.8-5 Revision 10
ODCM Specifications Bases B 3.8 BASES
)
Gaseous Effluents
' ' 40 CFR 190 (continued) 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.
Ra'diolocical Environmental Monitorina Monitoring Program The rad: logical environmental monitoring program required by this speci'::a::or provides measurements of radiation and of radioactive materials in :n::e s scsure pathways and for those radionuclides, which lead to the higre:: :.:er:1al radiation exposures of MEMBERS OF THE.PUBLIC resulting from tne : :
-a::crs at the sites. This monitoring program implements Section ~
I'.' E : -
.::endix I to 10 CFR Part 50 and supplements the radiological e"h.e :
- ring program by verifying that the measurable concentrations of na:erials and levels of radiation are not higher than expected on
- ra:: c.:::. :' ;r.e effluent measurements and the modeling of the environmental tne t:.
ec::r- :.::%ays.
Tne -+L e: cetection capabilities for environmental sample analyses are tab.fatz: in :erms of the Lower Limit of Detection (LLD). The LLO's required by Ta:le.* E E 2 of the specifications are considered optimum for routine ennr:n.<r:a1 reasurements in industrial. laboratories. The monitoring program was ce.e:c:e: u:1112ing the experience of the first seven years of comercial
. opera:10-Pcgram changes may be initiated based on the additional opera:10 ei e>:erience.
Land Lse Census This spe: f1 cation is provided to ensure that significant changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiclogical environmental monitoring program are made if required by the results.of this. census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.
(continued)
PBAPS Units 2 and 3 ODCM B 3.8-6 Revision 10
ODCM Specifications' Bases B 3.8 y
BASES Radioloaical Environmental Monitorina (continued)
Interlaboratory Comparison Program The requirement for 3articipation in an Interlaboratory Comparison Program is provided to ensure tlat independent checks on the precision and accuracy of the measurements of radioactive material ir environmental sample matrices, are-performed as part of the quality assurance v % ram for environmental Jesults are reasonably valid for j
monitoring, in order to demonstrate that th
- the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50, 1