ML101250144
| ML101250144 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/28/2010 |
| From: | Exelon Nuclear |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML101250144 (126) | |
Text
Page 1 of 62, Rev. 13 Offsite Dose Calculation Manual Revision 13 Peach Bottom Atomic Power Station Units 2 and 3 02.200 0 Exelon Nuclear Docket Nos. 50-277 & 50-278
Page 2 of 62, Rev. 13 Table of Contents I.o 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. ODCMS 4.8.C.5.1 E. Technical Requirements Manual Test Requirement (TR) 3.5.3 F. ODCMS 4.8.C.7.1 and 4.8.C.7.2 V. Nuclear Fuel Cycle Dose Assessment - 40 CFR 190 and 10 CFR 72.104 A. ODCMS 4.8.D.1.1 and 4.8.D.1.2 VI. Radiological Environmental Monitoring Program A. ODCMS 4.8.E.1.1 and 4.8.E.1.2 VII. Bases Appendix A Radioactive Effluents Control Program
Page 3 of 62, Rev. 13 I. Purpose The purpose of the Offsite Dose Calculation Manual is to establish methodologies and procedures for calculating doses to individuals in areas at and beyond the SITE BOUNDARY due to radioactive effluents from Peach Bottom Atomic Power Station.
The results of these calculations are required to determine compliance with the requirements of Specification 5.5.4, "Radioactive Effluent Controls Program" of Appendix A to Operating Licenses DPR-44 and DPR-56, "Technical Specifications for Peach Bottom Atomic Power Station Units No.
2 and 3". The Radioactive Effluents Control Program is located in Appendix A of this Offsite Dose Calculation Manual and contains Offsite Dose Calculation Manual Specifications (ODCMS) and their associated Bases which implement the requirements of Technical Specification 5.5.4.
II. Setpoint Determination for Liquid & Gaseous Monitors II.A Liquid Radwaste Activity Monitor SetDoint 02.200 A sketch of the Liquid Radwaste System is presented in Figure 0
- 4. Each tank of radioactive waste is sampled prior to release.
A small liquid volume of this sample is analyzed for gross gamma activity in a NaI well counter. This NaI well counter activity is then converted to an equivalent liquid radwaste monitor reading.
CPS (R/W Monitor) [Net CPM/ml (well) x Eff W/RW] +
Background CPS Where:
CPS (R/W Monitor) liquid radwaste gross activity monitor reading in CPS Net CPM/ml (well) gross gamma activity for the radwaste sample tank [determined by the well counter]
Eff W/RW conversion factor between well counter and liquid radwaste gross activity monitor [determined by calibrating both detectors with the same liquid radioactive source]
Background CPS background reading of the liquid radwaste gross activity monitor in CPS Exceeding the expected response would indicate that an incorrect sample had been obtained for that release and the release is automatically stopped.
Page 4 of 62, Rev. 13 The alarm and trip pot setpoints for the liquid radwaste activity monitor are determined from a calibration curve for the alarm pot and trip pot. The alarm pot setting includes a factor of 1.25 to allow for analysis error, pot setting error, instrument error and calibration error. The trip pot setting includes a factor of 1.35 to allow for analysis error, pot setting error, instrument error and calibration error.
II.B Licquid Radwaste Release Flowrate Setpoint Determination The trip pot setpoint for the liquid radwaste release flowrate 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 be used. The Peach Bottom radwaste system has two flow monitors - high flow (5 to 300 gpm) and low flow (0.8 to 15 gpm). The factor of 1.2 allows for pot setting error and instrument error. The flow rate determination includes a margin of assurance which includes consideration of this error such that the instantaneous release limit of 10 CFR 20 is not exceeded.
II.C Setpoint Determination for Gaseous Radwaste A sketch of the Offgas Radwaste Treatment System is presented 02.200 in Figure 2. Sketches of the Ventilation Treatment Systems for o Units 2 and 3 are presented in Figures 3 and 4 respectively.
The high and high-high alarm setpoints for the main stack radiation monitor, Unit 2 roof vent radiation monitor and Unit 3 roof vent radiation monitor are determined as follows:
is set at approximately 3 02.200 High Alarm - the high alarm setpoint x background.
High-High Alarm - the high-high alarm setpoint is set at a release rate from this vent of approximately 30% of the instantaneous release limit as specified in ODCMS 3.8.C.l.a for the most restrictive case (skin or total body) on an unidentified basis. To determine these setpoints, solve the gaseous effluent dose rate equations in section IV.A of the ODCM to determine what main stack release rate and roof vent release rate will produce a dose rate of 150 mrem/yr to the total body (30% of the limit of 500 mrem/yr) and a dose rate of 900 mrem/yr to the skin (30% of the limit of 3000 mrem/yr) 02.200 from each release point. Using the highest (most restrictive) release rate for each release point determine monitor response required to produce this release rate assuming a normal vent flow rate and pressure correction factor. Set the high-high alarm for approximately this monitor response.
Page 5 of 62, Rev. 13 II.D. Setpoint Determination for Gaseous Radwaste Flow Monitors 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:
Low Flow Alarm - 1.5 x l05 cfm High Flow Alarm - 5.4 x 105 cfm III. Liquid Pathway Dose Calculations III.A Liquid Radwaste Release Flow Rate Determination Peach Bottom Atomic Power Station Units 2 and 3 have one common discharge point for liquid releases. The following calculation assures that the radwaste release limits are met.
The flow rate of liquid radwaste released from the site to areas at and beyond the SITE BOUNDARY shall be such that the concentration of radioactive material after dilution shall be limited to 10 times the concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases and 2E-4 *Ci/ml total activity concentration for all noble gases as specified in ODCMS 3.8.B.1. This methodology is consistent with the additional guidance the NRC provided to the industry during the implementation of the updated 10 CFR 20 which changed the criterion for controlling 02.200 release rate based on Effective Concentration (EC) values in 0 the updated 10 CFR 20 as opposed to the Maximum Permissible Concentration (MPC) values in the former 10 CFR 20.
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. While non-gamma 02.200 emitters are not specifically addressed, the conservatisms 0 inherent in the calculation of the maximum permissible release rate are more than adequate to account for them. From this gamma isotopic analysis the maximum permissible release flow rate is determined as follows:
Page 6 of 62, Rev. 13 Determine a Dilution Factor by:
Dilution Factor =Z Ci / ml1 l0 x ECLi JICi / mli = the activity of each identified gamma emitter in *Ci/ml ECLi The effluent concentration specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases or 2 x 10-4 gCi/ml for noble gases.
Determine the Maximum Permissible Release Rate with this Dilution Factor by:
Release Rate (gpm) = A x 2.0 x 105 B x C x Dilution Factor A = The number of circulating water pumps running which will provide dilution 2.0 x 105 the flow rate in gpm for each circulating water pump running B = margin of assurance which includes consideration of the maximum error in the activity setpoint, the maximum error in the flow setpoint, and possible loss of 5 out of the 6 possible circulating water pumps during a release. The value used for B is 10.0.
C concentration gradient factor. The value used for C is 5.0 for discharge canal water levels less than 104' and 3.0 for canal water levels 02.200 greater than 104'. This just adds another 0 factor of conservatism.
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 equation below. This dose calculation uses those appropriate radionuclides listed in Table III.A.I. These radionuclides account for virtually 100 percent of the total body dose and organ dose from liquid effluents.
The dose for each age group and each organ should be calculated to determine the maximum total body dose and organ dose for each quarter and the year, as appropriate.
Cumulative dose files for quarterly and yearly doses should be maintained separately and the maximum total body and organ dose reported in each case. CM-i NRC URI 88-33-01, T00353.
Page 7 of 62, Rev. 13 D'C= Z AiM At, CiF i'
where:
D = The cumulative dose commitment to the total body or any organ, , from liquid effluents for the total time period EAt,2, in mrem.
e=1 At, The length of the eth time period over which Ci, and F, are averaged for the liquid release, in hours.
Cil The average concentration of radionuclide, i, in undiluted liquid effluent during time period At, from any liquid release, (determined by the effluent sampling analysis program, ODCMS Table 4.8.B.1), in 1 1Ci/ml.
Ai = The site related ingestion dose commitment factor to the total body or organ, T, for each radionuclide listed in Table III.A.1, in mrem-ml per hr- ý1 Ci. See Site Specific Data.**
Ft The near field average dilution factor for Cil 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 pathway.
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
Page 8 of 62, Rev. 13 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
Ai, DOSE FACTOR (MREM-ML PER HR-*Ci)
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 02.200 o CR-51 1. 49E+00 1. 53E+00 1. 69E+00 MN-54 9. 82E+02 1. OOE+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 02.200 CO- 57 4 55E+01 4. 71E+01 5. 78E+01 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 Y-91M 5.85E-13 6.14E-13 9.35E-14 Y-93 1.27E-03 1.34E-03 2.16E-03 NB-95 1. 52E+02 1.56E+02 1.68E+02 NB-95M no data no data no data ZR-95 1. 77E-01 1.72E-01 3 .48E-01 02.200 0 ZR-97 1. 56E-03 1. 56E-03 3 .43E-03 MO-99 2. 91E+01 3. 01E+01 5. 53E+01 TC-99M 3. 33E-02 3 .33E-02 4 93E-02 RU-103 3 57E+00 3. 60E+00 5. 97E+00 RU-105 1. 73E-01 1. 78E-01 3 16E-01 AG-110 M 2.13E+00 2 04E+00 4. 23E+00
Page 9 of 62, Rev. 13 02.200 0 SN-113 no data no data no data 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 SB-124 6.33E+02 6.54E+02 7.54E+02 02.200 0
SB-125 2.15E+02 2.51E+02 3.08E+02 1-131 1.86E+02 1.79E+02 2.36E+02 1-133 1.97E+01 2.03E+01 3 .20E+01 02.200 0 1-135 2.04E+00 2.06E+00 3.12E+00 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 02.200 0 CS-138 2.65E-09 2.78E-09 3.25E-09 02.200 BA-139 5.01E-07 5.17E-07 1.18E-06 BA-140 3.66E+01 3.62E+01 7.42E+01 LA- 140 1.92E-02 1.97E-02 2.78E-02 LA- 142 2.46E-08 2.52E-08 3.59E-08 02.200 0 CE-141 1.45E-02 1.46E-02 3.86E-02 CE-143 1.68E-03 1.69E-03 4.44E-03 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.
Page 10 of 62, Rev. 13 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
A., DOSE FACTOR (MREM-ML PER HR-PCi)
LIVER RADIO-NUCLIDE ADULT TEEN CHILD H-3 2. 13E+00 1.53E+00 2. 70E+00 NA-24 1. 65E+02 1.70E+02 1. 98E+02 P-32 9. 55E+04 1. 04E+05 1. 01E+05 02.200 CR-51 no data no data no data I 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 02.200 CO-57 2 . 74E+01 2. 81E+01 2. 86E+01 c0a CO-5 8 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 Y-91M no data no data no data Y-93 no data no data no data NB-95 2. 83E+02 2.84E+02 2.35E+02 NB-95M no data no data no data ZR-95 2.61E-01 2. 50E-01 3.91E-01 02.200 ZR-97 8.43E-03 3 .39E-03 5.82E-03 0
MO-99 1. 53E+02 1. 58E+02 2.23E+02 TC-99M 2.61E-03 2. 57E-03 2.98E-03 RU- 103 no data no data no data RU- 105 no data no data no data AG-110 M 3.58E+00 3.36E+00 5.30E+00
Page 11 of 62, Rev. 13 02200 SN-113 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 SB-124 3.01E+01 3.09E+01 2.79E+01 02.200 o SB-125 9.57E+01 1.17E+01 1.04E+02 1-131 3.25E+02 3.32E+02 4.16E+02 1-133 6. 48E+01 6.66E+01 8 .45E+01 02.200 I-135 5.52E+00 5.55E+00 1.63E+00 I 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 CS-138 5.34E-09 5.56E-09 5.12E-09 02.200 o BA-139 1.22E-08 1.25E-08 2.17E-08 BA- 140 7.OOE-01 6.90E-01 lIE+00 LA- 14 0 7.28E-02 7.40E-02 8.25E-02 LA-142 9.89E-08 1.01E-07 1.15E-07 02.200 o CE-141 1.28E-01 1.27E-01 2.60E-01 CE-143 1.52E+01 1.51E+01 3.07E+01 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.
Page 12 of 62, Rev. 13 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
Ai. DOSE FACTOR (MREM-ML PER HR-1 1 Ci)
BONE RADIO-NUCLIDE ADULT TEEN CHILD H-3 no data no data no data NA-24 1. 65E+02 1. 70E+02 1. 98E+02 P-32 2.38E+05 2. 58E+05 3.35E+05 02.200 CR-51 no data no data no data MN-54 no data no data no data FE-55 8. 12E+02 8.47E+02 1. 19E+03 FE-59 1.26E+03 1. 30E+03 1.68E+03 02.200 CO-57 no data no data no data 0
CO-58 no data no data no data CO-60 no data no data no data ZN-65 2.69E+04 2. 43E+04 2. 51E+04 SR-89 3 .08E+04 3 .30E+04 5. 19E+04 SR-90 7. 67E+05 6. 31E+05 6. 78E+05 Y-91M 1. 51E-11 1. 61E-1I 2 .57E-11 Y-93 4. 58E-02 4 90E-02 7. 77E-02 NB-95 5. 08E+02 5. 12E+02 6.04E+02 NB-95M no data no data no data 02.200 ZR-95 8.13E-01 7. 94E-01 1. 78E+00 ZR-97 1.69E-02 1.71E-02 4.03E-02 MO-99 no data no data no data TC-99M 9.24E-04 9.22E-04 1.52E-03 RU- 103 8. 30E+00 8.43E+00 1.55E+01 RU-lOS 4.39E-01 4. 59E-01 8. 71E-01 AG-110M 3. 87E+00 3'. 5sE+00 7. 84E+00
Page 13 of 62, Rev. 13 02.200 0 SN-113 no data no data no data TE-129M 1.27E+04 1.37E+04 1.80E+04 TE-131M 1.12E+03 1.21E+03 1.56E+03 TE-132 2.29E+03 2.42E+03 3.07E+03 SB-124 1.60E+03 1.68E+03 2.15E+03 SB-125 4.75E+03 1.07E+03 1.39E+03 1-131 2.28E+02 2.38E+02 4.13E+02 1-133 3.72E+01 3.92E+01 6.84E+01 1-135 2.11E+00 2.16E+00 3.66E+00 CS-134 3.47E+05 3.55E+05 4.30E+05 CS-136 3.45E+04 3.46E+04 4.1OE+04 CS-137 4.44E+05 4.75E+05 6.01E+05 CS-138 2.70E-09 2.90E-09 3.68E-09 02.200 0
.BA- 13 9 1.71E-05 1.77E-05 4.07E-05 BA- 140 5.57E+02 5.63E+02 1.27E+03 LA- 140 1.44E-01 1.51E-01 2.36E-01 LA-142 2.18E-07 2.28E-07 3.94E-07 02.200
° CE-141 1.89E-01 1.90E-01 5.21E-01 CE-143 2.06E-02 2.07E-02 5.66E-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.
Page 14 of 62, Rev. 13 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
Ai, DOSE FACTOR (MREM-ML PER HR-gCi)
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 02.200 CR-51 3. 28E-01 3 .35E-01 2 .57E-01 0
MN-54 1. 53E+03 1.51E+03 1.13E+03 FE-SS no data no data no data FE-59 no data no data no data 02.200 CO-57 no data no data no data a
CO-58 no data no data no data CO-60 no data no data no data ZN-65 5. 72E+04 5.41E+04 4 . 22E+04 SR-89 no data no data no data SR-90 no data no data no data Y-91M no data no data no data Y-93 no data no data no data NB-95 2.79E+02 2.75E+02 2.21E+02 NB-95M no data no data no data ZR- 95 4.09E-01 3.68E-01 5. 60E-01 02.200 ZR-97 5. 14E-03 5 14E-03 8 .35E-03 0
MO-99 3.46E+02 3 61E+02 4 . 77E+02 TC-99M 3. 96E-02 3 .83E-02 4. 33E-02 RU-103 3.17E+01 2. 97E+01 3. 91E+01 RU-105 5. 68E+00 5 78E+00 7. 66E+00 AG-I1OM 7. 04E+00 6 .40E+00 9. 86E+00
Page 15 of 62, Rev. 13 02.200 o SN-113 no data no data no data TE-129M 5.31E+04 5.74E+04 5.29E+04 TE-131M 5.55E+03 6.01E+03 5.22E+03 TE-132 1.43E+04 1.47E+04 1.27E+04 02.200 SB-124 no data no data no data 0
SB-125 no data no data no data 1-131 5.57E+02 5.73E+02 6.82E+02 1-133 1.12E+02 1.16E+02 1.41E+02 02.200 I-135 8.86E+00 8.77E+00 1.01E+01 CS-134 2.67E+05 2.66E+05 2.19E+05 CS-136 7.57E+04 7.42E+04 6.OOE+04 CS-137 2.06E+05 2.15E+05 1.87E+05 CS-138 3.92E-09 4.10E-09 3.60E-09 02.200 0 .BA-139 1.14E-08 1.18E-08 1.90E-08 BA- 140 2.38E-01 2.34E-01 3.62E-01 LA- 140 no data no data no data LA- 142 no data no data no data 02.200 0
CE-141 5.94E-02 5.98E-02 1.14E-01 CE-143 6.70E-03 6.77E-03 1.29E-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.
Page 16 of 62, Rev. 13 TABLE III.A.1 LIQUID EFFLUENT INGESTION DOSE FACTORS (DECAY CORRECTED)
Ai, DOSE FACTOR (MREM-ML PER HR- 1 1 Ci)
GI-LLI RADIO-NUCLIDE ADULT TEEN CHILD H-3 2. 13E+00 1. 53E+00 2.70E+00 NA-24 1. 65E+02 1. 70E+02 1. 98E+02 P-32 1. 73E+05 1. 41E+05 5. 98E+04 02.200 CR-Si 3.74E+02 2. 57E+02 8. 98E+01 MN-54 1. 58E+04 1. 04E+04 3 38E+03 FE-55 3 .22E+02 2 60E+02 1. 17E+02 FE-59 9. 90E+03 7. 15E+03 2 84E+03 02.200 CO-57 6. 94E+02 5 .24E+02 2. 34E+02 CO-58 2 35E+03 1. 56E+03 6.04E+02 CO-60 6 30E+03 4. 33E+03 1.70E+03 ZN-65 5 38E+04 3 .58E+04 1. 18E+04 SR-89 4 94E+03 3. 93E+03 2. 01E+03 SR-90 2 . 22E+04 1. 77E+04 9. 13E+03 Y-91M 4 .44E-11 7.58E-10 5. 03E-08 Y-93 1. 45E+03 1.50E+03 1. 18E+03 NB-95 1. 72E+06 1.21E+06 4.35E+05 NB- 95M no data no data no data ZR-95 8. 27E+02 5 78E+02 4.08E+02 ZR-97 1. 06E+03 9. 19E+02 8.81E+02 02.200 0
MO-99 3. 54E+02 2. 82E+02 1.85E+02 TC-99M 1. 54E+00 1. 69E+00 1.69E+00 RU-103 9. 69E+02 7 04E+02 4. 01E+02 RU- 105 2 69E+02 3. 70E+02 5.69E+02 AG-IIOM 1. 46E+03 9. 43E+02 6. 30E+02
Page 17 of 62, Rev. 13 02.200 SN-113 no data no data no data TE-129M 6.40E+04 5.15E+04 2.19E+04 TE-131M 5.44E+04 4.63E+04 2.19E+04 TE-132 7.02E+04 4.85E+04 1.37E+04 SB-124 4.53E+04 3.38E+04 1.35E+04 02.200 0 SB-125 5.93E+04 4.85E+04 2.13E+04 1-131 8.58E+01 6.57E+01 3.70E+01 1-133 5.82E+01 5.03E+01 3.40E+01 02.200 1-135 6.24E+00 6.16E+00 5.03E+00 0
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.OOE+03 3.60E+03 CS-138 2.28E-14 2.52E-12 2.36E-09 02.200 0 1BA- 139 3.04E-05 1.58E-04 2.35E-03 BA-140 1.15E+03 8.69E+02 6.43E+02 LA- 140 5.34E+03 4.25E+03 2.30E+03 LA-142 7.22E-04 3.08E-03 2.27E-02 02.200 0
CE-141 4.89E+02 3.63E+02 3.24E+02 CE-143 5.69E+02 4.54E+02 4.49E+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.
Page 18 of 62, Rev. 13 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.l 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 Analysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.
- a. Gross Release Method D TB = Vb,,s + K (/Q)vQ'NV DS [LS (-/-Q)s + l.lB] ~NS +[Lv + 1.1M] (x/Q) bN v where:
The location is the site boundary, 1097m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases.
DT3 = total body dose rate, in mrem/yr.
Ds skin dose rate, in mrem/yr.
V = 4.72 X 10- mrem/yr per gCi/sec; the constant for Kr-88 accounting for the gamma radiation from the elevated finite plume. This constant was developed using MARE program with plant specific inputs for PBAPS.
Page 19 of 62, Rev. 13 IV.A.l.a (Cont'd)
QNS = The gross release rate of noble gases from the stack determined by gross activity stack monitors averaged over one hour, in gCi/sec.
K = 1.47 X 104 mrem/yr per 1 1Ci/m3 ; the total body dose factor due to gamma emissions for Kr-88 (Reg. Guide 1.109, Table B-l).
12.200 (x--) = 9.19 X 10-7 sec/M 3 ; the highest calculated 0 annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
QNV = The gross release rate of noble gases in gaseous effluents from vent releases determined by gross activity vent monitors averaged over one hour, in gCi/sec.
Lv = 2.37 x 103 mrem/yr per gCi/mr; the skin dose factor due to beta emissions for Kr-88. (Reg.
Guide 1.109, Table B-l).
Ls = 9.73 X 10' mrem/yr per gCi/m'; the skin dose factor due to beta emissions for Kr-87. (Reg.
Guide 1.109, Table B-i).
(-/Q)) = 9.97 X 10-' sec/M 3 ; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
B = 1.74 X 10- mrad/yr per Ci/isec; the constant for Kr-87 accounting for the gamma radiation from the elevated finite plume. This constant was developed using MARE program with plant specific inputs for PBAPS.
M = 1.52 X 10' mrad/yr per LCi/m 3 ; the air dose factor due to gamma emissions for Kr-88.
(Reg. Guide 1.109, Table B-l).
1.1 = Unit conversion, converts air dose to skin dose, mrem/mrad.
Page 20 of 62, Rev. 13 IV.A.1. b. Isotopic Analysis Method
= [(Li (X/Q) S+ l.1B1 ) + (i+ l.1Mj) (x,'Q)v bi where:
The location is the site boundary, 1097m SSE from the vents. This location results in the highest calculated dose to an individual from noble gas releases.
DTB = total body dose rate, in mrem/yr.
Ds= skin dose rate, in mrem/yr.
Vi = The constant for each identified noble gas radionuclide for the gamma radiation from 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.l, in mrem/yr per *Ci/sec.
is = The release rate of noble gas radionuclide, i, in gaseous effluents from the stack determined by isotopic analysis averaged over one hour, in gCi/sec.
K1 = The total body dose factor due to gamma emissions for each identified noble gas radionuclide. Values are listed on Table IV.A.1, in mrem/yr per ýtCi/m 3 .
12.200 (x-Q) = 9.19 X 10-7 sec/m3 ; the highest calculated 0 V annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases.
Qiv= The release rate of noble gas radionuclide, i, in gaseous effluents from all vent releases determined by isotopic analysis averaged over one hour, in gCi/sec.
L+/- = .The skin dose factor due to beta emissions for each identified noble gas radionuclide.
Values are listed on Table IV.A.l, in mrem/yr per ýCi/m 3 .
Page 21 of 62, Rev. 13 IV.A.l.b (Cont'd)
(-)9 = 9.97 X 10.8 sec/m3 ; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
= The constant for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume.
The constants were developed using MARE program with plant specific inputs for PBAPS.
Values are listed on Table IV.A.I, in mrad/yr per gCi/sec.
Mi= The air dose factor due to gamma emissions for each identified noble gas radionuclide.
Values are listed on Table IV.A.l, in mrad/yr per tCi/m3 .
1.1 = Unit conversion, coverts air dose to skin dose, mrem/mrad.
Page 22 of 62, Rev. 13 TABLE IV.A.l - Constants for Isotopic Analysis Method (corrected for decay during transit)
Plume-Air Total Body Skin Gamma Air Beta Air Plume-Body Dose Factor Dose Factor Dose Factor Dose Factor Dose Factor Dose Factor B, K, L. M N, V1 Radionuclide (mrad/yr per (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per (mrem/yr per gCi/sec ) 11Ci/ml) ýLCi/m 3) ýLCi/m,) ýLCi/m,) gCi/sec )
Kr-85m 4.02E-05 1.17E+03 1.46E+03 1.23E+03 1.97E+03 3.76E-05 Kr-87 1.74E-04 5.92E+03 9.73E+03 6.17E+03 1.03E+04 1.66E-04 Kr-88 4.90E-04 1.47E+04 2.37E+03 1.52E+04 2.93E+03 4.72E-04 Xe-133 1.19E-05 2.94E+02 3.06E+02 3.53E+02 1.05E+03 1.l1E-05 Xe-133m 1.09E-05 2.51E+02 9.94E+02 3.27E+02 1.48E+03 1.01E-05 Xe-135 6.37E-05 1.81E+03 1.86E+03 1.92E+03 2.46E+03 5.95E-05 Xe-135m 6.61E-05 2.53E+03 5.76E+02 2.72E+03 5.99E+02 6.17E-05 Xe-138 1.52E-04 6.98E+03 3.26E+03 7.28E+03 3.75E+03 1.46E-04 The values K,, L,, M,, and N, are taken from Reg. Guide 1.109, Table B-1. The values Bi and Vi were developed using the MARE program with plant specific inputs for PBAPS.
Page 23 of 62, Rev. 13 IV.A.2 Iodine-131, iodine-133, tritium and radioactive materials in particulate form, other than noble gases, with half-lives greater than eight days:
The dose rate shall be determined for either of two critical organs and most restrictive age group. Child thyroid dose is limiting when iodine releases exceed 10 percent of the total release rates. The teenager lung dose is limiting when iodine is either not present or a small fraction of the total release.
When it is not clear which organ dose will be limiting, doses for both restrictive age group organs will be calculated and the limiting organ dose identified.
D=j Pi [W s+Výv+Výv i
where:
The location is the site boundary, 1097m SSE from the vents.
D = dose rate to the critical organ most restrictive age group, in mrem/yr.
P= The dose parameter for radionuclides other than noble gases for the inhalation pathway.
The dose factors are based on the critical organ, and most restrictive age group. All values are from Reg. Guide 1.109 (Tables E-5, 12.200 E-8, E-9 and E-10). Values are listed on 0 Table IV.A.2, in mrem/yr per gCi/m3 W= 1.03 X 10-7 sec/m3 ; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY from stack releases. (SSE boundary)
ýis = The release rate of radionuclides; i, in gaseous effluents from the stack determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in gCi/sec.
Wv = 4.78 X 10-7 sec/m 3 ; the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY for all vent releases. (SSE boundary)
Page 24 of 62, Rev. 13 IV.A.2. (Cont'd)
=V The release rate of radionuclide, i,in gaseous effluents from all vent releases, determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in gCi/sec.
= The release rate of radionuclide, i, in gaseous effluents from the auxiliary boiler stack releases, determined by the oil sampling and analysis program (ODCM Specification Table 4.8.C.1) in gCi/sec as calculated below:
, C vV x 3 78 5 x z
=
i Z T where:
The location is the site boundary, 1097m SSE from the vents.
Civ = activity concentration measured in oil for nuclide, i, in gCi/ml.
3785 = milliliters per gallon.
Z = gallons of oil consumed.
T = number of seconds used for release Method (a) 60 second Method (b) number of seconds used to burn oil for release.
Page 25 of 62, Rev. 13 TABLE IV.A.2 Pi CONSTANTS FOR CRITICAL ORGAN FOR THE MOST RESTRICTIVE AGE GROUP (mrem/yr per gCi/m3 )
INFANT CHILD INFANT TEENAGER THYROID LUNG DOSE THYROID LUNG DOSE DOSE RADIONUCLIDE DOSE FACTOR FACTOR FACTOR FACTOR H-3 6.47E+02 6.47E+02 1.13E+03 1.27E+03 C-14 5.31E+03 5.31E+03 6.73E+03 4.87E+03 NA-24 1.06E+04 1.06E+04 1.61E+04 1.38E+04 P-32 no data no data no data no data Cr-51 5.75E+01 1.28E+04 8.55+01 2.10E+04 MN-54 no data 1.OOE+06 no data 1.98E+06 FE-55 no data 8.69E+04 no data 1.24E+05 MN-56 no data 1.25E+04 no data 1.52E+04 CO-58 no data 7.77E+05 no data 1.34E+06 FE-59 no data 1.02E+06 no data 1.53E+06 CO-60 no data 4.51E+06 no data 8.72E+06 12.2008 NI-63 no data 2.09E+05 no data 3.07E+05 CU-64 no data 9.30E+03 no data 1.11E+04 NI-65 no data 8.12E+03 no data 9.36E+03 ZN-65 no data 6.47E+05 no data 1.24E+06 ZN-69 no data 1.47E+03 no data 1.58E+03 BR-83 no data no data no data no data BR-84 no data no data no data no data BR-85 no data no data no data no data BR-86 no data no data no data no data BR-88 no data no data no data no data BR-89 no data no data no data no data
Page 26 of 62, Rev. 13 SR-89 no data 2 . 03E+06 no data 2 .42E+06 SR-90 no data 1.12E+07 no data 1.65E+07 Y-90 no data 2 . 69E+05 no data 2 . 93E+05 SR-91 no data 5.26E+04 no data 6 .07E+04 Y-91M no data 2. 79E+03 no data 3.20E+03 Y-91 no data 2 .45E+06 no data 2.94E+06 SR-92 no data 2.38E+04 no data 2. 74E+04 Y-92 no data 2 .45E+04 no data 2.68E+04 Y-93 no data 7. 64E+04 no data 8. 32E+04 NBE-95 no data 4. 79E+05 no data 7. 51E+05 ZR-95 no data 1. 75E+06 no data 2. 69E+06 ZR-97 no data 1.10E+05 no data 1.30E+05 MO-99 no data 1.35E+05 no data 1.54E+05 TC-99M. no data 8. 11E+02 no data 1.15E+03 TC-101 no data 5. 84E+02 no data 6. 67E+02 RU-103 no data 5. 52E+05 no data 7. 83E+05 RU-105 no data 1.57E+04 no data 1.82E+04 RU-106 no data 1. 16E+07 no data 1.61E+07 12.200 AG-110M no data 3 . 67E+06 no data 6.75E+06 8
TE-125M 1. 62E+03 4.47E+05 1. 92E+03 5. 36E+05 TE-127M 4 .87E+03 1.3!E+0o 6 . 07E+03 1. 66E+06 TE-127 1.85E+00 1. 04E+04 1. 96E+00 1.12E+04 TE-129M 5.47E+03 1. 68E+06 6.33E+03 1. 98E+06 TE-129 6 . 75E-02 3 . OOE+03 7.14E-02 3 .30E+03 1-130 1. 60E+06 no data 1. 85E+06 no data 1-131 1.48E+07 no data 1. 62E+07 no data TE-131M 8. 93E+01 1. 99E+05 9. 77E+01 2. 38E+05 TE-131 1.58E-02 2 . 06E+03 1.70E-02 2. 34E+03
Page 27 of 62, Rev. 13 1-132 1.69E+05 no data 1.94E+05 no data TE-132 2.79E+02 3.40E+05 3.18E+02 4.49E+05 1-133 3.56E+06 no data 3.85E+06 0.OOE+00 CS-134 no data 7.97E+04 0.OOE+00 1.46E+05 1-134 4.45E+04 no data 5.07E+04 no data 1-135 6.96E+05 no data 7.92E+05 no data CS-136 no data 1.18E+04 no data 1.78E+04 CS-137 no data 7.13E+04 no data 1.21E+05 CS-138 no data 6.54E+01 no data 7.87E+01 BA-139 no data 5.95E+03 no data 6.46E+03 BA-140 no data 1.60E+06 no data 2.03E+06 LA-140 no data 1.68E+05 no data 2.14E+05 BA-141 no data 2.97E+03 no data 3.29E+03 12.200 CE-141 no data 5.17E+05 no data 6.14E+05 0
BA-142 no data 1.55E+03 no data 1.91E+03 LA-142 no data 8.22E+03 no data 1.02E+04 CE-143 no data 1.16E+05 no data 1.30E+05 PR-143 no data 4.33E+05 no data 4.83E+05 CE-144 no data 9.84E+06 no data 1.34E+07 PR-144 no data 1.61E+03 no data 1.75E+03 ND-147 no data 3'122E+05 no data 3.72E+05 W-187 no data 3.96E+04 no data 4.74E+04 NP-239 no data 5.95E+04 no data 6.49E+04
Page 28 of 62, Rev. 13 IV.B. ODCMS 4.8.C.2.1 The air dose in areas at and beyond the SITE BOUNDARY due to noble gases released in gaseous effluents shall be determined by the expressions below.
The air dose shall be determined by either of two methods.
Method (a), the Gross Release Method, assumes that all noble gases released are the most limiting nuclide - Kr-88 for gamma radiation and Kr-87 for beta radiation. Method (b), the Isotopic Analysis Method, utilizes the results of noble gas analyses required by ODCMS 4.8.C.1.1.
IV.B.l for gamma radiation:
- a. Gross Release Method
- 3.17 x 10v [M (x/Q) + B where:
The location is the SITE BOUNDARY 1097m SSE from the vents. This location results in the highest calculated gamma air dose fromnoble gas releases.
Dy = gamma air dose, in mrad.
3.17 x 10-8 = years per second.
M = 1.52 x 104 mrad/yr per ýCi/m3 ; the air dose factor due to gamma emissions for Kr-88.
(Reg. Guide 1.109, Table B-l) 12.200 = 9.19 x 10-7 sec/M 3 ; the highest calculated 8 ' 'V annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
QV= The gross release of noble gas radionuclides in gaseous effluents from all vents, determined by gross activity vent monitors, in gCi. Releases shall be cumulative over the calendar quarter or year as appropriate.
Page 29 of 62, Rev. 13 IV.B.1. a (Cont'd)
B = 4.90 x 104 mrad/year per gCi/sec; the constant for Kr-88 accounting for the gamma radiation from the elevated finite plume.
The constant was developed using the MARE program with plant specific inputs for PBAPS.
Qs= The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitor in jCi.
Releases shall be cumulative over the calendar quarter or year as appropriate.
- b. Isotopic Analysis Method D
= 3.17 x 10-' XH (jQ)v ýv + Bi where:
The location is the SITE BOUNDARY, 1097m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.
Dy = gamma air dose, in mrad.
3.17 x 10-8 = years per second.
M+/- = The air dose factor due to gamma emissions for each identified noble gas radionuclide.
Values are3 listed on Table IV.A.1, in mrad/yr per tCi/m .
12.200 = 9.19 x 107 sec/M3 ; the highest calculated average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
Qiv= The release of noble gas radionuclides, i, in gaseous effluents from all vents as determined by isotopic analysis, in 9Ci.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
Bi = The constant for each identified noble gas 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.I, in mrad/yr per gCi/sec.
Page.30 of 62, Rev. 13 IV.B.l. b. (Cont'd)
Qis =The release of noble gas radionuclides, i, in gaseous effluents from the stack determined by isotopic analysis, in Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.
IV.B.2. for beta radiation:
- a. Gross Release Method Do 3.17 x 10-' N Rxi/-Q)v ýV + (i/-)s 'ýS1 where:
The location is the SITE BOUNDARY 1097m SSE from the vents. This location results in the highest calculated gamma air dose from noble gas releases.
Do = beta air dose, in mrad.
3.17 x 10-' = years per second.
N = 1.03 x 104 mrad/yr per 1 1Ci/m 3 ; the air dose factor due to beta emissions for Kr-87.
(Reg. Guide 1.109, Table B-l) 12.200 (x--) v = 9.19 x 10-7 sec/M3 ; the highest calculated 0
annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
QV= The gross release of noble gas radionuclides in gaseous effluents from all vents determined by gross activity vent monitors, in *Ci. Releases shall be cumulative over the calendar quarter or year, as appropriate.
(-/Q) = 9.97 x 10-' sec/M3 ; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
Qs= The gross release of noble gas radionuclides in gaseous releases from the stack determined by gross activity stack monitors, in 1LCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
Page 31.of 62, Rev. 13 IV.B.2. b. Isotopic Analysis Method DP
= 3.17 x 10' i Ni [(iiQ)v ýiv + (iQ)s ýiS 3.17 x 10-' = years per second.
Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide.
Values are listed on Table IV.A.l, in mrad/yr per ýCi/m3 .
12.200 8
(9--) v = 9.19 X 10-7 sec/m 3 ; the highest calculated "Q) annual average relative concentration from vent releases for any area at or beyond the SITE BOUNDARY.
= The release of noble gas radionuclide, i, in gaseous effluents from all vents as determined by isotopic analysis, in gCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
(x-Q) = 9.97 x 10 sec/M 3 ; the highest calculated annual average relative concentration from the stack releases for any area at or beyond the SITE BOUNDARY.
Qis =The release of noble gas radionuclide, i, in gaseous effluents from the stack as determined by isotopic analysis, in gCi.
Releases shall be cumulative over the calendar quarter or year, as appropriate.
IV.C ODCMS 4.8.C.3.1 The dose to an individual from iodine-131, iodine-133, tritium and radioactive materials, in particulate form and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY.
The dose shall be determined for the limiting organ. Infant thyroid doses are dominating any time that either iodine-131 release rates are more than two (2) percent of total release rates or iodine-133 exceeds 25 percent of total release rates.
In these cases only iodine-131 and iodine-133 are potentially significant.
For cases where there is no detectable iodine releases, doses shall be determined for infant bone and liver. Both bone and liver doses are calculated because the controlling dose is dependent upon the presence of strontium.
Page 32 of 62, Rev. 13 IV.C (Continued)
When it is not clear whether thyroid, bone, or liver doses are controlling, all three shall be calculated and the limiting dose identified.
D=3.17x108-"Fe Ri WsQs +Wv Qv +Wvqv i
where:
Location is the critical pathway dairy 1431m WSW from vents.
D = limiting dose to the critical infant organ, 02.200 from the milk, or inhalation, or ground plane 8 pathways, in mrem.
3.17 x 10 = years per second.
F= Fraction that is elemental (0.5 for iodines and 1.0 for all other elements).
RI= The dose factor for each identified radionuclide; i, in m2 (mrem/yr) per *Ci/sec except tritium, which is in mrem/yr per RCi/m'. The dose factors are for the critical individual organ for the most restrictive age group, infant. Values are listed in Table IV.C.I for the ingestion pathway, Table 02.200 IV.C.2 for the inhalation pathway, and Table 0 IV.C.3 for the ground plane pathway. See Site Specific Data.**
WS* = 8.78 x 10-10 meters -2; (D/Q) for the food pathway for stack releases except tritium 3 which uses a (%/Q) of 8.78 x 10-8 sec/M .
Q~= The release of radionuclide, i, in gaseous effluents from the stack determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1), in gCi. Releases shall be cumulative over the calendar quarter or. year, as appropriate.
S1.58 x10-9 meters-2 ; (D-/) for the food pathway for vent releases except tritium which uses a (X/Q) of 1.58 x 10- sec/mi.
- See Note 2 and 3 in Bases
Page 33 of 62, Rev. 13 IV.C (Continued)
- v = The release of radionuclide, i, in gaseous effluents from the vents determined by the effluent sampling and analysis program (ODCMS Table 4.8.C.1) in pCi. Release shall be cumulative over the calendar quarter or year, as appropriate.
q~v= The release of radionuclide, i, in gaseous effluents from the auxiliary boiler stack releases, determined by the oil sampling and analysis program (ODCMS Table 4.8.C.1) in pCi. Release shall be cumulative over the calendar quarter or year, as appropriate.
Page 34 of 62, Rev. 13 TABLE IV.C.1 Ri CONSTANTS INGESTION PATHWAY (m2 (mrem/yr) per gCi/sec)*
Infant Infant Infant T Radionuclide Infant Bone Infant Liver Thyroid Infant Kidney Infant Lung Infant GI-LLI Skin Body H-3 no data 1.30E+03. 1.30E+03 1.30E+03 1.30E+03 1.30E+03 no data 1.30E+03 C-14 1.26E+09 2.70E+08 2.70E+08 2.70E+08 2.70E+08 2.70E+08 no data 2.70E+08 NA-24 4.48E+06 4.48E+06 4.48E+06 4.48E+06 4.48E+06 4.48E+06 no data 4.48E+06 P-32 4.74E+10 2.79E+09 no data no data no data 6.41 E+08 no data 1.84E+09 CR-51 no data no data 3.35E+04 .7.32E+03 6.51 E+04 1.50E+06 no data 5.13E+04 MN-54 no data 1.93E+07 no data 4.28E+06 no data 7.09E+06 no data 4.38E+06 FE-55 7.09E+07 4.58E+07 no data no data 2.24E+07 5.81E+06 no data 1.22E+07 MN-56 no data 9.24E-03 no data 7.94E-03 no data 8.39E-01 no data 1.59E-03 CO-58 no data 9.57E+06 no data no data no data 2.39E+07 no data 2.39E+07 FE-59 7.92E+07 1.38E+08 no data no data 4.09E+07 6.61 E+07 no data 5.45E+07 CO-60 no data 4.69E+07 no data no data no data 1.12E+08 no data 1.11E+08 NI-63 1.88E+10 1.17E+09 no data no data no data 5.80E+07 no data 6.54E+08 CU-64 no data 5.42E+04 no data 9.17E+04 no data 1.11E+06 no data 2.51E+04 NI-65 1.03E+00 1.16E-01 no data. no data no data 8.85E+00 no data 5.29E-02 ZN-65 2.69E+09 9.22E+09 no data 4.47E+09 no data 7.78E+09 no data 4.25E+09 ZN-69 3.09E+04 5.56E+04 no data 2.31E+04 no data 4.54E+06 no data 4.14E+03 BR-83 no data no data no data no data no data no data no data 1.20E-01 BR-84 no data no data no data no data no data no data no data 1.64E-23 BR-85 no data no data no data no data no data no data no data no data RB-86 no data 6.69E+09 no data no data no data 1.71 E+08 no data 3.31E+09 12.200 RB-88 no data 5.60E-45 no data no data no data 5.45E-45 no data 3.07E-45 0 RB-89.
no data 9.86E-53 no data no data no data 3.36E-53 no data 6.79E-53 SR-89 4.58E+09 no data no data no data no data 9.42E+07 no data 1.31E+08 SR-90 6.55E+10 no data no data no data no data 8.18E+08 no data 1.67E+10 Y-90 1.99E+02 no data no data no data no data 2.74E+05 no data 5.33E+00 SR-91 7.94E+04 no data no data no data no data 9.40E+04 no data 2.87E+03 Y-91 M 1.66E-19 no data no data no data no data 5.53E-16 no data 5.65E-21 Y-91 2.77E+04 no data no data no data no data 1.98E+06 no data 7.37E+02 SR-92 1.36E+00 no data no data no data no data 1.47E+01 no data 5.05E-02 Y-92 1.57E-04 no data no data no data no data 3.01 E+00 no data 4.43E-06 Y-93 6.31 E-01 no data no data no data no data 4.98E+03 no data 1.72E-02 NB-95 1.98E+05 8.16E+04 no data 5.85E+04 no data 6.89E+07 no data 4.72E+04 ZR-95 2.62E+03 6.40E+02 no data 6.89E+02 no data 3.19E+05 no data 4.54E+02 ZR-97 1.19E+00 2.04E-01 no data 2.05E-01 no data 1.30E+04 no data 9.31 E-02 MO-99 no data 6.07E+07 no data 9.07E+07 no data 2.OOE+07 no data 1.18E+07 TC-99M 8.04E+00 1.66E+01 no data 1.78E+02 8.67E+00 4.82E+03 no data 2.14E+02 TC-101 7.44E-60 9.38E-60 no data 1.11E-58 5.11E-60 1.59E-57 no data 9.28E-59 RU-103 2.97E+03 no data no data 6.18E+03 no data 3.61E+04 no data 9.93E+02 RU-105 2.36E-03 no data no data 1.73E-02 no data 9.38E-01 no data 7.94E-04 RU-106 9.54E+04 no data no data 1.13E+05 no data 7.24E+05 no data 1.19E+04 AG-110M 1.87E+08 1.37E+08 no data 1.95E+08 no data 7.09E+09 no data 9.04E+07 SB-124 5.31E+07 7.81E+05 1.41 E+05 no data 3.32E+07 1.64E+08 no data 1.64E+07 SB-125 5.23E+07 5.06E+05 6.55E+04 no data 3.03E+07 6.98E+07 no data 1.08E+07 TE-125M 5.68E+07 1.90E+07 1.91E+07 no data no data 2.71 E+07 no data 7.68E+06
Page 35 of 62, Rev. 13 TE-127M 1.82E+08 6.03E+07 5.26E+07 4.48E+08 no data 7.34E+07 no data 2.20E+07 TE-127 1.85E+03 6.19E+02 1.50E+03 4.51 E+03 no data 3.88E+04 no data 3.97E+02 TE-129M 1.84E+08 6.32E+07 7.08E+07 4.61 E+08 no data 1.10E+08 no data 2.84E+07 TE-129 7.99E-10 2.76E-10 6.70E-10 1.99E-09 no data 6.39E-08 no data 1.87E-10 1-130 1.04E+06 2.28E+06 2.56E+08 2.51 E+06 no data 4.89E+05 no data 9.17E+05 1-131 7.97E+08 9.39E+08 3.08E+ 11 1.10E+09 no data 3.35E+07 no data 4.13E+08 TE-131M 9.87E+05 3.97E+05 8.05E+05 2.73E+06 no data 6.69E+06 no data 3.28E+05 TE-131 1.03E-32 3.79E-33 9.15E-33 2.62E-32 no data 4.14E-31 no data 2.88E-33 1-132 3.66E-01 7.43E-01 3.48E+01 8.29E-01 no data 6.02E-01 no data 2.65E-01 TE-132 6.17E+06 3.05E+06 4.51 E+06 1.91 E+07 no data 1.13E+07 no data 2.85E+06 1-133 1.06E+07 1.54E+07 2.81 E+09 1.81 E+07 no data 2.61E+06 no data 4.52E+06 CS-134 1.90E+10 3.54E+10 no data 9.11E+09 3.73E+09 9.61 E+07 no data 3.57E+09 1-134 4.81E-12 9.86E-12 2.30E-10 1.10E-11 no data 1.02E-11 no data 3.51E-12 1-135 3.21E+04 6.39E+04 5.73E+06 7.12E+04 no data 2.31 E+04 no data 2.33E+04 CS-136 5.80E+08 1.71 E+09 no data 6.80E+08 1.39E+08 2.59E+07 no data 6.37E+08 12.200 CS-1 37 2.77E+10 3.24E+10 no data 8.71 E+09 3.53E+09 1.01 E+08 no data 2.30E+09 8 CS-138 2.58E-23 4.20E-23 no data 2.09E-23 3.27E-24 6.71 E-23 no data 2.04E-23 BA-139 1.26E-07 8.32E-11 no data 5.OOE-i 1 5.04E-11 7.95E-06 no data 3.63E-09 BA-140 7.09E+07 7.09E+04 no data 1.68E+04 4.35E+04 1.74E+07 no data '3.65E+06 LA-140 1.18E+01 4.67E+00 no data no data no data 5.49E+04 no data 1.20E+00 BA-141 1.41E-45 9.65E-49 no data 5.80E-49 5.87E-49 1.72E-44 no data 4.44E-47 CE-141 1.42E+04 8.69E+03 no data 2.68E+03 no data 4.49E+06 no data 1.02E+03 BA-142 7.43E-80 6.18E-83 no data 3.56E-83 3.74E-83 3.07E-79 no data 3.66E-81 LA-142 4.99E-11 1.83E-11 no data no data no data 3.11E-06 no data 4.39E-12 CE-143 1.16E+02 7.70E+04 no data 2.24E+01 no data 4.49E+05 no data 8.78E+00 PR-143 4.38E+02 1.64E+02 no data 6.09E+01 no data 2.31 E+05 no data 2.17E+01 "CE-144 1.14E+06 4.68E+05 no data 1.89E+05 no data 6.55E+07 no data 6.40E+04 PR-144 1.70E-53 6.59E-54 no data 2.39E-54 no data 3.07E-49 no data 8.58E-55 ND-147 2.58E+02 2.65E+02 no data 1.02E+02 no data 1.68E+05 no data 1.63E+01 W-187 1.79E+04 1.24E+04 no data no data no data 7.31E+05 no data 4.30E+03 NP-239 1.06E+01 9.51 E-01 no data 1.90E+00 no data 2.75E+04 no data 5.37E-01 NP-237 5.33E+07 3.53E+06 no data 1.41 E+07 no data 1.83E+06 no data 2.33E+06 NP-238 1.02E+02 2.56E+00 no data 5.58E+00 no data 3.42E+04 no data 1.57E+00
- Tritium Ri values in units of mrem/yr per gCi/m 3
Page 36 of 62, Rev. 13 TABLE IV.C.2 Ri CONSTANTS INHALATION PATHWAY (mrem/yr per gCi/m')
Infant Infant Infant T Radionuclide Infant Bone Infant Liver Thyroid Infant Kidney Infant Lung Infant GI-LLI Skin Body Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Skin T Body H-3 no dara 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 no data 6.47E+02 C-14 2.65E+04 5.31E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31E+03 no data 5.31E+03 NA-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 no data 1.06E+04 P-32 2.03E+06 1.12E+05 no data no data no data 1.61 E+04 no data 7.74E+04 CR-51 no data no data 5.75E+01 1.32E+01 1.28E+04 3.57E+02 no data 8.95E+01 MN-54 no data 2.53E+04 no data 4.98E+03 1.OOE+06 7.06E+03 no data 4.98E+03 FE-55 1.97E+04 1.18E+04 no data no data 8.69E+04 1.10E+03 no data 3.33E+03 MN-56 no data 1.54E+00 no data 1.10E+00 1.25E+04 7.17E+04 no data 2.21E-01 CO-58 no data 1.22E+03 no data no data 7.77E+05 1.11E+04 no data 1.82E+03 FE-59 1.36E+04 2.35E+04 no data no data 1.02E+06 2.48E+04 no data 9.48E+03 CO-60 no data 8.02E+03 no data no data 4.51E+06 3.19E+04 no data 1.18E+04 NI-63 3.39E+05 2.04E+04 no data no data 2.09E+05 2.42E+03 no data 1.16E+04 CU-64 no daa 1.88E+00 no data 3.98E+00 9.30E+03 1.50E+04 no data 7.74E-01 NI-65 2.39E+00 2.84E-01 no data no data 8.12E+03 5.01E+04 no data 1.23E-01 ZN-65 1.93E+04 6.26E+04 no data 3.25E+04 6.47E+05 5.14E+04 no data 3.11E+04 ZN-69 5.39E-02 9.67E-02 no data 4.02E=02 1.47E+03 1.32E+04 no data 7.18E-03 BR-83 no data no data no data no data no data no data no data 3.81 E+02 BR-84 no data no data no data no data no data no data no data 4.OOE+02 BR-85 no data no data no data no data no data no data no data 2.04E+01 BR-86 no data 1.90E+05 no data no data no data 3.04E+03 no data 8.82E+04 12.200 BR-88 no data 5.57E+02 no data no data no data 3.39E+02 no data 2.87E+02 BR-89 no data 3.21E+02 no data no data no data 6.82E+01 no data 2.06E+02 SR-89 3.98E+05 no data no data no data 2.03E+06 6.40E+04 no data 1.14E+04 SR-90 4.09E+07 no data no data no data 1.12E+07 1.31 E+05 no data 2.59E+06 Y-90 3.29E=03 no data no data no data 2.69E+05 1.04E+05 no data 8.82E+01 SR-91 9.56E+01 no data no data no data 5.26E+04 7.34E+04 no data 3.46E+00 Y-91M 4.07E-01 no data no data no data 2.79E+03 2.35E+03 no data 1.39E-02 Y-91 5.88E+05 no data no data no data 2.45E+06 7.03E+04 no data 1.57E+04 SR-92 1.05E+01 no data no data no data 2.38E+04 1.40E+05 no data 3.91E-0 1 Y-92 1.64E+01 no data no data no data 2.45E+04 1.27E+05 no data 4.61E-01 Y-93 1.50E+02 no data no data no data 7.64E+04 1.67E+05 no data 4.07E+00 NB-95 1.57E+04 6.43E+03 no data 4.72E+03 4.79E+05 1.27E+04 no data 3.78E+03 ZR-95 1.15E+05 2.79E+04 no data 3.11E+04 1.75E+06 2.17E+04 no data 2.03E+04 ZR-97 1.50E+02 2.56E+01 no data 2.59E+01 1.10E+05 1.40E+05 no data 1.17E+01 MO-99 no data 1.65E+02 no data 2.65E+02 1.35E+05 4.87E+04 no data 3.23E+01 TC-99M 1.40E-03 2.88E-03 no data 3.11E-02 8.11 E+02 2.03E+03 no data 3.72E-02 TC-101 6.51E-05 8.23E-05 no data 9.79E-04 5.84E+02 8.44E+02 no data 8.12E-04 RU-103 2.02E+03 no data no data 4.24E+03 5.52E+05 1.61 E+04 no data 6.79E+02 RU-105 1.22E+00 no data no data 8.99E-01 1.57E+04 4.84E+04 no data 4.10E-01 RU-106 8.68E+04 no data no data 1.07E+05 1.16E+07 1.64E+05 no data 1.09E+04 AG-110M 9.98E+03 7.22E+03 no data 1.09E+04 3.67E+06 3.30E+04 no data 5.OOE+03 TE-125M 4.76E+03 1.99E+03 1.62E+03 no data 4.47E+05 1.29E+04 no data 6.58E+02 TE-127M 1.67E+04 6.90E+03 4.87E+03 3.75E+04 1.31 E+06 2.73E+04 no data 2.07E+03 TE-127 2.23E+00 9.53E-01 1.85E+00 4.86E+00 1.04E+04 2.44E+04 no data 4.89E-01 TE-129M 1.41 E+04 6.09E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 no data 2.23E+03 TE-129 7.88E-02 3.47E-02 6.75E-02 1.75E-01 3.OOE+03 2.63E+04 no data 1.88E-02
Page 37 of 62, Rev. 13 1-130 6.36E+03 1.39E+04 1.60E+06 1.53E+04 no data 1.99E+03 no data 5.57E+03 1-131 3.79E+04 4.44E+04 1.48E+07 5.18E+04 no data 1.06E+03 no data 1.96E+04 TE-131M 1.07E+02 5.50E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 no data 3.63E+01 TE-131 1.74E-02 8.22E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 no data 5.00E-03 1-132 1.69E+03 3.54E+03 1.69E+05 3.95E+03 no data 1.90E+03 no data 1.26E+03 TE-132 3.72E+02 2.37E+02 2.79E+02 1.04E+03 3.40E+05 4.41 E+04 no data 1.76E÷02 1-133 1.32E+04 1.92E+04 3.56E+06 2.24E+04 no data 2.16E+03 no data 5.60E+03 CS-134 3.96E+05 7.03E+05 no data 1.90E+05 7.97E+04 1.33E+03 no data 7.45E+04 1-134 9.21E+02 1.88E+03 4.45E+04 2.09E+03 no data 1.29E+03 no data 6.65E+02 1-135 3.86E+03 7.60E+03 6.96E+05 8.47E+03 no data 1.83E+03 no data 2.77E+03 CS-136 4.83E+04 1.35E+05 no data 5.64E+04 1.18E+04 1.43E+03 no data 5.29E+04 CS-137 5.49E+05 6.12E+05 no data 1.72E+05 7.13E+04 1.33E+03 no data 4.55E+04 CS-1 38 5.05E+02 7.81E+02 no data 4.1 OE+02 6.54E+01 8.76E+02 no data 3.98E+02 BA-139 1.48E+00 9.84E-04 no data 5.92E-04 5.95E+03 5.10E+04 no data 4.30E-02 BA-140 5.60E+04 5.60E+01 no data 1.34E+01 1.60E+06 3.84E+04 no data 2.90E+03 LA-140 5.05E+02 2.OOE+02 no data no data 1.68E+05 8.48E+04 no data 5.15E+01 BA-141 1.57E-01 1.08E-04 no data 6.50E-05 2.97E+03 4.75E+03 no data 4.97E-03 CE-141 2.77E+04 1.67E+04 no data 5.25E+03 5.17E+05 2.16E+04 no data 1.99E+03 BA-142 3.98E-02 3.30E-05 no data 1.90E-05 1.55E+03 6.93E+02 no data 1.96E-03 LA- 142 1.03E+00 3.77E-01 no data no data 8.22E+03 5.95E+-04 no data 9.04E-02 CE-143 2.93E+02 1.93E+02 no data 5.64E+01 1.16E+05 4.97E+04 no data 2.21E+01 PR-143 1.40E+04 5.24E+03 no data 1.97E+03 4.33E+05 3.72E+04 no data 6.99E+02 CE-144 3.19E+06 1.21E+06 no data 5.38E+05 9.84E+06 1.48E+05 no data 1.76E+05 12.200 PR-144 4.79E-02 1.85E-02 no data 6.72E-03 1.61 E+03 4.28E+03 no data 2.41E-03 8 ND-147 7.94E+03 8.13E+03 no data 3.15E+03 3.22E+05 3.12E+04 no data 5.00E+02 W-187 1.30E+01 9.02E+00 no data no data 3.96E+04 3.56E+04 no data 3.11E+00
'NP-239 3.71 E+02 3.32E+01 no data 6.62E+01 5.95E+04 2.49E+04 no data 1.88E+01 U-232 3.60E+08 no data no data 3.36E+07 2.09E+09 6.10E+04 no data 2.98E+007 U-233 7.62E+07 no data no data 1.53E+07 4.98E+08 5.64E+04 no data 5.36E+06 U-234 7.31E+07 no data no data 1.50E+07 4.89E+08 5.53E+04 no data 5.25E+06 U-235 7.01E+07 no data no data 1.41E+07 4.59E+08 7.03E+04 no data 4.93E+06 U-236 7.01E+07 no data no data 1.44E+07 4.69E+08 5.19E+04 no data 5.04E+06 U-237 4.55E+02 no data no data 1.13E+03 1.28E+05 1.83E+04 no data 1.21 E+02 U-238 6.71E+07 no data no data 1.32E+07 4.28E+08 4.96E+04 no data 4.61E+06 NP-237 4.03E+09 2.39E+09 no data 1.08E+09 4.89E+08 7.14E+04 no data 1.76E+08 NP-238 3.74E+03 8.47E+02 no data 2.06E+02 1.29E+05 3.61E+04 no data 5.82E+01 PU-238 3.77E+09 2.35E+09 no data 6.50E+08 1.26E+09 6.57E+04 no data 1.78E+08 PU-239 4.10E+09 2.46E+09 no data 6.93E+08 1.19E+09 5.99E+04 no data 1.88E+08 PU-240 4.10E+09 2.45E+09 no data 6.92E+08 1.19E+09 6.10E+04 no data 1.88E+08 PU-241 1.18E+08 2.59E+07 no data 1.61 E+07 1.07E+06 1.26E+03 no data 4.35E+06 PU-242 3.81 E+09 2.37E+09 no data 6.68E+08 1.14E+09 5.88E+04 no data 1.81 E+08 PU-244 4.44E+09 2.72E+09 no data 7.64E+08 1.31 E+09 8.76E+04 no data 2.07E+08 AM-241 4.41E+09 2.73E+09 no data 1.11E+09 5.68E+08 6.69E+04 no data 1.83E+08 AM-242M 4.55E+09 2.60E+09 no data 1.12E+09 2.30E+08 8.41E+04 no data 1.89E+08 AM-243 4.34E+09 2.63E+09 no data 1.08E+09 5.39E+08 7.84E+04 no data 1.78E+08 CM-242 1.79E+08 1.21E+08 no data 2.37E+07 4.16E+08 7.14E+04 no data 7.98E+06 CM-243 3.46E+09 2.13E+09 no data 5.47E+08 5.94E+08 7.03E+04 no data 1.48E+08 CM-244 2.90E+09 1.78E+09 no data 4.49E+08 5.71E+08 6.80E+04 no data 1.24E+08 CM-245 4.51 E+09 2.74E+09 no data 7.32E+08 5.49E+08 6.34E+04 no data 1.90E+08 CM-246 4.48E+09 2.74E+09 no data 7.32E+08 5.59E+08 6.23E+04 no data 1.90E+08 CM-247 4.35E+09 2.70E+09 no data 7.21 E+08 5.49E+08 8.19E+04 no data 1.86E+08 CM-248 3.61E+10 2.23E+10 no data 5.94E+09 4.52E+09 1.32E+06 no data 1.54E+09 CF-252 3.32E+09 no data no data no data 1.92E+09 2.59E+05 no data 1.41 E+08
Page 38 of 62, Rev. 13 TABLE IV.C.3 Ri CONSTANTS GROUND PLANE PATHWAY (mrem/yr per gCi/m3 )
AG-I1OM 3.44E+09 AM-241 6.85E+08 AM-242M 9.61E+07 AM-243 5.03E+09 BA-139 1.06E+05 BA-140 2.05E+07 BA-141 4.18E+04 BA-142 4 .49E+04 BR-83 4.87E+03 BR-84 2.03E+05 BR-85 no data C-14 no data CE-141 1.37E+07 CE-143 2. 31E+06 CE-144 6.96E+07 CF-252 4.83E+10 CM-242 6.85E+05 CM-243 7.05E+09 CM-244 7.84E+06 CM-245 3.67E+09 CM-246 3.86E+06 CM-247 8.51E+09 CM-248 2.63E+10 12.200 CO-58 3. 79E+08 8 CO-60 2.32E+10 CR-51 4. 66E+06 CS-134 6.91E+09 CS-136 1.50E+08 CS-137 1.30E+10 CS-138 3.59E+05 CU-64 6.07E+05 FE-55 no data FE-59 2.72E+08 H-3 no data 1-130 5.51E+06 1-131 1.73E+07 1-132 1.23E+06 1-133 2. 45E+06 1-134 4.46E+05 1-135 2.52E+06 LA-140 1.92E+07 LA-142 7.60E+05 MN-54 1.38E+09 MN-56 9.04E+05 MO-99 3.99E+06 NA-24 1.19E+07 NB-95 1.37E+08 ND-147 8.40E+06
Page 39 of 62, Rev. 13 NI-63 NI-65 2.97E+05 NP-237 5.42E+09 NP-238 4.53E+06 NP-239 1.71E+06 P-32 no data PR-143 no data PR-144 1.83E+03 PU-238 4.65E+06 PU-239 3.06E+06 PU-240 5.02E+06 PU-241 1.14E+07 PU-242 4.26E+06 PU-244 3.46E+09 RB-86 8.97E+06 RB-88 3.31E+04 RB-89 1.23E+05 RU-103 1.08E+08 RU-105 6.36E+05 RU-106 4.22E+08 SB-124 S.98E+08 SB-125 2.38E+09 SR-89 2.16E+04 SR-90 no data SR-91 2.15E+06 SR-92 7.77E+05 TC-101 2.04E+04 TC-99M 1.84E+05 TE-125M 1.55E+06 TE-127 2.98E+03 12.200 TE-127M 9.17E+04 8 TE-129 2.62E+04 TE-129M 1.98E+07 TE-131 2.92E+04 TE-131M 8.03E+06 TE-132 4.23E+06 U-232 9.12E+06 U-233 8.90E+09 U-234 2.45E+06 U-235 1.24E+10 U-236 8.13E+04 U-237 5.16E+07 U-238 4.26E+08 W-187 2.36E+06 Y-90 4.49E+03 Y-91 1.07E+06 Y-91M 1.OOE+05 Y-92 1.80E+05 Y-93 1.83E+05 ZN-65 7.46E+08 ZN-69 no data ZR-95 2.45E+08 ZR-97 2.96E+06
Page 40 of 62, Rev. 13 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:
- a. gamma air dose - IV.B.1
- b. beta air dose - IV.B.2
- c. organ dose - IV.C The projected dose calculation shall be based on expected release from plant operation. The normal release pathways result in the maximum releases from the plant. Any alternative release pathways result in lower releases and, therefore, lower doses.
IV.E Technical Requirements Manual Test Requirement (TR) 3.5.3 IV.E.1 The recombiner hydrogen analyzers currently used at Peach Bottom are Whittaker Electrochemical type. (Analyzers 4083A and 4083B on Unit 2. Analyzers 5083A and 5083B on Unit 3.)
IV.E.2 The calibration gas for the Whittaker Analyzers is 2%
Hydrogen, Balance Air.
IV.F ODCMS 4.8.C.7.1 and 4.8.C.7.2 IV.F.I 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 calculated by the equation in IV.A.2.
The dose rate from radioactive particulate release shall be determined by either of two methods. Method (a), total instantaneous release assumes that the total activity contained in the waste oil is released in the first minute of incineration. Method (b) uses the activity release over the entire time of incineration.
For normal operations, it is assumed that Method (a) will be used, since the total activity from the waste oil is expected to contribute an insignificant dose compared to the annual limits. However, in the event that the activity is significantly higher than administrative or regulatory limits, then Method (b) would be used because it is more accurate in calculating the dose rate.
Since the auxiliary boiler stacks are at approximately the same height as the reactor vents and discharge from the auxiliary boilers will also be heated, the use of the reactor vent D/Q value for the calculations is considered conservative.
Page 41 of 62, Rev. 13 IV.F.2 The dose to an individual from radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to areas at and beyond the SITE BOUNDARY from the incineration of contaminated waste oil from the auxiliary boiler stacks shall be calculated by the equation in IV.C.
V.A. ODCMS 4.8.D.1.1 and 4.8.D.1.2 V.A.I ODCMS 4.8.D.1.l The total gaseous and liquid cumulative dose contributions are limited by ODCMS 3.8.D.1 to 3.0 mrem for whole body and critical organ, and 55 mrem for the thyroid to preserve assumptions set forth in the 10CFR72.212 report for the TN-68 spent fuel casks that are stored on the Independent Spent 02.200 Fuel Storage (ISFSI) pad. Exceeding these action levels does 0 not necessarily result in the overall 40CFR190 or IOCFR72.104 requirements not being met. Further calculations are required to determine compliance.
Whole Body The whole body dose contribution from liquid and gaseous effluents shall be determined by the following method:
D WB = DT + Dr where:
DWB = whole body dose from liquid and gaseous effluents, in mrem.
D, = cumulative dose commitment to the total body from liquid effluents, in mrem (Determined by ODCM Section III.B).
Dr = gamma air dose, in mrad (Determined by ODCM Section IV.B, with mrad equivalent to mrem).
Critical organ(except thyroid)
The critical organ(except thyroid) dose contribution from liquid and gaseous effluents shall be determined by the following method:
DCo =D, +Dr +D where:
DC0 = critical organ(except thyroid) dose from liquid and gaseous effluents, in mrem.
V.A.I (Continued)
Page 42 of 62, Rev. 13 D,= cumulative dose commitment to any organ from liquid effluents, in mrem (Determined by ODCM Section IIIT.B).
Dr = gamma air dose, in mrad (Determined by ODCM Section IV.B, with mrad equivalent to mrem).
D = limiting dose to the critical organ(except thyroid),
in mrem (Determined by ODCM Section IV.C).
Thyroid The thyroid dose contribution from gaseous effluents shall be determined by the following method:
DThY= D, + Dr + D where:
DThy= thyroid dose from gaseous effluents, in mrem.
D, = cumulative dose commitment to any organ from liquid effluents, in mrem (Determined by ODCM Section III.B).
Dr = gamma air dose, in mrad (Determined by ODCM Section IV.B, with mrad equivalent to mrem) .
D = limiting dose to the thyroid, in mrem (Determined by ODCM Section IV.C).
V.A.2 ODCMS 4.8.D.1.2 The cumulative dose from all sources(i.e. gas and liquid effluents and direct radiation) is calculated by summing the individual doses obtained in ODCMS 4.8.D.1.1 for whole body (DwB) , critical organ (Dco) and thyroid(D,) with the TLD measured dose(mrem) minus the background dose.
Whole Body The cumulative whole body dose from liquid, gas and direct radiation shall be determined by the following method:
D Tota= Dw + D where:
D""" = whole body dose equivalent from all sources, in mrem.
V.A.2 (continued)
Page 43 of 62, Rev. 13 DWB = whole body dose from liquid and gaseous effluents, in mrem.
DD Dose from direct radiation, in mrem(after subtracting background).
Critical Organ(except thyroid)
The cumulative critical organ(except thyroid) dose from liquid, gas and direct radiation shall be determined by the following method:
DTOa'= Dc° + DD where:
D/],,IO = critical organ(except thyroid) dose equivalent from all sources, in mrem.
Dco = critical organ(except thyroid) dose from liquid and gaseous effluents, in mrem.
DD = Dose from direct radiation, in mrem(after subtracting background).
Thyroid The cumulative thyroid dose from gas and direct radiation shall be determined by the following method:
D&"tah = D + D Thy Th where:
DT*,a= thyroid dose equivalent from all sources, in mrem.
D7/,17= thyroid dose from gaseous effluents, in mrem.
DD = Dose from direct radiation, in mrem(after subtracting background).
The dose contribution is calculated at the discharge point for liquids and in the worst sector for gases. If necessary, the dose contribution from liquid and gas may be calculated for a real individual.
Page 44 of 62, Rev. 13 VI.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.l from the locations shown on Figures VII.A.l, VII.A.2, and VII.A.3, and shall be analyzed pursuant to the requirements of Table VII.A.l.
Page 45 of 62, Rev. 13 TABLE VII.A-l ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion I. Direct Radiation Site Boundary 1L 1,256 feet NE of site 1 set of four (4) TLDs Gamma Dose quarterly 1A 1,396 feet SE of site from each location at 2 4,661 feet SE of site least quarterly iI 2,851 feet SSE of site Gamma dose quarterly iC 4,513 feet SSE of site 1F 3,755 feet S of site 2,707 feet SSW of site TLD sites were chosen 40 7,050 feet SW of site in accordance with INN 2,547 feet WSW of site Peach Bottom ODCMS IH 3,104 feet W of site Table 4.8.E.1 Item 1.
IG 3,173 feet WNW of site Site Boundary stations lB 2,587 feet NW of site all sectors except 1E 3,136 feet NNW of site several along 02.08 1K 4604 feet SW of site Conowingo Pond. These Intermediate sectors are monitored Distance 15 19, 449 feet N of site by stations on the 22 13,230 feet NNE of site east side of Conowingo 44 27,480 feet NE of site Pond. The 5 mile 32 15, 213 feet ENE of site vicinity stations 45 18, 524 feet ENE of site cover all sectors.
14 10,397 feet E of site 17 21,966 feet ESE of site The distant and 31A 24,105 feet SE of site special interest 4K 45,721 feet SE of site stations provide 23 5,276 feet SSE of site information in 27 13, 859 feet S of site population centers and 48 25,772 feet SSW of site control locations.
3A 19, 114 feet SW of site 49 20, 673 feet WSW of site 50 25,677 feet W of site 51 20, 511 feet WNW of site 26 22, 093 feet NW of site 6B 30,538 feet NW of site 42 21, 954 feet NNW of site
Page 46 of 62, Rev. 13 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion Distant 43 26,931 feet NNE of site and 5 24,482 feet E of site Special 16 67,788 feet E of site Interest 24 58,048 feet ESE of site 2B 3,768 feet SSE of site 46 23,483 feet SSE of site 47 22,153 feet S of site 18 51,413 feet W of site 19 C 106,354 feet WNW of site II. Airborne Particulates IZ 1,396 feet SE of site Approximately 1 cfm Gross beta analysis 1B 2,587 feet NW of site continuous flow on each weekly IC 4,513 feet SSE of site through glass fiber sample. Gamma 3A 19,114 feet SW of site filter which is spectrometry shall be 5H2 C 162,565 feet NE of site collected weekly. done when gross beta exceeds ten times the These stations yearly mean of provide for coverage control station value.
of the highest annual average ground level Gross beta analysis D/Q near the site done Ž24 hr after boundary, the sampling to allow for community with the Radon and Thoron highest annual daughter decay.
average D/Q and a control location.
Gamma Spec on quarterly composite by location.
Page 47 of 62, Rev. 13 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion Iodine lz 1,396 feet SE of site A TEDA impregnated Iodine 131 weekly lB 2,587 feet NW of site flow-through IC 4,513 feet SSE of site cartridge is 3A 19,114 feet SW of site connected to air 5H2 C 162,565 feet NE of site sampler and is collected weekly at site filter change.
III. Waterborne Surface ILL C 1,256 feet NE of site Sample collected Gamma isotopic 1MM 5,470 feet SE of site from a continuous analysis monthly; water sampler, monthly. In event H-3 on quarterly sampler is composite inoperable, grab samples will be collected each calendar day until sampler returned to service.
Drinking 4L 45,721 feet SE of site Sample collected Gross beta and gamma 61 C 30,337 feet NW of site from a continuous isotopic monthly, water sampler monthly. In event H-3 on quarterly sampler is composite inoperable, weekly grab samples will be collected until sampler returned to service.
Page 48 of 62, Rev. 13 TABLE VII.A-1 ODCM - Peach Bottom Atomic Power Station Radiological Environmental Monitoring Program Pathway Station Distance and Direction Collection Method Analyses Code from PBAPS Vents and Discussion Sediment 4J 7,346 feet SE of site A sediment sample Gamma isotopic analysis is taken down each sample stream of discharge semi-annually.
IV. Ingestion Milk V C 32,736 feet W of site Sample of fresh 1-131 analyses on each J 5,119 feet W of site milk is collected sample I R 4,694 feet WSW of site from each farm U 11,414 feet SSW of site biweekly when cows Gamma isotopic analysik 02.08 are on pasture or Cs-134, -137 by (April through chemical separation October), monthly quarterly at other times.
Fish 4 7,162 feet SE of site Two species of Gamma isotopic analyses 6 C 57,347 feet NW of site recreationally on edible portions.
important fish (predator and bottom feeder) sampled in season or semiannually if not seasonal.
Food Two offsite locations of Samples of three Gamma isotopic and Products' highest predicted annual (3) different 1-131 analysis average ground level D/Q and kinds of broad one location (15-30 km leaf vegetation distance) in the least monthly when prevalent wind direction as available if milk determined using the results sampling is not of the most recent annual performed Land use Survey.
C = Control Location
Page 49 of 62, Rev. 13 FIGURE VII.A.1 ENVIRONMENTAL SAMPLING STATIONS AT SITE BOUNDARY AREA TO PEACH BOTTOM
Page 50 of 62, Rev. 13 FIGURE VII.A.2 ENVIRONMENTAL SAMPLING STATIONS AT INTERMEDIATE DISTANCES FROM PEACH BOTTOM SITE
Page 51 of 62, Rev. 13 h
FIGURE VII.A.3 ENVIRONMENTAL SAMPLING STATIONS AT REMOTE DISTANCES FROM PEACH BOTTOM SITE
Page 52 of 62, Rev. 13 GUARD BED 02.08 Figure 1
. 13 FUME HOOD EXHAUST LAB & TOILET EXHAUST NORMAL RANGE MONITOR (2AS185)
CHEM LAB - PARTICULATE
.EXHAUST
- IODINE
- NOBLE GAS TURBINE BLDG OPERATING FLOOR EXHAUST TURBINE BLDG EQUIP CELL EXHAUST TURBINE BLDG AREA EXHAUST REACTOR BLDG EQUIP CELL WIDE RANGE 02.200 EXHAUST MONITOR 8 (205845/205846)
(285185)
REACTOR BLDG EXHAUST
- PARTICULATE
- IODINE
- NOBLE GAS REFUELING FLOOR EXHAUST RADWASTE AREA EXHAUST RADWASTE BLDG EQUIP CELL EXHAUST (2)
EXELON NUCLEAR n.....
FILTER EXHAUST PBAPS UNIT 2 VENTILATION EXHAUST WASTE TREATMENT SYSTEM FAN Figure 2
13 02.200 8
Figure 3
oo C
C)
(2)
CONDENSATE STORAGE III Hl-(D 41.
CIRCULATING WATER DISCHARGE CANAL RE (OUTLET OF RBCCVA) oD t SERVICE WATER z 0 EMERGENCY SERVICE WATER - C (OUTLET OF RHR) EXELON NUCLEAR P
HIGH PRESSURE SERVICE WATER PBAPS UNITS 2 &3 LIQUID RADWASTE TREATMENT SYSTEM P
PUMP HJ
Page 56 of 62, Rev. 13 VII. Bases Liquid Effluent Release Flow Rate Determination Non-gamma emitting radionuclides (H-3, Fe-55, Sr-89/90) are not detected by the effluent monitor and , therefore, are not directly included in the release flow rate determination.
While tritium accounts for nearly all the activity released, it is not a significant contributor when determining the permissible flow rate. Examining releases over the years 2004
- 2006, the average diluted H-3 contribution to its limiting concentration in liquid effluents was 0.03%. This contribution is not expected to change significantly over time, since the concentration of H-3 in effluents can be expected to remain fairly consistent in effluent releases regardless of fuel conditions, activation product releases,
- and waste processing.
02.2008 Based on relative abundances, other non-gamma emitting radionuclides only contributed up to nearly 3 % of the concentration limit. It is reasonable to assume that the abundances of these non-gamma will remain the same relative to other fission and/or activation products under varying conditions. Therefore, under conditions of elevated effluent radionuclide levels, the gamma-emitting radionuclides can be expected to be the main contributors to limiting conditions on liquid effluent concentrations. The maximum permissible release flow rate determination methodology presented in III.A offers an additional factor of conservatism of 30 to 50 which is more than adequate to account for the non-gamma emitting radionuclides.
Site Specific Data NOTE 1 Liquid dose factors, Ai,, for section III.B were developed using the following site specific data. The liquid pathways involved are drinking water and fish.
24 1 A,,=(U/D + UF xBFj*xDFxRCxe-U = liters per year; maximum age group usage of drinking water (Reg. Guide 1.109, Table E-5).
D = 5.4; average annual dilution at Conowingo intake UP kg per year; maximum age group usage of fish (Reg. Guide 1.109, Table E-5)
B = bioaccumulation factor for nuclide, i, in
.freshwater fish. Reg. Guide 1.109, Table A-l, except P-32 which uses a value of 3.0 x 103 pCi/kg per pCi/liter.
Page 57 of 62, Rev. 13 ko 1.14 x l0' = (10' pCi/gCi x 10' ml/i )/ 8760 hr/yr) units conversion factor.
DF, dose conversion factor for nuclide, i, for the age group in total body or organ, as applicable. Reg. Guide 1.109, Table E-11, except P-32 bone which uses a value as indicated below.
3.0 x 10-5 mrem/pCi RC 1.16; reconcentration from PBAPS discharge back through PBAPS intake.
02.2008 2 decay constant for nuclide i, hr-1 The data for D, and RC were derived from data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos. 50-277 and 50-278) Radioactive Effluent Dose Assessment, Enclosure A, September 30, 1976. All other data except P-32 BF and DF were used as given in Reg.
Guide 1.109, Revision 1, October 1977. The P-32 BF and DF were used in accordance with information supplied in Branagan, E.F., Nichols, C.R., and Willis, C.A., "The Importance of P-32 in Nuclear Reactor Liquid Effluents",
NRC, 6/82. The teen and child dose factors were derived by the ratio of the adult bone dose factors in Reg. Guide 1.109 and Branagan, et al.
Page 58 of 62, Rev. 13 VII. (Cont'd)
NOTE 2 02.200 To develop constant R for the ingestion pathway 8 in section IV.C, the following site specific data were used:
R c (D/Q)=K' "'(,ý) Fm (r) (DF~Li)rs (+ f fseA" jth where:
K' 106 pCi/gCi; unit conversion factor Q =1 50 kg/day; cow's consumption rate Up = 330 l/yr; yearly milk consumption by an infant 2, = radioactive decay constant for nuclide of interest, sec-' (e.g. 9.97 x i0- 7 sec-1 for 1-131) 2 Pv 5.73 x 10-7 sec-1; decay constant for removal of activity in leaf and plant surfaces Fm stable element transfer coefficient for nuclide of interest, day/liter (e.g. 6.0 x 10-3 day/liter for 1-131) r = fraction of deposited nuclide retained in cow's feed grass, 1.0 for radioiodine; 0.2 for particulates DFLi = ingestion dose factor in infant for nuclide of interest, mrem/pCi (e.g. 1.39 x 10-2 mrem/pCi for 1-131)
=p 0.6; the fraction of the year the cow is on pasture (average of all farms) f, 0.487; the fraction of cow feed that is pasture grass while the cow is on pasture (average of all farms)
Y 0.7 kg/M2 ; the agricultural productivity of pasture feed grass 2.0 kg/m2; the agricultural productivity of stored feed
Page 59 of 62, Rev. 13 VII. (Cont'd) tf 1.73 x 105 sec (2 days); the transport time from pasture, to cow, to milk, to receptor th 7.78 x 106 sec (90 days); the transport time from pasture, to harvest, to cow, to milk, to receptor NOTE 3 02.200 To develop constant R for tritium for the 8 ingestion pathway in section IV.C, the following site specific data were used:
The concentration of tritium in milk is based on the airborne concentration rather than the deposition. The following additional constants and formula are used:
Rca(X/Q)=K'K' "F. QF U, (DFLI) [0.75(0.5/ H)]
where:
K = 103 gm/kg; a constant of unit conversion H = 14.61 gm/m 3 ; absolute humidity of the atmosphere 0.75 = the fraction of total feed that is water 05 = the ratio of the specific activity of the feed grass water to the atmospheric water The pathway is the grass-cow-milk ingestion pathway.
These data were derived from data published in Peach Bottom Atomic Power Station Units 2 and 3 (Docket Nos.
50-277 and 50-278) Radioactive Effluent Dose Assessment, Enclosure A, September 30, 1976. All other data were used as given in Reg. Guide 1.109, Revision 1, October 1977.
ODCMS 4.8.B.2.1, Licquid Pathway Dose Calculations The equations for calculating the doses due to the actual release rates of radioactive materials in liquid effluents were developed from the methodology provided in 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 NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", October 1978.
Page 60 of 62,. Rev. 13 ODCMS 4.8.C.1.1 and 4.8.C.1.2 Dose Rate Noble Gases The equations for calculating the dose rate due to the actual release rates of radioactive noble gases in gaseous effluents were developed from the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of .Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",
August 1978, and the atmospheric dispersion model presented in Information Requested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. The specified equations provide for determining the dose rates in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.
The dose rate due to noble gas release as calculated by the Gross Release Method is much more conservative than the dose calculated by the Isotopic Analysis Method.
Assuming the release rates given in Radioactive Effluent 02.200 Dose Assessment, September 30, 1976, the values 8 calculated by the Gross Release Method for total body dose rate and skin dose rate are 6.0 times and 5.7 times, respectively,, the values calculated by the Isotopic Analysis Method.
Dose Rate 1-131, 1-133, Tritium and Radioactive Material in Particulate Form.
The model Technical Specification LCO of NUREG-0133 for all radionuclides and radioactive materials in particulate form and radionuclides other than noble gases requires that the instantaneous dose rate be less than the equivalent of 1500 mrem per year.
The release data from 1994 to 1996 were evaluated and the critical organs were determined to be the child thyroid or teenager lung. The child thyroid dose rate is limiting when iodine releases exceed 10 percent of the total release rates. The teenager lung dose rate is limiting when iodine is either not present or a small fraction of the total release.
Because of good fuel performance the amount of 1-131 released has decreased. The thyroid may not be the critical organ. When it is not clear which organ dose is limiting, doses for the child thyroid and teenage lung are calculated.
Page 61 of 62, Rev. 13 ODCMS 4.8.C.2.1 Dose 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 Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, NUREG-0133 "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", August 1978, and the atmospheric dispersion model presented in Information Requested in Enclosure 2 to letter from George Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. The specified equations provide for determining the air doses in areas at and beyond the SITE BOUNDARY based upon the historical average atmospheric conditions.
The dose due to noble gas releases as calculated by the Gross Release Method is much more conservative than the dose calculated by the 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.
ODCMS 4.8.C.3.1 Dose, Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form The equation for calculating the doses due to the actual release of 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 Requested in Enclosure 2 to Letter from George Lear to E. G. Bauer dated February 17, 1976, September 30, 1976. These equations provide for determining the actual doses based upon the historical average atmospheric conditions.
Page 62 of 62, Rev. 13 VII. (Cont'd)
Compliance with the 10 CFR 50 limits for radioiodines, 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 infant thyroid, infant liver and infant bone dose. These organs were determined to be the critical organs based on the release data from 1994 to 1996.
Because of a decrease in the amount of 1-131 released, the thyroid may not be the critical organ. The isotopic analysis method is used to calculate dose to the infant thyroid, infant liver and infant bone.
APPENDIX A RADIOACTIVE EFFLUENTS CONTROLS PROGRAM CONTAINING OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS (ODCMS) AND BASES FOR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 REVISION 13.
RADIOACTIVE EFFLUENTS CONTROLS PROGRAM TABLE OF CONTENTS
- 3. 8.A Definitions ....................................... ODCM 3.8.A-1 3 .8.B Liquid Radwaste Effluents ......................... ODCM 3.8.B-1 3 .8.C Gaseous Effluents ................................. ODCM 3.8.C-1 3 .8.D 40 CFR 190 and 10 CFR 72.104 ...................... ODCM 3.8.D-1 3 .8.E Radiological Environmental Monitoring ............. ODCM 3.8.E-1 3 .10 Reporting Requirements ............................ ODCM 3.10-1 B 3.8 ODCM Specifications Bases ......................... ODCM B 3.8-1 PBAPS Units 2 and 3 ODCM 3. 8 Revision 13
Definitions 3.8.A ODCMS 3.8.A Definitions
NOTE-------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Offsite Dose Calculation Manual Specifications and Bases.
Term Definition FUNCTIONAL TESTS A FUNCTIONAL TEST is the manual operation or initiation of a system, subsystem, or component to verify that it functions within 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).
OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and all necessary attendant instrumentation, controls, normal and emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
GASEOUS RADWASTE Any system designed and installed to reduce TREATMENT SYSTEM radioactive gaseous effluents by collecting 02.200 primary coolant system off gases from the main 8 condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
INSTRUMENT CALIBRATION An INSTRUMENT CALIBRATION means the adjustment of an instrument signal output so that it corresponds, within acceptable range, and accuracy, to a known value(s) of the parameter, which the instrument monitors. The INSTRUMENT CALIBRATION shall encompass the 02.200 0 entire instrument including the sensors and alarm, interlock and/or trip functions and shall include the INSTRUMENT FUNCTIONAL TEST.
The known value of the parameter shall be injected into the instrument as close to the primary sensor as practicable.
PBAPS Units 2 and 3 ODCM 3.8.A-1 Revision 13
Definitions 3.8.A ODCMS 3.8.A Definitions (continued)
INSTRUMENT CHECK An INSTRUMENT CHECK is a qualitative 02.2008 determination of acceptable FUNCTIONALITY by observation of instrument behavior during operation. This determination shall include, where possible, comparison of the instrument with other independent instruments measuring the same variable.
INSTRUMENT FUNCTIONAL An INSTRUMENT FUNCTIONAL TEST means the TEST injection of a simulated signal into the instrument as close to the primary sensor as practicable to verify the FUNCTIONALITY 02.200 including alarm and/or trip functions and 8 channel failure trips.
MEMBERS OF THE PUBLIC MEMBERS OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE Contains the current methodology and CALCULATION MANUAL parameters used in the calculation of offsite doses resulting from radioactive gaseous and 02.200 liquid effluents in the calculation of gaseous 0 and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program.
FUNCTIONAL- FUNCTIONALITY An attribute of SSCs that is not controlled by TS. An SSC is functional or has functionality when it is capable of performing its specified function, as set forth in the CLB.
Functionality does not apply to specified 02.200 0 safety functions, but does apply to the ability of non-TS SSCs to perform other specified functions that have a necessary support function.
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.
PBAPS Units 2 and 3 ODCM 3.8.A-2 Revision 13
Definitions 3.8.A 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 channel response when the channel sensor is exposed to a 02.200 source of increased radioactivity.
8 Figure 3.8.A.l SITE BOUNDARY (including gaseous and liquid effluent release points)
PBAPS Units 2 and 3 ODCM 3.8.A-3 Revision 13
Liquid Radwaste Effluents 3.8.B.1 3.8.B 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:
- a. 10 times the concentration specified in 10 CFR 20 Appendix B, Table 2, Column 2 for radionuclides other than noble gases; and
- b. 2 X 10-4Ci/ml total activity concentration for all dissolved or entrained noble gases.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Concentration of A.1 Initiate actions to Immediately radioactive material decrease the release released to areas at rate of radioactive or beyond the SITE materials to restore BOUNDARY exceeding concentration to limits, within limits.
OR Immediately A.2 Initiate actions to increase the dilution 02.200 flow rate to restore 0
concentration within limits.
OR Immediately A.3 Initiate actions to decrease the release rate of radioactive materials and increase the dilution flow rate to restore concentration within limits.
PBAPS Units 2 and 3 ODCM 3.8.3-1 Revision 13
Liquid Radwaste Effluents 3.8.B.1 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.1.l Take a sample of each batch of Prior to each liquid effluent and analyze for the release 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.1.2 Record radioactive concentrations During each and volume before dilution of each release batch of liquid effluent released, the average dilution flow, and length of time over which each discharge occurred.
ODCMS 4.8.B.1.3 Perform radioactive liquid waste In accordance sampling and activity analysis. with Table 4.8.B.1 PBAPS Units 2 and 3 ODCM 3.8.B-2 Revision 13
Liquid Radwaste Effluents 3.8.B.1 Table 4.8.B.1 (Page 1 of 2)
Radioactive Liquid Waste Sampling and Analysis SAMPLE TYPE SAMPLE SAMPLE ANALYSIS SAMPLE LOWER FREQUENCY LIMIT OF DETECTION (LLD)
(a), (d), (e)
Waste Tank to Each batch Quantitative 5 X 10-tHCi/ml be released (b) Analysis of Identifiable Gamma Emitters 1-131 1 X 10-lOCi/ml Proportional 31 days (c) Fe-55 1 X 10-lgCi/ml Composite of Batches Tritium 1 X 10RCi/ml Gross Alpha 1 X 10-7Ci/ml Proportional 31 days (c) Sr-89 5 X 0 -8 gCi/ml Composite of Batches Sr-90 5 X 10'gCi/ml One Batch 31 days Dissolved noble 1 X l0 5 Ci/ml gases (a) The Sample Lower Limit of Detection is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. The values for the lower limit of detection are based on a 95% confidence level.
(b) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, each batch shall be isolated and thoroughly mixed to assure representative sampling.
(c) A composite sample is one in which the quantity of the sample is proportional to the quantity of liquid waste discharged and in which the method of sampling results in a sample representative of the liquids released.
PBAPS Units 2 and 3 ODCM 3.8.B-3 Revision 13
Liquid Radwaste Effluents 3.8.B.1 Table 4.8.B.1 (Page 2 of 2)
Radioactive Liquid Waste Sampling and Analysis (d) The principal gamma emitters for which the minimum detectable level specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level. When unusual circumstances result in sample detectable limits higher than required, the reasons shall be documented in the Radioactive Effluent Release Report. The values listed are believed to be attainable.
(e) Certain mixtures of radionuclides may cause interference in the measurement of individual radionuclides at their detectable limit especially if other radionuclides are at much higher concentrations. Under these circumstances use of known ratios of radionuclides will be appropriate to calculate the levels of such radionuclides.
PBAPS Units 2 and 3 ODCM 3.8.B-4 Revision 13
Liquid Radwaste Effluents 3.8.B.2 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.2 The dose or dose commitment to a MEMBER OF THE PUBLIC 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. < 3.0 mrem to the total body and < 10.0 mrem to any organ during any calendar quarter; and
- b. < 6.0 mrem to the total body and < 20.0 mrem to any organ during any calendar year.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated dose A.1 Submit a Special report 31 days from the release to the NRC that will of radioactive identify cause(s) for materials in exceeding limits, liquid effluents action(s) taken exceeds required to reduce releases of limits, radioactive materials in liquid effluents, corrective action(s) 02.2008 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.
PBAPS Units 2 and 3 ODCM 3.8.B-5 Revision 13
Liquid Radwaste Effluents 3.8.B.2 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.2.1 Determine cumulative dose contributions 31 days in accordance with the methodology and parameters in the ODCM.
PBAPS Units 2 and 3 ODCM 3.8.B-6 Revision 13
Liquid Radwaste Effluents 3.8.B.3 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.3 The following conditions shall be met:
- a. Dilution water flow rates necessary to satisfy requirements of ODCMS 3.8.B.1 shall be maintained;
- b. The gross activity monitor and the flow monitor on 02.200 8
the waste effluent line shall be FUNCTIONAL; and
- c. The liquid effluent control monitor shall be set in accordance with methodology and parameters in the ODCM to alarm and automatically close the waste discharge valve prior to exceeding limits in 02.200 ODCMS 3.8.B.1; and 0
02.200 d. The service water, emergency service water, and 8
high pressure service water effluent line radiation monitors shall be FUNCTIONAL.
APPLICABILITY: During release of radioactive wastes.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Gross activity A.1 Initiate action to Immediately monitor on the restore monitor .to waste activity FUNCTIONAL status.
line inoperable.
AND A.2 Analyze two Prior to independent samples release of tank's contents.
02.200 8 AND A.3 Perform independent Prior to verification of the release release rate calculations and discharge line valve line-up using at least two technically qualified members of the facility staff.
PBAPS Units 2 and 3 ODCM 3.8.B-7 Revision 13
Liquid Radwaste Effluents 3.8.B.3 flflMPF~dSATnPV MFA~I Pg~ (Cr~n+-inij~d'~
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Flow monitor on B.1 Initiate action to Immediately the waste effluent restore monitor to line inoperable. FUNCTIONAL status.
AND B.2 --------- NOTE-------
Pump performance curves 02.200 may be used to estimate 0
flow.
Estimate waste effluent 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> line flow rate.
AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter C. Required C.1 Suspend release of Immediately Compensatory radioactive effluents Measures and via this pathway.
associated Completion Time of Condition A or B not met.
OR Dilution water flow rates not satisfying requirements of ODCMS 3.8.B.1.
D. Radiation monitor D.1 Collect grab samples and At least once on service water, analyze for radioactivity per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 02.200 emergency service at a lower limit of 0 water, or high detection or no more than pressure service 107 microCurie/ml.
water effluent line inoperable. I PBAPS Units 2 and 3 ODCM 3.8.B-8 Revision 13
Liquid Radwaste Effluents 3.8.B.3 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME E. Liquid radwaste E.l Submit a Special Report effluents to the NRC to determine 02.2008 radiation monitors the reason the inoperable for > inoperability was not 30 days. corrected in a timely manner.
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.1 Perform INSTRUMENT CHECK of liquid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> radwaste effluents radiation monitor. during release ODCMS 4.8.B.3.2 Perform INSTRUMENT CHECK of liquid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> effluent flow monitor. during release ODCMS 4.8.B.3.3 Perform INSTRUMENT FUNCTIONAL TEST of 3i days liquid radwaste effluents radiation monitor, including FUNCTIONALITY demonstration of the radwaste 02.2008 discharge automatic isolation valve and control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.
ODCMS 4.8.B.3.4 Perform SOURCE CHECK of liquid 92 days 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.
PBAPS Units 2 and 3 ODCM 3.8.B-9 Revision 13
Liquid Radwaste Effluents 3.8.B.3 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.6 Perform INSTRUMENT CALIBRATION of the liquid effluents flow monitor. 12 months ODCMS 4.8.B.3.7 Perform INSTRUMENT CHECK of service 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> water effluent line radiation during monitor. release ODCMS 4.8.B.3.8 Perform INSTRUMENT FUNCTIONAL TEST of service water effluent line radiation monitor, including FUNCTIONALITY demonstration of the control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.
ODCMS 4.8.B.3.9 Perform SOURCE CHECK of service water 31 days 02.2008 effluent line radiation monitor.
ODCMS 4.8.B.3.10 Perform INSTRUMENT CALIBRATION of the service water effluent line radiation monitor with a known radiation source.
ODCMS 4.8.B.3.11 Perform INSTRUMENT CHECK of emergency 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> service water effluent line radiation during monitor. release ODCMS 4.8.B.3.12 Perform INSTRUMENT FUNCTIONAL TEST of 92 days emergency service water effluent line radiation monitor, including FUNCTIONALITY demonstration of the control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.
PBAPS Units 2 and 3 ODCM 3.8.B-10 Revision 13
Liquid Radwaste Effluents 3.8.B.3 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.3.13 Perform SOURCE CHECK of emergency service water effluent line radiation 31 days monitor.
ODCMS 4.8.B.3.14 Perform INSTRUMENT CALIBRATION of the 18 months emergency service water effluent line radiation monitor with a known radiation source.
ODCMS 4.8.B.3.15 Perform INSTRUMENT CHECK of high 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pressure service water effluent line during radiation monitor. release 02.200 ODCMS 4.8.B.3.16 Perform INSTRUMENT FUNCTIONAL TEST of 92 days 8 high pressure service water effluent line radiation monitor, including FUNCTIONALITY demonstration of the control room annunciation in response to alarm/trip setpoint being exceeded and an instrument INOP failure.
ODCMS 4.8.B.3.17 Perform SOURCE CHECK of high pressure 31 days service water effluent line radiation y monitor.
ODCMS 4.8.B.3.18 Perform INSTRUMENT CALIBRATION of the 18 months high pressure service water effluent line radiation monitor with a known radiation source.
PBAPS Units 2 and 3 ODCM 3.8.B-11 Revision 13
Liquid Radwaste Effluents 3.8.B.4 3.8.B Liquid Radwaste Effluents ODCMS 3.8.B.4 Liquid effluent releases shall be processed through one of the radwaste subsystems.or combination of subsystems listed below:
a.waste collector filter and demineralizer; 02.200 b.floor drain filter and demineralizer; 8
c.fuel pool filter demineralizer; d.chemical/oily waste cleanup subsystem; e.laundry drain filter APPLICABILITY: Prior to all liquid effluent release(s) whenever the release(s) would 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 COMPLETION MEASURE TIME A. Liquid waste A.1 Submit a Special Report 31 days discharged without to the NRC that includes,.
required an explanation of why processing. liquid radwaste was discharged without required processing, 02.200 identification of any 8 inoperable equipment or subsystems and the reason for the inoperability, the action taken to restore the inoperable equipment to FUNCTIONAL status, and the action(s) taken.
PBAPS Units 2 and 3 ODCM 3.8.B-12 Revision 13
Liquid Radwaste Effluents 3.8.B.4 ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.B.4.1 Project doses due to liquid 31 days effluent releases to areas at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.
ODCMS 4.8.B.4.2 Demonstrate FUNCTIONALITY of the 92 days waste collector filter and demineralizer and the floor drain filter by analyzing the liquid processed through the subsystem and determining it meets the requirements of ODCMS 3.8.B.1.
ODCMS 4.8.B.4.3 Demonstrate FUNCTIONALITY of the Prior to release fuel pool filter demineralizer of liquid by analyzing the liquid effluents processed through the subsystem processed by this and determining it meets the subsystem 02.200 requirements of ODCMS 3.8.B.1.
8 ODCMS 4.8.B.4.4 Demonstrate FUNCTIONALITY of the Prior to release chemical/oily waste cleanup of liquid subsystem by analyzing the effluents liquid processed through the processed by this subsystem and determining it subsystem meets the requirements of ODCMS 3.8.B.1.
ODCMS 4.8.B.4.5 Demonstrate FUNCTIONALITY of the Prior to release laundry drain filter by of liquid analyzing the liquid processed effluents through the subsystem and processed by this determining it meets the subsystem requirements of ODCMS 3.8.B.1.
PBAPS Units 2 and 3 ODCM 3.8.B-13 Revision 13
Gaseous Effluents 3.8.C.l 3.8.C Gaseous Effluents ODCMS 3.8.C.1 The dose rate at or beyond the SITE BOUNDARY due to radioactive materials in gaseous effluents released from the two reactors at the site shall be limited to the following:
- a. For noble gases, < 500 mrem per year to the total body and < 3000 mrem per year to the skin; and
- b. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days, < 1500 mrem per year to any organ.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Dose rates at or beyond A.1 Initiate actions Immediately the SITE BOUNDARY exceed to decrease
-02.2008 limits due to release rates to radioactive material in comply with gaseous effluents. limits.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.1.1 Verify the dose rate due to noble In accordance gases in gaseous effluents is with sampling within limits in accordance with and analysis methods and procedures of the program ODCM. specified in Table 4.8.C.1 (continued)
PBAPS Units 2 and 3 ODCM 3.8.C-1 Revision 13
Gaseous Effluents 3.8.C.1 ODCMS REQUIREMENTS (Continued)
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.1.2 Obtain representative samples and In accordance verify the dose rate due to with sampling iodine-131, iodine-133, tritium, and analysis and all radionuclides in program particulate form with half lives specified in
> 8 days in gaseous effluents are Table 4.8.C.1 within limits in accordance with the methods and procedures of the ODCM.
PBAPS Units 2 and 3 ODCM 3.8.C-2 Revision 13
Gaseous Effluents 3.8.C.1 Table 4.8.C.l (page 1 of 2)
Radioactive Gaseous Waste Sampling and Analysis from Main Stack, Vent Stacks, and Auxiliary Boiler Exhaust Stack SAMPLE TYPE SAMPLE SAMPLE ANALYSIS SAMPLE FREQUENCY LOWER LIMIT OF DETECTION (LLD)
(a) (d)
Grab Sample 31 days (b) Quantitative analysis of identifiable gamma 1X10-4gci/cc (C) emitters Grab Sample 92 days Tritium 1 X l06gCi/cc Charcoal 7 days (c) 1-131 1 X 10- 12gCi/cc(C)
Filters Particulate 7 days (c) Quantitative analysis 1 X 1O 10°Ci/cc(c)
Filters of identifiable gamma emitters 1-131 1 X 10- 2 gCi/cc(c)
Particulate 31 days Gross Alpha i X 1o-1 gci/cc Filters (composite of weekly filters)
Particulate 31 days Sr-89 1 X 10 11 gci/cc Filters (composite of Sr-90 1 X 10- 1 gCi/cc weekly filters)
Noble Gas Continuously Noble Gas Gross or y 1 X I0l6OCi/cc Monitor (Main Stack)
Noble Gas Continuously Noble Gas Gross or 1 X 10-6LCi/cc Monitor (Roof Vents)
Auxiliary Prior to Quantitative analysis 5 X 10- 7 gCi/ml Boiler Waste batch of identifiable gamma Oil Grab Sample release for emitters burn PBAPS Units 2 and 3 ODCM 3.8.C-3 Revision 13
Gaseous Effluents 3.8.C.l Table 4.8.C.1 (page 2 of 2)
Radioactive Gaseous Waste Sampling and Analysis from Main Stack, Vent Stacks, 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 1-131 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD may be increased by a factor of 10. This requirement does not apply if (1) analysis has shown that the dose equivalent 1-131 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 appropriate to calculate the levels of such radionuclides. Nuclides which are below the sample detectable limit for the analyses should not be reported as being present at the sample detectable limit level.
PBAPS Units 2 and 3 ODCM 3.8.C-4 Revision 13
Gaseous Effluents 3.8.C.2 3.8.C Gaseous Effluents ODCMS 3.8.C.2 The air dose at or beyond the SITE BOUNDARY due to noble gases in gaseous effluents released from the two reactors at the site shall be limited to the following:
- a. For gamma radiation, < 10 mrad during any calendar quarter;
- b. For beta radiation, < 20 mrad during any calendar quarter;
- c. For gamma radiation, < 20 mrad during any calendar year; and
- d. For beta radiation, < 40 mrad during any calendar year.
APPLICABILITY:At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated air dose A.1 Submit a Special 31 days at or beyond the Report to the NRC that SITE BOUNDARY from identifies causes for radioactive noble exceeding limits, gases in gaseous corrective actions effluents exceeds taken to reduce the limits, releases, and corrective actions to assure that subsequent releases are within limits.
PBAPS Units 2 and 3 ODCM 3.8.C-5 Revision 13
Gaseous Effluents 3.8 .C.2 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.2.1 Determine cumulative dose contributions 31 days for noble gases in accordance with the methodology and parameters in the ODCM.
PBAPS Units 2 and 3 ODCM 3.8.C-6 Revision 13
Gaseous Effluents 3.8 .C.3 3.8.C Gaseous Effluents ODCMS 3.8.C.3 The dose to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY from iodine-131, iodine-133, tritium and all radionuclides in particulate form, with half lives > 8 days, in gaseous effluents released from the two reactors at the site shall be limited to:
a.< 15 mrem during any calendar quarter; and b.< 30 mrem during any calendar year.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Calculated dose from A.1 Submit a Special 31 days the release of Report to the NRC that iodine-131, identifies causes for iodine-133, tritium exceeding limits, and radionuclides in corrective actions particulate form, taken, and proposed with half-lives corrective actions to
> 8 days in gaseous assure that subsequent effluents exceeds releases are within limits, limits.
PBAPS Units 2 and 3 ODCM 3.8.C-7 Revision 13
Gaseous Effluents 3.8.C.3 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.3.1 Determine cumulative dose contributions 31 days for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives > 8 days in accordance with the methodology and parameters in the ODCM.
PBAPS Units 2 and 3 ODCM 3.8.C-8 Revision 13
Gaseous Effluents 3.8.C.4 3.8.C Gaseous Effluents ODCMS 3.8.C.4 The following conditions shall be met:
- a. Main stack dilution flow shall be > 10,000 cfm;
- b. One vent stack noble gas monitor and one main 02.2008 stack noble gas monitor shall be FUNCTIONAL and set to alarm in accordance with the methodology and parameters in the ODCM;
- c. One vent stack iodine filter and one main stack iodine filter and one vent stack particulate filter and one main stack particulate filter with 02.2008 their respective flow rate monitors shall be FUNCTIONAL; and
- d. One vent stack flow rate monitor and one main 02.2008 stack flow rate monitor shall be FUNCTIONAL and set to alarm in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: During release of radioactive wastes.
PBAPS Units 2 and 3 ODCM 3.8.C-9 Revision 13
Gaseous Effluents 3.8.C.4 COMPENSATORY MEASURES
NOTE-------------------------------------
Separate condition entry is allowed for each instrument.
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. One required vent A.1 Collect two 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> stack noble gas independent grab monitor inoperable, samples from the AND affected effluent OR release pathway. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> One required main thereafter stack noble gas AND monitor inoperable.
A.2 -------- NOTE---------
Perform independent verification of the release rate calculations using at least two technically qualified members of the facility staff.
Analyze grab samples 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from from the affected time of release pathway for collection activity.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.C-10 Revision 13
Gaseous Effluents 3.8.C.4 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. One required vent B.1 Initiate action to Immediately stack iodine filter collect samples from inoperable, the affected effluent release pathway OR continuously with auxiliary sampling One required vent equipment such that stack particulate each sample period filter inoperable. duration is 02.200 approximately 7 days.
8 OR AND One required main 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after stack iodine filter B.2 Analyze collected end of each inoperable. samples. sampling period OR One required main stack particulate filter inoperable.
C. One required vent C.1 Estimate flow rate 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> stack flow rate from the affected monitor inoperable, effluent release AND pathway.
OR Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> One required main thereafter stack flow rate monitor inoperable.
D. Main off-gas stack D.1 Initiate action to re- Immediately dilution flow establish main off-gas
< 10,000 cfm. stack flow > 10,000 cfm.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.C-11 Revision 13
Gaseous Effluents 3.8.C.4 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME E. One or more E.1 Initiate a Condition Report required to explain the reason radioactive inoperability was not 02.200 8
gaseous effluent corrected in a timely monitoring manner.
instrumentation channels inoperable for
> 30 days.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 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 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 the main stack flow rate monitors.
ODCMS 4.8.C.4.3 Section Removed ODCMS 4.8.C.4.4 Perform 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 Section Removed (Continued)
PBAPS Units 2 and 3 ODCM 3.8.C-12 Revision 13
Gaseous Effluents 3.8.C.4 ODCMS REQUIREMENTS (Continued) C ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.4.6 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack noble gas radiation monitors with a known radioactive source positioned in a reproducible geometry with respect to the sensor.
ODCMS 4.8.C.4.7 Perform INSTRUMENT CALIBRATION of the 18 months vent stack and main stack flow rate monitors.
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.
ODCMS 4.8.C.4.9 Section Removed ODCMS 4.8.C.4.10 Perform SOURCE CHECK of vent stack and 92 days main stack noble gas radiation monitors.
02.200 8
ODCMS 4.8.C.4.11 Perform SOURCE CHECK of vent stack and 92 days main stack flow rate monitors.
PBAPS Units 2 and 3 ODCM 3.8.C-13 Revision 13
Gaseous Effluents 3.8.C.5 3.8.C Gaseous Effluents ODCMS 3.8,C.5 Gaseous effluents shall be processed through the Gaseous Waste Treatment System described below prior to discharge:
- a. Steam jet air ejector discharge shall be processed through the recombiner, holdup pipe, off-gas filter, and off-gas stack;
- b. Mechanical vacuum pump and gland steam exhauster discharge shall be processed through the off-gas stack;
- c. Auxiliary boiler exhaust shall be processed through the auxiliary boiler stack when burning radioactive waste oil;
- d. Reactor, turbine, radwaste, and recombiner building atmospheres shall be processed through permanently or temporarily installed equipment in the appropriate building ventilation system and the vent stack, with the exception of the following unmonitored exhausts:
- 1. Recirculation M-G set and reactor building cooling water equipment rooms;
- 2. Control room utility and toilet rooms;
- 3. Cable spread room;
- 4. Emergency switchgear rooms;
- 5. 125/250 VDC battery rooms and the 250 VDC battery rooms, and
- 6. Administration building maintenance decontamination area.
APPLICABILITY: P: *ior to all gaseous release(s) whenever the rE *lease(s) would cause the projected dose, when it averaged over 31 days to exceed 0.6 mrem to any 01 *gan (combined total from the two reactors at the sP te).
PBAPS Units 2 and 3 ODCM 3.8.C-14 Revision 13
Gaseous Effluents 3.8.C.5 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Gaseous waste A.l Submit a Special Report Immediately discharged without to the NRC that required processing. explains the reasons gaseous radwaste was discharged without processing, identifies 02.2008 inoperable equipment or subsystems and the reasons for the inoperability, identifies actions taken to restore the inoperable equipment to FUNCTIONAL status, and action(s) taken.
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 ODCM 3.8.C-15 Revision 13
Gaseous Effluents 3.8.C.5 ODCMS REQUIREMENTS (Continued)
ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.5.3 Demonstrate FUNCTIONALITY of required 92 days gaseous radioactive waste system 02.200 equipment by analyzing the gaseous waste 0
processed through the required equipment to determine it meets the requirements of ODCMS 3.8.C.1 PBAPS Units 2 and 3 ODCM 3.8.C-16 Revision 13
Gaseous Effluents 3.8.C.6 3.8.C Gaseous Effluents ODCMS 3.8.C.6 PURGING of the primary containment shall be:
- a. Through the Standby Gas Treatment System whenever 02.2008 primary containment is required to be FUNCTIONAL; and
- b. Through the Reactor Building Ventilation Exhaust System or the Standby Gas Treatment System 02.2008 whenever primary containment is not required to be FUNCTIONAL.
APPLICABILITY: During PURGING of the primary containment.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirement of A.1 Initiate action to Immediately ODCMS 3.8.C.6 not suspend PURGING.
02.2008 met.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.6.1 Verify primary containment PURGING Prior to is through required effluent release PURGING pathway of ODCMS 3.8.C.6. primary containment PBAPS Units 2 and 3 ODCM 3.8.C-17 Revision 13
Gaseous Effluents 3.8.C.7 3.8.C Gaseous Effluents ODCMS 3.8.C.7 Burning of radioactive waste oil shall be allowed:
- a. In accordance with the requirements of IOCFR20.2004.
- b. Through the Auxiliary Boilers (Common) with the exhaust stack of the affected auxiliary boiler as a release point for radioactive effluents.
- c. With the radioactive content of the oil determined prior to incineration.
- d. With the radioactive effluents from this pathway summed with other effluents from the site and reported to the Commission in the Radioactive Effluent Release Report.
APPLICABILITY: At all times COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Gaseous effluents A.1 Submit a Special Report to Immediately discharge without the NRC that explains the required processing reasons gaseous radwaste or was discharged without Gaseous effluents processing, identifies exceed limits inoperable equipment or 02.200 8 specified in subsystems and the reasons 3.8.C.3 for the inoperability, identifies actions taken to restore the inoperable equipment to FUNCTIONAL status, and action(s) taken.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.C.7.1 Project doses due to gaseous effluent Each Batch releases at or beyond the SITE Incinerated BOUNDARY.
ODCMS 4.8.C.7.2 Determine dose and dose rate Each Batch contributions for radionuclides in Incinerated particulate form with half lives > 8 days in accordance with the methodology and parameters in ODCM Section IV.F.
3.8.D 40 CFR 190 and 10 CFR 72.104 PBAPS Units 2 and 3 ODCM 3.8.C-18 Revision 13
40 CFR 190
- q n1 ODCMS 3.8.D.1 The annual dose equivalent to a real individual who is located beyond the SITE BOUNDARY from all uranium fuel cycle sources within 8 kilometers shall be:
- a. < 25 mrem to the total body;
- b. < 75 mrem to the thyroid.
- c.
- 25 mrem to any other critical organ; and
- d. < 3.0 mrem contribution from liquid and gaseous effluents for whole body and critical organ doses.
- e. < 55 mrem contribution from gaseous effluents for thyroid dose.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A.A- NOTE------------ Immediately A. Annual cumulative Calculations shall include liquid and gaseous direct radiation effluents dose does contributions from reactor not meet ODCMS units and outside storage 3.8.D.1 items d or e. tanks.
A.1 Initiate actions to determine whether the limits in ODCMS 3.8.D.1 items a, b or c have been exceeded.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.D-1 Revision 13
40 CFR 190 "i Rqn 1 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Dose limits of B.1 Submit a Special Report 31 days ODCMS 3.8.D.1 items to the NRC that a, b or c have been includes the corrective exceeded. action(s) taken, the schedule for achieving conformance with required limits, estimates of radiation exposure to the real individual 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.
AND
NOTE----------
Only applicable if the release condition resulting in violation of 40 CFR 190 or 10 CFR 72.104 has not been corrected.
B.2 Submit a request for a variance in accordance 31 days with 40 CFR 190 and a request for an exemption from 10 CFR 72.104.
PBAPS Units 2 and 3 ODCM 3.8.D-2 Revision 13
40 CFR 190 3.8.D.I ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.D.1.l Determine total gas and liquid 31 days cumulative dose contributions in accordance with methodology and parameters in the ODCM.
ODCMS 4.8.D.1.2 Determine the cumulative dose 92 days contribution from gas and liquid effluents and the direct radiation from the reactor units and from high and low level radwaste storage in accordance with the methodology and parameters in the ODCM.
PBAPS Units 2 and 3 ODCM 3.8.D-3 Revision 10
Radiological Environmental Monitoring 3.8.E.1 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.1 Radiological environmental monitoring samples shall be collected at locations and analyzed as specified in Table 4.8.E.1 and the ODCM.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Milk samples A.1 Identify locations for 31 days permanently obtaining replacement unavailable from any samples and add them of the sample to radiological locations listed in environmental the ODCM. monitoring program.
Delete locations from which samples are unavailable.
02.2008 AND A.2 Identify in the AREOR Prior to the cause of the submittal in unavailability of next AREOR samples and new locations for obtaining samples and include in the report revised figures and tables for the ODCM reflecting the new locations.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.E-1 Revision 13
Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME B. Level of B.1 Submit a Special Report Immediately radioactivity as a to the NRC which result of plant includes an evaluation effluents in an of any release environmental conditions, sampling medium at environmental factors, one or more or other aspects which locations specified caused the action level in the ODCM exceeds of Table 3.8.E.1 to be the action levels of exceeded and the Table 3.8.E.1 when corrective actions to be averaged over the taken to reduce calendar quarter. radioactive effluents so that the potential OR annual dose to a MEMBER OF THE PUBLIC is less 02.2008 Level of than the calendar year radioactivity as a reporting level of result of plant Table 3.8.E.1.
effluents in an environmental sampling medium atý one or more locations specified in the ODCM exceeds the action levels of Table 3.8.E.1 when averaged over the calendar quarter and more than one radionuclide from Table 3.8.E.1 is detected and the equation in ODCMS 4.8.E.1.2 is satisfied.
(continued)
PBAPS Units 2 and 3 ODCM 3.8.E-2 Revision 13
Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. Radionuclides other C.I NOTE------- ------
than those in Only required if the Table 3.8.E.1 radionuclides detected and the detected are the potential annual result of plant dose to a MEMBER OF effluents.
THE PUBLIC is greater than or equal to the Submit a Special 31 days after calendar year limits Report to the NRC to end of of ODCMS 3.8.B.2, or evaluate any release affected ODCMS 3.8.C.2, or conditions, calendar ODCMS 3.8.C.3, or environmental quarter ODCMS 3.8.D.1. factors, or other 02.2008 aspects which caused the action 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 Table 3.8.E.1 AND (continued)
PBAPS Units 2 and 3 ODCM 3.8.E-3 Revision 13
Radiological Environmental Monitoring 3.8.E.1 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION TIME MEASURE C. (continued) C.2 ------- NOTE--------
Only required if the radionuclides detected are not the result of plant effluents.
Describe the condition Prior to in the Annual submittal of Radiological next Annual Environmental Operating Radiological Report. Environmental Operating Report D. Requirements of D.1 Prepare and submit, in Immediately ODCMS 3.8.E.1 the Annual Radiological not met. Environmental Operating Report, a description of the reasons for not 02.2008 conducting the radiological environmental monitoring program as required and the actions taken to prevent reccurrence.
PEAPS Units 2 and 3 ODCM 3.8.E-4 Revision 13
Radiological Environmental Monitoring 3.8 .E.1 ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.1.1 NOTES----------------
- 1. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous. conditions, seasonal unavailabilities, malfunction of automatic sampling equipment or other legitimate reasons.
- 2. If equipment malfunction occurs, an effort shall be made to complete corrective actions prior to the end of the next sampling period.
Collect radiological environmental In accordance.
monitoring samples at the locations with and analyze as specified in Table 4.8.E.1 Table 4.8.E.1 and the ODCM.
ODCMS 4.8.E.1.2 ------------- NOTE----------------
All radionuclides used in this evaluation shall be averaged on a calendar quarterly basis.
Evaluate the concentration of 92 days radioactivity as a result of plant effluents in an environmental sampling medium against the following equation:
concentration(l)
+
reporting level(l) concentration(2)
+
reporting level(2)
PBAPS Units 2 and 3 ODCM 3.8.E-5 Revision 13
Radiological Environmental Monitoring 3.8.E.1 Table 3.8.E.1 (page 1 of 1)
Reporting Levels for Radioactivity Concentration in Environmental Samples 12.2008 Action Levels ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS (pCi/l) PARTICULATE (pCi/kg, wet) (pCi/l) (pCi/kg, wet)
OR GASES (pCi/m 3 )
H-3 20,000*
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300
- For drinking water samples. This is 40 CFR part 141 value.
PBAPS Units 2 and 3 ODCM 3.8.E-6 Revision 13
Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 1 of 3)
Radiological Environmental Monitoring Program EXPOSURE PATHWAYAND/OR SAMPLE NUMBEROF SAMPLES AND SAMPLE LOCATION(a) SAMPLING AND COLLECTION TYPE AND FREQUENCY OF ANALYSIS FREQUENCY(b),(c)
- 1. Direct Radiation(e) At least 40 routine monitoring stations either with two or more dosimeters or with Every 31 days Every 31 days (Gamma dose) one instrument for measuring and recording dose rate continuously to be placed as follows: 1) an inner ring of stations in the general area of the SITE BOUNDARYand or or an outer ring in the 3 to 6 mile range from the site. A station is in each sector of each ring except as dictated by local geography. The balance of the stations Every 92 days Every 92 days (Gamma dose) are in special interest areas such as population centers, nearby residences, schools and in areas to serve as control stations.
- 2. Airborne Continuous sampler Radioiodine canisters: 1-131 Radioiodine and Particulates Samples from 5 locations: operation with sample analysis every 7 days collection every 7 days
- a. 3 samples from close to the SITE BOUNDARYlocations (in different sectors) of or required by dust Particulate sampler: (f) gross the highest calculated annual average ground level D/Q. loading, whichever is beta radioactivity analysis more frequent. following filter change; gamma
- b. I sample from the vicinity of a community having the highest calculated annual isotopic analysis of composite (by average ground level D/Q. location) 92 days
- c. 1 sample from a control location unlikely to be affected by the plant.
- 3. Waterborne
- a. Surface a. 1 sample upstream Composite (b) sample Gamma isotopic (d) analysis every over 31 day period. 31 days. Composite for tritium
- b. 1 sample downstream analysis at least every 92 days (continued)
PBAPS Units 2 and 3 ODCM 3.8.E-7 Revision 13
RadiologicalEnvironmental Monitoring 3.8.E.1 Table 4.8.E.l (page 2 of 3)
Radiological Environmental Monitoring Program EXPOSURE PATHWAY AND/OR SAMPLE NUMBER OF SAMPLES AND SAMPLE LOCATION SAMPLING AND COLLECTION TYPE AND FREQUENCY OF ANALYSIS FREQUENCY (b),(c) 3.Waterborne (cont'd)
- b. Drinking
- a. 1 sample of each of 1 to 3 of the nearest water supplies that could be affected by its Composite (b) sample over 31 composite for gross beta and discharge. day composite period gamma (d) isotopic analyses every 31 days. Composite for
- b. 1 sample from a control location. tritium analysis at least every 92 days
- c. Sediment from 1 sample from downstream area with existing or potential recreational value. Every 6 months Gamma isotopic (d) analysis Shoreline every 6 months
- 4. Ingestion
- a. Samples from milking animals in 3 locations within 3 miles distance having the highest
- a. Milk dose potential. Every 14 days when animals are Gamma isotopic (d) analysis or on pasture, every 31 days at 134, 137 Cs by chemical
- b. 1 sample from milking animals at a control location (unlikely to be affected by the other times, separation every 92 days. I-plant). 131 analysis of each sample.
- b. Fish a. 1 sample of each commercially and recreationally important species in vicinity of Sample in season, or every Gamma isotopic (d) analysis on discharge point when available. 6 months if they are not edible portions.
seasonal.
- b. 1 sample of same species in areas not influenced by plant discharge when available.
- c. Food Products a. Samples of 3 different kinds of broad leaf vegetation grown nearest offsite garden of Every 31 days when available if Gammzaisotopic (di and 1-131 highest annual average ground level D/Q if milk sampling is not performed, milk sampling is not performed, analysis Every 31 days when available if
- b. 1 sample of each of the similar broad leaf vegetation grown 15 - 30 km distant in the milk sampling is not performed least prevalent wind direction if milk sampling is not performed. Gamma isotopic (d) and 1-131 analysis PBAPS Units 2 and 3 ODCM 3.8.E-8 Revision 13
Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.1 (page 3 of 3)
Radiological Environmental Monitoring Program NOTES (a) Fixed sample locations are shown in the Offsite Dose Calculation Manual, Table VII.A.1 and Figures VII.A.1, VII.A.2, and VII.A.3. At times it may not be possible or practicable to obtain samples of the media of choice at the most desired location or time. In those instances suitable alternative media and locations may be chosen for the particular pathway in question. Such necessary deviations are reported in the Annual Radiological Environmental Operating Report.
(b) Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(c) Sample collection frequencies are defined as follows:
7 days 7 calendar days +/- 2 days 14 days 14 calendar days +/- 3 days 31 days 31 calendar days +/- 8 days 92 days 92 calendar days +/- 10 days 6 months 6 calendar months + 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.
(f) If the gross beta activity in air attributable to plant operation is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
PBAPS Units 2 and 3 ODCM 3.8.E-9 Revision 13
Radiological Environmental Monitoring 3.8.E.1 Table 4.8.E.2 (page 1 of 2)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS~a)
Lower Limit Of Detection (LLD)
(bW ANALYSIS WATER AIRBORNE FISH MILK FOOD PRODUCTS SEDIMENT (pCi/l) PARTICULATE (pCi/kg, (pCi/l) (pCi/kg, wet) (pCi/kg, (pCi/m 3) wet) dry)
Gross 4 0.01 Beta H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 PBAPS Units 2 and 3 ODCM 3.8.E-10 Revision 13
Radiological Environmental Monitoring 3.8.E.l Table 4.8.E.2 (paqe 2 of 2)
Notes:
(a) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable at 95% confidence level, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.
(b) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.66S*
E .V - 2.22 Y - exp (-?At)
Where:
LLD is the a priori lower limit of detection as defined above (as picocuries per unit mass or volume),
S is the standard deviation of the background counting rate or of the counting rate of blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per disintegration),
V is the sample size (in units of mass or volume),
2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable) is the radioactive decay constant for the particular radionuclide, and At for the environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
Typical values of E, V, Y, and At should be used in calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.
PBAPS Units 2 and 3 ODCM 3.8.E-11 Revision 13
Radiological Environmental Monitoring 3.8.E.2 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.2 A land use census shall be conducted and shall identify the location of the nearest milk animal in each of the 16 meteorological sectors within a distance of five miles.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Land use census A.1 Add the new location to 31 days identifies a the radiological location which environmental yields a calculated monitoring program.
dose or dose commitment (via the AND same exposure pathway) that is at least 20% greater than a location from which samples are currently being obtained in accordance with ODCMS 3.8.E.1. (continued)
PBAPS Units 2 and 3 ODCM 3.8.E-12 Revision 13
Radiological Environmental Monitoring 3.8 .E.2 COMPENSATORY MEASURES (Continued)
CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. (continued) A.2 -------- NOTE---------
The indicator sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from the 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 Radioactive Dose the next Assessment Report and Radioactive include the revised Dose figures and tables Assessment for the ODCM Report reflecting the new location.
B. Land use census B.1 Identify the new Prior to identifies a location in the submittal of location which Radioactive Dose the next yields a calculated Assessment Report. Radioactive dose or dose Dose commitment that is Assessment greater than values Report currently being calculated in ODCMS 3.8.C.3.
PBAPS Units 2 and 3 ODCM 3.8.E-13 Revision 13
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-to- 12 months door survey or by consulting local agriculture authorities or by some other appropriate means.
PBAPS Units 2 and 3 ODCM 3.8.E-14 Revision 13
Radiological Environmental Monitoring 3.8.E.3 3.8.E Radiological Environmental Monitoring ODCMS 3.8.E.3 Analyses shall be performed on radioactive materials supplied as part of the EPA Environmental Radioactivity Intercomparison Studies Program, or another Interlaboratory Comparison Program traceable to NIST.
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME A. Requirements of A.1 Include corrective Immediately 02.2008 ODCMS 3.8.E.3 not met.
actions to prevent recurrence in the I
Annual Radiological Environmental Operating Report.
ODCMS REQUIREMENTS ODCMS REQUIREMENT FREQUENCY ODCMS 4.8.E.3.1 Include a summary of the results of In accordance the Interlaboratory Comparison with Technical Program in the Annual Radiological Specification Environmental Operating Report. 5.6.2 PBAPS Units 2 and 3 ODCM 3.8.E-15 Revision 13
ODCM Specifications Bases B 3.8 3.10 Reporting Requirements ODCMS 3.10.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report shall be submitted in accordance with the requirements of Technical Specification 5.6.2. In addition to the requirements of Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report shall include or reference from previous reports:
- a. A summary description of the radiological environmental monitoring program including sampling methods for each sample type, size, and physical 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 3.8.E.2; and
- d. Results of the Interlaboratory Comparison Program required by ODCMS 3.8.E.3 and discussion of all analyses in which the LLD required by Table 4.8.E.2 was not achievable.
ODCM 3.10.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with the requirements of Technical Specification 5.6.3. In addition to the requirements of Technical Specification 5.6.3, the 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 61) shipped offsite during the report period:
- 1. Container volume;
- 2. Total curie quantity (specify whether determined by measurements or estimate);
- 3. Principal radionuclides (specify whether determine by measurement of estimate);
PBAPS Units 2 and 3 ODCM B 3.8-1 Revision 13
ODCM Specifications Bases B 3.8
- 4. Source of waste and processing employed (e.g.,
dewatered spent resin, compacted dry waste, evaporator bottomed); and
- 5. Type of container (e.g., LSA, Type A, Type B, Large Quantity).
- b. A list and description of unplanned releases from the site to areas at or beyond the SITE BOUNDARY of radioactive materials in gaseous and liquid effluents made during the reporting period.
- c. Changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM) and a list of new locations for dose calculations and/or environmental monitoring identified by the land use census required by ODCM 3.8.E.2.
- d. Annual summary of hourly meterorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. The licensee has the option of retaining this summary of required meterorological data on site in a file that shall be provided to the NRC upon request.
- e. 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.
- f. 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.
- g. The meterorological conditions 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 (ODCM).
PBAPS Units 2 and 3 ODCM B 3.8-2 Revision 13
ODCM Specifications Bases B 3.8
- h. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Guidance for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.
PBAPS Units 2 and 3 ODCM B 3.8-3 Revision 13
ODCM Specifications Bases B 3.8 B 3.8 ODCM SPECIFICATIONS BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in Section 20.1302 of 10 CFR, Part 20. At the same time, the licensee is permitted the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in Section 20.1302 of 10 CFR, Part 20. It is expected that in using this operational flexibility under unusual operating conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable.
Liquid 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 BOUNDARY will be within 10 times the concentration levels specified in 10 CFR, Part 20, Appendix B, Table 2, Column 2. This instantaneous limitation provides additional assurance that the levels of 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, Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR, Part 20.1302 to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICP) Publication 2.
Dose This specification is provided to implement the requirements of Sections I.E., IXIA and I.E. of Appendix I, 10 CFR Part 50. ODCMS 3.8.B.2 implements the guidance set forth in Section I.E. of Appendix I and provides the required operating flexibility to implement the guides set forth in Section I.E. of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations in the ODCM implement the requirements in Section IXIA 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 appropriate pathways is unlikely to be substantially underestimated. The equations described in the Offsite Dose Calculation Manual for calculating the doses due to the actual release rates (continued)
PBAPS Units 2 and 3 ODCM B 3.8-4 Revision 13
ODCM Specifications Bases B 3.8 BASES Liquid 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 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of liquid 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 effluents during actual or potential release of liquid 02.2008 effluents. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
System Operation 02.2008 The FUNCTIONALITY of the Liquid Radwaste Treatment System ensures that I this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as 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 Liquid Radwaste Treatment System were specified as a suitable fraction of thl ýqiide set forth in Section II.A of Appendix*
I, 10 CFR, Part 50, for liquid effluents.
The chemical/oily waste cleanup subsystem may include the portable Epicor oil/water emulsion system (as described in RW-625), an installed chemical/oily waste cleanup subsystem, or equivalent chemical/oil waste system.
The laundry drain filter may be used to process liquid wastes containing detergents or similar cleaning agents. Wastewater such as river water that is acceptable for release may be processed through the laundry drain filter.
(continued)
PBAPS Units 2 and 3 ODCM B 3.8-S Revision 13
ODCM Specifications Bases 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 beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Part 20, Appendix B, Table 2, and Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC with the appropriate occupancy factors are given in the ODCM. The specified limits restrict, at all times, the gamma and beta dose rates above background to a MEMBER OF THE PUBLIC, at or beyond the SITE BOUNDARY to
< 500 mrem/year to the total body or to < 3000 mrem/year to the skin.
These dose rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to < 1500 mrem/year.
Dose, Noble Gases This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of. Appendix I, 10 CFR Part 50. ODCMS 3.8.C.2 implements the guidance set forth in Section II.B of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." ODCMS 4.8.C.2.1 implements the requirements in Section III.A of Appendix I that conformance with the guidance of Appendix I be shown by calculational procedures based on models and data 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 provided in.Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and the atmospheric dispersion model submitted on 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." 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 3.8-6 Revision 13
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 implements the guidance set forth in Section II.C of Appendix I and provides the required operating flexibility to implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the ODCMS 4.8.C.3.1 implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The ODCM calculational methods for calculating the doses due to the 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 calculations were: 1) individual inhalation of airborne radionuclides, 2) 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 02.2008 gaseous effluents. The FUNCTIONALITY 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)
PBAPS Units 2 and 3 ODCM B 3.8-7 Revision 13
ODCM Specifications Bases B 3.8 BASES Gaseous Effluents (continued)
System Operation 02.2008 The FUNCTIONALITY of the Gaseous Radwaste Treatment System ensures that this system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR, Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR, Part 50 and design objective Section II.D of Appendix I to 10 CFR, Part 50. The specified limits governing the use of appropriate portions of the Gaseous Radwaste Treatment System were specified as a suitable fraction of the guidance set forth in Section II.B and II.C of Appendix I, 10 CFR, Part 50, for gaseous effluents.
To determine if gaseous effluents shall be processed through installed treatment equipment, the average projected dose will be determined.
For gaseous effluent pathways other than the specified unmonitored exhausts, treatment and monitoring will only be required for pathways that are significant. Regulatory Guide 1.109, "Calculations of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
states that a pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways. Therefore, the total dose from all release pathways that do not require treatment or monitoring can not exceed 10 percent of the limit specified in Section II.C of Appendix I, 10 CFR Part 50.
Containment PURGE ODCMS 3.8.C.6 requires that the primary containment atmosphere receive treatment for the removal of gaseous iodine and particulates prior to release to provide reasonable assurance that PURGING operations will not result in exceeding the annual dose limits of 10 CFR Part 20 for areas at or beyond the SITE BOUNDARY.
PBAPS Units 2 and 3 ODCM B 3.8-8 Revision 13
ODCM Specifications Bases B 3.8 BASES 40 CFR 190 and 10 CFR 72.104 This specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR 20.1301(d) as well as the dose limitations specific to Independent Spent Fuel Storage Installation (ISFSI) operations in accordance with 10 CFR 72.104.
Over the long term, as more ISFSI casks are placed on the ISFSI pad, it is expected that ISFSI operations will become the prominent contributor to the limits in this section. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The 10 CFR 72.212 report prepared in accordance with ISFSI requirements assumes a certain array of casks exists on the pad. The dose contribution from this array of casks in combination with historical uranium fuel cycle operations (e.g. PBAPS 2 & 3) prior to ISFSI operations was analyzed to be within the 40 CFR 190 and 10 CFR 72.104 limits. The difference between 40 CFR 190/10 CFR 72.104 limits and the analyzed ISFSI cask array contribution are identified in ODCMS 3.8.D.1 items d and e. Therefore, these values are used as assumptions in calculating combined ISFSI and PBAPS 2 & 3 doses. If these PBAPS 2 & 3 liquid and gas radiation values are exceeded, an evaluation is performed to determine if the overall 40 CFR 190 and 10 CFR 72.104 limits have been exceeded.
If the dose limits of 40 CFR 190 or 10 CFR 72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption /variance is required to be submitted to the NRC.
The requirement that the dose limits of 10CFR 72.104 apply to "any real individual" are controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose in the south end of the site, the member of the public as defined in 40 CFR 190 at this area is the same as the "real individual" identified in the 72.212 report. The location for the real individual identified in the ISFSI 72.212 report is the limiting individual for calculating dose.
PBAPS Units 2 and 3 ODCM B 3.8-9 Revision 13
ODCM Specifications Bases B 3.8 BASES Radiological Environmental Monitoring Monitoring Program The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the two reactors at the sites. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.
The required detection capabilities for environmental sample analyses are tabulated in terms of the Lower Limit of Detection (LLD). The LLD's required by Table 4.8.E.2 of the specifications are considered optimum for routine environmental measurements in industrial laboratories. The monitoring program was developed utilizing the experience of the first seven years of commercial operation. Program changes may be initiated based on the additional operational experience.
Land Use Census This specification is provided to ensure that significant changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological 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.
interlaboratory Comparison Program The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices, are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.